ML20155G951

Rev 1 to M01-1258-002, Decommissioning Cost Analysis for Myaps

ML20155G951
Person / Time
Site:	Maine Yankee
Issue date:	10/31/1997
From:	Cloutier W, Palmer C, Seymore F External (Affiliation Not Assigned)
To:
Shared Package
ML20155G948	List: ML20155G945 ML20155G951 ML20155G959
References
M01-1258-002, M01-1258-002-R01, M1-1258-2, M1-1258-2-R1, NUDOCS 9811090266
Download: ML20155G951 (150)

Text

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Document .Vo. M01-L?58-002 4

DECO 3DIISSIONING COST ANALYSIS for the MAINE YANKEE ATOMIC POWER STATION Y )

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M:ine Yankee Atomic Power St: tion Document M01-1258-002, Rev.1

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i Decommleeioning Cost An lysis Pag 2 licfxit 2

APPROVALS Project Manager AAb /o 38 f7 )

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• A. Clouti , fr. Date Technical Manager - . . - *v .m _- /0[27M> '

Ddte Francis W. Se@re Quality Assurance Manager b46dh Caroly/A. Paimer

/e/27/97 Date '

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Maine Yankee Atomic Pzw:r Sention Document M01-1258 002, Rev.1 l Decommissioning Ccst Andysis Pag 2 liiefsit t

TABLE OF CONTENTS I -

i- l l2 SECTION-PAGE 4 1

EXE CUTIVE S UMMARY .... .. ... . . ... . ....... . .......... ..................... ......... ...... .... ... .. .... vii-xii

1. INTRO D U CTIO N . . .. .. .. .. . .. . .. . . . . . . . . . . . . .. . . . . . . . . . . . .... ....... ....... . . . . . . . . . . . .. . . . . . . . . . . . . ... . . . . . . . . . . . 1 1 1.1 Objective of S tudy.. . ......... .. . . ... ....... ... . . ................ ...... . ..... ...... ..... . .. .......... . ... .. . 1 1 l' 1.2 Site Descrip tion ...... ..... . . . . . . . . . ..... ...... . ..... ...... ............... . ........ ... ...... ........... . ... .. 1- 1

1. 3 Re gulatory G uidance .. .. . . . . .. . ... .. . . ... ... . . . .. .. . ...................... ...... ... .. ....... ...... . . .. . .. 1-2 1.3.1 Nucle ar Waste Policy Act .................................................................. 1.-4 l 1.3.2 Low. Level Radioactive Waste Policy Amendments Act ..................15 i

l 2. DECON DE COMMISSIONING ALTERNATIVE .............................................. 2 1 2.1 Pe riod 1 - Prep aratio ns .. . .. . . ... ....... . . . .. . . . . . . . .... .......... ... ...... .... . .... . . . ... . . . .. . .. .... .. 2 2 l

2.2 Period 2 - Decommissioning Operations & License Termination .............. 2 5 2.3 Final Site Survey - License Termination..................................................... 2-7 l

2.3.1 NRC Criteria for Decommissioning .................................................. 2 8 l

2.3.2 NRC Decommissioning Process and Survey Procedures................. 2-9 2.4 Pe riod 3 S ite Re storation .. ............ . .......................................... ................ 2- 11 2.5 Post-Period 3 - ISFSI Operations and Demolition .................................... 2 12 l 3. C O ST E STIMATE . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .

l l 3.1 B asis o f E s tim ate . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . .. . . .. . . . . .. . ... . ... . . ... . . ... . . . . . . .. . . .

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3. 2 M e t hodolo gy . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.3 Financial Components of the Cost Model .................................................... 3-4 l

3. 3.1 Co ntin ge ncy . . . .. . . . . . . . . . . . . . . . . . .. . .. . .. .. . .. . . . .. .. . . . . . . . . .. . . . . . . . . . . .. .. . .. . . . . . . . . . . . . . . . . .. . . 3-4  !

3. 3.2 Financial Risk . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .. . . . . . . . . . .. . .. . . . .. .. . . . .. .. .. ... . . . . . .. . . . . . . .. .. . . . . 3 3.4 Site-Specific Co nsideratio ns ......................................................................... 3-9 3.4.1 Spe nt Fuel Disposition ..... . .. . .. ........ . ................................. ............ ....... . 3-9 3.4.2 Reactor Vessel and Internal Components ........................................ 3-10 3.4.3 Steam Generators and Other Primary Coolant System Components 3-10 3.4.4 Main Turbine and Conde nser............................................................ 3 11

3. 4. 5 Transp orta tio n Me tho ds .. . . . . . . .. . . . . . . . . . . . . . .. . . .. ... . . . .. . . . .. . . . .. . . . . . . . .. . . . . . . . .. . . . 3- 1 1 3.4.6 Low Level Radioactive Waste Disposal and Recycle ....................... 3-12 3.4.7 Site Conditions Following Decommissioning ................................... 3-12 3 . 5 As s um p tio ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3. 6 Co st Estim ate S um m ary . . . . ... . .. . .. .... . .... .. .. . .. . ..... .... .. . . .. . .. .... .. .... . ... ... . .. . . . .. . . . . 3- 18 p

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Mdne Yankee Atomic PawwSt tion Document M01-1258-002, Rev.1 Decommineioning Cost An: lysis Pag 2ivcfxil  !

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TABLE OF CONTENTS

. (continued) l l SECTION-PAGE U

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4. SCHED ULE ESTIMATE . ... ................................ .......................... .. .. . .................. 4 1 l

4.1 Schedule Estimate Assumptions .................................................................. 4-1 4.2 Project Sched ule .. ... ..... ............ ........ . .. . ..... ........ ................. ........ ... .... ........ . .. .l. 42 i

l 5.' RADIOACTIVE WASTES ..................... ........ . .. . . ...................... ............. .. . ........ . ... . 5- 1 1 r

l 6. RESULTS...............................................................................................................6-1

7. RE FE RE N C E S . . . . . .. . . . . . . . .. . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. ... . . . . . . . .. .. . . . . . . . . . . . . . . . ... . .

TABLES 1

Summary of Major Contributors to the Cost of Decommiasioning..................xii i 3.1 Schedule of Decemmissioning Expenditures................................................ 3-20 l 5.1 Decommiasioning Radioactive Waste Burial Volumes .................................. 5 3 l

6.1 Summary of Major Contributors tc the Cost of Decommissioning................ 6-5 FIGURES 4.1 D eco m missio ning Activity Sche d ule .. . . . . .. . . . . . .. . . . . . . . ... .. . . . . .. . . ... . .. . . . . . . . . . . .. . . . . . . . . . . 4 3 l 4.2 Deco mmissic n i n g Timeline ...... .... .. . .. . . . . . . . . ... ..... .. .. .... . .. ... ............... .. ......... .. . . 4- 10 5.1 Low Level Radioactive Waste Processing Flow Chart .................................. 5-4 l

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APPENDICES A. Unit Cust Factor Develop me nt ............... .... .... . ... . ... ... .. ................ ..... .... .................... A- 1 B . Unit Co s t Fa :to r Lis tin g .. ... . ... ... . ... . . .. .. . . . . . . . . . . . . .. . .. . . .. . . . .. . . . . . . . . .. . . ... .. .. . . . . . .. . . .. . . . .. . . . . . . . B- 1 l

O. De taile d Cos . Analysis . . . . .. . .. . ... . .. ... ...... . . . . . . . . . . . . . .. . . . .. . . . . . ... .. . . . . . .. . . . . .. . . . . . . . . . . . .. . .. . . .. . . . ... C - 1 D. Work Difficalty Factor Adjustme nts ........................................................................D 1 E. Work Are a Duratio n Workshee ts .............................................................................E- 1 F. Work Are a O u tline s . . .... . . . . . . .. . . .. ... . . . . . . .. .. . .. . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . . .. .... .. .. . . . . . ..

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McIn1 Ycnkee Atomic P:wxr Station Doce s1nt M01-1258-002, Rev.1 Decommissioning Cost An:ly:is Pags v cfzil 1

l REVISION LOG

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e2 t' ORA'Yo7 w asses IQ GIthWe*di c;;, omu m psuys M-ReasoniroQeg;m r- 7 =1 wsfo W 0 9/08/97 1 07-9725 10/27/97 Executive Editorial text changes in Summary, Executive Smnmary. Property Section 3, tax adjustment in Appendix C Section 6, which resultedin modifications Appendix C to the costs reported in the Executive Summary, Section 3 i and Section 6. Reassignment  !

of Post-Period 3 costs in Appendix C to " License Termination."

Maine Yankee Atomic Power Station Document M01-1258-002, Rev.1 Decomminaioning Cast Analysis Page vi ofsit LIST OF EFFECTIVE SECTIONS M01-1258-002, Revision 1

! l Section Revision Data l l

Preface 1 10/27/97 , ,.

1 0 9/08/97 )

2 0 9/08/97 I 8 1 10/27/97 4 0 9/08/97 5 0 9/08/97

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6 1 10/27/97 7 0 9/08/97 Anoendices A 0 9/08/97 B 0 9/08/97 C 1 10/27/97 D 0 9/08/97 j E 0 9/08/97 F 0 9/08/97 l

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Mains Yanhn Atomic Pow:r Statirn Document M01-1:58-OO2, Rev.1 D;crmmissirning Co:t Analy;is Page vil ofxii EXECUTIVE SU1GIARY A site-specific cost analysis was prepared for decommissioning the Maine Yankee l 8 Atomic Power Station (Maine Yankee plant) for the Maine Yankee Atomic Power Company (MYAPC) by TLG Services, Inc. This study includes a comprehensive cost and schedule estimate for completing the decommissioning based upon a detailed l

accounting of the plant inventory. The requirements for component disposition'and '

the associated time to complete were combined to produce the proposed project schedule. The resulting cost to decommission (decontaminate and dismantle) the Maine Yankee plant is estimated at approximately $380.6 million, in 1997 dollars.

The major cost contributors are associated with labor, site remediation and the disposition of low level radioactive waste, as well as anedlary expenses such as property taxes, licensing fees, insurance premiums, etc. In addition, the expense associated with the construction of an on-site independent spent fuel storage installation is $52.2 mdlion. Operation of the facility during the period following the completion of the decommissioning activities at the site until the transfer of the fuel off-site c,an be accomplished is estimated to add an additional $75.4 million. The latter two costs totaling $127.6 million are attributable to the governments failure to perform its obligation to take the waste. Both costs are included in this study for a total cost of $508.2 mdlion.

The costs are based on several key assumptions in areas of regulatory requirements, 6nancing, component characterization, high level radioactive waste management, the availability for disposal of low level radioactive waste, performance uncertainties (contingency) and site restoration requirements. A complete discussion of the assumptions relied upon in this analysis is provided in Section 3.

The major cost contributors to the cost to decommission the Maine Yankee plant are discussed in Section 6. A copy of the summary information provided in Table 6.1 is reproduced at the end of this summary for completeness. A schedule of annual expenditures is provided at the end of Section 3, with the associated sequence of significant project activities provided in Section 4. A detailed reporting of the information used to generate the summary tables contained within this document can be found in Appendix C.

Alternatives and Reculations The Nuclear Regulatory Commission (NRC) provided general decommissioning guidance in a rule adopted on June 27, 19881, setting forth technical and Snancial 2

U.S. Code of Federal Regulations, Title 10. Parts 30, 40,50, 51,70 and 72 " General Requirements for Decommissioning Nuclear Facilities," Nuclear Regulatory Commission, Federal Register Volume 53 Number 123 (p 24018+), June 27,1988.

i Mrine Yankn Atrmic Prwxr Station Document M01-1258-002, R1v.1 Decommineioning Cost Analysis Prgs vili efxii criteria for decomminaioning licensed nuclear facilities. The regulations addressed

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pinnning needs, timing; funding methods, and environmental review requirements for i decoinmissioning. The rule also defined three decommiasioning alternatives as being acceptable to the NRC - DECON, SAFSTOR and ENTOMB. The NRC also recognized that some combination of the first two alternatives would also be appropriate in some I instances.

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DECON was defined by the rule as "the alternative in which the equipment, structures, and portions of a facility and site containing

. radioactive contaminants are removed or decontaminated to a level that permits the property to be released for unrestricted use shortly after cessation of operations." 2 SAFSTOR was defined as "the alternative in which the nuclear facility is placed and maintained in a condition that allows the nuclear facility to be safely stored and subsequently decontaminated (deferred  :

decontamination) to levels that permit release for unrestricted use." 3 i

ENTOMB was defined as "the alternative in which radioactive conta'minants are encased in a structurally long-lived material, such as concrete; the entombed structure is appropriately maintained and continued surveillance is carried out until the radioactive material decays to a level permitting unrestricted release of the property." 4 In 1996 the NRC published revisions to the general requirements for decommissioning nuclear power plants to clarify ambiguities and codify procedures and terminology as a means of enhancing efficiency and uniformity in the decommissioning process. The amendments allow for greater public participation and better define the transition process from operations to decommissioning. A draft regulatory guide (DG-1067), issued in June of 1997, further describes the methods and procedures that are acceptable to the NRC staff for implementing the requirements of the 1996 revised rule that relate to the initial activities and the major phases of the decommissioning process. The costs and schedules presented in this estimate follow the general guidance and recommended sequence presented in the amended regulation.

Methodolorv The methodology used to develop the decommissioning cost estimate for the Maine Yankee plant follows the basic approach originally presented in a document 8 Ihid. Page FR24022, Column 3.

8 Ibid.

4 lhid. Page FR24023, Column 2.

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Mrine Yankn Atomic P:wsr Statlan Documsnt M01-1358-002, Rev.1 D:c:mmissi:ning Cost Analy:is Pags is afxil developed for the Atomic Industrial Forum (now Nuclear Energy Institute), entitled

" Guidelines for Producing Commercial Nuclear Power Plant Decommiasioning Cost Estimates 5." This reference describes a unit cost factor method for estimating decontamination and dismantling activity costs. The unit cost factors used in this l.

study reflect site specific costs, as well as the latest available information on worker l productivity, waste handling and material disposition in decommiasioning a nuclear facility. The data obtained from the Shippingport Station Decommissioning Project, completed in 1989, as well as from TLG's involvement in the decommissionin'g i planning and engineering for the Shoreham, Yankee Rowe, Trojan, Rancho Seco, 1

Pathfinder, and Cintichem reactor facilities, is reflected within this estimate.

An activity duration critical path is used to determine the total decommissioning program schedule required for calculating the carrying costs which include program management, administration, field engineering, equipment rental, quality assurance, and security. This systematic approach for assembling decommissioning estimates ensures a high degree of confidence in the reliability of the resulting costs.

Continzencv Consistent with industry practice, contingencies are applied to the decontamination and dismantling costs developed as, " specific provision for unforeseeable elements of cost within the defined project scope, particularly important where previous  !

experience relating estimates and actual costs has shown that unforeseeable events which willincrease costs are likely to occur."8 The cost elements in this estimate are based on ideal conditions; therefore, the types of unforeseeable events that are almost certain to occur in decommissioning, based on industry experience, are addressed through a percentage contingency applied on a line item basis. This contingency factor is a nearly universal element in all large scale construction and demolition projects. It should be noted that contingency, as used in this estimate, does not account for price escalation and inflation in the cost of decommissioning over the period of performance.

Contingency within decommissioning estimates is not used as a safety factor. Safety factors provide additional security and address situations that may never occur.

Contingency funds, by contrast, are expected to be fully expended throughout the program. Application of contingency on a line item basis is necessary to provide assurance that sufficient funding will be available to accomplish the intended tasks.

l 5 T.S. LaGuardia et al.," Guidelines for Producing Commercial Nuclear Power Plant i

Decommissioning Cost Estimates." AIF/NESP 036. May 1986.

• Project and Cost Engineers' Handbook, Second Edition, American Association of Cost Engi-l

' neers. Marcel Dekker, Inc., New York, New York. p. 239.

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M: ins Yankse Atomic Pcww Station Document M01 1*58-00*, Rev.1 Dec:mmissioning Cost Ancly:is Pags x of xil Low Level Radioactive Waste Discosal The ' contaminated and activated material generated in the decontamination and dismantling of a commercial nuclear reactor is classified as low level radioactive waste, although not all of the material is suitable for " shallow land" disposal. With i the passage of the " low Level Radioactive Waste Disposal Act" in 1980, and its l Amendments of 19857, the states became ultimately responsible for the disposition of low-level radioactive waste generated within their own borders. Maine, along witl Vermont, joined with Texas to form a conipact for the disposal oflow level radioactive waste generated by the three states, with Texas as the host state. Approval of the compact has been progressing through House and Senate committees; however, the schedule for the actual opening of such a facility is still uncertain. Consequently, for purposes of this analysis, low-level radioactive waste generated in the decontamination and dismantling of the Maine Yankee plant is destined for the currently operating Barnwell Low-Level Radioactive Waste Management Disposal Facility (Barnwell), located in Barnwell, South Carolina. This site is expected to be available to support near term decommissioning operations and has the established rate structure available to estimate waste disposal costs.

With the high cost of disposal at the Barnwell facility, a large portion of the I contaminated material generated during decommissioning will be first routed through commercial waste recovery vendor (s) for volume reduction. Reduction in the  !

volume of material requiring controlled disposal was assumed to be accomplished through a variety of methods including surveying (for non-verified clean material),

incineration, compaction and metal melt. Costs for waste conditioning and associated recovery fractions were based upon representative market prices and performance data from vendors providing these types of services.

High Level Waste Congress passed the " Nuclear Waste Policy Act" 8 in 1982, assigning the responsibility for disposal of spent nuclear fuel created by the commercial nuclear generating plants to the Department of Energy (DOE). This legislation also created a Nuclear Waste Fund to cover the cost of the program, which is funded by the sale of electricity from the Maine Yankee plant (and an estimated equivalent for assemblies irradiated prior to April,1983). The target date for startup of the federal Waste Management System was originally 1998.

The backlog of spent fuel in the national inventory, delays in site characterization,

? Low Level Radioactive Waste Policy Amendments Act of 1985,"Public Law 99-240,1/15/86.

8 Nuclear Waste Policy Act of 1982 and Amendments, Public Law 97 425; Stat. 2201 (January 7,1983) as amended by Public Law 100-203 (December 22,1987) and Public Law 102 486 (October 24,1992).

M: ins Yankn Atomic Paw:r Station Docum:nt M01-1258-002, Rw.1 l Dec1mmissioning Ccct Ancly:is Pagsxi cfsit and intermittent progress in the development of a waste transportation system, make it necessary to reflect spent fuel storage in the cost and schedule of commercial reactor decommiasioning. After several delays, DOE estimates that the geologic l repository will be operational sometime between the years 2010 and 2015. For the l basis of this cost analysis, MYAPC has assumed that the high level waste repository or some interim storage facility will be operational by 2010. Interim storage of the fuel, until DOE has completed the transfer, will be in an independent facility to be constructed at the Maine Yankee plant site. This will allow MYAPC to proceed I l decommissioning and the termination of its operating license in the shortest time l l possible.

Site Restoration The efficient removal of the contaminated materials at the site and verification that residual radionuclide concentrations are below the NRC limits will result in substantial damage to many of the site structures. Blasting, coring, dnlling, scarification (surface removal), and the other decontamination activities will substantially damage power block structures, potentially weakening the footings

! and structural supports. Prompt demolition following license termination is clearly the most appropriate and cost-effective option. It is unreasonable to anticipate that these structures would be repaired and preserved after the radiological contamination is removed. The cost to dismantle site structures with a work force already mobilized on site is more efficient and less costly than if the process is deferred. Experience at shutdown generating stations has shown that plant facilities quickly degrade without continual maintenance, adding additional expense and creating potential hazards to the public, as well as to the demolition work force.

This study assumes that site structures will be removed to a nominal depth of three feet below the local grade level. The site will then be regraded.

Recommendations This analysis presumes that MYAPC willinitiate decontamination and dismantling activities at the Maine Yankee plant site as quickly as possible, with decommissioning engineering and planning scheduled in this analysis to begin in August 1997. While this may not be possible, e.g. due to financial constraints, any delay in the program start will tend to increase the total projected cost of the l program. Sigmficant delays may be better accommodated through the incorporation of a safe storage period where the on site organization and level of plant activity is

minimized. However, the cost to defer decommissioning will be dictated, in part, by I the availability of the current organization to support such an activity in the future I and the cost to maintain this expertise in the interim.

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l M:Ine Ycnhee At:mic Power Station Document M01-1258-002, Rev.1 Dec:mmienioning C:st An lysis Pag 2xit cfxil l

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SUMMARY

OF MAJOR CONTRIBUTORS to the-COST OF DECOMMISSIONING

- Work Activity Cost Percent of or Cost Category (thousands,975)t.2 Total Cost 1. ,

Staffing 133,216 26.21 LLRW Burial 83,379 16.41 Removal 60,214 11.85

ISFSI Siting, Construction and Licensing 52,249 10.28 Property Taxes 31,031 6.11 Waste Conditioning / Recycling 22,473 4.42 j

! Security Services 15,930 3.13 l l Non radiological Demolition 15,078 2.97 Transportation 12,881 2.53 Decontamination 12,024 2.37 License Termination Survey 10,580 2.08 Soil Remediation 9,063 1.78 Plant Energy Budget 8,944 1.76 Insurance 7,420 1.46 l NRC ISFSI Fees 6,936 1.36 l Packaging 6,339 1.25 NRC and EP Fees 6,309 1.24 Fixed Overhead 5,904 1.16 Remaining Costs 3 8.253 Lfi2 Total $508,221 100.00 Notes:

1. Columns may not add due to rounding.

2. All costs include contingency with the exception of property taxes.

3. Remaining costs include site characterization, building modifications, temporary services and support equipment.

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Mrine Yankes Atomic Paw 1r Station Documsnt M01-1258 002, Rw. O Decommiacioning Cast Analysis Ssetian 1, Pags 1 of 5

1. INTRODUCTION

This decommissioning cost analysis is designed to provide the Maine Yankee Atomic Power Company (MYAPC) with sufficient information to prepare the financial pinnning documents for decommissioning, as required by the Nuclear Regulatory Commission (NRC). It is not a detailed engineering document, but a cost estimate prepared in advance of the detailed engineering preparations required to carry out the decommiasioning of the Maine Yankee Atomic Power Station (Maine Yankee plant). This analysis is also intended to support the production of required licensing documentation, e.g. the Post Shutdown Decommissioning Activities Report (PSDAR).

1.1 OBJECTIVE OF STUDY The objective of the study is to prepare a comprehensive estimate of the cost, a detailed schedule of the associated activities, and the resulting volume oflow-level radioactive waste generated'in decommissioning the Maine Yankee plant.

The plant operating license was issued by the Atomic Energy Commission in 1972. The license permitted operation until October 2008. The plant was shutdown for an unscheduled outage in December 1996, and after initial plans

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to restart, MYAPC decided to permanently close the nuclear generating unit in August of 1997. This study evaluates the immediate decommissioning of the facility as described in Sections 2 and 3.

1.2 SITE DESCRIPTION The Maine Yankee plant is located in the town of Wiscasset, Maine on 740 acres of land bounded by Back River on the east, mainland on the north and Birch Point Road on the west. The plant is comprised of a single nuclear generating unit with supporting facilities. The station was designed and built by Stone & Webster Engineering Corporation and is comprised of a Combustion Engineering, Inc. (CE) pressurized water reactor (PWR) and an ABB turbine with a Westinghouse generator.

The Nuclear Steam Supply System (NSSS) consists of a pressurized water reactor and a three loop Reactor Coolant System. The generating unit has a reference core design of 2700 MWt (thermal) with a corresponding gross electrical output of 920 megawatts (electric) with the reactor at rated power.

The Reactor Coolant System is comprised of the reactor vessel and three heat transfer loops, each contaimng a vertical shell and U tube steam generator, and a vertical centrifugal reactor coolant pump. In addition, the system

Maine Yankee At:mic P:wsr Station Document M01-1258-002, R:v. 0 Decommissioning Co:t Analyris Szction 1, Pags 2 ef 5 includes a electrically heated pressurizer, a pressurizer quench tank and

. interconnected piping. The system is housed within a " containment structure,"

which is a seismic design, reinforced concrete structure. The reactor containment consists of a steel-lined reinforced concrete cylinder with a hemispherical dome and an essentially flat reinforced concrete foundation mat.

The welded steel liner plate, anchored to the inside face of the containment, ,

serves as a leak-tight membrane. The liner on top of the foundation mat is i i protected by approximately two feet of concrete.

l Heat produced in the reactor was converted to electrical energy by the Steam i and Power Conversion System (SPCS). A turbine generator system converts )

the thermal energy of steam produced in the steam generators into mechanical l shaft power and then into electrical energy. The unit turbine-generator.

consists of a tandem compound unit with external moisture separation and live steam reheating. It consists of one high pressure double flow turbine and two double-flow low-pressure turbines driving a direct. coupled generator at 1800 rpm. The turbine is operated in a closed feedwater cycle which condenses the I steam; the heated feedwater is returned to the steam generators. Heat I rejected in the main condenser is removed by the Circulating Water System (CWS).

The CWS provides the heat sink required for removal of waste heat in the power plant's thermal cycle. The system has the principal function of removing heat by absorbing this energy in the main condensers. Water for operation is taken from the Back River, through a screen well house, and pumped through the condenser tubes. Return water is discharged to the river.

1.3 REGULATORY GUIDANCE i i

The Nuclear Regulatory Commission (NRC or Commission) provided decommissioning guidance in the rule " General Requirements for Decommissioning Nuclear Facilities," (Ref.1) published and adopted on June 27, 1988. This rule amended NRC regulations to set forth technical and financial criteria for decommissioning licensed nuclear facilities. The regulation addressed decommissioning planning needs, timing, funding methods, and environmental review requirements. The intent of the rule was to ensure that decommissioning would be accomplished in a safe and timely manner and that adequate licensee funds would be available for this purpose.

Subsequent to the rule, the NRC issued Regulatory Guide 1.159, " Assuring the Availability of Funds for Decommissioning Nuclear Reactors," (Ref. 2) which provided guidance to the licensees of nuclear facilities on methods acceptable to the NRC staff for complying with the requirements of the rule. The regulatory guide addressed the funding requirements and provided guidance on the

, 4 l Maine Yankee Atomic Poww Station Document M01-1:58-002, Rev. O \

Decommissioning Co:t Analyiis Secti:n 1, Pag 2 3 el5 l content and form of the financial assurance mechanisms indicated in the rule amendments.

I The rule defined three decommissioning alternatives as being acceptable to the

[ NRC: DECON, SAFSTOR and ENTOMB.

l DECON was defined by the rule as "the alternative in which the -

equipment, structures, and portions of a facility and site containing radioactive contaminants are removed or decontaminated to a level that permits the property to be released for unrestricted use shortly after cessation of operations."

i SAFSTOR was defined as "the alternative in which the nuclear i

facility is placed and maintained in a condition that allows the nuclear facility to be safely stored and subsequently decontnminated (deferred decontnmination) to levels that permit release for unrestricted use."

. ENTOMB was defined as "the alternative in which radioactive contammants are encased in a structurally long lived material, such as concrete; the entombed structure is appropriately maintained and continued surveillance is carried out until the radioactive material decays to a level permitting unrestricted release of the property."

The rule placed limits on the time allowed to complete the decommissioning process. For SAFSTOR, the process is restricted in overall duration to 60 years unless it can be shown that a longer duration is necessary to protect public health and safety. The guidelines for ENTOMB are similar, providing the NRC with both suficient leverage and flexibility to ensure that these deferred options are only used in situations where it is reasonable and consistent with the definition of decommissioning. Consequently, with the new restrictions, the SAFSTOR and ENTOMB options are no longer decommissioning alternatives in themselves, as neither terminates the license for the site. At the conclusion of a 60-year dormancy period (or longer for ENTOMB if the NRC approves such a case), the site would still require significant remediation to meet the definition of unrestricted release and license termination. Further, the NRC does not believe that ENTOMB is generally a viable option for a power reactor due to the long lived nature of the radionuclides involved.

In 1996 the NRC published revisions to the general requirements for l decommissioning nuclear power plants (Ref. 3). When the decommissioning regulations were adopted in 1988, it was assumed that the majority of

Mrine Ycnkn Atomic P wsr Station Docum1nt M01-1258-002, Rw. 0 Decomminoloning Coit Analysis Section 1, Pags 4 cf 5 i

licensees would decommission at the end of the operating license life. Since

- that time, several licensees had permanently and prematurely ceased operations without having submitted a decommissioning plan. In addition, l 3 these licensees requested exemptions from certain operating requirements as being unnecessary once the reactor is defueled. Each case has been handled individually without clearly defined generic requirements. The NRC amended the decommiasioning regulations in 1996 to clarify ambiguities and codify procedures and terminology as a means of enhancing efficiency and uniformity l in the decommissioning process. The new amendments allow for greater public participation and better define the transition process from operations to i decommiasioning.

't Under the revised regulations, licensees would submit written certification to the NRC within 30 days after the decision was made to cease operations.

Certification would also be required once fuel had been permanently removed from the reactor vessel. Submittal of these notices would entitle the licensee to a fee reduction and eliminate the obligation to follow certain requirements needed only during operation of the reactor. Within two years of submitting notice of permanent cessation of operations, the licensee would be required to submit a Post Shutdown Decommissioning Activities Report (PSDAR) to the NRC. This report would describe the planned decommissioning activities, the associated sequence and schedule, and an estimate of expected costs. Prior to completing decommissioning, the licensee would be required to submit an application to the NRC to terminate the license, along with a license termination plan.

1.3.1 Nuclear Waste Poliev Act Congress passed the Nuclear Waste Policy Act in 1982 (Ref. 4), assigning the responsibility for disposal of spent nuclear fuel from the commercial generating plants to the Department of Energy (DOE). Two permanent disposal facilities were envisioned as well as an interim facility. To recover the cost of permanent spent fuel disposal, this legislation created a Nuclear Waste Fund through which money was to be collected from the consumers of the electricity generated by commercial nuclear power plants. The date targeted for startup of the federal Waste Management System was 1998.

After pursuing a national site selection process, the Act was amended in 1987 to designate Yucca Mountain, Nevada, as the only site to be evaluated for geologic disposal of high level waste. Also in 1987, DOE announced a five year delay in the opening date for the repository, from 1998 to 2003. Two years later, in 1989, an additional 7 year delay was announced, primarily due to problems in obtaining the required permits from the state of Nevada to

Mine Yankee At:mic Psw:r Sentian Document M011258-002, R:v. O Decommiseloning Co:t An: lysis Section 1, Pags 5 cf 5 perform the required characterization of the site. DOE has projected additional delays as a result of proposed Congressional reductions in appropriations for the program.

Utilities have responded to this impasse by initiating legal action and constructing supplemental storage as a means of maintaining operating margins. The U.S. Court of Appeals for the D.C. Circuit recently confirmed DOE's statutory obligation to provide spent fuel disposal beginning in 1998, regardless of whether the agency has an operating repository. However, since the agency is not currently in default, the court declined to prescribe

" remedies" in the likely event DOE fails to uphold its obligation.

, For purposes of the decommiasioning cost estimate, DOE is assumed to initiate spent fuel acceptance from the Maine Yankee plant starting in the year 2010.

Based on this starting date and information received from the DOE's Office of Civilian Radioactive Waste Management, MYAPC has estimated that transfer of fuel can be completed by the year 2023, 1.3.2 Low-Level Radioactive Waste Poliev Amendments Act

~

Congress passed the " Low-Level Radioactive Disposal Act" in 1980, declaring l the states as being ultimately responsible for the disposition of low level radioactive waste generated within their own borders. The fedeal law encouraged the formation of regional groups or compacts to implement this objective safely, efficiently and economically, and set a target date of 1986.

With little progress, the " Amendments Act" of 1985 (Ref. 5) extended the target, with specific milestones and stiff sanctions for non compliance.

However, more than 10 years later, no new sites have been developed and even l the most advanced program is far behind schedule.

Maine, along with Vermont, joined with Texas to form a compact for the disposal of low level radioactive waste generated by the three states, with Texas as the host state. Approval of the compact has been progressing through House and Senate committees; however, the schedule for the actual opening of such a facility is still uncertain. Consequently, for purposes of this analysis, low level radioactive waste generated in the decontamination and dismantling of the Maine Yankee plant is destined for the currently operating Barnwell '

Low Level Radioactive Waste Management Disposal Facility (Barnwell),

located in Barnwell, South Carolina. This site is expected to be available to l support near term decommissioning operations and has the established rate structure available to estimate waste disposal costs.

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l Mins Yankie Atzmic Pawn Station Documsnt M01 1258-002, Rev. O Dec:mmissioning Cost Anclyzia Section 2, Pags 1 a(12

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2. DECON DECO 1GIISSIONING ALTERNATIVE i

The following sections describe the basic activities associated with the decontamination and disassembly of the plant. Although detailed procedures for each activity required are not provided, and actual sequences of work may vary, the i activity descriptions provide a basis not only for estimating, but also for the expected  !

scope of work, i.e. engineering and planning at the time of decommissioning.  !

The DECON alternative deals with the prompt removal of radioactive materials from the site following the cessation of operations. This study does not address the cost to remc7e spent fuel from the site as such costs are assumed to be funded through the  !

surcharge on electrical generation (1 mill / kwhr). However, the study does recognize l

the constraint imposed by the spent fuel residing on site during the decommissioning process. The potential for extended fuel storage is addressed through the construction of a separately licensed Independent Spent Fuel Storage Facility (ISFSI), permitting ,

decommissioning to proceed on the nuclear unit, resulting in the termination of the  !

operating license.

The conceptual approach that the NRC has chosen in its amended regulations is to divide decommissioning into three phases. The initial phase commences with the effective date of permanent cessation of operations and involves the transition of both plant and licensee from reactor operations, i.e., power production, to facility de-activation and closure. During Phase I, notification is to be provided to the NRC certifymg the permanent cessation of operations and the removal of fuel from the reactor vessel. The licensee is then prohibited by the NRC from reactor operation.

Within two years of notification to cease reactor operations, the licensee is required to provide the NRC with a PSDAR, providing a description of the licensee's planned decommissioning activities, a corresponding schedule and an estimate of expected costs. The PSDAR will also address whether environmentalimpacts associated with the proposed decommissioning scenario have already been considered in previously prepared environmental statement (s). Ninety days following the NRC's receipt of the PSDAR, the licensee may initiate certain decommissioning activities without specific NRC approval, under a modified Title 10 of the Code of Federal Regulations, Section 50.8 review process. (All subsequent references to the Title 10 of the Code will be by section number only, i.e. j50.59). The regulations permit up to 3% of the generic decommissioning cost to be available for planning, with an additional 20% available following the 90. day waiting period and certification of permanent defueling.

Remaining funds will be available to the licensee upon submittal of a detailed, site-specific cost estimate.

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Phase II. identified by the NRC in the new rule, addresses licensed activities during a storage period, applicable to the dormancy phases of a deferred decommissioning

l 1

M:ine Ycnkn At:mic P:w;r Station Document M01-1238-002, Rev. O d Decommissioning C:st Analy:is Secti:n 2, Pags 2 ef12 alternative such as SAFSTOR or ENTOMB. Phase II is not considered in this study, since decommissioning is scheduled to commence immediately. Phase III pertains to the activities involved in license termination. The submittal of an application to terminnte the license, along with a termination plan, marks the commencement of this phase. The termination plan contains a detailed site characterization, i.e.,

location, type and amount of radioactivity, a description of any remaining dismantling activities to be accomplished, detailed plans for a final survey and.the planned end use of the site. Phase III activities and costs are included within this estimate.

The TLG methodology divides the decommissioning project into periods, based upon major milestones in the project. Phase I of the NRC 1996 amended regulations corresponds roughly to DECON Period 1 and Phase III corresponds to DECON Period

2. The NRC Phase II has no corresponding period in the DECON mode, being applicable only to the dormancy period of SAFSTOR (Period 2). TLG's Period 3, Site Restoration, is not addressed in the amended regulations.

2.1 PERIOD 1 - PREPARATIONS ,

Detailed preparations are undertaken to provide a smooth transition from plant operations to site decommissioning. The orgamzation required to manage the intended decommissioning activities is assembled from availabic plant staff and outside resources, as required. This staffing transition process, which is considered within the study, covers retraining of selected plant staff and offering retention incentives for key personnel. Preparations include the planning for permanent defueling of the reactor, revision of technical specifications appurtenant to the operating conditions and requirements, a characterization of the facility and major components, and the development of the PSDAR.

Eneineerine and Plannine Prior to the commencement of decommissioning operations, MYAPC will certify the permanent cessation of operations and the removal of fuel from the reactor vessel. The PSDAR, required within two years of the notice to cease operations, provides a description of the licensee's planned decommissioning activities, a timetable, and the associated financial requirements of the decommissioning program. Upon receipt of the PSDAR, the NRC will make the document available to the public for comment in a local hearing to be held in the vicinity of the reactor site. Ninety days following submittal and 1GC receipt of the PSDAR, the licensee may begin to perform major decommissioning activities under a modified 50.59 procedure, i.e., without specific NRC approval. Major activities are defined as any activity that results

M:ine Yankie Atrmic Powxr Statisn Drcum<nt M01-1!58-00!, Rev. 0 Decommincioning Cost Analysis Section 2, Pag 2 3 ef12 in permanent removal of major radioactive components, permanently modifies the containment structure, or results in dismantling components (for shipment) containing Greater than-Class C waste (GTCC as defined under

$61). Major components are further defined as comprising the reactor vessel and internals, large bore reactor recirculation system piping, and other large radioactive components. The Commiasion is including the following additional criteria for use of the $50.59 process in decommiasioning: the proposed activity must not 1) foreclose release of the site for possible unrestricted use, 2) significantly increase decommiasioning cost, 3) cause any significant environmentalimpact, or 4) violate the terms of the licensee's existing license.

Consequently, in conjunction with the development of the PSDAR, activity specifications, cost benefit and safety analyses, work packages and procedures, etc., will need to be assembled in support of the proposed decontamination and dismantling activities.

The decommissioning program outlined in the PSDAR will be designed to accomplish the required tasks within the As-Low-As Reasonably-Achievable (ALARA as defined in $20) guidelines for protection of personnel from exposure to radiation hazards. It will also address the continued protection of the health and safety of the public and the environment during the dismantling activity.

The Commission recognizes that the existing operational technical specifications will need to be reviewed and modified to reflect plant conditions and the safety concerns associated with permanent cessation of operations.

The environmental impact associated with the planned decommissioning activities will need to be considered, with an environmental report on specific i and unique concerns required to be submitted to the NRC for consideration and possible preparation of an environmentalimpact statement.

I Site Precarations Following final plant shutdown and in preparation for actual decommissioning activities, the following activities are initiated: i

. Preparation of site support and storage facilities, as required.

. Isolation of the spent fuel storage services and fuel handling systems from the rest of power block such that decommissioning operations can commence on the balance of the plant. This activity is carried out by plant personnel in accordance with existing operating technical specifications.

Decommissioning operations are assumed to be scheduled around the fuel storage and handling systems to the greatest extent possible, such that the overall project schedule is optimized. Current dry storage cask designs are

Msine Yankee Atomic P seerSt:tian Document M01-1558-002, Rev. 0 Decomminaioning Cost Analysis Section 2, Page 4 of12 licensed for spent fuel with a core diachay decay time averaging approximately five years or longer. Therefore, decommianinning operations

, for the fuel storage and handling area cannot be expected to begin prior to L

five years after the cessation of plant operations. As spent fuel decays to the point that it meets the heat load criteria of the dry storage casks, it will ,

be transferred to the dry storage facility. It is assumed that all fuel is I transferred to dry storage within 78 months from the cessation of operations.

l

. Preparation for Large Component Removal Project (LCRP). Preparation of I

i. all engineering and licensing documentation. Preparation of barge transportation route; upgrade / build barge loading area. Procurement of all needed materials, shielding, identification of heavy-lift and grouting contractors. .

. Conducting radiation surveys of work areas; major components (including the reactor vessel and its internals); sampling of internal piping 4

' contamination levels; and primary shield cores.

. Correlation of survey data to packaging and transportation criteria.

. Characterization of current inventory of all hazardous waste and l preparation for shipment and disposal off site.

. Processing of residual liquid and solid waste inventories.

. Removal of allitems of furniture, tools, mobile equipment such as forklifts, trucks bulldozers, other similar mobile equipment and other such items of property owned by MYAPC that will be easily removed without the use of special equipment.

. Removal of all equipment and material in warehouses not essential to the decommissioning operations.

. Remediation of all asbestos from the site.

, . Determination of transportation and disposal container requirements, including shielding and stabilization for activated materials and/or hazardous material. Fabrication or procurement of such containers.

2

. Development of procedures for occupational exposure control, control and release ofliquid and gaseous efHuent, processing of radwaste including Dry Active Waste (DAW), resins, filter media, metallic and non-metallic

M:ine Yankee Atomic P:wsr Station Document M01-1358-002, R1v. O Decommissioning Cest An11yzis Section *, Pags 5 e(12 components generated in decommissioning, site security and emergency l .

programs, and industrial safety.

Following submittal of the PSDAR and certification of permanent removal of fuel from the reactor vessel, the licensee may commence major decommiasioning activities (under certain conditions). Unlimited access to the decommissioning fund will require the preparation of a detailed site-specific cost estimate for submittal to the NRC. In addition, a license termination plan, submitted as a supplement to the Final Safety Analysis Report (FSAR) or equivalent, needs to be prepared at least two years prior to the license termination date.

2.2 PERIOD 2 -

DECOMMISSIONING OPERATIONS & LICENSE TERMINATION For the DECON alternative, significant decommissioning activities involve:

. Construction of temporary facilities and modification of existing storage facilities to support the dismantling activities. These may include additional changing rooms and contaminated laundry facilities for increased work force, establishment of laydown areas to facilitate equipment removal and preparation for off-site transfer, upgrading roads, railroads or barge facilities to facilitate hauling and transportation, and modiEcations to the Containment to facilitate access of large/ heavy equipment.

. Design and fabrication of special shielding and contamination control envelopes, special tooling and remotely operated equipment. Modification of the refueling cavity to support segmentation activities and preparation of rigging equipment for segmentation and removal of piping sections, coolant pumps and other components, including the reactor vessel and its internals.

. Procurement of required shipping canisters, cask liners, and Low Specific Activity (LSA) containers from suppliers.

. Decontamination of components and piping systems as required to control (mimmize) worker exposure. Removal, and preparation for shipment to an off-site recycling vendor of piping and components as they are no longer essential to support decommissioning operations.

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Mrine Ycnkee Atomic P:wxr Station Document M01-1258-002, Rev. 0 Decomminoloning Cost Analysis Section 2, Pag 2 6 ef12 s

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• Removal of steam generators and pressurizer for shipment and burial.

Decontamination of external surfaces as required, and seal-welding of all i openings. These components can serve as their own burial containers.

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. Segmentation of upper and lower core support structures and in-core instrumentation and package segments in shielded casks. These operations

are performed remotely by cutting equipment within a contamination

l. control envelope. Ship and bury packaged items which meet $61 Class "C" requirements or less.

i

e Disassembly / segmentation of remaining reactor internals and package in

j. shielded casks. The operations are conducted under water using remotely j operated tooling and a contamination control envelope or other i

contamination barrier (s). Ship and bury packaged items which meet $61 l

] Class "C" requirements or less.

l

, . Packaging of GTCC components into Fuel Bundle Canisters (F'B Cs) and j transfer to the ISFSI.

. Segmentation / sectioning of the reactor vessel, placing segments into j shielded containers. The operation is performed remotely in air using a j contamination control envelope. Sections are placed in liners and stored

! using a remote or shielded crane. The liners are loaded into shielded l transport casks for disposal at a commercial shallow-land waste disposal facility.

l

. Segmentation / sectioning of the neutron shield tank structure formerly surrounding the reactor vessel and placing segments into shielded I containers. The operation is performed remotely in air using a contamination control envelope. Sections are placed in liners and stored using a remote or shielded crane. The liners are loaded into shielded transport casks for disposal at a commercial shallow land waste disposal facility.

At least two years prior to the anticipated date of license termination, a License Termination Plan is required to be prepared. Submitted as a supplement to the FSAR, or equivalent, the plan must include: a site characterization, description of the remaining dismantling activities, plans for site remediation, procedures for the final radiation survey, designation of the end use of the site, an updated cost estimate to complete the decommissioning, and any associated environmental concems. The NRC will notice the receipt of

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the plan and make the plan available for public comment, and schedule a local hearing. Plan approval will be subject to any conditions and limitations as

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M:ine Yankee Atomic P:wxr Station Docum:nt M01-1258-002, Rev. 0 Decommissioning Cost An:ly:is Section 2, Pag 2 7 ef12 deemed appropriate by the Comminaion. The licensee may then commence with the final remediation of site facilities and services, including:

Removal of remaining plant systems and associated components in each defined area as they become nonessential to the decommissioning program or worker health and safety (e.g., waste collection and treatment systems, electrical power and ventilation systems, etc.). -

l Routing of material removed in the decontamination and dismantling of the nuclear unit to a central processing area. Material certified to be free of l

contamination will be released for unrestricted disposition, e.g., as scrap,  :

recycle or general disposal. Contan1inated material will be characterized and segregated for additional off-site processing (disassembly, chemical i cleaning, volume reduction, waste treatment, etc.), and/or packaged for  !

controlled disposal at a low-level radioactive waste disposal facility. l Removal of contaminated equipment and material from all contaminated areas using radiation and contamination control techniques until radiation surveys indicate that the structures can be released for unrestricted access and conventional demolition.

Decontamination of remainmg site buildings and facilities with residual contaminants. Packaging and disposal of all remaining low level radioactive waste along with any remaming hazardous and toxic materials.

Removal of contaminated equipment and material from the remaining Contninment Building and fuel storage areas as well as any other contaminated areas once the spent fuel pool has been emptied. Remove steel liner from the spent fuel pool. Package contaminated material in standard LSA containers, including contaminated pool concrete for shipping and burial.

Remove remaining components, equipment and plant services in support of the area release survey (s).

2.3 FINAL SITE SURVEY-LICENSE TERMINATION Incorporated into the License Termination Plan, the Final Survey Plan details the radiological surveys to be performed once the decontamination activities are completed. The Final Survey Plan is developed using the guidance provided in NUREG/CR-5849, " Manual for Conducting Radiological Surveys in Support of License Termination." This document delineates the statistical approaches to survey design and data interpretation used by the

Mrine Yankn Atomic Pawxr Station Documsnt M01-1258-002, Rev. O Decommissioning Cost Analyzis Section 2, Pag 2 8 ef12 m.

Environmental Protection Agency (EPA). It also identifies state-of-the-art,

. commercially available, instrumentation and procedures for conducting radiological surveys. Use of this guidance ensures that survey design and implementation are conducted in a manner that provides a high degree of confidence that applicable NRC criteria are satisfied. Once the survey is complete, the results are provided to the NRC in a format that can he verified. The NRC then reviews and evaluates the information, performs an independent confirmation of radiological site conditions, and makes a determination on final termination of the license.

The NRC will terminate the license ifit determines that the site remediation has been performed in accordance with the License Termination Plan and the Final Survey Plan, and that appropriate documentation has been presented to demonstrate that the facility is suitable for release. Once all applicable requirements are satisfied, the NRC can terminate the f 50 license.

2.3.1 NRC Criteria for Decommissionine l NRC's requirements for decommissioning and license termination are contained in f 30.36, f40.42, f50.82, 70.38, and f72.54. However, these ,

regulations do not provide generally applicable radiological criteria for i decommissioning as, historically, radiological data unique to specific sites has l been utilized for site release determmation. The NRC's current position on residual contamination criteria, site characterization, and other related decommissioning issues is outlined in a NRC document entitled " Action Plan to Ensure Timely Cleanup of Site Decommissioning Management Plan Sites,"  ;

which was published in the Federal Register on April 6,1993 (57 FR 13389).

Pending the establishment of generic decommissioning criteria through rulemaking, the NRC will continue to consider existing guidance, criteria, and practices listed in the April 1993 Action Plan. The NRC considers the i following cleanup criteria to determine whether sites are sufficiently decontaminated to permit release for unrestricted use:

Reculatorv Guide 1.86 and Poliev and Guidance Directive FC 83 - 23 Regulatory Guide 1.86 " Termination of Operating Licenses for Nuclear Reactors," (June 1974) and Policy and Guidance Directive FC 83-23, t

" Termination of Byproduct, Source, and Special Nuclear Material Licenses" (November 1983), contain surface contamination limits for unrestricted use at reactors and materials facilities by listing radionuclides in groups that are roughly based on their relative radiotoxicity. Both documents provide surface contamination limits in terms of disintegrations per minute per 100 square centimeters, but Policy and Guidance Directive FC 83-23 provides additional

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Mrine Yankee At:mic Powsr Station Document M01-258-002, Rev. 0 L%~~.minnioning Ccet Analyzis Section 2, Pags 9 ef a surface contamination levels in terms of average and maximum radiation levels for beta-gamma emitters.

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NRC Office of Nuclear Reactor Rerulation Letter to Stantnrd University.

NRC Docket No. 50-401 (Auril 1982)

Enclosure 1 to this letter provides NRC guidance on acceptable levels of Co-60, Cs-137, and Eu-152 which are radionuclides that may exist in concrete, components, and structures under consideration for release for unrestricted use. This guidance recommends that residual radiological contammation be removed such that the indoor exposure rate at 1 meter from surfaces is less ,

than or equivalent to 5 microR per hour above background, with an overall '

dose objective of 0.1 mSv/y (10 mrem / year).

Other Regulations and Standards Aeolicable to Decommissionine

. Title 40 of the Code of Federal Regulations, Section 190," Environmental Radiation Protection Standards for Nuclear Power Operation" - limits radiation doses to members of the public from radioactive materials introduced into the general environment as the result of operations that are part of the nuclear fuel cycle.

• 520 " Standards for Protection Against Radiation" - regulates the receipt, possession, use, transfer, and disposal oflicensed material by any licensee in such a manner that the total dose to an individual does not exceed the radiation protection standards. According to $20.1001, the total dose to an individual includes doses from licensed and unlicensed radioactive material and from radiation sources other than background radiation. In addition, the requirements of 920.1301 apply to NRC licensed facilities during decommissioning and when the facility is operational. This regulation prohibits licensees from releasing radioactive materials to an unrestricted area in concentrations that exceed the limits specified in $20 or that exceed limits otherwise authorized in an NRC license.

• $50 Appendix I - provides numerical guidance for keeping radioactive materials in liquid and gaseous effluents released to unrestricted areas "as low as reasonably achievable" during normal operations of a nuclear power reactor.

2.3.2 NRC Decommissioning Process and Survev Procedures NRC licensees are required to conduct radiation eurveys of the premises where the licensed activities were conducted and submit a report describing

M:ine Yankee Atomic Poww Station Document M01-125S 002, Rev. 0 Decommissioning Cost Anclysis Section 2, Pag 210 cf12 I

the survey results. The survey process follows requirements contained in 130.36, $40.42, $50.82, $70.38, and $72.54 which pertain to the I decommissioning of a site and termination of a license. This process leads to- ~

the unrestricted release of a site. However, some of these requirements, may not be necessary if an alternate method of release can be demonstrated.

Basically, the NRC decommiasioning process is comprised of the following steps:

1) Site characterization, including preparing the characterization plan, performing the characterization, and preparing the characterization report;

2) NRC review and approval of the site characterization plan and site characterization report;

3) Development and submission oflicense termination plan;

4) NRC review and approval oflicense termination plan;

5) Performance of decommissioning actions described in the plan;

6) Performance of termination survey and submittal of the termination survey report;

7) NRC performance and documentation of confirmatory survey; and

8) NRC termination oflicense.

Criteria for residual contamination, occupational exposure, and radiation concentration levels are designed to ensure that radioactivity is reduced to a level that permits unrestricted release of the site. The NRC issued its final rule, " Radiological Criteria for License Termination," which addresses the radiological criteria for decommissioning. This rule, along with NUREG-1500, " Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staffs Draft for Comment," would be incorporated into the site release criteria, as appropriate. In addition, any state or federal regulations regarding release criteria (e.g., defi!,itions of" background") would be included in the criteria.

Mrine Yankee Atzmic P:wxr Station Document M01-1258-002, R:v. O Decommissioning Cett Analyzis Section 2, Pag 211 of12 2.4 Period 3 -Site Restoration Following completion of decommissioning operations, site restoration activities may begin. Efficient removal of the contaminated materials and verification that residual radionuclide concentrations are below the NRC limits will result in substantial damage to many of the structures. Blasting, coring, drilhng, scarification (surface removal), and the other decontamination activities will substantially damage power block structures including the Containment, Service and Turbine Buildings. Verifying that subsurface i radionuclide concentrations meet NRC site release requirements may require  !

removal of grade slabs and lower floors, potentially weakening footings and 4 structural supports. This removal activity will be necessary for those facilities and plant areas where historical records, when available, indicate the potential for radionuclides having been present in the soil, where system failures have been recorded, or where it is required to confirm that subsurface process and drain lines were not breached over the operating life of the unit.

This cost study presumes that non-essential structures and site facilities will be dismantled as a continuation of the decomminaioning activity. Foundations i and exterior walls are assumed to be removed to a nominal depth of three feet below grade. This depth of removal allows for clearance of the exposed rebar mats, embedded conduit and piping. and structural steel produced in demolition. The three foot depth also allows for the placement of both gravel for drainage, as well as topsoil so that vegetation can be established for erosion i control. Site areas affected by the dismantling activities will be cleaned and the plant area graded as required to prevent ponding and inhibit the refloating of subsurface materials. Activities include: l

. Demolition of the remaining portions of the primary contamment structure l and interior portions of the Containment. Internal floors (and walls if I above grade) are removed from the lower levels upward, using controlled  !

blasting techniques. Concrete rubble and clean fill produced by demolition l activities may be used to backfillbelow-grade voids. Suitable materials can be used on site for fill; otherwise the rubble is trucked off site for reuse elsewhere. i

. Removal of remaining buildings, including the Turbine, and Service buildings along with other site structures by using conventional demolition techniques.

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d Mrine Yankee Atomic Power St:: tion Document M01-1258-002, Rev. O Decomminaioning Cost Analysis Section 2, Paga 12 ef1* i 1

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2.5 Post-Period 3 -ISFSI Operations and Demolition Following the transfer of the spent fuelinventory from the fuel pool, the ISFSI will continue to operate independently. Transfer of spent fuel to a DOE or interim facility will be exclusively from the ISFSI once the spent fuel storage pool has been emptied and the structure released for decommiasioning.

Assuming initiation of the Federal Waste Management System in 2010, this

study assumes that the DOE will be able to complete the transfer of spent fuel l from the Maine Yankee site by the year 2023.

l The Commission will terminate the $72 license if it determines that site remediation has been performed in accordance with a license termination plan ~

and the terminal radiation survey and associated documentation ' demonstrate that the facility is suitable for release. Once the requirements are satisfied, the NRC can terminate the license for the ISFSI. The area will graded and landscaped to conform with the surrounding environment.

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Maine Yenkn Atsmic Pow 1r Station Documsnt M01-1258-002, Rev.1 Decommiseloning Co:t Analy:is Section 3, Pag 21 ef 0 I

3. COST ESTIMATE A site-specific cost estimate was prepared for decommissioning the Maine Yankee plant. The estic. ate accounts for the unique features of the site, including the NSSS, electric power generating systems, structures, and supporting facilities. The basis of the estimate and its sources ofinformation, methodology, site-specific considerations, assumptions and total costs are described in this section.

3.1 BASIS OF ESTIMATE

I The estimate was developed by identifying specific work areas as the l incremental units. Each accessible area was . visually inspected arid characterized for specific decommissioning characteristics. Specific consideration included material accessibility and egress, radiological conditions, and physical limitations for staging work crews. An inventory and l the attributes of each area were documented. Only a few areas were not accessible for ALARA reasons, these included the pipe tunnel in the auxiliary building and areas around the reactor vessel in containment. These areas

were characterized from schematic drawings and information supplied by plant personnel.

Drawings and other plant documentation were used to plan and schedule activities in high radiation areas and areas currently inaccessible due to the l

plant's configuration. The unit factors, used in developing equipment and component removal costs, were adjusted for the working conditions determined for each area.- Adaptation of the unit factors was accomplished by the manipulation of the duration adjustment variables or " Work Difficulty Factors" (WDF).

Low. level radioactive waste generated in the decontamination and dismantling of the Maine Yankee plant is assumed to be destined for the Barnwell facility.

Current rates of disposal were used. These include a unit disposal cost ranging L from $4.50 to $7.50 per pound of waste and a $0.30 per millicurie surcharge.

l The waste stream is assumed to be conditioned to the maximum extent possible, e.g., through decontamination, volume reduction, incineration, etc., so as to avoid the high cost of direct disposal. Contaminated soil is assumed to be sent to the Envirocare disposal facility in Clive, Utah at a disposal charge of

$87 per cubic foot.

! Spent fuel was assumed to be relocated to an on site ISFSI after approximately 6.5 years of cooling. This allows decontamination and dismantling activities to I

Meine Yankn At mic Powsr Station ,

Document M01-1258-002, Rev.1 Decommissioning Cost Analysis Section 3, Pigs 2 cf 20 l I

proceed on the spent fuel storage areas without the current constraint to maintain spent fuel storage pool systems and services.

Maine Yankee plant structures and facilities will be remediated, dismantled, and demonstrated to be free of contnmination. Site restoration is the most prudent action considering the destructive nature of the decontamination '

processes and the availability of a mobilized and trained work force. -

l MYAPC, as licensee, will oversee the decommissioning operations. The plant staf will be augmented with the necessary resources to ensure a safe and efficient operation. This organization will supervise the decontamination and dismantling of the nuclear unit. Oversight will continue, in a reduced capacity, I during site restoration and beyond to ensure proper management of the spe'n t fuel.

3.2 METHODOLOGY The methodology used to develop this cost estimate follows the basic approach originally advanced by the Atomic Industrial Forum (now Nuclear Energy Institute) in their program to develop a standardized model for decommissioning cost estimates. The results of this program wer2 published as AIF/NESP 036, " Guidelines for Producing Commercial Nuclear Power Plant Decommissioning Cost Estimates," (Ref. 6). This document presents a unit factor method for estimating direct activity costs, simplifying the estimating process. Unit factors for the removal of equipment, concrete, steel, etc., were constructed from the labor cost information provided by MYAPC. The direct activity, or activitv-deoendent. cost can then be estimated using the plant inventory developed for cach work area.

l Appendix A presents the detailed development of a typical site specific unit cost factor. Wage rates were provided by MYAPC, while equipment and consumables were estimated from industry cost guides. Appendix B provides the values contained within one set of factors developed for the Maine Yankee plant analysis.

The unit factors used in this study reflect the latest available data concerning worker productivity'during decommissioning, including field experience from the Shippingport Station Decommissioning Project completed in 1989, as well as from TLG's involvement in the decommissioning planning and engineering l

s for the Shoreham, Yankee Rowe, Trojan, Rancho Seco, Pathfinder, and i, Cintichem reactor facilities.

M-ine Yankee At:mic Poww Station Document M01-1258-002, Rev.1 Decommissioning Ccst Analy:is Section 3, Pag 2 3 ef 50 The unit cost factor method provides a demonstrable basis for establishing

. reliable cost estimates. The detail available in the unit cost factors for activity time, labor costs (by craft), and equipment and consumable costa provides assurance that cost elements have not been omitted. These detailed unit cost factors, coupled with the plant-specific inventory of piping, components and structures, provide a high degree of confidence in the reliability of the cost -

estimates. . -

Work Difficulty Factors

, Work Difficulty Factors (WDFs) were assigned to each erea, commensurate with the inefficiencies associated with working in confined, hazardous environments. The ranges used for the WDFs are as follows:

. Access Factor - 0% to 40%

. Respiratory Protection Factor - 0% to 50%

. Radiation /ALARA Factor - 0% to 100%

. Protective Clothing Factor - 0% to 30%

. Work Break Factor - 8.33%

These factors and their associated range of values were developed in conjunction with the Atomic Industrial Forum's Guideline Study. The factors (and their suggested application) are discussed in more detail in this publication. The WDF assigned to each work area is delineated in Appendix D. l 1

l Scheduline Procram Durations  !

An area-by-area activity duration critical path was used to develop the total decommissioning program schedule. The unit cost factors, adjusted for WDF's as described above, were applied against the inventory of materials to be removed in each defined work area. Each work area was assessed for the most efficient number of workers / crews for the decommissioning activities. These adjusted unit cost factors were applied against the available manpower so that an overall duration for removal of components and piping for each work area could be calculated. The spreadsheets detailing this process for each area are attached as Appendix E. Outlines of the major work areas in the power block are shown in Appendix F.

The program schedule is used to determine the ceriod-deoendent costs for program management, admmistration, field engineering, equipment rental, contracted services, etc. The study relies upon regional, or site-specific salary

' and wage rates for the personnel associated with the intended program.

M-ine Ycnkn Atomic P:wsr Station D: cum nt M01-1:58-002, R:v.1 Decommissioning Cost Anrlysis Sectirn 3, Paga 4 af 30 3.3 FINANCIAL COMPONENTS OF THE COST MODEL TLG's cost model is comprised of a multitude of distinct cost line items, calculated using the unit cost factor methodology described earlier. Period-dependent and collateral costs are added to produce a comprehensive accounting of the identified expenditures. However, the resulting costs in and of themselves do not comprise the total cost to accomplish the project goal of license termination.

l 3.3.1 Contineency Inherent in any cost estimate that does not rely on historical data is the inability to specify the precise source of costs imposed by factors such as tool breakage, accidents, illness, weather delays, labor stoppages, etc. Contingency fn1611a this role in TLG's cost model. Contingency is added to each line item to account for costs that are difficult or impossible to develop analytically. Such costs are historically inevitable over the duration of a job of this magnitude; therefore, this cost analysis includes monies to cover these types of expenses.

The activity- and period. dependent costs are combined to develop the total decommissioning costs. A contingency is then applied on a line-item basis, using one or more of the contingency types listed in Chapter 13 of the AIF/NESP-036 Guidelines Study. This reference also identifies the types of unforeseeable events that are likely to occur in decommissioning and provides guidelines for the application of contingency.

i

" Contingencies" are defined in the American Association of Cost Engineers  ;

" Project and Cost Engineers' Handbook" (Ref. 7) as " specific provision for unforeseeable elements of cost within the defined project scope; particularly important where previous experience relating estimates and actual costs has shown that unforeseeable events which willincrease costs are likely to occur."  :

The cost elements in this estimate are based upon ideal conditions and l maximum efficiency; therefore, consistent with industry practice, a contingency I factor has been applied. It should be noted that contingency, as used in this estimate, does not account for price escalation and inflation in the cost of decommissioning over the program duration.

{

The use and role of contingency within decommissioning estimates is not a  !

" safety factor issue." Safety factors provide additional security and address I situations that may never occur. Contingency funds are expected to be fully 1 expended throughout the program. They also provide assurance that  ;

sufficient funding is available to accomplish the intended tasks. Some of the rationale for (and need to incorporate) contingency within any estimate is

Mrine Yankee Atomic P:wsr Station Documsnt M01-1258-002, R:v.1 Decommissioning Cost Analysis Sscticn 3, Pags 5 of 50 1

offered in the following discussion. An estimate without contingency, or from which contingency has been removed, can disrupt the orderly progression of events and jeopardize a successful conclusion to the decommissioning process.

The most technologically challenging task in decommiasioning a nuclear generating unit will be the disposition of the reactor vessel and internal components, which have become highly radioactive after a lifetime of exposure to radiation produced in the core. The disposition of these highly radioactive components forms the basis for the critical path (schedule) for decommissioning operations. Cost and schedule are interdependent and any deviation in schedule has a significant impact on cost for performing a specific activity.

1 Disposition of the reactor vessel internal components involves the j underwater cutting of complex components that are highly radioactive. Costs j are based upon optimum segmentation, handling, and packaging scenarios.

The schedule is primarily dependent upon the turnaround time for the heavily-shielded shipping casks, including preparation, loading and decontamination of the containers for transport. The number of casks required is a function of the pieces generated in the segmentation activity, a value calculated on optimum performance of the tooling employed in cutting the various subassemblies. The risk and uncertainties associated with this task are that the expected optimization may not be achieved, resulting in delays and additional program costs. For this reason, contingency must be included to mitigate the consequences of the expected inefficiencies inherent in this complex activity, along with related concerns associated with specialty tooling modifications and repairs, field changes, discontinuities in the coordination of plant services, system failure, water clarity, lighting, computer controlled cutting software corrections, etc. Experience in decommissioning other plants in the past has shown that many of these problem areas have occurred during, and in support of, the segmentation process. Contingency dollars are an integral part of the total cost to complete this task. Exclusion of this component puts at risk a successful completion of the intended tasks and, potentially, follow on related activities.

1 The following list is a composite of some of the activities, assembled from Q past decommissioning programs, in which contingency dollars were needed to respond to, compensate for, and/or provide adequate funding of decontamination and dismantling tasks:

M:ine Ycnkee At mic P:werSt: tion Document M01-1258-002, Rev.1 l Decommissioning Cest Analysis Section 3, Pass 6 ef 20

)

i Incomplete or Changed Conditions:

. Unavailable / incomplete operational history which led to a 4

recontamination of a work area, because a sealed cubicle (incorrectly l identified as being non-contaminated) was breached without controls.

. Surface coatings covering contamination which, due to an incomplete characterization, required additional cost and time to remediate.

. Additional decontamination, controlled removal, and disposition of previously undetected (although at some sites, suspected) contamination due to access gained to formerly inaccessible areas and i components.

. Unrecorded construction modifications, facility upgrades, maintenance, enhancements, etc., which precipitated scheduling delays, more costly removal scenarios, additional costs (e.g., for re-engineering, shoring, structural modifications), and compromised l worker safety.

Adverse Working Conditions: l

. Lower than expected productivity due to high temperature environments, resulting in a change in the working hours (shifting to I l

cooler periods of the day) and additional manpower.

. Confined space, low-oxygen environments where supplied air was necessary and additional safety precautions prolonged the time required to perform required tasks.

Maintenance, Repairs and Modifications

. Facility refurbishment required to support site operations, including those needed to provide new site services, as well as to maintain the integrity of existing structures.

. Damage control, repair, and maintenance from birds' nesting and fouling of equipment and controls.

. Building modification, i.e., re supporting of floors to enhance loading capacity for heavily shielded casks.

M:ine Yankee Atomic Pow:r Station Docum:nt M01-1:58-002, Rev.1 Decommissioning Cost Analysis Section 3, Pags 7 cf 20

. Roadway upgrades on site to handle heavier and wider loads; roadway rerouting, excavation, and reconstruction.

. Raquests for additional safety margins by a vendor.

. Requests to analyze accident scenarios beyond those defined by the removal scenarios (requested by the NRC to comply with " total scope of - ~

regulation").

. Additional collection of site runoff and processing of such due to l disturbance of natural site contours and drainage. l i

. Concrete coring for removal of embedments and internal conduit, piping, and other potentially contaminated material not originally I identified as being contaminated. I I

. Modifications required to respond to higher than expected worker I exposure, water clarity, water disassociation, and hydrogen generation from high temperature cutting operations.

. Additional waste containers needed to accommodate cutting particulates (fines), inefficient waste geometries and excess material.

Labor

. Turnover of personnel, e.g., craft and health physics. Replacement of '

labor is costly, involving additional trnining, badging, medical exams, l and associated processing procedures. Rocruitment costs are incurred i for more experienced personnel and can include relocation and living expense compensation.

. Additional personnel required to comply with NRC mandates and requests.

. Replacement of personnel due to non qualification and/or incomplete certification (e.g., welders).

Schedule

. Schedule slippage due to a conflict in required resources, i.e., the licensee was forced into a delay until prior (non licensee) commitments of outside resources were resolved.

, Maine Yankee Atomic Puow Station Document M01-1258-002, Rev.1 L Decomminoloning C:st An: lysis Section 3, Pags 8 ef10 i

i; e Rejection of material by NRC inspectors, requiring refabrication and causing program delays in activities required to be completed prior to i, decommissioning operations.

i' Weather

. Weather-related delays in the construction of facilities required to - '

support site operations (with compensation for delayed mobilization j made to vendor).

. Frozen crane hydraulics prior to a majorlift.

. Destruction of an exterior asbestos containment enclosure due to '

violent winds.

The cost modelincorporates considerations for items such as those described above, generating contingency dollars (at varying percentages of total line-item cost) with every activity.

3.3.2 FmancialRisk l

In addition to the routine uncertainties that contingency addresses, another )

cost element that is necessary to consider when answering the question of decommissioning cost relates to other types and levels of uncertainties. These consist of changes in work scope, pricing, job performance and other variations that could conceivably, but not necessarily, occur. Consideration of such items may be necessary to address the question concerning how costly the decommissioning project could become, within a range of probabilities. TLG considers these types of costs under the broad term "Anandal risk." This cost study, however, does not add any additional costs to the estimate for financial risk. Financial risk is typically addressed through a probability analysis using a Monte Carlo type simulation program. The output of such a simulation typically includes a curve and range of probabilities for various cost estimates.

Included within the category of Enancial risk are:

. Delays in approval of the decommissioning (or license termination) plan due to intervention, public participation in local community meetings, legal challenges, state and local hearings, etc.

. Changes in the project work scope from the baseline estimate, involving the discovery of unexpected levels of contaminants,

r Maine Ycnkee Atrmic Pawsr Statirn Document M01.H58-00?, Rev.1 t Decommienioning Ccet Analysis Section 3, Pags 9 cf 50 i

n i

contamination in places not previously expected, contaminated soil previously undiscovered (either radioactive or hazardous material contamination), variations in plant inventory or configuration not indicated by the as-built drawings.

. Regulatory changes, e.g., affecting worker health and safety, site '

release criteria, waste transportation, and disposal. - -

. Policy decisions altering federal and state commitments, e.g., in the ability to accommodate certain waste forms for disposition, or in the timetable for such.

. Pricing changes for basic inputs, such as labor, energy, materials, and burial. Some of these inputs may vary slightly, e.g. -10% to +20%;

burial could vary from 50% to +200% or more.

It has been TLG's experience that the results of a risk analysis, when compared with the base case estimate for decommissioning, indicate that the chances of the base decommiasioning estimate's being too high is a low probability, and the chances that the estimate is too low is a much higher probability. This is mostly due to the pricing uncertainty for burial, and to a lesser extent due to schedule increases from changes in plant conditions, and to pricing variations in the cost of labor (both craft and staff). TLG did not perform a risk analysis for this estimate and therefore the cost estimate in j this report does not include any additional costs to addressed the perceived i risk.

3.4 SITE-SPECIFIC CONSIDERATIONS There are a number of site specific considerations that affect the method for dismantling and removal of equipment from the site and the degree of restoration required. The cost impact of the considerations identified below is included in this cost study.

3.4.1 Soent Fuel Discosition Currently there are 1434 spent fuel bundles residing in the spent fuel pool.

This decommissioning estimate assumes that this inventory will be transferred to an ISFSI so that decommissioning operations may proceed on the nuclear unit. It is also assumed that the construction of and licensing of the ISFSI will be completed such that all of the fuel has been transferred to this facility by June, 2003. (Approximately 6.5 years following the cessation of reactor operations). This will allow decontamination and dismantling of the facility to

Mdne Yankn At:mic P:wer Station Document M01-1258-002, Rav.1 Decommissioning Cost Andy:is Section 3, P:ge 10 cf $0 proceed without being signWantly constrained by spent fuel caretaking activities. This estimate contains the capital costs required to construct and license the facility as well as to monitor the fuel in dry storage once the $50 license is terminated. The transfer of the fuel assemblies to DOE is not I expected to be completed until the year 2023.

3.4.2 Reactor Vessel and Internal Comoonents The reactor pressure vessel and reactor internal components are segmented for disposalin shielded transportation casks. Segmentation and packaging of the reactor internal components will be performed in the refueling cavity where a turntable and remote cutter will be installed. The vessel will be segmented in place, using a mast-mounted cutter. Transportation cask specifications and Department of Transportation (DOT) regulations will dictate segmentation and packaging methodology.

l The dismantling of reactor internal components at the Maine Yankee plant will generate radioactive waste generally unsuitable for shallow land disposal. This waste is _ generally referred to as " Greater than-Class-C" l (GTCC). Although the materialis not classified as high-level waste, DOE has indicated it will accept title to this waste for disposal at the future high level l

waste repository (Ref. 8). However, the DOE has not yet established an acceptance criteria or a disposition schedule for this material, and numerous questions remain as to the ultimate disposal cost and waste form

requirements. As such, for purposes of this study, the GTCC waste will be

! packaged and disposed of as high level waste, at a cost equivalent to that envisioned for the spent fuel.

3.4.3 Steam Generators and Other Primarv Coolant System Comoonents The steam generators' size, weight, and configurations and the limited access in the Containment itself, place constraints on the intact removal of these '

components. Little or no modifications to the building are necessary for extraction since many of the obstructions are removable panels or equipment.

The existing equipment hatch is large enough to accommodate removal.

Determination of the removal strategy requires several different considerations, including the rigging needed to maneuver and extract the generators, and the component preparations needed to transport the generators to a disposal site.

~ - -- __

Mrine Ycnkee At:mic Pawxr Station Documsnt M01-1258-002, R:v.1 Decommleesoning Cost Analy:is Secti:n 3, Pags il cf 20 A potential method for removal (and the one used for the basis in this estimate)

. is the extraction of the generators in a manner similar to that used for their installation, i.e. through the existing equipment hatch.

The generators will be rigged for removal, disconnected from the surrounding piping and supports, and maneuvered into the open area next to the equipment hatch where they will be lowered onto a dolly. The dolly will allow the lower end of the steam generator to rotate through the opening as it is being lowered.

Once the steam generator has been lowered to the horizontal position, it will be filled with low-density cellular concrete for stabilization of the internal contamination and to satisfy burial ground requirements. Nozzles and other openings will be welded closed. When this stage has been completed, the generator will be lifted onto a multi wheeled transporter and moved to an o'n-site storage facility. The remaining two generators and pressurizer will be removed using the same technique.

Once at the storage area, each generator will have a two-inch thick carbon steel membrane welded to its outside surface for shielding during transport.

The generators will be moved to a barge loading area where the generators on the multi-wheeled transporter will be barged down the east coast to the Barnwell facility. The barge can move up the Columbia River in South Carolina to a point approximately 30 miles from the disposal facility. From there, the generators will be moved the bunal facility with the multi-wheeled transporter.

3.4.4 Main Turbine and Condenser The main turbine will be dismantled using conventional maintenance l procedures. The turbine rotors and shafts will be removed to a laydown area. l The lower turbine casings will be removed from their anchors by controlled i demolition. The main condensers will also disassembled and moved to a laydown area. Material is then prepared for transportation to an off site recycling facility where it will be surveyed and designated for either  :

decontamination or volume reduction, conventional disposal or controlled l disposal. Components will be packaged and readied for transport in  !

accordance with the intended disposition. j i

l 3.4.5 Transoortation Methods j For the purposes of the cost estimate, it was assumed that the low-level radioactive waste produced and destined for controlled disposal will be moved overland by truck or shielded van to the Barnwell facility. The destination selected as the basis for the estimate of transportation costs is Barnwell, South  !

l J

Maine Ycnkr2 At:mic Power St:tien Document M01 1:58-002, Rev.1 Deconunissioning C:st Analysis Section 3, Pag 212 cf 50 Carolina. Transportation of the appropriate waste to a recycling center for estimating purposes is assumed to be Oak Ridge, Tennessee. Transportation of contaminated soilis assumed to be to Clive, Utah.

3.4.6 Low-Level Radioactive Waste Disuosal and Reevele All low-level radioactive waste generated in the decontamination and dismantling of Maine Yankee plant, with the exception of contaminated soil, is assumed destined for disposal at the Barnwell facility. Current base disposal rates were used. This consists of a sliding scale based on the packaging density of the waste as follows:

. Greater than 75 lbs/ft3 and less than 120 lbs/ft3 density $4.50 per pound

. Benveen 60.1 Ibs/ft3 and 75 lbs/ft3 density $5.50 per pound i

. Between 45 lbsift3 and 60 lbs/ft3 density $7.50 per pound j A surcharge of $0.30 per millicurie of waste is also assessed, with a maximum charge of $120,000 per shipment. l To the greatest extent practical, non.compactable low. level radioactive waste i will be conditioned to reduce the volume of material requiring controlled I disposal. Material from which the contamination is removed can be released as I scrap, requirmg no further cost consideration. The remaining material will be l processed the most cost effective methods i.e. further volume reduction or decontamination techniques and then packaged for controlled disposal as radioactive waste. Material / waste recovery and recycling are assumed to be l performed off site at a licensed processing center. Processing costs for metallic waste are reported in the cost estimate as "Other" costs for Plant Systems and Structures. Unit costs for processing metallic components ranged from $1 to $3 per pound, depending upon the handling and pretreatment involved and the required conditioning anticipated.

Compactable DAW, such as booties, glove liners, respirator filter cartridges, shipping containers, radiological controls survey materials, etc. are assumed to be incinerated.

3.4.7 Site Conditions Followine Decommissionine It is assumed that all Maine Yankee structures and site facilities will be dismantled following their decontamination. Structures will be removed to a nominal depth of 3 feet below grade. The voids will be backfilled with clean debris and capped with soil. The site will then be regraded to conform to the

Maine Yankee Atomic Power St: tion Document M01-1258-002, Rev,1 ,

Decommienioning Cost Antlysis Section 3, Pag 213 ef 20 l adjacent landscape. Vegetation would be established to inhibit erosion. The switchyard will remain in place, as will the site access road.

4 8.5 ASSUMPTIONS l l

The following key assumptions were used in developing the decommissioning '

cost estimate for the Maine Yankee plant. -

Estimatina Ensin l

1. The estimate is performed in accordance with the methodology described in the Atomic Industrial Forum - National Environmental Studies Project report AIF/NESP.036, " Guidelines for Producing ' Commercial Nuclear Power Plant Decommiasioning Cost Estimates." (Ref. 6). l 1

2. Decommiasioning costs are reported in the year of projected expenditure; however, the values are provided in 1997 dollars for the current estimate. Costs are not inflated or escalated over the period of performance.

3. Plant drawings, equipment and structural specifications, including

~

construction details, were provided by MYAPC. The inventory of plant equipment was performed on site by TLG personnel.

Labor Costs

1. The craft labor required to decontaminate and dismantle the nuclear unit will be acquired through standard site contracting practices. The current cost oflabor at the site is used as an estimating basis.

I

2. Utility staffing requirements will vary with the level of effort associated with the various phases of the project. Due to a premature shutdown, a large portion of the plant operations and maintenance staffing still exist at the plant. Once the decommissioning program commences, this staff (over a time period of six months) will be reduced to only those staff positions necessary to support the decommissioning program. MYAPC provided the levels of staffing for the project.

3. The costs associated for the transition of the maintenance organization to decommissioning, e.g., separation packages, retraining, severance, incentives, etc., are included in this estimate and were provided by

~

MYAPC.

l McIne Yankee Attmic Pow:r Stati:n Document M01-1:58-002, R:v.1 Decommissioning Cost Analysis Section 3, Page 14 of 20

4. LEAPC, as licensee, will oversee the decomminsioning operations. Site security, radiological controls and overall site adminiatration during l decommissioning and dismantling will be provided by hEAPC. This I organization will be supplemented with the expertise necessary to I

ensure that the intended program is completed safely and successfully.

i

5. Costs for site administration, operations, construction and maintenance )

personnel are based upon current hEAPC salary information, supplied I l by MYAPC. ,

l 1

6. Engmeermg services for such items as writing activity specifications, i detailed procedures, and work procedures are assumed to be provided by l i

contracted employees experienced with decommissioning operations 'to i augment the MYAPC decommissioning staff.

Desien Conditions

1. Any fuel cladding failure that occurred during the lifetime of the plant is

' assumed to have released fission products at sufficiently low levels that the buildup of Quantities of long lived isotopes (e.g. cesium 137,  !

strontium 90, or transuranics) has been prevented from reaching levels i exceeding those which permit the major NSSS components to be shipped under current DOT regulations and to be buried within the requirements of j61.

2. The estimated curie content of the vessel and internal components were '

derived from those listed in NUREG/CR 3474 (Ref. 9). Actual estimates were derived from the Ci/ gram values in NUREG/CR-3474 and adjusted for the different mass of the Maine Yankee components, operating life, l and periods of decay. Additional short lived isotopes were derived from NUREG/CR-0130 (Ref. 10) and NUREG/CR-0672 (Ref. 11) and benchmarked to the long lived values from NUREG/CR 3474.

l

3. Segmentation of the reactor vessel internal components will produce a limited quantity of activated materialin which radionuclide inventories will exceed Class C quantities, as defined i61. The GTCC material is generally not suitable for shallow land disposal and will most likely be disposed of as high-level waste in the DOE's geological repository (unless an alternative solution is approved by the NRC). The cost of disposal, unhke that for the spent fuel, is not addressed by DOE's 1 mill / kwhr surcharge. As such, the disposal cost for GTCC presumes the packaging of this material in canisters similar to those used for spent fuel and disposed of at an equivalent cost.

l Maine Yankee Atomic P wxr Station Docum:nt M01-1258-002, Rw.1 Decommineioning Cost Analysis Section 3, Page is cf 20 s

Transportation

1. Contaminated piping, components, and structural material other than the highly activated reactor vessel and internal components will qualify as LSA.I, II or III or SCO.I or II, as described in Title 49 of the Code of Federal Regulations, Section 173 (Ref.12). The contaminated material l will be packaged in Industrial Packages (IP I, II or III) for transport unless demonstrated to qualify as their own shipping containers. The l

reactor vessel and internal components are expected to be transported in h accordance with $71, as Type B. It is conceivable that the reactor, due to its limited specific activity, could qualify as LSA II or III. However, the high radiation levels on the outer surface would require that additional b shielding be incorporated with the packaging so as to attenuate the dose o to levels acceptable for transport.

l 2. Material requiring controlled disposal is assumed to be routed to the i j Barnwell facility located in Barnwell, South Carolina. Contaminated

! metallic waste will be routed to a recovery / recycling facility for ,

decontamination and volume reduction. Contaminated soil will be l shipped to the Envirocare Facility in Clive Utah. Transportation costs I are based upon published tariffs from Tri-State Motor Transit (Ref.13).

ll Truck transport assumes a maximum normal road weight limit of l

!!' 80,000 pounds for all shipments with the exception of the overweight

! shielded casks. Rates for shipping radioactive wastes were provided by l' Tri. State Motor Transit in published tariffs for this cargo.

3. Large components such as the steam generators and pressurizer are assumed to be barged to the Barnwell facility. The cost of barging was based on similar large component removal projects.

4. Transport of the highly activated metal, produced in the segmentation of the reactor vessel and internal components, will be by shielded truck cask. Cask shipments may exceed 95,000 pounds, including vessel segment (s), supplementary shielding, cask tie. downs and tractor trailer.

The maximum number of curies per shipment assumed permissible is based upon the license limits of available shielded shipping casks. The  ;

number and curie content of vessel and internal segments are selected to meet these limits.

5. The number of cask shipments out of Containment is expected to

.s average two every three weeks. Non cask shipments will be limited to

! three per week.

l

M:Ine Yankee Atomic Pow 2r Statisn Documsnt M01-1258-002, Rev.1 Decomminoloning Cost Analysis - Section 3, Page 16 of 20 Soent Fuel

1. The cost to remove and dispose of the spent fuel from the site is not

. reflected within the estimate to decommission the Maine Yankee plant.

Ultimate disposition of the spent fuelis the province of the DOE's Waste Management System, as defined by the Nuclear Waste Policy Act. Any delay in the transfer of spent fuel would increase the on-site management costs.

2. An ISFSI is assumed to be constructed at the site. The spent fuel is assumed to be transferred from the fuel pool to the ISFSI by June 2003, l so as not to significantly interfere with the decommissioning process.

The costs associated with the operation and maintenance 'of the spent fuel in the ISFSI are reflected within this estimate. Caretaking costs include staffing, insurance, taxes and fees as well as costs associated with final disposition of the facility.

3. The ISFSI design will utilize a multi-purpose (storage and transport),

dry shielded storage canister with a vertical, reinforced concrete storage silo. Approximately one half of the internal stainless steel liners are assumed to become activated over the storage period of the fuel. The cost of the disposition of this material, as well as the remainder of the ISFSI facility is included in the estimate.

4. GTCC material, generated in the segmentation of the reactor vessel internal components, is assumed to be stored in the ISFSI to await transfer to the geologic repository.

_ General

1. The existing plant equipment is considered obsolete and suitable for scrap as deadweight quantities only. No equipment is salvageable as used equipment.

2. Scrap generated during decommissioning is not included as a salvage credit line item hi this study for two reasons: (1) the scrap value merely l offsets the associated site removal and scrap processing costs, and (2) a l relatively low value " scrap exists in the market. Scrap processing and site removal costs are not included in the estimate.

l l 3. MYAPC will provide for the on site electrical power required to demolish the plant to be brought on site. For estimating purposes the plant is

Mdne Yankee Atomic P:wir Stati:n Docum:nt M01-H58-002, Rev,1 Decommincioning Cost Analyzis Section 3, Page 17 of 20 i

i assumed to be de4nergized. Replacement power costs are used to l estimate the cost of consumption during decommiasioning.

1

4. Current plant staffing will remove all items of furniture, tools, mobile  !

equipment such as forklifts, trucks, bulldozers, other similar mobile equipment, and other such items of personal property owned by MYAPC that will be easily removed without the use of special equipment at do  !

cost or credit to the project.

5. Existing warehouses will be cleared out of non essential material and remain for use by MYAPC and its subcontractors. The warehouses may be dismantled as they become unnecessary to the decommiasioning program.

6. Current MYAPC staffing perform the following activities at no cost or credit to the project during the first six months of the planning period:

. Fuel oil tanks will be emptied. Tanks will be cleaned by flushing or steam cleaning as required prior to disposal

. Acid and caustic tanks will be emptied.

. Lubricating and transformer oils will be drained and removed from site by a waste disposal vendor.

7. The decommissioning activities will be performed in accordance with the current regulations assumed to be in place at the time of decommissioning.

8. Material and equipment costs for conventional demolition and/or i

, construction activities were taken from R.S. Mean Construction Cost Data (Ref.14).

9. The study follows the principles of ALARA through the use of work duration adjustment factors, which incorporate such items as radiological protection instruction, mock.up training, the use of respiratory protection and personnel protective clothing. These items lengthen a task's duration, which increases the costs and lengthens the ,

overall schedule. ALARA planning is considered in the costs for i engineering and planning, and in the development of activity specifications and detailed procedures. Changes to $20 worker exposure limits may impact the decommissioning cost and projects schedule.

10. Nuclear liability insurance provides coverage for damage or injuries due to radiation exposure from equipment, material, etc. used during

M ine Yankee Atomic P:w:r Station Docum:nt M01-1258-002, Rev 1 Decommienioning Cost Ancly:is Section 3, Pag 217el20 assumed to be de-energized. Replacement power costs are used to estimate the cost of consumption during decommissioning.

4. Current plant staffing will remove all items of furniture, tools, mobile equipment such as forklifts, trucks, bulldozers, other similar mobile equipment, and other such items of personal property owned by MYAPC that will be easuy removed without the use of special equipment at so cost or credit to the project.

5. Existing warehouses will be cleared out of non-essential material and remain for use by MYAPC and its subcontnctors. The warehouses may be dismantled as they become unnecessary to the decommiasioning program.

6. Current MYAPC staffing perform the following activities at no cost or credit to the project during the first six months of the planning period:

. Fuel oil tanks will be emptied. Tanks will be cleaned by flushing or steam cleaning as required prior to disposal.

. Acid and caustic tanks will be emptied.

. Lubricating and transformer oils will be drained and removed from site by a waste disposal vendor.

7. The decommissioning activities will be performed in accordance with the current regulations assumed to be in place at the time of decommissioning.

8. Material and equipment costs for conventional demolition and/or construction activities were taken from R.S. Mean Construction Cost Data (Ref.14).

9. The study follows the principles of ALARA through the use of work duration adjustment factors, which incorporate such items as radiological protection instruction, mock up training, the use of respiratory protection and personnel protective clothing. These items lengthen a task's duration, which increases the costs and lengthens the overall schedule. ALARA planning is considered in the costs for engineering and plannmg, and in the development of activity specifications and detailed procedures. Changes to j20 worker exposure limits may impact the decommissioning cost and projects schedule.

10. Nuclear liability insurance provides coverage for damage or injuries due to radiation exposure from equipment, material, etc. used during

Maine Yankee Atomic Pcw:r Stxtion Document M01-1258-002, Rev.1

. Decommincioning Cost Ansly:is Section 3, Pags 18 ef 50 decommissioning. Nuclear liability insurance is phased out upon final

. decontamination of the site. Current nuclear liability and property insurance premiums are adjusted to reflect the increased activity during the decommissioning program. Nuclear property insurance will cease  !

upon termination of the $72 license.

11. The perimeter fence and in-plant security barriers will be moved as appropriate to conform with the Site Security Plan in force at the various stages in the project.

i

12. The existing electrical switchyard will remain after decommissioning in support of the utility's electrical transmission and distribution system. l The 115 Kv switchyard is assumed to be dismantled and is included in l this estimate.

13. Underground concrete pipe will be decontaminated and abandoned.

Underground steel pipe will be removed completely, surveyed for contamination, removed from the site, and disposed of as clean scrap.

. Electrical manholes are backfilled with suitable earthen material and abandoned.

i

14. All site vestiges are assumed to be removed to a nominal depth of three feet below grade level, with the non-contaminated subgrade foundations remaining in place. Holes will be drilled in each of the foundation basemats to allow for natural drainage. Building foundations will be backfilled with clean demolition debris, and the site will be graded and landscaped.

15. Contaminated metallic waste suitable for recycling will be sent off site to a waste recovery / recycling vendor for the most economical methods of processing to reduce the volume sent for burial.

16. The disposition of all hazardous waste currently stored on-site is included in this estimate. hlYAPC supplied the quantities of this waste, including quantities of asbestos.

17. Clean asbestos is disposed of in a licensed local landfill authorized to accept asbestos. Contaminated asbestos is buried as radioactive waste.

3.6 COST ESTDIATE SUhDIARY A summary of the radiological decommissioning costs and annual expenditures is provided in Table 3.1. Table 6.1 provides a breakdown of those same

_ _ - - - .. . . - - - - - ~ - . - - - - . - - . - - - - . - - - .. - - - . . .

Mdne Yankee Atomic P:w:r Station Docum:nt M01-1558-00 *, Rw.1 Decommineioning Cost Analysis Section 3, Pags 19 cf 20 ra@el=ical costs into the components of decontamination, removal, paelraains transportation, waste disposal, project management (staffing), and other. The costs were extracted from the detailed report in Appendix C, which provides a detailed listing of activities and associated costs for the decommissioning scenario. The following should be considered when reviewing this table:

e "Decon," as used in the headings of these tables, refers to decontamination activities as opposed to the NRC term DECON, which refers to the prompt removal decommissiening scenario.

e " Total," as used in the headings of these tables, is the sum of Decon, Remove, Pack, Ship, Bury, and Contingency, as well as other Miscellaneous items not listed (such as engineering and preparations).

• The subtotal for the aforementioned major cost categories does not include contingency, which is reported in a separate column.

. "Other" includes different types of costs which vary by the associated

• line item and do not readily fall into one of the other categories. For instance, in systems removal and structures decontamination, the

- "Other" cost consists of the off site recycling costs for low level radioactive waste. "Other" also includes the utility stafEng, taxes, insurance, plant energy budgets, and regulatory fees.

- ,- ,- - - - - . - , , _ . =- , - ,

Milne Yankee Atomic Poseer St: tion Document M01-1258-00?. Rx,1 Decommissioning Cost An: lysis Section 3, Pags %C of10 TABLE 3.1 SCHEDULE OF DECOMMISSIONING EXPENDITURES (thousands of1997 dollars)

Period 1 Period 2 Period 3 Post Period 3 . .

Year Properations E- She Resterodon Dry Fuel Storege Totels

• 1997 0 0 1998 31,843 31,843 1999 45,542 29,190 74,732 2000 81,494 81,494 2001 80.299 80,299 2002 69,630 69,630 2003 66,026 66,026 2004 2.896 19,647 22,543 2005 6,249 2,576 8,825 2006 3,702 3,702 2007 3,702 3,702 2008 3,712 3,712 2009 3,702 3,702 2010 3,702 3,702 2011 3,702 3,702 2012 + 3,712 3,712 2013 3,702 3,702 2014 3,702 3,702 2015 3,702 3,702 2016 3,712 3,712 2017 3,702 3,702 2010 3,702 3,702 2019 3,702 3,702 2020 3,712 3,712 2021 3,702 3.702 2022 3,702 3,702 2023 9,861 9,861 77,365 329,536 25,696 75,404 50s 221 ia

• Columm may not add due to rounding.

4

e. , 4

/

~

M:ina Yankee Atomic P:wer P!:nt Document M01-1258-002, Rev. 0 Decommissioning Cost Analysis Section 4, Pag 2 lef10

4. SCHEDULE ESTIMATE The schedule for the decommiasioning scenario considered in this study follows the sequence presented in the AIF/NESP-036 study, with minor changes to reflect recent experience and site-specinc constraints. In addition, the scheduling has been revised '

to reflect the spent fuel management plan outlined by MYAPC.

Figure 4.1 presents a schedule for the decommissioning alternative; the assumptions supporting this schedule are listed in Section 4.1. The key activities listed in the schedule do not reflect a one-to-one correspondence with those activities in the Appendix C cost table, but reflect dividing some activities for clarity and combining others for convenience. A legend defining the schedule nomenclature and depictions is also included. The schedule was prepared using the "Microsoft Project for Windows" computer software (Ref.15).

4.1 SCHEDULE ESTIMATE ASSUMPTIONS The schedule estimate reflects the results of a precedence network developed for the site decommissioning activities, i.e., a PERT (Program Evaluation and Review Technique) software package. The durations used in the precedence i network reflect the actual man hour estimates calculated for each area These man hour estimates for each area are shown in Appendix E. The maximum number of work crews were determined for each area to determine the total duration based on specific area WDFs. The schedule was then assembled, connecting a logical path of work areas with consideration of work crew availability and material access / egress. The following assumptions were made in the development of the decommissioning schedule. l l

. The fuel handling facilities will be isolated to serve as an interim wet  ;

fuel storage facility until such time that all spent fuel has been discharged from the spent fuel pool assumed to be in June, 2003.

Decontamination and dismantling of the fuel handling facilities are initiated once the transfer of spent fuel to the dry storage is complete.

• All work (except vessel and internals removal) is performed during an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> workday,5 days per week, with no overtime. There are eleven paid holidays per year.

. Vessel and internals removal activities are performed by using separate crews for different activities working on different shifts, with a corresponding backshift charge for the second shift.

Maine Yankee Atomic P:w:r Plant Document M01-1258-005!, R:v. O Decommissioning C:st Anclysis Section 4 Page 2 of10

. Multiple crews work parallel activities to the maMmum extent possible, )

consistent with: optimum efficiency; adequate access for cutting,  !

removal and laydown space; and with the stringent safety measures necessary during demolition of heavy components and structures. l l

. For removal of plant systems by area, the areas with the longest removal durations on the critical path are considered to determine the ~ .

duration. l 4.2 PROJECT SCHEDULE The period-dependent costs presented in the cost table in Appendix C are based upon the durations developed in the schedule the decomminaioning project.

Durations are established between several milestones in each project period; .

these durations are used to establish a critical path for the entire project. In l turn, the critical path duration for each period is used as the basis for determining the total costs for these period dependent items.

. A pr6 ject timeline for the decommissioning alternative is included in this section as Figure 4.2.

l M:ine Yankee Atomic Power Plant Docum:,nt M01-1258-002, Rev. 0 l Decommissioning Cost Analysis Section 4 Pag 2 3 ef10 l

l FIGURE 4.1 i 1 DECOMMISSIONING ACTIVITY SCHEDULE i

l D TamerName 19fT l 100S o l 1900 l 2000 l 2001 l 2002 l 2003 2004 l 2006 1 Pwed 3 Preparagone 2 LCRP/RVAJR Properadons M

3 LCRP in Contamment g 4 RVAIR 5 CB2-1 6 CB1-8

~3 7 CB1-2 g i 8 CB1-3 9 CB1 1

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10 CB1-4 g 11 CB1-5 g 12 CB17 g:

13 CB31

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14 CB3-2 y 15 CB3-3 g 16 CICl li 17 CPLE

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18 CCG 18 CB3-4 bi I 20 CS DECON .11 21 PUSA l

22 PUHV g 23 PUFN }

l 24 PUL 0

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l  ;

27 PUWG g l

i 23 PU48 g  ;

Project Mame Yankee Atomic Power P1 Cntical l l Task Ie ea -l Milestore $

M:Ine Yankee Atomic Power Plant Document M01-1258-002, Rev. 0 Decommissioning Cost Analysis Section 4 Pag 2 del 10 FIGURE 4.1 DECOMMISSIONING ACTIVITY SCHEnULE (Continued)

E) Task Name 1987 l 1000 1000 l 2000 l 2001 l 2002 l 2003 i 2004 l 2005 20 PUEC

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propct Meene Yankee Atomic Power Pi Critical l - l Task [ os: a b OA'l Milestone $

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, M:ine Yankee Atomic PowerPlant Document M01-1258-002, Rev. 0 Decommissioning Cost Analysis Section 4, Pag 2 5 cf10 l

FIGURE 4.1 DECOMMISSIONING ACTIVITY SCHEDULE (Continued)

D TaskName 1987 l 1000 1000 l 2000 ,

2001 l 2002 l 2003 l 2004 l 2006 57 EFPR l . .-

50 SBSR l

80 S8DR i

l 80 RMCC l

41 SVH g 82 CPHO 63 SPRS y 64 CEHO g SE Mem Transformers (X1/X24) g

$$ CW1 t 87 F1 l

88 CST SS STFB g 70 CONTAMINATED Soll REMOVAL g 71 NFIA l

72 RMCC DECON l

73 SVH DECON l

74 SPRS DECON g 75 TDSN g 76 TMSR g 77 MTGE .

78 FWH 73 TOBV I l

80 TDRW l

81 TDSS  ;

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. l l 83 TCTP i l  !

84 TCTU y i j

Protect Maine Yankee Atornic Power P1 Cntical l l Task l ^-a> . 'l Milestone (

I M:ine Yankee Atomic Power Plant Document M01 1258-002, Rev,0 DecommieSioning Cost Analysis Section 4, Pag 2 6ef10 l

l FIGURE 4.1 DECOMMISSIONINGACTIVITYSCHEDULE (Continued)

D Task Name ~1987 l 1800 1000 2000 li 2001 2002 l 2003 i 2004 l 2000

" ** B ..

Se TMEC g 87 TWOW g 30 ,

TMNC g to TMGL g 90 TMLT g 91 TMOV g 92 TMSE g M WW {

94 TMCH g 96 TMHO 96 TMWC g 97 TMWT g M WM g 99 TMFR 100 TMFA 101 TBRN g 102 TBR2 g 103 TSRU 104 TSRP g 105 ABR

{

104 CSR g 107 TBMS g 108 TBWT 109 DG2

'l i i 110 TCBA g 111 TC:A g I

112 TACA {

Pro # Mane Yankee Atomic Power Pi Critical I ,  :

l Task l-.< a 4 *:rj Maestone $

M:.ine Yankee Atomic PowerPlant Document M01-1258-002, Rev. O Decommiseloning Cost Analysis Section 4, Pag 2 7ef10 FIGURE 4.1 bECOMMISSIONING ACTIVITY SCHEnULE (Continued)

D TasitName 1887 l 1888 1 1888 1 2000 2001 l 2002 l 2003 l 2004 l 2006 113 TSLO g 114 TP2C j 118 TCNE gj i

its TCSE g 117 TBSO

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its TSPP g its TCPA g TFPA 120

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121 THOT

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122 TCOA 123 THEA .

124 TCA l

125 TBP

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128 TB DECON l

127 FUEL TO ORY STORAGE $

128 PAB DECON g 12s TBOA

-Q 130 TBOB y 131 SFPH g 132 RCAD j l 133 SFP Q 134 MCR f y 136 FBP  :  !  ;

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133 SBHP l 140 RCAW -

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McIn2 Yrnk 3 AtomicPowerPI:nt Document M01-1H8-002, R:w. 0 Dec:mmissioning Cost Analysis . Section 4, Paga 8 ef 10 l

l FIGURE 4.1 l

DECOMMISSIONING ACTIVITY SCHEDULE (Continued) l E) Task Name 1987 l 1988 l 1989 l 2000 2001 2002 1 2003 l 2004 l 2006 141 SBP l

142 SERVICE BUILDING DECON g 143 Finish of Final Survey 144 GH Systeme Removal

l. )l j

145 FOB Systeme Removal jg ide FPH Systems Removal -

l l 147 STP Systems Removal l l 148 Co.; mrera Interior Comolibon

{

l 148 PAB Interior Demolition 160 Turbine Building interior Demolition l

161 Fuel & RCA Interior Demoison g 162 Service Building Interior Demolition g 163 Equipment Hatch Interior Demolition ij l

164 Spray Building Interior Demoison p 166 Personnel Hatch Interior Demoiition

!l I

Steem Valve House Interior Demolition 166

]

167 Reactor MCC Room Interior Demolition 168 LSA Stronge Interiorcemolition Turbine Building Exterior Demoittion 169 0

160 Tubine Bulding Pedestal Demoittion

{

Turbine Building Backftll 141 l

162 Fuel & RCA Exterior Demoison g its Fuei & RCA Bacflu i' ,j i

164 LSA Storage Exterior comoison

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164 LSA Storage Backfin l

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144 Equipment Hatch Extenor Demolition  !

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147 Equipment Hatch BackfiR l

168 Spray Euilding Exterior Demolibon

{ l Project Maine Yankee Atomic Power P1 Catical 1 -

l Task I ->i*cwW W':,l Milestone

M:Ine Ycnkee Atomic PowerP!: nt Document M01-1258-002, Rev. O Dec:mmissioning Cost Analysis Section 4, Pagn 9if10 FIGURE 4.1 DECOMMISSIONINGACTIVITYSCHEDULE (Continued)

D Task Name 1887 l 1888 1 1880 l 2000 l 2001 l 2002 l 2003 2004 l 2006 its Spray Budding BackflB l

170 Personnel Hatch Exterior Demosuon g- '

171 Personnel Hatch BacMB l

172 Anadliery Building Extenor Demoenon g 173 Auxiliary Budding BacMD l

l 174 Steam Valve House Ext. Demoittion g 178 Steam Valve House Backfill g 178 Service Building Extenor comontion l

177 Service Building BacidiD l

173 Reactor MCC Extenor Demoution l

179 Reactor MCC BarMD 180 Reactor Building Exterior Demolition .g 181 Reactro Building Backfill l 182 Project Off!ce l 183 Landscape site 0 iu .no ,+

184 198 187 its 189 190 191 ,

. 3 192 193 l 1

184 196 1H

! Project Mame Yankee Atome Power Pt Cntical 1 i l Task I Aul- w e+ 9l Milestone $

l l

l

Maine Yankee Atomic PosserPirnt Document M01-125M02, Rev. O Decommiseloning Cost Analysis Section 4, Pag 210 ef10 FIGURE 4.2

. DECOMMISSIONING TDfETJNE 4

Wet Fuel Storage  ; 4 Dry Fuel Storese N Shutdown Period 3 Post Period 3 W1 2 Operation Surwy Dry M SW NSSS Post NSSS g 1972 1996 1997 1999 2001 2003 2004 2006 2023 Dec Dec Aus Aug June Oct Jan Apr Nov 2003 Ju2e Fuel to Dry Storage 4

4 4

M:Ine Yankee At:mic P:wer Station Document M01-n58-00*, Rev. O Dec:mmissioning Cost Analysis Section 5, Pags i cf 4 i

l

5. RADIOACTIVE WASTES l

The goal of the decommissioning program is the removal of all radioactive material from the site which would restrict its future use or termination of the NRC license.

This currently requires the remediation of all radioactive material at the site in excess of applicable legal limits. Under the Atomic Energy Act (Ref.15), the NRC is

! responsible for protecting the public from sources ofionizing radiation. Title 10 of the Code of Federal Regulations delineates the production, utilization, and disposal of l

radioactive materials and processes. In particular, j61 controls the bunal oflow-level radioactive material and j71 defines radioactive material.

l The radioactive waste volumes generated during the various decommissioning activities at the site are shown by line activity in the cost table in Appendix C. Waste volume summaries, shown in Table 5.1, are quantified consistent with g61 l

classifications. The volumes are calculated based on the gross container dimensions or, for components serving as their own waste container the volume is calculated based on the displaced value of the component.

Contaminated piping,. components and structural material, other than the highly-activated reactor vessel and internal components, will qualify as LSA I, II or III or SCO I or II, as described in Title 49 of the Code of Federal Regulations, Section 173.

The contaminated material will be packaged in Industrial Packages (IP I, II or III) for transport unless demonstrated to qualify as their own shipping containers.

For this study, commercially.available steel containers are presumed to be used for the disposal of piping, small components, and concrete. Larger components can serve as their own containers with proper closure of all openings, access ways, penetrations, etc. The reactor vessel and internals will be shipped in reusable shielded truck casks with disposable liners. In calculating disposal costs, the burial fees are applied against the liner volume, as well as the special handling requirements of the payload.

Packaging efficiencies are lower for the highly activated materials where high concentrations of gamma emitting radionuclides limit the capacity of the shipping canisters.

The waste volume generated in the decontamination and dismantling of the nuclear units is primarily generated during Period 2 of the decommissioning process.

Noncompactable (metallic) radioactive waste generated from removal of the plant equipment is assumed to be sent to an off. site vendor for recycling as a means of reducing the ultimate disposal volume. Considering typical plant conditions and industry experience, the inventory of contaminated material at the Maine Yankee

Maine Yenkn Atomic Pawar Station Document M01 1258-002, Rev. 0 Decommissioning Cost Analysis Section 5, Pag 2 ?ef 4 plant will be segregated based on the likelihood of volume reduction and decontamination for radiological free release.

Contaminated and activated material will be characterized on site with a signi&a.nt volume routed for additional processing. The material which is considered potentially contaminated when removed from a Radiologically Controlled Area (RCA) is sent to an an off-site vendor for processing. The vendor will first survey all material to determine which meet free release limits and those materials that need further i processing. After this initial survey material will be sorted into groups for similar processing that the vendor deems applicable dependant on the type of material and type of contamination. These processes include decontamination, volume reduction, and smelting of the waste. Figure 5.1 illustrates the processes of hadling and treating the waste once the material has been removed and sent off site for processing.

Low-level radioactive waste is destined for final disposal at the Barnwell facility.

Current base disposal assessed by the Barnwell facility were used to determine the burial cost. These rates consist of a sliding scale based on the packaging density of the waste as follows:

e Greater the 75 lbs/ft3 and less than 120 lbs/ft3 density $4.50 per pound

. Between 60.11bs/ft3 and 751bs/ft3 density $5.50 per pound e Between 45 lbs/ft3 and 60 lbs/ft3 density $7.50 per pound A surcharge of $0.30 per millicurie of waste is also assessed, with a maximum charge of $120,000 per shipment.

Compactable DAW, such as booties, glove liners, respirator filter cartridges, shipping containers, radiological controls survey materials, etc. are assumed to be incinerated.

The burial volumes reported in Table 5.1 reflect the savings resulting from reprocessing and recycling. Off site processing of non compactable metallic waste was estimated on a per pound basis, based on industry experience, and appears as an "other" cost in the detailed decommissioning cost tables in Appendix C.

A

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M:Ine Y:nkee Atomic Patur Station Document M01-1258-002, Rev,0 Decommissioning Cost Analysis Section 5, Pag 2 3 cf 4 TABLE 5.1

' DECOMMISSIONING RADIOACTIVE WASTE BURIAL VOLUMES Waste Volume 2 Classi (Cubic feet) . .-

1 A 179,263 l

B 14,561 C 1,564

>C 227 Total 195,615 i

4 1 Waste is classified according to the requirements as delineated in Tide 10 of the Code of Federal Regulations, Part 61.55 8 Columns may not add due to rounding.

i i

- .~. . .._.. .- .- -- .. - . -. . . ~ . .- . . - - . - . . . . . . . . - . .

1 Maine Yankee Atomic Power Station Document M01-1253-002, Rev. O Decomminotoning Cost Analysis Section 5, Page 4 of 4 1 1

1 i

l FIGURE 5.1 LOW-LEVEL RADIOACTIVE WASTE PROCESSING FLOW CHART 9

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M:inz Yanhes Atomic Pow:r Station Docum:nt M01-H53-n', Gev.1 Decrmmissioning Cost .Analy:is Section 6, Pays 1 af 5

6. RESULTS The cost projected to decommission the Maine Yankee plant, for the scenario evaluated, is approximately $508.2 million. The scenario constructed for this analysis assumes that MYAPC will initiate decontamination and dismantling activities in August of 1997. The cost includes the siting, construction and operation of an ISFSI.at l the site. Availability of this facility will allow decommissioning to proceed on the primary gener'ating plant and termination ofits operating license in the shortest time i possible. The cost reflects the site-specific features of the Maine Yankee plant, the i local cost oflabor, DOE's rate of acceptance for the spent fuel currently stored on site, and disposal of the low-level waste generated during decommissioning at the Barnwell I

facility in South Carolina.

The major cost contributors to the cost of decommissioning the Maine Yankee plant are summarized in Table 6.1. Staffing represents the largest single contributor to the overall cost. The magnitude of the expense is a function of both the size of the organization, presumed as necessary to manage the decommissioning, as well as the program duration. The size of the current operating organization is assumed to be reduced to less than 400 individuals by the start of decommissioning. Further reductions over the two year planning phase result in an staff of approximately 160 individuals. This organization is designated to support the active decontamination and  !

dismantling activitie-s scheduled to begin in August of 1999. The organization is I assumed to be self sufficient, providing the resources and expertise needed to manage l decommissioning operations as well as maintaining all essential corporate functions. ,

The staff is further reduced once the operating license has been terminated, for I conventional demolition and site restoration. Once decommissioning has been completed, MYAPC will maintain only those individuals required to support the ongoing transic of spent fuel to a DOE facility and ultimately, the decommissioning of the storage facility.

1 The disposal of low level radioactive waste represents the next largest contributor to the total program cost. For purposes of this analysis, the waste generated from decontamination and dismantling of the Maine Yankee plant was assumed to be disposed of at the currently operating facility in Barnwell, South Carolina. This facility has an established pricing schedule and is currently accessible to MYAPC.

With the high cost of controlled disposal, a large percentage of the contaminated material generated during decommissioning was first routed to a waste recycling / recovery center for pre processing. Pre treatment of the waste signuicantly reduced the volume of material ultimately designated for controlled disposal at the Barnwell facility. Contaminated soil removed from the site was assumed te be disposed of at Envirocare's facility in Utah.

- Mrina Yankn Atomic P;wsr Station Document M01-1258-002, kv.1 Dec:mmissioning Cost Anslysis Section 6, Pags 2 cf 5  :

. i l

)

Removal costs are primarily driven by the cost of labor. The costs identified in this analysis reflect composite labor costs for the Maine Yankee plant, as supplied by MYAPC. Materials and consumables associated with the removal activities were included using representative costs for the region. Productivity adjustments were based upon the working conditions identified for the particular plant area or major component through an on site evaluation.

The siting, construction and licensing of an ISFSI on site was presumed in tl$is analysis as a means to facilitate the decommissioning of the plant. With the spent fuel in the current wet storage pool, dismantling activities are restricted with limited i application of destructive processes. Relocation of the fuel to dry storage releases the fuel storage building for decommissioning. Storage of the fuel under a separate license provides additional flexibility in the event DOE is not able to meet it current commitments for completing the transfer of assemblies to an off-site facility and minimius the associated caretaking exoenses incurred by IWfAPC.

1 Waste conditioning and recycling costs are associated with the preconditioning and j volume reduction of the contaminated material generated from the decommissioning l

[' process. Recovery rates and processing costs are based upon currently available information from waste recyclers, although performance data is highly dependent upon the characteristics of the particular waste stream analyzed. With increased competition from the waste recyclers and decreasing volumes (and revenues), the Barnwell facility modified their past pricing policies for controlled disposal from one of volume to one based upon weight. This effectively mitigated the advantages of volume reduction, unless the mass is also reduced, e.g., through decontnmination and free-release of the material.

4 Contracted security services are identified as a separate line item expenditures in this analysis. While the staffis greatly reduced from operating levels, there remains a need to control personnel and material throughout the decommissioning program, while the plant's operating license remains in effect. Security is also required as long as spent fuel resides at the site. While cross. training, a reduced protected area and revised technical specifications have effectively reduced the size of the security force at other decommissioning sites, a significant number of personnel is still required to process the work force identified in this analysis and ensure public health and safety through the monitoring of material entering and leaving the site.

Non radiological demolition is a natural extension of the decommissioning process.

The methods employed in decontamination and dismantling are generally destructive and indiscriminate in inflicting collateral damage. With a work force mobilized to i

support decommissioning operations, non radiological demolition can be an integrated

)

w./ activity and a logical expansion of the work being performed in the process of 4 terminating the operating license. Prompt demolition reduces future liabilities and can

-~ . -. . ..

Mrine Ycnkee Atomic Pow 1r Section Docum:nt M01-258-002, Rev.1 Decommissioning Ccat Analy:is Section 6, Pag 2 3 cf 5 be more cost effective than deferral, due to the deterioration of the facilities (and therefore the working conditions) with time, Waste is transported to recycling centers and for controlled disposal primarily by truck. Large components such as the steam generators and pressurizer are moved to South Carolina by barge and with an overland transporter to the final burial site.

Intact shipment of the generators by rail was prohibited by the exterior dimensions.of the package and the clearances required by the railroad.

Decontamination was used to reduce the plant's radiation fields and minimi= worker exposure. On-site decontamination did not reduce the volume of contaminated material generated in the decommissioning process, except in instances where non-contaminated process systems were located in radiation control areas. These systems and components were surface decontaminated prior to their removal from the area, with the assumption that the components could then be free-released.

License termination survey costs are associated with the labor intensive and complex activity of verifying that contamination has been removed from the site to the levels specified by the regulating agency. This process involves a systematic survey of all remaining plant surface areas and surrounding environs, sampling, isotopic analysis and documentation of'the findings. The status of any plant components and materials ,

not removed in the decommissioning process will also need to be confirmed and will 1 add to the expense of surveying the facilities alone.

The cost reported for soil remediation is based upon n preliminary assessment conducted by MYAPC of the potential for contamination in the soil around the plant (based upon historical evidence). A detailed characterization was not performed. This allowance will be confirmed and/or modified based upon more detailed analyses to be l performed in conjunction with the formulation of a license termination plan.  !

l The remaining costs, representing approximately 10% of the total projected expense, l include allocations for waste packaging, energy consumption, mandated fees and

. required insurance premiums and other costs related to maintaining a viable organization. " Operating" costs, while generally reduced over the duration of the program, do need to be maintained either at a basic functional or regulatory level.

TLG has found that in most situations, prompt removal of the radioactive material from the site is the best and least costly plan of action for decommissioning. This is favored because it eliminates a potentiallong term safety hazard. More importantly, individuals familiar with the operation of the nuclear facility are still available to provide invaluable knowledge concerning the plant systems and plant operating history. Action in the short term also prevents any future concerns for structural deterioration of the existing buildings.

M:Ine Yankee At:mic Power Station Document M01-1258-002, Rev.1 l Decommissioning Cost Analysis Section G, Pag 2 5if 5 m ,

l TABLE 6.1 1

SUMMARY

OF MAJOR CONTRIBUTORS ,

to the l COST OF DECOMMISSIONING l Work Activity Cost Percent'of .

or Cost Category (thousands,973)12 Total Costi Staffing 133,216 26.21 IIRW Burial 83,379 16.41 l Removal 60,214 11.85

. ISFSI Siting, Construction and Licensing 52,249 10.28 Property Taxes 31,031 6.11 Waste Conditioning / Recycling 22,473 4.42 Security Services 15,930 3.13 l Non-radiological Demolition 15,078 2.97 Transportation 12,881 2.53 1 Decontamination 12,024 2.37 License Termination Survey 10,580 2.08 Soil Remediation 9,063 1.78 Plant Energy Budget 8,944 1.76 Insurance 7,420 1.46 NRC ISFSI Fees 6,936 1.36 Packaging 6,339 1.25 NRC and EP Fees 6,309 1.24 Fixed Overhead 5,904 1.16 Remaining Costs 3 8.253 162 Total $508,221 100.00 Notes

1. Columns may not add due to rounding.

2. All costs include contingency with the exception of property taxes.

3. Remaining costs include site characterization, building modifications, temporary services and support equipment.

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M::ine Yenhee Atornic P6mer Station Document M011258-002, Rev,0 Decommienioning Coat Analysia Section 7, Paga 23f 2 l

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)

I

7. REFERENCES (continued) l i

1

12. U.S. Department of Transportation, Section 49 of the Code of Federal ,

Regulations, " Transportation," Parts 173 through 178,1996. l

13. Tri-State Motor Transit Company, published tariffs, Interstate Commerce Comminaion (ICC) Docket No. MC-109097 and Supplements. l i

14. " Building Construction Cost Data 1997", Robert Snow Means Company, Inc.,  !

Kingston, Massachusetts.

15. "Microsoft Project for Windows 95," Version 4.1, Microsoft Corporation, Redmond, WA,1995. i l

l

16. " Atomic Energy Act" of 1954," (68 Stat. 919). j 1

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. _ _ . . . _ . . . - ._ _ _ _ _ . _ . _ _ _ . ~ . _ . _. ._. ._. . . _ _ _ _ . _ _ . _ . . . . _ _

Maine Yankee Atomic Power St: tion Docunsent M01-1258-002, Rev. O Decommissioning Coot Analysis Appendix A, Pag 2 lef 4 l l

i

)

1 e

e 3 S APPENDIXA UNIT COST FACTOR DEVELOPMENT e

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Maine Y:nkee Atomic P:w:r Stztion Document M011:58 002, Rev. O Decommissioning C st Analysis Appendix A, Pag 2 2 cf 4 APPENDIXA

. UNIT COST FACTOR DEVELOPMENT hmple: Unit Factor for Removal of Contaminated Heat hhanger < 3,000 lbs. j

1. SCOPE Heat exchangers weighing < 3,000 lbs. will be removed in one piece using a crane or small hoist. They will be disconnected from the inlet and outlet piping. The heat exchanger will be sent to the packing area.

2. CALCULATIONS Act Activity Activity Critical ID Description Duration Duration a Remove insulation 60 (b) b Mount pipe cutters 60 60 c Install contnminntion controls 20 (b) d Disconnect inlet and outlet lines 60 60 e Cap openings 20 (d) f Rig for removal 30 30 g Unbolt from mounts 30 30 h Remove contamination controls 15 15 i Remove, wrap in plastic, send to packing area 60 60 Totals (Activity / Critical) 355 255 Duration adjustment (s):

+ Respiratory protection adjustment (25% of critical duration) 64

+ Radiation /ALARA adjustment (20% of critical duration) .5.1 Adjusted work duration 370

+ Protective clothing adjustment (30% of adjusted duration) _111 Productive work duration 481

+ Work break adjustment (8.33 % of productive duration) 40 Totalwork duration min 521 min

• • • Total duration = 8.683 hr ***

M:Ine Yankee At:mic Pow:r Station Document M011258-001, Rev. 0 Decommissioning Cost Analysis App:ndis A, Pag 2 Scf 4 APPENDIXA

, (continued)

3. LABOR REQUIRED Crew Number Duration Rate Cost (hr) ($/hr) . .-

Laborers 3.00 8.683 $24.39 $635.34 Craftsmen 2.00 8.683 $33.15 $575.68 Foreman 1.00 8.683 $35.16 $305.29 General Foreman 0.25 8.683 $36.20 $78.58 Fire Watch 0.05 8.683 $24.39 $10.59 ,

Health Physics Technician 1.00 8.683 $34.14 $296,44 Totallabor cost $1,901.92 1

4. EQUIPhENT & CONSUMABLES COSTS Equipment C' osts none l

Consumables/ Materials Costs

_ Blotting paper 50 @ $0.43/sq ft {2} $21.50

. Plastic sheets / bags 50 @ $0.07/sq ft {3} $3.50

. Gas torch consumables 1 @ $7.24/hr x 1 hr {1} $7.24 Subtotal cost of equipment and materials $32.24 Overhead & profit on equipment and materials @ 16.000% $5.16 Total costs, equipment & material $37.40 TOTAL COST Removal of contaminated heat exchanger <3000 pounds: $1,939.32 Totallabor cost: $1,901.92 Total equipment / material costs: $37.40 ,

1 Total adjusted exposure man. hours incurred: 35.798 Total craft labor man. hours required per unit: 63.386 l

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l M:ine Yankee Atomic Pzwer Strtion Document M01-1258-002, R_ev. O Decommiseloning Cost Analysis App:ndix A, Pag 2 4 ef 4 i l .

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APPENDIXA

, (continhed) ,

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1

5. NOTES AND REFERENCES l

1. Durations are shown m mmutes. The integrated duration accounts for I those activities that can be performed in conjunction with ot.her activities, indicated by the alpha designator of the concurrent activity.

This results in an overall decrease in the sequenced duration.

2. Work difficulty factors were developed in conjunction with the AIF program to standardize decommissioning cost studies and are delineated in the " Guidelines" study (Ref. 6 , Vol 1, Ch. 5). .

3. Adjusted for regional material costs for Bath, hE.

I

4.

References:

,1. R.S. Means (1997) Division 016 Section 420-6360 pg 19

2. McMaster-Carr Ed.103

3. R.S. Means (1997) Division 015 Section 602-0200 pg 13 1

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M:ine Yankee Atomic P6a:r Statlon Document M011258-002, Rev. 0

. Decommissioning Cast Anclysis Appendix B, Paga Icf 8 4

1 h

4 APPENDIXB . ,

UNIT COST FACTOR LISTING (Sample of one set) e 0

.A

M:Ine Yrnkee Atomic PowerSt1 tion Document M01-1H8-002, Sw. 9 Dectmmissioning C:st Anrlysis Appendix B, P::ge 2 ef C APPENDIX B UNIT COST FACTOR LISTING (Power Block Structures Only)

A Unit Cost Factor Cost / Unit ($)

Removal of clean instrument and sampling tubing, S/ linear foot $0.27 Removal of clean pipe 0.25 to 2 inches diameter, $/ linear foot $3.39 Removal of clean pipe >2 to 4 inches diameter, $/ linear foot $4.13 Removal of clean pipe >4 to 8 inches diameter, $/ linear foot $ 8.13 Removal of clean pipe >8 to 14 inches diameter, $/ linear foot $15.63 Removal of clean pipe >14 to 20 inches diameter, $/ linear foot $20.30 Removal of clean pipe >20 to 36 inches diameter, $/ linear foot $29.88 Removal of clean pipe >36 inches diameter, $/ linear foot $35.50 Removal of clean valves >2 to 4 inches $42.71 Removal of clean valves >4 to 8 inches S 81.30 Removal of clean valves >8 to 14 inches v $156.27 Removal of clean valves >14 to 20 inches $203.04 Removal of clean valves >20 to 36 inches $298.78 Removal of clean valves >36 inches $355.03 Removal of clean piping / electrical structural steel, pound $1.30 Removal of clean pipe hangers for small bore piping $17.98 Removal of clean pipe hangers for large bore piping $64.21 Removal of clean pumps, <300 pound $135.45 Removal of clean pumps, 300-1000 pound $378.84 Removal of clean pumps,1000-10,000 pound $1,503.20 Removal of clean pumps, >10,000 pound $2,897.55 Removal of clean pump motors, 300-1000 pound $160,10 Removal of clean pump motors, 1000-10,000 pound $G27.18 Removal of clean pump motors, >10,000 pound $1,411.14 Removal of clean turbine-driven pumps < 10,000 pound $1,735.63 w

M:ine Ycnkee Atomic Pow:r St: tion DocumentM0N1258-002,Rto Y Decommissioning C:st Ancly:is Appendix B, Pag 2 3 u(8 l

l l

l APPENDIXB (continued)

Unit Cost Factor Cost / Unit ($)

- Removal of clean turbine-driven pumps > 10,000 pounds $3,877.71 Removal of clean heat exchanger <3000 pound $809.57 Removal of clean heat exchanger >3000 pound $2,036.61 i Removal of clean feedwater heater /deaerator $5,740.27 Removal of clean moisture separator / reheater . $11,799.98 Removalof clean tanks, <300 gallons $176.08 Removal of clean tanks, 300-3000 gallon $555.73 Removal of clean tanks, >3000 gallons, $/ square foot surface area $4.68 Removal of clean electrical equipment, <300 pound $ 74.59 Removal of clean electrical equipment, 300-1000 pound $260.65 Removal of clean electrical equipment,1000-10,000 pound . $521.30 Removal of clean electrical equipment, >10,000 pound $1,242.46 Removal of clean electrical transformers < 30 tons S 862.87 Removal of clean electrical transformers > 30 tons $2,484.93 Removal of clean standby diesel-generator, <100 kW $881.35 Removal of clean standby diesel generator,100 kW to 1 MW $1,967.24 Removal of clean standby diesel generator, >l MW $4,072.57 Removal of clean fluorescent light fixture $30.96 Removal of clean incandescent light fixture $15.29 Removal of clean electrical cable tray, $/ linear foot $6.98 Removal of clean electrical conduit, $/ linear foot $3.05 Removal of clean mechanical equipment, <300 pound $74.59 Removal of clean mechanical equipment, 300-1000 pound $260.65 Removal of clean mechanical equipment,1000-10,000 pound $521.30 Removal of clean mechanical equipment, >10,000 pound $1,242.46 t

I

M:ine knkee Atimic P:w:r Strtion Document M01-1258-002, Rev, 0 Decommissioning Cist An:ly:is AppandixB, P:ga 4 ef 8 l

l APPENDIX B j (continued)

Unit Cost Factor Cost / Unit ($)

Removal of clean HVAC equipment, <300 pound $74.59 I Removal of clean HVAC equipment, 300-1000 pound $260.65 Removal of clean HVAC eq&ipment,1000-10,000 pound $521.30 Removal of clean HVAC equipment, >10,000 pound $1,242.46 Removal of clean HVAC ductwork, $/ pound $0.55 Removal of contaminated instrument and sampling tubing, $/ linear foot $0.71 Removal of contaminated pipe 0.25 to 2 inches diameter, $/ linear foot $17.80 l Removal of contaminated pipe >2 to 4 inches diameter, $/ linear foot $31.22 Removal of contaminated pipe >4 to 8 inches diameter, $0inear foot $51.53 Removal of contaminated pipe >8 to 14 inches diameter, $/iinear foot $100.94 Removal of contaminated pipe >14 to 20 inches diameter, $/ linear foot $121.95 Removal of contnminated pipe >20 to 36 inches diameter, $/ linear foot $170.70 Removal of contaminated pipe >36 inches diameter, $/ linear foot $203.46 Removal of contaminated valves >2 to 4 inches $151.63 Removal of contaminated valves >4 to 8 inches $252.05 Removal of contaminated valves >8 to 14 inches $504.68 Removal of contaminated valves >14 to 20 inches $642.50 Removal of contaminated valves >20 to 36 inches $853.50 Removal of contaminated valves >36 inches $1,017.29 Removal of contaminated pipe hangers for small bore piping $55.73 Removal of contaminated pipe hangers for large bore piping $176.86 Removal of contaminated piping / electrical structural steel, pound $2.83 Removal of contaminated pumps, <300 pound $432.98 Removal of contaminated pumps, 300-1000 pound $1,001.17 Removal of contaminated pumps,1000-10,000 pound $3,283.86 I

O

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M:ine Y:nkee At:mic Pow 1r Steti:n Document M01-US8-00:!, llev. 0 Dec:mmissioning Cc:t Analy:i3 App;ndix B, Pagt 5 of 8 APPENDIX B (continued)

Unit Cost Factor Cost / Unit ($)

Removal of contaminated pumps, >10,000 pound $7,952.26 Removal of contaminated pump motors, 300-1000 pound $434.93 Removal of contnminated pump motors,1000-10,000 pound $1,333.75 Removal of contaminated pump motors, >10,000 pound $3,012.69 Removal of contaminated turbine-driven pumps < 10,000 pounds $3,914.37 Removal of contaminated turbine-driven pumps > 10,000 pounds $8,939.06 Removal of contaminated heat exchanger <3000 pound $1,939.32 Removal of contaminated heat exchanger >3000 pound $5,624.62 Removal of contaminated feedwater heater /deaerator $14,138.90 Removal of contaminated moisture separator / reheater $30,694.79 Removal of contnmmated seismic structural supports, pound $1.43 Removal of contaminated tanks, <300 gallons , $726.69 )

Removal of contnminated tanks, >300 gallons, $/ square foot $14.35 Removal of contaminated electrical equipment, <300 pound $333.65 Removal of contnmin ated electrical equipment, 300-1000 pound $796.22 Removal of contaminated electrical equipment,1000-10,000 pound $1,532.47 Removal of contaminated electrical equipment, >10,000 pound $3,071.07 Removal of contaminated fluorescent light fixture $150.39 Removal of contn minated incandescent light fixture $89.24 Removal of contaminated electrical cable tray, $/ linear foot $24.44 Removal of contaminated electrical conduit, $/ linear foot $31.21 Removal of contaminated mechanical equipment, <300 pound $379.67 Removal of contaminated mechanical equipment, 300-1000 pound $904.67 Removal of contaminated mechanical equipment,1000-10,000 pound $1,743.71 Removal of contaminated mechanical equipment, >10,000 pound $3,071.07 Removal of contaminated HVAC equipment, <300 pound $379 67 Removal of contaminated HVAC equipment, 3001000 pound $904.67 Removal of contaminated HVAC equipment, 1000-10,000 pound $1,743.71 Removal of contaminated HVAC equipment, >10,000 pound $3,071.07 Removal of contaminated HVAC ductwork, $/ pound $1.59

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M:ine Yankee Atomic P:wsr Stati:n Document M01-1258-002, Rev. 0 Dec:mmissioning Coat Anclyzia App:ndix B, Pag 2 6 ef 8 APPENDIXB l (continued) l 1

Unit Cost Factor Cost / Unit ($)

Removal / plasma are cut of contaminnted thin metal components, $/ linear in. $1.78 Additional decontamination of surface by washing, $/ square foot $3.86 l Additional decontammation of surfaces by hydrolasing, $/ square foot $16.54 j Decontamination rig hook-up and flush ,

$3,210.22 Chemical flush of components / systems, $/ gallon $8,00 Systems contaminated work area set up $1,524.48 Systems installation of contamination controls $17,023.07 Systems contaminated work are tear down $640.16 Removal of contaminated buried pipe 0 to 2 inches dia. $/ linear foot $79.54 Removal of contaminated buried pipe >2 to 4 inches dia. $/ linear foot $81.70 Removal of contaminated buried pipe >4 to 8 inches dia., $/ linear foot $83.87 i I

Removal of contaminated buried pipe >8 to 14 inches dia., $/ linear foot $86.03 Removal of clean standard reinforced concrete, $/ cubic yard $110.61 Removal of grade slab concrete, $/ cubic yard $147.51 Removal of clean concrete floors, $/ cubic yard $189.33 l Removal of sections of clean concrete floors, $/ cubic yard $593.07 Removal of clean heavily rein concrete w/#9 rebar, $/ cubic yard $148.90 Removal of contaminated heavily rein concrete w/#9 rebar, $/ cubic yard $1,006.66 Removal of clean heavily rein concrete wM18 rebar, $/ cubic yard $189.35 Removal of contaminated heavily rein concrete w/#18 rebar, $/ cubic yard $1,333.24 Removal heavily rein concrete wM18 rebar & steel embedments, $/cu yd $272.79 Removal of below-grade suspended floors, $/ square foot $189.33 Removal of clean monolithic concrete structures, $/ cubic yard $528.38 Removal of contaminated monolithic concrete structures, $/cu yd $1,005.82 Removal of clean foundation concrete, $/ cubic yard $414.36 Removal of contaminated foundation concrete, $/ cubic yard $936.51 Explosive demolition of bulk concrete, $/ cubic yard $20.26 Removal of clean hollow masonry block wall, $/ cubic yard $50.65

( Removal of contaminated hollow masonry block wall, $/ cubic yard Removal of clean solid masonry block wall, $/ cubic yard

$135.22

$50.65

M:Ine Ycnkee Atomic Paww Strtion Document M01-n58- . ev. 0 1 Dec:mmissioning C::t An:ly:ia Appendix B, Pcgc C of 8 APPENDIX B (continued)

[ Unit Cost Factor Cost / Unit (s) 1 Removal of contaminated free-standing steel liner, $/ square foot $16.68 l Removal of clean concrete-anchored steelliner, $/ square foot $3.51  !

Removal of contaminated concrete-anchored steelliner, $/ square foot $19.25 l Placement of scaffolding in clean areas, $/ square foot $9.57 Placement of scaffolding in contaminated areas, $/ square foot $13.28 Concrete wall sawing, linear foot of cut $17.71 Diamond wire cutting, concrete 1 to 2 foot thick, $/ square foot $241.03

Diamond wire cutting, concrete 3 to 6 foot thick, $/ square foot $494.80 Removal of piping / mechanical penetrations $1,069.00 i Structures contaminated work area set up $1,524.48 i Structures installation of contamination controls $17,023.07 l l

Structures contammated work area tear down $640.16 Landscaping w/ topsoil, $/ acre $15,066.64 Cost of CPC B-88 LSA box & preparation for use $792.47 l Cost of CPC B-25 LSA box & preparation for use $848.46 Cost of CPC B-12V 12 gauge LSA box & preparation for use $650.15 Cost of CPC B-144 LSA box & preparation for use $3,652.64 Cost of LSA drum & preparation for use $80.58 Cost of cask liner for CNSI 14-195 cask $7,748.83 l Cost of cask liner for CNSI 8-120A cask (resins) $7,709.75 Cost of cask liner for CNSI 8-120A cask (filters) $7,709.75 License termination survey / Interior / <2 meters, $/ square foot $2.20 l

License termination survey / Interior / >2 meters, $/ square foot $3.20 i

License termination survey / Interior / ceilings, $/ square foot $5.86 l License termination survey / Exterior / <2 meters, $/ square foot $2.20 i

License termination survey / Exterior / >2 meters, $/ square foot $3.20

. License termination survey / Interior / roofs, $/ square foot $5.86 License termination survey / Exterior / soil, $/ square foot $2.43

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M:Ine Yankee Atomic Power St: tion Document M01-1258 002, Rev.1 Decommiseloning Cost Analysis App:ndix C, Pass Icf 9 s

APPENDIX C DETAIT.ED COST ANALYSIS O

e r4

~-

Metae Teabee Asemie M Reeseen " BNSICSSent.Rees&

Appeenlie C Page B el9 Deceauminaieales Cease Anatsene ,

TABLE C-1 tsADdE YAf# TEE ATOtIIC POWER STA79001 ,

ASEA.gy4ftEA COST ESTmBATE (Thausende el 1997 Domers) .

Les Tene camme A CF S CF C CF eC CF tems am a-- teesneve Pach sedy genry Osher Cemegacy Teene PERIOD 1 Pleaming & See 7. ,-

t Sae chesecnensemen enswey . . . . . 1,371 208 1,578 1,5M . . . . . .

2 Ptese peep. a teep. evees . . . . . 1,008 271 2,078 2.074 . . . . . .

. . . - 1,524 220 1,757 1,757 . . . . . .

3 RaegmeCCEsaeetnerees. .

Set . . . . . 343 1,829 1,020 . . . . . ses 4 Decem pshnery tmey 1,797 332 13 1,354 000 984 5.814 S.814 - 2,507 . . . 38,806

& Aabesses semovei progresa .

543 . 133 162 744 . 495 2.077 2.877 . . 1.800 . . 374 S Decen lamh snenerv sveteme Peded 1 em Ceeen 1,000 1,150 . . . .

7 fues pees tudsten Aamwence . . . . . 150 1.150 . .

445 175 2,102 8.304 2.See 14,600 14.000 . 2.547 1.See . . 57,795 Sahasent Parted t Acebey comeo 1.229 f.797 I

Posted 1 " 1" " Ceeen 1 Decea : ,. See . . . . . S4 47s 878 . . . . . .

50 . . . .

2 Decan eapp6es 47 . . . . . 12 SS . .

730 . . . . tes 336 830 . . . . . . [

3 DOC eseW eelocedon espensee -

se . 400 492 2.237 . 737 3,335 3,333 . . 3,43s . . S$2 4 Procme hpad wease . . .

. . - - . 447 47 514 514 . . .

5 loansance 3,ses  ;

. . . . . 3,000 - 3,300 . . . . . .

e 6 Peeperty temas .

7 Heeshphyesceesecess - 458 . . . . I14 572 572 . . . . .

33 . . . . S 3e 3e . . .

8 Heavy agapmans seneet -

9 $mes test etswent,e . 20 . . . . 4 32 32 . . . . . .

g 352 .

10 Ompeset et DAW eeneresed . . . . 297 de 352 . . . . .

. . . . 2.038 306 2,343 2,143 . . . . . . 4 Il Peerd energy hendent .

12 ISFSa ceneoustom esponeesee . . . . .. 32,000. ~.- 4,000 38,300 34,800 . . . . . .

. . . . . 4,782 787 S,400 6.400 . . . . .

13 ISF $i sas eterstone

. . 1,000 150 1,150: 1,150 . . . . . . t 14 ISF$t teneles ==yt===a . . .

. . . . a.000 300 3,e00' s,300 . . . . . .

15 ISFSa lcenomg and permas .

. . . . 184 17 105 105 . . . .

18 NRC Fees .

165 . . .

. . . 150 15 165 . . .

17 Emergency Plerete Fees . .

. . . . . 996 148 1,145 1,145 . . . . . .

te See Seesey . . . .

. . . . . 653 De 751 751 . .

• tt Feed Owerhead Cent . . . .

. . . . . 361 54 414 414 . .

20 SeeN hicaneve +

400 Set 2.237 54,513 8,249 S7,072 57,872 . . S.438 . . 502 m h unstabeneand Cease Period t 724 1.249 Sten Coste - 2,784 . . . . .

. . . . . 2.404 361 2.784 .

Assesnessed Seed Coat 14,40s . . . .

. . . . . 12,523 1,478 14.401 . .

Sten Cent 4,339 75,744 13,000 90.718 98.713 - 2,547 7,248 . . 58,301 TITAL PEguoO 1 COST t ,953 3.045 855 878

.(

l aiedea Yeobee Asende her aseeien P - - 4003 3e80488, Sam # i Decessmeiseiemime Cneas Anefreie AppensHs 4 Pese 4 a(e 1ASLE C-1 ,

etNNE VASIKEE ATOGAIC POggER STAftest ,

AftEASY,4ftEA COST EsiusATE (T"ws st 1997 DeGersl Aceivery Decem Resa Peck endP sery osier 'Came o ney Teams Las venne clean a cP e cP c cP oc cP emme PERIOD 2 .

Mustser Semese supply Sysesse itemmoval et Reecaer ceenent Pyme 28 40 7 12 333 . til 534 638 . est . . . 2.30s 02 Pressineser Rebellers 7 37 2 3 123 - 44 2tf 217 . 298 - . - 3.413 03 Reecess Caetent Pumps & 6eesere 74 33 34 1.323 2J12 . 825 0.142 5.102 -

4.e00 . - . - 3 Jet l 84 Psessumes et 33 4 642 tJ43 - 444 2.425 2.428 - 2.208 . . . 2.345 85 Seeman Generesars 124 3.156 1,104 4.786 7J50 . 3A23 20A04 20.604 . 21.000 . . . 7A28

' e4 CRDessaCastSeswa Southme Rosievet 58 58 83 26 1.457 - 428 2.143 2.183 . 3.H1 . - - 3.561 ,

I 8.7 Reecess vesselinneemets 79 1.038 1.37e Ste 12.054 -

7.648 23.096 23,ses . l.See 4M 1.984 227 10.116 e e Reacter vessel 177 4.827 Ses 57e 9.20e . e.607 23.047 23.907 -

7.000 1.006 . . 35.M3 l See 18.832 3.174 0.188 34.984 - 22.111 78.e42 70.042 . 42.498 2.448 9.884 227 74.982 ,

8 Tesens e Rosmewe epent hselrects 238 20 7 8 795 1.007 Sie 3.578 3.570 - 1.887 . - - eJ3e  !

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RenesvalofGaeise W .

10 neesn TeessioGeneresar - 145 23 $ 300 000 271 tJ24 tJ28 . 306 . . . e.363 tt $4ehn Comesaners 1.040 344 30 15 1.518 3.448 1.e43 0.078 9.eM . 3 Ass . . . 18.3s3 s Dieposalof Plant systemas em 322 e e tot ses ist are e24 . a32 . . . te,007 l 12.1 Cat-t -

12 2 C81-2 - 308 8 7 106 827 144 778 7M - 620 - . . 14,43e i 152 138 717 787 . SIS - . . e,ets  ;

12.3 Ca t-3 - 247 7 7 173 12 4 C014 - 175 5 3 tie 57 e3 448 440 - 338 - . . SJtt ,

248 13 5 344 Se 140 438 830 . 012 . . . e,te2 i 12.5 C88 5 -

54 . . 3AS3 53 0.78 0 00 10 11 24 144 104 . .

12 9 C884 .

83 . R 828 78 123 0 95 29 10 30 157 157 . - .

12.7 C88-7 .

. . 3SJ48 e se 15 2e 377 443 444 2.394 2.398 . 1.844 -

12 0 CBl e 1.138

. . 17J12 0.17 558 31 20 715 650 448 2.200 2.200 -

2.188 .

12 9 C82-1 64 . . - 3.363 104 eH s.54 23 0 33 til til -

12.14 C8Lt -

See  !

12 18 C83-2 - 24 0.04 8.77 14 to il 64 84 . 41 . . .

0.15 tes 14 16 024 284 315 tAe7 3,es? . 024 . . . s.3s3 l t212 C83-3 463 443 316 - . 8.42s 1213 C834 - 165 8 5 tes 90 84 - .

. 72 2 2 36 42 34 tes les . tes . . . 2.206 12.94 CCG 232 - IJee i 8 82 56 3 3 78 72 44 260 284 - . .

12.15 CEHO See  !

22 024 022 5 5 4 40 44 . 14 - . .

12.14 CICI -

226 - 2.25e 1.te 70 3 4 76 78 Se 282 292 - . -

32.37 CPHO 10 . see ,

2 29 0.14 e.te 3 4 to 44 48 . - -

12 16 CPtE 123Als 12 Teanas 5 3.025 lie til 3.40S 2.133 2.158 ttJS$ ItJS4 - e.027 - . -

• 9

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Moine Yenhoe Assen8e Pmaser Suesten W 4S88808488. Ban 64 n.-- u..:. a-.r Os*8e Aa*% APP'- 4 Pnee 44 8 '

TABLE C-1 SAANE YAAABEE AToeIIC POMR STAftDel Aas A4Y,AltEA COST ESTueATE 6

(Tansessende et1987 Deement Aammesy '- manieve Pese sedP Bury Osmus M Teamt Las Tesus Cimes A CF 3 CF C CF DC CF mum "

Pounary AwaSary Biddne 3 33 129 4 6 139 138 98 Sgt $11 - 42 . . - 4,143 13 1 P2tA 132 P2tB e.le 183 3 2 88 40 59 277 277 - tes - . . 3.286 458  ;

151 7 7 ISS 130 SS SSF SSF - - - . 4.721 13 3 P2tC S O4 13 4 P2tO 14 ISS 13 19 293 225 144 Ste ete - es? . - - 332S to 288 4 3 SF , e2 110 S78 678 . 298 . - - ejes ISS P2tE 3,374 13 6 P2tH 8 02 117 2 2 48 30 48 24F 247 - tas . - -

27 201 8 9 100 378 167 830 33s . 833 - - . sy41 ,

13.7 P2tL 800 IS S P215 S ee 32 8.49 S.30 le a 12 42 82 - 28 - . . ,

IS S P2tV 8 54 69 0.77 S.72 to 16 25 130 138 - 82 - - . . 2.ste i 13to PLAD 8 30 147 4 3 e6 7e 72 343 383 . 2F2 . - - 4AM '

8 92 114 2 2 57 47 61 2F4 275 . les . . . 3,0e0 13 tt PLSA 13.12 PLCP S.te 71 125 1.00 29 22 28 154 854 - el . . . 2 Jet 2 57 29 38 SM 194 144 . - - 2,tes 43.13 PLDC 8 83 88 2 -

4.16 138 2 2 47 33 47 248 248 - 136 - - . 3.84e 13 14 PLEC 13.15 PLLA 1.e4 See & S 813 113 174 ste ete - 33s - . . to.Sas 93.98 PLPA 3 307 3 4 SS $4 134 Get get - les . - - 13,333  ;

43 97 PLPO e.12 63 e ft 1.00 to 23 22 Ste ite . 64 . . . IAst 7 231 148 150 See see . 374 - , . - g,727 a t it PLPT 2 306 le

• 0 24 36 8 9 IS 14 16 84 04 . 4e . . - spy? - '

13.19 PLPW 223 4,308 136 3 4 75 74 SS 36F 367 . . . -

1320 Pues -

42 232 232 213 9,00F 1325 PUDO - St 3 2 74 . SS - . . .

- SF 1.35 1.48 32 20 27 See les . e2 . - - 3.327 i 13 22 PUEC ISF 2Ast 9 97 Se 2 2 53 SS 43 238 230 . - . .

1323 PUFN 27 162 152 33 . . 1.829 62 121 1.48 28 42 - .

1324 PUHV t 143 178 933 933 . St2 - - . 12JM  !

4 306 e 8 174 8325 PUL 32 43 228 228 - let . . . 3,485 9 32 115 2 2 39 13.28 PUSA M M 27 - - . 1.364 l e 12 42 a.30 e.43 0 9 84 -

13.27 PUTC 33 144 164 186 . . - SAM  !

9 02 64 2 2 S3 40 .

1324 PUWG 1,968 18.688 10.608 - 8.008 - . . 134.738 13 Tasais 71 4,16e 97 94 2.258 1.tes t

i Testene Ondete 37 532 428 tJOB se 8 9 144 229 S32 -

14.1 Aan .

• - - - 3 14 . 13 - . - 377 142 DG2 - it 48 tM 198 1A24 1,024 148 14,722  !

14.3 FWH See 2 14

- 11 64 S4 - - . - 1.426 14 4 MCR . 43 . . -

41 024 2 8 28 21 110 114 18 tAtt 14.5 MTGE .

148 25 . - - - 8 38 31 .

14 6 OSR 63 ' 53 1 f.300 ' [

42 0.01 0.08 8.20 0.52 31 142 TACA .

2 57 3 1.338  ;

tes TBOA - 42 0.05 024 1.14 13 SF '

44 8 05 022 1.20 2 12 SS SS 4 t.374 14 9 1908 -

78 70 3 t,382 l Se e e4 S.te G 97 2 15 14.30 TeLO -

34 34 Mt i

. 26 0.02 0 07 S et 6.71 7 t 14.11 Tsaas 157 - - - - 3A2i

- 126 - - - . 31 157 -

to 12 TOP . 7 36 38 - . - . 382  !

14.13 TSpel - 2e . . .

- - GDI S.07 0 0F . . . . 2 i 14.14 TSRNt - S es . .

i

. S 31 - 31 - - - - 048 84.15 TBRN2 - 25 - - -

i

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30.to.ree - - - 00,., 88. ,

m q rey,,ogg Decommen' '*=E=r Coone Anatroie TASLE C-1 BAAaBIE YAfeLEE ATOIAC FotMEft STAT 1000 AftEA4Y AREACOSTESTatATE (T" Ma of teeF Desars) h " Rennove Pack SMp Bury OEar Castency Tesal Lin Tesus Close A CF S CF C CF H:CF Imus Turtsie suMne (cosamue4 see 14.38 TSSO - 24 0.02 e se 0.41 e st a 34 30 t 250 0 0e 0 54 2 S SS 332 332 e e.446 14.17 TeWT -

30s 2e 0.12 0.16 3 2 0 42 42 3 14 le TCA -

34 e.05 0 30 0.87 5 8 48 48 4 1.e63 84.14 TCSA -

2,487 -

86 8.20 124 5 15 26 138 133 13 84 20 TCDA -

2.244 72 0 07 8.32 1.50' 4 le SF 87 4 14 28 TCIA -

2.842 72 0 22 9.48 5 SF 22 118 114 16 14 22 TCNE -

3Als se 2 13 43 168 62 374 378 128 14 23 TCPA -

155 S.43 4 10 48 44 257 257 20 4.SFF

$4 24 TCSE -

Sti to 6 00 O ct 0 0F 0.13 S 24 24 a.28 I4.26 TCTP -

80 60 t 1,441

- 47 0 01 0 05 0.27 8.40 12 84 26 TCTU 4 743 26 8.82 1.t4 3 13 e 53 53 14 27 TDev -

2 T74 28 0 03 0 22 8 47 3 7 37 37 14 26 TORW -

70 to 1.338 44 0 23 0.70 S 14 9 is 14 24 TDSN -

7 7 - - - - IM S - - - -- 8.44 -

84.34 TOSS -

2.782 14 34 TFPA - SS S 43 4 le 42 3t SFS 175 Se 103 e 54 S 82 SF 34 2tS 2tS 3F 3.278 34 32 Tief -

300 les 1,ees 432 3.848 14.33 THEA - 185 14 1F 315 1.000 et 8.27 2 e 28 23 830 830 18 2.146 14.34 it4AE -

2.288 14.35 TMCit - 72 024 3 4 M 24 13S 836 le 52 025 2 8 24 19 teF teF 1F sat 4 14 34 Thev -

2e teF 107 e 2.234

- 70 0.83 1.0F 3 32 84 37 TMDW 426 438 et 8.000

- 288 S ee e 24 184 76 34 38 TMEC 330 338 76 S.eas

- 215 1.03 2 24 38 45 14 34 TMFA 34 38 105 1M 28 3.MF 44.40 TMFR - 112 0M 3 a 4 4 4F 28 set tot 27 2.384 I4 41 T3FV - 72 S.40

- 80 S ee 0.24 1.33 3 21 t% 305 4 2.SF2 84 42 T MG*_ te 1,176

- 38 e.14 1.24 3 IS 13 71 ft 14 43 Thm1D sie to 1.000

- 82 8 20 2 6 23 20 its 34 44 TheA les la 1,ses 14 45 TMLT - 64 8 20 2 6 te 20 tot 13 84 FS 78 8 1,3e8

- 45 0 12 1.1 l 3 14 44 TMNC 38 2.834

- et 8.50 $ 13 M 37 218 218 14.4 F TMSE M 8.844

- 204 8 81 8 le M M 366 361 14 48 TMSR 40 224 224 35 3.448

- 10e e St S 42 50 14 40 TMWC e 44 44 3 4e2 14 50 TMWT - 24 4 04 8 42 1 S 12 SF 38 283 213 34 3.2F1

- 102 1 S 14 St TP2C 163 83 538 313 8.tM

- 163 5 7 144 536 14 52 TSPP M e6 - - - - - 2.246 Se - - - - ti 14 53 TSRP -

2A4F 14 54 TSRu - et 0 02 O ct S.48 SM 23 113 143 1 8 44 8 20 28 8 83F 22 0 01 0 04 0.87 14 55 Tu -

8.275 0,103 at 2.008 - - - 843,400

- 4.544 34 134 474 t. Set 1.800 14 Tesats 8

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Asemmaans Af98 JS$4498, Sam #

Maine Yeabee Assasse % Seed ** Appemega c page gog n '

De '

= - eng Ceese Annipolo TABLE C-t RAAmeE YAgeKEE AToteC POWEtt STAftott AREA 4YMEA COST ESTtIAATE (Thousands of 1997 Demars) aury cak e Taeal Las Team cimam A CF S CF C CF 3C CF tihes

• M "--- Itanieve Pack Sedy .

Senacefuel BNet/SPR8 2 3 22 97 SF 7 2,149 15 8 DWST 13 M 0.58 0 20 2 25 44 37 194 194 75 2.SM t5 2 EFPR 13 70 1.13 f,245

- 41 0.15 0.12 4 2 18 69 50 le 15.3 FSP 8 9 le $2 92 24 lAee 35 4 LSA8 2 54 8.36 0 48 f,884 2 2 42 43 32 100 100 124 -

15 5 NFLA . 59 t,4e8 47 0.45 0 42 to 11 te M M 31 15 4 MCAD 543 893 est 4,883 t.14 255 7 6 169 127 127 15 7 RCAW 82 72 394 364 33 7,144 0 54 225 0 48 3 11 15 8 fueCC 3 9 45 45 5 835 0 73 30 0 00 0.14 2 15 9 380R to 82 20 f.288 I

• 15 le SSHP 2 30 0.42 0 48 te 15 82 1,482 0 32 0 62 7 15 34 140 tea 22

• 15.11 $884S 18 82 t,833

- 53 0.34 0.29 8 5 19 M M 24 15 82 SSP 2 4 29 29 4 SFS 15 13 385R 0.39 19 0 04 eM i 3 3 72 70 tit 824 624 210 f t.Mt 95 84 58TT 1 48 356 i8 M M 2 f.235 15 15 88VH . 44 4.0 0.1 1 l 32 28 33 370 17e e4 2.828 15.14 SFP 8 05 33 1.4 to 46 257 257 234 t,828 0 63 57 3 3 30 57 85.87 SFPH 5 5 to 53 53 to M4 0 29 32 0 20 8 28 85.44 SFPV 746 654 3.075 3,875 2.767 24.645 52 725 40 39 914 15.80 SPRS 172 357 838 836 20s 12.434 24 347 4 II tel 80,400 1520 SvH t,456 7.297 7,297 - 4.442 - . -

128 2.715 SS 75 9.603 1.365 15 Tenaan m .

332 173 1,0e8 t.ees ese 8.33e tes 14 15 320 18 i SWST .

4 50 22 134 330 82 SAe4 16 2 CST to 8.18 4 2,333

$3 . . . 14 Ts 73 -

18 3 CWI - .

. t 3 3 . Is 14 4 FI . 2 - . .

1,178

. 36 . . . . t 45 45 .

16 5 FOS . . S 27 27 . 737 16 6 FPH - 20 . .

54 2 - . . - 8.38 2 2 -

16 7 CH -

5 23 23 3 400

. 17 0 04 S et 1.11 -

3,000 IS S HRS 99 166 75 444 444 282 95 4 7 to t PWST .

187 265 158 aos ses 653 7.828 .

3 242 8 18 16.10 ftW$ilSCAT - 2 11 11 - 208 16.11 STFS - 9 - . .

542

. . 4 28 23 .

46.82 STPt - 17 - .

248 2 6 - - - - 2 to to - '

18 13 WEST-RCA . 4 22 22 - Set

- 17 - . . .

16 14 Yas4 Tranniosmere(X ttXt4/X16) 781 est 2.He 2,479 200 1,524 - - . 24214 5 744 27 38 417 to Teeman 543 2,774 2,774 . 148 - - - 18.840

- 2,018 t.17 8.59 Si 149 17 Erecs ecaNW1er eveteme semoval t

4 6

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genemoneneass.sgsadeg,mem6 s l Males Fenhes Aasen8e Poesr Seeden Appenane 4 Ja n ge Fs(s P las Ca8eAa*Isaia TAGLE C.t teAssE VANKEE AToenIC rotMER STAltON AREA 41Y, AREA COST ESTIAAATE (Thousande of 1967 Desars)

Peak Sedy Eury Genea

• Tesel Lis Temos Casen A CP S CP C CP aC CP ' Wwe

• -_ M-ft__2 _ - _

n a-a-h of Site Buddungs tes tes 4.357 4,367 - S.428 . . . 22.88F St l Consanmens 0ecenteneneden 543 206 SS 33 2.314 69 134 d38 630 . Fe6 . . . 3.884 70 SF G 4 298 18.2 Fueland RCA BuMne Decensembiamen 334 Set 25 - 3 2 139 - 48 214 2te . . - .

18.3 h - -- BMee Deconseeuneman t,148 1,782 . - . 3.884 I44 PAB P " - - - ' - -

105 7 17 le 733 IS 244 1.146 .

7 33 33 . S4 . . - SF .

10 5 RMCC Decensamenenen 3 . 0 0 22 .

• le 37 183 143 272 . . . 438 le t SVH n.'- --- -

8 7 2 2 112 - .

849 848 1,344 . . . 2,134 18 7 Sandse Bisheng Decensembiamen SS . 13 4 SS$ . teS -

F44 . . 1,383 18 4 Sprey tiahtie Decessemeiseen SS 2 7 4 304 4 tes 483 443 . .

64 474 479 . 479 . . . 1,348 8 4 276 54 ta t Tietme Bunne n -e-.**= IS 28 11,367 11.367 . 43,332 . . . 4.742 [

14.10 Censomniated Se4 Removal . El 777 1,195 7.250 - 2.005 48,288 847 11,900 344 3,tes 19J44 ISJ44 . 94,860 . . -

18 Tosene 928 427 t.262 3,827 10,900 . . . . 130,489 .

19 Ucenes ternbeatem ewvey . . - - - 7,063 10.000 .

. . . I 20 ORAu sensumesery onevey . - . . - BOS IS 121 323 . .

i Peded 2 AddlIIenalCaste 450 . . . .

28 Casse s.achaise ter st-- weeno ompee s . . . . t,sse . 2.297 2.297 .

i 22,479 40.008 170.388 170.000 238 147.400 2,441 1,084 22F actsees Sukeneel Pested 2 ActMIy Costa 3.594 28.992 4,400 9.838 80.114 Peded 2 taideseHhisted Caste . - et S78 878 . . . - . .

9 Decen e,apment See . -

STS . . . . . Set 847 447 . . .

2 Deceamapptee . . - t 730 . . . . See 639 830 . . .

3 DOC eteNseteceden . .

790 3,883 3.863 - - 4.473 . . t.eas  !

4 Presees aged iensas 27S . 3ee See 2.000 -

2.944 298 3.241 3.249 . -

S huisance . .

4.87F S.577 . . - - - .

e Properg temas . . . . . S.577 -

2.S$5 . . . . 041 3.207 3.207 - .

F Honsh phyease mopese .

923 - - . .

~

4.020 . . . . 3.204 a.233 8.313 8 Heavy ogapmens sensel -

. 364 . . . . SS 4 88 3F7 42 . .

e Smeetestscouvence 421 . . - . .

. 714 . . . . teT 821 .

10 Pipe emng egapmess 1,08F 1,087 . . . . . .

928 - . . . . 139 88 Deses see 252 1,932 1.932 . - - . . .

12 Depeast ef DAW generated - . . 20 - 1.800 88 874 674 . 572 . . . F78

_ E,apmest e . - 5 3 235 2Fe 13 De-.

S 434 see - - . . .

. . . S.637 844 JS.482 -

14 Plant energy budget . .

1,242 . . . . . -

. . . . , 1.168 117 1.282 15 NRC ISFS8 Fees ._

1,246 1,240 . . .

. . . . 1.127 st3 - - .

le NRC Feee .

. . a04 eo se4 es4 - . . . . .

17 Emergency Planreig Fees . -

. . . . - s,c73 761 S.e34 - 5.834 . -

le See seasey . . . . . .

. . . . . 3,438 $24 4.021 4.021 19 Fasad Overhead Case 360 . . + .

. . - 334 82S 958 . . .

20 LLRW Piecessee Eespmere . .

[

29 Stest kuentwo . . . - - 1,409 223 IJ12 tJt2 - - - . .

I 8,0$8 54J40 83,127 t.513 572 4.073 . . 1.894 g

' ' Cests Posted 2 2.449 12.402 344 529 2,241 30.879 subesent e i

r 4

i W Asse #seedet.See6 # i Ade&ne Fennee Asemsle Neer aseseess

!1 4.nina Obese Amelpede a- .m. C Peseaof8 TAALE C-1 ,

taAesE VAsetEE ATotec PotNER eTATIOlt AREASY4dtEA COST ESTeAATE (Theissends se tee 7 Demers) g

'- Semnese Pack sed, tury Gener Cassemey Teest Las Tasms Cemen A CP e CP C CP eC CP teus ,

Sten Cests *. . .

S t.583 3.738 13.328 13.321 . . .

Asseneseed Sten Cent SeJe2 e,eSe SeJ68 SeJ61 . . . . . .

$ sed Cens 4.063 41,384 4.e38 10.365 62,354 123.e34 SS.282 3e7.2e3 3e5.20s 1.083 tes.edt 7.388 1 e64 227 003.082 TOTAL Ptstt00 2 PEttI00 3

\

Demmelsten of Itasmeesmie She needhees 3.eSe . . . . 45e 3.518 352 3.105 . . . . 37Ast

.= 22.8 Centanoeuse .

. 2eg

- te . . . . 2 to . to . . .

22 2 t tS itV 5.mch Yord ressidensas 22 3 Aneminemen sidene & Ashanens - 7e . . . . 12 es - se . . . . i>4r 4ee . . . . 70 $30 . 438 . . . . y,4pe 22.4 CeasseneWeres Pump Heine .

. 5 . . . - e.7e e ese S . . . . 136 22.5 Onese Generness e2 . 3y40

- 187 . . . . 28 102 . tot . . .

22 8 Dahmer Area '

474 . - . . 71 645 84 400 . . . . s.264

.= 22 7 Eosysnesd Heldt .

3,333 22 e Fee Pisap Hause & Pond - 370 . . . - 27 206 - 205 . . . .

237 . . . . 3e 273 41 232 . . . . 5.34F

.= 22 e Fust And RCA tistene .

te 18 . . . . 3M

. e . . . . f.M .

22.18 Fuel ot PtenPHeise s ee e . tes

. e . - . . 128 te . . .

- 22.11 HusiReeseensiseer e et . et . ., . . 1.363

-22_t2 tsA sessnes sissene - 83 . . . .

as 22e 22e . . . . s.s34 l 22.13

- Casen saummes . toe . . . . .

44 366 - 365 . . . . 4,ter 22.84

^ -

- Yord F _

. 317 . - . . '

e7 . e7 . . . . g.2SF 22.15 Passemiel Hansh . 7e . . . . It tle see 133 763 . . . . sg 4eg

~ 22.18 Pusmary Anseery suedne & PW Tissist . 77e . . . .

. 67 . . . . e $$ te es . . . . eee 22.17 fleashr ta C C. Reean g,sey i 22.le Senese sistukig . $2F . . . . 7e see et $46 . . . .

. . f.eT e . e . . . . og l 22 to Semees Teeemmese Plese Pe

. F - .

. 34 204 44 20e . . . . 4,333

==222e epsey em - 204 . . .

38 2To 278 - . . . 3,see  !

22 21 esee tidene & Tissiel . 2H . . . . .

34 283 . 283 . . . . 4,4ee 2222 Gesen Vebe Heine - 228 . . . .

• Yord . Ste . . . . le 136 . 138 . . . . f.est 2223 Tenh F - tes 1,4e3 tes

. e7 . . . . 13 - .

22 24 Taenedessner F- 33,eet

. . . . 217 1, Gee 248 1,488 . . . .

2225 Testais eM . 1.444 Sage 432 . . SS 487 . 40F . . . . t l* . . .

2224 Tisheim Poessant ger -

. 20 . . . . 4 33 . 33 . . . .

2227 Wert eisedsis 14e I 222e Weser Teeeement NeemstaneenTenk End . 6 . . . . t 7 . 7 . . . .

. e.542 . . . .

1.431 10.073 945 18.028 - . . . te3J47 22 Tassen

}

She N d Aseleties

. . 413 3.145 - 3,385 . . . . 5.000  ;

23 Reemene Rieten .

2J52 . .

24 Gsede & tendecepe ete . So - . . - F ST . 8F . . . . 2ef 25 Feist eepert te NRC . .

i e

e

.f. +

= ,

l

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f_

g  %. {rk fa + .

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Deesenment N018256-068. Rem g Appeadts C,Pese9e19 Meine Yankee Atomie Peeper stettom Deeenmanionioning Coons Amstreae TABLE C-1 REAME YANKEE ATOttC POWER STATION AREASY, AREA COST ESTatATE (Theersands et 1997 Dommes)

S CF C CF >C CF Mhrs

• Las Tesse clean A CP Sury Other . p Total Pech Sadp M 0,- P~ R__-__

- - - 22,70$

6.472 S.472 - 8.83S 48 2.t$$ t,394 1.096 - - 5.665 Pened 3 Addaionee Costs 868 112 - 1ASt - -

- 182 842 f.0$$

28 ISFSa t.k. anne TenneteWon - 787 - -

27 ISFSI Desch - - - 2t8.38s 7.418 14.342 8.835 48 2.955 1.575 3.000 21.758

- 13.9T7 112 a.aaaa t reded 3 ActMry Costs

- 3,332 333 3.085 3.06S - - -

Peded 313ndiserttuated Costa - - - -

- 28.854 29.854 - -

1 kneense - - - 21.054 2,381 - - - -

- 3tt 2,389 -

2 Propertytames 2.070 - - -

- 110 - - -

- 94 tia - -

3 Heavy egapanses sental 96 - -

117 - - -

- 102 15 197 -

4 Smaa tocl eSowance - - -

0.854

, S.140 $14 8.854 -

S Pterd energy budget - - -

3.496 348 3.833 3.835 - -

S NRC ISFSIFees - - - -

1,184 8.951 S.058 895 - - -

7 EmergencyPlannbiOFees - -

- 7.784 113 - - - -

945 144 1,133 1.020 - -

0 See Seasty - - -

482 - - - -

- 419 63 482 0 Fined Owtised Coat - - - -

te Staff kzenswe 48.143 44.568 3.817 - - -

- - 43,102 2.914

- 2,188 -

e.Am., a undt we=d Costs Peded 3 4.090 39,350 28.223 3.134 Stas Cests - - -

- 27.299 StsN Cest - - - 298.388 101.300 80.200 2tAS4 8.635 48 2.965 71.944 10.095

- 18.144 112 TOTAL PERtOD 3 14.501 1.644 227 f 000.229 31.452 604.221 44S.223 22.987 179.263 S.807 11.689 43.650 271.824 8.0f 8 80.583 TOTAL COST TO CECOMRetsSsON

$ $08,221,000 TOTAL COST TO DECOMtitSStON INETH 19.09% CONTINGENCY:

$ ess,223 Ate TOTAL NRC LtCENSE TERARINA110N COST IS 95.47% OR:

$ 22,997A00 NON48UCLEAft DESIOUTION COST IS 4 53% OR:

196.814 CUSIC FEET TOTAL RADWASTE VOLutBE BURIED:

9.331 TONS TOTAL SCRAP IRETAL REMOVED:

1.044.229 BRAN 4 TOURS TOTAL CRAFT LABOR REQWtEMENTS:

. ~ . . . . . . . . . .. ~. - .- . _ .~.-..- ...... .. - - .- . - . . . . . ~ -

M:ine Yankee Atomic Power Strion Duument M01 1258-002, Rev. 0 Decommiseloning Cost Analysis Appendix D, Pags l ef 9 5

APPENDIX D WORK DIFFICULTY FACTOR ADJUSTMENTS l

Mring Yankee Atomic Pow:r Staion Document M01-12EC M, Rev, o D:c:mmissioning Cost Analysis Appendix D, Paga 2 ef 9 GUIDELINES FOR APPLYING

. WORK DURATION ADJUSTMENT FACTORS TLG has historically applied work duration adjustment factors in determinin g Unit cost factors to account for working in a radiologically controlled environment. In performing an area-by-area decommissioning estimate the work duration factors are applied on an " area" basis, based on the nominal area conditions. Wliere practical, areas are established based on similar working conditions.

The WDF's fall into five categories: access, respiratory protection, ALARA, protective clothing (PC), and work breaks. The guidelines of how these factors are assessed for each area is described below. Table D-1 outlines the WDF's for each area of the Maine Yankee plant.

1) Access Factor:

C'ontrolling Variables:

. Height of the component above the working floor

. Difficulty in working around the component (restricted access)

Source of Variable Information:

. Estimators observation or judgment

. Plant drawings Range ofAccess Factor Adjustments:

0% - Components are accessible and located near a working level floor or platform 10% - Scaffolding ( component less than <12 feet above floor) is required to access the majority of the components or the area around the components is congested.

20% - Scaffolding ( component less than <12 feet above floor) is required to access the majority of the components and the area around the components is congested.

30% Scaffolding ( component between 12 - 20 feet above floor) is required to l

access the majority of the components or the area around the components are extremely congested.

l

M:ine Yankee Atomic Power Stalon' Document M01-1258 002, Rev,0 -

Decommissioning Cost Analsis Appadix D, P:gs 3 cf 9 40% - Scaffolding ( component between 20 - 45 feet above floor) is roquired to access the majority of the components).

50% - Scaffolding ( component greater than 45 feet above floor) is required to access the majority of the components).

2) Respiratory Protection Factor: -

Controlling Variables:

. Component surface contamination levels (internal or external) i

. Type of work (potential to create an airborne problem) e General area surface contamination levels

. Site specific requirements for maintaining respirator qualifications *

(initial qualification, requalification, etc.)

• Personal air sampler requirements Sources of VariableInformation:  !

. Radiation Work PermitRequirements

. Area Survey Maps

. Site Radiation Protection Program Manual Range of Respiratory Protection Factor Adjustments: .

0%- Respiratory protection is not required (clean system or loose surface contamination has been removed).

25% - Respiratory protection is only required duringlimited segments of the work (i.e. physical cutting) 50% - Respiratory protection is continuously required while working on the component.

3) Radiation /ALARA Factor:

Controlling Variables:

. Component contact dose rate l

' . General area dose rate

. Site specific requirements for maintaining radiation worker qualification (initial qualification, requalification, etc.)

. Dosimetry requirements l

Sources of Variable Information:

i

. Area Survey Maps

. Site Radiation Protection Program Manual

'

• Radiation Work Permit Requirements r

- . . . .. . -- .- - .. - - _ - - _ _ - -- . -- _ ~ - -

M:ine Yankee Atomic Power Staion Document M01-1258-002, Rev, 0-Decommissioning Cost Anclysis App:ndix D, Prga 4 cf.9 Range of Radiation /ALARA Factor Adjustments:

(Note surface contamination levels are principally accounted for in protective clothing requirements and respiratory protection requirements)

~ 0% - The component is clean and is not locatedin a radiologically controlled area

- '10% - The component is located in a radiologically controlled area (General Area Radiation field < 2.5 mrem /hr).

20% - The component is located in a radiologically controlled area (General Area Radiation field between 2. 5 to 15 mrem /hr).

40% - The component is located in a radiologically controlled area (General Area Radiation field between 16 and 99 mrem /hr).

100% - The component is locatedin a radiologically controlled area (General Area Radiation field > 100 mrem /hr). ,

1 l

4) Protective Clothing Factor:

Controlling Variables:

. Component surface contnmination levels (internal or external)

. General area surface contamination levels

. Type of activity (wet / dry work, potential to create a surface contamination problem)

. Site specific work schedule arrangements l l

Sources of Variable Information:

. Radiation Work Permit Requirements l

. Area Survey Maps

. Site Radiation Protection Program Manual Range of Protective Clothing Factor Adjustments (alternate site specific schedules may dictate alternate adjustments):

0% - The component is clean and is not locatedin a radiologically controlled

. area.

30% - The component is clean or contaminated and is located in a surface contammation controlled area . Work is to be completed in accordance with

Maine Ycnhie Atomic Power Staton Document M01-1258-002, )teu, 0' D: commissioning Cost Analysis App:ndix D, Pags 5ef 9 9

the requirements of an RWP, which specifies a single or double set of"PC's",

or "PC's" with plastics.

50% - The components is located in a surface con 6 min ation controlled area.

Work is to be completed in accordance with the requirements of an RWP, which specifies " plastics" in addition to double PC's for protective clothing.

100% - The component is located in a surface con 6mination controlled areh'.'

Work is to be completed in accordance with the requirements of an RWP, which specifies double "PC's" and double " plastics". (extremely wet or humid working environment).

5) Work Break Factor:

Controlling Variables:

. Site specific work schedule arrangements Sources of VariableInformation:

. Typical site work schedule Range of Work Break Factor Adjustments:

8.33% , Workday schedule outlinedin AIF/NESP.036 (alternate site-specific schedules may dictate alternate adjustments).

4 6

Maine Yankee Atomic Power Staion Documen M01-1250-cy ou, c' Decommissioning Cost Analysis Appendix D, Fage 9 af 9 j TABLE D-1 WORK DIFFICULTY ADJUST 5ENT FACTORS Percentaae Lost Minutes Resp. Protect AREA AREA DESCRIPTION Acess Prot. ALARA Clothing ABR AUXILIARY BOILER ROOM 0% 25 % 48 144 BWST BWST 30 % 25% 96 144 CB1-1 CTMT CHRG FL S/G1 SEC MANWAY AREA 20 % 50% 192 240 CB1-2 CTMT CHRG FL S/G2 SEC MANWAY AREA 20 % 50% 192 240 CB1-3 CTMT CHRG FL S/G3 SEC MANWAY AREA 20 % 50% 192 240 CB1-4 SI TANK #2 & REGEN HEATEX E 67 30% 50% 192 240 I CB1-5 CTMT -2 LEVEL OUENCH TANK AREA 20 % 50 % 192 240 CB1-6 CTMT-2 LEVEL SUMP PUMP AREA 10% 25 % 96 144 CB1-7 CTMT LODINE FILTER AREA 20 % 50% 192 240 CB1-8 CTMT -2 LEVEL OUTSIDE LOCP 1 20 % 25% 96 144 CB2-1 CTMT PERSONNEL HATCH. INNER 20 % 25% 96 144 CB3-1 CTMT CAVITY HEAD AREA 40 % 50 % 192 240 CB3-2 CTMT CAVITY UPENDER PIT 30% 25% 192 240 CB3-3 CTMT CHRG FL PENETRATION ROOM 20% 25 % 96 144 CB3-4 CTMT POLAR CRANE (CR-1) 40% 25% 48 144 CCG CTMT CHRG FLOOR (GENERAL) 10 % 25% 96 144 .

CEHO CTMT EQUIP HATCH OUTER 20 % 25% 96 144 CTMT INCORE INSTRUMENT SUMP 20 % 25% 96 144 CICI CPHO CTMT PERSONNEL HATCH OUTER 10% 25% 48 144 50 % 25% 96 144 CPLE CTMT PZR DOGHOUSE LEVEL ELEV ROCM CST CONDENSATE SURGE TANK 20 % 0% 48 -

CW1 CIRC WTR PUMP HOUSE 10% 0% - -

0% 0% 48 -

DG-2 DG 2 ROOM 10% 25 % 48 144 DWST DWST 10% 25%- 48 144 EFPR EMERGENCY FEEDPUMP ROOM FI FOXBIRD ISLAND 0% 0% - -

FUEL OIL BUNKER 10% 0% 48 -

FOB FPH FIRE PUMP HOUSE 0%l 0% - -

30 %I 0% 48 144 FWH TURBINE BLDG FEEDWATER HEATERS GH GAS HOUSE 0%I 0% - -

HRB HIGH RADIATION BUNKER 0%) 25% 96 144 LLWB LOW LEVEL WASTE BLDG 0%i 0% 4 81 -

10%l 25% 4 81 144 LSAB LSA BUILDING MCR MAIN CONTROL ROOM 0% 0% 4 81 -

10% 0% 4 81 144 MTGE TURBINE DECK EXCITER AREA 20%l 25%' 9 61 144 NFLA NEW FUEL LAYDOWN AREA OSR OIL STORAGE ROOM 10 %I 0% 48f -

10%l 25% 96! 144 P21A PAB 21FT LEVEL VALVE ALLEY 144 10%I 25% 9 61 P218 lPAB 21FT LEVEL BORIC ACID PUMP AREA 10% 25 %I Eil[ 144l P21C IPAB 21FT LEVEL CHRG PP CUBICLE _

30 % 25%I 1921 240]

P210 iPAB 21FT LEVEL DEGAS CUBICLE 240' 30 %I 25%l 192l P21E PAB 21FT LEVEL EVAP CUBICLE 30 %I 25%l 4801 240l P21 H PAB 21FT LEVEL HEAT EXCHANGER ROOM

Maine Yanhee Atomic Power Staion Document M01-1258-002, Rev. 0

• D: commissioning Cost Analysis Appendix D, Page 7 of 9 TABLE D-1 WORE DIFFICULTY ADJUSTMENT FACTORS (continued)

Percentaae Lost Minutes Resp. Protect AREA AREA DESCRIPTION Acess Prot. ALARA Clothing P21V PAB 21FT LEVEL HPSI VALVE ROOM 20 % 25% 144 1'44 PLAD PAB LOWER LEVEL AERATED DRAIN TANK 30 % 25% 96 144 PLBA PAB LOWER LEVEL BORIC ACID MIX TANK 20 % 25% 96 144 i PLCP PAB LOWER LEVEL AUX CHG PMP CUBICLE 30% 25% 192 144 PLDC PAB LOWER LEVEL DEGAS CUBICLE 10 % 50% 96 144 )

20 % 50% 192 240 PLEC PAB LOWER LEVEL EVAP CUBICLE PLLA PAB LOWER LEVEL LETDOWN AREA 20 % 50% 480 240 20 % 50 % 192 240 PLPA PAB LOWER LVL CONT PENETRATION AREA 10% 25% 96 144 PLPD PAB LOWER LEVEL PRIMARY DRAIN TANK 30 % 50% 192 144 >

PLPT PAB LOWER LEVEL PIPE TUNNEL 20 % 25% 96: 144 PLPW PAB LOWER LEVEL PRI H2O PUMP AREA 20 % 25% 96 144 PU48 PAB UPPER LEVEL FN-48 AREA 30 % 25 %. 96 144 PUDD PAB UPPER LEVEL DECAY ORUM CUBICLE 10 % 25% 192 144 PUEC PAB UPPER LEVEL EVAP CUBICLE 10 % 25% 96 144 PUFN PAB UPPER LEVEL FN-1 A/B AREA 10 % 25% 96 144 PUHV PAB UPPER LEVEL HEATING AND VENT 20 % 25% 96 144 PUL PAB UPPER LEVEL (GENERAL) 10 % 25% 4 81 144 PUSA PAB UPPER LVL RADICAC STORAGE AREA 40 % 25% 192 144 PUTC PAB UPPER LEVEL VCT CUBICLE 10 % 25% 48 144 PUWG PAB UPPER LVL WASTE GAS CUBICLE 30% 25% 48 144 PWST PRIMARY WATER STORAGE TANK 20 % 25% 96 144 RCAD RCA DRUMMING ROOM 10% 25% 192 144 RCAW RCA WASTE SOLIDIFICATION 20 % 25% 96 144 l RMCC REACTOR MCC ROOM 20 % 25% 96 144 j RWST REFUELING WATER STORAGE TANK 144 '

10 % 25% 48 SBOR SERVICE BLOG DECON ROCM 144 SSHP SERVICE BLOG HP CHECKPOINT 10 % 25% 4 81 10 % 25% 48l 144 SBMS SERVICE BLOG MACHINE SHOP (HOT) 10 % 25% 4 81 144 SBSR SERVICE BLOG SEAL ROOM 0% 25% 4 81 144 SBTT SBTT Service Buildinc Test Tank Area 20 % 25% 9 61 144 SBVH SERVICE BLOG/STM AND VLV HSE ALLEY 20 % 25% 9 61 144 SFP SPENT FUEL POOL 10% 25% 96l 144 SFPH SPENT FUEL POOL HEAT EXCHANGER 10 % 25%, 4 81 144 SFPV SPENT FUEL POOL VENTILATION AREA 30 % 25%l 96 144 SPRB SPRAY BUILDING 0% 0%) - -

STFB STAFF BUILDING 20 % 0%l - -

STP1 SEWAGE TREATMENT PLANT 144 30 % 25%I 9 61 SVH STEAM / VALVE HOUSE 0%l 0%I 4 81 144 TACA TURBINE BLOG 21' AIR COMPR AREA 10%l 0%I 4 81 -

TEDA iTURSINE BLCG DIESEL ROCM A l 10 %l 0%I 4 81 -

TECS {TURSINE BLOG DIESEL RCCM S

Document M01-125 g .10 Maine Yankee Atomic Power Staion Decommissioning Cost Analysis Appendix D, ?v;,; 6 of g l

l TABLE D-1 i WORK DIFFICULTY ADJUSTMENT FACTORS l (continued) 20%l 0 84 48' 144 TBLO TURBINE BLDG LUBE CIL RES(LOP AREA) 20 % 0% 48 -

TBMS TURBINE BLOG MACHINE SHOP (COLD) 0% 0% 48 144 TBR1 TURSINE BLDG BATTERY ROOM #1 0% 0% 48 144 TBR2 TURBINE BLDG BATTERY ROOM #2 0% 0% 48 144 TBRN TURBINE BLDG BA1 itRY ROOM (NNS) 0% 0% 48 144 TBSO TURB BLOG 21' SEAL OIL AREA  !

20 % 0% 48 144 TBWT TURBINE BLOG WATER TREATMENT 144 20 % 0% 48 TCA TURBINE BLDG 21' CLARIFIER AREA 30 % 0% 96 144 TCBA TURBINE BLOG 21' CRANE BAY AREA 10% 0% 48 144 TCDA TURBINE BLOG 21' COND DISCH AREA 144 20 % 0% 48 TCIA TURBINE BLOG 21' COND INLET AREA 48 144 0%

10%

TCNE TURBINE BLOG 21' COND NORTH END 144 10% 0% 48 TCPA TURBINE BLOG 21' COND PUMP AREA 48 144 20 % 0%

TCSE TURBINE BLOG 21' COND SOUTH END 48 144 0% 0%I TCTP TURB BLDG CABLE TRAY ROOM (PROTCTD) 48 144 0% 0%l TCTU TURB BLOG CABLE TRAY RM (UNPROTCTD) 144 10 % 0% 48 TDBV TURBINE DECK BUDDHA VALVE AREA 48' 144 10% 0%

TDRW TURBINE DECK RAW WATER AREA 48 144 10 % 25%

TOSN TURBINE DECK STORAGE AREA NORTH 48 144 l 10% 0%

l TOSS TURBINE DECK STORAGE AREA SOUTH 48- 144 10 % 0%

TFPA TURBINE BLDG 21' ELEC FEED PP AREA 48 144 30 % 0%

1 THDT TURBINE BLDG 21' HEAT DRAIN TK AREA 96 144 0% 0%

THEA TURB BLOG 21' SCC /PCC HEAT EX AREA 48 144 10% 0%

TMAE TURB BLDG MEZZ LVL AIR EJECTOR AREA 48 144 10 % 0%

TMCH TURB BLOG MEZZ COOLER HEADERS 0% 48 144_

10%

TMOV TURB BLOG MEZZ LVL MAIN ST DUMP VV 0% 48 144 10 %

' TMDW TURS BLOG MEZZ DOMEST~.C WATER AREA 48 144 10% 0%l TMEC TURS BLDG MEZZ LVL EAST SIDE COND 96 144 10 % 25%'

TMFA TURB BLDG MEZZ LVL HV/ FAN AREA 48 144 20 % 0%

TMFR TURS BLOG MEZZ FEED REGULATING VLVS 48 144 10 % 0%I TMFV TURB BLOG MEZZ FEED VALVES 0%l 48 144 10%

TMGL TURB BLDG MEZZ LVL GEN LEADS AREA 0% 48 144 10 %

TMHD TURB BLOG MEZZ LVL HEAT DRAIN TK 10% l 0% 48 144 TMIA TURS BLOG MEZZ LVL INSULATOR AREA 0%l 48 144 10%

TMLT TURS BLOG MEZZ LVL TURB__ LUBE OIL TK 0%l 48 144 20 %

TMNC TURB BLOG MEZZ LVL NORTH END COND 0%i 4 81 144 10%

TMSE TURS BLDG MEZZ LVL SOUTH END COND 0%I 4 81 144 20 %

TMSR TURBINE DECK MOIST. SEPARATOR AREA 0% 4 81 144 10%

TMWC TURB BLOG MEZZ LVL' NEST SIDE COND 0% 4 81 144 10 %

TMWT TURB BLDG MEZZ LVL RAW WT TK AREA 0%) 48 144 10%

TP2C TURBINE BLOG 21' P-2C AREA 0%) 96 144 0%

TSPP ITURBINE BLOG 21' SCC /PCC PP AREA 0% 48 '44 0%

TSRP TURB BLOG SWITCHGEAR ROOM PROTECTED 48 144 l

0% 0%

l TSRU TURS BLDG SWITCHGEAR ROOM UNPROTECT

. - . - . - -. . . . . - . _ - .. .. . -- . ~ . _ - . - . . . . .-. .. . . . . - . . _ _ . . . - -

Maine Yankee Atomic PowerStaion Document M01-1258-002, Rev. 0 -

Decommissioning Cost An:% Appmdix D, Ptga 9 ef 9 TABLE D-1 WORK DIFFICULTY ADJUSTMENT FACTORS 4 -

(continued)

TU TURB BLDG / STAFF BLDG TUNNEL 0% 0% 48 144 WART WART BLDG 0% 0% - -

WEST AREA WEST OF CONTAINMENT 0% 0% 96 -

X14/x16 X-1A/B AREA 0% 0% - -

XS X-1S AREA 0% 0% -

e 9

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