ML20128P715
| ML20128P715 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/22/1992 |
| From: | Leslie Hill LONG ISLAND POWER AUTHORITY |
| To: | |
| Shared Package | |
| ML20128P641 | List:
|
| References | |
| PDXOM-01, PDXOM-1, NUDOCS 9302250085 | |
| Download: ML20128P715 (48) | |
Text
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(
i PDXOH-01 I Rev. 1
-_,/
') Effective Date 11/20/92 LIPA NUCLEAR MANAGEMENT <
- got CONTROL MANUAL NUCLEAR ORGANIZATION MANAGEMENT CONTROL PROGRAM FOR Decommissioning Termination Durvey Program Description
', { g (PDIOM-01) fs l
l l Approved DSto i 4' L//1. Hill l RVsident Manager l
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9302250005 930222 PDR H ADOCK 05000322 PDR
Prograss Des 3riptica .
PDION-01 Decommio:itairy Termic:tica surv:y arv. 1 l Peg) 1 cf 26 l
[ TERMINATION SURVEY PROGRAM DESCRIPTION TABLE OF CONTENTS 1.0 OBJECTIVE . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 REFERENCER . . . . . . . . . . . . . . . . . . . . . . . 3 3.0 DEEINITI.ONG . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . 7 4.1 LIPA - SNPS Resi13nt Manauer . . . . . . . . . . . 7 4.2 Decommissionina DeDartment.Managir . . . . . . . . 7 4.3 Nuclear Ouality Assurance DeDartment Manauer . . . 8 4.4 Nuclear Qperations suDDort DoDartment Managar . . . 8 4.4.1 Fuel Disposition Division Manager . . . . . . 8 4.5 Licensinc/Reculatory conDliance DoDartRent Rgaaggr . . . . . . . . . . . . . . . . . . . . . . 9 4.6 Finance and. Administration DoDartment Manacer . . . 9 4.7 Operations and Maintenance DoDarta3nt Managtg . . . 9 4.7.1 Rag.iolocical Controls Division Manacer . . 10 4.7.1.1 Termination survey Bection Eggg . . 10 4.7.1.2 IgImination Burvey Encineer . . . . . . 11 4.7.1.3 Health Phybics Encines.I . . . . . . . 11 4.7.1.4 Ragyaste Encineer . . . . . . . . . . 12 4.7.1.5 Radiochemistry Encineer . . . . . . .
12 I 4.7.2 Egplear Encing1Eina Division Manaqqr . . . . 12
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4.7.3 Maintenance Divisfon Manggar. . . . . . . . . 13 4.7.4 Operations Division Manaaet . . . . . . . . . 13 4.8 Shoreham salvgce Division (LILCO). . . . . . . . . . 13 5.0 PROGRAM DESCRIPIlQN . . . . . . . . . . . . . . . . . . . 14 5.1 Termination Survey Procram Overview . . . . . . . . 14 5.1.1 Backaround . . . . . . . . . . . . . . . . . 14 5.1.2 Technical ADDroach . . . . . . . . . . . . . 14 5.1.3 Procram Desien Approach. . . . . . . . . . . . 15 5.1.3.1 Responti)1e Orcanisation . . . . . . . 15 5.1.3.2 DApartmental InterfAqa . . . . . . . . 15 S.1.3.3 control of survey Units . . . . . . . 15 5.1.3.4 Survey of Facility Structural Areas and ODen Areas. . . . . . . . . . . . . 15 5.1.3.5 Egryev of Plant Systems . . . . . . . 16 5.1.3.6 pse of Historical Information . . . . 16 5.1.3.7 Release Record . . . . . . . . . . . 16 5.1.3.8 Final RfDort . . . . . . . . . . . . . 17 5.2 Procram ImDiementati2A . . . . . . * * . . . . . . . 17 5.2.1 ppgMainta . . . . . . . . . . . . . . . . . . 17 5.2.2 InDiementation Milestones . . . . . . . . . . 18 5.2.2.1 Planninc . . . . .3 . . . . . . . . 18 5.2.2.2 DeveloDuent . . . . . . . . . . . . . 18 5.2.2.3 Preliminarv_8urvey . . . . . . . . . . 18 5.2.2.4 Final Survey . . . . . . . . . . . . . 18 5.2.2.5 Final RoDort . . . . . . . . . . . . . 19 1
Program De:@riptir3 PCION-01 De:oenicoltairg T rminatics surv0y asy. 1 P:ga 2 cf 26
[f 5.3 5.2.3 Intearation with Proiset Schtdule Eurvey Process
. . . . . 19
. . . . . . . . . . . . . . . . . .. 19 f 5.3.1 Summary . . . . . . . . . . . . . . . . . . . 19
\ 5.3.2 Process Details . . . . . . . . . . . . . . . 19 5.4 Oraanisation and staffina . . . . . . . .. . . . . 19 5.4.1 Oraanization Chart . . . . . . . .. . . . . 19 5.4.2 staffina . . . . . . . . . . . . . . . . . . 20 5.5 conduct of operations . . . . . . . . . . . . . . . 20 5.5.1 Oraanisation operations . . . . . . . . . . 20 5.5.2 Fork Control . . . . . . . . . . . . . . . . 20 5.5.2.1 Encinegrina Support . . . . . . . . . . 20 5.5.2.2 Non-LIPA Asagig . . . . . .. . . . . . 21 5.6 Survey Ouality Asgurance . . . . . . . .. . . . . . 21 5.6.1 Decommissionina OA Procraa . . . . . . . . . 21 5.6.2 Internal Procram Measuras__ . . . . . . . . . 22 5.7 Tergipation survgv Plan . . . . . . . . .. . . . . 22 5.7.1 Plan Cont.pnts._ . . . . . . . . . . . . . . . 22 5.7.2 Ryrvey Unit ClassificatiED . . . . . . . . . 23 5.8 Procedure 3 . . . . . . . . . . . . . . . . . . . . 23 5.9 Work Instructiong . . . . . . . . . . . . . . . . . 24 6.0 INTERFActa . . . . . . . . . . . . . . . . . . . . . . . 24 6.1 Ouality Assurance . . . . . . . . . . . . . . . . 24 6.2 Decomgligionino Departgini_ . . . . . . . . . . . . 24 6.3 Work Control . . . . . . . . . . . . . . . . . . . 24 6.4 Safety Procram_ . . . . . . . . . . . . . . . . . .,25 f 6.5 F_ ire Protection . . . . . . . . . . . . . . . . . 25
/ 6.6 Security Plan . . . . . . . . . . . . . . . . . . 25 6.7 Nuclear Encineerina . . . . . . . . . . . . . . . 25 7.0 PROGRAM EVALUATION . . . . . . . . . . . . . . . . . . . 25 7.1 Routine F,1gdback . . . . . . . . . . . . . . . . . 25 7.2 Periodic Evaluation . . . . . . . . . .. . . . . . 25 8.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . 26 8.1 Criteria for Release of Shoreham Nuclear Power i
E11 tion for Unrestricted Use Pollowinq l Decommissionina . . . . . . . . . . . . . . . . . . 26 8.2 Termination Survey Process En==arv . .. . . . . . 26 8.3 Igraination survey Process Details . . . . . . . 26 8.4 Termination Survey Orcanisation Chart . . . . . . . 26 8.5 Igrmination Survey Final Report Outline . . . . . . 26 N
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Program Description PDION-01 Decommissicning rorsinstica survey Rry. 1 Pag. s or as PROGRAM DESCRIPTION FOR DHOREHAM DECOMMISSIONING TERMINATION BURVEY 1.O g N Ig n y2 Termination of the U. 6. Nuclear Regulatory Commission (NRC) license for the shoreham Nuclear Power Station (SNPS) requires that radioactive materials he removed and that residual radiation and contamination levels2 bp below limits identified in the shoreham 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 Burvey organization and the management control mechanisms for the Termination Survey Program in accordance with the requirements of the Long*faland Power Authority (LIPA) Nuclear Management Control Manual . This document also describes responsibilities of Shoreham Decommissioning Project organisations f in support of the Termination survey Program. A program overview is provided which includes a summary of the management approach and 9' major planning milestones. This Program Description establishes the basis for development of implementing plans and procedures. l l
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2.0 REFERENCES
2.1 LIPA Shoreham Decommissioning Plan, NRC Docket No. 50- !
322, as supplemented.
2.2 LIPA Nuclear Management Control Manual, " Nuclear Organization Management Control Program for Program Description Development, Review and Control", PDION-01 2.3 Long Island Lighting Company (LILCO), " Program i Description site Characterization Program, Shoreham l
Nuclear Power Station", Rev. 1, Oct. 10, 1990 (with addenda).
l 2.4 LILCO "Shoreham Nuclear Power Station Site Characterization Program Final Report", k3} 1990, with Addenda 2.5 LIPA Quality Assurance Manual b
Program pescriptics PDION-01 De:ommissir21:g Tarmic ticu Surv0y EsV. 1 Pag) 4 Cf 26 l 2.6 NRC " Manual for Conducting Radiological surveys in l
( support of License Termination", NUREG/CR-5849, DrafC ;
Report for Comment.
2.7 LILCO BNPS Updated Saf ety Analysis Report (USAR) and Defueled safety Analysis Report (DSAR), Docket No. 50-322, as amended.
2.8 LILCO SNPD Composite Component List (CCL).
2.9 U. 8. Atomic Energy Commitrion (AEC), Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors", June, 1974 3.0 DEFINITIONS 3.1 Characterif_g. tion Survey - Radiological survey measurements, supporting calculations and evaluations performed to establish the shoreham facility baseline radiological condition prior to decommissioning activities and to serve as a planning tool for the decommissioning effort. The characterisation survey activities are described in and contg lied by the site Characterization Program Description f 3.2 plit.eria DJ;Lgyannt - The document which describes the criteria that will be used for releasing the shoreham O facility for unrestricted use. It interprets the NRC guidance and outlines the technical bases for the Shoreham Termination survey. It is an attachment to this document.
3.3 History Pile - A compilation of information prepared for use in planning the termination survey of a survey unit.
It summarizes the operational history, characterization data, operational surveys and other information to establish the basis for the design of the termination survey.
3.4 Open Arel - A category of survey unit including open land areas, exterior surfaces of site buildings, paved or unpaved roadways, and equipment yards.
3.5 Qp.grational Survey - A radiological survey perrormed under SNP8 Health Physics procedures. All surveys not otherwise classified as termination surveys or characterization surysys are classifico as operationkl 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 survey.
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Prg graa Deacriptic3 PDION-01 Decommissiosing Torcination survoy Rry. 1 Pcgs 5 cf 26 3.6 Diructura - A category of survey unit including all BNPS
( site buildings and their inner surfaces (generally identified as civil structures). For purposes of the termination survey, all structures such as platforms, restraints, supports and other physical items not identified in the system "XFSK" drawings are considered to be structures. External surfaces of piping systems are also treated as structures in the termination survey.
3.7 QC Durvey -
An independent radiation survey, usually performed on a representative sample of a characterisation or termination survey to verify the results.
3.s Fe3104pe criteria 2 - A term used to identify the radiologica, criteria for release of the shoreham facility for unrestricted use. These criteria, which consist of specified limits for residual contamination and radiation levels, are identified in the Shoreham Decommissioning Plan and are described in detail in Attachment 0.1 of this document.
3.9 E_elease Record - A document which demonstrates a survey unit is suitabic for unrestricted usa. It contains evaluated survey data and supporting information to provide a concise record of the results and basis for the conclusion that the release criteria are satisfied.
3.10 pite Characteritation RePRIA - A report (including
[\ addenda) which documents the surveys, calculations and evaluations and present results of the BNPS Site Characterization Prrgram( he 3.11 Burvey Design - The process of determining the type, location, number and frequency (or density) of radiological measurements to be taken %ithin a survey unit for the termination survey.
3.12 p1rvey Instructiong - Written direction to survey personnel regarding the type and number cf measurements to be taken in a survey unit. A survey instruction generally includes marked maps, written text or both.
Each survey package includes servey instructions.
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Program nescription PDION-01 Decommissioning Torninstion survey RrV. 1 Pago 6 of 26 3.13 Eu.rvey Packagg - A collection of information in a
( standardir,ed format for controlling and documenting field ,
measurements taken for the termination survey. A survey package will be prepared for each survey unit.
3.14 survey 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 Burvey Unit -
A logical division of the facility );
structures, systems and site environs for purposes of performing and documenting the termination survey. The i survey unit is the basic entity for management of 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 aurvey Unit Classification - A term used to indicate the the potential for residual radioactive contamination
- within a survey unit.
3.17 Termination Survey -
Radiological measurements, evaluations and supporting activities undertaken to demonstrate that the Shoreham facility satisfies the radiological criteria to allow the NRC license to be terminated and the f acility and its property released for unrestricted use.
3.18 Termination Survey Plan - The document which provides the technical 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 i 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 termination survey and demonstrates that these instruments and measurements are capable of verifying the release criteria. . It is subordinate to this Program Description and provides the
- basis for specific termination survey procedures.
3.19 Termination Survey ReDort - A report describing the scope, methods, and results of the termination survey. It initiates the NRC review and final inspection of the f acility prior to termination of the f acility license. It is also called the Final Report.
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. Program Description FDIoN-01 De:ommicsicaing Tormicotion Survey RZv. 1 Pego 7 et 26 4.0 PJSPONSIBILITIES 4.1 LIPA - SNPS Resident Ms.nacer The LIPA - SNPS Resident Manager reports to the Rzecutive 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 license 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 Decommissionine Department M uscer.
The Decommissioning Department Manager reports to the Resident Manager and is responsible for management and direction of Shorehan decommissioning 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 termiration survey:
- a. Reviewing survey units and survey unit classifications to identify areas involved in decommissioning work. ,
k- b. Reviewing the termination survey schedule to verify O that surveys do not conflict with decommissioning work schedules and to minimize duplication of scaffolding and j 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 componsnts or making cuts) and restoring systems (if applicable) where decommissioning activities were completed, as requestad by operations & Mainte ance (0&M) Department management.
This support will be provided on a case-by-case basis.
Program Description PDION-01 i De:ommicoicsieg Torminatico surycy Erv. 1 l P:g2 s cf 26 4.3 Nuclear Quality Aj!uturance DeDartment Manacer The Nuclear Quality Assurance (NQA) Department Manager reports to the Executive Vice President, Shoreham Project and is responsible to the Resident Manager for the development and administration of the decommissioning QA program. He provides QAoversightoftheTegnationsurveyPrograminaccordance with the LIPA QA Manual . This oversight includes review of the Termination survey Program Description, the Termination survey Plan, termination survey procedures and other documents, as well as audit and surveillance of termination survey activities. Termination survey measurements are verified by independent Oc measurement of selected survey points under NQA surveillance.
4.4 helear Operations support Dep.grtment Manaaer The Nuclear Operations Dupport Department (NOSD) Manager reports to the Resident Manager and is responsible for managing station support services, including plant security, fire protection and safety, training and site administration services. He provides historical information such as engineering drawings, documents and other reference materials for the termination survey and provides training r.:
termination survey personnel. He also provides assistancA in document control, and reference materials for use in
( preparation of termination survey history files.
4.4.1 Fuel Disposition Division Managit The Fuel Disposition Division Manager reports to the NOSD Manager and is responsible for the planning, scheduling and coordination of activities involved with the removal of fuel from the shoreham facility. He is responsible for the following matters regarding the termination survey:
- a. Informing the Radiological Controls Division (RCD) Manager regarding plans, status and schedules for removal of the nuclear fuel from the Spent Fuel Pool.
- b. Requiring fuel shipment contractors to make reasonable efforts to limit the introduction of 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 t'uel transfer equipment.
- c. Minimizing the potential for contamination of affected areas as a result of fuel transfer
( activities.
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l Program De criptics PDIoN-01 Decommissienicg T0rmicotics survoy arv. 1 Pag 3 9 sf 26 4.5 Licensing / Regulatory Compliance Departagnt Manac3I The Licensing / Regulatory Compliance Department (LRCD) Manager reports to the Resident Manager and is responsible for licensing and regulatory matters (including NRC and other relevant agencies or regulatory bodies) relating to decommissioning of Shoreham. He 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 subr, 'ted to the appropriate regulatory agency in a timely o.nner.
- b. Keeping the RCD Manager informed of licensing 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 Q implementing documents and reports to ensure that they are accurate with regard to regu.*tatory requirements and related policy issues.
- e. scheduling review of designated termination survey i
documents by the LIPA Site Review Committee (SRC).
4.6 F1 Dance and Administration Dgp3rtment Manager 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. He provides procurement support services, strategic scheduling support, progress reporting and other administrative services to the program.
! 4.7 pnerations and MainteJULDee Department Manager l
The Operations and Maintenance (O&M) Department Manager reports to the Resident Manager and is responsible for l
( operations, maintenance, radiological control and plant engineering support for the decommissioning project. He is O
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Program De:cription PDIoN-01 Decommissicnicg Tormination survoy arv. 1 Pogs to of 26
, responsible for general policy guidance and management
.~
oversight of the termination survey program.,He is responsible for providing personnel and technical resources necessary to support the termination survey.
l 4.7.1 Radiolocical Controls Division Manacgr The RCD Manager reports to the O&M Department Manager and is responsible for the radiological health and safety of project personnel and the public. He is responsible for radiochemistry, haalth physics, radwaste handling and disposal, and for the termination survey. E's is responsible for personnel management and technical direction for the Termination Survey Program. He establishes and maintains budgetary controls for the program.
4.7.1.1 Terminajiion Survey Bection FLad The Termination Survey Section Head reports to the RCD Manager and is responsible for implementation of the Termination survey Program described in this program description. He is responsible fort
- a. Identification of technical and personnel j resources required, and selection of personnel.
- b. supervision of termination survey personnel, Keeping SNPS management informed regarding t
c.
the status and results of termination survey activities, and problem areas that may develop.
- d. In conjunction with the Project Controls Division of the P & A Department and the Work Planning & Scheduling Section of the O & M l Department, scheduling termination survey activities to meet project milestones,
- e. Coordinction of termination survey activities and requirements with other BNPS organizations.
- f. Representing the Shoreham Termination survey in communications with outside organizations.
- g. Notifying SNPS management when the termination survey of a survey unit is complete and establishing controls to prevent possible i
I recontamination or other events which would
( threaten the integrity of the termination survey results.
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Program De:Oriptico PDION-01 De;oenniasic irg r:rmir tica survcy asy 1 Page 11 of 26
[ 4.7.1.2 Termination survev Enoineer V The Termination survey Engineer reports to the Termination survey section Mead and is responsible for preparation of the Termination survey Plan, providing the necessary technical direction to the Termination survey Program. He is responsible fort
- a. Designing and implementing the Termination survey Plan to meet established objectives and regulatory requirements.
- b. Procuring and developing specialised instrumentation and equipment.
- c. Providing technical direction to termination survey personnel.
- d. In conjunction with the Health Physics Engineer, determine the most efficient schedule for survey of individual survey units in order to minimize the potential for resurvey or impact on decommissioning activities.
/ e. coordination of review of survey results,
/ preparation and approval of release records and (s
preparation of the Termination Survey Report.
l f. Identification of components which must be I
dissassembled (access provided) to accomplish surveys and initiation of the Maintenance work Requests (MWRs) by which this work will be controlled.
4.7.1.3 R9alth Physics Encine_pl The Health Physics Engineer reports to the RCD Manager and is responsible for health physics and radiological safety for the termination survey. He l
is responsible for the following regarding the i termination survey ,
1 l a. Providing instrumentation, instrument calibration services, instrument maintenance, l routine health physics supplies, counting room services, and related technical services.
- b. Providing personnel to supplement the l termination survey staff as needed, and to perform survey measurements. ,
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, r Program DoctriptiO3 . PDION-01 Decommiseioning rersiastica 0%rv0y asy. 1-Page 12 of 26
- o. . Providiny radiological information from characterisation and operational surveys.. Be informs the fermination survey sootion Road of any changes: in radiological conditions which could affect termination surveys of any area or system and acts to minimise the potential-spread of contamination throughout the-facility.
- d. Performing surveys of incoming radioactive transport vehicles or equipment and informs the Termination- survey- section Read of pertinent results. He performs surveys to help ensure that no new radioactive species are introduced into the shoreham facility. .i
- e. Implementing necessary controls to preventL recontamination of a survey- unit upon !
completion of uhe termination-survey.-
- f. Coordination of survey support and actual-survey activities to meet the project schedule.-
4.7 1.4 ,*adwaste Enaineer The Radwaste Engineer reports to the RCD Manager g and is responsible for radioaci.ive waste management and disposal for the shoreham Decommissioning a Project. ' No is responsible - for plant l decontamination services. He- provides decontamination support to the Realth Physics '
section and to the Termination survey section ' as requested. s a
! 4.7.1.5 Radiochemistry Engineer _
The Radiochemistry Engineer reports; to the RCD-Manager and is responsible for plant chemistry and-radiochemistry- services. Re_ provides-radioar.alytical support for:the termination survey-I' including gamma spectroscopy, gross : beta, alpha, ;
and other- specialised" radiochemistry _- analyses E on.
i l
l request. Me assists in special. studies to: identify l1 radionuclide composition and :ooncentrations of !
i, residual activity in various samples. and materials. .
4.7.2 Muclear Engineerina Division Manager The Nuclear Engineering Division (NED) Manager _ reports to -
L the OEM -Department. Manager.andJ-_is responsible for- ,
engineering services'and nuclear analysis. He provides-engineering support as required for station Modification! nw "
Packages which provide access (and restoration, if L
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Program De:criptica PCIoH-01 Decommiosi= ity Tarminatics surycy REV. 1 P gs 13 cf 26 l
f applicable) to systems for termination survey measurements. He is also responsible fort
- a. Providing data and environmental sampling cupport for the termination turvey from the Rkdiological Environmental Monitoring Program (REMP) through the LILCO Environmental Engineering Department,
- b. Providing data, results abd 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 Department 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 servicea, component disassembly and restoration and other services traditionally provided by the Maintenance Division, including preplanning of Maintenance Work Requests (MWRs) for component access or dissassembly, to support the termination survey. In most cases, the Maintenance Division will have lead responsibility for support of the I termination survey. In some cases, the Decommissioning 9 Department may be requested to provide services such as scaffolding or component disassembly.
4.7.4 operations Division Manaaer 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 aupport for the termination survey for system lineups, tagging, maintaining isolation of systems with completed termination surveys, and control of facility areas which have been surveyed. He notifies the RCD Manager of changes in facility 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) .
4.8 Shoreham Balvace Division (LILCol The Shoreham salvage Division Manager reports to the shoreham
^
site support Department Manager. He is responsible for review I
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Program Descriptics .
PDIoN-01 Decommissioning T rmicatica survey REV. 1 Pcgo 14 et 26 and concurrence with survey designs in order to assure the
(. followings
- a. LILco assests (salvageable components) are identified and removed from survey areas priar to conduct of the termination survey.
- b. Acknowledgement that components not removed from an area prior to the termination survey may not be available until after license termination.
- c. Concurrence with the planned final disposition of a system and/or component or identification of specific preservation requirements to be imposed upon completion of the termination survey.
5.0 PROGRAM DESCRIPTION 5.1 Termination Survey Procrgy Overview 5.1.1 Rockcround The termination survey has been identified as a key element in the success of the Shoreham decommissioning effort, in that timely termination of the NRC license f depends heavily an the quality of the termination survey k and its documentation. Further, the Shoreham facility first decommissioning represents the of a large l
commercial nuclear power facility in the U. 8. Unlike most previously decommissioned facilities, the shoreham plant structures aC the majority of the piping systems will be intact Lpon completion of decommissioning dismantlement and decontamination (D&D) activities. This repressats a significant increase in the degree of complexity and physical scope of the survey in comparison with previous decommissioning projects. The approach to the termination survey described below is responsive to these challenges.
5.1.2 Technical Approach The technical approach to the termination survey is based
- 'pon the NRC criteria for release of the facility for unrestricted use, as discussed in Attachment 8.1 of this program description. The methods guir design of the survey, instruments used, field measurement procedures, data collection and analysis, documentation and interpretation of results are derived technical literature (including draf t NUREG/CR-5849 from publip ),
,ged experience from recent nuclear facility decommissioning termination surveys, and consultation with knowledgeable peers. The technical approach is described in detail in i
m .._ . _ . , _._ - - . _ _ . _ . . _ _ - . - , - - . _ . .. . . _ .
- Program' Des 3riptio6 . .
- PeteN ,
- Deceastatiesity Torstaatica_surn y. <
EsV.--1 j P:gi 15qcf-26
. the shoreham 72rmination~ Survey Plan outlined;in sectionL U 4 5.7.. below. ,
5.1.3 Program Desian Annroach ,
5.1.3.1-Resnonsible-.Oraanisation
~
The Termination survey 'section,_ = within ' - the -
l Radiological Controls Division, isl responsible for development and-implementation'of the. termination
, survey. It will be_ managed and supportedDbyca, qualified staff. The Wealth Physics section will- 1 support the Termination survey section by providing-
- technicians,1 supplies,- administrative' support, designated technical support and other services. ;
5.1.3.2 Departmental Interface Appropriate methods shall be established' for.-
communication between the Termination _surveyr '
Section and other decommissioning project' groups (i.e. the- -Decommissioning Department, -the.
Operations section and the Maf.atenance sectionKoff the O&M Department) for scheduling termination-
. surveys.- Mechaninns shall be established:-for turnover of' facility areas for teruination surveys.
( '
5.1.3.3 Control of Burvey'Udit.g
- controls chall be established - for- -isolationL of survey - unats _ scheduled for- termination _ survey to minimize 'the possibility. of- . recontamination..
F u r t h e ,1m o r e , appropriate contrJ1s will- be -
maintained on all survey: units for :~which the:
termination survey has been completed.
5.1.3.4 survey of Facility' Structures and 9 pen Areas The termination survey _of fdcility structuresEand 4 epen areas'will be organised;by.dividingLthem intoi discrete entitles -for . management of _ the survey.-
Plant structures, :-systems -and outdoor-~ areas will be divided' into -survey units. andL subunits. The:
description 1 and identification' of; areas : for this--
purpose Hare based - primarily - upon : plant: general
. arrangement dy,ayings similar to those. contained in.
the SMPs USAR : . . . Each survey unit'or subunit will -
be-classified _ based'_on-the potential' for residual.
+
radioactive ' contamination within' the area it represents.
F' IAdp'th n
1
'9 *ea up' I 6 -W W k ?'b""
. - _ .__ - _ . _ . . _ . . . _ _ _ . _ _ _ _ _ _ . _ ~_ ._ .
- Program De:Sript130i PDION-01 * "
7;
- Decommicciosity Termisstics survcy; ask 1
.p:gs As of 26- l 5.1.3.5 survev of' Plant crattag-Plant I systems will be i nurveyed l andlevaluatodi as I i
- discrete / entities. : Identification c of J systems Evill: .
i
- f ollowj the i system
- index ;of: the .. Records - Management ;
File Code -List. ' Identification of;systemc contents and: boundaries will be - based on~ "MFSK" series -
drawings. Identification Lof? individual will be in accordance with the SNPS CCL,,gosponents l
. = Piping. a sections will be. identified by refetanoe to'"MFSK":
series drawings, installation isometric L drawings i and-Stone & Webster: Engineering. Corporation-(SWBC)=. ~_
line numbers as appropriate. . - Bach i system will ' be..
identified as a survey _ unit:for termination survey.
purposes. Each system survey unit may - be-- divided 1 -
into survey subunits.- such subunits will include a -
portion of the- system and J any _ contain af single__
component, . a group cf l components .or aisection , of .-
the system group.-- Portions of a system-contained' q within a system subunit shall be determined-to have?
equal- potential- for- residual radioactive- .
contamination. Each-survey unit or subunit will be.
classified based on 1 the potential - for:' residual -
radioactive -contaminationEin that portion of1 the -
system.
L:l ,-
5.1.3.6 Use of Historical Information. .
Determination that a - survey c unit < satisfies . ~ the - ' -
criteria for unrestricted release- shall1 be1 based '
upon an evaluation 1of<its; history as well as:upon- "
Termination Survey measurements. ' Maximum use shall-be made of ' historical. information. Historical infornation includes Joperating. _ history -and .other-relevant operational data, SWPS :Characterisation
- Program data, operational- and Jenvironacatal '
radiation ~ surveys and- data j reports.- Such ~
l_
information will -be- used: for . initial survey ' unit -
classification.- The : degree ! of. relinace given . to :
L historica1>datn considered' tor:use as-finalosurvey..
L data (see -also, 5.2.2.4 Final survev),1 depends on-the. conditions -and .' changes occurring. in the-interval prior t6 the time of the survey .and on the.-
l abilitt2to' document the data. integrity in-a'mannerE l consistent with_ termination survey data.
5.1.3.7 Raltase Record Demonstration that the shoreham facility satisfies the- criteria for- unrestricted use shall: be l documented for each survey unit. A document, called the Release - Record, ' will be prepared .for:
this purpose. The release record, prepared tin' a
-l 2 1 E l -= Ftiiz- A tpp
, Program De:criptics P; ion-01 <
De;ommissic2irg T0rmiactica survey Rry. 1 Pcg3 17 cf 26 i
L etandard format, contains survey data, survey I statistics,. a written evaluation and a
/( ]' determination that the release criteria are
(/ satisfied. Sufficient survey measurement data will be included in each release record as necessary to support the determinatian. In order to keep release records to a manngeable size, supporting.
. information such as the survey unit history file and field survey data may not -be physically included, but will be referenced and properly archived. survey units of similar composition, bistory and classification may be combined into a single release record to ease replication of administrative details. The release record will rot be " closed out" and given final approval until all identified remedial actions are satisfactorily complet.d. Release records will be prepared by the l Termination Survey Section. Each releass record I 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 g Committee (BRC).
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 8.5, will demonstrate that the facility is suitable for unrestricted use. The final report will cgmply with Section 4.e of Regulatory Guide 1.86 and the form and content of daaf c NUREG/CR-5849{o} . It willlow 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 Procram Implementetjp3 5.2.1 Documents The implementing documents for the termination survey consist of the Termination Survey Plan, Termination Survay Procedures, and Esalth 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 be produced as part of the termination O
Prcgram Descriptica P. TION-01 Decommissiening T rmicatien Survey azy. 1 P g3 18 of 26 survey include survey Unit History Files, survey Unit Survey Packages (including survey instructions), and
/. -.D Survey Unit Release Records. Documents and records U produced in support of tbs termination survey include survey instrument calibration records, survey instrument control check records, computer sof twnre verification l reports, facility background radiation measurements, and l perronnel training and qualification records.
5.2.2 Implementation MileAtgAqta Program implementation can be viewed in terms of five major phases or milestones planning, development, Preliminary Survey, Final Survey and Final Report.
5.2.2.1 Plannina The major planning phase milestones for program i 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, l and procurement, development and testing of i
~s 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.
1' 5.2.2.3 Preliminary Burvey l
The Preliminary Survey represents the transition from the development phase to the Final Survey Phase. The Preliminary Survey includes field testing of equipment and procedures through
! appropriate mockups and dry runs. Data collected l during the Preliminary Survey phase will be used to l aid in the overall final survey design and in the design of surveys of individual survey units.
i Termination survey quality control procedures will also be finalized in the Freliminary Survey phase.
l Preliminary surveys will not be conducted on all survey units. Rather, representative curvey units will be solacted.
5.2.2.4 Zin,Q t'grygy
( Final Survey measurements will begin when all l-
/ applicable prerequisites are met. These include use I
Program Descriptica .
P2 ion-01 Decommicsicateg T rwiectica survey Ray 1 P g3 19 af 26 of approved procedures (including Oc procedures),
(/7 work instructions and qualified technicians and
() acceptance of the area or system for Final Survey.
Final Survey measuraments mud ~certain Preliminary.
survey activities- may be performed concurrently throughout the facility in order to support the overall Decommissioning Project schedule. However, no tseasurements will be classified-as Final survey maanurements unisse applicable prerequisites are met.
5.2,.2.5 Final ReDort The Final Report phase includes completion of survey data evaluation, closure of survey data packages, preparation, verification and approval of release records and compilation of the Final Peport. Compilation of the Final Report will begin during the Final Survey phase.
5.2.3 Inteuration with Proiect Schedule Termination survey activities are included in the master project schedule including Preliminary survey activities and the Final Survey of each survey unit. Surveys will be scheduled to avoid conflict with decommissioning wdrk and fuel disposition activities.
~
5.3 Burvey Process 5.3.1 Summary A summary level schematic of the termination survey process is shown in Attachment 8.2. The. process is designed to allow Final Surveys to be conducted ' on selected survey units in parallel with decommissioning work elsewhere in the facility. Tho schematic shows the logic for accomplishing this.
5.3.2 Process Details A detailed view of the survey process is provided in Attachment 8.3. The schematic shows the principal activities, documents, and records produced.
5.4 Oraanization and Staffing 5.4.1 Orq1nization Chart A schematic of the termination survey organisation is shown in Attachment s.4. This shews the principal
( positions and reporting relationships in the termination survey organization. The organisation chart.shows the
Program Deceription PDIoMaol Decommissicaing Termination survey arv. 1 Pego 20 of 26
[ positions dedicated to the termination survey.
survey is managed by the Termination survey section Head The-who reports to the RCD Manager.
5.4.2 Staffine As shown in Attachment s.4, the Termination survey Section consistn of a full time staff of specialists.
This staf f will be supplemented, during field measurement activities, by personnel from the Health Physics section.
The survey measurements will be performed by qualified HP technicians. During the active measurament phases of the termination survey, several Lead Technicians will be assigned to the termination survey. They will supervise the Health Physics technicians assigned to work on the termination survey. Technician staffing levels will be adjusted as necessary to support the project schedule.
5.5 ggr. duct of OperatiotLS 5.5.2 Graanization Operations Conduct of termination survey organization and personnel management will be identified in applicable station management policies and procedures. Conduct of operations will be in accordance with applicable station policies k; and procedures.
5.5.2 Work Control Termination survey work will be conducted in accordance
! with applicable station work control procedure.s. curvey l maasurement, sample collection and instrument calibration will be controlled by Health Physics procedures, by Radiological Environmental Monitoring Program (REHP) procedures and by Termination Survey procedures. The station Maintenance Work Request (MWR) procedure will be used to request, document and control termination survey support work in the facility. The XER records shall serve as the primary method to document the final l
configuration of plant systar.s. To the maximum extent practicabla, survey 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 Encineerino sucDort Planning and conduct of the termination survey on systems will include consideration for the final
( system configuration requirements to support the facility. The extent to which a system (or a s
5
Program Deteriptir3 PDION-01 Decoussicciu2ico r:rminsti:2 surv:y arv. 1 P:go 21 cf 26
[ component) stust be restored - shril be determined p) during survey design. The need for 1'uture access to the system or a single component shall be determined in order thAt the impact on termination servey data validity can be assessed. Additionally, the survey design for a particular wystem survey unit . may require access to a point which is not achievable by i
dinassembly of mechanical joints. For systems which 4111 not be returned to a functional condition, engineering details will be provided for the necessary system disassembly. This may be accomplished through use of " generic" disassembly details. For systems required to remain functional, or where preservation requires full component or system integrity, _ additional engineering details will be provided to restore the system or component to the required condition. If actual configuration
, changes are made to piping systems or equipment l (other than restoring access flanges, covers, l joints, etc. to a " mechanic tight" condition), the l changes shall be documented on an Engineering Change
! Report (ECR).
5.5.2.2 Non-LIPA Assets Numerous components of the Shoreham f acility remain
(,] the property of the Long Island (LILCO). The termination survey Lighting company will be conducted
[V in such as manner as to preserve the value of such material to the maxicum extent practical. The l Dhoreham Salvage Division will review survey designs 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 necess,8ty for subsequent component removals.
5.6 Burvev Guality Assurance 5.6.1 Deconmissionina OA ProcIg3 The ternination survey is subjecg }o the provisions of the LIPA Quality Assurance Manual . Quality assurance is provided through oversight of the NQA Department.
Termination survey QA oversight will consi_st of review of Program docusents, program readiness assessments, (as discussed in Section 7.2 below), aad ongoing surveillance
( of program activities. Independent verification of final phase survey results will be performed under NQA 2
l v i
Program Descriptkb$ POIoN-01 Decomaiocienicg Torskastica survey REV. 1 Pcg3 22 of 25 Department surveillance and review of the release records.
5.6.2 Int &Ingl ProcI M 9Asurop..
Quality assurance is also provided through quality control elements built into termination survey program design and procedures. Termination survey QC procedures and methods w g be based on the principles outlined in NUREG/CR-5849 and the LIPA Quality Assurance Manual.
Termination survey program design includes provisions to ensure a high level of confidence that the f acility will natisfy 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 measuremen'.2, documentation of measurements and associated parameters, timely review of measurement results to identify anomalous results, and prompt attention to resolution of problems and discrepancies.
5.7 Termina1}on Survev_ Plan
( 5.7.1 Plan Contents The Termination Survey Plan provides technical guidance for conduct of the termination survey. It consists of an l expansion and upda g of Section 4.0 of the LIPA Decommissioning Plan . The Termination Survey Plan in controlled as a program document in a g rdence with the LIPA Nuclear Management Control Manual It covers the following topica:
Facility Background Information Site Information including Site Description and Condition at Time of the Final Survey survey overview including Objectives, contaminants, Organisation and Responsibilities, Training, Laboratory services, General Burvey Plan, Centative Schedule and Final Roport Burvey Plan including Instrumentation, Area Classification, Reference Grida, Surface Scans, Surface Activity Measurements, Exposure Rate Measurements, Goil/Bediment Bampling, Special Measurements, Background Level Determinations and sample Analysis
{
Progrea Descriptics P; ION-01 Deccammissiening Termiectics surycy krv. 1 P go 23 of 26
- Data Interpretation
-(-
Final Report 5.7.2 purvey Unfi classificattigjt The survey unit classification process is a major tool for planning and management of the termination survey.
The division of the facility into survey units and the l classification of those survey units will be controlled by station procedure. This allows for thorough review and approval while providing for limited revisions to the Termination survey Plan. The purpose of this i classification is to show the breakdown of site !
l structures, systems and areas into the principal survey l l units used to manage survey mansurement and data l l collection efforts. Each survey unit in then classified according to the potential for residual radioactive contamination. This classification guides the level of '
measurement intensity applied in the survey design.
Additionally, the survey design may further divide a ,
survey unit into survey subunits with the appropriate l classification given to each survey subunit. The classification for a survey subunit may indicate a lesser l j
potential for residual contamination than the survey unit l for which it is part, but in no caue will a survey j subunit be classified with a higher potential for i residual contamination. The survey Unit Classification ;
Description contains a listing of each survey unit which identifies its classification. It also includes a series of general arrangement (plan view) drawings by principal elevation of the major buildings. The drawings will show the individual survey units and their classification. The survey Unit Classification Description in the principal tool for communication of termination survey plans and interfacing with other decommissioning organizations to schedule survey activities.
5.8 procedures Many functions of the termination survey will be conduated under SNPS .Haalth Physics, Radiochemictry and Radiological Environmental Monitoring Program procedures. These include l operation and calibration of survey instruments. In addition, several processes unique to the Termination survey section have been identified and will bi controlled by procedurea.,
Termination survey procedures will be prepared in accordance with approved procedures for preparation, issuance, control and revision of Health Physics procedures. Topics which will be addressed in termination survey procedures include (but are not limited 1:
( ..
Decoent:siccicg T:rmiceties survcy Rgy. 1 P:g2 24 cf 26 conduct of survey operations History files V[] Release records survey measurerent quality control survey Unit turnover for Termination survey Isolation a control of Termination survey survey Units survey data receipt and managament Document control and m.anagement survey Unit classification 4 Background determination and documentation 5.9 werk Instructions 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 gr.g npA used in caser where data integrity is affected.
Examples are tasks performed by a 11mited number of personnel, 4 tasks which may change fairly fs aquently or which may be g
performed for a limited periode and tasks for which only general guidance is required. Work instructions are not used to introduce new tasks or to orpand 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.
INTERFACES 6.0 Principal programs and procedures that interface with the termination survey are identified below.
6.1 Ouality Assurance LIPA Quality Assurance Manut.1 LIPA Quality Assurance Procedures 6.2 J0ecommissionino DepartigaL.
PDIDD-01 Dettommissioning Program Description 6.3 Work control SP 12Z010.02 Station Modification Activities BP 12X011.01 Station Equipment Clearance Requests
Program De:Orlptics -P! ION-01 Decommi0sisning Termisation Sury y REV. 1 P ga 25 sf 26 SP 12X012.01 Radiation Work Permits EP 12I013.01 Maintenance Work Requests 6.4 Rafsty Prggran.
Shoreham site safety Manual 6.5 Fire Protection PDINE-11 Fire Protection Program F1I500.01 Organisation and Afrinistration of Fire Protect. ion Program SP 12I500.01 Fire Protection Program Description 6.6 Security Plan 6.7 Fyelear Enoineerina Radiological Environmental Honitoring Program (REMP)
PDINE-01 Intrim Management Control Program for Station Modifications NEIO1-03 Preparation, Revision & Approval of EEDCAs & ECRs 7.0 PROGRAM EVALUATION *
{ 7.1 Routine Feedback The RCD Manager is responsible for maintainir.g 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 problams that have arisen during the period, and ensure that this program is revised as necessary.
7.2 Periodic Evaluation Periodic evaluations will be perfortaed on the basis of aajor project milestones or other changes which could impact the program. The first comprehensive review of the program is planned prior to initiation of final survey phase measurements. This will be performed by the LIPA Nuclear Quality Assuranne Department with the assistance of outside technical experts who are experienced in decommissioning j surveys.
( _,
C l
.. . - . . ~.. . . _ . . -. - . .. .. ...
Program De:criptics'- .
,p; ION-CI-
- Decessissiccirg T : alm.tica Survey. -
- asy. ; l' Figs.26 ct 26:
M : S.o- ArrACEMENTS
~
)
-)
8.1' griteria for Release'of shorehan Ituclear Power'3tation.
for Unrestricted Use-Pollowino Decommissioning 8.2 Terminat. ion Survev: Process Summary _
S.3 feraination-Survey' Process Datails ,!
1 S.4 Tirmination Surv3v Oraanisation Chart ~ j l
, 8.5 Termination- Survey Final Report- Outline !
1
- I
-I l
ll l
. s 4
I a
I l
l 1 L I i
l
(
l 1
I a
in
'< sw--as v.rhy.-ns*g a .m. I
. _= .- - - . - -
LONG ISLAND POWER AUTHORITY Criteript orf Release of Shpfjsham_ Nuclear PQwer_Btatisj}
for UnrgjeirJcted Use Follgyino Decommf AR12hiA9_
1.0 Summary This document sodresses criteria for termination of the U. 8.
Nuclear Regulatory Comminsion license for Shoreham Nuclear Power Etation. A major condition for termination of the license is demonstration that the facility and the site are suitable for unrestricted use . Principal crite.ria for release g the facility are identified in the Eborcham Decommissioning Plan . These aret Limits for residual agf ace contamination levels contained in Regulatory Guide 1.SG . and A limit frr gamma radiation exposure rate established by the NRC staffa 5 micgR/hr above background measured at one meter from the surface )
1 cuidance for application of these criteria to nuclear power reactor l facilities is not clearly spelled out in approved regulatory !
documents. Criteria have not been established for volume l concentration limits on residual activity in building materials, equipment and soils. Due to factors which vary, such as the mix of g 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 V application to the Shoraham Facility.
! The following implementation principles are adopted to ensure that l the criteria are satisfied and the demonstration is properly j documented i
- 1. 1 The app)icable 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 maxigu;g acceptable levels. Reasonable efforts will be made to eliminate residual contamin:< tion, i.e. to reduce levels well below these limits.
l This document applies to structures and equi ,ent I remaining fixed in place at the facility. All items to_ be I removed from the facility which are potentially centaminated will be surveyed using shoreham Nuclear Power Gtation Procedures. All items found to be contaminated will be packaged and shipped as radioactive materials for proper disposition (disposal or re-use
{ under an appropriate radioactive materials license).
PDIOM-01 aev. 1 Attachment 8.1 (Page 1 of 7) l
1.2 Batisf action of the faci ~1ity release criterin vill be demonstrated by a comprehenkive radiation survey program.
This program, called the Termination survey Program
\ includes preliminary and final survey phases. The Termination Survey Program i gazed upon Section 4.0 of the LIPA Decommissioning P1 1.3. All areas subject to the facility licenso, and particularly those involved in or impacted by decommissioning activities are subject to thorough confirmation surveys pric to acceptance for termination survey. Areas not meeting the release critaria must be remediated and reconfirmed prJar to acceptance for the Termination Survey.
1.4 Determination that each defined survey area sat.i.sfies the release criteria is based on an evaluation of all relevant information, including operational history, site characterication data, decommissinniary records and confirmatory and termination survey measurements. This information will be complied into a standardized format called the release record. The release record will 3se prepared by the Termination survey section.
1.5 The final determination by the long Island Power Authority (LIPA) that an arer. sat!.sfies the release
, criteria will be made based upon an independent review of
( the release record. This review will be performed by
(^ designated individuals w.' thin the LIPA Organitation who i
t .
are independent from the Termination Survey Section.
1.6 Quality control (QC) measures will be applied to the
! Termination Survey Program to ensure the integrity of the l data and the accuracy of l
survey results. Survey procedures will incorporate quality control provisions.
External QA oversight will be provided by the Shoreham Nuclear Quality Assurance Department.
2.0 Discussion 2.1 R.e uulatorv Guide 1.86 33 glance contamination Tinits Table 1 of Regulatory GuMe 1.861 2 .idantifies acceptable contamination levels which must be satisfied for f acilitirsa to be released for unrestricted use. Table 1 limits urs established for four radionuclide groups classified on the basis of potential biological risk.
These limits are specified as levalg above background.
l
( The shoreham Characterization study , determined that f radionuclides in plant structures and systems (in-situ activation and surface contamination) are confined to PDIOM-01 Rev. 1 Attachment 3.1 (Page 2 of 7)
l boto-g p amitters. Thus, tho follcwing Tablo 1 limita j OPPl.Y8
, m. waximum fimod plus removable;a 15,000 disintegrations per minute (opr per 100 cu , (within an area no greater than 100 cm)) .
b., Average fixed plus removable; 5000 dpa per 300 cm , (averaged over an area no greater than one m ) .
2
- c. Removable; 1000 dpm per 100cm ,
Areas afhare contamination by alphe-emitters is a potential as a result of removal of the nuclear fuel from the facility shall be demonstrated to be released at limits levels for gross alpha. pumerically equal to the above Surface 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 comprismo primarily of Ni-63 and Mn-54. In radia. tion survoys to evaluate surface beta-gamma leve h., co-60 contributes about 99 per cent to the detector response, with the remaindor due largely to Mn-54. Fe-55 and Ni-63 are not detectable with typical survey instruments. In determining faci.lity surface contamination levels at Shoreham for evaluation against Regulatory Guide 1.86
%ble 1 limits, the activity due to Fe-55 and Wi-63 is not included.
O 2
Regulatory Guide 1.86 defines beta-gamma emitters as
nuclides with decay modes other than alpha amission or spontaneous fission." Certain other beta-gamma emitters are specifically excluded from this category in the Table, e.g., Sr-90 and Iodines. These are listed in a more restrictive category which includes isotopes of Th, U, and Ra.
3 The Shoreham 8 pent Fuel Pool has not been characterised due to the presence of the spent fuel. When the pool is emptied, a radiological characterization will be performed and the appropriate limits from Regulatory Guide 1.06 Table 1 will be applied based upon the radionuclidec found to be present.
PD30M-01 Rev. 1 Attachment 0.1 (Page 3 of 7)
A 2.2 Gamma Exposure Rate Criterion The L microR/hr (above background) at one water exposure
( -rato critarion applies to radiation fields produced by
/3 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) is not readily measurable with portable field instrumentation, however. A commonly accepted practice in facility termination sur'ays is to use sensitive rate meters (usually scintillation detectors) calibrated to measure absort ad dose rate (rad units).
At shoreham, an appropriately calibrated pressurised ion I
chamber (PIC) vill be used as the reference instrument for measuring gamma exposure rates. For convenience, ,
other instruments such as scintillation rate meters will be used for the majority of measurements. correlations will be established between scintillation detectors and i the PIC for determining compliance with the 5 microR {
(above background) criterien. Since gamma radiation !
fields from contamination and neutron activated materials I at Shoreham are dominated by Co-60, instruments will be )
calibrated with co-60 or sources with comparable gamma l energies.
2.3 Demonstration that Doses from Rolldual Activity are ALARA l V The numerical limits on surface contamination and gamma
~D exposure rate described e.bove are chosen so that the (d radiation risk to individuals is negligible regardless of conditions of use or occupancy of the facility.
l At present no regulatory consensus has been reached for determining acceptable radiation doses from residual activity from decommissioned facilities. The U. 8.
Nuclear Regulatory Commission (NRC) staff has stre.tsd that the 100 millirem (total ef fective dose equivalent) per year limit for members of ge public in the recently
$ssued 10CFR20 regulktiogs will be applicable to decommissioned fucilities #'3'7 This is clearly a regulatory maximum limit and does not constitute an ALARA level. The NRC staff has proposed that 10 millires to an individual, (the so called maximum exposed individual) be used as an A!. ARA benchmark for evaluetion of decommissioned liennsed facilities. However, this matter is still under review and is the subject of a proceeding to develop an interagency consensus between the NRC the Envirogental Protection Agency and' the Department of Energy Radiation doses have been calculated for post-decommissioning facility occupancy and use scenarios at
( shoreham. These have been calculated using methods under
N
[V PDIOM-01 Rev. 1 Attachment 8.1 (Page 4 of 7)
dovolopacnt by tho U. S. NuclCar Rcqulatory CommiCoica for purpocco of ovaluating fooilitico containing Icw levels of radioactive maf rial in buildings and soil following decommissioning
(
[
b Doses were calculated which result from total surface contamination levels (fixed plus removable) equal to 5000 j
dpm/100 cm (from the Regulatory Guide 1.86 Table 1 limits identified in Section 2.1 above). They were calculatedforamixtureofradionuclidesf"dentifie6in the Shoreham site Characterisation Study . In this pathway analysis, the isotopic composition of facility residual contamination was inferred from neutron activation analysis results, from smear sample aanlysis and from environmental sample results. For this base case, the ccatributions of co-60 and F6-55 are assumed to be present in roughly equal proportions, comprising about 90 per cent of the total activity. The resultant doses 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 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 f.ontatination in the Termination Survey' at I< Shoreham. As expected, the resulting calculated doses
] are approximately twice the base case resulta, yielding about 6 millirem per year to the maximum exposed individual.
The results summarised above represent conservativa uppcr limits for doses expected from unrestricted use 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 Guide Table 1 limit values throughout the facility. It is expected that actual residual activity levels will be much less than this.
2.4 Befidual Radioactivity Concentrations in Buildin(2 Naterials and Soil Release limits have not been established for residual radioactivity concentrations in building materials gd soil for decommissioned nuclear reactor facilities .
Acceptability of building materials (e. g., neutron activated concrete), and coil containing residual radioactivity at Shoreham will ba detsrained primarily by
, satisfaction of the 5 microR/hr above background
( criterion. That is, the ganma exposure rate measured at PDIOM-01 Rev. 1 Attachment 8.1 (Page 5 of 7) i
eno cotor fr a tho curfcco of collo cr building matcriolo ch311 b3 1Cs0 th n 5 CicrCR/hr Obov3 th3 backgr;und radiation exposure rate.
I 2.5 Residual Radioactivity in Systems and EcViDuent surface contamination on plant systsas and oguipment lef t in place in the facility will be evaluated against the Regulatory Guide 1.86 Table 1 limits ' identified in section 2.1 above. Gamma radiation fields fron-surface contamination and neutron induced gamma emitters in equipment must also satisfy the 5 microR/hr (above background) criterion. The gamma fields will be evaluated in locations (at one meter from surfaces) that are considered to be readily occupiable. Accessible equipment and components will be removed if contamipation levels cannot be reduced below 5000 dpm per 100 cm fixed plus than removap)le one m andactivity below (averkged over100 1000 dpa per an cm' arearenovable no larger activity, contamination levels of up to 15,000 dpm fired plus removable vigl be acceptable in localized araas (less than 100 cm ) that are not readily accessibic, e.g., within piping buried in concrete or localised areas in large fixed components such as heat exchangers or tanks.
2.6 p_glermination of Backcround Radiation Levels The criterie for release of the facility for unrsstricted use are all specified as levels above background.
Background count rate or dose rate levels (as the case 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 G6 cay processes, srrors and uncerthinties in instrument responses, and errors inherent in measurement processes combine to produce uncertainties in measurements of background and in measurements of residual activit','. The l magnitude of the uncertainty -associated with these l measurements is in some cases comparable to the average values of a series of measurements. Thus it becomes l
essential to identify and properly account for the background (and its variation) for each type of measurement.
l Backgrounds for each of the types of measurements and instruments used in the Termination Survey will be determined. MeasureAents will be made of background in a manner that eliminates possible contributions from
! Shoreham facility residual activity. The contributio; of ,
building natorials of constructic' will be evaluated.
Sufficient measurements will be taken to obtain valid l statistical characterizations of background.
?
o l
PDX0M-01 Rev. 1 Attachment 8.1 (Page 6 of 7) l
3.0 Roforoncoc (A 3.1 Long Island Power Authority, " Decommissioning Plan for Shoraham Nuclear Power Station", December, 1990, as amended.
3.2 U. S. Atomic Energy Commission, Regulatory Guide 1.86,
" Termination of Operating Licenses for Nuclear Reactors",
June 1974.
3.3 U. S. Nuclear Regulatory Commission, " Final Generic Environmental Impact Statement on Decommissioning of Ituelear Pacilities", NUREG-058G, August, 1988.
3.4 Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterisation Program Final Report" May, 1990, (with addenda; June, 1990, October, 1990).
3.3 U. S. Nuclear Regulatory Commission, 10CFR Part 20,
" Standards for Protection Against Radiation; Pinal Rule",
Federal Register, May, 21 ,1991.
3.6 J. C. Malaro, U. S. Nuclear Regulatory Commission,
" Residual Contamination Criteria for Decontamination of Nuclear Facilities", presented to the Health Physics Society Thirty Sixth Annual Meeting, Washington, D. C.,
. July 1991.
3.7 R. A. Meck, U. S. Nuclear Regulatory Commission, " Status Report on Establishing Decommissioning Criteria",
presented to the Health Physics Society Thirty Sixth Annual Meeting, Washington, D. C., July 1991.
3.8 W. E. Kennedy and R. A. Peloquin, " Residual Radioactive contamination from Decommissioning," Prepared for the U.
S. Nuclear Regulatory Commission, NUREG/CR-5512, Draft January, 1990.
3.9 H. Deer et. al., "Shoreham Nuclear Power Station Post-Decommissioning Dose Pathway Analysis Report", Long Island Lighting Company report to Long Island Power Authority, Draft, August 1991, h
C PDr. fit-01 Rev. 1 Attachment D.1 (Page 7 of 7) l
Termination Survey Process Summcry Division of facility f, into Survey Units 1P Tes Affected No by Decormt.
Activiiles il y Decommissioning
.ctivities Completed
(....... .........
Operational Remediallon (Confirmatlon)
(Removal and/or Radiation Decor.tamination) survey di Area he meets Acceptance si Criteria I. ?
b
\ 'M v.s Release Survey Unit for Survey qr Isolate Area /
Control Access U
Terminat ion -
Survey Review Survey Data Area No meets release criterla 1
,Y e s Isolate Area / '
Control Access frg 18/t3/92 a plotest
~j j T ere*2 e
j l. Prccess cescribec for individual survey unit.
- 2. Operational (confirmation) surveys performed on selected areas.
PDIOM-01 Rev. 1 Attachment 8.2 (Page 1 of 1)
. Tormination Survoy Process Dateiis Sureer Unit /
$ubunit- Inittel Pitng Cicssified' 4 Classification W Character.
lastion JL
\ -
Detailed 4----
Evaluation Operational History 8 Radiological l' $urveys Estory ' Prepare File History File Decceeniss ioning Activilles-Completed Y
Place on Survey Schedule Y
Operational Updated 4 History (Confirmation) Remediation Survey l File I 1r Unit Turnover for Termination
$urvey i
.f I
Isolate, i
l , Control Access ir Preilminary Survey Data Processing Perform Data Report 4 and Analys6s 4 -- Prelim Survey I (cptional) (optional)
,' i .
Final Survey Finst Design M Survey Instructions final ir Survey Data Report g i Data Processing Perform l' 4 and Analysis ; Final Survey
- l. ->
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' Prepare Isolate,
. Release Record Verify P
Independent
(- Release Record - 4 Review and Approval of Release Record 14/13/92
'Tersw3 PDION-01 'Rev. 1 Attachment 8.3 (Page 1 of 1) ;
3
1---
Termination Survey Organization Chart I
Manager Radiological ControlsDiv.
I 8
Termination HP Engineer ........................... Survey Section Head l
l l Termination l Survey l Engineer l
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i l Rad. Engineer Rad Engineer Rad Engineer RadEngineer l CAD, Graphics Data,instrum'n Systems Documentation l
i l
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! I Survey RadEngloeer(s) Database Data Supervisor (s) Survey Programmer Clerk l
Survey Technicians 9/21/92 Terma4 O
PDIOM-01 Rev. 1 Attachment 8.4 (Page 1 of 1) I
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( TgIpination survey FID31 Report Outline v
Bhoreham Nuclear Power Station Decommissionine Termination survey Final Report 1.0 Background Information 2.0 Site Information 2.1 Site Description 2.2 Bite conditions at Time of Final Survey 2.3 Identity of Potential Contaminanto and Release Guidelines j 3.0 Final Status Survey Overview 3.1 survey Objectives 3.2 _ Organization and Rasponsibilities 1
3.3 Instrumentation 3.4 Burvey Procedures '
['i 3.4.1 Area classification
(_/
3.4.2 Reference Grids 3.4.3 Burface Scans 3.4.4 Surfacs Activity Measurements 3.4.5 Exposure Rate Measurements 3.4.6 Boil / Sediment Sampling 3.4.7 Special Measurements and Samples 3.5 Background Level Determinations 3.6 sample Analysis 3.7 Data Interpretation 3.8 Records 4.0 survey Findings and Results
{ 4.1 Background Levels O
PDIOM-01 REV. 1 Attachment 8.5 (page 1 of 2)
f; Termination Survey Final ReDort Outline ig 4.2 Building Surveys 4.3 Grounds Surveys' 4.4 System Surveys 4.5 Data Evaluation 4.6 Residual Activity Inventory 5.0 summary 6.0 ADDendices The final!;eport will contain appendices of supporting data.and information which include the following:
6.1 Tabulated Results for Individual Sur rey Units 6.2 Survey Map Index 6.3 Survey Procedures 6.4 Data Processing 6.5 Statistical Methods 7.0 Attachments The Release Record for each Burvey ULit or a summary of each'will ,
- be included as attachmaats to the final report.
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4 w.s NUCLF.AR ORGANIZATIONMANAGEMENTCONTROLPROGRAMMANUAL p>Dcny3 q3ygp;p hen, PR OGRAM DESCRLPTION WUMENT CHANGE NOTICE satgy L og ATTECTED DOCUME:
PDX0M-01, Rev. 1! Decommissionin;; Termination Survey Program Description ,,
(2) DE5CMPTION OF CHANGE (5): g ,-
a) Add section 5.7.2 entitled Plan Revisions to provide O /~~ E ~ O a method for administering changes to the Termination .
Survey Plan.
b) Add Attachma.nt 8.6' Termination Survey Plan Document
- Change Notice.
' #E "'
c) Provide updated Table of Contents. t d) Provide re-paginated pages of Revision 1. 4 I -
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4 Program Des':riptira '
PD-DCN NO93X003 PDIOM-01 Decommissir.itg Termitotica servcY REV. 1 SHEET Q. OTLP :ge 2 cf 26 5.2.3 Intecration with Proiect Schedule . . . . . 19 f- 5.3 Eurvey Proce;g . . . . . . . . . . . . . . . . . . 19
( ) 5.3.1 Egnatly . . . . . . . . . . . . . . . . . . . 19
's ' 5.3.2 Process Details . . . . . . . . . . . . . . . 19 5.4 Orcariigtion z and Staffing . . . . . . . . . . . . . 19 5.4.1 Draanization Chart . . . . . . . . . . . . . 19 5.4.2 gtaffinc . . . . . . . . . . . . .. . . . . . 20 5.5 Conduct of Operations . . . . . . . . . . . . . . . 20 5.5.1 Orcanization Operations _ . . . . . . . . . . 20 5.5.2 Work Control . . . . . . . . . . . . . . . . 20 5.5.2.1 Encineerina Support . . . . . . . . . . 20 5.5.2.2 Non-LIPA Assets . . . . . . . . . . . . 21 5.6 Eurvey Ouality Assurance . . . . . . . . . . . . . . 21 5.6.1 Decommissionino OA Procram . . . . . . . . . 21 5.6.2 Internal Procram Measures . . . . . . . . . 22 5.7 Termination Survey Plan . . . . . . . . . . . . . . 22 5.7.1 Plan Contents . . . . . . . . . . . . . . . 22 5.7.2 Plan Revisions . . . . . . . . . . . . . . . . 23 j 5.7.3 Survey Unit Classification . . . . . . . . . 23 l 5.8 Procedures . . . . . . . . . . . . . . . . . . . . 24 l 5.9 Work Instructioha . . . . . . . . . . . . . . . . 24 6.0 INTERFACES . . . . . . . . . . . . . . . . . . . . . . . 25 6.1 Ouality Assurance . . . . . . . . . . . . . . . . 25 6.2 Decommissioninc Department . . . . . . . . . . . . 25 6.3 Work Control . . . . . . . . . . . . . . . . . . . 25 6,4 Eg(aty Proctam_ . . . . . . . . . . . . . . . . . . 25 6.5 Fire Protection . . . . . . . . . . . . . . . . . 25 9, 6.6 6.7 Security Plan Huclear Engineering _
25 25 1
7.0 PROGRAM EVALUATION . . . . . . . . . . . . . . . . . . . 26 l 7.1 Routine Feedback . . . . . . . . . . . . . . . . . 26 7.2 Periodic Evaluation . . . . . . . . . . . . . . . . 26 8.0 ATTACHMEHIE . . . . . . . . . . . . . . . . . . . . . . 26 8.1 Criteria for Release of Shoreham Nuclear Power Station for Unrestricted Use Fol)Jtinq j Decommissioninc . . . . . . . . . . . . . . . . . . 26
! 8.2 Termination Survey Process Summary . . . . . . . . 26 8.3 Termination Survey Process Details . . . . . . . 26 8.4 1ermination Survey Orcanization Chart . . . . . . . 26 8.5 T4rmination Survey Final Report Outline . . . . . . 26 l 8.6 Termination Survey Plan Document Chance Notice . . . 26 l l
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9 Progrr.c Description 'N PDIoN-01 Deromaissiccing Torminatica survoy SHEETLOFg ggy, 3 Page 23 of 26
( -
Data Interpretation A
Q -
Final Report 5.7.2 Plan Revisions Revisions to the Termination Survey Plan may be originated by any appropriate department within LIPA.
Proposed revisions shall be directed to the Termination Survey Section for processing. The Termination Survey Section Head shall be responsible for coordination and resolution of all proposed revisions to the Termination-Survey Plan.
Similar to LIPA program descriptions, minor (non-programmatic) inaccuracies do not necessitate revision of the Termination Survey Plan. These changes shall be documented on a Termination Survey Plan Document Change Notice (TSP-DCN) and shall be incorporated during the next Plan revision. For major changes-to the T9rmination Survey Plan, the Termination Survey Section Head shall determine whether the Termination Survey Plan is to be revised or if a TSP-DCN is to be issued.
Attachment 8.6 provides che Termination Survey Plan f Document change Notice form. Plan revisions and TSP-p DCN's are administered in the manner prescribed for T program description revisions and/or DCN's in Sect (Q 5.6.4 of the LIPA Nuclear Management Control Manual. g 5.7.3 Survey Unit Classificat_ ion The survey unit classification process is a major tool for planning and management of the termination survey.
The division of the facility into survey units and the classification of those survey units will be controlled by station procedure. This allows for thorough review and approval while providing for limited revisions to the Termination Survey Plan. The purpose of this classification is to show the breakCown of site structures, systems and areas into the principal survey units used to manage survey measurement and data collection efforts. Each survey unit is then classified according to the potential for residual radioactive contamination. This classification guides the level of measurement intensity applied in the survey design.
Additionally, the survey design may further divide a survey unit into survey subunits with the appropriate classification given to each survey subunit. The classification for a survey subunit may indicate a lesser potential for residual contamination than the survey unit for which it is part, but in no case will a survey subunit be classified with a higher potential for C[)
PD-DCN NO,93X002 ~
Program Descriptica SHEETiOFj~ PDroM-01 Decommissicaiag Termin2tien survey REV. 1 Page 24.of 26 h residual contamination. The Survey Unit Classification Description contains a listing-of each survey unit which identifies its classification. It also includes a series -
of general arrangement (plan view) drawings by principal elevation of the major buildings. The drawings will show the individual survey units and their classification. The Survey Unit Classification Description is the principal.
tool for communication of termination survey plans and interfacing with other decommissioning organizations to schedule survey activities.
5.8 Procedures Many functions of the termination survey will be conducted under SNPS Health Physics, Radiochemistry and Radiologicki Environmental Monitoring Program procedures. These include operation and calibration of survey instruments. In addition, several processes unique to the Termination Survey Section have been identified and will-be controlled by procedures.
Termination survey procedures will be prepared in accordance with approved procedures for preparation, issuance, control and revision of Health Physics procedures. Topics which will-be addressed in termination survey procedures include (but are not limited to):
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 Background determination and documentation S.9 Work Instructions Work instructions are used to describe and control processes which require some degree of standardization but less control than processes controlled by procedures. Work instructions AT& Ap1 used in cases where data integrity is affected.
Examples are tasks performed by a limited number of personnel, m tasks which may change fairly frequently or which may be 4
Program Descriptito PD-DCN NO,93X002 Decommicsiccing Cermi20tica survey ' SHEET 1 0F 1 ~ ' ggy, 3 Page 25 of 26
-(. performed for a limited period, and tasks for which only
/ ~N 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 IJ{TERFACES Principal programs and procedures that interface with the termination survey are identified below.
6.1 ouality Assurance LIPA Quality Assurance Manual LIPA Quality Assurance Procedures 6.2 pecommissionino Department PDXDD-01 Decommissioning Program Description 6.3 Work Control SP 12X010.02 Station Modification Activities SP 12X011.01 Station Equipment clearance Requests SP 12X012.01 Radiation Work Permits -
SP 12X013.01 Maintenance Work Requests 6.4 Bafety Procram i
Shoreham Site Safety Manual l 6.5 Fire Protection PDXNE-11 Fire Protection Program F1X500.01 Organization and Administration of Fire Protection Program SP 12X500.01 Fire Protection Program Description 6.6 Security Plan 6.7 Nuclear Encineerina Radiological Environmental Monitoring Program (REMP)
PDXNE-01 Intrim Management Control Program for Station Modifications NEXO1-o Preparation, Revision & Approval of EEDCRs & ECRs l l
[v3
____-_________-__=___-.
.,J.-.
Progre.a DescripO cn PD-DCN NO.93X002 Pem 01 Desommicsicaing Torminatica-survoy SHEET 10F7 arv. 1 Page 26 of;26-7.0 PROGRAM EVALUATION 7.1 Routine Feedback The-RCD Manager is responsible for maintaining this program-description. He may delegate this r e s p'o n s i b i l i t y l t o 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 arisen during _ the . period, and ensure that - this program is revised as necessary.
7.2 Periodic Evaluation Periodic evaluations will be performed on the basis of major project milestones or other changes which could impact.the program. The first comprehensive review of the progrsm is 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 i surveys. _j 8.0 ATTACHMENTS 8.1 Criteria for Release of Shoreham Nuclear Power Station for Unrestricted Use followinc Decommissioninc l 8.2 Termination Survey Process Summary 8.3- Termination Survey Process Details 8.4 Termination Survey Orcanization Chart 8.5 Termination Survey Final ReDort Outline 8.6 Termination Survey Plan Document Chance Notice b
- - ,---.i** mast.svo ;t SllEE Q OF 1 01,?a TERMINATIONSURVE PL4N Tsp-DCu no.
snEET W f'L" w -DOCUMENT CHANGE NOTICE OF (1) AFFECTED DOCUMENT: -
(2) DESCRIPTION OF CHANGE (S): : tmetan e.ar
/
(4) ORIGINATOR OF CHANGE: DATE:
(5) RESPONSIBLE MANAGER: DATE:
(6) CONCURRENCES OF AFFECTED MANAGERS APPROVED: DATE:_
.f Attachment 8.6 (Page 1 of 1) 3.=ensowouq,pefuwp1=ge=> --
Termination Survey Report for Turbine System (N31)
APPENDIX D. TERMINATION SURVEY PLAN s,
b