ML13093A029

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Decommissioning Funding Report, Page 51 of 120 Through 85 of 120
ML13093A029
Person / Time
Site: Humboldt Bay
Issue date: 04/01/2013
From:
Pacific Gas & Electric Co
To:
NRC/FSME
Shared Package
ML130930039 List:
References
HBL-13-003
Download: ML13093A029 (35)
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Text

Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 The safety organization reviews all job safety analyses, conduct the fall and fire protection training, issue confined space and burn (hot-work or fire) permits, conduct the safety meetings, review work packages, and oversee work in the field. Administration includes procedures, document control and records management functions and payroll. Many changes to plant procedures and license based documents are required to support decommissioning activities.

There exists several hundred procedures that will continue to require revisions as systems are removed and program requirements change. New procedures and desk guides are continually created for recurring, routine, or complex decommissioning activities that require standard controls and a higher level of approval.

Within plant operations are functions requiring clearances.

That is the need to identify, mark, and clear energized and active systems to assure that work can proceed safely prior to the start of decommissioning field activities.

This effort incorporate a number of methods to assure that these systems are not impacted during decommissioning activities including established Clearance and tagging processes, physical marking of systems and walk downs with field supervision.

3.6.5 Radiation

Protection:

The Radiation Protection organization is divided into several functional areas, and they include: ALARAIJob Coverage; Instrumentation and Respiratory Protection; and Dosimetry.

The Radiation Protection organization structure is depicted in Attachment G. The ALARAIJob Coverage functional area is responsible for writing Routine and Special Work Permits (RWPs and SWPs) for work in radiological areas, Radiological Job Coverage; ALARA; Performing radiological surveys of work areas; prescribing and monitoring HEPA ventilation systems, HEPA vacuums, and associated alpha contamination controls; and revising procedures and programs.

Also included are the RP General and Foreman and Access Control personnel.

The Instrumentation and Respiratory Protection functional area is responsible for Radiological Instrumentation, fixed and portable; revising procedures and programs; preparing, issuing, maintaining, decontaminating, and testing respiratory protection devices; fit testing; calibrating, issuing, and maintaining radiological measuring equipment (meters, air samplers, breathing zone air samplers (BZAS) , etc.) The Dosimetry functional area is responsible for Dosimetry issue, retrieval, and processing; whole body counting; revising procedures and programs; generating reports to the NRC and State of CA regulators; and generating dose reports for monitored employees.

3.6.6 Radiological

Materials Control and Count Room: The Count Room and Effluents functional area is responsible for analyzing radiological constituents of work area and environmental samples; calibration and maintenance of instrumentation; bioassay sampling (due to potential intakes of transuranics);

internal and external dose assessment; emergent radiological hazard evaluation; developing ALARA reviews and controls, coordinated with Engineering/Project work packages; evaluating post decommissioning building/area status relative to Page 51 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 DCGLs for buildings, soils, and groundwater; revising procedures and programs; and generating reports to the NRC and State of CA regulators.

3.S.7 Environmental:

The Environmental is responsible for: developing an environmental plan; testing for radiological) chemical and physical hazards in the work areas; characterizing materials for recycling prior to shipping; characterizing materials for disposal or processing prior to shipping; identifying residual chemical and physical parameters around the site that prevent free release to public access; revising Environmental and safety procedures and programs; evaluating, obtaining permits and interfacing with stakeholders who have concerns about areas of Cultural, Paleontological, and Biological significance of the site and surrounding areas; developing surveillance and monitoring plans for areas of Cultural, Paleontological, and Biological significance; environmental sampling and remediation; sampling to support discharge permits (monitoring of NPDES and license required parameters);

generating and obtaining approval of revisions to the NPDES Permit as needed; environmental sampling to characterize the site and waste streams; and developing remediation and site closure reports. 3.S.8 Site Services Site Services is responsible for ISFSI Security, general site Security, Training, and coordination with corporate Licensing to control the 10 CFR§72 license. ISFSI Security is responsible for monitoring and maintenance of the ISFSI facility and the general industrial security of the balance of the HBPP site. The ISFSI Security organization is depicted in Attachment I. ISFSI Special Projects is responsible for a variety of duties including security training, procedure writing, ISFSI Licensing, and Access Authorization.

The site training group is responsible for developing, revising, maintaining, and delivering general training to all employees on site as required by their individual job functions and assignments.

The training function for discipline specific training remains the responsibility of the owner departments.

The radiation protection training for the site staff and for the radiation protection staff needs continue to be updated to meet the new hazards that will be encountered during decommissioning of Unit 3. The activities planned for the future include the complete removal of the remainder of all piping systems and radioactive components in unique and remote locations (Le., off-gas tunnels, embedded piping, reactor vessel cavity, etc.). This activity requires specialized tooling and presents unique hazards to the workers and the environment.

10 CFR Part 19.12, of the NRC regulations, requires training, "commensurate to the hazard". As plant systems are open and actively moved onsite and offsite for disposal, new radiological hazards present themselves.

Experience has shown that a well trained work force is much more efficient and safe when training is completed at or near the time of the work evolution.

3.S.9 FSS A project lead will be assigned to develop the License Termination Plan (LTP) to release the site for industrial use. The L TP is required to be submitted to the NRC for approval at least two years before Page 52 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 license termination and it will provide detailed site characterization, descriptions of remaining dismantlement activities, plans for site remediation, detailed plans for the final rad survey, description of the end use of the site, updated site specific estimations of the remaining decommissioning costs, and an update to environmental report. Based on experience gained from other sites that have decommissioned, submittal of this plan as early as practical will facilitate early end-state decisions and will facilitate stakeholder involvement.

The Final Status Survey (FSS) functional area is responsible for site characterization and assumed Historical Site AssessmentiL TP consideration during decommissioning; insuring performance of turnover surveys when decommissioning of an area is complete to insure compliance with building, soils, and groundwater DCGLs for future FSS; performing and documenting the survey; revising procedures and programs; and generating reports to the NRC and State of CA regulators.

The Count Room and Effluents functional area is responsible for analyzing radiological constituents of work area and environmental samples; calibration and maintenance of instrumentation; bioassay sampling (due to potential intakes of transuranics);

internal and external dose assessment; emergent radiological hazard evaluation; developing ALARA reviews and controls, coordinated with Engineering/Project work packages; evaluating post decommissioning building/area status relative to DCGLs for buildings, soils, and groundwater; revising procedures and programs; and generating reports to the NRC and State of CA regulators.

Costs shown in the table below are in thousands.

3.7 Staffing

Costs Staffing includes both PG&E employees and contract employees under their direct supervision.

This labor cost category includes general project support functions that cannot typically be identified with a single project activity.

Functions performed by staff include engineering, radiation monitoring and protection, environmental support and compliance, training, licensing, contracting, and procurement.

PG&E also deploys workers that can be attributed to a specific work activity so that the costs can be assigned to that cost category.

In some cases these workers are PG&E employees or PG&E contract employees (e.g., site security associated with the ISFSI and some labor associated with removal of plant systems).

In other cases PG&E retains a third party contractor on a time and material basis to provide labor, most notably in connection with removal of plant operating systems. The staffing costs for HBPP Unit 3 Decommissioning aligned reasonably well with the 2009 cost estimate when compared to the baseline scope of work. The costs for the first two years were $12M below the planned amount of $55M. During this period HBPP Unit 3 transitioned into full scale decommissioning of the Unit 3 nuclear plant after 30 years of SAFSTOR. HBPP Unit 3 ended the year 2010 by successfully completing removal of all large nuclear components and safely transporting these oversized, overweight shipments to their disposal sites. These large nuclear Page 53 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 components include Spent Fuel Pool Racks, High and Low Pressure Turbines, Turbine Crossover, Main Condenser Halves and the Reactor Head. In 2011 to 2012 staffing levels increased

$5M higher than the planned amount of $55M to provide additional oversight as the site transitioned into multiple high-risk radiological significant removal activities.

During this period all the steam piping, feed water piping and other plant systems have been removed from the turbine building.

A proof of concept was underway to surface decontaminate one of the ancillary rooms to vet out the development of the specifications to prepare the turbine building for early demolition in 2012 in lieu of 2014. This re-sequencing was part of a recovery plan to offset the challenges that the project team experienced with the reactor vessel project. The three years from 2013 to 2015 represents the period of decontamination, demolition, and soil remediation with staffing levels ramping down at a budget of $54M for this period. The forecasted spending plan is about 4M higher because of a need to support completion of the reactor vessel project including draining of the reactor vessel and spent fuel pool and removal of the remaining active systems from the Liquid Radwaste Building.

To support removal of the caisson that spans from January 2016 to June 2018, the staffing costs will be about $22M. To complete final site restoration in the latter part of 2018 and administrative close out of the project in 2019 which includes submittal of the license termination request, invoicing and records, an estimated staffing cost of $6M is included.

PG&E has updated its estimates of labor expenses. The direct labor hour estimates for future work were developed based on actual experience to date, anticipated decommissioning methods, radiological conditions expected, safety requirements and other factors. Based on this information, crew sizes for each resource were estimated and applied to the duration of each major activity to calculate a total man-hour estimate.

These estimates together with anticipated billing rates, were used to estimate the labor cost to perform the remaining decommissioning work. PG&E has increased the 2009 estimate of $23 million by an additional

$32.8 million. The staffing costs are summarized in the table below 2012 to the end of the decommissioning in $millions:

Total Staffing per Year ($ in Millions) 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2025 Total $23 $21 $18 $15 $10 $11 $11 $0 $0 $0 $0 $0 $0 $0 $109 Page 54 of 120 Decommissioning P roj e ct Report for Humboldt B a y P ow e r P lant Unit 3 3.8 SMALL VALUE CONTRAC T S R e v. 0 Th e 2 009 Cos t S tudy es tim a t e includ e d $10.1 M a nd a n a dditi o n a l $1.7M in c onting e n cy t o c o v e r in s urance cost s , plant energy, prop e rty t axes, N R C fees and emergency planning fees. The actu a l costs were higher than the estimate of the recurring costs associated with essential services to support a large staffing organization.

Many of these recurring costs were nominal at the time of the original estimate and grew proportionally with the growth of the decommissioning staffing.

These contract cost categories include, but are not limited to: janitorial services, building maintenance services, portable toilet rental and maintenance, temporary lighting, parking lot striping and maintenance, signage, furniture rental and office supplies, trash and refuse collection, and communications services. The ETC estimates in the table below were established based on costs incurred to date for small dollar vendors, specialty contracts, and NRC fees. The forecast in the table below is in nominal dollars and have not been de-escalated to 2011 dollars. Small Contracts (Cost in Thousands)(Nominal 2009 Spent ETC Dollars) CPUC Total Including Caisson 10,084 23,198 28,703 Specialty Contracts 10,852 Programs and P l ans (Cross Contamination, Software, Revise U3 License for Decom) 1,515 Other 4,566 Difference between budget 82.3M and Spent 89M (prior to 2009) 6,264 I nfrastructu re 2,482 Count Room Lab Services 1,444 Misc. Construction 47 RP Support Staff (Discrete) 30 Director Staff Support 1,856 Decom Staff Support (Discrete) 2,033 Engineering Staff SUPQort(Disc r ete) 610 Environmental 160 Office Supplies 3,834 Final Site Survey 123 Adjustment for 2012 based on expenditures 1,569 Specialty Contracts 14,515 The forecasted costs for small dollar vendors was calculated using the established burn rates, spreading them over different periods of time based on schedule milestones.

The burn rates Page 55 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 decrease incrementally throughout the project. Many recurring costs are assumed to continue as the project moves forward. Each cost was evaluated based on their need during each of the four milestone periods -Systems Removal, Building Demolition, Caisson Removal, and Administrative Closeout.

These recurring costs include Janitorial Service, Phone and other utility costs, Environmental Sampling Analysis, California Coastal Commission Fees, EPRI Membership, Legal Services, among others. Several one-time purchases were omitted from the burn rate calculation although a portion was kept to account for any unknown items or services required in the coming years. These include, but are not limited to educational courses, unique instruments, minimal construction costs, short term support services, and specialty office supplies.

Specialty contracts forecast for the remaining of the project is $14.5 million. These contracts are for consultation services above and beyond overhead staffing.

These costs include specialty services for areas such as trained root cause analysis consultants, support updating project plans and procedures as needed throughout the project, corrective action program support services, risk assessments, benchmarking, auditing, permitting support, engineering and geotechnical assessment of deep excavations, organizational assessment, unique ISM training, review and analysis to ensure FSAR compliance, Licensing support for L TP review and submittal, technical RP activities to downsize the emergency plan, as well as other services to support unknown requirements.

Cost in Systems Civil Works -Demolition of Admin Thousands Removal BuildinQs Caisson Removal Closeout 2012 2013 2014 2015 2016 2017 2018 2019 Monthly Burn $319 $160 $160 $160 $115 $115 $115

$40 Rates Year Totals $3,828 $1,917 $1,917 $1,917 $1,375 $1,375 $1,375

$485 3.9 Project Tools and Equipment Typical tools and equipment purchased to support the decommissioning project include many general tools of varying sizes such as wrenches, hammers, screw drivers, and drills; as well as electrical equipment, carpentry materials, various cutting equipment, replacement blades, and pipe fitting tools, to name a few. Other specialty customized materials have also been required during the decommissioning process. Unlike other nuclear facilities, HBPP Unit 3 had to be incrementally removed to safely control the radiological hazards associated with the unique alpha contamination at this site. This process involves the controlled cutting and disassembly of each system, which required an extensive amount of various other tools and equipment, including one-of-a-kind specialty devices. The remaining work requiring the continued purchases of many tools and equipment was evaluated to determine the costs going forward to complete the project. An independent assessment was also done in order to calculate the projected forecast.

By evaluating the previous purchases, an average burn rate was established to forecast the costs over the remainder of the project. Large one time purchases were removed from the average expenses.

Some potential for additional one-time expenses exist and were included in the proposed forecast.

Small hand tools and safety hardware has to be replaced on a regular basis. This was assumed in the evaluation of the average burn rate and is also included in the projected forecast.

Page 56 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 The table below shows the forecasted costs for the tools and equipment required to complete the project. The forecast decreases incrementally each year as the project continues.

The decrease each year was determined based on the amount of remaining work according to the scheduled milestones to complete the project. The amounts in the table below are in nominal dollars and have not been de-escalated to 2011 dollars. "0 "0 "0 "0 "0 "0 Qj .... Qj .... Qj .... Qj .... Qj .... Qj .... 11\ 11\ 11\ 11\ 11\ 11\ 0 Qj 0 Qj 0 Qj 0 Qj 0 Qj 0 Qj Q. m b.O Q. o::t b.O Q. In b.O Q. U) b.O Q.,..., b.O Q. co b.O o .-I "0 o .-I "0 o .-I "0 0.-1"0 0.-1"0 o .-I "0 History ... 0 ... 0 ... 0 ... 0 ... 0 ... 0 0.. N co 0.. N co 0.. N co 0.. N co 0.. N co o..NCO Tools and Hardware $ 449,592.34

$ 396,534.86

$ 346,269.88

$ 262,494.91

$ 206,644.93

$ 189,889.93 Construction Supplies $ 503,452.19

$ 444,038.58

$ 387,752.00

$ 293,941.03

$ 231,400.38

$ 212,638.19 Total Tools and Supplies $ 953,044.53

$ 840,573.43

$ 734,021.87

$ 556,435.94

$ 438,045.31

$ 402,528.12 Monthly Burn Rate $ 79,420.38

$ 70,047.79

$ 61,168.49 $ 46,369.66

$ 36,503.78

$ 33,544.01 3.10 Health Physics Supplies/RP Tools and Equipment The remaining work requiring Health Physics Supplies/RP Tools and Equipment include radiological monitoring and surveying, confined space activities, asbestos abatement, scaffolding, excavation, site grading, final status survey, and site closeout.

It is expected that the burn rate for the required materials will increase in 2013 then incrementally decrease as the project continues and comes to a close. The anticipated spend for 2012 is $2.9M increasing to $3.7M in 2013 and decreasing to $2.2M in 2014, and $1.8M in 2015. Typical tools and equipment purchased to support this project include but are not limited to AVS-28A Air Samplers (and other type air samplers), HEPA Ventilation Systems, Radiation Detection Instrumentation (count room and field instruments), Visqueen, thousands of sample containers as well as other items to help control the spread of contamination and protect the public health and safety. Unlike other nuclear facilities, HBPP Unit 3 had to be incrementally removed to safely control the radiological hazards associated with the unique alpha contamination at this site. This process involves the controlled cutting and disassembly of each system, which required an extensive amount of various other tools and equipment, including one-of-a-kind specialty devices. As the Decommissioning progresses other large purchases and/or irregular purchases that are necessary to complete the project include but are not limited to;

  • Continuing support activities such as legacy waste, reactor vessel, and spent fuel pool work, which are underwater highly radioactive work. These support activities involve the significant purchases of materials, tools and equipment.

These types of work are requiring highly technical camera systems to be able to support the underwater activities that include configurable, radiation-tolerant split-head monochrome video cameras and support equipment for highly radioactive environments.

  • Due to the unique extreme alpha radiological contamination at HBPP Unit 3 there is a significant need to coat and encapsulate such surfaces as walls and floors as well as components and equipment in order to protect the health and safety of the worker, to prevent overexposures and contaminating personnel, and to meet the Waste Acceptance Page 57 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 Criteria at waste disposal sites. These type systems are of a unique design and require specialized equipment and coatings.
  • As plant monitoring equipment is dismantled there is a NRC requirement to ensure that the remaining work is monitored and sampled to ensure the spread of contamination is controlled.

This will be done with specialized RAD-H-2000 sampling systems along with other specialized equipment and instrumentation.

The estimate for tools and equipment is based on decommissioning experience to date and anticipated future needs. Due to the unique extreme alpha radiological contamination at HBPP Unit 3 the rate for tools and equipment is largely affected.

In many systems and the associated control methods required, once contaminated with alpha, tools and equipment often need to be disposed of as radioactive waste to protect workers, and to avoid the spread of contamination.

The table below demonstrates the expected cost of these specialized tools and equipment required to complete the project. The average monthly burn rate was established based on the amount spent during the last couple of years of the project. Materials considered for this calculation were those which were recurring purchases only, previous one time purchases were not included.

Looking at the number of current activities compared to the number of scheduled activities for 2013, it is assumed that the burn rate for the recurring purchases will remain the same. The average burn rate decreases each year based on the number of activities requiring specialty radiological tools and equipment as a percentage of the base year. The buyer of the radiological protection materials was consulted for the calculation of the percentages going forward in the project shown in blue in the table below. Since the one time purchases were not included in the burn rate calculation, the buyer forecasted the one time tools and equipment costs required to complete the project. These costs were projected for each year they will be incurred based on the scheduled milestones through project completion.

The costs in the table below are in nominal dollars and have not been escalated to 2011 dollars. RP Tools and Equipment Calculation 2013 2014 2015 2016 2017 Average Monthly Burn Rate (See Backup) 200,000 120,000 80,000 40,000 20,000 Percentage of Work Activities (from base year 2013) 100% 60% 40% 20% 10% 0% I i I , I i I , Average Common Supplies/Equipment I $2,400,000 I $1,440,000 I $960,000 1 $480,000: $240,000 , $0 Boat/Ba rge fo rca na I sa mples $5,000 $0 1 $0 $0 1 $0 1 $0 Ca rt(s)/Wagon(s)1 nstr/FSS/Supplies

! $40,000 SO! $O i $O i $0 $0 Specialized Cameras, Monitors, Control Panels, Radiation

! r , , , Detection Systems, I nstrumentation etc) $1,156,413

$721,413; $726,413 $486,413

$386,413 $0 $29,808 $17,338' $10,950' $5,779 $3,042 $0 Additional Sample Containers above average usage i $8,148 $4,739 $2,993

$1,580' $831. $0 Misc Supplies $60,000 $60,000 $60,000' $60,000 $60,000 $60,000 Totals $3,699,369 $2,243,489

$1,760,356 , $1,033,771

$690,286 $60,000 Page 58 of 120 Decommissioning Project Report for Humboldt Bay P ow e r P lant Unit 3 I 15,174 I Rad Protection (not including Caisson) 9 , 169 Rad Protection Material Contracts 3,459 Rad Protection (Caisson) 1 , 725 Glove Bags 821 3.11 Spent Fuel Management Rev. 0 Four additional years (2021 to 2024) are required to store high level radioactive waste on site since the probability of the DOE's ability to accept this waste for long term storage at its Yucca Mountain Nuclear Waste Repository is uncertain.

Spent Fuel Management 62,608 Security 47,243 ISFSIO&M 7,925 ISFSI Rem oval 2,000 NRC Fees 2,940 Transfer to DOE 2,500 PG&E will maintain the ISFSI until the DOE is ready to accept the spent nuclear fuel and GTCC wastes. The DOE is assumed to begin taking the fuel and wastes in 2024. Once the DOE provides the schedule accepting packages, PG&E can begin the planning and processes needed to transfer the spent fuel and GTCC to the DOE. Once the initial site restoration from decommissioning efforts for HBPP Unit 3 are complete, the project management, planning, and administrative resources will be released.

This phase of decommissioning is expected to occur in 2019. Between 2019 and 2024, the site will be maintained by the ISFSI Security force. The project management, planning, and administrative resources necessary for the initial planning phase of fuel transfer, ISFSI decommissioning, and site restoration will not be available on site. The planning phase for fuel and GTCC transfer is expected to take six months to a year of effort prior to the first dry runs for fuel transfer and transport to the DOE. During the planning phase, PG&E establish the following:

  • plans to mobilize and demobilize the Vertical Cask Transporter (VCT);
  • hardware and components necessary to facilitate the transfer (e.g., rigging, M& TE such as torque wrenches; transport components such as overpacks and rail cars; and consumables such as lubricants)
  • support services required to facilitate the transfer (e.g., Radiation Protection monitoring and support, Quality Control oversight; and Industrial Safety Technicians);
  • Stakeholder interfaces with local, State, and Federal regulatory and oversight authorities including the CA Coastal Commission, NRC, EPA, and DOE;
  • Permitting for material transfer, ISFSI demolition, and final site grading; Page 59 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 .. Updated procedures and processes necessary to facilitate the transfer of fuel and the demolition of ISFSI structures;

.. Crew size, crew training and qualification requirements, schedule, and duration to support the transfer of the canisters containing the spent nuclear fuel and GTCC from the ISFSI vaults to the shipping conveyance.

.. Plans for ISFSI demolition, final status surveys, and final site grading; and .. A termination plan for the 10 CFR §72 license. The planning process costs will be comprised primarily of overhead staffing costs. Once the plans are approved, PG&E will procure the tools, equipment, components, and systems necessary to support the fuel and GTCC transfer to the DOE. Finally, prior to beginning the transfer process, PG&E will procure crews to perform the transfer and the support services needed to facilitate the transfer.

PG&E expects to self-perform the transfer of fuel and GTCC to the DOE. The transfer process involves a limited number of simple, albeit risky steps. Those steps include: .. Removing a vault lid and verifying the radiological parameters of the vault contents;

.. Bringing the VCT into the ISFSI through the security screening check point. The VCT is required equipment because of its single failure-proof rating. This rating required for heavy lifts of fuel and of components adjacent to fuel; .. Lift the fuel or GTCC package from the vault; .. Move the VCT to the transport conveyance and load the contents onto the conveyance; and .. Perform transport radiation surveys and deliver package and transport documentation to the carrier. Once the carrier has accepted the package, it becomes the property of the DOE and PG&E's responsibilities for the material are terminated.

There are six packages to be transported.

Transfer of the six packages is expected to take about one year (two months per package).

After the last package is accepted by the carrier, the requirements to maintain a Security can be terminated.

The site can now be demolished, surveyed, graded, and released.

PG&E expects that the ISFSI demolition, site restoration, final status survey and final site grading will be perform using a bid specification and fixed-price competitive bid process similar to that used for the Civil Works projects.

Page 60 of 120 Decommi ss ioning P roject Report for Humboldt Ba y P ow e r P lant Unit 3 3.1 2 Remo v a l of P l a n t S y ste m s , S i te In fras tructu re , Rea ct o r V esse l Rem o v a l 65,813! Remainder of Plan t S y s tems 39,473 Direct Labor 32,814 Craft 17,748 Radiation Protection 15,066 Liquid Radwaste System 6,659 Site Infrastructure 2,074 Waste Handling Building 2,701 Common Site Support -Caisson and Canals 6,196 Relocation of Trailer City 2,542 Groundwater Treatment 2,893 Groundwater Treatment System Operation 761 Reactor Vessel Removal 15,368 Rev. 0 The direct labor hours for craft "self-perform" work, RP technicians and RP Deconners, including first line supervisors, has been estimated for each remaining major decommissioning activity.

These estimates together with estimated billing rates, were used to estimate the labor cost to perform this decommissioning work. The direct labor hour estimates for future work were developed based on actual experience to date, anticipated decommissioning methods, radiological conditions expected, safety requirements and other factors. Based on this information, crew sizes for each resource were estimated and applied to the duration of each major activity to calculate a total man-hour estimate.

The staffing required to provide direct oversight of work and to provide for escort duties included at RP technicians and Deconners for each work crew entering radiologically controlled areas. The RP technicians collected samples, observed the work practices of the workers, functioned as escorts, and were tasked with taking immediate and direct control of the work area in the event of a radiological problem. The deconners transported samples to the counting facility, maintained cleanliness of the areas, acted as escort backups, and assisted with construction and removal of the contamination boundaries.

The success of the staffing levels is seen in the successful removal of many thousands of pounds of highly contaminated components and debris with no personnel contaminations, no unplanned exposures, and no releases to the environment.

Costs in table above are in thousands.

3.13 Contingency The assumptions, basis and definition of contingency as defined in Establishing an Appropriate Contingency Factor for Inclusion in the Decommissioning Factor for Inclusion in the Decommissioning Revenue Requirements, Study Number: DECON-POS-H002 Revision 8, Status: Final April 2009 apply. However, contingencies were estimated on a line-item basis. Page 61 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 Costs in contingency table below are in thousands.

Total contingency is $94.5M and includes the contingency associated with Caisson Removal and Canal Remediation i I ... ....

. .. .... 1,1-

... , * "'I..':: I NDCTP Breakdown Contingecy Percentage Total ----Staffing 15% & 25% 23,597 ISFSI Mati r 10% I 748 : J ! Transfer CaskllSFSI Demo ,.. 15% 675 NRC lic/Misc Contr ,'" 10% ! 751 ; I FSS-ISFSI

,. 25% -5,336 Tools/Equip

.'" 10% \ 1,625 i I i Disposal ,.. 10% 11,821 Civil Works r 15% I 14,337 I ! i Turb Demo/GWTS

,. 15% 2,428 Caisson ," 25% ! 19,500 ! i Site Infrasfr ,.. 20% 1,076 Env Contracts r 25% i 2,077 : Small Contracts

,. 10% 1,333 Permitting r 15% ; 168 : Fluor ,. 25% 2,622 RP Discrete r 25% ! 2 , 285 j RPV/LRW ,. 25% 4,137 ------------

$94,515 ----------------Page 62 of 120 SCHEDULE ESTIMATE Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 PG&E has scheduled the remainder of the decommissioning of the HBPP site over a period of approximately eight years finishing in 2019. The current schedule completes the segmentation of the Reactor Pressure Vessel (RPV) in early 2014. The spent fuel pool will be removed in early 2016. Permitting for the caisson removal project will commence in 2013 with the caisson removal project planned for 2 % years beginning in 2016 and completing in mid-2018.

PG&E has summarized its "HBPP Project Planning Schedule" into three separate summary schedule graphics titled: "Schedule Summary with Key Milestones" depicting key Project milestone events; "Summary Planning Schedule" that summarizes major work components and illustrates primary sequencing of decommissioning operations; and, "PG&E Self-Perform Work" that describes principal elements of work to be performed directly by PG&E managed forces. Moreover, PG&E's "Summary Planning Schedule" provides a clear depiction of the schedule impact the decision to remove the Reactor Caisson and Spent Fuel Pool (SFP) has on the performance period required to complete the Project. 3.14 HBPP

SUMMARY

SCHEDULE WITH KEY MILESTONES The Level 1 Schedule Summary with Key Milestones below captures the work completed to date and the planned work going forward to the end of the decommissioning project. As seen in the schedule, the focus for 2013 and 2014 is to complete the removal of plant systems, intake and discharge canal remediation, above ground structure removal, and preparation for caisson removal. A significant deviation from previously planned work is the decision to remove the caisson rather than decontaminate and abandon it in place. Removal of the caisson requires additional planning, permitting, and extensive preparatory work. These activities can be performed in parallel with other planned and scheduled work. The physical removal of the caisson is planned to take about 2 % years, time that must be added in to scheduled activities.

While the caisson removal work is in progress, any other work in the immediate area will be precluded due to the safety conflicts that arise in the vicinity of deep excavations.

The 2 % year schedule extension is identified in the schedule below as the shaded area that begins in 2016 and runs through the middle of 2018. By adding the work at this point in the planned activities, "Site Restoration" and "Administrative Closeout" are pushed into late 2018 and 2019 respectively.

The "Administrative Closeout" activity is planned for a twelve month period using greatly reduced staffing levels. The activity is planned to ensure that all the paperwork that documents the decommissioning process is in good order, properly filed, and safely archived.

By performing the activity at this point, it will reduce the errors and delays that could occur when the DOE is ready to accept spent nuclear fuel-and GTCC wastes. Page 63 of 120 SUM0700 Fos s il Decommissioning Complete (B ase line) SUM0570 Units 1 & 2 Above G rade Demo (Base line) SUM05 6 0 Units 1 & 2 Above Grade Demolitions (Actu a l) SUM0590 U1 & 2 B e low Grade/SUe Restor a tion (8ase llne) SUM0710 Unil2 Pad Remova l* Partial SUM0720 Unit 1 Pad and Remainder of Unit 2 P ad Removat ... _-'" .--.---._. __ ._.------..* ----_ ... SUM0470 lTP to NRC SUM0460 LTP Public Meeting SUM0640 T urbina Building D o me to Slab +1 2 (Ba se IiM) SUM0600 T urbine Building Demo to Slab +'2 E lev (Actual) SUM0610 T urbine Building Slab D em o! R e mov a l SUM0620* LRW Equipment Removals/Building Demo SUM0510 Refueling Buidlng Removals and Decontamination SUM0530 Complete T r a nsf e r of Loaded Cask 6 to IS FS I ---SUM0 55 0 CCC Approval for SFP J Caisson Removal SUM0460 Slurry Wall Con s truction SUMOSOO Caisson Remov a l SUM0 56 0 CCC Approval for Canals Remedi a tion SUM04 5 0 Complete Intake/Discharge Canals R e med l ations SlJM0490 -U, , 2 ,&3 Int a k e/Disch a rg e Lines R emo v a ls*Phase 2 SUM0 5 40 SUM05 2 0 Site Re s to ra tion SUM0730 Adm i n is tr a tiv e C lo seou t I Start Oate Fl nl ,h Oil!!) Da ta Dat G j:!l.In Da t e Level 1 Schedule Summary with Key Milestones l i l: l a ii r.;r;;,.r o.,-,J .... r ** r. i l ffl/l.1'" ;r-----r--MLJ lJiALS.!.OlN I D J I C: I U 1 A I UI ." Decomniiss l on\tJg goinplete 31D EC 16A Fossil Decommissioning .\ .. ' .. ,.. ' 01F EB 10A 3 0MAR 12A iUnlts 1& 2 Move Grade Demo II.. .11. " ..... I I Foss il EPe Business C ase 02AUG10A 31AUG11A 1 & 2 Above Grade Demolitions (Actual) 01JAN16A 31DEC16A 1 25JUN13A 21AUG13A 23JUL14A lSS!;P 14A 15MAY13A 01AUG13A 01DEC13A 28 FE B14A 10JAN13A 24JUN13A 14JAN16A 13APR16A 29FEB12A 19FEB14A 02JUL12A 14JAN16A 13DEC13A -17JUN13A 20 FE B14A 22JUL 14A 14JAN16A 30JUL18A 1 2 MAR14A 12MAR14A 11MAR1 5 A 1 2 M ARi5A-10DEC14A 31JUL16A 24DECl8A 01JAN19A 31D E C19A Unit 2 Pad Removal* Parlial Unit 1 Pad and Remainder of Unit 2 P; Id' lTP to NRC

  • lTP Public Meeting
  • Turbine Building Demo to Slab +12 (Baseline) 1------i' I I Turbine Building Domo to Slab .12 Elev (Actual) LRW Equipment Aemovals/Bulldinp Demo Rofuoling BUiding Removals and Complete Transfer of Loaded Cask 6 to ISFSI
  • cec Approval lor SFP/Caisson Removal
  • HBPP Nuclear DGtommissionirtB Spend Plan SlSO r------------------., 1;'$J /' !mo /' SlUt z Wall Construction Approval for Canals Relnedialion CDP Amendment Approval TUrbine BiJllding Slab Den10J Removal -.,' , , , I I , I I' ; . !.§ <200 Complete Intake/Discharge Canals Rernedllall'ot)s
, , : I " ( I f ! :150 '----:-=

I _______ .: ___ __ .:. _ _____ { I I 7009 6lM 3 6M I}ti or 'lO M OO M ___ _ 2 010 C, 3 M 20 11 .M GCiM s s o P, I Of 2012 81 M 80 M Approval for SUe ReEHqraU(lln. Restoration OtJANI 2 CPUT 310eC l 1 OlJANI 2 tOil) fndl", r.l j n _AL11I .. 1 2 Qll S heat 1 of 1 Pacific Gas & Electric Company HBPP Fossil and Nuclear Decommissioning Projects Summary Schedule Milestones " Administrative Closeout L-_ © Primavera Systems , Inc , Page 64 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 3.15 CRITICAL PATH

SUMMARY

Rev. 0 PG&E has developed its Critical Path Method (CPM) "HBPP Project Planning Schedule" to reflect long range planning and coordination for the Project. PG&E's "HBPP Project Planning Schedule" provides relatively detailed planning of major tasks including "self-perform" work in addition to work that is to be performed by independent Contractors.

This schedule generally illustrates the level of interface and coordination that will be required on the Project and identifies anticipated constraints and/or special considerations for planning/scheduling purposes.

Decommissioning of the Reactor and Refueling Building (RFB), including the removal of the Reactor Caisson and SFP, drives the current Critical Path for the Project. It is important to note that a key milestone driving the Critical Path is the removal of components that are segmented and packaged under the shielding water of the SFP. Structure demolition including, but not limited to, RFB demolition, Caisson/SFP removal, etc., cannot be initiated until the SFP is drained following completion of segmenting, packaging, and removal of all components from the SFP. The integrated critical path schedule is depicted on the "Project Planning Schedule" below. Chronologically, the schedule shows the following activities:

3.15.1 2012 The Critical Path activities throughout 2012 are primarily in the RFB. Refueling Building (RFB) includes the following components and systems:

  • Reactor Equipment/Instrument Chamber -contains piping, valves, instruments, etc., and is accessed through an Access Shaft at the +12 Elevation of the RFB. The components within the Reactor Equipment/Instrumentation Chamber are subdivided by: those components that are not attached to the RPV; and, those that fall under the grouping "RPV External w/i Equip. /Instr. Chamber" that are attached to the RPV and their removal is dictated by the water level in the RPV.
  • Reactor Caisson
  • Spent Fuel Pool (SFP)
  • RFB/SFP Area (+12) Operating Floor
  • Suppression Chamber -includes Ring Header and Downcomers The RFB work includes Energy Solutions' (ES) Removal of Internals from the Reactor Pressure Vessel (RPV), transferring the internals to the SFP, followed by the segmenting of those components within the SFP. The transfer of the Reactor Core assembly (Chimney) to the SFP has been completed.

Maintaining the water level in the RPV for shielding purposes, removal/relocation of the remaining RPV Internals is currently underway and scheduled to be completed by March 2013. Once the remainders of RPV Internals are removed/relocated to the SFP, the RPV will then be drained. Concurrent with the Reactor Vessel Internals transfer and segmentation work, PG&E continues to perform non-Critical Path removals of piping, valves, instruments, etc., throughout the RFB. Page 65 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 PG&E is nearly complete with its removal of equipment and components from the Turbine Building and has awarded a Contract to an independent Contractor for demolition of the Turbine Building that is to take place the first half of 2013. PG&E also continues with its Equipment/Pipe Removals from the Liquid Radwaste Building (LRW) throughout 2012. 3.15.2 2013 The Project's Critical Path in 2013 will initially remain with the removal of RPV Internals until that project is completed in March. Once the RPV Internals have been removed, the RPV will be drained and a fixative applied. Finally, the component beneath the RPV will be removed (e.g. Control Rod Drive Mechanisms (CRDMs), air gap nozzles, etc.). A secondary Critical Path will proceed concurrently with the RPV Internals work. The second critical path involves removal of piping, valves, instruments, etc., from the Reactor Access Shaft. For the last half of 2013, the Project's Critical Path will be dominated by the Segmentation and Removal of the Reactor Vessel itself from the Reactor concrete Caisson. Significant Milestones that will occur in 2013 include California Coastal Commission's (CCC) approval for SFP and Caisson Removals, and the transfer of Cask 6 containing Greater Than Class C (GTCC) waster from the SFP to the ISFSI. This final transfer of material to the ISFSI is necessary prior to draining the SFP. Non-critical path work in the RFB includes removal of the Ring Header and Downcomers from the Reactor Suppression Chambers with completion planned for January 2014. A significant effort will be put forth to remove equipment and components from the Liquid Radwaste Building LRW), Off-Gas Tunnels, and Hot Machine Shop; and to remove the LRW Building to its slab, the Hot Machine Shop structure, the Stack (including foundation), the SAS Building, and sections of Reactor Intake/Discharge Lines that lie in the path of the to-be-constructed Slurry Wall. 2013 will also see the demolition of the Turbine Building down to its foundation slab by June. Upon removal of the Turbine Building, Slurry Wall Pre-Trenching will proceed in coordination with the removals noted above. 3.15.3 2014 The Project Critical Path in 2014 will continue in the RFB with the Segmentation and Removal of the Reactor Vessel through May 2014 followed by the removal of Asbestos from pipe, equipment and penetrations in the Reactor Drywell, and the removal of Drywell Systems. Work in the RFB is scheduled to be completed by December 2014. Concurrent with the work within the RFB, construction of the Slurry Wall is scheduled to occur between February and July 2014. The Slurry Wall will encompass the RFB, North Yard, South Yard and Turbine Building Slab and be constructed to a depth of approximately 170' deep to mitigate the intrusion of subsurface water into below grade excavations.

Dewatering within the Slurry Wall containment will begin at the completion of the Slurry Wall and will proceed in concert with draining of the Spent Fuel Pool. Page 66 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 Currently, the Low Level Waste Storage Building (LLW), the Solid Waste Handling Buildings (SWH), and the High Level Storage Vault (HLSV) in the Upper Yard are scheduled for removal and backfill in 2014. However, the decontamination and removal of the Upper Yard structures are relatively independent of other operations and thus have considerable schedule float. Another significant milestone achievement will be CCC's approval for Remediation of the Project's Intake and Discharge Canals in March 2014 with physical work planned to take place immediately thereafter through to March 2015. 3.15.4 2015 Project Critical Path work in 2015 will continue in the RFB with removal of the Drywell Liner followed by removal of Activated Concrete scheduled for completion September 2015. At this point, demolition of the RFB Building structure to +12 elevation and removal of the RFB+12 Slab at the Crane Bay will occur and be completed January 2016. Remediation of the Intake/Discharge Canals will continue through March 2015 at which time the remaining I ntake/Discharge Piping will be removed starting at the Discharge Canal head structure location.

These removal efforts are planned for completion November 2015. 3.15.5 2016 -2018 The Project Critical Path for 2016 through March 2018 revolves around Caisson/SFP Removal and backfill efforts. Coincidental with the Caisson/SFP Removal excavations, remaining Below Grade structures within the Slurry Wall compound (e.g. Turbine Building Slab, LRW Slab, SAS, Off-Gas Tunnels, utilities, etc.) will also be removed.

Once removals are completed, FSS Surveys and corresponding backfill operations will be conducted through completion in July 2018. Final Site Restoration work will then continue through the end of the year. 3.15.6 2019 With physical Project work completed, 2019 will provide for the Administrative Closeout associated with License Termination.

Page 67 of 120 Planning Schedule Summary 2MB F M fA M J A. S Q N [} "-F M. A M REA C T OR V ESSE L REM OV ALS AN D S E G ME NTATIONS Drain Reactor Vessel . . --------,

  • RPV In t ern a l s Re mov a l & S eg men ta tion __________

____ . ______ . ____________

.. _, 'RPV Vesse l Shell Segmenta t ion __ lIiIiIiIiIIIlillillliIiIII.

___ -----L ----------r -------------* -----------REFUELlNGfTURBINE BUILDINGS REMOVALS EQuimentlComponent Removals :.,.."';

t : REFUELING BUILDING STRUC T URES DEMOLITION

'Remove Liner and Activated

-1 lle.m()ve Su p-ression Chambe r s L in ers G) NW j TURBINE BUILDING STRUCTURES DEMOLITION Demo Turbine Buildi n g Demo to Slab ( EI. 12) SLURRY WALL CONSTRUCTION

'Pre-Trench for Slur Wall t I I I ,Re , fueling Bu if(:l i ng to +12 ! I ;Install --------"--------------------------within Slu r ry Wall ____ J _________________________

_ , , I ---_.!... __ ._-Sh E}[}t 1 0 1 2 ---**r"' ___ -...... t o .2fi xcavalions l Demolltions to j I ! I I 1 I I I !

Removal Areas Page 68 of 120 BELOW GRADE (below +12) DEMOLITIONS UPPER YARD STRUCTURES DEMOLITION LOWER YARD REMOVALS INTAKEIDISCARGE CANALS REMEDIATIONS SITE RESTORATION ADMINISTRATIVE CLOSEOUT Start Date Finish Date Data Date Run Date Demo North Yard Stack and SAS to Elevation

+12 I I I I © Primavera I _ bemo LRW Building to +12 Elevation I ,-_.-va I --.-_. --.---* -. I I I I South Yard Tunnels Decon/Equipment Removals ----______ I_ ------_.----_. : _ _ _ 'Demo Hot Machine Shop & U3 Circ Water Lines Inc. _. ___ . __ ..J Yard Structures and Backfill Intake & Dischar p e Canals Remediation 01JAN12 CPUT 31DEC11 01JAN12 300CT1211: 22 Planning Schedule Summary ."

U1,2,&3 Intake/Dischar p e Lines ! .

Pacific Gas & Electric Company " .." " -, .,' .,' . ".,' .. ' =: .

Sheet 2 of Humboldt Bay Power Plant Decommisioning Proj,ect Planning Schedule Summary .' . I '.

Close-Out Page 69 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 3.16 SELF PERFORM SCHEDULE Rev. 0 To better capture the details of the work that PG&E will self-perform, the "PG&E Self Perform Schedule" below was developed based on extensive planning done to complete the activities.

The majority of the remaining work that will be self-performed is scheduled for 2013 and 2014. That work generally is comprised of the following activities:

3.16.1 2013 The activities in 2013 will focus on packaging and removal of GTCC wastes, Turbine building demolition, completion of systems removal, and preparation and commencing Reactor Pressure Vessel (RPV) segmentation.

3.16.2 2014 The activities in 2014 will focus on completing RPV segmentation, packaging, and disposal; draining the spent fuel pool; and final systems removal from the caisson, drywell, and fuel building.

Page 70 of 120 PG&E Self Perform Schedule I I I 1 4RI=4: 1 l I 2013 ActllOVIty Activity OrDurlg Actual Early Early Predecessors Successors I J 1 F T NI I A i NI T T T:J 1 4: I so -Nil Description Duration Start I Finish _ ' ! 2014 2015 i F I M A' M J! J I A I S" T a l IiiT'D T J F T Pi A I .... I J ! J ! A S i , ...

! ! 'of Shaft Remqvals.2 *54 Elev. ! ,:: : Chamber Downcomer!Rlngheader Removal i **

i Tumine I 18 o l RFB 1 040 i l 1 24J 1 03' 0360 B-Reslns to WCS 38 o RFB 105 1 SJAN 13' 07MAR13 'cn",u:""u;WC S .-*--0*2-a-0-+S-h-iP-B/-C-W-as-te-t-o-W-C-S------------t--6-1 f-----O+R--F-B-+---+-1 O-O--+1 2-BJAN-I-3-' "--l-2-'-2A--P-R-1-3 -+-1 0-250-----.-----+--------

--.-.---.. --1 /: .:\ .. ', Shli)B/( 10 y."', .... "

RP;V &l iP':

R1 Oec?"

0110 Devel o p Access to Valve Gallery 21 o RFB : 01 13FEB13' 13MAR13 0180 Drail1 RPV & Apply Fixatives 16 o RFB : 050 i 04MAR13 25MAR13 1 0230' 0140" 0310 0210 Remove RV Decon Facility 23 o RFB 1 065 04MAR13 03APR13 1 0230' 0140 I CRDMs Removal 63 o RFB 1 030 26MAR13 20JUN13 01BO' 0120 , 0220' , v.-C CR RDDMI;I.1 S S Removal-.. --.. --' -----i 0250 Control Rods Blades 21 o RFB lBMARI3' 15APR13 0280 7

>ds Blades 0220 Build RPV Containment S t rucuture 44 o RFB !070 21JUN13 21AUG13 : '--"' __ :l. ..... (.!'!Ulld Containment

8===:sJ EmerQlent=y Condenser Removal-------' --, ; I; :!. . :: is==, ;:._a.lv .e_ , ,G.a_ .. I:le:,rv J. EqUipment Removal.

2 , , : tiesumf al l er TB Demo. .: . 0140' 0150', 0240' 0150 Emergency Condenser Removal 59 o RFB '035 21JUN13 11SEP13 0220' 0380 0310 Valve Gallery Equipment Removal -Phase 2 97 o RFB 120 25JUN13 06NOV13 01BO, 0320' 0240 RPV Shell Segmentalion 188 o RFB 080 22AUG13 12MAY14 0220' 0260' -T nr

  • Shel! S. egnlenl:atlcl" .: ' .... L ... .. -.-,,=, = .. *. :: ':.,', .*'-nlc .... 'v* 6 1e: s* .. *f*er* .... ** .. t-i c i ... I*S***F****S .. -I .. * .... ,-.. -.......... . u c i !,
I 0290 Setllp Equipment, Load Cask 6, Transfer to ISFSI 18 o RFB 110 19NOV13' 12DEC13 0350', 0380 0350 Remove Condensate Demineralizers 50 o RFB 1 0 13DEC13 20FEB14 0290' I .. _ ...... _ ... .l. .... ',; . ts==,

ShaH Removals -66 Elev. , t::, i'.!: :! 0120 I Access Shaft Component Removals -66 Elev. 70 o RFB 020 28FEB14 05JUN14 0100', 0140 0340' 0340 Grout Embedded Piping/Drains in RFB 89 o RFB 130 06JUN14 08OCT14 0260 Drywell Cavily/Systems Abatement 43 o RFB !090 13MAY14 10JUL14 0270 Drywell Cavity Systems Removals 90 o RFB 1 095 11JUL14 13NOV14 0120' 0240' 0270' ----!---0260' I L

...... c,)utut Embedded Piping/Drains In flFB j : ,. 9rywell I I ._._ .. _i i i I I I I I i 0380 Drain SPF and Apply Fixatives 128 o RFB 23JUL14" 16JAN15 0150,0290 i l rir}ft .. Cavity i , -= '.,,"" SPF and Appiy Fixatives I

to start in conjunction deiNaterirlgl 0170 LRW Component Removals -Phase 2 (by Contractor) 215 LRW 1 045 01JAN13A 28OCT13A 0330 Grout Embedded Piping/Drains in LRW 52 LRW 125 29OCT13A 08JAN14A __

0370 Hot Maching Shop Component Removals & Demo 256 LRW 04FEB13A 27JAN14A 0190 1 0llgas Tunne l s Component Removals 344 TNL !055 030CT12A 27JAN14A : . : I , , wi/r in Wall. .! LRW Removals.

Phase 2 (by

i: : I C::=:::::J Grout Embedded In : I Hot , Machlng: Shop CompoJ;lent Rem bval$ & Demo! :,' I : Offgas Component Remov.lls , .. ....
! . 1 : I SlartDate Finish Date DsUl Date Run Date © Primavera Systems Inc. 01JAN13 [CPU2 1 6JAN15 01JAN13 01NOV1210: 39 PACIFIC GAS & ELECTRIC HUMBOLDT BAY POWER PLANT PG&E Self Peiform Work , : ; : Sheet 1 of 1 Page 71 of 120 4 RADIOACTIVE WASTE Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 The objectives of the decommissioning process are lthe removal of all radioactive material from the site that would restrict its future use and the termination of the NRC license. This currently requires the remediation of all radioactive material at the site in excess of applicable legal limits. Under the Atomic Energy Act, the NRC is responsible for protecting the public from sources of ionizing radiation.

Title 10 of the Code of Federal Regulations delineates the production, utilization, and disposal of radioactive materials and processes.

In particular, Part 71 defines radioactive material as it pertains to transportation and Part 61 specifies its disposition.

Soil remediation and management (SR&M), which encompasses excavations, handling, stockpiling, sampling, reuse and off-site disposal, is an integral part of a nuclear decommissioning project and represents a significant portion of PG&Es HBPP Decommissioning Project (HBPP Decon) cost. HBPP Decon developed a comprehensive scope of work for Unit 3 building demolition (Civil Works) to solicit pricing from major demolition contractors.

The HBPP Decommissioning Project Team is currently evaluating bid proposals from three major demolition contractors.

Each of the contractors' proposals has an SR&M component.

At the time the previous cost estimate was prepared, the only disposal option available to HBPP was Clive, UT. PG&E currently has an approved exemption to dispose low-level radioactive waste at US Ecology's (USEI) disposal site in Grand View, 10. USEI's Waste Acceptance Criteria (WAC) threshold for radiologically-contaminated soils is isotope-specific, but is generally less than 13pCi./gm.

for Cs-137 as a surrogate for all. 4.1.1 CIVIL WORKS APPROACH The HBPP Decommissioning Project is transitioning from self-performing contaminated system removal to a contracting strategy for building decontamination and demolition.

Detailed work scopes and demolition work execution specifications were prepared to solicit pricing proposals from industry-proven demolition contractors.

The work scopes are collectively referred as Civil Works. The HBPP site has a known high ground water table. During the course of developing the Civil Works design specifications it became increasingly obvious that control of ground water would become a critical design issue for removal of the deeper sub-surface structures including the turbine building foundation mat, the off-gas tunnel, and the spent fuel pool. Concurrent with development of the Civil Works specifications, a feasibility study was commissioned for removal of the Refuel Building (RFB) sub-grade caisson. During the initial work of the study, the engineering company performing the study recommended installation of a slurry wall to limit water intrusion in deep excavations.

Slurry wall construction had many apparent advantages and the Project opted to install a slurry wall to facilitate removal of sub-grade structures.

Excavation of the circulating water lines from under the footprint of HBGS' new 60-KV switchyard provided visual evidence of the site's soil characteristics.

The density, water-content, and cohesiveness of the clay-like soil provide a better understanding that these properties would resist migration of radionuclide contaminants.

Page 72 of 120 Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 Subject matter experts on site agree that radiological contamination in the soils will be localized at the sources of leaks and spills. Absent of a complete radiological characterization profile of the site's radiologically-controlled area (RCA), general assumptions for specifically-designated areas within the RCA were recommended by the Radiation Protection and accepted the Project Management Team. These assumptions are reflected in the table of estimated soil excavation and disposal volumes. Page 73 of 120

\I(cv.II." r.lwrn!i DAtmaT rt*:7t:'T H .* Tm ....... ... '1"1t1; I)\.1JLllltoUllK IS

-\,ill LAlLI'"!.

FOR r wt'" .... Caisson ",-l!I.UHn

'.VoIIl Tf1' ESTIMATED REMOVAL CAISSON .CONCRETE UPPER 70 , 000 CuFt CAISSON CONCRETE LO'NER 69 , 000 CLIFt SLURRY VVALL PRE-TRENCH 114 , 000 CuFt SLURRY WALL SOILS 459 , 000. CuFt CAISSON SOIL EXCAVATION 317 , 000 CuFt 9 I I 0 0 .::a ' ANCHOR BLOCK HIICHCR , ___ '. ,----, " , -.. .,.-.. "'" ". . r*ll. L--" ..... .......' .

,--, 'J -.<i";;"" **.**** '., . 'A \ ." ,_J L ** " * ....... '. . ". _ * ,bNCHOR BLOCK II W ,----I ," "::: '-', <.) C, .; *.* .r:. " .-.,-\, ... " m-:.t r ,*." * ;:...,J, -., r" .,,-. .... .. . . .. , ',. . . .. ., ... -' .,..". .. , ...... " ........ " ........ ...... '. , l' -'--... ",;' I .... . ." ' \ ,...... ::........ \ \, RfLA..... , j', ,.". .... ..:::=..J

_..,.it:* \ .... e:.:::.... \. \, \. PIPING. ItII THIS pREA PRE'JICUSL"f I .:;..-;-. \ .. ' ',' TCuv RD le,t ... /.*.. "', ... REMO'o.'EO FOR GOKV nrA , *

  • d .... .... .. ' ESTIh1.t.\TED

)4,800 CU.FT. SOIL ',',1, '. __ '., floJ'lJCHOR aLOCK -../' ........ ..... oJ EKc:r..VATED

(, 4Q'x.3C*.:a') .l' L.--.-'\ . ,." '. f " 'I' I'" ...... . I t I J ,. \ .......... \ ... t ,-'. * .-" !r ',', I I / .......

""\ '. " .. -----f"UTURE " ., I SVIlTCH"r'ARC

..,...-, I F'ENCE -----.-' , E S Tl tvfAT E D P I P E R E M O VA L I COOLING JAIATER SITE PLAN N T S

...n=t I n=l Ln=t TOTA: BEF ffi E Y Ya l Oe" U N I T* R C A. IH T;: R\.i ": ::'0" 89 0 74 59" 1 7 0t 1 7 6 1 *1 42 U 6 87 3 87 .!.8 2 2.! 7 5 2 4 t -O TA l 1 5 1 NOTE; 1 INT'ERMODAL WITH tAl!<ED LENrmtS & SI2ES OF PIPE LEGEND cccuroJG WAlER INTA K E PIP I NG TO BE re E MO V'EC _ COOLING OISCHt1RCE PIPING TO BE REMOVED COOLING WATER IDISCHARGE PIPING ,.NCHOR BLOCKS TO REMAIN BLOCK or* -J -

BUJCK TO BE REM()'I)ED (389 CuFt.) PIPlt,JC mCHOR BLOCKS TO T1"PICAL REINFORCED CONCRETE PIPING ZOOi CPIJC NOel? ASSU MED THE EXI5nNG CONCRETE CIRCULAilLNG WATER PIPING 'iIlU BE MtJO IN PLt1.cE. SOl LS REMOV."'l R=M OVA l ,-n.4 /.r .. r.H:ir. R I ¥ .:.r*.: .;.1: '" l!)( h v ... I f': .': L fji r-',Jr.1 II M r '-t.' .: , I t 1..!-11 U l t. EXHIBIT 8 COOUt\(; WATER SrTE Pl.fltN Page 77 of 120 4.1.4 RCA Yard Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 The entire RCA is paved for contamination control and for housekeeping considerations.

It is assumed that two, 2-in. courses of paving are present. A" of the paving wi" be stripped and disposed.

The sub-paving soils within the RCA yard are segregated by general areas (Upper, North, & South) based on sub-grade commodities and structures, described as follows: Upper Yard-The area generally north and east of the Liquid Radwaste Building to the RCA fence line. This area has minimal subgrade piping and structures and is considered relatively radiologica"y-clean.

Radiation Protection estimates that most of the contamination is contained in the first 1" of soil under the paving. The excavation estimate is based on the assumed paving depth along with 1" of soil is removed and disposed.

North Yard-This area contains deeper sub-grade off-gas tunnels, radwaste discharge lines, pump pits, instrument vaults, a concrete water tank, and building foundations.

A six-foot average depth is considered a sufficient volume to envelope a" excavations for the sub-grade commodities and structures in the North Yard. RP wi" make an initial, judgmental assessment of which soils wi" be disposed or retained for reuse. Currently RP anticipates that half of the excavated soil wi" be disposed offsite. LRW Building-The LRW building is within the North Yard but its 4488 sq. ft. footprint area was not included with the North Yard surface area computation.

It is assumed to be excavated to the nominal six-foot depth of the North Yard. The top one-foot depth is assumed sufficiently contaminated to require offsite disposal.

South Yard-surface paving, off-gas tunnel, radwaste drain lines, and Hot Machine Shop grade slab. A five-foot average depth is considered a sufficient volume to envelope a" excavations for the sub-grade commodities and structures in the South Yard. Designation of soils for disposal and reuse will be by RP on-the-spot; in the field, as described under "North Yard", above: Currently RP anticipates that 25% of the excavated soil wi" be disposed offsite. 4.1.5 Outside RCA Radwaste Discharge Line-350-l.f. of 4" C.1. pipe @ 3'nominal depth discharging to the Discharge Canal. The bottom-most 10-in. depth of the excavated trench, along the entire run, is assumed sufficiently contaminated for disposal at Clive. The balance of the upper-most excavated material is assumed sufficiently contaminant-free for reuse on site. North Yard Drainage System-508-l.f. of perforated corrugated metal pipe and reinforced concrete pipe (outside of the North Yard) discharging to the Intake Canal. Assuming an impacted, full cross-section of 55 sq. ft. based on a five-foot excavated depth. Based on limited sampling characterization data, it is assumed that 75%) of the excavated soil will be reused on site. Page 78 of 120

.RUBB TEN SL.A;B .A.R E A 1 OF SOIL REMOVAL l' DEEP E X CLIJDING SL , A.BS 10% DISPOS A.l= SOLID R A D lllA STE STOR., FF=29'-Bj

/ LEGEN , D Soils and Substructures r LO\t\J' LE V EL I R A D W.A.SlE STOR., , / ./ HIGH LE V EL ST , OR. V.A..ULT, LID 55. VA ULT LINERS, (4) / . / EL 30', GROUND EL 2.8' (3) , FOOllNGS STACK SL A B R EFU EL. 'B LD G ,. SL A B TURBINE. BLDG. SLAB --. ---ESllMATED REMOVAL ITE M W ITHIN OUTSIDE PERCENT OF SWRRY WALL SLURRY WALL DISPOSAL SOILS AREA '1 8;170 CuR. 100% SOILS AREA 2 38 , 349 CuR. 24 , 0 1 5 CuR. 50% SO I LS AREA 3 27 , 836 CuF t 20 , 164 CuR. QUANlllY DISPOSED 8.170 CuF f. 31.18 2 CuF f. 11 , 334 CuFt. DI SCHA.R GE A L II-.JLET .. -.-41> TO DISCH.A, RGE , ......... C.A.NAL I"'ILET -----------------------

COOLING \h;A TER RETURN PIPES (TYP)_/ ,-A RE A .3 OF SOIL ! REMO V.A L 5' DEEP I 25% DI SPOSAL ,I I IE=4.46 \ BLOC K " Y" \ '-IE=4.40* L A IICHOR BLOCK " x" \"'IE=3.84' E X HIBIT C SOIL &: SUBSTRUCTURE E X C.A.VA.TIONS W ITHI t\1 UI'JIT 3 R A DIOLOGIC A L CO I\J TROL A REA Page 79 of 120

4.1.6 Canals

Decommissioning Project Report for Humboldt Bay Power Plant Unit 3 Rev. 0 The intake structure could not be surveyed for free release due to inaccessible internal surfaces.

Additional silting has occurred since the original estimate and is assumed to require disposal.

The material that has silted into the canal contains biological material and is not suitable a site backfill also due to the non-compatibility of the silty material.

Discharge Canal Outfall to the Bay -Asbestos bonded metal pipe must be removed since it presents both an environmental liability and is slightly radiologically contaminated..

In the discharge canal, the plan is to remove the silt that has built up after the circulating water pumps were turned off after the fossil plants shutdown in Sep 2010. Then to remove the silt that has built up during plant operations from the 1950s to the +1 ft. EI. from the construction excavation or at about -7ft. EI. Then there is a 0.5 foot excavation into the sides and bottom of the canal. Page 80 of 120 Intake and Discharge Canals r NEW FENCE I-':---y.

  • . ___ ,)
  • 1."#

(SEE SHEETS} " . -"<' ... . I' " \. \ .. "" \ .,>/ \. ;;. SEAWEED PfT 1."'All.

"."",,'--':A, SL."J3

--y,p> ,,_ ... " .. -... .,...*'-

SEAl'1EED PIT AFTt:R \" NEW

  • . -o\lER SLAB UNDER "\ \

eoKV SV;1TCHYARD PROJECT \ lH E UNIT J INTAKE SlRUCTURE IS A OOh1PARTMEN TED. REJNFORCEO CONCRETE BOX "rTl-i O\lI:.RALL OF' x 22.* 'lADE 2.4' DEEP. SIMILJ.R TO THE UUITS 1 .I\NO 2 S1RUC11JRES.

lHE TOP SLAB OF mE STRUCTURE IS AT ELEV.i\llCXIl

+12'. A PRECAST CONCRETE DECK IS PRO'..1DEO BETWEEN UNITS 2 AND 3 INTAKE STRUCT\JRES FOR ACCESS i'IITH A 25-TaII CAPACITY TRUCK FOR MAINTENANCE OF ll-iE BAR RACKS AND SCREENS. ll-iE INTAKE 5mUC11JRE WAS PROVlOE1l

""ll-i EMBEODED SHEET PILE SECnON TO ALLOW FUlURE EXP.4NSION Ih1tAEOIATELV ADJACENT TO ll-iE STRUCruRES. , f STRUCTURF CONCRFTF {GtFtj GRAVFI (CtF(t OTHFR {CtFt) INTAKE STRl"l1...IRES 2S 405 26,OLC rause) ACCESS SLAe (nc;tc'l) 24 RIP RAP ee5 10 !J\LS J<1 JQ , J.QO 1. 6 -10 TON P1UNGS ESllUAlEO AT 2.4 curt. 2. RIP RAP REMOVAL +/-6S5 CuR: FOR POS9BLE RE-USE AFTER FSS 3. 2009 <;PUC COST ESllf.'A TE AllO\,m I TAKE STRUCTU RE 10 REt,. AIN IN Pu\CE ."JIlO BACKFl LL INTAKE 1Mn-t Q..EAN Au... AERIAL \11 El'i OF ImAKE SJRUCTURE ltllfAKE STRUC1URE

&

'."All.

FROM F'ORtAER SEA,'(EED prr METftL BRIDGE FACED wi 'A'ODD PLftNf(S SLAB "

LEFT t& AREA BACKFILLED UI1JDER SDK\!

PROJECT FORMER PIT EXHIBIT 0 I SlRUCTURES C6NllL Page 81 of 120 OUTLET HEADWALL N.T.S. 4.1.7 Intake and Discharge Canals 11 4 FlO W Structure

  • L I' SECTION A-A N.T.S. .----------'1 16 12 D --4 0 § [u. 8 -1Z COOLING WATER DISCHARGE HEADWORKS t-J , T.S; ESTH li lATED REM OVA L SILT ABOVE O' FUTURE SILT SILT BELO W O' EXCAVATED SOIL 20.169 20 , 169 99J02 18.786 NOTE: E XCAVAT I O N SO I L T OTAL BASED O N 6" DE P T H E X HIBIT E 01 C.A N , fI,L REI'v'1 ED I A TI O N Page 82 of 120

4.1.8 Summary

Decommissioning Project Report for Humboldt Bay Pow e r Plant Unit 3 Rev. 0 Th e exca v a t e d volum es a nd di s po sa l v o lum es a re s umm a ri ze d on th e t a bl e s h o wn o n th e n e xt page. The volumes material excavated; volume of radioactive waste generated during the various decommissioning activities; and the disposal solutions are summarized in Tables 5.1 through 5.4. The reactor vessel and internals are categorized as large quantity shipments and, accordingly, will be shipped in reusable, shielded truck casks with disposable liners. In calculating disposal costs, the burial fees are applied against the liner volume, as well as the special handling requirements of the payload. Packaging efficiencies are lower for the highly activated materials (greater than Type A quantity waste), where high concentrations of gamma-emitting radionuclides limit the capacity of the shipping canisters.

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/ Material Handli 12932 52315 Caisson Waste Di 24037 Canal Remediation Waste Dis 20224 Page 83 of 120 TABLE 5.1 WASTE DISPOSAL

SUMMARY

-SO I L Area Excavated (ft 3) Reused Disposed Total C ai sson Soi I 75% 25% Sheet Pile and Nail Wall 317,030 237,773 79,258 100% Pre-Trench within RCA 62,736 62,736 -,-,---100% Pre-Trench outside of RCA 50,940 50,940 SI urry Wall 459,000 459,000

---""" v ol'. " ft.) -" 889,706 747,713 141,994 wt. (lb.) 115,661,780 97,202,690 18,459,155 Cire Water lines 100% less local Local spill soill vol. (cu. ft.) 237,257 213,257 24,000 wt. (lb.) 30,843,410 27,723,410 3,120,000 RCA (Excavated less disposed)

Upper Yard (19,608 sq.ft.)* 8,170 0 8,170 North Yard (13,870 sq. ft.) 62,364 31,182 31,182 South Yard (10,027 sq. ft.) 45,335 34,001 11,334 vol. (cu. ft.) 115,869 65,183 50,686 wt. (I b.) 15,062,970 8,473,823 6,589,148 Outside RCA (Excavated less disposed)

Radwaste Di scharge Li ne 1,050 971 79 North Yard Drainage System 27,940 19,300 8,640 LRW Bldg 26,928 22,440 4,488 vol. (cu. ft.) 55,918 42,711 13,207 wt. (lb.) 7,269,340 5,552,450 1,716,891 Subtotal vol. (cu. ft.) 409,044 321,151 87 , 893 Subtota l vol. (I b.) 53,175 , 720 41,749 , 682 11,426 , 038 Canals 100% I ntake canal Sediment 23,601 23,601 Discharge canal Sediment 99,702 99,702 Excavation 18,786 18,786 Silt buildup 20,169 20,169 Silt buildup (future) 20,169 20,169 Subtotal vol. (cu. ft.) 182,427 182,427 Subtotal vol. (lb.) 23,715,510 23,715,510 Totals (fe): 1,481,177 1,068,864 412,313 Totals (Ib): 192,553,010 138,952,372 53,600,703 Page 84 of 120 TABLE 5.2 WA STE D I SPOSAL S U MMAR Y -CONCRETE , I [rota I Volume (fe, Disposed Area i Recycle Total C aiss o n C on crete Caisson Upper Concrete 70,315 0 70,315 Caisson Lower Concrete 68,877 0 68,877 -Turbine Building Slab 75,600 0 75,600 Pre-Trench 13,095 0 13,095 vol. (cu. ft.) 227,887 0 227,887 wt. (lb.) 34,183,050 0 34,183,050 RCA Above Ground Structures 122,162 0 122,162 Below Grade 67,250 0 67,250 Embedded Pipe 3,509 0 3,509 vol. (cu. ft.) 192,921 0 192,921 wt. (lb.) 27,344,489 0 27,344,489 Outside RCA Misc Areas 467 0 467 Radwaste Discharge Li ne 2,308 0 2,308 Oily Water Separator 4,290 0 4,290 Circ Water Piping (Unit 1,2, & 3) 14,453 0 14,453 Inventory of Recyclable Concrete 10,151 10,151 0 vol. (cu. ft.) 31,668 10,151 21,517 wt. (lb.) 4,750,190 1,522,650 3,227,540 Subto t al vol. (cu. f t.) 224 , 590 10, 1 51 214 , 439 Subtota l v ol. (I b.) 32 , 094 , 679 1, 522 ,6 50 30,572, 0 29 Fossil Demolition Unit 1 Pad Concrete and Footings 16,283 16,283 0 Unit 2 Slab 77,139 77,139 0 Subtotal vo l. (cu. ft.) 93,422 93 , 4 22 0 Subtota l vol. (l b.) 1 4 , 013,300 1 4 , 013 , 300 0 Canals Intake Structure 34,390 34,390 0 Discharge Canal Inlet/Outlet Structures 2,248 0 2,248 Subtotal vol. (cu. ft.) 36,638 34,390 2,248 Subtotal vol. (lb.) 5,495,700 5,158,500 337,200 3 Totals (ft 1.: 582,537 137,963 444,574 Totals (Ib): 85 , 786,729 20,694,450 65,092,279 Page 85 of 120

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