ML19321B365
| ML19321B365 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/31/1988 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19321B366 | List: |
| References | |
| NUDOCS 8805110309 | |
| Download: ML19321B365 (75) | |
Text
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DECOMMISSIONING PROGRAM PLAN for the DRESDEN NUCLEAR POWER STATION UNIT 1
~~
~ ~ ~ COMMONWEALTH EDISON COMPANY March, 1988 Revision 2 O
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TABLE OF CONTENTS Page 1
i INTRODUCTION 2
1.
FACILITY OPERATION 2
1.1 Licensing and Construction History 4
l.2 Site Characterization 6
1.3 Facility Characterization 16 2.~
PROGRAM OBJECTIVES 2.1 Decommissioning Alternative Description 16 19 2.2 Cleanup Criteria 20 2.3 Licensing Summary 3.
PROGRAM MANAGEMENT AND ADMINISTRATION 21 3.1 Project Organization and Responsibilities 21 1.2 Organization and Responsibilities during 23 SAFSTOR Dormancy 25
~
4.
PROGRAM SCHEDULE AND COST 25 4.1 Program Schedule 25 4.2 Program Costs 26 4.3 Financial Assurance 32 5.
LICENSING ISSUES 5.1 Compliance with Current Regulation 32 5.2 License Modification 33 s
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5.3 Revised Technical Specifications 34 5.4 Residual Radioactivity 35 43 6.
DECOMMISSIONING ACTIVITIES 43 6.1 Safe Storage 43 6.2 Systems Status for SAFSTOR Period 46 6.3 Dormancy Period 47 6.4 Systems Status for Dormancy Period 49 -
6.5-Delayed Dismantlement 6.6 Site Release Criteria 50 53 7.
WASTE MANAGEMENT 7.1 Radioactive Materials 53 7.2 Radioactive Hazardous Materials 54 54 7.3 Hazardous Materials 7.4 Nonradioactive Materials 55 56 8.
REFERENCES Results of 1985 July and October Radiation Surveys at Dresden Unit 1 57 v'
l INTRODUCTION l
~
i Commonwea1th Edison Company plans to decommission the Dresden Nuclear Power Station Unit 1 by mothballing the facility in a safe storage condition until Dresden Units 2 & 3 are ready for r
decommissioning.
If an extended life program for Units 2 & 3 is not initiated, all three Dresden units will be decommissioned by removal of radioactivity and dismantling beginning in the year 2017.
This year is based on an assumed 30-year interval (30 years being the time duration that would provide the optimal benefit of reduced occupational dose versus storage time, e.g. Cobalt 60 will have decayed to less than 2% of its initial value), but will actually depend on the dates for shutdown for Dresden Units 2 and 3.
This Decommissioning Plan describes generic and site-specific
~
detailed information relative to project planning.
The objectives of the program are identified and the elements implemented to achieve those objectives are described.
Decommissioning is defined in the U.S. NRC's Proposed Rules as follows (Ref. 1):
"Decommission means to remove (as a facility) safely from service and reduce residual radioactivity to a level that permits release of the property for unrestricted use and
~ termination of..license."
This definition permits a two-phased approach:
mothballing upon permanent shutdown of the facility and delayed dismantling at a
later, pre-planned time.
This approach was selected by Commonwealth Edison because Dresden Unit 1 can be safely and inexpensively maintained in dormancy on the shared site with Dresden Units 2 & 3.
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FACILITY OPERATION 1.1 LICENSING AND CONSTRUCTION HISTORY Dresden Unit I was the first nuclear plant built by private industry.
It was a cooperative effort by Commonwealth Edison and a "Nuclear Power Group" (NpG) that 'ncluded six other electric utilities.
General Electric Company designed the plant and offered it at a fixed contract price of $45 million,
$15 million of which was contributed by NPG.
Commonwealth
~ Edison provided the remaining funding, the site, the electrical switchyard and other accessories.
Bechtel Corporation was the engineer-constructor.
Table 1.1 provides a chronology of Dresden Unit I licensing and construction history.
1.1.1 Operating History Dresden Unit 1 produced power commercially from July, 1960 to October 31, 1978, generating approximately-15,800,000 MWehr of electricity.
The unit was taken off-line on October, 1978 to backfit it with eg'uipment to meet new federal regulations and to perform a chemical decontamination of major piping systems.
While it was out of service for retrofitting, additional regulations were issued following the March, 1979
~
incident'at Three Mile Island.
The estimated cost to bring Dresden Unit 1 into compliance with these new regulations was more than $300 million.
Commonwealth Edison concluded that the age of the unit and its relatively small size did not warrant the investment.
The chemical decontamination of the primary system was, performed and 753 curies of Cobalt-60 and 12.4 curies of Cesium-137 were removed.
Decontamination was completed in September 1984 and preparations began shortly thereaf ter to mothball the f acility for decommissioning.-
,1,. l. 2 Abnormal Events Dresden Unit I had si3nificant problems associated with control rods and undertook a control rod blade replacement program from November 1960 through March 1961. In April of 1961, criticality testing was conducted with new control blades.
On June 2 of 1961, turbine generator operation was resumed.
The license
- power of the unit was increased from 630 MWt to 700 MWt
~~in September of 1962.
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t TABLt 1.1
?
DRESDEN UNIT 1 LICENSING AND CONSTRUCTION CHRONOLOGY.
j Date Activity i
March 31, 1955 preliminary Safety Report submitted to
}
Atomic Energy Commission Tay 4, 1956 Construction permit issued November 28, 1956 Site preparation work begun June, 1957 Major construction work begun-June 12, 1957 Final Safety Report submitted to Atomic Energy Commission
- March, 1959 Reactor pressure vessel shipped September 23, 1959 Construction completed October 13, 1959 Fuel loading begun October 15, 1959 First nuclear chain reaction initiated
... ?
November 16, 1959 Operating License issued i
April 15, 1960 First electricity generated s,
t Full power operation begun - 180,000 June 29, 1960 kilowatts (net)
August 1, 1960 Commercial operation begun l
October 12, 1960 Official dedication December 31, 1962 Achieved 73% annual capacity factor, exceeding Edison's best coal plant June 1, 1976 World's first test of chemical cleaning on i
portion of reactor.piping (Task K corrosion Test Loop)
October 31, 1978 Unit shutdown for modification to meet new regulations
~
September, 1984 Completion of world's first full-scale chemical cleaning of entire primary system October, 1984 Decision made to decommission unit
- Nuclear Regulatory Commission
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The unit had a history of minor steam leaks and erosion in steam piping in the early and mid-1960s - perhaps related to the use of saturated steam.
There were also fuel failures during the time of September through December of 1964 and other periods which, although not leading to off-gas releases above limits, did cause redistribution of radionuclides from the fuel to other parts of the primary system.
This higher rate of fuel failures at Dresden Unit I was not typical for the earlier BWR units.
During'other outages in the late 1960s, ultrasonic inspections were made on extensive sections of primary piping and welds because of concerns regarding intergranular cracking failures in some of the smaller 304 stainless steel pipi.ng.
i Several systems in the plant used admiralty brass (Cu-Ni) heat exchange surfaces, including the main condenser.
Most of these were taken cut of service and-replaced with stainless steel tubing.
In the sixth partial refueling, the condenser was retubed fr'om-admiralty brass to 304L stainless steel'.
The use of Cu-Ni surfaces did lead to translocation and deposition of corrosion production throughout the operating systems at levels above more modern units.
The use~of carbon steel in the secondary feedwater system may have also contributed to the elevated corrosion radionuclide levels.
These foregoing events led to the need to perform a chemical decontaminatior. of
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the primary system.
1.2 SITE CHARACTERIZATION Dr.esden Nuclear power Station Unit 1 (Dresden 1) is located on a 953-acre site near the confluence of the Des Plaines, Kankakee and Illinois Rivers.
The plant shares the site with -
Units 2 and 3.
l'. 2.1 Topography The topography of the site is essentially rolling prairie, with gentle slopes at maximum elevation differences of approximately 25 feet.
1.2.2 Soils and Geology
. LThe Dresden site lies in the Morris Quadrangle, where there is less than 200 feet between the highest and lowest points.
The bedrock in this area is almost at the surface, with a shallow covering of sandy loam soil.
This bedrock is in the Maquoketa formation of the Upper Ordovician series; the formation is of an upper limestone phase with a lower shale phase.
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i Underlying the Maquoketa formation is the i
Galena-platteville-formation of the Middle Ordovician I
series.
It is comprised of a dolomite upper layer and a limestone lower layer; this formation has a slight tilt to the east.
1.2.3 Hydrology 1.
Suface Hydrology The surface diainage is collected by a channel that runs through the center of the site and empties into the Illinois River.
There are several marshy arcas at the upper ends of the channel, indicating little surface percolation.
The closest river is the Illinois, circling around the north side of the site before proceeding in a southerly direction.
The Illinois originates within one half mile of the site's eastern boundary, at the confluence of the Des plaines and Kankakee.
i 2.
Groundwater Hydrology There are many shallow wells surrounding the site.
The Maquoketa formation yields negligible amounts of water and tapped by many domestic wells.
The lower aquifiers,
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fed from absorption areas in southern/central Wisconsin, exist under artesian conditions and have a general
,V southerly.slope.
However, the artesian pressure map indicates that the hydraulic gradient actually slopes in a general north-easterly direction due to heavy pumping in the Joliet and Chicago area.
l.2.4 Seismology The' best seismology data available (Loyol'a University) -
sh';ws that over the last 100 years less than a dozen earehqua'Aes ocurred within a radius of 150 miles from Chice,o.
There is nothing in the geological structure of the area surrounding the site to suggest that this zone would be susceptible to major earthquakes.
1.2.5 Climatology and Meteorolay The average rnnual wind velocity, derived from three local weather stations, varies from eight to eleven
~miles per hour from a south/southwest direction.
The average annual temperature ranges from 38 to 41 degrees minimum and 59 to 61 degrees maximum.
The average annual percipitation was 33 to 36 inches with an average snowfall varying from 21 to 34 inches.
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4 1.3 FACILITY CHARACTERIZATION r
The.Dresden site consists of three boiling water reactors (BKRs).
Dresden.1 had a gross output of 210 MWe, while the The output of Units 2 and 3 totals approximately 2660 MWe.
description of the general plant, plant structures and systems l
is included herein.
1.3.1 General Plant Description Dresden 1 consists of a General Electric (GE) dual-cycle I
BWR and a GE dual-admission turbine unit with the
~
necessary support and auxiliary systems.
The reactor vessel, with its hemispherical ends, totals 41 feet in height and 12 feet, 2 inches in diameter.
I The reactor containment is a sphere, constructed of steel plates of required curvature and butt welded i
together.
Other main process buildings include the Turbine Building for housing the power extraction -
system, the Fuel Building for storing and hendling new/used fuel, and the Radioactive Waste Facility.
l.3.2 Plant Structures The layout of the plant structures is shown in Figure 1.1.
A brief description of the main plant structures
~
is conf&ined herein.
1.
The Turbine Building for Unit 1 is situated west of the reactor building; at its west end is the common Unit 2/3 turbine building (see figure 1.1).
2.
The Fuel Handling Building is south of the reactor building, with the new fuel storage building to the east.
To the west is the shop and warehouse.
3.
The Control Room (shared facility for Units 1, 2 and. 3 ) -
is located at the juncture of the Unit 1 turbine building and the Units 2/3 turbine.building.
The Access Control Building is located at.the south end of the Unit 1 turbine building.
Dresden modification M12-2/3-87-05 is being proposed to separate the Unit 1 Control Room from the Units 2 and 3 Control Room. Necessary Unit 1 controls will be re-located in the Unit 2 and 3 Control Room area.
4.-
The _Radwaste BuiIding is located 150 feet due east of
- the Fuel Handling Building.
Its controlled area is 160 feet wide by 200 feet deep.
The types of waste processed include spent damineralizer resins and filter media.
5.
The HPCI Building is due ecst of the Reactor Building and north of the Radwaste Building.
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FIGURE 1.1 PLANT STRDCTURES EbbWW 9864f
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Tha Crib Housa is northwast of the reactor building and north of tha heating boiler house which adjoins the north side of the Unit 1 turbine building.
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The Off-Gas Building is between the crib house to the west and the fuel oil storage tanks to the east.
It is directly'north of the Reactor Building.
8.
Entrance to the plant is via the Gatehouse, which is south of the Reactor Building.
9.
To the west of the Gate House is the new Administration and Training Center.
The visitor's Center lies southwest of the Reactor Building and northwest of the Gatehouse.
1.3.3 Plant Systems 1.
Reactor and Accessories The Reactor Vessel is made of low-alloy steel, clad inside with stainless steel.
The shell thickness opposite the nuclear fuel is 5-5/8" (including the 3/8" cladding).
A drawing of the reactor vessel is pr5sented in Figure 1.3.
The Nuclear Core of the reactor has space for 488 fuel assemblies (never loaded in excess of 464).
Each assembly.consists of a zircoloy channel with an arrangement of 35 or 36 fuel rods in a 6X6 matrix (sintered UO2 pellets with an average of 2.24 wt percent per bundle average enrichment) encased in zircoloy cladding.
The Control Rod Drive System is comprised of 80 control rod drive mechanisms, each fitted with cruciform control rods made of stainless steel and boron carbide; each red contains 44 tubes of boron compacted to 70% of theoretical density.
The Liquid Poison System is manually operated and is shown in Figure 1.4.
It basically consists of a reservoir containing Sodium Pentaborate, a pressure equalizer and a feedli'e running from the reservoir to n
the sparger system.
The Fuel Handling System involves loading and unloading the reactor core through approximately 40 feet of water
, using a fuel grapple crane for lifting.
Fuel is
- transfered from the Reactor refueling canal located in
- the Sphere to the bottom of the transfer pool in the -
Fuel Building through a vertical transfer tube.
The transfer baskets hold up to 16 fuel bundles each.
Fuel moves horizontally in a transfer basket through a canal in a level below grade outside the enclosure (see Figure 1.5). Due to the possibility of fuel.rupture, provisions were made to remove the ruptured fuel from the sphere in i
a sealed container.
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2.
Steam Supply System The Steam Supply System is comprised of a steam
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Thera are four separate recirculation loops, each consisting of a secondary steam generator, recirculating pump and secondary valves.
Each loop can be
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independently isolated.
The steam generator and associated pump units are installed in separate shielded compartments and may be isolated from the remainder of the system.
3.
power Extraction System As indicated in Figure 1.2, the saturated primary and secondary steam enter the dual-a.dmission turbine f.com the main steam lines which connect the reactor plant to the turbine.
The primary steam enters the first stage of the high pressure turbine, while the significantly lower pressure secondary steam (approximately 500 psig) enters the ninth stage of the high pressure turbine.
The tandem compound turbine consists of high pressure, intermediate pressure, and double-flow low pressure sections.
The three sections are on one shaft, connected to the generator.
The generator is rated at 245,000 kVA, at a power factor of 0.85, and 30 psig hydrogen cooled with field excitation by either of two exciter sets with automatic voltage regulation.
4.
Reactor Recirculation Water Cleanup System
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The water cleanup system consists of two identical loops.
Each loop contains a booster pump, a regenerative and non-regenerative heat exchanger, and a demineralizer.
The regenerative heat exchanger uses the recirculating water from the demineralizer for cooling.
5.
Condensate System The condensate system includes the condensate pumps, steam jet air ejector condensers, gland steam exhauster condensers, condensate demineralizers, chemical feeders,
_ rondensate storage tank, and condensate drip tank systems.
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Electrical System
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This system is a "Unit System" in whirit the generator, main power Transformer 1, and statica service Transformer 11 are all solidly connected together.
Station service Transformer 12 is connected to the 138 kV bus and supplies half the auxiliary power with Transformer 11 providing the other half.
Reserve station service Transformer 13 supplies a limited amount of auxiliary power in the absence of normal power.
7.
Control and Instrument System The devices used for control and instrumentation are i
extensive and include combinations of hydraulic, pneumatic, mechanical and electrical components interconnected in a single device.
8.
Fire Protection System Fire protection services are provided by a pressurized water system serving most areas throughout the buildings and grounds, and portable extinguishers at strategic locations.
This system is connected to Units 2 & 3 via Unit 2.
The Unit 1 Diesel Fire pump is.located in the Unit 1 Crib House.
9.
Air Systems (s*
Instrument air is connected to Units 2 & 3 and is provided by an air compressor situated in Unit 1, with two additional compressors for backup and maintenance operations.
The instrument air is free of moisture, oil~
and grit.
Compressed air for general service is supplied at 100 psig for distribution throughout the
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plant and yard facilities from the service air system.
10 HVAC System The heating steam supply system fe'eds steam to provide heat.and various other services.
Each major building has its own ventilation system.
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PROGRAM OBJECTIVES Dresden Unit I will be prepared for decommissioning by maintaining it in the Safe Storage (SAFSTOR).mode for up to 30 years, or until Units 2 & 3 are decommissioned and dismantled.
At the end of the safe storage period, Unit 1 will be decommissioned by dismantling (DECON).
The' objectives of the decommission ing program are:
1.
To maintain Dresden'1 systems and structures needed to support operation of Units 2 and 3.
2.
To secure all nonessential Unit 1 systems and structures to prevent deterioration and ensure there wil,1 be no potential for release of contained radioactivity.
To dispose of radioactive and hazardous wastes remaining 3.
on-site in preparation for the SAFSTOR dormancy period.
4.
To store spent fuel temporarily on-site until a federal repository is available for permanent disposal.
5.
To decontaminate plant floors and areas enraute to or adjacent to operating equipment or repetitive survey/monitoring locations.
To prepare a radiological baseline characterization of the 6.
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plant, and a menitoring ano surveillance program for the SAFSTOR dorman;r t' 'od.
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7.
To devitalize all a:eas no longer containing vital equipment and amend the Security Plan accordingly.
2.1 DECOMMISSIONING ALTERNATIVE DEECRIPTION The SAFSTOR decommissioning alternative represents the minimal effort required to prepara the facility for protective storage and to provide safety to the public from residual radioactivity-remaining at the site.
The facility is left essentially intact and all structures are maintained in a sound condition.
Systems not required to be operational for maintenance/surveillance during the SAFSTOR dormcncy period will be drained, de-energized and secured.
Minimal cleaning or removal of loose contamination and/or fixation and seriing of remaining contamination will be performed.
All access to contaminated areas will be sealed or sufficiently secured to provide controlled access for inspection and maintenance.
The o9erall decommissioning process of SAFSTOR followed by 4
delaye'd'dimantling is organized into five separate periods,'
including:
Period 1:
SAFSTOR Operations Period 2:
Dormancy Period 3:
Delayed Dismantling Engineering and Preparations Period 4:
Decommissioning Operations and License Termination
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Period 5:
Site Restoration Yt'-
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i 2.1.1 Period 1:
SAFSTOR Operations 7,.
In general, Period 1 activities include the engineering and planning effort to revise the Dresden Unit 1 Technical Specifications for the safe storage period and obtain a possession-only license (POL) amendment to the operating license.
The POL will be issued by the U.S.
NRC in accordance with Title 10 of the Code of Federal Regulations Parts 30, 50, 51 and 70.
The POL will require that the plant be.maintained in safe storage in accordance with the revised Technical Specifications.
The POL was obtained for Dresden Unit 1 in July, 1986 when Operating License (No. DPR-2) was amended to a possess-but-not-operate status (Amendment No. 36).
The preparations for SAFSTOR include the activities described herein:
Drain, de-energize ar. ! secure all noncontaminat-ed, non-essential systems.
Remove filter e'ements and demineralizer resin beds for shipment and burial.
Drain reactor vessel; reactor vessel internals will remain in place.
DraiN, de-energize and secure all contaminated systems; decontaminate as required.
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Prepare the spent fuel storage pool for long term storage of fuel.
Provide for maintenance of fuel pool water chemistry.
Lighting, fire protection, HVAC and alarm systems will be maintained, as required, for continued use during SAFSTOR dormancy.
e Clean loose surface contamination from building
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access pathways.
Access to radioactive or contaminated areas will be controlled in accordance with normal Station 4
Procedures.
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2.1.2 period 2:
7ormancy Activities required during the dormancy period for the SAFSTOR alternative include a 24-hour guard force, preventive/corrective maintenance on area lighting, general building maintenance, heating and ventilation of buildings, routine radiological inspections of J
contaminated buildings, maintenance of structural integrity, and an environmental and radiation monitoring program.
Maintenance and equipment inspection activities are provided by the full time utility maintenance staff.
Their duties are to maintain the facility in a safe condition, to provide adequate lighting, ventilation, and heating, and to perform periodic preventive raintenance on essential equipment.
An environmental surveillance program will be carr,ied out during the dormancy period to prevent releases of radioactivity to the environment; any such releases will be'identified and quantified.
The environmental surveillance program is a modified/abbreviated version of that carried on during normal plant operations.
primary physical security is provided by the Dresden Units 2..&.3 security force on a 24-hour basis for the duration of the dormancy period.
Security during thir' period is primarily conducted to prevent unauthorized
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entry.
Security detection and notification systems will be used during SAFSTOR in accordance with the station Security plan.
Liaison with local law enforcement agencies will be maintained and their assistance requested as necessary.
2.1.3 period 3:
Delayed Dismantlino Engineering and preparations This work will presumably be performed concurrently or requentially with the decommissioning of Dresden Units 2
& 3.
In general, all reactor dismantling engineering, planning and site preparations occur during this period.
Utility and Decommissioning Operations Contractor (DOC) management staffs will be selected and mobilized on-site.
Decommissioning activity specifications and detai'led procedures will be prepared for removal.of systems, components and structures.
The
~ overall decommissioning sequence will be developed. -
~~preparations will include selection cf specialty contractors, long-lead tooling and equipment, arrangements for radioactive waste disposal and construction of site temporary facilities for the workforce.
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2.1.4 Period 4:
Decommissionino Operations and License Termination The decommissioning operations during this period will be directed at removing all radioactivity from systems, components and structures.
Minimal chemical decontamination will be required since most short-lived radionuclides will have decayed to levels low enough to The permit removal with low occupational exposure.
reactor vessel and internals will be segmented, packaged, shipped end buried.
Similarly, the steam drum, steam generators and all associated pumps and piping will be removed for controlled burial.
All components and structures with radioactivity levels above US NRC Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors", Table 1 (Ref. 2) lim.its will be removed.
The facility will be surveyed to certify the removal of rafk activity, and the license may be terminated.
2.1.5 Period 5:
Site Restoration Following completion of the decommissioning operations, site restoration activities may begin.
These involve demolition and removal of remaining structures although
~~
it is dipscted that the switchyard will remain.
All building foundations will be backfilled.
Site areas affected by the dismantling activities will be cleaned
(
up and the plant site will be graded and restored.
A final dismantling program report will be prepared and submitted to the U.S. NRC.
2.2 CLEANUP CRITERIA The criteria to be applied for determining the disposition of -
radioactive materials removed from the site for unrestricted use are either SmR/hr above background at one meter from tP3 surface or 10 mRem/year above background, considering
'r'easonable proximity and occupancy.
Permissible surface contamination levels will be in accordance with U.S. NRC Regulatory Guide 1.86, Table 1 therein.
The same criteria will be applied for termination of the licease during delayed dismantling.
For the safe storage period, all accessible areas within the f acility having radiation levels in excess of 5 mRem/hr will be Criteria markedr shielded or protected by physical barriers.
for disposition and disposal of hazardous and toxic wastes including asbestos will be in accordance with U.S. EPA Title 40, Part 61 (Ref. 3).
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2.3 LICENSING
SUMMARY
The licensing objective of the Dresden Unit 1 decommissioning l
' program is to first obtain a POL amendment to the operating license.
This FOL will require that the facility be maintained j
in safe storage in accordance with the provisions of the
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Revised Technical Specifications.
These specifications identify the necessary criteria, tests, limiting conditions of operation, and surveillance requirements; they have been d
revised to reflect the shutdown status of the facility.
The POL was obtained for Dresden Unit 1 in July, 1986 when Operating License (No. DPR-2) was amended to a possess-but-not-operate status (Amendment No. 36)
The POL will remain in effect until completion of Period 4, "Decommissioning Operations," when all radioactive material will have been removed from the site.
Upon inspection and certification by the NRC that radioactivity above Regulatory Guide 1.86 Table 1 limits has been removed, the NRC will terminate the facility license.
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PROGRAM MANAGEMENT AND ADMINISTRATZON Commonwealth Edison has identified a decommissioning project team to manage the program to prepare Dresden Unit 1 for SAFSTOR.
The team consists of a Decommissioning Project Manager responsible for the on-site project staff and general office project staff.
The Project Manager will also be responsible for all subcontractors.
3.1 PROJECT ORGANIZATION AND RESPONSIBILITIES The Project Manager will report directly to the Vice President-BWR Operations.
This will ensure that high level management attention will be available to commit personnel and resources to properly and safely prepare the plant for decommissioning.
The overall organization is shown in Figure 3.1.
3.1.1 Vice President - BWR Operations The Vice President - BWR Operations is responsible,.for the authorization and approval of the decommissioning project.
He has the authority to commit personnel and resources to prepare the plant for SAFSTOR safely, on schedule and within budget.
The Vice President - BWR Operations is also the chai rman of the General Of fice Project Team.
He is responsible for reviewing the
'Decommissioning Plan, proposed possession-only license (POL) amendments, and the Revised Technical Specifications.
3.1.2 Proiect Manager The Project Manager has the responsibility to develop the Decommissioning Plan and POL amendment application with Revised Technical Specifications.
These responsibilities include:
identifying and coordinating the prcject team participants developing a decommissioning plan schedule and budget developing a decommissioning program cost estimate I
and schedule preparing for and obtaining Commonwealth Edison approval of the Decommissioning Plan 1
meeting with the NRC and other regulatory agencies to ensure compliance with regulatory requirements resolving NRC comments on the Decommissioning Plan, POL amendment participating on the General Office Project Team to review the Decommissioning Plan
& ~
3.1.3 On-Site Project Team The On-Site Project Team has the responsibility to 4
review and prepare the Revised Technical Specifications for the SAFSTOR POL amendment.
They will participate in the General Office Project Team review of the Decommissioning Plan.
This team will also be responsible for implementing the plant preparations for SAFSTOR.
Most of this work can be performed by on-site personnel.
Some of the work may be contracted.
3.1.4 General Office Proiect Team The General Office Project Team has the responsibility to prepare the POL amendment with Revised Technical
+
Specifications for submittal to the NRC.
They are also.
responsible for the development of the Decommissioning Plan, cost estimate and schedule, funding plan and Environmental Report.
The resources available from this General Office Project Team constitute all the technical support needed to prepare or review the submitt'al- '
documents.
3.1.5 Consultants and Contractors Specialty consultants and contractors will be used to assist-Commonwealth Edison in preparing documentation and performing-site preparations for SAFSTOR.
The development of a detailed site-specific cost estimate and schedule for decommissioning was prepared using industry accepted guidelines.
Consulting assistance to Commonwealth Edison was provided in the-development of the Decommissioning Plan.
Specialty contractors may be used to perform spot decontamination, waste packaging and disposal services.
Additional services may be required to provide additional or modified security monitoring equipment, and environmental surveillance data acquisition equipment.
The consultants will report to the Project Manager directly.
Specialty contractors will report to-the Station Manager.
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E 3.2 ORGANIZATION AND RESPONSIBILITIES DURING SAFSTOR DORMANCY The'Station Manager will have responsibility for ensuring maintenance and surveillance during SAFSTOR dormancy, and for preparing.quarterly surveys of radiation levels..Annual status reports must be submitted to the NRC.
Work activities for maintenance and surveillance will be performed primarily by Commonwealth Edison personnel on site or from other Stations.
If necessary, contractor assistance will be used to perf orm services beyond the capabilities or availability of Commonwealth Edison personnel.
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i DECOMMISSIONING PRGIECT ORGAEIZATION e
VICE PRESIDENT -
BWR OPERATIONS PRGIECT MANAGER L
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ON-SITE PROJECT TEAM GEWERAL OFFICE PROJSCT TEAM CONSULTANTS/SUBCONTRACTORS I
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-Station Manager
~BWR Engineering Deconnaissioning Plan Consultants
-Operating Engineer
-Licensing
-Tech Staff Supervisor
-Financial Planting
-Rad-Chem Supervisor
-Environmental AZfairs
-Security Administrator
-Production Services Department l
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4.
PROGRAM SCHEDULE AND COST The overall program and schedule for decommissioning Dresden Unit 1 consists of five periods starting with SAFSTOR-Mothballing and ending with Site Restoration, as described in Section 6 herein.
The
^
decommissioning program costs were estimated in a site-specific.cost estimate (Ref. 4) for each period of the program.
A summary of the estimated costs is included in this section.
A financial plan has been developed to assure decommissioning funds will be available to safely decommission and dismantle the facility.
A brief description of the plan is described in this section.
4.1 PROGRAM SCHEDULE An overview of the program schedule showing major milestones for prompt Removal/Dismantling and Mothballing is shown in Figure 4.1.
Delayed dismantling will reflect an abbreviated prompt dismantling sequence.
The program consists of SAFSTOR-Mothballing, Dormancy, Decommissioning preparations, Decommissioning Operations and Site Restoration.
The Dormancy period is shown on an assumed 30-year interval, but will actually depend on the dates of shutdown for Dresden Units 2 &
3.
Table 4.1 shows the durations in years for each period of I
--- the program. --
4.2 PROGRAM COSTS ci A summary of the decommissioning costs for each period of the program is shown in Table 4.2.
The costs are in 1985 dollars and include 25*5 contingency for all periods except Dormancy l
(the work activities for Dormancy are considered expense items
~
and shall be funded from appropriate Station budgets.
These activities are well defined and there is little cause for variability).
These estimates do not include any allowance for.
inflation, interest or federal tax effects; these factors are accounted for in the Financial plan described in Section 4.3 herein.
The estimate is based on the assumption that all work activities will be performed by a Decommissioning Operations Contractor (DOC) reporting to the Commonwealth Edison's decommissioning project Manager and team.
The costs include all management, engineering and planning, decontamination equipment and structure removal, packaging, shipping and burial of reipoved materials.
Collateral costs such as equipment rental, health physics supplies, nuclear liability insurancs, site property taxes and staff relecation have plant energy, been accounted for and distributed to their respective periods of expenditure.
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4.3 FINANCIAL ASSURANCE Commonwea'lth Edison Company ("Edison") currently uses an internal funding method commonly referred to as the negative net salvage method for accumulating decommissioning costs.
The Illinois Commerce Commission ("Commission") in a 1980 order directed Edison to prepare special accounting procedures for the amounts provided for end-of-life decommissioning costs of its nuclear plants.
In that same year the Chief Accountant of the Commission approved Edison's accounting procedures.
Edison's negative net salvage method treats decommissioning costs the same way that Edison treats all other plant removal costs; that is, estimated decommissioning costs are recovered throt:gh depreciation charges over the life of the plant.
The funds collected through depreciation charges are used by Edison to satisfy its financial and other daily ]bligations, including investment in bondable property.
This use of the funds benefits Edison's ratepayers through reductions in the rate base which result from increases in the accumulated provisions for depreciation.
- Thus, this method permits the ratepayers to earn effectively the same rate
~ of return as Edison earns on its rate base.
At the time of decommissioning, Edison will use conventional financing methods to pay the costs incurred.
The assurance provided by the negative net salvage method is based on-Edison's ability--to obtain external financing at the time decommissioning funds are required.
Several factors provide the necessary confidence in that fund raising ability.
Historically,
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Edison has been able to raise the funds needed to meet its obligations.
Currently, Edison's senior securities are rated Baal by Moody's Investors Service and BBB+ by Standard & poor's --
ratings that allow Edison to raise new money in capital markets at-reasonable rates.
I r. the future, one of Edison's primary goals is to improve these ratings
'.o the AA level, thus ensuring financial stability and even stronger capabilities for raising additional
~
funds.
Although Edison's future financial position cannot be predicted precisely for 20 to 30 years from now, Edison is currently completing a large construction program which will provide adequate generation capacity for several years.
Thus, a declining construction budget is forecasted for the next seve al years.
During that period, it is estimated, given adequate rate relief, that the majority of Company's cash requirements will be internally generated.
For these reasons, the negative net salvage method, by permitting reinvestment of decommissioning funds into bondable property should provide reasonable assurance that decommissioning funds will be available when needed.
Edison believes that all the alternatives proposed by the NRC for' funding decommissioning costs provide reasonable assurance that funds will be available as decommissioning costs are incurred.
The main difference between these alternatives is the degree of surety which each method provides.
Therefore, in choosing from among the alternatives, the question is what additional cost level to be borne i
t by Edison's ratepayers is justified for that additional degree of assurance.
Ratepayer cost is a very sensitive issue today.
Great strides are underway by regulators and utilities alika to ensure reliable service at the least cost.
Therefore, the total cost of each of the alternatives has to be a significant factor in selecting a funding method.
Arguably, the method which provides the highest degree of reasonable assurance is the prepayment external funding method.
In terms of present valued revenue requirements, however, this method is much more expensive than the internal sinking fund method.
The total present valued revenue requirements of the external sinking fund method, although significantly less expensive than that of the prepayment external funding method, are still significantly more expensive than Edison's current internal funding method.
Edison believes that the small additional degrees of assurance provided at significant increases in the cost to ratepayers are not'warranted.
Therefore, absent any showing that Edison will not be able to carry out conventional financing to meet the decommissioning costs of the plants, Edison believes that the internal methods, and part'icularly the negative net salvage method, r.ot only provide reasonable assurance that funds will be available at time of decommissioning, but also result in a lower cost to Edison's ratepayers.
Edison is a large, fully integrated electric utility.
For such a utility, the funds necessary for decommissioning any one unit are small relative to the utility's overall size, financial condition and cash flow.
The estimated e -ts of decommissioning one unit are
(_
approximately $150 million (sw.tud in 1987 dollars) as detailed in Table 4.3.
A utility that can afford to build a 1,100 megawatt nuclear generating unit and to incur costs of approximately $335 million a year to operate and maintain it can be relied upon to bear the $150 millio.1 cost of decommissioning.
Thus, there'is no need to establish a separate, external fund to guarantee the availability of decommissioning funds when needed.
Indeed, for the reasons discussed above, an external fund would penalize Edison's customers -
by requiring them to pay decommissioning costs significantly higher than is warranted.
For these reasons, Edison believes that its curreh't method of funding decommissioning costs internally provides an equitable and adequate accumulation method for decommissioning costs.
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l MOTIIBALLING SCllEDULE l
i NG Activity 0
12 24 36 48
.60 72 1.
Process wastes 2.
Request possession-l only license 3.
Drain and secure con-taminated systems i
4.
Prepare surveillance and monitoring systems 5.
Decontaminate building pathways 5.
Radiation survey and post radiation signs 7.
Secure all building accesses; prepare final report i
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PROMPT REMOVAL/DISMANTLING SCitEDULE Activity, '
MONTilS 0
12 24 36 48 60 72 1.
Remove fuel from site and process j
i wastes 2.
Prepare dismantling plan for NRC 3.
Prepare activity specifi-cations and procedures 4.
Remove and dispose.of plant systems 5.
Segment and dispose of vessel and internals 6.
Remove and dispose of tur-bine generator/condensers 7.
Demolish and dispose of primary containment interior 8.
Radiation survey for resi-dual contamination 9.
Break secondary contain-ment; remove crane 10.
Demolish remaining reactor building I
11.
Demolish remaining build-ings and structures 12.
Backfill, grade and landscape site i
13.
Final radiation survey; report to NRC 14.
Terminate license i
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.t TABLE 4.1 SCHEDULE ESTIMATE
SUMMARY
Duration Expected Date Activity (years) of Completion Period 1:
SAFSTOR Mothballing 1
Period 2:
Dormancy 30
- December, 2017 Period 3:
Delayed Dismantling Preparations 0.5 June, 2018 Period 4:
Decommissiong Operations 4.5 December, 2022 Period 5:
Site Restcration 1.5 June, 2024 Actual duration will depend on the decommissioning schedule of-Dresden Units 2 & 3.
- Approximately one (1) year from date of NRC approval of Decommissioning Plan.
s TABLE 4.2
SUMMARY
OF DECOMMISSIONING COSTS Activity Estimated Cost Period 1:
SAFSTOR Mothballing
$~ 6,860,300 Period 2:
Dormancy (30 years) 11,700,000 Period 3:
Delayed Dismantling Preparations 9,651,000 Period 4:
Decommissiong Operations 61,334,000 Period 5:
Site Restoration 18,570,000 Total
$108,115,300 All costs are in 1985 dollars and include 25% contingency (Dormancy has no contingency)
TABLE 4.3 Commonwealth Edison Company r~ '
Estimated Decommissioning Costs For Operating or Recently Retired Nuclear Generating Units Decommissioning costs are comprised of several components including labor, materials, equipment, specialty contractors and license fees.
Decommissioning cost estimates for each of the Company's currently operating or recently retired nuclear generating units are as follows:
($ millions)
Per Unit Total Dresden 1
$110 110 Dresden 2 & 3 170 340
__Quad Cities 1 &_2 (C.E. Portion - 75%)
125 250 LaSalle County 1 & 2 190 380 Zion 1 & 2 150 300
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Byron 1 & 2 150 300 Braidwood 1 150 150
$ 1,830 These estimates were made in November 1986 and are stated in 1987 dollars.
These figures were determined using information develo'ped in site specific studies of comparable nuclear units and adjusted for Edison unit size and characteristics.
The costs for Dresden Unit 1, a substantially smaller unit than Edison's other units, are based on a study performed in November 1985 by TLG Engineering (a consulting firm specializing in analysis of commercial reactor decommissioning).
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5.
LICENSING ISSUES g,
The decommissioning of Dresden 1 will require conformance to current federal and state regulations.
The preparations require modifications to the existing license, and assurance that the process will protect public health and safety.
5.1 COMPLIANCE WITH CURRENT REGULATION The decommissioning of Dresden 1 will be performed in accordance with current regulatory requirements, guidance and standards as prescribed by the USNRC, USDOT, US EPA and the State of Illinois.
A list of applicable regulatiot:s is included herein:
NRC Reg.
Guidance 10 CFR 19 Notices, instructions and reports to.
workers; inspections 10 CFR 20 Standards for protection against radiation 10 CFR 30 Rules of general applicability to domestic licensing of source material
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Domestic licensing of source material 10 CFR 40
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10 CFR 50 Domestic licensing of production and utilization facilities 10 CFR 51 Licensing and regulatory policy and procedures for environmental protection 10 CFR 70 Domestic licensing of special nuclear material 10 CFR 61 Licensing requirements for land disposal of radioactive waste.
10 CFR 71 Packaging and transportation of radioactive material.
10 CFR 73 Physical protection of plants and materials 1
10 CFR 140 Financial protection requirements 10 CFR -15 0 Exemptions and continued regulatory authority in agreement states under Section 274 10 CFR 170 Fees and facilities and material licenses and other regulatory services under the Atomic Energy Act of 1954, as amended
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Regulatory Termination of operating licenses fer Guide 1.86 nuclear power plants Proposed Decommissioning criteria (2/11/85) for Rule nuclear facilities U.S. DOT Regulations 49 CFR 170-190 Hazardous material regulations - DOT U.S. Regulations 40 CFR 190 Environmental radiation protection standards for nuclear power operations 5.2 LICENSE MODIFICATION As part of the decommissioning of Dresden Unit 1 the operating liccese needs to be amended to a "Possession-Only License" (POL).
The POL was obtained for Dresden Unit 1 in July, 1986 when Operating License (No. DpR-2) was amended to a possess-but-not-operate status (Amendment No. 36) 5.2.1 Criticality Prevention Description To prevent criticality, fuel has been removed from the s
reactor core and placed in the spent fuel pool.
As stated in the suggested Revised Technical Specifications, the fuel pool water level shall he recorded daily; minimum water level has been established at 18 feet.
The suggested revised Technical Specifications also prohibit fuel from being loaded into, the reactor core.
l 5.2.2 Safety Analysis Since the spent fuel is in racks of'the correct geometry (to prevent criticalities) and under water at all times (to provide shielding), criticality should not occur.
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5.3' REVISED TECHNICAL SPECIFICATIONS t
Changes will be made to the Dresden Unit 1 Technical Specifications to reflect the POL strtus of Dresden Unit 1.
5.3.1 Justification The changes described in Section 5.3.2 should not involve significant hazards as defined in 10 CFR 50.92
-l since all.fuel has been taken out of the core and placed into storage for eventual disposal.
The changes will be i'
reviewed to ensure that the health and safety of workers i
and the general public are not adversely affected.
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5.3.2 Overview The change to a POL status entails several changes,.
within the Technical Specifications of Dresden Unit 1.
The following is a brief overview-of those sections of l
the specifications that will be changed.
i
- Rewording of Facility Operating Licen:ce No. DpR-2 to possess and maintain but not to operate the facility. (The FOL was obtained for Dresden Unit 1 in July,_19.86 when Operating License'(No. DpR-2) was, amended to a possess-but-not-operate status [Amendment l
No. 36])
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- Deletion of those systems and components that will no longer be used
- Changes to operating descriptions may be made for' those systems remaining in service to protect the health and safety of the public
'- Surveillance frequencies and parameters will be changed for systems/components remaining in service l
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5.4 RESIDUAL RADIOACTIVITY In August, 1932 Pacific Northwest Laboratory (PNL) conducted a survey at Dresden Unit 1 to estimate the residual radioactivity.
This estimate did not include:
neutron-activated parts of the pressure vessel and the biological shield, or radioactivity in residues and resins in tanks and pumps, or the spent fuel i
stored on site.
However, esticates t'or the neutron-activated l
components were prepared in 1937 by TLG Engineerig, Inc., a consultant to CECo, using the ORIGEN2 cocputer code.
Table 5.4
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shows the reactor vessel and internals, and biological shield concrete radioactive inventory as of 1988.
The results of the PNL survey are shcwn on Table 5.1, Residual Radionuclide Concentration in Corrosion Film:, Table 5.2, Residual Radionuclide Inventories in Various Operating Systems, and Table 5.1. Total Residani Radionuclide Inventory.
j 5.4.1 Final R:*iatien Survey t
A radiation survey was conducted by Commonwealth Edison's health physics personnel in July and October of:1985.
The surveys show dosa rates in mR/hr, smears counted for rem vable alpha and ceta-gamma, surface contamination and air sample results.
Results are shown in Attachment A.
~~
Concreti core samples and sediment/scil samples were taken as part of the PNL survey conducted in August 1982.
l The concentrati;ns in the first segment (0-1 cm) of all concrete core samples were above Regulatory Guide 1.86, l
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Table I limits.
The second segment (1-2 cm) in all cores except the Make-up Demineralizer Rcom were also abr.ve the reccc.mended limit.
Core sample results are showr. cn Table 5.5.
i Several soil semples obtained from the exclusion area j
strand Dresden Unit 1 either approach Or exceed the i
In it cf the Urett Envi r onment al Irpict Statement on decommissioning of nuclear facilities.
The results are shown as Table 5.5.
i 5.4.2 Radiation Protection Program i
During the SAFSTOR and decommissioning periods, a radiation protection program will be maintained to
.procide for the health and safety of workers and the
.general public.
The program will prcvide the necessary monitoring and centrol of radiological conditions.
5.4.3 Industrial Safety and Hvciene Procram I
Commonwealth Edison Company has an industrial safety program that will be used during the SAFSTOR and decstmissioning period.
The program includes accident preventirn, nazardous material control, and nazardous raste canagement.
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TABLE 5.3 TOTAL RESIDUAL RADIONUCLIDE INVENTORY Radienuclide (b}
Half-l.ife (years)
Inventory (curies)
August, 1982 Oct. 31, 1978 (a)
(ShutdoEn')
60 o S.27 660 1,080 C
55 e 2.7 200 650 F
63N1 100 110 110 65 n 0.668 9.3 450 Z
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134Cs 2.06 0.060 0.21 238 u 87.7 0.059 0.061 P
241Am 432 0.046 0.046 239-240Pu 24,100 0.030 0.030 242 m 0.446 0.0085 2.9 C
Total I,030 2,350 (a) Excluding neutron-activated pressure vessel and internals, biological shield, concrete surfaces, residues, sludges and'resins in tanks and smps, and spent fuel.
(b) Other long-lived radionuclides specifically Itsted in 10 CFR 61,(9) e.g.,
Nd, 99 c, and IIII, were not included in the inventory because of their 94 7
insignificant concentrations in the residual radioactive corrosion films
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f 6.
DECOMMISSIONING ACTIVITIES 6.1 SAFE STORAGE During decommissioning, systems no longer required will be secured and isolated.
The objectives of system lay-up are as follows:
- Drain all systems.
- In September 1984, the primary system was chemically cleaned and 753 curies of Cobalt-60 and 12.4 curies of Cesium-137 were removed.
Other source terms in routinely accessible areas will either be remove or shielded.
- Connections will be sealed to prevent ler*'-c (rom operational systems to inoperable systems.
- De-energize instrument and control equipment to intperable cystems.
Generic Activities Systems and equipment not required for use in the shutdown mode will be secured in preparation for decommissioning.
Activities will include (1) draining and securing systems, (2)
-- de-energizing instruments and controls, (3) isolating non-operational from operational systems, and, (4) de-vitalizing appropriate security areas.
v 6.2 SYSTEMS STATUS FOR SAFSTOR PERIOD The following describes the systems that will be placed in
+
lay-up condition as part of the Dreiden Unit 1 safe storage.
1
- 1. Reactor Enclosure Drain Tanks and Fuel Handling Water Treatment System (Drawing M1000)
The following components and piping will be layed up as described above:
Fuel handling canal and associated piping from the reactor water filter (M-1001 D-4) and to the waste i
neutralizer tank (M1002 C-4).
Also, piping from the secondary steam'sample drain to secondary steam generator waste collection tanks, from the reactor cleanup demineralizet system to the permanent resir. storage tank T-ll3.
Small bore piping from the slurry mix tank to the reducing flange upstream of valve V-32.
- 2. Radwaste Collector Tank, Filters, and Waste Demineralize,r Tank (Drawing M1001)
The waste demineralizer tank C-9, waste filter tank C-25C and reactor waste filter C25A will be taken out of service.
This system will remain intact with the exception of the following:
(s 1 -; --
o..
- B1Iwdown tank C-21 and associated pipi~ng leading to and from the tank h
-- Condenser demineralizer regenerative solution drain and the spare line going into waste tank T-117
- Waste neutralizing filters and piping to M-77
- Radwaste acid tank T-130 and piping to M-88 j
- Radwaste caustic tank
[
- 2" drain line tc trench.
i
- Line to waste 6emineralizer tank i
- Line to waste concentrator
- River discharge line from M-78 Piping from M-96 to waste concentrator
- piping from M-104 to filters l'
- 3. Turbine Building Floor Drain, Tank. and Laundry waste Treatment System (Drawing M-1003'i
[
All systems will remain in use with the exception of:
l
- Laundry tanks T-il9B and T-119A and overflow piping
- Drain cooler area drains, tank and line to turbine sump.
l
- 4. Liquid Waste Storage and Holdup Tanks (Drawing M-1004)
Appropriate lines in this system will be taken out-of service.
~
- 5. Sludge'Handling, Resin Storage and Waste Concentrator (Drawing M21005)
All dominer'alizer piping, including the spare line leading
.')
into the permanent resin storage tank T-ll3, will be taken iA' out of service.
- 6. Service Water System (Drawing M-1009)
The waste neutralizer cooler and secondary steam generator waste tank coolers, including the 3" piping leading to a:.A 4
from the coolers, will be'taken out of service.
The waste vapor condenser will be taken'out of service and its 2" piping.
The'complete system for hydrogen. turbine lube oil and isolated-phase bus air cooler also will be taken out of service.
- 7. Cooling Water System (Drawing M-1010)
This system will remain in service to cool the following j
systems:
i
- Service air compressor i
- Heating boiler feed pumps
)
~Turbine building cooling water heat exchangers
- Tnstrument air compressor j ackets
- HVAC systems 1.
(_J
~ _ _ _.-,..-
,._.,..;..-_ _ ! L - ---.,. - _. _ _ _. _ _ _ _ ~ _*
t t
- 8. Well Water System (Drawing M-1011)
Well water will not be used to supply water to the Unit 1
.makeup demineralizer feed pumps, degasifier and ion exchange tanks, etc.
Other lines taken out of service will be the condenser vacuum pump and feed lines to T-ll6 (A&B),
T-23 (A&B), resin flush water, T-120, E-5 emergency condenser, fuel handling canal, T-122 (A&B), G-54 (A,B,C&D) and the reactor enclosure sump.
- 9. Fire Systems (Drawing M-1012)
The fire'system will remain in service.
- 10. Service Air System (Drawing M-1013) f Service air to the reactor enclosure will be taken out of service unless reactivated for routine maintenance.
- 11. Instrument Air (Drawing M-1013)
Instrument air to the reactor enclosure will be taken out of service unless reactivated for routine maintenancs.
- 12. Plant Heating System (Drawing M-1014)
The heat steam coils to the demineralizer water storage tank T-105 and the well water storage tank T-108 will be taken out of service.
- 13. Fuel and Lube Oil System (Drawing M-1015)
The turbine'lube oil system, feed pump lube oil system, and
~
lines feeding the emergency diesel generator will be taken out of service.
i
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- 14. Cleanup and Condensate Demineralizer Systems A1s es 1 1 be taken out of service.
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- 15. Reactor Enclosure Air Conditioning Water System (Drawing M-1018)
The room heating and cooling units, specificaly K-174, K-175 (A to D), K-176 (A to F), and K-177 (A&B) will be taken out of service.
- 16. Control Rod Hydra"lic System (Drawing M-1019)
This system will be taken out of service.
- 17. Turbine (Drawing M-1020)
The turbine will be taken out of service.
- 18. Main Steam and Condensate (Drawing M-1021)
The gas sampler lines connected to the stack will remain in service, along with the main condenser E-1.
All other piping and associated equipment will be taken out of service.
- 19. Nuclear Steam Supply System (Drawing M-1022)
The entire NSSS will be taken out of service.
r 6.3 DORMANCY pERIOD During the safe storage dormancy period, administrative i
procedures, structures, components and equipment will be
__ maintained for_the continued safety of workers and the general public.
( )
Generic List of Activities Radiation Survey A baseline radiological survey was taken prior to the Safe Storage period.
Routine quarterly surveys will be established to compare with the baseline survey.
Operation of Plant Systems Systems will be operated as required by the Revised Technical Specifications.
The operation will be in
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accordance with approved procedures.
Maintenance of Structures, Systems and Components The maintenance program will be a modified continuation of the existing program and will include both preventive and corrective maintenance.
The preventive maintenance aspect will provide for regular surveillance of structures, systems and components.
The frequency will be dependent upon previous plant experience, on going conditions and the 1
Revised Technical Specifications.
The corrective maintenance aspect will provide for appropriate action to be'taken in the event of degraded systems, components or structures. V l
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All structures will be maintained in accordance with the generic activities listed above.
Maintenance may include the following items:
Painting the exterior of the reactor building sphere, turbine building and other facilities
- Repair of fencing and/or barriers
- Repair of roofit systems to prevent leaks Maintenance of the security systems
- Periodic sting of the fire protection system
- Radwaste
,stem
- Heating ind ventilation where necessary 6.4 SYSTEMS STATUS FOR DORMANCY PERIOD The systems 14sted herein will remain operational during the safe storage period; they are required to protect health,and safety of the workers and general public.
Operating procedures will be revised to reflect safe sto,age status.
- 1. Fuel Handling Water Treatment Sycrem All systems will remain in service as necessary to provide cooling for the fuel taken from th? reactor.
- 2. Radwaste C_ollector Tank, F:
ars and Waste Demineralizer Tank The radwaste collector tank T-109 will remain in service to
,- s, collect wastes from the '.Vilowing areas.
The associated pump, valves and contro, for these areas will be maintained in an operable condition.
- Turbine building flocr drain
- Condenser demineralizer
- Waste condensate
- Sluice water from permanent resin storage tank T-ll3
~
- Off-standard water return
- Liquid waste storage tank
- Secondary steam generator waste collection tanks
- Associated piping running to waste neutralizer tank
- Surge tank T-124
- 3. Waste Neutralizer Tank and Secondary Steam Generator Collector Tanks The waste neutralizer tanks will remain in service to collect waste from the.radwaste building and the secandary steam generator collection tank.
This includes associated pumps, valves and controls..They will be maintained in an operable condition.
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- 4. Turbine Building Floor Drain and Laundry Waste Treatment 3
s
-System The turbine building floor drainage system will remain intact to facilitate future decommissioning needs.
- 5. Liquid Waste Storage and Hold-up Tanks The waste hold-up tanks T-129 '
B and C remain in service along with their associated -
-ps, valves and controls.
- 6. River Water Systems This system will remain in service to provide water for the service water system.
7.
Service Water System Service water to the air conditioning units for the reactor enclosure, the auxiliary buildings and the fuel handling building will remain in service.
- 8. Cooling Water System The service air compressors, heating boilers, feed pumps, the turbine btailding cooling water heat exchangers.and the instrument air compressor jackets will remain in service.
i
- 9. Well Water System Both wells will remain in service to provide water for the domestic Water system and will be maintained as appropriate.
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- 10. Fire protection System This system will remain in service to protect the health s
and safety of workers and the general public.
- 11. Air Systems Service air and Instrument air will remain in service up to the reactor enclosure.
- 12. Plant Heating System
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The Unit 1C Heating Boiler will remain in service.
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- 14. Reactor Enclosure Air Conditioning Water System Heating and cooling units K173-A through K173-K will remain in service, as necessary.
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- 15. Main Steam and Condensate Only two systems will remain in service:
the gas sampling lines connected to the stack and the main condenser (E-1).
6.5 DELAYED DISMANTLEMENT The ultimate removal of radioactivity and decommissioning of Dresden Unit I will not occur until Units 2 and 3 are retired from service and readied for decommissioning.
For the purpose of this decommissioning plan it will be assumc3 that Dresden Unit I will be decommissioned independent of Units 2&3.
The following section describes the activities to remove the remaining radioactivity and terminate the license.
Generic List of Activities Period 1:
preparation In preparation for the final dismantlement of Dresden Unit 1 the following activities will be accomplished:
Review plant drawings and specifications perform a._detailed radiation survey Define the major work sequence perform a safety a'nalysis fS Calculate the residual byproduct material inventory
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prepare specific removal procedures for plant systems components and equipment, etc.
Period 2:
Decommissioning Operations Dismantling may begin upon receipt of the dismantling order from the NRC.
The decommissioning operations involve the following:
Construct temporary facilities to support dismantling activities Decontaminate and dispose of piping/components Remove and dispose of the spent fuel racks Decontaminate and dispose of the NSSS Remove major equipment (turbine, condenser, CRD's, etc.)
Decontaminate site buildings Ship all remaining radioactive materials and fuel Conduct final radiation survey to assure that all radioactive materials have been removed Remove and dispose of plant systems/associated components in accordance with the sequence established.
These systems t
include:
- Radwaste
- River, weII and service water
- Fire
- Instrument and service air
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Site Restoration and Licanse Terminatior!
Following completion of the decommissiong operations, site restoration activities may begin.
This involves demolition and removal of the remaining site buildings i.e.,
reactor enclosure, turbine building, fuel handling building, fuel storage building, circulating kater intake, the stack and other miscellaneous site structures.
The building foundations will be backfilled with non-contaminated material.
Th plant site will be graded and landscaped as required.
A final dismantling program report will be prepared and
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submitted to the NRC, along with a request for terminatio'n of the possession only license.
Following NRC approval, the license will be terminated and the site may be released for unrestricted use.
6.6 SITE RELEASE CRITERIA prior to the release of Dresden Unit 1 for unrestricted use,
~ and to comply~with Regulatory Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors," a radiological site
(_ 'j release survey will be made.
This survey will show the 7-s following items:
- Identification of areas surveyed Show that reasonable effort has been made to r(duce
- residual contamination to levels as low as are reasonably achievable
' Description of the scope of the survey and general procedures followed The survey results will be recorded in units that comply
- with the latest revision of Regulatory Guide 1.86, Table 1 i
i 6.6.1 Survey Desions Indoor Survey In accordance with NUREG/CR-2082, "Monitoring for I
(.Compliance with Decommissioning Termination Survey i
Criteria" (Ref. 6.), each indoor survey is divided into t
two sub-units:
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4 (1) Lower surfaces, comprised of floor surfaces, wall surfaces, up to a height of 2m, and any cther surfaces easily accessible to a surveyor standing on the floor, and (2) overhead surfaces, comprised of ceiling surfaces, wall surfaces higher than 2m and all other surfaces not described in (1) above (i.e., on top of piping or beams).
The areas to be surveyed will be divided into a rectangular grid system.
The survey block will be no less than im nor more than 3m on a side.
There should be at least 30 survey blocks in the population.
The radiological conditions to be characterized include direct alpha contamination levels, beta-gamma dose rates at lem above the surface, external gamma radiation 1.evels at im above the floor, and removable alpha and-beta' contamination levels.
The surveyor will record all measurements and the average of five measurements of each type in each block is to be reported as an "unbiased" measurement for that block, and the measurements at the "beta-gamma maximum point" are reported_as. "b!
rd" measurements.
Smear or dust samples wit.1 be taken at Jome of the beta-gamma,maximum points for correlation of data, g,
t Escords of the survey should contain, as a minimum, the following:
. (1) Survey block numbers, identifiable to a scale drawing and The building name or number i
The building floor number a
The surfaces surveyed The type of measurement and unit (2) Name of sutveyor, dato of survey (3).Type, model number, calibration date and sensitivity of instruments used Outdoor Survey In general outdoor curveys are the same as indoor surveys
,with the following exceptions:
(1) No survey block should be less than 5m nor more than 15m on a side (2) Soil samples will be collected to determine radionuclide concentrations
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4 (3) Water and air samples will be collected in-addition to biota sampling to define-radionuclides present or
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movement on-or off-site-(4) Core drilling will be taken if.there.is any reason to suspect subsurface contaminatian.
The number of cores will be dependent upon the extent of' contamination 1
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WASTE MANAGEMENT
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Wastes from decommissioning operations consist of four types:
Radioactive materials Radioactive hazardous materials Hazardous materials Nonradioactive materials These estimated types and quantities of these wastes will be identified for each period of the decommissioning operations.
7.1 RADIOACTIVE MATERIALS r
The total quantity of radioactive materials for each period is shown in Table 7.1 and is based on the decommissioning study for Dresden Unit 1 (Ref. 4).
The volume of wastes include the burial container volume at an average void fraction of 40% to 60%.
These wastes consist of solidified decontamination solvents used during decommissioning, piping, valves, pumps,-
heat exchangers, concrete and structural steel from buildings.
Most of the materials for controlled burial are catego'rized as i
Low Specific Activity (LSA) material containing less than Type A quantities, as defined in 49 CFR 173-189 (Ref. 7).
The reactor vessel.and materials are mostly Type B shipments and must be shipped in reusable shielded casks with disposable liners.
Some portions of the vessel remotely located from the
(-
core center (e.g., vessel head) can qualify as LSA material and would be shipped as an LSA shi'pment.
TABLE 7.1 RADIOACTIVE WASTE VOLUME Volume, cu yd's Activity J
257
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SAFSTOR Mothballing Period 1 (Note 1)
Period 2 Dormancy 10 Period 3' Delayed Dismantling Preparations Period 4 Decommissioning Preparations 9,056-Period 5 Site Restorations (Note 2)
Note l Minimal radioactive waste is expected to be generated
--during Dormancy.
Most of it can be disposed of at Dresden 2 or 3.
Note 2 No radioactive ma*erial should be expected during this phase of the decammissioning project.
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i 7.2 RADIOACTIVE RAZARDOUS MATERIALS The primary'source of radioactive-hazardous materials would be from asbestos insulation on contaminated piping and components.
The estimated volume of this waste is approximately 535 cubic assuming all insulation contains asbestos.
It is
- yards, assumed the controlling hazard is radioactivity and therefore the waste must be buried in a commercial low-level waste, shallow land burial facility.
The Dresden Unit 1 Decommissioning Study cost estimate was based on this waste being packaged in the same burial containers as the associated piping and components.
7.3 c.l.;ARDOUS MATERIALS The source of hazardous materials would be from asbestos..
insulation on noncontaminated piping and components, and from transformers contaminated with polychlorinated bypheny-1s (PCBs).
The amount of noncontaminated asbestos insulation is approxi.nately 129 cubic yards, assuming all insulation-contains The Iaain and substation transformers are assumed to asbestos.
be contaminated with PCBs.
The amount of oil in each is shown in Table 7.2.
TABLE 7.2 TRANSFORMER OIL VOLUMES Transformer Volume Number (gals) 1 10,400 11 2,850 12 4,875 13 911 14 340
'. 5 340
+
16 340 17 340 20,396 These,materials are classified'as hazardous.under the Resource Conserv.ation and Recovery Act (RCRA) (Ref.8).
They are being disposed of at approved hazardous waste disposal facilities as part of CECO's continuing program to dispose of PCBs., _.
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i 7.4 NONRADIOACTIVE MATERIALS Nonradioactive-(and nonhazardous) waste materials will be generated during the ultimate dismantling of Dresden Unit 1.
The wastes will consist of clean piping, components, structural steel, concrete rubble and miscellaneous trash.
The estimated t
volume of this material is approximately 6,890 tons of scrap and 31,000 cubic yards of concrete rubble and trash.
There are no federal regulations governing disposal of this material in local landfills.
Local ordinances may require a dumping permit and a disposal fee.
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- 8. REFERENCES 1.
U.S. NRC Proposed Rules, "Decommissioning Criteria for Nuclear
'i Facilities," Federal Register, Vol. 50, No. 28
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(February 11, 1985) 2.
U.S. NRC Regulatory Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors" l
3.. U.S. Code of Federal Regulations, EPA Tit_c 40, "Protection of the Environment," Part 61 r
4.
Decommissioning Study for the Dresden Nuclear Power Station Unit 1," prepared for Commonwealth Edison Company by TLG Engineering, Inc. (November, 1985) 5.
U.S. NRC, "Technology, Safety and Costs of Decommissioning a Reference Boiling Water Reactor," NUREG/CR-0672, prepared by Battelle Pacific Northwest Laboratory (June, 1980) 6.
U.S. NRC, "Monitoring for Compliance with Decommissioning-Termination Survey Criteria", NUREG/CE-2082, Oak Ridge National Laboratory (June, 1981) 1 7.
U.S. Code of Federal Regulations, Transportation Title 49, Parts 173-178 8.
The Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act of 1976, RCRA Public Law 94-5800
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ATTACHMENT A RESULTS OF 1985 JULY IJ1D OCTOBER SURVEYS OF DRESDEN UNIT 1
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