RS-10-006, Llrwsf LAR Support Technical Report Supporting Engineering Change Request (ECR) No. 09-00301 Type: Document Change Request (DCR) Subtype: Dsgn, Appendix E Through End

Llrwsf LAR Support Technical Report Supporting Engineering Change Request (ECR) No. 09-00301 Type: Document Change Request (DCR) Subtype: Dsgn, Appendix E Through End

ML100200013
Person / Time
Site:	Peach Bottom
Issue date:	12/03/2009
From:	Propst N URS Corp
To:	Exelon Nuclear, NRC/FSME, Office of Nuclear Reactor Regulation
Shared Package
ML100200009	List: ML100200010 ML100200011 RS-10-006, Llrwsf LAR Support Technical Report Supporting Engineering Change Request (ECR) No. 09-00301 Type: Document Change Request (DCR) Subtype: Dsgn, Appendix E Through End RS-10-006, Peach Bottom Llrwsf LAR Support Technical Report Supporting Engineering Change Request (ECR) No. 09-00301 Type: Document Change Request (DCR) Subtype: Dsgn, Cover Through Appendix D RS-10-006, Peach Bottom, Units 1, 2 and 3, Request for License Amendment to Allow Receipt and Storage of Low-Level Radioactive Waste
References
29487-NCS0097, RS-10-006 09-00301, Rev 0
Download: ML100200013 (113)

Text

{{#Wiki_filter:TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 APPENDIX E FIRE HAZARD ANALYSIS REPORT FOR INTERIM RADWASTE STORAGE FACILITY PEACH BOTTOM ATOMIC POWER STATION Appendix E 1 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 INTRODUCTION 1.0 Scope 1.0.1 This section consists of a review of fire protection and life safety related to the Low Level Radioactive Waste Storage Facility (LLRWSF) Project for Peach Bottom Atomic Power Station. Information gathered for the analysis includes drawings and specifications listed as referenced documents 1.1 Limitations 1.1.1 This analysis was performed as part of the Peach Bottom LLRWSF 10 CFR 50.59 LAR Support Technical Report, and presumes no substantive changes have been made to the facility since 1983. 1.2 Criteria for Evaluation 1.3.1 Combustible fire loadings used in developing the results of this Fire Hazard Analysis are as follows: Combustible Fire Loading Electrical insulation 10,000 btu/lb Vehicle tires (rubber- butyl) 19,700 btu/lb Oil (any type, 2, one pint each) 150,900 btu/gal High-density polyethylene 20,000 btu/lb Diesel fuel (fuel oil) 135,500 btu/gal Class B/C: Resins (when dried) 18,800 btu/lb Class A 8,000 btu/lb 1.3.2 Transient combustibles and their use in the project's facilities are considered to be limited. Materials used during maintenance activities and paper supplies are considered transient. Temporal loading and unloading of containers are considered transient at the truck bay. Appendix E- 2 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 1.3.3 Electric power, control, and instrumentation cable construction meets the smoke and flame test requirements of IEEE 383/UL 1277. 1.3.4 Occupational Safety and Health Administration Regulations meet the following: 29CFR1910.22 General Requirements - Walking or Working Surfaces 29CFR1910.23 Guarding Floor and Wall Openings 29CFR1910.24 Fixed Industrial Stairs 29CFR1910.27 Fixed Ladders 29CFR1910.30 Dock Boards These regulations were used as guidance in design of working areas and other personnel occupied areas of the facility. 1.3.5 The LLRWSF serves for interim and long term storage of containerized radwaste. This facility is not reactor safe-shutdown related (safety-related). 1.3.6 Pennsylvania Code of Fire and Panic Regulations. The fire protection system is designed to appropriate standards to meet these regulations. The applicable structural requirements for the facility are also referred to in these regulations. These requirements are met by use of the Uniform Building Code (equivalent to 1967 edition). Appendix E- 3 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 1.3 Evaluation Assumptions 1.3.1 For the purposes of this report, outside walls are not considered requiring a fire rating unless an exterior combustible (i.e., oil filled transformer, etc.) exists, which creates an exposure hazard. 1.3.2 Small quantities of grease (< one pound) or oil (< one quart) used as a lubricant in valves, motors, pans, damper operators and pumps will not be considered as contributing to a fire when contained within packing glands, bearings, or reservoirs. 1.3.3 Electric power and electric equipment such as motor control centers will not contribute significantly to the fire loading due to their metal enclosures. Similarly, totally enclosed electric motors are not considered to contribute significantly to fire loading. 1.3.4 It is assumed that a postulated fire is unlikely to exist if only electrical cables are involved. The construction of the specified electrical power, control, and instrumentation cable meets IEEE 383/UL 1277 which certify the cables non-propagational and fire resistance capabilities. 1.3.5 Electrical faults will be mitigated by selective tripping of breakers or blowing of fuses. 1.3.6 All cables, except festoon cables servicing the bridge crane, are in conduit. 1.4 Definitions 1.4.1 FIRE AREA- An area of a facility that is separated from other areas by complete fire barriers with at least a two hour rating. This includes walls, floors, and ceilings, with any openings therein protected with seals or closures having a fire resistance rating equal to that of the barriers. 1.4.2 FIRE ZONE- the subdivisions of fire areas (as defined above) which are subdivided by fire rated partitions or special separation. Appendix E- 4 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 1.4.3 HIGHLY PROTECTED RISK - The term involves the use and application of judgment and thus does not lend itself to a precise, fixed definition applicable, in all locations and situations. It has the same meaning and intent as is commonly understood when this or the term, improved risk, is used in the insurance industry. Generally, a Highly Protected Risk property is one that would qualify for complete insurance coverage by the Factory Mutual System, the Industrial Risk Insurers, and other industrial insurance companies that limit their insurance underwriting to the best protected class of industrial risk. The most evident characteristic of such a property is the existence of reliable, automatic fire extinguishing systems throughout all buildings of combustible construction or content where the building is vital to operational, continuity or may experience a large property loss from fire in the absence of an automatic extinguishing system. 1.4.4 DESIGN BASIS FIRE - A fire that is the most severe accident of this type. In postulating such a fire, failure of automatic and manual fire suppression provisions is assumed except for those safety class items/systems that are specifically designed to remain available (structurally or functionally) through the event. 1.4.5 FIRE HAZARD ANALYSIS - An analysis, documented in report form, which establishes a systematic approach to fire protection design which will ensure that all fire protection requirements are met and will facilitate a fire protection review. The analysis is documented in report form in the facility project files and referenced by the Safety Analysis Report. 1.4.6 MAXIMUM CREDIBLE FIRE LOSS - The maximum loss that could occur from a combination of events resulting from a single fire. Any installed fire protection systems are assumed to function as designed. Due to the uncertainties of predicting human action, the effect of emergency response is generally omitted except for post-fire actions such as salvage work, shutting down water systems, and restoring production. 1.4.7 MAXIMUM POSSIBLE FIRE LOSS - The maximum possible loss that could occur in a single fire area assuming the failure of both automatic and manual fire extinguishing actions. Appendix E- 5 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 2.0. PURPOSE AND OBJECTIVES 2.1 Fire Protection Design Analysis The purpose and objectives of this analysis are to: A. Demonstrate that the hazards to on-site personnel and off-site population as a result of a fire are maintained as low as reasonably achievable, in accordance with NRC regulations and Peach Bottom Atomic Power Station policy. B. To insure facility compliance with the applicable NFPA requirements in the areas of fire protection and life safety. C. Determine and recommend those special fire prevention and protection features and controls necessary to achieve a level of "Highly Protected Risk fire protection. 3.0 REFERENCE CODES, STANDARDS, AND DRAWINGS The following codes, standards, and reference documents have been utilized in the development of this report, and, except for NFPA 801 were current when the LLWRSF was originally assessed via a 50.59 evaluation (1992). 3.1 Codes and Standards (and other references) A. National Fire Protection Association (NFPA) Standards B. Uniform Building Code (equivalent to 1967 edition) C. Edison Electric Institute, Suggested Guidelines for Completing a Fire Hazards Analysis for Electric Utility Facilities D. American National Standards Institute ANSI C97.1 ANSI Y14.15 ANSI S1.2 ANSI C37 Appendix E- 6 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 ANSI C57 NEMA AB1, PB2, SG3, SG5, ST1, TR1, TR27, 210, AND ICS (Industrial Controls and Systems) E. U.S. Government-Occupational Safety and Health Administration (OSHA) Part 1910, Title 29 of Federal Regulation" F. 10CFR50.59- Domestic Licensing of Production and Utilization Facilities, Changes, Tests, and Experiments G. Underwriters Laboratory (UL), Fire Resistance Directory H. Dry Active Waste Storage Containers - ASTMA 36 and 49CFR173.198 I. Radiation Monitoring - NEMA 250, ANSI 13.10, USNRC Reg. Guide 1.43 Section C4.33 J. Dry Active Waste (DAW) Storage Containers - ASTM A 36, 49 CFR173.198. K. Forklift Truck (for DAW Container Transfer) - ANSI B56.1, UL 583 3.2 Drawings As listed on the Fire Hazard Analysis Detail Sheets Specifications None 4.0 FACILITY OVERVIEW 4.1 Description, Location, Construction This facility provides long-term storage of Class B/C radioactive wastes resulting from normal operations. In July 2008, Barnwell Burial Facility stopped receiving generated Radwaste material from out of compact nuclear facilities. Class B/C radioactive wastes generated by the Peach Bottom Station and potentially Limerick Station will be accepted at this facility. This facility is located on the site of Peach Bottom Atomic Nuclear Station. Appendix E- 7 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 The facility is comprised of three major areas including a cell storage area (for storage of dewatered resins and high-level DAW), a warehouse storage area (for storage of Dry Active Waste) and a service area (for material transfer, treatment, and control operations). A. The Cell Storage area contains 35 concrete storage cells for the storage of dewatered condensate and reactor water cleanup resins and other appropriately packaged materials. The inner cell walls are 1-2 thick while the outer walls of north, south and west perimeter cells are 3 feet thick. Each cell is covered with two overlapping removable concrete cell covers that are approximately 2 feet in thickness. Eighteen (18) cells are approximately 36 feet in depth. The east and west perimeter cells are somewhat larger to allow equal storage capacity due to crane hook coverage limits. Each of these cell will accommodate four (4) 8-120 high integrity containers (HICs) stacked upright to four (4) levels high. The containers are supported by stacking rack grids. Five additional partial cells are located along the south perimeter to allow full crane coverage of the adjacent cells. The partial cells are serviced by an auxiliary hoist of the overhead bridge crane. B. Dry Active Waste (DAW) Storage Area is located adjacent to the Cell Storage Area and encompasses of 6,000 square feet in an open warehouse configuration. The thickness of the concrete wall adjacent to the cells is 2.5 feet and that of the remaining three walls is 1.5 feet. Space for storage of approximately 80,750 cubic feet of compacted or non-compactible DAW is available. C. Service Area adjoins both the Cell Storage Area and DAW Storage Area and included those areas required for the transfer, treatment. Control and accountability of the low-level radioactive waste to be stored in the facility.

i. Truck Bays- there are two truck bays (indoor and outdoor) for the receipt and shipment of low level radioactive waste. The indoor truck bay has a drain which leads to the facility sump system so that precipitation runoff from the transport vehicle will be contained for analysis prior to discharge.

ii. Control Room/Records Center - Within the facility main control room are the controls for the bridge crane which is used for the transfer and placement of waste containers, and the closed circuit television system which is used for remote operating capabilities. Also located adjacent to the control room is an area for the storage of radioactive waste storage and shipping records. This area will also accommodate a data base computer system for Appendix E- 8 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 recording waste receipt and shipment information, such as decay calculations, for shipping purposes. iii. Local Control Room - A shielded local control room is located on the Cell Storage Area operating floor Level to provide line-of-sight viewing of the overhead bridge crane. This is necessary to accomplish such operations as transfer of HICs from stacking containers to shipping casks and movement of large contaminated items. iv. Access Control Area - Access to the waste storage areas is controlled by health physics personnel within the access control area. The health physics counting room and instrument room are located here as well as personnel decontamination area, sanitary facilities, and a protective clothing storage and change area.

v. Sump/Sump Pump Area - The facility hot sump tank and cold sump (concrete sump) and their associated pumps are located in this area. These sumps collect both the contaminated and non-contaminated liquids produced within the facility via a drain system.

vi. Dry Active Waste Staging Area - The forklift truck storage area and the fire service valve room are located here. The forklift truck is used for the transfer and stacking of DAW containers within the facility. vii. WAC Equipment Room - The W A C equipment room contains the air handling units for the Cell Storage Area, DAW Storage Area, Truck Bay, hot sump and DAW Staging Area. The air conditioning equipment serving the main control room/records center and the access control area are also located here. viii. Electrical Equipment Room - The Electrical Equipment Roam contains the 480 volt switchgear from which the electrical components within the facility are powered. Two 480 volt motor control centers are also located here. 4.2 Important Processes, Equipment, and Cabling Amounts of waste to be moved into the storage area are limited to the size of one transportation vehicle at any given time. Stored waste is expected to be processed waste in the form of dewatered resin. Dewatered resin waste will be contained in high integrity containers (HICs) made of molded high-density polyethylene or poly HICs in metal shells. The HICs contain filtered vents and are corrosion resistant. The standard HIC will Appendix E- 9 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 be 8-120, but others containers sizes have been generated and are currently waiting for long-term storage. Corrosive or reactive wastes are not authorized for LLRWSF storage without first processing to neutralize those conditions which may lead to corrosiveness or reactivity of the material to be stored. The following paragraph describes the LLRWSF truck unloading/loading process. A tractor-trailer is moved into the truck bay area. The tractor is disengaged and the truck removed from the facility. The truck bay doors are then closed. The ventilation system is shut down. The trailer's contents are removed by a remote-operated crane and hoisted into the storage area. The LLRWSF cranes are equipped with a winch system which permits them to be manually retracted over the truck bay without electrical power or functioning drive motors. The design of container lifting equipment is such that dropping a container is highly unlikely. Additionally, containers are constructed in accordance with DOT standards and are, therefore, highly resistant to impact damage. Consequently, the probability that a container drop will occur and the contents be released within the truck bay is low, and in any case will not credibly spread beyond the Truck Bay zone. With the truck removed, significant sources of potential ignition are not available in the truck bay. Additionally, Automatic and Manual Fire Suppression and smoke detectors are provided for the truck bay. Consequently, the probability that any combustible contents will be released or exposed to any source of ignition within the truck bay is low, and with Truck Bay fire suppression systems installed, in any case will not credibly spread beyond the Truck Bay zone. 4.3 Epoxy Coating Data on epoxy utilization, thickness of application, type of epoxy (if used), etc. for the PBAPS LLRWSF were not provided to URS - Washington Division by Exelon. Therefore, the following discussion and conclusions are based upon the assumed similar LaSalle County Station IRSF epoxy use. However, if available, Exelon confirmatory data searches are suggested. In any case, due to the Peach Bottom facility construction, a source of ignition for a fire in an open cell to initiate a wall or floor epoxy fire in the cell (if at all credible), initiating an epoxy fire that spreads throughout the cell and could potentially with enough time initiate a HDPE HIC fire event without such events being noticed by the operators involved with the operations during the cell being open is considered incredible. The LaSalle County Station IRSF Specification for Field Painting, Specification No. 70160-2000-14, a corresponding or equivalent epoxy coating for the PBAPS LLRWSF is assumed as follows: interior concrete floors with sprayed on one coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel primer/finish, with a dry film thickness (DFT) of 10 to 30 mils; interior concrete walls with a seal coat of Keeler & Appendix E- 10 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 Long No. 4129 Epoxy Clear Curing Compound, 0.5 to 1.5 DFT, + strike flush coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel, 1.0 to 5.0 DFT, + body coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel) thickness, 20 to 40 mils DFT. NRC Industry Notice 2007-26 on Combustibility of Epoxy Floor Coatings at Commercial Nuclear Power Plants defines a non-combustible material as:

a. A material which in the form in which it is used and under the conditions anticipated, will not ignite, burn, support combustion, or release flammable vapors when subjected to fire or heat; and

b. Material having a structural base of noncombustible material, as defined in a., above, with a surfacing not over 1/8-inch thick that has a flame spread rating not higher than 50 when measured using the test protocol of American Society for Testing and Materials (ASTM) E 84, Standard Test Method for Surface Burning Characteristics of Building Materials.

On July 22, 2009, URS - Washington Division personnel met with Mr. John De Barba, Field Technical Service Manager for PPG Protective & Marine Coatings, the current owner of Keeler & Long, to discuss the flame spread rating of the Keeler & Long epoxy surface finish 4500. Mr. De Barba initially provided test results performed in accordance with ASTM Standard E-84, indicating tested values of 45 for all thicknesses tested up to 25 mils dry film thickness. Mr. De Barba indicated that thicknesses above this level would not be applicable despite the Field Painting Specification, as cracking of the coating takes place above these thicknesses which would render them as unacceptable upon inspection. However, in response to a URS - Washington Division request for additional information regarding flame spread ratings of thicker Keeler & Long epoxy No. 3500, Mr. De Barba provided additional ASTM Standard E-84 test results of a flame spread index of 53.059 for coatings up to 30 mils in dry mil thickness. Industry Notice 2007-26 indicates that epoxy floor coverings at the Donald C. Cook Nuclear Power Plant with thickness between 0.115 inches (115 mils) and 0.230 inches (230 mils) with flame spread ratings of 140 to 150, and at the Duane Arnold Energy Center with a flame spread rating of 110, were acceptable with respect to not causing fires to propagate. As Exelon IRSF epoxy floor coating thicknesses and flame spread Appendix E- 11 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 ratings are both less than one-half those considered acceptable with respect to combustibility at other plants, the Exelon IRSF epoxy floor coating is considered acceptable with respect to not causing fires to propagate. In conclusion, although testing for up to 30 mils dry film thickness of KL3500 resulted in Flame Spread Rating slightly above 50, the epoxy coating is considered non-combustible based on: x Epoxy dry film thicknesses sufficient to result in flame spread ratings above 50 would be subject to cracking upon application, and therefore actual thicknesses would have flame spread ratings below 50. x Industry Notice 2007-26 actual plant data indicates non-combustibility of epoxies at much greater thicknesses and higher flame spread ratings. 4.4 Fire Protection Systems The Fire Protection System is designed in accordance with appropriate National Fire Protection Association, standards and with ANI (American Nuclear Insurers) recommendations. This system provides fire detection, audible and visual alarms, and fire extinguishing systems incorporating both automatic and manual features. Upon fire suppression system actuation, fixed fire extinguishing systems will automatically actuate in certain areas of the facility. Concurrently, audible and visual alarms will be activated locally, in the facility control room and in the main plant control room. In addition, a variety of manually operable fire extinguishing equipment will be available for manual control and extinguishing fires involving various classes of hazard. 4.4.1 Water Supply System - The water supply system consists of a new connection to the existing 8-inch fire main located at the North Warehouse. The existing fire main provides adequate water volume and pressure to meet the fire protection needs of the facility. An 8-inch flanged connection with a post indicator valve is used in the tie-in at the northwest corner of the North Warehouse. The underground supply main consists of an 8-inch cement-lined cast iron, pipe with cement-lined cast iron fittings. A11 fittings are restrained and anchored in accordance with National Fire Protection Association (NFPA) Standard - NFPA 24. 4.4.2 Sprinkler System - Wet pipe sprinkler systems are provided for the protection of areas where combustibles will be stored or may accumulate including the facility control room/records storage area, the access control area, the Truck Bay, the DAM Staging Area, and the DAW Storage Area. Appendix E- 12 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 The sprinkler system design meets the requirements of NFPA 13, "Installation of Sprinkler Systems," for Ordinary Hazard Groups II and III. Those areas where combustibles may accumulate and which are normally unoccupied are designated as Group II (DAM Storage Area). DAW is considered a Class A combustible material. Those areas where combustibles may accumulate and which are normally occupied are designated as Group III (control room/records storage area, access control area, Truck Bay, DAW Staging Area). Sprinkler system actuation is accomplished by the melting of a fusible link on the sprinkler from the heat generated by a fire, releasing water only from those sprinklers which have opened. Water Flow in any sprinkler system feed main will cause actuation of the zone water flow detector switch, activating local and remote fire alarms, and signaling the existence of a fire condition at the annunciator panel. The sprinkler system isolation valve is supervised by either a position switch or operating controlled lock. 4.4.3 Standpipe and Hose Stations, Hydrant with Hose Cart House - The facility hose stations are provided for manual control and extinguishing of fires by facility personnel. They are designed and located in accordance with NFPA 14, "Installation of Standpipe and Hose Stations," to provide coverage for all areas of the facility. The design water flow and duration is 100 gpm for 30 minutes. Valves are provided for isolation of the standpipe and its risers from the facility fire protection supply system, and are supervised in the same manner as the sprinkler system isolation valve. Each hose station is equipped with a 1-1/2 inch pressure restricting angle valve, a 100' length of 1-1/2 inch neoprene-lined collapsible fire hose, a swinging hose reel, a 2-1/2 gallon pressurized water fire extinguisher and a spanner wrench. One 6-inch fire hydrant is provided for facility and/or fire department personnel. It is equipped with American National Fire Hose connection screw threads to be compatible with fire department hose fittings. A curb box operated valve is provided in the hydrant supply line to allow for isolation of the hydrant for repair. A hose cart house is provided at the hydrant location for storage of firefighting equipment. It contains a hose cart, approximately 600 feet of 2-1/2 inch fire hose, approximately 400 feet of 1-1/2 inch fire hose and an equipment box containing items necessary to maintain reliable operation of the fire hose and hydrant systems. The fire hydrant and hose cart hose are located and installed in accordance with NFPA 24, "Outside Protection." Appendix E- 13 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 4.4.4 Fire Extinguishers - Pressurized water, CO2, and appropriately sized dry chemical fire extinguishers have been located throughout the facility as required by NFPA 10, Portable Fire Extinguishers. 4.4.5 Alarms and Annunciators - In addition to the sprinkler system and its associated control initiated alarms and annunciations, there are manual pull box-type fire alarms on each floor of the facility and local and remote alarm bells. Flashing red alarm lights and buzzer units are provided to give audible and visual signals at both the facility control room and the main plant control room. The system is designed in accordance with NFPA 72D, "Proprietary Protective Signaling Systems. Located in the facility control room, the fire annunciator panel monitors the power supply and provides all control and supervisory functions required for the sprinkler, standpipe and hose, manual fire alarm, low temperature detection, and in-duct smoke detection systems. Fire conditions in the storage facility are divided into the following zones: Zone 1 - Service Head Area Zone 2 - Truck Bay and DAW Staging Area Zone 3 - DAM Storage Area Zone 4 - Cell Storage Area, local control room, and fan room These conditions will appear on the facility fire annunciators panel and in the main plant control room as separate indications for each zone. Any fire condition received activates all facility fire alarm bells simultaneously. A common trouble signal will be transmitted to the main plant control room from the facility annunciator panel for any trouble condition. The annunciator panel is provided with a battery backup should normal 120-volt AC power be interrupted. Also, low temperature detectors are located in those areas of the storage facility in which water filled piping is installed and which are most susceptible to freeze conditions. The detectors are set to alarm at a temperature of 38o F (Normal facility temperature is maintained at a minimum of 40o F), utilizing normally closed contacts. These detectors provide trouble input to the facility fire annunciator panel, and are displayed as a single low temperature indication. 4.4.6 Operational Hazards - The application of water on fires in the vicinity of high voltage electrical equipment could constitute a life hazard to personnel due to the electrical conductivity of water. Adjustable pattern spray nozzles are installed with the hose stations. These adjustable water Appendix E- 14 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 spray nozzles must be operated in the fog setting, at distances as recommended by the manufacturer from any energized electrical equipment. A positive identification of these limits is included in the administrative control and training of facility personnel. 4.4.7 There are no fire detection systems in the storage area. The likelihood of fire in this area is acceptably low, as shown in Section 6.3, paragraph 11 below. Testing and maintenance - The fire protection system and associated equipment are tested and maintained in accordance with the manufacturers recommendations, the Pennsylvania Code of Fire and Panic Regulations, the National Fire Protection Association standards, and Exelon performance standards. 4.5 Manual Fire Suppression Systems Interior: The facility hose station is provided for manual control and extinguishing of fires by facility personnel The design water flow and duration is 100 gpm for 30 minutes. Each hose station is equipped with a 1 1/2 inch pressure restricting angle valve, a 100 length of 1 1/2 inch neoprene-line collapsible fire hose, a swinging hose reel, a 2 1/2 gallon pressurized water fire extinguisher and a spanner wrench. Pressurized water, CO2, and appropriately sized dry chemical fire extinguishers have been located throughout the facility as required by NFPA 10, Portable Fire Extinguishers. See Attachment 6.4 - Fire Protection Equipment Location Sketch for details. Exterior: One 6-inch fire hydrant is provided for the facility and/or fire department personnel. A hose cart house is provided at the hydrant location for storage of firefighting equipment. It contains a hose cart, approximately 600 ft of 2 1/2 inch fire hose, approximately 400 feet of 1 1/2 inch fire hose and an equipment box containing items necessary to maintain reliable operation of the fire hose and hydrant system. Offsite Fire Department assistance is available via York County. 4.6 Ventilation Description Air handling units and air conditioning units are included in the facility to maintain the following interior temperatures: Control Rooms, Access Control Area Records Center 72 - 78o F Truck Bay/DAW Staging Area 65 - 104o F DAM Storage Area 45 - 104o F Cell Storage Area (including cell interior) 45 - 104o F Appendix E- 15 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 Building ventilation is provided by air handling units and roof exhausters. Building heating is provided by electric unit heaters and electric coils in the air handling units. No HEPA and/or charcoal filtration is provided in the ventilation exhaust system. Appendix E- 16 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 5.0 DESIGN BASIS FIRE ANALYSES 5.1 Design Basis Fire Analysis Data Sheets The sheets on the following pages (Attachment 6.0) provide detailed information for each fire zone and/or area. This analysis focused on the areas involving Class B/C waste. 5.2 Ignition Sources Ignition sources in the LLRWSF storage bay are relatively limited. NFPA reported that 29% of fires initiates by an electrical ignition source and 34% by open flames. . In the LLRWSF, there is no human accessibility in the storage bay; therefore the only credible ignition source is failure of the crane cable and direct contact with the combustible material. As calculated in IRSF Storage Bay Fire HIC Spacing Assessment L-003429, Rev 000, such direct contact would be required for a period of 1,386 seconds to result in ignition. In addition, Peach Bottom created procedures to minimize the risk of fire in the LLRWSF building such as loading/unloading containers, periodic surveillance, fire detectors and automatic suppression at some classifies Class III areas. Appendix E- 17 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.0 ATTACHMENTS 6.1 DESIGN BASIS FIRE ANALYSIS TRUCK BAY AREA 6.2 DESIGN BASIS FIRE ANALYSIS CONTROL ROOM 6.3 DESIGN BASIS FIRE ANALYSIS STORAGE AREA 6.4 FIRE PROTECTION EQUIPMENT LOCATION SKETCH Appendix E- 18 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.1 DESIGN BASIS FIRE ANALYSIS TRUCK BAY AREA

1.0 BUILDING

Low Level Radioactive Waste Storage Facility (LLRWSF) 2.0 FIRE AREA OR ZONE: LLRWSF-Zone 2 2.1 ROOM: Truck Bay Area

2.2 LOCATION

N/A 2.3 REFERENCE DRAWING NOS. 6280-M-2401, 6280-M-2402, 6280-M-2403, 6280-M-2405, 6280-M-2406, 6280-M-2407, 6280-M-2408, 6280-M-2409, 6280-M-2410, 6280-M-2415. 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 concrete N/A ext. wall EAST 30 concrete N/A ext. wall SOUTH 30 concrete None WEST 30 concrete N/A ext. wall 3.2 FLOOR 18 or 24 concrete N/A el. 135-6 (unexcavated beneath) 3.3 CEILING 24 concrete N/A 3.4 DOORS 12x16 stl. Rollup N/A ext. 7x 31/2 HM N/A ext. 10 x 14 stl. rollup N/A ext. 68 x 31/2 HM 90 min. -B label 3.5 ROOF 2 conc. N/A ext. Appendix E- 19 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 4.0 FLOOR AREA: 1849 SQ.FT. LENGTH: 21 6 WIDTH: 86 0 HEIGHT: 54 0

5.0 VOLUME

99,846 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Cold or Hot Sump) 7.0 VENTILATION SYSTEM DESCRIPTION The building ventilation is provided by air handling units and roof exhausters. Local air heaters and electric coils are used during winter season. The temperature range of various areas is stated below: x Control Rooms, Access Control Area/Records Center (72 - 78oC) x Truck Bay/DAW Staging Area (65 - 104oC) x DAW Storage Area (45 - 104oC) x Cell Storage Area (45-104oC) 8.0 FIRE PROTECTION TYPE 8.1 SUPPRESSION Automatic Fire Suppression 8.2 DETECTION Smoke detectors in truck bay 8.3 MANUAL Manual Hoses 8.4 EXTINGUISHERS 20 lb class ABC or BC per NFPA 10 8.5 OTHER None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E- 20 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 HEAT OF TOTAL HEAT HEAT COMBUSTIBLE AMOUNT COMBUSTION POTENTIAL POTENTIAL Fuel Oil 200 gal 135,500 Btu/gal 27,100,000 Btu 14,657 Btu/sq.ft Vehicle tires 800 lbs 19,700 Btu/lb 15,760,000 Btu 8,524 Btu/sq.ft Transients: HIC 950 lbs 20,000 Btu/lb 19,000,000 Btu 10,276 Btu/sq.ft. Class B/C 6500 lbs 18,800 Btu/lb 122,200,000 Btu 66,090 Btu/sq.ft. 9.2 TOTAL FIRE LOADING IN AREA: 99,546 BTU/sq.ft. 9.3 TOTAL HEAT POTENTIAL: 184,060,000 BTU 9.4 Equivalent Severity: approximately 75 minutes O

9.5 TEMPERATURE

1805 F 10.0 PROCESS HAZARDS None. 11.0 DESIGN BASIS FIRE DESCRIPTION A fire starting in the truck bay is not considered credible because the three elements of fire (combustible material, ignition source, and unlimited oxygen supply) are not present at the same time. Exelon loading and unloading procedures are followed to minimize fire potential risks. See Section 4.2 for loading/unloading procedure description. In case of an incredible fire in the truck bay, manual and automatic suppression, and the Peach Bottom fire brigade are available for immediate remediation. Only during this transient loading/unloading event there is a possible fire risk, which would be controlled. 12.0 CONSEQUENCES OF DESIGN BASIS FIRE No consequences are postulated. Appendix E- 21 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: GROUP III 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: Meets all requirements 13.4 EXIT LIGHTING/SIGNS: Meets all requirements 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: Meets all requirements 13.7 TRAVEL DISTANCE TO EXIT: Meets all requirements 13.8 STAIRS: Meets all requirements 13.9 DOOR HARDWARE: Meets all requirements Appendix E- 22 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.2 DESIGN BASIS FIRE ANALYSIS CONTROL ROOM

1.0 BUILDING

Low Level Radioactive Waste Storage Facility (LLRWSF) 2.0 FIRE AREA OR ZONE: LLRWSF- Zone 4 2.1 ROOM: Control Room & Records Center

2.2 LOCATION

N/A 2.3 REFERENCE DRAWING NOS. 6280-M-2401, 6280-M-2402, 6280-M-2403, 6280-M-2405, 6280-M-2406, 6280-M-2407, 6280-M-2408, 6280-M-2409, 6280-M-2410, 6280-M-2415. 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 conc. N/A ext. wall EAST 12 CMU & 30concrete N/A ext. wall SOUTH 36 conc. 3-hr (lower) WEST 30 conc. N/A ext. wall 3.2 FLOOR 20 conc. N/A slab on grade 3.3 CEILING 30 conc. 3.4 DOORS west 7 -2 X 3 HM N/A ext. south (2) 7 2 X 3 HM 90 min. B-label 3.5 ROOF N/A. N/A ext. Appendix E- 23 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 4.0 FLOOR AREA: 644 SQ.FT. LENGTH: 28 0 WIDTH: 23 0 HEIGHT: 8 6

5.0 VOLUME

5,474 CU.FT 6.0 FLOOR DRAINS YES NO X 7.0 VENTILATION SYSTEM DESCRIPTION Heating and cooling for the control room is provided by a split system air conditioning unit with heating coil. Control room design conditions are 72 F minimum, 78 F maximum. Fire dampers are provided at points of penetration through fire-rated walls. 8.0 FIRE PROTECTION TYPE

8.1 SUPPRESSION

Wet automatic sprinkler system and manual extinguishers

8.2 DETECTION

Smoke detectors in control/record room

8.3 MANUAL

Hose station are provided

8.4 EXTINGUISHERS

Pressurized water, CO2 and dry chemical fire extinguisher , NFPA 10

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E- 24 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 HEAT OF TOTAL HEAT HEAT COMBUSTIBLE AMOUNT COMBUSTION POTENTIAL POTENTIAL Transients: 3,000 lbs 8,000 Btu/lb 24,000,000 Btu 37,267 Btu/sq.ft. Others none 9.2 TOTAL FIRE LOADING IN AREA: 37,267 BTU/sq.ft. 9.3 TOTAL HEAT POTENTIAL: 24,000,000 BTU 9.4 Equivalent Severity: less than 30 minutes 10.0 PROCESS HAZARDS None. 11.0 DESIGN BASIS FIRE DESCRIPTION During maintenance operations, welding spark ignites pile computer paper stock. Fire spreads to consume 3,000 lbs of transients combustibles classified as wood products, paper and electronic. 12.0 CONSEQUENCES OF DESIGN BASIS FIRE Loss of ordinary combustible in control room ( i.e. , paper, wood products, cloth, etc.). Loss of electrical cable in conduit. Heat damage to cable and electronic components of control equipment. Loss of use of facility during repair period. 13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Group III 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: Meets all requirements 13.4 EXIT LIGHTING/SIGNS: Meets all requirements 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: Meets all requirements Appendix E- 25 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 13.7 TRAVEL DISTANCE TO EXIT: Meets all requirements 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: Meets all requirements Appendix E- 26 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.3 DESIGN BASIS FIRE ANALYSIS STORAGE AREA

1.0 BUILDING

Low-Level Radioactive Waste Storage Facility (LLRWSF) 2.0 FIRE AREA OR ZONE: LLRWSF - Zone 4 2.1 ROOM: Storage Area

2.2 SCENARIO

16 units of 8-120 High Density Polyethylene (HDPE) (Non-steel shelled) High Integrity Containers (HIC), 4 layer.

2.3 LOCATION

N/A 2.4 REFERENCE DRAWING NOS. 6280-M-2401, 6280-M-2402, 6280-M-2403, 6280-M-2405, 6280-M-2406, 6280-M-2407, 6280-M-2408, 6280-M-2409, 6280-M-2410, 6280-M-2415. CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE 3.0 WALL RATING NORTH 36 concrete EAST 30 concrete None SOUTH 36 3-hr (lower) WEST 36 concrete N/A ext. wall 3.1 FLOOR 30 reinforced N/A ext. wall concrete mat stiffened N/A slab on grade by internal rebar 3.2 CEILING 24 concrete (cover over cell) 3.3 DOORS None 3.4 ROOF 2 concrete. N/A ext. Appendix E- 27 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 4.0 TOTAL FLOOR AREA: 9,253 SQ.FT. LENGTH: 109 6 WIDTH: 84 6 HEIGHT: 58 4.1 CELL FLOOR AREA: 192 SQ.FT. LENGTH: 11 0 WIDTH: 17 5 HEIGHT: 36 4.2 CELL FLOOR AREA: 270 SQ.FT. LENGTH: 15 6 WIDTH: 17 5 HEIGHT: 36 4.3 CELL FLOOR AREA: 163 SQ.FT. LENGTH: 11 WIDTH: 14 10 HEIGHT: 36 4.4 CELL FLOOR AREA: 230 SQ.FT. LENGTH: 15 6 WIDTH: 14 10 HEIGHT: 36 4.5 CELL FLOOR AREA: 197 SQ.FT. LENGTH: 11 WIDTH: 17 11 HEIGHT: 36 4.6 CELL FLOOR AREA: 278 SQ.FT. LENGTH: 15 6 WIDTH: 17 11 HEIGHT: 36 5.0 TOTAL VOLUME: 536,660 CU.FT 5.1 CELL (11 X 175 X 36) VOLUME: 6,897 CU.FT 5.2 CELL (156 X 175 X 36) VOLUME: 9,719 CU.FT 5.3 CELL (11 X 1410 X 36) VOLUME: 5,874 CU.FT 5.4 CELL (156 X 1410 X 36) VOLUME: 8,277 CU.FT 5.5 CELL (11 X 1711 X 36) VOLUME: 7,095 CU.FT 5.6 CELL (156 X 1711 X 36) VOLUME: 9,998 CU.FT Appendix E- 28 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.0 FLOOR DRAINS YES X NO (drains to Cold/Hot Sump) 7.0 VENTILATION SYSTEM DESCRIPTION The ventilation system available for the storage cells are three (3) power roof ventilators positioned on the ceiling of the LLRWSF. Cell Storage Area (45-104oC) 8.0 FIRE PROTECTION

8.1 SUPPRESSION

No automatic suppression

8.2 DETECTION

Duct detectors in the ventilation system and ionization detectors in the truck bay area

8.3 MANUAL

(2) Hose Stations

8.4 EXTINGUISHERS

Portable fire extinguishers on multiple areas

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE The fire loading in on an arbitrary 15.5x14.8 storage cell assumes that the resins are dried out for conservatism. Heat of Total Heat Heat Combustible Amount Units Combustion Units Potential Units Potential Units HDPE 16 HICs (15.5x14.8) Cell (ft2) HICs 15,200 lbs 20,000 Btu/lb 3.04E+08 Btu 1.322+06 Btu/sq.ft 6500 Per HIC Class B/C: 104,000 lbs 18,800 Btu/lb 1.955E+9 Btu 8.503E+6 Btu/sq.ft Transients: 0 lbs 9.2 TOTAL FIRE LOADING IN AREA: 9.826x106 BTU/sq.ft. 9.3 TOTAL HEAT POTENTIAL: 2.26x109 BTU 9.4 Equivalent Severity: over 5 days Appendix E- 29 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 10.0 PROCESS HAZARDS None. 11.0 DESIGN BASIS FIRE DESCRIPTION Fire in a closed (covered) cell and fire initiation on a temporarily open cell are considered incredible. The probability of having a source of ignition in the storage area is remote. The storage bay is lighted and during the transient process where an unique cell cover is off, operators are constantly monitoring the area. The possibility of a cable igniting (e.g., from a short circuit) and being in direct contact for the sufficient time required to ignite a HIC is unrealistic. Adjacent cells are maintained closed until cell is loaded/unloaded; this closure ensures no postulated ignition source could enter a cell, and also ensures insufficient oxygen would be available to sustain a postulated fire. Two manual hose stations are available at the top of cell for manual extinguishing of a fire event, see Attachment 6.4 - Fire Protection Equipment Location Sketch. In addition, the Peach Bottom Fire Brigade will respond to a fire in this area. Consequently, there is no credible fire scenario in the Storage Cell. 12.0 CONSEQUENCES OF DESIGN BASIS FIRE A postulated fire would be extinguished by manual suppression by the PB Fire Brigade. Any drainage will be collected in the cold/hot sump system until the sump reaches its maximum capacity and the cell drain lines begin to back up the flow. No fire spreading will occur in the adjacent cells since reinforced concrete will contain such an incredible fire for days. Due to the availability of the fire suppression system and the wet nature of the stored resin, no resin burning resulting in radioactivity release is postulated. 13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Group II 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: None required 13.4 EXIT LIGHTING/SIGNS: None required 13.5 CORRIDOR WIDTH: N/ A Appendix E- 30 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 13.6 EXITS AND EGRESS: None required 13.7 TRAVEL DISTANCE TO EXIT: N/A 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: N/A 14.0 RECOMMENDATION A fire in the LLRWSF storage cell is considered incredible. In the event such an incredible fire occurs during a loading/unloading procedure when the cell is opened, personnel would be available and be able to see the fires initiation, and manual fire hoses and the fire brigade are adequate to prevent the fire from spreading within the LLRWSF storage area. Appendix E- 31 of 32

TECHNICAL REPORT Project No. 29487-NCS0097 SUPPORTING ECR No. 09-00301 ENGINEERING CHANGE Rev. 0 REQUEST Date: 12/03/09 6.4 FIRE PROTECTION EQUIPMENT LOCATION SKETCH Appendix E- 32 of 32

ATTACHMENT 4 Analysis No. PM-750 Container Drop Accident Analysis

oeSlgn A nalysis . M' aJor ReVlslon c over Sheet Design Analysis (Major Revision) [Last Page No. 8/ Atl. D-2 Analysis No.: 1 PM-750 Revision: 2 1

Title:

3 Container Drop Accident Analysis EC/ECR No.: 4 09-00301 Revision: S 0 Station(s): ' Peach Bottom Component(s): 14 Unit No.: 00 Discipline: Descrip. Code/Keyword: 10 Safety/QA Class: " Non-Safety System Code: 12 Structure: 13 CONTROLLED DOCUMENT REFERENCES 15 Document No.: FromfTo Document No.: FromfTo From From To From From From If yes, see SY-AA-Is this Design Analysis Safeguards Information? 16 Yes 0 No I:8J 101-106 If yes, Does this Design Analysis contain Unverified Assumptions? 11 Yes 0 No I:8J ATflAR#: This Design Analysis SUPERCEDES: ,. Rev. 0 Description of Revision (list affected pages for partials): 19 Re-analyzed for Radwaste data received from Limerick Station and to adjust the Peach Bottom source term to a nominal 400 Rlhr container. All pages of the body are new, with the Rev. 0 version used for inputs and included as Attachment C for convenience. Preparer: Will;OM, ~ Print Name

                                                                               ~4u
                                                                                   'SJ;Name
                                                                                                                        %a.b=t Date Method of Review:          21  Detailed Review       I:8J  Alternate Calculations (attached)            0      TestingD Reviewer:       22                v, I l fLj'r<'~                               ~/{/ IVU-                                   1/~ 7/d'l Print Name                                 Sign Name                      Date Review Notes:                  Independent review I:8J            Peer review 0        All inputs, assumptions, approaches, numerical analyses, and results were independently reviewed and checked.
*w ~.c",ai Analyses Only; External Approver:" Donald Gardner                                    'ftc 71 fti?v',;;

r ({lin p,_./

                                                                                                  'i  !'-jit!~d
                                                                                                     , .. I v              7(2'  f J!

Pnn! Name Date U,:nName Exelon Reviewer: 7. :J, Ai5C/ Sit A /" lkkutJ9 PnntName U Sl~e

                                                                                        "-/

Date! I f Independent 3'd Party Review Reqd? Yes 0* No f.8l Exelon Approver: Print Name Sign Nam" Dale

CC-AA-309 Revision 9 Page 17 of 17 ATTACHMENT 1 Owners Acceptance Review Checklist for External Design Analysis Page 1 of 1 PM-750 REV: DESIGN ANALYSIS NO. - y~ No N/A

1. Do assumptions have sufficient rationale? 0 0

                                                                                         ~

Are assumptions compatible with the way the plant is operated and with the 2. licensing basis? 0 0

3. Do the design inputs have sufficient rationale? 0 0 4.

Are design inputs correct and reasonable with critical parameters identified, if appropriate? ~ 0 0 5. Are design inputs compatible with the way the plant is operated and with the licensing basis? ~0 0 6. 7. 8. Are Engineering Judgments clearly documented and justified? Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? Do the results and conclusions satisfy the purpose and objective of the

/

ui 0 0 0 0 0 0 Design Analysis? 9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? ~ 0 0 10. Does the Design Analysis include the applicable design basis documentation? ~ 0 0 11. Have any limitations on the use of the results been identified and transmitted to the appropriate organizations? 0 0 ~

12. Are there any unverified assumptions? 0 rn/ 0 13.

Do all unverified assumptions have a tracking and closure mechanism in place? 0 0 ~ 14. Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change? 0 0 or' Do the sources of inputs and analysis methodology used meet current

                                                                                        .~ 0 technical requirements and regulatory commitments? (If the input sources or

15. analysis methodology are based on an out-of-date methodology or code, 0 additional reconciliation may be required if the site has since committed to a more recent code) 16.

Have vendor supporting technical documents and references (including GE DRFs) been reviewed when necessary? ~D 0 17. Have margin impacts been identified and documented appropriately for any negative impacts (Reference ER-AA-2007)? ~D 0 EXELON REVIEWER:

                         .~
                                 ,Msc.i'        ~

DATE: lijiZ#1

CALCULATION No L-003430 REV. 001 PAGE iii TABLE OF CONTENTS OWNERS ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS ..................................................................................... 2

1. Introduction & Purpose............................................................................ 4

2. Inputs........................................................................................................ 4

3. Assumptions............................................................................................. 5 3.1 Technically Justified Assumptions ..................................................................... 5 3.2 Assumptions that Require Verification............................................................... 5

4. References................................................................................................ 5

5. Method of Analysis.................................................................................. 6 5.1 Design Basis Container Activity......................................................................... 6 5.2 Internal Events .................................................................................................... 6

6. Numeric Analysis..................................................................................... 7 6.1 Bounding Design Basis Container Contents....................................................... 7

7. Results...................................................................................................... 8

8. Conclusion ............................................................................................... 8 ATTACHMENT A: Peach Bottom: MicroShield Runs and Excel Spreadsheets ...... A-1 ATTACHMENT B: Limerick: MicroShield Runs and Excel Spreadsheets .............. B-1 ATTACHMENT C: PM-750 Rev. 0........................................................................... C-1 ATTACHMENT D: Computer Disclosure Sheets ..................................................... D-1

CALCULATION No L-003430 REV. 001 PAGE 4

1. Introduction & Purpose The purpose of this calculation is to re-analyze the design basis event of Container Drop during waste handling for the Peach Bottom Low Level Radwaste Storage Facility (LLRWSF) for currently expected design basis source terms, including for radwaste received from the Limerick Station. This analysis is to demonstrate that the dose consequences of this bounding event do not exceed a small fraction (10 percent) of 10 CFR Part 100 dose limits, as per Reference (7), the General Information section of Generic Letter 81-38 entitled Storage of Low-Level Radioactive Wastes at Power Reactor Sites, and as suggested in the EPRI Guide (Reference (3)).

2. Inputs Parameter Value Basis i Limerick Container 250 rem/hr Assumption 3.1.1 Contact Dose Rate for Nominal Analysis i Peach Bottom Container 400 rem/hr Assumption 3.1.1 Contact Dose Rate for Bounding Analysis i Container Isotopic Mix: UFSAR Table 11.4-8, RWCU Reference (9), with Limerick Power Station Phase Separator column, 60 day decay decayed 60 days conservatively used as typical practice is for resins to not be packaged until at least 60 days after discharge.

i Container Isotopic Mix: Table 1 in Attachment A Reference (6) Peach Bottom Station i Resin Density: Used for 0.9 g/cc Assumption 3.1.3 Container Content i Resin Density: Used for 0.69 g/cc Reference (6) Release Fraction Assumption 3.1.3 i Number of Containers 1 Assumption 3.1.2 Dropped i Container Drop Height 46-9(1424.94cm) Reference (6) i Mixing Credit 100%, well mixed It is expected that the nature of the

CALCULATION No L-003430 REV. 001 PAGE 5 accident event will cause significant mixing. i Calculated 2-hour X/Q at 9.20E-04 Reference (6) the Exclusion Area Boundary (EAB) for ground level release (sec/m3) i Fraction Released: 3% Reference (6) Container Drop i Breathing Rate: at EAB 3.47E-04 Reference (6)

3. Assumptions 3.1 Technically Justified Assumptions 3.1.1 Analyses are for an actual resin isotopic mix from Limerick, based on a nominal 250 R/hr container to permit off-site shipment, and a Peach Bottom isotopic mix from Rev. 0 of this calculation (attached) adjusted to a nominal 400 R/hr container.

3.1.2 The crane in the LLRWSF can only carry one container at a time and therefore one container will be assumed to drop into an area below, permitting a relatively ready release for the drop accident. 3.1.3 A denser material will yield a high radioactivity content for a given contact dose. A lower density will yield a higher release fraction upon HIC failure from impact. 3.2 Assumptions that Require Verification There are no assumptions that require verification in this calculation.

4. References (1) NUREG-1320, Nuclear Fuel Cycle Facility Accident Analysis Handbook, May 1988.

(2) 10 CFR 100, Reactor Site Criteria. (3) EPRI, Guidelines for Operating an Interim On Site Low Level Radioactive Waste Storage Facility - Revision 1, February 2009. (4) Peach Bottom Drawing No. 6280-M-2405-9, 2-1/2 Year Onsite Radwaste Storage Facility, Section A-A. (5) U.S. Department of Energy, External Dose-Rate Conversion Factors for Calculation of Dose to the Public, July 1988, (FGR-11).

CALCULATION No L-003430 REV. 001 PAGE 6 (6) Peach Bottom Calculation PM-750, Container Drop Accident Analysis, October 1992. (7) URS: Washington Division, Design Change Package, Peach Bottom LLRWSF LAR Support. (8) USNRC-Standard Review Plan, Section 11.4-A, Design Guidance for Temporary Storage of Low-Level Radioactive Waste, Revision 3, March 2007. (9) Limerick UFSAR, Chapter 11, Table 11.4-8, Expected Radionuclide Inventories of Solid Waste Management System Components, current as of this calculation.

5. Method of Analysis In general, these analyses determine or utilize:

(1) a bounding design basis container content; (2) fraction of contained activity released for airborne dispersion, from Ref. 6 (attached); (3) appropriate dispersion factors; (4) resulting doses at the Exclusion Area Boundary (the bounding location for the assumed instantaneous ground level release) 5.1 Design Basis Container Activity The Chem-Nuclear system polyethylene HIC has an inner diameter of 60 inches and a fill line height of 72 inches. The HICs contents will have a bounding isotopic mixture from either Limerick or Peach Bottom. The Limerick HIC contents will have decayed for a period of 60 days and are at a contact dose rate of 250 rem/hr for Limerick waste, and 400 rem/hr for bounding Peach Bottom waste. 5.2 Internal Events 5.2.1 Container Drop In this accident, one container will be moved from the LLRWSF Storage Area, over the Local Control Room and then dropped at the North end of the building. This accident is illustrated in Figure 5.2-1. It is shown here that the container will free fall from a height of 170-9 and fall to an elevation 118. Upon impact the container will rupture and a fraction of resin will be released to the surrounding area.

CALCULATION No L-003430 REV. 001 PAGE 7 Figure 5.2-1

6. Numeric Analysis 6.1 Bounding Design Basis Container Contents Bounding HICs generated at Peach Bottom are assumed to have a contact dose rate of 400 R/hr. A container with this contact dose rate may require a hold in storage for a decay period. Containers shipped from Limerick are assumed to have a maximum contact dose rate 250 R/hr, because of limitations on dose rates exterior to a transport package.

Shielding analyses have been performed on an all Co-60 basis to simulate worst case conditions. However, a design basis event involving postulated airborne releases and inhalation doses must consider relative inhalation dose conversion factors. For this reason, isotopic mixes for the bounding resin sources were evaluated using the following process.

1. For Limerick, RWCU phase separator characteristics from UFSAR Table 11.4-8 Expected Radionuclide Inventories of Solid Waste Management System Components were used. For Peach Bottom, Table 1 from Reference (6)

Design Basis RWCU Resin was used.

2. These 2 mixes were each placed in a nominal HIC to determine a contact dose rate, using MicroShield. For Limerick, a decay before container loading period of 60 days was assumed, and the resulting mix of isotopes adjusted using MicroShield to result in the 250 R/hr contact dose container for Limerick and the 400 R/hr contact dose for Peach Bottom.

3. These isotopic mix concentrations were then multiplied by effective inhalation dose conversion factors from FGR-11 (Reference 5) and then summed to

CALCULATION No L-003430 REV. 001 PAGE 8 determine which mix would yield the maximum inhalation dose. The result of this step was that Peach Bottom had the bounding isotopic mix.

4. With the bounding isotopic mix in a container, the contents were adjusted proportionally to yield the design basis 400 R/hr Peach Bottom Container, which based on both isotopics and contact dose rate limits, is bounding.

5. Accidents are evaluated based on multiplying the following factors: (1) Container Contents; (2) the number of containers affected; (3) the release fraction applicable to the event, from Reference 6; (4) the Peach Bottom EAB X/Q for ground level releases, from Reference 6; (5) a Breathing Rate of 3.47E-4 m3/s, from Reference 6; and (6) Dose Conversion Factors from Reference (5).

7. Results This calculation was performed to evaluate the Peach Bottom LLRWSF internal design basis event of a container drop as a bounding event. The methodology is conservative as discussed below. The calculated doses are:

Event Calculated Dose Limit Container Drop 0.736 rem 2.5 rem Some of the conservatisms applied in this calculation are listed below. i Containers are assumed to have a contact dose rate of 400 R/hr, which is the maximum anticipated in the LLRWSF. i As historically used, Release Fractions for container drop use a conservative NUREG-1320 based dry powder spill scenario to determine an airborne fraction. The worst case Powdex-like resin is expected to be wet and to be less easily made airborne. Larger bead resin would be even less likely to become airborne. The assumed drop is from the maximum release height with a resulting calculated airborne release fraction of 0.0294, which is rounded to 0.03. i All airborne activity is assumed to be instantly released to the environment from the LLRWSF. No particle settling is assumed either in the LLRWSF or in transit to the EAB.

8. Conclusion By performing this evaluation, it has been concluded that a container drop of a Peach Bottom HIC is a bounding event. The level of conservatism includes significant safety factors for calculating an effective dose release to the EAB through a container drop.

Doses from the bounding internal events in the LLRWSF are within 10% of 10 CFR 100 limits.

A B C D E F G H I J 1 LGS UFSAR Table 11.4-8 2 EXPECTED RADIONUCLIDE INVENTORIES OF SOLID WASTE MANAGEMENT SYSTEM COMPONENTS 3 4 Nuclide Ci 5 Br-83 8.97E-01 6 Br-84 1.81E-02 7 Br-85 1.86E-05 8 I-131 1.70E+02 9 I-132 8.43E+00 10 I-133 6.73E+01 11 I-134 5.44E+00 12 I-135 1.98E+01 13 Rb-89 4.27E-02 14 Cs-134 5.21E+00 15 Cs-136 1.11E+00 16 Cs-137 1.24E+01 17 Cs-138 3.68E-01 18 Na-24 2.24E+01 19 P-32 1.15E+01 20 Cr-51 4.63E+02 21 Mn-54 1.00E+01 22 Mn-56 1.69E+01 23 Fe-55 1.74E+02 24 Fe-59 3.52E+00 25 Co-58 2.69E+01 26 Co-60 7.07E+01 27 Ni-63 1.79E-01 28 Ni-65 1.01E-01 29 Cu-64 6.44E+01 30 Zn-65 3.27E+01 31 Zn-69 2.23E-01 32 Sr-89 1.24E+01 33 Sr-90 1.07E+00 34 Sr-91 6.22E+00 35 Sr-92 3.62E+00 36 Y-91 8.37E+00 37 Y-92 7.08E+00 38 Y-93 6.66E+00 39 Zr-95 9.25E-01 40 Zr-97 1.43E-02 41 Nb-95 1.14E+00 42 Nb-98 3.12E-01 43 Mo-99 2.35E+01 44 Tc-99m 3.91E+01 45 Tc-101 6.18E-01 46 Tc-104 9.90E-01 47 Ru-103 2.20E+00 48 Ru-105 1.30E+00 49 Ru-106 5.07E-01 50 Ag-110m 1.64E-01 51 Te-129m 4.12E+00 52 Te-131m 5.17E-01 53 Te-132 1.37E-01 54 Ba-139 1.54E+00 55 Ba-140 2.10E+01 56 Ba-141 1.23E-01 57 Ba-142 2.14E-02 58 La-142 1.02E+00 59 Ce-141 3.29E+00 60 Ce-143 1.71E-01 61 Ce-144 4.99E-01 62 Pr-143 2.38E+00 63 Nd-147 1.39E-01 64 W-187 1.22E+00 65 Np-239 6.92E+01 66 67 3.36E+01 68 69 1.44E+03 Calc. No. PM-750, Rev. 1, Attachment A, Page A-1 of A-11

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4 5 Filename Run Date Run Time Duration 6 LGS.msd 13-Aug-09 9:22:45 AM 0:00:06 7 Project Info 8 Case Title LGS 11.4-8 9 Description before decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: ICRP-38 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ag-110m 1.64E-01 6.07E+09 4.92E-02 1.82E+03 29 Ba-137m 1.17E+01 4.34E+11 3.52E+00 1.30E+05 30 Ba-139 1.54E+00 5.70E+10 4.62E-01 1.71E+04 31 Ba-140 2.10E+01 7.77E+11 6.30E+00 2.33E+05 32 Ba-141 1.23E-01 4.55E+09 3.69E-02 1.36E+03 33 Ba-142 2.14E-02 7.92E+08 6.41E-03 2.37E+02 34 Br-83 8.97E-01 3.32E+10 2.69E-01 9.95E+03 35 Br-84 1.81E-02 6.70E+08 5.43E-03 2.01E+02 36 Ce-141 3.29E+00 1.22E+11 9.86E-01 3.65E+04 37 Ce-143 1.71E-01 6.33E+09 5.13E-02 1.90E+03 38 Ce-144 4.99E-01 1.85E+10 1.50E-01 5.53E+03 39 Co-58 2.69E+01 9.95E+11 8.06E+00 2.98E+05 40 Co-60 7.07E+01 2.62E+12 2.12E+01 7.84E+05 41 Cr-51 4.63E+02 1.71E+13 1.39E+02 5.14E+06 42 Cs-134 5.21E+00 1.93E+11 1.56E+00 5.78E+04 43 Cs-136 1.11E+00 4.11E+10 3.33E-01 1.23E+04 44 Cs-137 1.24E+01 4.59E+11 3.72E+00 1.38E+05 45 Cs-138 3.68E-01 1.36E+10 1.10E-01 4.08E+03 46 Cu-64 6.44E+01 2.38E+12 1.93E+01 7.14E+05 47 Fe-55 1.74E+02 6.44E+12 5.22E+01 1.93E+06 48 Fe-59 3.52E+00 1.30E+11 1.06E+00 3.90E+04 49 I-131 1.70E+02 6.29E+12 5.10E+01 1.89E+06 50 I-132 8.43E+00 3.12E+11 2.53E+00 9.35E+04 51 I-133 6.73E+01 2.49E+12 2.02E+01 7.46E+05 52 I-134 5.44E+00 2.01E+11 1.63E+00 6.03E+04 53 I-135 1.98E+01 7.33E+11 5.94E+00 2.20E+05 54 La-140 2.10E+01 7.77E+11 6.30E+00 2.33E+05 55 La-142 1.02E+00 3.77E+10 3.06E-01 1.13E+04 56 Mn-54 1.00E+01 3.70E+11 3.00E+00 1.11E+05 57 Mn-56 1.69E+01 6.25E+11 5.07E+00 1.87E+05 58 Mo-99 2.35E+01 8.70E+11 7.04E+00 2.61E+05 59 Na-24 2.24E+01 8.29E+11 6.71E+00 2.48E+05 60 Nb-95 1.14E+00 4.22E+10 3.42E-01 1.26E+04 61 Nb-98 3.12E-01 1.15E+10 9.35E-02 3.46E+03 62 Nd-147 1.39E-01 5.14E+09 4.17E-02 1.54E+03 63 Ni-63 1.79E-01 6.62E+09 5.37E-02 1.99E+03 64 Ni-65 1.01E-01 3.74E+09 3.03E-02 1.12E+03 65 Np-239 6.92E+01 2.56E+12 2.07E+01 7.68E+05 66 P-32 1.15E+01 4.26E+11 3.45E+00 1.28E+05 Calc. No. PM-750, Rev. 1, Attachment A, Page A-2 of A-11

A B C D E F G H I 67 Pr-143 2.38E+00 8.81E+10 7.13E-01 2.64E+04 68 Pr-144 4.92E-01 1.82E+10 1.47E-01 5.46E+03 69 Rb-89 4.27E-02 1.58E+09 1.28E-02 4.74E+02 70 Rh-103m 2.19E+00 8.12E+10 6.58E-01 2.43E+04 71 Rh-106 5.07E-01 1.88E+10 1.52E-01 5.62E+03 72 Ru-103 2.20E+00 8.14E+10 6.59E-01 2.44E+04 73 Ru-105 1.30E+00 4.81E+10 3.90E-01 1.44E+04 74 Ru-106 5.07E-01 1.88E+10 1.52E-01 5.62E+03 75 Sr-89 1.24E+01 4.59E+11 3.72E+00 1.38E+05 76 Sr-90 1.07E+00 3.96E+10 3.21E-01 1.19E+04 77 Sr-91 6.22E+00 2.30E+11 1.86E+00 6.90E+04 78 Sr-92 3.62E+00 1.34E+11 1.09E+00 4.02E+04 79 Tc-101 6.18E-01 2.29E+10 1.85E-01 6.85E+03 80 Tc-104 9.90E-01 3.66E+10 2.97E-01 1.10E+04 81 Tc-99m 3.91E+01 1.45E+12 1.17E+01 4.34E+05 82 Te-129m 4.12E+00 1.52E+11 1.24E+00 4.57E+04 83 Te-131m 5.17E-01 1.91E+10 1.55E-01 5.73E+03 84 Te-132 1.37E-01 5.07E+09 4.11E-02 1.52E+03 85 W-187 1.22E+00 4.51E+10 3.66E-01 1.35E+04 86 Y-90 1.07E+00 3.96E+10 3.21E-01 1.19E+04 87 Y-91 8.37E+00 3.10E+11 2.51E+00 9.28E+04 88 Y-92 7.08E+00 2.62E+11 2.12E+00 7.85E+04 89 Y-93 6.66E+00 2.46E+11 2.00E+00 7.39E+04 90 Zn-65 3.27E+01 1.21E+12 9.80E+00 3.63E+05 91 Zn-69 2.23E-01 8.25E+09 6.68E-02 2.47E+03 92 Zr-95 9.25E-01 3.42E+10 2.77E-01 1.03E+04 93 Zr-97 1.43E-02 5.29E+08 4.29E-03 1.59E+02 94 Buildup: The material reference is Source 95 Integration Parameters 96 Radial 30 97 Circumferential 30 98 Y Direction (axial) 60 99 Results 100 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 101 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 102 No Buildup With Buildup No Buildup With Buildup 103 0.0394 1.30E+13 2.80E+05 9.71E+05 1.29E+03 4.47E+03 104 0.2952 3.38E+12 1.16E+06 4.30E+06 2.19E+03 8.14E+03 105 0.3768 5.86E+12 2.81E+06 9.23E+06 5.46E+03 1.79E+04 106 0.561 5.40E+12 4.53E+06 1.24E+07 8.87E+03 2.43E+04 107 0.8063 3.53E+12 4.98E+06 1.18E+07 9.46E+03 2.25E+04 108 0.903 6.25E+11 1.04E+06 2.38E+06 1.95E+03 4.45E+03 109 1.1516 3.80E+12 9.06E+06 1.91E+07 1.63E+04 3.43E+04 110 1.3239 3.04E+12 8.91E+06 1.80E+07 1.55E+04 3.13E+04 111 1.3798 1.11E+12 3.47E+06 6.92E+06 5.97E+03 1.19E+04 112 1.6035 8.48E+11 3.31E+06 6.33E+06 5.47E+03 1.05E+04 113 1.793 2.87E+11 1.32E+06 2.45E+06 2.11E+03 3.92E+03 114 1.941 2.30E+10 1.19E+05 2.17E+05 1.86E+02 3.39E+02 115 2.1111 1.07E+11 6.27E+05 1.12E+06 9.54E+02 1.70E+03 116 2.2948 1.60E+10 1.07E+05 1.86E+05 1.58E+02 2.75E+02 117 2.4906 5.43E+10 4.09E+05 6.98E+05 5.90E+02 1.01E+03 118 2.6343 9.38E+09 7.69E+04 1.29E+05 1.09E+02 1.83E+02 119 2.7542 8.29E+11 7.26E+06 1.21E+07 1.01E+04 1.69E+04 120 2.9708 5.17E+09 5.07E+04 8.29E+04 6.90E+01 1.13E+02 121 3.1388 1.31E+09 1.39E+04 2.24E+04 1.86E+01 3.00E+01 122 3.333 2.18E+09 2.53E+04 4.02E+04 3.31E+01 5.28E+01 123 3.4433 5.14E+08 6.26E+03 9.89E+03 8.13E+00 1.28E+01 124 3.6416 9.61E+08 1.27E+04 1.98E+04 1.62E+01 2.53E+01 125 3.8609 6.33E+08 9.11E+03 1.40E+04 1.14E+01 1.75E+01 126 3.9651 8.84E+07 1.32E+03 2.02E+03 1.64E+00 2.51E+00 127 4.1711 1.24E+07 2.00E+02 3.02E+02 2.44E-01 3.68E-01 128 Totals 4.19E+13 4.96E+07 1.09E+08 8.68E+04 1.94E+05 Calc. No. PM-750, Rev. 1, Attachment A, Page A-3 of A-11

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4 5 Filename Run Date Run Time Duration 6 Limerick.msd 12-Aug-09 4:04:29 PM 0:00:07 7 Project Info 8 Case Title LGS 11.4-8 9 Description with 60 day decay, before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: ICRP-38 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-227 8.06E-24 2.98E-13 2.42E-24 8.94E-20 29 Ag-110 1.85E-03 6.83E+07 5.54E-04 2.05E+01 30 Ag-110m 1.39E-01 5.14E+09 4.16E-02 1.54E+03 31 Ba-137m 1.17E+01 4.32E+11 3.50E+00 1.30E+05 32 Ba-139 4.8914e-315 1.81E-304 1.4663e-315 5.4251e-311 33 Ba-140 8.03E-01 2.97E+10 2.41E-01 8.90E+03 34 Ba-141 35 Ba-142 36 Bi-211 1.73E-24 6.40E-14 5.19E-25 1.92E-20 37 Br-83 3.79E-182 1.40E-171 1.14E-182 4.21E-178 38 Br-84 39 Ce-141 9.15E-01 3.39E+10 2.74E-01 1.02E+04 40 Ce-143 1.25E-14 4.63E-04 3.75E-15 1.39E-10 41 Ce-144 4.31E-01 1.60E+10 1.29E-01 4.78E+03 42 Co-58 1.50E+01 5.53E+11 4.48E+00 1.66E+05 43 Co-60 6.92E+01 2.56E+12 2.07E+01 7.67E+05 44 Cr-51 1.03E+02 3.82E+12 3.09E+01 1.14E+06 45 Cs-134 4.93E+00 1.82E+11 1.48E+00 5.47E+04 46 Cs-135 6.49E-09 2.40E+02 1.95E-09 7.20E-05 47 Cs-136 4.64E-02 1.72E+09 1.39E-02 5.15E+02 48 Cs-137 1.24E+01 4.57E+11 3.70E+00 1.37E+05 49 Cs-138 50 Cu-64 4.78E-33 1.77E-22 1.43E-33 5.30E-29 51 Fe-55 1.67E+02 6.17E+12 5.00E+01 1.85E+06 52 Fe-59 1.38E+00 5.12E+10 4.15E-01 1.53E+04 53 Fr-223 1.09E-25 4.05E-15 3.28E-26 1.21E-21 54 I-129 1.71E-08 6.34E+02 5.14E-09 1.90E-04 55 I-131 9.64E-01 3.57E+10 2.89E-01 1.07E+04 56 I-132 4.04E-07 1.49E+04 1.21E-07 4.48E-03 57 I-133 9.72E-20 3.59E-09 2.91E-20 1.08E-15 58 I-134 59 I-135 5.21E-65 1.93E-54 1.56E-65 5.78E-61 60 Kr-83m 1.62E-181 5.99E-171 4.85E-182 1.80E-177 61 La-140 8.03E-01 2.97E+10 2.41E-01 8.90E+03 62 La-141 5.16E-113 1.91E-102 1.55E-113 5.73E-109 63 La-142 6.78E-282 2.51E-271 2.03E-282 7.52E-278 64 Mn-54 8.75E+00 3.24E+11 2.62E+00 9.71E+04 65 Mn-56 1.30E-167 4.80E-157 3.89E-168 1.44E-163 66 Mo-99 6.36E-06 2.35E+05 1.91E-06 7.05E-02 67 Na-24 2.83E-28 1.05E-17 8.48E-29 3.14E-24 68 Nb-93m 4.14E-11 1.53E+00 1.24E-11 4.59E-07 69 Nb-95 7.92E-01 2.93E+10 2.37E-01 8.78E+03 70 Nb-95m 3.57E-03 1.32E+08 1.07E-03 3.96E+01 71 Nb-97 3.45E-28 1.28E-17 1.03E-28 3.83E-24 72 Nb-97m 3.04E-28 1.12E-17 9.10E-29 3.37E-24 73 Nb-98 74 Nd-147 3.15E-03 1.16E+08 9.44E-04 3.49E+01 75 Ni-63 1.79E-01 6.62E+09 5.36E-02 1.98E+03 76 Ni-65 9.71E-174 3.59E-163 2.91E-174 1.08E-169 77 Np-239 1.48E-06 5.48E+04 4.44E-07 1.64E-02 78 P-32 6.26E-01 2.32E+10 1.88E-01 6.95E+03 79 Pa-231 4.41E-21 1.63E-10 1.32E-21 4.89E-17 80 Pb-211 1.97E-24 7.29E-14 5.91E-25 2.19E-20 81 Pm-147 1.51E-03 5.57E+07 4.52E-04 1.67E+01 82 Po-211 5.09E-27 1.88E-16 1.53E-27 5.65E-23 83 Po-215 1.80E-24 6.64E-14 5.38E-25 1.99E-20 Calc. No. PM-750, Rev. 1, Attachment A, Page A-4 of A-11

A B C D E F G H I 84 Pr-143 1.12E-01 4.13E+09 3.35E-02 1.24E+03 85 Pr-144 4.25E-01 1.57E+10 1.27E-01 4.71E+03 86 Pr-144m 7.67E-03 2.84E+08 2.30E-03 8.51E+01 87 Pu-239 1.85E-05 6.86E+05 5.56E-06 2.06E-01 88 Ra-223 1.72E-24 6.37E-14 5.16E-25 1.91E-20 89 Rb-89 90 Re-187 6.65E-14 2.46E-03 1.99E-14 7.38E-10 91 Rh-103m 7.62E-01 2.82E+10 2.28E-01 8.45E+03 92 Rh-105 1.03E-13 3.80E-03 3.08E-14 1.14E-09 93 Rh-106 4.53E-01 1.68E+10 1.36E-01 5.02E+03 94 Rn-219 1.80E-24 6.65E-14 5.39E-25 1.99E-20 95 Ru-103 7.63E-01 2.82E+10 2.29E-01 8.46E+03 96 Ru-105 3.04E-98 1.12E-87 9.11E-99 3.37E-94 97 Ru-106 4.53E-01 1.68E+10 1.36E-01 5.02E+03 98 Sm-147 1.25E-15 4.61E-05 3.74E-16 1.38E-11 99 Sr-89 5.44E+00 2.01E+11 1.63E+00 6.04E+04 100 Sr-90 1.07E+00 3.94E+10 3.19E-01 1.18E+04 101 Sr-91 1.46E-45 5.40E-35 4.37E-46 1.62E-41 102 Sr-92 4.00E-160 1.48E-149 1.20E-160 4.43E-156 103 Tc-101 104 Tc-104 105 Tc-99 9.57E-07 3.54E+04 2.87E-07 1.06E-02 106 Tc-99m 6.13E-06 2.27E+05 1.84E-06 6.79E-02 107 Te-129 7.78E-01 2.88E+10 2.33E-01 8.63E+03 108 Te-129m 1.19E+00 4.42E+10 3.58E-01 1.33E+04 109 Te-131 4.14E-16 1.53E-05 1.24E-16 4.59E-12 110 Te-131m 1.84E-15 6.80E-05 5.51E-16 2.04E-11 111 Te-132 3.92E-07 1.45E+04 1.18E-07 4.35E-03 112 Th-227 3.32E-24 1.23E-13 9.96E-25 3.69E-20 113 Th-231 2.75E-15 1.02E-04 8.25E-16 3.05E-11 114 Tl-207 2.00E-24 7.39E-14 5.99E-25 2.22E-20 115 U-235 2.83E-15 1.05E-04 8.48E-16 3.14E-11 116 W-187 8.89E-19 3.29E-08 2.67E-19 9.86E-15 117 Xe-131m 9.71E-02 3.59E+09 2.91E-02 1.08E+03 118 Xe-133 4.90E-03 1.81E+08 1.47E-03 5.43E+01 119 Xe-133m 7.12E-09 2.63E+02 2.13E-09 7.89E-05 120 Xe-135 1.09E-46 4.02E-36 3.26E-47 1.21E-42 121 Xe-135m 8.34E-66 3.09E-55 2.50E-66 9.25E-62 122 Y-90 1.07E+00 3.94E+10 3.19E-01 1.18E+04 123 Y-91 4.13E+00 1.53E+11 1.24E+00 4.58E+04 124 Y-91m 9.24E-46 3.42E-35 2.77E-46 1.02E-41 125 Y-92 6.66E-122 2.46E-111 2.00E-122 7.39E-118 126 Y-93 8.02E-43 2.97E-32 2.41E-43 8.90E-39 127 Zn-65 2.76E+01 1.02E+12 8.27E+00 3.06E+05 128 Zn-69 129 Zr-93 5.02E-09 1.86E+02 1.50E-09 5.56E-05 130 Zr-95 4.83E-01 1.79E+10 1.45E-01 5.36E+03 131 Zr-97 3.20E-28 1.18E-17 9.60E-29 3.55E-24 132 Buildup: The material reference is Source 133 Integration Parameters 134 Radial 30 135 Circumferential 30 136 Y Direction (axial) 60 137 Results 138 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 139 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 140 No Buildup With Buildup No Buildup With Buildup 141 0.0074 3.37E+12 2.11E+03 2.45E+03 8.73E+02 1.02E+03 142 0.3192 3.88E+11 1.48E+05 5.27E+05 2.83E+02 1.01E+03 143 0.4384 7.62E+10 4.51E+04 1.38E+05 8.84E+01 2.70E+02 144 0.6068 8.28E+11 7.76E+05 2.06E+06 1.51E+03 4.02E+03 145 0.8128 1.11E+12 1.58E+06 3.75E+06 3.01E+03 7.13E+03 146 0.8927 1.41E+10 2.31E+04 5.29E+04 4.32E+01 9.92E+01 147 1.1628 3.11E+12 7.52E+06 1.58E+07 1.35E+04 2.83E+04 148 1.3321 2.58E+12 7.64E+06 1.54E+07 1.33E+04 2.67E+04 149 1.3846 7.76E+09 2.43E+04 4.85E+04 4.18E+01 8.33E+01 150 1.6033 3.13E+10 1.22E+05 2.33E+05 2.02E+02 3.85E+02 151 1.7798 1.03E+07 4.68E+01 8.69E+01 7.50E-02 1.39E-01 152 1.9636 7.52E+06 3.98E+01 7.20E+01 6.18E-02 1.12E-01 153 2.1784 1.57E+08 9.71E+02 1.71E+03 1.46E+00 2.58E+00 154 2.3476 2.57E+08 1.78E+03 3.08E+03 2.61E+00 4.52E+00 155 2.5206 1.03E+09 7.90E+03 1.35E+04 1.13E+01 1.93E+01 156 2.5532 3.28E+07 2.56E+02 4.35E+02 3.67E-01 6.22E-01 157 2.7986 3.52E+05 3.16E+00 5.23E+00 4.38E-03 7.26E-03 158 2.9009 2.00E+07 1.89E+02 3.10E+02 2.59E-01 4.26E-01 159 3.1182 7.79E+06 8.20E+01 1.33E+02 1.10E-01 1.78E-01 160 3.3128 1.49E+06 1.71E+01 2.72E+01 2.25E-02 3.58E-02 161 3.4345 1.98E-273 2.40E-278 3.79E-278 3.12E-281 4.93E-281 162 3.6364 5.93E-273 7.82E-278 1.22E-277 9.98E-281 1.56E-280 163 3.8674 6.49E-21 9.35E-26 1.44E-25 1.17E-28 1.80E-28 164 4.0104 2.64E-274 4.01E-279 6.11E-279 4.95E-282 7.55E-282 165 4.2389 8.79E-23 1.45E-27 2.18E-27 1.76E-30 2.64E-30 166 Totals 1.15E+13 1.79E+07 3.81E+07 3.28E+04 6.91E+04 Calc. No. PM-750, Rev. 1, Attachment A, Page A-5 of A-11

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4 5 Filename Run Date Run Time Duration 6 LGS.msd 12-Aug-09 4:07:45 PM 0:00:07 7 Project Info 8 Case Title LGS 11.4-8 9 Description with 60 day decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: ICRP-38 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-227 2.33E-23 8.63E-13 6.99E-24 2.59E-19 29 Ag-110 5.35E-03 1.98E+08 1.60E-03 5.93E+01 30 Ag-110m 4.02E-01 1.49E+10 1.20E-01 4.46E+03 31 Ba-137m 3.38E+01 1.25E+12 1.01E+01 3.75E+05 32 Ba-139 1.4160e-314 5.24E-304 4.2445e-315 1.5705e-310 33 Ba-140 2.32E+00 8.60E+10 6.96E-01 2.58E+04 34 Ba-141 35 Ba-142 36 Bi-211 5.01E-24 1.85E-13 1.50E-24 5.56E-20 37 Br-83 1.10E-181 4.06E-171 3.29E-182 1.22E-177 38 Br-84 39 Ce-141 2.65E+00 9.80E+10 7.94E-01 2.94E+04 40 Ce-143 3.62E-14 1.34E-03 1.09E-14 4.02E-10 41 Ce-144 1.25E+00 4.62E+10 3.74E-01 1.38E+04 42 Co-58 4.33E+01 1.60E+12 1.30E+01 4.80E+05 43 Co-60 2.00E+02 7.41E+12 6.00E+01 2.22E+06 44 Cr-51 2.99E+02 1.11E+13 8.95E+01 3.31E+06 45 Cs-134 1.43E+01 5.28E+11 4.28E+00 1.58E+05 46 Cs-135 1.88E-08 6.95E+02 5.63E-09 2.08E-04 47 Cs-136 1.34E-01 4.97E+09 4.03E-02 1.49E+03 48 Cs-137 3.58E+01 1.32E+12 1.07E+01 3.97E+05 49 Cs-138 50 Cu-64 1.38E-32 5.12E-22 4.14E-33 1.53E-28 51 Fe-55 4.83E+02 1.79E+13 1.45E+02 5.36E+06 52 Fe-59 4.00E+00 1.48E+11 1.20E+00 4.44E+04 53 Fr-223 3.17E-25 1.17E-14 9.49E-26 3.51E-21 54 I-129 4.96E-08 1.84E+03 1.49E-08 5.50E-04 55 I-131 2.79E+00 1.03E+11 8.37E-01 3.10E+04 56 I-132 1.17E-06 4.33E+04 3.51E-07 1.30E-02 57 I-133 2.81E-19 1.04E-08 8.43E-20 3.12E-15 58 I-134 59 I-135 1.51E-64 5.58E-54 4.52E-65 1.67E-60 60 Kr-83m 4.69E-181 1.73E-170 1.40E-181 5.20E-177 61 La-140 2.32E+00 8.60E+10 6.96E-01 2.58E+04 62 La-141 1.50E-112 5.53E-102 4.48E-113 1.66E-108 63 La-142 1.96E-281 7.27E-271 5.89E-282 2.18E-277 64 Mn-54 2.53E+01 9.38E+11 7.60E+00 2.81E+05 65 Mn-56 3.76E-167 1.39E-156 1.13E-167 4.17E-163 66 Mo-99 1.84E-05 6.81E+05 5.51E-06 2.04E-01 67 Na-24 8.18E-28 3.03E-17 2.45E-28 9.08E-24 68 Nb-93m 1.20E-10 4.43E+00 3.59E-11 1.33E-06 69 Nb-95 2.29E+00 8.48E+10 6.87E-01 2.54E+04 70 Nb-95m 1.03E-02 3.83E+08 3.10E-03 1.15E+02 71 Nb-97 9.99E-28 3.70E-17 2.99E-28 1.11E-23 72 Nb-97m 8.79E-28 3.25E-17 2.63E-28 9.75E-24 73 Nb-98 74 Nd-147 9.11E-03 3.37E+08 2.73E-03 1.01E+02 75 Ni-63 5.18E-01 1.91E+10 1.55E-01 5.74E+03 76 Ni-65 2.81E-173 1.04E-162 8.43E-174 3.12E-169 77 Np-239 4.29E-06 1.59E+05 1.29E-06 4.75E-02 78 P-32 1.81E+00 6.71E+10 5.43E-01 2.01E+04 79 Pa-231 1.28E-20 4.73E-10 3.83E-21 1.42E-16 80 Pb-211 5.70E-24 2.11E-13 1.71E-24 6.33E-20 81 Pm-147 4.36E-03 1.61E+08 1.31E-03 4.84E+01 82 Po-211 1.47E-26 5.45E-16 4.42E-27 1.64E-22 83 Po-215 5.20E-24 1.92E-13 1.56E-24 5.77E-20 Calc. No. PM-750, Rev. 1, Attachment A, Page A-6 of A-11

A B C D E F G H I 84 Pr-143 3.23E-01 1.20E+10 9.69E-02 3.59E+03 85 Pr-144 1.23E+00 4.55E+10 3.69E-01 1.36E+04 86 Pr-144m 2.22E-02 8.22E+08 6.66E-03 2.46E+02 87 Pu-239 5.37E-05 1.99E+06 1.61E-05 5.95E-01 88 Ra-223 4.98E-24 1.84E-13 1.49E-24 5.53E-20 89 Rb-89 90 Re-187 1.93E-13 7.13E-03 5.77E-14 2.14E-09 91 Rh-103m 2.20E+00 8.16E+10 6.61E-01 2.45E+04 92 Rh-105 2.98E-13 1.10E-02 8.92E-14 3.30E-09 93 Rh-106 1.31E+00 4.85E+10 3.93E-01 1.45E+04 94 Rn-219 5.20E-24 1.92E-13 1.56E-24 5.77E-20 95 Ru-103 2.21E+00 8.17E+10 6.62E-01 2.45E+04 96 Ru-105 8.79E-98 3.25E-87 2.64E-98 9.75E-94 97 Ru-106 1.31E+00 4.85E+10 3.93E-01 1.45E+04 98 Sm-147 3.61E-15 1.34E-04 1.08E-15 4.00E-11 99 Sr-89 1.58E+01 5.83E+11 4.72E+00 1.75E+05 100 Sr-90 3.09E+00 1.14E+11 9.25E-01 3.42E+04 101 Sr-91 4.22E-45 1.56E-34 1.27E-45 4.68E-41 102 Sr-92 1.16E-159 4.28E-149 3.47E-160 1.28E-155 103 Tc-101 104 Tc-104 105 Tc-99 2.77E-06 1.02E+05 8.30E-07 3.07E-02 106 Tc-99m 1.77E-05 6.56E+05 5.32E-06 1.97E-01 107 Te-129 2.25E+00 8.33E+10 6.75E-01 2.50E+04 108 Te-129m 3.46E+00 1.28E+11 1.04E+00 3.84E+04 109 Te-131 1.20E-15 4.43E-05 3.59E-16 1.33E-11 110 Te-131m 5.32E-15 1.97E-04 1.59E-15 5.90E-11 111 Te-132 1.14E-06 4.20E+04 3.40E-07 1.26E-02 112 Th-227 9.62E-24 3.56E-13 2.88E-24 1.07E-19 113 Th-231 7.97E-15 2.95E-04 2.39E-15 8.84E-11 114 Tl-207 5.78E-24 2.14E-13 1.73E-24 6.41E-20 115 U-235 8.19E-15 3.03E-04 2.46E-15 9.09E-11 116 W-187 2.57E-18 9.52E-08 7.72E-19 2.85E-14 117 Xe-131m 2.81E-01 1.04E+10 8.42E-02 3.12E+03 118 Xe-133 1.42E-02 5.24E+08 4.25E-03 1.57E+02 119 Xe-133m 2.06E-08 7.62E+02 6.18E-09 2.29E-04 120 Xe-135 3.15E-46 1.16E-35 9.44E-47 3.49E-42 121 Xe-135m 2.42E-65 8.94E-55 7.24E-66 2.68E-61 122 Y-90 3.09E+00 1.14E+11 9.25E-01 3.42E+04 123 Y-91 1.20E+01 4.43E+11 3.59E+00 1.33E+05 124 Y-91m 2.67E-45 9.89E-35 8.02E-46 2.97E-41 125 Y-92 1.93E-121 7.13E-111 5.78E-122 2.14E-117 126 Y-93 2.32E-42 8.59E-32 6.96E-43 2.58E-38 127 Zn-65 7.98E+01 2.95E+12 2.39E+01 8.85E+05 128 Zn-69 129 Zr-93 1.45E-08 5.37E+02 4.35E-09 1.61E-04 130 Zr-95 1.40E+00 5.17E+10 4.19E-01 1.55E+04 131 Zr-97 9.27E-28 3.43E-17 2.78E-28 1.03E-23 132 Buildup: The material reference is Source 133 Integration Parameters 134 Radial 30 135 Circumferential 30 136 Y Direction (axial) 60 137 Results 138 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 139 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 140 No Buildup With Buildup No Buildup With Buildup 141 0.0074 9.74E+12 6.10E+03 7.09E+03 2.53E+03 2.94E+03 142 0.3192 1.12E+12 4.29E+05 1.53E+06 8.19E+02 2.92E+03 143 0.4384 2.21E+11 1.31E+05 3.99E+05 2.56E+02 7.82E+02 144 0.6068 2.40E+12 2.25E+06 5.97E+06 4.38E+03 1.16E+04 145 0.8128 3.21E+12 4.58E+06 1.09E+07 8.70E+03 2.06E+04 146 0.8927 4.07E+10 6.67E+04 1.53E+05 1.25E+02 2.87E+02 147 1.1628 9.01E+12 2.18E+07 4.58E+07 3.90E+04 8.20E+04 148 1.3321 7.48E+12 2.21E+07 4.46E+07 3.84E+04 7.74E+04 149 1.3846 2.25E+10 7.04E+04 1.40E+05 1.21E+02 2.41E+02 150 1.6033 9.06E+10 3.53E+05 6.75E+05 5.84E+02 1.12E+03 151 1.7798 2.97E+07 1.35E+02 2.52E+02 2.17E-01 4.03E-01 152 1.9636 2.18E+07 1.15E+02 2.09E+02 1.79E-01 3.24E-01 153 2.1784 4.55E+08 2.81E+03 4.96E+03 4.23E+00 7.47E+00 154 2.3476 7.45E+08 5.14E+03 8.90E+03 7.55E+00 1.31E+01 155 2.5206 2.98E+09 2.29E+04 3.89E+04 3.28E+01 5.59E+01 156 2.5532 9.49E+07 7.42E+02 1.26E+03 1.06E+00 1.80E+00 157 2.7986 1.02E+06 9.14E+00 1.52E+01 1.27E-02 2.10E-02 158 2.9009 5.78E+07 5.47E+02 8.98E+02 7.49E-01 1.23E+00 159 3.1182 2.26E+07 2.37E+02 3.84E+02 3.18E-01 5.14E-01 160 3.3128 4.30E+06 4.94E+01 7.88E+01 6.50E-02 1.04E-01 161 3.4345 5.72E-273 6.94E-278 1.10E-277 9.02E-281 1.43E-280 162 3.6364 1.72E-272 2.26E-277 3.53E-277 2.89E-280 4.51E-280 163 3.8674 1.88E-20 2.71E-25 4.16E-25 3.39E-28 5.21E-28 164 4.0104 7.63E-274 1.16E-278 1.77E-278 1.43E-281 2.18E-281 165 4.2389 2.54E-22 4.19E-27 6.30E-27 5.08E-30 7.64E-30 166 Totals 3.33E+13 5.18E+07 1.10E+08 9.49E+04 2.00E+05 Calc. No. PM-750, Rev. 1, Attachment A, Page A-7 of A-11

A B C D E F G H 1 Container Drop Event: Limerick Isotopic: Table 11.4-8 2 9.200E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 3.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 2.50E+02 Actual Container Contact 9 10 6.769E-01 Total Inhalation Dose 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ac-227 2.33E-23 1.810E-03 1.886E-21 0% 14 Ag-110 5.35E-03 0.00E+00 0.000E+00 0% 15 Ag-110m 4.02E-01 2.170E-08 3.897E-04 0% 16 Ba-137m 3.38E+01 0.00E+00 0.000E+00 0% 17 Ba-139 1.4160e-314 4.640E-11 0.000E+00 0% 18 Ba-140 2.32E+00 1.010E-09 1.048E-04 0% 19 Ba-141 0.00E+00 2.180E-11 0.000E+00 0% 20 Ba-142 0.00E+00 1.110E-11 0.000E+00 0% 21 Bi-211 5.01E-24 0.00E+00 0.000E+00 0% 22 Br-83 1.10E-181 2.410E-11 1.182E-187 0% 23 Br-84 0.00E+00 2.610E-11 0.000E+00 0% 24 Ce-141 2.65E+00 2.420E-09 2.864E-04 0% 25 Ce-143 3.62E-14 9.160E-10 1.482E-18 0% 26 Ce-144 1.25E+00 1.010E-07 5.631E-03 1% 27 Co-58 4.33E+01 2.940E-09 5.685E-03 1% 28 Co-60 2.00E+02 5.910E-08 5.289E-01 78% 29 Cr-51 2.99E+02 9.030E-11 1.205E-03 0% 30 Cs-134 1.43E+01 1.250E-08 7.970E-03 1% 31 Cs-135 1.88E-08 1.230E-09 1.033E-12 0% 32 Cs-136 1.34E-01 1.980E-09 1.188E-05 0% 33 Cs-137 3.58E+01 8.630E-09 1.379E-02 2% 34 Cs-138 0.00E+00 2.740E-11 0.000E+00 0% 35 Cu-64 1.38E-32 7.480E-11 4.620E-38 0% 36 Fe-55 4.83E+02 7.260E-10 1.566E-02 2% 37 Fe-59 4.00E+00 4.000E-09 7.156E-04 0% 38 Fr-223 3.17E-25 1.680E-09 2.377E-29 0% 39 I-129 4.96E-08 4.690E-08 1.039E-10 0% 40 I-131 2.79E+00 8.890E-09 1.109E-03 0% 41 I-132 1.17E-06 1.030E-10 5.382E-12 0% 42 I-133 2.81E-19 1.580E-09 1.985E-23 0% 43 I-134 0.00E+00 3.550E-11 0.000E+00 0% 44 I-135 1.51E-64 3.320E-10 2.237E-69 0% 45 Kr-83m 4.69E-181 0.00E+00 0.000E+00 0% 46 La-140 2.32E+00 1.310E-09 1.360E-04 0% 47 La-141 1.50E-112 1.570E-10 1.049E-117 0% 48 La-142 1.96E-281 6.840E-11 6.001E-287 0% 49 Mn-54 2.53E+01 1.810E-09 2.049E-03 0% 50 Mn-56 3.76E-167 1.020E-10 1.713E-172 0% 51 Mo-99 1.84E-05 1.070E-09 8.795E-10 0% 52 Na-24 8.18E-28 3.270E-10 1.196E-32 0% 53 Nb-93m 1.20E-10 7.900E-09 4.229E-14 0% 54 Nb-95 2.29E+00 1.570E-09 1.608E-04 0% 55 Nb-95m 1.03E-02 6.590E-10 3.044E-07 0% 56 Nb-97 9.99E-28 2.240E-11 9.996E-34 0% 57 Nb-97m 8.79E-28 0.00E+00 0.000E+00 0% 58 Nb-98 0.00E+00 3.310E-11 0.000E+00 0% 59 Nd-147 9.11E-03 1.850E-09 7.532E-07 0% 60 Ni-63 5.18E-01 1.700E-09 3.931E-05 0% 61 Ni-65 2.81E-173 9.320E-11 1.170E-178 0% 62 Np-239 4.29E-06 6.780E-10 1.299E-10 0% 63 P-32 1.81E+00 4.190E-09 3.394E-04 0% 64 Pa-231 1.28E-20 3.470E-04 1.980E-19 0% 65 Pb-211 5.70E-24 2.350E-09 5.989E-28 0% 66 Pm-147 4.36E-03 1.060E-08 2.065E-06 0% 67 Po-211 1.47E-26 0.00E+00 0.000E+00 0% 68 Po-215 5.20E-24 0.00E+00 0.000E+00 0% 69 Pr-143 3.23E-01 2.190E-09 3.164E-05 0% 70 Pr-144 1.23E+00 1.170E-11 6.430E-07 0% 71 Pr-144m 2.22E-02 0.00E+00 0.000E+00 0% 72 Pu-239 5.37E-05 1.160E-04 2.781E-04 0% 73 Ra-223 4.98E-24 2.120E-06 4.719E-25 0% Calc. No. PM-750, Rev. 1, Attachment A, Page A-8 of A-11

A B C D E F G H 74 Rb-89 0.00E+00 1.160E-11 0.000E+00 0% 75 Re-187 1.93E-13 1.470E-11 1.265E-19 0% 76 Rh-103m 2.20E+00 1.380E-12 1.359E-07 0% 77 Rh-105 2.98E-13 2.580E-10 3.430E-18 0% 78 Rh-106 1.31E+00 0.00E+00 0.000E+00 0% 79 Rn-219 5.20E-24 0.00E+00 0.000E+00 0% 80 Ru-103 2.21E+00 2.420E-09 2.388E-04 0% 81 Ru-105 8.79E-98 1.230E-10 4.833E-103 0% 82 Ru-106 1.31E+00 1.290E-07 7.555E-03 1% 83 Sm-147 3.61E-15 2.020E-05 3.258E-15 0% 84 Sr-89 1.58E+01 1.120E-08 7.883E-03 1% 85 Sr-90 3.09E+00 3.510E-07 4.838E-02 7% 86 Sr-91 4.22E-45 4.490E-10 8.471E-50 0% 87 Sr-92 1.16E-159 2.180E-10 1.127E-164 0% 88 Tc-101 0.00E+00 4.840E-12 0.000E+00 0% 89 Tc-104 0.00E+00 2.220E-11 0.000E+00 0% 90 Tc-99 2.77E-06 2.250E-09 2.784E-10 0% 91 Tc-99m 1.77E-05 8.800E-12 6.972E-12 0% 92 Te-129 2.25E+00 2.420E-11 2.434E-06 0% 93 Te-129m 3.46E+00 6.470E-09 9.999E-04 0% 94 Te-131 1.20E-15 1.290E-10 6.899E-21 0% 95 Te-131m 5.32E-15 1.730E-09 4.110E-19 0% 96 Te-132 1.14E-06 2.550E-09 1.293E-10 0% 97 Th-227 9.62E-24 4.370E-06 1.878E-24 0% 98 Th-231 7.97E-15 2.370E-10 8.438E-20 0% 99 Tl-207 5.78E-24 0.00E+00 0.000E+00 0% 100 U-235 8.19E-15 3.320E-05 1.215E-14 0% 101 W-187 2.57E-18 1.670E-10 1.920E-23 0% 102 Xe-131m 2.81E-01 0.00E+00 0.000E+00 0% 103 Xe-133 1.42E-02 0.00E+00 0.000E+00 0% 104 Xe-133m 2.06E-08 0.00E+00 0.000E+00 0% 105 Xe-135 3.15E-46 0.00E+00 0.000E+00 0% 106 Xe-135m 2.42E-65 0.00E+00 0.000E+00 0% 107 Y-90 3.09E+00 2.280E-09 3.143E-04 0% 108 Y-91 1.20E+01 1.320E-08 7.055E-03 1% 109 Y-91m 2.67E-45 9.820E-12 1.173E-51 0% 110 Y-92 1.93E-121 2.110E-10 1.818E-126 0% 111 Y-93 2.32E-42 5.820E-10 6.039E-47 0% 112 Zn-65 7.98E+01 5.510E-09 1.965E-02 3% 113 Zn-69 0.00E+00 1.060E-11 0.000E+00 0% 114 Zr-93 1.45E-08 8.670E-08 5.624E-11 0% 115 Zr-95 1.40E+00 6.390E-09 3.991E-04 0% 116 Zr-97 9.27E-28 1.170E-09 4.845E-32 0% 117 118 119 Total Rem 6.769E-01 Calc. No. PM-750, Rev. 1, Attachment A, Page A-9 of A-11

A B C D E F G H 1 Container Drop Event: Limerick Isotopic: Table 11.4-8 2 0.00092 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.03 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 250 Actual Container Contact 9 10 =F119 Total Inhalation Dose 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 ='LGS Final'!A28 ='LGS Final'!E28 0.00181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D13*E13 =F13/$F$119 14 ='LGS Final'!A29 ='LGS Final'!E29 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D14*E14 =F14/$F$119 15 ='LGS Final'!A30 ='LGS Final'!E30 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D15*E15 =F15/$F$119 16 ='LGS Final'!A31 ='LGS Final'!E31 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D16*E16 =F16/$F$119 17 ='LGS Final'!A32 ='LGS Final'!E32 0.0000000000464 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D17*E17 =F17/$F$119 18 ='LGS Final'!A33 ='LGS Final'!E33 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D18*E18 =F18/$F$119 19 ='LGS Final'!A34 ='LGS Final'!E34 0.0000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D19*E19 =F19/$F$119 20 ='LGS Final'!A35 ='LGS Final'!E35 0.0000000000111 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D20*E20 =F20/$F$119 21 ='LGS Final'!A36 ='LGS Final'!E36 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D21*E21 =F21/$F$119 22 ='LGS Final'!A37 ='LGS Final'!E37 0.0000000000241 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D22*E22 =F22/$F$119 23 ='LGS Final'!A38 ='LGS Final'!E38 0.0000000000261 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D23*E23 =F23/$F$119 24 ='LGS Final'!A39 ='LGS Final'!E39 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D24*E24 =F24/$F$119 25 ='LGS Final'!A40 ='LGS Final'!E40 0.000000000916 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D25*E25 =F25/$F$119 26 ='LGS Final'!A41 ='LGS Final'!E41 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D26*E26 =F26/$F$119 27 ='LGS Final'!A42 ='LGS Final'!E42 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D27*E27 =F27/$F$119 28 ='LGS Final'!A43 ='LGS Final'!E43 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D28*E28 =F28/$F$119 29 ='LGS Final'!A44 ='LGS Final'!E44 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D29*E29 =F29/$F$119 30 ='LGS Final'!A45 ='LGS Final'!E45 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D30*E30 =F30/$F$119 31 ='LGS Final'!A46 ='LGS Final'!E46 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D31*E31 =F31/$F$119 32 ='LGS Final'!A47 ='LGS Final'!E47 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D32*E32 =F32/$F$119 33 ='LGS Final'!A48 ='LGS Final'!E48 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D33*E33 =F33/$F$119 34 ='LGS Final'!A49 ='LGS Final'!E49 0.0000000000274 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D34*E34 =F34/$F$119 35 ='LGS Final'!A50 ='LGS Final'!E50 0.0000000000748 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D35*E35 =F35/$F$119 36 ='LGS Final'!A51 ='LGS Final'!E51 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D36*E36 =F36/$F$119 37 ='LGS Final'!A52 ='LGS Final'!E52 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D37*E37 =F37/$F$119 38 ='LGS Final'!A53 ='LGS Final'!E53 0.00000000168 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D38*E38 =F38/$F$119 39 ='LGS Final'!A54 ='LGS Final'!E54 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D39*E39 =F39/$F$119 40 ='LGS Final'!A55 ='LGS Final'!E55 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D40*E40 =F40/$F$119 41 ='LGS Final'!A56 ='LGS Final'!E56 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D41*E41 =F41/$F$119 42 ='LGS Final'!A57 ='LGS Final'!E57 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D42*E42 =F42/$F$119 43 ='LGS Final'!A58 ='LGS Final'!E58 0.0000000000355 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D43*E43 =F43/$F$119 44 ='LGS Final'!A59 ='LGS Final'!E59 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D44*E44 =F44/$F$119 45 ='LGS Final'!A60 ='LGS Final'!E60 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D45*E45 =F45/$F$119 46 ='LGS Final'!A61 ='LGS Final'!E61 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D46*E46 =F46/$F$119 47 ='LGS Final'!A62 ='LGS Final'!E62 0.000000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D47*E47 =F47/$F$119 48 ='LGS Final'!A63 ='LGS Final'!E63 0.0000000000684 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D48*E48 =F48/$F$119 49 ='LGS Final'!A64 ='LGS Final'!E64 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D49*E49 =F49/$F$119 50 ='LGS Final'!A65 ='LGS Final'!E65 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D50*E50 =F50/$F$119 51 ='LGS Final'!A66 ='LGS Final'!E66 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D51*E51 =F51/$F$119 52 ='LGS Final'!A67 ='LGS Final'!E67 0.000000000327 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D52*E52 =F52/$F$119 53 ='LGS Final'!A68 ='LGS Final'!E68 0.0000000079 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D53*E53 =F53/$F$119 54 ='LGS Final'!A69 ='LGS Final'!E69 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D54*E54 =F54/$F$119 55 ='LGS Final'!A70 ='LGS Final'!E70 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D55*E55 =F55/$F$119 56 ='LGS Final'!A71 ='LGS Final'!E71 0.0000000000224 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D56*E56 =F56/$F$119 57 ='LGS Final'!A72 ='LGS Final'!E72 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D57*E57 =F57/$F$119 58 ='LGS Final'!A73 ='LGS Final'!E73 0.0000000000331 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D58*E58 =F58/$F$119 59 ='LGS Final'!A74 ='LGS Final'!E74 0.00000000185 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D59*E59 =F59/$F$119 60 ='LGS Final'!A75 ='LGS Final'!E75 0.0000000017 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D60*E60 =F60/$F$119 61 ='LGS Final'!A76 ='LGS Final'!E76 0.0000000000932 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D61*E61 =F61/$F$119 62 ='LGS Final'!A77 ='LGS Final'!E77 0.000000000678 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D62*E62 =F62/$F$119 63 ='LGS Final'!A78 ='LGS Final'!E78 0.00000000419 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D63*E63 =F63/$F$119 64 ='LGS Final'!A79 ='LGS Final'!E79 0.000347 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D64*E64 =F64/$F$119 65 ='LGS Final'!A80 ='LGS Final'!E80 0.00000000235 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D65*E65 =F65/$F$119 66 ='LGS Final'!A81 ='LGS Final'!E81 0.0000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D66*E66 =F66/$F$119 67 ='LGS Final'!A82 ='LGS Final'!E82 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D67*E67 =F67/$F$119 68 ='LGS Final'!A83 ='LGS Final'!E83 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D68*E68 =F68/$F$119 69 ='LGS Final'!A84 ='LGS Final'!E84 0.00000000219 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D69*E69 =F69/$F$119 70 ='LGS Final'!A85 ='LGS Final'!E85 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D70*E70 =F70/$F$119 71 ='LGS Final'!A86 ='LGS Final'!E86 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D71*E71 =F71/$F$119 72 ='LGS Final'!A87 ='LGS Final'!E87 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D72*E72 =F72/$F$119 73 ='LGS Final'!A88 ='LGS Final'!E88 0.00000212 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D73*E73 =F73/$F$119 74 ='LGS Final'!A89 ='LGS Final'!E89 0.0000000000116 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D74*E74 =F74/$F$119 75 ='LGS Final'!A90 ='LGS Final'!E90 0.0000000000147 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D75*E75 =F75/$F$119 76 ='LGS Final'!A91 ='LGS Final'!E91 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D76*E76 =F76/$F$119 77 ='LGS Final'!A92 ='LGS Final'!E92 0.000000000258 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D77*E77 =F77/$F$119 78 ='LGS Final'!A93 ='LGS Final'!E93 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D78*E78 =F78/$F$119 79 ='LGS Final'!A94 ='LGS Final'!E94 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D79*E79 =F79/$F$119 80 ='LGS Final'!A95 ='LGS Final'!E95 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D80*E80 =F80/$F$119 81 ='LGS Final'!A96 ='LGS Final'!E96 0.000000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D81*E81 =F81/$F$119 Calc. No. PM-750, Rev. 1, Attachment A, Page A-10 of A-11

A B C D E F G H 82 ='LGS Final'!A97 ='LGS Final'!E97 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D82*E82 =F82/$F$119 83 ='LGS Final'!A98 ='LGS Final'!E98 0.0000202 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D83*E83 =F83/$F$119 84 ='LGS Final'!A99 ='LGS Final'!E99 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D84*E84 =F84/$F$119 85 ='LGS Final'!A100 ='LGS Final'!E100 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D85*E85 =F85/$F$119 86 ='LGS Final'!A101 ='LGS Final'!E101 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D86*E86 =F86/$F$119 87 ='LGS Final'!A102 ='LGS Final'!E102 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D87*E87 =F87/$F$119 88 ='LGS Final'!A103 ='LGS Final'!E103 0.00000000000484 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D88*E88 =F88/$F$119 89 ='LGS Final'!A104 ='LGS Final'!E104 0.0000000000222 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D89*E89 =F89/$F$119 90 ='LGS Final'!A105 ='LGS Final'!E105 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D90*E90 =F90/$F$119 91 ='LGS Final'!A106 ='LGS Final'!E106 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D91*E91 =F91/$F$119 92 ='LGS Final'!A107 ='LGS Final'!E107 0.0000000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D92*E92 =F92/$F$119 93 ='LGS Final'!A108 ='LGS Final'!E108 0.00000000647 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D93*E93 =F93/$F$119 94 ='LGS Final'!A109 ='LGS Final'!E109 0.000000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D94*E94 =F94/$F$119 95 ='LGS Final'!A110 ='LGS Final'!E110 0.00000000173 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D95*E95 =F95/$F$119 96 ='LGS Final'!A111 ='LGS Final'!E111 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D96*E96 =F96/$F$119 97 ='LGS Final'!A112 ='LGS Final'!E112 0.00000437 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D97*E97 =F97/$F$119 98 ='LGS Final'!A113 ='LGS Final'!E113 0.000000000237 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D98*E98 =F98/$F$119 99 ='LGS Final'!A114 ='LGS Final'!E114 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D99*E99 =F99/$F$119 100 ='LGS Final'!A115 ='LGS Final'!E115 0.0000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D100*E100 =F100/$F$119 101 ='LGS Final'!A116 ='LGS Final'!E116 0.000000000167 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D101*E101 =F101/$F$119 102 ='LGS Final'!A117 ='LGS Final'!E117 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D102*E102 =F102/$F$119 103 ='LGS Final'!A118 ='LGS Final'!E118 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D103*E103 =F103/$F$119 104 ='LGS Final'!A119 ='LGS Final'!E119 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D104*E104 =F104/$F$119 105 ='LGS Final'!A120 ='LGS Final'!E120 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D105*E105 =F105/$F$119 106 ='LGS Final'!A121 ='LGS Final'!E121 0 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D106*E106 =F106/$F$119 107 ='LGS Final'!A122 ='LGS Final'!E122 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D107*E107 =F107/$F$119 108 ='LGS Final'!A123 ='LGS Final'!E123 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D108*E108 =F108/$F$119 109 ='LGS Final'!A124 ='LGS Final'!E124 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D109*E109 =F109/$F$119 110 ='LGS Final'!A125 ='LGS Final'!E125 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D110*E110 =F110/$F$119 111 ='LGS Final'!A126 ='LGS Final'!E126 0.000000000582 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D111*E111 =F111/$F$119 112 ='LGS Final'!A127 ='LGS Final'!E127 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D112*E112 =F112/$F$119 113 ='LGS Final'!A128 ='LGS Final'!E128 0.0000000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D113*E113 =F113/$F$119 114 ='LGS Final'!A129 ='LGS Final'!E129 0.0000000867 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D114*E114 =F114/$F$119 115 ='LGS Final'!A130 ='LGS Final'!E130 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D115*E115 =F115/$F$119 116 ='LGS Final'!A131 ='LGS Final'!E131 0.00000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D116*E116 =F116/$F$119 117 118 119 Total Rem =SUM(F13:F116) Calc. No. PM-750, Rev. 1, Attachment A, Page A-11 of A-11

A B C D E F 1 Table 1 - PM-750 Rev. 0 2 Design Basis RWCU Resin 3 Nuclide uC/cc 4 Ag-110m 1.840E+00 5 Am-241 8.393E-05 6 C-14 2.727E-03 7 Cm-242 1.005E-03 8 Cm-244 9.028E-05 9 CO- 58 4.600E+00 10 Co-60 6.059E+01 11 Cr-51 1.700E+00 12 CS-134 2.442E+01 13 CS-137 2.826E+01 14 Fe-55 5.450E+00 15 H-3 1.151E-03 16 I-129 3.956E-05 17 I-131 3.040E+00 18 Mn- 54 2.990E+00 19 Nb-95 1.030E+00 20 Ni-63 4.840E-01 21 Pu-238 2.670E-04 22 Pu-239 1.272E-04 23 Pu-241 2.543E-02 24 Sr-90 3.391E-02 25 Sr-92 4.062E+01 26 Tc-99 4.239E-02 27 Zn-65 1.046E+02 Calc. No. PM-750, Rev. 1, Attachment B, Page B-1 of B-7

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4 5 Filename Run Date Run Time Duration 6 PeachBottom.msd 12-Aug-09 4:38:07 PM 0:00:05 7 Project Info 8 Case Title PM-750 Table 1 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Standard Indices 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Excluded 26 Library: ICRP-38 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ag-110m 6.14E+00 2.27E+11 1.84E+00 6.81E+04 29 Am-241 2.80E-04 1.04E+07 8.39E-05 3.11E+00 30 Ba-137m 8.92E+01 3.30E+12 2.67E+01 9.89E+05 31 C-14 9.10E-03 3.37E+08 2.73E-03 1.01E+02 32 Cm-242 3.35E-03 1.24E+08 1.01E-03 3.72E+01 33 Cm-244 3.01E-04 1.11E+07 9.03E-05 3.34E+00 34 Co-58 1.53E+01 5.68E+11 4.60E+00 1.70E+05 35 Co-60 2.02E+02 7.48E+12 6.06E+01 2.24E+06 36 Cr-51 5.67E+00 2.10E+11 1.70E+00 6.29E+04 37 Cs-134 8.15E+01 3.01E+12 2.44E+01 9.04E+05 38 Cs-137 9.43E+01 3.49E+12 2.83E+01 1.05E+06 39 Fe-55 1.82E+01 6.73E+11 5.45E+00 2.02E+05 40 H-3 3.84E-03 1.42E+08 1.15E-03 4.26E+01 41 I-129 1.32E-04 4.88E+06 3.96E-05 1.46E+00 42 I-131 1.01E+01 3.75E+11 3.04E+00 1.12E+05 43 Mn-54 9.97E+00 3.69E+11 2.99E+00 1.11E+05 44 Nb-95 3.44E+00 1.27E+11 1.03E+00 3.81E+04 45 Ni-63 1.61E+00 5.97E+10 4.84E-01 1.79E+04 46 Pu-238 8.91E-04 3.30E+07 2.67E-04 9.88E+00 47 Pu-239 4.24E-04 1.57E+07 1.27E-04 4.71E+00 48 Pu-241 8.48E-02 3.14E+09 2.54E-02 9.41E+02 49 Sr-90 1.13E-01 4.19E+09 3.39E-02 1.25E+03 50 Sr-92 1.36E+02 5.01E+12 4.06E+01 1.50E+06 51 Tc-99 1.41E-01 5.23E+09 4.24E-02 1.57E+03 52 Y-90 1.13E-01 4.19E+09 3.39E-02 1.25E+03 53 Zn-65 3.49E+02 1.29E+13 1.05E+02 3.87E+06 54 Buildup: The material reference is Source 55 Integration Parameters 56 Radial 30 57 Circumferential 30 58 Y Direction (axial) 60 59 Results 60 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 61 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 62 No Buildup With Buildup No Buildup With Buildup 63 0.015 5.18E+08 6.58E-01 7.66E-01 5.65E-02 6.57E-02 64 0.02 2.54E+09 9.30E+00 1.28E+01 3.22E-01 4.45E-01 65 0.03 2.39E+11 2.88E+03 6.40E+03 2.85E+01 6.34E+01 66 0.04 5.24E+10 1.16E+03 4.14E+03 5.14E+00 1.83E+01 Calc. No. PM-750, Rev. 1, Attachment B, Page B-2 of B-7

A B C D E F G H I 67 0.05 3.38E+03 1.09E-04 5.49E-04 2.91E-07 1.46E-06 68 0.06 3.70E+06 1.56E-01 9.57E-01 3.10E-04 1.90E-03 69 0.08 9.83E+09 6.11E+02 4.21E+03 9.66E-01 6.67E+00 70 0.1 5.88E+07 4.87E+00 3.23E+01 7.45E-03 4.94E-02 71 0.15 1.66E+08 2.31E+01 1.27E+02 3.80E-02 2.09E-01 72 0.2 1.51E+11 3.07E+04 1.45E+05 5.42E+01 2.55E+02 73 0.3 4.64E+10 1.63E+04 5.99E+04 3.09E+01 1.14E+02 74 0.4 4.81E+11 2.51E+05 8.00E+05 4.88E+02 1.56E+03 75 0.5 6.06E+11 4.32E+05 1.24E+06 8.47E+02 2.44E+03 76 0.6 6.93E+12 6.39E+06 1.71E+07 1.25E+04 3.33E+04 77 0.8 4.20E+12 5.86E+06 1.40E+07 1.11E+04 2.66E+04 78 1 1.45E+13 2.81E+07 6.20E+07 5.17E+04 1.14E+05 79 1.5 1.22E+13 4.30E+07 8.37E+07 7.24E+04 1.41E+05 80 2 1.52E+08 8.28E+02 1.49E+03 1.28E+00 2.31E+00 81 3 2.69E+05 2.68E+00 4.36E+00 3.63E-03 5.92E-03 82 Totals 3.94E+13 8.41E+07 1.79E+08 1.49E+05 3.20E+05 Calc. No. PM-750, Rev. 1, Attachment B, Page B-3 of B-7

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4 5 Filename Run Date Run Time Duration 6 PeachBottomFinal.msd 12-Aug-09 4:42:53 PM 0:00:05 7 Project Info 8 Case Title PM-750 Table 1 source term adjustment to 400 R/hr, and 9 Description resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Standard Indices 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Excluded 26 Library: ICRP-38 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ag-110m 7.67E+00 2.84E+11 2.30E+00 8.50E+04 29 Am-241 3.50E-04 1.29E+07 1.05E-04 3.88E+00 30 Ba-137m 1.11E+02 4.12E+12 3.34E+01 1.24E+06 31 C-14 1.14E-02 4.20E+08 3.41E-03 1.26E+02 32 Cm-242 4.19E-03 1.55E+08 1.26E-03 4.64E+01 33 Cm-244 3.76E-04 1.39E+07 1.13E-04 4.17E+00 34 Co-58 1.92E+01 7.09E+11 5.75E+00 2.13E+05 35 Co-60 2.52E+02 9.34E+12 7.57E+01 2.80E+06 36 Cr-51 7.08E+00 2.62E+11 2.12E+00 7.86E+04 37 Cs-134 1.02E+02 3.76E+12 3.05E+01 1.13E+06 38 Cs-137 1.18E+02 4.36E+12 3.53E+01 1.31E+06 39 Fe-55 2.27E+01 8.40E+11 6.81E+00 2.52E+05 40 H-3 4.80E-03 1.77E+08 1.44E-03 5.32E+01 41 I-129 1.65E-04 6.10E+06 4.94E-05 1.83E+00 42 I-131 1.27E+01 4.69E+11 3.80E+00 1.40E+05 43 Mn-54 1.25E+01 4.61E+11 3.73E+00 1.38E+05 44 Nb-95 4.29E+00 1.59E+11 1.29E+00 4.76E+04 45 Ni-63 2.02E+00 7.46E+10 6.05E-01 2.24E+04 46 Pu-238 1.11E-03 4.12E+07 3.34E-04 1.23E+01 47 Pu-239 5.30E-04 1.96E+07 1.59E-04 5.88E+00 48 Pu-241 1.06E-01 3.92E+09 3.18E-02 1.18E+03 49 Sr-90 1.41E-01 5.23E+09 4.24E-02 1.57E+03 50 Sr-92 1.69E+02 6.26E+12 5.07E+01 1.88E+06 51 Tc-99 1.77E-01 6.54E+09 5.29E-02 1.96E+03 52 Y-90 1.41E-01 5.23E+09 4.24E-02 1.57E+03 53 Zn-65 4.36E+02 1.61E+13 1.31E+02 4.83E+06 54 Buildup: The material reference is Source 55 Integration Parameters 56 Radial 30 57 Circumferential 30 58 Y Direction (axial) 60 59 Results 60 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 61 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 62 No Buildup With Buildup No Buildup With Buildup 63 0.015 6.97E+12 8.85E+03 1.03E+04 7.59E+02 8.84E+02 64 0.02 3.18E+09 1.16E+01 1.60E+01 4.03E-01 5.55E-01 65 0.03 2.99E+11 3.60E+03 7.99E+03 3.56E+01 7.92E+01 Calc. No. PM-750, Rev. 1, Attachment B, Page B-4 of B-7

A B C D E F G H I 66 0.04 6.54E+10 1.45E+03 5.17E+03 6.42E+00 2.29E+01 67 0.05 4.22E+03 1.36E-04 6.86E-04 3.63E-07 1.83E-06 68 0.06 4.63E+06 1.95E-01 1.20E+00 3.88E-04 2.38E-03 69 0.08 1.23E+10 7.63E+02 5.26E+03 1.21E+00 8.33E+00 70 0.1 7.34E+07 6.08E+00 4.03E+01 9.30E-03 6.16E-02 71 0.15 2.07E+08 2.89E+01 1.58E+02 4.75E-02 2.61E-01 72 0.2 1.89E+11 3.83E+04 1.81E+05 6.76E+01 3.19E+02 73 0.3 5.80E+10 2.03E+04 7.48E+04 3.85E+01 1.42E+02 74 0.4 6.01E+11 3.13E+05 9.99E+05 6.10E+02 1.95E+03 75 0.5 7.57E+11 5.39E+05 1.55E+06 1.06E+03 3.05E+03 76 0.6 8.66E+12 7.99E+06 2.13E+07 1.56E+04 4.16E+04 77 0.8 5.24E+12 7.32E+06 1.74E+07 1.39E+04 3.32E+04 78 1 1.81E+13 3.51E+07 7.75E+07 6.46E+04 1.43E+05 79 1.5 1.52E+13 5.37E+07 1.05E+08 9.04E+04 1.76E+05 80 2 1.90E+08 1.03E+03 1.87E+03 1.60E+00 2.88E+00 81 3 3.36E+05 3.34E+00 5.45E+00 4.53E-03 7.40E-03 82 Totals 5.62E+13 1.05E+08 2.24E+08 1.87E+05 4.00E+05 Calc. No. PM-750, Rev. 1, Attachment B, Page B-5 of B-7

A B C D E F G H 1 Container Drop Event: Peach Bottom Isotopic: Table 1, PM-750 2 9.200E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 3.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 4.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 7.358E-01 Total Inhalation Dose 10 11 Isotope Ci in container InhaleDCF Dose (rem) 12 Ag-110m 7.67E+00 2.170E-08 5.947E-03 1% 13 Am-241 3.50E-04 1.200E-04 1.500E-03 0% 14 Ba-137m 1.11E+02 0.00E+00 0.000E+00 0% 15 C-14 1.14E-02 5.640E-10 2.291E-07 0% 16 Cm-242 4.19E-03 4.670E-06 6.990E-04 0% 17 Cm-244 3.76E-04 6.700E-05 9.008E-04 0% 18 Co-58 1.92E+01 2.940E-09 2.014E-03 0% 19 Co-60 2.52E+02 5.910E-08 5.333E-01 72% 20 Cr-51 7.08E+00 9.030E-11 2.286E-05 0% 21 Cs-134 1.02E+02 1.250E-08 4.546E-02 6% 22 Cs-137 1.18E+02 8.630E-09 3.632E-02 5% 23 Fe-55 2.27E+01 7.260E-10 5.893E-04 0% 24 H-3 4.80E-03 1.730E-11 2.966E-09 0% 25 I-129 1.65E-04 4.690E-08 2.763E-07 0% 26 I-131 1.27E+01 8.890E-09 4.025E-03 1% 27 Mn-54 1.25E+01 1.810E-09 8.060E-04 0% 28 Nb-95 4.29E+00 1.570E-09 2.408E-04 0% 29 Ni-63 2.02E+00 1.700E-09 1.225E-04 0% 30 Pu-238 1.11E-03 1.060E-04 4.215E-03 1% 31 Pu-239 5.30E-04 1.160E-04 2.198E-03 0% 32 Pu-241 1.06E-01 2.230E-06 8.446E-03 1% 33 Sr-90 1.41E-01 3.510E-07 1.773E-03 0% 34 Sr-92 1.69E+02 2.180E-10 1.319E-03 0% 35 Tc-99 1.77E-01 2.250E-09 1.420E-05 0% 36 Y-90 1.41E-01 2.280E-09 1.151E-05 0% 37 Zn-65 4.36E+02 5.510E-09 8.584E-02 12% 38 39 40 Total Rem 7.358E-01 Calc. No. PM-750, Rev. 1, Attachment B, Page B-6 of B-7

A B C D E F G H 1 Container Drop Event: Clinton Isotopic: Table 12.2-12 2 0.00092 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.03 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr 8 9 =F40 Total Inhalation Dose 10 11 Isotope Ci in container InhaleDCF Dose (rem) 12 =PeachBottomFinal!A28 =PeachBottomFinal!E28 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*D12*E12 =F12/$F$40 13 =PeachBottomFinal!A29 =PeachBottomFinal!E29 0.00012 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 =F13/$F$40 14 =PeachBottomFinal!A30 =PeachBottomFinal!E30 0 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 =F14/$F$40 15 =PeachBottomFinal!A31 =PeachBottomFinal!E31 0.000000000564 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 =F15/$F$40 16 =PeachBottomFinal!A32 =PeachBottomFinal!E32 0.00000467 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 =F16/$F$40 17 =PeachBottomFinal!A33 =PeachBottomFinal!E33 0.000067 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 =F17/$F$40 18 =PeachBottomFinal!A34 =PeachBottomFinal!E34 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 =F18/$F$40 19 =PeachBottomFinal!A35 =PeachBottomFinal!E35 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 =F19/$F$40 20 =PeachBottomFinal!A36 =PeachBottomFinal!E36 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 =F20/$F$40 21 =PeachBottomFinal!A37 =PeachBottomFinal!E37 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 =F21/$F$40 22 =PeachBottomFinal!A38 =PeachBottomFinal!E38 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 =F22/$F$40 23 =PeachBottomFinal!A39 =PeachBottomFinal!E39 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 =F23/$F$40 24 =PeachBottomFinal!A40 =PeachBottomFinal!E40 0.0000000000173 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 =F24/$F$40 25 =PeachBottomFinal!A41 =PeachBottomFinal!E41 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 =F25/$F$40 26 =PeachBottomFinal!A42 =PeachBottomFinal!E42 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 =F26/$F$40 27 =PeachBottomFinal!A43 =PeachBottomFinal!E43 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 =F27/$F$40 28 =PeachBottomFinal!A44 =PeachBottomFinal!E44 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 =F28/$F$40 29 =PeachBottomFinal!A45 =PeachBottomFinal!E45 0.0000000017 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 =F29/$F$40 30 =PeachBottomFinal!A46 =PeachBottomFinal!E46 0.000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 =F30/$F$40 31 =PeachBottomFinal!A47 =PeachBottomFinal!E47 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 =F31/$F$40 32 =PeachBottomFinal!A48 =PeachBottomFinal!E48 0.00000223 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 =F32/$F$40 33 =PeachBottomFinal!A49 =PeachBottomFinal!E49 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 =F33/$F$40 34 =PeachBottomFinal!A50 =PeachBottomFinal!E50 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 =F34/$F$40 35 =PeachBottomFinal!A51 =PeachBottomFinal!E51 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 =F35/$F$40 36 =PeachBottomFinal!A52 =PeachBottomFinal!E52 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 =F36/$F$40 37 =PeachBottomFinal!A53 =PeachBottomFinal!E53 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 =F37/$F$40 38 39 40 Total Rem =SUM(F12:F37) Calc. No. PM-750, Rev. 1, Attachment B, Page B-7 of B-7

iIl- IS~I 1. Calculation No. Y 1'1 ... 7 5</J

                                                                ~P  . " S£RVIC E Page 1 of       63
                                                                    ~

NUCLEAR ENGINEERING CALCULATION COVER SHEET GROUP 2. 0 LGS UNIT(S) ..:L(3 M-20599 Re~ 4/92 Q-' PBAPS / DQCTYPE 061

3. Initiating Document: '1-31 4. Responsi,ble B~an~h: , , S s R- R.... 15. Total Nl; ~f Sheets: 16. La~~:eet No: 1 7. o Safety Related

                                                                                       -rSD P_o:l                                                                                                       ~ Non-Safetv Related
                                                                                                                                                                                                                                  ~l!J

9. System/Topic No.:

8.

Description:

      -ro EVa Ic),j: ..}!....- I&Jl'olc 3, J Q;n~.I"ta41 << w'OrfTCd.!L                                                ~ ~OG-               '#-" -'I' Structure: low lei/,j ~wr~l,rf& r... fll J

Cct'l1;;;l1u !fCt!.Ij,n+tn VoI,/lif -It- Drf,/I/J Ln,r ~11i.1""112 v{/ctl f.$,A ') Component: /VI/I RECORD OF REVISIONS

12. Vendor Calc. 13. Other Calcs 14. Sionatures

10. No. 11. Description of Revision Number Rev. Requiring Revision Preparer Reviewer Approver / Date

                                                          .¢                          DM'!JJ1U)                                              NIh            0       A/ol').e          .~~ p~.~ 1~'f_~~~~O/9:J-
                                                                                                                                                                                                .RR-   II ~ q'Z.

15. Provides Info to: 16.

Related Calc. Number! Receives Info from:

                                                                                                                                                                                                           ~anual Calc. No. PM-750, Rev. 1, Attachment C, Page C-1 of C-52 Computer Computer program and version Supersedes:                                                                                                                          SPe~lfo          &11: ,ol,.z..

FORM 5610 REV 4/91 United Engineers CALCULATION SET NO. lleonstruct... CALCULATION

SUMMARY

                                                                                                                                                                           ~f\Il-750 A IIayIIIe-. Company                                                                       & CONTROL SHEET                                                                                                                                              PRELIM.                             FINAL                          VOID             REVISION Page 1 9f 2                                                                                                                                                                        .,/                                              o DISCIPLINE PECO PBAPS - Units 2 & 3 PROJECT TITLE                                                          I OW I eve! R adwaste Storage Faci1ity                                                                                                                                  J.O.                      '71 1" "Sl'7 LLRWSF                                                                                                                                                                         Non-Safety Related STRUCTURE OF SYSTEM                                                                                                                _                  DESIGN CLASSIFICATION SUBJECT                                Container Drop Accident Analysis COMPLETED BY                                       ~ ~                                                                                                                                                                           DATE CHECKEDBY                                        PJ ~                                                                   Pf-tkf R~,Jd::                                                                                            DATE B~d tf j u1IJJ I

APPROVED L

• e. S c:: d 7l DATE /o/:J.-¥9 L-SDE OR MGR OF STAFF GROUP 7 REASON FOR REVISION:

                                                  . ww'ORIOINALCALCULJ\TION*****

SHEETS REVISED, ADDED OR DELETED o PROBLEM STATEMENT:

                       . . ~. . TO"'eviiliiiife"ffie'radiologi"caIconseqiiencesofii'worsf'case**contiiinec**liaridIing**iicci"denf*invo[viiig*ffie***diop****
                  . "'ofatinercontainingRWCUresin:'                                                           W                                                                     ** *****                   ***       * ' **      w.ww'                                                                                                 . . w.w.

SUMMARY

/CONCLUSIONS:

                                            ... m.*.*.*.~ w * * * *'.' ".w *.Wr_W....        * ** "<"CoW" ** ,' W~.' **--.'w_*....          *..*
                                                                                                                                    *.-.w_~_._   -.-.-~,  *.*.*m.*....*** h . W

• _ow* ** '.*.*.*.w_* '.-.*~*_*_* ...*-~w ***'.' 'un* *..'., .. . ', . ..-....*..' 'r_',** .. ,'.**.,~* 'W.. ** ** M
• n * ***'" *** .w, *,~* w.,~*.

The accident analyzed involves a drop of a RWCU liner, assumed to contain activity at a level that is the highest"observed*ovec*the**IasHive**years:*Jiom*fuemaxlmum*credi6Ie'heighi:'***w., , , *.*****.,****_w****, . . . .***.w** ..*.. - *****:Airborne**releaseswfrom***the*rupture(l*containerare*conservativelywmodelled,wbasedwoft'8wformula.for..

                            . . . unconfmedpowderspills,.takenformNUREG",.132Q.. (ReL..2)+.No.. creditis.taken.for.. settling.ofparticulate .
                                . . i.!!t:h,~ !?!1i!<:li!!g~._ ..r~A!'~._<l~§.ig!! . !?,<l:§i.§ '!£<:!<:l~!!t.K:/Q§ C!!.~.!1~~ . !Q ~.~.ti!l!a.:!~ 4Q~. ~ ~~.!~w~!Jh~,.g~~.~ ~Qt:h .

external doses (cloud shine) and internal dose rates (from inhalation) are calculated. The resulting doses are:

            * . *.w* * . *.w*** *******.w***..*. **Ww**.....w*..External**Dose                                                                               m  **.***     w.**_,O;OO§6**fem,,***, **.S.~ . pag~.14 ..fQ!:.thymig.
                                              ........w..w w.~.....w "                 lnternal..Dose w ~, ,.,                                                     ~ , Q*.1069.. rem._, w~2.~~.~~.~~~~!!1~l!.!:.._

• m Total 0.1125 rem Calc. No. PM-750, Rev. 1, Attachment C, Page C-2 of C-52

FORM 5610 REV 4/91 CALCULATION SET NO. CALCULATION

SUMMARY

fM-750

                                                                                                                                                                                      & CONTROL SHEET                                                                                                                                      PRELIM.                FINAL                  VOID                 REVISION Pa@c 2 of ~                                                                                                                                                        ."...                                        o PECO PBAPS - Units 2 & 3                                                                                                                                                                                          DISCIPLINE                           N&Jcl~d/'

PROJECT TITLE Low Level Radwaste Storage Facility J.O 7112.287 DESIGN BASIS: __._---- ........................**_....._-- __---

                                                -'1. Desig"ilbasTsconialn'er IsotoplCConieiit'is based onworst'ohserved RWctr'c"esm from "records-"'-
 '--'-'---'deSCfioeatI1R'er.l-:--"' ............-..                                                                                                                                                                               .                               ----.-                                                                                                                  _.                 N . ._                ..
 . . . . . . . . ._            ..                                                      N                                       _          _.                          _

_.._2_Airborne release..bas.ed..olLNUREG.~.1320_Methodolog)dOLpo.wder-spills _._ _ *************..*._ *_ *.W.*,W N *

3. Accident ground level X/Qs for PBAPS at the LLRWSF location derived from Ref. 4.

~----4': *******Ca!cul"tewdoseslllust***be***less*thatr*l()-FR*****!*Oo-limits-of*25***rem***whole'"body-at***the**EAB:-.- -

....                                                                                                _ _._ __                                                                             *---_00-                                                        ____                                                                                                                                                                  _0.
..............       _                             .._                                             ~     _--                                      ......................................._..._ ._ _..                                  ......*........*         0_*                                      ..........*..*......*..*..*....****                         ...*..*        - - - _ _-                          ..

UNVERIFIED ASSUMPTIONS/OPEN ITEMS: _.. _--_." _---- ................................ ~NON'E - - _. .................. _......_- ......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ ._ _N _ _. _ _ _ _ _ _ _ - _**** -

REFERENCES:

(SPECIFICATIONS, DRAWINGS, CODES, CALCULATIONS, TEXTS, REPORTS, COMPUTER DATA, FSAR, ETC.)

                    ...................... _._._                                                                    SEE..FAGE.19 FORblST-GFALL REFE.RENCES                                                                                                                                                                    *.*.~     __W~*_ ..M                 *         *.. ww               _                          _    ...
                                                                                                                                                                                                                                                                                                                                                ~ *... _ " " ' , . =                      ~_           _~_
                                                                                                  ..............................._ =    ~,~. _ _"                    ,.,     ,.,                     ~ ~_ _~"                                                          ~.~-... ""~~,"~                            ,                                                                                                        **<.w.'.w'"
                                                                                  ........... w~                                        .~                                       _w.~_               _                                                                                                          ~-_.                                                 _-_.~-_                                   " _.            _--

1---- -.--- .................. __ .._~- ......................._-- ~----- -----_ _---_ .

                ...........................                       _                       _-                       -           _         ~-

_ _ _ _ _ _*_ _......_ _0.*..._ _ ....._ 0 0 _....._ _

                                                                                                                                                              .......................,......_-                                                                                               ................ __..      ~--_                 . __ _-_                                           ~              _--_ ...

Calc. No. PM-750, Rev. 1, Attachment C, Page C-3 of C-52

FORM 5007 REV 4/91 CALCULATION SET NO. REV. COMPo BY CHK'D. BY GENERAL COMPUTATION PM-1S0 .M6-- P11A: A~Company SHEET a Jo/:;h~ PRELIM. FINAL VOID DATE Ie 1;z.~/9z.. PROJECT PECO PBAPS - Units 2 & 3 Low Level Radwaste Storage Facility

                                                                             /

SHEET 5 OF 53 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112.287 INTRODUCTION & PURPOSE The design basis (worst case) accident for the LLRWSF has been selected by PECO as a container drop during handling. The container is assumed to hold the maximum amount of activity observed, over the last five years, in an RWCU resin liner. The container is assumed to drop from the maximum crane lift height to the floor in an empty storage cell. A very conservative set of assumptions is used to establish the amount of activity which becomes airborne and leaves the LLRWSF. Accident meteorological assumptions are those previously established for PBAPS design basis accidents. The purpose of this calculation is to provide assurance that calculated doses from this accident are well within 10 CFR 100 limits at the Exclusion Area Boundary. Since this accident is modeled as a puff release, doses at the LPZ would be significantly lower. Utilization of this calculation by persons without access to the pertinent factors and without proper regard for its purpose could lead to erroneous conclusions. Should it become desirable to use this calculation to support design or station activities other than those explicitly specified in this section, the responsible engineering branch (as noted in block 4 of the cover sheet) shall be contacted to ensure that the purposes, assumptions, judgments, and limitations are thoroughly understood. Calc. No. PM-750, Rev. 1, Attachment C, Page C-4 of C-52

FORM 5007 REV 4/91 UniIed. . . . .ers GENERAL CALCULATION SET NO. REV. COMPo BY CHK'D BY II ConsInICIm's COMPUTATION f'JVJ- 750 ,-,6- ~ A~~ny 0 SHEET PRELIM. FINAL VOID DATE

                                                                                                                }.;AT~

IO/IJI/~z J,..~ 1-7/1'1-PECO PBAPS - Units 2 & 3 / PROJECT Low Level Radwaste Storage Facility SHEET 6 OF 53 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 711' ,,)Q'7 ASSUMPTIONS TABLE 1 shows the conservatively selected isotopic mix. This mix is a composite of two historical containers. The first container's contents are from the worst case container handled over the last 5 years, for whole body dose purposes. 1-131 content was taken from the worst case container for thyroid dose purposes. The methodology for airborne release is based on guidance from NUREG-1320 (Ref. 2) for unconfined powder spills. NUREG-1320 provides algorithms based on empirical data. Airborne material from powder spills occurs because of shear forces as the material falls, and on rebound as the material hits the floor. In the dropped container case, no shear contributions would be expected since the material remains in the container during the fall. Additionally, the dewatered resin is of a consistency of wet sand, so a dry powder assumption is considered conservative for rebound purposes. Also the ruptured container is still likely to limit particulate rebound to a significant extent. No credit is taken for this phenomenon. The airborne activity is conservatively assumed to be instantly mixed in the LLRW free air space above the storage area; and to be instantly released. This analysis is done without taking any credit for (1) gravitational settling before exhaust from the LLRWSF; (2) building ventilation system shutoff; and (3) plateout which would be expected as some fraction of the material comes in contact with available surfaces. The safety related UE&C computer code SPECISO (Ref. 3) is used to convert isotopic data into the source terms in units of Mev/dis.Ci. Data from PECO (Ref. 4) for X/Q is used to generate the X/Q at the distance from the LLRWSF to the EAB (see attachment A-2). The dose conversion factors for calculating the inhalation total body dose are taken from Reg Guide 1.109 (Ref. 5). Calc. No. PM-750, Rev. 1, Attachment C, Page C-5 of C-52

FORM 5007 REV 4/91 CALCULATION SET NO. REV. COMPo BY CHK'D BY GENERAL COMPUTATION f'M-7~() A """"'Company SHEET PRELIM. FINAL VOID o PECO PBAPS - Units 2 & 3 ,/ PROJECT Low Level Radwaste Storage Facility SHEET 7 OF ~3 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112 287 TABLE 1 DESIGN BASIS RWCU RESIN# (Ref. 1) Nuclide mCi/Liner uCi/cc Cr-51 4239.8 1.700E+00 Mn-54 7443.1 2.990E+00 Co-58 11453.1 4.600E+00 Zn-65 260746.3 1.046E+02 Sr-92 101226.5 4.062E+01 Nb-95 2564.3 1.030E+00 Ag-110m 4590 1.840E+00 Cs-134 60869.7 2.442E+01 Fe-55 13589.9 5.450E+00 Co-60 150998.6 6.0S9E+01 Cs-137 70422.9 2.826E+01 Sr-90 84.507 3.391E-02 Ni-63 1208 4.847E-01 H-3 2.87 l.151E-03 C-14 6.79 2.727E-03 I-129 0.099 3.956E-OS Tc-99 105.634 4.239E-02 Cm-242 2.5 1.005E-03 Pu-241 63.4 2.543E-02 Pu-238 0.665 2.670E-04 Pu-239 0.317 l.272E-04 Am-241 0.209 8.393E-05 Cm-244 0.225 9.028E-05 I-131 7320 3.040E+00 All isotopes except I-131 taken from Attachment A-I, page 21 of this calculation. This container had the overall activity observed over the 1987-1991 period. The I-131 value was selected to maximize thyroid doses and is from a different RWCU container (Attachment A-I, page 41). Calc. No. PM-750, Rev. 1, Attachment C, Page C-6 of C-52

FORM 5007 REV 4/91 United~ CALCULATION SET NO REV. COMPo BY CHK'D BY GENERAL A..,...... IlConstruCtors Company COMPUTATION PM-750 0

                                                                                                 ~t:-         PrJ(

PECO PBAPS - Units 2 ~!ET PRELIM FINAL VOID DATE

                                                                             ,/                  Ipl;l.~)}1- lbb;h2--

PROJECT Low Level Radwaste Storage Facility SHEET r' OF 53 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112.287 AIRBORNE RELEASE NUREG-1320(Ref. 2) provides an equation for calculating the airborne release from powder spills which are a function of mass spilled, spill height and spill density. Fraction airborne = 1 x 10-8 X H21 Pp (Ref.2, page 4.71) Where H = Spill height, cm Pp = Powder density g/cm 3 H = 170'-9" - (118) - (6) = 46'-9" = 1424.94 cm Where 170'-9" is the elevation of the hook, 118' is floor elevation and 6' is a nominal length of the liner. Hook and floor elevations are taken from Ref. 6. Since Ref. 1 does not provide resin density for this particular shipment, this density is determined by taking the average of 5 other waste shipments, See Table 2. The resulting density is: Pp = 0.69 g/cc Therefore, fraction airborne = lxlO- 8 x (1424.94)2 1(6.9E-Ol) = 0.0294 TABLE 3 shows the total Ci. released from dropped liner. Calc. No. PM-750, Rev. 1, Attachment C, Page C-7 of C-52

FORM 5007 REV 4191 United. . . . .ers GENERAL CALCULATION SET NO. REV. COMPo BY CHK'D BY

 .. ConstruCtors                                                    I' /11-750 A~Company COMPUTATION                                                      ."'7 G...
                                                                                                          ~

SHEET PRELIM. FINAL VOID 0 jL,t~h')/ DATE 1~/d~iI-- PECO PBAPS - units 2 & 3 PROJECT Low Level Radwaste Storage Facility SHEET

                                                                      ,  V OF 53              DATE        DATE SUBJECT container Drop Accident Analysis                   J.O. 7112      287 TABLE 2 EVALUATION OF AVERAGE DENSITY FOR RWCU LINERS SHIPMENT NUMBERS 90-0001  90-0002 90-0003 91-0001           91-0002       87-0001 87-0001           Average
                     ******** ******** ******** ******** ********                 #1       #2        ********

VOLUME (cc) 2.55E+06 2. 69E+06 2 .12E+06 2. 83E+06 2. 41E+06 3. 06E+06 2. 49E+06 2. 59E+06 WEIGHT (gm) 2.35E+06 1.57E+06 1.48E+06 2.00E+06 1.55E+06 not available 1.79E+06 DENSITY(g/cc) 9.20E-01 5.84E-01 6.95E-01 7.07E-01 6.43E-01 not available 6.90E-01 Calc. No. PM-750, Rev. 1, Attachment C, Page C-8 of C-52

FORM 5007 REV 4/91 United. . . .ers GENERAL CALCULATION SET NO. REV. COMPo BY CHK'D BY

 ..COnsInICtors A """"'Company COMPUTATION                             pM-1fo                  ,.., (,-   ifR SHEET PECO PBAPS - Units 2 & 3 PRELIM. FINAL

/

VOID 0 DATE

                                                                                               ;"I,d~L     l/TX, iiI n   1'L PROJECT Low Level Radwaste Storage Facility SHEET    10    OF  5.~

DATE DATE SUBJECT Container Drop Accident Analysis J.G 7112 287 TABLE 3 RWCU RESIN RELEASED IN DESIGN BASIS CONTAINER DROP Nuclide mCi/Liner uCi/cc TOTAL RELEASED(Ci) Cr-5l 4239.8 1. 700E+00 1.25E-Ol Mn-54 7443.1 2.990E+00 2.19E-Ol Co-58 11453.1 4.600E+00 3.37E-Ol Zn-65 260746.3 1.046E+02 7.67E+00 Sr-92 101226.5 4.062E+Ol 2.98E+00 Nb-95 2564.3 1.030E+00 7.55E-02 Ag-110m 4590 1.840E+00 1.35E-Ol Cs-134 60869.7 2.442E+Ol 1.79E+00 Fe-55 13589.9 5.450E+00 4.00E-Ol Co-60 150998.6 6.059E+Ol 4.44E+00 Cs-137 70422.9 2.826E+Ol 2.07E+00 Sr-90 84.507 3.391E-02 2.49E-03 Ni-63 1208 4.847E-Ol 3.55E-02 H-3 2.87 1.15lE-03 8.45E-05 C-14 6.79 2.727E-03 2.00E-04 I-129 0.099 3.956E-05 2.91E-06 Tc-99 105.634 4.239E-02 3.11E-03 Cm-242 2.5 1.005E-03 7.36E-05 Pu-241 63.4 2.543E-02 1.87E-03 Pu-238 0.665 2.670E-04 1.96E-05 Pu-239 0.317 1. 272E-04 9.33E-06 Arn-241 0.209 8.393E-05 6.15E-06 Cm-244 0.225 9.028E-05 6.62E-06 I-131 7320 3.040E+00 2.15E-Ol TOTAL 2.05E+Ol Calc. No. PM-750, Rev. 1, Attachment C, Page C-9 of C-52

FORM 5007 REV 4/91 Uniled~ CALCULATION SET NO. REV. COMPo BY CHK'D. BY

 .. ConstrUCtors                        GENERAL A . . . . . . . Company              COMPUTATION                         fM-750                        /1/6-     MtJ<..

0 PECO PBAPS - Units 2 & 3 SHEET PRELIM. FI/ VOID DATE ID/H'h1; Jbh;Jqv

                                                                                                                  .  ~

PROJECT Low Level Radwaste Storage Facility SHEET II OF 53 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112.287 EXTERNAL WHOLE BODY DOSES External whole body doses should be calculated using a semi-infinite cloud model, the gamma dose rate in air is: D,: = 0.25 E-" X (Ref. 7 , page 1.3-2) Where D,,' = gamma dose rate from an infinite cloud (rem/sec) E"y = average gamma energy per disintegration (Mev/dis) X = concentration of gamma emitting isotope in the cloud(curie/m3) This equation can be written as: D y = 0.25 x X/Q x Ei (E-"i XCi) Where D" = gamma dose from an infinite cloud (rem) E"yi = average gamma energy per disintegration per isotope i Ci = curie released of isotope i of the liner X/Q = atmospheric dispersion parameter used for the determination of the ground-level concentration ( sec/m 3 ). See derivation below under" Accident X/Q Value". Computer code SPECISO is used to generate the average gamma energy per disintegration. TABLE 4 shows the use of SPECISO output to generate E-"i for each isotope. Also TABLE 5 shows the result. Calc. No. PM-750, Rev. 1, Attachment C, Page C-10 of C-52

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                                                           ************************************ SPECISO OUTPUT (MEV/CI/SEC) *************************************   TOTAL                                                       a.

t;c gam. enrgy. 2.00E-Ol 4.00E-Ol 9.00E-Ol 1.35E+OO I.BOE+OO 2.20E+OO 2.60E+OO 3.00E+OO 4.00E+OO 5.00E+OO Mev/Sec-Ci Mev/dis* r III  ::s rad ionucl ide C/l .... ()

                                                                                                                                                                                                               ~                t"t't"t' 1    3 o O.OOE+OO   O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO    O.OOE+OO                     lDC/l 0 G) 6 14 o O.OOE+OO      O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO    O.OOE+OO    ~

tIlN (/)~m 24 51 o 4.14E+07 1.16E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.20E+09 3.25E-02 ~ 25 54 o 5.09E+07 O.OOE+OO 3.09E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.10E+10 8.37E-Ol b2> ICZ

                                                                                                                                                                                                               ~                tot                m-i m 26 55 o 6.14E+07      O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   6.14E+07    1. 66E-03                   lllW                m>>::D 27 58 o 6.30E+07      O.OOE+OO    3.57E+10   O.OOE+OO   3.20E+08   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   3.61E+10    9.75E-Ol                    10                  -i-i>>

27 60 o O.OOE+OO O.OOE+OO 3.32E+06 9.26E+l0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9. 26E+1O 2.50E+OO ~ (1) -r 28 63 o O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ~ I2j 0 30 65 o 1. 17E+08 O.OOE+OO 5.37E+08 2.09E+l0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.16E+10 5.83E-Ol III Z 0 38 90 o O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ~ [Il 41 95 o O.OOE+OO O.OOE+OO 2.83E+l0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.83E+l0 7.65E-Ol .... 43 99 o O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO rt 47 110 1 6.17E+06 1.43E+07 6.70E+l0 1.20E+l0 2.29E+l0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+ll 2.75E+00 '< 53 129 o 9. 15E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9. 15E+08 2.47E-02 53 131 o 1.49E+08 1. 16E+l0 2.31E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+l0 3.80E-Ol 53 133 o 7.08E+06 1.30E+08 2.02E+10 2.10E+09 6.98E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.25E+l0 6.08E-Ol 55 134 o 9.32E+06 3.63E+06 5.48E+10 1.16E+09 1.54E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.75E+1O 1.55E+00 '-- 00 I "U 55 137 o O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0 m II m

                                                                                                                                                                                                                                                   ,.-           0 56 137 1 9.03E+07     O.OOE+OO    2.20E+l0   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   2.21E+l0    5.97E-Ol               ~                                      ,l>

56 140 o 5.57E+08 3.86E+08 4.60E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5. 54E+09 1.50E-0l §:-o

                                                                                                                                                                                                               ~                                                 0 57 140 o 6.02E+07     2.35E+09    1.79E+10   3.53E+09   5.64E+l0   O.OOE+OO   4.06E+09   O.OOE+OO   O.OOE+OO   O.OOE+OO   8.43E+l0    2.28E+OO                                                 ~    ,cl>

58 141 o 2.82E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+09 7.62E-02 ." I

                                                                                                                                                                                                               ~                                                 :::j
                                                                                                                                                                                                                          -P 94 238 o 5.92E+07     O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   5.92E+07    1.60E-03                                 ,,~                  0 94 239 o 2.42E+07     O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   2.42E+07    6. 54E-04              0                                      z 00 94 241 o O.OOE+OO     O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO   O.OOE+OO    O.OOE+OO
                                                                                                                                                                                                               ~
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                                                                                                                                                                                                                                                            ~    ~

95 241 o 9.73E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9. 73E+08 2.63E-02 z 96 242 o 6.19E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6. 19E+07 1.67E-03 < () 96 244 o 5.58E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.58E+07 1. 51E-03 ~ 0 a

• TOTAL (MEV/SEC/CI) / 3.7E+l0 (OIS/SEC/CI) II 0 m

                                                                                                                                                                                                                                              '"                 0 0                      ~o~                 0 l>                                         ;::
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Calc. No. PM-750, Rev. 1, Attachment C, Page C-11 of C-52 0 0 I l>

                                                                                                                                                                                                                      -l                                         "0 m

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                                                                                                                                                                                                                                        '~~

FORM 5007 REV 4/91 UnitedEngineers GENERAL CALCULATION SET NO. REV. COMPo BY CHK'D BY 1I0. . . . .tors COMPUTATION P"'-75,; ".,~ t(!< A IIIIyIIIeGIICompany SHEET PRELIM FINAL VOID 0 DATE PECO PBAPS - Units 2 & 3

                                                                             ,/'                 Ir-/t/ln..      'iJ 7 1t-It))ftAJh PROJECT Low Level Radwaste Storage Facility SHEET     '3    OF   53             DATE          DATE SUBJECT           Container Drop Accident Analysis             J.e. 7112 2B7 TABLE 5 EXTERNAL GAMMA DOSE external gamma Mev/dis      RELEASED (Ci)                dose RADIONUCLIDE                                                       (rem) 1      3 0 H3          O.OOE+OO         8.45E-05                 O.OOE+OO 6 14 0 C14             O.OOE+OO          2.00E-04                O.OOE+OO 24 51 0 CR51            3.25E-02         1. 25E-01                9.34E-07 25 54 0 MN54            8.37E-0l          2.19E-01                4.21E-05 26 55 0 FE55            1.66E-03          4.00E-01                1. 53E-07 27 58 0 C058            9.7SE-01          3.37E-01                7.56E-05 27 60 0 C060            2.50E+00          4.44E+00                2.56E-03 28 63 0 NI63            O.OOE+OO          3.55E-02                O.OOE+OO 30 65 0 ZN65            5.83E-01          7.67E+00                1.03E-03 38 90 0 SR90            O.OOE+OO          2.49E-03                O.OOE+OO 38 92 0 SR92            1.34E+00          2.98E+00                9.18E-04 41 95 0 NB95            7.65E-01          7.55E-02                1.33E-05 43 99 0 TC99            O.OOE+OO         3.11E-03                 O.OOE+OO 47 110 1 AG110M         2.75E+00          1. 35E-01               8.55E-OS 53 129 0 Il29           2.47E-02          2.91E-06                1. 66E-11 53 131 0 Il31           3.80E-01          2.15E-01                1.88E-05 53 133 0 Il33           6.08E-01          O.OOE+OO                O.OOE+OO 55 134 0 CS134          1.55E+00          1. 79E+00               6.40E-04 55 137 0 CS137          O.OOE+OO          2.07E+00                O.OOE+OO 56 137 1 BA137M         5.97E-01         1.96E+00                 2.69E-04 56 140 0 BA140          1. 50E-01         O.OOE+OO                O.OOE+OO 57 140 0 LA140          2.28E+00          O.OOE+OO                O.OOE+OO 58 141 0 CE141          7.62E-02          O.OOE+OO                O.OOE+OO 94 238 0 PU238          1.60E-03          1.96E-05                7.21E-12 94 239 0 PU239          6.54E-04         9.33E-06                 1.40E-12 94 241 0 PU241          O.OOE+OO          1.87E-03                O.OOE+OO 95 241 0 AM241          2.63E-02          6.15E-06                3. 72E-11 96 242 0 CM242          1.67E-03          7.36E-05                2.83E-11 96 244 0 CM244          1.5lE-03          6.62E-06                2.30E-12 2.22E+01                5.63E-03 Calc. No. PM-750, Rev. 1, Attachment C, Page C-12 of C-52

FORM 5007 REV 4/91 CALCULATION SET NO REV. COMPo BY CHK'D BY GENERAL pM-750 A~Company COMPUTATION ..;""'1'1{,- #J( 0 SHEET IJ~Jr~ PRELIM. FINAL VOID DATE PECO PBAPS - Units 2 & 3 V I~/.if/,).. PROJECT Low Level Radwaste Storage Facility SHEET I Lf- OF 53 DATE DATE SUBJECT Container Drop Accident Analysis J.O 7112.287 INTERNAL WHOLE BODY DOSE The internal whole body dose can be calculated as: Dt'Y = X/Q x B x E(C j x DFJ (from Ref. 5 [Reg. Guide 1.109]) Where Dt'Y = total body inhalation dose (rem) B = breathing rates 3.47E-04 m3/sec for time interval between 0 - 8 hrs (from Reference 7). X/Q = atmospheric dispersion parameter (from Ref. 4) used for the determination of the ground-level concentration ( sec/m3 ). See derivation below under" Accident X/Q Value". C j = quantity of isotope i released during the accident (curies) DF j = total body dose conversion factor for isotope i (rem/Ci) (from Reg Guide 1.109) TABLE 6 shows the internal whole body dose. THYROID DOSE The thyroid dose can be calculated using the above formula, substituting thyroid dose factors for DFi . Total iodine releases are taken based on the highest value observed over the last 5 years in any RWCU resin liner at PBAPS (See Attachment A-I). Table 6 shows the thyroid dose from iodines. This dose is then combined with thyroid dose contributions that are part of the whole body dose. The total thyroid dose is 0.215 rem, which is well below the 300 rem dose limit of 10 CFR 100. Calc. No. PM-750, Rev. 1, Attachment C, Page C-13 of C-52 -----J

FORM 5007 REV 4191 United~ GENERAL CALCULAnON SET NO. REV. COMPo BY CHK'D BY IlConstnIc.... ~t c;:.

                                                                                                              .1t~

A~Company COMPUTATION -71'0 SHEET PRELIM. FINAL VOID 0 DATE PECO PBAPS - Units 2 & 3 / IO/z.~L 10. " PROJECT Low Level Radwaste Storage Facility SHEET 15 OF 53 DATE DATE SUBJECT Coeta jeer Drop Ace i dent Ana] ys is J.O. .",., "$:1" TABLE 6 INTERNAL TOTAL BODY DOSE (INHALATION) Nuclide T.Body Dose Factor' T.Body Dose(rem) (mrem/pCi) Cr-51 1.25E-08 4.979E-07 Mn-54 7.87E-07 5.503E-05 Co-58 2.59E-07 2.787E-05 Zn-65 5.82E-06 1. 426E-02 Sr-92 3.64E-ll 3.461E-08 Nb-95 5.26E-07 1. 267E-05 Ag-llOm 7.43E-07 3.204E-05 Cs-134 9.1OE-05 5.204E-02 Fe-55 4.93E-07 6.294E-05 Co-60 1.85E-06 2.624E-03 Cs-137 5.35E-05 3.539E-02 Sr-90 7.62E-04 6.049E-04 Ni-63 1.81E-06 2.054E-05 H-3 1. 58E-07 4.260E-09 C-14 4.26E-07 2. 717E-08 I-129 6.91E-06 6.427E-09 I-131 2.56E-06 1. 757E-04 Tc-99 1.37E-04 1. 360E-04 Cm-242 7.50E-04 1. 761E-05 Pu-241 1.29E-03 7.683E-04 Pu-238 6.66E-02 4.161E-04 Pu-239 7.53E-02 2.242E-04 Am-241 6.47E-02 1. 270E-04 Cm-244 3.51E-02 7.419E-05 TOTAL 1.069E-Ol

                  , From  Reg Guide 1.109, Rev 1. if provided, otherwise, Rev. O.

THYROID THYROID TOTAL RELEASED DOSE FACTOR DOSE Nuclide mCi/Liner uCi/cc (Ci) (mrem/pCi)' (rem) I-129 0.099 3.96E-05 2.91E-06 0.00555 5.16E-06 I-131 7320 3.04E+00 2.15E-Ol 0.00149 1.02E-Ol TOTAL THYROID DOSE FROM IODINES 1.02E-Ol THYROID DOSE FROM IODINES PLUS EXTERNAL AND INTERNAL WHOLE BODY CONTRIBUTIONS 2.15E-Ol Calc. No. PM-750, Rev. 1, Attachment C, Page C-14 of C-52

FORM 5007 REV. 4/91 United~ CALCULATION SET NO. REV. COMPo BY CHK'D. BY GENERAL IlConstnICIm's COMPUTATION PM-750 ..-n~ P11\ A...,...... SH EET 0

                                                                                                            /uft-~JL-l/

Company PRELIM. FINAL VOID DATE PECO PBAPS - Units 2 &3 / Ibl;J/h~ PROJECT Low Level Radwaste Storage Facility SHEET 1-"< OF S~ DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112.287 ACCIDENT X/O VALUE The two-hour accident X/Q values for the ground-level release are taken from attachment A-2, TABLE 1. (This attachment is Ref. 4.) Then the two-hour accident X/Q values are plotted as a function of distance to allow interpolation for the distance of 442 meters( distance from the LLRW to the EAB). Distance from the LLRW to the EAB The Exclusion Area Boundary per FSAR Figure 2.2.5 is 2700 Ft. from center of each reactor building. The distance from the center of the unit 3 reactor building to the center of the LLRW is 1250 Ft. Therefore, the distance from the LLRW to the EAB is estimated to be 1450 Ft. or 442 meters. Figure 1. shows the two -hour accident X/Q as a function of distance. According to this plot the X/Q value for the distance of 442 meters is 9.2E-04 sec/ m3 . Calc. No. PM-750, Rev. 1, Attachment C, Page C-15 of C-52

FORM 5007 REV. 4191 United~ GENERAL CALCULATION SET NO REV. COMPo BY CHK'D BY II ConsInICIors COMPUTATION ~~-7S0 .",,~ f>P}( A IIayIIIeea Cofrpany SHEET PRELIM. FINAL 0

                                                                                                                           ,l,,~lr~

VOID DATE PIce PIAl'S - Unit. 2 , 3 Low Level Ra4wa.te Stora;e 'aoility

                                                                                       /'                    I~/z.'hl.-

I PROJECT SHEET 17 OF 53 DATE DATE SUBJECT Container Drop Aooi4ent Analysi. J.O. 7112.287

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Calc. No. PM-750, Rev. 1, Attachment C, Page C-16 of C-52

FORM 5007 REV 4/91 CALCULATION SET NO. REV COMPo BY CHK'D BY United~neers GENERAL

 .. ConstruCtors               COMPUTATION                         f""-? 50                     /1Itc,.. M'K A~Company 0

SHEET

                                                                                                           'iJt;r;,~

PRELIM. FINAL VOID DATE PECO PBAPS - Units 2 & 3 / 1CiJ'/J.~l. { PROJECT Low Level Radwaste Storage Facility SHEET let OF 5.3 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 7112.287 COMPUTER SPREADSHEET VERIFICATION In this calculation a QUATRO-PRO spreadsheet is used to evaluate whole body dose. Therefore, a method of hand calculation is used to verify the QUATRO-PRO spreadsheet. 1- External Whole Body Doses: A- Cr-51 From TABLE 4 total released for Cr-5l is 1.25E-Ol Ci and mev/dis is 3.25E-02. Therefore, the external whole body dose for Cr-5l is = 0.25 . X/Q . E--y . C

        = 0.25x (9.2E-04) x (3.25E-02) x (1.25E-Ol) = 9.34E-07 rem, with QUATRO-PRO the number is 9.34E-07 rem.

B- Co-60 From TABLE 4 total released for Co-60 is 4.44 Ci and mev/dis is 2.50. Therefore, the external whole body dose for Co-60 is =0.25 . X/Q . E--y . C

        = 0.25x (9.2E-04) x (2.50) x (4.44) = 2.55E-03 rem, with QUATRO-PRO the number is 2.56E-03 rem.

2- Internal Whole Body Doses: A- Cs-137 From TABLE 2 total released for Cs-137 is 2.07 Ci and from TABLE 5 dose factor for Cs-137 is 5.35E-05 mrem/pCi. Therefore, the internal whole body dose for Cs-137 is = X/Q . B . C . DF

       =(9.2E-04)x (3.47E-04)x (2.07)x (5.35E-05)x (lE+09) = 3.535E-02 rem, with QUATRO-PRO the number is 3.539E-02 rem.

B- H-3 From TABLE 2 total released for H-3 is 8.45E-05 Ci and from TABLE 5 dose factor for H-3 is 1.58E-07 mrem/pCi. Therefore, the internal whole body dose for H-3 is = X/Q . B . C . DF

       =(9.2E-04)x (3.47E-04)x (8.45E-05)x (1.58E-07)x (1E+09) = 4.262E-09 rem, with QUATRO-PRO the number is 4.260E-09 rem.

Calc. No. PM-750, Rev. 1, Attachment C, Page C-17 of C-52

FORM 5007 REV 4/91 UniIed . . . . .ers GENERAL CALCULATION SET NO. REV. COMPo BY CHK'D. BY

 ..ConsInICtors                    COMPUTATION                           PM-7S0            <.-      ~e-
                                                                                                               ~

A""'" Company SHEET PRELIM. FINAL VOID 0 PECO PBAPS - Units 2 & 3 ~ DATE lty'all9z /cft-;h'l PROJECT Low Level Radwaste Storage Facility SHEET \~ OF S3 DATE DATE SUBJECT Container Drop Accident Analysis J.O. 711? ?87 REFERENCES

1. Collection of radwaste Shipment Summary Reports, "All RWCU liners '87 to present",

Summary for Shipment No. DR-87-0001, Sheet 2.

2. NUREG-1320, "Nuclear Fuel Cycle Facility Accident Analysis Handbook", May 1988.

3. UE&C Computer Program SPECISO, Ver. 1.0, Oct. 1992.

4. Letter, Patrick T. Brennen (Meteorological Evaluation Services, Inc.) to Mr. Alan Marie (PECO), Dec. 18, 1979, which provides accident X/Qs.

5. USNRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1", Rev. 0, Mar. 1976 and Rev. 1, Oct. 1977.

6. PBAPS Drawing No. 6280-M-2406, Rev. 8, "2-1/2 Year Onsite Radwaste Storage Facility, Plan - EI135'-6" and Section B-B Looking West", 9120/85.

7. USNRC Regulatory Guide 1.3, "Assumptions used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors",

Rev. 2, June 1974.

8. PBAPS UFSAR, Chapter 2, Figure 2.2.5., current UFSAR as of this calculation.

9. 10 CFR 100, "Reactor Site Criteria".

Calc. No. PM-750, Rev. 1, Attachment C, Page C-18 of C-52

 '\ *
       ."I -                                                             PJ'-w.l.Iyt,t
                                                                                  ~~.~ PM-7fo PHILADELPHIA ELECTRIC COMPANY                            AH... c.\.~"c      ~ _\

PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 ~~j;z.~53 BASED UPON ANALYSIS OF EACH INDIVIDUAL RESIN CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT BAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO THE TOTAL VOLUME OF RESIN CONTAINED IN SHIPMENT NO. DR-87-0001. RWCu RESIN 40-

                                                                                         \~

ISOTOPIC ANALYSIS REPORT: NUCLIDE MC/LlNER A2 VALUE UC/CC CR-51 2872.3 600.00 0.94 MN-54 7218.4 20.00 2.36 CO-58 10705.2 20.00 3.50 ZN-65 305960.7 30.00 100.03 SR-92 2499.3 10.00 0.82 NB-95 628.9 20.00 0.21 AG-ll0m 3020.5 7.00 0.99 CS-134 81996.9 10.00 26.81 ESTIMATED ACTIVITY: FE-55 14187.1 1000.00 4.64 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE MC/LINER A2 VALUE UC/CC CO-60 157634.0 7.00 51.54 CS-137 95027.4 10.00 31.07 ESTIMATED ACTIVITIES: SR-90 114.033 0.40 3.728E-02 NI-63 1261.1 100.00 4.123E-Ol H-3 3.279 1000.00 1.072E-03 C-14 7.09 60.00 2.319E-03 1-129 0.133 2.00 4.350E-05 TC-99 142.541 25.00 4.660E-02 ESTIMATED TRANSURANIC ACTIVITIES: CM-242 3.38E+00 1.105E-03 PU-241 8.55E+Ol 2.796E-02 PU-238 8.98E-01 2.936E-04 PU-239 4.28E-01 1.398E-04 AM-241 2.82E-01 9.228E-05 CM-244 3.04E-Ol 9.927E-05 TOTAL TRANSURANICS: 2.500E+00 (NCI/GH) ALPHA EMITTERS TOTALS: - Tl/2 > 5 YEARS 254280.4 83.14 TOTALS: - ALL NUCLIDES 680497.3 222.49 " Calc. No. PM-750, Rev. 1, Attachment C, Page C-19 of C-52

u£ 14 fM-750

                                                                                       \\\\o.j._.....\    1\-\

PHILADELPHIA ELECTRIC COMPANY S\..u:.,\- ~\ c\ 53 PEACH BO'rl'OM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH INDIVIDUAL RESIN CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO THE TOTAL VOLUME OF RESIN CONTAINED IN SHIPMENT NO. DR-87-0001. RWCU RESIN.. ~..)./~J tt'l--- z.. q~ ~ 6 ..f-ISOTOPIC ANALYSIS REPORT: v~ aV~'")L 1.1.1~ I .5 ~/-:r. NUCLIDE MC/LINER A2 VAWE UC/CC CR-51 4239.8 600.00 1.70 MN-54 7443.1 20.00 2.99 CO-58 11453.1 20.00 4.60 ZN-65 30.00 104.63 SR-92 NB-95

                                              ~ 101      .~

2!564. 10.00 20.00 40.62 1.03 3'2} AG-110m 4590.0 7.00 1.84 CS-134 60869.7 10.00 24.42 ESTIMATED ACTIVITY: FE-55 13589.9 1000.00 5.45 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE MC/LlNER A2 VAWE UC/CC CO-60 150998.6 7.00 60.59 CS-137 70422.9 10.00 28.26 ESTIMATED ACTIVITIES: SR-90 84.507 0.40 3.391E-02 NI-63 1208.0 100.00 4.847E-Ol H-3 2.870 1000.00 1.151E-03 C-14 6.79 60.00 2.727E-03 1-129 0.099 2.00 3.956E-05 TC-99 105.634 25.00 4.239E-02 ESTIMATED TRANSURANIC ACTIVITIES: CM-242 2.50E+00 1.005E-03 PU-241 6.34E+01 2.543E-02 ./ PU-238 6.65E-01 2.670E-04 PU-239 3.17E-01 1.272E-04 AM-241 2.09E-Ol 8.393E-05 CM-244 2.25E-01 9.028E-05 TOTAL TRANSURANICS: 2. 117E+00 (NCI/GM) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 222896.7 89.44 TOTALS: - ALL NUCLIDES 685379.5 275.01 Calc. No. PM-750, Rev. 1, Attachment C, Page C-20 of C-52

                                                                                   ~.:i', P~-150 A\-\~~_\

sW~:I...~53 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH INDIVIDUAL RESIN CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO THE TOTAL VOWME OF RESIN CONTAINED IN CONTAINER NO. DR-89-0001. RWCU SYSTEM RESIN (82') + CONDENSATE SYSTEM RESIN (18') ISOTOPIC ANALYSIS REPORT: NUCLIDE MC/LINER A2 VALUE UC/CC Mn-54 326.3 *20.00 0.11 Co-58 0.0 20.00 0.00 Zn-65 43116.4 30.00 14.10 Nb-95 0.0 20.00 0.00 Cs-134 9252.1 10.00 3.03 ESTIMATED ACTIVITY: Fe-55 6443.2 1000.00 2.11 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE MC/LlNER A2 VALUE UC/CC Co-60 74768.8 7.00 24.45 Cs-137 23206.2 10.00 7.59 ESTIMATED ACTIVITIES: Sr-90 27.132 0.40 8.872E-03 Ni-63 1242.5 100.00 4.063E-01 H-3 111.000 1000.00 3.630E-02 C-14 0.419 60.00 1.370E-04 1-129 0.055 2.00 1.802E-05 Tc-99 0.423 25.00 1. 385E-04 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 7.61E-01 2.487E-04 Pu-241 1.98E+01 6.483E-03 Pu-238 2.37E-01 7.753E-05 Pu-239 1.04E-01 3.389E-05 Am-241 7.47E-02 2.443E-05 cm-244 1.62E-01 5.294E-05 TOTALTRANSURANICS: 2.355E-01 (NCI/GM) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 99377.8 32.50 TOTALS: - ALL NUCLIDES 158515.7 51.83 Calc. No. PM-750, Rev. 1, Attachment C, Page C-21 of C-52

                                                                               ~.~ \'lM-7~O
                                                                              ""~~\ ~-\

s""-.c.J- ~'3 { 5 3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD f1, DELTA, PA., 17314 BASED UPON ANALYSIS OF THE CONDENSATE SYSTEM RESIN IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 3.68E+05 CC'S OF RESIN (RESIN WEIGHT 2.35E+05 GRAMS) IN CONTAINER DR-89-0002. CLASS A/S CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE MC/LINER A2 VALUE UC/CC Mn-54 52.1 20.00 0.14 Fe-59 0.0 10.00 0.00 Cr-51 2712.1 600.00 7.37 Sb-124 0.0 5.00 0.00 Co-57 0.0 90.00 0.00 Co-58 225.4 20.00 0.61 Zn-65 1019.5 30.00 2.77 Ag-110m 128.4 7.00 0.35 Zr-95 65.2 20.00 0.18 Nb-95 75.8 20.00 0.21 1-131 52.6 10.00 0.14 Cs-134 63.3 10.00 0.17 ESTIMATED ACTIVITY: Fe-55 102.5 1000.00 0.28 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE MC/LINER A2 VALUE UC/CC Co-60 1512.4 7.00 4.11 Cs-137 186.0 10.00 0.51 ESTIMATED ACTIVITIES: Sr-90 0.076 0.40 2.051E-04 Ni-63 322.1 100.00 8.751E-01 H-3 0.157 1000.00 4.277E-04 C-14 0.016 60.00 4.232E-05 1-129 0.003 2.00 7.630E-06 Tc-99 0.005 25.00 1.460E-05 ESTIMATED TRANSURANIC ACTIVITIES: Calc. No. PM-750, Rev. 1, Attachment C, Page C-22 of C-52

Am-241 9.28E-04 2.521E-06 cm-244 3.31E-03 8.994E-06 TOTAL TRANSURANlCS: 3.240E-02 (NCl/GH) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 2020.9 5.49 TOTALS: - ALL NUCLIDES 6517.7 17.71 cuQ. ~ r~-75()

                                                                        ~-\\-c>.c.\~\ 1\-\

Sh~  ::t'-\{ 5 :> Calc. No. PM-750, Rev. 1, Attachment C, Page C-23 of C-52

eaQ~{t PM-7~O

                                                                                 ""\~~ ~-\

cs.~ Q5 ~ "3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD 11, DELTA, PA., 17314 BASED UPON ANALYSIS OF THE RWCU PHASE SEPE~TORS, SAMPLED 02/03/90 THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2548516.1 CC'S OF RESIN (RESIN WEIGHT 2345666.6 GRAMS) IN CONTAINER DR-90-0001. CLASS B

                                                              \.

RWCU SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 6.10E+03 6.10E+06 2.39E+00 Ba-140 2.68E+03 2.68E+06 1.05E+00 Cr-51 3.0,lE+05 3.01E+08 1. 18E+02 Tc-99m 1.32E+04 1.32E+07 5.18E+00 La-140 2.98E+03 2.98E+06 1. 17E+00 Co-58 2.58E+04 2.58E+07 1.01E+01 Zn-65 7.62E+04 7.62E+07 2.99E+01 Ag-110m 1. 19E+04 1. 19E+07 4.68E+00 Zr-95 2.23E+03 2.23E+06 8.75E-01 Nb-95 4.56E+03 4.56E+06 1.79E+00 1-131 2.87E+03 2.87E+06 1. 13E+00 Cs-134 2.22E+03 2.22E+06 8.70E-01 ESTIMATED ACTIVITY: Fe-55 8.65E+02 8.65E+05 3.40E-01 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uci/LINER uCi/cc Co-60 9.98E+04 9.98E+07 3.92E+01 Cs-137 4.45E+03 4.45E+06 1.75E+00 ESTIMATED ACTIVITIES: Sr-90 5.48E+00 5.48E+03 2.15E-03 Ni-63 1.10E+03 1.10E+06 4.31E-01 B-3 1.29E+02 1.29E+05 5.04E-02 C-14 5.46E-01 5.46E+02 2.14E-04 1-129 6.06E-03 6.06E+OO 2.38E-06 Tc-99 7.75E-02 7.75E+01 3.04E-05 Calc. No. PM-750, Rev. 1, Attachment C, Page C-24 of C-52

W-# r"'-7 ~() M-\o.cl.....--\- t\-\ -ESTIMATED ACTIVITIES: s\J2..6'{~3 Sr-90 5.481+00 5.48B+03 2.15B-03 Ni-63 1.10E+03 1.10E+06 4.31E-01 8-3 1.291+02 1.29B+05 5.041-02 C-14 5.461-01 5.46E+02 2.141-04 1-129 6.061-03 6.061+00 2.381-06 Tc-99 7.751-02 7.75E+01 3.041-05 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 1.56E-01 6.13E-05 Pu-241 3.91E+00 1.54E-03 Pu-238 4.43E-02 1.74E-05 Pu-239 1.99E-02 7.80E-06 Am-241 1.37E-02 5.38E-06 cm-244 2.72E-02 1.07E-05 TOTAL TRANSURANICS: 4.48E-02 (nCi/qm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 105517.9 41.40 TOTALS: - ALL NUCLIDES 557633.4 218.81 Calc. No. PM-750, Rev. 1, Attachment C, Page C-25 of C-52

J. -:II fl'?-750 (

         'RlJC,(.( . ~"'Om1 87 - ~                                                    A~~\-~~,

. '"::>~:l..7uf53 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD 11, DELTA, PA., 17314 BASED UPON ANALYSIS OF THE 2B PHASE SEPERATOR, SAMPLED 06/26/90 THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 481386.4 CC'S OF RESIN (RESIN WEIGHT 281155.71 GRAMS) IN CONTAINER DR-90-0002. CLASS A/U CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 2.61E+01 2.61E+04 5.42E-02 Ba-140 3.32E+01 3.32E+04 6.90E-02 Cr-51 4.17E+02 4.17E+05 8.65E-01 Tc-99m O.OOE+OO O.OOE+OO O*. OOE+OO La-140 1.84E+01 1.84E+04 3.82E-02 Co-58 8.84E+01 8.84E+04 1.84E-01 Zn-65 6.71E+02 6.71E+05 1.39E+OO Ag-110m O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 1.46E+01 1. 46E+04 3.04E-02 Nb-95 2.43E+01 2.43E+04 5.05E-02 I-131 1.21E+01 1.21E+04 2.52E-02 Cs-134 3.24E+01 3.24E+04 6.74E-02 ESTIMATED ACTIVITY: Fe-55 2.58E+01 2.58E+04 5.37E-02 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 3.01E+02 3.01E+05 6.26E-01 Cs-137 9.78E+01 9.78E+04 2.03E-01 ESTIMATED ACTIVITIES: Sr-90 4.76E-01 4.76E+02 9.89E-04 Ni-63 4.25E+01 4.25E+04 8.82E-02 H-3 6.64E-01 6. 64E+02 1.38E-03 C-14 1.58E+00 1.58E+03 3.29E-03 I-129 1.48E-03 1.48E+OO 3.07E-06 Calc. No. PM-750, Rev. 1, Attachment C, Page C-26 of C-52

e.:c...t" 11 PN-750 Pu-238 . 1.49E-03 3.10E-06 Pu-239 4.97E-04 1.03E-06 Aa-241 1. 17E-04 2.44£-07 , CJI-244 1.39E-03 2.88£-06 TOTAL TRANSURANICS: 1.24E-02 (nC!/91Il) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 444.3 0.92 TOTALS: - ALL NUCLIDES 1807.2 3.75

                                                                                    ~{\-\

S~~i~S3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF THE XX PHASE SEPERATOR, SAMPLED THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 0.0 CC'S OF RESIN (RESIN WEIGHT 0.0016538 GRAMS) IN CONTAINER DR-90-0002. CLASS A/U CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uC!/cc Mn-54 O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 O.OOE+OO O.OOE+OO O.OOE+.OO Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO La-140 O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO 0.00£+00 Zn-65 O.OOE+OO O.OOE+OO O.OOE+OO Aq-110m O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO Nb-95 O.OOE+OO O.OOE+OO 0.00£+00 1-131 O.OOE+OO O.OOE+OO 0.00£+00 Calc. No. PM-750, Rev. 1, Attachment C, Page C-27 of C-52

                                                                  ~. if! 1"/1-7.7"0
                                                                                          ~I\-\

THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS SW Z ?1-S3 NUCLIDE mCi/LINER uCi/LINER UCi/cc Co-60 O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO ESTIMATED ACTIVITIES: Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO B-3 3.90E-09 3.90E-06 1.38E-03 C-14 O.OOE+OO O.OOE+OO O.OOE+OO 1-129 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 O.OOE+OO O.OOE+OO O.OOE+OO ESTIMATED TRANSURANIC ACTIVITIES: cm-242 O.OOE+OO O.OOE+OO Pu-241 O.OOE+OO O.OOE+OO Pu-238 O.OOE+OO O.OOE+OO Pu-239 O.OOE+OO O.OOE+OO Am-241 O.OOE+OO O.OOE+OO CDl-244 O.OOE+OO O.OOE+OO TOTAL TRANSURANICS: O.OOE+OO (nCi/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 0.0 0.00 TOTALS: - ALL NUCLIDES 0.0 0.00 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD f1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH BATCH OF RESIN CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 3.17E+06 CC'S OF RESIN (RESIN WEIGHT 1.85E+06 GRAMS) IN CONTAINER DR-90-0002. Calc. No. PM-750, Rev. 1, Attachment C, Page C-28 of C-52

ea!lrPM-7fo

                                                                                   .~\~~ t\-\
                                                                                   ~\'J-3e4s3 RWCU SYSTEM RESIN , CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT:

NUCLIDE mCi/LINER uCi/LINER uci/cc Mn-54 6.85E+03 6.85E+06 2. 16E+OO Ba-140 3.32E+01 3.32E+04 1.05E-02 Cr-51 8.67E+04 8.67E+07 2.74E+01 Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.42E+03 2.42E+06 7.62E-01 Co-58 2.35E+04 2.35E+07 7.42E+OO Zn-65 1.77E+05 1.77E+08 5.59E+01 Aq-110m 4.88E+03 4.88E+06 1. 54E+OO Zr-95 1.46E+01 1.46E+04 4.61E-03 Nb-95 2.04E+03 2.04E+06 6.44E-01 I-131 7.11E+02 7.11E+05 2.24E-01 Cs-134 3.43E+03 3.43E+06 1.08E+OO ESTIMATED ACTIVITY: Fe-55 1.28E+04 1.28E+07 4.04E+OO THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 7.13E+04 7.13E+07 2.25E+01 Cs-137 6.32E+03 6.32E+06 1.99E+OO ESTIMATED ACTIVITIES: Sr-90 8.38E+OO 8.38E+03 2.64E-03 Ni-63 8.59E+02 8.59E+05 2.71E-01 B-3 1.76E+OO 1.76E+03 5.56E-04 C-14 1.76E+OO 1.76E+03 5.56E-04 I-129 9.94E-03 9.94E+OO 3.14E-06 Tc-99 5.71E-02 5.71E+01 1.80E-05 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 4.25E-03 1.34E-06 Pu-241 5.33E+OO 1.68E-03 Pu-238 6.92E-02 2.18E-05 Pu-239 2.97E-02 9.36E-06 Am-241 2.03E-02 6.39E-06 cm-244 4.55E-02 1.43E-05 TOTAL TRANSURANICS: 8.89E-02 (nCi/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 78525.1 24.76 TOTALS: - ALL NUCLIDES 399217.8 125.88 Calc. No. PM-750, Rev. 1, Attachment C, Page C-29 of C-52

eJ. #/'#-750

                                                                                    ~~.-..\- 1\- \
                                                                                   '~W3\~ 5~

PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD t1, DELTA, PA., 17314 . BASED UPON ANALYSIS OF THE RWCU PHASE SEPERATORS, SAMPLED 06/26/90 THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2690100.3 CC'S OF RESIN (RESIN WEIGHT 1571164.3 GRAMS) IN CONTAINER DR-90-0002. CLASS B RWCU SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uci/cc Mn-54 6.83E+03 6.83E+06 2.54E+00 Ba-140 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 8.63E+04 8.63E+07 3.21E+01 Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.40E+03 2.40E+06* 8.92E-01 Co-58 2.34E+04 2.34E+07 8. 71E+00 Zn-65 1.77E+05 1.77E+08 6. 56E+01 Aq-110m 4.88E+03 4.88E+06 1.81E+00 Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO Nb-95 2.02E+03 2.02E+06 7.51E-01 1-131 6.99E+02 6.99E+05 2.60E-01 Cs-134 3.40E+03 3.40E+06 1.26E+00 ESTIMATED ACTIVITY: Fe-55 1.28E+04 1.28E+07 4.75E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 7.10E+04 7.10E+07 2.64E+01 Cs-137 6.23E+03 6.23E+06 2.31E+00 ESTIMATED ACTIVITIES: Sr-90 7.91E+00 7.91E+03 2.94E-03 Ni-63 8.17E+02 8. 17E+05 3.04£-01 B-3 1.10E+00 1.10E+03 4.09E-04 C-14 1.80E-01 1.80E+02 6. 68E-05 Calc. No. PM-750, Rev. 1, Attachment C, Page C-30 of C-52

J.1t~1¥.7ft> A- -ffa-cf,,.,J-A _ ,

                                                                                           ""..J- ~~ ~53 Pu-241                 5.28E+00                                 1.96E-03 Pu-238                  6.77E-02                                2.52E-05 Pu-239                 2.92E-02                                 1.09E-05 Am-241                 2.01E-02                                 7.49E-06" CDl-244                4.41E-02                                 1.64E-05 TOTAL TRANSURANICS:                       1.03E-01 (nCi/gm)

ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 78080.8 29.03 TOTALS: - ALL NUCLIDES 397410.5 147.73

                                                            ~-'--" ..

Calc. No. PM-750, Rev. 1, Attachment C, Page C-31 of C-52

4f+nJ..,~.:f/j _I slJ-.3 ~ 125,J PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA.,. 17314 BASED UPON ANALYSIS OF THE RWCU PHASE SEPERATORS, SAMPLED 11/01/90 THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2123763.5 CC'S OF RESIN (RESIN WEIGHT 1475500.0 GRAMS) IN CONTAINER DR-90-0003. CLASS B RWCU SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 7.80E+03 7.80E+06 3.67E+00 Fe-59 2.56E+02 2.56E+05 1.20E-01 Cr-51 1.09E+05 1.09E+08 5.13E+01 Zr-97 6.08E+02 6.08E+05 2.86E-01 La-140 9.83E+02 9.83E+05 4.63E-01 Co-58 2. 14E+04 2.14E+07 1.01E+01 Zn-65 1.26E+05 1.26E+08 5.94E+01 Ag-110m 1.05E+04 1.05E+07 4.93E+00 Zr-95 2.46E+03 2.46E+06 1. 16E+00 Nb-95 6.76E+03 6.76E+06 3.18E+00 1-131 6.49E+02 6.49E+05 3.06E-01 Cs-134 3.81E+03 3.81E+06 1.79E+00 ESTIMATED ACTIVITY: Fe-55 9.53E+03 9.53E+06 4.49E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uci/cc Co-60 5.30E+04 5.30E+07 2.49E+01 Cs-137 6.80E+03 6.80E+06 3.20E+00 ESTIMATED ACTIVITIES: Sr-90 8.63E+00 8.63E+03 4.06E-03 Ni-63 6.09E+02 6.09E+05 2.87E-01 B-3 1.03E+00 1.03E+03 4.86E-04 C-14 1.34E-Ol 1.34E+02 6.3).E-05 Calc. No. PM-750, Rev. 1, Attachment C, Page C-32 of C-52

NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 5.30£+04 5.30£+07 2.49£+01 Cs-137 6.80E+03 6.80E+06 3.20E+00 ESTIMATED ACTIVITIES: Sr-90 8.63E+00 8.63E+03 4.06E-03 Ni-63 6.09E+02 6.09E+05 2.87£-01 B-3 1.03E+00 1.03E+03 4.86E-04 C-14 1.34E-01 1.34E+02 6.31E-05 I-129 9.24E-03 9.24E+00 4.35E-06 Tc-99 4.90E-02 4.90E+01 2.31E-05 ESTIMATED TRANSURANIC ACTIVITIES: ca-242 4.56E-03 2.15E-06 Pu-241 5.77E+00 2.72E-03 Pu-238 7.40E-02 3.48E-05 Pu-239 3.19E-02 1.50E-05 Am-241 2.20E-02 1.04E-05 ca-244 4.81E-02 2.27E-05 TOTAL TRANSURANICS: 1.19E-01 (nCi/qm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 60393.1 28.44 TOTALS: - ALL NUCLIDES 360392.7 169.70 tal!1//~-7.5C) t\~~"-\ s'hJ- 34~S~ Calc. No. PM-750, Rev. 1, Attachment C, Page C-33 of C-52

                                                                                ~,~~~-\
                                                                                 '>~~5<:{S3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH BATCH OF RESIN CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT 

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 3.06E+06 CC'S OF RESIN (RESIN WEIGHT 2.16E+06 GRAMS) IN CONTAINER DR-91-0001. CLASS B RWCU SYSTEM RESIN & CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 2.38E+04 2.38E+07 7.77E+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 7.71E+04 7.71E+07 2.52E+01 Ba-140 8.68E+02 8. 68E+05 2.84E-01 La-140 1.65E+03 1.65E+06 5.41E-01 Co-58 2.59E+04 2.59E+07 8.48E+OO Zn-65 2.20E+05 2.20E+08 7.21E+01 Ag-110m 1.40E+04 1.40E+07 4.58E+OO Zr-95 8.67E+02 8.67E+05 2.84E-01 Nb-95 4.29E+03 4.29E+06 1.40E+OO 1-131 2.01E+03 2.01E+06 6.56E-01 Cs-134 4.43E+04 4.43E+07 1.45E+01 ESTIMATED ACTIVITY: Fe-55 5.85E+03 5.85E+06 1.91E+OO THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uci/LINER uCi/cc Co-60 1. 15E+05 1. 15E+08 3.76E+01 Cs-137 6.07E+04 6.07E+07 1.99E+01 ESTIMATED ACTIVITIES: Sr-90 3.47E+02 3.47E+05 1.13E-01 Ni-63 1.35E+03 1.35E+06 4.42E-01 B-3 2.94E-01 2.94E+02 9.62E-05 C-14 6.48E+OO 6.48E+03 2.12E-03 1-129 8.48E-02 8.48E+01 2.77E-05 Calc. No. PM-750, Rev. 1, Attachment C, Page C-34 of C-52

Pu-238 8.08E-Ol 2.64E-04 Pu-239 2.63E-Ol 8.61E-05 0-241 1.87£-01 6.11£-05 ca-244 5.32E-01 1.74£-04 TOTAL TRANSURANICS: 8.283E-01 (nCi/qm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 177321.4 57.98 TOTALS: - ALL NUCLIDES 598479.2 195.70 JllfJ~-7fO

                                                                           ~~-\
                                                                           ~~ '3     t c{- s'~

PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH CONDENSATE BATCH CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2.27E+05 CC'S OF RESIN (RESIN WEIGHT 1.60E+05 GRAMS) IN CONTAINER DR-91-0001. CLASS A/S CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LlNER uci/cc Mn-54 6.15E+01 6. 15E+04 2.71E-01 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 1.68E+02 1. 68E+05 7.43E-01 Ba-140 9.21E+00 9.21E+03 4.07E-02 La-140 6.70E+00 6.70E+03 2.96E-02 Co-58 6.77E+01 6.77E+04 2.99E-01 Zn-65 6.04E+02 6.04E+05 2. 66E+00 Calc. No. PM-750, Rev. 1, Attachment C, Page C-35 of C-52

Cs-134 1.19E+02 1.19E+05 5.26E-01 E~TIMATED ACTIVITY: Fe-55 2.86E+01 2.86E+04 1.26E-01 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 3.23E+02 3.23E+05 1.43E+00 Cs-137 1. 64E+02 1.64E+05 7.25E-01 ESTIMATED ACTIVITIES: Sr-90 1.18E-01 1. 18E+02 5. 19E-04 Ni-63 4.55E+01 4.55E+04 2.01E-01 H-3 1.41E-02 1.41E+01 6.22E-05 C-14 1.75E+00 1.75E+03 7.74E-03 1-129 2.48E-03 2.48E+00 1.10E-05 Tc-99 3.61E-02 3.61E+01 1.60E-04 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 6.36E-04 2.81E-06 Pu-241 5.31E-02 2.34E-04 Pu-238 1.34E-03 5.92E-06 Pu-239 5.26E-04 2.32E-06 Am-241 4.49E-04 1.98E-06 cm-244 8.15E-04 3.60E-06 TOTAL TRANSURANICS: 1.956E-02 (nCi/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 534.7 2.36 TOTALS: - ALL NUCLIDES 1693.7 7.48 J ~ltv/-1ft) ~~~r-.-\ S"'~37 i 53 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH RWCU BATCH CONTAINED IN THE LINER, THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2.83E+06 CC'S OF RESIN /j (RESIN WEIGHT 2.00E+06 GRAMS) .<-- :

                                                                                        .I IN CONTAINER DR-91-0001.                                   . /

Calc. No. PM-750, Rev. 1, Attachment C, Page C-36 of C-52

 ~wcu SYSTEM RESIN rSOTOPIC ANALYSIS REPORT:

NUCLIDE mCi/LINER Mn-54 2.37E+04 2.37E+07 8.37E+00 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 7.70E+04 7.70E+07 2.72E+01 Ba-140 8.59E+02 8.59E+05 3.03E-01 La-140 1. 65E+03 1. 65E+06 5.82E-01 Co-58 2.59E+04 2.59E+07 9. 14E+00 Zn-65 2.20E+05 2.20E+08 7.76E+01 Aq-110m 1.40E+04 1.40E+07 4.94E+00 Zr-95 8.59E+02 8. 59E+05 3.03E-01 Nb-95 4.26E+03 4.26E+06 1.51E+00 1-131 1.98E+03 1.98E+06 6.98E-01 Cs-134 4.42E+04 4.42E+07 1.56E+01 ESTIMATED ACTIVITY: Fe-55 5.82E+03 5.82E+06 2.06E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 1.15E+05 1.15E+08 4.04E+01 Cs-137 6.05E+04 6.05E+07 2.14E+01 ESTIMATED ACTIVITIES: Sr-90 3.47E+02 3.47E+05 1.23E-01 Ni-63 1.31E+03 1.31E+06 4.61E-01 B-3 2.80E-01 2.80E+02 9.89E-05 C-14 4.73E+00 4.73E+03 1.67E-03 1-129 8.23E-02 8.23E+01 2.91E-05 Tc-99 1.76E+00 1.76E+03 6.20E-04 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 1.58E+00 5.60E-04 Pu-241 4.83E+01 1.71E-02 Pu-238 8.07E-01 2.85E-04 Pu-239 2.63E-01 9.28E-05 Am-241 1.87E-01 6.59E-05 cm-244 5.31E-01 1.87E-04 TOTAL TRANSURANICS: 8.930E-01 (nci/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 176786.7 62.43 TOTALS: - ALL NUCLIDES 596785.5 210.75 Calc. No. PM-750, Rev. 1, Attachment C, Page C-37 of C-52

J# 1'1'4-750

                                                                              ~J~-"
                                                                              $\\~ '39c~53 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH BATCH OF RESIN CONTAINED IN THE LINER l THE FOLLOWING SHIPMENT 

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 3.06E+06 CC'S OF RESIN (RESIN WEIGHT 1.97E+06 GRAMS) IN CONTAINER DR-91-0002. CLASS B RWCU SYSTEM RESIN & CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 1. 43E+04 1.43E+07 4.66E+00 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 8.22E+04 8.22E+07 2.69E+Ol Ba-140 1.55E+02 1.55E+05 5.06E-02 La-140 2.58E+03 2.58E+06 8.42E-01 Co-58 2. 17E+04 2.17E+07 7.09E+00 Zn-65 1.50E+05 1.50E+08 4.91E+01 Ag-II0m 6.44E+03 6.44E+06 2.10E+00 Cs-136 1. 28E+03 1.28E+06 4.19E-01 Nb-95 1.94E+03 1.94E+06 6.33E-01 1-131 7.80E+03 7.80E+06 2.55E+00 Cs-134 8.52E+04 8.52E+07 2.79E+01 ESTIMATED ACTIVITY: Fe-55 4.77E+03 4.77E+06 1.56E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 7.72E+04 7.72E+07 2.53E+01 Cs-137 8.65E+04 8.65E+07 2.83E+01 ESTIMATED ACTIVITIES: S;--90 4.77E+02 4.77E+05 1.56E-01 Nl.-63 1. 46E+03 1.46E+06 4.79E-01 H-3 2.54E-01 2.54E+02 8.31E-05 C-14 2.75E+01 2.75E+04 8.98E-03 1-129 1.70E-01 1.70E+02 5.55E-05 Tc-99 3.23E+00 3.23E+03 1.06E-03 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 2.18E+00 7.13E-04 Pu-241 6.73E+01 2.20E-02 Pu-238 1.13E+00 3.70E-04 Pu-239 3.71E-01 1.21E-04 Am-241 2.65E-01 8.67E-05 cm-244 7.44E-01 2.43E-04 TOTAL TRANSURANICS: 1.276E+00 (nci/gm) ALPHA EMITTERS TOTALS: - Tl/2 > 5 YEARS 165787.7 54.21 TOTALS: - ALL NUCLIDES 544407.5 178.01 Calc. No. PM-750, Rev. 1, Attachment C, Page C-38 of C-52

J It /'I'?- 750 f}-Mw/",J-,;. _( PHILADELPHIA ELECTRIC COMPANY s J,~lLc ~..53 PEACH BOTTOM ATOMIC POWER STATION RD t1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH CONDENSATE BATCH CONTAINED IN THE LINER THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSA~l DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 6.51E+05 CCIS OF RESIN (RESIN WEIGHT 4.20E+05 GRAMS) IN CONTAINER DR-91-0002. CLASS B CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 8.33E+02 8.33E+05 1.28E+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 4.12E+03 4.12E+06 6.32E+OO Ba-140 1.55E+02 1.55E+05 2.38E-01 La-140 4.51E+02 4.51E+05 6.92E-01 Co-58 1.17E+03 1.17E+06 1.80E+OO Zn-65 8.90E+03 8.90E+06 1.37E+01 Aq-110m 3.07E+02 3.07E+05 4.72E-01 Cs-136 6.09E+01 6.09E+04 9.35E-02 Nb-95 1.09E+02 1.09E+05 1.68E-01 1-131 4.83E+02 4.83E+05 7.41E-01 Cs-134 3.64E+03 3.64E+06 5.58E+OO ESTIMATED ACTIVITY: Fe-55 3.99E+02 3.99E+05 6.13E-01 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 4.50E+03 4.50E+06 6.91E+OO Cs-137 3.79E+03 3.79E+06 5.82E+OO ESTIMATED ACTIVITIES: Sf- 90 2.72E+OO 2.72E+03 4.17E-03 Nl.-63 6.35E+02 6.35E+05 9.75E-01 H-3 3.69E-02 3.69E+01 5.67E-05 C-14 2.45E+01 2.45E+04 3.75E-02 1-129 5.73E-02 5.73E+01 8.79E-05 Tc-99 8.34E-01 8.34E+02 1.28E-03 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 1.47E-02 2.25E-05 Pu-241 1.23E+OO 1.88E-03 Pu-238 3.09E-02 4.75E-05 Pu-239 1.21E-02 1.86E-05 Am-241 1.04E-02 1.59E-05 cm-244 1.88E-02 2.89E-05 TOTAL TRANSURANICS: 1.722E-Ol (nCi/qm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 8959.2 13.76 TOTALS: - ALL NUCLIDES 29574.6 45.41 Calc. No. PM-750, Rev. 1, Attachment C, Page C-39 of C-52

                                                                                   ~hf'n-7?o IJ~/~~_I r                                                                           ~t~~/~S3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH RWCU BATCH CONTAINED IN THE LINEBL THE FOLLOWING SHIPMENT 

SUMMARY

REPORT HAS BEEN PREPARED FOR DIS~SAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 2.41E+06 CC'S OF RESIN (RESIN WEIGHT *1.55E+06 GRAMS) IN CONTAINER DR-91-0002. CLASS.B RWCU SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc JoIn-54 1.34E+04 1.34E+07 5.58E+00 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 7.81E+04 7.81E+07 . 3.25E+01 Ba-140 O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.12E+03 2.12E+06 8.83E-01 Co-58 2.05E+04 2.05E+07 8.52E+00 Zn-65 1.41E+05 1.41E+08 5.87E+Ol Ag-110m 6.13E+03 6.13E+06 2.55E+00 Cs-136 1.22E+03 1.22E+06 5.08E-01 Nb-95 1.83E+03 1.83E+06 7.59E-01 1-131 7.32E+03 7.32E+06 3.04E+00 Cs-134 8. 16E+04 8.16E+07 3.39E+01 ESTIMATED ACTIVITY: Fe-55 4.37E+03 4.37E+06 1. 82E+OO THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 7.27E+047.27E+07 3.02E+01 Cs-137 8.27E+04 8.27E+07 3.44E+Ol ESTIMATED ACTIVITIES: S;-90 4.74E+02 4.74E+05 1.97E-01 Nl.-63 8.29E+02 8.29E+05 3.44E-01 H-3 2.17E-01 2.17E+02 9.02E-05 C-14 3.00E+00 3.00E+03 1.25E-03 1-129 1.12E-Ol 1.12E+02 4.67E-05 Tc-99 2.40E+00 2.40E+03 9.97E-04 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 2.16E+00 8.99E-04 Pu-241 6.61E+Ol 2.74E-02 Pu-238 1.10E+00 4.58E-04 Pu-239 3.59E-01 1.49E-04 Am-241 2.55E-Ol 1.06E-04 cm-244 7.25E-01 3.01E-04 TOTAL TRANSURANICS: 1.574E+00 (nCi/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 156828.5 65.16 TOTALS: - ALL NUCLIDES 514832.9 213.90 Calc. No. PM-750, Rev. 1, Attachment C, Page C-40 of C-52

rztJtu 8 7- ~a..L'~~ all E6t=td liners f() r I-R;i~ "'3 JXbt:J Jilt. - A#.-./..JA-I PHILADELPHIA ELECTRIC COMPANY 1'1-7f{J ~JJ-V2-- .~- PEACH BOTTOM ATOMIC POWER STATION 7-?J RD '1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH BATCH OF RESIN CONTAINED IN THE LINER l THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR DISPOSAL DOCUMENTATION AND COMPLIANCE WITH THE CURRENT NRC REGULATIONS. THIS

SUMMARY

APPLIES TO 3.06E+06 CCIS OF RESIN (RESIN WEIGHT 2.02E+06 GRAMS) IN CONTAINER DR-92-0001. CLASS B r~ ( '.',-

                                                                                          \

RWCU SYSTEM RESIN & CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER uCi/LINER uCi/cc Mn-54 2.53E+04 2.53E+07 8.29E+00 Co-57 5.53E+01 5.53E+04 1.81E-02 Cr-51 3.21E+05 3.21E+08 1.05E+02 Ba-140 2.01E+03 2.01E+06 6.58E-01 La-140 2.40E+03 2.40E+06 7.83E-01 Co-58 2.73E+04 2.73E+07 8.93E+00 Zn-65 2.56E+05 2.56E+08 8.38E+01 Aq-110m 1.46E+04 1.46E+07 4.77E+00 Zr-97 1.99E+03 1.99E+06 6.49E-01 Nb-95 3.76E+03 3.76E+06 1.23E+00 1-131 7.20E+02 7.20E+05 2.35E-01 Cs-134 2.32E+04 2.32E+07 7.57E+00 ESTIMATED ACTIVITY: Fe-55 1.44E+04 1.44E+07 4.71E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER uCi/cc Co-60 1.41E+05 1.41E+08 4.62E+01 Cs-137 2.86E+04 2.86E+07 9.36E+00 ESTIMATED ACTIVITIES: S+-90 3.52E+01 3.52E+04 1.15E-02 Nl.-63 1.96E+03 1.96E+06 6.39E-01 H-3 5.25E+00 5.25E+03 1.72E-03 C-14 5.81E+00 5.81E+03 1.90E-03 1-129 4.97E-02 4.97E+01 1.62E-05 Tc-99 4.51E-01 4.51E+02 1.47E-04 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 8.10E-01 2.65E-04 Pu-241 3.80E+01 1.24E-02 Pu-238 7.39E-01 2.42E-04 Pu-239 1.99E-01 6.49E-05 Am-241 1.59E-01 5.19E-05 cm-244 5.74E-01 1.88E-04 TOTAL TRANSURANICS: 8.286E-01 (nCi/gm) ALPHA EMITTERS TOTALS: - T1/2 > 5 YEARS 171874.3 56.20 TOTALS: - ALL NUCLIDES 864975.6 282.84 Calc. No. PM-750, Rev. 1, Attachment C, Page C-41 of C-52

e5J1.eteo'lological evaluation Se'lvices, c!Jnc. 134 BROADWAY. AMITYVILLE. N. Y. 11701 TEL: 516-691-3395 December 18, 1979 Hr. Alan Marie Philadelphia Electric Company 2301 Market Street N2-1 philadelphia, PA 19101

Dear AI:

As per your recent telephone request, we have computed accident X/Q values out to 50 miles for the Peach Bottom reactor vents and off-gas stack. These calculations have been made according to the guidelines of Regulatory Guide 1.145, using the 8/67 through 7/71 meteorological data base. These calculatiol\s were previously sent by telecopier to yourself and to D. A. Klein of Bechtel on December 13 and 14, 1979. Vent X/Q The vent X/Q values were computed assuming a ground-level release, using winds from the 75-ft. level of Tower 2, uncor-rected for source elevation. The resul ts of these calcula-tions for the various time periods following an accident are shown in Figure 1. The maximum values occurred in the SE sector at each distance. The two-hour accident X/Q values are plotted as a function of distance in Figure 2. As you can see, the plot is fairly smooth, and any interpolation between the receptor points given in Figure 1 should produce a negligible error. Off-Gas Stack X/Q The off-gas stack X/Q values for the various time periods following an accident are shown in Figure 3. It should be noted that in the interest of time, these calculations have J been made in a very conservative manner, assuming the highest terrain of all 16 sectors for each receptor distance. As per Regulatory Guide 1.145, stack fumigation has been / ' assumed to occur for the first one-half hour of the accident. Gu ide 1.145 is primarily des igned for EAB and LPZ evalua-tions, and gives no guidance on how far downwind fumigation should be assumed to occur. After consultation with Joe Levine of the NRC Hydro-Meteorological Branch, we decided to correct only those receptors within 1 mile for stack fumiga-tion. Calc. No. PM-750, Rev. 1, Attachment C, Page C-42 of C-52

adl#PH-7?O 1J#ae/",~11 <;/,J- $I?"~~~ Mr. Alan Marie December 18, 1979 Page 2 Due to both the meteorology and terrain, the maximum two-hour X/Q at each receptor distance did not always occur in the same sector. At close-in receptors (less than 4,600 m) the "_ ~ two-hour X/Q values were caused by the very unstable

 ~urs. The very unstable case occurs predominantly with ESE and SE winds, putting the maximum values at the close-in distances in the WNW and NW sectors.             At the farther dis-tances, as the terrain becomes higher, the .5% two-hour X/Q values are caused by the stable case and occur in the NE and ENE sectors. Therefore, the X/Q's in Figure 3 are the maximum sector values at each receptor distance.

A plot of the maximum two-hour X/Q versus distance from the off-gas stack is shown in Figure 4. Due to both the fumiga-tion and terrain corrections, the plot is quite "bumpy" with several peaks. It is for this reason that we did not use a uniform receptor spacing in Figure 3, and instead chose the appropriate distances such that no peaks would be missed if one were to interpolate X/Q values between the receptor dis-tances. As I have stated earlier, the off-gas stack calculations were done very conservatively for the sake of time. If the re-sulting isodose curves are too high, we could produce a less conservative set of X/Q's if given more time. However, until we actually do it, I cannot make an estimate on how much lower the numbers would be. Sincerely yours,

                                         *.B,t     Jk~_.-

Patrick T. Brennan PTB:rg Enc. Calc. No. PM-750, Rev. 1, Attachment C, Page C-43 of C-52

FIGURE 1 I PEACH BOTTOM VENT ACCIDENT X/Q

                                                                                                                                                                                                                                                              ':0 SE SECTOR
                                                                                                                                                         .5 % PROBABILITY                                                                                      -

8/67.- 7/71 DATA BASE

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Calc. No. PM-750, Rev. 1, Attachment C, Page C-44 of C-52 I

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Calc. No. PM-750, Rev. 1, Attachment C, Page C-45 of C-52

FIGUlili J I PEACH BOTTOM OFF - GAS STACK ACCIDENT X/Q MAXIMUM SECTOR

                                                                                                                                                                                                       )~l.
                                                                                                                                                   .5% PROBABILITY                                    ~,

l"1 8/67 ~ 7/71 DATA BASE D;~T...."t- C-'\ 2.~k 11 L I' J.... 72 4 (, 2. If J-.... 3'001..- '/710 L...,

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t Calc. No. PM-750, Rev. 1, Attachment C, Page C-46 of C-52

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FIGURE 3 con't PEACH BOTTOM OFF - GAS STACK ACCIDENT X/Q MAXIMUM SECTOR .,

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Calc. No. PM-750, Rev. 1, Attachment C, Page C-47 of C-52

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IflO IO~ 000 Calc. No. PM-750, Rev. 1, Attachment C, Page C-48 of C-52

FORM 5611 UNITED ENGINEERS AND CONSTRUCTORS COMPUTER DISCLOSURE SHEET DISCIPLINE /VudeaC CLIENT* ~h,' Cl1 ~ t. \ ~~\'~ ~\ ....~tr',*c. Co~9C\","\. DATE 'o/'J.-t/9 ~ PROJECT - PB~gS UlA:h. .,. / '3 \.0-",,) \~"'~l R&\.~wk ~+ur-J.\t.. F.lc,*\,1:;- JOB NO. 7 II ~.2.Y7

                                                                                                                                                                ~ CALC. SET      fNJ- 750 PROGRAM(S) USED                 REV. NO.                    REV. DATE                              STATUS PRELIM. 0 FINAL             6!'"
                                                                 ~~Ec.."!SO                                                   o~. \992
                                                                                                    '*0                                                             VOID              0 UE&C PREQUALlFICATION           YES     ~

NO 0 RUN NO. DESCRIPTION ANALYSIS DESCRIPTION

                                                                                             /'0       d,-".. J         -Ii.- "'Ve/~ Jtim_,! ~"<1Jl         r~ r   t::s 1'",+~r~+\'O Vl THE ATTACHED COMPUTER OUTPUT HAS BEEN REVIEWED, THE INPUT DATA CHECKED, AND THE RESULTS APPROVED FOR RELEASE INPUT CRITERIA FOR THIS ANALYSIS WERE ESTABLISHED BY     ~ a~kl1l*                ON          10 I ?oJ 9,2-RUN BY     ~

I'-Zj~ . 1""- C,,/~i..tt~/*

                                                                                                                                                                                                           ~
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CHECKED BY P... ~ fRQ,-Jq ~~ APPROVED BY REMARKS-Calc. No. PM-750, Rev. 1, Attachment C, Page C-49 of C-52

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cJ(1f I'n-7.7'CJ 29 ~kr5(~53 H3 1 C14 1 CR51 1 MN54 1 FE55 1 C058 1 C060 1 NI63 1 ZN65 1 SR90 1 SR92 1 NB95 1 TC99 1 AG110M 1 1129 1 1131 1 1133 1 CS134 1 CS137 1 BA137M 1 BA140 1 LA140 1 CE141 1 PU238 1 PU239 1 PU241 1 AM241 1 CM242 1 CM244 1 10 0.2 0.4 0.9 1.35 1.8 2.2 2.6 3.0 4.0 5.0 M Calc. No. PM-750, Rev. 1, Attachment C, Page C-50 of C-52

JII J'/'?- 7.5CJ 1l~5:J..~ INPUT

SUMMARY

Number of Isotopes: 29 Isotopes to be considered and amount (Ci): 1 3 0 H3 1.000E+00 6 14 0 C14 1.000E+00 24 51 0 CR51 1.000E+00 25 54 0 MN54 1.000E+00 26 55 0 FE55 1.000E+00 27 58 0 C058 1.000E+00 27 60 0 C060 1.000E+00 28 63 0 NI63 1.000E+00 30 65 0 ZN65 1.000E+00 38 90 0 SR90 1.000E+00 38 92 0 SR92 1.000E+00 41 95 0 NB95 1.000E+00 43 99 0 TC99 1.000E+00 47 110 1 AG110M 1.000E+00 53 129 0 1129 1.000E+00 53 131 0 1131 1.000E+00 53 133 0 1133 1.000E+00 55 134 0 CS134 1.000E+00 55 1370 CS137 1.000E+00 56 137 1 BA137M 1.000E+00 56 140 0 BA140 1.000E+00 57 140 0 LA140 1.000E+00 58 141 0 CE141 1.000E+00 94 238 0 PU238 1.000E+00 94 239 0 PU239 1.000E+00 94 241 0 PU241 1.000E+00 95 241 0 AM241 1.000E+00 96 242 0 CM242 1.000E+00 96 244 0 CM244 1.000E+00 Number of Energy Groups: 10 Output as (P)hotons/sec or (M)EV/sec: M Energy Group Upper Boundaries (MEV) 2.00E-01 4.00E-01 9.00E-01 1.35E+00 1.BOE+00 2.20E+00 2.60E+00 3.00E+00 4.00E+00 5.00E+00 1 3 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6 14 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 24 51 0 4.14E+07 1. 16E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 25 54 0 5.09E+07 O.OOE+OO 3.09E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 26 55 0 6.14E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 58 0 6.30E+07 O.OOE+OO 3.57E+10 O.OOE+OO 3.20E+OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 27 60 0 O.OOE+OO O.OOE+OO 3.32E+06 9.26E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 28 63 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 30 65 0 1.17E+OB O.OOE+OO 5.37E+08 2.09E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 38 90 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 38 92 0 O.OOE+OO 2.65E+08 7.00E+08 2.49E+09 4.61E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 41 95 0 O.OOE+OO O.OOE+OO 2.83E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 43 99 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 47 110 1 6. 17E+06 1.43E+07 6.70E+10 1.20E+10 2.29E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 53 129 0 9.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 53 131 0 1.49E+OB 1.16E+10 2.31E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 53 133 0 7.0BE+06 1.30E+08 2.02E+10 2.10E+09 6.9BE+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 55 134 0 9.32E+06 3.63E+06 5.48E+10 1.16E+09 1.54E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 55 137 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 56 137 1 9.03E+07 O.OOE+OO 2.20E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 56 140 0 5.57E+08 3.86E+08 4.60E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 57 140 0 6.02E+07 2.35E+09 1.79E+10 3.53E+09 5.64E+10 O.OOE+OO 4.06E+09 O.OOE+OO O.OOE+OO O.OOE+OO Calc. No. PM-750, Rev. 1, Attachment C, Page C-51 of C-52

C<<./'r If f~-7fi:J 58 141 0 2.82E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

                                                                                                       >kd-fJ     !53 94  238 0 5.92E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO 94  239 0 2.42E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO 94  241 0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO 95  241 0 9.73E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO 96  242 0 6.19E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO 96  244 0 5.58E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  O.OOE+OO O.OOE+OO   O.OOE+OO  O.OOE+OO TOTALS 6.12E+09 1.60E+10 2.85E+11 1.35E+11 1.27E+11 O.OOE+OO 4.06E+09 O.OOE+OO O.OOE+OO O.OOE+OO Calc. No. PM-750, Rev. 1, Attachment C, Page C-52 of C-52

Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August 2009 Project: Peach Bottom Atomic Power Station Job No. NCS0097 Container Drop Accident Analysis Program(s) used Rev No. Rev Date Calculation Set No.: PM-lSO, Rev. 1 Excel for Attachment Spreadsheets N/A N/A Status [ ] Prelim. [X] Final [ ] Void URS Prequalification [ ] Yes [X] No Run No.

Description:

Analysis

Description:

Spreadsheets were used to execute arithmetic manipulations of numbers, for various applications within the attachments of this analysis. As a first step, it was verified that the spreadsheets duplicated the calculated values. All of the inputs were checked for consistency with their source and their use, and all results were checked for consistency with expected values. Spreadsheet formula pages are included with the calculations. The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established. By: On: 8/2009 Run by: W. Golden .-U/~ Checked by: H. Rothstein

                             ~ r~~

Approved by: D. Gardner ~~ Remarks: These spreadsheets were applied in a straight-forward manner and were hand checked. Calc. No. PM-750, Rev. 1, Attachment D, Page D-I of D-2

Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August 2009 Project: Peach Bottom Atomic Power Station Job No. NCS0097 Container DroD Accident Analvsis Program(s) used Rev No. Rev Date Calculation Set No.: PM-750, Rev. 1 Microshield 8.01 (MC-201) 0 4/2009 Status [ ] Prelim. [X] Final [ ] Void URS Prequalification [X] Yes [ ] No Run No.

Description:

Analysis

Description:

MicroShield was used to develop HIC isotope mixes and adjust them for decay and to produce the HIC contact dose rates, for use of the resulting Curie levels for each isotope in the Excel spreadsheet. All of the inputs were checked for consistency with their source and their use, and all results were checked for consistency with expected values. The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established. By: On: 8/2009 Run by: W. Golden ~~. Checked by: H. Rothstein ~ !~-

                                ~~J---<-'~'R._,-

Approved by: D. Gardner Remarks: The program was applied in a straight-forward manner and was hand checked. Calc. No. PM-750, Rev. 1, Attachment D, Page 0-2 of 0-2}}