ML20207G988

Rev 6 to Trojan Nuclear Plant Decommissioning Plan

ML20207G988
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/03/1999
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20207G976	List: ML20207G969 ML20207G988
References
PGE-1061, PGE-1061-R06, PGE-1061-R6, NUDOCS 9903120212
Download: ML20207G988 (35)

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l TROJAN DECOMMISSIONING .PfAN d 5.2 SPENT FUEL M ANAGEMENT FUNDING PLAN . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-5 1

5.3 DECOMMISSIONING FUN DING PL AN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6  :

5.3.1 CURRENT DECOMMISSIONING FUNDING CAPABILITIES . . . . . . . . . . . . 5-6 5.3.2 TNP CO-OWNERS' DECOMMISSIONING FUNDING PLANS . . . . . . . . . . . 5-7 5.3.2.1 PG E Fundi n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7 5.3.2.2 EWEB/B PA Fundin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-8 5.3.2.3 PP& L Fund i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -9

6. TECHNICAL SPECIFICATIONS AND ENVIRONMENTAL PROTECTION PLAN................................................................6-1 6.1 TECHNICAL SPECIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1  ;

6.2 ENVIRONMENTAL PROTECTION PLAN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-3

7. QUALITY ASSURANCE PROVISIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1  ;

7.1 OUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 j f] 8. PHYSICAL SECURITY PLAN PROVISIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1 l V

8.1 PHYSICAL SECURITY PL AN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1 .

l 8.2 FITNESS FOR DUTY PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-2

9. FIRE PROTECTION PROG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-1 9.1 FIRE P ROTECTION PL A N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9- 1 APPENDIX A STATE OF OREGON ORDER APPROVING TROJAN DECOMMISSIONING PLAN WITH SUPPLEMENTAL l CONDITIONS ADDED ON OCTOBER 15,1998 I I

PLAN REVIEW REPORT l

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n TROJAN DECOMMISSIONING Pl.AN LIST OF TABLES FOR DECOMMISSIONING PLAN Table Title l 2.2-1 Radiation Exposure Projections 2.2-2 Decommissioning Waste Classification and Volume Projections  :

2.2-3 Steam Generators and Pressurizer Removal Volume Projections 2.2-4 Reactor Vessel Internals Removal Volume Projections i 2.2-5 Major Components Removed (By Year) 3.1-1 Radioactive Effluent Summary, Noble Gases -

3.1-2 Radioactive Effluent Summary, Iodine and Particulates (excluding tritium) 3.1-3 Radioactive Effluent Summary, Liquids 3.1-4 Structures Burial Volume and Contamination Activity Projections 3.1-5 Status of Buildings in the Radiologically Controlled Area 3.1-6 System Burial Volume and Surface Activity Projections j 3.1-7 Isotopic Distribution (Decay Corrected to 1994 and 1998) 3.1-8 10 CFR Part 61 Classification by Component One Year After Shutdown 3.1-9 10 CFR Part 61 Classification by Component Five Years After Shutdown 4.2-1 Regulatory Guide 1.86 Acceptable Surface Contamination Levels 5.1-1 Estimate of" Trust Fund" Decommissioning Costs (1997 dollars) 1 J 5.1-2 Decommissioning Cost Estimate for Trojan Nuclear Plant -

Itemized Decommissioning Expenditure Schedule (1997 $ x 1000) 1 5.3-1 Status of Decommissioning Trust Funds as of December 31,1998 I 5.3-2 Portland General Electric Decommissioning Trust Fund Cash Flow as of 12/31/98 l

- (Nominal $ x 1000) 5.3-3 EWEB/BPA Decommissioning Trust Fund Cash Flow as of 12/31/98 l (Nominal $ x 1000) 1 5.3-4 Pacific Power & Light Decommissioning Trust Fund Cash Flow as of 12/31/98 l l (Nominal $ x 1000)

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LIST OF EFFECTIVE PAGES Section/Page Revised Date Title Page June 1996' Pagei- December 1996 Page1i February 1998  !

Page iii _

June 1997 Pages iv through vi February 1998 Page vii March 1999 Pages viii and ix June 1996 Page x March 1999 Pages xi and xi' June 1996 Page xiii and xiv March 1999 Section 1 Page 1-1 June 1997 Pages 1-2 through 1-6 March 1999 Page 1-7 December 1996 Section 2 Page 2-1 ' December 1996 Page 2-2 February 1998 L Page 2-3 March 1999 Pages 2-4 and 2-5 February 1998 Page 2-6 March 1999 Pages 2-7 through 2-11 February 1998 Page 2-12 June 1997 Pages 2-13 through 2-15 February 1998 Pages 2-16 and 2-17. ' March 1999 Pages 2-18 through 2-29 February 1998 Pages 2-30 through 2-35 June 1997 Pages 2-36 and 2-37 March 1999 Page 2-38 February 1998 Pages 2-39 through 2-43 June 1997 Table 2.2-1 March 1999 Table 2.2-2 February 1998 Table 2.2-3 June 1996 Table 2.2-4 February 1998 Table 2.2-5 December 1998 Figure 2-1 June 1997 xiii Revision 6

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i TROJANDECOMMISSIONING PLAN O' LIST OF EFFECTIVE PAGES Section/Page Revised Date Figures 2-2 through 2-9 June 1996 Figures 2-10 and 2-11 February 1998 ,

Section 3 ,

Pages 3-1 through 3-8 June 1996 Page 3-9 March 1999 l Pages 3-10 through 3-16 February 1998 i Pages 3-17 through 3-37 June 1996  ;

l Page 3-38 December 19% i Pages 3-39 through 3-78 February 1998  :

Tables 3.1-1 through 3.1-4 June 1996  !

Table 3.1-5 l Pages 1 of 8 through 7 of 8 June 1996 Page 8 of 8 December 1996  !

Table 3.1-6 February 1998  !

Tables 3.1-7 through 3.1-9 June 1996 Figures 3-1 through 3-39 June 1996 l Section 4 June 1996 s Pages 4-1 through 4-6 June 1996 i Table 4.2-1 June 1996  :

Section 5 i Pages 5-1 through 5-8 March 1999 )

Tables 5.1-1 and 5.1-2 March 1999 l

Tables 5.3-1 through 5.3-4 March 1999 i Section 6 Pages 6-1 through 6-3 June 1996 I Section 7 j Page 7 June 1996 Section 8 Pages 8-1 and 8-2 June 1996 Section 9'

, Page 9-1 December 1996 l- Appendix A March 1999 l' l Appendix B June 1996 l l 1

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C) Following fuel transfer to the ISFSI, dismantlement of the radioactive systems, components, and l structures is scheduled. Components and structures will be removed consistent with approved  !

. plant procedures and processes, including the TNP Nuclear Quality Assurance Program, where  :

appropriate. The Nuclear Quality Assurance Program provides controls for quality-related

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activities pertaining to the operation, maintenance, design, modification, and decommissioning i l of TNP. Section 7. discusses the Nuclear Quality Assurance Program. l l I The TNP Decommissioning Plan was submitted January 26,1995, in accordance with the' l l existing requirements of 10 CFR 50.82, " Application for termination oflicense," Paragraph (a), I i

! which required submittal of a proposed Decommissioning Plan within two years of permanent l l

l cessation of operations. The Decommissioning Plan is considered to be the Post-Shutdown I i Decommissioning Activities Report (PSDAR) per revision to 10 CFR 50.82, effective I i August 28,1996. The objective of the Decommissioning Plan is to demonstrate TNP can be -I i decommissioned in a safe manner and to describe plans for demonstrating the facility and site '

meet the criteria for release for unrestricted use. The plan is designed to allow implementation flexibility in actual decommissioning activities to incorporate evolving technology, where L appropriate.

1.1.2 CONTENTS OF THE DECOMMISSIONING PLAN The Decommissioning Plan was prepared in accordance with 10 CFR 50,82(b)

- [10 CFR 50.82(a)(4) as of August 28,1996) and the guidance provided in Draft Regulatory Guide DG-1005," Standard Format and Content for Decommissioning Plans for Nuclear Reactors." In part, the Decommissioning Plan discusses TNP decommissioning methodology and organization, estimated costs and available funds, major tasks and schedules, protection of occupational and public health and safety including site characterization, radiation protection, i waste management, and analyses of hypothetical dec,ommissioning events. It also addresses a j number of additional areas and programs such as quality assurance, fire protection, and physical security provisions.

The license termination plan will be a supplement to the DSAR or equivalent and will be submitted at least 2 years before terminatic,n of the license date.

The license termination plan will include.

1. A site characterization; l 2. ' Identification of remaining dismantlement activities;

3. Plans for site remediation; i 1-2 Revision 6 I'

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TROJANDECOMMISSIONING PLAN

4. Detailed plans for the final radiation survey;

5. A description of the end use of the site, if restricted;

6. An updated site-specific estimate of remaining decommissioning costs; and

7. A supplement to the environmental report, pursuant to 51.53, describing any new

information or significant environmental change associated with the licensee's l proposed termination activities.

1.2 MAJOR TASKS. SCHEDULES AND ACTIVITIES .

TNP decommissioning is divided into two broad periods

transition, and decontamination and dismantlement. Decommissioning will be followed by site restoration. This section provides a brief description of these activities. Details are provided in Section 2.2.

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2.1 DESCRIPTION

OF MAJOR ACTIVITIES The Transition Period began with permaner.t plant shutdown in January 1993 and will continue until spent fuel is transferred to an ISFSI. The Decontamination and Dismantlement Period will begin once the spent fuel is transferred to the ISFSI. Site restoration will begin following termination of the Part 50 license and involves the final disposition of structures, systems, and components.

Throughout TNP decommissioning, PGE may use contractors to provide specialized services or to supplement the facility staff when necessary. PGE will administer the tasks and oversee contractors as delineated in Section 2.5.

Storing fuel at TNP during and after plant decommissioning significantly impacts both the process and costs associated with decommissioning. The TNP contract with DOE," Standard Contract for -

Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste," stipulates services provided by DOE shall begin not later than January 31,1998. This contract clause provides the basis for the

) schedule forecast in DOE's annual acceptance priority ranking for receipt of spent fuel and/or high

level waste. The published schedule specifies the first TNP shipment to be in 2002 (the fifth year of' repository operation,~ assuming initial operation in 1998), and the final shipment is projected for .;

2018. Recogr.izing the uncertainty, but with no better formal estimate, the contract dates for fuel shipment are currently being used for planning purposes. The spent fuel management plan is discussed in Section 3.3.

1.2.1.1 Transition Period During this period, PGE will maintain systems and components required to support decommissioning and spent fuel storage in accordance with the Facility Operating (Possession Only) License NPF-1 and administrative procedures. Activities anticipated include assessing the 1-3 Revision 6

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TROJAN DECOMMISSIONING PLAN

.i functional requirements for systems, structures, and components; deactivating systems, structures, l

and components; some dismantling, including removal of steam generators, pressurizer, and other  !

systems / components not necessary for assuring safe spent fuel storage in the spent fuel pool; and  :

maintaining safe spent fuel storage. PGE will also conduct detailed decommissioning project ,

planning, prepare engineering specifications and procedures, procure special equipment needed to support decommissioning, and negotiate service contracts required for decommissioning  ;

activities.  !

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Major activities scheduled to occur following Decommissioning Plan approval during the  !

Transition Period include system deactivations and system / component removal not necessary for j safe storage of fuel; limited decontamination of structures; reactor vessel internals removal or l reactor vessel with internals intact removal; decontamination and dismantlement planning; ,

licensing and constructing an ISFSI; and transferring the fuel from the spent fuel pool to the i ISFSI.

• Spent fuel will be transferred from the spent fuel pool to facilitate decontamination and ,

dismantlement. Once the spent fuel is transferred to the ISFSI, the Transition Period ends and the Decontamination and Dismantlement Period begins.

. 1.2.1.2 Decontamination and Dismantlement  :

Major activities planned during the Decontamination and Dismantlement Period include l

- removing remaining contaminated systems and components, decontaminating structures, and a j final radiation survey to verify radioactivity has been reduced to sufficiently low levels to allow for unrestricted release of the site.

~ Contaminated systems, components, and structural material will be decontaminated or removed and packaged. The packaged material will either be shipped to an off-site processing facility, shipped directly to a low-level radioactive waste disposal facility, or otherwise handled in

-accordance with applicable regulations.-

Decontaminating plant structures may be completed concurrent with removing equipment and systems and may include the use of a variety of techniques ranging from water washing to surface material removal. Demolishing certain buildings may be necessary based on degraded structural integrity as a result of decontamination efforts and/or removal of systems and components, surrounding walls, or other barriers.

. A final radiation survey will be' performed to determine the final condition of the site after l decontamination activities are complete. The purpose of the final radiation survey is to demonstrate radiological conditions at TNP are within the final site release criteria to support  :

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i TROJANDECOAfAflSSIONING PLAN l O license termination. Upon completing the final survey, a fmal survey report will be submitted to

! the NRC.

! 1.2.1.'3 Site Restoration Nonradiological site remediation activities are scheduled to be completed following termination of the Facility Operating (Possession Only) License NPF-1. Nonradiological site remediation activities are scheduled to begin around 2018 and conclude in 2019. Some site restoration activities will be completed during the Transition and Decontamination and Dismantlement Periods of decommissioning.

1.2.2 FNAL RELEASE CRITERIA i TNP decommissioning will safely reduce radioactivity at the site to acceptable levels thereby allowing release of th , site for unrestricted use. Release criteria are discussed in Section 4.2.

1.2.3 SCHEDULE FOR DECOMMISSIONING / SITE RESTORATION ACTIVITIES i A detailed schedule for decommissioning / site restoration activities is presented in Section 2.2.

The following is an overview of the current TNP decommissioning / site restoration project Lvf) t

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January 1993 - Early 2000 Transition Period l l Late 1994 - Late 1995 - Large Component Removal Project Late 1996 - Late 1998 Complete planning / building an ISFSI Early 1997 - Late 1999 Reactor Vessel and Internals Removal Early 1999 - Early 2000 Transfer spent nuclear fuel to the ISFSI I Early 2000 - Late 2002 Decontamination and Dismantlement Period l Mid 2001 Submit application for termination of the license I i Late 2002 Complete fmal radiation survey Late 2002 - Mid 2018 Caretaking

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Mid 2018 - Late 2019 Demolish buildings i

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i TROJAN DECOAIAflSSIONING PLAN O 1.3 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN

SUMMARY

t This section provides a summary of the final estimated costs and funding methodology for TNP .

decommissioning, spent fuel management, and nonradiological decommissioning activities. The  !

decommissioning cost est; mate and the co-o vners' plan for assuring availability of funds for  !

. completing these activities is provided in Section 5.

l 1.3.1 COST ESTIMATE

SUMMARY

i TNP radiological decommissioning, dry spent fuel storage, and nonradiological I decommissioning costs are estimated at approximately $433 million in 1997 dollars. Costs are 1 derived from a cost estimate prepared by PGE and TLG Services, Inc. Table 5.1-1 provides an l itemized summary ofcosts. l 1.3.2 FUNDING PLAN

SUMMARY

1.3.2.1 Current Decommissioning Funding Capabilities  !

Co-owners separately collect and maintain funds for decommissioning. Funds are collected through rates and deposited to external trust funds. Because TNP was shutdown prematurely, the  ;

extemal trust funds contain only a portion of the total amount needed for decommissioning. As i of December 31,1998, approximately $80 million were in the funds, which is in excess of I decommissioning expenses through 1998. Table 5.3-1 summarizes the status of the I decommissioning trust funds.

1.3.2.2 Decommissioning Funding Plans The decommissioning trust fund cash flow and funding plan for each of the co-owners are presented in Tables 5.3-2,5.3-3, and 5.3-4. The co-owner funding information incorporates trust fund contribution schedules and necessary financial assurance and bridging funds. The trust fund ,

contribution schedules are based on funding requirements for both radiological and l nonradiological decommissioning costs, as well as financing costs and specific spent fuel j management costs including planning, design, construction,~ operations and maintenance (O&M), J and decommissioning of an ISFSI.

As indicated above, decommissioning trusts will not initially contain the funds necessary to complete radiological decommissioning prior to the start of the Decontamination and .

Dismantlement Period. Therefore, prior to commencing this period, each co-owner will secure l and maintain a financial assurance mechanism in accordance'with 10 CFR 50.75," Reporting and recordkeeping for decommissioning planning." Additional funding plan details are provided in Section 5.  ;

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TROJAN DECOMMISSIONING PLAN i O 6 Maintaining safe storage of spent fuel.

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7. Dismantlement and removal of some systems / components not necessary for assuring safe spent fuel storage in the spent fuel pool. l i

The Transition Period began with permanent plant closure in January 1993 and will continue i until the spent fuel is transferred to the ISFSI. Decontamination and dismantlement of the  !

remaining facility radioactive systems, components, and structures are scheduled to be conducted upon completion of the transfer of spent fuel to the ISFSI. For planning purposes, it was .

assumed that spent fuel and high-level waste will be stored in the spent fuel pool until 1999, at

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which time it will be transferred to the ISFSI. Some dismantlement activities may occur during the Transition Period. l i

Major activities planned during the Decontamination and Dismantlement Period include:

1. Removal of remaining contaminated systems and components;  ;

2. Decontamination of structures; and I

3. Final radiation survey.

O Major decontamination and dismantlement activities are expected to last from early 2000 to the I i i

end of 2002. The final radiation survey will be completed following decontamination and I j dismantlement.

Some activities, such as detailed planning, may continue through more than one period.  ;

2.2.3 TRANSITION PERIOD Plant closure activities were initiated following the decision to permanently cease TNP power operations in January 1993. These activities culminated with the plant in a safe transition state  !

awaiting decontamination and dismantlement. Detailed project planning and engineering )

activities for the Decontamination and Dismantlement' Period, as discussed in Section 2.2.4.2, l will begin during the Transition Period. Plant activitics will continue to be implemented in 1 compliance with the existing possession only license and other regulatory requirements.  !

Removal of the four steam generators and pressurizer has been completed. These components were disposed of at the US Ecology radioactive waste disposal facility near Richland,

, Washington. Removal of the steam generators and pressuri7er were accomplished through a new opening in the south face of the Containment Building. That opening is equipped with a door so that the Containment Building can be maintained in a closed condition except during active

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TROJANDECOMMISSIONING PLAN L O acceptable levels, allowing for release of thel site for unrestricted use. This information provides i the basis for development of the programs and proceduces for ensuring safe decommissioning and a basis for detailed planning and preparation to be completed prior to initiating decontamination and dismantlement activities. l l

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During this period, the remaining contaminated systems and components will be decontaminated or removed, packaged, and either shipped to an offsite processing facility, shipped directly to a low-level radioactive waste disposal facility, or handled by other attematives in accordance with applicable regulations (e.g., greater than Class C waste).

Decontamination ofplant structures may be completed concurrently with equipment removal. j Decontamination of structures may include a variety of techniques ranging from water washing i to surface material removal. Contaminated structural material may be packaged and either I shipped to a processing facility, or shipped directly to a low-level radioactive waste disposal facility. Alternative disposal methods, in accordance with applicable regulations, may also be used.

' A comprehensive final radiation survey will be completed following the removal or -I decontamination of contaminated systems, components, and structures. The survey.will verify that radioactivity has been reduced to sufficiently low levels to allow the release of the site for

[ unrestricted use. Upon completion of the final survey, PGE will submit a report to support license termination per 10 CFR 50.82 and State of Oregon regulations. A discussion of the final radiation survey is provided in Section 4.

' 2.2.4.2 Detailed Planning and Engineering Activities Detailed project plans will be developed in accordance with design control procedures to support the decontamination and dismantlement activities before they are initiated. The plans will be used to develop work packages, support ALARA reviews, aid in estimating labor and resource requirements, and track decommissioning costs and schedule.

Work packages will be used to implement the detailed plans and provide instructions for actual field implementation. The work packages will address discrete units of work and will include j

. appropriate hold and inspection points. Administrative procedures will control work package  ;

' format and content, as well as the review and approval process.

2.2.4.3 General Decontamination and Dismantlement Considerations The following general decontamination and dismantlement considerations, as applicable, will be

. incorporated into the decommissioning work packages. Specific considerations are presented in Section 2.2.5.

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q TROJAN DECOMMISSIONING PLAN 2.2.5.4 Reactor Vessel The reactor vessel supported and contained the reactor core, directed coolant flow through the core, and facilitated operation, control, and handling of reactor components. The reactor vessel is a fabricated cylinder with a hemispherical bottom head and a removable hemispherical upper head. It contains the core support and other internal structures. The reactor vessel has four inlet and four outlet nozzles located in a horizontal plane below the upper head flange. The reactor vessel is carbon steel with weld deposited austenitic stainless steel on surfaces that were exposed to the reactor coolant.  :

The vessel is contaminated and activated. The reactor vessel may be removed with the reactor vessel internals intact or the internal. may be separately removed. Separate reactor vessel internals removal is discussed in Se ion 2.2.5.3. The following specific considerations apply.

The reactor vessel upper head can be sed ofintact, in segments, or with the reactor vessel. I Ifit is disposed ofintact, a cover plate will be installed over the bottom flange. Control rod drive l mechanism (CRDM) housings and other attachments to the head will be removed and the  !

penetrations sealed. If the reactor vessel upper head is disposed ofin segments, the upper head l can be processed using cutting methods suitable for cutting thick, highly activated components.

The sections can then be packaged and shipped. If disposed of with the reactor vessel, the upper head will be attached to the vessel by means of tensioned studs. The number of studs will be sufficient to maintain the integrity of the. vessel package under transportation conditions. l (b'

The reactor vessel may also be removed intact, with or without the internals or upper head, or sectioned. The method selected will be based on an evaluation of the ease of execution, personnel exposure, schedule impact, transportation availability, and cost.

Ifigh dose rates from the activated surfaces of the reactor vessel may require the use of special shielding and handling methods to ensure that personnel exposure is maintained ALARA.

Neutron irradiation from the reactor operation generated activation products in the reactor vessel.

Based on the neutron activation analysis shown in Tables 3.1-8 and 3.1-9, the reactor vessel can be disposed of as 10 CFR Part 61, Class A waste (vessel wall) and Class C waste (vessel clad).

The reactor vessel and reactor internals, packaged together, can be disposed of as Class C waste. ,

The radionuclide content estimates will be verified with a radiation survey of the reactor vessel.

Detailed classification evaluations will be completed as a part of detailed planning of the reactor vessel removal activity.

Intact vessel removal would involve shipping the vessel, with or without the internals, to a low-level radioactive waste disposal facility in one piece. This may require cer:ification of an exclusive use shipping container for transporting the vessel, or the vessel may serve as its own shipping container. If removed together, the reactor vessel and internals will be shipped as a

(] NRC-approved Type B (as exempted) package. A safety analysis report will be prepared to I

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TROJANDECOMMISSIONING PLAN 1 support NRC appwsl of the package. The following items will be considered if the vessel, with or without the internals, is ren.eved intact:

1. Removal of support attachments;

2. Removal of piping up to the nozzles and capping the nez7Jes;

3. Installation of a cover over the vessel flange to reduce dose rate and control airbome radioactivity; 4.- Removal of water from the vessel;

5. Application of a fixative coating or grouting to stabilize remaining internal surface contamination;

6. Reconfiguration of the polar crane to its 400 ton capacity;

7. Selection of an appropriate lifting point on the vessel;

8. Attachment of a skid box or upending device for handling the vessel; and

9. Routing the vessel through the construction opening and loading it onto a transporter.

Segmented vessel removal would involve shipping vessel sections to a low-level radioactive waste disposal facility inside appropriate shipping containers.

Sectioning of the vessel can be performed by appropriate cutting or machining processes. The vessel is lined with stainless steel which limits methods for sectioning. However, removal of the stainless steel lining with machining, grinding, or other techniques would expose the carbon steel vessel wall. The carbon steel could then be sectioned using appropriate thermal or mechanical cutting techniques. Altematively, the vessel could be filled with grout and sliced into sections

. using a diamond wire saw. The following items will be considered if the vessel is removed in sections:

1. Shipping the lower hemispherical head in one piece after removal and plugging of incore detector sleeves;

2. Use of a water purification system and/or an underwater vacuum cleaner in the proximity of the cutting to minimize contamination levels in the water and to maintain clarity when water is in the vessel during cutting operations; O

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TROJANDECOMMISSIONING PLAN O The Steam Generator Blowdown Building is located south of the Main Steam Support Structure, between the Containment Building and Turbine Building. It houses the steam generator  ;

blowdown tank, heat exchanger, pump, and associated valves and instruments. The building has l a reinforced concrete slab floor, reinforced masonry block walls, and a reinforced concrete roof .

- supported by steel beams and metal decking. The building has a foundation curb designed to contain liquid spills. j The Radwaste Annex is a single-story windowless structure adjacent to the north wall of the Fuel Building. It is utilized for laundry sorting, storage, and frisking, as well as solid waste

• compaction and drum storage. l The Wright-Schuchart-Harbor (WSH) Warehouse is a Quonset type building that is used to store  !

parts and materials to support plant activities.

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The Steam Generator Blowdown Building, Main Steam Support Structure, and Radwaste Annex I

are potentially contaminated.

2.2.6 DECOMMISSIONING EXPOSURE PROJECTIONS A summary of the projected radiation exposures for the removal of the steam generators and

( pressurizer, decommissioning activities, and spent fuel management activities is presented in Table 2.2-1. These represent conservative estimates of radiation exposure. 3 These estimates are for planning purposes only; detailed exposure estimates and exposure controls will be developed in accordance with the requirements of the Radiation Protection Program (Section 3.2.1) during detailed planning of these activities.

The 1995 exposure projections incorporate the following assumptions and bases: 1

1. Area dose rates are based on radiological surveys that have been adjusted to account for radioactive decay to the estimated start of decommissioning activities;

2. The projected exposure for decommissioning activities is based on site information;

3. The projected exposure for removal of the steam generators and pressurizer is based on detailed project planning; j

4. Personnel radiation exposure during the Transition Period (1994-mid-1998) is estimated to be approximately 2 person-rem per year, excluding some dismantlement j

< activities; and '

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5. Estimated personnel exposure due to the transfer of fuel to the ISFSI is i approximately 1.6 person-rem for each of the estimated 36 casks. '

t The 1999 exposure projections incorporate the actual exposure for the completed steam I generators and pressurizer removal, the intact removal of the reactor vessel and internals, and I l revis:d estimates for normal plant operations and fuel transfer to the ISFSI. The exposure I projection for the fuel transfer to the ISFSI includes a reduction in the estimated number of casks I  ;

to 34. I 2.2.7 DECOMMISSIONING RADIOACTIVE WASTE PROJECTIONS ,

The radioactive waste management program (Section 3.3) will be used to control the generation, j processing, handling, shipping, and disposal of radioactive waste during decommissioning. l Activated and contaminated systems, structures, and components represent the largest volume of low-level radioactive waste expected to be generated during decommissioning. Other forms of waste generated during decommissioning include:

1. Contaminated water;

2. Used disposable protective clothing;

/

3. Expended abrasive and absorbent materials;

4. Expended resins and filters;

5. Contamination control materials (e.g., strippable coatings, plastic enclosures); and

6. Contaminated equipment used in the decommissioning process.

Tables 2.2-2,2.2-3, and 2.2-4 provide projections of waste volumes for decommissioning. The waste volume projections are conservative estimates obtained from the decommissioning cost estimate, removal of the steam generators and pressurizer, and removal of the reactor vessel with intemals intact or removal of the reactor vessel internals. Included in thi3 estimate is 340 fP of greater than Class C radioactive waste from the reactor vessel internals if they were removed l separately and segmented. This waste would be disposed of with the spent fuel.

The decommissioning cost estimate (Section 5) assumes that cost effective waste volume reduction methods are limited. It also assumes significantly contaminated or activated materials are sent directly to a disposal facility. However, alternative processing methods will be i

. evaluated during decommissioning.

O V

2-37 Revision 6 l

TROJANDECOMMISSIONING PLAN Table 2.2-1 Radiation Exposure Projections l

l Exposure - 1995 Exposure - 1999 I L Activity (person-rem) (person-rem) i Steam generators and pressurizer removal 138 546 I Reactor vesselinternals removal 50' -

I Dismantlement-l Reactor vessel 35' 67 I

' Nuclear steam supply system 51 51 1 Spent fuel racks 19 19 I Balance ofplant systems 165 165 i Structures 46 46 l Miscellaneous - 20 20 I i Subtotal 336 368 1 1'

l Normal plant operations 9 30 i Fuel transfer to ISFSI 58 99 I Total 591 551 I l

l

' These exposure projections assume the reactor vessel internals are removed separate from the reactor vessel and segmented. The radiation exposure projection for the intact removal of the reactor vessel and the internals together is approximately 67 person-rem.

6 This value is an actual exposure for this completed activity. I t

Revision 6 i _ _ _ _

i i

TROJANDECOMMISSIONING PLAN

\/ major structural material compositions including Type 304 stainless steel, pressure vessel carbon  !

steel, concrete, and plate /rebar carbon steel.

r i

'A listing of 10 CFR 61 classification by component, one and five years after shutdown, is included l in Tables 3.1-8 and 3.1-9. One year following shutdown, the radioactivity content of activated l components was estimated at 4.2 x 106 Ci. Five years following shutdown, the calculated activity of the activated components was approximately 2 x 10' Ci. Predominant radionuclides include "Fe, {

• Co, and Ni. r If disposed of separately of the reactor internals, it is anticipated that most parts of the reactor vessel will meet Class A burial waste criteria. If the reactor internals are removed separate from the I i

reactor vessel and segmented, the core baffle, core formers, and lower core plate are expected to be GTCC. Poitions of the reactor vessel internals that are GTCC waste will be stored in the ISFSI.

. Intact disposal of the reactor internals with the reactor vessel will meet Class C burial waste criteria.

3.1.2.4 Environment The environmental survey, which included representative outdoor areas, focused on the impact of '

TNP operation on the environment due to the release of radioactive material. Operational and  ;

preoperational environmental monitoring data were used to measure and evaluate the impact.

Additional sampling was conducted to augment, or better. define, areas requiring biased surveys. [

1

( Survey results were compared to background data to determine the overall consequences of TNP operation.

During Phase I of the site characterization plan, soil, sediment, and surface water were sampled.

Exposure rates were measured wherever soil was sampled, except where exposure rates were inf!<.cnced by onsite structures. Paved areas onsite were scanned for beta contamination or sampled and analyzed for gamma emitters. A general site map, enclosed at the end of Section 3 as Figure 3-3, shows the site divided into zones. Survey maps depicting sample points by grid location are provided in Figures 3-4 through 3-14. Survey maps were not included for zones where no samples were collected (i.e., Zones 4,13,15, and 16).

Biased sample locations were determined from reviewing plant records that documented radiological events at TNP frem 1975 to 1993 (see Section 3.1.1.2 and Appendix 3.1 A). Corrective action programs were reviewed and interviews conducted with PGE personnel to help determine i potential sample locations.

Sampling results were compared to release.concentraiion values developed from the site release criteria of 15 mremlyr TEDE (Total Effective Dose Equivaledt). The concentration of radioactive 3-9 Revision 6 n.

y - ,, . - ,# _. -,--____

l TRO.1AN DECOMMISSIONING PLAN  ;

O 5. DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN ,

In accordance with 10 CFR 50.82(a)(4), the TNP-specific cost estimate and funding plan as I

' incorporated into this section provide: I j l

1. An updated estimate of total and remaining TNP decommissioning costs; I  :

I  !

2. A comparison of the estimated costs with present funds set aside for i  :

decommissioning; and l l

l l

3. The plan for assuring the availability of adequate funds for completion of I .l decommissioning and release of the TNP site for unrestricted use. I l

)

5.1 DECOMMISSIONING COST ESTIMATE This section provides the results of and basis for a cost estimate prepared by PGE with assistance from TLG Services, Inc. (TLG) for the decommissioning of TNP. Incorporated into this cost estimate are costs of activities involved in radiological decommissioning necessary for termination of TNP's Part 50 license, as well as expenditures necessary to complete nonradiological site restoration activities. The costs of removal and disposal of nonradioactive structures and materials beyond that necessary for license termination have been identified O- separately from radiological decommissioning costs.

Also separately identified are cost projections and funding requirements for the onsite management ofirradiated fuel until possession and title of the irradiated fuel is transferred to DOE for ultimate disposal. The description of the spent fuel management costs and associated funding plan provided in this rection, together with the description of the spent fuel management program in Section 3.3.1, fulfill the requirements of 10 CFR 50.54(bb). 1 5.1.1 COST ESTIMATE RESULTS Summcrizing the results of the TNP cost estimate, Table 5.1-1 provides estimates of total 1

- decommissioning costs as well as decommissioning costs that remain as of January 1,1999. As I indicated in Table 5.1-1, the costs (in 1997 dollars) for the selected decommissioning i alternative are estime_d to total approximately $239,893,000 for radiological decommissioning - l

^

activities, approximately $51,138,000 for nonradiological decommissioning activities (site I restoration), and approximately $132,527,000 for dry spent fuel storage. Costs associated with I securing and maintaining decommissioning financial assurance and bridging funds are projected to total approximately $9,566,000. A detailed schedule of TNP's decommissioning I and spent fuel management costs, totaling approximately $433,124,000 of decommissioning i trust fund-related expenditures, is provided in Table 5.1-2 and described in Section 5.1.2. I 5-1 Revision 6

mi'

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l_ 5.1.2 COST ESTIMATE DESCRIPTION

! The initial Decommissioning Plan decommissioning cost estimate was based largely on the TNP-specific cost estimate performed for PGE by TLG Services, Inc. in May 1994. The methodology used to develop the cost estimate followed the approach presented in -

AIF/NESP-036, " Guidelines to Producing Decommissioning Cost Estimates," and the DOE

" Decommissioning Handbook." These guidance documents utilize a unit cost factor method for estimating decommissioning activity costs. Unit cost factors incorporate site-specific considerations whenever practicable. Using plant drawings and inventory documents, quantities and volumes of the equipment and material to be removed during decommissioning were estimated. Unit cost factors were applied to the volumes and quantities to estimate the

'" activity dependent" costs. " Period dependent" costs were determined from a critical path

- schedule based on the removal activity duration.

At the end of each year, PGE updates the decommissioning cost estimate based on actual I decommissioning progress and with an estimate of remaining costs based on the best available I infonnation about the remaining scope of the decommissioning effort. The update generally I results in changes to the timing of fund expenditures, and may reflect changes to the scope of l

- major projects. The cost estimate reflects updated staffing requirements, remaining scheduled I decommissioning equipment removal efforts, adjustments for current radioactive waste disposal I

( volumes and costs, and an update of the estimate to disposition non-radiological hazards. I The results of PGE's decommissioning cost estimate have been incorporated into Table 5.1-2, which provides a comprehensive expenditure schedule for the decommissioning of TNP This table incorporates an annual breakdown of projected costs associated with radiological and nonradiological decommissioning, spent fuel management, and decommissioning expenditure financing activities. The decommissioning c%t estimate expenditure schedule contained in Table 5.1-2 is described in the remainder of this section.

5.1.2.1 Radiolon_ical Decommissionino Costs l

1 The cost schedule for radiological decommissioning activities is incorporated into Table 5.1-2, I which reflects tne results of the decommissioning cost estimate for TNP. Consistent with current NRC policy, the TNP decommissioning cost estimate considers radiological I decommissioning costs to be only those costs associated with normal decommissioning activities necessary for termination of the Part 50 license and release of the site for unrestricted use.: The decommissioning cost estimate does not include in radiological decommissioning I costs those costs associated with spent fuel management or the disposal of nonradioactive 'j structures and materials beyond that necessary to terminate TNP's Part 50 license.

5-2 Revision 6  ;

l

__ , _ . _ _ , _ 1

1

)

gm TROJAN DECOMMISSIONING PIAN l

() Radiological decommissioning activity costs are separately identified in Table 5.1-2 as I i

j "DECON/ License Termination." Burial costs were derived from PGE modeling and analysis I oflow-level radioactive waste disposal costs as updated in early 1999, which more I conservatively reflect projected burial rates. Contingencies were applied to each area of the I cost estimate (i.e., decontamination and dismantlement, waste disposal, final survey, etc.) at I appropriate rates. No credit was taken for equipment salvage value. I StanadJ ongoing financial controls have been established and executed to ensure funds are i expended consistent with the provisions of 10 CFR 50.82(a)(8). Throughout the budgetary I process and budget year, costs associated with new projects or activities are evaluated to determine their correct cost classification, i.e., fuel management, radiological, nonradiological I

~

decommissioning, etc. As a result, only costs which meet the intent of the TNP l Decommissioning Plan and TNP License Termination Plan, upon approval, are submitted for I reimbursement from the decommissioning trust. Periodically, variances between the e:;timate j and actual costs will be reviewed as they relate to the total cost estimate to provide assurance that the cost estimate continues to be reasonable. This complies with 10 CFR 50.82(a)(8)(i)(A).

In addition, PGE corporate fincance personnel review the TNP co-owners' trust fund activity and balance periodically. Any significant activity which is inconsistent with the Decommissioning Plan and License Termination Plan, upon approval, would be brought to the I attention of TNP management.

g U The decommissioning cost estimate reflects costs in 1997 dollars, and has been updated to I I

account for work performed through 1998 where TNP expended funds for decommissioning I activities. The decommissioning cost estimate reflects updated staffing requirements, I i remaining scheduled decommissioning equipment removal efforts, and adjustments for I radioactive waste disposal volumes and costs to reflect the latest burial cost projections. I Costs required to maintain spent fuel in a safe storage condition are not funded by the trust fund j while the spent fuel remains in wet storage. Once the spent fuel is transferred to dry storage, there are sufficient trust fund annual contributions to cover annual costs. This is described in I i Sections 5.2 and 5.3.2 and Table 5.1-2. This complies with 10 CFR 50.82(a)(8)(i)(B).

1 In accordance with 10 CFR 50.82(a)(8)(i)(C) and 10 CFR 50.75(e), the TNP co-owners I periodically assess the financial assurance amount required to complete radiological decommissioning. The established financial assurance mechanisms (i.e., letter of credit) are I )

adjusted as necessary to ensure that the sum of trust fund balances and letter of credit amounts l l equals the amount needed to complete radiological decommissioning. " Bridge" funds are I described in Section 5.3. I (3

5-3 Revision 6

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

TROJANDECOMMISSIONING PLAN 5.1.2.2 Nonradiological Decomminioning Costs f Although not required by NRC regulations, the decommissioning cost estimate for TNP l incorporates nonradiological decommissioning costs, as indicated in Table 5.1-2. The TNP  ;

' decommissioning cost estimate considers nonradiological decommissioning costs to be those  !

costs associated with site remediation and demolition and removal of uncontaminated  ;

. structures. The decommissioning cost estimate does not include in nonradiological ,

e decommissioning costs those costs associated with spent fuel management or radiological . l l decommissioning activities. j i .;

5.1.2.3 Soent Fuel Management Costs l Implementation costs associated with spent fuel management are reflected in the projected cost I

. schedule for the onsite management ofirradiated fuel detailed in Table 5.1-2. Spent fuel ,

management costs begin with ongoing spent fuel pool operation, surveillance, and maintenance  !

activity costs, and continue through ISFSI planning, construction, and operation until -)

possession and title of the irradiated fuel is transferred to the DOE for ultimate disposal I (assumed in this estimate to be completed in 2018). As indicated in Table 5.1-2, spent fuel {

pool operation expenditures are projected to end in early 2000 as a result of the transfer of the i 1 spent fuel pool contents to the ISFSI. Costs associated with onsite management of the spent j O fuel will then involve ISFSI operation, maintenance, and surveillance expenditures. Finally, upon transfer of the ISFSI contents to an offsite repository, spent fuel management costs end in 2018 with final expenditures necessary for ISFSI decommissioning activities..

)

PGE has analyzed spent fuel operations and maintenance costs related to storage in both the spent fuel pool and the ISFSI. The methodology used in this analysis considered plant-specific values, as applicable, for labor, material, and outside professional services requirements as well as for other distributed items such as overheads, property and liability insurance, regulatory fees, fire protection activities, and power usage. The results of this analysis were then incorporated into the decommissioning cost study. <

5.1.2.4 Financial Activity Costs j

. Additional costs may be incurred by each TNP co-owner as necessary during decommissioning I to secure and maintain assurance that adequate funds will be available to complete radiological i decommissioning of the TNP site, and to secure loans or other " bridging" mechanisms to augment existing funds to cover near-term decommissioning costs. The financial assurance costs (e.g., letter of credit and loan interest fees) indicated in Table 5.1-2 are based on the basis I points and projected amount of required financial assurance appropriate for each co-owner as described in Section 5.3," Decommissioning Funding Plan." The loan costs in Taole 5.1-2 are based on the interest rate and loan amount appropriate for each TNP co-owner requiring C

5-4 Revision 6

1 i

TROMN DECOMMISSIONING PL4N l financial bridging as described in Section 5.3. The method which each co-owner will use to i

. provide the required financial assurance mechanism and bridging funds is described in detail in l Section 5.3.

l 5.2 SPENT FUEL MANAGEMENT FUNDING PLAN l i l Spent fuel management costs are segregated in Table 5.1-2 into spent fuel pool operation j l

costs and dry storage (ISFSI) costs. Ongoing costs associated with the storage of spent j fuel and other high-level radioactive waste in the spent fuel pool are currently l incorporated into the TNP O&M budget, and are expected to continue to be funded m j this manner until the contents of the spent fuel pool are transferred to the ISFSI. Costs  !

associated with dry storage activities, including ISFSI planning, construction, O&M, and l decommissioning, as reflected under the column heading " Dry Storage" in Table 5.1-2, will be  !

funded with decommissioning trust funds collected for that purpose. Additional details on the I

- decommissioning trust fund collections for each TNP co-owner are provided in Section 5.3.

~

5.3 DECOMMISSIONING FUNDING

PLAN 5.3.1 CURRENT DECOMMISSIONING FUNDING CAPABILITIES Each of the TNP co-owners separately collect and maintain funds for the decommissioning of O. TNP. These funds are collected through rates and deposited to external trust funds in

~

accordance with .10 CFR 50.75. Because the TNP was shutdown prematurely, the external trust I t funds established by the TNP co-owners currently contain only a portion of the total amount  !

needed for site radiological decommissioning. Table 5.3-1 summarizes the status of the TNP i

- co-cwners' decommissioning trust funds as of December 31,1998. l l

The NRC's general policy requires, prior to the start of the Decontamination and Dismantlement Period, either funds needed for decommissioning (as the term." decommission" is defined in 10 CFR 50.2, " Definitions") to be available or an appropriate financial vehicle to I

be secured and maintained that will assure the availability of adequate funds for completion of l radiological decommissioning. As indicated above, the trusts established by the TNP l co-owners for decommissioning will not contain the funds nece'ssary for completion of radiological decommissioning prior to the start of the Decontamination and Dismantlement Period. Thus prior to commencing this period, each TNP co-owner is required to secure a  !

financial assurance mechanism allowed by 10.CFR 50.75(e). This financial assurance must be l l

- maintained until tenninatior, of TNP's Part 50 license. Furthermore, during the Decontamination and Dismantlement Period, a co-owner's decommissioning trust fund balance I may be reduced to a point where it will be necessary in certain instances to borrow or otherwise i

. provide " bridging" funds to complete decontamination activities and allow scheduled collections to restore the decommissioning, trust fund balance.

i-l

'5-5 Revision 6

I p TROJAN DECOMMISSIONING PLAN

\ "}

5.3.2 TNP CO-OWNERS' DECOMMISSIONING FUNDING PLANS Each of the TNP co-owners has established a program in conjunction with specified goals for the collection of funds for the decommissioning of TNP. Each TNP co-owner maintains a l decommissioning fund collection schedule which ensures that each co-owner's portion of the j decommissioning activity expenditures will be fully funded. These trust fund contribution schedules are based on funding requirements for both radiological and nonradiological decommissioning costs, as well as financing costs and specific spent fuel management costs including planning, design, construction, O&M, and decommissioning of an ISFSI. These collection schedules do not include funding for spent fuel pool O&M costs since these costs are l being paid with O&M budget funds rather than decommissioning trust funds. The decommissioning trust fund cash flow for each of the TNP co-owners, based on the expenditure i schedule in Table 5.1-2 and the co-owner contribution schedules, is described below.

5.3.2.1 PGE Funding Table 5.3-2 provides PGE's decommissioning trust fund cash flow in nominal dollars  !

(2.37% escalation) during decommissioning. The trust fund expenditures described in this table i  !

are PGE's share (67.5%) of the expenditures described in Table 5.1-2, with the exception of spent fuel pool O&M costs since these costs are being paid with O&M budget funds rather than I decommissioning trust funds. The trust fund contributions listed in Table 5.3-2 are based upon (V7 PGE's decommissioning trust fund contribution schedule which ensures that PGE's portion of I

the decommissioning activity expenditures will be fully funded.

I Projected requirements for bridging funds have been incorporated into PGE's decommissioning trust fund cash flow. As previously discussed, PGE's external trust fund currently contains i only a portion of the total amount needed for PGE's share of site radiological decommissioning costs. Based on the decommissioning trust fund cash flow analysis presented in Table 5.3 2, bridging funds are anticipated to be required in the year 2000 to complete decontaminauon I activities and allow scheduled collections to restore the decommissioning trust fund balance.

Projected interest on bridging funds has been incorporated into PGE's trust fund cash flow as I )

indicatc t w Table 5.3-2.

In addition, because the trusts established by the TNP co-owners for decommissioning will not contain the funds necessary for completion of radiological decommissioning prior to the start of the Decontamination and Dismantlement Period, each TNP co-owner must secure a financial assurance mechanism allowed by 10 CFR 50.75, and maintain this assurance until termination of TNP's Part 50 license. PGE's financial assurance mechanism will consist of the decommissioning trust fund balance together with a letter of credit. Because financial assurance will be maintained only for radiological decommissioning activities, the I methodology used to determine the size of the letter of credit ensures that if a given amount of f~)

5-6 Revision 6 1

{

r-TRO.lAN DECOMMISSIONING PLAN the decommissioning trust fund is used for purposes other than radiological decommissioning 1 activities during a current year, the portion of the financial assurance provided by the letter of credit must be increased by the same amount. This methodology can be summarized as follows:

La = Ti - T2 + T3 where La = Letter of Credit Portion of Financial Assurance Needed for Current Year T i= Total costs of remaining radiological decommissioning activities 1 T 2= Current decommissioning trust fund balance T 3= Portion of trust balance planned for non-radiological costs during current year i Financial assurance for remaining radiological decommissioning activities will be calculated at I the beginning ofeach year and will be periodically reviewed during each year to ensure that an

' adequate level of financial assurance is maintained.

5.3.2.2 EWEB/BPA Fundino BPA is obligated through Net Billing Agreements to pay costs associated with EWEB's share of TNP, including decommissioning and spent fuel management costs. BPA will fulfill the decommissioning funding obligations of EWEB, including providing financial assurance for EWEB's portion ofdecommissioning costs in a manner stipulated in 10 CFR 50.75(e)(1)(iv) I for Federal government licensees. Table 5.3-3 provides BPA/EWEB's decommissioning trust fend cash flow in nominal dollars (2.37% escalation) during decommissioning. The trust fund I expenditures described in this table are BPA/EWEB's share (30%) of the expenditures described in Table 5.1-2, with the exception of spent fuel pool O&M costs since these costs are

- being paid with O&M budget funds rather than decommissioning trust funds. The trust fund contributions listed in Table 5.3-3 are based upon BPA/EWEB's decommissioning trust fund contribution schedule which ensures that BPA/EWEB's portion of the decommissioning

, activity expenditures will be fully funded.

Projected requirements for bridging funds have been incorporated into BPA/EWEB's decommissioning trust fund cash flow. As previously discussed, BPA/EWEB's external tiast

' fund currently contains only a portion of the total amount needed for

'BPA/EWEB's share of site radiological decommissioning costs. Based on the

' decommissioning trust fund cash flow analysis presented in Table 5.3-3, bridging funds

, will be required to complete decontamination activities and allow scheduled collections to restore the decommissioning trust fund balance. These bridging funds'are not expected to incur interest costs since BPA, as a government entity, will provide the additional -

decommissioning funding when necessary according to the schedule listed in Table 5.3-3.

5-7 Revision 6

k t

TROJAN DECOMMISSIONING PLAN As allowed by 10 CFR 50.75(e)(1)(iv), BPA, as a Federal government entity fulfilling the I i decommissioning funding obligations of EWEB, a licensee, will provide financial assurance in i the form of a statement ofintent. The statement ofintent will contain a reference to the TNP  !

decommissioning cost estimate described in Section 5.1, indicating that funds for radiological l decommissionmg will be obtained when necessary.  !

5.3.2.3 PP&L Fundino

{

Table 5.3-4 provides PP&L's decommissioning trust fund cash flow in nominal dollars  !

(2.37% escalation) during decommissioning. The trust fund expenditures described in this table I  ;

are PP&L's share (2.5%) of the expenditures described in Table 5.1-2, with the exception of  !

spent fuel pool O&M costs since these costs are being paid with O&M budget funds rather than 1

' decommissicning trust funds. The trust fund' contributions listed in Table 5.3-4 are based upon i PP&L's decommissioning trust fund contribution schedule which ensures that PP&L's portion l l of the decommissioning activity expenditures will be fully funded. l i l l Based on the decommissioning trust fund cash flow analysis presented in Table 5.3-4, PP&L's l decommissioning trust balance will remain adequately funded during decommissioning such l that bridging funds will not be required. However, because the trusts established by the TNP ,

co-owners for decommissioning will not contain the funds necessary for completion of  ;

l radiological decommissioning prior to the start of the Decontamination and Dismantlement .

Period, PP&L must secure a financial assurance mechanism allowed by 10 CFR 50.75, and

]

l l maintain this assurance until termination of TNP's Part 50 license. PP&L's financial assurance

! mechanism will consist of the decommissioning trust fund balance together with a letter of I credit. The methodology for determining the size of the letter of credit is as described in Section 5.3.2.1,"PGE Funding."

)

1 l

i 1

. 5-8 Revision 6 i

i

TROJAN DECOMMISSIONING PLAN Table 5.1-1 Estimate of " Trust Fund" Decommissioning Costs (1997 dollars)

Total Total Costs I (Start-to-Finish) Remaining as of I Costs January 1,1999 l Radiological (NRC) Decommissioning Costs I Reactor Vessel and Internals Removal and Disposal 25,898,000 14,386,000 l Dismantlement, Decontamination, and Remediation 157,200,000 97,853,000 i Waste Disposal 38,233,000 23,888,000 I i t

Final Survey 18,562,000 17,802,000 I Total 239,893,000 153,929,000 1

]

I Nonradiological Decommissioning Costs l Site Restoration 51,138,000 50,517,000 I l Total 51,138,000 50,517,000 I O Dry Spent Fuel Management Costs 1

ISFSI Construction and Decemmissioning 62,925,000 41,109,000 l ISFSI Operation and Maintenance 69,602,000 69,496,000 1 Total 132,527,000 110,605,000 I I  :

Financing Costs i Financial Assurance 461,000 461,000 I Decommissioning Bridge Loans 9,105,000 9,105,000 1 Total 9,566,000 9,566,000 1

- l Total Tmst Fund Expenditures $433,124,000 $324,617,000 I Revision 6 p

V ll

,,,emme e.m Table 5.1 Decommissioning Cost Estimate itemized Decommissioning EQ (1997 $ x 100 Radiological j Total Trust Expenditures Decommissioning Total Total Total Total Total Radiological Nonradiological Spent Fuel Financing Combined DECON/

Decommissioning Decornmissioning Management Actntdy Trust License Year Experotures Expenditures Expenditures ExpendMures Expenditures Termination 1993 0 0 0 0 0 1994 7,992 0 0 0 7,992 7,992 1995 15,837 0 1.102 0 16,939 15,837 1996 8,529 492 3,144 0 12.165 1997 8.529 19.309 45 7,974 0 27,326 19,309 1998 34,297 86 9,703 0 44,086 34,297 1999 55,029 8,286 26,354 0 89,669 55,029 2000 43,324 5,059 12,272 637 61,292 43,324 2001 39,168 3,083 3,739 1,462 47,452 39,168 2002 14,672 1,719 , 3,736 1,930 22,057 14,672 2003 1,736 335' 3,729 1,977 7,777 1,736 2004 0 304 3,718 1.569 5,591 2005 0 304 3,703 1.114 5,121

, 2C% 0 305 3,681 660 4.646 2007 0 304 3,655 205 4,164 2008 0 304 3,621 11 3,936 2009 0 305 3,580 1 3,886 2010 0 304 3,533 0 3.837 2011 0 304 3,476 0 3,780 2012 0 304 3,476 0 3,780 2013 0 304 3.476 0 3,780 2014 0 304 3,476 0 3,780 2015 0 304 3,476 0 3,780 2016 0 304 3,476 0 3,780 2017 0 304 3.476 0 3,780 2018 0 10.933 10.951 0 21,884 2019 0 14.105 0 0 14.105 2020 0 304 0 0 304 2321 0 304 0

_ 0 304 2022 0 304 0 0 304 2023 0 1,625 0 0 1,825 t Total 239.293 51.138 132,527 9.566 433,124 239.893 i

f #

TROJANDECOMMISSIONING PW I

t. -

g

...s>.

or Trojan Nuclear Plant i-I penditure Schedule ,

q e--[St, '

I

-,s., ,ty.:e[ i I

N:nradiological Spent Fuel Management Financing I Decommissioning Activities SFP Dry Storage l Rernediation Spent l Costs for l Activites / Fuel ISFS1 Maintaining l Site Pool Construction & ISFSI Financial Costs of I Restoration O&M Decomrnissioning O&M Assurance I Loans I

0 0 0 l O 1,102 0 l 492 3.144 0 1 45 7.974 0 I 86 9,596 107 8,286 10,279 24,644 1.710 l

5.059 7.709 8,612 3,660 238 399 I 3,083 0 3,739 153 1,309 l 1,719 0 3,736 I 55 1,875 y

335 0 3,729 15 1,962 l

304 0 3,718 1,569 l 304 0- 3,703 t,114 1 305 0 3,681 660 304 0 3,655 205 304 l 0 3.621 11 l

305 0 3.580 1 1 304 0 3,533 I 304 0 3,476 304 0 3,476 l l

304 0 3,476 l

304 0 3,476 1 304 0 3,476 I 304 0 3,476 l 304 l 0 3,476 l

10,93? , 7.853 3.098 l 14,105 I 304 304 1 l

304 l

1,825 I

I 51,138 17.988 62,925 69,602 461 I 9.105 Revision 6

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No3rtozr2 - o i -

4 i

TROJANDECOAfAflSSIONING Pl.AN e

Table 5.3-1 Status of Decommissioning Trust Funds as of December 31,1998 l l r Trojan Co-Owner Fund Balance as of 12/31/98' l 1

Portland General Electric (PGE) $62,858,000 I l i

Eugene Water & Electric (EWEB)/ $14,207,000 l Bonneville Power Administration (BPA) i Pacific Power & Light (PP&L) $3,387,000 l I

Total $80,452,000 1 O

l l

o 'The 1998 end-of-year trust fund balances include an adjustment for trust expenditures I incurred in November and December 1998 that were not paid out of the trust in 1998. l l

Revision 6

TROJANDECOMMISSIONING PLAN t t

?

. t Telde 8.3-2 PerGand GeneralElectree i P---

_ ., Trust Fund Cash Fleur As Of120W88 i (9to6ainel$ x 1988) g ~

PGE PGE PGE l PGE y Sndge Loon Bridge Leon Trust Fund Trust Fund Trust Fund Leser of l Trust Fund Funding and internet Year Expenditures Conenbutione ' Leserof Credit .I Not Eermngs EOY Bolence Interest Peyrnent A B Accruel Credit Fee I C D . E l' 1996 F G H I 1997 I

1998 62.856 l 1999 (62,953) 14,041 546 14,492 l 2000 (43,593) 14.041 0 0 15,306 l 2001 (33,836) 14,041 (425) 70,306 0 0 19,957 (246) g 2002 (15,158) (1,427) 46,224 14.041 0 0 1,175 (162) 2003 f2.ne)) 16,497 l (4,471) 14,041 0 (58) 2004 0 (9,554) (2,241) 4,472 l (3,175) 14,041 0 (16) 0 (10,ema) (1,835) g 2005 (3.237) 14.041 0 0 (10,804) 2006 (3,297) 14,041 (1,334) g 0 0 2007 (3,352) 14,041 (10.744) (80g) 236 6,291 (4,633) 2006 (3,403)- 14,041 war; 644 17,317 i

2009 (3,447) (257) (14)  !

i 14.041 1,078 28,975 2010 (3,486) 14,041 (14) (1) 1,527 41,056 I 2011 (3,515) (1) 14.041 1,992 53,574 I i 2012- (3,599) 628 1,958 l 52,561 2013- (3,684) 1,896 50,773 1 2014 (3,771) 1,828 48,830 l 2015 (3,861) 1,754 46,723 l 2016 (3,952) 1,673 44,444 < ]

2017 (4,046) 1,583 41,98.1 [

2018 (23,976) 710 18,715 g 2019 (15,820) 120 3,015 g 2020- (349) 111 2,778 g 2021 (358)

' 102 2,522 g 2022 (366) 92 2,248 g 2023 (2,248) 0 0 g '

Total (252,953) 183,161 I 17,850 (10,435)

, (10,'**) (482)  !

s NOTE 1:

Possive numbers indicate cash Hour into trust fund; nogeeve numbers Indicate cash 8our out of trust Aand, i NOTE 2 : Cunent EOY botence = previous year EOY belance + cupent year A + 8 + C + E + H, Revision 6

m

& N.) TROJANDECOMMISSIONING PIM Table 5.3-3 EWEBIBPA Decommissioning Trust Fund Cash Flow As Of 12/31/98 (Nominal $ x 1000)

EWEB / BPA 1 EWEB/BPA EWEB IBPA EWEBfBPA Bridge Loan G 4 Loan I Trust Fund Trust Fund Trust Fund Letter of Year Trust Fund Fundmg and Interest g Expenditures Contnbubons Letter of Credit Net Eamings EOY Balance Interest Payment A B Accrual Credit Fee g

C D E 1996 F G H l 1997 y

~1998 1 14,207 1999 (27,979) 2,618  !

710 0 10,444 2000 (19,374) 2,749 I 0 0 16,625 2001 (15.038) 650 3's 681 I 2002 15,038 (6,737) 650 67 I 1,398 6,737 2003 (1,987) 650 102 2,150 I 2004 1,987 (1,411) 650 140 2,940 1,411 l 2005 (1,439) 650 179 3,769 1,439 l 2006 (1,465) 650 221 4,640 1,465 1 2007 (1,490) 650 265 5,555 1,490 l 2008 (1,512) 650 310 6,515 1,512 l 2009 (1,532) 650 358 7,523 1,532 l 2010 (1,549) 650 409 8,582 1,549 l 2011 (1,562) 650 462 9,694 1,562 l 2012 (1,599) 650 517 10,861 1,599 l 2013 '1,637) 650 576 12,086 1,637 2014 (1,676) l 650 637 13.373 2015 1,676 g (1,716) 650 701 14,724 1,716 g 2016 (1,756) 650 769 16,143 1,756 2017 g (1,798) 650 840 17,633 1,798 2018 (10,656) 0 g

882 7,858 0 2019 (7,031) 0 g 393 1220 0 2020 (155) O I 61 1,126 '

2021 0 (159) 0 56 1,024 I 2022 0 (163) 0 51 912 I 2023 0 (999) 0 0 0 l 87 I

Total (112.420) 16,417 8,736 73,060 I l

NOTE 1 :

Positive numbers indicate cash flow into trust fund; negative numoers indicate cash flow out of trust fund. l NOTE 2 : Current EOY balance = previous year EOY balance + cunen,t year A + B + C + E + H.

NC .J 3 : BPA will provide bridging funds as necessary from their operating budget, and thus wlR incur no loan Revision 6 costs.

Financial assurance wiR be provided by a statement of intent as anowed by 10 CFR 50,75.

e v = o'"" " co 's 'o"'" p Table 5.34 Pacific Power & Light hommissioning Trust Fund Cash Flow As Of 12/31194 (Nominal $ x 1000)

I PP & L PP & L PP & L I PP & L BraiveLoan BiMy. Loen Trust Fund Trust Fund Trust Fund Letter of l Trust Fund. Fundog and Interaet Year Expenditures Contnbutons Letter of Credit Net Eamings EOY Balance interest Payment I A B Acaual Credit Fee C D E F l

1996 G H l 1997 l

1398 3,387 l 1999 (2,332) 565 100 1,720 l 2000 (1,615) 565 41 704 l 2001 (1,253) 565 1,346 3 14 (7) [

2002 (561) 565 961 (5) 0 15 [

2003 (166) 307 578 (3) 0 155 [

2004 (118) 307 160 (1) 4 348 g 2005 (120) 307 13 548 2006 l (122) 307 22 755 g 2007 (124) 307 31 969 g 2008 (126) 307 41 1.191 g 2009 (128) 307 51 1,421 g 2010 (129) 307 61 1,660 g 2011 (130) 305 72 1,907 2012 (133) 0 83 1,857 2013 (136) 0 I 81 1,80;t 2014 (140) 0 I 78 1,740 2015 (143) 0 I 75 1,672 2016 (146) 0  !

72 1,598 2017 (150) ,O I 69 1,517 2018 (888) 0 I 48 677 2019 (586) 0 I 17 108 2020 (13) 0 I 5 100 2021 (13) 0 I 4 91 2022 (14) 0 I 4 81 2023 (83) 0 I 2 0 I

Total (9.369) 5.021' I 977 (16) l NOTE 1:

Positive numbers indicate cash flow into trust fund; nogetive numbers indicate cash flow out of trust fund.

NOTE 2 : Cunent EOY balance = previous year EOY balance + curTent year A + B + C + E + H, Revision 6 1

l, .

j l

TROJANDECOMMISSIONING PLAN 1 PGE-1061 l

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l i, APPENDIX A STATE OF OREGON ORDER APPROVING TROJAN DECOMMISSIONING PLAN WITH SUPPLEMENTAL l CONDITIONS ADDED ON OCTOBER 15,1998 i PLAN REVIW REPORT i i

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1 Revision 6 4

O V

November 11,1998 DEPARTMENT OF ENERGY '

Joel Westvold, Licensing Manager Trojan Nuclear Plant 71760 Columbia River Highway Rainier, OR 97048 l

Dear Mr. Westvold,

On October 15,1998 the Oregon Energy Facility Siting Council (EFSC) voted to approve your

" Reactor Vessel and Internals Removal Plan." The EFSC approval was based on representations made in the plan, in your July 9,1998 update to the plan , and on representations made in your p October 15,1998 response to OOE questions.

This approval is subject to the attached conditions, which should be considered supplemental conditions to EFSC's March 1996 " Order Approving the Decommissioning Plan."

Please keep the Office of Energy informed of any significant changes in the plan or the shipment schedule.

Sincerely, 4 -7 -

Adam Bless Oregon Office ofEnergy John A. Mhr Governor attachment s_

625 Marion Street NT Salem, OR 97310 (503) 378-4040 FAX (503) 373-7806 Toll-Free 1-800-221-8035

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Attachment:

Supplemental Conditions to the EFSC Decommissioning Order, approving the Reactor Vessel and Internals Removal Plan Conditions Added on October 15.1998

{

10. PGE may remove and dispose of the reactor vessel and internals in one piece for

• transportation by barge in accordance with PGE's January 30,1997 " Reactor Vessel and Internals Removal Plan" as updated by PGE July 9,1998 letter JDW-014-98TF and as 1

further updated in PGE October 15,1998 letter VPN-064-98 to David Stewart-Smith.

Representations in this plan, as updated, shall be considered commitments by PGE.

I1. Representations in PGE's " Application for 10 CFR 71 Certi6cate of Compliance" shall be considered commitments by PGE.

12. - PGE shall not take action to preclude reactor vessel internals removal by segmentation and shipment until the NRC has issued final approval of the reactor vessel package for shipping under 10 CFR 71 and the Washington Department of Health has permitted, in writing, burial of the reactor vessel package under Washington law.

13. PGE shall not take action to preclude reactor vessel internals removal by segmentation and shipment until OOE has received evidence that demonstrates reasonable assurance that U.S. Department of Transportation (USDOT) will approve the shipment under 49 CFR 173.

14. PGE shall not proceed with shipment of the reactor vessel package until OOE has issued final approval of the Transportation Safety Plan, PGE-1077, and USDOT has finally approved the shipment under 49 CFR 173.

O

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