ML20210C627
| ML20210C627 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/15/1999 |
| From: | Zinke G Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GAZ-99-20, MN-99-19, NUDOCS 9907260111 | |
| Download: ML20210C627 (29) | |
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3 MaineYankee 321 OLD FERRY RD.
- WISCASSET, ME 04578-4922 July 15,1999 MN-99-19 GAZ-99-20 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington,DC 20555
References:
(a) License No. DPR-36 (Docket No. 50-309)
Subject:
Information on Maine Yankee's License Termination Plan (MYLTP)
Gentlemen:
On July 7,1999, Maine Yankee Atomic Power Company (MYAPC) met with the NRC staff to discuss the preparation of our License Termination Plan. Maine Yankee provided the staff with information on several key topics including: phased release of site lands, rubblization, area classification and survey unit design. We appreciated this opportunity for feedback and discussion.
The purpose of this letter is to transmit draft documents to the NRC for information only. Attached are the following draft documents:
A. Site Characterization Summary In Support of Part 50 License Termination B. A copy of the latest decommissioning schedule with milestones identified We will also be sending the following information.
Identification of any instance on site footprint reduction under 10 CFR 50.59.
Feedback received from public forums on rubblization.
Copies of references, codes or any other literature used in support of rubblization.
Site Map showing the phased release of site lands.
Definition of"rubblization" If there is any other information ofinterest to the NRC staff, please let us know.
We believe that this information will be helpful in supporting upcoming presubmission MYLTP meetings and will provide a springboard for clarifying mutual expectations. The final MYLTP is expected to be submitted for NRC review and approval by November 1,1999.
k0 0 9907260111 990715 PDR ADOCK 05000309 W PDR
+ . _ _ _ _ _ _ _ _ _ _ _ _ .
. UNITED. STATES NUCLEAR REGULATORY COMMISSION MN-99-19 i Attention: Document Control Desk Page Two
- j. If you have any questions, please contact me at 207-882-5824.
Very truly y rs, O George A. Zinke, Director Nuclear Safety & Regulatory Affairs Department Attachments l
)
a: Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. M. K. Webb, NRR Project Manager Mr. J. T. Greeves, Director, Division of Waste Management )
Mr. M. C. Roberts, NRC Region I Mr. C.L. Pittiglio, NMSS Project Manager, Decommissioning Mr. M.T. Masnik, Section Chief, Project Directorate IV & Decommissioning Mr. P. J. Dostie, State of Maine, Division of Health Engineering Mr. U. Vanags, State of Maine, Nuclear Safety Advisior r
I l
Attachnent A MAINE YANKEE i
SITE CHARACTERIZATION
SUMMARY
IN SUPPORT OF j PART 50 LICENSE TERMINATION i
I l
l July 6,1999 DRAFT Stone & Webster Engineering Co.
Boston MA
~:
3.0 SITE ChlARACTERIZATION SURVEY METHODS Site characterization was performed by two different contractors using similar but not identical methods and techniques. These differences are noted within the methods and results sections of this report. !
3.1 Organization and Resoonsibilities 1
GTS Duratek was the prime contractor for the initial characterization surveys conducted from the fall of 1997 through the spring of 1998. GTS performed surveys and provided hand held instrumentation. Subcontractors provided the follow:ng specialized services.
. IT Corporation performed the hazardous materials characterization survey and drive over scans.
. Duke Engineering & Services performed the activation analysis. l
- Canberra Industries provided on site laboratory instruments. l
. Team Associates performed the asbestos characterization.
. Quanterra performed off site laboratory analyses.
Stone and Webster was the prime contractor for continuing characterization activities which took place from the fall of 1998 through the summer of 1999. Stone and Webster collected samples and performed on site surveys and analyses. Duke Engineering Services performed the laboratory analyses for the hard-to-detect radionuclides.
3.2 Characterization Data Categories Survey categories for site characterization were designated by GTS as surfaces and structures, systems, environs (soils, sub-slab soils, sediments and ground water) for both "affected" and " unaffected" locations based on the likelihood of the area being contaminated. Stone and Webster used the same designa: ions for clarity and ease of comparing data.
Surfaces and Structures This category included building interiors and exteriors with associated structures, j and, where applicable, the e.uerior surfaces of plant systems and components because these surfaces have the same potential for residual levels of radioactive material as the building surfaces in which they are located. Surface and structure survey packages also included ancillary buildings and structures. Structural background measurements were also included in this category.
In total, the survey category included approximately 7,850 measurements in
unaff$cted areas and approximately 6,350 measurements in affected areas. This intentional bias toward unaffected surfaces and structures ensured no unsurveyed or undetected locations were likely to exist. Affected structure surveys included 18 concrete core samples. Because rubblized concrete was considered to be a primary source for evaluating the radiological release criteria, Stone and Webster took an additional 40 concrete core samples to improve the nuclide data.
Systems >
This category included inSrior surfaces of process piping, components, ventilation ductwork, and installed drains and sumps. The levels of radioactive material on the internal surfaces of plant systems and components primarily depend on process operations. Therefore, these survey packages were separate from surface and structure survey packages. Plant system survey packages generally included one piant system.
This survey category included approximately 3,800 unaffected system measurements and approximately 1,050 affected system measurements. Again the surveys were biased toward the unaffected systems to provide a high likelihood of identifying any existing contaminated pipe or component.
Stone and Webster conducted additional systems surveys in order to bound the extent of contaminated components within non-Restricted Area structures. ,
J j
Environs J
Land areas were surveyed and sampled to detect the presence and extent of soil contaminadon. Approximately one-third of the 820-acre site land area received a gamma scan. Exposure rate measurements taken over the entire property used a grid system to ensure adequate survey of all areas. Nearly 300 soil samples were taken of which 180 were from unaffected areas. One survey package in this category was devoted to obtaining background soil and exposure measurements from an area similar in physical characteristics to, but located several miles from, the site.
Sediment, ground water and surface water samples were also included in this I category. j
. Stone and Webster took additional soil samples for determining the amounts and ratios of the hard-to-detect radionuclides in soils.
Soils from beneath foundation slabs will be sampled and analyzed when the soil is exposed during remediation. Scan and fixed surveys of pavement were performed to identify potential sub-surface contamination. Two areas of soil contamination beneath pavement were documented in the HSA. One area of sub-slab leakage from the liquid waste effluent line occurred underneath the Service Building floor. The
1 resuits of this soil contamination were contained in the 50.75(g) file.
I 3.3 Characterization Survey Desien Characterization surveys were designed to sample each structure, system and land area onsite for the presence of radioactive contamination. A heavy emphasis was placed on non-affected (non-i '.pacted) systems, structures and areas with 2750 more surveys taken on non-affected systems,1500 more surveys taken on non-affected surfaces and structures, and 18 survey packages devoted to non-affected areas versus 7 for affected areas. This emphasis ensured that the full nature and extent of the contamination was identified and characterized.
The radiological characterization survey was organized, performed and reported in ;
one of five " Groups" Each group is comprised of plant areas containing similar types of media, or material, and sitt.ilar contamination potential. The types of media included surfaces, structures, systems and environs. The environs category included ,
facility grounds within and outside the Restricted Area, the liquid effluent pathway, '
Montsweag Bay, groundwater wells and remote locations within the Maine Yankee Atomic Power Plant site boundaries. The contamination potential for the media in a given group was generally categorized as affected and unaffected. Affected areas have medium to high potential for containing contamination. Unaffected areas have a low or no potential for containing contamination. The affected/ unaffected designation was not intended to indicate final survey classification status, but was intended as a j I
general descriptor of contamination potential. The methods for converting the characterization survey results to classification of plant areas for final site survey is described in Section 5 of the License Termination Plan.
The Maine Yankee facility was divided into five groups and 127 packages which are ;
listed in section 3.4. Groups were organized according to media type and l contamination potential. Each j;roup was further subdivided into survey packages l that correspond to specific p!?nt areas with similar operational history or physical l location.
The survey package breakdown is contained in Attachment B. All plant areas are included in one of the survey groups / packages. The five groups are listed below.
. Group A-Affected Surfaces and Structures
. Group B-Unaffected Surfaces and Structures
. Group C-Affected Systems
. Group D-Unaffected Systems
. Group R-Radiologically Affected or Unaffected Environs These group designators were also used by Stone and Webster during continued characterization for survey package identification.
L,
' Non/ radiological data were collected and grouped into one of the following two
. categories listed below. The environs hazardous material characterization surveys
' included testing for PCBs, RCRA metals, semi- volatile organic compounds and volatile organic compounds.
. Group E-Hazardous Materials on Structures, Systems or Surfaces
.' Group H-Hazardous Materials in Environs Activation analysis calculations were also performed for the reactor vessel and internals.
3.4 Survey Findings And Results The results of the characterization surveys are reported by survey group and package number as identified below.
PACKAGE - GROUP "A" Affected Structures nnd Surfaces Survey Packages NUMBER
~ A0100 Containment Building - Elevation -2 ft.
A0200 Containment Building - Elevation -20 ft.
A0300 Containment Building - Elevation 46 ft A0400 Fuel Building - Elevation 21 ft.
A0500 Demineralized Water Storage Tank TK Elevation 21 ft.
A0600 Primary Auxiliary Building i Elevation 11 ft.
A0700 Primary Auxiliary Building - Elevation 21 ft.
'A0800 Primary Auxiliary Building - Elevation 36 ft. )
i A0900 Service Building Hot Side - E!evation 21 ft. I i
A1100 Low Level _ Waste Storage Building Elevation 21 ft.
A1200 RCA Building - Elevation 21 ft.
A1300 Equipment Hatch Area - Elevation 21 ft.
A1400 Personnel Hatch Area - Elevation 21 ft.
A1500 Mechanical Penetration Room - Elevation 21 ft.
A1600 Electrical Penetration Room _ All Elevations A1700 Containment Spray Building All Elevations A1800 Auxiliary Feed Pump Room - Elevation 21 ft.
A1900; HV 9 Area - Elevation 21 ft.
A2100- Refueling Water Storage Tank (RWST) TK Elevation 21 ft.
I,. )
e PACKAGE GROUP "A" Affected Structures and Surfaces Survey Packages NUMBER A2200 Borated Water Storage Tank (BWST) - Elevation 21 ft.
A2300 Processed (Primary) Water Storage Tank (PWST) - Elevation 21 ft.
A2400 Test Tanks 14A/14B -Elevation 21 ft.
' A9900 - Concrete core contammation profile sampling A9901 Activation analysis core sampling A9902 Activation analysis core sampling MCKAGE GROUP "B" Unaffected Structures and Surfaces Survey Packages NUMBER ;
i B0100 Turbine Deck Elevation 61 ft.
B0200 Control Room - Elevation 21 ft. ;
B0300 Motor Control Center (MCC)/ Battery Room - Elevation 62 ft.
B0400 Fire Pump House - Elevation 1 ,
B0500 Condenser Bay - Elevation 21 ft. j
'B0600 Condenser Bay - Elevation 39 ft.
B0700 Service Building Cold Side - Elevation 21 ft.
B0800 Fuel Oil Building - Elevation 21 ft.
B0900 Emergency Diesel Generators - Elevation 21 ft.
B1000 Auxiliary Boiler Room - Elevation 21 ft.
B1100 Recirculating Water Pump House - All Elevations B1200 Administration Center - Elevation 21 ft.
B1300 WART Building - All Elevations B1400 Visitor and Information Center - Elevation 1 l B1500 Warehouse 2 - Ele <ation 1 e
B1600 Training Annex Building - Elevation 1 B1700 Staff Building - All Elevations B1800 Spare Generator Building - Elevation 1 B1900 Environmental Services Building - All Elevations B2000 Bailey Barn - Elevation 1 B2100 Lube Oil Storage Room Turbine Building Elevation 21 ft.
B2200 Cold Machine Shop Turbine Building Elevation 21 ft.
B2300 Cable Vault Room - Turbine Building Elevation 39 ft.
, J
]
i PACKAGE GROUP "B" Unaffected Structures and Surfaces Survey Packages ,
l NUMBER B2400 Staff Building Tunnel - Staff Building to Turbine Building Elevation 21 ft.
B9800 Structural Background Survey PACKAGE GROUP "C" Affecat hit Systems Survey Packages q NUMBER !
C0100 Primary and Post Accident Sampli:.g System C0200 Waste Solidification System C0300 Containment Spray System C0400 Emergency Core Cooling System J C0500 Residual Heat Removal System C0600 Primary Vents and Drains C0700 Fuel Pool Cooling System C0800 Waste Gas Disposal System C0900 Pressurizer and Pressurizer Relief System ;
k C1100 Reactor Coolant System l l
Cl200 Boron Recovery System )
)
Cl300 Chemical and Volume Control System Cl400 Liquid Waste Disposal System C1500 Primary Auxiliary Building Drains C1600 Primary Auxiliary Building Ventilation C1800 Containment Ventilation System C1900 Steam Generators
PACKAGE GROUP "D" Unaffected Plant Systems Survey Packages NUMBER D0100 Condensate System D0200 Water Treatment Plant Systems D0300 Potable Water System D0400 Sanitary Sewer System D0500 Circulating Water and Screen Wash System D0600 Service Water System D0700 Fire Protection System D0800 Lube Oil System D0900 Compressed Air System D1000 Auxiliary Boiler System D1100 Steam Generator System D1200 Main and Reheat Steam System D1300 Auxiliary Steam System D1400 Main Turbine and Turbine Control System D1500 Steam Dump and Turbine Bypass System .
D1600 Main Feedwater System D1700 Emergency / Auxiliary Feedwater System D1800 Heater Drain and Extraction Steam System D1900 Component Cooling Water System D2000 Vac"um Priming and Air Removal System D2100 Amertap System D2200 Secondary Plant Scaling System D2300 Auxiliary Diesel Generator D2400 Secondary Sample and Chemical Addition System D2500 High Pressure Drains D2600- Environmental Services Laboratory Systems D2700 Administration Building HVAC System I
D2800 Information Building HVAC System D2900 Turbine Building Ventilation System D3000 Staff Building HVAC System D3100 Service Building HVAC System D3200 Hydrogen and Nitrogen System D3300 Turbine Building Sumps and Drains D3400 Low Level Radioactive Waste Storage Facility
r:- .
I. ,
PACKAGE GROUP "R" Environs Affected and Unaffected Survey Packages
! NUMBER ,-
AFFECTED R0100 RCA portion (West Side) of Protected Area Yard
- R0200 Balance of Protected Area (East Side)
R0300 Roof and Yard Drains #006, #007 and #008
-R0400 Forebay Area Shorelines R0500 Bailey Point
'R0600 Ball Field R0700 Construction Debris Landfill UNAFFECTED-R0800 Administration and Parking Areas R0900 Balance of Plant Areas R1000 Foxbird Island R1100 Roof and Yard Drains #005, #009-12, #017 and N-12 R1200 Low Leve! Radicactive Waste (LLRW) Storage Building Yard R1300 Dry Cask Storage Area R1400 Westport, Montsweag Bty. Bailey Point Cove and Plant Area Shorelines R1500 Ash Road Area Rubble Piles R1600 Owner Controlled Area West of Bailey Cove R1700 Owner Controlled Area North of Old Ferry Road R1800 Bailey House Area R1900 Bailey Cove R2000 Diffusers R2100 Maintenance Yard (Stockyard)
R2200' Background R2300 SFPI Substation Stab R2400 IT Duplicate Samples R2500 Driveover Elevated Areas R2501 Follow-u samp! n at Elevated Soil Sam le Locations (south of Refueling Water Storace ank an ontractor Parking to 1
~ .' o Habrdous and cl and areas as spec}emical material tried in the tables surveys for Group E andwere Groupperformed on data H. below. The the materials, for systems ge ggoge presented in the Summary of Site Characterization Data section PACKAGE GROUP "E" Plant Surfaces, Structures and Systems Hazardous Material NUMBER Survey Packages E0100 Protected Area Paint E0200 Plant Electric Components E0300 Transformer Oils E0400 Plant Pump Oils E0500 Various Plant Fluids E0600 Component Cooling Water E0700 Brass, Bronze and Cadmium Plated Components E0800 Plant Batteries
.E0900 Mercury Components E1000 Asbestos insulation and Other Materials E1100 Asbestos Centaining Components E1200 Lead Shielding E1300 Paint Outside Protected Area PACKAGE GROUP "H" Environs Areas Hazardous Material Survey Packages NUMBER H0100 Oil and Hazardous Material Transfer and Handling Areas (4)
-H0200 Diesel Oil Tank Loading Are H0300. Main, North, Spare and Shutdown Transformers H0400 Roof and Yard Drains #006, #007 and #008 H0500 Solid Waste Storage Area H0600 Primary and Secondary Side Waste Storage Building Yard Areas H0700 Drumming / Decontamination Waste Accumulation Area H0800 Diffuser Forebay H0900 Reactor Water Storage Tank Area H1000 Groundwater Monitoring Wells B-201 through 206, MW-100 BK-1 H1100 Warehouse Yards H1200 Fire Pond and Yard Area H1300 Construction Debris Landfill H1400 Bailey Point H1500 Administration and Parking Areas
i l PACKAGE) %? GROUP "H", En,virons Areas Hazardous Material Survey Packages g -
H1600 Roof and Yard Drains #005, #009-12 and N-12 H1700 Surface Flow Drain #005 H1800 Balance of Plant Area H1900 Foxbird Island 1 l
H2000 Low Level Waste Storage Yard !
l H2100 Dry Cask Area H2200 Environmental Services Laboratory H2300 Switchyards H2400 Areas Outside Plant Impact 6.0
SUMMARY
6.1 Impact Of Characterization Data On Decontamination And Decommissionine Characterization data confirgied what was known about the Maine. Yankee site in terms of the level and extent.of radioactive contammation. A major portion (700 acres) of the site met the classification of non-imoacted. Restricted Area pnmary systems, structures and environs were found to be contammated to expected' levels. Non-Restricted Are.a systems and structures were found to be less than expected DCGLs Service Water Conslensate/ Aux excent as oreviously Condensate, Turbine B.ldknown (e.g.,
suplos and liquidPCC/S.CC,ffluent e discharg,e pipmg). Non-Restricted Area environs surveys identified three small areas of surface contammation j i
north of the forebay Trom, RWST leakage was co,nfirmed and boun)ded.(Contractor's pa '
There were n.o changes in either waste volumes or waste activity values following site charactenzation. )
The data compiled by GTS Duratek and as supplemented by the Stone and Webster's !
continued characterization rneasurements,are sufficient to project schedules and waste .
volumes evaluate dqcontamination techmques, perform dose assessments and evaluate I any safely or health issues affecting workers on site.
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