ML20128B964

Rev 0 to Shoreham Decommissioning Project Termination Survey Plan

ML20128B964
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Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	10/31/1992
From:	LONG ISLAND POWER AUTHORITY
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ML20128B961	List: ML20128B964 SNRC-2014, Forwards Rev 0 to Shoreham Decommissioning Project Termination Survey Plan
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{{#Wiki_filter:( i LONG lSLAND POWER AUTHORITY Shoreham Decommissioning Project Termination Survey Plan Revision 0 l Prepared by Termination Survey Section Radiological Controls Division Operations and Maintenance Department Shoreham Nuclear Power Station i Tn 1pTin~ nw October,1992 a i JiiillhiU. bJi; 38A 28a 2 8!a88822 H PDR

l--- 1 i i l-Effective /fo/92 Date: // t i i j 7.,0NG ISLAND POWER AUTHORITY I SHOREHAM DECOMMISSIONING PROJECT l TERMINATION SURVEY PLAN i I i Reviewed by: [ l.n /q L, j Sihature Date l-LIPA Site Review Committee l Approved by: /f ffgt L LesbieM.' Hill Date LIPA-SNPS Resident Manager-- i ,e l i 5. .i 4 d

~ Terminatloc. Survey Plan Rev. 0 Preface 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 for 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 Management Control Manual, Termination Survey Program Description (LIPA92).1 The methods described are derived 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 into account conditions at the Shoreham facility. i This Plan is a companion document to the Shoreham Decommissioning Project 1 Termination Survey Program Des:ription (LIPA92). The Program Description describes the organization and management responsibilities for the Termination Survey Program. -i-

4 j Termination Survey Plcn Rev. O I SHOREHAM DECOMMISSIONING PROJECT ~ TERMINATION SURVEY PLAN ) Table of Contents d i Section Title Page No. I 1.0 Historical Background Information 1-1 i i 2.0 Site Information 2-1 ( 3.0 Termination Survey Overview 3-1 l 4.0 Survey Plan and Procedures 4-1 i 5.0 Data Interpretation 5-1 \\ 6.0 Report 6-1 4 7.0 References 7-1 i 8.d Glossary 1 Appendices: I A.. Survey Design Guidelines .A-1 i ( o l [ -ii-l

s Termination Survey Pian Rev. 0 - j-i List of Tables i 5 l r l-Number Iille Page No. f 2.1 Shoreham Termination Survey '2-3 Classification Summary i 3.1 Acceptable Surface Contamination Levels 3-1 1 4.1 Termination Survey Instrument Summary .4-3 4.2 Detector Sensitivities 4-4 i l 6.1 Termination Survey De: ail Data Report - Structures 6-3 List of Figures i. Number Iille Page No. 2.1 Shoreham Site.(Partial) Showing Termination 2-4 f Survey Area I- { 4.1 -View of Structural Survey Unit Showing 4 - 12 Grid Placement. 4.2 'Shoreham Decommissioning Termination .'4 - 13 Survey Grid Map l 1 -iii- -,-.-u. .w .---rw w an-re ,--+m e.cr-*' --=w w v w e ry h y n--v - - =r y-

^ Termination Survey Plan Rev. O i 1.0 Historical Background Information The Shoreham Nuclear Power Station (SNPS) consists of a boiling water reactor (BWR) nuclear steam supply system (NSSS) and a turbine generator both furnished by General l 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). l Pursuant to the 1989 agreement among The lang Island Lighting Company (LILCO), the State of New York and the long Island Power Authority (LIPA), power generating operations at the Shoreham Nuclear Power Station (SNPS) were terminated. The irradiated l fuel was removed from the reactor 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 i (NRC) in June,1992 (USNRC92). The objective of the approved DECON alternative is to decontaminate the SNPS facility and site and release them for unrestricted - use. To i accomplish this, radioactive portions of the reactor pressure vessel and pressure vessel i internals will be disassembled, segmented and removed. Contaminated and/or activated i portions of plant piping systems and equipment will be decontaminated or removed as described in the LIPA Decommissioning Plan (LIPA90). 4 J 4 1-1 A .y ,,m

9 a Tstminstion Survsy Plan Rev. 0 2.0 Site Information 4 2.1 Site Description The Shoreham Nuclear Power Station site is located in the Town of Brookhaven, Suffolk County, New York on the north shore of Long Island. The site is approximately 50 miles east of tne confluence of the East River and Long Island Sound which is near La 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).' 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 slope about 30 feet in height which traverses the site in an east-west direction immediately to the south of the 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 aren is a mixture of grass and weeds with a few shrubs and small trees. 2.2 Site Conditions for Termination Survey The Shoreham Facility will be largely left intact following Decommissioning. Dismantlement of structures will be confined to small portions of the Reactor, Radwaste and Turbine Buildings. Removal will be for purposes of removing contaminated structures and to provide paths for removal of contaminated piping and equipment. As l f Under the Asset Transfer Agreement, approximately 11 acres of the site which include l the power block, adja.:ent office and support buildings and connecting roadways have l been transferred to LIPA for conduct of the decommissioning (LIPA90). I 2-1 l

4 Termirolon Survey Plan Rev. O described in the LIPA Decommissioning Plan (LIPA90), all radioactive piping and equipment will be dismantled and removed from the facility and disposed of as radioactive waste at a licensed radioactive waste disposal facility. This includes reactor vessel internals and major portions of 14 plant systems. 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 facili.ty and environs have been evaluated to identify the areas to be covered in the Termination Survey. The Termination Survey focuses on the area within within the Secured Area fence as shown in Figure 2.1. The area, (approximately 20 acres), contains the Reactor, Radwaste and Turbine buildin;;s, 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 of individuals from exposure to radiation. Following completion of Shoreham Decommissioning and removal of the irradiated fuel from the 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. 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 525 individual " survey units" for management of the Survey. Each survey unit is classified as "affected" or " unaffected" 4 for survey implementation.2 Affected areas are largely 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. 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 operations. This is well documented by the Shoreham Radiological Environmental Monitoring Program (REMP). The REMP will be continued through Shoreham decommissioning to ensure that any contamination of the site environs which could occur as a result of decommissioning activities is detailed. 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 rad oactive 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). 2-2

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Termination Survey Pl:n Rev. O i

i. 4 i Table 2.1 l Shoreham Termination Survey Classification Summary r I Total No. No. of Affected No. of Unaffected DESCRil* TION CODE of Survey Units Survey Units Survey Units STRUCTURFS i Reactor Bldg. RB 110 110 t l Drywell PC 22 22 l Suppression Pool SP 13 13 i Turbine Bldg. TB 114 10 104 l-Radwaste Bldg RW 77 77 Control Bldg CB __9 -9 O & S Bldg OB 12 12 1 0 & S Bldg Annex AB 21 21 i f Other Site Bldgs OS. 25 1 24 Structure Totals 403 233 170__ j j - OUTSIDE AREAS Site Grounds SG 10 10' i-- Structure Exteriors SE 32 32 l 42 42 Outside Area Totals [ - PLANT SYSTEMS SU 82 -38 44 TOTALS-527 271 256 i e 2-3 1 ~

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• -a- - Secured Area Boundary

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. ~.. -. - 4 Termination Survey Plan Rev. 0 l 3.0 Termination Stirvey Overview I i 3.1 Survey Objectives The Termination Survey-is designed _ to demonstrate. that licensed radioactive materials have been removed such that residual levels of radioactive contamination - j are below applicable Regulatory Guide 1.86 limits (USAEC74). These are shown j 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 l release limits are activation' products dominated by Co-60. These are beta-gamma f 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 plant contamination deposits, the presence of the irradiated fuel + in the facility provides a potential-source of alpha contamination. Instruments and L

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methods are being incorporated into the survey which are adequate to measure alpha - l surface activity at levels below the limits in Table 3.1. i Table 3.1 Acceotable Surface Contamination IEvels (dpm per 100 cm') i 4 1 i Fixed Plus Removable Removable Activity Averane Maximum Beta-Gamma 5,000 15,000 1,000 t i l Alpha 5,000_ 15,000 1,000-I In addition, to tiie 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 i 5 pR/hr above. background, measured _ at one meter from surfaces,(LIPA90), i 3.2 Identity of Contaminants y L The Shoreham Characterization Study (LILC090a) 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 is contained in activated materials of the Reactor-l- Pressure Vessel and Vessel Internals which will be removed from the. site. The { calculated radioactivity composition of the activated components las of July,1990)- is: Fe-55; 69%; Co-60,28%; and Ni-63,2%. Very minor amounts of other species are 3-1 e i e ,r--, -+w,,- a,-- n. N w-m m ew n-,.ywrr-e--

e Termination Survey Plan Rev. O l calculated to be present, including: H-3, C-14, and Ni 59 (LILC090a). Laboratory analysis of activated Reactor Pressure Vessel and Pressure Vessel internals samples indicates the presence oflow 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 shows that these are comprised largely of Co-60 and Fe-55, with an average Fe-55:Co4t ratio of approximately 0.2(0.21 +/- 0.13)(TU92). 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 Esponsibilities An organization, identified as the Termination Survey Section of the Redblogical Controls Division, has been created within the LIPA - Shoreham Decommhsioning 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 "Hralth Physics Technician Selection, Training and Qualification Program" procedure. The training and qualification acceptance criteria from this procedure will be adopted. The training will include classroom and functional job performance training on Termination Survey procedures and specialized instrumentation. The training and qualification process for individual technicians will require from three to five days to complete. Termination Survey technicians will generally be selected from the pool of techn:cians who have previously been qualified to perform HP responsibilities on the Shoreham Decommissioning Project. 3.4.2 Classroom Training Classroom training includes: an overview of the Termination Survey Program, instrumentation, and procedures. The overview willcover Termination Survey 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. 3-2

Termination Survey Plan Rev. 0 3.4.3 Functional Training Functional training will involve hands-on performance of principal HP technician Termination Survey tasks. A survey of a typical Survey Unit will be performed by each technician under the surveillance of a qualified instructor. 3.5 Laboratory Services Laboratory radioanalytical services of the Snoreham Nuclear Power Station Radiochemistry Section, 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; and gas proportional counting. The Radicchemistry Section operates under an approved QA program and procedures. A contract is in 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 4 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 erection of scaffolding, system tagout and system breaches for system surveys; 10) performance of the survey; and

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

3.6.1 Initial Classification The iniual classification of the facility into "affected" and " unaffected" areas provides an overall planning basis for the Termination Survey. It was 3-3

^ Termination Survey Plan Rev. O 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 classi0 cation 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 summarites the operational and radiological history of each 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 relevant 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. For system history files, it identifies the interfacing piping systems and 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 radiation use history (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 Turnover 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. Decommissioniag activities are completed, all tools are removed, housekeeping and area cleanup is completed, decontamination of affected structural areas and system residual components is completed and verified by operational radiological surveys,and scaffolding needed to be left in place for Termination Survey is identified. 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, 3-4 l l

.~... _.. 4 Termination Survey Plan Rev. 0 structures and outside areas is controlled by a Termination' Survey procedure. I F 3.6.4 Walkdown s 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-l 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 4 i alignment to provide r.ccess for surveys. Safety concerns such as _ access to confined spaces, high walls, and ceilings,' are identified and resolved. It is j noted that for survey units involved with decommissioning activities, the walkdown is best completed when the final configuration it e own, usually l near c: after the completion of decommissioning - work. Early mformation is available through Decommissioning work packages and material takeoff lists and drawings. i. 3.6.5 Survey Design I The survey design results in the identification of 'he locations.-(grid blocks, system components) to be surveyed and the type of radiological measurement or sample 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 i is prepared in accordance with a Termination Survey procedure. 3.6.6 Engineering Once the survey design is prepared, - engineering review and support l 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. __ L 3.6.7 Work Planning and Scheduling i-Upon completion of any required engineering review, ' the - physical-. l 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. j and indicate whether a system is to be isolated or returned _ to service. The - 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 - ~ l is then placed' upon the Project work schedule for performance, l i 3-5 4 m .--, e nw-ne. ,e .,.,+,n ~-m. -n

Termiretion Survey Plan Rev. 0 3.6.8 Survey Instructions The survey instructions are provided to the 1 rad 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 verif~. cation 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 The 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 beeil 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, smear samples for removable surface contamination .ind 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. 3.6.11 Restoration and Isolation

a. Systems After survey measurements have been taken, reviewed and approved, and QC verification survey 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 MWR, the system is isolated to protect against recontamination. Isolation and control of plant systems after Termination Survey is performed under a specific approved procedure.

It is noted that many plant support and service systems will be returned to service after completion of Termination Survey 3-6

TGrmination Survey Plan Rev. O measurements. Examples are: compressed air, heating and cooling, ventilation and fire protection. 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, each area is posted and access is controlled to prevent or minimize possible contamination. This is controlled by an approved station procedure.

3.7 Quality Assurance 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 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:

a. Selection and Training of Personnel 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 training and job-functional training. Training and qualification records are maintained on all technicians selected for the Termination Survey.

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 of Standards and Technology (NIST), or by qualified vendors with the results traceable to NIST. Measurements are performed using approved written procedures for each instrument. Control of instruments is established by an instrument control procedure.

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Termination Survey Pla. Rev. O

c. Survey Documentation Each Termination Survey measurement is identified by date, instrument, technician, location, type of measurement, and mode of instrument operation.

d. Quality Control - 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 by the LIPA 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,

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

h. Records Management J

Generation, handling and storage of Termination Survey design and data packages is controlled by an approved procedure.

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 indepw. cat review prior to acceptance for final management approval.

k. Control of Surveyed Areas and Systems Administrative, (i.e., procedural) and physical controls are established 3-8

Termination Survey Plan Rev. O on areas and systems to minimize the possibility of contamination subsequent to the survey.

1. Control of Vendor Supplied Services Essential services, such as instrument 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. conuuct of QC replicate sampling measurements, b. routine verification of survey measurement data prior to acceptance for data processing, c. control charts for individual instruments, d. testing of computer data calculation programs, 4 e. validation of historical operational survey data used as final survey data, f f. documentation of surveys, and g. custody ofinstruments, samples and measurement data. 3.8 Schedule i l The Termination Survey detailed schedule is maintained within the Project Schedule l by the Project Controls Division of the Finance and Administration Department and the Work Planning Section of the Operation and' Maintenance Department. The Termination Survey is scheduled to be completed in several major phases which encompass distinct portions of 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 October 1,1993, with the final phase to be completed following removal of the irradiated fuel from the facility. The current schedule date for completion of fuel removal is April 1994. 3-9

I Termination Survey Plan Rev. 0 1 ] 3.9 Survey Report y 4 Upon completion of the survey measurements, processing of the resultant data, and evaluation of the results, a 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 Final Seport will follow the I guidance of Draft NUREG/CR-58.'9 (BE92) regarding content.- The Report is - described in Section 6.0. Interim.eports-will be submitted for the major survey phases as discussed above. i i i 4 i i i l-I r I I i 5 i i i l 3 - 10

Tcrmination Sur<ey Plan Rev. 0 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 Radwaste Iluildings 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. Thc 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 measurernents of site soil and outdoor surfaces in the Site Characterization Program (LILCO90a) and in the REMP program prior to, during, and subsequent to Shorehara operation. The Survey Plan and procedures are designed accordingly, to focus 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 evaluate <l. Instrumentation to be used for gamma exposure rate measurements and spe-ial purpose measurements is also described, i 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 conta.nination monitoring willbe for the most part operated with data logging survey meters. Several instruments have been selected for special purpose measurements. A portable gamma s}rctrometer has been obtained for use in the Termir.atien Survey. It can distinguish l between plant-derived residual activity and natural background source 4' l r

Termination Survey Pl:2 Rev.O cor.tributions to measured levels. This capability will be of value if unexplained high levels or other anomalies are encountered. A portable radon monitor will be utilized to evaluate building radon concentration effects on gamma background levels, if necessary. 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 rate, wunting times for background and for background plus source count. The results are shown for the principal instruments used for beta gamma direct surface measurements. Smear counters for measurement of removable surface act vity, of modern design (anti-coincidence low background), have nominal beta gamma MDAs of approximately '100 dpm/100 cm', and alpha MDAs of approximately 20 dpm/100 cm. The gamma exposure rate measurement instrument sensitivities in the normal modes of operation are: Pressurized ion chamber: 1 pR/hr j llicron micro Rem meter: 2 - 3 prem/hr. The detection sensitivity of the pressurized ion chamber can be lowered, if necessary, by using the device in the integration mode. 4 4-2

Ten.nination Survey Plan Rev. O Table 4.1 Termination Survey Instrument Summary Purpose Type Manufacturer Detector Measurement Dese 1ption Units (Window area and density) Direct GM Pancake LND, WBJ and 15.5 cm' area counts per Surface others (2 mg/cm') minute (cpm) Beta-Gamma Hand held Aptec 126 cm' area epm Direct large area GM G mg/cm') Surface Hnd held Aptec 252 cm' area epm large area GM G mg/cm') 2 Flocr Monitor Aptec 756 cm area epm large area GM 3 detectors O mg/cm') Alphn Direct ZnS Scint. Eberline 59 cm' area cpm Surface (0.5 mg/cm') Removable Gas flow

Canberra, 25.5 cm' area epm surface proportional Tennelee thin window Beta-Gamma (low bkg.)

Removable Gas Dow

Canberra, 25.5 cm' area epm

.orface alpha proportional Tennelec thin window Gamma Pressurized Reuter Stokes 8 liter sphere pR/hr exposure rate ion Chamber Gamma dose Scint.

Bieron I in. plastic prem/hr rate detector scintillator Multi-purpose Data-logging Eberline multiple detector-survey meters depeatent

Background

Portable gamma Canberra 3in.Nal epm and special spectrometer scintillator - measurements Radon levels Radon monitor Niton solid state pCl/l or working level e= 4-3

Terminction Survey Man Rev. O Table 4.2 Detector Sensitivities 1 Detector Detector Efficiency llackground' hiDA' [ cal. source]' Winde,w Area (41r epm /dpm) (cpm) (dpm/100 cm') (cm') Aptec Ghi 126 0.04 120 550 [100em'] (0.02) (l100) Aptec Ght 252 0.06 230 500 [512 cm'] (0.06) (500) Aptec 756 0.05 810 1150 Floor hion. (0.05) (1150) l [512 cm'] l Pancake Ght 15.5 0.07 26 950 2 [15 cm ] (0.03) (2200) r Notes: 1. Calibration sources used for these efficiencies are National Institute of Standards & Technology (NIST) traccable. The sources consist of Co 60 uniformly deposited on a surface of the area indicated within the brackets [ ]. 2. The efficiency is determined by counting the source with the detector in a fixed position at one cm from the source. Efficiencies shown in parentheses are " scanning" efficiencies obtained by moving the detector at I to 1.5 in./sec over the source. 3. Instrument backgrounds are determined by a 30 minute count. 4.

nstrument hiDAs are calculated using equation 4.1 and the appropriate efficiency, fixed or scanning. Scanning h1DAs are shown in parentheses.

l l 4-4

1 i i Termination Survey Plan Rev. 0 i The minimum detectable activity for surface beta gamma measurements is j estimated using the following equation:' i (4.1) A s+a i 1 MDQf, g !s I where: k= Coefficient from the Normal frequency distribution for the l assigned level of significance (assumes probabilities of type I and type 11 errors are equal), I S= Sample (plus background) count rate (cpm), l j B.= Background count rate (cpm), 4 l t, = Sample count time (minutes), 1 t, = Background count time (minutes), and i I E = Instrument detection efficiency, corrected for detector area, 2 cpm /(dpm/100 cm ). The MDAs shown in Table 4.2 are calculated at the two sigma level, i.e., k = 2 l (approximately 98 % confidence level). As discussed in the Table 4.2 footnotes, these-MDAs represent detection sensitivities under static conditions with fixed 4 geometries. For scanning type surveys, the detection sensitivity is reduced. Threshold or practical detection limits have been empirically determined for each l detector used in the scanning mode. This was donc 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 i in Table 4.2 as the values in parentheses. 4 - 4.2.3 Calibration and Maintenance Instruments and detectors used in the Termination Survey will be calibrated and i maintained at Shoreham Nuclea Power Station according to approved Station i procedures. Detectors for surface beta gamma measurements are calibrated using NIST traceable Co-60 sources. Specialind instruments, for example, the pressurized lon chamber, are calibrated by the vendors. 1 Minimum detectable activity derivations vary somewhat in the literature. The formula' 8 used here is similar to the method reported-in NCRP Report No. 58.(NCRP 85). 4 : .s .a. - ~... ~, _ _ _.. _... -

Termination Survey Plan Rev. 0 4.3 Survey Plan 4.3.1 Classification Each survey unit is classified into one of two strata which identifies each unit as 'affected" or ' unaffected". Units idcr.tified 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 (Lil CO90a) and the history of radioactive 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 sun'cys. For surveys designed on the basis of prescribed sampling plans, whether random or systematic, gridding provides a means of selecting individual measurement locations. hiapping is used to document measurement locations. Detailed guidance for gridding is contained in Appendix A. Figure 4.1 shows grid placement in a st:uctural survey unit classified as affected (an equipment room). Fir.tement of grids in structures is directed by a specific Termination Survey Work Instruction, 4.3.3 Grid hiaps Grid maps are used for survey design and to document the measurement locations. Figure 4.2, Shoreham Decommissioning Termination Survey Grid hiap, shows a typical grid map of a structural survey unit, it shows the floor and walls up to two meters. This map is identified s the base map for the survey unit. Additional grid maps may be prepared for subunits as needed to plan and document surveys of subunits. 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 and proceed sequentially west to cast numbering each row on the floor from south to nnrth in a continuing sequence. Grids are numbered in sequence for each subunit similarly as 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 hiaps Survey maps are prepared to document the details of survey measurements in circumstances where grid maps are not practical. Survey maps are typically prepared 4-6

Tctmination Survey Plan Rev. O to document detailed surveys of piping and system components.' 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 screen large areas efficiently and to detect surface contamination

• hot spots", i.e., localhed areas above three times the 5.000 dpm/100 cm average fixed plus iemovable surface contamination release 2

criterion limit. 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. In structures 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 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. Soil samples will be collected and analyzed in accordance with approved Environmental Sampling procedures. It should be recalled that system component and equipment exterior surfaces are 2 included in the survey of the structural survey unit in which they reside. The component interior surfaces are surveyed in the survey of the system survey unit to which the component belongs. Survey maps ofindividual components rnay thus be prepared for each type of survey. 4-7

1 4 l Termination Survey Plari Rev. O t - 4.3.10 Special Sampling and Measurements a l

a. Sampling of Sediment and 1_oose Material a

l Samples of loose paint, dust or other sediment are collected for laboratory analysis as part of biased sampling and measurements. Such samples may be 1 collected in drain receptacles, sumps, and other catchments in affected areas. I Selected storm drain catchments may be sampled in accessible locations on { the site. These samples are qualitatively analyzed by gamma spectroscopy for j Co 60 3 f

b. Embedded Piping Surveys l

Specialized measurements' will be taken to demonstrate that normally 1 inaccessible piping, e.g., embedded piping is below the release limits for i surface contamination. This includes the use of calibrated detectors extended { into piping runs in a controlled manner and the use of location encoding and j data acquisition equipment to document the measurements. ] 4.4 Background level Determination 1 4.4.1 General Requirements Backgrounds are established for each type of instrument to be used for surface i contamination and gamma exposure rate measurements. Surface contamination j 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 j background responses of the pressurized ion chamber and microrem instruments l must be determined. In addition, backgrounds are determined for speciallred ~ 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, t i 4.4.2 Objectives of Background Determinations l The objectives of background determinations for Shoreham Decommissioning Termination Survey measurements are to: l

a. estrblish ' the' reference background mean values for each type of 4-instrument-detector used in the Survey:-

1 3 Samples with detectable Co-60 will be further evaluated by taking direct 4 - surface beta gamma measurements for comparison with the applicable limits for surface contamination from Table 3.1,1f remediation cannot be reasonably accomplished.. 4-8 4 e e-ecee =, ,e ---n--e. --.,r ---w --ea ev-- 3,e,m, ,mww-g= r -o-graar ew w

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Termination Survey I'lan llev. O

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 Terrnination Survey measurements in specific locations.

4.4.3 llackground hicasurements 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. 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 concrrte pads, loading docks, pavement, roofs and HVAC exhausts. A protocol similar to that described above will be used,

b. Direct Surface Alpha Measurements

'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, 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. 49

Tumination Survey Plan Rev. O

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

e. Gamma Exposure it.te Measurements A Reuter-Stokes pressurized ion chamber is used to establish gamma dose rate background characteristics at the Shoreham site for purposes of 2

demonstrating that residual contamination levels are below 5 pR/hr above background (measured at one meter), it is used as the reference instrument for establishing the pR response of portable microrem rneters. 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. A reference value for the outdoor gamma exposure rate has been established for the Shoreham site. It is based upon a series of pressurizal 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 pR/hr, with a standard error of the mean of 0.5 pR/hr (EG&G84). A series of outdoor measurements will be taken with a pressurized ion chamber in the vicinity of the Shoreham site to confir n or update this result, as the case may be. I A series of paired measureme'its 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 pR/hr 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 Na! detectors are used. Thus it will be necessary either to provide a mockup of an embedded pipe, for example, or to develop empincal correction factors for backgrounds when surveying such equipment. To this end, a series of background measurements will be performed in embedded piping and in large components which can be ascertained to be free of radioactive contamination. 4.4.4 Documentation And Control of Background Measurements Background measurements are collected and recorded in accordance with a Termination Survey procedure. 4 - 10

j { Tennindion Survey Plan Rev. O a 4.5 Sample Analysis l 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. i 4 I i i M d 4 - 11 F -r,,,---- n

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4 Termination Survey Plan Rev. 0 5.0 Data Interpretation All measurements will be converted to the appropriate units for comparison with release criteria limit values. Surface activity measurements will be converted to units of dpm per 100 cm. Gamma dose rate measurements willbe converted to exposure rate units of R/hr 2 and the background value willbe subtracted to obtain net exposure rate. These calculations willbe performed using equations given in Section 8.00f draft NUREG/CR-5849 (BE92). Average values for each survey unit (and/or subunit) will be cornpared with the release criteria values. Confidence intervals will be estimated for mean values of each survey unit (and/or subunit) at the 95% confidence level. 5.1 Conversion of Measurements to Reporting Units 5.1.1 Direct Measurements - Total Surface Activity ] Measurements of surface contamination activity are converted from observed gross counts per minute to net activity concentration by subtracting the background counting rate for the instrument and correcting the net count rate 2 for geometry and efficiency to obtain results in dpm/100 cm units. 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 l the smear counting detector and correcting the net count rate for detector geometry and efficiency. 5.1.3 Gamma Exposure Rate Measurements Most of the gamma field measurements are taken with microrem meters. A correction factor willbe. applied to each reading to convert to units of R/hr, as discussed in paragraph 4.4.3.e. The gamma exposure rate background is then subtracted from the gross pR/hr value to obtain net exposure rate in units of pR/hr. 5-1

i i Tcrmination Survey Plan Rev. 0 ] 5.2 Comparison With Release Csteria Limits l 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. Average Surface Fixed plus Removable Contamination 2

I Individual measurements: Do not exceed 15,000dpm/100 cm (contaminated area not to exceed l 2 100 cm ), 1 2 Population - random sampling: Upper limit of confidence interval for the mean value is below 2 f _5000 dpm/100 cm, d Population - biased sampling: Ifindividual measurements are all 2 1 below 5000 dpm/100cm, the criterion is attained. 1

b. Removable Surface Contamination 2

Individual measurements: Do not exceed 1000 dpm/100 cm, Population - random sampling: Upper limit of confidence interval for the mean value is below 2 i 1000 dpm/100 cm, 1 i Population - biased sampling: Ifindividual measuremer'.s are all 2 below 1000 dpm/100cm, the criterion is attained. l l I I 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. 2 The confidence interval is calculated using Normal statistics at the 95 percent confidence level with alpha = 0.05. Alpha denotes the probability of falsely concluding that the limit l has been attained, that is, the probability of a type I error (MA90). 5-2 ,..,,.,,,...,..~w. __._.,,_,.,.,_,,,,r, m ..m_m.,,,-_..,-- ,,m.,... ,m..,, ..,_.-,m._,.-

'Icrmination Survey Plan Rev. 0 5.2.2 Attainment of 5 microR per hour Criterion Individual measurements: Net exposure rate does not exceed 4 10 R/hr. Population - random sampling: Upper limit of the confidence interval for the mean net exposure rate does not exceed 5 pR/hr. Population - biased sampling: All individual net exposure rates are less than 10 R/hr and the mean is less than 5 pR/hr. 5.2.3 Evaluation of Soil Sample Results I Since soil contamination from Shoreham operations has not been detected in the Site Characterization Study (LILCO90a), or in the REhiP 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 RChfP h1DAs and historical REh1P measurement result ranges for individual isotopes. For gamma emitters where no REhiP data exists, as in the case of Co-60 in soil, results below 1.0pCi/gm average concentration in the top 15 cm. of the soil column will be considered to be below levels comparable to the release limits for surface contamination. 3 3 The guideline value of 1.0pCilgm in soilis applied to the total concentration of Forelam produced gamma emitting radionuclides. 5-3

Termination Survey Plan Rev. 0 \\ 6.0 Report I Upon completion of the Termination Survey, a final report willbe 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 willaddress the following topics. The report willprovide adequate data and discussion of each topic to meet the intent of NUREG/CR-5849 (BE92).A detailed outline of the report is contained in the Termination Survey Program Description. (LlPA92).

a. Background

b. Site Description

c. Facility Description

d. Operating History

c. Decommissioning Activities

f. Termination Survey Prxedures

g. Survey Findings

h. Summary 6.2 Reporting of Survey Findings 6.2.1 Summary Measuremern results will be reported at se.,eral levels of detail. A summary of the measurement results and overall conclusions showing that the facility meets the release criteria willbe provided. A tabular data summary will show the results for each major category of survey unit: structures, outdoor areas and piant systems.This tabulation willidentify the number of survey units, the number of measurements of each type: total 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 will be compared to the release criteria surface activity limits in Table 3.1.

A summary of gamma exposure rate i measurements will present a similar treatment showing that the mean value 6-1

Terndnation Survey Man Rev. O is less than 5 microR/hr above the background value. 6.2.2 Summary Data Reporting for Each Survey Unit 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 l level) will be reported in tabult.r form. Dese will be reported in units of dpm/100 cm for each type of measurement: total surface beta gamma, total 2 surface alpha, removable surface beta gamma and removable surface alpha activity concentration. Gamma exposure rate measurement results will be reported showing thc, number of measurements and upper limit of the confidence interval about the mean (at the 95 % con 0dence level) for each survey unit, (and/or subunit). The release limit value for cach type of measurement will be shown on the report. Results cf sampling measurements, e.g., sediment, paint, concrete, other debris will be reported for each survey unit. Any portions of individual sun'ey units not meeting release criteria will be remediated. The Final Report willidentify all such areas and will report the prior and post remediation measurement results. 6.2.3 Detailed Data Reporting The results of each measurement taken in the Termination Survey will be tabulated. Due to the volume, these data will not be included in the final report, but will be available as an attachment. Table 6.1 shows an example of a typic:.1 format for individual measurement tabulations for a structural survey unit. Resuhs of alpha activity measurements will be reported in a similar format for those survey units where alpha measurements are taken. Tables of similar format will be reported for systems and outdoor survey units. 6-2

Table 6.1 Repor1 Date: 31-Aug-92 Termination Survey Detail Data Report - Structures Pg.1 of 4 4 Survey Un't ID TB014 Building: Turbine Elev.15 ft. Survey Date: 8/24/92 Name: ' A' RFPT Rm. Subunit: floors and lower walls Subunit No. TB014x1 Instrument Type FIMon. GM LAD Smear Ctr microRem instrument ID 1132666 142310 1-ADX40123 DD1234 o Det. area (sq.cm) 750 126 50.2 NA Eff (or corr fact) 0.06 0.04 0.47 1.59 Bkgd(cpm or UR/ht) 810 120 0.9 7.7 total beta-gamma removable beta-gamma observed not Block ID point auri scan gepm dpm/100cm2 gepm dpm/100cm2 uRem/hr uR/hr F1 1 sat 122 52.7 1.3 0.9 4.0 -1.3 F4 2 sat 114 -159.5 2 2.3 3.0 -2.9 F7 3 sat 118 -54.8 0.5 -0.9 3.0 -2.9 4 F11 4 sat 129 233.7 5.1 8.9 3.0 -2.9 F12 5 sat 122 56.3 3.3 5.1 5.0 0.3 3 FIS 6 sat 121 15.4 2.2 2.0 6.0 1.8 F21 7 sat 113 -173.8 0.4 -1.1 4.0 -1.3 F24 8 sat 129 216.8 1.8 1.9 5.7 1.3 F31 9 sat 122 62.1 0.9 0.0 3.6 -2.0 F32 10 sat 114 -139.8 3.1 4.7 4.4 -0.7 F33 11 sat 127 166.2 0.6 -0.6 4.0 -1.3 F39 12 sat 117 -71.0 2.1 2.6 3.3 -2.4 F43 13 sat 127 180.6 2.1 2.6 5.6 1.2 F44 14 sat 127 171.3 3.4 5.2 3.0 -2.9 F48 15 sat 119 -23.9 0.7 -0.4 4.8 -0.1 F50 16 sat 114 -146,0 3.2 4.9 3.1 -2.7 F51 17 sat 114 -160.6 1.5 1.3 5.8 1.6 F55 18 sat 125 130.7 0.5 -0.9 5.8 1.5 F57 19 sat 123 82.5 0.9 0.0 5.0 0.2 F62 20 sat 122 45.6 4.8 8.2 4.3 -0.8 F66 21 sat 115 -131.8 4.0 6.6 5.8 1.4 F70 22 sat 113 -165.8 0.6 -0.0 4.4 -0.7 F72 23 sat 129 219.2 3.0 4.5 5.5 1.0 F76 24 sat 114 -140.7 0.9 0.0 4.8 0.0 F77 25 sat 116 -94.4 0.7 -0.4 4.1 -1.2 F79 26 sat 118 -56.8 0.4 -1.1 3.3 -2.4 W2 27 sat 126 145.R 0.2 -1.5 4.3 -0.9 W5 28 sat 120 12.0 4.1 6.8 3.7 -1.8 W7 29 sat 114 -141.2 0.8 -0.2 4.4 -0.7 W8 30 sat 120 -11.8 0.6 -0.6 5.0 0.2 W11 31 sat 111 -219.6 5.0 8.7 3.7 -1.9 W16 32 sat 112 -190.6 1.8 2.0 3.9 -1.5 W18 33 sat 112 -202.2 3.5 5.5 3.1 -2.8 W21 34 sat 120 5.8 3.3 5.0 5.5 1.1 6-3

-. -=_ 4 Termim.tlon Survey Plan Rev. O i a 7.0 References BE92, J. D. Berger, " Manual for Conducting Radiological Surveys in Support of 1.lecnse Termination *, NUREG/CR-5849 Draft, June,1992. EG&G84, EG&G Energy bicasurements, "An Aerial Radiological Survey of the Shoreham Nuclear Power Station and Surrounding Area, Brookhaven, New York," EGG-10282-1041, prepared for the U. S. Department of Energy, h! arch,1984 LILCO90, long Island Lighting Company, " Updated Safety Analysis Report - Shoreham Nuclear Power Station," Docket No. 50 322, Rev. 4, Decernber 1990. LILCO90a, Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," hiay 1990, (with addenda; June & Oct.1990). LIPA90, Long Island Power Authority, *Shoreham Nuclear Power Station Decommissioning Plan," NRC Docket No. 50-322, December 1990, as supplemented. LIPA92, Imng Island Power Authority, LIPA Nuclear Management Control Manual,

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

LIPA92a, ler.g Island Power Authority, Quality Assurance hianual, Appendix N, " Decommissioning Activities," June, 15, 1992. MA90, F.H.C Marriott, "A Dictionary of Statistical Terms",1xngman 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, *Terminatica of Operating Licenses for Nuclear Reactors," June 1974.

USNRC92,

" Order Approvirg the Decommissioning Plan and Authorizing Decommissioning of Shoreham Nuclear Power Station, Unit 1," Docket No. 50-322, June 11,1992. 7-1

l Termination Survey Phn Rev. 0 8.0 Glossary Affected Area A designation assigned to a survey unit which indicates that the survey unit has a potential for containing residual radioactive contamination. A]pha _Affected Area - A designation assigned to a survey unit which indicates that the potential exists for alpha contamination, j Blased 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 Survev - A radiological survey and supporting evaluations performed to establish the Shoreham Facility baseline radiological cont'ition 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, tretor, etc. which is identified in the Shoreham Composite Component List. Composite Component List (CCL) - A controlled listing of components installed at Shoreham. The CCL identifies all components other than cable tray and conduit supports 4 in the SNPS design. The CCL also deFnes 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. i Confidsnce Irvel - The probability a, associated with a confidence interval which expresses the probability that the confidence interval contains the population parameter value being estimated (MA90). DUCON - The decommissioning alternative which involves prompt removal of radioactive materiata to achieve residual contamination and radiation levels which are below limits established to permit the facility to be released for unrestricted uce. Direct Measurement - A radiological smvey measurement performed by holding a detector stationary on or close to the surface and recording the response, libtory 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. 8-1

4 Termin: tion Survey Nn Rev. 0 Maintenance Work Request (MWR)- A form used at Shoreham Nuclear Power Station, controlled by a station procedure, to initiate and track work activities. hka)urement Imcation - A distinct or discrete area or subdivision of a survey unit, usually on a scale of one meter or less selected for performance of radiological survey measurements. In affected structural or outdoor survey units, a measurement location is adequately represented by a single grid block. In a system survey unit, a component such as a valve is referred to as a measurement location or survey location. NRC - U. S. Nuclear Regulatory Commission j Oncrational Radiological Survey - A radiological survey performed under Shoreham 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. Plant Structures All Shoreham Nuclear Power Station site buildings and their surfaces (generally identified as civil structures). For purposes of the Termination Survey, all structures such as platforms, restraints, supports and othei physical items not identified in the system MSFK 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 v;Jue of a parameter, such as contamination level mean value in the entire survey unit (or subunit), based upon a sample of measured values. Power Bleck - 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 Irdex - A listing, controlled by a station procedure, which identifies and assigns a unique identification code to each plant system. OC Verification Survev - 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. 8-2

1 Tormination Survey Non Rev. O 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. _ elease Record - A document compiled for each Survey Unit (structure, system or R 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 4 results and basis for the conclusion that the release criteria are satisfied. j i Scan Survey - A qualitative radiological monitoring trrhnique which is performed by moving a detector over a 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 j surveys, calculations and evaluations and presents the results of the SNFS Site Characterization Program. Subunit - A Subunit is a subdivision of a survey unit used in the survey design to establish the appropriate level of survey intensity within a survey unit which contains structures, equipment items or other properties which make up a complex survey unit. Survey Design The process of determining the type, location, number and frequency (or density) of radiological measurements to be taken in the Termination Survey. Survey Design Guidelines - Criteria established to provide the appropriate level of survey intensity for systems, structures and outdoor areas, based upon their classification. Survev Insinletions - 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 Package - A collection ofinformation in a standardized format for controlling and 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 control form, 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. 8-3

Termination Survey Pain Rev. O Survev Unli 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 rnanagement of the Termination Survey. Three categories of survey units have been established: plant systems, structures and outdoor ateas. Survey Unit Classincation Description - A listing of all survey units established for the Shoreham Decommissioning Project Termination Survey which identifies the classification of each as "affected" or " unaffected". l System Final Connguration: - The status of plant systems following completion of the Termination Survey. The fmal configuration establishes the nature of the controls required to maintain the integrity of survey results. It also determines the nature of configuration 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 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. Systematic Samplc - A sample which is obtained by some systematic method as opposed to a random sample; for example, selection from a list using a specified interval 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 Survev - Radiological measurements, evaluations and supporting activities undertaken to demonstrate that the Shorcham facility satisfies the criteria for unrestricted use. Termination Survey field activities are divided into phases called the Preliminary and Final surveys. Termination Survey Section - A Section established within the Radiological Controls Division, Operation 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. 8-4

J 2 Termination Survey Pica Rev. 0 1. ] Ne 1 Error In the statistical theory of hypothesis testing, the error lacurred by l rejecting a hypothesis when it is actually true (MA90). In the Termination Survey j 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. i i Tvoe II Error - The probability of deciding that the facility (or a survey unit) does not meet the release criteria, when the true condition is that the facility does meet the criteria. De Type 11 error probability is denoted by #. i ] Unaffected Area - A designation used to identi, a survey unit which is not expected to j contain residual radioactivity from licensed operations based upon the operating history and radiological surveys. i j Work Instruction A document used to guide performance of a task. Work instructions i 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 1 j

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Termination Survey Plan Rev. O Appendix A Survey Design Guidelines 1.0 Introduction This Appendix provides guidance for preparation of the design of the Shoreham Decommissioning Project Termination Survey.It incorporates the guidance in NUREG/CR-5849 (BE92) with adaptations to account for conditions at the Shoreham facility. The objective of survey design is to define the measurements necessary to demonstrate that the facility satisfies the release criteria. As it is not feasible to perform detailed radiological I surveys of 100 percent of the facility, measurements are performed at selected krations. 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 to the likelihood of encountering residual radioactivity. This approach is implemented at the facility level by classification of individual 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 2.1 Facility Organization and Classification At the facility level, the design and organization for the survey consists of the following:

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

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

c. classification of survey units into two major strata based upon potential for residual contamination, i.e.,affected and unaffected, and d establishment of a reference grid system for identification of measurement locations.

2.2 Survey Design for Individual Survey Units The Termination Survey is implemented in the field at the individual survey unit level.The design isdeveloped, measurement instructions prepared and measurements A-1

Termination Survey Plan Rev. O a completed for each survey unit independently. The guidelines in this Appendix are applied to each survey unit based upon its classi0 cation 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 denned as a division of the facility consisting of like entitles 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.. Structures For ' :rmination Survey purposes, structures include the indoor portions of site balldings including the exterior surfaces of plant systems, equipment and furnishings located therein Structural survey units are established by division of the facility buildings into discrete (usually contiguous) geographical areas takint; advantage of existing structural boundaries where possible, i.e., rooms or major elevations of small buildings. L 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 miscellar.cous outdoor structures include equipm:nt storage pads, switchyard transformers and storage tanks, for example. 3.1.3 Systems Systems included in the Termination Survey as survey units include all nuclear steam supply, reactor control, and process systems, and building servia systems associated with the SNPS design and described in the SNPS USAR (LILCO90). Each system identified in the Records Management File Code List is treated as an individual survey unit. A system survey unit encompasses the interior surfaces of fluid carrying piping and components of the system. 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

\\ Tennination Survey Plan Rev. O 3.3 Sire and Scope of Survey Units 3.3.1 Structures l A structural survey unh includes the entire surface arca of floors, walls, ceilings, and outside surfaces of equipment and furnishings. The sire of structural survey units is established by natural boundaries such as rooms in i 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 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 roon, size or building floor plan sire. Unaffected areas in large buildings may be combined 4 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 pk ag and other systems are 7 "MFSK" series of flow established by the controlling drawings, usual' 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 7 possibility of containing residual contamination and than identified as unaffected have a very low probability of residual ccatamination. Classification of individual survey units is based on the history of radioactive r sterials 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 usign purposes when the following conditions apply:

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

Termin6a Survey Plan Rev. 0 known contamination oased on radiological surveys, c.

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 sutvey 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 utillration history and radiological survey results, and

b. not classified as affected.

4.2 Systems 4.2.1 Affected Systems Systems are classified as affected for survey des;gn purposes if th: 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 circulated, stored or processed radioactive materials, including: primary coolant, radioactive process or treatment niedia which were associated with the operation or control of the Nuclear Steam Supply System (NSSS) st.eh that they could become contaminated or experience neutron activation; or where records indicate spills or occurrences which ccald have resulted in contamination.

4.2.2 Unaffec:ed Systems l 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.

A-4

d Termination Survey Plan Rev. 0 4.3 Reclassi6 cation Survey units may be reclassified subsequent to the initial classificatiori according to the following critetia: 4 i 4.3.1 Upward Reclassification i A survey unit must be reclassified from unaffected to affected if at eny dme in the survey planning, design, or durir.g the actual survey, new information i i is ob sined which indicates that the criteria for an unaffected survey unit are no loager satisfied. Upward reclassification of the survey ur' is required if any surface contamination measurcenent exceeds 75 percent t iy of the limit i values in Table 3.1 of the Termination Suvey Plan. That is,if a direct surface 2 l contamination measurement results exceeds: 3750 dpm/100 cm averaged 2 ove* an ama not e=ceeding one wth or 12,500 dpm/100 cm n a localized area 100 cm or less; or removable surface cor.tamination exceeds 750 2 2 l dpm/100 cm If a survey unit is reclassified upward, st mt measurements must be taker to meet su.vey design guidelines for rc areas. i 4.3.2 Downward Reclassification A survey unit may be reclassified downward from affected to unaffected pric. 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 i i contamination is detected and records indicate that there is no history of j 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 i scope of !!.e Survey to ensure that applicable release criteria limits for alpha contamination are satisfied. A survey unit (structural area, system or outdoor area) i is classified at au drt s affected area if the following conditions apply: i a alpha activity greater than 25 percent of release criteria limits has been detected, or

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

In alpha affected survey units, direct meas: tents and measurements of surface alpha contamination are added to the list of measurements normally performed at i the selected measuo. ent locations. Surface scans for alpha' activity are performed in the vicinity _of the ' elected -measurement locations. l A-5 ~

Termination Survey Plan Ren 0 5.0 Reference Grid System and Gridding of Survey Units l The reference grid system for the Termination Survey establishes a discrete-uniform subdivision of areas covW by the survey.The principal objectives of grid marking are: to ) 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 mundaries of areas needing remediation. 5.1 Gridding Affected Areas 5.1.1 Indoor Areas

a. Floors and Iewer 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 ceil'ngs of affected structural survey units if the areas a c determined to be suspect as defined in Section 7.1.2.lf determined to be suspect, the areas are gridded in accordance with Paragraph a. above. If the area is not suspect, the guidance in Paragraph c. below is applied.

c. Other Surfaces Grids are marked on surfaces of equipment and other ncn-regular

( surfaces in affected structural survey units as needed to aid in the design of surveys and to control and document the location of measurements. If not possible to mark such items into one meter square grids, regularly spaced markings one meter apart may be used. 5.1.2 Outdoor Areas

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

b. Roofs and Building Exterior Walls Roofs and exterior wallsin 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.

1 A-6

Tumination Survey Plan Rev 0 5.2 Gridding IInaffected 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 controi scan surveys. 5.2.2 Outdoor Areas Grid marking of surfaces in outdoor areas is not required. If desired for reference purposes, grids may be used. 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 FNPS facility is to document a measurement location with an uncertainty of less than one meter. To ensure that this is attained, griu 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 i In affected areas, structures are generany 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 and equipment, additional subunits may be needed. Separate subunits are un; ally 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 A-7

Termination Survey Plan Rev. 0 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 elemuus 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 separate components are usually divided into subunits for 3 survey design purposes. A typical subunit comprises a large bore component and the adjacent piping. Usually tanks, heat exchangers and other vessels are treated as subunits. 6.4 Classification of Subunits Subunits may be classined differently from the survey unit in which it resides under certain conditions. A subunit within an affected survey unit may be classiGed as 4 unaffected if it is a physically separate entity with no likely mechanism for transfer of contamination from the affected portions to the unaffected portions. The typical applit ation of this classification option is the classincation 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. 7.0 Measurement Location and Frequency of Measurements 7.1 Structures 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: l Large, oore at SNPS refers to piping and the piping system components associatd with piping having inside diameters of 3 inches or greater. A-8

Termination Survey Plan Rev. O 2

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 survcy 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 affe-ted areas are surface scanned over 100% of the area. Measurements are taken at fixed locations. Measurements are taken systemrtically 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. Survey intensity of upper walls and ceilings classified as affected areas is determined based upon the suspected level of residual contamination.

a. Not Suspect The rule for determination than an area is not suspect is: expected contamination levels must be below 75 percent of release criteria guide 2

line values, i.e.,below the following values: 3750 dpm/100 cm direct 2 surface average,12,500dpm/100 cm direct surface maximum and 750

2. 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: 5000 dpm/100 cm. That is, the scanning 2 method must be capable of detecting levels below 2750dpm/100 cm averaged over 2 an area not to exceed one m. As described in Section 4.20f the Termination Survey Plan, the Termination Survey instrumentation scanning sensitivities are below this value, so the conditional measurement f::quencies in NUREG/CR-5849 are not invoked. A-9

j.

Termination Survey Plan Rev. 0 2 dpm/100 cm removable surface contamination, ~1f the area is not j suspect, a minimum of 30 measurements locations are selected on horizontal - surfaces, and 30 on ' vertical surfaces. The measurement 2 j density shall be at least one measurement every 20 m averaged over i the area of the subunit. A scan survey is performed in the immediate i area of each selected measurement location. The scan survey covers an 1 2 l 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 i occurred and on surfaces where contamination potential is highest. 1 I

b. Suspect, t

l If any area is suspected to be or is above the levels prescribed in Paragraph a above, the survey protocol i_s the same as for the floors j' and ' lower walls of an affected area. That is, a 100 percent scan with l the fixed location measurement frequency.of one measurement every i second grid block, for a minimum of 30.The area is gridded in 1 m grids. 7.1.3 Unaffected Areas

a. Inside The Power Block i

Floors and lower walls of unaffected indoor areas-(structures) within the Power Block are scan survey ed over a minimum of ten percent of f the ' area, focusing on walkways' and common!y 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 i surface area) are required whichever is greater. i 2 Thirty locations or an average of one measurement location-per 50 m, i 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 1

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 2 one per 50 m, whichever is greater. Lower walls are not included in the survey of floor areas. -l l Thirty locations are selected at random from the walls (including lower-2 alls) and ceiling areas, ~or an average of one per 50 m, whichever is w greater. No scan survey is performed. ) H . A - 10

~ Termination Survey Plan Rev. 0 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 4 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 take-n at each measurement location.

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

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

a. Paved Areas Paved areas are surface scanned over at least 10 percent of the area with a beta-gamma detector.

Direct surface contamination measurements are made at a minimum of 30 randomly selected locations.

b. Unpaved Areas Unpaved areas are surface scanned over at least 10 percent of the area with a gamma detector (NAI or microrem). Microrem measurements at one meter from the ground surface are taken at 30 randomly selected locations.

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 A - 11

. ~. _ l-Tumination Survey Plan Rsv. 0 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 i 2 g design should focus on likely areas for deposition, e.g., downwind of stacls, i l - vents and drains. 4-7.2.4 Unaffected Areas - Building Exteriors I The survey of exterior surfaces of buildings and structures which are classified f as unaffected is as follows: i,

a. Exterior Walls Surfaces l

The survey of building exterior walls focuses on the area within two meters of the ground surface. The areas are surface scanned over a j 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 greater. l

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 i buildings, if any of these surfaces are classified as affected, they are i 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 areas _which are classified as unaffected are not surveyed. l 7.2.5 So.il hns:1.g l Soil samples willbe collected from the the site grounds for the Termination l: Survey. Thirty locations will be selected at random from the site. The soil i_ samples will be collected from the top 15 cm. of the soil column and will be l analyzed as REMP samples. The analysis willinclude gamma spectroscopy for Co-60. [ l Additional soil samples are collected as needed to support the Termination j Survey 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 aajacent to or below catchments,, sumps'and building foundations. t i 7.3 Plant Systems l 7.3.1 Selection of Measurement Locations Surveys of systems are biased sampling surveys. Selection of measurement j locations in both affected and unaffected systems' focuses on the kcations_ with _ I A ' - 12 e

- - ~ !e Termination Survey Plan Rev. O l the highest probability for contamination considering the system design and j 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-i piping in piping systems. A component includes any discrete element which-is distinguishable from piping. When a component is removed or opened _for i 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. l-The survey design should take advantage oflow cost access methods including j destructive cutting of piping, (where permitted). 1 1 l 7.3.2 Breakdown Into Subunits h j 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 i system in which they are located. In piping systems, each fluid carrying j interface to other systems is usually established as a subunit. j-7.3.3 Survey Measurements i The interior surfaces of components selected for survey. measurements are j usually scanned over 100 percent of the accessible. area. Where physical size [ permits, locations are selected such that both direct and removable surface i 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 l= such as the Condenser Hotwell. At least one-direct surface and removable surface contamination measurement is taken at each location l 7.3.4 Measurement-Frequency - Affected Systems i i In general, the measurement ' frequency is strongly influenced by the size and-l complexity of a system. In affected systems, the design guideline' is a minimum. j of 30 measurement locations. Exceptionsa may_ arise where the system is j limited in physical extent such that 30 discrete locations cannot'be identified. 1 7.3.5 Measurement Frequency - Unaffected Systems 2 i _ In unaffected - systems,'a minimum of 10 measurement. locations' will be j 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. A - 13 r--:ws,---,r<---w my v v w,r, ,-m r -.-4 ,-w. w -,ry--t y-r y --r,+-- r-.,w-ew

. ~ ~ - -.. - ~.. . -. _. ~ 4.. }. Termination Survey P!an Rev 0 l 'e 7.3.6 Embedded Piping. i i Two piping systems, Liquid Radioactive Waste (Gil), and Fuel Pool Cooling. -and cleanup (G41), have substantial. lengths of piping which are embedded in i- . reinforced concrete structural nwmbers, i.e., floors and walls.The embedded piping in G11-and G41 systems are each established as separate survey units for the Termination Survey. For management of the survey, each may be i further divided into subunits for survey design and control purposes. All GilJ i-and G41 embedded piping is classified as affected. Detailed surveys are i performed with detectors inserted into embedded piping runs. All openings and normal access points (cleanouts) willbe surveyed. All runs of piping will be systematically surveyed over at least 25 percent of their length. s ! ~. r ei. i. i F ~ i i 4 a i i I l-i A -14 2

I a i i J 1 ENCLOSUREI New Chapter 4.0 - SNPS Decommissioning Plan i Proposed Termination Survey I l 4 l' a i

4 Shoreham Decommissioning Plan 4 4 4.0 PROPOSED TERMINATION SURVEY 4.1 Termination Survey Overview-4.1.1 Survey Objectives l The Termination Survey is designed to demonstrate that licensed radioactive materials have been removed such that residual levels of radioactive contamination are below applicable Regulatory Guide 1.86 limits (Ref.4-1). These are shown in Section 4.2, Release Criteria. Radiation detection i 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, hence

~

the limits for beta-gamma emitters shown in section 4.2 apply. i The applicable release limits for alpha emitters are also shown in Section 4.2. These are for Natural Uranium, U-235, U-238 and associated decay products. Though none has been detected in plant contamination deposits, the presence of the irradiated fuel in the f acility provides a potential source.of a alpha contamination. Instruments and methods are being incorporated into the survey which are adequate to measure alpha surface activity at levels below the limits in section 4.2, 4.1.2 Identity of Contaminants 1 The Shoreham Characterization Study (Ref. 4-5) reported a total facility radioactivity inventory due.to Shoreham operations of about 600 Curies (C1), (not including the irradiated fuel and control blades). All but a very small fraction (less than one C1) of this inventory is contained in 4 i activated materials of the Reactor Pressure Vessel and Vessel I Internals which will be removed from the site. The calculated l 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 calculated to be present, j including: H-3, C-14, and Ni-59. Laboratory analysis of i activated Reactor Pressure Vessel and Pressure Vessel internals samples indicates the presence of low levels of Mn-54, Zn-65, and Ni-63, in addition to Co-60. Analysis - of bi',nield wall samples show low levels of Co-60, Mn-54 and Eu-152 (TU92). 4-1 4 + w

Shoreham Decommissioning Plan t Detectable radionuclides in surface corrosion deposits are confined to a small number of radionuclides. An analysis of piping system corrosion products shows that these are comprised largely of Co-60 and Fe-55, with an average Fe-55:Co-60 ratio of approximately 0.2 (0.21 +/- 0.13). Laboratory analysis of plant corrosion product deposits has not identified the presence of reactor-produced alpha emitters above lower limits of detection. 4.1.3 organisation 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 (Ref. 4-7). 4.1.4 Training Technician Qualification A job qualification for Termination Survey technicians will be established under the existing Shoreham Station " Health Physics Technician Selection, Training and Qualification Program" procedure. The training and qualification acceptance criteria from this procedure will be adopted. The training will include classroom and functional job performance training on Termination Survey procedures and specialized instrumentation. The training and qualification process for individual technicians will require from three to five days to complete. Termination Survey technicians will generally be selected from the pool of technicians who have previously been qualified to perform HP responsibilities on the Shoreham Decommissioning Project. Classroom Training Classroom training includes: an overview of the Termination Survey Program, instrumentation, and procedures. The overview will cover Termination Survey 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. 4-2

4 4 J Shoreham Decommissioning Plan i Functional Training i i Functional training will involve hands-on performance of principal HP technician Termination Survey tasks. A survey of l a typical Survey Unit will be performed by eacn technician under the surveillance of a qualified instructor. l 4.1.5 Laboratory services { Laboratory radioanalytical services of the Shoreham Nuclear Power. Station 11adiochemistry Section, Radiological Controls-Division will be used in support of the Termination Survey. l The on-site capabilities include gamma spectroscopy (GeLi) of l filters, smears and bulk samples;-liquid scintillation; and j gas proportional counting. The ; adiochemistry Section operates i under an approved QA program and procedures. A contract will also be maintained with _ a qualified vendor for specialized radiological analysis of samples on an as-needed basis. i Vendors are selected in accordance with the requirements of j. the LIPA QA Manual, Appendix N. l t 4.2 Release Criteria Acceptable Surface Contamination Lgy_gl.g (dpm per 100 cm* ) i Fixed Plus Removable Removable-l Activity Avera c_q Maximum f Beta-Gamma 5,000 15,000 1,000 1 l Alpha 5,000 15,000 1,000 t In addition, to the limits shown above, the gamma exposure rate at one meter from accessible surfaces in the facility l buildings and outdoor areas shall not exceed 54R/hr above background, measured at-one meter from surfaces, j 4.3 g3Aeral survey Plan i 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- ] 4-3 i b 1 c -n

Shoreham Decommissioning Plan 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. Key interfaces between survey activities and other decommissioning work activities have been 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 erection of scaffolding, system tag out 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. 4.3.1 Initial classification The initial classification of the facility into "af fected" and "unaf fected" areas provides an overall planning basis for the Termination Survey. It was conducted using results from the Shoreham Site Characterization Program and the recommendations of experienced Shoreham personnel using the classification criteria contained in the Shoreham Termination Survey Plan 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. 4.3.2 History File Preparation The history file is a compilation, in a standardized format, which summarizes the operational and radiological history of each 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 (Ref. 4-5) radiological surveys and other relevant information. Specific operating history which could affect the radiological status is sought in this review.

The purpose af this process is to provide a substantive basis l 4-4

1 Shoreham Decommissioning Plan for the survey unit classification, and hence the level of intensity of the Termination Survey. 1 The history file contains a summary description of the survey unit. For system history files, it identifies the interfacing piping systems and summarizes relevant operational data. i 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 radiation use history (if any) is summarized. Possible outcomes of the review 'a r e : '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. 4.3.3 Turnover for Termination Survey Prior to acceptance of a survey unit (structure, system or outdoor area) for the Termination

Survey, a

number of 1 conditions must-be satisfied. Decommissioning activities are completed, all tools are removed, housekeeping and area 4 cleanup is completed, decontamination of affected structural areas and system residual components is completed and verified ' by operational radiological surveys, and scaf folding needed to be left in place for Termination Survey is identified. Radiological surveys verifying the status of the area, if a i 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. 4.3.4 -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, _ ard 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, 4-5

Shoreham Decommissioning Plan 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 af ter the completion of decommissioning work. Early information is available through Decommissioning work packages and material takeoff lists and drawings. 4.3.5 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 sample to be collected at each location. The design is based upon the guidelines in Shoreham Termination Suvey Plan Appendix A. The design of the survey for individual survey units is prepared in accordance with a Termination Survey procedure. 4.3.6 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 review implemented through approved engineering procedures. 4.3.7 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 returned to service. The 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. 4.3.8 Survey Instructions The survey instructions are provided to the Lead HP technician assigned responsibility for the specified survey unit. They i specify the number and type of radiological measurements to be taken at each location or component identified in the survey 4-6 l l

Shoreham Decommissioning Plan 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, 4.3.9 Field Support The MWR identifies each component or survey location requiring support work and tag outs. 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 of large tanks once access is provided and saf ety precautions have been satisfied. 4.3.10 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, smear samples for removable surface contamination and gamma exposure rate measurements. The measurements are discussed in Section 4.0 of the Survey

Plan, (Ref.

4-?). 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 tne instructions.

4.3.11 Restoration and Isolation Systems After survey measurements have been taken, reviewed and approved, and QC verification survey 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 MWR, the system is isolated to protect against recontamination. Isolation and control of plant systems af ter Termination Survey is performed - under a specific approved procedure. It is noted that many plant support and service systems will be returned to service af ter completion of Termination Survey measurements. Examples are: compressed

air, heating and cooling, ventilation and fire protection. When a system is 4-7

Shoreham Decommissioning Plan 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. 4 Structures and outdoor Areas l measurements are completed in structures and outdoor Aft areas, each area is posted and access is controlled to prevent or minimize possible contamination. This in controlled by an approved station procedure. 4.3.12 Quality Assurance 4.3.12.1 General Provisions As indicated in Section 7.0 and in the Termination Survey

Program, quality assurance for the Termination Survey is subject to the provisions of the LIPA Quality Assurance Manual.

In addition, the Termination Survey Program has established quality control measures as an integral part of 4 the program. Principal measures established to meet quality objectives are: a) Selection and Training of Personnel 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 training and job-functional training. Training and qualification records are maintained on all technicians selected for the Termination Survey. 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 of Standards and Technology (NIST), _ or by qualified vendors with the results traceable to NIST. Measurements are performed using approved written procedures for each instrument. Control of instruments is established by an instrument control procedure. 4-8

Shoreham Decommissioning Plan c) Survey Documentation Each Termination Survey measurement is identified by

date, instrument, technician,

location, type of measurement, and mode of instrument operation.

d) Quality Control - Verification Replicate measurements are performed independently on a selected sample of survey measurements on an ongoing basis. e) Written Procedures Termination Survey tasks which are essential to survey data quality are controlled by procedures reviewed by the LIPA Site Review Committee. f) Mockup of Procedures and Processes Dry runs and mockups are performed to test principal procedures and methods prior to inplementation in the

field, g)

Chain of Custody Written procedures establish responsibility for custody of samples and survey data between the point of measurement or collection until final results are obtained. h) Records Management Generation, handling and storage of Termination Survey design and data packages are controlled by an approved procedure, 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. l 4-9

Shoreham Decommissioning Plan k) Control of Surveyed Areas and Systems Administrative, (i.e., procedural) and piersical controls are established on areas and systems to minimite the possibility of contamination subsequent to the survey, 1) Control of Vendor Supplied Services Essential services, such as instrument 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.

4.3.12.2 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 t.urvey measarement data prior to acceptance for data processing, c) control charts for individual instruments, d) testing of computer data calculation programs, e) validation of historical operational survey data l used as final survey data, f) documentation of surveys, and g) custody of instruments, samples and measurement data. 4.3.13 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 Operation and Maintenance Department. The Termination Survey is scheduled to be completed in several major phases which encompass distinct portions of the facility. Upon completion of each phase the release records will be compiled and the survey units covered will be 4-10 \\

i 4 Shoreham Decommissioning Plan available for NRC verification surveys. All except the final phase of the Survey are scheduled for completion by October 1, i 1993, with the final phase to be completed following removal i of the irradiated fuel from the facility. The current j schedule date for completion of fuel removal is April 1994. j 4.3.14 survey Report l Upon completion of the survey measurements, processing of the i resultant data, and evaluation of the results, a final _ report will be prepared for submission to the Nuclear Regulatory Commission. This report will meet.the intent of Regulatory Guide 1.86 (Ref. 4-1) for final survey reporting. The Final j Report will follow the guidance of Draft NUREG/CR-5849 (Ref. 4-4) regarding content. Interim reports will be submitted for the major survey phases as discussed above, i 4.3.15 Changes to the Termination Survey Plan The planning, scope and methods to conduct the Termination Survey are based on the best available inforwaation as to the potential for residual contamination fron. decommissioning-activities. As discussed in reference 4-4, changes to Plans and Procedures-may be necessary based-on unanticipated findings on conditions encountered as the survey progresses. Administrative procedures have been established to control i changes to the Shoreham Termination Survey Plan, as well as chanages to implementing procedures, i i. i i o i s a 4-11

Shoreham Decommissioning Plan 4.4 References 4-1 U.S. Nuclear Regulatory Commission, Regulatory Guide 1.86, " Termination of Operating Licenses For Nuclear Reactors," June 1974. 4-2 U.S. Nuclear Regulatory Commission, " Technology and cost of Termination Surveys Associated with Decommissioning of Nuclear Facilities," NUREG/CR-2241, February 1982. 4-3 U.S. Nuclear Regulatory Commission, " Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," NUREG-0586, August 1988. 4-4 U.S. Nuclear P,egulatory Commission, " Manual for Conducting Radiological Surveys in Support of License Termination" Draft Report, NUREG-CR-5849, J<AU-9 2 / C 57, June 1992. 4-5 Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program, Final Report," May 1990; Addendum 1, June 1990; Addendum 2, August 1990. 4-6 U.S. Nuclear Regulatory Commission, " residual Radioactive Contamination from Decomb'ssioning, Draft Report for Comment, "NUREG/CR-5512, January 1990. 4-7 Shoreham Decommissionina Project Termination Survey Plan. Rev. O, October 1992. f 4-12 l l

} 4 h d i 1 ENCLOSURE 2 i Shoreham Deconunissioning Project i l Termination Survey Plan, Revision 0 October 1992 i i i 4 i 1

. mas.__ s_ m aap. i 1 i i ENCLOSURE 3 i NUCLEAR ORGANIZATION MANAGEMENT CONTROL PROGRAM } FOR Decommissioning Termination Survey Program Description Revision 1 (PDXOM-01) i 7

1* 4 L 6 PDXOM-01 Rev. 1-Effective Date.//t o/r/t-1 LIPA NUCLEAR MANAGEMENT CONTROL MANUAL 4 i j i NUCLEAR ORGANIZATION MANAGEMENT CONTROL PROGRAM FOR Decommissioning Termination Survey Program Description (PDXOM-01) 4 i i ikEfiL Date Approved L[ Hill RVsident - Manager 1 4 e 7 - 'p M r 'r aag. . J i l, I i (, m g,g ; i i I

i i ? Progrc3 Description PDIoM-01 Decommissicaing T3rminatico Survey REV. 1 . rage 1 of 26 TERMINATION SURVEY PROGRAM DESCRIPTION l TABLE OF CONTENTS l 1.0' OBJECTIVE.. 3 2.0 REFERENCE 8 3 4 3.0.s11,111.0,.. i 4.0 RESPONSIBILITIES 7 4.1 LIPA - SNPS Resident Manager 7 4.2 Decommissionina Department Manaaer -7 l 4.3 Muglear Ouality Assurance Department Manager 8 l 4.4 Nuclear Operations suonort Department Manaaer. 8 j 4.4.1 Fuel Disposition Division _ Manager 8 4.5 Licensina/Reculatory CoMDliance DoDartment-Mantqct 9 4.6 Finance and Administration Department Manager. 9 4.7 Coeraticps and Maintenance Department Manager... 9 4.7.1 Radioloaical Controls Division Manaaer 10 4.7.1.1 Israination Survey Section Road 10 4.7.1.2 Termination Survey Engineer. 11 1 4.7.1.3 Health Physics Encingar 11 4.7.1.4 Radwaste Engineer 12 l 4.7.1.5 Radiochemistry Encineer 12 4.7.2 Nuclear Encineerina Division ManactX 12 4.7.3 Maintenance Division Manaaer. .13 l 4.7.4 Operations Division Manaaet. 13-l 4.8 Shoreham Salvace Division (LILCO). 13 l 5.0 PROGRAM DESCRIPTION. 14 l 5.1 Termination Survey Procram Overview. 14 5.1.1 Backaround 14 5.1.2 Technical Anuroach 14 5.1.3 Procram Desien ADoroach. 15 i 5.1.3.1 Responsible Oraanisation. 15 5.1.3.2 Departmental Interface 15 i 5.1.3.3 Control of Survey Units 15 5.1.3.4 Survey of-Facility Structural Areas And Open Areas. 15 l 5.1.3.5 Survey of Plant Systems 16 [ 5.1.3.6 Use of Historical Information -16 5.1.3.7 Raltese Record 1( 5.1.3.8 Final Report 17 5.2 Procram Implementation. 17 5.2.1. Documents.. 17 e 5.2.2 Implementation Milestones. 18 5.2.2.1 Plannina-18 5.2.2.2 Devt.lopment 18 5.2.2.3 Preliminary Survey. 18 l 5.2.2.4, Final Survey 18 5.2.2.5 Final Report-. 19 + .- ~, m.... ,N-

. ~ t l' Progrec Deccriptica PDION-01 j-De:oemissicaing Tcrainntica survey REV. 1 l Page 2 of 26 [', 5.2.3 intearation with Proiact schedule 19 19 5.3 Survey Process 19 5.3.1 Summary. l 5.3.2 Erpcess Details. 19 ........ =.. -..... l 5.4 Oraanization and Staffing. 19 5.4.1-Oraanisation Chart 19 -5.4.2 Staffing 20 i 5.5 Ronduct of Operations. 20 5.5.1 Oraanisation Operations-20 1 5.5.2 Work Control 20 5.5.2.1 Encineerina Support. .-20 v 5.5.2.2 Non-LIPA Assets. 21 i-5.6 Survey Ouality Assurance. 21 5.6.1 Encommissionina OA-Procran 21 [ 5.6.2 Internal Program Measures. 22 j 5.7 Termination Survey Plan. 22 i 5.7.1 Plan Contents 22 5.7.2 Survey-Uni ^ Classificati2B 23 .... =..... 5.8 Procedures 23 5.9 -Work Instructions-. .. -...............-.24 24 l 6.0 INTERFACES 6.1 Quality Assurance 24 6.2 Decommissionina Department 24 j 6.3 Epik Control 24 25 1 6.4 Safety Proarag_. i 6.5 Fire Protection 25 6.6 Security Plan 25 I 6.7 Nuclear Encineerina 25 i i 7.0 PROGRAM EVALUATION. 25 7.1-Routine Feedback 25 b 7.2 Periodic Evaluation 25 1 8.0 ATTACEMENTS 26 l 4.1 Criteria for Release of Shoreham Nuclear-Power Station for Unrestricted Use Followina i Decommissionina. 26 l 8.2.T3.rmination Survey Process 8"===rv-26 8.3 Termination survey Process Details-26 S.4 Termination-Survey Oraanisation Chart. -26 4.5 Termination Survey Final Report Outline-. 26 1, y 1 i e i ). ~ ~ ~,. n..

Program Descriptica PDION-01 Decommissioning Torci=stica survey 7,sv. 1 Page 3 of 26 w PROGRAN DESCRIPTION 'R SHOREMAM DRCONNISSIO*,3ING TERMINATION SURVEY 1.0 9141CTIVE Termination of the U. 5. Nuclear Regulatory Commission (NRC) license for the shoreham Nuclear Power Station (SNPS) requires that radioactive materials be removed and that residual radiation and conthmination levels bg below limits identified in +,ue shoreham 2 Decommissioning Plan This will be demonstrated through a comprehensive radiation survey of the

facility, called the Termination survey.

Due to the specialised nature of termination surveys and the magnitude of the effort, a Termination survey Program has been established within the Shoreham Decommissioning Project. The principal objective of this document is to describe the Termination, survey organisation and the management control mechanisms for the Termination survey Program in accordance with therequirementsoftheLong,jslandPowerAuthority(LIPA) Nuclear Management control Manual This document also describes responsibilit 11s of shoreham Decommissioning Project organisations in support or the Termination survey Program. A program overview is provided which includes a summary of the management approach and major planning milestones. This Program Description establishes the basis for development of implementing plant and procedures.

2.0 REFERENCES

2.1 LIPA Shoreham Decommissioning Plan, NRC Docket No. 50-322, as supplemented. 2.2 LIPA Nuclear Management Control

Mahual,

" Nuclear Organization Management control Program for Program Description Development, Review and Co? trol", PDXON-01 2.3 Long Island Lighting Company (L tCO), " Program Description Site Characterisation

Program, Shoreham Nuclear Power 8tation", Rev.

1, Oct. 10, 1990 (with addenda). 2.4 LILCO "Shoreham Wuclear Power Station site Characterisation Program Pinal Report", May 1990, with -Addenda 2.5 LIPA Quality Assurance Manual

-. - ~. - -.. _ _. -. . - - ~.. - -. - - -. -. _ 1 I l* Program Deccripticn PDION-01 De ommississiig T3rm133tian SurvCy RsV. 1 Page 4 of 26 l 2.6 NRC " Manual for Conducting Radiological Surveys in support of License Termination", NUREG/CRa5849, Draft Report for Comment. 2.7 LILCO SNP5 Updated Safety Analysis Report (USAR) and Defueled Safety Analysis Report (DSAR), Docket No. 50-322, as amended. 2.8 LILCO SNPS Composite Component List (CCL). j 2.9 U. S. Atomic Energy Commission (ABC), Regulatory Guide l 1.46, " Termination of operating Licenses for Nuclear Reactors", June, 1974 1 4 3.0 DEFINITIONS 3.1 Chang.g_terisa tion survey Radiological survey j measurements, supporting calculations and evaluations pet Nrmed to establish the shoreham facility baseline radiological condition prior to decommissioning activities and to serve as a planning tool for the l decommissioning offort. The characterisation survey-activities are described in and con led by the site Characterisation Program Description 3.2 gglieria Document - The document which describes the criteria that will be used for releasing the shoreham facility for unrestricted use. It interprets the NRC guidance and outlines the technical bases for the i Shoreham Termination survey. It is an attachment to this document. 3.3 Kl.tiqry_lile - A compilation of information prepared for use in planning the termination survey of a survey unit'. It summarires the operational history, characterisation

data, operational surveys and other' information to establish the basis for the ' design of the termination survey.

3.4 ppen Area - A category of survey unit including open land areas, exterior surfaces of site buildings, paved or unpaved roadways, and equipment yards. 3.5 Doerational survey A radiologi' cal survey performed under-SNPS Health Physics procedures. All surveys not otherwise classified as termination surveys or characterisation surveys are ' classified as operational surveys. These include surveys for radiological control purposes, for decommissioning planning and information, and for confirmation that a survey unit. is ' ready for the termination survoy.- w w -,,,,-e w,,_.. n ~_n-~,,-a.- ,.,.-w,- .,,-,e ,wv. m -.,e nv .-n. ,,-,.+.-~e- ..nm,,w

4 t Program Demariptica PDION-01 ) Decossissisning TorminStien surycy REV. 1 l Page 5 of 26 l J. 3.6 Atruct.ure - A category of survey unit including all SNP5 site buildings trad their inner surfaces (generally i identified as civil structures). For purposes of the termination survey, all structures such as platforms, restraints, supports and other physical items not i identitied in the system "MF5R" drawings are considered to be structures. External surf aces of piping systems are i also treated as structures in the termination survey. t { 3.7 0 C.. 8_u r y_t y - A n independent radiation survey, usually l perforn:ed on a representative sample of a l characterisation or termination survey to verify the results. i 3.8

Ralten, critaria A

term used to identify the radiological criteria for release of the shoreham f acility for unrestricted use. These criteria, which l consist of specifisJ limits for residual contamination l and radiation levels, - are identified in the shoreham Decommissioning Plan and are described in detail in.1 of this document. 3.9 Release Record - A document which demonstrates a survey i unit is suitable for unrestricted use. It contains l evaluated survey data and supporting information to prov 4.de a concise record of.the results and basis for the i condusion that the release criteria are saticfied. A report (including 3.10 Sitg., Characterisation ReppIl addenda) which documents the surveys, calculations and l evaluations and presents the SNPS Bite Characterisation Program,*{.he results of 3.11 3urvey Desian - The process of determining - the type,

location, number and. frequency (or density) of radiological measurements to be taken within a survey unit for the termination survey.

Written direction to survey 3.12 survey Instructions personnel regarding the type and number of measurements to be taken in a survey unit. A survey instruction generally includes marked maps, written. text or both. Each survey package includes survey instructions. f ,-~-r,, y-- y ,,,,,-y---nm,..,,y -,--,,--y m, ,v,..w,, mm- - -,

Progr:0 Descriptica PDIoN-01 De:ommissiezing Torsiastica survey AsV. 1 Page 6 of 26 3.13 survey Packggg A collection of information in a standardised format for controlling and documenting field measurements taken for the termination survey. A survey package will be prepared for each survey unit. 3.14 gurygv subunit - A logical division of a survey unit, determined to be required by the survey design, to ensure radiological measurements of appropriate number - and frequency (or density) are obtained. 3.15 survey Unit A logical division of the facility structures, systems and site environs for purposes of performing and-documenting the termination survey. sue survey unit is the basic entity for management d the termination survey. A survey unit may consist of a plant system, a room, a cubicle, a portion of a large room, a major building elevation, outdoor surfaces of a building, or a paved outdoor area as appropriate. 3.16 survey Unit classification - A term used to indicate the the potential for residual radioactive contamination within a survey unit. 3.17 Israination survey Radiological measurements, evaluations and supporting activities undertaken to demonstrate that the shoreham f acility satisfies the radiological criteria to allow the NRC license to be 1 terminated and the facility and its property released for unrestricted use. 3.18 Traination survey Plan - The document which provides the tavanical direction for conduct of the termination survey. The Termination survey Plan describes the organization of the-facility into survey units; defines survey unit-classifications, and specifies--the-general survey design for a survey unit. The Termination survey Plan specifies the survey measurements to be taken and the instruments-to be used for the terairdw lon survey and demonstrates that these instruments and ses surements are capable of verifying the release criter_a._ It is subordinate to this Program Description and provides the basis for specific termination-survey procedures.- 3.19 Termination survey Recori - A report ' describing the scope, methods, and results of the termination survey. It initiates the NRC review and final inspection. of the facility prior to-termination of the f acility license. It is-also called the Final Report.:

I Program De:cription PlitoM-01 Decommissic2ing Terminatica Surv0y REV. 1 Page 7 of 26 4.0 M P_QEpIDILIT m 4.1 LIPA - SEPS RegjAeat_M m qn_ The LIPA - SNPS Resident Manager reports to the Executive Vice President, Shoreham Project. He has overall responsibility for ensuring that the shoreham decommissioning project is successfully completed in a safe manner, within budget and on schedule. He is responsible for ensuring that all licensed radioactive materials are removed and that the facility is suitable for unrestricted use. He implements LIPA senior management policies and provides overall management direction for the termination survey program. 4.2 Decommissionino Departagnt Manaaer The Decommissioning Department Manager reports to the Resident Manager and is ?n3ponsible for management and direction of Shoreham decomiaissioning activities. This includes engineering, work planning, and field implementation including coordination and direction of decommissioning contractors. He is responsible for the following matters in regard to the termination surveys

a. Reviewing survey units and survey unit classifications to id ntify areas involved in decommissioning work.

b. Reviewing the termination survey schedule to verify that surveys do not conflict with decommissioning work schedules and to minimize duplication of scaffolding and other access support. c. Informing the Termination Survey staff when decommissioning work is completed in an area, prior to demobilization of decommissioning workers.

d. Ensuring remediation is performed, such as additional component removal or housekeeping, if areas are found not to be ready for the termination survey.

e. Leaving scaffolding available for termination survey use after decommissioning activities in a work area are completed, if requested by the Termination Survey Section. Subsequent removal of this scaffolding may also be requested.

f. Providing access (opening plant system components or making cuts) and restoring systems (if applicable) where decommissioning activities were completed, as requested by operations & Maintenance (o&M) Department management.

This support will be provided on a case-by-case basis.

I !l' Progrea Descriptica resoN-01 Degoesisoitzing Torsisatica survey REV. 1 j 1 Page 8 of 26 4.3 Nuclear Quality Assurance Department Manager-- l The Nuclear Quality Assurance (NQA) Department Manager reports 4 to the Executive Vice - President, shoreham Project and is responsible to the Resident Manager for the development and i administration of the decommissioning QA program. Ne provides { QAoversightoftheTelgsgaationsurveyPrograminaccordance with the LIPA QA Manual This oversight includes review of i the Termination survey Program Description, the Termination survey 'lan, termination survey proce6ures and other documents, as well as audit and surveillance of termination j - survey activities. Termination survey measurements are l verified by independent Oc measurement of selected survey points under NQA surveillance. d 4.4-Nuclear operations sun.ggI) Departagnt Manager i The Nuclear operations support Department (NosD) Manager i reports to the Resident Manager and is responsible for managing station supert services, including plant security, fire protection an^ th M vc training and site administration i services. He pr4 ui.m ttetC %al -information such as engineering _drawin(% deow,.e 41 other reference materials l for the terminati<.3 9 weg M provides training for-l termination survey para m si. He also provides assistance in i document

control, and reference materials for use in preparatiot of terminatioa rurvey history files.

4.4.1-Euel DisDosition Division Majigggt i i The Fuel Disposition Division Manager reports to the l NosD Manager and is responsible for the

planning, scheduling and coordination of activities involved with the removal of' fuel' from the shorehm facility.

He is responsible - for the following matters regarding the j termination survey: 1 j a. Informing the Radiological controls Division l (RCD) Manager regarding plans, status and schedules l! for removal of the nuclear fuel from the spent Fuel Pool. i b. Requiring fuel shipment contractors to make reasonable efforts to limit - the. introduction of l radioactive contamination to the shoreham facility from outside sources. This includes providing the Health Physics Engineer with radiation surveys from vendors and other-information on incoming casks and -other fuel transfer equipment. 4 c. Minimising the' potential for contamination of affected areas as-a result. of fuel transfer l activities. 4 1 1 a . - - ~w n -. - - -,,,,,--n,,.an..,,,,r--- r -n,--,, e --,--a-,- ,n -en,-. < +,, -,,., ~ -. ~,. - -

Progrca Descriptica PDION-01 Decossiscissing Termination survey REV. 1 Page 9 of 26 4.5 Licensina/Resulatory.conD11&nce Department Manager The Licensing / Regulatory Compilance Department (LRCD) Manager reports to the Resident Manager and is responsible for licensing and regulatory matters (including MRC and other relevant agencies or regulatory bodies) relating to decommissioning of shoreham. Es is responsible for the following matters in regard to the termination surveys a. Ensuring that regulatory issues regarding-the termination survey are identified and that LIPA position papers and/or responses to regulatory questions are developed, reviewed and submitted to the appropriate regulatory agency in a timely manner. b. Keeping the RCD Manager. informed of 31 censing and regulatory issues and decisions which may affect the termination survey.

c. serving as liaison between LIPA and the NRC (and other governmental agencies) on all licensing and regulatory matters involving the termination survey -and the application for termination of the facility license, including scheduling of verification surveys and review of the final report in support of the project schedule.

d. Reviewing the Termination Survey Program and major implementing documents and reports to ensure that they are accurate with regard to regulatory requirements and related policy issues, e. scheduling review of designated termination survey documents by the LIPA site Review Committee (SRC). 4.6 F_inance and A4 ministration DoDartment M4ntger The Finance and Administration (F&A) Department Manager reports to the Resident Manager and is responsible for financial and administrative functions related to Shoreham decommissioning. He provides management direction for procurement of personnel and equipment, budgets and cost controls for - the termination - survey program. Ne provides procurement support services, strategic scheduling support, progress reporting and other administrative services to the program. 4.7 Operations and-Maintenance Department Manaan The Operations and. Maintenance (0&M) Department Manager reports to the Resident Manager and is responsible for operations, maintenance, radiological control and -plant engineering support for the decommissioning project. He is-

_ _ _ = Program Descriptica PDIoW-01 f J pe:ommissiesing T0rsicatica surv0y REV. 1 Page 10 of 26 responsible for general policy guidance, and management 4 oversight of the termination survey program. He is responsible for providing personnel and technical resources necessary to support the termination survey. 4.7.1 R_adioloaical Controls Divisign Manager The RCD Manager reports to the D&K Department Manager and 4 is responsible for the radiological health and safety of 3 project personnel and the public. He is responsible for radiochemistry, health physics, radwaste handling and

disposal, and for the termination survey.

He is responsible for personnel management and technical direction for the Termination Survey Program. He establishes and maintaihs budgetary controls for the program. 4 4.7 1.1 Termination surygv Section Hegjll The Termination Survey Section Head reports to the i RCD Manager and is responsible for implementation of l the Termination survey Program described in this program description. He is responsible fort a. Identification of technical and personnel resources required, and selection of personnel.

b. Supervision of termination survey personnel.

c. Keeping SNPS management informed regarding the status and results of termination survey f

activities, and problem areas that may develop. d. In conjunction with the Project controls Division of the F & A Department and the Work Planning & Scheduling Section of the O & M Department, scheduling termination survey activities to meet project milestones. e. Coordination of termination survey activities and requirements with other UNP8 organizations. f. Representing the bhoreham Termination survey in c)mmunications with outside organizations. g. Notifying SNPS management when the termination survey of a survey unit is complete and establishing controls to prevent possible recontamination or other events which would threaten the integrity of the termination survey results.

- - - -. - - _ - - _. ~ - - - - _. _., - - - - - - -.. - \\ j< Program Deccriptica PDIoN-01 Desoesississing Torminatica survey REV. 1 j Pcg3 11 of 26 4.7.1.J Itraination survey EncinggI J I The Termination survey Engineer reports to the j Termination survey section Nead and is responsible for preparation of the Termination survey Plan, i providing the necessary technical direction to the j Termination survey Program. No is responsible fort j

a. Designing and implementing the Termination survey Plan to meet established objectives and regulatory requirements.

b. Procuring and developing specialised instrumentation and equipment. I c. Providing technical direction. to i termination survey personnel. i l d. In conjunction with the - Mealth Physics i

Engineer, determine the most officient' i

schedule for survey of-individual survey i units in order to minimise the potential for resurvey or impact on decommissioning l activities. l l e. Coordination of review of survey results, preparation and approval of release records and i preparation of the Termination survey Report. I i

f. Identification of components which must be I

dissassembled (access provided) to accomplish i aurveys and initiation of the Maintenance Work Requests (MWRs) by which this work will be controlled. 4.7.1.3 Mealth Physics EngingpI The Health Physics Engineer reports to the RCD Manager and is responsible for health physics and i radiological safety for the termination survey. He is responsicle for the following regarding the termination-survey: a. Providing instrumentation, instrument [ calibration services, instrument maintenance, routine health physics supplies, counting room 4 services, and related technical services. b. Providing-perequel to supplement the termination survey wi.a f f as needed, and to perform survey measurements. l - I

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i i I f Prsgrc.s De osriptica PDION-01 l Doroemississing Terminatics survey asV. 1 l 4 2 Page 12 of 26 t c. Providing radiological information from l characterization and operatinaal surveys. Ne 1 informs the Termination survey section Naad of any changes in radiological conditions which l could affect termination surveys of any area or system and acts to minimise the potential spread of contamination throughout-the t j facility. I i

d. Performing surveys of incoming radioactive

{ transport vehic3 es or equipment and informs i the Termination survey section Mead or l pertinent results. Ne performs surveys to help ensure that no new radioactive species i are-introduced into the shoreham facility. e. Implementing necessary controls to prevent l recontamination of a survey unit-- upon l completion of the termination survey. I f. coordination of survey support and actual i survey activities to meet the projecs schedule. I i 4,7.1.4 Radwaste Encing.gr The Radwaste Engineer reports to the RCD Manager and is responsible for radioactive waste management i and disposal for the shoreham Decommissioning Project. He is responsible for plant decontamination services. He provides i decontamination support to the Health Physics i section and to the Termination survey section as requested. \\ l 4.7.1.5 Radiochemistry Engineer i 4 { The Radiochemistry Engineer reports to t h e - F.C D i l Manager and is responsible for plant chemistry and radiochemistry services. He provides i radionnalytical support for the termination survey including gamma spectroscopy,. gross beta, alpha, 1 i and other specialised radiochemistry analyses on 4 request. He assists in special studies to identify radionuclide composition and concentrations of j residual activity in various samples and materials. i 4.7.2 Nuclear Enaineerina Division Manager The Nuclear Engineering Division (NED) Manager reports to the OEM Department Manager and is-responsible for engineering services and nuclear-analysis. He provides engineering support as requir94.for station Modification ] Packages-which provide e-:es s (and restoration,. if i i ...-....,---.,,...-~.-~..-e-..-4...---,-,,,,--,,,.a.s..- -..-~---,-..-.--.,,,,1---,----m#.-,.v.,-,,~.-.,.,-.-.m.#.,-.-.,.---.. - - ~, - -.

Progrca Description PDIoM-01 Decommissis2ing Torsicatien survey REV. 1 Pag 3 13 of 26 applicable) to systems for termination survey measurements. He is also responsible fort a. Providing data and environmental sanapling l support for the termination survey from the Radiological Environmental Monitoring Program (REMP) through the LILCO Environmental Engineering Department. b. Providing data, results and interpretations relating to the radiological condition of the shoreham facility, as requested. 4.7.3 Maintenance Division Manager The Maintenance Division Manager reports to the OEM Depar6 ment Manager and is responsible for maintenance of all plant mechanical and electrical equipment, instrument and controls systems and building janitorial services. He provides scaffolding, system access, utility services, component disassembly and restoration and other services traditionally provided by - the Maintenance Division, including proplanning of Maintenance Work Requests (MWRs) for component access or diseassembly, to support the termination survey. - In most

cases, the Maintenance Division will have lead responsibility for support of the termination survey. In some cases, the Decommissioning Department may be requested to provide services such as scaffolding or component disassembly.

4.7.4 Operations Division ManaggI The Operations Division Manager reports to the OEM Department Manager and is responsible for operating the f acility in accordance with NRC license and Technical specification requirements. He provides support for the termination survey for system

lineups, tagging, maintaining isolation of nyatoms with completed termination surveys, and control of facility areas which have been surveyed.

He notifies the RCD Manager of changes in f acility configuration which could change the habitability conditions in termination survey areas or which could change radiological status of any system or area. He is responsible for daily work planning and scheduling of plant activities for the conduct and support of the termination survey. He provides input to the Termination survey section on the-operational history of systems-(used in preparation of system history files).-- 4.s ghorehan salvace Division (LILcol The shoreham salvage Division Manager reports to the shoreham site support Department Manager. He is responsible for review

l Program Descriptica PDIoN-01 l Desommissiezing Torsinctica survey aEV. 1 Page 14 of 26 }*. and concurrence with survey designs in order to assure the { followingt

a. LILco assests (salvageable components) are identified and removed from survey areas prior to conduct of the termination survey.

b. Acknowledgement that components not removed from an area prior to the termination survey may not be availeble until after license termination.

i s

c. Concurrence with the planned final disposition of a system and/or component or identification of specific j

preservation requirements to be imposed upon completion of the termination survey. j 5.0 PROGRAN DESCRIPTION j l 4.1 Termination survey Program Overview i i-5.1.1 Rs.skaround i The termination survey has been identified as a key j element in the success of the shoreham decommissioning j effort, in that timely termination of the NRC license-i depends heavily on the quality of the termination survey l and its documentation. Further, the shoreham facility represents the first 43 commissioning of a large i commercial nuclear power facility in the U. 8. Unlike j most previously decommissioned facilities, the shoreham plant structures and the majority of the piping systems will be intact upon completion of decommissioning dismantlement and decontamination (D&D) activities. This i represents a significant increase in the - degree - of l complexity and physical-scope of the survey in comparison i with previous decommissioning projects. The approach to l the termination survey described below is responsive to l these challenges. 1 5.1.2 yachnical Aporoach The technical approach to the termination survey is based i upon -the NRC ~ criteria for release of the facility for unrestricted use, as discussed in Attachment 8.1 of this program description. The methods for _ design of the i survey, instruments used,-- fielt' measurement procedures, data-collection and-- -analysis, -documentation -and-publip ), results are derived from (including draf t NUREG/CR-5849,ged interpretation' of . technical literature experience from recent nuclear facility decommissioning termination surveys,-and consultation with knowledgeable j peers. The technical approach is-described in detail in- ,,c& eor < mm..~s o,-,,~m.,w-+--~.,----a,a,m---,,,,--+m-se-e-a ~m o +----w.---m.ww----w-c, m m,-- n-e m a - -,,rm,. ,- e n, ,,-,-++vvn-e r e, wwr

1 j Progres Deact(ptica POION-01 j Decommissicaing Tsreinstion survey RzV. 1 Page 15 of 26 3 i the shoreham Termination survey PlaA ot ' :ned in section 5.7 below. .i l 5.1.3 Program Desian Annroach 5.1.3.1 Responsible Oruanisati.qm i l The Termination survey

section, within the Radiological Controls Division, is responsible for development and implementation of the to:mination i

survey. It will be managed and supported by a i qualified staff. The Nealth Physics section wil'i support the Termination survey section by providing technicians,

supplies, administrative

support, i

j designated technical support and other services. ( f.1.3.2 Departmental Inter. face i. r' Appropriate methods shall be established for i communication between the Termination survey I section and other decommissioning project groups (i.e. the Decommissioning Department, the operations section and the Maintenance section of l the O&M Department) for scheduling termination 1 i surveys.. Mechanisms shall be established for j turnover of facility areas for termination surveys. l 5.1.3.3 control of survey Units i controls aball be established for isolation of survey units scheduled for termination survey to minimize the possibility of recontamination. Furthermore, appropriate controls will bs maintained on all survey units for which the L termination survey has been completed. i j 5.1.3.4 survey of Facility structures anad open Ar.gan l l The termination survey of facility structures and j open areas will be organised by dividing them into discrete entities for management of the survey. l Plant structures, systems and outdoor areas will be divided into survey. units and subunits. The i description and identification of areas for this. j purpose are based primarily upon plant ' general arrangement dyagings similar to those contained in the SNPs UsAR Each survey unit or subunit will i be classified based on the potential for residual radioactive contamination within the arsa-it represents. \\;- =

I' Progrco Description PDIoN-01 i Decommicsicsing Tormination Surycy s V. 1 1 Page 16 of 26 l 5.1.3.5 survey of Plant M ggg i { Plant systems will be surveyed and evaluated as discrete entities. Identification of systems will i follow the system inder of the Records Management File Code List. Identification of system contents and boundaries will be based on iMFSR" series drawings. Identification of individss3 will be in accordance with the SNPs CCL *gosponents i 2 Piping l i sections will be identified by reference to 9MFSK" j series drawings, installation isometric drawings i and stone & Webster Engineering Corporation (SWEC) line numbers as appropriate. Each system will be i identified as a survey unit for termination survey purposes. Each system survey unit may be divided i into survey subunits. such subunits will include a portion of the system and may contain a - single i component, a group of components or a section of the system group. Portions of a system contained within a system subunit ishall be determined to have a equal potential for residual radioactive contamination. Each survey unit or subunit-will be classified based on the potential for _ residual l radioactive contamination in that portion of the j system. { 5.1.3.6 p_tp of Histgrical Information i Determination that a survey unit satisfies the criteria for unrestricted release shall be based upon an evaluation of its history as well as upon Termination survey measurements. Maximum use shall be made of historical-information. Historical information includes operating history and other i relevant operational data, SNPs Characterisation Program

data, operational-and environmental radiation surveys and rJata reports.

such information will be used for initial survey unit classification. The degree of. reliance given to i historical data considered for use as final survey data (see also, 5.2.2.4 Einal survev), depends on the conditions and changes occurring in .the interval prior to the time of the survey and on the ability to document the data integrity in a manner 4 i consistent with termination survey data. 1 4 5.1.3.7 Release Record Demonstration that the shoreham facility satisfies the criteria -for unrestricted use shall be i documented _ for each survey unit. A document, i called - the Release Record, will be prepared for-this purpose. - The release record, prepared in a-

Program Deccription PDIoN 01 Decommissicaing Torsinstica survcy RsV. 1 Page 17 of 26 standard

format, contains survey

data, survey statistice, a

written evaluation and a determination that the release criteria are satisfied. Gufficient survey measurement data will be included in each release record as necessary to support the determination. In order to keep release records to a manageable size, supporting information such as the survey unit nistory file and field survey data may not be physically

included, but will be referenced and properly archived.

survey units of similar composition, history and classification may be combined into a single release record to ease replication of administrative details. The release record will not be " closed out" and given final approval until all identified remedial actions are satisfactorily completed. Release records will be prepared by the Termination survey section. Each release record will be required to undergo independent technical review by an individual who has had no direct responsibility for design of the survey or evaluation of the data for the survey unit for which the release record is prepared. Each release record will be reviewed by the NQA Department. LIPA management approval of each release record shall be documented through the site. Review Committhe (SRC). 5.1.3.8 Final Report A final report will be prepared for submittal to the NRC. The

report, an outline of which is provided in Attachment s.5, will demonstrate that the facility is suitable for unrestricted use. The final report will-- cgaply with section 4.e of Regulatory Guide-1.86 and g low the form and content of draft NUREG/CR-5849 It will contain the results of the individual release records which may be attachments to the final report or the information contained within the release records may be reformatted and summarised.

5.2 FI_9_qtan Imolementation 5.2.1 Documents The implementing documents for the termination survey consist of the - Termination-Survey Plan, Termination Survey Procedures, and Health Physics Procedures (and work instructions). The final result-and conclusions of the termination survey will be-reported in the Termination Survey Final Report. Other documents and records which will re produced as part of the termination

Program Deceriptica PDION-01 Decossississing Tcrainatics Survey REV. 1 Page 18 of 26 survey include survey Unit Mistory Files, survey Unit survey Packages (including survey instructions), and survey -Unit Release Records. Documents and records produced in support of the termination survey include survey instrument calibration records, survey instrument control check records, computer sof tware - verification reports, f acility background radiation measurements, and personnel training and qualification records. 5.2.2 Implementation Milestones Program implementation can be viewed in terms of five major phases or milestonest

planning, development, Preliminary Survey, Final Survey and Final Report.

5.2.2.1 Plannina_ The major planning phase milestones for program development are preparation and approval of the Termination survey Plan and preparation of the list of survey units. 5.2.2.2 Development Development activities include

staffing, preparation of survey procedures and instructions, and procurement, development and testing of equipment.

Background

radiation studies and development of data management software and procedures will also occur during the development phase. Preparation of Survey Unit History Files will be initiated in the development phase. 5.2.2.3 Preliminary Survey The Preliminary survey represents the transition from the development phase to the Final Survey Phase. The Preliminary survey includes field testing of equipment and procedu".1 through appropriate mockups and dry runs. D*. oc11ected during the Preliminary survey _ phase wk. be used to aid in the overall final survey design and in the design of surveys of individual survey units. Termination survey quality control procedures will also be finalised in the Preliminary Survey phase. Preliminary surveys will not be conducted on all survey units. Rather, representative survey units will be selected. 5.2.2.4 Final Survey Final Survey measurements will begin when all applicable prerequisites are met. These include use

(-.-....-.-. - ~ -.. I i Program Pescriptics PDION-01 Desoesissioning Terminctica survey a:V. 1 1 j Page 19 of 26 i'. of approved procedures (including QC procedures), j work instructions and qualified technicians and acceptance of the area or system for Final Survey, j Final Survey measurements and certain Preliminary i survey activities may be performed concurrently throughout the facility in order to support the overall Decommissioning Froject schedule. However, 1 no measurements will be classified as Final Survey measurements unless applicable prerequisites are i met. 5.2.2.5 Final Report i The Final Report phase includes completion of survey data evaluation, closure of survey data ] packages, preparation, verification and approval of i release records and compilation of the Final. Report. Compilation of the Final Report will begin i during the Final survey phase. l 1 5.2.3 Intearation with Proiect Schedule 1 l Termination survey activities are included in the master project schedule including Preliminary survey activities i and the Final survey of each survey unit. Surveys will be scheduled to avoid conflict with decommissioning work j and fuel dispositifn activities. j j 5.3 survey-Process l i 5.3.1 Summary l l A summary level-schematic of the termination survey j process is shown in Attachment 8.2. The process is j designeG to allow Final surveys to be conducted on j selected survey units in parallel with decommist.ioning l work elsewhere in the facility. The schematic shows the I logic for accomplishing this. i 5.3.2 Process Details A detailed view of the survey process is provided in 4 Attachment a.3. The schematic shows the principal j activities, documents, and records produced. i l 5.4 Oraanisation and Staffing ) 5.4.1.QIganisation chart i A ~ schematic of the termination survey organisation is shown in Attachment s.4. This shows. the. principal l _ positions and reporting relationships in the termination i p survey organisation. The organisation chart shows the l

i PDICM-01 I Program De:criptica De:ommissicaing Torcisatics Surycy REV. 1 Page 20 of 26 3 l'- positions dedicated to the termination survey. The j survey is managed by the Termination survey section Mead who reports to the RCD Manager. l

5. 4.2 finfling I

As shown in Attachment s.4, the Termination survey section consists of a full time staf f of specialists. 3 This staff will be styplemented, during field measurement 1 activities, by personnel from the Nealth Physics section. ? The survey measurements will be performed by qualified NP technicians. During the active measurement phases _of the termination survey, several Lead Technicians will be assigned to the termination survey. They will supervise l the Health Physics technicians assigned to work on the termination survey. Technician staffing levels will be i adjusted as necessary to support the project schedule. 5.5 Conduct of operations i 5.5.1 Qtgenization operations-Conduct of termination survey organisation and personnel management will-be identified in applicable station management policis, and procedures. Conduct of operations will be in accordance with applicable station policies and procedures. i l 5.5.2 jfork_ Control Termination survey work will be conducted in accordance with applicable static? work control procedures. survey measurement, sample colicotion and instrument calibration will be controlled -by Nealth Physics procedures, by i l Radiological Environmental Monitoring Program (REMP) procedures and by Termination survey procedures. The station Maintenance Work Request (MWR) procedure will be used to request, document and control termination suvoy support work in the facility. The NWR records shall serve as the primary method to document the final configuration of plant systems. To the maximum extent I practicable, curvey unit structural surfaces, system components, and outside area sampling excavations (if performed) should remain open and accessible until completion of the NRC confirmation survey has been completed. 5.5.2.1 Engineerina Sgyport Planning and conduct of the termination survey on systems will -include consideration for the final t system configuration requirements to support the i facility. The extent to which a system (or a

-.. _ ~. - -. _. - _ -. - - - - _... _ -. _. - - -... l_ Program Descriptica PozoN-01 i Defoesississisg Toreinstica Surycy asy. 1 Page 21 of 26 I'. component) must be restored shall be determined l during survey design. The need for future access to 4 the system or a single component shall be determined in order that the impact on termination survey data i 2 validity can be assessed. Additionally, the survey design for a particular system survey unit may require access to a point which is not achievabl9 by i disassembly of mechanical joints. For systems which j will not be returned to a - functional condition, engineering details will be provided for the j necessary system disassembly. This may be accomplished through use of " generic" disassembly i details. For systems required to remain functional, i or where prerervation requires full component or l system integrity, additional engineering details j will be provided to restore the system or component to the required condition. If actual configuration changes are made to piping systems or equipment (other. than restoring access

flanges, covers, 4

joints, etc. to a " mechanic tight" condition),.the changes shall be documented on an Engineering change l Report (ECR). 1 5.5.2.2 Non-LIPA Asset.3 Numerous components of the shoreham facility remain-the pWoperty of the Long Island Lighting company 4 (LILCO). The termination survey will be conducted i in such as manner as to preserve the value of such material to - the maximum extent practical. The shoreham salvage Division will review survey designs l to determine the impact on salvageable equipment. MWRs for the disassembly of salvageable components will also be reviewed. This review will ensure the final configuration of a system or component is fully agreed upon prior to the termination survey of a

system, area, or_ component.

This provides assurance that termination survey results will not be impacted by the necessity for subsequent component removals. 5.6 survev_cuality Assurance i l 5.6.1 Decommissigning OA Proatan The termination survey is-subjec Q o-the provisions of i ^, Quality assurance the:LIPA Quality Assurance-Manual is provided-through oversight of the-NQA Department.- Termination survey QA oversight will consist of review of-i program documents, program readiness assessments, (as discussed in section 7 2 below), and ongoing surveillance of program activities. Independent verification of final phase survey results will be-performed under-NQA l [ i

Program Descriptics PDIoH-01 Decomalscic itg T0rmiactics Surycy REV. 1 Page 22 of 26 Department surveillance and review of the release records.

5. 6. 2 1RL91Dal Procram Mealgrap__

Quality assurance is also provided through quality control elements built into termination survey program design and procedures. Termination survey ;)C procedures and methods w be ba. sed on the principles outlined in NUREG/CR-5849}1,1 and the LIPA Quality Assutance Manual. Termination survey program design includes provisions to ensure a high level of confidence that the facility will satisfy the release criteria. These includes a fully documented program, thorough review of area and system histories, survey measurement intensity adjusted according to likelihood of residual contamination, preliminary survey of selected areas to verify the effectiveness of survey methods, close supervision and control of measurement processes, training for personnel involved in survey measuredents, documentation of measurements and associated parameters, timely review of measurement results to identify anomalous results, and prompt attention to resoluV 'n of problems and discrepancies. 5.7 Tgnnination Survey Plan 5.7.1 Plan Contents The Termination Survey Plan provides technical guidance for conduct of the termination survey. It consists of an expansion and upda section 4.0 of the LIPA Decommissioning Plan {eg ofThe Termination Survey Plan is controlled as a program document in ageprdance with the LIPA Nuclear Management control Manual It covers the following topics: Facility Background Information Site Information including Site Description and condition at Time of the Final Survey survey overview including objectives, contaminants, organization and Responsibilities,

Training, Laboratory Services, General Survey Plan, Tentative Schedule and Final Report Survey Plan including Instrumentation, Area Classification, Reference Grids, Surface Scans, Surface Activity Measurements, Exposure Rate Mossurements, soil / sediment

Sampling, special he N$urement s, Background Level Daten inations and Sample Analysis

) i' Program Descriptica PDION-01 ] Deconsiosioning rorsination survey REY. 1 Page 23 of 26 Data Interpretation Final Report 5.7.2 survey Unit classification The survey unit classification process is a major tool for p?euning Atd management of the termination survey. 3 The di 'sion of the facility _into survey units and the classiitcation of those surywy units will be controlled j by station procedure. This allows for thorough review and apptJval while providing for limited revisions to the ) Termination survey Plan. The purpose of -this classification ,s to show the breakdown of site structures, systems and areas into the principal survey l units used to manage survey measurement and data collection efforts. Each survey unit is then classified i according to the - potential for residual radioactive j contamination. This classification guides the level of j measurement intensity applied in the survey design. Additionally, the survey design may further divide a i survey unit into survey subunits with the appropriate classification given to each survey subunit. The 3 j classification for a survey-subunit may indicate a lesser j potential for residual contamination than the survey unit for which it is part, but in no case will a survey i subunit be classified with a higher potential for j residual contamination. The survey Unit classifiaation j Description contains a listing of each survey unit which identifies its classification. It also includes a series l of general arrangement (plan view)-drawings by principal j elevation of the major buildings. The drawings will show the individual survey units and their classification. The i survey Unit Classification Description is the principal tool for communication of termination survey plans and l interfacing with other decommissioning organisations to i l schedule survey activities. i 5.8 Procedures Many functions of the termination surve) will be conducted j under sNPs Health Physics, Radiochemistry and Radiological l_ Environmental Monitoring-Progre's procedures. These include operation and calibration of surywy instruments. In addition, j several - processes unique to the Termination survey section have-been identified and will be controlled by-procedures, i Termination survey procedures will be:prepared in accordance with. approved procedures for preparathon,' issuance, control L and revision of Health Physics procedures. Topics which will be addressed-in termination survey procedures include (but are not limited to): l..

Progr3 Descriptics P2 ION-01 De:ommissic312g T rsicatics Wurvey REY. 1 Page 24 of 26 conduct of survey operations History files Release records survey measurement quality control survey Unit turnover for Termination survey Isolation & control of Termination survey survey Units survey data receipt and management Document control and management survey Unit classification Backgrcund determination and documentation 5.9 Work Instructiong Work instructions are used to describe and control processes which require some degree of standardisation but less control than processes controlled by procedures. Work instructions 313 n91 used in cases where data integrity is affected. Examples are tasks performed by a limited number of personnel, tasks which may change fairly frequently or which may be performed for a limited period, and tasks for which only general guidance is required. Work instructions are not used to introduce new tasks or to expand work beyond the scope of existing procedures. Work instructions for termination survey will be prepared, issued, and controlled in accordance with the approved procedure for Health Physics work instructions. 6.0 INTERTACES Principal programs and procedures that interface with the termination survey are identified below. 6.1 Quality Assurance LIPA Quality Assurance Manual LIPA Quality Assurance Procedures 6.2 Decommissionino Denartment PDXDD-01 Decommissioning Program Description 6.3 Work control SP 12X010.02 Station Modification Activities SP 12X011.01 Station Equipment Clearance Requests

= Program Descriptics PDION-01 De:ommissicni%g 70rmi20 tics survey REV. 1 Page 25 of 26 SP 12X012.01 Radiation Work Permits SP 12X013.01 Maintenance Work Requests l 6.4 giftty ProgLaA, shoreham Site 8?fety Manual 6.5 Fire Protection i PDXNE-11 Fire Protection Program F1X500.01 Organization and Administration of Fire 4 Protection Program SP 12X500.01 Fire Protection Program Description 6.6 figprity Plan 6.7 Nuclear Encineerinq Radiological Environmental Monitoring Program (REMP) PDXNE-01 Intria Management Control Program for Station Modifications NEX01-03 Preparation, Revision & Approval of E&DCRs & ECRs 7.0 PROGRAM EVALUATI.9E 7.1 Boutine Feedback The RCD Manager is responsible for maintaining this program description. He may delegate this responsibility to the Termination Survey Section Head. Persons having suggestions or comments on this program should present them to the RCD Manager or his designee. At the annual review, or sooner if required, the RCD Manager shall resolve problems that have i arisen during the period, and ensure that this program is revised as necessary. 7.2 P_griodic Evaluation Periodic evaluations will be performed on the basis of major project milestones or other changes which could impact the l program. The first comprehensive review of the program is l planned prior to initiation of final survey phase measurements. This will be performed by the LIPA Nuclear Quality Assurance Department with the assistance of outside technical experts who are experienced in decommissioning surveys. i i

Program De criptien PDION-01 Decommississing Termiettica survoy Azy. 1 Page 26 of 26 8.0 &7.TAQEMEJCER l 8.1 Criteria for Release of shorehan Wuple.gr Power station igr Unrestricted Use Following Dec.9331311oning l 8.2 Termination sury3v Process 8"===ry__ 8.3 Igraination Survey Process Details 8.4 Termination Survey Oraanisation Chart 8.5 Igraination Survey Final Report Outling_ I. 6 j i d i i t 1 ( 1 4 r v -w .,w -y-,, -y,,, ,, - - ~

LON3 ISLAND PO';ER AUTHORITY Criteria for Release of Sha n ham Nuclear Power StatiQD for Unrestricted Upe Followino Decomnipsioning_ 1.0 Hymmary This document addresses crateria for termination of the U. 8. Nuclear Regulate;y Commission license for Shoreham Nuclear Power Station. A major condition for termination of the license is demonstration that the facility and the site are suitable for unrestricted une. Principal criteria for release gf the facility g are identified in the Shoreham Decommissioning Plan These are: Limits for residual agr, face contamination levels contained in Regulatory Guide 1.86 and A limit for gamma radiation exposure rate established by the NRC staf f s 5 mic R/hr above background measured at one meter from the surface Guidance for application of these criteria to nuclear power reactor facilities is not clearly spelled out in appreved regulatory documents. Criteria have not been established for volume concentration limits on residual activity in building materials, equipment and soils. Due to f actors which vary, such as the mix of radionuclides involved, radiation background and site conditions, interpretation of the criteria may vary when applied to different sites. This document provides interpretation of the criteria for application to the Shoreham Facility. The following implementation principles are adopted to ensure that the criteria are satisfied and the demonstration is properly documented: 1.1 The applicable Regulatory Guide 1.86 surface contamination limits and the 5 microR per hour (above background) criterion are used as acceptance criteria for decommissioning remediation activities. These limits are used as maximum acceptable levels. Reasonable efforts i will be made to eliminate residual contamination, i.e. to reduce levels well below these limits. 1 This document applies to structures and equipment remaining fixeG in place at the facility. All items to be removed from the facility which are potentially contaminated will be surveyed using Shoreham Nuclear Power Station Procedures. All items found to be contaminated will be packaged and shipped as radioactive materials for proper disposition (disporal or re-use under an appropriate radioactive materials license). PDX0M-01 Rev. 1.1 (Page 1 of 7) l l 1

i 1 l J 1.2 satisfsatz.on of the facility relv se criteria will be I demonstrated by a comprehensive rad' ; Lion survey program. l'- This program, called the Termis 4.an survey Program includes preliminary and final n my phases. The l Termination survey Progrks is jassa ,.a section 4.0 of the LIPA Decommissioning Plan l 1.3. All areas subject to the facility

license, and j

particularly those involved in or impacted by decommissioning activities are subject to thorough confirmation surveys prior to acceptance for termination j survey. Areas not meeting the release criteria must be remediated and reconfirmed prior to acceptance for the l Termination survey. I 1.4 Determination that each defined survey area satisfies the release criteria is based on an evaluation of all i relevant inf ormation, including operation 41 history, site i characterisation' data, decommissioning records and l confirmatory and termination survey measurements. This information will be compiled into a standardised format i called the release record. The release record will be { 4 j _ prepared by the Termination survey section. l 1.5 The final determination by the Long Island Power i t Authority (LIPA) that an area satisfies the release l criteria will be made based upon an indspendent review of. i the release record. This review will be performed by designated individuals within the LIPA Organisation who l are independent from the Termination survey section. \\ l 1.6 Quality control (Qc) measures will.be applied to the Termination survey Program to ensure the integrity of the data and the accuracy of survey results. . survey l procedures will incorporate quality control provisions. External QA oversight will be provided by the snoreham l Nuclear Quality Assurance Department. i l 2.0 Discussion L i 2.1 Reaulatory Guide 1.86 surface _ Contamination Limits 2 Table 1 of Regulatory Guide 1.86 identifies acceptable contamination levels which must be satisfied.for facilities to be released-for unrestricted use. Table 1 limits are establinhed for -four radionuclide -- groups classified on the basis of potential biological risk. These limits are specified as levolg above background. j The shoreham Characterisation study determined that -radionuclides in plant structures and systems (in-situ i activation and surface contamination) are-confined _ to i PDION-01 Rev. 1.1 (Page 2 of 7) V -,-.----%----,e ee.-. -wmm-- .w<-w.ns,--e,r. .-,.wwu,, .,,.,c-.n,y. ,ee -ww., ,.,,.,-r-%. ,,,,wc-e.y-,, -y., myw %%ww, M.~ u n re u-- , y -r irm.rvy-ve-

i ~ l i j beta-gapa emitters. Thus, the following Table 1 limits j apply: l. a. Maximum fixed plus removable; 15,000 disintegrations per minute (dpapper 100 cm#, (within an area no greater than 100 cm ). j a i b.,Ryerage fimod plus. removable; 5000 dpa per 400 cm, (averaged over an area no greater than one m ). I I I

c. Removable; 1000 dpa per 100cm.

{ = l Areas where contaminatior, by alpha-emitters is a l potential as a result of removal of the nuclear fual from the facility shall be demonstrated to be released at l limits levels for gross { alpha. punerically equal to the above Burface contamination at Shoreham is comprised of mostly co-60 and Fe-55.. The remainder, which together contribute about five per cent of the total activity, is l comprised primarily of Ni-63 and Mn-54. In radiatica l surveys to evaluate surface beta-gamma levels, co-60 ) contributes about 99 per cent to the detector response, l with the remainder due largely to Mn-54. Fe-55 and Ni-63 are not detectable with typical survey instruments. In j determining facility surface contamination levels at shoreham for evaluation against Regulatory Guide 1.86 l Table 1.11mits, the activity due to Fe-55 and Ni-63 is l not included. 1 I i l l Regulatory Guide 1.86 defines beta-gamma emitters as l "nuclides with decay z; odes other than alpha emission or spontaneous fission." certain other beta-gamma emitters are specifically excluded from this category in the

Table, e.g.,

Br-90 and-Iodines. These are listed in a more restrictive category which includes isotopes of Th, U, and Ra. I i -.3 F The Shorehan spent Fuel-Pool has not been characterised due to the presence of'the spent fuel. When the pool:is j

emptied, a

radiological characterisation will. be performed and the appropriate limits. f rom Regulatory - Guide.1.86 Table 1 will be applied based upon the radionuclides found to be present. PDIOM-01 Rev. 1 astachment 8.1 (Page 3.of 7) l l --.a..

2.2 Gamma Exposure Rate Criterion The 5 microR/hr (above background) at one meter exposure rate criterion applies to radiation fields-produced by residual gamma emitters. While there is no formal definition of this criterion, it is usuaQy stated in Roentgens, the unit of radiation exposure Exposure rate (in Roentgens)

1. s not readily measurable with portable field instrumentation, however.

A commonly accepted practice in facility termination surveys is to use sensitive rate meters (usually scintillation detectors) calibrated to measure absorbed dose rate (rad units). At shoreham, an appropriately calibrated pressurised ion chamber (PIC) will be used as the reference instrument for measuring gamma exposure-rates. For_ convenience, other instruments such as scintilhtion rate meters will-be used for the majority of measucements. Correlations will be established between scintillation detectors and the PIC for determining compliance with 4Ae 5 microR (above background) criterion. Since gamma radiation fields from contamination and neutron activated materials at shoreham are dominated by co-60,; instruments will be calibrated with co-60 or sources with comparable gamma energies. 2.3 Demonstration that Doses:from Residual Activity are ALARA The numerical limits on surface contamination and gamma exposure rate described above are chosen so that the radiation risk to individuals is negligible regardless of conditions of use or occupancy of the facility. At present no regulatory consensus has been reached for determining acceptable radiation doses from residual activity from decommissioned facilities. The U. s. Nuclear Regulatory Commission (NRC) staff has stated that 4 the 100 milliren (trtal ef fective dose equivalent) per year limit for sempers of ge public in the recently issued 10CFR20 regulatiogs will be applicable to facilities 3'# This is clearly a decon.missioned regulatory maximum limit and does not constitute an ALARA level. The NRC staf f has proposed that 10 millires to an individual, (the so ot.'. led maximum exposed individual) be used P. s an ALARA benchmark for evaluation of decommissioned licensed facilities. However, this matter is still under review and is the subject of a proceeding to develop an interagency consensus between the NRC the m g.ipental Protection Agency and the Department of ~ enegy Radiation doses have been calculated for post-decommissioning facility occupancy and use scenarios at shoreham. These have been calculated using methods under PDIOM-01 Rev. 1.1 (Page 4 of 7)

development by this U. G. Nuclear Regulatory Commission for purposo of evaluating facilities containina low levels of radioactive mag rial in buildings an( soil following decommissioning Doses were calculated which result from total surface contaminat4on levels (fixed plus removsble) equal to 5000 dpm/100 cm (from the Regub.cory Guide 1.86 Table-1 g limits identifie6 in section 2.1 above). .They were calculated for a mixture of radionuclides g entified in the Shoreham site chareoterisation study In this pathway analysis, the isotopio compcsition of facility residual contamination was inferred from neutr7n activation analysir results, from smear sample analysis and from environatatal sample results. For this base case, the contributions of Co-60 and Fe-55 are assumed to be present in roughly equal proportions, comprising about 90 per cent of the total activity. The resultant deses are about 3 millirem per year to the maximum exposed individual from all pathways. It is noted that Fe-55 contributes less than one per cent of the calculated dose (total effective dose equivalent). The dose pathway study cited above # also evaluated doses 3 q using the assumption that Fe-55 was not present in residual facility contamination. This case approximates the situation where essentially all the activity-is due to co-60 as is implied in the methods used to measure surface contamination in the Termination Survey - at Shoreham. As expected, the resulting calculated doses are approximately twice the base case results, yielding aboitt 6 millirem per year to the maximum exposed individual. The result VWarised above represent consor.W.ive upper s limits for a v 3 expected from unrestrict M ise of the Shoreham facility following decommissioning. The exposure scenarios use conservative-generic assumptions and pathway models. The source terms are based on the -assumption that residual contamination is at Regulatory miide Table 1 limit values throughout the facility. It is expected that actual residual activity levels will be much less than this. 1 2.4 Residual Radioictivity Concentrations in Building Materials and Boil Release limits have not been established for residual radioactivity concentrations in building materials go soll for decomr.issionec nuclear reactor facilities . Acceptability of ' building materials (e.. g., neutron-activated concrete), -and soil containing residual

adioactivity at Shoreham will be determined primarily by uatisfaction of-the 5

microR/hr above _ background l c?iterion. That is,-the gamma exposure rate measured at PDIOM-01 Rev. 1.1 (Page 5 of 7) l o

i 5-l*lh ono estor fran the curfcos of 00110 or building catoriolo

~

shall be less than 5 microR/hr above the background j'. radiation exposure rate. l 2.5 Residual Radioactivity in Syst. gag and Equipment j surface contamination on plant systems and equipment lef t in place.in the facility will be evaluated against the i Regulatory Guide 1.86 Table 1 limits identified in Section 2.1 above. Gamma radiation-fields from surface j contamination and neutron induced gamma - emitters in i equipment must also satisfy the 5 microR/hr (above background) criterion. The gamma f M J's will be evaluated in locations (at onG seter from m).'eces) that i are considered to be readily occupiablo Accessible i equipment and components will be, removed it v atamination levels cannot be reduced below 5000 dpa per 100 ca' fixed j plus removap)le activity (averaged over an arop no larger than one m and below 1000 dpa per 100 cm removable l activity. Contamination levels of up to 15,000 dpa fixed plus removable wi41 be acceptable in localised areas (less than 100 cm ) that are not readily accessible, j e.g., within piping buried in concrete or localised areas in large fixed components such as heat exchangers or tanks. 2.6 Determination of backaround Radiation Levels 3 l The criteria for release of the facility for unrestricted t-use are all specified as levels above background. Background count rate or dose rate levels (as the case l may be) for the instruments used in the Termination Survey are comparable to the expected residual activity levels in the facility. The random nature of radioactive decay processes, errors and-uncertainties in instrument-responses, and errors inherent in measurement processes combine to produce uncertainties in. measurements of background and in measurements of residual activity. The magnitude of the uncertainty associated.with these i measurements is in some cases comparable to the average j values of a series of measurements. Thus it becomes essential to identify and properly account for the background (and its variation) for each type of 3 measurement, i Backgrounds for each of the. types of measurements and instruments used in the Termination Survey will be determined. Measurements will be made of background in-a manner that eliminates possible contributions from Shoreham facility residual activity. The contribution of building materials of construction' will-be evaluated. Sufficient measurements will be taken to obtain valid {. statistical characterizations of background. I PDIOM-01 Rev. 1.1 (Page 6 of 7) i

i j

3. 0_ _ References

}, l 3.1 Long Island Power Authority, " Decommissioning Plan-for i Shoreham Nuclear Power Station",

December, 1990, as j

amended. 3.2 U. 8. Atomic Energy Commission, Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors", June 1974. l 3.3 U. 8. Nuclear Regulatory -' Commission, " Final Generic j Environmental Impact 8tatement _. on Decommissioning of-Nuclear Facilities", NUREG-0586,~ August, 1988. 4 l 3.4 Long Island Lighting Company, "Shorehen Nuclear Power { 8tation site characterisation Program Final Report" May, 1990,-(with addenda; June, 1990, October, 1990). 3.5 U. 8. Nucas r - Regulatory Commission,. ' 10CFR Part 20, j " Standards for Protection Against Radiation; Firal Rule", i Federal Register, May, 21,1991. 3.6 J. C.

Malaro, D.

S.. Nuclear Regulatory Commission, " Residual Contamination Criteria for Decontamination.of Nuclear Facilities", presented - to tho ' Healt% -Physics i Society Thirty sixth Ar.nual Meeting, Washingtoh. % C., I July 1991. 3.7 R. A. Meck, U. 8. Nuclear Regulatory Commission, " Status .= Report on Establishing Decommissioning Criteria", { presented to~ the Health Physics society Thirty Sixth l Annual Meeting,. Washington, D. C., July 1991. l 3.8 W. E. Kennedy and R. A.- Peloquin, " Residual Radioactive 3 Contamination from Decommissioning," Prepared for the U. i [ S. Nuclear Reglilatory Commission, NUREG/CR-5512, Draft R January, 1990. t } 3.9 -M. Beer-- et. al., "Shoreham Nuclear Power station Post- ~ _ Decommissioning Dose Pathway Analysis. Report", Long. i _ Island Lighting company report to Long Island Power j Authority, Draft, August _1991. I l PDION-01 Rev. 1.1-(Page 7 of 7) -.-.. - 1

Termination Survey Process Summary Division of facil(Ly into 3urver Units 1 4 g. 1 ( / / y Dec mde. [N No fec d Ve: b tir4%les U ? Decmeal s s i onIng Actieiilis Compteted b_ 4....... ) i Operational e Remediation (Confirmat im ) (Removal und/or P.adi at i on i Decontamination) survey h -d Area No niee t s j Acceptance 4 a Criterie o; - l Release Survey Unit for survey I. \\ v l l Dotate Area / I t Control Access l I Q i T T erml ea t i ori 3urvey Revien Surver Data-I. rea ho meets release Crliefle 1 f / Yes If 6 isolate Area / IControlAccess 10/13/V2 Notest T a rasW2 1 Process described for indlH dual survey unit.

2. Operational (confirmation) surveys per formed on selected areas.

l l PDIOM-01 Rev. 1.2 (Page.1 of-1) l l l i b e

Termination Survey Process Details ^ Survey Unit / Subunit Initlel Plant Classified 4 4-- Character-.. Classification- -laation x y Detailed vh._ Evaluation Operational J History &, Radiological IP Surveys History Prepare 4 File History File Decommissioning Activities Completed Y Place . on Survey Schedule Y Operatlonal (Confirmation) Remediatlon Updated' 4--- History Survey File U y Unit Turnover -or termination. l turvey U

lsolate, Control Access y

Freliminary 'S Survey Dsta Processing' Perform Data Peport 4 and Analysis 4 Preilm Survey t o* Wor.a t ) (optlonal) %_r 4 L_ Final Survey-tinal Design Surver Instr uctions Final U Survey-Data Resoct Det.a Processing Perform 4 and Analysis 4-final /*% Survoy O i, u-U Prepare Isolate. Aalease Record- .Vertfy U-1 INiependent ' (1914414 Review and ( Record - d Approval of Releste Record 10/13/92 1erm#3 '\\,. 'PDIOM Rev..'1

Attachment:

8.3 (Page 1 of 1) .s. .~m- ---_______a----______._-_.._

i a Termination Survey Organization Chart 1 Wanager Radiological Controts Div. J l i 1 l-1 Termination HP Engineer Survey i SectionHead l i l i I l l Termination j l Survey l l Engineer i l i i i l t i l l l 1 l Rad. Engineer Rad Engineer Rad Engineer RadEngineer l CAD, Graphics Data, Instr d n Systems Documentation 1 l I l ]- t 1 l I Survey RadEngineer(s) Database Data Supervisor (s) Survey Programmer Clerk i 2 i i Survey Technicians h 9/21/92 Term #4 a PDIOM-01 Rev. 1.4 (Page 1 of 1) e

4 Termination Survey Final Report Outline Shoreham Nuclear Power Station Decommissionina Termination Survey Final ReDort 1.0 Background Information 2.0 Site Information 2.1 Site Description 4 2.2 Site Conditions at Time of Final Survey 2.3 Identity of Potential Contaminants and Release Guidelines 3.0 Final Status Survey Overview l 3.1 Survey Objectives 3.2 Organization and Responsibilities 3.3 Instrumentation 3.4 Burvey Procedures 3.4.1 Area Classification l l 3.4.2 Reference Grids l 3.4.3 Surface Scans 3.4.4 Surface Activity Measurements 3.4.5 Exposure Rate Measurements I 3.4.6 Boil / Sediment sampling l i 3.4.7 Special Measurements and Samples 3.5 Background Level Determinations ( 3.6 Sample Analysis l l 3.7 Data Interpretation-3.8 Records 4.0 Survey Findings and Results 4.1 Background Levels PDIOM-01 REV. 1.5 (page 1 of 2)

k i -e Termination Survey Final Report Outline 4.2 Building Surveys 4.3 Grounds surveys 4.4 system Surveys 4.5 Data Evaluation i 4.6 R6midual Activity Inventory 5.0 Summary j 6.0 hpoendices The final report will contain appendices of supporting data and information which include the following: 6.1 Tabulated Results for Individual Survey Units 6.2 Survey Map Index 6.3 Survey Procedures 6.4 Data Processing I 6.5 Statistical Methods 7.0 Attachments The Release Record for sach Survey Unit or a summary of each-will be included as attachments to the final report. I L l l PDXOM-01 Rev. 1.5 (Page-2 of 2) l l l

T t 4 j 4 i ENCLOSURE 4 Safety Evaluation Termination Survey Plan, Rev. 0 October 1992 a A .}

- - -.~. = - - -. -. - 1 d Appendix 12.1 Page 1 of 3 SHOREllAM NUCLEAR POWER STATION SAFETY EVALUATION CHECKLIST-1 CHECKLIST APPLICABLE TO: Termination Survey Plan. Rev. O. October 1992 l SAFETY EVALUATION - PART A i Does the item to which this checklist is applicable represent: i Yes X No ___ A change to the station or procedures as described in the DSAR/DP; or a test or experiment not described in the DSAR/DP7 If the answer to the above is "Yes", attach a detailed description of the item being-evaluated and an identification of the affected section(s) of the DSAR/DP. i j Does the item to which this checklist is applicable represent: l Yes X No A decommissioning activity? If the answer to the above is "No", mark the next two questions as N/A and continue with Parts B and C, Otherwise, answer the following questions, { Yes X No ___ Does the proposed decommisstoning activity deviate from the DP? i Yes No _3_ Is the proposed activity a new decommissioning activity not previously addressed in the DP7 I If the answer to both of the above questions is "No", complete Parts B, C and D. If the answe" to either of the above two questions is "Yas", attach a detailed description of the t'.:m being evaluated and an indication of the affected sections of the DP and complete ?#rts B, C and D. SAZETY EVALUATION - PART B l l a No X Will this item require a change to the Station Technical Specifications? j If the answer to the above is "Yes", identify the specification (s)-affected and/or attach the applicable page(s) with the change (s) indicated, 4 i SPF 12X004,02-1 Rev. 1 't i a 1 SP 12X0004.02 Rev, 1 Page 8

Appendix 12.1 Page 2 of 3 SAFETY EVALUATION - PART C As a result of the item to which this evaluation is applicable: Yes No X Will the probability of occurrence of an accident previously calculated in the DSAR/DP be increased? Yes No X Will the consequences-of an accident previously evaluated in the DSAR/DP be increased? Yes No X Will the probability of malfunction of equipment previously evaluated in the DSAR/DP be increased? Yes No X Will the consequences of a malfunction of equipment previously evaluated in the DSAR/DP be increased? Yes No X Will the possibility be created for an accident of different type than any previously evaluated in the DSAR/DP? Yes No X Will the possibility be created for a malfunction of a different type than any previously evaluated in the DSAR/DP? Yes No X Will the margin of safety as defined in the basis for any Technical Specification be reduced? If the answer to any of the preceding is "Yes", and unreviewed safety question is involved, Justify the conclusion that an unreviewed safety question is or is not involved. Attach additional pages as necessary. SAFETY EVALUATION - PART D This section shall be completed if the item being evaluated-is a decommissioning activity. Will the proposed decommissioning activity have an adverse effect on: Yes No X Nuclear Safety? Yes No X Compliance with regulatory requirements? Yes No X Safe fuel storage? Yes No X Security? Yes No X Interfacing with operational systems? g Yes No X Contamination control? l Yes No X Isolation from clean systems? If the answer to any of the preceding is "Yes", a general safety concern is involved. The justification for answering the applicable Parts (A-D) above should:be documented using the safety evaluation format shown in Appendix 12.2. Refer to Section 8.1 of this procedure for additional guidance. SPF 12X004.02-1, Rev. 1 S P-- 12X0004. 02 Rev. 1 Page 8

d Appendix 12.1 Page 3 of 3 //!/N f 2i-PREPARED BY: [tr32L 7, NEWh DATE: U[/I[9E / 9 r0 REVIEWED BY; ~ /Q DATE: Note: If this safety evaluation is the result of a' Station Procedure Change-Notice (SPCN), 2-no review is required. l SAFETY EVALUATION - PART E fl' The SRC Secretary shall ensure this part is completed after SRC approval. In'i t rEls Date l An information copy of this completed safety evaluation (including / <k all attachments) has been sent to Quality Systems. I,b // initials D' ate l i i i i l I i l SPF 12X004.02-1 Rev. i ) i l i l i l SP 12X0004.02 Rev. 1 Page-8 ) i

Initiatina Dgcumentt Shoreham Decommissioning Project Termination Survey Plan, Rev. O, October 1992 PreDared bV: Clyde T. Newson Scope of Safety Evaluation: This Safety Evaluation (SE) addresses changing the existing Decommissioning Plan (DP), Section 4.0, Proposed Final Radiation Survey to reflect The Shoreham Decommissioning Project Termination Survey Plan, Rev. O, October 1992.

References:

1. USNRC, Draft NUREG/CR-5849, J.D.-Berger, Manual for Conducting Radiological Surveys in Support of License Termination, June l 1992. 2. USNRC, Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, June 1974. 3. Long Island Lighting Company (LILCO), Shoreham Nuclear Power 4 St.. tion Site Characterication Program, Final Report, May 1990, plus addenda. 4. Long Island Power Authority (LIPA), Shoreham Nuc] ear Power Station, NRC Docket No. 50-322, Decommissionir.g Plan, as amended. 5. Code of Federal Regulations, 10CFR50.59 Discussion: The DP Section 4.0, Proposed Final Radiation Survey will be replaced. The now Section 4.0 references the Termination Survey Plan, Rev. O, Oct. 1992. The basis for the Termination Survey Plan, is the draft NUREG/CR-5849, J.D. Berger, " Manual for Conducting Radiological Surveys in Support of License Tormination", June 1992, (Ref.1). On the other hand, the decommissioning activity formerly described in DP Section 4.0 is based largely on the statistical and sampling methodology developed in-NUREG/CR-2082, " Monitoring for Compliance with Decommissioning Termination Surve Criteria", June 1981. The methodology in the Termination Survey Plan, differs from the former DP Section 4.0, however, the Vermination Survey Plan is designed to achieve the same results as the present Section 4.0 in releasing the facility and site for unrestricted use and termination of NRC License NP7-82 by meeting the requirements of USNRC, Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors", June 1974 (Ref.2). The Termination Survey Plan provides the overall program which will govern the activities needed to release _the facility and site for unrestricted use

-2 and terminate NRC license NPF-82 by meeting the regulatory criteria set forth in U.S. Nuclear Regulatory Commission, Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors", June 1974. Summary: Implementation of the Termination Survey Plan, Rev. O, October 1992 will provide the documentation that the site and facility meet the criteria of Regulatory Guide 1.86. (Ref.2) for unrestricted use, Using the most recent NRC endorsed guidance provided in the Draft NUREG/CR-5849 (Ref.1) in developing the Termination Survey Plan, Rev. O, October 1992 enhances the overall programmatic approach and provides a high degree of confidence that the final radiation survey will provide adequately documented evidence that the regulatory requirements for releasing the facility and site were met for unrestricted use and the termination of NRC license NPF-82. l

== Conclusion:== Based on the above discussion, Safety Evaluation Checklist and listed references, implementation of the Shoreham Decommissioning Project, Termination Survey Plan, Rev. O, October 1992, does not represent an unreviewed safety question because the plan provides administrative direction for preforming radiological surveys. Also, modifications and work activities are governed by Station Procedures which will be evaluated to determine the existence of an unreviewed safety question. Implementation of the guidance in draft NUREG/CR-5849,-in lieu of the guidance formerly proposed in DP Section 4.0 (i.e. NUREG/CR-2082) will not resul'c in any change in radiological impact to workers or the public. (%)L L%w /lllW9z-Clyde T. Newson Date i

ENCLOSURE 5 Minutes - Site Review Conunittee 1

MEETING. MINUTES ' ivc. 2 l 19 3 2. Site Review Committee Meetina Date Issued Attendina: L. M. Hill, Chairatn A. Bortz, Chairman N. Nilsen, Member L.F. Britt, SRC Sacretary L. Lewin, Member W. Maloney, Member F. Petschauer, Member E. Montgomery, Member J.-Wynne, Member M. Tucker, Alt. Member G. Gisonda, Guest C. Newson, Guest L. Henry, Guest V. Demers, Guest Meetina Called to order by Chairman: Date: November 19, 1992 Time: 9:15 A.M. Meetina 92-095 ADoroval of Previous Minuteg: New Items 92-095-001 SPCN 92-700 SP #67X001.02 Rev. G, " Termination. Survey Procedure". Based upon a presentation by M.

Tucker, operations and Maintenance Department, this procedure has-been reviewed in accordance with 10CFR50.59 and SRC has de.termined that there are no unreviewed safety questions.

This item does not result in environmental impacts different from and exceeding those set forth in the licensee's Supplement to Environmental Report December 1990. This item has been approved. i Item Closed 92-095-002 Safety Evaluation of Termination Survey Plan Rev. O and Deconanissioning Plan Section 4. Based upon a presentation by M.

Tucker, Operations and Maintenance Department, this procedure has been reviewed in accordance with 10CFR50.59 and SRC has determined that there are no unreviewed safety questions.

This item does not result in environmental impacts different from and exceeding those set forth in the licensee's Supplement to Environmental Report December 1990. This item has been approved as revised. l Item Closed Meetina Adiourned by Chairman: Time: 10:b0 P.M. ADoroval of Minutes: V Chairman -}}