ML20062L030

Environ Evaluation of Onsite Storage Facility for Low Level Radwaste

ML20062L030
Person / Time
Site:	Fermi
Issue date:	08/31/1982
From:	SARGENT & LUNDY, INC.
To:
Shared Package
ML20062L027	List: ML20062L024 ML20062L030
References
NUDOCS 8208180102
Download: ML20062L030 (43)

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i ENVIRONMENTAL EVALUATION L

OF THE ONSITE STORAGE FACILITY FOR LOW-LEVEL i i

RADIOACTIVE WASTE I I

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i ENRICO FERMI ATOMIC POWER PLANT, UNIT 2 .

DOCKET NO. 50-341 i O  !

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i PREPARED FOR f THE DETROIT EDISON COMPANY l PROJECT NO. 6139-41 i

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by j SARGENT & LUNDY l O AUGUST 1982 P

8208180102 820816  !

PDR ADOCK 05000341  :

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TABLE OF CONTENTS PAGE i Summary 1 1.0 Introduction 2 1.1 Purpose 2 1.2 Need 3 1.3 Scope 3 2.0 Onsite Storage Facility Description 4 2.1 General 4 f

2.2 Description of Wastes 5 2.3 Design Features 6 ,

3.0 Operation of the Onsite Storage Facility 19 3.1 Storage 19 i 3.2 Decontamination 20 j 3.3 Handling 23 (

4.0 Radiological Considerations 23  !

4.1 Normal Operation 23 4.2 Postulated Accidents 24 I 5.0 Environmental Assessment 28 .

5.1 Environmental Effects of the Proposed 3 Action 28 i 5.2 Unavoidable Adverse Environmental Effects 31 5.3 Irreversible and Irretrievable Commitments I of Resources 31 6.0 Alternatives Available to Onsite Storage '

Facility 32 5 6.1 Offsite Disposal (No Action Alternative) 32 6.2 f Operation of an Offsite LLRW Storage Facility 32  !

6.3 Onsite Interim Storage in Existing t j

Facilities 33 7.0 Cost Benefit Discussion 34 6 8.0 Decommissioning 36 I 9.0 Applicable Codes and Regulations 38  !

t 9.1 Structural 38

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, 9.2 Radiological 39 i

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LIST OF TABLES PAGE Table 2.1 Radionuclide Content and Volumes of Dry Active Waste 13 I  !

Table 2.2 Principal Nuclides To Be Shipped For -

Each Type of Waste, in Curies Per Year, and Total Annual Curies Inventory For Normal Operation 14-17 I Table 2.3 Annual Volume of Solids Shipped From  !

Normal Processing 18

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LIST OF FIGURES Figure 2.1 Onsite Storage Facility Plot Plan

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Figure 2.2 Onsite Storage Facility Floor Plan i i j t

i Figure 2.3 Onsite Storage Facility Cross Section I i

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SUMMARY

An Onsite Storage Facility (OSSF) is being constructed at the I Fermi 2 site for the temporary storage (up to 5 years) of low level radioactive waste prior to shipment offsite to a licensed commercial disposal site. The construction of this facility is to ensure that the uncertain availability of commercial disposal sites will not adverse]y affect future power generation at Fermi 2.

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An environmental evaluation of the ef fects of construction and I operation of the facility has been conducted and it is concluded that the proposed action will not significantly affect the quality of the human environment and will provide the Applicant a means to manage responsibly the low level radioactive waste generated at the Fermi 2 plant that is compatible with the pre-sent uncertainties associated with offsite disposal.

D The proposed facility is located entirely within the protected area of the Fermi 2 plant and is essentially an extension of the  !

present radwaste facility. The land has already been disturbed during construction of Fermi 2 and, therefore, there are no effects in addition to those already stated in the environmental .

i report reviewed by the NRC, and discussed in the Final Environ-mental Statements for Fermi 2.

The OSSF is designed such that operations will be conducted in accordance with the guidelines concerning radiological protec- I tion of employees and general public. The radiological doses associated with the facility are negligible and within the limits of 10 CFR 20, 10 CFR 50 Appendix I, 10 CFR 100, and 40 CFR 190. i

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1.0 INTRODUCTION

1.1 PURPOSE V)

This environmental evaluation is being submitted as supporting information for the construction of an Onsite Storage Facility

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(OSSF) to allow the temporary (up to 5 years) storage of low I level radioactive waste (LLRW) at the Enrico Fermi Atomic Power Plant, Unit 2 (Fermi 2) prior to shipment offsite to an approved r commercial disposal site. Although it is not the applicant's intent to use the OSSF, the construction of this facility is to ensure that the uncertain availability of commercial disposal space will not adversely affect future electric power generation at Fermi 2. It is necessary that Detroit Edison develop a plan for disposal of LLRW that is flexible, that meets the needs of Fermi 2, and is compatible with the developing regional low level .

waste management compacts, i.

1.2 NEED '

Detroit Edison has an application pending for a license to operate Fermi 2, a 3292 MWT boiling water reactor.  ;

Operation of Fermi 2 will result in the planned and controlled generation of low level radioactive waste consisting of ion  ;

exchange and condensate demineralizer resins and miscellaneous  ;

tras h s uch as glass , paper , rags , mopheads , booti es , gloves , towels , etc .  :

The developments in recent years with respect to disposal of low -

level radioactive waste have resulted in a situation where access i to a commercial, licensed disposal site is very uncertain.  !

Currently The Detroit Edison Company has no volume allocation at the Barnwell, South Carolina site and it is not expected that  ;

this condition will change. The State of Washington is i

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currently considering adopting regulations that would effec-tively deny access to the Hanford site by noncompact states O- beginning early in 1983.

If these or similar regulations are adopted, the bulk of the waste generators currently utilizing the Hanford site could be expected to shift to the Beatty, Nevada site. Faced with this development and recognizing the rather small licensed capacity of  ;

the Beatty site, the State of Nevada would likely take measures l

to curtail use of the site by noncompact states. Finally, the [

establishment of a regional disposal site for the Midwestern '

region is unlikely to occur prior to 1988 or 1989.

In view of the above conditions, it is necessary to provide ,

capacity for the temporary storage of sufficient quantities of low level radioactive waste at Fermi 2 to avoid impacting the operation of the plant should offsite commercial disposal become unavailable.

O 1.3 SCOPE The scope of this evaluation is limited to the OSSF. The infor-mation presented consists of the facility description, environ-mental and radiological assessments, and information regarding

facility operation and decommissioning.

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2.0 ONSITE STORAGE FACILITY DESCRIPTION O 2.1 GENERAL The OSSF is a "T"-shaped building located entirely within the Fermi 2 protected area and is essentially an extension of the present radwaste building as shown in Figure 2.1. The facility houses offices, a control room for the facility crane, a dry active waste (DAW) compactor, empty drum storage, the asphalt storage tanks and associated pumps for the radwaste solidifi-cation system, a truck loading bay, and temporary storage space for 5 years of generated LLRW consisting of 3912 drums of solid-ified waste and 6160 drums of DAW. A plr.n view of the f acility is shown in Figure 2.2; cross sections of the facility are shown in Figure 2.3.

The facility provides a protective barrier around the stored LLRW to:

o Protect the waste containers from the effects of the environment, o Prevent the uncontrolled release of the waste to the environment, and e Provide shielding f rom the radiation emitted by the waste.

The OSSF is a Non-Safety Related, Non-Seismic Category 1 struc-ture (i.e., one whose failure would not release significant amounts of radioactivity and would not require reactor shutdown) i I

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designed in accordance with the guidance provided in the codes, standards, and regulations listed in Section 9.0 of this docu-k ment.

The exterior and interior walls are constructed of reinforced concrete, with a reinforced concrete slab roof. The facility is not designed for the effects of a design basis tornado or earth-quake. The elevation of the building is such that, at elevation 583 feet, it is above the 100-year flood level of 578 feet.

2.2 DESCRIPTION

OF WASTE The radioactive wastes temporarily stored in this f acility are of two general types: dry active wastes and solidified (in asphalt) wastes. Low-level wastes are stored in two different areas of the OSSF as indicated in Figure 2.2. The solidified waste is stored in four storage cells located in the southern half of the facility; dry active waste is stored in the northern half of the facility in two storage cells. The truck bay separates the two V areas.

2.2.1 Dry Active Waste The dry active wastes (DAW) generally have a low radioactivity level and can be handled by direct contact. The DAW is collected in containers located in various zones around the plant. The filled containers are sealed and then normally transferred to the OSSF. Table 2.1 provides the total annual activity (Ci) for the DAW. l l

These wastes are of two types: compressible (the great majority) and noncompressible. The compressible wastes are drummed and processed in the compactor area. The noncompressible wastes are packaged manually into steel drums, bypassing the compactor, and put directly into temporary storage. DAW will be stored in l

18-gauge DOT-17H 55-gallon drums.

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The compreesible troch, which is mnde up of low-activity mate-rial, including glass, paper, rags, mop heads, booties, gloves, o and towels, is normally transported from the radwaste huilding to the compactor room in plastic bags. The trash is then placed in the drums, compacted, and a lid fastened on the drum. A forklift truck transports the drum to the storage area.

2.2.2 Solidified Waste Asphalt is used as the solidification agent for all the solidi-

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fled liquid waste usually consisting of evaporator bottoms, resins, and sludges. The asphalt and waste are combined in a  :

special extruder / evaporator-heated process that simultaneously removes the water from the waste while producing a homogeneous product. This is a continucus feed process in which the waste asphalt product is continuously discharged into 18 gauge DOT-17E 55-gallon drums, where it cools, forming a solid homogenous monolith with no freestanding water. The filled drums are cooled, capped, and sealed with a crimper to form containers

• suitable for storage in the OSSF or for offsite disposal.

O Tables 2.2 and 2.3 list the normal expected curie content and i volume of materials that are produced annually in the solid rad- '

waste system.

2.3 DESIGN FEATURES 2.3.1 Radiological 1

2.3.1.1 Shielding The shielding design takes into account such considerations as:

e Direct and scatter radiation paths, e Ducts and other voids or penetrations in shield walls, O

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e Multiple radiation sources and source transport paths that may contribute to che dose rate in any given area.

Specifically, the design for radiation shielding includes:

e Outer shield walls that protect the yard area from direct radiation, o Roof slab that protects the yard area from air scatter and the HVAC equipment room from direct radiation, e Truck bay shield walls that protect truck bay workers '

from direct radiation and a low roof that protects truck bay workers from the scatter off the main roof slab, e Shielding around the swipe, decontamination, and labeling area that protects truck bay workers during Q

%J the associated operations, e Storage cell walls that protect workers during any necessary maintenance in adjoining storage cells, and e Shielding around the dry active waste compactor area that protects surrounding areas from potential sources in this area.

The OSSF radiation shielding is designed to maintain doses at the exclusion area boundary within the guidelines of 40 CFR 190, and 10 CFR 50 Appendix I. Radiation exposure to onsite employees is maintained within the guidelines of 10 CFR 20. The shielding is designed assuming that the entire storage space will be filled with drums of solidified waste, l

i For conservatism, the facility's shielding was based upon a I

nominal 200-Ci drum with a specific spectral activity as follows:

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Group (MeV)

( MeV/cc-sec 1 0.3 3.11 x 10 6 2 0.8 8.25 x 10 6 ll 3 1.3 6 2.88 x 10 j 4 1.7 4.24 x 10 6 5 2.2 1.02 x 10 5 6 2.5 1.42 x 10 5  !

7 2.8 4 5.60 x 10 8 4.0 1.50 x 10 1  !

The actual average drum content is expected to be 7 Ci, based on dividing the total annual curie content (Table 2. 2) by the annual number of expected drums (Table 2.3).

() 2.3.1.2 Radiation Monitoring Area radiation monitors ( ARM 's) are provided in the truck bay area near the office area and the dry active waste compactor (Figure 2.2). If predetermined radiation setpoints are exceeded, r alarms are sounded both locally and in the control room of the onsite storage facility.

The HVAC system is designed to hold the building at a minimum of 1/4-inch negative W.G., thus ensuring that no unmonitored releases can occur. Effluent radiation monitoring is provided by an off-line three-channel monitor that takes a representative sample from the exhaust duct of the HVAC system. If predeter- '

mined setpoints are exceeded, an alarm will sound.

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2.3.1.3 Ventilation O The HVAC system in the OSSF consists of:

e The heating and ventilating (H& V) system for the main storage areas, o The HVAC system for the control room and offices, o The H&V system for the asphalt storage tank and pump rooms, o The compactor ventilation package, and e The H&V system for the HVAC equipment room.

All the major equipment of the system is located in the HVAC equipment room located on the roof of the OSSF (Figure 2.3). i' Control of potential airborne contamination is provided by a design that ensures that air will flow from areas of lesser potential contamination to areas of greater potential contami- '

nation. Specifically, air will tend to flow:

l e From outside the facility to inside the facility,  !

e From the truck bay to the drum storage area, and I

e From the control room and offices to the compactor area.

The air is exhausted through prefilters and HEPA filters and is monitored before its release to the environment.

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Measures have been taken to provide airflow barriers in the three openings between the OSSF and radwaste building to minimize any differential flow.

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The exhaust from the DAW compactor is filtered and routed

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directly to the facility's exhaust to minimize airborne contami-nation in the compactor room.

2.3.1.4 Maintenance To reduce the possible exposure of personnel during maintenance, the following concepts have been incorporated into the design of the onsite storage facility:

e Lighting is provided via the bridge crane; no lights  ;

have to be replaced over the stored radwaste; e The swipe, visual examination, and decontamination area is provided with shielding to limit exposure during these operations; e Epoxy coatings are provided on all floors and walls

() where contamination could occur; and e Maintenance of the crane and its cables is performed in low-dose areas.

2.3.2 Drain System The OSSF is provided with an extensive system of drains and l trenches. All floors in the truck bay and pallet loading area l are sloped so that any spillage is directed towards one or more of the drains. Because of this network, curbs are not used.

All drains in potentially contaminated areas of the CSSF are routed directly to the floor drain collector subsystem cf the j

i main liquid radwaste system. These include drains in the dr um storage areas, the truck bay area, the drum decontamination sta-tion, the pallet loading area, the HVAC equipment room, and the <

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drum compactor crea. Thaco draina are cdaquntely sized for all normally expected influents and will also drain water from the es fire suppression system.

2.3.3 Fire Protection System The OSSF is structurally a separate building and is, therefore, a separate fire protection area. Only a portion of the facility is attached to any other building. The walls, floor, and ceiling of the OSSF are of reinforced concrete or concrete block. Personnel doors to the radwaste building and the rooms housing the asphalt storage tank and pumps are Underwriters Laboratories Label A fire doors.

The fire protection system for the OSSF is designed in accordance with NFPA-13. All fire protection equipment is listed by Under-writers Laboratories, and fire protection and fire detection drawings were approved by the Applicant and its insurer.

I Fire detection equipment is designed to annunciate and alarm d locally in the control room of the OSSF. Fire suopression equip-ment consists of a hydraulic sprinkler system through-out the l facility. A manual hose station with sufficient hose to reach all areas in the facility is located in the truck bay area. Nater is supplied from the existing fire protection system by a 6-inch diameter header pipe. Fire suppression water is collected in the liquid drain trenches and routed to the radwaste treatment system.

1 Drummed radioactive waste is segregated into two distinct storage areas (Figure 2.2), a configuration that will reduce ^he spread of a fire from areas of potential combustion to other '

areas. In addition, potentially combustible DAW stored in the i facility is sealed in steel drums. Fire protection for the truck bay, which is separated from the two storage areas by reinforced concrete walls, is provided by the sprinkler system.

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The HVAC system for the OSSF automatically shuts down on sensing smoke in the outside air supply and exhaust air ducts.

The rooms housing the asphalt storage tank and pumps are provided '

with 3-hour fire barrier walls and doors and an automatic fire detection and sprinkler system. The HVAC systems for these rooms are separate from the rest of the facility, with no interaction possible, and are provided with fire dampers at firewalls that automatically shut down the systems should a fire occur.

2.3.4 Security The entire onsite storage facility is inside the protected area fence and as such is subj ect to all the applicable security ,

requirements.

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t r RADIONUCLIDE CONTENT AND VOLUMES OF DRY ACTIVE WASTE  !

ACTIVITY TOTAL ANNUAL  !

RADIONUCLIDE (%) ACTIVITY (Ci) ,

Co-58 24.0 0.96 <

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, Co-60 7.2 0.29 .

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Cr-51 62.0 2.48  ;

8 Nb-95 6.8 0.27 i

t Cs-137 traces --

TOTAL 100.0 4.00 i.

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t I r "A Survey and Evaluation of Handling I

, Source: AIF/NESP-0800,  !

j and Disposing of Solid Low-Level Nuclear Fuel Cycle '

Wastes," October 1976.

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TABLE 2.2 PRINCIPAL NUCLIDES TO BE SH'.PPED FOR EACH TYPE OF WASTE, IN CURIES PER YEAR, AND TOTAL AN"JAL CURIES INVENTORY FOR NORMAL OPCdATION Reactor Radwaste Condensate Total Water Deminer- Deminer- Annual Cleanup alizer alizer Evaporator Curie Nuclide Resins Resins Resinslo) Concentrates Inventory Br-83 0.00000C-01(b) 1.16913E+00 1.79188C-01 1.26541E-06 1.34832E+00 Kr-83m 0.00000C-01 2.23875E+00 3.57437E-01 5.134770-06 2.59620E+00 3r-84 0.00000C-01 3.79683C-03 7.22983C-04 1.47834E-21 4.51981E-03 Br-85 0.00000C-01 1.17410E-29 2.97303C-28 0.00000C-G1 3.09044E-28 Kr-85m 0.00000C-01 1.70549C-02 3.20709C-03 6.96688C-07 2.02626C-02 Kr-85 1.64861E-04 4.16776C-06 2.28148C-05 1.15575C-08 1.91856E-04 g Rb-89 0.00000C-01 2.29746C-06 7.26265C-07 0.00000C-01 3.02373C-06

^ Sr-89 1.55621E+01 1.27933C+00 5.842570+00 3.34361E-03 2.26873C+01 Sr-90 3.58794C+00 9.36143C-02 4.92849C-01 2.49293E-04 4.17465E+00 Y-90 3.58795C+00 5.26558C-02 4.44097C-01 1.73498C-04 4.08487E+00 Sr-91 0.00000C-01 4.55337E+00 1.26589C+00 1.61166C-03 5.82087E+00 Y-91m 0.00000C-01 2.82625C+00 7.87717C-01 1.00640C-03 3.61497E+00 Y-91 1.21848C+01 8.24790C-01 3.97733C+00 2.23782C-03 1.69892E+01 Sr-92 0.00000C-01 2.47462E&00 3.89607C-01 6.74929C-06 2.86423E+00 Y-92 0.00000C-01 6.64099C+00 1.24570E+00 1.78962E-04 7.88687C+00 Y-93 0.00000C-01 4.85833C+00 1.41013C+00 1.96238C-03 6.27043E+00 Cr-95 1.57499C+00 9.60073C-04 5.393380-01 2.68565C-06 2.11529E+00 Mb-95m 1.65299C+00 4.73829C-04 4.42228C-01 1.62325C-06 2.09569C+00 Nb-95 2.61582C+00 9.74696C-04 5.60955C-01 2.68190C-06 3.17776C+00 Zr-97 1.08471C-27 1.04047C-04 8.87943C-03 9.42086C-08 8.98356C-03 Nb-97 1.16775C-27 1.10213C-04 9.48918C-03 1.01409C-07 9.59949E-03 Uh-98 0.00000C-01 2.77908C-04 1.14920C-02 1.52077C-16 1.17699C-02 Mo-99 1.80834C-05 1.07704C-01 2.05713C+01 2.22873C-04 2.06792C+01

a. This column a1so inc1udes the floor-drain fi1ter backwash, etched-disk fiIter backwash, waste-collector fiIter backwash, fue1 pool fi1ter backwash, and waste-surge-tank sludge letdown activities.

b. 0.00000C-01 = 0.00000 x 10-1

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TABLE 2.2 PRINCIPAL NUCLIDES TO BE SHIPPED FOR EACH TYPE Of iASTE, IN CURIES PER YEAR, AND TOTAL ANNUAL CURIES INVENTORY FOR NORMAL OPERATION (Cont'd)

Reactor Radwaste Condensate Total Water Deminer- Deminer- Annual Cleanup alizer alizer Evaporator Curie Nuclide Resins Resins Resins (a) Concentrates Inventory Tc-99m 1.87070C-05(b) 1.46689E+01 2.37162C+01 1.92686E-03 3.83871E+01 Tc-101 0.00000C-01 1.81282E-05 6.08910C-06 0.00000E-01 2.42173E-05 Ru-103 2.20486C+00 2.30702C-03 1.25215E+00 6.47858E-06 3.45932E+00 Tc-104 0.00000E-01 2.87602C-04 7.80338C-05 2.83144E-35 3.65636C-04 Ru-105 0.00000C-01 9.30097E-03 4.29059C-01 4.05422E-07 4.38360E-01 Ru-106 1.53887E+00 3.93809C-04 2.29075C-01 1.06855E-06 1.76834C+00 Rh-106 1.53887E+00 3.93809C-04 2.29075C-01 1.06855E-06 1.76834E+00 l g Te-129m 3.75800E+00 4.94976C-01 2.15068C+00 1.28384E-03 6.40495C+00 Te-129 2.37146C+00 3.11601E-01 1.35664C+00 8.09914C-04 4.04051E+00 I-129 1.61769E-06 1.29582E-06 1.03468C-05 9.82573C-09 1.32701E-05 Te-131m 5.28299C-15 3.21862C-01 1.97728C-01 4.21576C-04 5.20011C-01 I-131 2.08989C+00 3.62692C+01 9.87310C+01 8.51000C-02 1.37175C+02 Te-131 1.17864E-15 7.18051C-02 4.41124C-02 9.40528C-05 1.16012C-01

, Te-132 1.0988IE-06 6.60390C-02 9.43046C-02 1.30020C-04 1.60475C-01 1-132 1.13181E-06 1.06982C+0L 1.71027C+00 1.41802C-04 1.24086C+01 1-134 0.00000C-01 8.41247C-01 1.34697C-01 6.47984C-13 9.75944E-01 I-133 9.23764C-19 1.16435C+02 5.42991C+01 1.16970C-01 1.70852C+02

%e-133m 1.43926C-07 2.63818C+00 3.83174C+00 6.17179C-03 6.47609C+00 Xc-133 2.37272C-01 5.97500C+0L 1.64427C+02 1.59239C-01 2.24574C+02 I-l35 9.23764C-19 1.16435C+02 5.42991C+01 1.16970C-01 1.70852C+02 Xe-135m 1.78663C-19 2.25194C+01 1.05018C+01 2.26227E-02 3.30438C+01 Xe-135 1.64040C-18 1.09360C+02 6.99436C+01 1.75982C-01 1.79479C+02 Cs-lis 3.72609C-05 4.09811C-06 1.00149C-05 2.56413C-08 5.93995C-05 l a. This column also includes the floor-drain filter backwash, "t ehml-d i sk f i I tar i>ackwash, waste-collector fi1ter backwash, fue1-pool fi1 tor backwash, and waste-surge-tank sludge letdown activities.

b. 1.87070C-05 = 1.87070 x 10-5

O O O TABLE 2.2 PRINCIPAL NUCLIDES TO BE SHIPPED FOR EACH TYPE OF WASTE,

, IN CURIES PER YEAR, AND TOTAL ANNUAL CURIES INVENTORY FOR NORMAL OPERATION (Cont'd)

Reactor Radwaste Condensate Total Water Deminer- Dominer- Annual Cleanup alizer alizer Evaporator Curie Nuclide Resins Resins Resins (a) Concentrates Inventory Cs-134 1.42393C+01(b) 3.99392E-01 2.08376E+00 1.06357E-03 1.67235E+01 Cs-136 1.29514E-01 2.19260E-01 7.40740E-01 5.40141E-04 1.09005E+00 Cs-137 4.10138C+01 1.06855E+00 5.63376E+00 2.84968E-03 4.77190E+01 Ba-137m 3.87991C+01 1.01085E+00 5.32955E+00 2.69580E-03 4.51422E+01 Cs-138 0.00000C-01 5.89863E-03 1.11825C-03 3.66434E-21 7.01687C-03 Ba-139 0.00000C-01 4.90355E-01 7.26507E-02 1.60171E-09 5.63005C-01 Ba-140 2.35146C+00 4.36177E+00 1.46271C+01 1.07336E-02 2.13511E+01 g La-140 2.70655C+00 3.11746C+00 1.53337E+01 9.42156E-03 2.ll671E+01 m Ba-141 0.00000E-01 4.06755E-05 1.09453C-05 8.37480E-36 5.16208E-05 La-141 0.00000C-01 3.67579E-01 6.52748C-02 8.13933C-06 4.32862E-01 Cc-141 2.72762C+00 4.96286C-02 2.00840E+00 1.33889C-04 4.78579C+00 Ba-142 0.00000E-01 9.93434E-09 4.80804C-09 0.00000E-01 1.47424E-08 La-142 0.00000E-01 5.32882E-02 1.23686C-01 8.34322E-10 1.76974E-01 Ce-143 3.58693C-14 9.46458E-04 1.14481E-01 1.45301E-06 1.15429E-01 Pr-143 3.22923C-01 4.23921E-03 1.92350C+00 1.16520E-05 2.25067E+00

Ce-144 1.23703C+00 3.84279E-04 2.22451E-01 1.053960-06 1.45986E+00 Pr-144 1.23708C+00 3.84295C-04 2.22461C-01 1.05401C-06 1.45993C+00 Nd-147 9.02960C-03 2.87530E-04 1.19639C-01 7.69413C-07 1.28956E-01 Np-239 4.70100E-06 4.28149t+01 4.57041C+01 7.59366C-02 8.85950C+01 Ma-24 9.85574C-28 1.72775C+01 6.40198C+00 1.23525C-02 2.36918E+01 P-32 1.81213C+00 2.22655E+00 7.76057E+00 5.52214C-03 1.18048E+01 Cr-51 3.54584C+02 6.670978-01 3.47340C+02 1.86896C-03 7.02593E+02 Mn-54 2.94357C+01 8.98101E-03 5.20572C+00 2.46272C-05 3.46508C+01

a. This column also includes the floor-drain filter backwash, etched-disk filter backwash, waste-collector filter backwash, fuel-pool filter backwash, and waste-surge-tank sludge letdown activities.

b. 1.42393C&01 = 1.42193 x 10 1

p (

I r

TABLE 2.2 PRINCIPAL NUCLIDCS TO DE SilIPPED FOR EACil TYPE OF WASTE, IN CURIES PER YEAR, AND TOTAL ANNUAL CURIES INVENTORY FOR NORMAL OPERATION (Cont'd)

Reactor Radwaste Condensate Total Water Deminer- Deminer- Annual Cleanup alizer alizer Evaporator Curie Nuclide Resins Resins Resins (d) Concentrates Inventory Fe-55 4.80489C+02(b) 1.30242C-01 7.57080C+01 3.54709C-04 5.56327E+02 Mn-56 0.00000C-01 1.01819C-01 3.94358C+00 2.163261:-07 4.04539E+00 Co-58 4.31221C+01 2.41628C-02 1.36386C+01 6.75429C-05 5.67849C+01 Fe-59 3.93650C+00 3.500291:-03 1.920611:+00 9.82639C-06 5.86061C+00 Co-60 1.98741C+02 5.23095C-02 3. 0 4 0 6 81: + 01 1.42102C-04 2.29201C+02 Ni-63 5.123911:-01 1.310731:-04 7.61813C-02 3.56077C-07 5.88905C-01

s. Cu-64 2.44057C-32 4.046931:-01 1.02585C+01 2.59771C-04 3.06634C+01

" Ni-65 0.00000C-01 5.852361:-04 2.25569f:-02 1.05046E-09 2.314221:-02 2n-65 7.996651:+01 2.64156E+00 1.34771C+01 7.01766C-03 9.60922C+01 2n-69 0.00000C-01 2.51141C-02 3.93268C-03 1.40124C-11 2.904681:-02 2n-69m 0.00000C-01 1.45397C-13 6.63999E-12 0.00000C-01 6.78519C-12 Ag-llom 4.00952C-01 1.27699C-04 7.38763C-02 3.50656C-07 4.74956C-01 W-187 2.55098C-18 7.11581E-03 7.20539C-01 8.82722E-06 7.27664_C-01 Total 1. 35228I:+0 3 5.95575E+02 1.15740C+03 8.299091:-01 1.10 60 91; + 0 3 ( C )

a. This column also includes the floor-drain filter backwash, etched-disk filter backwash, waste-collector filter backwash, fuel-pool filter backwash, and waste-surge-tank sludge letdown activities.

h. 4.80489C+02 = 4.80489 x 102,

c. This table represents actual batch processing, which may not produce evenly filled drums. Because the PPD (Figure 11.2-2) at line 70 is calculated assuming each process fills drums evenly, the total annual-curies inventory indicated in Figure 11.2-2 is slightly higher than that indicated in this table.

TABLE 2.3

<3 ANNUAL VOLUME OF SOLIDS SHIPPED I ) FROM NORMAL PROCESSING Estimated Annual Annual ShippedSg{idified Number of Drums System Volume (gal) Shipped RWCU demineralizer resins Condensate / filter demineralizer resins Waste collector and 6,583.5 133 floor drain etched- F disk backwash solids Fuel-pool filter backwash Radwaste demineralizer resins 11,286.0 228 Evaporator bottoms 5,148.0 104 g- ,

'x~ Total 23,017.5 465

a. These volumes are the solidified product volumes as shipped in 55-gallon drums assumed to be 90 percent full.

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3.0 -OPERATION OF THE ONSITE STORAGE FACILITY

's _ / -

3.1 STORAGE - '

3.1.1 Solidified Waste The asphalt solidification system in the radwaste building dewaters and solidifies the radwaste in 55-gallon drums. The drums of solidified waste are then moved f rom the radwaste build-ing to the onsite storage facility by either of the two methods described below.

a. A transfer cart in the radwaste building transfers drums of solidified waste to the drum transfer sta-tion (Figure 2.2) . Once in this area, the drums are remotely transferred onto a roller accumulator-con-veyor. The drums roll to the end of the accumulator-conveyor and are lifted by the bridge crane from the

() conveyor and placed either into the drum weighing and swipe-test station or directly into storage.

b. A main conveyor along tha north wall of the radwaste building accepts drums of solidified waste from a series of conveyors that are perpendicular to the main conveyor. The drums pass into the storage facility at the boundary of the radwaste building by being deposited onto a roller conveyor that deposits the drums onto the drum weighing and swipe-test sta-tion (Figure 2) . This second conveyor will be used as an alternate to the accumulator-conveyor.

Up to eight drums can be stacked vertically in layers in the storage areas. As each layer is completed, grating is placed on top by the bridge crane to provide stability for the next layer of drums.

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The storage capacity is separated into cubicles by inner walls allowing for segregation of waste drums by radioactivity level s/ and/or waste type (e .g . , solidified resins or solidifi~ed concen-trates).

Sample drums from each batch of solidified radwaste resins can be stored in the test and sample area of the OSSF (Figure 2.2) .

Here, periodic inspection of each representative drum can be pur-formed by removing the drum to the drum weighing and swipe-test station for visual inspection.

3.1.2 Dry Active Waste (DAW)

To decrease the volume of DAW to be removed from the site, the OSSF uses a high-efficiency, in-drum compactor system with an ,

internal filtration and ventilation system.

The ventilation system controls any contaminated particles that may be released while the packaging equipment is being operated.

\-) The compacting press has an air exhaust system consisting of a hood, a prefilter, an absolute filter, and an exhaust fan. This system is so arranged that when the ram descends to compress waste material, the air exhaust system descends until the hood is just above the drum and in position to filter the air from the drum as the material is compressed.

Drums of compacted waste are moved from the compactor area into

, the facility by a forklift truck. The crane then lifts each drum and performs essentially the same functions as with the drums of solidified waste.

3.2 DECONTAMINATION I

If a drum should require decontamination, it will be placed into ,

the drum decontamination station. The decontamination station consists of a stainless steel cylinder with a lid into which the drum is lowered from above by the bridge crane.

20

Once the dr um is inside the station, the lid is closed and hot

-~

water heated by steam is sprayed on all sides of the drum. After (s_)g this cleaning cycle, the drum is air dried. The water ,used in the process goes to the liquid radwaste system in the radwaste build-ing, and the air is vented to the onsite storage facility's HVAC system. After decontamination, the drum is again swipe-tested.

3.3 HANDLING i

3.3.1 Loading Retrieving drums of solidified waste from storage for offsite disposal is performed with the bridge crane. Retrieval of drums .

of compacted trash is done by either a forklift truck or the bridge crane. Each drum of solidified waste is picked up from storage and either swipe-tested and decontaminated or placed directly onto a circular shipping pallet that holds seven drums.

A fully loaded pallet is lifted by the bridge crane and placed

(-- into a shielded transport cask (if needed), which is mounted on a

(/ truck trailer located in the truck bay.

1 After loading a cask, the bridge crane places the lid on the cask l

and the shipment is trucked to an offsite disposal area. Alter-natively, drums of solidified waste can be shipped in ,

openended casks. This involves the bridge crane picking up a

• l drum from storage and placing the drum on the cask self-loading  ;

device. The cask would be mounted on a truck. Drums of DAW are l placed onto a flatbed truck or open van by the bridge crane or a forklift truck.

I

, 3.3.2 Drum-Handling System f

j Within the storage facility proper, drums are handled by a 10-ton

! capacity electric overhead traveling bridge crane and by forklif t truck (DAW). The bridge crane is remotely operated from the OSSF i control room. The crane system is designed for precise placement O- of the 55-gallon drums.

l 21 i l

l _ _ _ . _ __ __ . . _ . __ . - , -

The bridge and trolley is accurately positioned by the use of a closed-circuit-TV monitoring system and a coordinate target

(} system. Dedicated TV cameras mounted on the trolley ate directed at the indices of each of two perpendicular coordinates: one coordinate hangs from a crane rail, and the other is attached to a wall. This system enables the operator to accurately position the bridge and trolley by viewing the TV monitor and lining up cross hairs on the camera lens with the appropriate coordinate.

Additional dedicated TV cameras are mounted in the drum accumu-lator-conveyor and at the drum weighing and swipe-test station.

i The drum grab has the capacity to lift up to 6000 pounds. It is supplied with a motor-operated jaw actuator for positive load release control. To ensure positive control, the cable has to be slack (no load) before the jaw can operate. Magnetic particle testing has been used by the manufacturer to determine the 1 presence of discontinuities at or near the surface of the crane hook, lifting eyes, and all weldments. Should a drum drop occur,

( a tipped drum uprighting attachment is used.

\--

For personnel safety and to assist positioning accuracy, the drum 1

must be raised to the full "up" position before high-speed opera-tion is possible with the bridge or trolley. The drum clears all obstacles and is supported to eliminate swinging.

t j Two bridge motors with separate circuitry are provided so that one motor could serve as a backup, if needed. Eye bolts are attached to the bridge to allow the crane to be towed by a build-ing-mounted winch if both motors become defective.

l l

i o

4.0 RADIOLOGICAL CONSIDERATIONS O A radiological assessment has been performed for the. OSSF for both normal operation and postulated accidents.

4.1 NORMAL OPERATION No gaseous or volatile radiation sources are stored in the OSSF, and therefore, no radiological releases are anticipated during normal operation of the OSSF. All radioactive wastes are stored within the plant protected area, inside a reinforced concrete structure, that is kept at a negative 1/4-inch W.G. air pressure.

All ventilation exhausts are monitored for radiation.

4.1.2 Offsite Doses 4.1.2.1 Airborne Effluents

() Since no gaseous or volatile radiation sources are stored in the OSSF, ro gaseous radioactivity is released during normal opera-3 tions a+nd no offsite doses will result.

I 4.1.2.2 Liquid Effluents No liquid radwaste is stored in the OSSF. As discussed in Sub-section 2.3.2, all liquid drains in the OSSF are routed to the Fermi 2 radwaste facility. As a result, no radioactive liquid is i released from the OSSF and no offsite doses will result.

4.1.2.3 Radiation Shine to Offsite Areas Offsite doses due to direct radiation shine emanating from the stored drums were calculated using the ISOSHLD point-kernal shielding computer code. The shielding design and the assump-tions used are discussed in Subsection 2.3.1.1. Annual dose rates O

23

were calculated at the exclusion area boundary (915 meters),

3 assuming 100% occupancy time and at the shoreline of Take Erie (91.4 meters), assuming a 5% occupancy. The results are as follows:

RADIAL ASSUMED ANNUAL ,

DISTANCE OCCUPANCY DOSE RATE 91.4 meters 5% 0.35 mrad /yr '

915 meters 100% 0.21 mrad /yr In both cases the calculated dose rates are below the design objective of 1 mrad / year.

4.1.3 Summary of Normal Operation Offsite Doses In summary, doses to persons offsite for the OSSF are well within the limits of 10 CFR 20, 10 CFR 50 Appendix I and 40 CFR 190.

D 4.2 POSTULATED ACCIDENTS  !

The following postulated events were assessed to determine if they would contribute to the radiological exposure of personnel offsite.

4.2.1 Tornado ,

i The minimum thickness of the exterior concrete walls of the OSSF below elevation 624 feet is 54 inches and a bove elevation ,

624 feet it is 28 inches. The minimum thickness of the concrete slab for the roof is 24 inches. It is unlikely that a tornado would damage a structure of this nature to the exte . that the building's contents would be scattered.

i i

I

i 4.2.2 Flood O

The onsite storage facilf ty is located above the 10b'-year flood elevation of 578 feet. The drum storage area is at elevation 587.0 feet, 4 feet above the plant grade elevation of 583.0 feet.

Therefore, the 100-year flood will not affect the building  ;

contents.

4.2.3 Drum Drop The radioactive warte is kneaded in the solidification system to micron-size particles which are individually coated and homog-j eneously dispersed in an asphalt binding agent. This process eliminates the possibility of free-standing water in the matrix.

In a Brookhaven National Laboratory (BNL) test (" Properties of Radioactive Wastes and Waste Containers," August 1979, BNL-NUREG-50957), BNL reported that asphalt, being a thermo-plastic material, merely deforms as a compressive load is h)

O applied. Asphalt / waste samples deformed elastically under load.

Therefore, even if a drum of solidified waste should be drooped and split open, the asphalt would deform elastically, and no water or radioactive particles would be released.  ;

4.2.4 Fire ,

Due to the extensive fire protection system designed into the OSSF (Subsection 2.3.3), which includes automatic shutdown of the ventilation system, automatic sprinkler system initiation, and fire hoses, a sustained fire in the OSSF was not considered credible.

25 i

For purposes of assessing the consequences of such a hypothetical event, an evaluation was made of the offsite dose resulting from i the release of the radioactivity contained in the D,AW storage drums to the environment using the following assumptions.

e A 5-year inventory (five times the annual DAW inventory in Table 2.1) is involved in the fire, e 1.5% of this inventory becomes airborne *,

e Regulatory Guide 1.3 breathing rate and immersion dose calculation assumptions are applied,

-4 e X/Q = 1.52 x 10 ,

e Regulatory Guide 1.109 critical organ dose conversion factors are applied, e Affected personnel are assumed to be at the exclusion area boundary during the entire time of plume passage, ,

and e Plume centerline concentrations are assumed.

The resultt, of the analysis are tabulated below:

i

• Nuclear Regulatory Commission Staff Environmental Impact i

Appraisal of Low-Level Radioactive Waste Storage at Tennessee Valley Authority Browns Ferry Nuclear Plant, June 1982.

I I 26

t i

EXCLUSION AREA BOUNDARY DOSES AND EFFECTIVE DOSE EQUIVALENTS DUE TO THE BURNING OF A 5-YEAR DAW INVENTORY EFFECTIVE AFFECTED TISSUE DOSE "T* DOSE EQUIVALENT Whole body (Gamma) 0.006 mrad 1.0 0.006 mrem Skin (Beta) 0.001 mrad 0.01 0.0001 mrem Thyroid (Iodine) 0.001 mrad 0.03 0.0001 mrem Lung 1.38 mrad 0.12 0.166 mrem TOTAL 0.173 mrem

• w = Weighing factor as recommended in ICRP No. 26.

T The resultant effective dose equivalent to a member of the general public is well below the limits specified in 10 CFR 100.

() Initiation of the OSSF sprinkler system as a result of the fire i results in no radiological dose offsite from liquid releases since all water drains to the Fermi 2 radwaste building liquid collection system. ,

i i

27

5.0 ENVIRONMENTAL ASSESSMENT The environmental effects of constructing and operating the Fermi 2 plant are presented in the Applicant's Environmental Report Construction Permit stage and Operating License stage.

These effects were evaluated by the NRC and are discussed in the Final Environmental Statement, July 1972, and the Final Environ-mental Statement, NUREG-0769, August 1981. This document, there-fore, is limited to the environmental effects of constructing and operating the Onsite Storage Facility.

5.1 ENVIRONMENTAL EFFECTS OF THE PROPOSED ACTION 5.1.1 Construction of the OSSF Construction-related effects associated with the OSSF are mini-mized since the facility is located on an area of the site that i has already been modified by the construction of the Fermi 2

/m

(} plant buildings and that is still undergoing final construction of the plant.

Construction of the OSSF began in June 1982 and will be completed about June 1983. There will be some additional effects asso-ciated with this activity such as fugitive dust, noise, and socioeconomics; however, these are negligible.

5.1.1.1 Air Quality Since the site is still under construction, the additional small quantity of fugitive dust created will be handled in connection

with the overall site dust suppression program.

5.1.1.2 Noise

, The usual sources of noise associated with the construction l

() activity will be present. These noise impacts are temporary and negligible when associated with an active construction project.

l 28

5.1.1.3 Land Use O- The land use impacts are minimized since the OSSF is being built as an extension of the Fermi 2 radwaste building on an area of the site that has already undergone extensive construction.

5.1.1.4 Solid Waste A small amount of solid waste will be generated due to the con-struction of the OSSF. These wastes will be handled in accor-dance with applicable State and Federal Regulations.

5.1.1.5 Sanitary Waste Portable chemical toilets presently in use at the site, will be used by the construction workers during the construction period.

5.1.1.6 Cultural 1

The proposed action will have no effect on any known archaelogi-cal or cultural resources since it is wholly within previously disturbed areas of the Fermi site.

5.1.1.7 Endangered or Threatened Species The proposed action will have no effect on any known endangered or threatened species since construction is on previously dis-turbed areas of the Fermi site.

5.1.1.8 Flood Plains and Wetlands The Fermi site is located in a flood plain area. A Certificate of l

Consistency under the Coastal Zone Management Act has been l obtained from the State of Michigan for the construction of Fermi 2 in its present location. Since the OSSF is an extension of that construction, it is included in the original certi-fication.

29 l

L 5.1.1.9 Socioeconomic i

Since there are presently about 2400 construction workers on the Fermi site, the estimated additional 50 workers required to con-struct the OSSF will have no socioeconomic impact on the sur-rounding area or region.

5.1.2 Operation of the OSSF 5.1.2.1 Radiological Effects Airborne Effluents Since no gaseous or volatile radiation sources are stored in the OSSF, no gaseous radioactivity will be released f rom the f acility during normal operation and there will be no resultant offsite doses.

Liquid Effluents No liquid radwaste is stored in the OSSF. The drain system for the OSSF is routed to the Fermi 2 radwaste building to the liquid radwaste system; therefore, there will be no liquid effluents from the facility that will result in an offsite dose.

Radiation Shine Offsite doses due to direct radiation shine were calculated and reported in Subsection 4.1. 2.3. The annual dose rates of 0.35 mrad /yr at the shoreline of Lake Erie and 0.21 mrad /yr at the exclusion area boundary are well within 10 CFR 20, 40 CFR 190, and the design objective of 1 mrad /yr.

30

Postulated Accidents O Off t $ Me doses were calculated for a hypothetical incen. diary event of unknown origin that burned a 5-year inventory of DAW drums.

The resulting effective dose equivalent of 0.173 mrem is well within the limits of 10 CFR 100.

Other postulated events discussed in Section 4.2 result in no radiological exposure to the general public offsite.

5.1.2.2 Other Effects The operation of the OSSF will have no adverse ef fects on the environment since it is a storage facility that has essentially no effluents to the atmosphere or to Lake Erie that would affect air or water quality. ,

5.2 UNAVOIDABLE ADVERSE ENVIRONMENTAL EFFECTS O There are no significant adverse environmental effects associated with the construction and operation of the OSSF.

5.3 IRREVERSIBLE AND IRRETRIEVABLE COMMITMENTS OF RESOURCES l Other than the materials of construction that are used in the i OSSF, there are no irreversible and irretrievable commitments of l

resources.

I i

31

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6.0 ALTERNATIVES AVAILABLE TO ONSITE STORAGE FACILITY f) 6.1 OFFSITE DISPOSAL (NO ACTION ALTERNATIVE)

The no action alternative is based on the use of the 455-drum storage capacity in the rad waste building as the only capacity for interim storage of LLRW. The viability of this alternative is dependent upon the continued availability of offsite licensed commercial disposal sites. As stated in Section 1.2, the present and future shipment of LLRW offsite is at best uncertain. Any discontinuity in shipment of LLRW offsite could potentially shut Fermi 2 down in approximately 6 months.

The benefits of this alternative would be a savings of $6 x 10 6 in OSSF construction costs and $100,000 in annual operating and maintenance costs.

As generator of LLRW at the Fermi 2 plant, the Applicant does not -

consider this a viable alternative to either the planned manage-() ment of LLRW or the continued generation and distribution of electricity to its customers.

6.2 OPERATION OF AN OFFSITE LLRN STORAGE FACILITY l

Construction and operation of an offsite LLRW storage facility would consist of essentially the same facilities. However, in addition to the information contained in this document, addi-tional costs and impacts would be incurred:

e Independent NRC licensing action,

! e Additional federal, state, and local permits, 1

I e Purchase of a new site, p 32 U

e Additional environmental effects from construction, o Additional costs related to LLRW handling, trans-portation, operation and maintenance, and security, and e Possible additional radiological exposure due to  !

increased handling and transportation. '

The Applicant considers this alternative to be less desirable i than the proposed action because the environmental, radiological, and financial effects would be greater for the same benefit.

6.3 ONSITE INTERIM STORAGE IN EXISTING FACILITIES ,

Several areas within the Fermi 2 plant were considered for stor-age; however, most of these areas were already designated for other purposes. In many cases, increased handling and trans-w portation of the LLRW would result with the potential for  !

increasing radiation exposures.

l l Certain areas within the Fermi l plant were identified. An eval-uation of this alternative revealed that with the exception of the purchase'of a new site and the environmental effects of con-struction, the additional costs and impacts would be similar to those listed in Section 6.2. Thus, the onsite storage of LLRW in  :

existing facilities results in more significant effects than the proposed action and is not considered a viable alternative.

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7.0 COST BENEFIT DISCUSSION O No anticipated significant environmental impacts andfcosts are associated with the construction and operation of the Fermi 2 OSSF; there are no significant direct environmental benefits derived from its operation.

The estimated cost of the onsite storage facility at Fermi 2 is approximately $6 x 10 6 (1982 dollars). The annual levelized facility costs, that is, interests, taxes, and depreciation (at an assumed 12.7% annual interest rate) is estimated to be  ;

$800,000. In addition, annual operation and maintenance costs are estimated to be approximately $100,000 (1982 dollars). Total levelized annual cost for the facility is estimated to be 6

$8.4 x 10 over the 30-year life of Fermi 2.

If an offsite low-level radwaste disposal facility were available to which all wastes could be shipped, the estimated annual cost of disposal would be (1982 dollars) :

Barnwell, South Carolina $347,000 Beatty, Nevada $622,000 Hanford, Washington $670,200 Since the OSSF at Fermi defers but does not eliminate this dis-posal cost, the direct disposal option would be the preferred alternative, if it were available.

The principal benefit of providing the OSSF is to ensure against  ;

an adverse impact on power generation at Fermi 2. Without off-site disposal and in the absence of the OSSF, shutdown could result within a year. Avoided costs will be the dollar amount to replace the power from Fermi 2 with power generated from higher cost fuel of approximately $18.6 x 10 6 per month (1982 dollars).

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Fixed cost to the Applicant of carrying the non-productive l Fermi 2 plant investment is estimated at $22.1 x 10 6 per month O' (1982 dollars) . Also, non-productive wages of $4.4 x.10 6 (1982  ;

dollars) per month are an added cost in the event of a shutdown.

The benefit lost to the regional society includes the inter-ruption of local property taxes estimated to exceed S600,000 per month (1982 dollars).

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8.0 DECOV* 'SSIONING l \ l Low level radioactive waste will be stored in the OSSF as needed when the Termi 2 plant becomes operational. The applicant antic-ipates shipping LLRW offsite to a licensed commercial disposal facility es long as such a site is available; thus the facility was designed for a 5-year storage capacity.

Near the end of the Fermi 2 plant life, a final decision will be made concerning the methods of decommissioning the OSSF. There are currently several options available:

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e Placing the storage facility in an inactive state and providing a security and monitoring force for an indef-inite time.

e Sealing all radioactive material inside the storage facility in a technique known as entombment.

O e Retrieving all radioactive waste containers and trans-porting to another facility. The storage site can then be decontaminated as necessary, leaving the area as <

close to its original state as possible.

No specific method will be selected at this time since actual decommissioning for the storage facility will not be necessary for the life of Fermi 2. Other methods may be developed in this time period which are more advantageous than the above methods.

At this time it is the applicant's intention to retrieve all stored radioactive waste and ship offsite. If, for some reason, the stored material cannot be removed for offsite disposal, the material can remain in the storage facility. Security and envi-ronmental monitoring precautions will be continued until either O

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the material is disposed of offsite or the facility is decom-missioned. The viability of the latter option depends on con-d tainer dose rates and specific acivities as well as a. regulatory definition of the radiation and concentration levels which are considered acceptable. e The applicant is implementing the following guideline criteria and additional considerations related to facility decom-  :

missioning:

r e Decontaminable coatings will be used in the onsite storage facility to facilitate decontamination.

o Materials that cannot be decontaminated to the unrestricted levels identified in Table I of Regulatory i Guide 1.86 will be disposed of by transporting to a

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permanent disposal site.

O e Materials that meet the unrestricted levels of Regu-latory Guide 1.86 will be disposed of in routine 7 fashion.

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9.0 APPLICABLE CODES AND REGULATIONS The criteria and guidance for the design, construction, and oper-ation of the OSSF are listed below.

9.1 STRUCTURAL j

1. ACI-318-77: American Concrete Institute, Building Code Requirements for Reinforced Concrete.

2. AISC-1978: American Institute of Steel Construction, Specification for the Design Fabrication and Erection of Structural Steel for Buildings.

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3. ANSI-58.1-72: American National Standards Institute, Build-ing Code Requirements for Minimum Design Loads in Buildings and Other Structures. The wind loading will be based on the ,.

50-year mean recurrence interval. '

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4. UBC-79: Uniform Building Code. The main plant requirements for the operating basis and safe shutdown earthquakes will l not be considered, in accordance with U.S. Nuclear Regulatory Commission (NRC) Generic Letter 81-38. The OSSF is designed to comply with the UBC-79 requirements for Seismic Zone 1. <

5. OSHA: Occupational Safety and Health Administration require-ments.

6. ACI-531-79: American Concrete Institute, Building Code Requirements for Concrete Masonry Structures. ,

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7. NRC Regulatory Guide 1.143: Pipes, joints, and fittings of the piping from the main radwaste system to the piping connection for the portable solidification system.

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9.2 RADIOLOGICAL

1. Code of Federal Regulations, Title 10, Part 20, (10 CFR 20),

" Standards for Protection Against Radiation."

2. Code of Federal Regulations, Title 10, Part 50, (10 CFR 50),

" Licensing of Production and Utilization Facilities."

3. Code of Federal Regulations, Title 10, Part 71, (10 CFR 71),

" Packaging of Radioactive Materials for Transport and Trans-portation of Radioactive Materials Under Certain Conditions."

4. Code of Federal Regulations, Title 10, Part 100 (10 CFR 100) ,

" Reactor Site Criteria." j

5. Code of Federal Regulations, Title 40, Part 190, (40 CFR 190) , l

,_, " Environmental Radiation Protection Standards for Nuclear I

(,) Power Operations."

6. Regulatory Guide 7.1, " Administrative Guide for Packaging and Transporting Radioactive Materials."

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7. Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable."

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8. American National Standards Institute, ANSI N13.1-1969, l " Guide for Sampling Airborne Radoactive Materials."

9. American National Standards Institute, ANSI N13.10-1973,

" Specifications for Performance of Onsite Instrumentation for Continuously Monitoring Radioactivity in Effluents."

10. ANSI /NFPA 801-1975, " Facilities Handling Radioactive

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(,, Materials, Recommended Fire Protection Practices."

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