ML20059K106

Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny

ML20059K106
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Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	08/25/1993
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ML20059K099	List: ML20059K086 ML20059K106
References
PROC-930825, NUDOCS 9311150190
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l PROPOSED l

CONFIRMATORY SURVEY PLAN FOR THE i

SIIOREIIAM NUCLEAR POWER STATION BROOKHAVEN, 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 j

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 power 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 fuel poolin August 1989.

Various reactor components, piping systems, and other equipment became radiologically l

l contaminated as a result of reactor operation. The primary contaminants which have been i

l identified during characterization studies include iron-55, cobalt-60, nickel-63, and smaller quantities of tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152.'

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 I

Prepared by the Environmental Survey and Site Assessment Program, Energy / Environment Systems Division, Oak Ridge Institute for Science and Education, under interagency agreement -

1 (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 will be conducted over an appoximate eighteen month period, terminating in the removal of the spent fuel from the site during July 1994 and completing the final surveys in October 1994. The initial phase, performed during February 1993, involved the termination survey of the internal components i

of the main turbine. The schedule for the remaining portions of the decommissioning and termination surveys is outlined in Table 1.

It is the policy of the NRC to perform confirmatory surveys of facilities that have undergone decommissioning 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 a confirmatory radiological survey of the SNPS decommissioning project.

The intent of this survey plan is to provide a general overview and approach that ESSAP will use to conduct the confirmatory process. Prior to the initiation of on-site confirmatory activities for each phase, this survey plan may be modified to address building or area specific survey requirements.

SITE DESCRIPTION l

l 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 Long Island Sound (Figure 1). The SNPS is located on a 32.4 ha (80 ac) portion of a larger l

202 ha parcel of land owned by the LILCO. The site is bounded on the north by Long Island i

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 l

Shorch.m Nuclear Power Staton - August 25.1993 (Revised) 2 6:%i

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are to be addressed during the confirmatory surveys 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 of the three j

2 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 occurrcaces may have resulted 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.

i Table 2 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 licensee'; procedures and termination survey results.

J Shoreham Wck r Power Stauon - August 25,1993 (Revbed) 3 hw w.wra.s.wra mem l

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RESPONSIBILITY Work described in this survey plan will be performed under the direction of Michele Landis, Project Manager 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 either a revised survey plan 4

1 or the site log book.

DOCUMENT REVIEW AND LIPA PROCEDURE SURVEILLANCE ESSAP will review LIPA's termination survey procedures as well as the release records for those survey units selected for confirmatory survey. Review of additional release records will j

be dependent upon findings as the surveys progress. Documents will be reviewed for adequacy, i

l accuracy, completeness, and consistency. In addition, ESSAP will review and then conduct i

observational surveillances of the embedded piping procedures for appropriateness. and consistency in field application.

PROCEDURES A survey team from ESSAP will conduct three confirmatory surveys at the site and perform independent visual inspections, measurements, and sampling. ESSAP will select 10% of the survey units indicated in Table 2 for confirmatory surveys. Of the population ESSAP surveys, 50% will be randomly selected affected survey units,30% will be randomly selected unaffected survey units, and 20% will be affected or unaffected survey units, chosen by the NRC or ESSAP, on the basis of findings as the surveys progress. Figures 3 through 6 provide flow charts which illustrate an overview of, and the implementation of this plan. 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.

l Shoreham Nuclear Power Station. Augud 25,1993 (Revised) 4

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J SURVEY PROCEDURES: INTERIOR i

Reference System 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).

Surface Senns e,W p

i Surface scans for alpha, beta, and gamma activity, will be performed over floors, lower walls, t9 f each structural survey unit. Additional scans will be performed over portions

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of upper wall, ceiling, and system surfaces as well as locations 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 ZnS, gas proportional, GM, and/or NaI detectors coupled to ratemeters or ratemeter-scalers with audible indicators.

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Surface Activity Measurements 4

s 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 radiation detected by surface scans.I 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. Direct measurements, together with LIPA, will also be made at 6 to 10 locations within the facility to compare ESSAP and LIPA instrument responses. -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.

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Exnosure Rate Measurements Background exposure rate measurements will be made at approximately 10 locations within i

buildings of similar construction as those in the power block but without a history of radiological usage. 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 I m above surfaces using a pressurized ionization chamber (PIC).

Embedded Pinine Confirmation of the radiological status of embedded piping will be accomplished primarily through surveillance of the methodologies and procedures utilized. Procedures and data for the instrument calibrations and quality control factors also will be reviewed. In addition, random independent measurements will be made at accessible openings and traps.

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

SURVEY PROCEDURES: EXTERIOR Reference System The grid systems established by LIPA on the site grounds and exterior building surfaces will be I

used by ESSAP for reference.

Shorcism Nucker Power Statum. Augunt 25.1993 (Revmal) 6 h % W mWie h W h MI

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i Surface Scans Survey units that consist of site grounds will be gamma scanned and if a paved area or exterior building surface, alpha and beta scans will also be performed. Scans will be performed using l

Nal, gas proportional, GM, and/or ZnS detectors, coupled to ratemeters or ratemeter-scalers l

with audible indicators.

Surface Activity Measurements ESSAP will perform a minimum of 30 direct measurements for total beta activity levels for confirmatory survey units that are exterior building surfaces. Alpha direct measurements will also be made if surface scans identify alpha contamination. Direct measurements will be made j

using gas proportional, GM, and/or ZnS detectors coupled to ratemeter-scalers. A smear sample for determining removable activity will be collected from each direct measurement location.

Exposure Rate Measurements Background exposure rate measurements will be performed at 6 locations within 0.5 to 10 km of the site. Exposure rate measurements will also be performed within each survey unit.

Exposure rates will be measured at I m using a PIC.

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Background. oil samples will be collected from each bacxground exposure rate measurement location. Site soil samples will be collected from unpaved outdoor locations where elevated direct rad on is detected by surface scans.

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Confirmatory Analysis Soil samples collected by LIPA may be requested for confirmatory analysis.

I Shoretam Nuclear Power Statma - Auget 25,1993 (Revmed) 7 h:\\emmapiplarswhorehamishoretam 001 l

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SAMPLE ANALYSIS AND DATA INTERPRETATION 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 l

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background proportional counter.

Soil samples will be analyzed by solid state gamma i

spectrometry. The spectra will be reviewed for uranium and gamma-emitting fission and

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activation products. Soil samples will be reported in units of pCi/g. Smear and direct '

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measurement data will be converted to units of dpm/100 cm and exposure rates to R/h. Data will then be compared to the LIPA results and NRC guidelines. Sun ey results will be presented I

l in a draft report at the completion of each confirmatory phase and submitted to the NRC for j

j review and comment.

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DATA EVALUATIONS AND COMPARISONS 1

3 The data sets collected from each survey unit, investigated by both LIPA and ESSAP, will be evaluated individually. The hypothesis to be tested, described below, was developed based on a comparison of calibration procedures and instrumentation used by ESSAP and LIPA.' Results

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of that comparison indicate that the calibration procedures, from which the LIPA efficiency j

factors are calculated, are inherently conservative. That is, when measurements are made by both LIPA and ESSAP, the LIPA reported activity level will be higher than the activity level reported by ESSAP.

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Therefore, for a statistical evaluation of ESSAP and LIPA data for a given survey unit, a one-l tailed t test will be performed. The null hypothesis will be that in a survey unit, surface.

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activities as calculated by ESSAP are equal to or greater than those determined by LIPA, i.e.,

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H:pm,2pm. This hypothesis will be calculated at the 95% confidence level (0.05 level e

N /b2 of significance). If the hypothesis is rejected at that confidence level, the alternative hypothesis f-will be accepted i.e., H,:

< pay The est statistic, t, will be calculated using the m,

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Is the LIPA surface activity mean for a sYrvey unit b 5

Is the ESSAP surface activity mean for the same survey unit nt Is the number of LIPA direct measurement data points n,

Is the number of ESSAP direct measurement data points S, So Are the standard deviations, t

The calculated t is then compared to the critical value of Student's t-distribution (one-tailed) for the appropriate degrees of freedom.

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If in a given survey unit a) the H.: in 2 A;m'cannotabe rejected at the 0.05 level of significance or-b)Xp-Xp, ESSAP data will be compared to the appropriate NRC contamination j

guidelines at the 95% confidence level per Draft NUREG/CR-5849.

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'i$ he The results ofdoil samples analyzed by both ESSAP and LIPA ill be evaluated using a pair-wise comparison t-test. For each soil sample, the difference between ESSAP and LIPA analytical results will be calculated (d). The test statistic t will be calculated using the following equation:

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is the difference between ESSAP and LIPA analytical measurements for a soil sample d

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" f k ct pe-su o-t The null hypothesis is that thery are nc differences between ESSAP and LIPA analytical measurements i.e., H,:[ptC 3 pg The calculated value of t is compared to the critical value

([d for the appropriate degrees of freedom at the 95%

of student t-distributi confidence level (0.05 level of signific ce). If-the-calculatcd+4c leet than t. - 4 hen-the-null -

1 Jtypothesis is awyted.

Should the data and statistical tests of the data. fail-4o reject the null hypothesis,-or in the cme of-soil analyscseemparisons reept 'he m'11 bypnthetis, ESSAP will evaluate additional options and alternatives and confer with the NRC as to the recommended approach.

GUIDELINES Should-ESSAP-data require enmparison to the NRC nuidelines (when the null hypothesis-must be2ccEptea), then ESSAP's cata wili bc wmpaicd is thc accupiabic suffice contamination leveP MoundirrRegulatory Umac tS6. The applicable 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:

breh.m Nale.r Power Stauo. August 25,1993 (Resined) 10 m.,w. m s w a im

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2 5,000 6-7 pm/100 cm, averaged over Im 15,000 B-y dpm/100 cm, maximum in a 100 cm area 2

2 Removable Activity d

2 1,000 6-7 pm/100 cm 1

The alpha guidelines are:

Total Activity 2

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

2 15,000 a dpm/100 cm, maximum in a 100 cm area Removable Activity t

1,000 a dpm/100 cm 2

Exposure rates will be compared to the 5 pR/hr criteria currently being used by the NRC.2 Soil i

sample results will be compared to the background concentration levels or to the current site specific NRC criterion of 8 pCi/g average concentration of Shoreham produced gamma-emitting i

radionuclides in the top 15 cm.

Shorcharn Nuclear Power staiwn. August 25,1993 (Revined)

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Tentative Confirmatory Schedule Month / year Duration Phase II: Turbine Building and Outside Surveys Document Review October 1993 2 weeks Confirmatory Survey November 1993 1.5 weeks Sample Analysis August 1993 2 weeks Draft Report September 1993 5 weeks Phase III: Reactor Building Surveys Document Review February 1994 2 weeks i

Confirmatory Survey February / March 1994 1.5 weeks i

Sample Analysis March 1994 2 weeks l

Draft Report April /May 1994 5 weeks l

l Phase IV: Rad Waste Building, Spent Fuel Pool, l

Fuel Transport Route Surveys Document Review October 1994 2 weeks Confirmatory Survey November 1994 2 weeks Sample Analysis November / December 1994 2 weeks Draft Report February 1995 5 weeks Shoreham Nwlear Power Stauon - Augu.t 25,1993 (Rev.ed) 12 6:se e pi.e.s. hor.h '- -- ooi s

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a LIST OF CURRENT PROCEDURES TO BE USED IN TIIE SURVEY j

Applicable procedures from ORISE ESSAP Survey Procedures Manual (Revision 7; May 31, 1992) include:

I Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 1

-l 5.2 Electronic Calibration of Ratemeters

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5.3 Gamma Scintillation Detector Check-Out and Cross Calibration l

5.4 Alpha Scintillation Detector Calibration and Check-Out l

5.5 GM Detector Calibration and Check-Out

'l 5.6 Proportional Detector Calibration and Check-Out 5.7 Pressurized Ionization Chamber Calibration and Check-Out

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5.8 Floor Monitor Check-Out 4

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5.10 Field Measuring Tape Calibration i

Section 7.0 Scanning and Measurement Techniques j

i 7.1 Surface Scanning I

7.2 Alpha Radiation Measurement 7.3 Beta Radiation Measurement 7.4 Gamma Radiation (Exposure Rate) Measurement Section 8.0 Sampling Procedures 8.1 Surface Soil Sampling i

8.2 Subsurface Soil Sampling j

8.3 Sample Identification and Labeling Section 9.0 Integrated Survey Procedures 4

9.1 Background Measurements and Baseline Sampling i

9.2 General Survey Approaches and Strategies i

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hrch.m Nuclear Power Swion - Augunt 25.1993 (Revoed) 13 6:s spi "

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4 Section 11.0 Quality Assurance and Quality Control l

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Document Review I

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I Data Data tabulation tabulation Report FIGURE 3: Overview of the SNPS Confirmatory Process Shorcham Nuc6 car Power Stataum - August 25.1993 (Revised) 17 bWMemhmM

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FIGURE 4: Survey Unit Selection

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TABLE 1

SUMMARY

OF TIIE SIIOREHAM NUCLEAR POWER STATION DECOMMISSIONING SCIIEDULE l

Description Decommissioning and Termination Survey Completion Schedule Turbine Building Interior Structures' September 1993 Turbine Building Systems' Site Grounds Site Structures Exteriors Reactor Building Interior Structures February 1994 Reactor Building Systems Rad Waste Building Interior Structures June 1994 Rad Waste Building Systems i

Spent Fuel Pool and Fuel Transport October 1994 Routes

• An interior building structure is defined to include floors, walls, ceilings, and the external surfaces of l

equipment and plant systems.

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' Systems are defined as the internal surfaces and components of plant piping and equipment.

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TABLE 2 l

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SUMMARY

OF TIIE SNPS FACILITIES AND ASSOCIATED SURVEY UNITS l

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Description No. of Affected No. of Unaffected Total No. of

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Turbine Building Structures 10 104 114 i

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Reactor Building Structures 110 0

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Rad Waste Building Structures 77 0

77 Drywell 22 0

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Suppression Pool 13 0

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Plant Systems 38 44 82

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32 32 Total 270 190 460 4

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Shoret sn Nu.icar T'ower Station - August 25,1993 (Revoed) 2I h.bepplanserdamentam 001

REFERENCES 1.

Long Island Lighting Company, "Shoreham Nuclear Power Statior, Site Characterization Program Final Report," May 1990.

2.

Letter from T. J. Vitkus, ORISE to David Fauver, U.S. Nuclear Regulatory Commission, "Results of Field Survey Instrumentation Cross-Comparisons and Issue Resolution, Shoreham Nuclear Power Station, Brookhaven, New York - Docket File No. 50-322", June 14, 1993.

3.

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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Shorch.m Nude.r Power St.taan. August 25.1993 (Revunxi) 22 6:s pspi m s.so 6 ooi r

APPENDIX A i

Turbine Bldg.

Radwaste Bldg. and R M or Activity and Outdoor uel Storage and Building' Areas Transportation Areas Plan Preparation Total Cost:

$21,000

$21,000

$19,500 Document Review

% of 7.5 %

7.3 %

9%

Total Cost

• 7.5 %

7.3 %

9%

Survey Preparation On-Site Activities Total Cost:

$78,100

$85,300

$47,900 Travel 24 %

24 %

25 %

Surface Scans g or 19 %

18 %

9%

Direct Measurements Total Cost

• 12 %

18 %

12 %

i Sampling

<1%

<1%

<1%

Sample Analysis Total Cost:

$3,200

$1,800

$1,800 Smear Analysis

% of 1%

1%

1%

Total Cost

• 1%

<1%

Gamma Spectrometry Report Preparation Total Cost:

$37,800

$36,300

$36,300 l

Data Tabulation 4%

4%

5%

Illustration

% of 9%

7%

10 %

Draft and Final Report Text 14 %

13.4 %

19 %

Preparation & Review Total Cost Estimate

$140,000

$144,400

$105,600

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

Stuercham %cicar Power Stat.on. August 25,1993 (Revsed) 23 6:1, spi wso,.i s.ho 6.- ooi