ML20207Q502
| ML20207Q502 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/23/1986 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20207Q498 | List: |
| References | |
| 15737-2-G03-107, 15737-2-G03-107-R05, 15737-2-G3-107, 15737-2-G3-107-R5, NUDOCS 8701270437 | |
| Download: ML20207Q502 (35) | |
Text
{{#Wiki_filter:, 3183-017 Nuclear T E R 13737-2-co3-107 sEv. 5 _ ISSUE DATE June 7, 1985 0 ITS O NSR: .
@ NITS TMI-2 olvlSION TECHNICAL EVALUATION REPORT FOR Waste Handling and Packaging Facility COG ENG C # OJ DATE 6 / 7 /*
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DOCUMENT PAGE 1 OF 35 EPD 3361210 64
3183-017 NO.
!klLJ(3lf3 Ell' 15737-2-G03-107 Title PAGE OF Technical Evaluation Report for Waste Handling and Packaging 2 35 Facility Rev.
SUMMARY
OF CHANGE O Issued For Use 1 Revised and Issued for Use 2 Revised and Issued for Use 3 Revised specific levels for beta / gamma and alpha smearable surface contamination to levels for unrestricted release. Revised description of fire detectors and sprinkler heads, and added HVAC detectors. Deleted reference to fire ho cs. Revised de:cription of equipment exhausts. 4 Revised radioactivity source terms, offsite doses, and environmental assessment. Revised ventilation and negative pressure criteria. 5 Minor changes throughout document. EPD-3M15 11:8A
LATEST LATEST LATEST LATEST LATEST LATEST LATEST REV. SHEET REV. SHEET REV. SHEET REV. SHEET REV. SHEET REV. SHEET REV. SWEET 1 5 2 5 . 5 4 3 4 4 - 5 4 6 2 7 4 8 4 9 0 10 5 11 4 12 5 13 4 14 3 15 5 16 0 17 o 18 1 19 4 20 5 21 4 22 4 23 4 24 4 25 4 26 5' 27 4 28 4 29 4 30 4 31 m 32 4 33 4 34 4 35 4 E E REv. REVISION STATUS SHEET JOB 15737 T SP EC. N O. 3183-017 8 2-G03-107 h n ggCHygL Technical Evaluation Report for 4 Waste Handling and Packaging 5 DOCUMENT TITLE: PAGE 3 OF 35 l Facility D
15737-2-G03-107 3183-017 Waste Handling and Packaging Facility Technical Evaluation Report
; Table of Contents
.E*l' 1.0 Introduction 6 1.1 General 6 1.2 Organization of Report 6 1.3 Conclusion 6 2.0 Facility Description 7 2.1 Purpose of Facility 7 2.2 Summary Description 7 2.2.1. Location 7 2.2.2 Building Description 7 j 2.2.3 Design Basis 7 2.2.4 General Arrangement 8 2.3 Major Systems 11 2.3.1 HVAC 11 2.3.2 Other Major Systems 14 3.0 Technical Evaluation 18 3.1 General 18 3.2 Dose Assessment and Accident Analyses 18 3.2.1 On-Site Dose Assessment 18 3.2.2 Off-Site Dose Assessment 19 3.2.2.1 Normal Operations 19 3.2.2.2 Contaminated Material Fire 22 3.2.2.3 Liquid Spill from Processing Equipment 23 3.3 occupational Exposure 24 3.3.1 Layout 25 3.3.2 Shielding 25 3.3.3 Airborne Contamination Control 26 3.3.4 Radiation Monitoring 26 3.4 Design Conditions 26 3.4.1 Normal Operations 26 3.4.2 Incidents of Moderate Frequency 26 3.4.3 Infrequent Incidents 27 4.0 Safety Evaluation 33 4.1 Technical Specifications / Recovery Operations Plan 33 4.2 Unreviewed Safety Questions 33 5.0 Environmental Assessment 34 6.0 References 35 0422Y Rev. 4
15737-2-003-107 3183-017 P,, age TABLES
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3-1 Fractipnal Isotopic Distributions for Normal and Defueling 28 Waste in the WHPF 3-2 Calculated Annual Airborne Releases from the WHPF 29 3-3 Calculated Annual Dese to the Maximally Exposed Individual 30 from Releases from the WHPF 3-4 Inhalation Dose Calculated at the Exclusion Area Boundary 31 from a Fire in the WHPF 3-5 Calculated Dose to the Maximally Exposed Individual from 32 a Spill of Contaminated Process Liquids in the WHPF FIGURES
- 1. Location of WHPF 16
- 2. Layout of WHPF and Location of Equipment 17 I
l i i I l l l 0422Y Rev. 4
15737-2-G03-107 3183-017 1.0 Introduction 1.1 General TheexistingTMI-2radwastemanagementfacilitiesarealready proving inadequate for the demands placed on them, and significant increases in the waste quantities and waste diversity are anticipated with the increase in recovery-related activities. To accommodate the increase in waste quantity and waste diversity, a new facility, capable of handling the projected waste streams efficiently, is required. The Waste Handling and Packaging Facility (WHPF) is designed for processing and packaging solid radioactive waste generated during recovery operations of TMI Unit 2. The waste will consist of dry active waste (DAW) such as contaminated clothing, and contaminated tools and equipment. Processing, as used in this document, will consist of compaction, size reduction and decontamination of this contaminated material. Depending on the level of contamination after processing through the decontamination systems, tools and equipment will be re-used, discarded as radioactive waste or discarded as clean trash. The WHPF is not a storage facility and no radioactive waste will be stored therein. 1.2 Organization of Report This report is organized as follows: After this introduction, a description of the design and operation of the facility is presented. This is followed by a discussion of
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the safety issues associated with the facility. The report concludes with the safety evaluation required by 10CFR50, paragraph 50.59, " Changes, Tests and Experiments," and an environmental assessment. 1.3 Conclusion The evaluation of the safety concerns detailed in this report results in the following conclusions: o The WHPF fulfills the need for a new facility capable of accommodating the projected waste streams associated with recovery-related activities, o The construction and operation of the facility is not an unreviewed safety question as defined in 10CFR50, paragraph 50.59. 0422Y Rev. 2
15737-2-G03-107 3183-017 2.0 Facility Description 2.1 Purpose of the Facility TheWHPFprovidesfacilitiesforprocessingandpackagingDAWand contaminated tools and equipment from the AFHB and reactor building. The following functions will be performed in the WHPF:
- a. Sectioning and disassembly of large pitees of equipment to a size that will fit into a 55 gallon drrm or a 4 ft x 4 ft x 6 ft low specific activity (LSA) box. This size reduction will be accomplished by use of plasma are and Oxy-acetylene torches as well as hand held tools.
- b. Decontamination of tools and equipment by electro-polisher, paint digester or an abrasive blaster, as required.
- c. Compaction of DAW in 55 gallon drums,
- d. Packaging uncompactible trash and equipment into LSA boxes or drums.
- e. Temporary staging of radiocctive material prior to, during and after processing (i.e., packaging, decontaminating, compaction, sectioning and disassembly).
- f. Receiving radioactive waste, tools and equipment from the reactor building and AFHB and shipping radioactive waste after processing and/or packaging to an onsite staging facility.
2.2 Summary Description 2.2.1 Location As shown in figure 1, the WHPF will be located to the southwest of I the more eastern Unit 2 cooling tower, to the east of the respirator cleaning facility. 2.2.2 Building Description The WHPF, shown in figure 2, is a poured concrete / masonry block building with corrugated roof decking and exterior brick veneer finish. The exterior walls, with the exception of the administrative area and equipment room, are shield walls of reinforced concrete, at least 12" thick, to a minimum height of 10 feet. Concrete masonry blocks will be used above the shield wall. 2.2.3 Design Basis The design of the facility shall conform to the recommended design practices of the American Concrete Institute (ACI), American Institute of Steel Construction (AISC), Building Officials and Code Administrators International (BOCA), and National Fire Protection Association (NFPA). 0422Y Rev. 4
15737-2-G03-107 3183-017 The facility is designed for the probable natural phenomena as required by the BOCA Basic Building Code, local building ordinance, and other national codes and standards. The WHPF is designed as a non-seismic Category I structure. It is designed for seismic loads determined in accordance with the BOCA Basic Building Code. Environmental and operational live loads are determined in accordance with the General Project Design Criteria and applicable ANSI standards. The WHPF is designed to conform with 10CFR20, paragraph 20.1(c). This ensures that personnel exposures associated with the WHPF are ALARA. .In addition, access to the building will be controlled in accordance with the Radiological Control Procedures in effect at TMI Unit 2. 2.2.4 General Arrangement The WHPF is comprised of the following areas: o Inspection area o Compactible trash packaging area o Contamination control area o Disassembly and sectioning area o Decontamination area o Personnel access area o Administrative areas o Receiving and shipping area o Equipment room o Separation, segregation and survey area o Non-compactible staging and packaging area o Swipe test area o Fork lift battery charging area o High radiation staging area Figure 2 shows the layout of these areas and the location of major equipment.
- 2.2.4.1 Inspection Area Equipment and tools awaiting sectioning or decontamination will be
- staged in this area. Packages may be opened for further evaluation, sorting or repackaging. An inspection hood is provided to micimize l the generation of airborne radioactivity if required during the inspection process. Containers leaving this area will not have smearable surface activity exceeding the limits for unrestricted release, as defined in the GPUN Radiation Protection Plan.
2.2.4.2 Compactible Trash Packaging Area In this room, compactible DAW will be compacted in 55 gallon drums. Drums leaving this area will be wiped down to ensure their smearable surface activity does not exceed the limits for unrestricted release. 0422Y Rev. 4
15737-2-003-107 , 3183-017 j 2.2.4.3 Contamination Control Area This is an area where personnel leaving the compactible trash-packaging area can remove the outer layer of their protective clothing. Changing into street clothes may be done in the personnel access control area (section 2.2.4.6). 2.2.4.4 Disassembly and Sectioning Area This area will be used to reduce the size of contaminated equipment and tools by cutting and disassembly. Equipment used for reduction will include plasma are cutting tools and hand held tools. Size reduction is required for: o tools and equipment that are too large to be packaged into drums or LSA boxes; o tools and equipment that need, and are suitable for, decontamination but are too large for the decontamination systems. 2.2.4.5 Decontamination Area This area will contain the following decontamination systems: o Electro-polisher o Paint digester o Abrasive blaster These systems will be used to decontaminate tools and equipment from the containment building or AFHB. A rinse tank will be provided to rinse the tools and equipment after decontamination in the electrc polisher or paint digester. A self-contained emergency shower and eyewash will be provided in this area. The decontamina-tion system equipment, including filters, will each have a contact dose rate that does not exceed 50 ares /hr. Ion exchangers will have a maximum contact dose rate of 100 arem/hr. 2.2.4.6 Personnel Access Control Area This area provides space for personnel to dress prior to entering the contaminated areas of the WHPF, and lockers where they can leave their street clothes. The personnel access control area will also be used for changing back into street clothes upon leaving the contaminated area. Personnel monitoring and frisking will be performed on exiting the contaminated area. This area is designed to ensure that a general area dose rate of 1 arem/ hour is not exceeded. Temporary shielding in the work areas will be provided as necessary to ensure this limit is not exceeded. 0422Y Rev.0
15737-2-G03-107 > 3183-017 2.2.4.7 Administrative Area The administrative area comprises the office, lunch room, area for pendingmachines,toiletfacilitiesandastoragearea. The administrative area is designed to ensure that dose rates of 0.5 ares / hour in the general area, or 0.25 ares /hr in the office will not be exceeded. In addition to the reinforced concrete walls between the administrative area and separation, segregation and survey area, temporary shielding in the adjacent work area will be used as necessary to ensure these limits are not exceeded. The office provides space for record keeping and administrative chores such as completing radiation survey records. The storage area will be used to store supplies needed for the various rooms in the administrative area. 2.2.4.8 Receiving and Shipping Area This area is used for receiving unprocessed DAW and contaminated tools and equipment from the AFHB and reactor building and for shipping the packaged materials, in LSA boxes or 55 gallon drums, to-l an onsite staging facility. Containers ready for shipping will not
- have smearable surface activity which exceeds the limits for
! unrestricted release. - 2.2.4.9 Equipment Area 4 ^ The HVAC equipment, compressor and air purification equipment for the compressed air system, and de-ionizing equipment for processing
! domestic water into desineralized water will be located in this j area. The equipment area is designed to ensure a dose rate of 2.5 arem/hr will not be exceeded. Temporary shielding in the adjacent i
work area will be used as necessary, in addition to the reinforced concrete wall separating these areas, to ensure this dose rate is not exceeded. 2.2.4.10 Separation, Segregation and Survey Area This area provides space for receiving and surveying contaminated waste, tools and equipment transported to the WHPF, staging incoming waste, and determination of the appropriate processing method. All waste and contaminated tools and equipment entering this uncontaminated area will be pre-packaged to ensure a smearable surface activity that does not exceed the limits for unrestricted release. Packages will be labelled in accordance with existing Radiological Controls and Waste Management procedures. No packages will be opened in this area. Temporary shielding will be used as required to reduce the direct dose rate to personnel in the area. 2.2.4.11 Non-Compactible Staging and Packaging Area. Dry active waste that is non-compactible will be packaged into LSA boxes in this area. This area will be used as a staging area for contaminated waste and equipment before processing and while awaiting shipping from the facility. All waste and contaminated ) 0422Y Rev. 5
15737-2-G03-107 3183-017 equipment in this area will be pre-packaged to ensure smearable surface activity does not exceed the limits for unrestricted release. No packages will be opened in this area. 2.2.4.12 SdipeTestArea This is an area of low background radiation provided for taking radiation surveys of the containers and for counting the activity of smears. 2.2.4.13 Fork Lift Battery Charging Area This area is provided for charging the batteries of the fork lifts. It will also be used by personnel who will view operations in the compactible trash packaging area through the window in the wall separating the two areas. 2.2.4.14 High Radiation Staging Area This area is provided as a staging area for containers with contact dose rates in excess of 100 ares /hr. 2.3 Major Systems 2.3.1 Heating, Ventilating and Cooling (HVAC) 2.3.1.1 Design Bases The WHPF HVAC System will:
- a. Maintain a negative pressure with respect to ambient conditions within the contaminated areas of the WHPF by exhausting more air than is supplied and filtering the air being exhausted in order to limit the quantity of airborne contaminants released to the environment.
l l b. Direct air flow from areas of lower contamination toward areas t of higher contamination.
- c. Maintain a winter temperature of 700F and a suaner temperature of 750 F in the WHPF for outdoor design temperatures of Summer 940FDB 750FWB Winter 70F except in the receiving and shipping area and in the equipment room. These areas will have winter heating and forced or natural ventilation for summer cooling. The design temperatures are:
Summer Winter Receiving and shipping area 1040F (max) 600F , Equipment room 1040F (max) 600F ! 0422Y Rev. 4 j
.. -. . - =
15737-2-G03-107-3183-017
- d. Provide exhaust hoods or other devices for process equipment in order to limit exposure of personnel to airborne contamination.
.e . Maintain the concentrations within the process areas of the WHPF below maximum permissible limits as defined in 10CFR20, Appendix B, Table I, Column 1.
- f. Limit releases of airborne radioactivity to the environment below the concentrations established by 10CFR20, Appendix B, Table'II, Column 1 and the TMI-2 Environmental Technical Specifications.
- g. Supply filtered ventilation to provide approximately 5 air changes per hour.
2.3.1.2 System Description 2.3.1.2.1 General Description The WHPF HVAC system will be divided into several areas which are described in section 2.3.1.2.2. The administrative area, shipping and receiving area and the equipment room are clean areas and are each served by separate heating and ventilation systems which are not associated with the HVAC system for the potentially contaminated work areas of the WHPF. All penetrations are sealed between clean areas, e.g. the administrative area, and the processing areas. A radiation monitor is provided in the exhaust to the atmosphere from the potentially contaminated areas, downstream of the filter, to monitor radioactive releases to the environment. Excessive levels will automatically shut down the exhaust and supply systems. Supply units are not permitted to run unless the exhaust system is on. Flow direction from relatively clean to more contaminated areas is maintained by appropriately arranging supply and exhaust quantities to each air space. 2.3.1.2.2 System Operation Shipping and Receiving In winter time the temperature of this area is maintained at or above 600F. During the summer forced or natural ventilation will prevent the temperature from rising above a maximum temperature of 1040F. Due to the location of the equipment access doors leading into the separation, segregation and survey area from the shipping and receiving area, the negative pressure in the potentially contasinated areas will cause air to flow from the shipping and receiving area into these areas during normal operation. Equipment Room During the winter the temperature of this area is maintained above 600F, In summer, forced or natural ventilation will prevent the temperature of this area from rising above 1040F. 0422Y ; Rev. 5 !
15737-21G03-107 3183-017 Administrative Area This area will have an independent HVAC system to heat, cool and ventilate the area. The air, which may be recirculated within the administrative area, will not require filtering before. recirculating or exhausting to the outside. Air from the toilet areas will not be recirculated. Air conditioning is provided by a heat pump system with mechanical cooling which will-also provide supplementary electric heat as required. This system is controlled by a wall mounted programmable thermostat. Potentially Contaminated Work Areas One or more HVAC units will be provided for these areas. Air will be supplied at a constant flow rate and temperature all year round. Duct mounted temperature controls will be provided. A temperature switch, which senses the outdoor air temperature, determines whether the refrigeration system or the heating coil is required to be in operation. Electric reheat coils controlled by room thermostats may be used to maintain temperature in each zone. Outside air will be supplied to the WHPF for cooling and heating the
-air, and for ventilation, as required. Air may also be taken from j clean areas for makeup for this HVAC system. Recirculated air or induction units ray be used to maintain the required supply air temperature. If recirculated air-is used, it will be HEPA filtered. Air from the sectioning area, electro polisher, rinse tank and paint digester will not be recirculated.
Exhaust hoods are installed at each equipment location where fumes or other contaminants are generated, in order to reduce the exposure l to operating personnel. Air flow through these hoods, except for the compactor exhaust, may be continuous. When the compactor is in operation the main exhaust fan draws air from the compartment above the barrel through a HEPA filter and discharges it to the main exhaust system. When the compactor is not-in operation, a control damper opens and the same room exhaust flow rate is maintained as when the compactor was operating. A differential pressure gauge, l which is an integral part of the compactor, indicates when the filters must be changed. The inspection table hood exhausts directly to the main exhaust system through the main HEPA filters. i Exhaust and supplied air quantities will be regulated to ensure a l negative pressure is maintained in the potentially contaminated work areas relative to ambient condition. Preferably some of the exhaust hoods will be in continuous operation when the system is operated. As additional hoods are placed in use, the quantities exhausted and supplied will be adjusted to maintain a constant exhaust rate from the building. (Exhaust steps up before supply and supply steps down before exhaust). I t 0422Y + Rev. 4
~ - - - = _ _
15737-20G03-107 3183-017 2.3.2 Other Major Systems 2.3.2.1 Compressed Air Th'e compressed air system consists of compressors and an air purification package. Compressed air for the WHPF is provided by two 100 cfa, 125 psig, compressors located in the equipment room. An air distribution system is provided throughout the facility. The compressed air furnished is primarily for tools used in the facility. The system is also capable of providing breathing quality air when used in conjunction with the air purification package and appropriate radiological control procedures. Breathing air may be required during certain sectioning processes. Condensate drained from the compressed air system will be routed to the sanitary drainage system. r 2.3.2.2 Demineralized Water Demineralized water is provided for sytten make-up by processing i domestic water within the WHPF. This processing equipment consists of replaceable / rechargeable de-ionizing resin tanks and associated piping and accessories. Water is routed through a distribution system to the decontamination area and battery charging area of the WHPF. Controls limit to 50 gallons the amount of water that can be supplied to the process area without resetting the controls. Resin regeneration will not be done in this facility. 4 2.3.2.3 Fire Protection A sprinkler system will cover the entire facility. The system shall conform to the applicable portions of National Fire Protection Association (NFPA) chapter 13. The system will consist of fusible sprinkler heads, piping and fittings, isolation valve with tamper-proof switch, and an adjustable time-delay action deluge valve with abort switch. The deluge valve will be actuated by a signal from a heat or ionization detector, or manually. The sprinkler system shall be for ordinary hazard (group 1). The building shall be zoned as required. Heat detectors set for 1350 F shall be placed appropriately throughout the facility. Smoke detectors will be located inside the inlet ducting to the KVAC. Audible fire alarms, which are activated by the detectors, shall annunciate simultaneously at the local panel, and in the plant main control room. Signals for trouble, alarm, and system discharge shall be annunciated. All wiring shall be supervised. A signal from any detector shall initiate the alarms and the time-delay action to open the deluge valve. Auxiliary contacts shall be provided in the panel to shutdown the HVAC system. T 0422Y Rev. 3
i
-15737-2-G03-107 3183-017-i Fire hose standpipes will be provided in conformance with the applicable portions of NFPA Codes and Standards. Portable fire e,xtinguishers will be provided throughout the facility in accordance ilth NFPA Codes and Standards.
2.3.2.4 Waste and. Drain Systems
- A sanitary drain system from the toilet area of the WHPF will be routed to the plant sanitary system. Clean, uncontaminated condensate from the HVAC system may also be discharged to this system.
Spills or leakage within the process area from processing equipment,
.he demineralized water system and from the sprinkler system will be t
contained in the individual areas and will not he' discharged into this waste and drain system. 2.3.2.5 Domestic Water System Domestic hot and cold water will be provided to the toilet area. Demineralized water will be processed from domestic water. 2.3.2.6 Electrical Electrical service is provided to supply power for lighting, receptacles and electrically operated equipment. All electrical . equipment, structures and metal components are grounded. 2.3.2.7 Communications
-The WHPF communication system interfaces with the existing plant PA communication system.
2.3.2.8 Radiation Monitoring A portable airborne radioactivity monitor with local readout and alara is provided for personnel protection. Exhaust to the atmosphere is isokinetically sampled for particulate activity. An exhaust monitor is provided with local alara, readout and recorder, and remote alara in the main control room. Portable monitors will be used as required. Area radiation monitors will be provided as 4 required by radiological control procedures. Air samples from the building exhaust, which are used to assess radiological releases to the cavironment, will be analyzed for alpha activity. In the event any of these samples shows a significant increase in the frequency of alpha detection, the level of analytical scouting for the alpha emitters will be increased appropriately to address the situation. 0422Y Rev. 5
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15737-2-G03-107-3183-017 3.0 Technical Evaluation 3.1 General This section summarizes the safety issues which were considered in the design of the WHPF. These issues deal with the expected i performance of the facility during normal operations and various i design basis events. The safety issues associated with the operation of the WHPF are: o Demonstrating compliance with 10CFR20 with respect to on-site dose limits. o Demonstrating compliance with 10CFR50, Appendix I, with respect to offsite radiation doses due to releases of radioactivity to the environment from normal operations within the WHPF. o Assessing the consequences of potential accidents in the WHPF that cauld lead to radioactive releases to the environment. 1 o Demonstrating compliance with the principles of ALARA. *h , Each of these issues is addressed in the following sections. l 3.2 Dose Assessment and Accident Analysis - i 3.2.1 On-Site Dose Assessment The WHPF exterior walls will be reinforced concrete or grout filled CHU blocks and will be 10 feet high. These walls will be thick enough to ensure that the direct dose rates from material in the building will not exceed the following dose rates: Dose Limit Minimum
- Wall Thickness
-outside building 2.5 area /hr 12 inches
-site boundary fence 0.6 area /hr 12 inches i
These wall thicknesses are based on the dose rates from 20 drums, each with a contact dose rate of 100 ares /hr in 2 rows, stacked 2 high, staged adjacent to the wall. The calculation of the dose rates was performed using an interactive computer program designed 7 l_ to solve gamma ray transport problems using the point kernel method. Any response function can be calculated by specifying appropriate conversion factors and Berger buildup factor parameters. The program library contains attenuation coefficients and buildup factor parameters for common shielding materials, and dose equivalent and absorbed dose conversion factore. The problem geometry must be described by a set of up to 15 orthogonal slabs, i right cylinders, and/or right parallelepipeds. 0422Y Rev. 1
15737-2-G03-107 3183-017 4 These assumptions are also used in calculating the wall thicknesses required to ensure that the following dose rates within the facility are not exceeded: Dose Limit Minimum Wall Thickness
-Personnel access area 1.0 ares /hr 15 inches
-Administrative area 0.5 area /hr 15 inches
-Office 0.25 area /hr 15 inches
-Equipment area 2.5 area /hr 12 inches The wall for the personnel access area will be filled CMU block.
The other walls will be formed of poured concrete. Since radiation field strengths are not precisely known for i components that may be staged or processed in the WHPF, temporary shielding and/or administrative controls may be required to limit the radiation field directly outside the WHPF. This may include limiting personnel access to particular areas outside of the WHPF to prevent unnecessary personnel exposure. Administrative controls will be in accordance with radiological control procedures.
- 3.2.2 Off-Site Dose Assessment 3.2.2.1 Normal Operations 3.2.2.1.1 Airborne Dose
] The handling of contaminated material in the WHPF was evaluated to determine the resultant offsite doses from airborne activity released from the facility. The only source for airborne radioactivity in the WHPF will be the result of activities related to processing contaminated material from the reactor building and AF HB. To assess this dose, the following assumptions were made:
- a. The material staged in the separation, segregation and survey area and in the non-compactible staging and packaging area of the WHPF is radiologically clean, that is, it will not have smearable surface activity that exceeds the limits for unrestricted release.
- b. The total annual activity available for release from dry active waste and contaminated tools and equipment being processed in the contaminated areas of the WHPF is equivalent to the activity of:
120,000 ft 3 dry active waste (DAW) and 12,000 ft 3 contaminated tools and
- equipment (ref. 1) 500 Curies total 0422Y Rev. 4
15737-2-003-107 3183-017 I
- c. Of this activity 10-6 is released due to material handling. .
; This release fraction is based on the airborne release fraction due to a drum containing compacted waste breaking open through
' ; impact The10-{ref.2)forallmaterialhandlingexceptsectioning.
< release fraction from sectioning is based on the i assumptions that a high fraction of activity along the cut line
) may become airborne but that only a small fraction of the
; equipment and tools will be sectioned, and only a small
- fraction of the surface area is in the cut zone. No credit is taken for the WHPF building or ventilation system filters in
- reducing the release of radioactive materials.
- d. The assumed isotopic distributions of radioactive materials processed through the WHPF are listed in Table 3-1 for the two waste streams expected to predominate during the recovery period. Defueling waste may include transuranic and other -
fuel-related isotopes, and normal waste is composed primarily of cesium-134, cesium-137 and strontium-90. The isotopic distributions were derived from radwaste conversion factors for these waste streams, which are developed according to TNI-2 procedures. l e. To assess offsite doses from normal operations it was assumed that half the activity released is from defueling waste and , half is from normal waste. i Table 3-2 lists the estimated annual airborne releases based on the ! above assumptions. i The dose to the public was calculated for these releases based on i the following parameters.
- a. The nearest milk cow is located 1.1 miles east cf the release point. The corresponding meteorological dispersion and deposition parameters at this location are 6.91 x 10-6
- sec/m3 and 2.05 x 10-8 / ,2 for X/Q and D/Q, respectively,
! at this location.
i b. The nearest residence and garden are 0.4 mile south-south-east i of the release point. The corresponding meteorological parameters are 5.57 x 10-5 eec/,3 and 2.10 1 10-7/m2 for X/Q and D/Q, respectively, at this locetion. l c. The nearest mest and milk goats are 1.2 miles north of the release point. The corresponding meteorological parameters are 7.83 x 10-6 eeef,3 and 1.71 x 10-8/,2 for X/Q and D/Q, respectively, at this location. i i d. The vegetable intake for the individual of interest is assumed ' to be from the location of the nearest garden. t <
- e. The dose rate from the ground plane source was calculated based i on the location of the nearest residence as described in b.
above. l l ! 0422Y Rev. 5
_ - . . .- .--. ----- - - ._ ~ - . _-. 15737-2-G03-107 3183-017 i l The locations were obtained from a table cf receptor locations and the meteorological parameters were obtained from the E4I-Unit 1
-Offsite Dose Calculation Manual (ODCM), and are applicable to
. Unit 2. The resulting annual dose to the maximally exposed
-individual is suasarized in Table 3-3.
The most restrictive dose is to a child's bone. This maximum calculated dose is 0.2 ares /yr when the milk consumed is from a
- goat. This dose is a small fraction of the 10CFR50 Appendix I '
limits for the site. The mariaua total body dose is 3.4 x 10-2 ares / year. If credit is taken for the NEPA filters in the WHPF ventilation exhaust these annual doses will be further reduced by a factor of 1000. The average particulate release from the WHPF is 1.6 x 10-5 pCi/sec, which is based on 500 curies throughput with a release fraction of 10-6, averaged over the period of one year. This is a , vergsmallpercentageoftheTechnicalSpecificationlimitof2.4x 10' pCi/sec for particulates. 3.2.2.1.2 Skyshine and Direct Dose Rate The whole body dose to a member of the public from all sources in the fuel cycle is limited to 25 area / year by 40CFR190. An analysis was made to determine the contribution to this dose from operation of the WHPF. Both direct and air-scattered (skyshine) radiation were considered in this analysis. The following parameters were used:
- a. The WHPF is in the S and SSE sectors. The nearest residence for these sectors is in the SSE sector sad is 0.4 miles from the facility;
- b. Credit was taken for 12 inch concrete outer walls of the WHPF, but no credit was taken for inner walls or roof; j c. A total source of 3.83 x 1011 ganaa/see is used for the j skyshine analysis. This source ters includes the contribution from all sources within the WHPF that contribute to the skyshine dose (e.g. waste containers, equipment, etc.);
- d. The direct offsite dose is from drums staged in the WHPF with a contact dose rate of 100 ares /hr;
- e. The gamma emissions from the WHPF are assumed to be Cs-137 energy (0.662 mev).
- f. An occupancy factor of 0.7 at the residence was assumed.
1 The skyshine dose calculation was performed utilizing a previous { skyshine calculation done for the Interia Solid Waste Staging i Facility (see Ref. 6). This calculation used a point-kernel theory ! 4 l 0422Y Rev. 4
3183-017 computer code which accounts for the scattering in air. The degradation of the scattered photon's energy is determined from the , incident energy and angle of scatter of the uncollided photons. l
. The Klein-Nishina differential scattering cross section formulation
; is used to assess the probability of scattering from the i
differential scattering volume (air). Multiple scattering in air is also accounted for by applying a buildup factor. The total annual dose to a member of the public was calculated to
]
be 0.87 ares from skyshine and direct radiation from the WHPF. l This annual dose is at a distance of 0.4 miles from the WHPF. ) However, the distance to the nearest residence from the site is j measured from the mid point between the MI-l and MI-2 reactor i buildings. The WHPF is approximately 0.5 miles from this j residence. Therefore the dose contribution to the nearest i residence from the site resulting from the operation of the WHPF , I will be a small fraction of the 40CFR190 limit of 25 ares / year. i I 3.2.2.2 Contaminated Material Fire ,, j For the purpose of evaluating the consequences of a potential fire in the WHPF the following assumptions were made , 4 l a. The total activity assumed available for release in a fire is ' the total activity of the staged material (from ref. 1), both awaiting processing and awaiting shipment, plus the expected activity from waste and equipment being processed. Using conservative assumptions regarding the volume of waste in the WHPF, the total activity assumed to be present at any one time in the WHPF is eithers o 10 curies defueling waste, or i o 15 curies defueling and normal waste (50% each, by activity).
- b. Although auch of the waste at any time will be in sealed metal containers, the release fraction was chosen as 10-2, which is i
derived for waste burning in an open fire (ref. 2). i
- c. No credit was taken for HEPA filtration or' the ,WHPF building in reducing the releases of airborne radioactivity from the WHPF.
- d. Accident breathing rates were used (ref. 3).
i e. No credit was taken for the fire protection system, that is, all waste present in the building was assumed to be involved in the fire. , The resulting inhalation dose was calculated using the 1-hour meteorological dispersion parameter (X/Q) of 6.1 x 10-4 sec/m3 for a ground level release. This is discussed in Appendix 2D of the Three Mile Island Unit 2 Final Safety Analysis Report (FSAR).
- The resulting doses are tabulated in Table 3-4.
I 0422Y Rr,v. 4 i , i
. - - , . . _ . . . _ . - - . . , - _ , _ . - , - _ _ _ . _ _ . , - - - - - - . - - - _ _ , , . _ _ . , - - - . , _ _ , - _ _ . _ _ _ _ __-._y_ m _._.---_..-.m., , , .
15737-2-G03-107 1 3183-017 The maximum calculated offsite dose in the event of a fire in the WHPF was for the case of 10 curies of defueling waste in the
-building. The maximum organ dose and the whole body dose are a small fraction of the dose limits set by 10CFR100 for a comparable
" limiting organ or whole body. The consequences of this accident are also compared to 10CFR20, which defines a limiting whole body dose of 500 millirea/ year to unrestricted areas due to normal operations. Since specific organ dose limits are not given in 10CFR20, the separate organ doses were evaluated according to ICRP Publication 26 (ref. 9), which states that, for dose limitation, the risk should be equal whether the whole body is irradiated uniformly or whether there is non-uniform irradiation, as in the current case. The methodology and weighting factors contained in ICRP Publication 26 were used to determine the whole body dose which is equivalent in risk to the doses given in Table 3-4. The resultant maximum equivalent whole body dose is 119 millires which is well within the 10CFR20 limit of 500 millires for the maximum annual dose to the whole body in an unrestricted area.
3.2.2.3 Liquid Spill from Processing Equipment For the purposes of evaluating the consequences of an airborne release from a potential spill, or leakage, from the processing equipment in the WHPF the following assumptions were made:
- a. It is assumed that the total content of all tanks in the process area is spilled. This results in a total of 0.95 ci available for release based on each tank and filter having a contact dose rate of 50 mrem /hr and a 100 ares /hr contact dose rate for the ion exchangers. The isotopic distribution is assumed to be that of defueling waste.
- b. The HEPA filter in the ventilation exhaust was not considered in estimating the doses from the airborne release from a liquid spill.
- c. A release fraction of 10-4 was used, based on the airborne release in a liquid spill (Table 7, ref. 4).
- d. Accident breathing rates were used (ref. 3)
The resulting inhalation dose was calculated using the 1-hour meteorological dispersion parameter (X/Q) of 6.1 x 10-4 sec/m3 for a ground level release. This is discussed in Appendix 2D of the Three Mile Island Unit 2 Final Safety Analysis Report (FSAR). The resulting doses are tabulated in Table 3-5. The maximum calculated offsite dose from an airborne release resulting from a liquid spill in the WHPF is 0.62 mrem to a j teenager's bone. The HEPA filter in the WHPF exhaust ventilation was not taken into consideration in determining the doses from a liquid spill. If credit is taken for the filter the dose will be reduced by a factor of 1000. 0422Y Rev. 4
15:37-2-G03-107 3183-017 An evaluation was also made of the effects of liquid effluent from a potential spill or leakage. In this evaluation the following assumptions were made.
- a. Liquid in the decontamination equipment has a total activity of 0.95 C1, as explained for the airborne release from a liquid l spill. It is all released in the liquid effluent. The volume of the liquid is estimated as approximately 2000 gallons.
- b. The isotopic distribution is assumed to be that of defueling waste.
- c. The entire liquid volume is released to the east channel, and' no dilution of the effluent occurs in the east channel. Tha river flow is 10,000 cfs at the das elevation (ref. 5 Figure 2.4-6). A dilut. ion factor is applied for mixing with the river beyond this point. This factor is 3.0 x 10-7 and is the
~
l i ratio of the flow rate of contaminated liquid over the das in the east channel and the flow rate of the river. This effluent will be diluted by mixing with the Susquehanna River water. Criteria are given in 10CFR20, Appendix B, based on the ' concentration of an isotope (C i) and its maximum permissible concentration (MPC 1 ), from Table II of Appendix B of 10CFR20, for l which an isotope may be considered not present in a mixture. These criteria are: A SPC
- Ad and CA +C B
+ " < 0. 25 .
MFC MPC A B The greatest C /MPCA A is 6.9 x 10-2, for Sr-90. Application of the second criteria results in a sua of 7.0 x 10-2 As both of the criteria are met for a spill from the decontamination equipment in the WHPF, this release does not need to be considered i in calculations of doses from liquid effluent releases. 3.3 Occupational Exposure Minimization of personnel radiation exposures is a primary consideration in the design of the WHPF. The design and operational philosophies for the facility follow the guidelines set forth in NRC Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Revision 3, June 1978. This section describes the design features that are provided to ensure that exposures are ALARA. 0422Y Rev. 4
15737-2-G03-107 3183-017 3.3.1 Layout The WHPF general arrangement provides for separation of higher j radiation areas from lower radiation areas. This separation is 1 achieved through distance and through the use of physical barriers for shielding and minimizing the spread of contamination. For example, the compacting area is separated from the non-compactible staging and packaging area by a 12 inch grout filled CMU wall. Decontamination equipment is consolidated in the area reserved for decontamination equipment, and can be surrounded by temporary shielding, as necessary. This shielding will protect personnel in the contaminated work area from this potential source of direct l radiation. Personnel access to and from the WHPF is provided through the office, in the administrative area, and through the receiving and shipping area. Access to the separation, segregation and survey area is from the administrative area and the receiving and shipping area. Personnel access to the equipment room is through the administrative area. These areas of the WHPF will have the lowest general-area radiation level. 3.3.2 Shielding Shield walls inside the WHPF include the grout filled CMU walls around the compacting and decontamination areas. This shielding, coupled with appropriate health physics control of each area, provides assurance that occupational exposures will be minimized in these areas. The 15 inch thick concrete shield wall separating the administrative area and equipment roca from the remainder of the facility will be a minimum of 10 feet high. This will ensure that dose rates of 0.5 area /hr in the general administrative areas, 0.25 area /hr in the office and a dose rate of 2.5 area /hr in the equipment room are not exceeded. The grout filled CMU block shield wall around the personnel access control area will be a minimum of 15 inches thick and 10 feet high. This will ensure a dose rate of 1.0 area /hr is not exceeded in this area. Separate, shielded areas are provided for staging containers of waste that have a contact dose rate in excess of 100 area /hr, and for taking smears from and surveying containers. Exterior concrete walls will be 10 feet high to satisfy radiation shielding requiresents for uncontrolled areas outside the WHPF. The requirement to design the facility so that the radiation field on the outside of the facility is maintained at no greater than 2.5 ares /hr will ensure that the radiation field will not exceed the 0.6 ares /hr limit established for the site boundary fence. 0422Y Rev. 4
15737-2-G03-107 3183-017 l l Since it is not known precisely what radiation sources will be introduced into the WHPF during the recovery, temporary shielding or restricted access both inside and outside the WHPF will be used
,;as necessary to ensure compliance with the dose rate criteria.
Figure 2, Layout of WHPF and Location of Equipment, provides additional details on the location of shield walls. 3.3.3 Airborne Contamination Control The WHPF ventilation system is designed to draw air from areas of low potential for contamination to areas of higher potential for contamination. Air from contaminated, or potentially contaminated areas will be filtered by HEPA filters prior to recirculation or discharge to the atmosphere. Radioactive waste and equipment entering the WHPF will be packaged or wiped down to ensure its smearable surface activity does not exceed limits for unrestricted release. All material staged in the staging areas will have a smearable surface activity that does not exceed limits for unrestricted release. Separate hoods will be used as required for inspection, compaction, sectioning and decontamination. An individual HEPA filter is incorporated into the design of the compactor. 3.3.4 Radiation Monitoring The radiation monitoring system, described in Section 2.3.2.8 will alert personnel to abnormally high airborne radiation levels. Steps can then be taken to minimize personnel occupancy in the affected areas or to reduce the airborne levels as appropriate. Additional radiation monitoring equipment will be provided in accordance with existing radiological controls procedures. 3.4 Design Conditions The design conditions which must be satisfied are specified in the TMI-2 GPDC. These fall into three categories: normal operation, incidents of moderate frequency, and infrequent incidents. Each of these categories is addressed below. 3.4.1 Normal Operations Normal operation conditions are discussed in the previous sections. These operations will be carried out without unplanned or uncontrolled releases of radiesetive materials to the environment. 3.4.2 Incidents of Moderate Frequency The WHPF and the equipment provided with the WHPF serve no nuclear safety related functions and since there is no interface with any safety system, it will not interfere with the performance of any safety related feature, such as safe shutdown systems. The effects of loss of electrical power in the WHPF, inadvertent actuation of a 0422Y Rev. 5
15737-2-G03-107 3183-017 component provided with the WHPF, single operator error associated with the operation of the WHPF, or a single failure of an active component in the WHPF, such as the HVAC, are enveloped by tha
,. analyses of infrequent incidents. They will not, therefore, endanger the health and safety of the public.
Normal operations in the WHPF will involve the handling of contaminated radioactive material. During the course of handling the packages there is the possibility that a package could be broken open. This would not result in an uncontrolled release of radioactivity to the environment because of the design of the HVAC system, discussed in Section 2.3.1. Releases of radioactivity to the environment would be minimized by the filters in the filtered exhaust system provided with the WHPF. The result of a package breaking open is envelop i by the normal release calculation. 3.4.3 Infrequent Incidents 3.4.3.1 Tank Rupture or Pipe Break Tanks containing liquid are located in the decontamination room (decontamination equipment and rinse tank). Demineralized water will be connected by pipes from the domestic water inlet, through ' the ion exchanger and to equipment, as required. The decontamination area is surrounded by a concrete curb which prevents any spill in this area from flowing into other areas of the facility. Any spill from a pipe leakage in areas other than these will be manually cleaned. Potential offsite doses from a spill of contaminated liquid have been previously evaluated (see Section 3.2.2.3). 3.4.3.2 Fire An automatic water suppression system and portable fire extinguishers are provided to extinguish any fire within the WHPF. The radiological effects offsite from a fire in the WHPF are discussed in sections 3.2.2.2. 3.4.3.3 Operating Basis Earthquake (0.B.E.) In the event of an 0:B.E. it is postulated that containers of waste and the decontamination equipment will rupture. The effects of this are enveloped by the liquid spill and fire analyses. 0422Y Rev. 4
15737-2-G03-107 3183-017 Table 3-1
~
- Fractional Isotopic Distributions For Normal and Defueling Waste in the WHPF Isotope Defueling Waste Normal Waste Sr-90 0.50 0.073 Cs-134 0.10 0.024 Cs-137 0.34 0.903 Pu-238 3.0 E-4 Pu-239 3.4 E-3 Pu-240 9.1 E-4 Pu-241 4.1 E-2 An-241 5.6 E-3 4
0422Y Rev. 4
15737-2-G03-107 3183-017 TABLE 3-2 .. CALCULATED ANNUAL AIRBORNE RELEASES FROM THE WHPF Radionuclide Annual Release (curies) Sr-90 1.5 x 10-4 Cs-134 3.1 x 10-5 Cs-137 3.1 x 10-4 Pu-238 7.4 x 10-8 Pu-239 8.6 x 10-7 Pu-240 2.3 x 10-7 Pu-241 1.0 x 10-5 Am-241 1.4 x 10-6 0422Y Rev. 4
15737-2-G03-107 3183-017 TABLE 3-3
. CALCULATED ANNUAL DOSE TO THE MAXIMALLY
- EXPOSED INDIVIDUAL FROM RELEASES FROM THE WHPF I. Annual Dost from Inhalation, Vegetable Intake, Meat Consumption, Cow Milk, and Ground Plane Dose to Organ (arem/yr)
Age Group Bone Total Body M Liver Adult 2.0E-1 3.1E-2 1.0E-2 2.3E-2 l Teen 1.9E-1 2.6E-2 1.5E-2 2.5E-2 Child 1.9E-1 3.1E-2 1.4E-2 2.5E-2 Infant 5.7E-2 '7.5E-3 1.1E-2 1.8E-2 II. Annual Dose from Inhalation, Vegetable Intake, Heat Consumption, Goat Milk, and Ground Plane Dose to Organ (arem/yr) Age Group Bone Total Body M Liver Adult 2.0E-1 3.4E-2 1.0E-2 2.5E-2 Teen 1.9E-1 2.9E-2 1.6E-2 3.0E-2 Child 2.1E-1 3.4E-2 1.SE-2 3.2E-2 Infant 7.5E-2 1.0E-2 1.2E-2 3.4E-2 l 0422Y Rev. 4
15737-2-G03-107 3183-017 TABLE 3-4
. INHALATION DOSE CALCULATED AT THE EXCLUSION AREA 1- BOUNDARY FROM A FIRE IN THE WHPF Controlling Organ Weighting Equiv. Whole Og Age Group Dose (area) Factor (Ref. 9) Body Dose (area)
Bone Tcensger 656 0.12* 70.7 Total Body Teenager 27 1.0 27.0 Lung Teenager 64 0.12 7.7 Liver Teenager 96 0.06 5.9 Total 119.3
- Weighting factor for red bone marrow is used for all bone dose. This overestimates the equivalent whole body dose since some radionuclides tend to remain deposited on the bone surfaces, for which a lower weighting factor may be used.
1 i
- 0422Y Rev. 4
15737-2-G03-107 3183-017 TABLE 3-5 CALCULATED DOSE TO MAXIMALLY EXPOSED INDIVIDUAL FROM A SPILL OF CONTAMINATED PROCESS LIQUIDS IN THE WHPF Og Controlling Age Group Dosc (area) Bone Teenager 6.2E-1 Total Body Teenager 2.6E-2 Lung Teenager 6.1E-2 Liver Teenager 9.2E-2 t 0422Y Rev. 4
15737-2-G03-107 3183-017 l 1 4.0 Safety Evaluation j I 10CFR50, paragraph 50.59, " Changes, Tests and Experiment", permits the holder of an operating license to make changes to the facility provided the change does not involve a modification of the THI-2 Technical l Specifications and the change is determined not to be an unreviewed safety question. As summarized below, the operation of the WHPF does not require
.a modification to the T41-2 Technical Specifications and is deemed not to be an unreviewed safety question as defined in 10CFR50.
4.1 Technical Specifications / Recovery Operations Plan Operation of the WHPF with respect to staging and decontaminating contaminated material will not require a change to the Technical Specifications. The Recovery Operations Plan will be revised to include the radiation monitor for each exhaust to the environment from potentially contaminated areas or from decontamination equipment. 4.2 Unreviewed Safety Questions The WHPF does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Final Safety Analysis Report. As demonstrated in Section 3, the consequences of various accidents are well within acceptable limits. The only interface between systems provided in the WHPF and any Important to Safety (ITS) systems is for fire protection. Tie-ins between the WHPF and ITS systems will be done in accordance with procedures approved for THI-2. Therefore, the WHPF will not impact existing ITS structures or systems and there will be no increase in the probability of an accident or malfunction of equipment important to safety. The possibility of an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created by the existence of the WHPF, Also, the operation of the WHPF does not result in a reduction in the margin of safety as defined in the THI-2 Technical Specifications since the WHPF does not impact any systems covered in the technical specifications and any release of radioactivity from the WHPF will be monitored for compliance with THI-2 Environmental Technical Specifications. Based on the above, the WHPF is deemed not to be an unreviewed safety question as defined in 10CFR50. 0422Y Rev. 4
15737-2-G03-107 3183-017 5.0 Environner.tal Assessment The activities associated with the operation of the WHPF have been
-evaluated to ensure that these activities do not pose unacceptable Prisk to the health and safety of the public and to IMI workers. In addition, these activities have been evaluated to ensure that the environmental impact from the operation of the WHPF is acceptably low and does not exceed acceptance criteria established for similar activities in the 241-2 PEIS (ref. 7).
Proposed activities in the WHPF are similar in nature to those activities associated with solid waste packaging and handling as described in Reference 7. Postulated releases of radioactive materials to the environment from the normal operation of the WHPF are presented and discussed in Section 3.2.2.1 of this TER. These
< releases are similar to those estimates in Reference 7, thtt is, normal activities should result in a maximum organ and whole body dose of less than 1 millires to the maximally exposed offsite individual. It is worthwhile to reiterate that the doses reported in this TER do not take credit for the ventilation and HEPA filtration systems which will be operated in the WHPF. HEPA filters normally provide greater than 99.9% efficiency for the removal of airborne particulates.
Accident scenarios evaluated in this TER are presented and discussed in Sections 3.2 and 3.4. Offsite radioactive releases were quantified for a fire involving all contaminated materials in the WHPF and a spill of all contaminated process liquids. The maximum calculated offsite doses were for a fire and are listed in Table 3-4. These doses are a small fraction of the limits for offsite ! exposures from accidents presented in 10CFR100, which are 25 rem to the whole body and 300 rem to an organ (thyroid). Section 10.4.1.2 of Reference 7 compares the results of a fire in a low level waste storage area to the requirements of 10CFR20. According to . 10CFR20.105(a) the maximum permissible dose to the whole body in any i period of one calendar year in an unrestricted area is 500 area. The calculated maximum equivalent whole body dose is 119 arem due to a fire in the WHPF, which is well within the 10CFR20 limit of 500 arem. Specific collective occupational exposures for the operation of the WHPF have not been calculated. The exposures will be maintained as low as reasonably achievable as discussed in Section 3.3 of the ! TER. The availability of adequate facilities for waste handling, such as provided in the WHPF, is important in maintaining low j occupational exposures for these activities. Reference 7 estimates a range of exposures from 39 to 99 person-rem for all handling and packaging of solid wastes. Reference 8 estimates 97 to 485 person-rem for radiotetive waste management and transportation. Handling and packaging of radioactive waste in the WHPF should not ' adversely impact the total collective exposures for these activities. i ! 0422Y Rev. 4
'- ~
~ '
^
~ 15737-2-G03-107 3183-017 In conclusion, the activities associated with the operation of the WHPF will have negligible environmental impact and will have no
. unacceptable consequences to the health and safety of the public or to THI workers.
1-6.0 References
- 1. " Technical Plan, Solid Waste Handling and Packaging Facility",
Rev. O, Jan. 1985.
- 2. " Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants", Wash-1238, December 1972.
- 3. Reg. Guide 1.4, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactor," Rev. 2, June 1974.
- 4. NUREG/CR-2139, " Aerosols Generated by Free Fall Spills of Powders and Solutions in Static Air", December, 1971.
A
- 5. THI-2 FSAR
- 6. Technical Evaluation Report for the Interin Solid Waste Staging Facility, 15737-2-G03-105, Rev. 7.
- 7. NUREG-0683 Final Programmatic Environmental Impact Statement-Related to the Decontamination and Disposal of Radioactive
- Wastes Resulting from March 28, 1979, Accident Three Mile Island Nuclear Station, Unit 2, March 1981.
- 8. NUREG-0683, Supplement No.1 to the Final Programmatic Environmental Impact Statement, Final Supplement Dealing with
. Occupational Dose, October, 1984.
- 9. ICRP Publication 26, " Recommendations of the Internationsi Commission on Radiological Protection," adopted January 17, 1977.
l l a i 0422Y Rev. 4 i
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