ML050940386
| ML050940386 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/28/2005 |
| From: | Maine Yankee Atomic Power Co |
| To: | NRC/FSME |
| References | |
| Download: ML050940386 (97) | |
Text
DMYAPC License Termination Plan Revision 4 February 28, 2005 MAINE YANKEE LTP SECTION 3 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES
MYAPC License Termination Plan Page 3-i Revision 4 February 28, 2005 TABLE OF CONTENTS 3.0 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES.......... 3-1 3.1 Introduction.......................................................... 3-1 3.1.1 Purpose....................................................... 3-1 3.1.2 Decommissioning Progress Update................................. 3-2 3.1.3 Decontamination & Dismantlement Process Summary.................. 3-3 3.2 Remaining Dismantlement Activities...................................... 3-7 3.2.1 Major Decommissioning Activities................................. 3-7 3.2.2 Dismantlement Activity Schedule.................................. 3-9 3.2.3 Material Removal Sequence...................................... 3-23 3.2.4 Final State-of-the-Site Description................................. 3-24 3.3 Methods of Decontamination and Dismantlement............................ 3-29 3.3.1 Decontamination of Systems and Components....................... 3-29 3.3.2 Dismantlement of Systems and Components......................... 3-30 3.3.3 Decontamination of Structures.................................... 3-32 3.3.4 Building Demolition and Site Restoration........................... 3-35 3.4 Evaluation of Dismantlement Activities................................... 3-41 3.4.1 Systems Review............................................... 3-41 3.4.2 System Deactivation............................................ 3-41 3.4.3 Nuclear Safety and Regulatory Considerations....................... 3-44 3.5 Radiological Impacts of Decontamination and Dismantlement Activities......... 3-45 3.5.1 Waste Characterization.......................................... 3-45 3.5.2 Radioactive Waste Projections.................................... 3-45 3.5.3 Occupational Exposure.......................................... 3-50 3.5.4 Public Exposure............................................... 3-54 3.5.5 Expected Radiological Conditions................................. 3-54 3.5.6 Contamination Control.......................................... 3-55 3.6 Coordination with Other Regulatory Agencies.............................. 3-57 3.6.1 Regulatory Agencies............................................ 3-57 3.6.2 Advisory and Community Entities................................. 3-59 3.6.3 Environmental and Regulatory Issues.............................. 3-60 3.7 References.......................................................... 3-61 ATTACHMENT 3A Drawings Associated with Specific Decommissioning Tasks
MYAPC License Termination Plan Page 3-ii Revision 4 February 28, 2005 List of Tables Table 3-1 Major MY Area/Systems, Structures, and Components Removed (By Year).................... 3-10 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)........... 3-11 Table 3-3 Structures and Facilities Within the Scope of Work for Demolition........................... 3-35 Table 3-4 Status of Major MY Systems, Structures, and Components................................. 3-42 Table 3-5 Safety Related Mechanical Components................................................ 3-45 Table 3-6 Nuclides Checked for by 10 CFR61 Analysis............................................ 3-46 Table 3-7 10 CFR61 Sample Analysis Results (Typical)............................................ 3-47 Table 3-8 Projected Activities and Volumes..................................................... 3-48 Table 3-9 Total Low-level Waste Volume per Maine Yankee Decommissioning......................... 3-49 Table 3-10 Approach to Handling of Building Materials for Regulatory Release.......................... 3-50 Table 3-11 Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled................ 3-51
MYAPC License Termination Plan Page 3-1 Revision 4 February 28, 2005 3.0 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES 3.1 Introduction 3.1.1 Purpose This section of the LTP describes the remaining dismantlement activities at MY pursuant to 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 information to 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 also provided. 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 Yankees coordination with these agencies and groups is generally described.
An evaluation of the remaining decontamination and dismantlement activities is described 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 corresponding schedule for the proposed license amendment and the schedule for needed approval.
MYAPC License Termination Plan Page 3-2 Revision 4 February 28, 2005 3.1.2 Decommissioning Progress Update Shortly after the submittal of the 10 CFR 50.82(a)(1) certifications, Maine Yankee assembled 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 radiological characterization 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. Four phases of site dismantlement, some of which run in parallel, were defined by Stone &
Websters 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.
The construction of the ISFSI has been completed, and movement of spent fuel was l
completed in the first quarter of 2004. In preparation for constructing the ISFSI, final l
MYAPC License Termination Plan Page 3-3 Revision 4 February 28, 2005 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) system. 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. During 2003 l
and 2004, remaining above grade structures in the Industrial Area were surveyed and l
demolished including the Spray Building, Primary Auxiliary Building, Fuel Building and l
Containment Building.
l On 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 application to release these lands, combining the previous two applications into one application and revising the presentation of the characterization data and results. Statistical analyses were presented to demonstrate that the residual activity, if any, in these lands is indistinguishable from background. On November 19, 2001, Maine Yankee supplemented its combined application, making certain clarifications including land survey information. The NRC granted this request for the release of these lands in July 2002. See Section 1.4.2.
3.1.3 Decontamination & Dismantlement Process Summary Decontamination & dismantlement activities will be supported by detailed project planning 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.
Systems and components removed and released from the secondary side of the plant for commercial disposal are surveyed in accordance with plant procedures based upon a no
MYAPC License Termination Plan Page 3-4 Revision 4 February 28, 2005 1 In accordance with NRC Circular 81-07 and IE Information Notice No. 85-92 l
detectible radioactivity standard. The controlling procedure specifies that the instrumentation must be capable of detecting beta/gamma (and alpha if suspected) radioactivity1 at or below the levels listed below:
a.
Total surface beta/gamma contamination @5000 dpm/100 cm2 b.
Loose surface beta/gamma contamination @1000dpm/100 cm2 l
c.
Fixed alpha contamination @100 dpm/100 cm2 d.
Loose surface alpha contamination @ 20 dpm/100 cm2 e.
Gamma dose rates of 10 micro rem/hr This procedure requires that material be evaluated for probability of radioactive l
contamination by utilizing knowledge of process which may include review of surveys, l
the historical site assessment, characterization surveys or other knowledge of material l
history. Survey requirements are increased according to the greater probability for l
contamination. For instance, materials with no probability for contamination are subject l
to an aggregate dose rate survey and a validation survey which includes a truck monitor l
or acceptable alternative. Materials with a low probability for contamination are subject l
to a biased direct frisk (typically approx. 10% of surface area) and loose surface l
contamination survey prior to packaging as well as the above requirements for aggregate l
and validation survey following packaging. Materials with a high probability for l
contamination are subject to the above requirements for low probability materials l
however the entire accessible surface area of the materials are subject to a direct frisk l
prior to packaging. Additional or alternative survey requirements are also specified for l
special situations including volumetric materials, difficult to survey items, systems or l
components and samples.
l A separate procedure has been implemented with the same detection levels, augmented by 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 water washing 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, a comprehensive 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:
MYAPC License Termination Plan Page 3-5 Revision 4 February 28, 2005 Phase 1:
Prepare Site & Release Non-Impacted Areas Phase 2:
Dismantle Commodities & Decontaminate Structures Phase 3:
Demolish Buildings & Restore Site Phase 4:
Establish Independent Spent Fuel Storage Installation (ISFSI)
These 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 Areas The preparations period began with permanent plant closure on August 7, 1997.
This phase involved the demolition of miscellaneous tanks, buildings, fences and vehicle 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 Structures Commodities are dismantled and removed during this phase. Following commodity removal, 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 Site During this phase, structures will be demolished to an elevation corresponding to three feet 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
MYAPC License Termination Plan Page 3-6 Revision 4 February 28, 2005 below grade. Other buildings are designated for either industrial reuse, recycling, or offsite disposal; and are dispositioned accordingly.
Activated portions of remaining foundations above the Activated Concrete DCGLs will be removed.
Several options exist for sequencing building demolition activities with FSS. These demolition 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 status survey will be performed on the basement surfaces before fill material is placed and on the remaining building footprint after fill material is placed. The status of dismantlement, remediation and FSS activities will be frequently communicated to state and NRC authorities to ensure adequate time for confirmatory measurements, if necessary, prior to the basement being filled. Listed below are some options for sequencing building demolition activities with FSS.
Option 1 Complete Building Demolition prior to FSS:
Will require special attention to keeping the elements (weather) out of the basement during FSS and confirmatory measurements Option 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 3 Building 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 to perform confirmatory measurements.
Fill basement areas with soil fill material.
Complete the demolition of the building down to the 17 ft.
elevation.
Perform confirmatory measurements on the surface of the l
soil fill material after super structure demolition.
This option would require actions to:
Keep the elements out of foundation area which do not have a 21 ft floor (e.g. SFP portion of the Fuel Building).
Prevent recontamination pathways to the basement during
MYAPC License Termination Plan Page 3-7 Revision 4 February 28, 2005 above 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 during this Phase. Maine Yankees 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 the ISFSI, 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 an applicability statement to certain technical specifications that describe requirements associated with the spent fuel pool. This license amendment has been approved prior to demolition of the spent fuel pool.
3.2 Remaining Dismantlement Activities The purpose of this section of the LTP is to indicate each dismantlement activity which remains 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.
3.2.1 Major Decommissioning Activities 10 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.
MYAPC License Termination Plan Page 3-8 Revision 4 February 28, 2005 Those activities are summarized as follows:
a.
Removal of the steam generators and the pressurizer. The external surfaces 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 with the 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 the core 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 the core shroud) are stored on site for later transport with the spent fuel to a 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 reactor vessel, and place the segments into shielded containers.
g.
Segment the RCS and other large-bore piping, decontaminate to acceptable 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.
h.
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 fuel facility 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
MYAPC License Termination Plan Page 3-9 Revision 4 February 28, 2005 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 containment building and stored for later shipment. The reactor vessel was loaded into a l
transport/disposal container (DOT approved). The vessel and its container were l
moved onto a sea-going barge and transported via the Atlantic Ocean, Intercoastal Waterway, then up the Savannah River where it was offloaded at the Savannah l
River Site. After barge offloading, the vessel package was transported overland l
for disposal at the GTS DURATEK low level radioactive waste disposal facility, near Barnwell, South Carolina. These activities were coordinated with the State l
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.
3.2.2 Dismantlement Activity Schedule In relation to plant commodities and internal structures, the projects approach to dismantlement 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.
NSSS component removal should be completed approximately three and one half years 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 and GTCC waste storage) will be decontaminated, as necessary, and dismantled after USDOE has removed the stored materials.
MYAPC License Termination Plan Page 3-10 Revision 4 February 28, 2005 Table 3-1 Major 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) 2002 Spray Building Steam and Valve House Primary Vent Stack 115 KV yard limited (Switchyard remains) 2003 Emergency Feedwater Spent fuel pool (limited)
Boron waste storage tank (BWST)
Primary water system Fire protection system limited Spent fuel pool
MYAPC License Termination Plan Page 3-11 Revision 4 February 28, 2005 Table 3-1 Major MY Area/Systems, Structures, and Components Removed (By Year)
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 required The remaining decommissioning schedule represented in Table 3-2 will be revised during 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 surveys indicate that the structures can be released for unrestricted access and conventional demolition. By the Winter of 2002, after the fuel is transferred to the ISFSI, the SFP and its supporting systems are scheduled for D&D.
Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date TG0102-2 TG01 Demo Main Generator 2Q 01 Z-0139 SBHP HP Checkpoint / Chem Lab Commodity Ripout 2Q 01 Z-0141 SB01 SBP Service Building Proper 2Q 01
MYAPC License Termination Plan Page 3-12 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date SPRB01-8 HV7 HV-7 & 9 Room Commodity Ripout 2Q 01 0194X P21E P21E - PAB El 21' Evap Cubicle Segment EV-2 2Q 01 PULG01-1 PULG PAB 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 01 PULG01-4 PULG PAB 36' - Boric Acid Storage Tank Demolition 2Q 01 0130 SPRB Spray Building Commodity Ripout 2Q 01 PUDD01-1 PUDD Remove Block Wall from Decay Drum Cube Opening 2Q 01 SPRB01-10 SPRB Spray Pump Rebuild Room Commodity Removal 2Q 01 PUDDO1-3 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 0144X CB14 SIT #2 Cut-Up 2Q 01 PUDD01-7 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 PH Personnel Hatch Area Commodity Ripout 3Q 01 TB0006-7 TB00 Turb. Bldg. - Galbestos Siding Removal 3Q 01
MYAPC License Termination Plan Page 3-13 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date 0141X CB14 Regen HX Commodity Removal 3Q 01 CB11 Demo RCP #1 Pump Pedestal 3Q 01 PUDD01-2 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 Z-0157P RMCC Reactor MCC Room Commodity Removal 3Q 01 CB1201-7 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
MYAPC License Termination Plan Page 3-14 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date 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 Pedestal 4Q 01 TB0006-22 TB00 Turbine Building Demo (Ph I - Excl. North Wall) 4Q 01 Z-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 Retaining Walls 4Q 01 0226 TK33 Remove CWPH Ferrous Sulfate Storage Tk (TK-
- 33) 4Q 01 CW0006-2 CCW1 Circ Water Pump Shaft Backfill 4Q 01
MYAPC License Termination Plan Page 3-15 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date CW0006-9 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 TB0006BG TB00 Turb Bldg Foundation Subgrade Demo 4Q 01 Z-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 02 0153 CCG1 CTMT 46' Charging Floor Commodity 1Q 02 0150 CB32 CTMT Upender - Remove Commodities/Cut Liners 1Q 02 CB3301-3 CCOA Remove CTMT 46' Outer Annulus Jib Crane 1Q 02 0156 CPLE Remove CTMT Elevator Room Commodities 1 1Q 02 P21L01-5 P21L P21L - PAB El 21' Remove Monorail 1Q 02
MYAPC License Termination Plan Page 3-16 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date CB3301-2 CCOA Remove CTMT 46' Outer Annulus Monorail 1Q 02 Z-0337 YDPH MPH - Montsweag - Remove Commodities &
Backfill 1Q 02 Z-0397 345K Electrical Tower Demolition (B Parking Lot) 1Q 02 CCOAF 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 02 CB18F CB18 CTMT EL -2' OA Final Ripout 2Q 02 0726S DWST DWST -Subgrade Foundation Demolition 2Q 02 0731 X MSGH Demo Gas House Foundation 2Q 02 SBTTBF SBTT SBTT Subgrade Foundation Demo Backfill 2Q 02 0727S RWST RWST/SCAT Tank Subgrade Foundation Demo 2Q 02 DWSTBF DWST DWST Subgrade Foundation Demo Backfill 2Q 02 GHBF MSGH Gas House Foundation Backfill 2Q 02 PP-4 RWST RWST/SCAT Foundation Packaging/Processing C&D 2Q 02 RWSTBF RWST RWST/SCAT Subgrade Foundation Demo Backfill 2Q 02 0569 SPRB Spray Building Demolition 2Q 02 SBFD SBF Softball Field Demolition (Dugouts & Fencing) 2Q 02 SPRAY CCG1 Remove CTMT Spray Rings 2Q 02 0719 YDBG Barge Slip / Road Demolition 2Q 02
MYAPC License Termination Plan Page 3-17 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date 0159 CB34 Remove Commodities CTMT Polar Crane (CR-
- 1) 2Q 02 Z-0156 SVH1 Steam Valve House Demolition (Above Grade) 2Q 02 CB2101F 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 PUFN01-3 PUFN PAB El 36' Fan FN-1B Removal 3Q 02 PAB11FR PA00 PAB 11' Final Ripout 3Q 02 HV7DEMOS HV7 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 02 Z-0197S AD00 Admin Bldg / Gatehouse Subgrade Demo 4Q 02
MYAPC License Termination Plan Page 3-18 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date LSACOM 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 02 PAB21FR PA00 PAB 21' Final Ripout 4Q 02 TB0006-22X TB00 Turbine Building Demo (Ph II North Wall) 4Q 02 0215 PABR PAB Roof Area Commodity Removal 4Q 02 0728 WART Wart Building Demolition (Above Grade) 4Q 02 PUFN01-5 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 02 0253 SFP2 Spent Fuel Pool Area Commodity Removal 4Q 02 MYM16 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
MYAPC License Termination Plan Page 3-19 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date 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 PT001 SFP6 RCA Pipe Tunnel Commodity Removal 4Q 02 PAB36FR 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 03 0254 SFP2 Spent Fuel Pool - Cut Liner/Fuel Racks 1Q 03 0222COM 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 FI Forebay/Seal Pit Demolition 1Q 03 MYM11 PA00 PAB Structure Demolition Complete 1Q 03 Z-0172S PA00 Primary Aux Bldg Subgrade Demolition 1Q 03
MYAPC License Termination Plan Page 3-20 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date 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 Subgrade Demolition 1Q 03 0235 BWST BWST Berm Demolition 2Q 03 0515 BWST BWST Tank & Commodity Ripout 2Q 03 0235S BWST BWST Subgrade Demolition 2Q 03 0233 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/Processing C&D 2Q 03 PP-16 PWST PWST Demolition Packaging/Processing C&D 2Q 03 PWSTBF 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 0228 DIFF Diffuser Piping Demolition 2Q 03 Z-0347XS MSW4 MSW4 - Warehouse #4 Subgrade Demolition 2Q 03 Z-0347X1 MSW2 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 03 Z-0367 MSIC Information Center Demolition 3Q 03
MYAPC License Termination Plan Page 3-21 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date Z-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 Foundation Demolition 3Q 03 0224 FPH1 Fire Pump House Commodities 3Q 03 0717 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 03 Z-0069S STFB Staff Building & Tunnel Demo (Subgrade) 4Q 03 Z-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 03
MYAPC License Termination Plan Page 3-22 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date Z-0437S SEAL SEAL - Seal Pit Outfall Demolition (Below Grade) 4Q 03 Z-0297 YARD FPHS - Fire Protection Hose/STA/Hydrants Demo 4Q 03 0257 SF00 SFP / RCA Building Demolition 1Q 04 Forebay Sediment Assessment/Remediation 1Q 04 MYM13 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 04 0591 Final Doc. Submittal to NRC 2Q 04 0287 Decommissioning Complete / Non ISFSI Land Released 3Q 04 ISFSI 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, etc 2026**
Final Facility Site Survey 2026**
Release of the Facility Site for unrestricted use 2026**
MYAPC License Termination Plan Page 3-23 Revision 4 February 28, 2005 Table 3-2 Area of Activity & Decommissioning Activities Schedule (Arranged Chronologically)
Activity Number Activity Description Completion Date Termination of Maine Yankee Atomic Power Companys Part 50 License 2026**
- Projected date for DOE to have taken possession and removed stored materials.
3.2.3 Material Removal Sequence Removal sequence may be dictated by access and material handling restrictions or by 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 be sectioned 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 the containment 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 transport systems. 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
MYAPC License Termination Plan Page 3-24 Revision 4 February 28, 2005 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 ton auxiliary hook) b.
Fuel Building Overhead Crane; c.
Equipment Room Monorails; and d.
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 and regulations. 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 inside the 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 temporary or 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.
3.2.4 Final State-of-the-Site Description The purpose of this section is to present a conceptual description of the site following 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,
MYAPC License Termination Plan Page 3-25 Revision 4 February 28, 2005 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 remaining basement foundations will be filled with a soil fill material following any required remediation and FSS activities.
The former Low Level Waste Storage Building [now the ISFSI Security Operations 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 Building These buildings will be demolished to three feet below grade. Concrete duct banks, 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.
MYAPC License Termination Plan Page 3-26 Revision 4 February 28, 2005 Containment, Primary Auxiliary Building, Fuel Building and Containment Spray Building These 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 amounts of lead and/or PCBs. This paint will be removed prior to final status survey. 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 Radiation Bunker, Main Steam and Valve House, Emergency Feedwater Pump Room, LSA Building, 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. Building footings and foundations may remain.
Circulating Water Pump House The Circulating Water Pumphouse (CWPH) will be demolished (demolish concrete 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 Plant The Sewage Treatment Plant inlet pipes (coming from the TB/SB) will be removed, with outlet piping inspected, decontaminated (if required) and left buried, prior to building demolition to 3 feet below grade.
MYAPC License Termination Plan Page 3-27 Revision 4 February 28, 2005 Foundations associated with Tanks, Guard Towers, Meteorological Towers, Yard Crane Footings, Vehicle Barriers, Transformers and Above Grade Structures including: Warehouse 2/3, 4 and 5, Administrative Building (Front Office),
Gatehouse, Staff Building, Collection Center, Information Center The meteorological tower will be dismantled and removed. The concrete footings and attached guide lines will be removed to three feet below grade and the area backfilled. 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 Piping Buried fire protection and raw water piping will be left in place. The CW and portions 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 Sidestorm 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 regarding the NRPA process)
Maine Yankee evaluated the final disposition of the Forebay, seal pit, and diffuser l
piping. As part of a NRPA process, Maine Yankee analyzed remedial options and l
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 evaluated l
included: (1) leave in place as exists; (2) secure and leave in place; (3) partial l
removal and; (4) complete removal. The types of impact that will be considered in the analyses include environmental impacts (water quality, marine wetlands,
MYAPC License Termination Plan Page 3-28 Revision 4 February 28, 2005 freshwater wetlands and land use), ecological impacts including flora, fauna and marine resources, and impacts on natural resources and navigation. The evaluation addressed the following options:
l Diffuser Pipe, Foxbird Island - onshore below grade. Options include capping and leaving in place or removal, backfill and restoration to existing grade/conditions.
Diffuser Pipe, Mudflats - below the sediment/water interface. Options include capping and leaving in place or removal, backfill and restoration of the tidal flats.
Diffuser Pipe, Offshore above the sediment/water interface. The first option involves 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 were left in l
place.
Forebay. All options involved demolishing the seal pit and removal of concrete l
down 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 included removal of l
the west bank of the Forebay to re-establish tidal flow. The second option involved leaving the west bank of the Forebay in place, cutting down berms to l
above the high water elevation, and using this material as fill for the forebay. The third option involved leaving the berms in their present configuration.
l Fire Pump House and Fire Pond This pond existed solely for the purpose of holding water supplied from Montsweag 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 systems
MYAPC License Termination Plan Page 3-29 Revision 4 February 28, 2005 The Bailey farm house, barn and well water structure will be demolished to three feet 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 restrictive covenants against excavating basements, drilling wells for drinking or irrigation water, or residential construction.
Independent Spent Fuel Storage Installation (ISFSI)
After the DOE transports all the stored spent fuel and GTCC wastes from the ISFSI, 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 Dismantlement 3.3.1 Decontamination of Systems and Components Systems and components removed and released from the secondary side of the plant 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 reduce contamination 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 liquid inadvertently 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;
MYAPC License Termination Plan Page 3-30 Revision 4 February 28, 2005 b.
Sludge removed from the tank is stabilized prior to shipment in conjunction with the Maine Yankee Process Control Program (PCP); and c.
Wastewater will be processed and analyzed before being discharged.
3.3.2 Dismantlement of Systems and Components Dismantlement methods can be divided into two basic types: non-destructive means 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 (usually submerged 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. Other dismantlement 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:
MYAPC License Termination Plan Page 3-31 Revision 4 February 28, 2005 a.
Areas within the Restricted Area (RA) of the plant Systems and components will be removed from each area of the building/structure/yard, packaged, and either transported to an
MYAPC License Termination Plan Page 3-32 Revision 4 February 28, 2005 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 internal system contamination.
Systems and components identified during the site characterization and 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.
3.3.3 Decontamination 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 are implemented 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 DCGL and 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.
MYAPC License Termination Plan Page 3-33 Revision 4 February 28, 2005 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).
The removal of concrete consisting of the upper 1 or 2 feet of a thick slab such 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 used for 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 Be Demolished (located higher than three feet below grade)
Contaminated concrete structures above three feet below grade may not be completely 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 Grade Concrete 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 Segmentation Most metallic wastes will not be decontaminated on site. Sponge blasting using various media ranging from non-aggressive for surface cleaning to
MYAPC License Termination Plan Page 3-34 Revision 4 February 28, 2005 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.
Internal building steel within the RA will be dismantled, packaged, and shipped 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 been exposed 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. Buried pipe 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, and decontamination 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.
MYAPC License Termination Plan Page 3-35 Revision 4 February 28, 2005 Areas with activity above DCGL values will be remediated.
3.3.4 Building Demolition and Site Restoration Table 3-3 describes the structures and facilities within the scope of the decommissioning along with the condition of release and final configuration.
Table 3-3 Structures and Facilities Within the Scope of Work for Demolition Building or area description Condition of release Final configuration of structure Containment building 1
Demo. 3 ft below grade; backfill Steam and valve house 1
Demo. 3 ft below grade; backfill Spray building 1
Demo. 3 ft below grade; backfill Containment equipment hatch outer 1
Demo.
Containment personal hatch outer 1
Demo.
LSA building 1
Demo. 3 ft below grade; backfill Reactor MCC room 1
Demo. 3 ft below grade; backfill Emergency feed pump room 1
Demo. 3 ft below grade; backfill Primary auxiliary building 1
Demo. 3 ft below grade; backfill Fuel building 1
Demo. 3 ft below grade; backfill RA building 1
Demo. 3 ft below grade; backfill Service building - hot side 1
Demo. 3 ft below grade; backfill Service building test tanks (TK-14A/B) 1 Complete demo.; remove pads; backfill Demin. water storage tank (TK-21) 1 Complete demo.; remove pads; backfill Primary water storage tank (TK-16) 1 Complete demo.; remove pads; backfill Boron water storage tank (TK-13 A/B) 1 Complete demo.; remove pads; backfill Refueling water storage tank (TK-4
& TK-54) and greenhouse 1
Complete demo.; remove pads; backfill
MYAPC License Termination Plan Page 3-36 Revision 4 February 28, 2005 Table 3-3 Structures and Facilities Within the Scope of Work for Demolition Building or area description Condition of release Final configuration of structure Offgas stack 1
Complete demolition Aux boiler stack 1
Complete demolition High radiation bunker 1
Demo. 3 ft below grade; backfill Turbine building 2
Demo. 3 ft below grade; backfill WART/I&C building 2
Complete demolition; backfill LLWB - Low level waste building 2
Complete demolition; backfill FI - Foxbird island TBD To Be Determined (TBD) based on alternatives analysis Security/Gatehouse building 3
Demo. 3 ft below grade; backfill Administration building 3
Demo. 3 ft below grade; backfill Fuel oil bunker 3
Demo. 3 ft below grade; backfill Gas house 3
Complete demolition; backfill Circ water pump house 3
Demo.West wall down to 3 ft below grade (17' elevation) and East wall to -3 ft elevation; backfill and add rip rap Temporary power shack - West of fuel building 3
Complete demolition; backfill Modular office buildings (2) 3 Complete demolition 8 Sided storage building 3
Complete demolition Test pit 3
Complete demolition; backfill West - area West of the containment Building including (3) guard towers 3
Complete demolition; backfill Condensate storage tank (concrete pad only) 3 Demo. 3 ft below grade; backfill Transformer including elect tower and concrete structures/pad see below see below
MYAPC License Termination Plan Page 3-37 Revision 4 February 28, 2005 Table 3-3 Structures and Facilities Within the Scope of Work for Demolition Building or area description Condition of release Final configuration of structure
- 1. X-IA 3
Remove transformer for disposition; demo. pads; backfill
- 2. X-IB 3
Remove transformer for disposition; demo. pads; backfill
- 3. X-24 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 4. X-26 3
Remove transformer for disposition; demo. 3 ft below grade ; backfill
- 5. X-28 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 6. X-IS 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 7. X-14 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 8. X-16 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 9. X-16A 3
Remove transformer for disposition; demo. 3 ft below grade; backfill
- 10. X-16B 3
Remove transformer for disposition; demo. 3 ft below grade; backfill Temp generator/transformer/pagoda (cold & dark equipment) 2 Remove transformer for disposition; demo. pagoda Outside protected area STPI - Sewage treatment plant 3
Demo. 3 ft below grade; backfill Lift station 3
Demo. 3 ft below grade; backfill Information center bldg (including concrete pad and blocks 4 ft x 4 ft x 4 ft) 3 Demo. 3 ft below grade; backfill
MYAPC License Termination Plan Page 3-38 Revision 4 February 28, 2005 Table 3-3 Structures and Facilities Within the Scope of Work for Demolition Building or area description Condition of release Final configuration of structure Collection site 3
Demo. 3 ft below grade; backfill Staff building/staff tunnel 3
Demo. 3 ft below grade; backfill Annex - WHSE 4 3
Complete demolition; backfill WHSE 2 & 3 - warehouse 3
Demo. 3 ft below grade; backfill WHSE 5 - warehouse 3
Complete demolition; backfill FPH - fire pump house/retention pond 3
Demo.; level; backfill Seal pit (outfall)
TBD To Be Determined (TBD) based on Alternatives Analysis Barge slip area 3
grade area adjacent to slip Pre-fab building (generator) and yard 3
Complete demolition; backfill ELECT towers (inside industrial area) 3 Demo. towers and pads; backfill Railroad cars (4) - includes track spur from fuel bldg to the property line 3
Demo. rail cars; remove rails to location designated; grade Well water house 3
Demo. to 3 ft below grade; backfill MET tower and equip. inside fenced area 3
Demo. 3 ft below grade; backfill Electrical fence (around radio tower area) 3 Complete demolition; backfill Concrete blocks - 4ft x 4ft x4ft Vehicle barriers 3
Remove initially and store for use; then demo.
Remove outside utilities - 3 ft below grade
- 1. Potable water 3
Demo. 3 ft below grade; backfill
MYAPC License Termination Plan Page 3-39 Revision 4 February 28, 2005 Table 3-3 Structures and Facilities Within the Scope of Work for Demolition Building or area description Condition of release Final configuration of structure 2
Clean rebar has no detectable, plant-derived radioactivity associated with it. Rebar will be surveyed in accordance with free release criteria and disposed of as scrap. If activated rebar is discovered it will be disposed of as radwaste.
- 2. Utility light poles 3
Demo. 3 ft below grade; backfill
- 3. Fire hydrant hose stations 3
Demo. 3 ft below grade; backfill
- 4. Sanitary lines 3
Demo. 3 ft below grade; backfill Notes:
a.
Number 1 denotes that the bldg/area will undergo decontamination and the commodities will 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 for building demolition.
Property, structures and facilities will be demolished to a level three feet below present 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 elevations below 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.
e.
Demolish the building structure to 3 feet below grade. Separate the clean2 rebar from the concrete.
f.
Prepare the demolished concrete for shipment offsite.
g.
Release rebar using established radiological release procedures and ship rebar to metal recycling contractor.
MYAPC License Termination Plan Page 3-40 Revision 4 February 28, 2005 The structures specified as Condition of Release 2 in Table 3-3, are those that are on 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, commodities identified 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 release criteria.
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 in Table 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).
Therefore, buildings, structures, and facilities identified as Condition of Release 3 in 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.
MYAPC License Termination Plan Page 3-41 Revision 4 February 28, 2005 3.4 Evaluation of Dismantlement Activities 3.4.1 Systems 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.
3.4.2 System Deactivation SSCs, which are not Important to the Defueled Condition (ITDC), nor required to support 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 to decontamination, 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 applicable chemical safety program. Plant drawings are revised to indicate abandoned/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 system boundary valves. As additional systems are deactivated, existing isolation
MYAPC License Termination Plan Page 3-42 Revision 4 February 28, 2005 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 Yankees procedures Temporary liquid and solid waste processing systems may be used during decommissioning 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 3-4 Status of Major MY Systems, Structures, and Components System/Component/Structure Required for Defueled Condition Status Reactor coolant system NO Removal mostly complete Reactor vessel internals NO Segmentation and Removal complete Reactor vessel NO Removal complete Secondary component cooling water system NO Removal ongoing Potable water system Wiscasset water system YES Preparations for partial removal are ongoing, portion remaining in service to support SFP System and site needs Spent fuel pool and fuel handling equipment YES Preparations for partial removal are ongoing, portion remaining in service to support SFP System Spent fuel pool cooling system YES Will remain in service as long as materials are stored in the SFP Spent fuel pool cooling and demineralizer system YES Will remain in service as long as materials are stored in the SFP Plant effluent system YES Rerouted to support Forebay remediation and dismantlement Containment ventilation systems YES Preparations for removal are ongoing as portions of system are no longer required to support decommissioning or SFP
MYAPC License Termination Plan Page 3-43 Revision 4 February 28, 2005 Table 3-4 Status of Major MY Systems, Structures, and Components System/Component/Structure Required for Defueled Condition Status Fuel building ventilation systems YES Will remain in service as long as materials are stored in the SFP Instrument and service air systems NO Preparations for removal of Components not required for support of spent fuel pool are ongoing.
Solid radioactive waste system YES Will remain in service as long as materials are stored in the SFP, and support decommissioning activities after removal of SFP contents.
Liquid radioactive waste system YES Will remain in service as long as materials are stored in the containment Building, Auxiliary Building, or SFP, and support decommissioning activities after removal of SFP contents.
Radiation monitoring system YES Preparations for partial removal of Components not required for support of spent fuel pool are ongoing Electrical systems YES Preparations for partial removal of Components not required for support of spent fuel pool are ongoing in Accordance with decommissioning Fire protection systems YES Preparations 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 building NO Preparations for removal are ongoing.
Impact on fuel transfer canal minimized through redesign
MYAPC License Termination Plan Page 3-44 Revision 4 February 28, 2005 Table 3-4 Status of Major MY Systems, Structures, and Components System/Component/Structure Required for Defueled Condition Status Auxiliary building YES Preparations for partial removal of components not required for support of spent fuel pool are ongoing in accordance with decommissioning schedule Turbine/generator building (has a wall that supports the SFPI systems)
NO Removal complete except for wall that supports the SFPI systems Low level waste storage building NO Converted over to the Security and Ops bldg for ISFSI 3.4.3 Nuclear Safety and Regulatory Considerations The following general considerations, as applicable, will continue to be incorporated 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 under a general Part 72 license. Work packages are implemented in accordance with 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 the ISFSI, Maine Yankee will dismantle and demolish the spent fuel pool. Maine Yankee submitted a license amendment, pursuant to 10 CFR 50.90, to add an applicability statement to certain technical specifications that describe requirements associated with the spent fuel pool. On February 6, 2002, this license amendment was approved.
Dismantlement activities will be conducted to ensure the safe storage of spent fuel and to protect the public health and safety as well as the common defense and security. Maine Yankees Quality Assurance Program (QAP) defines the mechanical SSCs in Table 3-5 as safety related.
MYAPC License Termination Plan Page 3-45 Revision 4 February 28, 2005 Table 3-5 Safety Related Mechanical Components Component Safety Class Spent fuel pool cooling loop suction piping (from the pool wall up to and including the siphon protection) 3 Fuel transfer tube 3
Blind flange on containment side of fuel transfer tube 3
Valve FP-21 (transfer tube isolation valve) 3 Other items are identified by the Quality Assurance Program (QAP) as requiring a degree 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 B to the Maine Yankee Quality Assurance Program.
3.5 Radiological Impacts of Decontamination and Dismantlement Activities 3.5.1 Waste Characterization The MY Decommissioning Project Waste Management Plan includes waste disposal 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.
3.5.2 Radioactive 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 Yankees 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 Plan Page 3-46 Revision 4 February 28, 2005 Table 3-6 Nuclides Checked for by 10 CFR61 Analysis Nuclide Principal Emissioni Nuclide Principal Emissioni Nuclide Principal Emissioni Ag-110m gamma Zr-93 beta
- Nb-94 (in activated metal -
C-14, Ni-59, Ni-63) gamma Am-241 alpha Sn-126 beta
+Kr-85 gamma C-14 beta Iso-U alpha
- Cr-51 gamma Cm-242 alpha K-40 gamma
- Fe-59 gamma Cm-243/244 alpha Zn-65 gamma
- Nb-95 gamma Co-57 gamma Eu-154 gamma
- Zr-95 gamma Eu-155 gamma
- Mo-99 gamma Co-60 gamma Eu-152 gamma
- I-131 gamma Cs-134 gamma Tl-208 gamma
- Xe-133 gamma Cs-137 gamma Bi-212 gamma
- Ba-140 gamma Fe-55 ec Pb-212 gamma
- La-140 gamma H-3 beta Bi-214 gamma
- Ce-141 gamma Mn-54 gamma Pb-214 gamma
- Sn-113 gamma Ni-59 ec Ra-226 gamma
- Sb-124 gamma Ni-63 beta Ac-228 gamma
- Ru-103 gamma Pu-238 alpha Pa-234m gamma
- Co-58 gamma Pu-239/240 alpha Th-234 gamma Pu-241 beta U-235 gamma Sb-125 gamma Be-7 gamma Sr-90 beta Ce-144 gamma
- Tc-99 beta Sb-126 gamma
- +I-129 beta Sn-126 gamma iAnalysis performed measuring this principal emission
- for waste classification
- for Rx pwr operations (short lived) + in spent fuel
MYAPC License Termination Plan Page 3-47 Revision 4 February 28, 2005 Table 3-7 10 CFR61 Sample Analysis Results (Typical)
These values are shown to present relative fractions of nuclides historically present.
RESIN LIQUID SMEAR CAVITY DRAIN UPENDER
- 3 SG SAMPLE FILTERS ACTIVITY DOWN FILTER SMEAR BOWL l
µCi/g
µCi/sample
µCi/sample
µCi/sample
µCi/sample
µCi/sample 8/21/96 9/4/96 6/18/97 ACTIVITY ACTIVITY SMEAR 7/23/96 6/10/98 ACTIVITY NUCLIDE 3/28/98 H-3 2.00E-01 1.86E-02 1.40E-01 15500 C-14 8.51E-02 4270 Mn-54 8.01E-01 1.63E-03 1.00E-02 1.00E-03 1260 Fe-55 9.81E+00 7.49E-01 2.46E-01 2.58E-01 4.33E-02 160000 Co-57 2.07E-02 2.37E-04 4.79E-04 Co-58 7.70E-02 4.15E-02 674 Co-60 9.68E+00 1.64E+00 4.48E-01 3.61E-01 1.14E-01 147000 Ni-59 1.04E-01 Ni-63 1.42E+01 1.40E+00 3.34E-01 8.97E-02 3.86E-02 18700 Zn-65 Sr-90 2.38E-01 2.74E-02 370 Zr-93 Nb-94 Tc-99 6920 Ag-110m 1.37E-03 Sb-125 2.72E-01 2.62E-03 5.81E-03 1.61E-03 2.95E-03 2110 Sn-126 I-129 Cs-134 2.00E+01 5.54E-03 Cs-137 3.72E+01 3.35E-03 8.06E-02 1.03E-02 Ce-144 2.45E-03 Eu-152 Eu-154 Eu-155 U-234 U-235 U-238 Pu-238 6.67E-04 1.53E-04 1.45E-05 1.83E-04 1.20E-05 6.9 Pu-239/240 2.79E-04 1.91E-04 2.24E-05 6.02E-04 1.53E-05 5.3 Pu-241 2.05E-02 1.65E-02 1.98E-03 2.32E-02 9.60E-04 315 Am-241 3.56E-04 2.71E-04 3.00E-05 2.77E-04 1.55E-05 3.4 Cm-242 1.64E-04 3.21E-06 6.10E-06 Cm-243/244 4.53E-04 2.34E-04 1.19E-05 8.50E-06 1.8
MYAPC License Termination Plan Page 3-48 Revision 4 February 28, 2005 Table 3-8 Projected Activities and Volumes Activity Curies Volume Reactor vessel and internals 2,200,000 Ci 11,500 Cu.Ft.
Large NSSS components Steam Generators Pressurizer 1,600 Ci 27,000 Cu.Ft.
Activated Concrete 390 Ci 23,000 Cu. Ft.
Contaminated Debris (Structural Steel, etc) 0.10 Ci 163,000 Cu. Ft Contaminated Concrete 1.75 Ci 900,000 Cu. Ft.
Radioactive Water 0.5 Ci 850,000 Gallons Soil 0.1 Ci 25,000 Cu. Ft This volume is an estimate, subsurface soil will be sampled and surveyed following commodity removal The Total Estimated Radwaste Volumes Transported and Buried are described in Table 3-9 (reproduction of Table 1 - PMP 9.0 Rev A, Section 6.3). Although the total estimated radwaste volumes exceeds the 18,340 m3 described in NUREG-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 be disposed 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 (from demolition 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 Plan Page 3-49 Revision 4 February 28, 2005 Table 3-9 Total Low-level Waste Volume per Maine Yankee Decommissioning Item Vol ft3 Transportation Mode Disposal/Process Disposal Volume ft3 Reactor Pressure Vessel (RPV) 9,500 Barge Direct Disposal 9,500 Non-GTCC RPV Hardware 1,500 Cask/Truck Direct Disposal 1,500 RPV Head 300 Cask/Truck Direct Disposal 300 Pressurizer 2,200 Barge Processing VR 21.3/1*
100 Reactor Coolant Pumps &
Motors 4,800 Train/Truck Direct Disposal 4,800 Steam Generators 20,000 Barge Processing VR 21.3/1*
940 Radioactive Contaminated Metal 150,000 Truck Processing VR 21.3/1*
7,040 Dry Active Waste (DAW)
Resin 13,000 Truck Processing VR 21.3/1*
610 Liquid Waste Processing 400 Cask/Truck Direct Disposal 400 Spent Fuel Pool Purification Resin 150 Cask/Truck Direct Disposal 150 Pre-Existing Waste 200 Cask/Truck Direct Disposal 200 Contaminated Soil 25,000 Train Direct Disposal 25,000 Radioactive Concrete 900,000 Train Direct Disposal 900,000 Used Oil, Radioactive 270 Truck Processing/
Incineration 0
TOTAL VOLUME SHIPPED 1,127,320 ft3 (31,924 m3 )
[74% increase over NUREG value-18,340 m3]
TOTAL DISPOSAL VOLUME @ a Volume Reduction of 176,770 ft3 950,550 ft3 (26,920 m3)
[47% increase over NUREG value-18,340 m3]
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 Plan Page 3-50 Revision 4 February 28, 2005 Table 3-10 below describes the approach to handling building materials for regulatory release.
Table 3-10 Approach to Handling of Building Materials for Regulatory Release No.
Type of building material Approach 1
Areas with low contamination potential Free-release in accordance with procedures 2
Concrete with medium to high surface contamination potential (at elevations above - 3 feet below grade)
Ship offsite for disposal at Envirocare or Barnwell or an appropriate disposal facility Concrete with medium to high surface contamination potential (at elevations below - 3 feet below grade)
Remediate to acceptance criteria levels and leave in place, with removed material disposal at Envirocare or Barnwell 3
Contaminated metals removed Ship to processor or for disposal at Envirocare or Barnwell Non-contaminated metals removed Ship to processor for scrap or disposal 4
Built-up tar roofing, inner layer of siding (with actual or potential contamination)
Process at LLW treatment facility or directly dispose at Envirocare Clean tar roofing, siding Ship to a processor or disposal 5
Outer layer of siding (Galbestos)
Surface release survey; send to asbestos landfill 6
Refueling cavity and spent fuel pool liners Process at LLW treatment facility 3.5.3 Occupational Exposure The 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.
Table 3-11 lists estimated exposure/area of activity Attachment A at the end of this document provides pictorial reference using the Acronym assigned to the
MYAPC License Termination Plan Page 3-51 Revision 4 February 28, 2005 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 3-11 Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled Area/Activity Title Exposure DC.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 REM DC.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 CB3-2 DC.2.03.01.12 CB3-3 DC.2.03.01.13 CB3-4 CTMT Loop #1 CTMT 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 CTMT 46' Penetration Room CTMT Polar Crane (CR-1) 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 6.078 REM 4.042 REM
MYAPC License Termination Plan Page 3-52 Revision 4 February 28, 2005 Table 3-11 Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled Area/Activity Title Exposure 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 CPLE CTMT Charging Floor CTMT Equip Hatch Outer (PE-3)
CTMT Incore Instrument Sump CTMT Personal Hatch Outer Area CTMT Elevator & Room 3.105 REM 3.871 REM 6.533 REM
.728 REM
.173 REM DC.2.03.02 Primary Auxiliary Bldg 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 PUWG PAB 21' Level Valve Alley PAB 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
.506 REM
.316 REM
.529 REM
.279 REM DC.2.03.04 Service/fuel
MYAPC License Termination Plan Page 3-53 Revision 4 February 28, 2005 Table 3-11 Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled Area/Activity Title Exposure building/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 SVH Demineralizer 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
.046 REM
.314 REM
.044 REM
.293 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.2.03.05.10 RWST/SCAT DC.2.03.05.11 STFB DC.2.03.05.12 STPl DC.2.03.05.13 West - RCA Boron 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 Tanks Staff Building & Tunnel Sewage Treatment Plant RCA Yard Area - West Side
.162 REM
.003 REM
.528 REM
MYAPC License Termination Plan Page 3-54 Revision 4 February 28, 2005 Table 3-11 Estimated Exposure/Area of Activity & Decommissioning Activities Scheduled Area/Activity Title Exposure Total Estimated exposure for the project 937.543 REM 3.5.4 Public Exposure Continued application of Maine Yankees Radiation Protection Program, Waste Management 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.
3.5.5 Expected Radiological Conditions Characterization of concrete within the Restricted Area (RA) of the site shows the following:
1.
Painted concrete has surface contamination up to 1 million dpm/100 cm2 (worst case) which is amenable to surface remediation techniques such as wiping, washing, power washing or abrasive surface removal.
2.
Bare concrete has surface contamination, absorbed contamination and activation 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 activation products 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 generate airborne 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 processes and procedures have proven successful for controlling
MYAPC License Termination Plan Page 3-55 Revision 4 February 28, 2005 decontamination 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 resulting GTCC waste into NAC UMS casks for storage at the ISFSI. This segmentation process used an abrasive water jet. Special precautions were taken to capture the residue (SWARF) resulting from this segmentation.
3.5.6 Contamination Control Due to the large scope of the D&D and the need for some FSS activities to be performed 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 training b.
Installation of barriers to control access to surveyed areas c.
Installation of barriers to prevent the migration of contamination from adjacent overhead areas d.
Installation of postings requiring personnel to perform contamination monitoring prior to surveyed area access e.
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 routine survey 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 Controls Airborne radioactive particulate emissions will continue to be filtered, and effluent discharges sampled/monitored and quantified. Consideration is given to the following items:
MYAPC License Termination Plan Page 3-56 Revision 4 February 28, 2005 a.
Operation of the appropriate portions of the containment ventilation 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 building ventilation system, as required.
c.
Operation of the appropriate portion of the fuel building ventilation system 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 to result 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 be applied 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 Control Work activities are planned to minimize the spread of contamination. Liquids are contained 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 confine internal 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 other walls, ceiling, or floors may be removed to permit removal of systems and components.);
MYAPC License Termination Plan Page 3-57 Revision 4 February 28, 2005 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 to facilitate packaging of components removed in large pieces; and g.
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.)
3.6 Coordination with Other Regulatory Agencies The decommissioning and termination of Maine Yankees 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.
3.6.1 Regulatory Agencies The following federal, state and local agencies have some level of involvement in Maine Yankees 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.
b.
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.
The 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
MYAPC License Termination Plan Page 3-58 Revision 4 February 28, 2005 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 Discharge Elimination 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 EPAs behalf. MDEP has issued a new discharge license to Maine Yankee c.
US Department of Transportation ( DOT) - The DOT regulates the packaging, 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.
d.
US Coast Guard - The Coast Guard has authority to control vessel traffic in 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.
e.
US Department of Energy (DOE) - The DOE has a contractual obligation to take receipt and dispose of Maine Yankees GTCC waste and spent nuclear fuel.
f.
Maine Department of Environmental Protection (MDEP) - The MDEP is the 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 resources including coastal and freshwater wetlands. These aspects are discussed in more detail in Section 8.6.
MYAPC License Termination Plan Page 3-59 Revision 4 February 28, 2005 g.
Maine Department of Human Services - The Department of Human Services 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.
h.
Maine Department of Inland Fisheries and Wildlife (IF&W) - IF&W does not 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.
i.
Maine Department of Marine Resources (DMR) - DMR does not directly regulate activities at Maine Yankee. However DMR does provides technical support to MDEP on projects involving potential impacts to coastal wetlands.
j.
Maine Department of Transportation (MDOT) - MDOT has permitting authority 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.
k.
Maine Historic Preservation Commission - Maine Yankee has coordinated with 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.
l.
Town of Wiscasset (Town) - The Town has permitting authority over new development 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.
m.
The Maine Turnpike Authority-has a long standing agreement that placarded shipments of LLW will only travel on the Turnpike during daylight hours.
n.
The Maine State Police-are given a courtesy call before each LLW shipment leaves the site. This is not an official requirement.
3.6.2 Advisory and Community Entities
MYAPC License Termination Plan Page 3-60 Revision 4 February 28, 2005 a.
The State Nuclear Safety Advisor responsibilities include advising the Governor 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 of four 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 and Decommissioning 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 Nuclear Pollution 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.
3.6.3 Environmental and Regulatory Issues Section 8.6 of the LTP provides a detailed discussion of how non-radiological environmental and regulatory issues associated with decommissioning are being addressed with the cognizant state and federal agencies having jurisdiction over those issues.
MYAPC License Termination Plan Page 3-61 Revision 4 February 28, 2005 3.7 References 3.7.1 NUREG-1700, Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans 3.7.2 NRC Regulatory Guide 1.179, Standard Format and Content of License Termination Plans for Nuclear Power Reactors (January 1999) 3.7.3 Post Shutdown Decommissioning Activities Report 3.7.4 Characterization Survey Report for the Maine Yankee Atomic Power Plant, Volumes 1-8, 1998 GTS Duratek 3.7.5 Site History Report, Stone and Webster Environmental Technology and Services (November 1999), transmitted via James T. Kilbreth letter to Joan Jones, State of Maine, dated November 16, 1999 3.7.6 Kim Tripp, US Fish and Wildlife Services, letter to David Asherman, dated July 21, 1999, regarding federally listed species.
3.7.7 NRC letter to Maine Yankee, dated July 30, 2002, Issuance of Amendment No. 167, license amendment approving partial release of site lands
MYAPC License Termination Plan Revision 3 October 15, 2002 ATTACHMENT 3A Drawings Associated with Specific Decommissioning Tasks These drawings are provided For Information Only to support the readers understanding and correlation of decommissioning tasks, anticipated radiation exposure, and physical locations involved in the subject tasks. A Page 1 of 33
MYAPC License Termination Plan Revision 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 Room RMCC RMCC RMCC 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 Elevation SFP02 SFP04 SFPV A Page 2 of 33
MYAPC License Termination Plan Revision 3 October 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 2nd Floor General Area SBP Figure 3-25 Service Building 39 Elevation SB05 SB07 SB08 Figure 3-26 Cable Vault Room 49 Elevation SB09 SB10 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 A Page 3 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Containment Building
-2' Elevation General Area Containment Building
-2' Elevation General Area Figure 3-1 Figure 3-1 RCP Platform RCP Platform
- 1 S/G Platform
- 2 S/G Platform
- 3 S/G Platform
- 3 S/G Platform
- 1 SIT
- 1 SIT
- 2 SIT
- 2 SIT ELEVATOR ELEVATOR
- 3 SIT
- 3 SIT CB-17 CB-17 CB-13 CB-13 CB-16 CB-16 CB-18 CB-18 CB-14 CB-14 CB-11 CB-11 P
Q TA Z
U N
R E
K NCH P
Q TA Z
U N
R E
K NCH CICI CICI Outer Annulus Outer Annulus CB-15 CB-15 MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 4 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Containment Building 20'Elevation General Area Containment Building 20'Elevation General Area Figure 3-2 Figure 3-2 SIT #2 SIT #2 SIT #1 SIT #1 SIT #3 SIT #3 OPEN TO
-2' EL.
OPEN TO
-2' EL.
CB-21 CB-21 CB-14 CB-14 CPHO CPHO CEHO CEHO CB-16 CB-16 CB-13 CB-13 CB-11 CB-11 Outer Annulus Outer Annulus MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 5 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Containment Building 46' Elevation General Area Containment Building 46' Elevation General Area Figure 3-3 Figure 3-3 OPEN TO OPEN TO
-2' EL.
-2' EL.
OPEN TO OPEN TO 20' EL.
20' EL.
OPEN TO OPEN TO 20' EL.
20' EL.
CCG CCG CB-34 CB-34 CP-32 CP-32 CPLE CPLE CB-33 CB-33 ABOVE ELEVATOR MACHINE ROOM ABOVE ELEVATOR MACHINE ROOM POLAR CRANE POLAR CRANE MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 6 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Primary Auxiliary Building 11' Elevation General Area Primary Auxiliary Building 11' Elevation General Area Figure 3-4 Figure 3-4 PLPA PLPA PLAD PLAD PLPD PLPD PLDC PLDC PLEC PLEC PLPW PLPW PLLA PLLA MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 7 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Primary Auxiliary Building 21' Elevation General Area Primary Auxiliary Building 21' Elevation General Area Figure 3-5 Figure 3-5 P21L P21L PLAD PLAD P21H P21H P21L P21L PLPD PLPD P21D P21D P21E P21E MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 8 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Primary Auxiliary Building 36' Elevation General Area Primary Auxiliary Building 36' Elevation General Area Figure 3-6 Figure 3-6 PUSA PUSA PUSA PUSA PUTC PUTC PUDD PUDD PUWG PUWG PUHV PUHV PU-48 PU-48 PUFN PUFN PUEC PUEC PULI PULI PUFN PUFN PULI PULI MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 9 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Containment Building Electrical Penetration Room Containment Building Electrical Penetration Room Figure 3-7 Figure 3-7 RMCC RMCC RMCC RMCC RMCC RMCC MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 10 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Containment Building Mechanical Penetration Room Levels 4 & 5 Containment Building Mechanical Penetration Room Levels 4 & 5 Figure 3-8 Figure 3-8 Level 4 Level 4 Level 5 Level 5 MS-M-20 MS-M-20 MS-M-30 MS-M-30 MS-M-10 MS-M-10 SVH1 SVH1 MYAPC License Termination Plan Revision 3 OCtober 15, 2002 A Page 11 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Spray Buliding 4' Elevation Spray Buliding 4' Elevation Figure 3-9 Figure 3-9 SBRP SBRP MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 12 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Spray Building 6' Elevation Spray Building 6' Elevation Figure 3-10 Figure 3-10 SBRP SBRP MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 13 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Spray Building 11' Elevation Spray Building 11' Elevation Figure 3-11 Figure 3-11 SBRP SBRP Trench Trench Sump Pumps Sump Pumps MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 14 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Spray Building 12' & 21' Elevation Spray Building 12' & 21' Elevation Figure 3-12 Figure 3-12 MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 15 of 33
Spray Building 20' & 30' Elevations General Area Spray Building 20' & 30' Elevations General Area MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Figure 3-13 Figure 3-13 RMCC RMCC ELECTRICAL ELECTRICAL SBRP SBRP 30' Elevation 30' Elevation MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 16 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Fuel Building 21' Elevation Decon Room Fuel Building 21' Elevation Decon Room Figure 3-14 Figure 3-14 RCAD RCAD Drumming Room Drumming Room MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 17 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN RCA Storage Building Waste Solidification RCA Storage Building Waste Solidification Figure 3-15 Figure 3-15 RCAW RCAW MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 18 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Fuel Building 21' Elevation Spent Fuel Pool Heat Exchanger Area Fuel Building 21' Elevation Spent Fuel Pool Heat Exchanger Area Figure 3-16 Figure 3-16 SFPH SFPH HEAT EXCHANGER MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 19 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Fuel Building 21'Elevation Fuel Laydown Area Fuel Building 21'Elevation Fuel Laydown Area Figure 3-17 Figure 3-17 SFP03 SFP03 MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 20 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Figure 3-18 Figure 3-18 NFLA NFLA Fuel Building New Fuel Storage 31-1 1/2 Elevation MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 21 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Fuel Building 44'-6" Elevation Fuel Building 44'-6" Elevation Figure 3-19 Figure 3-19 SFP02 SFP02 SFP04 SFP04 SFPV SFPV Fuel Bridge Spent Fuel Pool MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 22 of 33
MAINE YAN KEE ATOMIC POWER CO.
LICENSE TERMINATIO N PLAN Montsweag Bay Figure 3-20 N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 23 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Site Area Layout Site Area Layout Figure 3-21 Figure 3-21 HRB HRB BUILDING BUILDING REACTOR REACTOR TURBINE HALL TURBINE HALL HOUSE HOUSE SCREEN SCREEN CCWI CCWI SERVICE BUILDING SERVICE BUILDING STPI STPI 10 10 30 30 STAFF BUILDING STAFF BUILDING ADMIN.
ADMIN.
CENTER CENTER PWST PWST X-19 X-19 X-16 X-16 PAB PAB 50 50 PARKING PARKING 30 30 30 30 WAREHOUSE #2 WAREHOUSE #2 SWITCHYARD SWITCHYARD 115KV 115KV FIRE POND FIRE POND FPHI FPHI MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 24 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN SERVICE BUILDING 21'ELEVATION SERVICE BUILDING 21'ELEVATION FIGURE 3-22 FIGURE 3-22 SBMS SBMS SB03 SB03 SBHP SBHP SBSR SBSR SB02 SB02 SBP SBP SB011 SB011 SBDR SBDR SBP SBP ALL COMMODITIES OUT BY 04/01/2001 ALL COMMODITIES OUT BY 04/01/2001 MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 25 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Service Building 21'Elevation Control and Computer Room Service Building 21'Elevation Control and Computer Room Figure 3-23 Figure 3-23 Control Room Computer room MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 26 of 33
MAINE YAN KEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Cold Side Service Building 30'-10" Elevation 2nd Floor General Area Figure 3-24 N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 27 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Service Building 39' Elevation Figure 3-25 SB07 SB05 SB08 TURBINE BUILDING N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 28 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Cable Vault Room 49' Elevation Figure 3-26 SB09 SB10 N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 29 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Turbine Building 21'Elevation Figure 3-27 SUMP TSPP TBSO TCNE THEA TCBA TMC TCDA TCSE TP2C THDT TFPA TBMS TCA TBLD N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 30 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Turbine Building 61' Elevation Figure 3-28 TDRW TSRU TSRP TBR2 MTGE TDSN TDBV TDSS TD01 N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 31 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Turbine Building 39' Elevation Figure 3-29 TMWC TMFA TMFR TMIA FWH TMHD TMSE TMLT TMDW TMDV TMFV TMWT TCTP TMGL TDR2 TMCH TMNC TMAE TMEC TCTU N
MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 32 of 33
MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN MAINE YANKEE ATOMIC POWER CO.
LICENSE TERMINATION PLAN Final Site Configuration Final Site Configuration Figure 3-30 Figure 3-30 ROUTE 144 ROUTE 144 PLANT ACCESS ROAD X
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X SECURITY/
OPS BLDG.
ISFSI WISCASSET MAINE YANKEE WESTPORT AIRPORT WESTPORT BRIDGE ROAD U.S. ROUTE 1 ROUTE 144 BACK RIVER LITTLE ISLAND OAK BAILEY POINT MONTSWEAG BAY FOXBIRD ISLAND 115KV SWITCHYARD 345KV SWITCHYARD ISFSI MYAPC License Termination Plan Revision 3 October 15, 2002 A Page 33 of 33