ML022970077

Maine Yankee'S License Termination Plan, Section 3, Table of Contents - Attachment 3A, Figure 3-30

ML022970077
Person / Time
Site:	Maine Yankee
Issue date:	10/15/2002
From:	Maine Yankee Atomic Power Co
To:	Document Control Desk, NRC/FSME
References
+sisprbs20060109, -RFPFR
Download: ML022970077 (98)

Text

MYAPC License Termination PlanRevision 3 October 15, 2002MAINE YANKEELTP SECTION 3IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES MYAPC License Termination PlanPage 3-iRevision 3 October 15, 2002TABLE OF CONTENTS3.0IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES..........3-13.1Introduction..........................................................3-13.1.1Purpose.......................................................3-13.1.2Decommissioning Progress Update.................................3-23.1.3Decontamination & Dismantlement Process Summary..................3-33.2Remaining Dismantlement Activities......................................3-73.2.1Major Decommissioning Activities.................................3-83.2.2Dismantlement Activity Schedule..................................3-93.2.3Material Removal Sequence......................................3-243.2.4Final State-of-the-Site Description.................................3-253.3Methods of Decontamination and Dismantlement...........................3-303.3.1Decontamination of Systems and Components.......................3-303.3.2Dismantlement of Systems and Components.........................3-313.3.3Decontamination of Structures....................................3-323.3.4Building Demolition and Site Restoration...........................3-353.4Evaluation of Dismantlement Activities...................................3-413.4.1Systems Review...............................................3-413.4.2System Deactivation............................................3-413.4.3Nuclear Safety and Regulatory Considerations.......................3-443.5Radiological Impacts of Decontamination and Dismantlement Activities.........3-463.5.1Waste Characterization..........................................3-463.5.2Radioactive Waste Projections....................................3-463.5.3Occupational Exposure..........................................3-513.5.4Public Exposure...............................................3-553.5.5Expected Radiological Conditions.................................3-553.5.6Contamination Control..........................................3-563.6Coordination with Other Regulatory Agencies..............................3-583.6.1Regulatory Agencies............................................3-583.6.2Advisory and Community Entities.................................3-613.6.3Environmental and Regulatory Issues..............................3-623.7References..........................................................3-62 MYAPC License Termination PlanPage 3-iiRevision 3 October 15, 2002ATTACHMENT 3ADrawings Associated with Specific Decommissioning Tasks List of TablesTable 3-1Major MY Area/Systems, Structures, and Components Removed (By Year)...................3-10Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)...........3-12Table 3-3Structures and Facilities Within the Scope of Work for Demolition..........................3-35Table 3-4Status of Major MY Systems, Structures, and Components.................................3-42Table 3-5Safety Related Mechanical Components................................................3-45Table 3-6Nuclides Checked for by 10 CFR61 Analysis............................................3-47Table 3-710 CFR61 Sample Analysis Results (Typical)...........................................3-48Table 3-8Projected Activities and Volumes.....................................................3-49Table 3-9Total Low-level Waste Volume per Maine Yankee Decommissioning........................3-50Table 3-10Approach to Handling of Building Materials for Regulatory Release.........................3-51Table 3-11Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled................3-52 MYAPC License Termination PlanPage 3-1Revision 3 October 15, 20023.0IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES 3.1Introduction3.1.1Purpose This section of the LTP describes the remaining dismantlement activities at MY pursuantto 10 CFR 50.82(a)(9)(ii)(B) and following the guidance of NUREG 1700 and Regulatory Guide 1.179. Information is presented to demonstrate that these activities will be performed in accordance with 10 CFR Part 50 and will not be inimical to the common defense and security or to the health and safety of the public pursuant to 10 CFR 50.82(a)(10). Information which demonstrates that these activities will not have a significant effect on the quality of the environment is provided in LTP Section 8. The dismantlement activities described in this section provide the NRC the informationto support their determination to terminate the license pursuant to 10 CFR 50.82(a)(11)(i). Therefore, this section was written to clearly indicate each dismantlement activity which remains to be completed prior to qualifying for license termination. Furthermore, information is provided on the final state of the site including structural remnants, basement foundations and buried piping and conduits. This information ensures that the scope of any possible residual contaminated materials associated with the final state of the site are considered in dose modeling, survey design and environmental assessment. Any changes to the dismantlement activities described in this section which are made pursuant to 10 CFR 50.59 must also consider the impact of those changes on the final state of the site and any impacts on dose assessment, survey design or environmental assessment.Information related to the remaining decontamination and dismantlement tasks is alsoprovided. This information includes an estimate of the quantity of radioactive material to be released to unrestricted areas, a description of proposed control mechanisms to ensure areas are not recontaminated, estimates of occupational exposures, and characterization of radiological conditions to be encountered and the types and quantities of radioactive waste. This information supports the assessment of impacts considered in other sections of the LTP and provides sufficient detail to identify inspection or technical resources needed during the remaining dismantlement activities. Many of these dismantlement tasks require coordination with other federal, state or local regulatory agencies or groups. Maine Yankee's coordination with these agencies and groups is generally described.An evaluation of the remaining decontamination and dismantlement activities isdescribed in this section. This evaluation presents summary supporting justification for the conclusion that, pursuant to 10 CFR 50.59, activities may be conducted without obtaining a license amendment pursuant 10 CFR 50.90. Where activities require Maine Yankee to obtain a license amendment, such activities are identified along with the MYAPC License Termination PlanPage 3-2Revision 3 October 15, 2002corresponding schedule for the proposed license amendment and the schedule for neededapproval. 3.1.2Decommissioning Progress Update Shortly after the submittal of the 10 CFR 50.82(a)(1) certifications, Maine Yankeeassembled a System Evaluation Review Team (SERT) to evaluate each plant system, structure and component (SSC) against applicable regulatory and design basis requirements. These evaluations resulted in the classification of SSCs as available and/or abandoned. Applicable systems were drained, de-energized and deactivated as appropriate for turnover to the Decommissioning Operations Contractor (DOC). The reactor coolant system was chemically decontaminated to reduce source term in preparation for dismantlement. Systems and functions required to support the safe storage of spent fuel were redesigned,as necessary and consolidated into the Spent Fuel Pool Island (SFPI). Electrical power was provided from the 115KV incoming line with a back up diesel generator specifically for security, but available for the SFPI. An industrial water-to-air cooling system replaced the primary component cooling /service water systems that serviced the spent fuel pool cooling and clean up system. Makeup water is supplied from the PWST with back up from the Wiscasset water supply and the fire protection service system. A portable mix tank and pump batches borated water when required in the make up for the

spent fuel pool.During the fall of 1997 and spring of 1998, Maine Yankee conducted a radiologicalcharacterization of the site through GTS Duratek. Appropriate historical information was compiled into the Historical Site Assessment (HSA). This site characterization, which is summarized in LTP Section 2, was conducted to assist companies bidding for a contract to decommission the site with additional characterization to be conducted as necessary thereafter. During the fall of 1998, Maine Yankee reviewed bids and selected Stone & Webster as the DOC. Under Maine Yankee oversight, Stone & Webster conducted various decontamination and dismantlement activities until May 2000 when the contract was cancelled. The overall project schedule defines the current status and remaining activities. Fourphases of site dismantlement, some of which run in parallel, were defined by Stone &

Webster's contract. As part of preparing the site, Phase 1 removed structures to increase the free area needed for large vehicles and equipment. The removal work has been completed and involved the removal of guard towers, some tanks and other structures.

Efforts to release non-impacted areas are ongoing. Phase 2 initiated activities for commodity removal, dismantlement and structure decontamination. This phase is currently in-progress. Phase 3 consists primarily of demolition activities as well as site restoration activities. Phase 4 consists of the construction of an Independent Spent Fuel Storage Installation (ISFSI) and movement of spent fuel to dry storage.

MYAPC License Termination PlanPage 3-3Revision 3 October 15, 2002The construction of the ISFSI has been completed, and movement of spent fuel has lcommenced and is scheduled to be completed in 2003. In preparation for constructing the lISFSI, final status surveys of the land area and the ISFSI Security Operation Building(SOB), formerly the Low Level Waste Storage Building (LLWSB), were initiated in the fall of 1999 through summer of 2000. In preparation for fuel transfer, Maine Yankee conducted a complete inventory and inspection of the contents of the spent fuel pool during 2000. Some major decommissioning activities have been completed and others are in-progress. Reactor coolant system piping, reactor coolant pumps and motors, steam generators and the pressurizer have been removed and shipped offsite for processing and/or waste disposal as appropriate. Other small commodities have also been removed and shipped offsite. Reactor vessel internals were segmented using an abrasive water jet (AWJ) lsystem. Greater-than-class-C (GTCC) waste generated as a result of the segmentation project were loaded into NAC UMS casks and stored onsite at the ISFSI.

lOn January 3, 2001, Maine Yankee submitted an application to amend the license to release a portion of the site classified as non-impacted. This application provides the NRC with the information specified in LTP Section 1.4.2. This land area contains a few structures including the Eaton farmhouse. While some non-radiological remediation was conducted on the farmhouse, no dismantlement activities are required to be completed prior to removing this land area from the jurisdiction of the Part 50 license as requested in the proposed license amendment On April 10, 2001, Maine Yankee submitted a second application to amend the license to release an additional portion of the site classified as non-impacted. On August 16, 2001, Maine Yankee resubmitted its lapplication to release these lands, combining the previous two applications into one lapplication and revising the presentation of the characterization data and results.

lStatistical analyses were presented to demonstrate that the residual activity, if any, in lthese lands is indistinguishable from background. On November 19, 2001, Maine lYankee supplemented its combined application, making certain clarifications including lland survey information. The NRC granted this request for the release of these lands in lJuly 2002. See Section 1.4.2.

l3.1.3Decontamination & Dismantlement Process SummaryDecontamination & dismantlement activities will be supported by detailed projectplanning and scheduling. This planning supports as low as reasonably achievable (ALARA) reviews, estimation of labor and resource requirements, while tracking cost and schedule. Work packages are used to implement the detailed plans and provide instructions for actual field implementation. The work packages address described units of work and include appropriate hold and inspection points. Administrative procedures control work package format and content, as well as the review and approval process.

MYAPC License Termination PlanPage 3-4Revision 3 October 15, 2002 1 In accordance with NRC Circular 81-07 lSystems and components removed and released from the secondary side of the plant forcommercial disposal are surveyed in accordance with plant procedures based upon a no detectible radioactivity standard. The controlling procedure specifies that the instrumentation must be capable of detecting beta/gamma (and alpha if suspected) lradioactivity 1 at or below the levels listed below:

la.Total surface beta/gamma contamination @5000 dpm/100 cm 2b.Loose surface beta/gamma contamination @1000/100 cm 2c.Fixed alpha contamination @100 dpm/100 cm 2ld.Loose surface alpha contamination @ 20 dpm/100 cm 2e.Gamma dose rates of 10 micro rem/hrA separate procedure has been implemented with the same detection levels, augmentedby additional controls for the release of material from the radiologically restricted area.

Generally, systems and components removed from the primary (radiologically controlled) side of the plant are packaged and either transported to an offsite processing facility, a low-level radioactive waste (LLRW) disposal facility, or an appropriate disposal facility.Decontamination of structures will include a variety of techniques ranging from waterwashing to surface material removal. Structural material may be packaged and either transported to an offsite processing facility, a LLRW disposal facility, or an appropriate disposal facility.Following the removal or decontamination of systems, components, and structures, acomprehensive final status survey (FSS) will be completed as described in section 5 of this LTP. As referred to above, the dismantlement activities will be carried out in the following four phases:Phase 1:Prepare Site & Release Non-Impacted AreasPhase 2:Dismantle Commodities & Decontaminate StructuresPhase 3:Demolish Buildings & Restore SitePhase 4:Establish Independent Spent Fuel Storage Installation (ISFSI)

MYAPC License Termination PlanPage 3-5Revision 3 October 15, 2002These phases may be implemented in parallel and are not necessarily sequential. A brief discussion of the four phases follows:Phase 1: Prepare Site & Release Non-Impacted AreasThe preparations period began with permanent plant closure on August 7, 1997.

This phase involved the demolition of miscellaneous tanks, buildings, fences andvehicle barriers, etc. to allow ease of access to the site. During this phase, as demonstrated by this LTP, no radiological contaminants were found North of Old Ferry road, or West of Bailey Cove, and these areas are therefore designated and expected to be released on an early basis in accordance with 10 CFR Part 20 Subpart E (Radiological Criteria for Unrestricted Use), the enhanced state clean-up standards, and 10 CFR 50.82 (a)(11)(i) and (ii).This phase also included site characterization activity, license basis document revision,spent fuel pool island construction and system evaluation, re-classification and, as appropriate, deactivation as described above. Phase 2: Dismantle Commodities & Decontaminate StructuresCommodities are dismantled and removed during this phase. Following commodityremoval, applicable portions of structures are decontaminated as necessary. Maine Yankee intends to demolish structures, with few exceptions, down to three feet below grade. For structures on the secondary side of the plant, sufficient surveys are conducted prior to demolition to ensure that any applicable portions of the structure are decontaminated. For structures on the primary (radiologically controlled) side of the plant, those portions of the structure above three feet below grade will generally be demolished, packaged and either transported to a LLRW disposal facility or an alternate disposal facility. Some metals, such as rebar, may be recycled, as appropriate, if the metals can be released using a no detectable radioactivity standard. Basement surfaces below three feet below grade will be decontaminated and remediated (paint removal, chemical stain removal, etc.) as necessary and a final status survey will be performed before the basement is filled with soil. Phase 3: Demolish Buildings & Restore SiteDuring this phase, structures will be demolished to an elevation corresponding to threefeet below grade. These demolition activities will be reviewed during planning to ensure no adverse effect on the SFPI (i.e. walls of adjacent buildings that have a support function of the SFP will remain intact). Concrete buildings will be demolished to 3 foot below grade. Other buildings are designated for either industrial reuse, recycling, or offsite disposal; and are dispositioned accordingly.

MYAPC License Termination PlanPage 3-6Revision 3 October 15, 2002Activated portions of remaining foundations above the Activated Concrete DCGLs willbe removed.Several options exist for sequencing building demolition activities with FSS. Thesedemolition sequences will be evaluated and selected with the objective of minimizing the potential for recontamination of surfaces that have already received a final status survey and maximizing the quality of the final status survey. For all options, a final statussurvey will be performed on the basement surfaces before fill material is placed andlon the remaining building footprint after fill material is placed. The status ofl dismantlement, remediation and FSS activities will be frequently communicatedl to state and NRC authorities to ensure adequate time for confirmatoryl measurements, if necessary, prior to the basement being filled. Listed below arel some options for sequencing building demolition activities with FSS.lOption 1Complete Building Demolition prior to FSS:Will require special attention to keeping the elements (weather) out of the basement during FSS and confirmatory measurementsOption 2 FSS prior to Building Demolition:Will require special attention for preventing the building demolition from re-contaminating surfaces below where FSS has been completed.Option 3Building Demolition not including a floor above grade (nominally 21 ft.). This option would:

- Seal openings in the upper floor to act as a roof.

- Perform FSS on basement floors, walls and ceilings (if applicable). - Allow MY to notify NRC and State of their opportunity toperform confirmatory measurements. -Fill basement areas with soil fill material.

-Complete the demolition of the building down to the 17 ft.

elevation. -Perform confirmatory FSS on the surface of the soil fillmaterial after super structure demolition.

This option would require actions to:

!Keep the elements out of foundation area which do nothave a 21 ft floor (e.g. SFP portion of the Fuel Building).

MYAPC License Termination PlanPage 3-7Revision 3 October 15, 2002

!Prevent recontamination pathways to the basement duringabove 21 ft building demolition and during basement soil fill operations. Other demolition sequencing options may be developed, as necessary, to achieve the objectives described above.Phase 4: Establish an Independent Spent Fuel Storage Installation (ISFSI)The ISFSI is designed, constructed and loaded with fuel stored in casks duringthis Phase. Maine Yankee's storage of spent fuel in the ISFSI will be conducted under a general Part 72 license pursuant to 10 CFR Part 72, Subpart K. Therefore, Maine Yankee will store fuel only in fuel casks approved by the NRC as listed in 10 CFR 72.214. Following complete transfer of the spent fuel from the spent fuel pool to theISFSI, Maine Yankee will dismantle and demolish the spent fuel pool. Maine Yankee has submitted a license amendment, pursuant to 10 CFR 50.90, to add anl applicability statement to certain technical specifications that describe requirements associated with the spent fuel pool. This license amendment hasl been approved prior to demolition of the spent fuel pool. l3.2Remaining Dismantlement Activities The purpose of this section of the LTP is to indicate each dismantlement activity whichremains to be completed prior to qualifying for license termination. This information is provided to support the NRC in making their determination to terminate the license pursuant to 10 CFR 50.82(a)(11)(i). In addition to identifying the dismantlement activities, information is provided on the final state of the site including structural remnants, basement foundations and buried piping and conduits. This information ensures that the scope of possible contaminated materials associated with the final state of the site are considered in dose modeling, survey design and environmental assessment. Any changes to the dismantlement activities described in this section which are made pursuant to 10 CFR 50.59 must also consider the impact of those changes on the final state of the site and any impacts on dose assessment, survey design or environmental assessment.

MYAPC License Termination PlanPage 3-8Revision 3 October 15, 20023.2.1Major Decommissioning Activities10 CFR 50.2 defines "major decommissioning activity" as any activity that results in permanent removal of major radioactive components, permanently modifies the structure of the containment, or results in dismantling components (separating and packaging GTCC waste) for shipment in accordance with 10 CFR 61.55. Those activities are summarized as follows:

a.Removal of the steam generators and the pressurizer. The externalsurfaces decontaminated as required, and all openings sealed-welded.

These components serve as their own transport containers. This activity

was completed in 2000.b.The reactor internals have been segmented such that the components withlthe lowest activity (upper guide structure and the uppermost and lowermost portions of the core support barrel assembly) will be shipped in the RPV,c.The segments with intermediate levels of activity (the center section of thecore support barrel assembly) will be shipped in casks for disposal in a near surface disposal site, and d.The segments that exceed class C limits (the core support plate and thecore shroud) are stored on site for later transport with the spent fuel to al USDOE disposal facility. e.Remove the RPV and place it into transport/disposal container, for shipment and disposal intact.f.Segment the neutron shield tank structure formerly surrounding the reactorvessel, and place the segments into shielded containers.g.Segment the RCS and other large-bore piping, decontaminate toacceptable limits, if necessary, for offsite direct disposal, size reduction/disposal, or offsite recycle as appropriate considering the residual activity level. This was mostly completed in 2000.

MYAPC License Termination PlanPage 3-9Revision 3 October 15, 2002h.The containment equipment access was modified (with closure capability)to facilitate moving a multi-wheeled transporter into containment for loading/ removal of large components. This task was completed.i.Once all spent fuel is removed from the spent fuel pool, the spent fuelfacility will be decontaminated and dismantled.The containment polar crane, and/or a crane set-up inside containment loads each large component onto a multi-wheeled transporter for removal through the

modified containment equipment hatch. The transporter moves the component(s) to the designated preparation/ temporary storage area within the industrial area.

Reactor coolant pumps and motors were shipped via truck, and rail. Rail or barge will be used for the reactor vessel head for transport offsite. The large components such as RPV, pressurizer, and steam generators were or will be transferred via the multi-wheeled transporter onto barges for shipment either directly to the disposal facility (as in the case of the reactor vessel), or to an offsite facility for additional decontamination and/or volume reduction prior to final disposal or recycle (for the other components). During 1999 and 2000, Maine Yankee removed containment piping and many components. Reactor vessel internals and the reactor vessel itself (with some internals) were processed and removed, in 2001 and 2002, from the containmentl building and stored for later shipment . The reactor vessel will be loaded into al transport/disposal container (DOT approved). The vessel and its container will be moved onto a sea-going barge and transported via the Atlantic Ocean, Intercoastal Waterway, then up the Savannah River where it will be offloaded at the Savannah River Site. After barge offloading, the vessel package will be transported

overland for disposal at the GTS DURATEK low level radioactive waste disposal facility, near Barnwell, South Carolina. These activities will be coordinated with

the State of Maine, US DOT, US Coast Guard, NRC, South Carolina Department

of Health and Environmental Control (SCDHEC), and the other States requiring notification of the shipment.3.2.2Dismantlement Activity Schedule In relation to plant commodities and internal structures, the project's approach todismantlement is to expeditiously remove these items, and transport for processing or disposal. It provides a safe, productive, and cost-effective means for commodity removal and accelerates access to the building surfaces for

decontamination efforts.

MYAPC License Termination PlanPage 3-10Revision 3 October 15, 2002NSSS component removal should be completed approximately three and one halfyears following cessation of operations. It is expected that the majority of plant structures and facilities will be decontaminated and dismantled within seven years

of cessation of operations as listed below in Table 3-1.The few facilities and structures required to support the ISFSI (spent fuel andGTCC waste storage) will be decontaminated, as necessary, and dismantled after

USDOE has removed the stored materials.

Table 3-1Major MY Area/Systems, Structures, and Components Removed (By Year)2001 PZR quench tank Rx vessel head Rx vessel internals Regenerative heat exchanger SI tank #2 Evaporators Turbine steam system Circulating Water Pumphouse Circulating water system Primary drain tank

Neutron shield tank Rx pressure vessel Turbine building (Phase I) 2002Spray Building Steam and Valve House MYAPC License Termination PlanPage 3-11Revision 3 October 15, 2002 Table 3-1Major MY Area/Systems, Structures, and Components Removed (By Year)Primary Vent Stack115 KV yard limited (Switchyard remains) 2003Emergency Feedwater Spent fuel pool (limited)

Boron waste storage tank (BWST)

Primary water system Fire protection system limited Spent fuel pool Spent fuel building Fire Protection System Primary Auxiliary Building

2004 PW - potable water connection (plant site)

Forebay Containment 2026 (or after DOE removes the stored materials)ISFSI site D&D with remediation as requiredThe remaining decommissioning schedule represented in Table 3-2 will be revisedduring the project. However, the LTP does not require revision to describe the schedule changes since this section is a general description of D&D activities and options. Existing lines of communication (i.e. weekly telecom) will be utilized to inform the NRC of any significant changes to major milestones in the schedule. Equipment and materials will be removed from areas unless the radiation surveysindicate that the structures can be released for unrestricted access and MYAPC License Termination PlanPage 3-12Revision 3 October 15, 2002conventional demolition. By the Winter of 2002, after the fuel is transferred to theISFSI, the SFP and its supporting systems are scheduled for D&D.

Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DateTG0102-2 TG01 Demo Main Generator 2Q 01Z-0139 SBHP HP Checkpoint / Chem Lab Commodity Ripout 2Q 01 Z-0141 SB01 SBP Service Building Proper2Q 01 SPRB01-8 HV7 HV-7 & 9 Room Commodity Ripout2Q 01 0194X P21E P21E - PAB El 21' Evap Cubicle Segment EV-2 2Q 01 PULG01-1 PULGPAB 36' General Area Commodity Ripout 2Q 01 PP-2 DWST DWST Foundation Pkg./Proc. C&D (Subgrade) 2Q 01 CB1501-5 CBQT Quench Tank Area -2' Commodity Removal 2Q 01 0192 P21H PAB 21' Letdown HX Room Commodity Removal 2Q 01PULG01-4 PULG PAB 36' - Boric Acid Storage Tank Demolition 2Q 010130 SPRB Spray Building Commodity Ripout 2Q 01 PUDD01-1 PUDD Remove Block Wall from Decay Drum CubeOpening 2Q 01SPRB01-10 SPRB Spray Pump Rebuild Room Commodity Removal2Q 01PUDDO1-3 PUDD PAB 36' Remove Waste Gas Surge Tank TK-10 2Q 01 PUDDO1-4 PUDD PAB 36' Remove Decay Drum Tank 60A 2Q 01 PUDD01-5 PUDD PAB 36' Remove Decay Drum Tank 60B 2Q 01 PUDD01-6 PUDD PAB 36' Remove Decay Drum Tank 60C 2Q 01 MYAPC License Termination PlanPage 3-13Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0144X CB14 SIT #2 Cut-Up 2Q 01PUDD01-7 PUDD PAB 36' Remove Decay Drum Tank 60D 2Q 01 PUDD01-8 PUDD PAB 36' Remove Decay Drum Tank 60E 2Q 01 0245 XS00 Remove/Rig out Spare Transformer (X-1S)2Q 01 TB0006-7X TB00 Turbine Building - ROOFING REMOVAL 3Q 01 PERH PHPersonnel Hatch Area Commodity Ripout 3Q 01 TB0006-7 TB00 Turb. Bldg. - Galbestos Siding Removal3Q 01 0141X CB14 Regen HX Commodity Removal 3Q 01CB11 Demo RCP #1 Pump Pedestal 3Q 01PUDD01-2 PUDD PAB 36' Decay Drum Cubicle Comm Rmvl 3Q 01 0053 CICI CTMT ICI Sump Commodity Removal 3Q 01 0083X CB13 SIT #3 Cut-Up 3Q 01 Z-0156P SVH1 Steam & Valve House Commodity Removal 3Q 01 RCP2PED CB12 Demo RCP #2 Pump Pedestal 3Q 01 SG1PED CB11 Demo SG #1 Pedestal Base 3Q 01 PUTC01-4 PUTC PAB 36' VCT Cubicle Commodity Ripout 3Q 01 P21L01-2 P21L PAB 21' General Area Commodity Removal 3Q 01 CB1501-11 CBQT Quench Tank Area Final Ripout 3Q 01 RCP3PED CB13 Demo RCP #3 Pump Pedestal 3Q 01 PUTC01-2 PUTC PAB 36' VCT Cubicle - Remove VCT TK-6 3Q 01 SG3PED CB13 Demo SG #3 Pedestal Base 3Q 01 MYAPC License Termination PlanPage 3-14Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DateZ-0157P RMCC Reactor MCC Room Commodity Removal 3Q 01CB1201-7 CB12 CTMT Loop 2 Final Rip Out 3Q 01 LOOP1C CB11 CTMT Loop 1 Commodity Removal Complete 3Q 01 LOOP1F CB11 CTMT Loop 1 Final Ripout 3Q 01 0211 PLAD PLAD PAB 11' ADT - Segment TK-12A 3Q 01 PUWG01-1 PUWG PAB 36' Waste Gas Cube Commodity Removal 3Q 01 0147 CB31 Remove Commodities/Cut Liners Rx Cavity Area 3Q 01 CW0006-7 CCW1 Circ Water Demo- Walls & Roof El. 21' 3Q 01 WH5BF MSW5 Warehouse #5 Subgrade Foundation Backfill 3Q 01 Z-0397Y 345K Electrical Tower Demolition (X-1A/B Area) 3Q 01 Z-0397S 345K Electrical Tower Subgrade Demo (B parking lot) 3Q 01 Z-0377 MSCL Collection Site Demolition 3Q 01 Z-0447 YMET Demo - MET (fences, house, tower, conc pads) 3Q 01 Z-0357 YDWW Well Water House Demolition 3Q 01 Z-0357S YDWW Well Water House Subgrade Demolition 3Q 01 TB0006-20 TB00 Turbine Hall Crane Demolition 4Q 01 0066X CB11 SIT #1 Cut-Up 4Q 01 P21E01-2 P21E P21E El 21' Evap Cubicle Grating 4Q 01 CB1301-8 CB13 CTMT Loop 3 Final Ripout 4Q 01 LOOP3C CB13 CTMT Loop 3 Commodity Removal Complete 4Q 01 TB0006-21 TG01 Turbine Pedestal4Q 01 MYAPC License Termination PlanPage 3-15Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DateTB0006-22 TB00 Turbine Building Demo (Ph I - Excl. North Wall) 4Q 01Z-0152X SB00 Service Building Demo (Phase I) (Above Grade) 4Q 01 CW0006-8 CCW1 Circ Water Pump House Demo - Slab @ 21' 4Q 01 PLAD01-2 PLAD PLAD PAB 11' ADT - Segment TK-12B 4Q 01 CW0006-10 CCW1 Circ Water Pump House Demolition RetainingWalls 4Q 010226 TK33 Remove CWPH Ferrous Sulfate Storage Tk (TK-

33) 4Q 01CW0006-2 CCW1 Circ Water Pump Shaft Backfill 4Q 01CW0006-9 CCW1 CW Pump House Demo Structure to High Water 4Q 01 CW0006-11 CCW1 Circ Water Pump House Concrete Demolition 4Q 01 0714 STP1 Sewage Treatment Plant Demolition 4Q 01 TB1BF TB00 Turbine Building Demo Phase 1 Backfill 4Q 01 PUEC01-1 PUEC PAB 36' Evap Cubicle Commodity Removal 4Q 01 STPBF STP1 Sewage Treatment Plant Demolition Backfill 4Q 01 PUHV01-1 PUHV PAB El 36' HVAC Rmv Comp Below HV-1,2 4Q 01 PUHV01-2 PUHV PAB El 36' HVAC Remove Filters 4Q 01 CWBF CCW1 CW Pump House Demo Backfill & Landscape 4Q 01 PUHV01-3 PUHV Remove Tubing, Piping, Conduit & HVAC Duct 4Q 01 PUHV01-4 PUHV PAB El 36' HVAC Remove Walkway 4Q 01 0311 PLPD PAB 11' PDT - Segment TK-11 (Primary Drain) 4Q 01 MYAPC License Termination PlanPage 3-16Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DateTB0006BG TB00 Turb Bldg Foundation Subgrade Demo 4Q 01Z-0152XS SB00 Service Building Subgrade Demolition (Phase 1) 4Q 01 0114 NSRV Segment Neutron Shield Tank 1Q 02 PLPA01-2 PLPA PAB 11' - PAB Sump Area Commodity Removal 1Q 020153 CCG1 CTMT 46' Charging Floor Commodity 1Q 020150 CB32 CTMT Upender - Remove Commodities/CutLiners 1Q 02CB3301-3 CCOA Remove CTMT 46' Outer Annulus Jib Crane 1Q 020156 CPLE Remove CTMT Elevator Room Commodities 11Q 02 P21L01-5 P21L P21L - PAB El 21' Remove Monorail 1Q 02 CB3301-2 CCOA Remove CTMT 46' Outer Annulus Monorail1Q 02 Z-0337 YDPH MPH - Montsweag - Remove Commodities &Backfill 1Q 02Z-0397 345K Electrical Tower Demolition (B Parking Lot) 1Q 02CCOAF CCOA CTMT 46' Outer Annulus Final Ripout 1Q 02 HV7DEMO HV7 HV-7 & 9 Building Demolition 1Q 02 0713S SBTT Service Bldg Test Tank Subgrade Foundation Demo 2Q 02CB18F CB18 CTMT EL -2' OA Final Ripout 2Q 020726S DWST DWST -Subgrade Foundation Demolition 2Q 02 0731X MSGHDemo Gas House Foundation 2Q 02 SBTTBF SBTT SBTT Subgrade Foundation Demo Backfill 2Q 02 MYAPC License Termination PlanPage 3-17Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0727S RWST RWST/SCAT Tank Subgrade Foundation Demo 2Q 02DWSTBF DWST DWST Subgrade Foundation Demo Backfill 2Q 02 GHBF MSGH Gas House Foundation Backfill 2Q 02 PP-4 RWST RWST/SCAT Foundation Packaging/ProcessingC&D 2Q 02RWSTBF RWST RWST/SCAT Subgrade Foundation DemoBackfill 2Q 020569 SPRB Spray Building Demolition 2Q 02SBFD SBF Softball Field Demolition (Dugouts & Fencing) 2Q 02 SPRAY CCG1 Remove CTMT Spray Rings 2Q 02 0719 YDBG Barge Slip / Road Demolition 2Q 02 0159 CB34 Remove Commodities CTMT Polar Crane (CR-

1) 2Q 02Z-0156 SVH1 Steam Valve House Demolition (Above Grade) 2Q 02CB2101F CB21 Final Commodity Removal CTMT El 20' 3Q 02 0136 CPHO CTMT Personnel Hatch Commodity Removal 3Q 02 CB3301-1 CCOA Remove CTMT 46' Outer Annulus Grating 3Q 02 0712 CPHO CTMT Personnel Hatch Demolition 3Q 02 CCFFR CCG1 CTMT 46' Charging Floor Final Ripout 3Q 02 0233DR PWST Drain Primary Water System 3Q 02 PUFN01-2 PUFN PAB El 36' Fan FN-1A Removal 3Q 02 Z-0152 SB00 Service Building Demo (Phase 2) Above Grade 3Q 02 MYAPC License Termination PlanPage 3-18Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DatePUFN01-3 PUFN PAB El 36' Fan FN-1B Removal 3Q 02PAB11FR PA00 PAB 11' Final Ripout 3Q 02 HV7DEMOSHV7 HV-7 & 9 Subgrade Demolition 3Q 02 PUFN01-4 PUFN PAB El 36' Install Temporary Roof 3Q 02 Z-0132 RCAD RCA Drumming Room Commodity Removal 3Q 02 Z-0135 SFP1 Fuel Bldg Proper Commodities Ripout 3Q 02 Z-0156S SVH1 Steam Valve House Subgrade Foundation Demo 3Q 02 Z-0157 RMCC Reactor MCC Room Demolition 3Q 02 Z-0197 AD00 Admin Bldg / Gatehouse Demolition 4Q 02 0513 PWST PWST - Primary Water Storage Tank Comm Rmvl 4Q 02Z-0197S AD00 Admin Bldg / Gatehouse Subgrade Demo 4Q 02LSACOM LSAB LSA Building Commodity Ripout 4Q 02 0711 CEHO Containment Equipment Hatch Demolition 4Q 02 PUFN01-1 PUFN PAB El 36' Cut Opening in Roof 4Q 02 ADBF AD00 Admin Bldg / Gatehouse Demolition Backfill 4Q 02 Z-0152S SB00 Serv Bldg Subgrade Demo (Phase 2) Below Grade 4Q 02PAB21FR PA00 PAB 21' Final Ripout 4Q 02TB0006-22XTB00 Turbine Building Demo (Ph II North Wall) 4Q 02 0215 PABR PAB Roof Area Commodity Removal 4Q 02 MYAPC License Termination PlanPage 3-19Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0728 WART Wart Building Demolition (Above Grade) 4Q 02PUFN01-5 PUFN PAB El 36' Fan FN-1A/B Area Commodities 4Q 02 PU4801-1 PU48 PAB El 36' Remove Duct 4Q 02 PU4801-2 PU48 PAB El 36' Remove Supports 4Q 02 Z-0131 SFP3 SFP Heat Exchanger Cubicle Commodity Removal 4Q 020253 SFP2 Spent Fuel Pool Area Commodity Removal 4Q 02MYM16 SB00 Service Building Demolition Complete 4Q 02 TB0006BG2 TB00 Turb Bldg Subgrade Demo (Below North Wall) 4Q 02 0728S WART Wart Building Subgrade Demolition 4Q 02 0569S SPRB Spray Building Subgrade Demolition 4Q 02 PERHD PH Personel Hatch Area Demolition 4Q 02 Z-0071 NFLA NFLA / Vault Commodity Demolition 4Q 02 PU4801-3 PU48 PAB El 36' Fan FN-48 Area Commodities 4Q 02 0230 X140 XFMRS X-14/16 Area Commodity Removal 4Q 02 Z-0140 RCAW RCA Bldg Commodity Removal 4Q 02 PERHDS PH Personnel Hatch Area Subgrade Demolition 4Q 02 Z-0137 SFP4 SFP Ventilation Room Commodity Removal 4Q 02 MONO PUSA PAB 36' Monorail Demolition 4Q 02 0738 X140 X-14/16/16A/16B Transformer Demolition 4Q 02 TB2BF TB00 Turbine Building Demo Phase 2 Backfill 4Q 02 MYAPC License Termination PlanPage 3-20Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion DatePT001 SFP6 RCA Pipe Tunnel Commodity Removal 4Q 02PAB36FR PA00 PAB 36' Final Ripout 4Q 02 0245FD XALL Transformer Foundations Demolition (All) 4Q 02 0236 115KV 115KV Tower Dismantlement (X-14 area) 1Q 03 Z-0207 CB00 Primary Vent Stack Demolition 1Q 03 0716 115KV 115KV Tower Subgrade Foundation Demo (X-14 Area) 1Q 030254 SFP2 Spent Fuel Pool - Cut Liner/Fuel Racks 1Q 030222COM HR00 High Rad Bunker Commodity Ripout 1Q 03 0231 SFPI Generator/Pagoda Area Commodity Removal 1Q 03 Z-0227 SFPI Generator/Pagoda Area Demolition 1Q 03 Z-0172 PA00 Primary Aux. Building Demolition 1Q 03 0227 SEAL FIForebay/Seal Pit Demolition 1Q 03 MYM11 PA00 PAB Structure Demolition Complete 1Q 03 Z-0172S PA00 Primary Aux Bldg Subgrade Demolition 1Q 03 0725 EFPR Emergency Feed Pump Room Demolition 1Q 03 0227S SEAL FI Forebay/Seal Pit Subgrade Demolition 1Q 03 0725S EFPR Emergency Feed Pump Room SubgradeDemolition 1Q 030235 BWST BWST Berm Demolition 2Q 030515 BWST BWST Tank & Commodity Ripout 2Q 03 MYAPC License Termination PlanPage 3-21Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0235S BWST BWST Subgrade Demolition 2Q 030233 PWST PWST Tank Demolition 2Q 03 0237 BWST Contaminated Soil Removal (BWST) 2Q 03 0233S PWST PWST Subgrade Demolition 2Q 03 PP-17 BWST BWST/Berm Demolition Packaging/ProcessingC&D 2Q 03PP-16 PWST PWST Demolition Packaging/Processing C&D 2Q 03PWSTBF PWST PWST Subgrade Demolition Backfill 2Q 03 0222 HR00 Demolition High Rad Bunker 2Q 03 Z-0347X MSW4 MSW4 - Warehouses #4 (Annex) Demolition 2Q 03 0228DIFF Diffuser Piping Demolition 2Q 03 Z-0347XS MSW4 MSW4 - Warehouse #4 Subgrade Demolition 2Q 03 Z-0347X1MSW2 WHSE - Warehouses #2/3 Demolition 2Q 03 0236L 115KV Drop 115 KV Power Lines 2Q 03 Z-0347X2 MSW2 WHSE - Warehouses #2/3 Subgrade Foundation Demo 3Q 03Z-0367 MSIC Information Center Demolition 3Q 03Z-0482 BLPT Bailey Farm House/BarnDemolition 3Q 03 Z-0482S BLPT Bailey Farm House/Barn Subgrade Demo 3Q 03 Z-0367S MSIC Information Center Subgrade Demolition 3Q 03 Z-0157S RMCC Reactor MCC Room Subgrade FoundationDemolition 3Q 03 MYAPC License Termination PlanPage 3-22Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0224 FPH1 Fire Pump House Commodities 3Q 030717 FR00 Fire Pump House Demolition (Above Grade) 3Q 03 0717S FR00 Fire Pump House Demolition (Below Grade)(Water from Fire Pond will be sampled and processed as necessary for release) 3Q 03Z-0069S STFB Staff Building & Tunnel Demo (Subgrade) 4Q 03Z-0257 YDTP Test Pit Demolition 4Q 03 Z-0387 YDLT LIFT - Lift Station Demolition 4Q 03 0257S SF00 RCA/Fuel Building Subgrade Demolition 4Q 03 0239 LSAB LSA Building Demolition 4Q 03 Z-0267 YDFC SECF - Security Fence Demolition 4Q 03 0722 YDOU Remove Outside Utilities (3 ft. below) Demo. 4Q 03 0239S LSAB LSA Bldg. Subgrade Foundation Demolition 4Q 03 Z-0417 YDSH Temp. Power Shack Demolition (Whitehouse) 4Q 03 Z-0417C YDSH Temp. Power Shack Foundation Demolition 4Q 03 Z-0307 YDLP ULP - Utilities Light Poles Demolition 4Q 03 Z-0437 SEAL SEAL - Seal Pit Outfall Demolition (Above Grade) 4Q 03Z-0437S SEAL SEAL - Seal Pit Outfall Demolition (Below Grade) 4Q 03Z-0297 YARD FPHS - Fire Protection Hose/STA/Hydrants Demo 4Q 03 MYAPC License Termination PlanPage 3-23Revision 3 October 15, 2002 Table 3-2Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)Activity NumberActivity DescriptionCompletion Date0257 SF00 SFP / RCA Building Demolition 1Q 04Forebay Sediment Assessment/Remediation1Q 04MYM13 SFP2 Spent Fuel Pool Demolition Complete 2Q 04 Z-0148 CB00 Containment Building Demolition 2Q 04 Z-0317 YDPW PW-Potable Water Connection Demolition 2Q 04 0724 YDSL Sanitary Lines Demolition 2Q 04 Z-0148S CB00 Containment Building Subgrade Demo 2Q 04 ROAD YDRP Site Roads & Parking Lots Demolition 2Q 04 Z-0407RT YDRR Railroad Tracks Demolition 2Q 04 Z-0237 MSMO MOD - Modular Offices (2) Demolition 2Q 040591Final Doc. Submittal to NRC2Q 04 0287Decommissioning Complete / Non ISFSI LandReleased 3Q 04ISFSI Dismantlement, Decommissioning and Remediation (After removal of all spent fuel) 2026**Dismantlement of structures, support buildings,fences, lighting and utilities poles 2026**Site Remediation, planting of grass, trees, etc2026**Final Facility Site Survey2026**

Release of the Facility Site for unrestricted use2026**

Termination of Maine Yankee Atomic PowerCompany's Part 50 License 2026**** Projected date for DOE to have taken possession and removed stored materials.

MYAPC License Termination PlanPage 3-24Revision 3 October 15, 20023.2.3Material Removal SequenceRemoval sequence may be dictated by access and material handling restrictions orby personnel exposure considerations. In most cases, a top-down approach will be used; materials and structures at the highest elevations are removed first to allow access to components in lower levels. In other cases, different approaches may prove more efficient.Generally, the first items removed are those that are not, or are only slightly,contaminated to preclude contamination by other equipment. However, personnel exposure considerations may not always allow this option. Where non-

contaminated equipment cannot be removed first, covers or other protection methods to ensure effective contamination control shall be used. Similarly, non-contaminated piping should be removed from pipe chases and horizontal pipeways before cutting pipes. If this is not possible, other precautions, such as covers, are used to minimize the spread of contamination.Where rapid cutting techniques are available, pipes and equipment can besectioned into pieces that are manageable using light rigging or by manual lifting.

Where slow cutting techniques are used the largest manageable pieces will typically be freed and moved to a more convenient location for further reduction.In the initial stages of decommissioning, most material removed from thecontainment building will pass through the modified equipment hatch and/or the additional 8' x 8' and 10' x 10' openings cut through the side of the containment that facilitates movement of materials when the larger opening is in use.The plant is equipped with multiple cranes, hoists, and lifting and transportsystems. These systems can be used to lift and transport components and equipment to support plant decommissioning activities. Forklifts, mobile cranes, front-end loaders, and other lifting and transport devices can also be used for plant decommissioning activities. The major installed plant cranes, hoists, and lifting and transport devices that are available to support decommissioning include:a.Containment Building Polar Crane (360 ton, dual 185 ton hooks, 15 tonauxiliary hook)b.Fuel Building Overhead Crane; MYAPC License Termination PlanPage 3-25Revision 3 October 15, 2002c.Equipment Room Monorails; andd.Fuel Building Yard Crane (125 ton main hook /20 ton auxiliary hook) e.Turbine Hall Overhead Crane f.Plant Equipment Monorail Systems The cranes continue to be maintained in accordance with applicable standards andregulations. The containment building equipment hatch modification allows the

multi-wheeled transport direct access into containment.The containment building polar crane is capable of reaching most locations insidethe containment building and can handle large, heavy loads. The fuel building yard crane has access into the fuel building via a roll up door for movement of heavy components. This crane is being upgraded to be single failure proof for use in transferring spent fuel out of the spent fuel pool in spent fuel storage casks. The fuel building crane is used to some extent for movement of components in the

spent fuel pool.Installed cranes, hoists, and monorails may be used in conjunction with temporaryor mobile lifting and transport devices to support decommissioning. The installed plant cranes, hoists, and other lifting devices can be decontaminated and dismantled when they no longer are required to support decommissioning activities.3.2.4Final State-of-the-Site Description

The purpose of this section is to present a conceptual description of the sitefollowing license termination and unrestricted release and to identify the extent of the types of media that must be considered in dose assessment, survey design and environmental assessment. Figure 3-30 shows the anticipated final state of the

site. At license termination, when the site will be released for unrestricted use, the site will be a backfilled and graded land area with possibly some above grade structures remaining depending on the industrial reuse of the site. Generally speaking, all of the above grade structures will be demolished to three feet below grade and the resulting concrete demolition debris will be disposed of offsite at either a low-level waste facility or an appropriate disposal facility except for the 345 & 115 kV switchyards and possibly other administrative buildings. The MYAPC License Termination PlanPage 3-26Revision 3 October 15, 2002remaining basement foundations will be filled with a soil fill material followingany required remediation and FSS activities. The former Low Level Waste Storage Building [now the ISFSI SecurityOperations Building-(SOB)] will remain in place until the fuel is transferred to the USDOE. The 115 kV switchyard and the 345 kV switchyard, will remain intact.

The road that travels past the ISFSI will remain in place, terminating near the 115 kV switchyard. The original plant access road will remain but terminate between the ISFSI and the former location of the Information Building. The existing railroad that serves the ISFSI with its two spurs will remain in place, with one spur terminating near the 115 kV switchyard and the other terminating at the edge of the old road bed (formerly between the Restricted Area and the Service Building). The Old Ferry Road (a public road) and public boat ramp will remain in place. Some below grade structures and systems will remain as described below:

Turbine and Service BuildingThese buildings will be demolished to three feet below grade. Concrete ductbanks, building footings and foundations below this elevation will remain in place. A Final Status Survey will be performed on the remaining building footprint before it is backfilled. Piping below the foundation from the following systems will be removed: Primary Component Cooling, Secondary Component Cooling, sanitary sewer, oil lines, and floor drains. Service water intake lines may remain in place. The service water discharge line may be removed if necessary following final status survey. The service water discharge line was used as part of the radiological effluent discharge flow path from the test tanks. The circulating water discharge pipe encasement top may be left in place or may be broken and the lines backfilled following final status survey. Containment, Primary Auxiliary Building, Fuel Building and Containment SprayBuildingThese buildings will be demolished to three feet below grade. Basement foundations below this level will remain in place and be backfilled with soil fill following remediation, as required, and final status survey. Some or all of the intervening walls and floors in the basements may be removed. The steel liner in the basement of the containment will remain in place. Many of the basement

concrete and steel liner surfaces are covered with paint known to contain trace MYAPC License Termination PlanPage 3-27Revision 3 October 15, 2002amounts of lead and/or PCB's. This paint will be removed prior to final statussurvey. The fuel transfer tube and bellows will be removed. The spent fuel pool

liner will be removed due to known contamination levels. Some limited amounts of embedded pipe which penetrate basement walls will remain in place. These embedded pipes are easily accessible from either side for final status survey.

Sub-mat "popcorn" concrete and its embedded drain lines around the sub-base of

the containment will remain in place. These lines lead to the containment foundation sump pump which has been regularly sampled for contaminants. The containment drain sump will be demolished to three feet below grade. The foundation drain discharge line to the storm drain system may be removed Above Grade Structures in the Radiological Controlled Area: High RadiationBunker, Main Steam and Valve House, Emergency Feedwater Pump Room, LSABuilding, Equipment Hatch/HV-7 & 9 Rooms, Ventilation Equipment Area,Reactor Motor Control Center Room.These structures will be demolished down to three feet below grade. Buildingfootings and foundations may remain.Circulating Water Pump HouseThe Circulating Water Pumphouse (CWPH) will be demolished (demolishconcrete 3' below grade with grade varying from El. 17' at the west wall to El. -3' at the east, backfill and cover with rock rip-rap). The intake structure which is below water level will remain in communication with the river. Outlet CW piping will be removed along with portions of the SW piping.Sewage Treatment PlantThe Sewage Treatment Plant inlet pipes (coming from the TB/SB) will beremoved, with outlet piping inspected, decontaminated (if required) and left buried, prior to building demolition to 3 feet below grade.Foundations associated with Tanks, Guard Towers, Meteorological Towers, YardCrane Footings, Vehicle Barriers, Transformers and Above Grade Structuresincluding: Warehouse 2/3, 4 and 5, Administrative Building (Front Office),Gatehouse, Staff Building, Collection Center, Information CenterThe meteorological tower will be dismantled and removed. The concrete footingsand attached guide lines will be removed to three feet below grade and the area MYAPC License Termination PlanPage 3-28Revision 3 October 15, 2002backfilled. Concrete foundations for tanks, guard towers, yard crane footings,vehicle barriers, transformers and buildings will be demolished to three feet below grade. Footings and foundations below three feet below grade may remain in place. Maine Yankee may determine that the Warehouses, Staff Building and Information Center can remain standing, after radiological release for unrestricted

use.Buried PipingBuried fire protection and raw water piping will be left "in place." The CW andportions of the SW pipes between the CWPH and the Turbine and Service buildings will be removed. Piping between the DWST/RWST and the CSPA locations will be removed. All buried piping in the alleyway (area formerly between the service and containment buildings) will be removed. "Hot

Side"storm drains will be decontaminated (if required) and left in place. Cold side storm drains will be left in place with the following caveats: All catch basins and manholes will be cleaned out, demolished to three feet below grade, and backfilled.Forebay, Seal Pit and Diffuser Piping (see also Sections 8.2 and 8.6.4 regardinglthe NRPA process)lMaine Yankee is continuing to evaluate the final disposition of the Forebay, sealpit, and diffuser piping. As part of a NRPA process, Maine Yankee is analyzingl remedial options and coordinating, as required, with the Maine Department of Environmental Protection and the U.S. Army Corps of Engineers. (Other responsible agencies coordinate through these two principal agencies). The key options under evaluation include: (1) leave in place as exists; (2) secure and leave in place; (3) partial removal and; (4) complete removal. The types of impact that will be considered in the analyses include environmental impacts (water quality, marine wetlands, freshwater wetlands and land use), ecological impacts including

flora, fauna and marine resources, and impacts on natural resources and navigation. The evaluation will address the following options:Diffuser Pipe, Foxbird Island - onshore below grade. Options includecapping and leaving in place or removal, backfill and restoration to existing grade/conditions. Diffuser Pipe, Mudflats - below the sediment/water interface. Optionsinclude capping and leaving in place or removal, backfill and restoration of the tidal flats.

MYAPC License Termination PlanPage 3-29Revision 3 October 15, 2002Diffuser Pipe, Offshore above the sediment/water interface. The first optioninvolves removal, possibly adding rip rap to the thrusters to form an artificial reef and augmented habitat. The second option involves leaving in place and filling with sand. This option may also include adding rip rap to form an artificial reef.The concrete saddle supports and thrust blocks for the diffuser piping may be leftin place. Forebay. All options involve demolishing the seal pit and removal of concretedown to three feet below grade, capping piping and trenches, and removing

contaminated sediments, if required, consistent with the assumptions and dose

assessment presented in Section 6.6.9. The first option also includes removal of the west bank of the Forebay to re-establish tidal flow. The second option involves leaving the west bank of the Forebay in place, cutting down berms to above the high water elevation, and using this material as fill for the forebay. The third option involves leaving the berms in their present configuration.Fire Pump House and Fire PondThis pond existed solely for the purpose of holding water supplied fromMontsweag Brook and pumping it to the fire water protection header surrounding the plant and adjacent buildings. It has no direct discharge path to the bodies of water surrounding Bailey Point. Demolition of the man-made, concrete lined Fire Water Pond, will return the site to conditions similar to pre-plant construction.

After draining, the concrete liner will be removed and the earthen impoundment leveled. Surface water will once again flow across this area The Fire Pump House will be demolished to three feet below grade and backfilled with soil- like fill.Bailey Farm House, Barn, Well water structure and systemsThe Bailey farm house, barn and well water structure will be demolished to threefeet below grade. Building footings and foundations may remain. Restricted Area (RA)The previously described Restricted Area (RA) will be radiologically released for unrestricted use. However, to assure compliance with non-radioactive environmental monitoring issues, it may be fenced, and the land deeded with MYAPC License Termination PlanPage 3-30Revision 3 October 15, 2002restrictive covenants against excavating basements, drilling wells for drinking orirrigation water, or residential construction. Independent Spent Fuel Storage Installation (ISFSI)After the DOE transports all the stored spent fuel and GTCC wastes from theISFSI, it will be decontaminated, if necessary, and demolished down to three feet below grade. A Final Status Survey will be performed for remaining lands and/or structures.

3.3 Methods

of Decontamination and Dismantlement3.3.1Decontamination of Systems and Components Systems and components removed and released from the secondary side of theplant for commercial disposal are surveyed in accordance with plant procedures based upon a no detectable radioactivity standard. Generally, systems and components removed from the primary (radiologically controlled) side of the plant are packaged and either transported to an offsite processing facility, LLRW disposal facility, or an appropriate disposal facility. Application of coatings and hand wiping may be used to stabilize or remove loose surface contamination.

Potentially or slightly contaminated components (i.e., lighting ballast, mercury

switches, etc) will be decontaminated onsite for release in accordance with plant radiological monitoring procedures for release.

Tanks and vessels are evaluated and, if required, flushed or cleaned to reducecontamination levels and remove sludge prior to sectioning and/or removal. The following considerations are incorporated into tank and vessel sludge removal activities:a.Precautions are taken to ensure that in the unlikely event liquidinadvertently is discharged from the tank it will be captured (i.e., plugged lines, attached catch container, or temporary berm installation) for processing by a liquid waste processing system;b.Sludge removed from the tank is stabilized prior to shipment inconjunction with the Maine Yankee Process Control Program (PCP); andc.Wastewater will be processed and analyzed before beingdischarged.

MYAPC License Termination PlanPage 3-31Revision 3 October 15, 20023.3.2Dismantlement of Systems and ComponentsDismantlement methods can be divided into two basic types: non-destructivemeans such as disassembly, and destructive means such as cutting. Disassembly generally means removing fasteners and components in an orderly non-destructive manner (the reverse of the original assembly). Cutting methods include but are not limited to water jet, flame cutting, abrasive cutting, and cold cutting.Water jet uses a very high-pressure stream of water to cut components (usuallysubmerged underwater). Flame cutting includes the use of oxyacetylene and other gas torches, carbon arc torches, air or oxy arc torches, plasma arc torches, cutting

electrodes, or combinations of these. Most of the torches can either be handheld or operated remotely with the appropriate devices. Abrasive cutting includes the use of grinders, abrasive saw blades, most wire saws, water lasers, grit blast, and other techniques that wear away metal. Cold cutting includes the use of band saw, blade saw, drilling, machining, shear, and bolt/pipe/tubing cutter devices.

Selection of the preferred method depends on the specific situation. Otherdismantlement technologies may be considered and used if appropriate.

Dismantling of systems includes the removal of valves and piping for disposal.

Most valves can be removed with piping. Larger valves and valves with actuators may be removed separately for handling purposes.Commodities are considered to be piping, HVAC, conduit, cable, cable tray,platform steel, pipe supports - basically any piece of equipment or material located within a building/structure that does not form an integral part of that structure. The removal of commodities will be based upon three general categorizations:a.Areas within the Restricted Area (RA) of the plant Systems and components will be removed from each area of thebuilding/structure/yard, packaged, and either transported to an offsite processing facility, a LLRW disposal facility (Class A, B, or C), or an appropriate disposal facility.b.Areas within the non-RA of the plant that may have some internalsystem contamination.

MYAPC License Termination PlanPage 3-32Revision 3 October 15, 2002Systems and components identified during the site characterizationand subsequently verified and bounded by Maine Yankee, will be remediated, and the balance of the building/structure surveyed and released for demolition. Remediation (leaving as is, removal, capping, or grouting) will depend on the level of radioactive contamination found (if any).c.Areas outside of the Restricted Area (RA) These areas have never been exposed to radiological contamination. Commodities will be demolished and removed with the building/structure upon completion of appropriate survey.3.3.3Decontamination of Structures Structure decontamination methods typically include wiping, washing,vacuuming, scabbling, spalling, and abrasive blasting. Selection of the preferred method is based on the specific situation. Other decontamination technologies will be considered and used if appropriate. If structural surfaces are washed to remove contamination, controls areimplemented in accordance with approved plant procedures to ensure that wastewater is collected for processing by liquid waste processing systems.

Airborne contamination control and waste processing systems are used as necessary to control and monitor releases.Concrete that is activated will be removed down to the activated concrete DCGLand sent to a low level radioactive waste disposal facility. Removal of contaminated (non-activated) concrete will be performed using methods that control the removal depth to minimize the waste volume produced. Appropriate engineering controls for control of dust and debris will be used to minimize the spread of contamination and reliance on respiratory protection measures.The following structural decontamination methods are described: a.In-situ Concrete Decontamination by Bulk Removal Diamond wire saw cutting may be used for the removal of volumetric concrete above the unrestricted use criteria, (or DCGL).

MYAPC License Termination PlanPage 3-33Revision 3 October 15, 2002The removal of concrete consisting of the upper 1 or 2 feet of a thick slabsuch as a building foundation mat will require volumetric removals beyond the limits of scabblers or shot blasting. Whether due to activation or to leakage of liquids into concrete, the material may be removed using a mini-hoe ram or demolition robot. These have the flexibility to access congested areas and can be controlled to limit the volume of waste

produced.b.In-situ Surface Decontamination of Concrete The expected depth of the contamination will establish the process usedfor the surface decontamination of concrete. Scabblers and shot blasting equipment fitted with vacuum collection systems may be used for surfaces with deeper contamination. Elsewhere, sponge blasting using one or more different media and wipe downs with solvents may be used. Cross-contamination and recontamination will be minimized using the vacuum collection systems.c.Decontamination of Plant Concrete Structures That Are to BeDemolished (located higher than three feet below grade)Contaminated concrete structures above three feet below grade may not becompletely decontaminated. They will be packaged and shipped off site for disposal at a LLRW disposal facility or appropriate disposal facility.d.Concrete Surfaces Located at Elevations Lower than Three Feet below GradeConcrete surfaces below three feet below grade will be decontaminated if required to established criteria. e.In-situ Surface Decontamination of Metals/Preparation of Metal -Surfaces for SegmentationMost metallic wastes will not be decontaminated on site. Sponge blastingusing various media ranging from non-aggressive for surface cleaning to heavy abrasive media or other methods for paint or oxide removal will be used and/or wipe downs with solvents. The contamination on exterior and/or interior metallic surfaces may be fixed prior to dismantling the

structure or component.

MYAPC License Termination PlanPage 3-34Revision 3 October 15, 2002Internal building steel within the RA will be dismantled, packaged, andshipped for processing, unless it can be easily determined that the steel can be released.Steel located within non-RA buildings, i.e., not considered to have beenexposed to radiological contamination, will be surveyed and released for demolition, i.e., Turbine Building, Circulating Water Pump Structure, etc.

The external structural steel of plant buildings has been assessed during walkdowns and, depending upon the area, will either be surveyed and released for demolition or dismantled for packaging and shipment to a

waste processor.f.Embedded and Buried Piping Survey and Decontamination There are two categories of pipe: buried pipe and embedded pipe. Buriedpipe is pipe run underground, buried in a trench and surrounded by soil, whereas embedded pipe is encased in concrete. Treatment of buried pipe will depend on results from the surveys associated with the RCRA closure

process as to whether it can be left in place, must be filled with inert material to be left in place, or must be removed. If buried pipe is to remain, it may be surveyed using the "pipe crawlers" to compare residual activity to the DCGLs or if the buried pipe is not expected to contain any residual activity, survey will only be conducted at accessible portions of the pipe, intakes or outfalls. The majority of embedded pipe (" 1000 feet)is expected to be removed when concrete is demolished to three feet below grade. Embedded pipe remaining will also be surveyed using "pipe crawlers" or other appropriate method to compare residual activity to DCGLs. The radiological pipe crawler allows in-situ survey, characterization, anddecontamination of underground (buried) and embedded piping. By using this technology, safety risks, demolition costs, and secondary waste are reduced. (This technology has been used by other licensees to unconditionally release over 18,000 linear feet of piping with verification by the NRC). Based on survey results a decision considering the best engineering practice, will determine whether the remaining buried or embedded piping will be left as is, capped, or grouted.Areas with activity above DCGL values will be remediated.

MYAPC License Termination PlanPage 3-35Revision 3 October 15, 20023.3.4Building Demolition and Site RestorationTable 3-3 describes the structures and facilities within the scope of thedecommissioning along with the condition of release and final configuration.

Table 3-3Structures and Facilities Within the Scope of Work for DemolitionBuilding or area descriptionCondition of releaseFinal configuration of structureContainment building1Demo. 3 ft below grade; backfillSteam and valve house1Demo. 3 ft below grade; backfill Spray building1Demo. 3 ft below grade; backfill Containment equipment hatch outer1Demo.

Containment personal hatch outer1Demo.

LSA building1Demo. 3 ft below grade; backfill Reactor MCC room1Demo. 3 ft below grade; backfill Emergency feed pump room1Demo. 3 ft below grade; backfill Primary auxiliary building1Demo. 3 ft below grade; backfill Fuel building1Demo. 3 ft below grade; backfill RA building1Demo. 3 ft below grade; backfill Service building - hot side1Demo. 3 ft below grade; backfill Service building test tanks (TK-14A/B)1Complete demo.; remove pads; backfillDemin. water storage tank (TK-21)1Complete demo.; remove pads; backfillPrimary water storage tank (TK-16)1Complete demo.; remove pads; backfill Boron water storage tank (TK-13 A/B)1Complete demo.; remove pads; backfillRefueling water storage tank (TK-4& TK-54) and greenhouse1Complete demo.; remove pads; backfill MYAPC License Termination PlanPage 3-36Revision 3 October 15, 2002 Table 3-3Structures and Facilities Within the Scope of Work for DemolitionBuilding or area descriptionCondition of releaseFinal configuration of structureOffgas stack1Complete demolitionAux boiler stack1Complete demolition High radiation bunker1Demo. 3 ft below grade; backfill Turbine building2Demo. 3 ft below grade; backfill WART/I&C building2Complete demolition; backfill LLWB - Low level waste building2Complete demolition; backfill FI - Foxbird islandTBDTo Be Determined (TBD) based onalternatives analysisSecurity/Gatehouse building3Demo. 3 ft below grade; backfill Administration building3Demo. 3 ft below grade; backfill Fuel oil bunker3Demo. 3 ft below grade; backfill Gas house3Complete demolition; backfill Circ water pump house3Demo.West wall down to 3 ft belowgrade (17' elevation) and East wall to -3 ft elevation; backfill and add rip rapTemporary power shack - West offuel building3Complete demolition; backfillModular office buildings (2)3Complete demolition8 Sided storage building3Complete demolition Test pit3Complete demolition; backfill West - area West of the containmentBuilding including (3) guard towers3Complete demolition; backfillCondensate storage tank (concretepad only)3Demo. 3 ft below grade; backfill MYAPC License Termination PlanPage 3-37Revision 3 October 15, 2002 Table 3-3Structures and Facilities Within the Scope of Work for DemolitionBuilding or area descriptionCondition of releaseFinal configuration of structureTransformer including elect tower and concrete structures/padsee belowsee below1. X-IA3Remove transformer for disposition; demo. pads; backfill2. X-IB3Remove transformer for disposition; demo. pads; backfill3. X-243Remove transformer for disposition;demo. 3 ft below grade; backfill4. X-263Remove transformer for disposition;demo. 3 ft below grade ; backfill5. X-283Remove transformer for disposition;demo. 3 ft below grade; backfill6. X-IS3Remove transformer for disposition;demo. 3 ft below grade; backfill7. X- 143Remove transformer for disposition;demo. 3 ft below grade; backfill8. X-163Remove transformer for disposition;demo. 3 ft below grade; backfill9. X- 16A3Remove transformer for disposition;demo. 3 ft below grade; backfill10. X- 16B3Remove transformer for disposition;demo. 3 ft below grade; backfillTemp generator/transformer/pagoda(cold & dark equipment)2Remove transformer for disposition;demo. pagodaOutside protected areaSTPI - Sewage treatment plant3Demo. 3 ft below grade; backfill MYAPC License Termination PlanPage 3-38Revision 3 October 15, 2002 Table 3-3Structures and Facilities Within the Scope of Work for DemolitionBuilding or area descriptionCondition of releaseFinal configuration of structureLift station3Demo. 3 ft below grade; backfillInformation center bldg (includingconcrete pad and blocks 4 ft x 4 ft x

4 ft)3Demo. 3 ft below grade; backfillCollection site3Demo. 3 ft below grade; backfillStaff building/staff tunnel3Demo. 3 ft below grade; backfill Annex - WHSE 43Complete demolition; backfill WHSE 2 & 3 - warehouse3Demo. 3 ft below grade; backfill WHSE 5 - warehouse3Complete demolition; backfill FPH - fire pump house/retention pond3Demo.; level; backfillSeal pit (outfall)TBDTo Be Determined (TBD) based onAlternatives AnalysisBarge slip area3grade area adjacent to slip Pre-fab building (generator) andyard3Complete demolition; backfillELECT towers (inside industrial area)3Demo. towers and pads; backfillRailroad cars (4) - includes trackspur from fuel bldg to the property

line3Demo. rail cars; remove rails to locationdesignated; gradeWell water house3Demo. to 3 ft below grade; backfill MET tower and equip. inside fenced area3Demo. 3 ft below grade; backfill Electrical fence (around radio tower area)3Complete demolition; backfill MYAPC License Termination PlanPage 3-39Revision 3 October 15, 2002 Table 3-3Structures and Facilities Within the Scope of Work for DemolitionBuilding or area descriptionCondition of releaseFinal configuration of structureConcrete blocks - 4ft x 4ft x4ft Vehicle barriers3Remove initially and store for use; then demo.Remove outside utilities - 3 ftbelow grade1. Potable water3Demo. 3 ft below grade; backfill

2. Utility light poles3Demo. 3 ft below grade; backfill

3. Fire hydrant hose stations3Demo. 3 ft below grade; backfill

4. Sanitary lines3Demo. 3 ft below grade; backfillNotes:a.Number 1 denotes that the bldg/area will undergo decontamination and the commoditieswill be removed prior to building demolition.b.Number 2 denotes that the bldg/area will have commodities removed and decontamination will be done as required. Remaining commodities will remain as is for building demolition.c.Number 3 denotes that the bldg/area is clean and the commodities will remain as is forbuilding demolition.Property, structures and facilities will be demolished to a level three feet belowpresent grade, with few exceptions. As a result of this approach, the following sequence of dismantlement and demolition will occur for buildings with

Condition of Release 1 identified in Table 3-3:a.Strip, package, ship commodities from the buildings (piping, steel,components, etc.) Commodities, including building steel determined to be clean may be released to the demolition contractor.b.Perform decontamination of the building concrete surfaces (at elevationsbelow 3 feet below grade) to meet established criteria levels. Package the debris from decontamination and ship for LLW processing and/or

disposal.c.Perform a final survey (sequence of "c" and "d" optional as described in section 3.1.3 )d.Release for demolition.

MYAPC License Termination PlanPage 3-40Revision 3 October 15, 2002 2Clean rebar has no detectable, plant-derived radioactivity associated with it. Rebar will besurveyed in accordance with free release criteria and disposed of as scrap. If activated rebar is discovered it will be disposed of as radwaste.e.Demolish the building structure to 3 feet below grade. Separate the clean 2rebar from the concrete.f.Prepare the demolished concrete for shipment offsite.

g.Release rebar using established radiological release procedures and shiprebar to metal recycling contractor.

The structures specified as Condition of Release 2 in Table 3-3, are those that areon the cold side of the plant and have been maintained as radiologically "clean,"

with the exception of some systems and equipment that may have internal contamination. Within these areas, the process for demolition will follow this

process:a.Remediate, package, and ship systems, components and, commoditiesidentified within the site characterization report and assessed and bounded by Maine Yankee. Structural steel of plant buildings will either be surveyed and released for recycling or dismantled for packaging and shipment as LLW material.b.Decontaminate, if required, to achieve the established radiological releasecriteria.c.Perform radiation surveys to allow material release to the demolition contractor.d.Release for demolition to the contractor.

e.Demolish structures and foundations to depth specified.

f.Subsurface piping to be handled as indicated above.

g.Perform final grade.The buildings, structures, and facilities identified as Condition of Release 3 inTable 3-3 are those that do not have a history of contamination and are therefore classified as "presumed clean." In certain cases there are minor exceptions to this generalization, based upon the information in the site characterization report, such as a small area within the information center and the staff building, that appear to have been remediated. Also, the site characterization report identifies higher activity levels within the basement of the environmental lab (Bailey House), that may be attributed to background from the granite. However, Maine Yankee will evaluate and release these individual areas in accordance with plant radiological release procedures to allow for demolition. Procedural controls identify the monitoring requirements for construction debris release (Refer to Section 3.1.3).

MYAPC License Termination PlanPage 3-41Revision 3 October 15, 2002Therefore, buildings, structures, and facilities identified as Condition of Release 3in Table 3-3 will be processed as follows:a.Remove ancillary equipment required for asset recovery (furniture, etc.) -(It is assumed that Maine Yankee will remove equipment designated for asset recovery, prior to the scheduled remediation/ demolition of the structure).b.Perform survey in accordance with established procedures and criteria.

c.Release for demolition to the contractor.

3.4Evaluation of Dismantlement Activities3.4.1Systems Review The license basis status of Maine Yankee systems, structures, and components(SSC), is summarized in Table 3-4. As indicated by this table, the majority of radiologically contaminated systems and components not required to support the storage of spent fuel have been abandoned and accepted for decommissioning in accordance with the plant System Evaluation Reclassification Team (SERT) file 98-136. SERT designates them as ready to be "accepted for decommissioning." These SSCs will be deactivated, dismantled, and disposed of in accordance with the schedule described above. NRC and other regulatory agencies will be informed of significant schedule changes during weekly

scheduled communications.3.4.2System Deactivation SSCs, which are not Important to the Defueled Condition (ITDC), nor required tosupport the Spent Fuel Pool (SFP) are placed in an "abandoned" status per a defined program [System Evaluation Reclassification Team (SERT) file 98-136],

which designates them as ready for "decommissioning". Those systems listed as "NO" in the "Required for SFP" Column in Table 3-4 have been eliminated from consideration in the license basis.Systems or components will continue to be abandoned/deactivated prior todecontamination, if necessary and dismantlement. In general, deactivation is implemented by mechanical isolation of interfaces with operating plant systems, draining piping/components, and de-energizing electrical supplies. Combustible material (e.g., charcoal form filters, lube oil) is removed from

abandoned/deactivated components where possible. Chemicals used in, or resulting from, decommissioning activities are controlled in accordance with the MYAPC License Termination PlanPage 3-42Revision 3 October 15, 2002applicable chemical safety program. Plant drawings are revised to indicateabandoned/deactivated portions of systems. Plant procedures are modified to reflect the changes when applicable.Abandonment/deactivation of plant systems is controlled by approved plant procedures. The deactivation plans are established to implement the desired system valve lineup changes and electrical isolations. The design change process

is used to remove components, lift electrical leads, install electrical jumpers, cut and cap piping systems, or install blank flanges as appropriate.Plant procedures provide controls over the operation of deactivated systemboundary valves. As additional systems are deactivated, existing isolation boundaries are re-evaluated and changed, as necessary, to reflect the new plant condition. Mechanical boundaries of abandoned SSCs (including boundary valves) are specifically identified in accordance with Maine Yankee's proceduresTemporary liquid and solid waste processing systems may be used duringdecommissioning for processing plant waste. These systems may include filters and/or demineralizers and may be used at one or more locations in the waste-processing path. Localized temporary ventilation equipment and HEPA filtration may be used to supplement building ventilation and minimize the spread of

radioactive particulate contamination.

Table 3-4Status of Major MY Systems, Structures, and ComponentsSystem/Component/StructureRequiredfor DefueledConditionStatusReactor coolant systemNO Removal mostly completeReactor vessel internalsNO Segmentation and Removal completel Reactor vesselNO Removal completel Secondary component cooling water systemNO Removal ongoingPotable water systemWiscasset water systemYESPreparations for partial removal areongoing, portion remaining in service to support SFP System and site needs MYAPC License Termination PlanPage 3-43Revision 3 October 15, 2002 Table 3-4Status of Major MY Systems, Structures, and ComponentsSystem/Component/StructureRequiredfor DefueledConditionStatus Spent fuel pool and fuelhandling equipmentYESPreparations for partial removal areongoing, portion remaining in service to support SFP SystemSpent fuel pool cooling systemYESWill remain in service as long as materialsare stored in the SFPSpent fuel pool cooling anddemineralizer systemYESWill remain in service as long as materialsare stored in the SFPPlant effluent systemYESRerouted to support Forebay remediationland dismantlement lContainment ventilationsystemsYESPreparations for removal are ongoing asportions of system are no longer required to support decommissioning or SFPFuel building ventilationsystemsYESWill remain in service as long as materialsare stored in the SFPInstrument and service air systemsNOPreparations for removal of Components not required for support of spent fuel pool are ongoing.Solid radioactive waste systemYESWill remain in service as long as materialsare stored in the SFP, and support decommissioning activities after removal of SFP contents.Liquid radioactive waste systemYESWill remain in service as long as materialsare stored in the containment Building, Auxiliary Building, or SFP, and support decommissioning activities after removal of SFP contents.

MYAPC License Termination PlanPage 3-44Revision 3 October 15, 2002 Table 3-4Status of Major MY Systems, Structures, and ComponentsSystem/Component/StructureRequiredfor DefueledConditionStatusRadiation monitoring systemYESPreparations for partial removal of Components not required for support of spent fuel pool are ongoingElectrical systemsYESPreparations for partial removal of Components not required for support of spent fuel pool are ongoing in Accordance with decommissioning Fire protection systemsYESPreparations for partial removal of components not required for support of spent fuel pool are ongoing (Back Up make-up water supply to Spent Fuel Pool )Containment buildingNOPreparations for removal are ongoing. Impact on fuel transfer canal minimizedl through redesignlAuxiliary buildingYESPreparations for partial removal of components not required for support of spent fuel pool are ongoing in accordance with decommissioning scheduleTurbine/generator building (has a wall that supports the SFPI systems)NORemoval complete except for wall thatlsupports the SFPI systemslLow level waste storage buildingNOConverted over to the Security and Opsbldg for ISFSI 3.4.3Nuclear Safety and Regulatory ConsiderationsThe following general considerations, as applicable, will continue to beincorporated into packages during the decommissioning period. . During the decommissioning period, dismantlement activities will be reviewed to ensure that they do not impact safe storage of fuel and GTCC wastes in the ISFSI licensed MYAPC License Termination PlanPage 3-45Revision 3 October 15, 2002under a general Part 72 license. Work packages are implemented in accordancewith administrative controls. When applicable, decommissioning work is reviewed against the requirements of 10 CFR 50.59, 50.82(a)(6) and/or 72.48 to ensure work that is being performed without prior NRC approval does not need a license amendment. Following complete transfer of the spent fuel from the spent fuel pool to theISFSI, Maine Yankee will dismantle and demolish the spent fuel pool. Maine Yankee submitted a license amendment, pursuant to 10 CFR 50.90, to add anl applicability statement to certain technical specifications that describe requirements associated with the spent fuel pool. On February 6, 2002, thisl license amendment was approved.lDismantlement activities will be conducted to ensure the safe storage of spent fueland to protect the public health and safety as well as the common defense and security. Maine Yankee's Quality Assurance Program (QAP) defines the mechanical SSCs in Table 3-5 as safety related.

Table 3-5Safety Related Mechanical ComponentsComponentSafety ClassSpent fuel pool cooling loop suction piping (from the pool wall up to and including the siphon

protection) 3Fuel transfer tube3Blind flange on containment side of fuel transfer tube3 Valve FP-21 (transfer tube isolation valve)3Other items are identified by the Quality Assurance Program (QAP) as requiring adegree of quality and are designated as QA Related (QAR). Following removal of fuel from the spent fuel pool, Maine Yankee will revise the Quality Assurance Program, pursuant to 10 CFR 50.54(a)(3) to delete the safety related and QAR classifications related to spent fuel storage in the spent fuel pool. Equivalent classifications for the ISFSI and the NAC UMS cask are specified in Appendix Bl to the Maine Yankee Quality Assurance Program.

MYAPC License Termination PlanPage 3-46Revision 3 October 15, 2002 3.5Radiological Impacts of Decontamination and Dismantlement Activities3.5.1Waste CharacterizationThe MY Decommissioning Project Waste Management Plan includes wastedisposal strategies, and addresses issues such as: estimates of the quantity of

radioactive material to be released, control mechanisms, and radioactive waste characterization. Radioactive waste has been characterized by sending representative samples for 10 CFR Part 61 analysis. Table 3-6 lists the nuclides for which the samples were analyzed. Table 3-7 presents typical sample Part 61 analysis results.3.5.2Radioactive Waste Projections Any data provided herein are estimated values and may or may not represent actual final volumes. The subject values shown in Table 3-7 provide relative fractions of nuclides historically present in Maine Yankee's waste streams. This and other information sources were used to identify those nuclides which were requested for Part 61 analyses. Alternate means and methods may be utilized when appropriate to reduce these volumes. The projected activities and volumes of radioactive material generated are summarized in Table 3-8 and 3-9.

MYAPC License Termination PlanPage 3-47Revision 3 October 15, 2002 Table 3-6Nuclides Checked for by 10 CFR61 AnalysisNuclidePrincipal Emission!!!!NuclidePrincipalEmission!!!!NuclidePrincipal Emission!!!!Ag-110mgammaZr-93beta*Nb-94 (in activated metal - C-14, Ni-59, Ni-63)gammaAm-241alphaSn-126beta+Kr-85gammaC-14betaIso-Ualpha#Cr-51gammaCm-242alphaK-40gamma#Fe-59gammaCm-243/244alphaZn-65gamma#Nb-95gammaCo-57gammaEu-154gamma#Zr-95gamma---Eu-155gamma#Mo-99gammaCo-60gammaEu-152gamma#I-131gammaCs-134gammaTl-208gamma#Xe-133gamma Cs-137gammaBi-212gamma#Ba-140gammaFe-55ecPb-212gamma#La-140gammaH-3betaBi-214gamma#Ce-141gammaMn-54gammaPb-214gamma#Sn-113gammaNi-59ecRa-226gamma#Sb-124gamma Ni-63betaAc-228gamma#Ru-103gammaPu-238alphaPa-234mgamma#Co-58gammaPu-239/240alphaTh-234gammaPu-241betaU-235gammaSb-125gammaBe-7gammaSr-90betaCe-144gamma*Tc-99betaSb-126gamma* +I-129betaSn-126gamma

!Analysis performed measuring this principal emission*for waste classification

1. for Rx pwr operations (short lived) + in spent fuel MYAPC License Termination PlanPage 3-48Revision 3 October 15, 2002 Table 3-710 CFR61 Sample Analysis Results (Typical)These values are shown to present relative fractions of nuclides historically present.RESIN LIQUIDSMEARCAVITY DRAINUPENDER#3 SGSAMPLEFILTERSACTIVITYDOWNFILTERSMEARBOWLl#Ci/g#Ci/sample#Ci/sample#Ci/sample#Ci/sample#Ci/sample8/21/969/4/966/18/97ACTIVITYACTIVITYSMEAR7/23/966/10/98ACTIVITYNUCLIDE 3/28/98H-32.00E-011.86E-021.40E-0115500C-148.51E-02 4270Mn-548.01E-011.63E-031.00E-021.00E-031260Fe-559.81E+007.49E-012.46E-012.58E-014.33E-02160000Co-572.07E-022.37E-044.79E-04 Co-587.70E-024.15E-02674 Co-609.68E+001.64E+004.48E-013.61E-011.14E-01147000Ni-591.04E-01 Ni-631.42E+011.40E+003.34E-018.97E-023.86E-0218700Zn-65Sr-902.38E-012.74E-02370Zr-93Nb-94Tc-99 6920Ag-110m1.37E-03Sb-1252.72E-012.62E-035.81E-031.61E-032.95E-032110 Sn-126I-129Cs-1342.00E+015.54E-03 Cs-1373.72E+013.35E-038.06E-021.03E-02Ce-1442.45E-03Eu-152 Eu-154 Eu-155U-234 U-235 U-238Pu-2386.67E-041.53E-041.45E-051.83E-041.20E-056.9Pu-239/2402.79E-041.91E-042.24E-056.02E-041.53E-055.3Pu-2412.05E-021.65E-021.98E-032.32E-029.60E-04315Am-2413.56E-042.71E-043.00E-052.77E-041.55E-053.4Cm-2421.64E-043.21E-066.10E-06Cm-243/2444.53E-042.34E-041.19E-058.50E-061.8 MYAPC License Termination PlanPage 3-49Revision 3 October 15, 2002 Table 3-8Projected Activities and VolumesActivityCuriesVolumeReactor vessel and internals2,200,000 Ci11,500 Cu.Ft. Large NSSS components Steam Generators Pressurizer1,600 Ci27,000 Cu.Ft.Activated Concrete390 Ci23,000 Cu. Ft.

Contaminated Debris (Structural Steel, etc)0.10 Ci163,000 Cu. FtContaminated Concrete1.75 Ci900,000 Cu. Ft.Radioactive Water0.5 Ci850,000 Gallons

Soil"0.1 Ci25,000 Cu. Ft

" This volume is an estimate, subsurface soil will be sampled and surveyed followingcommodity removalThe Total Estimated Radwaste Volumes Transported and Buried are described inTable 3-9 (reproduction of Table 1 - PMP 9.0 Rev A, Section 6.3). Although the total estimated radwaste volumes exceeds the 18,340 m 3 described inNUREG-0586 the associated impacts are bounded by those addressed in the FGEIS as discussed in detail in section 8.7.Materials removed and/or generated during the demolition process will bedisposed of based upon the origin of the material and the radiological survey findings prior to or after demolition.Radiologically contaminated concrete materials generated from the RA (fromdemolition at elevations above 3 feet below grade), will be shipped off site for disposal at a LLW facility or appropriate disposal facility. Disposal of building reinforcing steel and structural steel, which has been properly released, will be performed by the demolition contractor to scrap and/or landfill areas.

MYAPC License Termination PlanPage 3-50Revision 3 October 15, 2002 Table 3-9 Total Low-level Waste Volume per Maine Yankee Decommissioning ItemVol ft 3 Transportation ModeDisposal/Process Disposal Volume ft 3Reactor Pressure Vessel (RPV)9,500BargeDirect Disposal9,500Non-GTCC RPV Hardware1,500Cask/TruckDirect Disposal1,500RPV Head 300Cask/TruckDirect Disposal300 Pressurizer2,200BargeProcessing VR 21.3/1*100Reactor Coolant Pumps &Motors4,800Train/TruckDirect Disposal4,800Steam Generators 20,000BargeProcessing VR 21.3/1*940Radioactive ContaminatedMetal 150,000TruckProcessing VR 21.3/1* 7,040Dry Active Waste (DAW)

Resin 13,000TruckProcessing VR 21.3/1*610Liquid Waste Processing400Cask/TruckDirect Disposal400 Spent Fuel Pool Purification Resin150Cask/TruckDirect Disposal150Pre-Existing Waste200Cask/TruckDirect Disposal200Contaminated Soil25,000TrainDirect Disposal 25,000 Radioactive Concrete900,000 TrainDirect Disposal900,000 Used Oil, Radioactive270TruckProcessing/

Incineration 0TOTAL VOLUMESHIPPED 1,127,320 ft 3 (31,924 m 3 )[74% increase over NUREG value-18,340 m 3]TOTAL DISPOSAL VOLUME @ a Volume Reduction of 176,770 ft 3950,550 ft 3 (26,920 m 3)[47% increase over NUREG value-18,340 m 3] NOTE: This would require an additional .3 acre more than the 2 acres described in the NUREG.

• Past performance as of 01-16-01 indicates a 21.3 to 1 Volume Reduction MYAPC License Termination PlanPage 3-51Revision 3 October 15, 2002Table 3-10 below describes the approach to handling building materials forregulatory release.

Table 3-10Approach to Handling of Building Materials for Regulatory ReleaseNo.Type of building materialApproach1Areas with low contamination potentialFree-release in accordance with procedures2Concrete with medium to high surfacecontamination potential (at elevations above - 3 feet below grade)

Ship offsite for disposal atEnvirocare or Barnwell or an appropriate disposal facilityConcrete with medium to high surfacecontamination potential (at elevations below - 3 feet below grade)Remediate to acceptance criterialevels and leave in place, with

removed material disposal at Envirocare or Barnwell3 Contaminated metals removedShip to processor or for disposal atEnvirocare or BarnwellNon-contaminated metals removedShip to processor for scrap or disposal4Built-up tar roofing, inner layer ofsiding (with actual or potential

contamination)Process at LLW treatment facilityor directly dispose at Envirocare"Clean" tar roofing, sidingShip to a processor or disposal 5Outer layer of siding (Galbestos)Surface release survey; send to asbestos landfill6Refueling cavity and spent fuel pool linersProcess at LLW treatment facility3.5.3Occupational ExposureThe estimated total nuclear worker exposure during decommissioning is estimated to be 946 person-rem which is below the 1215 person-rem found acceptable for decommissioning in the reference PWR NUREG-0586 Table 4.3-2.

MYAPC License Termination PlanPage 3-52Revision 3 October 15, 2002Table 3-11 lists estimated exposure/area of activity Attachment A at the end ofthis document provides pictorial reference using the Acronym assigned to the decommissioning activity. Detailed planning precedes initiation of each specific activity, and includes engineering design, ALARA planning, and refinement of cost, schedule, and required resources estimates.

Table 3-11Estimated Exposure/Area of Activity & Decommissioning Activities ScheduledArea/ActivityTitleExposureDC.2 Period 2 (Decommissioning)DC.2.01 NSSS Removal

DC.2.01.01 Reactor coolant

piping DC.2.01.02 Pressurizer relief tank DC.2.01.03 Reactor coolant

pumps and motors DC.2.01.04 Pressurizer DC.2.01.05 Steam Generators

DC.2.01.06 CRDMs &

service structure removal

DC.2.01.07 Reactor vessel internals DC.2.01.08 Reactor vessel

93.951 REMDC.2.03 System removal DC.2.03.01 Containment DC.2.03.01.01 Cbl-1 DC.2.03.01.02 Cbl-2 DC.2.03.01.03 Cbl-3 DC.2.03.01.04 Cbl-4 DC.2.03.01.05 Cbl-5 DC.2.03.01.06 Cbl-6 DC.2.03.01.07 Cbl-7 DC.2.03.01.08 Cbl-8 DC.2.03.01.09 CB2-1 DC.2.03.01.10 CB3-1 DC.2.03.01.11 CB3-2CTMT Loop #1CTMT Loop #2 CTMT Loop #3 SI Tank #2 & Regen Ht Exch E-67 CTMT -2 Lvl Pressurizer Area CTMT -2 Lvl Sump Pump Area CTMT Iodine Filter Area CTMT -2' Outer Annulus CTMT 20' Outer Annulus Reactor Cavity Area CTMT Cavity Upender Pit 97.114 REM 65.745 REM

63.171 REM

11.592 REM

25.411 REM

22.608 REM 6.485 REM 43.334 REM

19.313 REM

19.615 REM

26.683 REM MYAPC License Termination PlanPage 3-53Revision 3 October 15, 2002 Table 3-11Estimated Exposure/Area of Activity & Decommissioning Activities ScheduledArea/ActivityTitleExposure DC.2.03.01.12 CB3-3 DC.2.03.01.13 CB3-4 DC.2.03.01.14 CCG DC.2.03.01.15 CEHO DC.2.03.01.16 CICI L DC.

DC.2.03.01.17 CPHO DC.2.03.01.18 CPLECTMT 46' Penetration RoomCTMT Polar Crane (CR-1)

CTMT Charging Floor

CTMT Equip Hatch Outer (PE-3)

CTMT Incore Instrument Sump

CTMT Personal Hatch Outer Area CTMT Elevator & Room 6.078 REM 4.042 REM 3.105 REM 3.871 REM 6.533 REM.728 REM .173 REMDC.2.03.02 Primary AuxiliaryBldg DC.2.03.02.01 P21A DC.2.03.02.02 P21B DC.2.03.02.03 P21C DC.2.03.02.04 P21D DC.2.03.02.05 P21E DC.2.03.02.06 P21H DC.2.03.02.07 P21L DC.2.03.02.08 P21S DC.2.03.02.09 P21V DC.2.03.02.10 PLAD DC.2.03.02.11 PLBA DC.2.03.02.12 PLCP DC.2.03.02.13 PLDC DC.2.03.02.14 PLEC DC.2.03.02.15 PLLA DC.2.03.02.16 PLPA DC.2.03.02.17 PLPD DC.2.03.02.18 PLPT DC.2.03.02.19 PLPW DC.2.03.02.20 PU48 DC.2.03.02.21 PUDD DC.2.03.02.22 PUEC DC.2.03.02.23 PUFN DC.2.03.02.24 PUHV DC.2.03.02.25 PUL DC.2.03.02.26 PUSA DC.2.03.02.27 PUTC DC.2.03.02.28 PUWGPAB 21' Level Valve AlleyPAB 21' Boric Acid Pump Area PAB 21' Charging Pump Cubicle PAB 21' Level Degas Cubicle PAB 21' Evap Cubicle PAB 21' Heat Exchanger Room PAB 21' General Area PAB 21' Sample Sink Area PAB 21' Level HPSI Room PAB Lower Lvl Aerated Drain Tank Area PAB Lower Lvl Boric Acid Mix Tank Area PAB Lower Lvl Aux Chrg Pump Cubicle PAB Lower Lvl Degas Cubicle PAB Lower Lvl Evap Cubicle PAB Lower Lvl Letdown Area PAB Lower Lvl Ctmt Penetration Area PAB Lower Lvl Primary Drain Tank Area PAB Lower Lvl Pipe Tunnel PAB Lower Lvl Primary Water Pump Area PAB Upper Lvl FN-48 Area PAB Upper Lvl Decay Drum Cubicle PAB Upper Lvl Evap Cubicle PAB Upper Lvl FN-1A/B Area PAB Upper Lvl Heat & Ventilation PAB Upper Lvl General PAB Upper Lvl Radioactive Storage Area PAB Upper Lvl VCT Cubicle PAB Upper Lvl Waste Gas Cubicle

.742 REM 6.387 REM 22.718 REM 9.160 REM 39.169 REM

16.495 REM 1.418 REM 2.799 REM.956 REM 22.184 REM

13.790 REM 5.054 REM 1.551 REM 13.751 REM

38.761 REM

28.907 REM

11.122 REM

30.815 REM

.289 REM

.485 REM

.512 REM 5.921 REM.506 REM

.383 REM 1.741 REM.316 REM

.529 REM

.279 REM MYAPC License Termination PlanPage 3-54Revision 3 October 15, 2002 Table 3-11Estimated Exposure/Area of Activity & Decommissioning Activities ScheduledArea/ActivityTitleExposure DC.2.03.04 Service/fuelbuilding/SVH/SPRB DC.2.03.04.01 DWST DC.2.03.04.02 EFPR DC.2.03.04.03 FBP DC.2.03.04.04 LSAB DC.2.03.04.05 NFLA DC.2.03.04.06 RCAD DC.2.03.04.07 RCAW DC.2.03.04.08 RMCC DC.2.03.04.09 SBDR DC.2.03.04.10 SBHP DC.2.03.04.11 SBMS DC.2.03.04.12 SBP DC.2.03.04.13 SBSR DC.2.03.04.14 SBTT DC.2.03.04.15 SBVH DC.2.03.04.16 SFP DC.2.03.04.17 SFPH DC.2.03.04.18 SFPV DC.2.03.04.19 SPRB DC.2.03.04.20 SVHDemineralizer Water Storage Tank (TK-21)Emergency Feed Water Pump Room Fuel Building Proper LSA Storage Building New Fuel Laydown Area / Fuel Vault RCA Drumming Room RCA Waste Solidification Reactor MCC Room Service Building Decon Room Service Building HP Checkpoint Service Building Machine Shop Service Building Proper Service Building Seal Room Service Building Test Tanks (TK-14 A&B)

Service Building Steam & Valve House Spent Fuel Pool Spent Fuel Pool Heat Exchanger Room Spent Fuel Pool Ventilation Room Spray Building Steam & Valve House

.103 REM.159 REM.628 REM 1.622 REM 8.772 REM.046 REM

.314 REM

.044 REM

.293 REM.111 REM 32.159 REM 9.120 REM.287 REM 78.093 REM

.054 REM DC.2.03.05 Miscellaneous DC.2.03.05.01 BWST DC.2.03.05.02 CST DC.2.03.05.03 CWl DC.2.03.05.04 Fl DC.2.03.05.05 FOB DC.2.03.05.06 FPH DC.2.03.05.07 GH L DC.2.03.05.08 HRB DC.2.03.05.09 PWST DC.2.03.05.10RWST/SCAT DC.2.03.05.11 STFB DC.2.03.05.12 STPl DC.2.03.05.13 West - RCABoron Waste Storage Tanks (TK-13 A&B)Condensate Serge Tank (TK-122)

Circulating Water Pump House Foxbird Island Fuel Oil Pump House & Bunker Fire Pump House

Gas House High Radiation Bunker Primary Water Storage Tank (TK-16)

RWST/SLAT TanksStaff Building & TunnelSewage Treatment Plant RCA Yard Area - West Side

.162 REM .003 REM.528 REM.068 REM 1.549 REM 7.136 REM MYAPC License Termination PlanPage 3-55Revision 3 October 15, 2002 Table 3-11Estimated Exposure/Area of Activity & Decommissioning Activities ScheduledArea/ActivityTitleExposureTotal Estimated exposure forthe project 937.543REM3.5.4Public ExposureContinued application of Maine Yankee's Radiation Protection Program, WasteManagement Plan, Radiological Effluents Controls Program and Radiological Environmental Monitoring Program assures public protection in accordance with 10 CFR 20. Details for remediation are provided in Section 4 of this LTP. LTP Section 8 contains an evaluation of estimated public exposure as a result of decommissioning activities including the transportation of radioactive waste. 3.5.5Expected Radiological Conditions Characterization of concrete within the Restricted Area (RA) of the site shows thefollowing:1.Painted concrete has surface contamination up to 1 million dpm/100 cm 2(worst case) which is amenable to surface remediation techniques such aswiping, washing, power washing or abrasive surface removal.2.Bare concrete has surface contamination, absorbed contamination andactivation products within the concrete matrix. Surface contamination levels are similar to those for painted concrete. Absorbed activity has been found to penetrate to a depth of approximately 1 mm.3.Concrete structures adjacent to the reactor vessel also showed activationproducts at levels of a few pCi/g except for the In Core Instrumentation (ICI) sump where levels were as high as 600-800 pCi/g to depths of several inches. These types of radioactivity are amenable to remediation by surface removal techniques except for the deeply deposited activation

products.4.Surface abrasive or surface removal remediation techniques may generateairborne radioactivity. Airborne activity will be controlled within the requirements of 10 CFR Part 20 and measured using standard processes and procedures existing within the radiation protection program. These MYAPC License Termination PlanPage 3-56Revision 3 October 15, 2002processes and procedures have proven successful for controllingdecontamination and demolition activities in the past while protecting the health and safety of the workers and the public.Maine Yankee has segmented the reactor vessel internals and loaded resultinglGTCC waste into NAC UMS casks for storage at the ISFSI. This segmentation process used an abrasive water jet. Special precautions were taken to capture thel residue (SWARF) resulting from this segmentation.3.5.6Contamination Control Due to the large scope of the D&D and the need for some FSS activities to beperformed in parallel with dismantlement activities, a systematic approach to controlling areas is established. Upon commencement of the FSS for survey areas within the Restricted Area (RA) where there is a potential for re-contamination, implementation of one or more of the following control measures will be required:a.Personnel trainingb.Installation of barriers to control access to surveyed areas c.Installation of barriers to prevent the migration of contaminationfrom adjacent overhead areasd.Installation of postings requiring personnel to performcontamination monitoring prior to surveyed area accesse.Locking entrances to surveyed areas of the facility f.Installation of tamper-evident labels g.Upon completion of FSS, the area is placed under periodic routinesurvey by Radiation Protection to ensure no re-contamination occurs. If re-contamination is identified, an investigation will be initiated that would result in corrective actions up to and including re-performance of the FSS on that area.During the D&D activities, measures will be maintained and/or established to control and monitor radwaste effluents. This consideration should not preclude the removal of penetrations and attachments to the containment building, provided that openings are closed, or can be closed in a timely manner.

Airborne ControlsAirborne radioactive particulate emissions will continue to be filtered, andeffluent discharges sampled/monitored and quantified. Consideration is given to the following items:

MYAPC License Termination PlanPage 3-57Revision 3 October 15, 2002a.Operation of the appropriate portions of the containmentventilation and purge system, or an alternate system, during decontamination and dismantlement activities in the containment building;b.Operation of the appropriate portion of the auxiliary buildingventilation system, as required.c.Operation of the appropriate portion of the fuel building ventilationsystem to support the fuel building.

NOTE: The auxiliary building roof physically supports the fuel building ventilation ducts.d.Use of local HEPA filtration systems for activities expected toresult in the generation of airborne radioactive particulate (e.g.

grinding, chemical decontamination, or thermal cutting of

components)When applicable during demolition engineering controls such as misting will beapplied to concrete surfaces. Where practical for ALARA purposes, temporary shielding is used during decommissioning activities. Some dismantlement activities may be performed under water for shielding purposes as well as

contamination control.Liquid/Particle ControlWork activities are planned to minimize the spread of contamination. Liquids arecontained within existing or supplemental barriers and processed by a liquid waste processing system prior to release. To minimize the potential for spread of contamination, the following considerations will continue to be addressed when planning decommissioning work activities.a.Covering of openings in contaminated components to confineinternal contamination;b.D&D of SSCs by decontamination in place, removal and decontamination, or removal and disposal;c.Removal of supports in conjunction with equipment removal or decontamination of supports in conjunction with building

decontamination;d.Removal of systems and components from areas and buildings prior to structural decontamination (block shield wall, portions of MYAPC License Termination PlanPage 3-58Revision 3 October 15, 2002other walls, ceiling, or floors may be removed to permit removal ofsystems and components.);e.Removal or decontamination of embedded piping, conduit, ducts, plates, channels, anchors as required, sumps, and sleeves during area and building structural decontamination activities;f.Use of local or centralized processing and cutting stations tofacilitate packaging of components removed in large pieces; andg.Removal of small or compact plant components and parts intact, where feasible. (This includes most valves, smaller pumps, some small tanks, and heat exchangers. These components could then be

decontaminated in whole or part, and reduced to smaller

dimensions in preparation for disposal or release.)

3.6Coordination with Other Regulatory AgenciesThe decommissioning and termination of Maine Yankee's Part 50 license involves, in addition to the NRC, coordination with a number of federal, state and local agencies as well as several advisory groups. This section outlines the broad responsibilities of those groups and also addresses specific environmental issues raised in the FGEIS in the context of the Maine Yankee site. 3.6.1Regulatory Agencies The following federal, state and local agencies have some level of involvement inMaine Yankee's decommissioning. Some have direct approval authority over site activities while others serve in an advisory capacity to other agencies. Their primary functions, programs, and regulatory authority are described below.a.US Environmental Protection Agency (EPA) - EPA has been engaged in discussions with various stakeholders about the Maine Yankee decommissioning process. The EPA is supporting the Maine Yankee decommissioning project in several areas. The EPA is enabled by Resource Conservation and Recovery Act (RCRA) to administer closure of facilities that were hazardous waste generators. Since the State of

Maine Department of Environmental Protection (MDEP) has been delegated authority to administer the RCRA program in Maine, EPA is serving in a technical support role for the Maine Yankee site closure.

EPA is expected to review all major closure related documents and advise MDEP on their adequacy.

MYAPC License Termination PlanPage 3-59Revision 3 October 15, 2002The EPA also is responsible for the Toxic Substances Control Act (TSCA)which serves as the primary means by which the use and disposal of PCBs and PCB-containing materials are controlled. PCBs have been identified

above the TSCA limits of 50 parts per million (ppm) in electrical cable sheathing and, in limited areas, painted structural steel and painted concrete surfaces.The EPA previously administered the National Pollutant DischargeElimination System (NPDES) permit program as authorized by the Clean Water Act in Maine. Maine Yankee maintained an NPDES permit during operation to reflect discharge of certain process wastewater during decommissioning. Effective January 12, 2001, MDEP administers the NPDES program on EPA's behalf. MDEP has issued a new discharge license to Maine Yankee b.US Department of Transportation ( DOT) - The DOT regulates thepackaging, labeling and shipment of waste materials offered for interstate commerce. Waste materials that are expected to be shipped from Maine Yankee during decommissioning that are regulated by the DOT include radiological wastes, mixed waste, and hazardous waste. DOT approved the transportation of the Pressurizer and Steam Generators as their own shipping containers and the shipping container for the Reactor Vessel. c.US Coast Guard - The Coast Guard has authority to control vessel trafficin the navigable waterways of the US. Barge shipment of large

components will be coordinated with the Coast Guard to ensure that all applicable requirements for securing loads and notifying the public are met.d.US Department of Energy (DOE) - The DOE has a contractual obligationto take receipt and dispose of Maine Yankee's GTCC waste and spent

nuclear fuel. e.Maine Department of Environmental Protection (MDEP) - The MDEP isthe lead state agency responsible to prevent, abate and control the

pollution of the air, water and land and prevent diminution of the natural environment of the state. The MDEP has authority in a variety of statutes and accomplishes its charge through a number of regulations. The MDEP regulates solid and hazardous waste activities, development activities at Maine Yankee through the Site Location of Development Law, industrial discharges, air emissions, and activities affecting significant natural MYAPC License Termination PlanPage 3-60Revision 3 October 15, 2002resources including coastal and freshwater wetlands. These aspects are discussed in more detail in Section 8.6.f.Maine Department of Human Services - The Department of HumanServices through the Division of Health Engineering (DHE) has responsibility for radiological programs within the state. DHE also sponsors the two State Nuclear Inspectors that monitor activities at Maine

Yankee.g.Maine Department of Inland Fisheries and Wildlife (IF&W) - IF&W doesnot directly regulate activities at Maine Yankee. IF&W does however provide technical support to the MDEP for permitting activities relating to development projects and projects that may affect significant natural resources. IF&W is also responsible for the Maine threatened and endangered species protection program.h.Maine Department of Marine Resources (DMR) - DMR does not directlyregulate activities at Maine Yankee. However DMR does provides technical support to MDEP on projects involving potential impacts to coastal wetlands.i.Maine Department of Transportation (MDOT) - MDOT has permittingauthority for new development projects generating over 100 passenger car equivalent trips in the peak hour. It is not anticipated that MDOT will have active involvement in decommissioning activities. j.Maine Historic Preservation Commission - Maine Yankee has coordinatedwith this organization for the preservation of the two identified archaeologic sites on Maine Yankee property. The specific location of archaeological sites is not provided to ensure their integrity is protected.k.Town of Wiscasset (Town) - The Town has permitting authority over newdevelopment projects such as the recently permitted Independent Spent Fuel Storage Installation (ISFSI) now under construction. The Town also has permitting authority over major earthwork projects. It is expected that final site grading will trigger Town review and approval requirements.l.The Maine Turnpike Authority- has a long standing agreement thatplacarded shipments of LLW will only travel on the Turnpike during daylight hours.

MYAPC License Termination PlanPage 3-61Revision 3 October 15, 2002m.The Maine State Police- are given a courtesy call before each LLW shipment leaves the site. This is not an official requirement.3.6.2Advisory and Community Entities a.The State Nuclear Safety Advisor responsibilities include advising theGovernor and legislature on nuclear power issues, specifically transport and storage of nuclear waste at Maine Yankee. The Advisor also consults with relevant federal agencies and coordinates the activities of state agencies with respect to decommissioning. Another duty is to keep abreast of related activities in other states and to advise the Governor and legislature on such activities. In addition to making these

recommendations and updates to the Governor, the Advisor prepares an

annual report.b.The Governor's Technical Advisory Panel (TAP) is currently comprised offour professors with expertise in radiological sciences from the University of Maine, Colorado State University, University of Michigan, and the University of Massachusetts Lowell. This panel was assembled in 1999 to provide independent evaluation of technical decommissioning issues and to advise the Governor accordingly. Panel members are Dr. C. T. Hess, Dr. F. Ward Whicker, Dr. Glenn Knoll, and Dr. George E. Chabot. c. The Maine Advisory Commission on Radioactive Waste andDecommissioning is charged with overseeing radioactive waste activities in the state, including the decommissioning process at Maine Yankee. The Commission meets on a quarterly basis. Its members include state legislators, members of the public, waste generators and state agency staff. d.The Maine Yankee Community Advisory Panel (CAP) was established in 1997 to enhance opportunities for public involvement in the decommissioning process of Maine Yankee. The CAP represents the community. By thoroughly reviewing the decommissioning process, the CAP is in a position to advise Maine Yankee on key issues of concern to the regional community. e.Friends of the Coast (FOC)- Friends of the Coast Opposing NuclearPollution is a local environmental organization founded in 1995. Friends of the Coast participates regularly in stakeholder discussions on the full range of decommissioning issues and has a seat on the Maine Yankee CAP.

MYAPC License Termination PlanPage 3-62Revision 3 October 15, 20023.6.3Environmental and Regulatory IssuesSection 8.6 of the LTP provides a detailed discussion of how non-radiologicalenvironmental and regulatory issues associated with decommissioning are being addressed with the cognizant state and federal agencies having jurisdiction over those issues.

3.7References3.7.1NUREG-1700, "Standard Review Plan for Evaluating Nuclear PowerReactor License Termination Plans"3.7.2NRC Regulatory Guide 1.179, "Standard Format and Content of LicenseTermination Plans for Nuclear Power Reactors" (January 1999)3.7.3Post Shutdown Decommissioning Activities Report 3.7.4"Characterization Survey Report for the Maine Yankee Atomic Power Plant", Volumes 1-8, 1998 GTS Duratek3.7.5"Site History Report," Stone and Webster Environmental Technology andlServices (November 1999), transmitted via James T. Kilbreth letter tol Joan Jones, State of Maine, dated November 16, 1999l3.7.6Kim Tripp, US Fish and Wildlife Services, letter to David Asherman,ldated July 21, 1999, regarding federally listed species.l3.7.7NRC letter to Maine Yankee, dated July 30, 2002, Issuance of AmendmentlNo. 167, license amendment approving partial release of site landsl MYAPC License Termination PlanRevision 3 October 15, 2002 ATTACHMENT 3A Drawings Associated with Specific Decommissioning Tasks These drawings are provided "For Information Only" to support the reader's understanding and correlation of decommissioning tasks, anticipated radiation exposure, and physical locations

involved in the subject tasks.

MYAPC License Termination PlanRevision 3 October 15, 2002 TABLE 3A-1 DECOMMISSIONING AREAS Figure Number Figure Title Areas Figure 3-1 Containment Building -2' Elevation General Area CB-11 CB-13 CB-14 CB-15 CB-16 CB-17 CB-18 CICI Figure 3-2 Containment Building 20' Elevation

General Area CB-11 CB-13 CB-14 CB-16 CB-21 CEHO CPHO Figure 3-3 Containment Building 46' Elevation

General Area CB-32 CB-33 CB-34 CP-34 CPLE Figure 3-4 Primary Auxiliary Building 11' Elevation

General Area PLAD PLDC PLEC PLLA PLPA PLPD PLPW Figure 3-5 Primary Auxiliary Building 21' Elevation

General Area PLAD PLPD P21D P21E P21H P21L P21L Figure 3-6 Primary Auxiliary Building 36' Elevation

General Area PU-48 PUDD PUEC PUFN PUFN PUHV PULI PULI PUSA PUSA PUTC PUWG Figure 3-7 Containment Building Electrical

Penetration RoomRMCCRMCCRMCC Figure 3-8 Containment Building Mechanical

Penetration Room Levels 4 & 5 SVH1 Figure 3-9 Spray Building 4' Elevation SBRP Figure 3-10 Spray Building 6' Elevation SBRP Figure 3-11 Spray Building 11' Elevation SBRP Figure 3-12 Spray Building 12' & 21" Elevation Figure 3-13 Spray Building 20' & 30' Elevations General Area RMCC SBRP Figure 3-14 Fuel Building 21' Elevation Decon Room RCAD Figure 3-15 RCA Storage Building Waste Solidification RCAW Figure 3-16 Fuel Building 21' Elevation Spent Fuel

Pool Heat Exchanger Area SFPH Figure 3-17 Fuel Building 21' Elevation Fuel Laydown

Area SFP03 Figure 3-18 Fuel Building New Fuel Storage 31'-1 1/2"

Elevation NFLA Figure 3-19 Fuel Building 44'-6" ElevationSFP02SFP04 SFPV MYAPC License Termination Plan Revision 3October 15, 2002 TABLE 3A-1 DECOMMISSIONING AREAS Figure Number Figure Title Areas Figure 3-20 Montsweag Bay Figure 3-21 Site Area Layout CCWI FPHI HRB PWST STPI X-16 X-19 Figure 3-22 Service Building 21' Elevation SB011 SB02 SB03 SBDR SBHP SBMS SBP SBP SBSR Figure 3-23 Service Building 21' Elevation Control and

Computer Room Figure 3-24 Cold Side Service Building 30'-10"

Elevation 2 nd Floor General Area SBP Figure 3-25 Service Building 39' ElevationSB05SB07SB08 Figure 3-26 Cable Vault Room 49' ElevationSB09SB10 Figure 3-27 Turbine Building 21' Elevation TBLD TBMS TBSO TCA TCBA TCDA TCNE TCSE TFPA THDT THEA TMC TP2C TSPP Figure 3-28 Turbine Building 61' Elevation MTGE TBR2 TD01 TDBV TDRW TDSN TDSS TSRP TSRU Figure 3-29 Turbine Building 39' Elevation FWH TCTP TCTU TDR2 TMAE TMCH TMDV TMDW TMEC TMFA TMFR TMFV TMGL TMHD TMIA TMLT TMNC TMSE TMWC TMWT Figure 3-30 Final Site Configuration M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N C o n ta in m e n t B u il d in g-2' E le v a ti o n G e n e ra l A re a C o n ta in m e n t B u il d in g-2' E le v a ti o n G e n e ra l A re a F ig u re 3-1 F ig u re 3-1 RC P Pla tfo rm RC P Pla tfo rm#1 S/G Pla tfo rm#1 S/G Pla tfo rm RC P Pla tfo rm RC P Pla tfo rm#2 S/G Pla tfo rm#2 S/G Pla tfo rm RC P Pla tfo rm RC P Pla tfo rm#3 S/G Pla tfo rm#3 S/G Pla tfo rm#1 S IT#1 S IT#2 S IT#2 S IT ELEVATOR ELEVATOR#3 S IT#3 S IT C B-1 7 C B-1 7 C B-1 3 C B-1 3 C B-1 6 C B-1 6 C B-1 8 C B-1 8 C B-1 4 C B-1 4 C B-1 1 C B-1 1 P Q T A Z U N R E K N C H P Q T A Z U N R E K N C H C IC I C IC I Ou ter A nn ulu s Ou ter A nn ulu s C B-1 5 C B-1 5 M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N C o n ta in m e n t B u il d in g 2 0'E le v a ti o n G e n e ra l A re a C o n ta in m e n t B u il d in g 2 0'E le v a ti o n G e n e ra l A re a F ig u re 3-2 F ig u re 3-2 SI T #2 SI T #2 SI T #1 SI T #1 SI T #3 SI T #3 OP EN T O-2' E L.OP EN T O-2' E L.C B-2 1 C B-2 1 C B-1 4 C B-1 4 C P H O C P H O C E H O C E H O C B-1 6 C B-1 6 C B-1 3 C B-1 3 C B-1 1 C B-1 1 O u te r A n n u lu s O u te r A n n u lu s M AI NE Y AN KE E A T OM IC P OW ER C O.LI CE NS E TE RM IN A TI ON P LA N M AI NE Y AN KE E A T OM IC P OW ER C O.LI CE NS E TE RM IN A TI ON P LA N C o n ta in m e n t B u il d in g 4 6' E le v a ti o n G e n e ra l A re a C o n ta in m e n t B u il d in g 4 6' E le v a ti o n G e n e ra l A re a F ig u re 3-3 F ig u re 3-3 O PE N TO O PE N TO-2' E L.-2' E L.O PE N TO O PE N TO 20' E L.20' E L.O PE N TO O PE N TO 20' E L.20' E L.C C G C C G C B-3 4 C B-3 4 C P-3 2 C P-3 2 C P L E C P L E C B-3 3 C B-3 3 AB O VE EL EV A TO R M AC HI NE RO O M AB O VE EL EV A TO R M AC HI NE RO O M P O LA R C R A N E P O LA R C R A N E MA INE Y AN KE E A TO MI C P OW ER CO.LIC EN SE TE RM INA TIO N P LA N MA INE Y AN KE E A TO MI C P OW ER CO.LIC EN SE TE RM INA TIO N P LA N P rim ar y A ux ili ar y B ui ld in g 1 1' E le va tio n G en er al A re a P rim ar y A ux ili ar y B ui ld in g 1 1' E le va tio n G en er al A re a Fi gu re 3-4 Fi gu re 3-4 PL P A PL P A PL AD PL AD PL PD PL PD PL D C PL D C PL EC PL EC PL PW PL PW PL LA PL LA M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N P ri m a ry A u x il ia ry B u il d in g 2 1' E le v a ti o n G e n e ra l A re a P ri m a ry A u x il ia ry B u il d in g 2 1' E le v a ti o n G e n e ra l A re a F ig u re 3-5 F ig u re 3-5 P 2 1 L P 2 1 L P L A D P L A D P 2 1 H P 2 1 H P 2 1 L P 2 1 L P L P D P L P D P 2 1 D P 2 1 D P 2 1 E P 2 1 E M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N P ri m a ry A u x il ia ry B u il d in g 3 6' E le v a ti o n G e n e ra l A re a P ri m a ry A u x il ia ry B u il d in g 3 6' E le v a ti o n G e n e ra l A re a F ig u re 3-6 F ig u re 3-6 P U S A P U S A P U S A P U S A P U T C P U T C P U D D P U D D P U W G P U W G P U H V P U H V P U-4 8 P U-4 8 P U F N P U F N P U E C P U E C P U L I P U L I P U F N P U F N P U L I P U L I M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N C o n ta in m e n t B u il d in g E le c tr ic a l P e n e tr a ti o n R o o m C o n ta in m e n t B u il d in g E le c tr ic a l P e n e tr a ti o n R o o m F ig u re 3-7 F ig u re 3-7 R M C C R M C C R M C C R M C C R M C C R M C C M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N C o n ta in m e n t B u il d in g M e c h a n ic a l P e n e tr a ti o n R o o m L e v e ls 4 & 5 C o n ta in m e n t B u il d in g M e c h a n ic a l P e n e tr a ti o n R o o m L e v e ls 4 & 5 F ig u re 3-8 F ig u re 3-8 Le ve l 4 Le ve l 4 Le ve l 5 Le ve l 5 MS-M-20 MS-M-20 MS-M-30 MS-M-30 MS-M-10 MS-M-10 S V H 1 S V H 1 M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S p ra y B u li d in g 4' E le v a ti o n S p ra y B u li d in g 4' E le v a ti o n F ig u re 3-9 F ig u re 3-9 S B R P S B R P M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S p ra y B u il d in g 6' E le v a ti o n S p ra y B u il d in g 6' E le v a ti o n F ig u re 3-1 0 F ig u re 3-1 0 S B R P S B R P M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S p ra y B u il d in g 1 1' E le v a ti o n S p ra y B u il d in g 1 1' E le v a ti o n F ig u re 3-1 1 F ig u re 3-1 1 S B R P S B R P Tre nch Tre nch Su mp Pu mp s Su mp Pu mp s M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S p ra y B u il d in g 1 2' & 2 1' E le v a ti o n S p ra y B u il d in g 1 2' & 2 1' E le v a ti o n F ig u re 3-1 2 F ig u re 3-1 2 S p ra y B u il d in g 2 0' & 3 0' E le v a ti o n s G e n e ra l A re a S p ra y B u il d in g 2 0' & 3 0' E le v a ti o n s G e n e ra l A re a M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F ig u re 3-1 3 F ig u re 3-1 3 R M C C R M C C E L E C T R IC A L E L E C T R IC A L S B R P S B R P 30' E lev ati on 30' E lev ati on M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F u e l B u il d in g 2 1' E le v a ti o n D e c o n R o o m F u e l B u il d in g 2 1' E le v a ti o n D e c o n R o o m F ig u re 3-1 4 F ig u re 3-1 4 R C A D R C A D D ru m m in g R o o m D ru m m in g R o o m M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N R C A S to ra g e B u il d in g W a s te S o li d if ic a ti o n R C A S to ra g e B u il d in g W a s te S o li d if ic a ti o n F ig u re 3-1 5 F ig u re 3-1 5 R C A W R C A W M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F u e l B u il d in g 2 1' E le v a ti o n S p e n t F u e l P o o l H e a t E x c h a n g e r A re a F u e l B u il d in g 2 1' E le v a ti o n S p e n t F u e l P o o l H e a t E x c h a n g e r A re a F ig u re 3-1 6 F ig u re 3-1 6 S F P H S F P H HEAT EXCHANGER M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F u e l B u il d in g 2 1'E le v a ti o n F u e l L a y d o w n A re a F u e l B u il d in g 2 1'E le v a ti o n F u e l L a y d o w n A re a F ig u re 3-1 7 F ig u re 3-1 7 S F P 0 3 S F P 0 3 M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F ig u re 3-1 8 F ig u re 3-1 8 N F L A N F L A F u e l B u i l d i n g N e w F u e l S t o r a g e 3 1'-1 1/2" E l e v a t i o n M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N F u e l B u il d in g 4 4'-6" E le v a ti o n F u e l B u il d in g 4 4'-6" E le v a ti o n F ig u re 3-1 9 F ig u re 3-1 9 S F P 0 2 S F P 0 2 S F P 0 4 S F P 0 4 S F P V S F P V Fu el Br idg e Sp en t F ue l P oo l MAI NE YAN KEE ATO MIC P OWER CO.LICENSE TERMINATIO N PLAN Montsweag Bay Fig ure 3-20 N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S it e A re a L a y o u t S it e A re a L a y o u t F ig u re 3-2 1 F ig u re 3-2 1 H R B H R B B U I L D I N G B U I L D I N G R E A C T O R R E A C T O R T U R B I N E H A L L T U R B I N E H A L L H O U S E H O U S E S C R E E N S C R E E N C C W I C C W I S E R V I C E B U I L D I N G S E R V I C E B U I L D I N G S T P I S T P I 1 0 1 0 3 0 3 0 S T A F F B U I L D I N G S T A F F B U I L D I N G A D M I N.A D M I N.C E N T E R C E N T E R P W S T P W S T X-1 9 X-1 9 X-1 6 X-1 6 P A B P A B 5 0 5 0 P A R K I N G P A R K I N G 3 0 3 0 3 0 3 0 W A R E H O U S E #2 W A R E H O U S E #2 S W I T C H Y A R D S W I T C H Y A R D 1 1 5 K V 1 1 5 K V F I R E P O N D F I R E P O N D F P H I F P H I M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S E R V IC E B U IL D IN G 2 1'E L E V A T IO N S E R V IC E B U IL D IN G 2 1'E L E V A T IO N F IG U R E 3-2 2 F IG U R E 3-2 2 S B M S S B M S S B 03 S B 03 S B H P S B H P S B S R S B S R S B 02 S B 02 S B P S B P S B 01 1 S B 01 1 S B D R S B D R S B P S B P A LL C O M M O DI TI ES O UT B Y 0 4/01/2 00 1 A LL C O M M O DI TI ES O UT B Y 0 4/01/2 00 1 M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N M A IN E Y A N K EE A T O M IC P O W ER C O.LI CE N SE TE RM IN A TI O N P LA N S e rv ic e B u il d in g 2 1'E le v a ti o n C o n tr o l a n d C o m p u te r R o o m S e rv ic e B u il d in g 2 1'E le v a ti o n C o n tr o l a n d C o m p u te r R o o m F ig u re 3-2 3 F ig u re 3-2 3 Co ntr ol Ro om Co mp ute r roo m MAI NE YAN KEE ATO MIC P OWER CO.LICENSE TERMINATIO N PLAN Cold Side Service Buil ding 30'-10" Elevation 2nd Floor Gener al Area Fig ure 3-24 N MAINE YANKEE ATOMIC POWER CO.

LIC ENSE TERMINATION PLAN Service Building 39' Elev ati on Figur e 3-25 SB07 SB05 SB08 TURBINE B UILDING N MAINE YANKEE ATOMIC POWER CO.

LI CEN SE TERMINATION PLAN Cable Vault Roo m 49' Elevation Figure 3-26 SB09 SB10 N MAINE YANKEE ATOMIC POWER CO.

LIC EN SE TERMINATION PLAN Tur bine B uildin g 21'Elev at ion Fig ure 3-27 SUMP TSPP TBSO TCNE THEA TCBA TMC TCDA TCSE TP2C THDT TFP A TBMS TCA TBLD N MAINE YANKEE ATOMIC POWER CO.

LI CEN SE TERMINATION PLAN Turbi ne Bui ld ing 61' E lev atio n Figure 3-28 TDRW TSR U TSR P TBR2 MTGE TDSN TDBV TDSS TD01 N MAINE YANKEE ATOMIC POWER CO.

LI CEN SE TERMINATION PLAN Turbi ne B uild ing 39' E lev atio n Figure 3-29 TMW C TMFA TMFR TMIA FW H TMHD TMSE TMLT TMDW TMDV TMFV TMW T TCTP TMGL TDR2 TMCH TMNC TMAE TMEC TCTU N MAINE YANKEEATOMIC POWER CO.LICENSETERMINATION PLANMAINE YANKEEATOMIC POWER CO.LICENSETERMINATION PLANFinal Site ConfigurationFinal Site ConfigurationFigure3-30Figure3-30 R O U T E 1 4 4 RO UT E 1 44 PLA NT ACC ESS RO AD X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X SE CU RIT Y/OP S BL DG.ISF SIWISCASSETMAINE YANKEEWESTPORT AIR PO RT WE STP OR T BRIDG E ROA D U.S. R O U T E 1 R O U T E 1 4 4BACK RIVERLITTLEISLANDOAKBAILEYPOINTMONTSWEAG BAYFOXBIRD ISLAND115KVSWITCHYARD345KV SWITCHYARDISFSI