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 SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E 1 of 32 APPENDIX E FIRE HAZARD ANALYSIS REPORT FORINTERIM RADWASTE STORAGE FACILITY PEACH BOTTOM ATOMIC POWER STATION TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 2 of 32 INTRODUCTION

1.0 Scope

1.0.1 This section consists of a review of fire protec tion 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 LoadingElectrical 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.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 3 of 32

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).

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 4 of 32

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.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 5 of 32

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. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 6 of 32

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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 7 of 32 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.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 8 of 32 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 9 of 32 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 10 of 32 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 & TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 11 of 32 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 12 of 32 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: 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. 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.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 13 of 32 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." TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 14 of 32 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 38 o F (Normal facility temperature is maintained at a minimum of 40 o 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 15 of 32 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, CO 2, 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 - 78 o F Truck Bay/DAW Staging Area 65 - 104 o F DAM Storage Area 45 - 104 o F Cell Storage Area (including cell interior) 45 - 104 o F TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 16 of 32 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. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 17 of 32 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 requiredfor 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. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 18 of 32

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

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 19 of 32 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

3.1 WALLNORTH

EAST SOUTH WEST 3.2 FLOOR 3.3 CEILING 3.4 DOORS

3.5 ROOFMATERIAL

30 concrete 30 concrete 30 concrete 30 concrete 18 or 24 concrete (unexcavated beneath) 24 concrete

12x16 stl. Rollup 7x 31/2 HM 10 x 14 stl. rollup 68 x 31/2 HM 2 conc. MIN. FIRE RATING N/A ext. wall N/A ext. wall None N/A ext. wall N/A el. 135-6

N/A N/A ext. N/A ext. N/A ext. 90 min. -B label N/A ext. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 20 of 32

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: Control Rooms, Access Control Area/Records Center (72 - 78 o C) Truck Bay/DAW Staging Area (65 - 104 o C) DAW Storage Area (45 - 104 o C) Cell Storage Area (45-104 o C) 8.0 FIRE PROTECTION

8.1 SUPPRESSION

8.2 DETECTION

8.3 MANUAL

8.4 EXTINGUISHERS

8.5 OTHER

TYPEAutomatic Fire Suppression Smoke detectors in truck bay Manual Hoses 20 lb class ABC or BC per NFPA 10 None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 21 of 32 COMBUSTIBLEAMOUNT HEAT OF COMBUSTION TOTAL HEAT POTENTIAL HEATPOTENTIAL 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 Class B/C 950 lbs 6500 lbs 20,000 Btu/lb 18,800 Btu/lb 19,000,000 Btu 122,200,000 Btu 10,276 Btu/sq.ft. 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 9.5 TEMPERATURE: 1805 O 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.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 22 of 32 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

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 23 of 32

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

3.1 WALLNORTH

EAST SOUTH WEST 3.2 FLOOR 3.3 CEILING 3.4 DOORS west south 3.5 ROOFMATERIAL 30 conc. 12 CMU & 30concrete 36 conc. 30 conc. 20 conc. 30 conc. 7 -2 X 3 HM (2) 7 2 X 3 HM N/A. MIN. FIRE RATING N/A ext. wall N/A ext. wall 3-hr (lower) N/A ext. wall N/A slab on grade

N/A ext. 90 min. B-label N/A ext.

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 24 of 32

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, CO 2 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 25 of 32 COMBUSTIBLE AMOUNT HEAT OF COMBUSTION TOTAL HEAT POTENTIAL HEATPOTENTIAL 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

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

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 27 of 32 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

3.0 WALLNORTH

EAST SOUTH WEST 3.1 FLOOR 3.2 CEILING 3.3 DOORS 3.4 ROOFMATERIAL 36 concrete 30 concrete 36 36 concrete 30 reinforced concrete mat stiffened by internal rebar 24 concrete (cover over cell) None 2 concrete. MIN. FIRE RATING None 3-hr (lower) N/A ext. wall N/A ext. wall N/A slab on grade

N/A ext. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 28 of 32

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 17'5" X 36') VOLUME

6,897 CU.FT 5.2 CELL (15'6" X 17'5" X 36') VOLUME

9,719 CU.FT 5.3 CELL (11' X 14'10" X 36') VOLUME

5,874 CU.FT 5.4 CELL (15'6" X 14'10" X 36') VOLUME: 8,277 CU.FT 5.5 CELL (11' X 17'11" X 36') VOLUME

7,095 CU.FT 5.6 CELL (15'6" X 17'11" X 36') VOLUME: 9,998 CU.FT

TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 29 of 32

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 (45-104 o C) 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.

Combustible Amount Units H eat of Combustion Units Total Heat Potential Units HeatPotential Units HDPE 16 HICs Cell (ft 2) H ICs 15,200 lbs 20,000 Btu/lb 3.04E+08 Btu (15.5x14.8) 1.322+06 Btu/sq.ft C lass B/C: 6500 104,000 Per HIC lbs 18,800Btu/lb 1.955E+9 Btu 8.503E+6 Btu/sq.ft Transients: 0 lbs

9.2 TOTAL

FIRE LOADING IN AREA: 9.826x10 6 BTU/sq.ft.

9.3 TOTAL

HEAT POTENTIAL: 2.26x10 9 BTU 9.4 Equivalent Severity: over 5 days TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 30 of 32 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 TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 31 of 32 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 RECOMMENDATIONA 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. TECHNICAL REPORT SUPPORTING ENGINEERING CHANGE REQUEST Project No. 29487-NCS0097 ECR No. 09-00301 Rev. 0 Date: 12/03/09 Appendix E- 32 of 32 6.4 FIRE PROTECTION EQUIPMENT LOCATION SKETCH

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

Sh c.M'R A o eSlgn nalysis aJor eVlslon over eet 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 Is this Design Analysis Safeguards Information? 16 Yes 0 No I:8J If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? 11 Yes 0 No I:8J If yes, 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. %a.b=t Preparer: Will;OM, Print Name'SJ;Name Date , Method of Review: 21 Detailed Review I:8J Alternate Calculations (attached) 0 TestingD Reviewer: 22 v, I lIVU-17/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 Analyses Only;Donald Gardner'ftc 71 fti?v',;;({lin'i 7(2'f J!External Approver:" r p,_./,..I v Pnn!Name U,:nName Date Exelon Reviewer: 7.:J, Ai5C/Sit lkkutJ9 A/" PnntName U 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 DESIGN ANALYSIS NO.PM-750 REV: 1---No N/A 1.Do assumptions have sufficient rationale? 0 0 2.Are assumptions compatible with the way the plant is operated and with the00 licensing basis?3.Do the design inputs have sufficient rationale? 0 0 4.Are design inputs correct and reasonable with critical parameters identified, if0 0 appropriate?5.Are design inputs compatible with the way the plant is operated and with the00 licensing basis?:/6.Are Engineering Judgments clearly documented and justified? 0 0 7.Are EngineeringJudgmentscompatible with the way the plant is operated00 and with the licensing basis?8.Do the results and conclusions satisfy the purpose and objective of the ui 0 0 Design Analysis?9.Are the results and conclusions compatible with the way the plant is operated 0 0 and with the licensing basis?10.Does the Design Analysis include theapplicabledesign basis00 documentation? 11.Have any limitations on the use of the results been identified and transmitted00to the appropriate organizations? rn/12.Are there any unverified assumptions? 0 0 13.Do all unverified assumptions have a tracking and closure mechanism in00place?14.Have all affected design analyses been documented on the Affected00 or'Documents List (ADL)for the associated Configuration Change?Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments?(If the input sources or15.analysis methodology are based on an out-of-date methodology or code,00 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 0 DRFs)been reviewed when necessary? 17.Havemargin impacts been identified and documented appropriately for any 0 negative impacts (Reference ER-AA-2007)?, Msc.i'lijiZ#1 EXELON REVIEWER:DATE: 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 Limerick Container Contact Dose Rate for Nominal Analysis 250 rem/hr Assumption 3.1.1 Peach Bottom Container Contact Dose Rate for Bounding Analysis 400 rem/hr Assumption 3.1.1 Container Isotopic Mix: Limerick Power Station UFSAR Table 11.4-8, RWCU Phase Separator column, decayed 60 days Reference (9), with 60 day decay

conservatively used as typical practice is

for resins to not be packaged until at

least 60 days after

discharge. Container Isotopic Mix: Peach Bottom Station Table 1 in Attachment A Reference (6) Resin Density: Used for Container Content 0.9 g/cc Assumption 3.1.3 Resin Density: Used for Release Fraction 0.69 g/cc Reference (6) Assumption 3.1.3 Number of Containers Dropped 1 Assumption 3.1.2 Container Drop Height 46-9(1424.94cm) Reference (6) 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. Calculated 2-hour X/Q at the Exclusion Area Boundary (EAB) for

ground level release (sec/m 3) 9.20E-04 Reference (6) Fraction Released: Container Drop 3% Reference (6) Breathing Rate: at EAB 3.47E-04 Reference (6) 3.Assumptions3.1Technically Justified Assumptions 3.1.1Analyses 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. 3.1.2The 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. 3.1.3A 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. 3.2Assumptions 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) 5.1Design 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.

5.2Internal Events 5.2.1Container 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 Analysis6.1Bounding 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 m 3/s, from Reference 6; and (6) Dose Conversion Factors from Reference (5). 7.ResultsThis 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. Containers are assumed to have a contact dose rate of 400 R/hr, which is the maximum anticipated in the LLRWSF. 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. 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.

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69ABCDEFGHIJNuclideCiBr-838.97E-01Br-841.81E-02Br-851.86E-05I-1311.70E+02 I-1328.43E+00I-1336.73E+01I-1345.44E+00I-1351.98E+01Rb-894.27E-02Cs-1345.21E+00Cs-1361.11E+00Cs-1371.24E+01Cs-1383.68E-01Na-242.24E+01P-321.15E+01Cr-514.63E+02Mn-541.00E+01Mn-561.69E+01Fe-551.74E+02Fe-593.52E+00Co-582.69E+01Co-607.07E+01Ni-631.79E-01Ni-651.01E-01Cu-646.44E+01Zn-653.27E+01Zn-692.23E-01 Sr-891.24E+01Sr-901.07E+00Sr-916.22E+00Sr-923.62E+00Y-918.37E+00Y-927.08E+00Y-936.66E+00Zr-959.25E-01Zr-971.43E-02Nb-951.14E+00Nb-983.12E-01Mo-992.35E+01Tc-99m3.91E+01Tc-1016.18E-01Tc-1049.90E-01 Ru-1032.20E+00Ru-1051.30E+00Ru-1065.07E-01Ag-110m1.64E-01Te-129m4.12E+00Te-131m5.17E-01Te-1321.37E-01Ba-1391.54E+00 Ba-1402.10E+01Ba-1411.23E-01Ba-1422.14E-02La-1421.02E+00Ce-1413.29E+00Ce-1431.71E-01Ce-1444.99E-01Pr-1432.38E+00Nd-1471.39E-01W-1871.22E+00Np-2396.92E+01 3.36E+01 1.44E+03 LGS UFSAR Table 11.4-8 EXPECTED RADIONUCLIDE INVENTORIES OF SOLID WASTE MANAGEMENT SYSTEM COMPONENTS Calc. No. PM-750, Rev. 1, Attachment A, Page A-1 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66ABCDEFGHIByCheckedRun DateRun TimeDuration13-Aug-099:22:45 AM0:00:0 6 LGS 11.4-8 before decay and resizin g 7 - Cylinder Volume - Side Shield sHeight182.88 cm (6 ft)Radius76.2 cm (2 ft 6.0 in )AXYZ#178.74 cm (2 ft 7.0 in )91.44 cm (3 ft)0.0 cm (0 in)Shield NDimensionMaterialDensitySource2.04e+05 in ³Water0.9 Transition Air0.0012 2 A ir Gap Air0.0012 2CiBqµCi/cm³Bq/cm³1.64E-016.07E+0 9 4.92E-0 2 1.82E+0 31.17E+014.34E+113.52E+0 0 1.30E+0 5 1.54E+0 0 5.70E+1 04.62E-011.71E+0 42.10E+017.77E+116.30E+0 0 2.33E+0 51.23E-014.55E+0 9 3.69E-0 2 1.36E+0 3 2.14E-0 2 7.92E+0 8 6.41E-0 3 2.37E+0 28.97E-013.32E+1 02.69E-019.95E+0 3 1.81E-0 2 6.70E+0 8 5.43E-0 3 2.01E+0 2 3.29E+0 01.22E+119.86E-013.65E+0 41.71E-016.33E+0 9 5.13E-0 2 1.90E+0 34.99E-011.85E+1 01.50E-015.53E+0 32.69E+019.95E+118.06E+0 0 2.98E+0 57.07E+012.62E+1 22.12E+017.84E+0 5 4.63E+0 2 1.71E+1 3 1.39E+0 2 5.14E+0 6 5.21E+0 01.93E+111.56E+0 0 5.78E+0 4 1.11E+0 0 4.11E+1 03.33E-011.23E+0 41.24E+014.59E+113.72E+0 0 1.38E+0 53.68E-011.36E+1 01.10E-014.08E+0 36.44E+012.38E+1 21.93E+017.14E+0 5 1.74E+0 2 6.44E+1 25.22E+011.93E+0 6 3.52E+0 01.30E+111.06E+0 0 3.90E+0 4 1.70E+0 2 6.29E+1 25.10E+011.89E+0 6 8.43E+0 03.12E+112.53E+0 0 9.35E+0 46.73E+012.49E+1 22.02E+017.46E+0 5 5.44E+0 02.01E+111.63E+0 0 6.03E+0 41.98E+017.33E+115.94E+0 0 2.20E+0 52.10E+017.77E+116.30E+0 0 2.33E+0 5 1.02E+0 0 3.77E+1 03.06E-011.13E+0 41.00E+013.70E+113.00E+0 0 1.11E+0 51.69E+016.25E+115.07E+0 0 1.87E+0 52.35E+018.70E+117.04E+0 0 2.61E+0 52.24E+018.29E+116.71E+0 0 2.48E+0 5 1.14E+0 0 4.22E+1 03.42E-011.26E+0 43.12E-011.15E+1 0 9.35E-0 2 3.46E+0 31.39E-015.14E+0 9 4.17E-0 2 1.54E+0 31.79E-016.62E+0 9 5.37E-0 2 1.99E+0 31.01E-013.74E+0 9 3.03E-0 2 1.12E+0 36.92E+012.56E+1 22.07E+017.68E+0 51.15E+014.26E+113.45E+0 0 1.28E+0 5 MicroShield 8.01 Washington Group International (8.00-0000) P-32 Nd-147 Ni-63 Ni-65 Np-239 Mo-99 Na-24 Nb-95 Nb-98 La-140 La-142 Mn-54 Mn-56 I-132 I-133 I-134 I-135 Cu-64 Fe-55 Fe-59 I-131 Cs-134 Cs-136 Cs-137 Cs-138 Ce-144 Co-58 Co-60 Cr-51 Br-83 Br-84 Ce-141 Ce-143 Ba-139 Ba-140 Ba-141 Ba-142 Library: ICRP-38 Nuclide Ag-110m Ba-137m Source Input: Grouping Method - Linear Energy Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Included Source Dimensions Dose Points Shields Project Info Case Title Description Geometry Date Filename LGS.msd Calc. No. PM-750, Rev. 1, Attachment A, Page A-2 of A-11 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128ABCDEFGHI 2.38E+0 0 8.81E+1 07.13E-012.64E+0 44.92E-011.82E+1 01.47E-015.46E+0 3 4.27E-0 2 1.58E+0 9 1.28E-0 2 4.74E+0 2 2.19E+0 0 8.12E+1 06.58E-012.43E+0 45.07E-011.88E+1 01.52E-015.62E+0 3 2.20E+0 0 8.14E+1 06.59E-012.44E+0 4 1.30E+0 0 4.81E+1 03.90E-011.44E+0 45.07E-011.88E+1 01.52E-015.62E+0 31.24E+014.59E+113.72E+0 0 1.38E+0 5 1.07E+0 0 3.96E+1 03.21E-011.19E+0 4 6.22E+0 02.30E+111.86E+0 0 6.90E+0 4 3.62E+0 01.34E+111.09E+0 0 4.02E+0 46.18E-012.29E+1 01.85E-016.85E+0 39.90E-013.66E+1 02.97E-011.10E+0 43.91E+011.45E+1 21.17E+014.34E+0 5 4.12E+0 01.52E+111.24E+0 0 4.57E+0 45.17E-011.91E+1 01.55E-015.73E+0 31.37E-015.07E+0 9 4.11E-0 2 1.52E+0 3 1.22E+0 0 4.51E+1 03.66E-011.35E+0 4 1.07E+0 0 3.96E+1 03.21E-011.19E+0 4 8.37E+0 03.10E+112.51E+0 0 9.28E+0 4 7.08E+0 02.62E+112.12E+0 0 7.85E+0 4 6.66E+0 02.46E+112.00E+0 0 7.39E+0 43.27E+011.21E+1 2 9.80E+0 0 3.63E+0 52.23E-018.25E+0 9 6.68E-0 2 2.47E+0 39.25E-013.42E+1 02.77E-011.03E+0 4 1.43E-0 2 5.29E+0 8 4.29E-0 3 1.59E+0 2 30 30 60 Fluence Rat e Fluence Rat e Exposure Rat e Exposure Rat e MeV/cm²/se c MeV/cm²/se cmR/hrmR/hrNo BuildupWith BuildupNo BuildupWith Buildup 1.30E+1 3 2.80E+0 5 9.71E+0 5 1.29E+0 3 4.47E+0 3 3.38E+1 2 1.16E+0 6 4.30E+0 6 2.19E+0 3 8.14E+0 3 5.86E+1 2 2.81E+0 6 9.23E+0 6 5.46E+0 3 1.79E+0 4 5.40E+1 2 4.53E+0 6 1.24E+0 7 8.87E+0 3 2.43E+0 4 3.53E+1 2 4.98E+0 6 1.18E+0 7 9.46E+0 3 2.25E+0 46.25E+111.04E+0 6 2.38E+0 6 1.95E+0 3 4.45E+0 3 3.80E+1 2 9.06E+0 6 1.91E+0 7 1.63E+0 4 3.43E+0 4 3.04E+1 2 8.91E+0 6 1.80E+0 7 1.55E+0 4 3.13E+0 4 1.11E+1 2 3.47E+0 6 6.92E+0 6 5.97E+0 3 1.19E+0 48.48E+113.31E+0 6 6.33E+0 6 5.47E+0 3 1.05E+0 42.87E+111.32E+0 6 2.45E+0 6 2.11E+0 3 3.92E+0 3 2.30E+1 0 1.19E+0 5 2.17E+0 5 1.86E+0 2 3.39E+0 21.07E+116.27E+0 5 1.12E+0 6 9.54E+0 2 1.70E+0 3 1.60E+1 0 1.07E+0 5 1.86E+0 5 1.58E+0 2 2.75E+0 2 5.43E+1 0 4.09E+0 5 6.98E+0 5 5.90E+0 2 1.01E+0 3 9.38E+0 9 7.69E+0 4 1.29E+0 5 1.09E+0 2 1.83E+0 28.29E+117.26E+0 6 1.21E+0 7 1.01E+0 4 1.69E+0 4 5.17E+0 9 5.07E+0 4 8.29E+0 46.90E+011.13E+0 2 1.31E+0 9 1.39E+0 4 2.24E+0 41.86E+013.00E+01 2.18E+0 9 2.53E+0 4 4.02E+0 43.31E+015.28E+01 5.14E+0 8 6.26E+0 3 9.89E+0 3 8.13E+0 0 1.28E+01 9.61E+0 8 1.27E+0 4 1.98E+0 41.62E+012.53E+01 6.33E+0 8 9.11E+0 3 1.40E+0 41.14E+011.75E+01 8.84E+0 7 1.32E+0 3 2.02E+0 3 1.64E+0 0 2.51E+0 0 1.24E+0 7 2.00E+0 2 3.02E+0 22.44E-013.68E-014.19E+134.96E+071.09E+088.68E+041.94E+05 4.1711 Totals 3.4433 3.6416 3.8609 3.9651 2.7542 2.9708 3.1388 3.333 2.1111 2.2948 2.4906 2.6343 1.3798 1.6035 1.793 1.941 0.8063 0.903 1.1516 1.3239 0.0394 0.2952 0.3768 0.561 Y Direction (axial) ResultsEnergy (MeV)Activity (Photons/sec) Buildup: The material reference is Source Integration Parameters Radial Circumferential Zn-65 Zn-69 Zr-95 Zr-97 Y-90 Y-91 Y-92 Y-93 Te-129m Te-131m Te-132 W-187 Sr-92 Tc-101 Tc-104 Tc-99m Ru-106 Sr-89 Sr-90 Sr-91 Rh-103m Rh-106 Ru-103 Ru-105 Pr-143 Pr-144 Rb-89 Calc. No. PM-750, Rev. 1, Attachment A, Page A-3 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83ABCDEFGHIByCheckedRun DateRun TimeDuration 12-Aug-0 94:04:29 PM0:00:0 7 LGS 11.4-8 with 60 day decay, before resizin g 7 - Cylinder Volume - Side Shield s Heigh t 182.88 cm (6 ft) Radiu s 76.2 cm (2 ft 6.0 in)AXYZ#178.74 cm (2 ft 7.0 in)91.44 cm (3 ft)0.0 cm (0 in)Shield NDimensionMaterialDensity Sourc e 2.04e+05 in ³Water0.9 Transitio n A i r 0.0012 2 A ir Ga p A i r 0.0012 2CiBqµCi/cm³Bq/cm³ 8.06E-2 4 2.98E-1 3 2.42E-2 4 8.94E-2 0 1.85E-0 3 6.83E+0 7 5.54E-0 4 2.05E+011.39E-015.14E+0 9 4.16E-0 2 1.54E+0 31.17E+014.32E+113.50E+0 0 1.30E+0 5 4.8914e-31 5 1.81E-30 4 1.4663e-31 5 5.4251e-3118.03E-012.97E+1 02.41E-018.90E+0 3 1.73E-2 4 6.40E-1 4 5.19E-2 5 1.92E-2 0 3.79E-18 21.40E-1711.14E-18 2 4.21E-17 89.15E-013.39E+1 02.74E-011.02E+0 4 1.25E-1 4 4.63E-0 4 3.75E-1 5 1.39E-1 04.31E-011.60E+1 01.29E-014.78E+0 31.50E+015.53E+114.48E+0 0 1.66E+0 56.92E+012.56E+1 22.07E+017.67E+0 5 1.03E+0 2 3.82E+1 23.09E+011.14E+0 6 4.93E+0 01.82E+111.48E+0 0 5.47E+0 4 6.49E-0 9 2.40E+0 2 1.95E-0 9 7.20E-0 5 4.64E-0 2 1.72E+0 9 1.39E-0 2 5.15E+0 21.24E+014.57E+113.70E+0 0 1.37E+0 5 4.78E-3 3 1.77E-2 2 1.43E-3 3 5.30E-2 9 1.67E+0 2 6.17E+1 25.00E+011.85E+0 6 1.38E+0 0 5.12E+1 04.15E-011.53E+0 4 1.09E-2 5 4.05E-1 5 3.28E-2 6 1.21E-21 1.71E-0 8 6.34E+0 2 5.14E-0 9 1.90E-0 49.64E-013.57E+1 02.89E-011.07E+0 4 4.04E-0 7 1.49E+0 4 1.21E-0 7 4.48E-0 3 9.72E-2 0 3.59E-0 9 2.91E-2 0 1.08E-1 5 5.21E-6 5 1.93E-5 4 1.56E-6 5 5.78E-611.62E-1815.99E-1714.85E-18 2 1.80E-17 78.03E-012.97E+1 02.41E-018.90E+0 3 5.16E-11 3 1.91E-10 2 1.55E-11 3 5.73E-10 9 6.78E-28 22.51E-2712.03E-28 2 7.52E-27 8 8.75E+0 03.24E+112.62E+0 0 9.71E+0 4 1.30E-16 7 4.80E-15 7 3.89E-16 8 1.44E-16 3 6.36E-0 6 2.35E+0 5 1.91E-0 6 7.05E-0 2 2.83E-2 8 1.05E-1 7 8.48E-2 9 3.14E-2 44.14E-111.53E+0 01.24E-114.59E-0 77.92E-012.93E+1 02.37E-018.78E+0 3 3.57E-0 3 1.32E+0 8 1.07E-0 3 3.96E+01 3.45E-2 8 1.28E-1 7 1.03E-2 8 3.83E-2 4 3.04E-2 8 1.12E-1 7 9.10E-2 9 3.37E-2 4 3.15E-0 3 1.16E+0 8 9.44E-0 4 3.49E+011.79E-016.62E+0 9 5.36E-0 2 1.98E+0 3 9.71E-17 4 3.59E-16 3 2.91E-17 4 1.08E-16 9 1.48E-0 6 5.48E+0 4 4.44E-0 7 1.64E-0 26.26E-012.32E+1 01.88E-016.95E+0 34.41E-211.63E-1 01.32E-214.89E-1 7 1.97E-2 4 7.29E-1 4 5.91E-2 5 2.19E-2 0 1.51E-0 3 5.57E+0 7 4.52E-0 4 1.67E+01 5.09E-2 7 1.88E-1 6 1.53E-2 7 5.65E-2 3 1.80E-2 4 6.64E-1 4 5.38E-2 5 1.99E-2 0 MicroShield 8.0 1 Washington Group International (8.00-0000) Po-211 Po-215 P-32 Pa-231 Pb-211 Pm-147 Nd-147 Ni-63 Ni-65 Np-239 Nb-95m Nb-97 Nb-97m Nb-98 Mo-99 Na-24 Nb-93m Nb-95 La-141 La-142 Mn-54 Mn-56 I-134 I-135 Kr-83m La-140 I-129 I-131 I-132 I-133 Cu-64 Fe-55 Fe-59 Fr-223 Cs-135 Cs-136 Cs-137 Cs-138 Co-58 Co-60 Cr-51 Cs-134 Br-84 Ce-141 Ce-143 Ce-144 Ba-141 Ba-142 Bi-211 Br-83 Ag-110m Ba-137m Ba-139 Ba-140 Library: ICRP-38 Nuclide Ac-227 Ag-110 Source Input: Grouping Method - Linear Energy Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Included Source Dimensions Dose Points Shields Project Info Case Title Description Geometry Date Filename Limerick.msd Calc. No. PM-750, Rev. 1, Attachment A, Page A-4 of A-11 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 166ABCDEFGHI1.12E-014.13E+0 9 3.35E-0 2 1.24E+0 34.25E-011.57E+1 01.27E-014.71E+0 3 7.67E-0 3 2.84E+0 8 2.30E-0 3 8.51E+01 1.85E-0 5 6.86E+0 5 5.56E-0 6 2.06E-01 1.72E-2 4 6.37E-1 4 5.16E-2 5 1.91E-2 0 6.65E-1 4 2.46E-0 3 1.99E-1 4 7.38E-1 07.62E-012.82E+1 02.28E-018.45E+0 3 1.03E-1 3 3.80E-0 3 3.08E-1 4 1.14E-0 94.53E-011.68E+1 01.36E-015.02E+0 3 1.80E-2 4 6.65E-1 4 5.39E-2 5 1.99E-2 07.63E-012.82E+1 02.29E-018.46E+0 3 3.04E-9 8 1.12E-8 7 9.11E-9 9 3.37E-9 44.53E-011.68E+1 01.36E-015.02E+0 3 1.25E-1 5 4.61E-0 5 3.74E-1 6 1.38E-11 5.44E+0 02.01E+111.63E+0 0 6.04E+0 4 1.07E+0 0 3.94E+1 03.19E-011.18E+0 4 1.46E-4 5 5.40E-3 5 4.37E-4 6 1.62E-41 4.00E-16 0 1.48E-14 9 1.20E-16 0 4.43E-15 6 9.57E-0 7 3.54E+0 4 2.87E-0 7 1.06E-0 2 6.13E-0 6 2.27E+0 5 1.84E-0 6 6.79E-0 27.78E-012.88E+1 02.33E-018.63E+0 3 1.19E+0 0 4.42E+1 03.58E-011.33E+0 4 4.14E-1 6 1.53E-0 5 1.24E-1 6 4.59E-1 2 1.84E-1 5 6.80E-0 5 5.51E-1 6 2.04E-11 3.92E-0 7 1.45E+0 4 1.18E-0 7 4.35E-0 3 3.32E-2 4 1.23E-1 3 9.96E-2 5 3.69E-2 0 2.75E-1 5 1.02E-0 4 8.25E-1 6 3.05E-11 2.00E-2 4 7.39E-1 4 5.99E-2 5 2.22E-2 0 2.83E-1 5 1.05E-0 4 8.48E-1 6 3.14E-11 8.89E-1 9 3.29E-0 8 2.67E-1 9 9.86E-1 5 9.71E-0 2 3.59E+0 9 2.91E-0 2 1.08E+0 3 4.90E-0 3 1.81E+0 8 1.47E-0 3 5.43E+01 7.12E-0 9 2.63E+0 2 2.13E-0 9 7.89E-0 5 1.09E-4 6 4.02E-3 6 3.26E-4 7 1.21E-4 2 8.34E-6 6 3.09E-5 5 2.50E-6 6 9.25E-6 2 1.07E+0 0 3.94E+1 03.19E-011.18E+0 4 4.13E+0 01.53E+111.24E+0 0 4.58E+0 4 9.24E-4 6 3.42E-3 5 2.77E-4 6 1.02E-41 6.66E-12 22.46E-1112.00E-12 2 7.39E-11 8 8.02E-4 3 2.97E-3 2 2.41E-4 3 8.90E-3 92.76E+011.02E+1 2 8.27E+0 0 3.06E+0 5 5.02E-0 9 1.86E+0 2 1.50E-0 9 5.56E-0 54.83E-011.79E+1 01.45E-015.36E+0 3 3.20E-2 8 1.18E-1 7 9.60E-2 9 3.55E-2 4 30 30 60 Fluence Rat e Fluence Rat e Exposure Rat e Exposure Rat e MeV/cm²/se c MeV/cm²/se c mR/h r mR/h rNo BuildupWith BuildupNo BuildupWith Buildup 3.37E+1 2 2.11E+0 3 2.45E+0 3 8.73E+0 2 1.02E+0 33.88E+111.48E+0 5 5.27E+0 5 2.83E+0 2 1.01E+0 3 7.62E+1 0 4.51E+0 4 1.38E+0 58.84E+012.70E+0 28.28E+117.76E+0 5 2.06E+0 6 1.51E+0 3 4.02E+0 3 1.11E+1 2 1.58E+0 6 3.75E+0 6 3.01E+0 3 7.13E+0 3 1.41E+1 0 2.31E+0 4 5.29E+0 44.32E+019.92E+01 3.11E+1 2 7.52E+0 6 1.58E+0 7 1.35E+0 4 2.83E+0 4 2.58E+1 2 7.64E+0 6 1.54E+0 7 1.33E+0 4 2.67E+0 4 7.76E+0 9 2.43E+0 4 4.85E+0 44.18E+018.33E+01 3.13E+1 0 1.22E+0 5 2.33E+0 5 2.02E+0 2 3.85E+0 2 1.03E+0 74.68E+018.69E+017.50E-0 2 1.39E-01 7.52E+0 63.98E+017.20E+016.18E-0 2 1.12E-01 1.57E+0 8 9.71E+0 2 1.71E+0 3 1.46E+0 0 2.58E+0 0 2.57E+0 8 1.78E+0 3 3.08E+0 3 2.61E+0 0 4.52E+0 0 1.03E+0 9 7.90E+0 3 1.35E+0 41.13E+011.93E+01 3.28E+0 7 2.56E+0 2 4.35E+0 23.67E-016.22E-01 3.52E+0 5 3.16E+0 0 5.23E+0 0 4.38E-0 3 7.26E-0 3 2.00E+0 7 1.89E+0 2 3.10E+0 22.59E-014.26E-01 7.79E+0 68.20E+011.33E+0 21.10E-011.78E-01 1.49E+0 61.71E+012.72E+012.25E-0 2 3.58E-0 2 1.98E-27 3 2.40E-27 8 3.79E-27 83.12E-2814.93E-281 5.93E-27 3 7.82E-27 8 1.22E-27 79.98E-2811.56E-28 06.49E-219.35E-2 6 1.44E-2 5 1.17E-2 8 1.80E-2 8 2.64E-27 4 4.01E-27 9 6.11E-27 9 4.95E-28 2 7.55E-28 2 8.79E-2 3 1.45E-2 7 2.18E-2 7 1.76E-3 0 2.64E-3 01.15E+131.79E+073.81E+073.28E+046.91E+04 3.8674 4.0104 2.5206 2.5532 2.7986 2.9009 1.7798 1.9636 4.2389 Totals 3.1182 3.3128 3.4345 3.6364 2.1784 2.3476 1.1628 1.3321 1.3846 1.6033 0.4384 0.6068 0.8128 0.8927Energy (MeV)Activity (Photons/sec) 0.0074 0.3192 Radial Circumferential Y Direction (axial) Results Zr-95 Zr-97 Buildup: The material reference is Source Integration Parameters Y-93 Zn-65 Zn-69 Zr-93 Y-90 Y-91 Y-91m Y-92 Xe-133 Xe-133m Xe-135 Xe-135m Tl-207 U-235 W-187 Xe-131m Te-131m Te-132 Th-227 Th-231 Tc-99m Te-129 Te-129m Te-131 Sr-92 Tc-101 Tc-104 Tc-99 Sm-147 Sr-89 Sr-90 Sr-91 Rn-219 Ru-103 Ru-105 Ru-106 Re-187 Rh-103m Rh-105 Rh-106 Pr-144m Pu-239 Ra-223 Rb-89 Pr-143 Pr-144 Calc. No. PM-750, Rev. 1, Attachment A, Page A-5 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83ABCDEFGHIByCheckedRun DateRun TimeDuration 12-Aug-0 94:07:45 PM0:00:0 7 LGS 11.4-8 with 60 day decay and resizin g 7 - Cylinder Volume - Side Shield s Heigh t 182.88 cm (6 ft) Radiu s 76.2 cm (2 ft 6.0 in)AXYZ#178.74 cm (2 ft 7.0 in)91.44 cm (3 ft)0.0 cm (0 in)Shield NDimensionMaterialDensity Sourc e 2.04e+05 in ³Water0.9 Transitio n A i r 0.0012 2 A ir Ga p A i r 0.0012 2CiBqµCi/cm³Bq/cm³ 2.33E-2 3 8.63E-1 3 6.99E-2 4 2.59E-1 9 5.35E-0 3 1.98E+0 8 1.60E-0 3 5.93E+014.02E-011.49E+1 01.20E-014.46E+0 33.38E+011.25E+1 21.01E+013.75E+0 5 1.4160e-31 4 5.24E-30 4 4.2445e-31 5 1.5705e-31 0 2.32E+0 0 8.60E+1 06.96E-012.58E+0 4 5.01E-2 4 1.85E-1 3 1.50E-2 4 5.56E-2 01.10E-1814.06E-1713.29E-18 2 1.22E-17 7 2.65E+0 0 9.80E+1 07.94E-012.94E+0 4 3.62E-1 4 1.34E-0 3 1.09E-1 4 4.02E-1 0 1.25E+0 0 4.62E+1 03.74E-011.38E+0 44.33E+011.60E+1 21.30E+014.80E+0 5 2.00E+0 2 7.41E+1 26.00E+012.22E+0 6 2.99E+0 2 1.11E+1 38.95E+013.31E+0 61.43E+015.28E+114.28E+0 0 1.58E+0 5 1.88E-0 8 6.95E+0 2 5.63E-0 9 2.08E-0 41.34E-014.97E+0 9 4.03E-0 2 1.49E+0 33.58E+011.32E+1 21.07E+013.97E+0 5 1.38E-3 2 5.12E-2 2 4.14E-3 3 1.53E-2 8 4.83E+0 2 1.79E+1 3 1.45E+0 2 5.36E+0 6 4.00E+0 01.48E+111.20E+0 0 4.44E+0 4 3.17E-2 5 1.17E-1 4 9.49E-2 6 3.51E-21 4.96E-0 8 1.84E+0 3 1.49E-0 8 5.50E-0 4 2.79E+0 01.03E+118.37E-013.10E+0 4 1.17E-0 6 4.33E+0 4 3.51E-0 7 1.30E-0 2 2.81E-1 9 1.04E-0 8 8.43E-2 0 3.12E-1 5 1.51E-6 4 5.58E-5 4 4.52E-6 5 1.67E-6 04.69E-1811.73E-17 01.40E-1815.20E-17 7 2.32E+0 0 8.60E+1 06.96E-012.58E+0 4 1.50E-11 2 5.53E-10 2 4.48E-11 3 1.66E-10 81.96E-2817.27E-2715.89E-28 2 2.18E-27 72.53E+019.38E+117.60E+0 0 2.81E+0 5 3.76E-16 7 1.39E-15 6 1.13E-16 7 4.17E-16 3 1.84E-0 5 6.81E+0 5 5.51E-0 6 2.04E-01 8.18E-2 8 3.03E-1 7 2.45E-2 8 9.08E-2 4 1.20E-1 0 4.43E+0 03.59E-111.33E-0 6 2.29E+0 0 8.48E+1 06.87E-012.54E+0 4 1.03E-0 2 3.83E+0 8 3.10E-0 3 1.15E+0 2 9.99E-2 8 3.70E-1 7 2.99E-2 8 1.11E-2 3 8.79E-2 8 3.25E-1 7 2.63E-2 8 9.75E-2 4 9.11E-0 3 3.37E+0 8 2.73E-0 3 1.01E+0 25.18E-011.91E+1 01.55E-015.74E+0 3 2.81E-17 3 1.04E-16 2 8.43E-17 4 3.12E-16 9 4.29E-0 6 1.59E+0 5 1.29E-0 6 4.75E-0 2 1.81E+0 0 6.71E+1 05.43E-012.01E+0 4 1.28E-2 0 4.73E-1 03.83E-211.42E-1 6 5.70E-2 4 2.11E-1 3 1.71E-2 4 6.33E-2 0 4.36E-0 3 1.61E+0 8 1.31E-0 3 4.84E+01 1.47E-2 6 5.45E-1 6 4.42E-2 7 1.64E-2 2 5.20E-2 4 1.92E-1 3 1.56E-2 4 5.77E-2 0 MicroShield 8.0 1 Washington Group International (8.00-0000) Po-211 Po-215 P-32 Pa-231 Pb-211 Pm-147 Nd-147 Ni-63 Ni-65 Np-239 Nb-95m Nb-97 Nb-97m Nb-98 Mo-99 Na-24 Nb-93m Nb-95 La-141 La-142 Mn-54 Mn-56 I-134 I-135 Kr-83m La-140 I-129 I-131 I-132 I-133 Cu-64 Fe-55 Fe-59 Fr-223 Cs-135 Cs-136 Cs-137 Cs-138 Co-58 Co-60 Cr-51 Cs-134 Br-84 Ce-141 Ce-143 Ce-144 Ba-141 Ba-142 Bi-211 Br-83 Ag-110m Ba-137m Ba-139 Ba-140 Library: ICRP-38 Nuclide Ac-227 Ag-110 Source Input: Grouping Method - Linear Energy Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Included Source Dimensions Dose Points Shields Project Info Case Title Description Geometry Date Filename LGS.msd Calc. No. PM-750, Rev. 1, Attachment A, Page A-6 of A-11 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 166ABCDEFGHI3.23E-011.20E+1 0 9.69E-0 2 3.59E+0 3 1.23E+0 0 4.55E+1 03.69E-011.36E+0 4 2.22E-0 2 8.22E+0 8 6.66E-0 3 2.46E+0 2 5.37E-0 5 1.99E+0 6 1.61E-0 5 5.95E-01 4.98E-2 4 1.84E-1 3 1.49E-2 4 5.53E-2 0 1.93E-1 3 7.13E-0 3 5.77E-1 4 2.14E-0 9 2.20E+0 0 8.16E+1 06.61E-012.45E+0 4 2.98E-1 3 1.10E-0 2 8.92E-1 4 3.30E-0 9 1.31E+0 0 4.85E+1 03.93E-011.45E+0 4 5.20E-2 4 1.92E-1 3 1.56E-2 4 5.77E-2 0 2.21E+0 0 8.17E+1 06.62E-012.45E+0 4 8.79E-9 8 3.25E-8 7 2.64E-9 8 9.75E-9 4 1.31E+0 0 4.85E+1 03.93E-011.45E+0 4 3.61E-1 5 1.34E-0 4 1.08E-1 5 4.00E-111.58E+015.83E+114.72E+0 0 1.75E+0 5 3.09E+0 01.14E+119.25E-013.42E+0 4 4.22E-4 5 1.56E-3 4 1.27E-4 5 4.68E-41 1.16E-15 9 4.28E-14 9 3.47E-16 0 1.28E-15 5 2.77E-0 6 1.02E+0 5 8.30E-0 7 3.07E-0 2 1.77E-0 5 6.56E+0 5 5.32E-0 6 1.97E-01 2.25E+0 0 8.33E+1 06.75E-012.50E+0 4 3.46E+0 01.28E+111.04E+0 0 3.84E+0 4 1.20E-1 5 4.43E-0 5 3.59E-1 6 1.33E-11 5.32E-1 5 1.97E-0 4 1.59E-1 5 5.90E-11 1.14E-0 6 4.20E+0 4 3.40E-0 7 1.26E-0 2 9.62E-2 4 3.56E-1 3 2.88E-2 4 1.07E-1 9 7.97E-1 5 2.95E-0 4 2.39E-1 5 8.84E-11 5.78E-2 4 2.14E-1 3 1.73E-2 4 6.41E-2 0 8.19E-1 5 3.03E-0 4 2.46E-1 5 9.09E-11 2.57E-1 8 9.52E-0 8 7.72E-1 9 2.85E-1 42.81E-011.04E+1 0 8.42E-0 2 3.12E+0 3 1.42E-0 2 5.24E+0 8 4.25E-0 3 1.57E+0 2 2.06E-0 8 7.62E+0 2 6.18E-0 9 2.29E-0 4 3.15E-4 6 1.16E-3 5 9.44E-4 7 3.49E-4 2 2.42E-6 5 8.94E-5 5 7.24E-6 6 2.68E-61 3.09E+0 01.14E+119.25E-013.42E+0 41.20E+014.43E+113.59E+0 0 1.33E+0 5 2.67E-4 5 9.89E-3 5 8.02E-4 6 2.97E-411.93E-1217.13E-1115.78E-12 2 2.14E-11 7 2.32E-4 2 8.59E-3 2 6.96E-4 3 2.58E-3 87.98E+012.95E+1 22.39E+018.85E+0 5 1.45E-0 8 5.37E+0 2 4.35E-0 9 1.61E-0 4 1.40E+0 0 5.17E+1 04.19E-011.55E+0 4 9.27E-2 8 3.43E-1 7 2.78E-2 8 1.03E-2 3 30 30 60 Fluence Rat e Fluence Rat e Exposure Rat e Exposure Rat e MeV/cm²/se c MeV/cm²/se c mR/h r mR/h rNo BuildupWith BuildupNo BuildupWith Buildup 9.74E+1 2 6.10E+0 3 7.09E+0 3 2.53E+0 3 2.94E+0 3 1.12E+1 2 4.29E+0 5 1.53E+0 6 8.19E+0 2 2.92E+0 32.21E+111.31E+0 5 3.99E+0 5 2.56E+0 2 7.82E+0 2 2.40E+1 2 2.25E+0 6 5.97E+0 6 4.38E+0 3 1.16E+0 4 3.21E+1 2 4.58E+0 6 1.09E+0 7 8.70E+0 3 2.06E+0 4 4.07E+1 0 6.67E+0 4 1.53E+0 5 1.25E+0 2 2.87E+0 2 9.01E+1 2 2.18E+0 7 4.58E+0 7 3.90E+0 4 8.20E+0 4 7.48E+1 2 2.21E+0 7 4.46E+0 7 3.84E+0 4 7.74E+0 4 2.25E+1 0 7.04E+0 4 1.40E+0 5 1.21E+0 2 2.41E+0 2 9.06E+1 0 3.53E+0 5 6.75E+0 5 5.84E+0 2 1.12E+0 3 2.97E+0 7 1.35E+0 2 2.52E+0 22.17E-014.03E-01 2.18E+0 7 1.15E+0 2 2.09E+0 21.79E-013.24E-01 4.55E+0 8 2.81E+0 3 4.96E+0 3 4.23E+0 0 7.47E+0 0 7.45E+0 8 5.14E+0 3 8.90E+0 3 7.55E+0 0 1.31E+01 2.98E+0 9 2.29E+0 4 3.89E+0 43.28E+015.59E+01 9.49E+0 7 7.42E+0 2 1.26E+0 3 1.06E+0 0 1.80E+0 0 1.02E+0 6 9.14E+0 01.52E+011.27E-0 2 2.10E-0 2 5.78E+0 7 5.47E+0 2 8.98E+0 27.49E-011.23E+0 0 2.26E+0 7 2.37E+0 2 3.84E+0 23.18E-015.14E-01 4.30E+0 64.94E+017.88E+016.50E-0 2 1.04E-01 5.72E-27 3 6.94E-27 8 1.10E-27 79.02E-2811.43E-28 0 1.72E-27 2 2.26E-27 7 3.53E-27 7 2.89E-28 0 4.51E-28 0 1.88E-2 0 2.71E-2 5 4.16E-2 5 3.39E-2 8 5.21E-2 8 7.63E-27 4 1.16E-27 8 1.77E-27 81.43E-2812.18E-281 2.54E-2 2 4.19E-2 7 6.30E-2 7 5.08E-3 0 7.64E-3 03.33E+135.18E+071.10E+089.49E+042.00E+05 3.8674 4.0104 2.5206 2.5532 2.7986 2.9009 1.7798 1.9636 4.2389 Totals 3.1182 3.3128 3.4345 3.6364 2.1784 2.3476 1.1628 1.3321 1.3846 1.6033 0.4384 0.6068 0.8128 0.8927Energy (MeV)Activity (Photons/sec) 0.0074 0.3192 Radial Circumferential Y Direction (axial) Results Zr-95 Zr-97 Buildup: The material reference is Source Integration Parameters Y-93 Zn-65 Zn-69 Zr-93 Y-90 Y-91 Y-91m Y-92 Xe-133 Xe-133m Xe-135 Xe-135m Tl-207 U-235 W-187 Xe-131m Te-131m Te-132 Th-227 Th-231 Tc-99m Te-129 Te-129m Te-131 Sr-92 Tc-101 Tc-104 Tc-99 Sm-147 Sr-89 Sr-90 Sr-91 Rn-219 Ru-103 Ru-105 Ru-106 Re-187 Rh-103m Rh-105 Rh-106 Pr-144m Pu-239 Ra-223 Rb-89 Pr-143 Pr-144 Calc. No. PM-750, Rev. 1, Attachment A, Page A-7 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73ABCDEFGH9.200E-04X/Q (sec/m^3)3.500E-04Breathing Rate (m^3/sec) 3.000E-02Release Fraction3.70E+12Conversion Factor (rem/Ci per Sv/Bq) 1.00E+00Containers/Accident 2.00E+02Container Contact - Nominal Baseline Analysis (R/hr)2.50E+02Actual Container Contact6.769E-01Total Inhalation DoseIsotopeCi in containerInhaleDCFDose (rem)Ac-2272.33E-231.810E-031.886E-21 0%Ag-1105.35E-030.00E+000.000E+00 0%Ag-110m4.02E-012.170E-083.897E-04 0%Ba-137m3.38E+010.00E+000.000E+00 0%Ba-1391.4160e-3144.640E-110.000E+00 0%Ba-1402.32E+001.010E-091.048E-04 0%Ba-1410.00E+002.180E-110.000E+00 0%Ba-1420.00E+001.110E-110.000E+00 0%Bi-2115.01E-240.00E+000.000E+00 0%Br-831.10E-1812.410E-111.182E-187 0%Br-840.00E+002.610E-110.000E+00 0%Ce-1412.65E+002.420E-092.864E-04 0%Ce-1433.62E-149.160E-101.482E-18 0%Ce-1441.25E+001.010E-075.631E-03 1%Co-584.33E+012.940E-095.685E-03 1%Co-602.00E+025.910E-085.289E-01 78%Cr-512.99E+029.030E-111.205E-03 0%Cs-1341.43E+011.250E-087.970E-03 1%Cs-1351.88E-081.230E-091.033E-12 0%Cs-1361.34E-011.980E-091.188E-05 0%Cs-1373.58E+018.630E-091.379E-02 2%Cs-1380.00E+002.740E-110.000E+00 0%Cu-641.38E-327.480E-114.620E-38 0%Fe-554.83E+027.260E-101.566E-02 2%Fe-594.00E+004.000E-097.156E-04 0%Fr-2233.17E-251.680E-092.377E-29 0%I-1294.96E-084.690E-081.039E-10 0%I-1312.79E+008.890E-091.109E-03 0%I-1321.17E-061.030E-105.382E-12 0%I-1332.81E-191.580E-091.985E-23 0%I-1340.00E+003.550E-110.000E+00 0%I-1351.51E-643.320E-102.237E-69 0%Kr-83m4.69E-1810.00E+000.000E+00 0%La-1402.32E+001.310E-091.360E-04 0%La-1411.50E-1121.570E-101.049E-117 0%La-1421.96E-2816.840E-116.001E-287 0%Mn-542.53E+011.810E-092.049E-03 0%Mn-563.76E-1671.020E-101.713E-172 0%Mo-991.84E-051.070E-098.795E-10 0%Na-248.18E-283.270E-101.196E-32 0%Nb-93m1.20E-107.900E-094.229E-14 0%Nb-952.29E+001.570E-091.608E-04 0%Nb-95m1.03E-026.590E-103.044E-07 0%Nb-979.99E-282.240E-119.996E-34 0%Nb-97m8.79E-280.00E+000.000E+00 0%Nb-980.00E+003.310E-110.000E+00 0%Nd-1479.11E-031.850E-097.532E-07 0%Ni-635.18E-011.700E-093.931E-05 0%Ni-652.81E-1739.320E-111.170E-178 0%Np-2394.29E-066.780E-101.299E-10 0%P-321.81E+004.190E-093.394E-04 0%Pa-2311.28E-203.470E-041.980E-19 0%Pb-2115.70E-242.350E-095.989E-28 0%Pm-1474.36E-031.060E-082.065E-06 0%Po-2111.47E-260.00E+000.000E+00 0%Po-2155.20E-240.00E+000.000E+00 0%Pr-1433.23E-012.190E-093.164E-05 0%Pr-1441.23E+001.170E-116.430E-07 0%Pr-144m2.22E-020.00E+000.000E+00 0%Pu-2395.37E-051.160E-042.781E-04 0%Ra-2234.98E-242.120E-064.719E-25 0%Container Drop Event: Limerick Isotopic: Table 11.4-8 60 day decay Calc. No. PM-750, Rev. 1, Attachment A, Page A-8 of A-11 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119ABCDEFGHRb-890.00E+001.160E-110.000E+00 0%Re-1871.93E-131.470E-111.265E-19 0%Rh-103m2.20E+001.380E-121.359E-07 0%Rh-1052.98E-132.580E-103.430E-18 0%Rh-1061.31E+000.00E+000.000E+00 0%Rn-2195.20E-240.00E+000.000E+00 0%Ru-1032.21E+002.420E-092.388E-04 0%Ru-1058.79E-981.230E-104.833E-103 0%Ru-1061.31E+001.290E-077.555E-03 1%Sm-1473.61E-152.020E-053.258E-15 0%Sr-891.58E+011.120E-087.883E-03 1%Sr-903.09E+003.510E-074.838E-02 7%Sr-914.22E-454.490E-108.471E-50 0%Sr-921.16E-1592.180E-101.127E-164 0%Tc-1010.00E+004.840E-120.000E+00 0%Tc-1040.00E+002.220E-110.000E+00 0%Tc-992.77E-062.250E-092.784E-10 0%Tc-99m1.77E-058.800E-126.972E-12 0%Te-1292.25E+002.420E-112.434E-06 0%Te-129m3.46E+006.470E-099.999E-04 0%Te-1311.20E-151.290E-106.899E-21 0%Te-131m5.32E-151.730E-094.110E-19 0%Te-1321.14E-062.550E-091.293E-10 0%Th-2279.62E-244.370E-061.878E-24 0%Th-2317.97E-152.370E-108.438E-20 0%Tl-2075.78E-240.00E+000.000E+00 0%U-2358.19E-153.320E-051.215E-14 0%W-1872.57E-181.670E-101.920E-23 0%Xe-131m2.81E-010.00E+000.000E+00 0%Xe-1331.42E-020.00E+000.000E+00 0%Xe-133m2.06E-080.00E+000.000E+00 0%Xe-1353.15E-460.00E+000.000E+00 0%Xe-135m2.42E-650.00E+000.000E+00 0%Y-903.09E+002.280E-093.143E-04 0%Y-911.20E+011.320E-087.055E-03 1%Y-91m2.67E-459.820E-121.173E-51 0%Y-921.93E-1212.110E-101.818E-126 0%Y-932.32E-425.820E-106.039E-47 0%Zn-657.98E+015.510E-091.965E-02 3%Zn-690.00E+001.060E-110.000E+00 0%Zr-931.45E-088.670E-085.624E-11 0%Zr-951.40E+006.390E-093.991E-04 0%Zr-979.27E-281.170E-094.845E-32 0%Total Rem6.769E-01 Calc. No. PM-750, Rev. 1, Attachment A, Page A-9 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81ABCDEFGH0.00092X/Q (sec/m^3)0.00035Breathing Rate (m^3/sec) 0.03Release Fraction 3700000000000Conversion Factor (rem/Ci per Sv/Bq) 1Containers/Accident 200Container Contact - Nominal Baseline Analysis (R/hr)250Actual Container Contact=F119Total Inhalation DoseIsotopeCi in containerInhaleDCFDose (rem)='LGS Final'!A28='LGS Final'!E280.00181=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D13*E13=F13/$F$119 ='LGS Final'!A29='LGS Final'!E290=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D14*E14=F14/$F$119='LGS Final'!A30='LGS Final'!E300.0000000217=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D15*E15=F15/$F$119='LGS Final'!A31='LGS Final'!E310=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D16*E16=F16/$F$119 ='LGS Final'!A32='LGS Final'!E320.0000000000464=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D17*E17=F17/$F$119 ='LGS Final'!A33='LGS Final'!E330.00000000101=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D18*E18=F18/$F$119='LGS Final'!A34='LGS Final'!E340.0000000000218=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D19*E19=F19/$F$119='LGS Final'!A35='LGS Final'!E350.0000000000111=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D20*E20=F20/$F$119 ='LGS Final'!A36='LGS Final'!E360=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D21*E21=F21/$F$119='LGS Final'!A37='LGS Final'!E370.0000000000241=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D22*E22=F22/$F$119='LGS Final'!A38='LGS Final'!E380.0000000000261=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D23*E23=F23/$F$119 ='LGS Final'!A39='LGS Final'!E390.00000000242=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D24*E24=F24/$F$119 ='LGS Final'!A40='LGS Final'!E400.000000000916=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D25*E25=F25/$F$119='LGS Final'!A41='LGS Final'!E410.000000101=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D26*E26=F26/$F$119='LGS Final'!A42='LGS Final'!E420.00000000294=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D27*E27=F27/$F$119 ='LGS Final'!A43='LGS Final'!E430.0000000591=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D28*E28=F28/$F$119='LGS Final'!A44='LGS Final'!E440.0000000000903=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D29*E29=F29/$F$119='LGS Final'!A45='LGS Final'!E450.0000000125=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D30*E30=F30/$F$119 ='LGS Final'!A46='LGS Final'!E460.00000000123=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D31*E31=F31/$F$119 ='LGS Final'!A47='LGS Final'!E470.00000000198=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D32*E32=F32/$F$119='LGS Final'!A48='LGS Final'!E480.00000000863=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D33*E33=F33/$F$119='LGS Final'!A49='LGS Final'!E490.0000000000274=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D34*E34=F34/$F$119 ='LGS Final'!A50='LGS Final'!E500.0000000000748=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D35*E35=F35/$F$119='LGS Final'!A51='LGS Final'!E510.000000000726=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D36*E36=F36/$F$119='LGS Final'!A52='LGS Final'!E520.000000004=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D37*E37=F37/$F$119 ='LGS Final'!A53='LGS Final'!E530.00000000168=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D38*E38=F38/$F$119 ='LGS Final'!A54='LGS Final'!E540.0000000469=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D39*E39=F39/$F$119='LGS Final'!A55='LGS Final'!E550.00000000889=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D40*E40=F40/$F$119='LGS Final'!A56='LGS Final'!E560.000000000103=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D41*E41=F41/$F$119 ='LGS Final'!A57='LGS Final'!E570.00000000158=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D42*E42=F42/$F$119='LGS Final'!A58='LGS Final'!E580.0000000000355=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D43*E43=F43/$F$119='LGS Final'!A59='LGS Final'!E590.000000000332=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D44*E44=F44/$F$119 ='LGS Final'!A60='LGS Final'!E600=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D45*E45=F45/$F$119 ='LGS Final'!A61='LGS Final'!E610.00000000131=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D46*E46=F46/$F$119='LGS Final'!A62='LGS Final'!E620.000000000157=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D47*E47=F47/$F$119='LGS Final'!A63='LGS Final'!E630.0000000000684=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D48*E48=F48/$F$119 ='LGS Final'!A64='LGS Final'!E640.00000000181=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D49*E49=F49/$F$119='LGS Final'!A65='LGS Final'!E650.000000000102=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D50*E50=F50/$F$119='LGS Final'!A66='LGS Final'!E660.00000000107=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D51*E51=F51/$F$119 ='LGS Final'!A67='LGS Final'!E670.000000000327=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D52*E52=F52/$F$119 ='LGS Final'!A68='LGS Final'!E680.0000000079=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D53*E53=F53/$F$119='LGS Final'!A69='LGS Final'!E690.00000000157=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D54*E54=F54/$F$119='LGS Final'!A70='LGS Final'!E700.000000000659=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D55*E55=F55/$F$119 ='LGS Final'!A71='LGS Final'!E710.0000000000224=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D56*E56=F56/$F$119='LGS Final'!A72='LGS Final'!E720=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D57*E57=F57/$F$119='LGS Final'!A73='LGS Final'!E730.0000000000331=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D58*E58=F58/$F$119 ='LGS Final'!A74='LGS Final'!E740.00000000185=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D59*E59=F59/$F$119 ='LGS Final'!A75='LGS Final'!E750.0000000017=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D60*E60=F60/$F$119='LGS Final'!A76='LGS Final'!E760.0000000000932=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D61*E61=F61/$F$119='LGS Final'!A77='LGS Final'!E770.000000000678=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D62*E62=F62/$F$119 ='LGS Final'!A78='LGS Final'!E780.00000000419=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D63*E63=F63/$F$119='LGS Final'!A79='LGS Final'!E790.000347=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D64*E64=F64/$F$119='LGS Final'!A80='LGS Final'!E800.00000000235=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D65*E65=F65/$F$119 ='LGS Final'!A81='LGS Final'!E810.0000000106=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D66*E66=F66/$F$119 ='LGS Final'!A82='LGS Final'!E820=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D67*E67=F67/$F$119='LGS Final'!A83='LGS Final'!E830=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D68*E68=F68/$F$119='LGS Final'!A84='LGS Final'!E840.00000000219=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D69*E69=F69/$F$119 ='LGS Final'!A85='LGS Final'!E850.0000000000117=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D70*E70=F70/$F$119 ='LGS Final'!A86='LGS Final'!E860=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D71*E71=F71/$F$119='LGS Final'!A87='LGS Final'!E870.000116=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D72*E72=F72/$F$119='LGS Final'!A88='LGS Final'!E880.00000212=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D73*E73=F73/$F$119 ='LGS Final'!A89='LGS Final'!E890.0000000000116=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D74*E74=F74/$F$119='LGS Final'!A90='LGS Final'!E900.0000000000147=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D75*E75=F75/$F$119='LGS Final'!A91='LGS Final'!E910.00000000000138=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D76*E76=F76/$F$119 ='LGS Final'!A92='LGS Final'!E920.000000000258=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D77*E77=F77/$F$119 ='LGS Final'!A93='LGS Final'!E930=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D78*E78=F78/$F$119='LGS Final'!A94='LGS Final'!E940=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D79*E79=F79/$F$119='LGS Final'!A95='LGS Final'!E950.00000000242=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D80*E80=F80/$F$119 ='LGS Final'!A96='LGS Final'!E960.000000000123=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D81*E81=F81/$F$119 Container Drop Event: Limerick Isotopic: Table 11.4-8 60 day decay Calc. No. PM-750, Rev. 1, Attachment A, Page A-10 of A-11 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119ABCDEFGH='LGS Final'!A97='LGS Final'!E970.000000129=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D82*E82=F82/$F$119='LGS Final'!A98='LGS Final'!E980.0000202=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D83*E83=F83/$F$119 ='LGS Final'!A99='LGS Final'!E990.0000000112=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D84*E84=F84/$F$119 ='LGS Final'!A100='LGS Final'!E1000.000000351=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D85*E85=F85/$F$119='LGS Final'!A101='LGS Final'!E1010.000000000449=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D86*E86=F86/$F$119='LGS Final'!A102='LGS Final'!E1020.000000000218=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D87*E87=F87/$F$119='LGS Final'!A103='LGS Final'!E1030.00000000000484=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D88*E88=F88/$F$119 ='LGS Final'!A104='LGS Final'!E1040.0000000000222=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D89*E89=F89/$F$119='LGS Final'!A105='LGS Final'!E1050.00000000225=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D90*E90=F90/$F$119='LGS Final'!A106='LGS Final'!E1060.0000000000088=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D91*E91=F91/$F$119 ='LGS Final'!A107='LGS Final'!E1070.0000000000242=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D92*E92=F92/$F$119 ='LGS Final'!A108='LGS Final'!E1080.00000000647=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D93*E93=F93/$F$119='LGS Final'!A109='LGS Final'!E1090.000000000129=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D94*E94=F94/$F$119='LGS Final'!A110='LGS Final'!E1100.00000000173=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D95*E95=F95/$F$119 ='LGS Final'!A111='LGS Final'!E1110.00000000255=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D96*E96=F96/$F$119='LGS Final'!A112='LGS Final'!E1120.00000437=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D97*E97=F97/$F$119='LGS Final'!A113='LGS Final'!E1130.000000000237=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D98*E98=F98/$F$119 ='LGS Final'!A114='LGS Final'!E1140=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D99*E99=F99/$F$119 ='LGS Final'!A115='LGS Final'!E1150.0000332=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D100*E100=F100/$F$119='LGS Final'!A116='LGS Final'!E1160.000000000167=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D101*E101=F101/$F$119='LGS Final'!A117='LGS Final'!E1170=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D102*E102=F102/$F$119 ='LGS Final'!A118='LGS Final'!E1180=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D103*E103=F103/$F$119='LGS Final'!A119='LGS Final'!E1190=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D104*E104=F104/$F$119='LGS Final'!A120='LGS Final'!E1200=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D105*E105=F105/$F$119 ='LGS Final'!A121='LGS Final'!E1210=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D106*E106=F106/$F$119 ='LGS Final'!A122='LGS Final'!E1220.00000000228=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D107*E107=F107/$F$119='LGS Final'!A123='LGS Final'!E1230.0000000132=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D108*E108=F108/$F$119='LGS Final'!A124='LGS Final'!E1240.00000000000982=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D109*E109=F109/$F$119 ='LGS Final'!A125='LGS Final'!E1250.000000000211=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D110*E110=F110/$F$119='LGS Final'!A126='LGS Final'!E1260.000000000582=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D111*E111=F111/$F$119='LGS Final'!A127='LGS Final'!E1270.00000000551=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D112*E112=F112/$F$119 ='LGS Final'!A128='LGS Final'!E1280.0000000000106=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D113*E113=F113/$F$119 ='LGS Final'!A129='LGS Final'!E1290.0000000867=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D114*E114=F114/$F$119='LGS Final'!A130='LGS Final'!E1300.00000000639=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D115*E115=F115/$F$119='LGS Final'!A131='LGS Final'!E1310.00000000117=$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D116*E116=F116/$F$119Total Rem=SUM(F13:F116) Calc. No. PM-750, Rev. 1, Attachment A, Page A-11 of A-11 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27ABCDEFNuclideuC/ccAg-110m1.840E+00 Am-2418.393E-05 C-142.727E-03Cm-2421.005E-03 Cm-2449.028E-05CO- 584.600E+00 Co-606.059E+01 Cr-511.700E+00 CS-1342.442E+01 CS-1372.826E+01 Fe-555.450E+00 H-31.151E-03I-1293.956E-05 I-1313.040E+00Mn- 542.990E+00Nb-951.030E+00 Ni-634.840E-01Pu-2382.670E-04 Pu-2391.272E-04 Pu-2412.543E-02 Sr-903.391E-02 Sr-924.062E+01 Tc-994.239E-02 Zn-651.046E+02 Table 1 - PM-750 Rev. 0 Design Basis RWCU Resin Calc. No. PM-750, Rev. 1, Attachment B, Page B-1 of B-7 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66ABCDEFGHIByCheckedRun DateRun TimeDuration12-Aug-094:38:07 PM0:00:0 5 PM-750 Table 1 before resizin g 7 - Cylinder Volume - Side ShieldsHeight182.88 cm (6 ft)Radius76.2 cm (2 ft 6.0 in )AXYZ#178.74 cm (2 ft 7.0 in)91.44 cm (3 ft)0.0 cm (0 in)Shield NDimensionMaterialDensitySource2.04e+05 in³Water0.9 TransitionAir0.00122Air GapAir0.00122CiBqµCi/cm³Bq/cm³ 6.14E+002.27E+111.84E+006.81E+042.80E-041.04E+078.39E-053.11E+008.92E+013.30E+122.67E+019.89E+059.10E-033.37E+082.73E-031.01E+02 3.35E-031.24E+081.01E-033.72E+01 3.01E-041.11E+079.03E-053.34E+001.53E+015.68E+114.60E+001.70E+05 2.02E+027.48E+126.06E+012.24E+06 5.67E+002.10E+111.70E+006.29E+04 8.15E+013.01E+122.44E+019.04E+05 9.43E+013.49E+122.83E+011.05E+06 1.82E+016.73E+115.45E+002.02E+053.84E-031.42E+081.15E-034.26E+01 1.32E-044.88E+063.96E-051.46E+001.01E+013.75E+113.04E+001.12E+05 9.97E+003.69E+112.99E+001.11E+05 3.44E+001.27E+111.03E+003.81E+04 1.61E+005.97E+104.84E-011.79E+048.91E-043.30E+072.67E-049.88E+00 4.24E-041.57E+071.27E-044.71E+00 8.48E-023.14E+092.54E-029.41E+02 1.13E-014.19E+093.39E-021.25E+031.36E+025.01E+124.06E+011.50E+061.41E-015.23E+094.24E-021.57E+03 1.13E-014.19E+093.39E-021.25E+033.49E+021.29E+131.05E+023.87E+06 30 30 60 Fluence RateFluence RateExposure RateExposure RateMeV/cm²/secMeV/cm²/secmR/hrmR/hrNo BuildupWith BuildupNo BuildupWith Buildup5.18E+086.58E-017.66E-015.65E-026.57E-022.54E+099.30E+001.28E+013.22E-014.45E-012.39E+112.88E+036.40E+032.85E+016.34E+01 5.24E+101.16E+034.14E+035.14E+001.83E+01 MicroShield 8.01 Washington Group International (8.00-0000) 0.015 0.02 0.03 0.04 Y Direction (axial) ResultsEnergy (MeV)Activity (Photons/sec) Buildup: The material reference is Source Integration Parameters Radial Circumferential Sr-92 Tc-99 Y-90 Zn-65 Pu-238 Pu-239 Pu-241 Sr-90 I-131 Mn-54 Nb-95 Ni-63 Cs-137 Fe-55 H-3 I-129 Co-58 Co-60 Cr-51 Cs-134 Ba-137m C-14 Cm-242 Cm-244 Library: ICRP-38 Nuclide Ag-110m Am-241 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Source Dimensions Dose Points Shields Project Info Case Title Description Geometry Date Filename PeachBottom.msd Calc. No. PM-750, Rev. 1, Attachment B, Page B-2 of B-7 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82ABCDEFGHI 3.38E+0 3 1.09E-0 4 5.49E-0 4 2.91E-0 7 1.46E-0 6 3.70E+0 61.56E-019.57E-013.10E-0 4 1.90E-0 3 9.83E+0 9 6.11E+0 2 4.21E+0 39.66E-016.67E+0 0 5.88E+0 7 4.87E+0 03.23E+017.45E-0 3 4.94E-0 2 1.66E+0 82.31E+011.27E+0 2 3.80E-0 2 2.09E-011.51E+113.07E+0 4 1.45E+0 55.42E+012.55E+0 2 4.64E+1 0 1.63E+0 4 5.99E+0 43.09E+011.14E+0 24.81E+112.51E+0 5 8.00E+0 5 4.88E+0 2 1.56E+0 36.06E+114.32E+0 5 1.24E+0 6 8.47E+0 2 2.44E+0 3 6.93E+1 2 6.39E+0 6 1.71E+0 7 1.25E+0 4 3.33E+0 4 4.20E+1 2 5.86E+0 6 1.40E+0 7 1.11E+0 4 2.66E+0 4 1.45E+1 3 2.81E+0 7 6.20E+0 7 5.17E+0 4 1.14E+0 5 1.22E+1 3 4.30E+0 7 8.37E+0 7 7.24E+0 4 1.41E+0 5 1.52E+0 8 8.28E+0 2 1.49E+0 3 1.28E+0 0 2.31E+0 0 2.69E+0 5 2.68E+0 0 4.36E+0 0 3.63E-0 3 5.92E-0 33.94E+138.41E+071.79E+081.49E+053.20E+05 1.5 2 0.15 0.2 0.3 0.4 0.05 0.06 3 Totals 0.5 0.6 0.8 1 0.08 0.1 Calc. No. PM-750, Rev. 1, Attachment B, Page B-3 of B-7 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65ABCDEFGHIByCheckedRun DateRun TimeDuration12-Aug-094:42:53 PM0:00:0 5 PM-750 Table 1 source term adjustment to 400 R/hr, and resizing 7 - Cylinder Volume - Side Shield sHeight182.88 cm (6 ft)Radius76.2 cm (2 ft 6.0 in )AXYZ#178.74 cm (2 ft 7.0 in)91.44 cm (3 ft)0.0 cm (0 in)Shield NDimensionMaterialDensitySource2.04e+05 in³Water0.9 TransitionAir0.00122Air GapAir0.00122CiBqµCi/cm³Bq/cm³ 7.67E+002.84E+112.30E+008.50E+043.50E-041.29E+071.05E-043.88E+001.11E+024.12E+123.34E+011.24E+061.14E-024.20E+083.41E-031.26E+02 4.19E-031.55E+081.26E-034.64E+01 3.76E-041.39E+071.13E-044.17E+001.92E+017.09E+115.75E+002.13E+05 2.52E+029.34E+127.57E+012.80E+06 7.08E+002.62E+112.12E+007.86E+04 1.02E+023.76E+123.05E+011.13E+06 1.18E+024.36E+123.53E+011.31E+06 2.27E+018.40E+116.81E+002.52E+054.80E-031.77E+081.44E-035.32E+01 1.65E-046.10E+064.94E-051.83E+001.27E+014.69E+113.80E+001.40E+05 1.25E+014.61E+113.73E+001.38E+05 4.29E+001.59E+111.29E+004.76E+04 2.02E+007.46E+106.05E-012.24E+041.11E-034.12E+073.34E-041.23E+01 5.30E-041.96E+071.59E-045.88E+001.06E-013.92E+093.18E-021.18E+03 1.41E-015.23E+094.24E-021.57E+031.69E+026.26E+125.07E+011.88E+061.77E-016.54E+095.29E-021.96E+03 1.41E-015.23E+094.24E-021.57E+034.36E+021.61E+131.31E+024.83E+06 30 30 60 Fluence RateFluence RateExposure RateExposure RateMeV/cm²/secMeV/cm²/secmR/hrmR/hrNo BuildupWith BuildupNo BuildupWith Buildup 6.97E+128.85E+031.03E+047.59E+028.84E+023.18E+091.16E+011.60E+014.03E-015.55E-012.99E+113.60E+037.99E+033.56E+017.92E+01 MicroShield 8.01 Washington Group International (8.00-0000) 0.015 0.02 0.03 Y Direction (axial) ResultsEnergy (MeV)Activity (Photons/sec) Buildup: The material reference is Source Integration Parameters Radial Circumferential Sr-92 Tc-99 Y-90 Zn-65 Pu-238 Pu-239 Pu-241 Sr-90 I-131 Mn-54 Nb-95 Ni-63 Cs-137 Fe-55 H-3 I-129 Co-58 Co-60 Cr-51 Cs-134 Ba-137m C-14 Cm-242 Cm-244 Library: ICRP-38 Nuclide Ag-110m Am-241 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Source Dimensions Dose Points Shields Project Info Case Title Description Geometry Date Filename PeachBottomFinal.msd Calc. No. PM-750, Rev. 1, Attachment B, Page B-4 of B-7 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82ABCDEFGHI 6.54E+1 0 1.45E+0 3 5.17E+0 3 6.42E+0 0 2.29E+01 4.22E+0 3 1.36E-0 4 6.86E-0 4 3.63E-0 7 1.83E-0 6 4.63E+0 61.95E-011.20E+0 0 3.88E-0 4 2.38E-0 3 1.23E+1 0 7.63E+0 2 5.26E+0 3 1.21E+0 0 8.33E+0 0 7.34E+0 7 6.08E+0 04.03E+019.30E-0 3 6.16E-0 2 2.07E+0 82.89E+011.58E+0 2 4.75E-0 2 2.61E-011.89E+113.83E+0 4 1.81E+0 56.76E+013.19E+0 2 5.80E+1 0 2.03E+0 4 7.48E+0 43.85E+011.42E+0 26.01E+113.13E+0 5 9.99E+0 5 6.10E+0 2 1.95E+0 37.57E+115.39E+0 5 1.55E+0 6 1.06E+0 3 3.05E+0 3 8.66E+1 2 7.99E+0 6 2.13E+0 7 1.56E+0 4 4.16E+0 4 5.24E+1 2 7.32E+0 6 1.74E+0 7 1.39E+0 4 3.32E+0 4 1.81E+1 3 3.51E+0 7 7.75E+0 7 6.46E+0 4 1.43E+0 5 1.52E+1 3 5.37E+0 7 1.05E+0 8 9.04E+0 4 1.76E+0 5 1.90E+0 8 1.03E+0 3 1.87E+0 3 1.60E+0 0 2.88E+0 0 3.36E+0 5 3.34E+0 0 5.45E+0 0 4.53E-0 3 7.40E-0 35.62E+131.05E+082.24E+081.87E+054.00E+05 1.5 2 0.15 0.2 0.3 0.4 0.05 0.06 3 Totals 0.5 0.6 0.8 1 0.08 0.1 0.04 Calc. No. PM-750, Rev. 1, Attachment B, Page B-5 of B-7 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40ABCDEFGH9.200E-04X/Q (sec/m^3)3.500E-04Breathing Rate (m^3/sec)3.000E-02Release Fraction3.70E+12Conversion Factor (rem/Ci per Sv/Bq)1.00E+00Containers/Accident4.00E+02Container Contact - Nominal Baseline Analysis (R/hr )7.358E-01Total Inhalation DoseIsotopeCi in containerInhaleDCFDose (rem)Ag-110m7.67E+002.170E-085.947E-03 1%Am-2413.50E-041.200E-041.500E-03 0%Ba-137m1.11E+020.00E+000.000E+00 0%C-141.14E-025.640E-102.291E-07 0%Cm-2424.19E-034.670E-066.990E-04 0%Cm-2443.76E-046.700E-059.008E-04 0%Co-581.92E+012.940E-092.014E-03 0%Co-602.52E+025.910E-085.333E-01 72%Cr-517.08E+009.030E-112.286E-05 0%Cs-1341.02E+021.250E-084.546E-02 6%Cs-1371.18E+028.630E-093.632E-02 5%Fe-552.27E+017.260E-105.893E-04 0%H-34.80E-031.730E-112.966E-09 0%I-1291.65E-044.690E-082.763E-07 0%I-1311.27E+018.890E-094.025E-03 1%Mn-541.25E+011.810E-098.060E-04 0%Nb-954.29E+001.570E-092.408E-04 0%Ni-632.02E+001.700E-091.225E-04 0%Pu-2381.11E-031.060E-044.215E-03 1%Pu-2395.30E-041.160E-042.198E-03 0%Pu-2411.06E-012.230E-068.446E-03 1%Sr-901.41E-013.510E-071.773E-03 0%Sr-921.69E+022.180E-101.319E-03 0%Tc-991.77E-012.250E-091.420E-05 0%Y-901.41E-012.280E-091.151E-05 0%Zn-654.36E+025.510E-098.584E-02 12%Total Rem7.358E-01 Container Drop Event: Peach Bottom Isotopic: Table 1, PM-750 Calc. No. PM-750, Rev. 1, Attachment B, Page B-6 of B-7 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40ABCDEFGH0.00092X/Q (sec/m^3)0.00035Breathing Rate (m^3/sec) 0.03Release Fraction 3700000000000Conversion Factor (rem/Ci per Sv/Bq) 1Containers/Accident200Container Contact - Nominal Baseline Analysis (R/h r=F40Total Inhalation Dos eIsotopeCi in containerInhaleDCFDose (rem)=PeachBottomFinal!A28=PeachBottomFinal!E280.0000000217=$A$2*$A$3*$A$4*$A$5*$A$6*D12*E12=F12/$F$40 =PeachBottomFinal!A29=PeachBottomFinal!E290.00012=$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13=F13/$F$40 =PeachBottomFinal!A30=PeachBottomFinal!E300=$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14=F14/$F$40 =PeachBottomFinal!A31=PeachBottomFinal!E310.000000000564=$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15=F15/$F$40 =PeachBottomFinal!A32=PeachBottomFinal!E320.00000467=$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16=F16/$F$40 =PeachBottomFinal!A33=PeachBottomFinal!E330.000067=$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17=F17/$F$40 =PeachBottomFinal!A34=PeachBottomFinal!E340.00000000294=$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18=F18/$F$40 =PeachBottomFinal!A35=PeachBottomFinal!E350.0000000591=$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19=F19/$F$40 =PeachBottomFinal!A36=PeachBottomFinal!E360.0000000000903=$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20=F20/$F$40 =PeachBottomFinal!A37=PeachBottomFinal!E370.0000000125=$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21=F21/$F$40 =PeachBottomFinal!A38=PeachBottomFinal!E380.00000000863=$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22=F22/$F$40 =PeachBottomFinal!A39=PeachBottomFinal!E390.000000000726=$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23=F23/$F$40 =PeachBottomFinal!A40=PeachBottomFinal!E400.0000000000173=$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24=F24/$F$40 =PeachBottomFinal!A41=PeachBottomFinal!E410.0000000469=$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25=F25/$F$40 =PeachBottomFinal!A42=PeachBottomFinal!E420.00000000889=$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26=F26/$F$40 =PeachBottomFinal!A43=PeachBottomFinal!E430.00000000181=$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27=F27/$F$40 =PeachBottomFinal!A44=PeachBottomFinal!E440.00000000157=$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28=F28/$F$40 =PeachBottomFinal!A45=PeachBottomFinal!E450.0000000017=$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29=F29/$F$40 =PeachBottomFinal!A46=PeachBottomFinal!E460.000106=$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30=F30/$F$40 =PeachBottomFinal!A47=PeachBottomFinal!E470.000116=$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31=F31/$F$40 =PeachBottomFinal!A48=PeachBottomFinal!E480.00000223=$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32=F32/$F$40 =PeachBottomFinal!A49=PeachBottomFinal!E490.000000351=$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33=F33/$F$40 =PeachBottomFinal!A50=PeachBottomFinal!E500.000000000218=$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34=F34/$F$40 =PeachBottomFinal!A51=PeachBottomFinal!E510.00000000225=$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35=F35/$F$40 =PeachBottomFinal!A52=PeachBottomFinal!E520.00000000228=$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36=F36/$F$40 =PeachBottomFinal!A53=PeachBottomFinal!E530.00000000551=$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37=F37/$F$40Total Rem=SUM(F12:F37) Container Drop Event: Clinton Isotopic: Table 12.2-1 2 Calc. No. PM-750, Rev. 1, Attachment B, Page B-7 of B-7 Calc. No. PM-750, Rev. 1, Attachment C, Page C-1 of C-521.Calculation No.Y 1'1...7 5</J iIl-." S£RVIC E PPage 1 of 63 CALCULATION COVER SHEET NUCLEAR ENGINEERING GROUP 2.0 LGS UNIT(S)..:L(3 M-205994/92 Q-'PBAPS/DQCTYPE 061 3.Initiating Document:-rSD P_o:l'1-31 4.Responsi,ble , , S s R-R....15.Total Nl; Sheets: 16. No: 1 7.o Safety RelatedNon-Safetv Related 8.Description:-ro EVa Ic),j:..}!....-I&Jl'olc 3, J <<w'OrfT Cd.!L 9.System/Topic No.:'#-"-'I'Cct'l1;;;l1u J!fCt!.Ij,n +tn VoI,/lif-It-Drf,/I/J Ln,r v{/ctl f.$,A Structure: low lei/,j r...fll Component: /VI/I'), RECORD OF REVISIONS 10.No.11.Description of Revision 12.Vendor Calc.13.Other Calcs 14.Sionatures Number Rev.Requiring Revision Preparer Reviewer Approver/Date.¢DM'!JJ1U)NIh 0 A/ol').e.RR-IIq'Z.--.,".-..--_....15.Provides Info to: 16..Related Calc. Number!Receives Info from: Computer Supersedes: Computer program and version &11: ,ol,.z.. Calc. No. PM-750, Rev. 1, Attachment C, Page C-2 of C-52 FORM 5610 REV 4/91 United Engineers lleonstruct ...A IIayIIIe-. Company CALCULATION

SUMMARY

&CONTROL SHEET Page 1 9f 2 PRELIM.CALCULATION SET NO. FINAL VOID.,/REVISION o PROJECT TITLE PECO PBAPS-Units 2&3 I OW I eve!R ad waste Storage Faci1ity DISCIPLINE J.O.'71 1""Sl'7 LLRWSF STRUCTURE OF SYSTEM_Non-Safety Related DESIGN CLASSIFICATION SUBJECT Container Drop Accident Analysis COMPLETED BYCHECKEDBY PJPf-tkf APPROVEDd tf j u1IJJ L*e.S c:: d 7l SDE OR MGR OF STAFF GROUP REASON FOR REVISION:..ww'ORIOINALCALCULJ\TION***** PROBLEM STATEMENT: DATE DATE DATE I/o/:J.-¥97 SHEETS REVISED, ADDED OR DELETED o........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_*....
• ..**.*.*m.*....***h.W*_ow***'.*.*.*.w_*

...****'.un**..'.,...',...-....*..r_',**.. 'W..****M*n****'"***.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 .... .. ..!?,<l:§i.§ ..!Q.. .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,,***, .. ..fQ!:.thymig. ........w..w " lnternal..Dose w ,.,, Q*.1069..rem._, w .._*m Total 0.1125 rem Calc. No. PM-750, Rev. 1, Attachment C, Page C-3 of C-52 FORM 5610 REV 4/91 CALCULATION SET NO.CALCULATION

SUMMARY

&CONTROL SHEET Pa@c 2 ofPRELIM.fM-750 FINAL VOID."...REVISION o PROJECT TITLE PECO PBAPS-Units 2&3 Low Level Radwaste Storage Facility DISCIPLINE 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.. _.__************* ..*._*_*.W.*,W N*3.Accident ground level X/Qs for PBAPS at the LLRWSF location derived from Ref.4.

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

--.................... _..._--.._---_...............* --_.._--_____0.....__.___*---_00-.............. _..__--....................................... _..._.__........*........*0_*..........

• ..*......*..*..*....****...*..*---_.._-UNVERIFIED ASSUMPTIONS/OPEN ITEMS:_.._--_."_----................................

--_................... _......_-...................... _--_._-_.__--........................ _*._--...................................... _.__N__._______-_****-....__--_.-_.._--__-_____-_.__--

REFERENCES:

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

_--.................. _....._-_._--........................ __..._--...................... _._._SEE..FAGE.19 FORblST-GFALL REFE.RENCES __..M**..ww__.................................. _=__" ,., ,.,__ ,*..._""',.=__**<.w.'.w'"...........__........................... __--___ "_.._--1-----.---.................. __......................... _--

---

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,......_-................ __....___-__--_... Calc. No. PM-750, Rev. 1, Attachment C, Page C-4 of C-52 FORM 5007 REV 4/91 GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO.REV.COMPo BY CHK'D.BY PM-1S0.M6--P11A: PRELIM.FINAL VOID a DATE /Ie 5 53 SHEET OF DATE DATE 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-5 of C-52 FORM 5007 REV 4/91 SUBJECT Container Drop Accident Analysis UniIed.....ers II ConsInICIm's GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility CALCULATION SET NO.REV.COMPo BY CHK'D BY f'JVJ-750 ,-,6-PRELIM.FINAL VOID 0 DATE / 1-7/1'1-SHEET 6 OF 53 DATE DATE 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-6 of C-52 A""""'Company FORM 5007 REV 4/91 GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO. PRELIM.FINAL VOID ,/SHEET 7 OF3 J.O.7112 287 REV.o COMPo BY CHK'D BY DATE DATE 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-7 of C-52 FORM 5007 REV 4/91 GENERAL IlConstruCtors COMPUTATION A..,...... Company PECO PBAPS-Units 2 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO REV.COMPo BY CHK'D BY PM-750PrJ(PRELIM FINAL VOID 0 DATE lbb;h2--,/ r'53 SHEET OF DATE DATE 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 H 2 1 P p Where H=Spill height, cm P p=Powder density g/cm 3 (Ref.2, page 4.71)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-8 of C-52 United.....ers..ConstruCtors FORM 5007 REV 4191 GENERAL COMPUTATION SHEET PECO PBAPS-units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT container Drop Accident Analysis TABLE 2 CALCULATION SET NO.REV.COMPo BY CHK'D BY I'/11-750."'7 G...PRELIM.FINAL VOID 0 DATE V , 53 SHEET OF DATE DATE J.O.7112 287 VOLUME (cc)WEIGHT (gm)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********2.55E+06 2.69E+06 2.12E+06 2.83E+06 2.41E+06 3.06E+06 2.49E+06 2.59E+06 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-9 of C-52 SUBJECT Container Drop Accident Analysis United....ers..COnsInICtors A""""'Company FORM 5007 REV 4/91 GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility CALCULATION SET NO.REV.COMPo BY CHK'D BY pM-1fo ,.., (,-ifR PRELIM.FINAL VOID 0 DATE l/TX,:/ iiI n 1'L 10SHEET OF DATE DATE 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-10 of C-52 FORM 5007 REV 4/91 ..ConstrUCtors GENERAL A.......Company COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO.REV.COMPo BY CHK'D.BY fM-750/1/6-MtJ<..PRELIM.FI/VOID 0 DATE Jbh;Jqv ID/H'h1;.II 53 SHEET OF DATE DATE 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/m 3)This equation can be written as: D y=0.25 x X/Q x E i (E-"i XCi)Where D"=gamma dose from an infinite cloud (rem)E"yi=average gamma energy per disintegration per isotope i C i=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-11 of C-52 til"1J rl c:D OJ 0'--'--m m ()()-1-1 g t"'tlot'J al t;o0 I t" TABLE 4 ,...lD'tl<tJ:lfj CONVERSION OF SPECISO OUTPUT TO A FORM SUITABLE FOR EXTERNAL DOSE CALCULATION.....'tl til r::d III I************************************ SPECISO OUTPUT (MEV/CI/SEC)

TOTAL a.Mev/dis*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 III::s rad ionucl ideC/l....()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 t"t't"t'0lDC/l 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 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-0225 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-Olb2>ICZ 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 tot m-i m 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-OllllW m>>::D 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+OOI2j 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-OlIII Z 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 0....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[Il.....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"U 0 I 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 m II 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-Olm 0 ,.-§:-o 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, 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-c, 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 P." I l>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:::j0 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 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..:J."00 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-0296 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<z 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 0 l>;::-l:tI m CD-<0 0 I l>"-l 0 m CD-<"T1 o:xl;: '" o o"oj:xl m:< Calc. No. PM-750, Rev. 1, Attachment C, Page C-12 of C-52 FORM 5007 REV 4/91 A IIIIyIIIeGIICompany United Engineers 1I0.....tors SUBJECT Container Drop Accident Analysis PROJECT GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 Low Level Radwaste Storage Facility CALCULATION SET NO.REV.COMPo BY CHK'D BY P"'-75,;t(!<PRELIM FINAL VOID 0 DATE)ftAJh ,/'Ir-/t/ln...It)'iJ 7 1t-'3 53 SHEET OF DATE DATE 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-13 of C-52 FORM 5007 REV 4/91 GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO REV.COMPo BY CHK'D BY pM-750..;""'1'1{,-

1. J(PRELIM.FINAL VOID 0 DATE V

I Lf-OF 53 SHEET DATE DATE 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 m 3/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/m 3).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 DF i.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.------J Calc. No. PM-750, Rev. 1, Attachment C, Page C-14 of C-52 FORM 5007 REV 4191 CALCULA nON SET NO.REV.COMPo BY CHK'D BY GENERAL IlConstnIc ....COMPUTATION -71'0 c;:. SHEET PRELIM.FINAL VOID 0 DATE PECO PBAPS-Units 2&3/ 10." PROJECT Low Level Radwaste Storage Facility SHEET 15 OF 53 DATE DATE SUBJECT Coeta jeer Drop Ace i dent Ana]ys is TABLE 6 J.O..",.,"$:1" INTERNAL TOTAL BODY DOSE (INHALATION) Nuclide*******Cr-51 Mn-54 Co-58 Zn-65 Sr-92 Nb-95 Ag-llOm Cs-134 Fe-55 Co-60 Cs-137 Sr-90 Ni-63 H-3 C-14 I-129 I-131 Tc-99 Cm-242 Pu-241 Pu-238 Pu-239 Am-241 Cm-244 T.Body Dose Factor'(mrem/pCi)

1.25E-08 7.87E-07 2.59E-07 5.82E-06 3.64E-ll 5.26E-07 7.43E-07 9.1OE-05 4.93E-07 1.85E-06 5.35E-05 7.62E-04 1.81E-06 1.58E-07 4.26E-07 6.91E-06 2.56E-06 1.37E-04 7.50E-04 1.29E-03 6.66E-02 7.53E-02 6.47E-02 3.51E-02 TOTAL T.Body Dose(rem)*********** 4.979E-07 5.503E-05 2.787E-05 1.426E-02 3.461E-08 1.267E-05 3.204E-05 5.204E-02 6.294E-05 2.624E-03 3.539E-02 6.049E-04 2.054E-05 4.260E-09 2.717E-08 6.427E-09 1.757E-04 1.360E-04 1.761E-05 7.683E-04 4.161E-04 2.242E-04 1.270E-04 7.419E-05 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 THYROID DOSE FROM IODINES PLUS EXTERNAL AND INTERNAL WHOLE BODY CONTRIBUTIONS 1.02E-Ol 2.15E-Ol Calc. No. PM-750, Rev. 1, Attachment C, Page C-15 of C-52 FORM 5007 REV.4/91 GENERAL IlConstnICIm's COMPUTATION A...,......

Company SH EET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO.REV.COMPo BY CHK'D.BY PM-750.P11\PRELIM.FINAL VOID 0 DATE L-l// 1-"<OFSHEET DATE DATE J.O.7112.287 ACCIDENT X/O VALUE The two-hour accident X/Q values for the ground-level release are taken from attachment2, 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/m 3. Calc. No. PM-750, Rev. 1, Attachment C, Page C-16 of C-52 FORM 5007 REV.4191 CALCULATION SET NO REV.COMPo BY CHK'D BY GENERAL II ConsInICIors COMPUTATION f>P}(A IIayIIIeea Cofrpany SHEET PRELIM.FINAL VOID 0 DATE PIce PIAl'S-Unit.2 , 3/' Low Level Ra4wa.te Stora;e'aoility I PROJECT 17 53 SHEET OF DATE DATE SUBJECT Container Drop Aooi4ent Analysi.J.O.7112.287"..w.II....C-..I It I (S)(£....1 ew/oee)o/x..1 1 1 I 1 I I , I I , , I , I I I 1 , , 1 I I 1 I , I____1-1_I---....---!.---4.------1 I , I I I I I I I 1 1 I 1 I , I I I----,-------1-r r ,-r--T--T---------1 1 , 1 I 1 I , I 1 1 , I I 1 I I , I----1-------1-r r,--r-T--T---------, 1 , I I I I I I I , I 1 1 1 1 I 1 I____1'_1__L_L_1.__1.1------I I'I 1 1 1 , I I 1 1 I 1 I 1 I I I I I 1 I 1 I I I I I I 1 I I 1 1 I I I-rr'-r-r-T--T---j------

---

1------1 I 1 1 I I 1 1 1 I I I I I I I 1 1 I I I I , 1 I I I I , I 1 1 1 I I I 1 I , I , LLLJ-L-L-l--J.---.l------

---

,-I 1 1 1 I , 1 I I I , , I I I I 1 I I , 1 I I I I , I 1 , 1 I I 1 I 1 1 I 1 1 I I 1 1 1 I 1 1 1 I 1 I 1 1 I 1 I I I I I I I I...J@*-----------.------------------ OUt-O!>...Jt-dwI-*Z lJ..-U U O!.<WeDWO!:I ZI:-l OW cfrl3

<_Z (DOO UHZ_...J H 0 OWo.......I:Z<H CZ'<..J X-I 0<Z 0 HUW UHZ.....Z U l----+------JH-++-+--+--+--t------:t----i'" 1-0....@S§"'":1:::>U-J<<< Calc. No. PM-750, Rev. 1, Attachment C, Page C-17 of C-52 FORM 5007 REV 4/91 ..ConstruCtors GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility SUBJECT Container Drop Accident Analysis CALCULATION SET NO.REV COMPo BY CHK'D BY f""-?50/1Itc,..M'K PRELIM.FINAL VOID 0 DATE / {let 5.3 SHEET OF DATE DATE 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-18 of C-52 FORM 5007 REV 4/91 SUBJECT Container Drop Accident Analysis UniIed.....ers..ConsInICtors A""'" Company GENERAL COMPUTATION SHEET PECO PBAPS-Units 2&3 PROJECT Low Level Radwaste Storage Facility CALCULATION SET NO.REV.COMPo BY CHK'D.BY PM-7S0<.-PRELIM.FINAL VOID 0 DATE/cft-;h'llty'all9zS3 SHEET OF DATE DATE 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 1 0 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-19 of C-52 ."'\*I-,-PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD'1, DELTA, PA., 17314 PJ'-w.l.Iyt,tPM-7fo AH..._\ 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 CO-60 157634.0 7.00 CS-137 95027.4 10.00 ESTIMATED ACTIVITIES: SR-90 114.033 0.40 NI-63 1261.1 100.00 H-3 3.279 1000.00 C-14 7.09 60.00 1-129 0.133 2.00 TC-99 142.541 25.00 ESTIMATED TRANSURANIC ACTIVITIES: CM-242 3.38E+00 PU-241 8.55E+Ol PU-238 8.98E-01 PU-239 4.28E-01 AM-241 2.82E-01 CM-244 3.04E-Ol TOTAL TRANSURANICS: 2.500E+00 (NCI/GH)ALPHA EMITTERS TOTALS:-Tl/2>5 YEARS 254280.4 TOTALS:-ALL NUCLIDES 680497.3" UC/CC 51.54 31.07 3.728E-02 4.123E-Ol 1.072E-03 2.319E-03 4.350E-05 4.660E-02 1.105E-03 2.796E-02 2.936E-04 1.398E-04 9.228E-05 9.927E-05 83.14 222.49 Calc. No. PM-750, Rev. 1, Attachment C, Page C-20 of C-52 u£14 fM-750\\\\o.j._.....\1\-\S\..u:.,\-\c\53 PHILADELPHIA ELECTRIC COMPANY 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. ISOTOPIC ANALYSIS REPORT: THIS

SUMMARY

APPLIES TO THE TOTAL VOLUME OF RESIN CONTAINED IN SHIPMENT NO.DR-87-0001. RWCU RESIN.. tt'l---z..6..f-I.5 NUCLIDE CR-51 MN-54 CO-58 ZN-65 SR-92 NB-95 AG-110m CS-134 ESTIMATED ACTIVITY: FE-55 MC/LINER A2 VAWE UC/CC 4239.8 600.00 1.70 7443.1 20.00 2.99 11453.1 20.00 4.6030.00 104.63 10110.00 40.62 3'2}2!564.20.00 1.03 4590.0 7.00 1.84 60869.7 10.00 24.42 13589.9 1000.00 5.45 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE MC/LlNER A2 VAWE CO-60 150998.6 7.00 CS-137 70422.9 10.00 ESTIMATED ACTIVITIES: SR-90 84.507 0.40 NI-63 1208.0 100.00 H-3 2.870 1000.00 C-14 6.79 60.00 1-129 0.099 2.00 TC-99 105.634 25.00 ESTIMATED TRANSURANIC ACTIVITIES: CM-242 2.50E+00 PU-241 6.34E+01./PU-238 6.65E-01 PU-239 3.17E-01 AM-241 2.09E-Ol CM-244 2.25E-01 TOTAL TRANSURANICS: 2.117E+00 (NCI/GM)ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 222896.7 TOTALS:-ALL NUCLIDES 685379.5 UC/CC 60.59 28.26 3.391E-02 4.847E-Ol 1.151E-03 2.727E-03 3.956E-05 4.239E-02 1.005E-03 2.543E-02 2.670E-04 1.272E-04 8.393E-05 9.028E-05 89.44 275.01 Calc. No. PM-750, Rev. 1, Attachment C, Page C-21 of C-52 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 Co-60 Cs-137 ESTIMATED ACTIVITIES: Sr-90 Ni-63 H-3 C-14 1-129 Tc-99 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 Pu-241 Pu-238 Pu-239 Am-241 cm-244 TOTALTRANSURANICS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES MC/LlNER A2 VALUE 74768.8 7.00 23206.2 10.00 27.132 0.40 1242.5 100.00 111.000 1000.00 0.419 60.00 0.055 2.00 0.423 25.00 7.61E-01 1.98E+01 2.37E-01 1.04E-01 7.47E-02 1.62E-01 2.355E-01 (NCI/GM)99377.8 158515.7 UC/CC 24.45 7.59 8.872E-03 4.063E-01 3.630E-02 1.370E-04 1.802E-05 1.385E-04 2.487E-04 6.483E-03 7.753E-05 3.389E-05 2.443E-05 5.294E-05 32.50 51.83 Calc. No. PM-750, Rev. 1, Attachment C, Page C-22 of C-52s""-.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-23 of C-52 Am-241 cm-244 TOTAL TRANSURANlCS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES 9.28E-04 3.31E-03 3.240E-02 (NCl/GH)2020.9 6517.7 2.521E-06 8.994E-06 5.49 17.71 cuQ. 1\-\::t'-\{5:> Calc. No. PM-750, Rev. 1, Attachment C, Page C-24 of C-52Q5"3 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD 11, DELTA, PA., 17314 BASED UPON ANALYSIS OF THE RWCU PHASE 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-25 of C-52 W-#r"'-7M-\o.cl.....--\- t\-\-ESTIMATED ACTIVITIES: 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-26 of C-52 ..('RlJC,(.(. 87-PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD 11, DELTA, PA., 17314 J.-:II fl'?-750 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-27 of C-52 0.92 e.:c...t" 11 PN-750 3.10E-06 1.03E-06 2.44£-07 2.88£-06 3.75 Pu-238.1.49E-03 Pu-239 4.97E-04 Aa-241 1.17E-04 CJI-244 1.39E-03 , TOTAL TRANSURANICS: 1.24E-02 (nC!/91Il) ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 444.3 TOTALS:-ALL NUCLIDES 1807.2 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-28 of C-52if!1"/1-7.7"0 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER Co-60 O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO ESTIMATED ACTIVITIES: Sr-90 O.OOE+OO O.OOE+OO Ni-63 O.OOE+OO O.OOE+OO B-3 3.90E-09 3.90E-06 C-14 O.OOE+OO O.OOE+OO 1-129 O.OOE+OO O.OOE+OO Tc-99 O.OOE+OO O.OOE+OO ESTIMATED TRANSURANIC ACTIVITIES: cm-242 O.OOE+OO Pu-241 O.OOE+OO Pu-238 O.OOE+OO Pu-239 O.OOE+OO Am-241 O.OOE+OO CDl-244 O.OOE+OO TOTAL TRANSURANICS: O.OOE+OO (nCi/gm)ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 0.0 TOTALS:-ALL NUCLIDES 0.0 SW Z?1-S3 UCi/cc O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.38E-03 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 0.00 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-29 of C-52 ea!lrPM-7fo t\-\ 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 Co-60 7.13E+04 7.13E+07 Cs-137 6.32E+03 6.32E+06 ESTIMATED ACTIVITIES: Sr-90 8.38E+OO 8.38E+03 Ni-63 8.59E+02 8.59E+05 B-3 1.76E+OO 1.76E+03 C-14 1.76E+OO 1.76E+03 I-129 9.94E-03 9.94E+OO Tc-99 5.71E-02 5.71E+01 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 4.25E-03 Pu-241 5.33E+OO Pu-238 6.92E-02 Pu-239 2.97E-02 Am-241 2.03E-02 cm-244 4.55E-02 TOTAL TRANSURANICS: 8.89E-02 (nCi/gm)ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 78525.1 TOTALS:-ALL NUCLIDES 399217.8 uCi/cc 2.25E+01 1.99E+OO 2.64E-03 2.71E-01 5.56E-04 5.56E-04 3.14E-06 1.80E-05 1.34E-06 1.68E-03 2.18E-05 9.36E-06 6.39E-06 1.43E-05 24.76 125.88 Calc. No. PM-750, Rev. 1, Attachment C, Page C-30 of C-52 eJ.#/'#-750 1\-\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-31 of C-52 A--ffa-cf,,.,J-A _,""..J- 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-32 of C-52 _I slJ-.3125,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-33 of C-52 NUCLIDE mCi/LINER uCi/LINER Co-60 5.30£+04 5.30£+07 Cs-137 6.80E+03 6.80E+06 ESTIMATED ACTIVITIES: Sr-90 8.63E+00 8.63E+03 Ni-63 6.09E+02 6.09E+05 B-3 1.03E+00 1.03E+03 C-14 1.34E-01 1.34E+02 I-129 9.24E-03 9.24E+00 Tc-99 4.90E-02 4.90E+01 ESTIMATED TRANSURANIC ACTIVITIES: ca-242 4.56E-03 Pu-241 5.77E+00 Pu-238 7.40E-02 Pu-239 3.19E-02 Am-241 2.20E-02 ca-244 4.81E-02 TOTAL TRANSURANICS: 1.19E-01 (nCi/qm)ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 60393.1 TOTALS:-ALL NUCLIDES 360392.7 uCi/cc 2.49£+01 3.20E+00 4.06E-03 2.87£-01 4.86E-04 6.31E-05 4.35E-06 2.31E-05 2.15E-06 2.72E-03 3.48E-05 1.50E-05 1.04E-05 2.27E-05 28.44 169.70 tal!1/ s'hJ-Calc. No. PM-750, Rev. 1, Attachment C, Page C-34 of C-52 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-35 of C-52 Pu-238 Pu-239 0-241 ca-244 TOTAL TRANSURANICS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES 8.08E-Ol 2.63E-Ol 1.87£-01 5.32E-01 8.283E-01 (nCi/qm)177321.4 598479.2 2.64E-04 8.61E-05 6.11£-05 1.74£-04 57.98 195.70'3 t c{-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 Mn-54 Fe-59 Cr-51 Ba-140 La-140 Co-58 Zn-65 mCi/LINER 6.15E+01 O.OOE+OO 1.68E+02 9.21E+00 6.70E+00 6.77E+01 6.04E+02 uCi/LlNER 6.15E+04 O.OOE+OO 1.68E+05 9.21E+03 6.70E+03 6.77E+04 6.04E+05 uci/cc 2.71E-01 O.OOE+OO 7.43E-01 4.07E-02 2.96E-02 2.99E-01 2.66E+00 Calc. No. PM-750, Rev. 1, Attachment C, Page C-36 of C-52 Cs-134 1.19E+02 1.19E+05 5.26E-01 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 Jltv/-1ft) 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 (RESIN WEIGHT 2.00E+06 GRAMS)IN CONTAINER DR-91-0001. /j.I.<--:./ Calc. No. PM-750, Rev. 1, Attachment C, Page C-37 of C-52 SYSTEM RESIN rSOTOPIC ANALYSIS REPORT: NUCLIDE mCi/LINER Mn-54 Fe-59 Cr-51 Ba-140 La-140 Co-58 Zn-65 Aq-110m Zr-95 Nb-95 1-131 Cs-134 ESTIMATED ACTIVITY: Fe-55 2.37E+04 O.OOE+OO 7.70E+04 8.59E+02 1.65E+03 2.59E+04 2.20E+05 1.40E+04 8.59E+02 4.26E+03 1.98E+03 4.42E+04 5.82E+03 2.37E+07 O.OOE+OO 7.70E+07 8.59E+05 1.65E+06 2.59E+07 2.20E+08 1.40E+07 8.59E+05 4.26E+06 1.98E+06 4.42E+07 5.82E+06 8.37E+00 O.OOE+OO 2.72E+01 3.03E-01 5.82E-01 9.14E+00 7.76E+01 4.94E+00 3.03E-01 1.51E+00 6.98E-01 1.56E+01 2.06E+00 THE FOLLOWING ISOTOPES HAVE HALF LIVES GREATER THAN FIVE YEARS NUCLIDE mCi/LINER uCi/LINER Co-60 1.15E+05 1.15E+08 Cs-137 6.05E+04 6.05E+07 ESTIMATED ACTIVITIES: Sr-90 3.47E+02 3.47E+05 Ni-63 1.31E+03 1.31E+06 B-3 2.80E-01 2.80E+02 C-14 4.73E+00 4.73E+03 1-129 8.23E-02 8.23E+01 Tc-99 1.76E+00 1.76E+03 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 1.58E+00 Pu-241 4.83E+01 Pu-238 8.07E-01 Pu-239 2.63E-01 Am-241 1.87E-01 cm-244 5.31E-01 TOTAL TRANSURANICS: 8.930E-01 (nci/gm)ALPHA EMITTERS TOTALS:-T1/2>5 YEARS 176786.7 TOTALS:-ALL NUCLIDES 596785.5 uCi/cc 4.04E+01 2.14E+01 1.23E-01 4.61E-01 9.89E-05 1.67E-03 2.91E-05 6.20E-04 5.60E-04 1.71E-02 2.85E-04 9.28E-05 6.59E-05 1.87E-04 62.43 210.75 Calc. No. PM-750, Rev. 1, Attachment C, Page C-38 of C-52 J#1'1'4-750 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 4.77E+03 4.77E+06 1.56E+00 LIVES GREATER THAN FIVE YEARS mCi/LINER uCi/LINER uCi/cc 7.72E+04 7.72E+07 2.53E+01 8.65E+04 8.65E+07 2.83E+01 165787.7 544407.5 mCi/LINER 1.43E+04 O.OOE+OO 8.22E+04 1.55E+02 2.58E+03 2.17E+04 1.50E+05 6.44E+03 1.28E+03 1.94E+03 7.80E+03 8.52E+04 4.77E+02 1.46E+03 2.54E-01 2.75E+01 1.70E-01 3.23E+00 2.18E+00 6.73E+01 1.13E+00 3.71E-01 2.65E-01 7.44E-01 1.276E+00 54.21 178.01 1.56E-01 4.79E-01 8.31E-05 8.98E-03 5.55E-05 1.06E-03 7.13E-04 2.20E-02 3.70E-04 1.21E-04 8.67E-05 2.43E-04 uCi/cc 4.66E+00 O.OOE+OO 2.69E+Ol 5.06E-02 8.42E-01 7.09E+00 4.91E+01 2.10E+00 4.19E-01 6.33E-01 2.55E+00 2.79E+01 uCi/LINER 1.43E+07 O.OOE+OO 8.22E+07 1.55E+05 2.58E+06 2.17E+07 1.50E+08 6.44E+06 1.28E+06 1.94E+06 7.80E+06 8.52E+07 4.77E+05 1.46E+06 2.54E+02 2.75E+04 1.70E+02 3.23E+03 (nci/gm)RWCU SYSTEM RESIN&CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE Mn-54 Fe-59 Cr-51 Ba-140 La-140 Co-58 Zn-65 Ag-II0m Cs-136 Nb-95 1-131 Cs-134 ESTIMATED ACTIVITY: Fe-55 THE FOLLOWING ISOTOPES HAVE HALF NUCLIDE Co-60 Cs-137 ESTIMATED ACTIVITIES: S;--90 Nl.-63 H-3 C-14 1-129 Tc-99 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 Pu-241 Pu-238 Pu-239 Am-241 cm-244 TOTAL TRANSURANICS: ALPHA EMITTERS TOTALS:-Tl/2>5 YEARS TOTALS:-ALL NUCLIDES Calc. No. PM-750, Rev. 1, Attachment C, Page C-39 of C-52 J It/'I'?-750 f}-Mw/",J-,;. _(s PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION RD t1, DELTA, PA., 17314 BASED UPON ANALYSIS OF EACH CONDENSATE BATCH CONTAINED IN THE LINER l THE FOLLOWING SHIPMENT

SUMMARY

REPORT HAS BEEN PREPARED FOR 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 3.99E+02 3.99E+05 LIVES GREATER THAN FIVE mCi/LINER uCi/LINER 4.50E+03 4.50E+06 3.79E+03 3.79E+06 CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE Mn-54 Fe-59 Cr-51 Ba-140 La-140 Co-58 Zn-65 Aq-110m Cs-136 Nb-95 1-131 Cs-134 ESTIMATED ACTIVITY: Fe-55 THE FOLLOWING ISOTOPES HAVE HALF NUCLIDE Co-60 Cs-137 ESTIMATED ACTIVITIES: Sf-90 Nl.-63 H-3 C-14 1-129 Tc-99 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 Pu-241 Pu-238 Pu-239 Am-241 cm-244 TOTAL TRANSURANICS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES mCi/LINER 8.33E+02 O.OOE+OO 4.12E+03 1.55E+02 4.51E+02 1.17E+03 8.90E+03 3.07E+02 6.09E+01 1.09E+02 4.83E+02 3.64E+03 2.72E+OO 6.35E+02 3.69E-02 2.45E+01 5.73E-02 8.34E-01 1.47E-02 1.23E+OO 3.09E-02 1.21E-02 1.04E-02 1.88E-02 1.722E-Ol 8959.2 29574.6 uCi/LINER 8.33E+05 O.OOE+OO 4.12E+06 1.55E+05 4.51E+05 1.17E+06 8.90E+06 3.07E+05 6.09E+04 1.09E+05 4.83E+05 3.64E+06 2.72E+03 6.35E+05 3.69E+01 2.45E+04 5.73E+01 8.34E+02 (nCi/qm)uCi/cc 1.28E+OO O.OOE+OO 6.32E+OO 2.38E-01 6.92E-01 1.80E+OO 1.37E+01 4.72E-01 9.35E-02 1.68E-01 7.41E-01 5.58E+OO 6.13E-01 YEARS uCi/cc 6.91E+OO 5.82E+OO 4.17E-03 9.75E-01 5.67E-05 3.75E-02 8.79E-05 1.28E-03 2.25E-05 1.88E-03 4.75E-05 1.86E-05 1.59E-05 2.89E-05 13.76 45.41 Calc. No. PM-750, Rev. 1, Attachment C, Page C-40 of C-52 r 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 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 4.37E+03 4.37E+06 LIVES GREATER THAN FIVE mCi/LINER uCi/LINER 7.27E+047.27E+07 8.27E+04 8.27E+07 RWCU SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE JoIn-54 Fe-59 Cr-51 Ba-140 La-140 Co-58 Zn-65 Ag-110m Cs-136 Nb-95 1-131 Cs-134 ESTIMATED ACTIVITY: Fe-55 THE FOLLOWING ISOTOPES HAVE HALF NUCLIDE Co-60 Cs-137 ESTIMATED ACTIVITIES: S;-90 Nl.-63 H-3 C-14 1-129 Tc-99 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 Pu-241 Pu-238 Pu-239 Am-241 cm-244 TOTAL TRANSURANICS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES mCi/LINER 1.34E+04 O.OOE+OO 7.81E+04 O.OOE+OO 2.12E+03 2.05E+04 1.41E+05 6.13E+03 1.22E+03 1.83E+03 7.32E+03 8.16E+04 4.74E+02 8.29E+02 2.17E-01 3.00E+00 1.12E-Ol 2.40E+00 2.16E+00 6.61E+Ol 1.10E+00 3.59E-01 2.55E-Ol 7.25E-01 1.574E+00 156828.5 514832.9 uCi/LINER 1.34E+07 O.OOE+OO 7.81E+07.O.OOE+OO 2.12E+06 2.05E+07 1.41E+08 6.13E+06 1.22E+06 1.83E+06 7.32E+06 8.16E+07 4.74E+05 8.29E+05 2.17E+02 3.00E+03 1.12E+02 2.40E+03 (nCi/gm)uCi/cc 5.58E+00 O.OOE+OO 3.25E+01 O.OOE+OO 8.83E-01 8.52E+00 5.87E+Ol 2.55E+00 5.08E-01 7.59E-01 3.04E+00 3.39E+01 1.82E+OO YEARS uCi/cc 3.02E+01 3.44E+Ol 1.97E-01 3.44E-01 9.02E-05 1.25E-03 4.67E-05 9.97E-04 8.99E-04 2.74E-02 4.58E-04 1.49E-04 1.06E-04 3.01E-04 65.16 213.90 Calc. No. PM-750, Rev. 1, Attachment C, Page C-41 of C-52 ---('.',-rztJtu E6t=td liners all 8 7-f ()r "'3 JXbt:J Jilt.-A#.-./..JA-I PHILADELPHIA ELECTRIC COMPANY 1'1-7f{JPEACH 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 ,",'.'.\1.44E+04 1.44E+07 4.71E+00 LIVES GREATER THAN FIVE YEARS mCi/LINER uCi/LINER uCi/cc 1.41E+05 1.41E+08 4.62E+01 2.86E+04 2.86E+07 9.36E+00 56.20 282.84 uCi/cc 8.29E+00 1.81E-02 1.05E+02 6.58E-01 7.83E-01 8.93E+00 8.38E+01 4.77E+00 6.49E-01 1.23E+00 2.35E-01 7.57E+00 1.15E-02 6.39E-01 1.72E-03 1.90E-03 1.62E-05 1.47E-04 2.65E-04 1.24E-02 2.42E-04 6.49E-05 5.19E-05 1.88E-04 uCi/LINER 2.53E+07 5.53E+04 3.21E+08 2.01E+06 2.40E+06 2.73E+07 2.56E+08 1.46E+07 1.99E+06 3.76E+06 7.20E+05 2.32E+07 3.52E+04 1.96E+06 5.25E+03 5.81E+03 4.97E+01 4.51E+02 (nCi/gm)171874.3 864975.6 mCi/LINER 2.53E+04 5.53E+01 3.21E+05 2.01E+03 2.40E+03 2.73E+04 2.56E+05 1.46E+04 1.99E+03 3.76E+03 7.20E+02 2.32E+04 3.52E+01 1.96E+03 5.25E+00 5.81E+00 4.97E-02 4.51E-01 8.10E-01 3.80E+01 7.39E-01 1.99E-01 1.59E-01 5.74E-01 8.286E-01 RWCU SYSTEM RESIN&CONDENSATE SYSTEM RESIN ISOTOPIC ANALYSIS REPORT: NUCLIDE Mn-54 Co-57 Cr-51 Ba-140 La-140 Co-58 Zn-65 Aq-110m Zr-97 Nb-95 1-131 Cs-134 ESTIMATED ACTIVITY: Fe-55 THE FOLLOWING ISOTOPES HAVE HALF NUCLIDE Co-60 Cs-137 ESTIMATED ACTIVITIES: S+-90 Nl.-63 H-3 C-14 1-129 Tc-99 ESTIMATED TRANSURANIC ACTIVITIES: cm-242 Pu-241 Pu-238 Pu-239 Am-241 cm-244 TOTAL TRANSURANICS: ALPHA EMITTERS TOTALS:-T1/2>5 YEARS TOTALS:-ALL NUCLIDES Calc. No. PM-750, Rev. 1, Attachment C, Page C-42 of C-52 '." e5J1.eteo'lological evaluation Se'lvices, c!Jnc.J 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,rected for source elevation. The resul ts of thesetions 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 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 LPZtions, 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 stacktion. Calc. No. PM-750, Rev. 1, Attachment C, Page C-43 of C-52 Mr.Alan Marie December 18, 1979 Page 2 adl#PH-7?O<;/,J-$I?"Due to both the meteorology and terrain, the maximum two-hour X/Q at each receptor distance did not always occur in the same sector.At close-in receptors (less than 4,600 m)the"_two-hour X/Q values were caused by the very unstable The very unstable case occurs predominantly with ESE and SE winds, putting the maximum values at the close-in distances in the WNW and NW sectors.At the farthertances, as the terrain becomes higher, the.5%two-hour X/Q values are caused by the stable case and occur in the NE and ENE sectors.Therefore, the X/Q's in Figure 3 are the maximum sector values at each receptor distance.A plot of the maximum two-hour X/Q versus distance from the off-gas stack is shown in Figure 4.Due to both thetion and terrain corrections, the plot is quite"bumpy" with several peaks.It is for this reason that we did not use a uniform receptor spacing in Figure 3, and instead chose the appropriate distances such that no peaks would be missed if one were to interpolate X/Q values between the receptortances.As I have stated earlier, the off-gas stack calculations were done very conservatively for the sake of time.If thesulting isodose curves are too high, we could produce a less conservative set of X/Q's if given more time.However, until we actually do it, I cannot make an estimate on how much lower the numbers would be.Sincerely yours,*.B,t Patrick T.Brennan PTB:rg Enc. Calc. No. PM-750, Rev. 1, Attachment C, Page C-44 of C-52 )+.b FIGURE 1 I PEACH BOTTOM VENT ACCIDENT X/Q SE SECTOR.5%PROBABILITY 8/67.-7/71 DATA BASE':0-f4B Ltt.D.......L.(-)2-k ,,-8'J.....I'"-72 k (,2.'1 4 3'001-.,710 t-.;/././.ObJE-J-1.2'13 P....:!L 2.10D*E--3 E-Cf 3.S'fI-.,_$.2'13£-S-dsoo*").S"DD-'t.3.732.£-&f -!1../"0£-5" 1*121 E-S: ,./DoE-r-- .3.000 E-li.J... J: 0 '.>016-5" 3. ..4_.._." 1000 ,.(, O()E-'t"'.2 II'tG-S'lIJI25E-S-

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Calc. No. PM-750, Rev. 1, Attachment C, Page C-46 of C-52 FIGUlili J I PEACH BOTTOM OFF-GAS STACK ACCIDENT X/Q MAXIMUM SECTOR.5%PROBABILITY 8/677/71 DATA BASE l"1 E4i)...."t-C-'\ 11 L I'J....72 4 (, 2.If J-....3'001..-'/710 L...,/00 tt-1.013 E-'I 3.2 e{S" E-t,.31{,$-'Iff."-, /*'13,E-1 3./33 E-i 1.£ili.S"_8.:--_..-----_...**..*-e'***' $"71 3*7'1t,£-, 1.0$'>£-" I.'17£-7 3.772.E-1 "..-j()OD*4."4£*&'2.27ifE-'C.ltJ£-7 '1."172 E-,/.39z'E',s-2.05"2.tI-1.1//E-S-'.3.'3'11.£-,}.S7'lE-b.>.1'1*11t-E-8'.g3'1£-8 8.'01£-'1 1'100---_.-._......--/bOO 1*12 3£-S-3.5"8'1£-" 1.0l8E-6 S.893£-7'1.9'13£-8 2.:3'7£-t 1.140£-8---'.000 /.37/'[-'4.7'13£-7 ?-*')1/$-1 '*Si3';-f: I<I.too t-" 3.71,0[-'2.'15"8£-" Cf.7&9f.-j 2.S1iE-7 , 2'800 S:/j,E-ij 1.1 f)00)./oo£-s-4.320£-" 2.g'lOE-'1./'12 F-(, 3.0'13£-7 ,.071J£-7&'.25"0£-s.-4300 I.'200£-.5'

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S'>'5'12.£-1*indicates concentrations corrected for fumigation tt"1'& Calc. No. PM-750, Rev. 1, Attachment C, Page C-47 of C-52 LPc FIGURE 3 con't PEACH BOTTOM OFF-GAS STACK ACCIDENT X/Q MAXIMUM SECTOR.5%PROBABILITY 8/67-7/71 DATA BASE D;..." c e..(rn\2'k 11 l.-I--72 k (,2.'1 k 3'COJ...'710S"2.t>0 1.'/'10 3.703£-'1.3s-e/E-{g 3.22.3£"/.002 E-'7 s-.641'1..G/0 t>J.300 E-S'-I, 3.3g'l£-b I."1-7'tr"-, 3."0£-'}.01'£-'7 5:7/1£-9,._----- J.S5'of-,5'.J.g'J E*" 1.'f12E-'3.33"';-'1 }.03£/E-7 s: 707 E-f--.._--_.....*..__....._....-...-.-_....-......".............'--<iCloo 1.300£-5" 5':280£-':3.3'-'1 t-' e-{, 3.//0£-i&f.lf.f5t"-8 C. /20.73 ,7*tiD()E-" 3.22'1£-6 2.071£-'/.18/£-'2.02of,-7 b.'21£-'3.7,'1 E--"il'ff:, 3./06£-" I*').73£-' 3./0'£-'7 1."7£"-8 2.S.2I£-'/."12.6'£"-8

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.. ..::-i..::::: it!;::::::::;:!'iI ....:*t c*...., ...;.-.,), IflO000 Calc. No. PM-750, Rev. 1, Attachment C, Page C-49 of C-52 FORM 5611 UNITED ENGINEERS AND CONSTRUCTORS COMPUTER DISCLOSURE SHEET DISCIPLINE /VudeaC CLIENT*Cl1t.\.... DATE'o/'J.-t/9PROJECT-UlA:h..,./'3\.0-",,) F.lc,*\,1:;- JOB NO.7 IICALC.SET fNJ-750 PROGRAM(S) USED REV.NO.REV.DATE STATUS PRELIM.0 FINAL 6!'"'*0\992 VOID 0 UE&C PREQUALlFICATION YESNO 0 RUN NO.DESCRIPTION ANAL YSIS DESCRIPTION /'0 d,-"..J-Ii.- Jtim_,!r t::s 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 ON 10 I?oJ 9,2-RUN BY .1""- CHECKED BY P...fRQ,-Jq APPROVED BY REMARKS-.\ Calc. No. PM-750, Rev. 1, Attachment C, Page C-50 of C-52 29 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 cJ(1f I'n-7.7'CJ Calc. No. PM-750, Rev. 1, Attachment C, Page C-51 of C-52 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 JII J'/'?-7.5 CJ Calc. No. PM-750, Rev. 1, Attachment C, Page C-52 of C-52 C<<./'r If 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>kd-f J!53 O.OOE+OO 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 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 Checked by: H.RothsteinApproved by: D.GardnerRemarks: 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 producetheHIC 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.GoldenChecked by: H.RothsteinApproved 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}}