ML20063D012

Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan

ML20063D012
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/30/1993
From:	LONG ISLAND POWER AUTHORITY
To:
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ML19303F826	List: ML20063D006 ML20063D012 ML20063D026
References
PROC-930430, NUDOCS 9402070285
Download: ML20063D012 (71)

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Termination Survey Plan Rev.1 PJeface This document describes the methods used by the Long Island Power Authority (LIPA) to demonstrate that radiation and radioactive contamination levels of the Shoreham Nuclear Power Station have been reduced to levels below criteria established for release

.~ar unrestricted use. It supplements and updates the description of the proposed final radiation survey presented in the Shoreham Decommissioning Plan (LIPA90).

This Plan describes the technical methods to be used and provides guidance for planning and design of the Termination Survey. It is prepared and controlled under the LIPA Nuclear Managemcat Control Manual, Termination Survey Program Description (LIPA92).1 The methods described a- '-"ved from regulatory guidance, specifically Regulatory Guide 1.86 (USAEC74) and draft NUREG/CR-5849 (BE92); and from recent U.S. reactor facility decommissioning experience (Pathfinder, Saxton, Shippingport, UC Berkeley), taking inta account conditions at the Shoreham facility.

(( Revision 0 of this Plan was issued November 20, 1992 and was used for early survey work beginning in January,1993. This latest revision incorporates changes necessitated by these early survey experiences as well as commitments made to the Nuclear Regulatory Commission (NRC) resulting from staff review of the Plan.))

I This Plan is a companion document to the Shoreham Decommissioning Project Termination Survey Program Description (LIPA92). The Program Description describes the organization and management responsibilities for the Termination Survey Program.

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s Termination Survey Plan Rev.1 SHOREHAM DECOMMISSIONING PROJECT TERMINATION SURVEY PLAN Table of Contents Section Iille Page No.

1.0 Historical Background Information 1-1 2.0 Site Information 2-1 i

3.0 Termination Survey Overview 3-1 4.0 Survey Plan and Procedures 4-1 5.0 Data Interpretation 5-1 6.0 Final Report 6-1 7.0 References 7-1 8.0 Glossary 8-1 Appendices:

A.

Survey Design Guidelines A-1

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O Termination Survey Plan Rev.1 List of Tables Number Iitle Page No.

2.1 Shoreham Termination Survey 2-4 Classification Summary 3.1 Acceptable Surface Contamination Levels 3-1 4.1 Termination Survey Instrument Summary 4-3 4.2 Detector Sensitivities 4-4 6.1 Termination Survey Detail Data Report 6-5 i

List of Figures Number Iille Page No.

2.1 Shoreham Site (Partial) Showing Termination 2-5 i

Survey Area 4.1 View of Structural Survey Unit Showing 4 - 12 Grid Placement 4.2 Shoreham Decommissioning Termination 4 - 13 Survey Grid Map

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Termination Survey Plan Rev.1 List of Ficures (Cont'd)

Number Title Page No.

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5.1 Total Surface Contamination 5-9 Data Processing -

Affected Survey Units 5.2 Total Surface Contamination 5 - 10 Data Processing -

'Onaffected Survev Units 5.3 Removable Surface Contamination 5 - 11 Data Processing 5.4 Gamma Exposure Rate 5 - 12 Data Processing 5.5 Soil Sample Data Processsing 5 - 13

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Tennination Survey Plan Rev.1 1.0 Historical Background Information The Shoreham Nuclear Power Station (SNPS) power generation plant consists of a boiling water reactor (BWR) nuclear steam supply system (NSSS) and a turbine generator both furnished by General Electric Company. The balance of the plant was designed by Stone

& Webster Engineering Corporation. The plant was designed to provide a gross electrical output of 849 Megawatts (LILCO90).

The SNPS achieved initial criticality in February 1985 following receipt of the initial operating license from the Nuclear Regulatory Commission (NRC). A license to operate at power levels not to exceed 5% of full power was granted and low power testing commenced in July 1985. The plant was operated. intermittently at power levels not exceeding 5% of full power until the final critical operation in January 1989. This operating history corresponds to 2.03 effective full power days (EFPD) of average fuel exposure (LIPA90).

Pursuant to the 1989 agreement among The Long Island Lighting Company (LILCO), the State of New York and the long Island Power Authority (LIPA), power generating operations at SNPS were terminated. The irradiated fuel was removed from the reactor pressure vessel in August 1989 and placed in the spent fuel pool.

The DECON alternative was selected for decommissioning SNPS and an order approving the LIPA Decommissioning Plan was issued by the US Nuclear Regulatory Commission (NRC) in June,1992 (USNRC92). The objective of the approved DECON alternative

[.[was)) to decontaminate the SNPS facility and site and release them for unrestricted use.

To accomplish this, ((the majority of thel] radioactive portions of the reactor pressure vessel and pressure vessel internals ((was)) disassembled, segmented and removed.

Contaminated and activated portions of plant piping systems and equipment ((were))

decontaminated or removed as described in the LIPA Decommissioning Plan (LIPA90).

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Termination Survey Plan Rev. I 2.0 Site Information l

l 2.1 Site Description The Shoreham Nucle.r Power Station site is located in the Town of Brookhaven, Suffolk County, New York on the nonh shore of Long Island. The site is approximately 50 miles east of the confluence of the East River and long Island Sound which is near I2 Guardia Airport.

The developed portion of the site comprises 80 acres, and is located within a larger parcel of 499 acres owned by the long Island Lighting Company (LILCO).8 The 499 acre parcel is bounded on the north by Long Island Sound and on the east by the Wading River marshland. It is bounded on the west by a parcel of approximately 429 acres known as the Shoreham West property, also owned by LILCO, and on the south by highway Route 25A. The 499 acre SNPS site property is divided across its midsection in the east-west direction by North Country Road which branches off Route 25A about three miles west of the site and rejoins 25A about three miles east of the site. North Country Road is about 1,500 ft. south of the Reactor Building at its closest point to the developed area of the site. Figure 2.1 shows the SNPS site plan and the location of major buildings on the developed portion of the site.

The site elevation varies from sea level at long Island sound (the northern boundary of the site) to elevation 200 feet midway between North Country Road and the southern border of the site. Except for the developed area, the site is wooded with wetlands along the east and west boundaries extending as much as 1,300 feet inland from the Sound. The developed portion of the site is fairly level with the exception of several graded slopes, the largest of which is a terraced s!:pe about 30 feet in height which traverses the site in an east-west direction immediately to the south of f.e Reactor Building. The ground surface covering in the developed area is mostly gravel with smaller portions devoted to lawn and paved areas (sidewalks, loading areas and roadways). The site soil cover in unpaved or undisturbed areas is a mixture of sand and glacial till (gravel). Vegetation cover in undisturbed areas is a mixture of grass and weeds with a few shmbs and small trees.

2.2 Site Conditions for Termination Survey The Shoreham (( facility remains largely intact)) following decommissioning.

Dismantlement of structures ((was)) confined to small portions within the Reactor, Radwaste and Turbine Buildings. Removal ((of such structures was performed to))

Under the Asset Transfer Agreement, approximately 11 acres of the site which include the power block, adjacent office and support buildings and connecting roadways have been transferred to LIPA for conduct of the decommissioning (LIPA90).

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Termination Survsy Plan Rev. I provide paths for removal of contaminated piping and equipment. As described in the LIPA Decommissioning Plan (LIPA90), ((most)) radioactive piping and equipment

((was)) dismantled, removed from the facility and disposed of as radioactive waste at a licensed radioactive waste disposal facility. This includes ((the)) reactor pressure vessel,

(( reactor pressure vessel)) internals and major portions of 14 plant systems.

(( Decontamination of plant piping and equipment was performed to a much lesser extent. Some such items include the reactor vessel bottom head, a portion of the main steam lines in the Reactor Building, the Condensate Storage Tank (CST), and Residual Heat Removal (RHR) system heat exchangers (shell only).)) It is estimated that greater than 75 percent of the piping and equipment on site during the time of reactor operation will remain after decommissioning is complete.

2.3 Site Areas Covered - Scope of Survey The Shoreham facility and environs have been evaluated to identify the areas to be covered in the termination survey. The termination survey focuses on the area within the Secured Area fence as shown in Figure 2.1. The area (approximately 20 acres) contains the Reactor, Radwaste and Turbine buildings, and other buildings, facilities, and grounds within the Secured Area fence. The Secured Area is described in the Shoreham Nuclear Power Station Updated Safety Analysis Report (LILCO90). The area within the Secured Area fence coincides with the Restricted Area defined in Shoreham radiological control procedures as the area where access has been controlled and radioactive materials controlled for purposes of protection ofindividuals from exposure to radiation. Following completion of Shoreham decommissioning and removal of the irradiated fuel from the J

site, areas outside the Restricted Area may be added to the survey if used for temporary storage or handling of irradiated fuel or other radioactive materials.

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Major attention in the termination survey is given to the areas most affected by reactor-operations and by decommissioning activities. The area covered by the termination survey has been divided into approximately ((450)) individual " survey units" for management of the survey. Each survey unit is classified as "affected" or " unaffected" for survey implementation.2 Affected areas are lcrgely confined to the Reactor and Radwaste buildings, and portions of the Turbine building. Table 2.1, Shoreham Termination Survey Classification Summary, summarizes the breakdown of the facility.

into affected and unaffected areas. This table is updated from time to time, as needed, and maintained via an approved procedure.

The environs of the facility beyond the area of the site encompassed by the termination survey have been demonstrated to be free of detectable radioactivity from Shoreham 2

An "affected" area as defined in draft NUREG/CR-5849 (BE92) and used in this Plan is a designation used to indicate that an area (survey unit) has a potential for containing residual radioactive contamination. An " unaffected" area is one which is not expected to contain residual radioactivity based upon the operating history and previous radiological surveys (see Glossary).

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Terminadon Survey Plan Rev.1 Monitoring Program (REMP). The REMP will be continued throughout Shoreham decommissioning to ensure that any contamination of the site environs which could occur as a result of decommissioning activities is detailed.

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t Termination Survey PI:s Rev.1 Table 2.1 Shoreham Termination Survey Classification Summary Total No.

No. of Affected No. of Unaffected DESCRIPTION CODE of Survey Units Survey Units Survey Units STRUCTURES Reactor Bldg.

RB 100 100 Drywell PC 21 21 Suppression Pool SP 13 13 Turbine Bldg.

TB 103 8

95 Radwaste Bldg RW 74 74 Control Bldg CB 4

4 O & S Bldg OB 4

4 0 & S Bldg Annex AB 4

4 Other Site Bldgs OS 2

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Structure Totals 332 217 115 OUTSIDE AREAS f

Site Grounds SG 7

7 Soil Samples SS 1

1 Structure Exteriors SE H

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PLANT SYSTEMS SU 84 38 46 TOTALS 438 255 183 i

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Termination Survey Plan Rev.1 3.0 Termination Survey Overview 3.1 Survey Objectives The termination surveyis designed to demonstrate that licensed radioactive materials have been removed such that residual levels of radioactive contamination are ielow applicable Regulatory Guide 1.86 limits (USAEC74). These are shown below in Table 3.1, Acceptable Surface Contamination Levels. Radiation detection instrumentation requirements for the survey are based upon the conclusion that the controlling radioactive species in determining compliance with Regulatory Guide 1.86 release limits are activation products dominated by Co-60. These are beta-gamma emitters as defined in Regulatory Guide 1.86(USAEC74), hence the limits for beta-gamma emitters shown in Table 3.1,below, apply.

The applicable release limits for alpha emitters are also shown in Table 3.1.These are for Natural Uranium, U-235, U-238 and associated decay products. Though none-has been detected in the plant contamination deposits, the presence of the irradiated fuel in the facility provides a potential source of alpha contaimnation. Instruments and methods are being incorporated into the survey which are adequate to measure alpha surface activity at levels below the limits in Table 3.1.

l Table 3.1 Acceptable Surface Contamination Levels (dpm per 100 cm')

Fixed Plus Removable Removable Activity Average Maximum Beta-Gamma 5,000 15,000 1,000 Alpha 5,000 15,100 1,000 In addition, to the limits shown in Table 3.1,the gamma exposure rate at one meter from accessible surfaces in the facility buildings and outdoor areas shall not exceed 5 R/hr above background, measured at one meter from surfaces (LIPA90).

3.2 Identity of Contaminants The Shoreham Characterization Study (LILCO90a) reported a total facility radioactivity inventory due to Shoreham operations of about 600 Curies (Ci) (not including the irradiated fuel and control blades). All but a very small fraction (less than one Ci) of this inventory ((was)) contained in activated materials of 2he reactor pressure vessel and vessel internals which ((have been)) removed from the site. The calculated radioactivity composition of the activated components (as of July,1990) is: Fe-55,69%; Co-60,28%; and Ni-63,2%. Very minor amounts of other species are 3-1

Te mination Survey Plan Rev.1 calculated to be present, including: H-3, C-14, and Ni-59 (LILCO90a). Laboratory -

analysis of activated reactor pressure vessel and vesselinternals samples indicates the presence of low levels of Mn-54, Zn-65, and Ni-63,in addition to Co-60. Analysis of bioshield wall samples show low levels of Co-60, Mn-54 and Eu-152 (TU92).

Detectable radionuclides in surface corrosion deposits are confined to a small number of radionuclides. An analysis of piping system corrosion products ((in nine (9) discrete samples)) shows that these are comprised largely of Co-60 and Fe-55, with ((a "best fit")) Fe-55:Co-60 ratio of approximately 0.2 (0.21 +/- 0.13)(TU92).

((The " average"value of the individual Fe-55:Co-60 ratios from these same 9 samples is 0.30. Accounting for isotopic decay from the time of collection until March,1994 (the estimated date of license termination), the average value becomes 0.20. This last number is used to adjust Individual measurements, as described in Section 5.0, to account for the Fe-55 not detected by survey instmments.)) Laboratory analysis of plant corrosion product deposits has not identified the presence of reactor-produced alpha emitters above lower limits of detection.

3.3 Organization and Responsibilities An organization, identified as the Termination Survey Section of the Radiological Controls Division, has been created within the LIPA - Shoreham Decommissioning Project organization for planning and implementation of the termination survey.The organization and responsibilities of the Termination Survey Section and the interfaces and responsibilities for all other elements of the Decommissioning Project Organization for the termination survey are described in the Termination Survey Program Description (LIPA92).

3.4 Training 3.4.1 Technician Qualification A job qualification category for termination survey technicians will be -

established under the existing Shoreham Station " Health Physics Technician l

Selection, Training and Qualification Program" procedure. The training and qualification acceptance criteria from this procedure will be adopted. The training willinclude classroom and functional job performance training on termination survey procedures and specialized instmmentation. The training and qualification process for individual technicians will require from three to five days to complete. Termination survey technicians will generally be j

selected from the pool of technicians who have previously been qualified to -

perform HP responsibilities on the Shoreham Decommissioning Project.

j 3.4.2 Classroom Training Classroom training includes: an overview of the Termination Survey Program, instrumentation, and procedures. The overview willcover termination survey i

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Termination Survey Plan Rev. I objectives, survey methods, the role and responsibilities of termination survey technicians, the importance of personnel safety, termination survey quality assurance, the Termination Survey Plan and program implementation.

3.4.3 Functional Training Functional training will involve hands-on performance of principal HP technician termination survey tasks. A survey of a typical (( structural and system)) survey unit will be performed by each technician under the surveillance of a qualified instructor.

3.5 l2boratory Services Laboratory radioanalytical services of the Shoreham Nuclear Power Station Radiochemistry Section ((and/or Health Physics Section)), ((both within the))

Radiological Controls Division willbe used in support of the termination survey.The on-site capabilities include gamma spectroscopy (GeLi) of filters, smears and bulk samples; liquid scintillation; gas proportional counting; (( gross beta-gamma counting of nnears; and gross alpha counting cf smears.)) ((Both Sections operate)) under approved QA programs and procedures. (( Additionally,)) a contract isin place with a qualified vendor for specialized radiological analysis of samples on an as-needed basis. Vendors are selected in accordance with the requirements of the LIPA QA Manual, Appendix N (LIPA92a).

3.6 General Survey Plan The termination survey is implemented at the individual survey unit level. Three categories or types of survey units have been established: 1) structures, which include building interiors, 2) plant systems and 3) outdoor areas. These categories combine survey units into groups with similar physical characteristics. The survey is planned for measurements to be taken for each survey unit independently. The measurement intensity of each survey unit is based upon its classification as affected or unaffected.

Due to the large scope of the termination survey and the requirement that some survey activities be conducted in parallel with decommissioning work, a systematic approach is necessary. Further, it is essential that key interfaces between survey activities and other decommissioning work activities be identified.

The termination survey planning and implementation process for each survey unit involves the following steps: 1) initial classification; 2) history file preparation and classification review; 3) turnover for termination survey; 4) walkdown; 5) survey design; 6) preparation of modification packages (primarily for plant systems surveys);

7) preparation of work requests and scheduling; 8) preparation of final survey instructions; 9) physical support activities such as crection of scaffolding, system tagout and system breaches for system surveys; 10) performance of the survey; and

11) post survey restoration and control of surveyed areas (isolation of systems after survey completion). These are described in the following paragraphs.

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Termination Survey Plan Rev.1 3.6.1 Initial Classification The initial classification of the facility into "affected" and " unaffected" areas provides an overall planning basis for the termination survey. It was conducted using results from the Shoreham Site Characterization Program (LILCO90a) and the recommendations of experienced Shoreham personnel using the classification criteria contained in Appendix A, Survey Design Guidelines. The classification status of all survey units is maintained in the Termination Survey Classification Description, which is controlled ' by a procedure of the same title.

3.6.2 History File Preparation The history file is a compilation, in a standardized format, which summarizes the operational and radiological history of eacn survey unit included in the termination survey. Preparation of the history file involves review of the system description, plant operating records, the Shoreham Characterization Report (LILCO90a), radiological surveys and other :xlevant information.

Specific operating history which could affect the radiological status is sought.

in this review. The purpose of this process is to provide a substantive basis for the survey unit classification, and hence the level of intensity of the termination survey.

The history file contains a summary description of the survey unit ((and,)) for system history files, summarizes relevant operational data. Relevant operational data includes operating lineups to radioactive systems, and other events which could affect the radiological status. Similarly, for structures and outdoor areas, the (( extent of radioactive materials involvementin the area))

(if any) is summarized.

Possible outcomes of the review are: the initial classification is verified, or it is modified to reflect the more thorough evaluation. Additionally, the review may suggest specific areas of a structure or components of a system which should be highlighted in the final survey. The review and conclusions are documented in a checklist. The history file also identifies the sources.of information used. It may contain summaries, excerpts or complete documents which are useful for survey design. The system history file and its preparation are described in a Termination Survey procedure.

3.6.3 Tumover for Termination Survey Prior to acceptance of a survey unit (structure, system or outdoor area) for-the termination survey, a number of conditions must be satisfied.

Decommissioning activities are completed, all tools are removed, housekeeping and area cleanup is completed, decontamination of affected stmetural areas and system residual components is completed and verified by 3-4

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Termination Survey Plan Rev.1 I

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operational radiological surveys,and scaffolding needed to be left in place for termination survey isidentified. Radiological surveys verifying the status of the area, if a structure, and remaining system components, if a system, are provided to the Termination Survey Section. Turnover and control of systems, structures and outside areas is controlled by a Termination Survey procedure.

3.6.4 Walkdown The walkdown is a key activity in the preparation of the survey design. For systems, it includes review of system flow diagrams and piping drawings, and physical walkdown of the system. Structures and outdoor areas are also physically walked down. A principal objective is to assess the physical scope of the survey unit and to identify potential breakdown into subunits. Special access needs are identified. Potential support requirements for_ conduct of surveys are identified, such as scaffolding, component disassembly, interference removal, engineering modifications, electrical tagout and system alignment to provide access for surveys. Safety concerns, such as access to confined spaces, high walls, and ceilings, are identified and resolved. It is noted that for survey units involved with decommissioning activities, the walkdown is best completed when the final configuration is known, usually near or after the completion of decommissioning work. Early information is available through Decommissioning work packages and material takeoff lists and drawings.

3.6.5 Survey Design The survey design results in the identification of the locations (grid blocks, system components) to be surveyed and the type of radiological measurement or sampie to be collected at each location. The design is based upon the guidelines in Appendix A.The design of the survey for individual survey units is prepared in accordance with a Termination Survey procedure.

3.6.6 Engineering Once the survey design is prepared, engineering review and support requirements are developed. In the rare instances where engineering modifications are required for surveys,the modification packages are prepared and the design reviewimplemented through approved engineering procedures.

3.6.7 Work Planning and Scheduling Upon completion of any required engineering review, the physical modifications are specified. Field work is implemented via the Maintenance Work Request (MWR) process. The MWRs identify all components which require opening, identify all modifications, indicate restoration requirements and indicate whether a system is to be isolated or retumed to service. The 3-5

1 Termination Survey Plan Rev.1 MWR process is also used to initiate support work and tagouts necessary for surveys of structural and outdoor survey units. The survey unit support work is then placed upon the Project work schedule for performance.

3.6.8 Survey Instructions The survey instructions are provided to the Lead HP technician assigned responsibility for the specified survey unit. They specify the number and type of radiological measurements to be taken at each location or component identified in the survey design. The instructions identify _ smear samples and other samples to be collected. The survey instructions identify those survey points (components or other specified locations) where QC verification surveys are required. The survey instructions are prepared by the designated Termination Survey Radiological Engineer in accordance with a Termination Survey procedure.

3.6.9 Field Support

' Die MWR identifies each component or survey location requiring support work and tagouts. In cases where special surveys are required such as components, embedded piping, or large tanks which are classified as affected, other preparation work may be required. This may include gridding oflarge tanks once access is provided and safety precautions have been satisfied.

3.6.10 Survey Measurements Termination survey measurements are conducted in accordance with Termination Survey procedures and the specific survey instructions for the survey unit. The measurements include surface scans, direct measurements of surface contamination, smean su../.. a for removable surface contamination and gamma exposure rate measurements. The measurements are discussed in Section 4.0. Prior to conducting the survey, a walkdown is conducted by the cognizant Termination Survey Radiological Engineer and the Lead HP technician to verify the survey locations and the details of the instructions.

3.6.I1 Restoration and Isolation

a. Systems After survey measurements have been taken, reviewed and approved,_

and QC verification sur/ey measurements have been completed in system survey units, the system is restored and components are

- replaced as specified in the MWR. If indicated in the hnVR, the system is isolated to protect against recontamination. Isolation ~ and control of plant systems after termination survey is performed under a specific approved procedure.

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Termination Survey Plan Rev.1 It is noted that many plant support and service systems will be returned to service after completion of termination survey ineasurements. Examples are: compressed air, heating and cooling, ventilation and fire protrtion. When a system is required to remain in service, administrative controls will be used to minimize the possibility of system contamination. These include, but are not limited -

to, surveillance activities to ensure that the system is not aligned or operated in a manner which could compromise termination survey results.

b. Structures and Outdoor Areas After measurements are completed in structures and outdoor areas,

(( appropriate controls are used)) to prevent or minimize possible contamination. This is controlled by an approved station procedure.

(( Numerous structural survey units have been defined within the Radiological Controlled Area (RCA) of the Shoreham facility. These include all of the stnicta-3 survey units which comprise the Reactor Building, the Turbine Building and the Radwaste Building, representing the majority of the areas within the power block. As sufficient numbers of surveys art completed in contiguous RCA survey units (with completion of the surveys being indicated by complete, approved release records) to allow manageable reduction of the RCA boundaries, these reductions will be made. Removal of such areas from the RCA provides additional assurance that material containing radioactivity is not used or transported through previously surveyed areas.))

3.7 Quality Assurance 1

3.7.1 General Provisions As indicated in the LIPA Decommissioning Plan and in the Termination Survey Program, quality assurance for the termination survey is subject to the 1

provisions of the Decommissioning Program Quality Assurance Manual (LIPA92a). In addition, the Termination Survey Program itself has established quality control measures as an integral part of the program. Principal measures established to meet quality objectives are:

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a. Selection and Training of Personnel i

Qualification requirements and responsibilities are established for key personnel performing termination survey tasks. A technician training and qualification program has been established which includes classroom trair.ing and job-functional training.

Training and qualification records are maintained on all technicians selected for the termination survey.

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Termination Survey Plan Rev. I

b. Instrumentation Selection, Calibration and Operation An evaluation and testing program was conducted to select radiation detection instrumentation for the survey. Instrument calibration is performed either under approved SNPS calibration procedures using calibration sources traceable to the National Institute ofStandards and Technology (NIST), or by qualified vendors with the results traceable to NIST. Measurements are performed using approved written procedures for each instrument. Control ofinstruments is established '

by an instrument control procedure.

c. Survey Documentation Each termination survey measurement isidentified bydate, instrument, technician, location, type of measurement, and mode of instrument operation.

d. Quality Contro' - Verification Replicate measurements are performed independently on a selected sample of survey measurements on an ongoing basis,

e. Written Procedures.

All termination survey tasks which are essential to survey data quality are controlled by procedures reviewed ((and approved)) by the LIPA i

Site Review Committee.

f. Mockup of Procedures and Processes Dry nms and mockups are performed to test principal procedures and methods prior to implementation in the field.

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g. Chain of Custody Written procedures establish responsibility for custody of samples and survey data between the point of measurement or collection until final-j results are obtained.

h. Records Management Generation, handling and storage of termination survey design and data packages is controlled by an approved procedure.

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Termination Survey Plan Rev.1

i. Data Management Software Computer programs generated for processing of survey measurement data shall be tested and verified.

j. Independent Review of Survey Results The release record of each survey unit is given independent review prior to acceptance for final management approval.

k. Control of Surveyed Areas and Systems 8

Administnative (i.e., procedural) and physical controls are established on areas and systems to minimize the possibility of contamination subsequent to the survey.

1. Control of Vendor Supplied Services Essential services,such asinstrument calibration and laboratory sample analysis, will be procured only from qualified vendors, in accordance with an approved procedure whose internal QA programs are subject to LIPA audit.

3.7.2 Termination Survey Quality Control Procedure A Termination Survey Quality Control procedure controls essential quality assurance activities not addressed in other procedures. These include:

a.

conduct of QC replicate sampling measurements, b.

routine verification of survey measurement data prior to j

acceptance for data processing, c.

control charts for individual instruments, d.

testing of computer data calculation programs, validation of historical opemtional survey data used as final e.

survey data, f.

documentation of surveys, and g.

custody ofinstruments, samples and measurement data.

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Termination Survey Plan Rev. I i

3.8 Schedule The termination survey detailed schedule is maintained within the Project Schedule by the Project Controls Division of the Finance and Administration Department and the Work Planning Section of the Operations and Maintenance Department.

The termination survey is scheduled to be completed in several major phases which encompass distinct portions of the facility. ((The first phase included only the survey of the SNPS main turbine. The second phase willinclude outside area survey units, structural survey units outside the power block, and systems and structural survey units within the Turbine Building. The third phase will include systems and structural survey units within the Reactor Building and the fourth phase will include systems and structural survey units within the Radwaste Building. He final phase -

includes all remaining survey units, the majority of which are those areas impacted by the removal ofirradiated fuel from the facility.)) Upon completion of each phase the release records will be compiled and the survey units covered will be available for NRC verification surveys. All except the final phase of the survey are scheduled for completion by Octoh-1,1993 =4h the final phase m he completed following removal of the irradiated fuel from the facility. The current schedule date for completion of fuel removal is (( December,1993 with final surveys and reporting to occur in early 1994.))

3.9

(( Final)) Survey Report

((Re Final Report)) will be prepared for submission to the Nuclear Regulatory Commission ((to)) meet the intent of Regulatory Guide 1.86(USAEC74) for final survey reporting. The Final Report will follow the guidance of Draft NUREG/CR-5849 (BE92) regarding content. ((The Final Report will be submitted in stages with an updated report prepared foreach of the majorsurveyphases discussed in Section 3.8. Each edition of the Final Report willinclude the survey measurements obtained during the appropriate phase and evaluation of the results. An update to the overall survey status report as well as other documents which comprise the Final Report will also be provided. The full outline of the Final Report is described in Section 6.0.))

9 3 - 10

Termination Survey Plan Rev.1 4.0 Survey Plan and Procedures 4.1 General The design approach of the Shoreham termination survey is considerably affected by the final configuration of the facility, which is largely intact with the majority of equipment left in place. The Reactor, Turbine and Radwar2 Buildings contain over 200 equipment rooms. These rooms contain approximately 80 plant piping systems and the majority of the systems occupy multiple rooms.

The majority of the survey effort is confined to the areas contained within the Reactor and Radwaste Buildings and those areas in the Turbine Building where radioactive materials were handled. These are classified as affected areas. The remainder of the areas within the scope of the survey are classified as unaffected. All radioactive material handling, movement and storage on the site has been controlled under approved procedures. No detectable activity of SNPS origin has been detected on the site grounds or environs following extensive measurements of site soil and outdoor surfaces in the Si:e Characterization Program (LILCO90a) and in the REMP program prior to, during, and subsequent to Shoreham operation. The survey plan and procedures are designed accordingly, to focus ((primarily)) on remaining plant structures and systems in the affected areas. Instrumentation has been selected and measurement procedures developed to detect and measure surface contamination levels (primarily Co-60) and gamma exposure levels in these affected areas.

4.2 Instrumentation Radiation detection and measurement instrumentation for the termination survey has been selected to provide reliable operation and adequate sensitivity to demonstrate attainment of the release criteria. An evaluation has been conducted of instruments and detectors produced by several manufacturers. Detectors have been selected based upon detection sensitivity, operating characteristics and expected performance in the field under conditions of use. The detectors selected and their detection characteristics are summarized in this Section. Recording instruments (survey meters) for use with these detectors have also been evaluated. Instrumentation to be used for gamma exposure rate measurements and special purpose measurements is also described.

4.2.1 Instrument Description The principal instruments selected for termination survey measurements are identified in Table 4.1, Termination Survey Instrument Summary. The detectors used for total surface contamination monitoring will be for the most part operated with data logging survey meters.

I 4-1

4

- Termination Survey Plan Rev.1 4.2.2 Detection Sensitivity The detection sensitivity of the detectors selected for surface contamination measurements has been evaluated. These results are summarized in Table 4.2, Detector Sensitivities. The minimum detectable activities are calculated using Equation 4.1. The minimum detectable activity, or MDA, is dependent on several factors: detector efficiency, background count ste, counting times for background and for background plus source count. The results are shown for the principal instruments used for beta-gamma direct surface measurements. ((These are " nominal" values using typical' background levels for ' each type. of detector.)) Smear counters for measurement of removable surface activity, of modern design (anti-coincidence low-background), have nominal-beta-gamma 2

MDAs of approximately 100 dpm/100 cm, and alpha MDAs of approximately 2

20 dpm/100 cm. The gamma exposure rate measurement instrument sensitivities in the normal modes of operation are:

Pressurized ion chamber:

1 R/hr Bicron microRem meter:

2-3 rem /hr.

The detection sensitivity of the pressurized ion chamber can be lowered, if.

necessary, by using the device in the integration mode.

j l

4-2

Termination Survey Plan Rev.1 The minimum detectable activity for surface beta-gamma measurements is estimated using the following equation:

-((

(k;k)

S+B s

(4.1)

MDA(cq"

),1 t

3 E(100) where:

k, = critical value at the upper, one-sided [(100 - a)%]

confidence level (C.L.) (for normal statistics, k, = 1.645 at 95% C.L.)

k = critical value at the lower, one-sided [(100 - b)%]

b confidence level (C.L.) (for normal statistics, k = 1.645 h

at 95% C.L.)

))

S=

Sample (plus background) count rate (cpm),

B=

Background count rate (cpm),

Sample count time (minutes),

t,

=

3 Background count time (minutes), and t

=

E= Instmment detection efficiency,((cou nts per disintegration, j

and A = Detector sensitive area (cm2).))

((The MDAs shown in Table 4.2 are calculated using the above Equation 4,1 with the indicated values of k for the 95% confidence level and assuming the probability of Type 1 and Type 2 errors to be equal.)) As discussed in the Table I

4.2 footnotes, these MDAs represent detection sensitivities under static conditions with fixed geometries. ((During)) scanning type surveys, the detection sensitivity may be reduced. (('Iherefore)) threshold or practical detection limits have been empirically determined for each detector used in the scanning mode. This was done via a series of measurements in a scanning mode whereby the detector was passed over calibrated sources of various dimensions at an established scanning speed to determine an effective scanning " efficiency". The scanning MDAs were then calculated using equation 4.1 with the scanning efficiency substituted for. E, the efficiency term. These results are shown in Table 4.2 as the values in parentheses.

4-5

L Termination Survey Plan Rev.1 4.2.3 Calibration and Maintenance Instruments and detectors used in the Termination Survey will be calibrated and maintained at Shoreham Nuclear Power Station according to approved Station procedures. Detectors for surface beta-gamma measurements are calibrated using NIST traceable Co-60 sources. Specialized instruments, for example, the pressurized ion chamber, are calibrated by the vendors.

4.3 Survey Plan 4.3.1 Classification Each survey unit is classified into one of two (( categories)) which identifies each unit as "affected" or " unaffected". Units identified as affected have a possibility of-containing residual contamination and those identified as unaffected have a very low probability of residual contamination. Classification of individual survey units is based on the site characterization study (LILCO90a) and the history of mdioactive materials involvement or potential for contamination of the survey unit. Criteria for classification of survey units are given in Appendix A.

4.3.2 Reference Grids Gridding consists of dividing areas to be surveyed into regular subdivisions for the purposes of identifying survey locations and for use as guides for scanning surveys.

For surveys designed on the basis of prescribed sampling plans, whether random or systematic, gridding provides a means of selecting individual measurement locations.

Mapping is used to document measurement locations. Detailed guidance for gridding is contained in Appendix A. Figure 4.1 shows grid placement in a structural survey unit classified as affected (an equipment room). Placement of grids in structures is directed by a specitic work instmetion.

4.3.3 Grid Maps Grid maps are used for survey design and to document the measurement locations.

Figure 4.2, Shoreham Decommissioning Termination Survey Grid Map, shows a typical grid map of a structural survey unit. It shows the floor and walls up to two meters. This map is identified as the base map for the survey unit. Additional grid maps may be prepared for subunits as needed to plan and document surveys of subunits.

l 4.3.4 Grid Numbering Grids are uniquely identified by an ID code or number. The numbering convention is to start at the reference location, ((usually the southwest corner,)) and proceed sequentially west to east numbering each row on the floor from south to north in a continuing sequence. Grids are numbered in sequence for each subunit similarly as -

4-6

Termination Survey Plan Rev. I described for the floor numbering. An individual grid block has a unique identification code as determined by its survey unit (or subunit) ID and the number of the grid block within that unit. The numbering convention is illustrated in Figure 4.2.

4.3.5 Survey Maps Survey maps are prepared to document the details of survey measurements in circumstances where grid maps are not practical. Survey maps are typically prepared to document detailed surveys of piping and system components.1 These may be prepared by the technician who performs the survey, or may be specially prepared by direction of Termination Survey Radiological Engineers for detailed surveys of complex components.

4.3.6 Surface Scans Surfaces will be scanned using detectors according to the prescriptions in Appendix A. (( Scanning surveys are performed to screan large areas efficiently i

to search for areas above the average total surface contamination release criteria and to detect " hot spots", i.e., localized areas above the maximum total surface contamination release criteria. The scanning methods utilized (instrument and survey technique) will be capable of detecting 75% of the average total surface 2

contamination release criteria, e.g., 3750 dpm/IO0 cm for total surface beta-gamma contamination. When scanning surveys indicate that contamination levels above the average total surface contamination release criteria may be present, appropriate follow-up investigation and/or measurements will be performed.))

4.3.7 Surface Activity Measurements Surface activity measurements are taken at measurement locations selected in accordance with the survey design guidelines in Appendix A. The general set of measurements is direct beta-gamma and removable beta-gamma. In areas and systems identified as alpha affected, direct surface and removable surface alpha measurements are taken.

4.3.8 Exposure Rate Measurements Gamma exposure rate measurements, when directed by survey design guidelines, are taken at one meter from surfaces at all measurement locations in structures and 3

It should be recalled that system component and equipment exterior surfaces are included in the survey of the structural survey unit in which they reside. The component interior surfaces are surveyed iu the survey of the system survey unit to which the component belongs. Survey maps of individual components may thus be prepared for each type of survey.

4-7

4 Termination Survey Plan Rev. I outdoor areas. In locations where it is not physically possible to locate an instrument one meter from the surface, gamma exposure rate measurements are not taken. The methods for gamma exposure rate measurements are discussed in Section 4.4.3 below.

4.3.9 Soil Sampling Soil samples will be collected in accordance with Section 7.2.5 of Appendix A.

Additional soil samples will be collected in the Termination Survey if a contamination event or spill occurs, or survey measurements indicate outdoor areas of elevated activity above applicable release criteria limits.

4.3.10 Special Sampling and Measurements

a. Sampling of Sediment and I.cose Material Samples of loose paint, dust or other sediment are collected for laboratory analysis as part of biasea sampling and measurements. Such samples may be collected in drain receptacles, sumps, and other catchments in affected areas.

Selected storm drain catchments may be sampled in accessible locations on the site. These samples are qualitatively analyzed by gamma spectroscopy for i

Co-60.

i

b. Embedded Piping Surveys t

Specialized measurements will be taken to demonstrate that normally inaccessible piping, e.g., embedded piping is below the release limits for surface contamination. This includes the use of calibrated detectors extended into piping runs in a controlled manner and the use oflocation encoding and data acquisition equipmer.t to document the measurements.

4.4 Background Level Determination 4.4.1 General Requirements Backgrounds are established for each type of instrument to be used for surface contamination and gamma exposure rate measurements. Surface entamination measurements include total surface beta-gamma and alpha, and removable surface beta-gamma and alpha. Gamma exposure rate measurements require determination of the gamma background response of detectors at one meter from surfaces. The background responses of the pressurized ion chamber and microrem instrument::

must be determined. In addition, backgrounds are determined for specialized detectors and detector systems. These include: large area detectors for floor monitoring, detectors for surveying piping interiors (multiple GM and Nal scintillators) and scintillation detectors used as area scanners.

4-8

Termination Survey Plan Rev. !

4.4.2 Objectives of Background Determinations

)

The objectives of background determinations for Shoreham Decommissioning Termination Survey measurements are to:

a. establish the reference background mean values for each type of instrument-de*ector used in the Survey;

b. assess the variability in background responses for principal detectors under different applications and conditions of use; and

c. determine the need for correction factors or special measurements to establish the background for Termination Survey measeements in specific locations.

4.4.3 Background Measurements Several locations have been identified which will be used to obtain measurement data for establishing backgrounds for each type of measurement. For direct surface and gamma exposure rates, several buildings have been identified which are of similar construction to SNPS facilities (reinforced concrete). These are in the vicinity, but not involved with Shoreham operations or having any history of radioactive materials use. One on-site building, the Colt Diesel Generator building, will be used due to its similarity in construction to the Reactor, Radwaste and Turbine Buildings.

Several off-site buildings have been identified which contain reinforced concrete construction. Principal candidates are: a fire house, a post office and a school in the Shoreham-Wading River community. Background determinations for each type of Termination Survey measurement will be performed as described below.

a

a. Direct Surface Beta-gamma Measurements -

To determine background for direct surface beta-gamma measurements, a series of counts of at least one minute duration will be taken in sequence.

The counts are accumulated by a scaler in the preset time accumulation mode. At least two locations within each selected building will be measured.

Outdoor background measurements will be performed on types of surfaces where beta-gamma surface measurements may be taken in the Termination Survey. These include concrete pads, loading docks, pavement, roofs and HVAC exhausts. A protocol similar to that described above will be used.

b. Direct Surface Alpha Mosurements The background response of alpha survey instruments is small in comparison with the response when contamination is present. Background means, standard deviations and standard errors of the mean will be established in at least two locations in each of the buildings selected.

4-9

Termination Survey Plan Rev. I

c. Removable Surface Beta-gamma Measurements Background determinations of beta-gamma smear counters are made by taking a series of counts of a blank smear. Background determination is performed in accordance with an approved procedure.

d. Removable Surface Alpha Measurements The alpha background count rate in smear counter proportional detectors is also very Inw. Mean values, standard deviation and standard errors of the mean will be determined from the data obtained using an approved procedure.

c. Gamma Exposure Rate Measurements A Reuter-Stokes pressurized ion chamber is used to establish gamma dose rate background characteristics at the Shoreham site for purposes of l

demonstrating that residual contamination levels are below 5 R/hr above background (measured at one meter). It is used as the reference instrument for establishing the pR response of portable microrem meters. The latter are used for the bulk of the Termination Survey gamma exposure rate measurements. A series of repeat measurements will be taken at various elevations in the buildings selected for the background study.

i A reference value for the outdoor gamma exposure rate has been established for the Shoreham site. It is based upon a series of pressurized ion chamber measurements taken one meter above the ground surface prior to the startup of the Shoreham reactor. The established mean value is 8.3 R/hr, with a standard error of the mean of 0.5 R/hr (EG&G84). A series of outdoor measurements will be taken with a pressurized ion chamber in the vicinity of the Shoreham site to confirm or update this result, as the case may be.

A series of paired measurements using the pressurized ion chamber and microrem meters will be performed to establish a correlation between the microrem meters and the pressurized ion chamber. A regression analysis will be performed to establish a " correction factor" for converting microrem measurements to R/ units.

f. Specialized Measurements It has been observed that detector background is affected when detectors are inserted inside massive components or within piping embedded in concrete.

This is particularly noticeable when Nal detectors are used. Thus it will be necessary either to provide a mockup of an embedded pipe, for example, or to develop empirical correction factors for backgrounds when surveying such equipment. To this end, a series of background measurements will be 4 - 10 1

i

Termination Survey Plan Rev.1 i

performed in' embedded piping and in large components which can be ascertained to be free of radioactive contamination.

((g. Verification of Background Measurement Population Each population of background measurements described above will be analyzed using Equation 8-22 of draft NUREG/CR-5849 (BE92) to i

demonstrate that the number of measurements in the data set is adequate to support the population statistics.))

t 4.4.4 Documentation And Control of Background Measurements Background measurements are collected and recorded in accordance with a Termination Survey procedure.

4.5 Sample Analysis As indicated in Section 3.5, an in-depth sample analysis capability is available for the Termination Survey. Routine samples of sediment, paint chips and debris will be qualitatively evaluated for the presence of Co-60 via gamma spectroscopy. The need for additional sampling and analysis will be determined on the basis of this initial evaluation.

1

?

+

i t

4-11

Figure 4.1 View of Structural Survey Unit Showing Grid Placement x

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DESCRFTION : *8* RECOMBD4ER ROOM a,

TURBINE BUILDING elev.15' GRID EIZE 1 X 1 METER I

Termination Survey Plan Rev. I 5.0 Data Interpretation All measurements ((are)) converted to the appropriate units for comparison with release criteria limit values. Surface activity measurements ((are)) converted to units of dpm per 2

100cm. Gamma dose rate measurements ((are)) converted to exposure rate units of pR/hr and the background value subtracted to obtain ((the)) net exposure rate. These calculations

((are)) performed using equations given in Section 8.0of draft NUREG/CR-5849 (BE92),

(( indicated below.)) (( Additional calculations are made to determine a "criticalvalue"for both total and removable surface activity measurements, to adjust these total and removable surface activity measurements for the presence of the undetected Fe-55 isotope whereappropriate, and to determine the measurement specific "actionlevel" which indicates the need for additional investigations and/or measurements.)) Average values for each survey unit (and/or subunit) ((are)) compared with the release criteria values. Confidence intervals ((are)) estimated for mean values of each survey unit (and/or subunit) at the 95%

confidence level. (( Figures 5.1 through 5.5 describe the flowpaths followed to convert, calculate, analyze and interpret the data for the four (4) basic types of survey measurements made for the termination survey.))

5.1 Conversion of Measurements to Reporting Units 5.1.1 Direct Measurements - Total Surface Activity Measurements of(( total)) surface contamination activity are convened from observed gross counts per minute to net activity concentration by subtracting the background counting rate for the instrument and correcting the net count 2

rate for geometry and efficiency to obtain results in dpm/100 cm units.

(( Total surface activity measurement results are reviewed to ensure that the applied background values are appropriate,i.e.,not "too hlgh"so as not to potentially " mask" areas of contamination.))

((The followingcalculations and conversions are applicable to measurements of total surface activity:

a. Unit Conversion ECPm - bepm dpm ad (5.1)

A E (100) where:

2 total surface activity [dpm/100 cm ),

dpm.

=

detector reading in gross counts per gepm

=

minute (assumed to be entirely due to Co-60 activity),

5-1

Termination Survey Plan Rev. I detector background in counts per bepm

=

minute, detector efficiency in counts per E

=

disintegration, and area of detector sensitive region (cm2).

A

=

b. Calculation of " Critical 12 vel", L, (in units of dpm/100 cm )

2 L, = 1.96 lS! + 5?

(5.2)

^

E (100) where:

Critical level, d..~ ming measurements L

=

e above normal background distribution, and counting error in sample measurement, or s,

=

5* =.f.2 g

where:

measurement total counts c

=

(sample plus background),

and measurement count time.-

t

=

counting error in background sh

=

measurement, or B

b " }t,

where:

total background counts, B

=

and background count time.

t

=

g 5-2 l

Termination Survey Plan Rev,1 detector efficiency in counts per E

=

disintegration, area of detector sensitive region (cm ),

2 A

=

and 97.5* percentile value of a one-tailed 1.%

=

normal distribution.

c. Adjustment for Fe-55 Measumments converted using Equation 5.1 which exceed the " critical level" as determined by Equation 5.2 are reported as having surface activity above background levels. This activity is assumed to nsult from residual Co-60 contamination. Therefore, adjustment for the undetected presence of Fe-55 is made as follows:

(5.3) dpmg = f (dpm) where:

surface activity concentration adjusted to dpmg

=

2 include Fe-55 [dpm/100 cm ], and surface activity concentration from dpm,

=

application of Equation 5.1, and f

numerical factor;

=

[ 1 + average Fe-55/Co-60 ratio = 1.20].

d. Calculation of " Action Level", La (in units of dpm/100 cm2)

M +4 (5.4)

La=3 E (100) where:

La Action level, defining those measurements

=

considered significantly above background (and assumed to include Fe-55). In survey units (or subunits) classified as

" Unaffected Areas", measurements above this level require additional investigation, 5-3

Termination Suney Plan Rev.1 including additional measurements and possible nelassification of the sun'eyunit (or subunit).

s, s3, E, and A are as defined for Equation 5.2,and 8

3 the 99.7 penentile value of the standard

=

normal distribution.I

]

5.1.2 Removable Contamination Measurements Measurements of removable surface activity are converted from gross count 2

rate to units of net dpm/100 cm by subtracting the background count rate of the smear counting detector and correcting the net count rate for detector geometry and efficiency.

((The following calculations and conversions are appropriate to measurements of removable surface activity:

a. Unit Conversion - determined by using Equation 5.1.

b. Calculation of "Criticallevel",L,-

determined by using Equation 5.2.

c. Adjustment for Fe-55 Similar to the treatment of total surface activity measurements, measurements of removable surface activity which exceed the " critical level" are adjusted to include the undetected Fe-55 activity using Equation 5.3.

d. Calculation of "Actionlevel",La For removable sviface activity measurements, the " action level",La,is 2

established at 250 dpm/.100 cm for all measurements. This value corresponds to 25 perrett of the removable residual contamination release criterion as specified in Table 3.1.

In survey units (or subunits) classified as " Unaffected Areas", measurements above this level require additional investigation, including additional measurements and possible reclassification of the survey unit (or subunit).))

1 I

The three (3) sigma coefficient represents the 99.7* percentile of the standard normal distribution (two-tailed), taken from NUREG/CR-2082, " Monitoring for Compliance with Decommissioning Termination Survey Criteria", p.132.

1 l

5-4 i

y

~

\\

-l Termination Survey Plan Rev. I measurements and possible reclassification of the survey unit (or -

subunit).))

5.1.3 Gamma Exposure Rate Measurements

)

Most gamma (( exposure rate)) measurements are taken with.microrem meters. A correction factor ((is)) applied to each reading to convert to units' of pR/hr, as discussed in paragraph 4.4.3.e. The-gamma exposure rate i

background is subtracted from the gross R/hr value to obtain net (( gamma)) _

exposure rate in units of pR/hr.

(( Gamma exposure rate measurement results are reviewedto ensure the applied background values are appropriate,:

i i.e.,not "too hlgh"so as not to potentially " mask" areas of elevated gamma exposure rates.))

j l

((The following calculations and conversion are applicable to gamma I

exposure rate measurements-(

a. Unit Conversion j

pR, q ( phm) _ (g)N (5.5) hr hr hr where:

1

(

correction factor, determined as described 1

q

=

in paragraph 1.4.3.e.

b. Calculation of "ActionI2 vel",La For gamma exposure rate measurements, the " action level", La, is i

established at 5 R/hr above background for all' measurements.

Measurements above this level require additional investigation, t

including additional measurements, and a calculation to demonstrate the exposure rate averaged over a 10 m2,,,, centered on the measurement location exceeding La does not exceed 5 pR/br above-background.))

i 5-5 l

Tennination Survey Plan Rev.1 5.2 Comparison With Release Criteria Limits The method outlined below will be used to demonstrate attainment of the release criteria limits.

5.2.1 Attainment of Release Criteria for Surface Contamination

a. (( Total Surface Activity (fixed plus removable contamination)))

2 Individual measurements:

Do not exceed 15,000dpm/100 cm (contaminated area not to exceed 2

100 cm ),

2 Population - random sampling:

Upper limit of confidence interval

(((Equation 5.6))) for the mean 2

value is below 5000 dpm/100 cm,

Population - biased sampling:

(( Upper limit of confidence interval (Equation 5.6) for the mean value is below 5000 dpm/

2 100 cm,jj i

b. Removable Surface Contamination 2

Individual measurements:

Do not exceed 1000 dpm/100 cm,

Population - random sampling:

Upper limit of confidence interval

(((Equation 5.6))) for the mean 2

value is below 1000 dpm/100 cm,

Population - biased sampling:

(( Upper limit of confidence interval (Equation 5.6) for the mean value is below 5000 dpm/

2 100 cm,)j 2

A population for Termination Survey purposes, refers to a survey unit (or subunit if so specified). More precisely, a population represents the collection of all possible values of a parameter, e.g., total surface contamination, being measured through a sample of its members.

5-6

Termmation Survey Plan Rev.1

((c. Calculation of Upper Limit of Confidence Interval 5'

(5.6) u, = x + tggh-where:

upper confidence limit of population mean, and u,

=

population mean value x

=

upper confidence level value (as obtained from t,g

=

Appendix B, Table B-1, of draft NUREG/CR-5849); df (degites of freedom) is equal to n - I and "a"is the false positive probability.

population standard deviation s,

=

number of measurements in the population n

=

))

5.2.2 Attainment of 5 microR per hour Criterion Individual measurements:

Net exposure rate does not exceed 10 R/hr.

Population - random sampling:

Upper limit of the confidence. interval

(( Equation 5.6))) for the mean net exposure rate does not exceed 5 R/hr, 2

"rhen averaged over a 10 m surface area.))

Population - biased sampling:

Upper limit of the confidence interval

(((Equation 5.6))) for the mean net exposure rate' does not exceed 5 pR/hr, 2

((when averaged over a 10 m area.))

5.2.3 Evaluation of Soil Sample Results Since soil contamination from Shoreham operations has not been detected in the Site Characterization Study (LILCO90a), or in the REMP Program, it is believed to be unlikely that detectable contamination will be found in the soil column on the site in the Termination Survey. As there is no limit or criterion for residual contamination in soil for release of the site for unrestricted use, soil radioactivity concentration measurements will be compared to REMP MDAs and historical REMP measurement result ranges 5-7

i Termmation Survey Plan Rev. I 1

t for individual isotopes. For gamma emitters where no REMP data exists, as-in the case of Co-60 in soil, ((the current NRC criterion is adopted and' risults below 8 pCi/gm average concentration in the top 15 cm of the ' soil column will be considered to be acceptable.))3 T

l t

't i

k i

't i

I

-i 3 The value of 8 pCi/gm in soil is applied to the total concentration of Shoreham-produced gamma <mitting radionuclides.

5-8 1

i l

. Figura 5.

TOTAL ~ SURFACE-CONTAMINATION DATA PROCESSING AFFECTED SURVEY UNITS

+

Conv t dem to dpm /100 cm' I

CeJculate catecal level. Lc. for each measueement Value NO Perform

~g addisonal 9

ourveys j

^

YES y

Adjust for Fe.55 Rernedleto h

Compare to Elevated Aree guideliries I

YES 15000 dpm /100cnf

?

NO Compere to guideline

( 5000 dpm /100 cm ' )

NOTES:

l Uet oil 2

5000 dem /100cm' -

O 1

d YES NO 3

ebove guideline-7 I

V Calculeton of local invoedgets background, eron everage Collect addisonal date 2

genwelly not (if necoseery)

M 80

+

g systems Calculate local eroe I

everage over 1 m'

'I above Lc Avg.

b YES 1

No

$000 dprn /100cm, 3

e 7

v Calculate summary stodouce. S.D C1 SU NO meste p

Mun criterte Col!ect addidonal 7

date ; recolculate i

l i

YES SU i

NO moete YES rose.

criterte V

7 Propero Final 5-9 e.

+

Figura 5-2 TOTAL SURFACE CONTAMINATION DATA PROCESSING v

UNAFFECTED SURVEY UNITS r

Convert data to dprn i 100 cm

• i Caiculate cridcal j

love.4, Lc, for each measurement

~

NO Reclaeolfy, rerned!ato if Lc necessesy and feeurvey 7

ao Affected survey unit A

YES Y

Adjust for Fe-65 Define extent of area ;

y Estabilah new subunit I

reclaeolficadon A

sedan level, La

-, eacs moaeurement to L a b

YES NO t

NOTES:

La e

V Uet all 1

enuouremente Guldeline value YES NO

?

<- 5000 dpm 100 crn'

?

y Evaluate background and measuremente; collect addidonal data (if necessary);

recalculats l

YES NO Le 1

s-7 Y

Calculate stadsdes :

Avg., S.D., C.L SU NO Mun criteria

?

YES V

Propera Final Data Report 5 - 10

1 Figura 5-3 j

=

REMOVABLE SURFACE CONTAMINATION DATA PROCESSING

{

+

Convert data to dpm /100 cm' l

Calculate enucal level, Lc, for each measurement Reclasalty, rernodiate (if necessary).

NO

~

resurvey as Affected L8 survey unit 7

YES y

Define ortent of m Adjust for Fe.55 estabiloh new sub unit p

if r - =ary i

W6W

^

surveys NO Affected YES S. U.

I Remediate V

V

^

Compare to Compare to guideline rectaselficadon 1

action level NO YES 250 dptn /100cm.

1000 dpm /100cm,

7 7

v YES NO inveedgate, cetain v

invest!gata, collect additional dets (if necessary)

)

YES 1000 dpm /100cm' 7

v v

(

250 dpm 100cm' NO 7

v Calculets summary

)

stagence, UCL 1

SU mesta yo Muu criteria

?

YES y

Prepare final dets report 5 - 11 o, e,

,.,.c-

- Figure 5 - 4 GAMMA EXPOSURE RATE DATA PROCESSING 1

Convert data to not uR/he l

Perform additional l

'"Y' Compere to A

elevated area guideline Remedlain I

A i

O YES 1

20 uR /hr 7

i NO I

compare to guideline value 1

YES A

NO

-1 5uR/k i

7 NOTES:

v 1

investigate background, Ust all Collect additional data 1

measuremente i

above guidelinee - !

+

1 C.iouisi. a.e,.ge e-, sis over 10 m '

Avg.

,YES 1

NO x

$ uR/hr

^

r 7

Y Calculats Avg., UCL I

UCL Collect additional VES A

data, recalculate 4 5 uR/hr NO uct 4

YES A

NO I

5 uR/hr 7

Y Release criteria satisfied,

Prepare final report 5 - 12

~i

- Figura 5-5 SOIL SAMPLE DATA PROCESSING

~

1. "*Y'I" individual

.)

t no.utts Soil Samples LLD's I

s n

susi.,

~'

Identify non.

backpound lootopes > LLD i

t Above Collect additional NO YES LLD samples

?

A Co - 60 o

above

'LD Remediate if 7

,,e.

YES V-Adjust for Fe - 55, Add Fe.55 amount i

?

V Sum all isotopes and compare to 8 pCl/ gm

.V i

um YES below NO t

a pCI/ gm 7

if

?

t Calculate Avg, UCL for all soil samples e

i UCL below NO

(

i 8pCi/ gm 7

um..:

7

@ us. sNPS REMP l

l

)

YES

"*" E"* d " *"

V

@ Popdation stanseum.

UCL, ce4culated only for l

Prepare data i w ine yuna..

oe.n is nps

.iussed report 3,,,,,,,,,,,,,,,,,,,,,,,

andwido.: s.u.

i 5 - 13 8.8W 05128#93 DMC Dnw 3

h

Termination Survey Plan Rev. I 6.0 Final Report Upon completion of ((each major phase of)) the Termination Survey, ((an updated)) Final Report will be prepared for submission to the Nuclear Regulatory Commission. This report will meet the intent of Regulatory Guide 1.86 (USAEC74) for final survey reporting. The report will follow the guidance of draft NUREG/CR-5849 (BE92) regarding content.

6.1 Topical Outline The Final Report will address the following topics. The report will provide adequate data and discussion of each topic to meet the intent of NUREG/CR-5849 (BE92). ((The following describes the format for the Final Report with regards to document volumes, topical outline and content:))

((

Volume I, Book 1 1.0 Background Information 1.1 Reason for Decommissioning 1.2 Management Approach 2.0 Site Description 2.1 Type and Location of Facility 2.2 Ownership 2.3 Facility Grounds 2.4 Facility Structures 2.5 Facility Systems 3.0 Operating History 3.1 Licensing and Operation 3.2 Processes Performed 3.3 Waste Disposal History and Practices 4.0 Decommissioning Activities 4.1 Objectives 4.2 Results of Previous Surveys 4.2.1 Site Characterization 4.2.2 Radiolo;tical Environmental Monitoring 4.2.3 Radiological Ernuent Reports j

4.3 Decontamination and Dismantlement Activities 4.4 Decommissioning Processes 5.0 Final Survey Methodology I

5.1 Sampling Parameters 1

5.2 Background Levels 5.3 Major Contaminants 5.4 Guidelines Established 6-1

l Termination Survey Plan Rev.1 5.5 Equipment and Techniques Applied 5.5.1 Survey Instruments and Equipment 5.5.2 Instniment Techniques 5.6 Survey Process 5.6.1 Survey Unit Classification 5.6.2 Reference Grids 5.6.3 Surface Scans.

5.6.4 Surface Activity Measurements 5.6.5 Exposure Rate Measurements 5.6.6 Soil and Sediment Sampling 5.6.7 Special Sampling 5.7 Survey Control 5.7.1 Quality Control and Quality Assurance 5.7.2 Personnel Training and Qualification 5.7.3 Instrument Calibrations 5.7.4 Custody of Data 5.7.5 Data Verification 5.7.6 Survey Records 5.8 Data Analysis and Statistical Evaluation Volume I, Book 2 6.0 Final Survey Findings 6.1 Data Results and Interpretation 6.2 Comparisons to Release Criteria 7.0 Summa. y I

Volume II, (Numerous Books)

Survey Unit Release Records 1.

Tabulated Results for Individual Survey Units 2.

QC Replicate Surveys 3.

Survey Maps Volume III, Book 1 Termination Survey Program Termination Survey Plan Implementing Procedures Volume IV,(Numerous Books)

Supporting Documentation 1.

Quality Assurance Audits 2.

Quality Assurance Surveillances

]

6-2

Termination Survey Plan Rev.1

((As discussed in Section 3.0,the Final Report will be updated and submitted upon completion of the various phases of the termination survey. The first of these reports contains the complete volumes, as described, with sufficient books included for Volumes II and IV for the extent of surveys completed. The second and subsequent editions of the Final Report consist of necessary updates to Volumes I and III, and additional books to be included in Volumes II and IV.))

(( Attachments and/or appendices are included with the Final Report to provide information which substantiates the survey findings and conclusions.

Such information includes, but is not limited to: Reports of Nuclear Quality Assurance Department (NQAD) audits and surveillances of the termination survey, quality control (QC) survey results, and survey unit release records (including applicable survey maps).))

6.2 Reporting of Survey Findings i

6.2.1 Summary

\\

Measurement results ((are)) reported at several levels of detail. A summary of the measurement results and overall conclusions showing that the facility meets the release criteria ((is)) provided. A tabular data summary ((is provided to)) show the results for each major category of survey unit:

structures, outdoor areas and plant systems. This tabulation (( identifies)) the number of survey units, the number of measurements of each type: total i

surface beta-gamma, total surface alpha, removable surface beta-gamma and removable surface alpha activity concentration, and gamma exposure rate.

Average values of surface contamination in units of dpm/100 cm'and upper limits of confidence intervals about the mean are reported ((for comparison))

to the release criteria surface activity limits in Table 3.1. A summary of gamma exposure rate measurements ((is presented by)) similar treatment, showing that the mean value is less than 5 microR/hr above the background

]

value.

l 6.2.2 Summary Data Reporting for Each Survey Unit

((Within the release record)) for each survey unit (and/or subunit), the number of measurements and the upper limit of the confidence interval about the mean (at the 95 % confidence level) ((are)) reported in tabular form.

These ((are))

reported in units of dpm/100 cm for each type of 2

measurement: total surface beta-gamma, total surface alpha, removable surface beta-gamma and removable surface alpha activity concentration.

Gamma exposure rate measurement results ((are)) reported showing the number of measurements and upper limit of the confidence interval'about the mean (at the 95 % confidence level) for each survey unit (and/or subunit).

The release limit value for each type of measurement ((is provided in)) the

(( release record)).

6-3 l

4

Terminnion Survey Plan Rev.1 Results of sampling measurements, e.g., sediment, paint, concrete, other debris, ((are)) reported ((in the release record)) for each survey unit.

Any portions ofindividual survey units ((found not to meet any of the various release criteria)) will((necessarily)) be remediated. ((The Final Report will identify all areas within the survey which required reclassification and/or remediation.

For each of these areas, the initiating survey results, investigation, corrective actions, and follow-up survey results will be provided.))

6.2.3 Detailed Data Reporting The result of each measurement tak.en in the termination survey ((are))

tabulated ((in the individual release record foreach survey unit)). Table 6.1 shows an example of a typical format for individual measurement tabulations for a structural survey unit. Results of alpha activity measurements ((are))

reported in a similar format for those survey units where alpha measurements are taken. Tables of similar format ((are used to report data)) for systems and outdoor survey units. (( Final data reports provide indication of individual measurements which exceed the " critical level", calculated as described in Section 5.0, and the adjustment for Fe-55 activity, where applicable. Furthermore, the release records for survey units classified as

" unaffected" provide a listing of individual measurements which exceed the

" action level", calculated as described in Section 5.0,and the results of the investigation of these measurements.))

6-4

i Termination Survey Plan Rev.1 Table 6.1 I

Termination Survey Detail Data Report l

page No.

1 Date: 04/07/93 SHOREHAM DECOMMISSIONING PROJECT Termination Survey Data Report Survey Unit ID. :SUO68 System Code: W23 Survey date 01/29/93 Name: CHLORINATION Building: MULTI BUILDING SYSTEM l

total surface activity (beta-gamma)

_____l____l_______l______j__________l_____l___l______l_____l_____

point lgcpmjbk_, cpm j eff ldpm/100cm2l Lc j>Lcl+Fe55 j Lr j>Lr 1l 33l 22 NO.017 "

647 l 855 l l

l1309 l

}

l l1184 5

23l 22 10.017 58 ' 773 '

e 6L 26l 22

'O.017 l 235 798 f

'1223 L 7l 31l 22

,0.017 529 839 L1285 u

11l 22l 22 l0.017 l 0

764 '

l 1171 12l 22l 22 10.017 l 0 l 764 1171 i 13l 29j 22 0.017 l 411 l 823

?

1260 L 17l 16l 22 0.017 l

-352 l 710.'

1088 18j 29l 22 0.017 l 411 l 823 L

1260 19l 21l 22 0.017

-58 l 756 l1157 l

23l 29l 22 O.017 411 l 823 q

l1260 24j 15l 22 0.017 l

-411 701 l1073 i

L i

25l 27l 22 0.017 l 294 807 1235 29 24l 22 10.017 l 117 781 1197 1

l 30:

17l 22 l0.017 l

-294, 720 l

1102 31 L 22l 22 l 0.017 l 0 ' 764 j 1171 1,35-27l 22 0.017 l 294 807 l 1235 l l

36l 41l 22 l0.017 l 1117 915 jX 1330 l1401 l 37" 28l 22 LO.017 l 352 815 l l1248 41 15l 22

'0.017 l

-411 701 l i

l1073 42L 24l 22 l0.017 l 117 i 781 l l

l1197 43l 20j 22 l0.017 l

-117 l 747 l

l1144 47l 21l 22 l0.017 l

-58 l 756 l

l1157 48l 32l 22 l0.017 l 588 l 847 i l

l1297 i

l l

6-5

i Termination Survey Plan Rev. I 7.0 References BE92, J. Berger, " Manual for Conducting Radiological Surveys in Support of License Termination", NUREG/CR-5849 Draft, June,1992.

EG&G84, EG&G Energy Measurements, "An Aerial Radiological Survey of the Shoreham Nuclear Power Station and Surrounding Area, Brookhaven, New York," EGG-10282-1043, prepared for the U. S. Department of Energy, March,1984.

LILCO90, Iong Island Lighting Company, " Updated Safety Analysis Report - Shoreham Nuclear Power Station," Docket No. 50-322, Rev. 4, December 1990.

LILCO90a, Iong Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990 (with addenda; June & Oct.1990).

LIPA90, Iong Island Power Authority, "Shoreham Nuclear Power Station Decommissioning Plan," NRC Docket No. 50-322, December 1990, as supplemented.

LIPA92, Long Island Power Authority, LIPA Nuclear Management Control Manual,

" Nuclear Organization Management Control Program for Decommissioning Termination Survey Program Description," PDXOM-01, February 1992.

LIPA92a, Long Island Power Authority, Quality Assurance Manual, Appendix N,

" Decommissioning Activities," June, 15, 1992.

MA90, F.H.C Marriott, "A Dictionary of Statistical Terms", Longman Scientific and Technical,1990.

NCRP85, National Council on Radiation Protection and Measurements, "A Handbook of Radioactivity Measurement Procedures," NCRP Report No. 58, Feb.1985.

TU92, M.

Tucker, " Technical Report on Radiochemical Analytical Results, Radionuclides, and Analytical Methods Affecting Termination Survey Plan Development," July 2,1992.

USAEC74, U. S. Atomic Energy Commission, Regulatory Guide 1.86, " Termination of -

Operating Licenses for Nuclear Reactors," June 1974.

USNRC92,

" Order Approving the Decommissioning Plan and Authorizing Decommissioning of Shoreham Nuclear Power Station, Unit 1," Docket No. 50-322, June 11,1992.

7-1

Termination Survey PL-m Rev. I 8.0 Glossary 2

[I' Action Level - A contamination level, denoted La (in dpm/100 cm, adjusted for Fe-55), used as the investigation threshold in unaffected survey units to evaluate the need for reclassification as affected. The action level is defined as:

2 Removable surface contamination measurements: 250 dpm/100 cm.

Total surface contamination measurements: the upper confidence limit at the 99.7 % confidence level, f3 sigma), of the net count distribution.

soil contamination: 6 pCi/pn.))

Affected Area - A designation assigned to a survey unit which indicates that the survey -

unit has a potential for containing residual radioactive contamination.

Aloha Affected Area - A designation assigned to a survey unit which indicates that the potential exists for alpha contamination.

Biased Sample - A method of selecting survey measurement locations which incorporates a non-random error, i.e., a method which selectively chooses locations for measurements which have a higher probability of contamination than those locations not selected.

Characterization Survey - A radiological survey and supporting evaluations performed

~

to establish the Shoreham Facility baseline radiological condition for planning decommissioning activities. The Characterization Survey activities are described in and controlled by the Site Characterization Program Description.

Comoonent - An individual equipment item, e.g., a valve, pump, tank, or motor, which is identified in the Shoreham Composite Component List.

l Composite Component List (CCL) - A controlled listing of components installed at Shoreham. The CCL identifies all components other than cable tray and conduit supports in the SNPS design. The CCL also defines which of these components are safety related, which were formerly safety related, as stated in the USAR, and which are not.

Confidence Interval - A range of values derived from a sample such that.there is a probability a, that a population parameter being estimated, e.g., a mean value, lies within the range.

Confidence Level - The probability a, associated with a confidence interval which expresses the probability that the confidence interval contains the population parameter value being estimated (MA90).

IfCritical Level - A calculated value, used to determine when a surface contamination measurement is above background, i.e., is due to contamination. It 8-1

A Termination Survey Plan Rev. I e

is defined as the upper confidence limit at the 97.5 % ' confidence level (1.96 sigma),

2 of the observed net count (converted to dpm/100 cm, and assumed to be a one-tailed normal distribution).))

DECON - The decommissioning alternative which involves prompt removal of radioactive materials to achieve residual contamination and radiation levels which are below limits established to permit the facility to be released for unrestricted use.

Direct Measurement - A radiological survey measurement performed by holding a detector stationary on or close to the surface and recording the response.

[IElevated Area Guideline - The value which individual measurements may not-exceed under any conditions. For total surface contamination the elevated area 2

guideline is 15,000 dpm/100 cm. For gamma exposure rate measurements, it is 10 pR/hr. Elevated area guidelines have not been established for removable surface contamination.))

(( Fixed Point Measurement A synonym for direct surface contamination measurement.))

Historv File - A compilation ofinformation prepared for use in planning the termination survey of a survey unit. It summarizes the operational history, characterization survey data, operational surveys and other information to help establish the basis for the design of the termination survey.

[fGuideline value - The principal numerical limits in the facility release criteria. The guideline values are:

2 total surface beta-gamma cratamination: 5000 dpm/100 cm,

2 removable surface beta-gamma contamination: 1000 dpm/100 cm,

2 total surface alpha contamination: 5000 dpm/100 cm,

2 removable surface alphn contamination: 1000 dpm/100 cm,

gamma exposure rate: 5 R/hr,and soil contamination: 8 pCi/gm.

NOTE: Under certain conditions, individual total surface contamination and gamma exposure rate measurements may exceed the guideline values, as long as they do not exceed the elevated area guideline values and local area average values do not exceed the guideline values.))

8-2

l

/

Termination Survey Plan Rev. I Maintenance Work Request (MWR)- A form used at Shoreham Nuclear Power Station, controlled by a station procedure, to initiate and track work activities.

NRC - U. S. Nuclear Regulatory Commission j

i Operational Radiological Survey - A radiological survey performed under Shoreham

-l Health Physics procedures. Operational surveys are distinct from, and usually performed prior to, termination surveys.

Outdoor Area - A category of survey units which includes site grounds, outside surfaces of buildings and small structures located out of doors.

l Plant Stmetures - All Shoreham Nuclear Power Station site buildings and their surfaces (generally identified as civil stnictures). For purposes of the termination survey, all structures such as platforms, restraints, supports and other physical items not identified in the system MFSK drawings are considered to be structures. External surfaces of piping systems, heating and ventilation systems, tanks, stacks, etc., are also treated as structures in the termination survey.

Population - A collection of all possible values of a radiological parameter being measured in the termination survey. A survey unit (or subunit) is considered to be a population for purposes of drawing inferences regarding the value of a parameter,'such as contamination level mean value in the entire survey unit (or subunit), based upon a sample of measured values.

Power Block - The group of major buildings on the SNPS site directly associated with electrical power generation. This group consists of the Reactor, Turbine, Radwaste, and Control buildings.

Process System Index - A listing, controlled by a station procedure, which identifies and assigns a unique identification code to each plant system.

OC Veri 6 cation Survey - A radiological survey which consists of repeat measurements at a specified fraction of the survey measurement locations in a survey unit, usually selected at random, to provide an independent check of termination survey measurements. Also called a QC replicate survey.

Random Sample - In survey design, a method for selection of measurement locations whereby each of the individual locations defined in the sample space has an equal probability of being selected. Related terms are: random selection and randomly selected.

Release Criteria - A term used to identify the radiological requirements for release of the Shoreham facility for unrestricted use. These requirements, which consist of specified limits for residual contamination and radiation levels, are specified in the Shoreham _

Decommissioning Plan.

i i

8-3 i

Termir.ation Survey Plan Rev. I Decommissioning Plan.

Release Record - A document compiled for each survey unit (structure, system or outdoor area) which demonstrates that it is suitable for unrestricted use. It contains evaluated survey data and supporting information to provide a concise record of the results and basis for the conclusion that the release criteria are satisfied.

[IReportine Units - The units in which each type of survey measurement is expressed for comp:sson to release criteria limits. For surface contamination measurements the reporting units art dpm/100 cm and for gamma exposure rate 2

measurements the units are pR/hr.))

Scan Survey - A qualitative radiological monitoring technique which is performed by moving a detector over a surface (typically within one cm of the surface) at a specified constant speed to detect elevated contamination or radiation levels. Similar terms applied to this technique are: Scan and Surface Scan.

Site Characterization Report - A report (including addenda) which documents the surveys, calculations and evaluations and presents the results of the SNPS Site Characterization Program.

Subunit - A subunit, as used in survey design, is a subdivision of a complex survey unit that incorporates a stmeture, on item of equipment, or some other feature in order to establish that an appropriate number of survey measurements be made within the subunit, as well as within the survey unit.

Survey Desien - The process of determining the type, location, number and frequency (or density) of radiological measurements to be taken in the termination survey.

Survev Desien Guidelines - Criteria established to provide the appropriate level of survey intensity for systems, structurer au ~"d oor areas, based upon their classification.

Survev Instructions - Written directions which specify the type and number of measurements to be taken in a survey unit. The. survey instructions are in a standard format on forms controlled by a Termination Survey procedure. Each survey package includes survey instructions.

(( Survey Location - A discrete area or subdivision of a survey unit that is smaller than a subunit but larger than a survey pob:. In survey design, a survey unit (or subunit) is divided into a collection of survey locations. Specific locations are selected in accordance with the design guidelines based upon the type and classification of the survey unit. In a structural or outdoor survey unit, a location is usually represented by a single grid block. In a system survey unit, a specified length of pip' g or a component such as a valve is referred to as a survey location.

m A survey location can contain one or mort survey points.))

l Survey Packacc - A collection ofinformation in a standardized format for controlling and 8-4

i Termination Survey Plan Rev. I documenting field measurements taken for the termination survey. A survey package is prepared for each Survey Unit. The survey package includes the survey instructions, a j

control forra, grid map (s), survey measurement data sheets and survey maps.

Survey Point - A smaller subdivision within an area designated as a survey location (grid block, system component) where local measurements are taken, generally referring to an 2

area covered by a detector, or an area of 100 cm when a smear is taken.

Survey Unit - A division of the facility consisting of a grouping of contiguous (usually) structural areas, outdoor areas, or functionally contiguous equipment items. The Survey Unit is the basic entity for management of the termination survey. Three categories of survey units have been established: plant systems, structures and outdoor areas.

1 Survey Unit Classification Descriotion - A listing of all survey units established for the termination survey which identifies the classification of each as "affected" or

" unaffected".

System Final Configuration: - The status un plant systems followi.g completion of the i

termination survey. The final configuration establishes the nature of the controls required to maintain the integrity of survey results. It also determines the nature of configuration i

control and engineering review of access methods needed to obtain survey measurements of system component internals. Four categories are established:

)

(a) Operable - maintained to meet Technical Specifications.

(b) Functional - Essential support, not required per Technical Specifications however, necessary for minimal plant functions, habitability, and preservation concerns.

(c) Protected - not to be operated in the defueled mode. These systems will be left in a de-energized, safe state and laid up in accordance with System Lay-up Implementation Package (SLIP), which specify maintenance and custodial services.

1 necessary to protect them pending disposition the LIPA possession only license.

(d) Decommissioned - taken out of service, and completely or partially removed.

Remnants of removed systems are abandoned in place.

1 Systematic Sample - A sample which is obtained by some systematic method as opposed to a random sample; for example, selection from a list using a specified intersal for selection (MA90). In a structural survey unit which has been uniformly gridded, a systematic sample could be comprised of every fourth block, for example.

Termination Survey - Radiological measurements, evaluations and supporting activities undertaken to demonstrate that the Shoreham facility satisfies the criteria for unrestricted use. Termination survey field activities ((may be)) divided into phases called the Preliminary and Final surveys.

8-5

Termination Survey Plan Rev.1 Termination Survey Section - A Section established within the Radiological Controls Division, Operations and Maintenance Department of the LIPA Decommissioning Project Organization to design and implement the termination survey.

Termination Survey Report - A report describing-the methods and results of the Termination Survey. It initiates the NRC review and final inspection of the facility for termination of the facility license. It is also called the Final Report. It will be issued in stages as phases of the Termination Survey are completed. The final update of the Termination Survey Report will document the completed Termination Survey.

Tvoe I Error - In the statistical theory of hypothesis testing, the error incurred by rejecting a hypothesis when it is'actually true (MA90). In the termination survey application it is the probability of deciding that the facility (or a survey unit) meets the release criteria, when in fact, it does not. Also called the a error; the error probability is denoted by a.

Type H Error - The probability of deciding that the facility (or a servey unit) does not-meet the release criteria, when the true condition is that the nacility does meet the criteria. The Type II error probability is denoted by S.

i Unaffected Area - A designation used to identify a smvey unit which is not expected to contain residual radioactivity from licensed operations based upon the operating history -

and radiological surveys.

Work Instruction - A document used to guide performance of a task. Work instructions are similar in format and content to a procedure and are issued and controlled under a station Health Physics procedure. A work instruction is approved at the Section Head level.

i 8-6

c

. l Terminraion survey Plan Rev.1 f

i Appendix A 1

i Survey Design Guidelines j

1.0 Introduction j

This Appendix provides guidance for preparation of the design of the ' Shoreham

{

Decommissioning Project Termination Survey.lt incorporates the guidance in NUREG/CR-5849 (BE92) with adaptations to account for conditions at the Shoreham facility.

De objective of surve !.esign is to define the measurements necessary to demonstrate that the facility satisfies tl

elease criteria. As it is not feasible to' perform detailed radiological l

surveys of 100 pero.. of the facility, measurements are performed at selected locations.

Due to the physical complexity of the facility with the possibility of residual contamination limited to a relatively small portion of the facility,a stratified sampling approach is utilized.

This approach adjusts the intensity of measurements according

• .o the likelihood. of a'

encountering residual radioactivity. This approach is implemented at the facility level by classification ofindividual survey units according to contamination potential. Survey units are further broken down into subunits, if necessary, to provide the appropriate degree of survey intensity for complex structures and plant systems.

2.0 Survey Design Process 1

2.1 Facility Organization and Classification At the facility level, the design and orynization for the survey consists of the f

i following:

a. division of the facility into discrete entities (survey units) for management of the survey, l

t

b. division of the facility into categories with similar physical characteristics, i.e.,stmetures, systems and outdoor areas, j

c. classification of survey units into two major strata based-upon potential for-i residual contamination, i.e.,affected and unaffected, and i

l

d. establishment of a reference grid system for identification of measurement

~

locations.

2.2 Survey Design for Individual Survey Units j

1 The Termination Survey is implemented in the field at the individual survey unit j

level.The design isdeveloped, measurement instmetions prepared and measurements A-1

..L...

Termination Survey Plcn Rev.1 completed for each survey unit independently. The guidelines in this Appendix are applied to each survey unit based upon its classification as affected or unaffected.

The guidelines establish the level of measurement intensity for each type of measurement needed to demonstrate that the release criteria are satisfied.

3.0 Facility Breakdown into Survey Units 3.1 Definition of Survey Unit A survey unit is defined as a division cf the facility consisting of like entities for purposes of management of the Termination Survey.Three categories or types have been established: structures, which include building interiors, plant systems, and outdoor areas. These categories allow the grouping of like elements.

3.1.1 Structures i

For Termination Survey purposes, structures include the indoor portions of site buildings inc1" dim the a-'~ior surfaces of pir* evstems, ecuipment and

~

furnishiags located therein. Structural survey units are established by division of the facility buildings into discrete (usually contiguous) geographical areas

.i taking advantage of existing structural boundaries where possible, i.e., rooms or major elevations of small buildings.

3.1.2 Outdoor Areas Outdoor areas include all site grounds determined to be within the scope of the Termination Survey, the outside surfaces of buildings and miscellaneous outdoor structures not identified as separate structures. These miscellaneous outdoor structures include equipment storage pads, switchyard transformers and storage tanks, for example.

t 3.1.3 Systems i

Systems included in the Termination Survey as survey units include all nuclear steam supply, reactor control, and process systems, and building service systems associated with the SNPS design and described in the SNPS USAR (LILC090). Each system identified in the Records Management File Code l

List is treated as an individual survey unit. A system survey unit encompasses 3

the interior surfaces of fluid carrying piping and components of the system.

E 3.2 Independence of Structures and Systems The survey of each individual survey unit is conducted independently. Interior surfaces of piping and equipment which comprise the system survey unit are surveyed independently of the exterior surfaces. Exterior surfaces of equipment and piping are included in the survey of the structural survey unit in which they are located.

A-2

e Ternunation Survey Plan Rev.1 3.3 Size and Scope of Survey Units 3.3.1 Structures A structural survey unit includes the entire surface area of floors, walls, ceilings, and outside surfaces of equipment and furnishings. The size of structural survey units is established by natural boundaries such as rooms in buildings or by building elevation in small buildings. The optimal floor area of a structural survey unit classified as affected is an area of approximately 2

100 m. Units with floor plans as small as 50 m'and as large as approximately 2

300 m can be established if necessary, due to variations in room size or building floor plan size. Unaffected areas in large buildings may be combined-to encompass multiple rooms of similar composition into a single survey unit for efficiency in survey administration as long as guidelines for measurement intensity are followed.

3.3.2 Outdoor Areas The size ofindividual outdoor area survey units which consist of site grounds is generally determined by features such as roadways, major building boundaries, fences, etc. Building exteriors (all surfaces) generally comprise a single survey unit.

3.3.3 Systems Each individual system within the scope of the Termination Survey is established as a survey unit. The boundaries of piping and other systems are established by the controlling drawings, usually the "MFSK" series of flow i

diagrams.

4.0 Classification of Survey Units by Contamination Potential After breakdown of the facility into survey units, each is classified into one of two strata which identifies each unit as "affected" or " unaffected". Units identified as affected have a possibility of containing residual contamination and those identified as unaffected have a very low probability of residual contamination. Classification of individual survey units is based on the history of radioactive materials involvement or potential for contamination of the overall survey unit.

4.1 Structures and Outdoor Areas 4.1.1 Affected Areas Structures and outdoor areas are classified as affected for survey design purposes when the following conditions apply:

a. areas with potential contamination based on operating history, or A-3

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Termination Survey Plan Rev.1 known contamination based on radiological surveys, or

b. areas where radioactive materials were used or stored, and where records indicate spills or occurrences which could have resulted in contamination.

4.1.2 Unaffected Areas Structures and outdoor area survey units are classified as unaffected if the following conditions apply:

a.not expected to contain residual radioactivity from licensed activities based upon the operating or utilization history and radiological survey results, and i

b. not classified as affected.

4.2 Systems 4.2.1 Affected Systems Systems are classified as affected for survey design purposes if the following conditions apply:

a. the potential for contamination exists based on operating history, or there is a known history of contamination based on radiological surveys, or

b. the system circuhted, stored or processed radioactive materials, including: primary coolant, radioactive process or treatment media which were associated with the operation or control of the Nuclear Steam Supply System (NSSS) such that they could become contaminated or experience neutron activation; or where records indicate spills or occurrences which could have resulted in contamination.

4.2.2 Unaffected Systems System survey units are classified as unaffected if the following conditions-apply:

a. not ' expected to contain residual activity based upon the operating or utilization history and radiological survey results, and

b. do not meet the criteria for classification as affected.

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h Tennination Survey Plan Rev.1 4.3 Reclassification Survey units may be reclassified subsequent to the initial classification according to the following criteria:

4.3.1 Upward Reclassification

((A survey unit (or subunit) must be reclassified from unaffected to affected if at any time in the survey planning, design, or during the actual survey,new information is obtained which indicates that the criteria for an unaffected survey unit are no longer satisfied. An investigation, to detennine whether upward reclassification of the survey unit (or subunit) is required, will be initiated if any total surface contamination measurement exceeds the " action level" calculated as described in Section 5.0 of this Plan, if any removable surface contamination measurement exceeds 25 percent of the removable surface contamination limit specified in Table 3.1, or if a single gamma exposure rate measurement exceeds 5 R/hr. The investigation of a survey unit (or subunit), including additional measurements taken to determine the extent of residual contamination present, should either conclude that the survey unit (or subunit) continues to meet the criteria foran unaffected area or the survey unit (or subunit) will be reclassified as an affected area. If a survey unit is reclassified upward, sufficient measurements must be taken to meet survey design guidelines for affected areas. Only under conditions of such reclassification is it acceptable to classify a subunit as an affected area within a survey unit previously classified as unaffected.))

4.3.2 Downward Reclassification A survey unit may be rec assified downward from affected to unaffected prior to the survey design if additional information is obtained such that the criteria for classification as an unaffected area are satisfied. For example, through the investigation for the history file preparation, additional survey results may become available subsequent to the initial classification which show that no contamination is detected and records indicate that there is no history of i

radioactive materials use.

4.4 Alpha Affected Areas Due to the lack of any history of alpha contamination from SNPS operations, alpha surveys are not routinely performed during the Termination Survey. However, in the event that alpha contamination is observed a mechanism is needed to expand the scope of the Survey to ensure that applicable release criteria limits for alpha i

contamination are satisfied. A survey unit (structural area, system or outdoor area) is classified as an alpha affected area if the following conditions apply:

a. alpha activity greater than 25 percent of release criteria limits has been detected, or i

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b. the area or system is immediate y involved with fuel handling or storage.

In alpha affected survey units, direct measurements and measurements of surface alpha contamination are added to the list of measurements normally performed at the selected measurement locations. Surface scans for alpha activity are performed in the vicinity of the selected measurement locations.

5.0 Reference Grid System and Gridding of Survey Units The reference grid system for the termination survey establishes a discrete-uniform subdivision of areas covered by the survey.The principal objectives of grid marking are: to i

establish measurement locations for the survey design and to document where measurements were taken if the need arises to verify measurement results by repeat measurements, or to establish boundaries of areas needing remediation.

5.1 Gridding Affected Areas 5.1.1 Indoor Areas

a. Floors and Lower Walls Floors and lower walls up to 2 meters from floor level are gridded, i.e.,

grids are marked on the surfaces. The grid size is one meter square.

b. Upper Walls and Ceilings Grids are marked on upper walls and ceilings of affected structural survey units if the areas are determined to be suspect as defined in Section 7.1.2.If determined to be suspect, the areas are gridded in 1

accordance with Paragra,"

above. If the area is not suspect, the l

guidance in Paragraph c. below is applied.

c. Other Surfaces Grids are marked on surfaces of equipment and other non-regular surfaces in affected stnictural survey units as needed' to aid in the design of surveys and to control and docuw at the location of measurements. If not possible to mark such it r.ts into one meter square grids, regularly spaced markings one m.*:r apart may be used.

5.1.2 Ou. door Areas

a. Site Grounds i

Site grounds in affected areas are marked offin 10 meter square grids.

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b. Roofs and Building Exterior Walls Roofs and exterior walls in affected areas are marked offinto grids not to exceed 5 meters square. Smaller grids (one to three meters square) may be used on small surfaces where the use of five meter grids would result in fewer than 10 grid blocks on a surface.

5.2 Gridding Unaffected Areas 5.2.1 Indoor Areas Grid marking of surfaces in unaffected indoor structural survey units is not required. However, grids may be marked for reference purposes. The grid size is optional (one to 10 meters square), commensurate with the size of the area.

Temporary grid markings may be used to control scan surveys.

5.2.2 Outdoor Areas Grid marking of surfaces in outdoor areas is not required. If desired for reference purposes, grids ma; " ased. The size is optional, but shall not exceed 30 meters square on site grounds and 10 meters square on building exterior surfaces.

5.3 Gridding for Systems Surveys Gridding on surfaces of system interiors is not normally performed. Identification of measurement locations is shown on survey maps which contain drawings or diagrams.

Interiors oflarge tanks and vessels in affected systems may be gridded as needed to design the survey. In such cases, the surfaces are marked off into one meter grids.

Square grids are used where possible, but tank ends and other non-rectangular surfaces are marked in regular shapes which approximate one meter in area.

5.4 Accuracy of Grid Marking An accuracy objective which is reasonable for the scale of the SNPS facility is to document a measurement location with an uncertainty of less than one meter. To ensure that this is attained, grid blocks will be marked to an accuracy within 15% of the specified dimension. This also allows for accommodation of areas of irregular shape within a grid block if needed. Remnant areas at the end of rows can be incorporated into the last full size grid block as long as the area of the resultant block is not greater than approximately 25% above the area of the specified grid size.

6.0 Stratification-Breakdown of Survey Units 6.1 Structures In affected areas, structures are generally divided into subunits for survey design and control. The floor and lower walls comprise a subunit and the upper walls and ceiling a separate subunit. Due to additional structural features and the presence of piping A-7

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Termination Survey Plan Rev. I and equipment, additional subunits may be needed. Separate subunits are usually created to establish " populations" where biased surveys are indicated. For example, piping penetrations in floors and walls where contaminated piping systems were removed are usually grouped into a subunit. A large sump or catchment basin -

location in a structural survey unit is treated as a separate subunit. Grating, decking, stairs and ladders are usually grouped into a subunit. Equipment skids are usually identified as subunits for survey of the exterior surfaces. Unaffected areas in structures need not be divided into subunits, but in some cases subunits may be used if needed to group elements in complex structures.

6.2 Outdoor Areas Outdoor site ground areas may be divided into subunits based upon the nature of the surface, e.g., to separate paved and unpaved areas which have different survey requirements.

6.3 Systems systems with multiple and separa:e components are usually divided into subunits for

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survey design purposes. A typical subunit comprises a large bore component 'and the 1

adjacent piping. Usually tanks, heat exchangers and other vessels are treated as subunits.

6.4 Classification of Subunits Subunits may be classified differently from the survey unit in which it resides under certain conditions. A subunit within an affected survey unit may be classified as unaffected ifit is a physically separate entity with no likely mechanism for transfer of contamination from the affected portions to the unaffected portions. The typical application of this classification option is the classification of upper walls, ceilings and overhead areas within an affected survey unit as unaffected. The converse is not allowed, however, i.e., classification of an affected subunit within a unit classified as unaffected, ((except as provided for in Section 4.3.1 for reclassified subunits.))

7.0 Measurement Location and Frequency of Measurements 7.1 Structures

-i This Section provides guidance for determining the frequency of measurements, i.e.,

the number of measurement locations in structural survey units (and/or subunits).

The frequency of measurements in affected areas is determined by:

j Large bore at SNPS refers to piping and the piping system components associated with piping having inside diameters of 3 inches or greater.

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a. the sensitivity of scanning surveys for floor and lower walls, and

b. the expected level of contamination relative to release criteria limits for upper walls and ceiling areas.

The measurement frequency in unaffected areas is not controlled by scan sensitivity.

Locations for fixed measurements are at or near the center of the one meter grid blocks. Unless specified otherwise in the following paragraphs, the measurements taken at fixed locations are: direct surface beta-gamma, removable surface beta-gamma (smear) and gamma exposure (or microrem) rate measurement at one meter from the surface.

In survey units classified as alpha affected, direct surface and removable surface -

alpha measurements are taken in addition to the measurements identified above.

7.1.1 Affected Areas - Floors and lower Walls Floors and lower walls of affected areas are surfacc scanned over 100% of the area. Measurements are taken at fixed locations. Measurements are taken systematically in every second grid block. At least 30 measurement locations are selected.

7.1.2 Affected Areas - Upper Walls and Ceilings In large structural survey units, and those with complex structures and piping in the overhead areas, the survey design is usually implemented by establishing individual subunits for vertical and horizontal surfaces and perhaps additional subunits for equipment and furnishings. Surveyintensity of upper walls and ceilings classified as affected areas is determined based upon the suspected level of residual contamination.

a. Not Suspect The nile for determining than an area is not suspect is: (( expected contamination levels must be below50 percent of release criterion for total surface contamination and below 25 percent of the release -

criterion for removable surface contamination, i.e.,below the following The scanning sensitivity value which triggers an increased frequency of fixed measurements is 75 percent of the surface contamination release criteria limit-for 2

average total surface contamination: 5000dpm/100 cm.That is,the scanning method 2

must be capable of detecting levels below 3750 dpm/100 cm averaged over an area not to exceed one m'. As described in Section 4.2 of the Termination Survey Plan, the Termination Survey instrumentation scanning sensitivities are below this value, j

so the conditional measurement frequencies in NUREG/CR-5849 are not invoked.

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values: 2500 dpm/100 cm direct total surface contamination and 250 dpm/100 cm' removable surface contamination.)) If the area is not suspect, a minimum of 30 measurement locations are selected on horizontal surfaces, and 30 on venical surfaces. The measurement density shall be at least one measurement every 20 m' averaged over the area of the subunit. A scan survey is performed in the immediate area of each selected measurement location. The scan survey covers an -

area of approximately one m' or greater. The measurement point locations are usually selected in a biased manner, i.e., focusing on locations where demolition, piping removal or other remediation work occurred and on surfaces where contamination potential is highest.

b. Suspect.

If any area is suspected to be or is above the levels prescribed in Paragraph a. above, the survey protocol is the same as for the floors and lower walls of an affected area. That is, a 100 percent scan with the fixed location meamrement frequency of one measurement every 2

second grid block, for a minimum of 30. The area is gridded in 1 m grids (square grids one meter on a side).

7.1.3 Unaffected Areas

a. Inside The Power Block Floors and lower walls of unaffected indoor areas (structures) within the Power Block are scan surveyed over a minimum of ten percent of the area, focusing on walkways and commonly traveled areas.

Measurement locations are randomly selected. At least 30 locations or 2

an average of one measurement per 50 m (of floor plus lower wall surface area) are required whichever is greater.

2 Thirty locations or an average of one measurement location per 50 m,

whichever is greater, are selected at random from upper walls and ceilings. No scan survey is performed.

b. Outside The Power Block Floors of unaffected areas outside the Power Block are scan surveyed over a minimum of ten percent of the area, concentrating on traffic areas At least 30 locations are selected at random, or an average of one per 50 m', whichever is greater. Irwer walls are not included in the survey of floor areas.

Thiny locations are selected at random from the walls (including lower 2

walls) and ceiling areas, or an average of one per 50 m, whichever is greater. No scan survey is performed.

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7.2 Outdoor Areas 7.2.1 Affected Areas - Site Grounds Affected site ground areas are surveyed according to the nature of the surface covering.

a. Paved Areas Paved areas are surface scan surveyed over 100 percent of the area with a beta-gamma detector. Measurement locations are selected 2

systematically to achieve an average of at least one per 10 m grid such that a minimum of 30 locations are surveyed. Direct and removable surface beta-gamma measurements and gamma exposure rate measurements (at one meter from the surface) are taken at each measurement location.

b. Unpaved Areas Unpaved areas are scan surveyed over 100 percent of the area using-a gamma detector. Gamma e'xposure rate measurements at one meter 2

from the surface are performed with at least one location per 25 m,

including at each location where a soil sample is collected, such that at least 30 locations are surveyed.

7.2.2 Unaffected Areas - Site Grounds Unaffected site ground areas are surveyed according to the nature of the ground surface.

j

((a. General - All Surfaces))

((A minimum of 30 survey locations are selected at random. At each location (at the approximate center of the grid), a gamma exposure rate measurement is taken at one meter from the surface. Gamma exposure rate measurements are also obtained at each of the randomly -

selected locations where soil samples are obtained.))

((b. Paved Areas))

j

((The paved areas within each survey unit are evaluated to identify i

traffic areas and areas with any potential for residual contamination.

These areas are scanned for beta-gamma contamination. All such areas are cleared of material as necessary to provide access for the survey. A minimum of 10 percent of paved areas will be scanned. A direct surface beta-gamma measurement is taken at or near the center A - 11

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Terminotion Survey Plan Rev. I of each survey location (grid block) identified for survey as described in paragraph 7.2.2.a,above.))

((c. Unpaved Areas))

(( Unpaved areas are surface scanned over at least 10 percent of the area with a gamma detector (NaI or microrem). Emphasis is placed on traffic areas and roadways.))

7.2.3 Affected Areas - Building Exteriors No building exteriors have been identified which are classified as affected. If classified as affected, they are scan surveyed over 100 percent of the area. A minimum of 30 measurement locations are selected on each of wall surfaces and roofs or an average of one per 20 m', whichever is greater. The survey design should focus on likely areas for deposition, e.g., downwind of stacks, vents and drains.

7.2.4 Unaffected Areas - Building Exteriors The survey of exterior surfaces of buildings and structures which are classified as unaffected is as follows:

a. Exterior Walls Surfaces The survey of building exterior walls focuses on the area within two meters of the ground surface. The areas are surface scanned over a minimum of 10 percent of the area. Measurement locations are randomly selected for a minimum total of 30 or an average of one per 2

50 m, whichever is ;;reater.

b. Roofs i

The survey of building roofs which are classified as unaffected is limited to the roofs of the Power Block and immediately adjacent buildings. If any of these surfaces are classified as affected, they are surveyed in accordance with the guidelines in paragraph 7.2.3above.

Otherwise the roof areas are surveyed at a minimum of 30 location or 2

one per 50 m,whichever is greater. Roofs of other buildings in outside 1

areas which are classified as unaffected are not surveyed.

I 7.2.5 Soil Sampling Soil samples will be collected from the site grounds for the Termination Survey. Thirty locations will be selected at random from the site. The soil samples will be collected from the top 15 cm of the soil column and will be analyzed as REMP samples. The analysis willinclude gamma spectroscopy for Co-60.

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e b

Termination Survey Plan Rev.1 Additional soil samples are collected as needed to support the Terminauon Smvey of plant systems, some of which extend beyond the Secured Area of the site. Soil samples may be collected, for example, from leach fields, soil adjacent to or below catchments, sumps and building foundations.

((Any soil sample containing detectable concentrations of Co-60,or any other non-naturally occurring radionuclides above the REMP detection limit (LLD), will be investigated to determine the source of the contamination, as well as the areal extent and depth of the contamination.))

7.3 Plant Systems 7.3.1 Selection of Measurement Locations Surveys of systems are biased sampling surveys. Selection of measurement locations in both affected and unaffected systems focuses on the locations with the highest probability for contamination considering the system design and operational characteristics. Typically, the inlets, outlets, system interfaces, system crud traps and flow impingement areas are selected. A " location"in a system survey design is generally identified as an area which includes a surface defined by the interior of a component or of a discrete-specified length of piping in piping systems. A component includes any discrete element which is distinguishable from piping. When a component is removed or opened for access for Termination Survey measurements, typically three measurement locations are established: the component interior surfaces and the two piping spool pieces immediately adjacent. In non-piping systems such as ventilation systems, locations are identified as local areas where air impinges, such as inlet and outlet baffles and ducting interior surfaces at bends and cleanouts.

The survey design should take advantage oflow cost access methods including destructive cutting of piping (where permitted).

7.3.2 Breakdown Into Subunits Systems, including mechanical systems, such as the main steam turbine, are broken down into subunits by functional areas, components or locations.

Large vessels and heat exchangers are usually considered to be subunits of the system in which they are located. In piping systems, each fluid carrying interface to other systems is usually established as a subunit.

7.3.3 Survey Measurements The interior surfaces of components selected for survey measurements are usually scanned over 100 percent of the accessible area. Where physical size permits, locations are selected such that both direct and removable surface contamination measurements can' be taken.

Gamma exposure rate measurements are not usually taken within system components, except where interiors are large enough for human occupancy, i.e.,large tanks and spaces i

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K' Termination Survey Plan Rev. I such as the Condenser Hotwell. At least one direct surface and removable surface contamination measurement is taken at each location.

7.3.4 Measurement Frequency - Affected Systems In general, the measurement frequency is strongly influenced by the size and complexity of a system. In affected systems, the design guideline is a minimum of 30 measurement locations. Exceptions may arise where the system is limited in physical extent such that 30 discrete locations cannot be identified.

7.3.5 Measurement Frequency - Unaffected Systems In unaffected systems, a minimum of 10 measurement locations will be selected. Similarly,in unaffected systems, the number of measurements may be limited by the physical extent of the system, so exceptions may be made to the minimum number guideline.

7.3.6 Embedded Piping Two piping systems, Liquid Radioactive Waste (Gil), and Fuel Pool Cooling and cleanup (G41), have substantial lengths of piping which are embedded in reinforced concrete structural members, i.e., floors and walls.The embedded piping in Gil and G41 systems are each established as separate survey units for the Termination Survey. For management of tb survey, each may be further divided into subunits for survey design and control purposes. All Gil and G41 embedded piping is classified as affected. Detailed surveys are performed with detectors inserted into embedded piping runs. All openings and normal access points (cleanouts) will be surveyed. All runs of piping will be systematically surveyed over at leart 25 percent of their length.

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