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LGS UFSAR CHAPTER 12 12.1-1 REV. 17, SEPTEMBER 2014 CHAPTER 12-RADIATION PROTECTION 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS REASONABLY ACHIEVABLE 12.1.1 POLICY CONSIDERATIONS 12.1.1.1 Management Policy It is the licensees policy to maintain occupational radiation exposure ALARA at LGS. This includes maintaining the annual dose to individuals working at the station ALARA, and keeping the annual integrated dose to station personnel ALARA. The management of this company is firmly committed to performing all reasonable actions to ensure that radiation exposures are maintained ALARA.
Sections 12.1.2 and 12.3 discuss the ALARA considerations that have been incorporated into the design of the LGS.
LGS will be operated and maintained in such a manner as to ensure that occupational radiation exposures are ALARA and that protection against radiation is in accordance with 10CFR20. The health physics provisions which accomplish this goal are described in Section 12.5.
12.1.1.2 Management Responsibilities Chapter 13 describes the Limerick Generating Station operating organization and the licensees corporate organization.
The President and Chief Nuclear Officer has the ultimate responsibility for operation of the Limerick Generating Station. This responsibility includes those activities necessary to ensure that radiation exposures are maintained ALARA. Responsibility is delegated to the Senior Vice President - Nuclear Operations and to the Vice President - Station Support (for all activities performed by the Station Support Department), and to the Vice President - Limerick Generating Station for all activities performed at the station. The Station Support Department provides technical support as needed to the Limerick Generating Station health physics organization in an effort to maintain the highest standards of exposure minimization. The Vice President - Limerick Generating Station delegates responsibility for the ALARA program through the Plant Manager to the Radiation Protection Manager who has responsibility for all actions required to maintain station exposures ALARA. The responsibilities of the Station Support Division staff, the Plant Manager, and Radiation Protection Manager in regard to ALARA are further described in Section 13.1.2.1.2.
These responsibilities correspond to the applicable functions described in Regulatory Guide 8.8, Rev. 3 and Regulatory Guide 8.10, Rev.1.
12.1.1.3 Policy Implementation The licensee provides the environment and support for the ALARA policy to function. The company's commitment to this policy is manifested in the plant design, established procedures, the provisions for review of procedures and plant design, provisions for subsequent procedure revisions and plant modifications, and the establishment of extensive varietal training programs.
LGS UFSAR CHAPTER 12 12.1-2 REV. 17, SEPTEMBER 2014 General Employee Training, which encompasses radiological health aspects, is described in Sections 13.2.1.2. Such training enhances personnel awareness of licensee management's policy of maintaining exposures ALARA, of actual and potential problems, and of the need to develop proper attitudes. The training stresses the individual's responsibility to cooperate in maintaining exposures ALARA and the importance of adhering to approved procedures. The content of the training is adjusted in recognition of the duties, responsibilities, and anticipated radiation exposure of those receiving instruction and includes information on the biological effects of such exposure. The staff of the Radiation Protection Manager has well defined functions, responsibilities, and authorities to ensure proper supervision and implementation of health physics procedures. The Radiation Protection Manager has the authority to prevent unsafe practices and to direct steps to prevent any unnecessary radiation exposures. The plant staff health physics group assures that communication with supervisors of the various station service groups (e.g.,
maintenance, construction, instrument technicians, contractors) and operating supervisors occurs for the purpose of evaluating a course of action regarding ALARA for specific station activities.
Such evaluation includes the review of appropriate procedures; the extent of existing or potential hazards, occupationally and to the general public; and the merits of applying special techniques to the performance of a job. Such communication with work forces is an effective means to respond to worker questions and concerns and to obtain information on actual working conditions, such as mobility, access, habitability, and necessary tooling, which can lead to future improvements.
The plant staff health physics group is knowledgeable of the origins of radiation exposure in the plant and its magnitudes. They recognize which jobs or locations cause the highest exposures.
This information is obtained via area surveys, Radiation Work Permits (or equivalent), and personnel dosimetry. Analysis of these and other data for repeat or similar activities is performed to determine whether exposures are being decreased or at least prevented from increasing.
There is prompt investigation of exposures of record which exceed expected values. Judicious application of dose extensions is exercised by review of prior data and analysis of the need for the exposure. The health physics procedures provide for appropriate documentation of reviews, surveys, analyses, and investigations such that corrective action or modification may be accomplished and subsequent data may be compared to the original data to verify effectiveness of the change. The need for modification to satisfy ALARA shall be based on consideration of the economics of equipment modification in relation to benefits to health and safety and other societal and socioeconomic considerations, including the utilization of atomic energy in the public interest.
To verify that the health physics operations at the station are functioning within the ALARA concept, a formal review shall be performed under the cognizance of the Station ALARA Council every three years (based upon the date of commercial operation of Unit 1). The review shall include review of applicable station procedures and practices, exposure records, the content of training programs which affect ALARA considerations, and consultation with the plant staff health physics group. The objective of the review is to evaluate the adequacy of the ALARA effort and, as appropriate, to determine means to lower exposures. The results of the review shall be documented, including identification of the procedures and records reviewed, the review team's evaluation, and any recommendations for improvements.
12.1.2 DESIGN CONSIDERATIONS This section describes those considerations which are applied to the plant design for the purpose of incorporating features which provide for maintaining occupational radiation exposures ALARA.
Refer to Sections 12.3.1, 12.3.2, and 12.3.3 for details of design for maintaining personnel radiation exposures ALARA.
LGS UFSAR CHAPTER 12 12.1-3 REV. 17, SEPTEMBER 2014 Experiences and data from operating plants are evaluated to decide if and how equipment or facility designs can be improved to reduce overall plant personnel exposures. During plant design, operating reports and data such as that given in WASH-1311, NUREG-75/032, NUREG-0109 and Compilation and Analysis of Data on Occupational Radiation Exposure Experienced at Operating Nuclear Power Plants (References 12.1-1 through 12.1-4, respectively), are reviewed to determine which operations, procedures or types of equipment were most significant in producing personnel exposures. Methods to mitigate such exposures have been implemented wherever possible and practicable.
12.1.2.1 General Design Considerations The objectives of the plant design for ALARA purposes are: to minimize the need for, and duration of, personnel access into high radiation areas, and to establish radiation levels as low as practicable in routinely occupied areas.
Both equipment and facility designs are considered in achieving these objectives during plant operations including normal operations, maintenance and repair, refueling operations, fuel storage, inservice inspection, waste handling and disposal, and other anticipated operational occurrences.
In addition to equipment and facility designs, system designs are considered to ensure that exposures are maintained ALARA. For example, both the primary coolant system and the condensate system are provided with cleanup capability to reduce the inventory of circulating corrosion products. This is one of the methods employed to minimize both the activation of these corrosion products and their subsequent deposition on the interior surfaces of piping and equipment.
The project design organization is responsible for ensuring that the design and construction of the facility are such that occupational exposures are ALARA. To the extent practicable, this includes:
a.
Design concepts and station features that reflect consideration of the activities of station personnel that might be anticipated and that might lead to personnel exposure to substantial sources of radiation; and assurance that station design features have been provided to reduce the anticipated exposures of station personnel to these sources of radiation.
b.
Specifications for equipment that reflect the objectives of ALARA, including among others, considerations of reliability, durability, serviceability, and limitations of internal accumulations of radioactive material.
12.1.2.2 Equipment Design Considerations Considerations for equipment design include:
a.
Reliability, long service life, maintenance and calibration requirements, durability.
b.
Convenience for servicing, including disassembly and reassembly, modular design concept for rapid component replacement, removal for servicing in lower radiation area.
LGS UFSAR CHAPTER 12 12.1-4 REV. 17, SEPTEMBER 2014 c.
Remote operation, inspection, monitoring, servicing, and repair including the use of special tools or equipment.
d.
Redundant equipment to reduce the urgency for immediate repairs, thus providing time for planning repairs with ALARA in mind.
e.
Isolation, draining, flushing, or decontamination of systems to reduce crud deposition and thus reduce radiation levels.
f.
Isolation of components from contaminated process fluids.
g.
Use of high quality components, such as valves, which minimize or preclude the leakage of radioactive material.
h.
Use of closed drain systems for contaminated process fluids to preclude the creation of airborne contamination that is due to spillage.
12.1.2.3 Facility Design Considerations Considerations for facility design include:
a.
Location of equipment according to the need for access to maintain, inspect, monitor, or operate so as to minimize radiation exposure.
b.
Use of valve stem extensions, articulated if necessary, to operate valves from behind shield walls.
c.
Transport of contaminated components for service in lower radiation areas or for reuse in other parts of the plant.
d.
Separation of sources of radiation such as pipe runs, storage tanks, and filters from normally occupied areas.
e.
Use of permanent shielding between sources of radiation and access and service areas.
f.
Maintaining ventilation flow paths from clean areas to contaminated areas.
g.
Use of surface coatings to facilitate decontamination.
h.
Use of labyrinth entrances to shielded cavities.
12.1.2.4 ALARA Design Review For the operating plant, procedures provide for review of subsequent plant design and modifications by the radiation protection group, when applicable, and documentation of an ALARA design review. Procedures are described in Section 12.1.3. The following material describes the ALARA design review for the initial plant design and construction and is historical in nature.
LGS UFSAR CHAPTER 12 12.1-5 REV. 17, SEPTEMBER 2014 Bechtel, as agent for the licensee, has developed an "In-Plant Radiation Exposure ALARA Review Specification". This specification was applied during all construction phases to perform multidisciplinary reviews of the plant to assure a design that:
a.
Maintains the annual operating and maintenance radiation doses to individuals ALARA b.
Keeps the annual integrated radiation doses to all personnel ALARA.
This specification defined the purpose of the review; established the project ALARA review team; and described the discipline ALARA review process, the extent and format of ALARA review meetings, and the method of noting and resolving ALARA design changes. This specification is consistent with design guidelines given in Regulatory Guide 8.8.
The Bechtel Project Mechanical/Nuclear Group was responsible for the overall coordination of the ALARA design review and the interaction between the various Bechtel project disciplines, Bechtel Construction, the Bechtel Staff Radiation Protection Group, and the licensee.
The groups involved in the ALARA review program and their relationships are shown on Figure 12.1-1.
An experienced engineer from the Mechanical/Nuclear Group served as the project ALARA coordinator and was responsible for overall coordination of the ALARA reviews. Duties included maintaining the ALARA Review Specification and the ALARA documentation file, expediting the ALARA reviews, and resolving any ALARA inconsistencies. The project ALARA coordinator obtained input and expertise from the licensee, the Radiation Protection Group, and other Bechtel groups, as required.
An engineer was assigned from each engineering discipline to serve as the discipline ALARA representative. The discipline ALARA representatives coordinated and conducted the ALARA reviews within the discipline, interfaced between the discipline and the project ALARA coordinator, and expedited any design changes that resulted from the ALARA review.
Engineers from the field were assigned as construction ALARA representatives. They were responsible for reviewing field designs and field modifications to existing designs for consistency with the ALARA Review Specification. The construction ALARA coordinator coordinated the ALARA reviews in the field and interfaced between construction and engineering.
Experienced radiation protection specialists from the staff of the chief nuclear engineer provided health physics and radiation protection design input to the project. A radiation protection specialist was assigned to support the project design and ALARA review and was responsible for interfacing between the group and the project ALARA coordinator. The radiation protection specialist represented the staff radiation protection group during the ALARA reviews.
The licensees ALARA coordinator was a licensee engineer who represented the licensee during the ALARA reviews. One of the responsibilities was to advise the project ALARA coordinator of potential ALARA problems based on the licensee's experience from operating plants, by receiving input from the licensees Health Physics and Operations groups. The licensees ALARA coordinator also reviewed and provided input to the ALARA Review Specification, reviewed
LGS UFSAR CHAPTER 12 12.1-6 REV. 17, SEPTEMBER 2014 exceptions to the ALARA design criteria, and provided licensee input for resolving ALARA inconsistencies that were identified during the ALARA review.
To facilitate documentation and coordination of the ALARA review effort, a scheduled system and activity design review approach was followed. Maximum review effort was expended on those systems and activities as identified in Table 12.1-1 that in the past had resulted in the highest occupational radiation exposures in operating plants. Each system and activity was divided into plant areas. The ALARA design review was conducted by reviewing each of these areas.
The design review was conducted in the home office by the discipline ALARA representatives, project ALARA coordinator, and the radiation protection specialist. The major tools used in the design review were the ALARA design review considerations checklist, which identified design features that were judged to be generally cost effective with respect to maintaining occupational radiation exposures ALARA, and the ALARA design review considerations sign-off sheet. The sign-off sheet documented the review of the design by the responsible discipline(s). The discipline ALARA representatives and the radiation protection specialist verified that the design considerations assigned to their groups were met.
The ALARA review of field designs and modifications was conducted by the construction ALARA representatives. The discipline responsible for the new design or modification was responsible for documenting that it had been reviewed for ALARA. The project ALARA coordinator coordinated any reviews that affected other disciplines or groups.
Compliance with the ALARA design review considerations was documented by the reviewer on the design review considerations sign-off sheets, which are kept on file. Any exceptions to the considerations were reviewed on a case-by-case basis.
12.1.2.5 ALARA Design Considerations for Decommissioning The design features necessary to maintain radiation exposures ALARA during decommissioning operations are, in general, the features that have been implemented to keep exposures ALARA during the operational life of the plant. These are discussed in Sections 12.1.2.1, 12.1.2.2, 12.1.2.3, and 12.3. Some of these features that are especially applicable to decommissioning are discussed below.
a.
Flushing and draining connections will provide for removal of radioactive fluids, allow rinsing to reduce residual activity, and provide an entry point for introduction of decontamination solutions.
b.
Ventilation systems to minimize the spread of airborne radioactivity will be particularly useful in preventing exposures to internal radioactivity during decommissioning when large quantities of airborne radioactive particulates can be generated by cutting, sawing, and demolition.
c.
The space envelopes reserved around equipment to facilitate maintenance will also allow for more rapid dismantling because cutting machines and other decommissioning equipment can be quickly installed with correspondingly lower exposure time.
LGS UFSAR CHAPTER 12 12.1-7 REV. 17, SEPTEMBER 2014 d.
The use of flanged connections on pumps in radioactive waste systems, and the removal provisions built into some major plant components, will reduce exposures to personnel during removal of these items.
e.
Separation of radioactive from nonradioactive systems, and location of active components of nonradioactive systems in low radiation areas, will permit dismantling of normally clean systems with minimal exposure to personnel.
f.
The availability of a complete, shielded radwaste facility will allow efficient low dose processing of residual fluids and decontamination solutions, as well as the packaging and shipping of solid radioactive materials. Other existing facilities, such as access control stations and decontamination areas, will also perform their intended functions in helping to keep exposures ALARA.
g.
The use of liners and protective coatings will lower exposures by minimizing decontamination times and by reducing the quantities of materials that must be handled as radioactive waste.
12.1.3 OPERATIONAL CONSIDERATIONS This section describes the development and implementation of operating procedures, including procedures for radiation protection and the ALARA program.
Plant procedures are further described in Section 13.5. Health physics operations are described in Section 12.5.
12.1.3.1 Procedure Development Various procedures are written for the different activities associated with plant operations. These include procedures for operating, maintenance, surveillance testing, fuel handling, emergencies, radiation protection, and administration. The development of each variety of procedure is described in the administrative procedures.
The different procedures are prepared by personnel having experience and expertise in that particular area. The experience gained from operation of the PBAPS units and other plants is incorporated into procedure development. Each procedure is reviewed and approved per Administrative procedure process. Health physics personnel review procedures for activities which can affect radiation exposure.
Procedures are subject to revision whenever improved techniques or increased safety are indicated.
12.1.3.2 Exposure Reduction Procedures The ALARA concept is first and foremost practiced on the job by communication between health physics technicians or health physics supervisors and the workers. The health physics representatives are aware of the radiation conditions and advise the workers accordingly.
LGS UFSAR CHAPTER 12 12.1-8 REV. 17, SEPTEMBER 2014 Specific radiation procedures describe the techniques to determine the radiological conditions in an area. Once determined, procedures describe the actions necessary to incorporate exposure reduction techniques as required.
12.1.3.3 General ALARA Techniques The predominant exposure dose is received during outages. Although ALARA considerations are not limited to outage work, the activities conducted during outages are the most significant for dose reduction.
During the outage planning stages, an ALARA representative is designated by Health Physics supervision to review the jobs planned and evaluate the need for an ALARA effort. Examples of some techniques that apply to an ALARA evaluation are:
a.
Reducing dose rate from a system by draining, flushing, filling, decontaminating.
b.
Installing permanent or temporary shielding if the net result is reduction in man-rem.
c.
Training workers to improve proficiency, thus reducing stay time in the radiation area.
d.
Maintaining the work force in radiation areas to the minimum required to perform the job efficiently and safely.
e.
Establishing control points in low radiation areas.
f.
Avoiding excess conservatism in prescribing protective clothing and respirators to avoid undue stress and decreased efficiency of the workers.
g.
Using special tools for remote handling of components.
h.
Planning and preparing techniques and tools needed to accomplish the job before the job is started.
i.
Using historical data for comparable jobs as guidelines and to establish an expected dose limit for the job.
j.
Using remote monitoring/alarming dosimeters in high radiation areas to maintain close checks on personnel exposures.
k.
Providing adequate communications to facilitate performance of the job and to alert workers to adverse changes in radiation conditions.
l.
Source identification and use of routine or special survey data.
m.
Construction of contamination containment devices such as glove boxes and tents.
n.
Removing components to low radiation areas for servicing or repair.
LGS UFSAR CHAPTER 12 12.1-9 REV. 17, SEPTEMBER 2014 o.
Planning for adequate space and auxiliary services, such as lighting, welding leads, service air lines, and TV cameras, as necessary to accomplish the work quickly.
p.
Establishing auxiliary ventilation/filtration systems.
q.
Wet transfer or storage of contaminated components to prevent airborne contamination.
r.
Contingency planning to account for known personnel hazards or accidents which may occur.
s.
Isolating systems to be worked on or possible load reductions or plant shutdowns to reduce doses.
The ALARA representative communicates with other disciplines (maintenance, operating, instrument and control, etc.) as appropriate to discuss the implementation of ALARA techniques.
The cooperation of more than one discipline is usually required for most jobs.
The dosimetry program consists of DLRs or equivalent badges processed by a National Voluntary Laboratory Accreditation Program (NVLAP) accredited contractor for official data of record.
Additionally, direct reading dosimeters are used as the unofficial dosimetric device. The computerized dosimetry record system and the ability to process the unofficial dosimetric device onsite provide a powerful tool for maintaining surveillance and managing each workers dose accumulation. The direct reading dosimeters provide immediate readings and are available to obtain estimated exposures whenever there is concern. Workers' assignments to radiation areas can then be limited if administrative guidelines or regulatory limits are approached.
This same system produces tabulated lists of workers' exposures-to-date for each supervisor.
These lists are provided routinely so the supervisors can know the dose accumulation of their workers, observe trends, and assign work duties more efficiently. Changes to the dosimetry program, such as contractor service versus onsite processing, frequency of badge changes, and types of dosimetric devices are made periodically to enhance the value of the program. Annual exposure reviews will be performed by the Engineer - Health Physics and Chemistry in order to identify groups with the highest exposure.
12.1.3.4 Operating Experience Experience gained during operation of PBAPS Units 2 and 3 serves as a basis for procedures, techniques, and administrative controls for LGS. Exposure data from specific jobs previously performed at PBAPS have caused design changes during construction of LGS. The LGS Hot Maintenance Decontamination Shop design incorporates lessons learned from PBAPS.
12.
1.4 REFERENCES
12.1-1 T.D. Murphy, WASH-1311, UC-78, "A Compilation of Occupational Radiation Exposure from Light-Water-Cooled Nuclear Power Plants 1969-1973", NRC, Radiological Assessment Branch, (May 1974).
LGS UFSAR CHAPTER 12 12.1-10 REV. 17, SEPTEMBER 2014 12.1-2 T.D. Murphy, et.al., NUREG-75/032, "Occupational Radiation Exposure at Light-Water-Cooled Power Reactors 1969-1974", NRC, Radiological Assessment Branch, (June 1975).
12.1-3 T.D. Murphy, et. al., NUREG-0109, "Occupational Radiation Exposure at Light-Water-Cooled Power Reactors 1968-1975", NRC, Radiological Assessment Branch, (August 1976).
12.1-4 C.A. Pelletier, et. al., National Environmental Studies Project, "Compilation and Analysis of Data on Occupational Radiation Exposure Experienced at Operating Nuclear Power Plants", Atomic Industrial Forum, (September 1974).
LGS UFSAR CHAPTER 12 12.1-11 REV. 13, SEPTEMBER 2006 Table 12.1-1 SYSTEMS AND ACTIVITIES INCLUDED IN ALARA REVIEW
- 1. Waste Management Systems
- a. Liquid Waste Management System
- b. Solid Waste Management System
- c. Gaseous Waste Management System
- 2. Reactor Water Cleanup System
- 3. Fuel Pool Cooling and Cleanup System
- 4. Condensate Demineralizer System
- 6. Residual Heat Removal System
- 7. Main Steam System
- 8. Air Removal System
- 9. Feedwater System
- 10. High Pressure Coolant Injection System
- 11. Reactor Core Isolation Cooling System
- 12. Maintenance Activities
- a. Drywell Area Activities
- b. Refueling Area Activities
- c. Main Condenser Area Activities
- d. Inservice Inspection Activities
- e. TIP Maintenance Activities
- f. CRD Removal and Maintenance Activities
- g. Local Leak Rate Testing Activities
LGS UFSAR CHAPTER 12 12.1-12 REV. 13, SEPTEMBER 2006 Table 12.1-1 (Cont'd)
- h. Hot Maintenance Shop Activities
- i. Snubber Inspection Activities
- 13. Miscellaneous
- a. Radiation Zone I and II Areas
LGS UFSAR CHAPTER 12 12.2-1 REV. 16, SEPTEMBER 2012 12.2 RADIATION SOURCES In this section the sources of radiation that form the basis for shield design and the sources of airborne radioactivity required for the design of personnel protective measures and for dose assessment are discussed and identified.
12.2.1 CONTAINED SOURCES The shielding design source terms are based on a noble gas fission product offgas release rate of 0.35 Ci/sec (after 30 minutes of decay) and the corresponding fission, activation, and corrosion product concentrations in the primary coolant. The guidance provided in ANSI N237 was not used to determine the shielding design source terms for LGS. The specific alternate methods used for calculating source term magnitudes are described in Section 11.1. The shielding design source terms in the primary coolant are listed in Tables 12.2-1 through 12.2-5. Throughout most of the primary coolant system, activation products, principally nitrogen-16, are the primary radiation sources for shielding design.
Basic reactor data and core region descriptions used for this section are listed in Tables 12.2-6 through 12.2-8.
The shielding design source terms are presented by enclosure location and system. Locations of the equipment discussed in this section are shown on the shielding and radiation zoning drawings, drawings N-110, N-111, N-112, N-113, N-115, N-116, N-117, N-118, N-119, N-120, N-121, N-122, N-124, N-125, N-126, N-127, N-128, N-130 N-131, N-132, N-133, N-134, N-135, N-136, N-137, N-140, N-141, N-142, and N-143. Detailed data on source descriptions for each shielded area are presented in Tables 12.2-11 through 12.2-13.
Shielding source terms presented in this section and associated tables are based on conservative assumptions about system and equipment operations and characteristics to provide reasonably conservative radioactivity concentrations for shielding design. For all systems transporting radioactive materials, conservative allowance is made for transit decay while at the same time providing for daughter product formation. Assumptions from NUREG-0016 (Reference 12.2-1) were also used where applicable. Therefore, the shielding source terms are not intended to approximate the actual system design radioactivity concentrations.
12.2.1.1 Primary Containment 12.2.1.1.1 Reactor Core The radiation within the drywell during full power operation includes neutron and gamma radiation resulting from the fission process in the core. Tables 12.2-9 and 12.2-10 list the multigroup neutron and gamma ray fluxes at the outside surfaces of the RPV and the primary shield at the core midplane. The gamma fluxes include those resulting from capture or inelastic scattering of neutrons within the RPV, the core shroud, and the primary shield, as well as gamma radiation resulting from prompt fission and fission product decay. The largest radiation sources after reactor shutdown are the decaying fission products in the fuel. Table 12.2-14 lists the fuel assembly source terms. Secondary sources include the structural material activation of the RPV, its internals, and the piping and equipment located in the primary containment; and the activated corrosion products accumulated or deposited in the internals of the RPV, the primary coolant piping, and other process system piping in the primary containment.
LGS UFSAR CHAPTER 12 12.2-2 REV. 16, SEPTEMBER 2012 12.2.1.1.2 Reactor Coolant System Sources of radiation in the RCS used for shielding design are fission products estimated to be released from fuel and activation and corrosion products that are circulated in the reactor coolant.
These sources are listed in Tables 12.2-1 through 12.2-5. The N-16 concentration in the reactor coolant, with HWC, is bounded at 4.8x10-5 Ci/gm of coolant at the reactor recirculation outlet nozzle.
12.2.1.1.3 Main Steam System Radiation sources in the main steam system piping include activation gases, principally N-16, and the corrosion and fission products carried over to the main steam system.
The N-16 concentration without HWC in the steam is assumed to be 5.0x10-5 Ci/gm of steam leaving the reactor vessel at the nozzle. Fission product radioactivity corresponds to an offgas release rate of 0.35 Ci/sec at 30 minutes decay from the reactor nozzle. Partition factors for carryover of radioactivity into the main steam system are 100% for gases, 2% by weight for halogens, and 0.1% by weight for particulates. These partition factors are applied to the reactor water shielding source terms as given in Tables 12.2-1 through 12.2-5.
Hydrogen injection by the HWC system causes the reactor water chemistry to become less oxidizing which results in a re-distribution of the N-16 normally produced by radiolysis in the reactor core. Under HWC conditions more of the N-16 is carried over into the steam and less remains in the reactor water. Under HWC conditions the N-16 concentration in the steam is 2.50x10-4 Ci/gm.
12.2.1.1.4 Drywell Sumps The concentrations of radioisotopes used for shielding design for the drywell equipment and floor drain sumps are listed in Table 12.2-15.
12.2.1.2 Reactor Enclosure and Refueling Area 12.2.1.2.1 Reactor Water Cleanup System Radiation sources in the RWCU system consist of those radioisotopes carried in the reactor water. The activity inventory is based on component transit times. The radioisotopes for the RWCU recirculation
- pumps, regenerative and nonregenerative heat exchangers, filter/demineralizers, holding pumps, and the backwash receiving tank are the accumulated fission, activation, and corrosion products, based on the inlet reactor coolant concentrations given in Tables 12.2-1 through 12.2-5, allowing for decay due to transit time. Tables 12.2-16 through 12.2-23 provide the shielding design source terms for these components.
12.2.1.2.2 Residual Heat Removal System The pumps, heat exchangers, and associated piping of the RHR system are carriers of radioactive materials. For plant shutdown, the RHR pumps and heat exchangers are the radiation sources, resulting from the radioisotopes carried in the reactor coolant after four hours of decay following shutdown. The source terms listed in Table 12.2-24 are used for the shielding calculations for this system.
LGS UFSAR CHAPTER 12 12.2-3 REV. 16, SEPTEMBER 2012 12.2.1.2.3 Reactor Core Isolation Cooling System Components of the RCIC system that contain radiation sources are the RCIC turbine and steam inlet and exhaust piping. The steam radioactivity, as discussed in Section 12.2.1.1.3, without decay correction for transit from the RPV steam nozzles, is used for the shielding calculations for this system and is listed in Table 12.2-25.
12.2.1.2.4 High Pressure Coolant Injection System The radiation sources for the HPCI system are the HPCI turbine and the steam inlet and exhaust piping. The steam radioactivity, as discussed in Section 12.2.1.1.3, decayed for the appropriate transit time, is used for the shielding calculations for this system and is listed in Table 12.2-26.
12.2.1.2.5 Core Spray System The core spray system components, during testing, use condensate from the CST which contains very low radioactivity concentrations (Table 12.2-87); therefore, no shielding is required.
12.2.1.2.6 Spent Fuel Storage and Transfer The predominant radiation sources in the spent fuel storage and transfer areas are the spent fuel assemblies. For shielding design purposes only, the spent fuel pool is assumed to contain 2862 fuel assemblies. These spent fuel assemblies are conservatively assumed to have 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of decay. Shielding design source terms are shown in Table 12.2-14.
12.2.1.2.7 Fuel Pool Cooling and Cleanup System Sources of radiation in the FPCC system result from the transfer of radioisotopes from the reactor coolant and crud deposits on spent fuel assemblies into the spent fuel pool during refueling operations. The shielding design source terms for the FPCC system are presented in Table 12.2-27. These source terms then undergo subsequent decay and accumulation on the FPCC filter/ demineralizers. Table 12.2-28 shows the FPCC filter/demineralizers shielding design source terms. The shielding design source terms for the FPCC heat exchanger are shown in Table 12.2-29.
12.2.1.2.8 Reactor Enclosure HVAC System Components of the reactor enclosure HVAC system that contain sources of radioactivity are the equipment compartment exhaust air filters. Table 12.2-30 shows the reactor enclosure equipment exhaust air filters shielding design source terms.
12.2.1.2.9 Control Rod Drives Shielding design source terms for the CRD mechanisms after removal from the RPV are shown in Table 12.2-31.
12.2.1.3 Turbine Enclosure 12.2.1.3.1 Primary Steam and Power Conversion Systems Radiation sources for piping and equipment that contain primary steam are based on the radioisotopes carried over into the main steam from the reactor coolant and include fission
LGS UFSAR CHAPTER 12 12.2-4 REV. 16, SEPTEMBER 2012 product gases and halogens, particulate fission and corrosion products, and gaseous activation products as discussed in Section 12.2.1.1.3. Steam density variations and steam transit times through equipment and pipes are factored into the shielding source term evaluation to account for volumetric dilution effects, radiological decay, and daughter product generation. Tables 12.2-32 through 12.2-36 show the shielding design source terms for the following components that use main steam; moisture separators, cross-around piping, feedwater heaters, steam seal evaporator, and the reactor feed pump-turbine.
12.2.1.3.2 Condensate and Feedwater Systems The radiation sources in the condensate and feedwater systems are based on decayed main steam radioactivity (Section 12.2.1.1.3). Eighty percent of the N-16 and 100% of the noble gases are assumed to be removed from the condensate and feedwater systems by the main condenser air removal system. The gaseous radiation sources in the hotwell are shown in Table 12.2-37; they are negligible in the remainder of the condensate and feedwater systems. The hotwell is designed for a two minute holdup of condensate, and therefore N-16 radioactivity at the condenser outlet is negligible. Particulate fission products, activated corrosion products, and the particulate daughter products from the decay of fission product gases in transit through the turbine and condenser are the inlet radiation sources to the condensate system. These shielding design source terms, as shown in Table 12.2-38, are present in the condensate pumps and piping and accumulate on the condensate filter/ demineralizers. Table 12.2-39 provides the shielding design source terms for the condensate filter/demineralizer and the condensate backwash receiving tank.
The shielding design source terms for the feedwater system are listed in Table 12.2-40.
12.2.1.3.3 Gaseous Radwaste Recombination System Shielding design sources in the gaseous radwaste recombination system originate from noble gases and other noncondensable gases removed from the main condenser, and the radioactivity entering with the extraction driving steam to the SJAEs. The radioactivity entering is based on the primary steam radioactivity as described in Section 12.2.1.1.3, decayed for the expected transit time to the SJAEs. Eighty percent of the N-16 and 100% of the noble gases are assumed to be removed from the condenser by the SJAEs. The specific activities or quantities of radioactivity, including particulate daughters, in the SJAE condenser, mechanical vacuum pump, offgas pipe, preheater, recombiner, recombiner catalyst, aftercondenser, and H2 analyzers, to be used for shielding design calculations, are shown in Tables 12.2-41 through 12.2-48.
12.2.1.3.4 Turbine Enclosure HVAC System Components of the turbine enclosure HVAC system that contain sources of radioactivity are the equipment compartment exhaust air filters and the SGTS air filters. Tables 12.2-49 and 12.2-50 show the turbine enclosure equipment exhaust air filters and the SGTS air filters shielding design source terms.
12.2.1.4 Radwaste Enclosure 12.2.1.4.1 Liquid Waste Management System Liquid radwaste is collected and processed as discussed in Section 11.2. The liquid waste management system shielding design sources are radioisotopes, including fission and corrosion products, present in the reactor coolant. The components of this system contain varying amounts of radioactivity, depending on the system and equipment design.
LGS UFSAR CHAPTER 12 12.2-5 REV. 16, SEPTEMBER 2012 The concentrations of radioisotopes used for shielding design for pipes, tanks, filters, demineralizers, abandoned and unused evaporators (Section 11.2.2.1.3), and equipment and floor drain sumps may be derived from or are listed in Tables 12.2-51 through 12.2-69. Shielding for each component of the liquid waste management system is based on reactor coolant concentrations given in Tables 12.2-1 through 12.2-5.
12.2.1.4.2 Solid Radwaste System The solid radwaste system collects, monitors, processes, packages, and provides temporary storage facilities for radioactive spent bead and powdered resins and dry solid wastes for offsite shipment and permanent disposal. The system is described in Section 11.4.
The high integrity containers used for packaging resin wastes are washed free of external surface contaminants and stored in concrete shielded compartments before shipment. The aforementioned operations are accomplished using remote container loading, transfer, and an overhead crane. Shielding design source terms for the solid radwaste system components are based on reactor coolant concentrations given in Tables 12.2-1 through 12.2-5 and are presented in Tables 12.2-70 through 12.2-77, and 12.2-101 through 12.2-103.
12.2.1.4.3 Radwaste Enclosure HVAC System Components of the radwaste and offgas enclosures HVAC system that contain sources of radioactivity are the equipment compartment exhaust air filters. Table 12.2-78 shows the radwaste and offgas enclosure equipment exhaust air filters shielding design source terms.
12.2.1.5 Offgas Enclosure 12.2.1.5.1 Gaseous Radwaste Charcoal Treatment System The gaseous radwaste charcoal treatment system as described in Section 11.3 is located in the offgas enclosure and receives effluent from the gaseous radwaste recombination system for further decay before release.
The shielding design terms for the charcoal treatment system components are based on the expected transit times for noble gases and the formation and accumulation of noble gas daughter products. These gases pass through the charcoal treatment system and out the turbine enclosure stack. The shielding design source terms for the piping, filters, and charcoal treatment system equipment are presented in Tables 12.2-79 through 12.2-82.
12.2.1.5.2 Offgas Enclosure HVAC System See Section 12.2.1.4.3 for the offgas enclosure HVAC shielding design source terms.
12.2.1.6 Shielding Design Sources Resulting from Design Basis Accidents The shielding design for the control room is based on radiation sources resulting from DBAs.
Control room shielding design considers radiation sources from the primary containment, the reactor enclosure, the turbine enclosure and control structure, and the SGTS filters. The shielding design source terms for these areas are given in Tables 12.2-83 through 12.2-86.
LGS UFSAR CHAPTER 12 12.2-6 REV. 16, SEPTEMBER 2012 With regards to the Independent Spent Fuel Storage Installation, a postulated accidental sealing failure can potentially produce a gaseous effluent. This effluent is limited by the requirements of 10CFR72.106, which does not require consideration of simultaneous contributions to dose from the plant.
12.2.1.7 Stored Radioactivity The only sources of radioactivity not stored inside the plant structures are the refueling water storage tank, the CST, 10CFR20.2002 storage area, the radwaste storage pad and designated material laydown areas in the protected area.
During normal operation of the Independent Spent Fuel Storage Installation only direct radiation is emitted from loaded dry storage containers. The radiation dose is limited by the requirements of 10CFR72.104, which considers the direct dose from the storage containers in combination with the normal plant sources and effluents.
The CST contains low concentrations of radioisotopes. A dike is provided around the CST so that unrestricted access is limited to areas with a dose rate less than 2 mRem/hr. The CST source terms are shown in Table 12.2-87.
The refueling water storage tank also has low concentrations of radioisotopes when water is returned from the refueling pool. The refueling water storage tank is surrounded by a dike which limits unrestricted access to areas with a dose rate less than 0.2 mRem/hr. The refueling water storage tank source terms are shown in Table 12.2-88.
Provisions have been made to recycle the water from both the condensate and refueling water storage tanks through the condensate filter/demineralizers.
The 10CFR20.2002 storage area is an area north of the radwaste storage pad and northwest of the spray pond. The area is approximately 1.5 acres in size and approved for storage of slightly contaminated soils, sediment and sludges as approved by the 10CFR20.2002 application. Annual and maximum limits for the amount of material and radioactivity concentration are established by the 10CFR20.2002 application for the material stored there. The offsite dose at the nearest residence will not exceed 0.101 mrem/year from the radioactive waste material stored at the 10CFR20.2002 storage area.
The radwaste storage pad is located outside the protected area, but within the site restricted area, southwest of the spray pond and northwest of the Unit 1 cooling tower. The waste material on the pad consists of low level waste being stored on a temporary (interim) basis, awaiting offsite shipment, and contaminated reusable material. Storage pad boundary dose rates are set such that exposure of personnel in unrestricted areas is in accordance with 10CFR20.1301 requirements. The normal offsite dose to any member of the public will not exceed 1.0 mR/year from the radioactive waste material on the storage pad and 1.0 mR/year from storage of contaminated reusable material.
Designated area within the protected area are used for temporary storage of very low level contaminated material. This material consists of reusable materials to support plant operations and maintenance activities, and materials awaiting processing or offsite shipment for subsequent recycling, recovery, or free release to the extent achievable. The normal offsite dose from this category of material is included in the 1.0 mr/yr limit from storage of contaminated reusable material on the radwaste storage pad.
LGS UFSAR CHAPTER 12 12.2-7 REV. 16, SEPTEMBER 2012 No other radiation sources aside from the Independent Spent Fuel Storage Installation (ISFSI) are normally stored outside the plant structures. Spent fuel is stored in the spent fuel pool until it is placed in the spent fuel shipping cask for offsite transport or into the ISFSI Transfer Cask for placement at the ISFSI for interim storage. Space is provided in the radwaste enclosure for storage of spent filter cartridges and solidified spent resins. Radiation sources stored inside the plant structures are shielded to provide a dose rate of less than 2 mRem/hr for all areas outside plant structures.
12.2.1.8 Special Sources Special materials used in the radiochemistry laboratory and sealed sources used for calibration require special handling equipment and are shielded accordingly. Unsealed sources and radioactive samples are handled in conventional hoods that exhaust to the ventilation system.
Design features provided are discussed in Section 12.3.1.
The TIP system gamma detector and its drive cable become radiation sources following activation by neutrons in the reactor. The level of the radiation source depends upon the material compositions of the components, the irradiation history and decay time. The material composition of the gamma TIP is shown in Table 12.2-89. The radiation levels from the detector and cable are shown in Table 12.2-104 for a range of decay times after the TIP is retracted from the reactor vessel.
The reactor startup sources are shipped to the site in special shielded casks. The sources are transferred from the cask to the source holders. The source holders are then loaded underwater into the reactor. The sources are removed from the reactor and placed in the spent fuel pool or sent offsite.
12.2.2 Airborne Radioactive Material Sources 12.2.2.1 Sources of Airborne Radioactivity The sources of airborne radioactivity found in the various areas of the plant are mostly from process leakage of the systems carrying radioactive gases, steam, and liquids. Depending on the type of the system and its physical condition, such as system pressures and temperatures, leakage is in the form of a gas, steam, liquid, or a mixture of these.
12.2.2.2 Production of Airborne Radioactive Materials Radioactive materials become airborne through a number of mechanisms. The most common production mechanisms are spraying, splashing, flashing, evaporation, and diffusion.
12.2.2.3 Locations of Sources of Airborne Radioactivity Practically all the sources of airborne radioactivity are found in the reactor, turbine, and radwaste and offgas enclosures. Within these structures the radioactivity is released in equipment cubicles, valve and piping galleries, sampling stations, radwaste handling and shipping areas, cleaning and decontamination areas, and repair shops.
12.2.2.4 Control of Airborne Radioactivity
LGS UFSAR CHAPTER 12 12.2-8 REV. 16, SEPTEMBER 2012 Ventilation is an effective means of controlling airborne radioactive materials. Ventilation flow paths are such that air from low potential airborne areas flows into higher potential airborne areas.
This flow pattern ensures that radioactivity released in the above mentioned source locations, which usually have low personnel access requirements, has little chance to escape into areas with a high personnel occupancy such as corridors, working aisles, and operating floors. Levels of airborne radioactivity are periodically checked by surveys of the plant by the radiation protection staff.
12.2.2.5 Methodology for Estimating the Concentration of Airborne Radioactive Material Within the Plant To estimate the airborne radioactive material concentrations at locations within the plant, the following methodology was used:
a.
Estimate the total airborne releases (in curies per year) for each of the plant enclosures.
b.
Estimate a distribution for these releases among the various equipment areas of each enclosure based on operating data and engineering judgement.
c.
Determine the annual exhaust flow from each equipment area.
d.
Calculate the resultant airborne radionuclide concentration (Ci/cc) in each equipment area based on the release distribution (Ci/yr) and exhaust flow rate (cc/yr).
The following sections discuss each step in the above procedure in more detail.
12.2.2.6 Estimation of Total Airborne Releases Within the Plant The estimated quantities of airborne radioactive material produced in the plant enclosures are given in Table 12.2-93. These releases were based upon BWR-GALE (Reference 12.2-1), a computerized mathematical model for calculating the release of radiological materials in gaseous and liquid effluents. Assumptions applicable to the development of Table 12.2-93 from BWR-GALE are as follows:
a.
The reactor enclosure releases are taken to be the sum of the auxiliary enclosure and containment enclosure releases calculated by BWR-GALE.
b.
Turbine enclosure releases from BWR-GALE are assumed to include any airborne radioactive material produced in the control structure.
c.
The radwaste enclosure releases from BWR-GALE are "per reactor" and consequently are doubled for LGS. Offgas enclosure releases are assumed to be included in the radwaste enclosure releases.
d.
Tritium releases from BWR-GALE are divided equally between the reactor and turbine enclosures.
LGS UFSAR CHAPTER 12 12.2-9 REV. 16, SEPTEMBER 2012 e.
Since the BWR-GALE code for gaseous releases is based on actual operating plant data, releases for both normal operations and anticipated operational occurrences are assumed to have been included.
12.2.2.7 Distribution of Airborne Releases Within the Plant In the approach taken to determine the anticipated distribution of gaseous effluents, it is assumed that all airborne radioactive material originates only within the equipment areas of the plant. It is further assumed that a major percentage of the release is generated within a few specific areas of each enclosure, with the remainder coming from other equipment areas. Eighty percent of each enclosure's release is distributed as described below among the major contributing areas, and 20% is assigned to the "other equipment areas" category. Releases are assumed to be generated continuously throughout the year except for the drywell, where a 30 day release period is used.
The basis for the selection and relative contributions of the major areas is EPRI report NP-495 (Reference 12.2-2). This report provides data on the important sources of iodine-131 at operating BWRs and uses measured data to determine the relative release rate from each source. The relative release rates for all airborne radionuclides are, except for reactor enclosures tritium, assumed to be directly proportional to the iodine-131 release rates. Since the spent fuel pool and the reactor vessel (when it is open during refueling) are the major sources of airborne tritium in the reactor enclosure, tritium releases for that enclosure are assigned entirely to the refueling area.
Table 12.2-94 lists the major airborne contributors in each enclosure and the percentage of the total enclosure release assigned to each. Tables 12.2-95 through 12.2-97 provide the specific equipment areas of the plant associated with the major contributors and the applicable exhaust air flow rates. Note that only those equipment areas that have a significant potential for airborne radioactive material releases were included in the "other equipment areas" category.
12.2.2.8 Estimated Airborne Radioactive Material Concentrations Within the Plant The airborne radionuclide concentrations for each equipment area were calculated using the following methodology. For a specific area, the appropriate enclosure release (Table 12.2-93) was multiplied by the applicable release percentage for the area (Table 12.2-94) and divided by the area's annual exhaust flow (Table 12.2-95, 12.2-96, or 12.2-97). The resultant concentrations are presented in Tables 12.2-98 through 12.2-100, which also include the fractions of the maximum permissible concentrations in air as defined in 10CFR20 Appendix B, Table I (pre-1994).
12.2.2.9 Changes to Source Data Since PSAR Airborne radioactive material sources were not specified in the LGS PSAR. Section 12.2.2 has been added in compliance with the "Standard Format and Content of Safety Analysis Report for Nuclear Power Plants," Regulatory Guide 1.70.
12.
2.3 REFERENCES
LGS UFSAR CHAPTER 12 12.2-10 REV. 16, SEPTEMBER 2012 12.2-1 NUREG-0016 (Revision 0), "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents From Boiling Water Reactors," Office of Standards Development, NRC, Washington, D.C. (April 1976).
12.2-2 EPRI NP-495, "Sources of Radioiodine at Boiling Water Reactors," Project 274-1, Final Report, (February 1978).
LGS UFSAR CHAPTER 12 12.2-11 REV. 13, SEPTEMBER 2006 Table 12.2-1 NOBLE GAS SHIELDING DESIGN SOURCE TERMS(1)
STEAM REACTOR WATER SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE HALF-LIFE (Ci/g)
(Ci/g)
Kr-83m 1.86 hr 6.68x10-3 Kr-85m 4.4 hr 1.20x10-2 Kr-85 10.74 yr 3.93x10-5 Kr-87 76.0 min 3.93x10-2 Kr-88 2.79 hr 3.93x10-2 Kr-89 3.18 min 2.55x10-1 Kr-90 32.3 sec 5.50x10-1 Kr-91 8.6 sec 6.48x10-1 Kr-92 1.84 sec 6.48x10-1 Kr-93 1.29 sec 1.94x10-1 Kr-94 1.0 sec 4.52x10-2 Kr-95 0.5 sec 4.12x10-3 Xe-131m 11.96 day 2.95x10-5 Xe-133m 2.26 day 5.70x10-4 Xe-133 5.27 day 1.61x10-2 Xe-135m 15.7 min 5.11x10-2 Xe-135 9.16 hr 4.32x10-2 Xe-137 3.82 min 2.95x10-1 Xe-138 14.2 min 1.75x10-1 Xe-139 40.0 sec 5.50x10-1 Xe-140 13.6 sec 5.89x10-1 Xe-141 1.72 sec 4.71x10-1 Xe-142 1.22 sec 1.43x10-1 Xe-143 0.96 sec 2.36x10-2 Xe-144 9.0 sec 1.10x10-3
( 1 )
All fission product specific activities are based on an offgas release rate of 0.35 Ci/sec at 30 minutes decay.
LGS UFSAR CHAPTER 12 12.2-12 REV. 13, SEPTEMBER 2006 Table 12.2-2 HALOGEN SHIELDING DESIGN SOURCE TERMS(1)
STEAM REACTOR WATER SPECIFIC ACTIVITY(2)
SPECIFIC ACTIVITY ISOTOPE HALF-LIFE (Ci/g)
(Ci/g)
Br-83 2.40 hr 1.05x10-3 5.25x10-2 Br-84 31.8 min 1.89x10-3 9.45x10-2 Br-85 3.0 min 1.19x10-3 5.95x10-2 I-131 8.06 day 9.10x10-4 4.55x10-2 I-132 2.28 hr 8.40x10-3 4.20x10-1 I-133 20.8 hr 6.23x10-3 3.12x10-1 I-134 52.3 min 1.68x10-2 8.40x10-1 I-135 6.7 hr 9.10x10-3 4.55x10-1 (1)
All fission product specific activities are based on an offgas release rate of 0.35 Ci/sec at 30 minutes decay.
(2)
A 2.0% by weight carryover from reactor water to steam is assumed.
LGS UFSAR CHAPTER 12 12.2-13 REV. 13, SEPTEMBER 2006 Table 12.2-3 OTHER FISSION PRODUCT SHIELDING DESIGN SOURCE TERMS(1)
STEAM REACTOR WATER SPECIFIC ACTIVITY(2)
SPECIFIC ACTIVITY ISOTOPE HALF-LIFE (Ci/g)
(Ci/g)
Sr-89 50.8 day 1.09x10-5 1.09x10-2 Sr-90 28.9 yr 8.05x10-7 8.05x10-4 Sr-91 9.67 hr 2.42x10-4 2.42x10-1 Sr-92 2.69 hr 3.85x10-4 3.85x10-1 Zr-95 65.5 day 1.40x10-7 1.40x10-4 Zr-97 16.8 hr 1.12x10-7 1.12x10-4 Nb-95 35.1 day 1.47x10-7 1.47x10-4 Mo-99 66.6 hr 7.70x10-5 7.70x10-2 Tc-99m 6.00 hr 9.80x10-4 9.80x10-1 Tc-101 14.2 min 4.90x10-4 4.90x10-1 Ru-103 39.8 day 6.65x10-8 6.65x10-5 Ru-106 368 day 9.10x10-9 9.10x10-6 Te-129m 34.1 day 1.40x10-7 1.40x10-4 Te-132 78.0 hr 1.72x10-4 1.72x10-1 Cs-134 2.06 yr 5.60x10-7 5.60x10-4 Cs-136 13.0 day 3.85x10-7 3.85x10-4 CS-137 30.2 yr 8.40x10-7 8.40x10-4 Cs-138 32.3 min 6.65x10-4 6.65x10-1 Ba-139 83.2 min 5.60x10-4 5.60x10-1 Ba-140 12.8 day 3.15x10-5 3.15x10-2 Ba-141 18.3 min 5.95x10-4 5.95x10-1 Ba-142 10.7 min 5.95x10-4 5.95x10-1 Ce-141 32.53 day 1.37x10-7 1.37x10-4 Ce-143 33.0 hr 1.23x10-7 1.23x10-4 Ce-144 284.4 day 1.23x10-7 1.23x10-4 Pr-143 13.58 day 1.33x10-7 1.33x10-4 Nd-147 11.06 day 4.90x10-8 4.90x10-5 Np-239 2.35 day 8.40x10-4 8.40x10-1 (1)
All fission product specific activities are based on an offgas release rate of 0.35 Ci/sec at 30 minutes decay.
(2)
A 0.1% by weight carryover from reactor water to steam is assumed.
LGS UFSAR CHAPTER 12 12.2-14 REV. 16, SEPTEMBER 2012 Table 12.2-4 COOLANT ACTIVATION PRODUCT SHIELDING DESIGN SOURCE TERMS STEAM REACTOR WATER SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE HALF-LIFE (Ci/g)
(Ci/g)
N-13 9.99 min 7.00x10-3 4.00x10-2 N-16*
7.13 sec 2.50x10+2 4.80x10+1 N-17 4.14 sec 2.00x10-2 6.00x10-3 O-19 26.8 sec 8.00x10-1 7.00x10-1 F-18 109.8 min 4.00x10-3 4.00x10-3
- With Hydrogen Water Chemistry.
(1)
Refer to LGS UFSAR Section 10.4.11 for the details of Hydrogen Water Chemistry System.
LGS UFSAR CHAPTER 12 12.2-15 REV. 13, SEPTEMBER 2006 Table 12.2-5 NONCOOLANT ACTIVATION PRODUCT SHIELDING DESIGN SOURCE TERMS STEAM REACTOR WATER SPECIFIC ACTIVITY(1)
SPECIFIC ACTIVITY ISOTOPE HALF-LIFE (Ci/g)
(Ci/g)
Na-24 15.0 hr 2.00x10-6 2.00x10-3 P-32 14.31 day 2.00x10-8 2.00x10-5 Cr-51 27.8 day 5.00x10-7 5.00x10-4 Mn-54 313.0 day 4.00x10-8 4.00x10-5 Mn-56 2.58 hr 5.00x10-5 5.00x10-2 Co-58 71.4 day 5.00x10-6 5.00x10-3 Co-60 5.25 yr 5.00x10-7 5.00x10-4 Fe-59 45.0 day 8.00x10-8 8.00x10-5 Ni-65 2.55 hr 3.00x10-7 3.00x10-4 Zn-65 243.7 day 2.00x10-9 2.00x10-6 Zn-69m 13.7 hr 3.00x10-8 3.00x10-5 Ag-110m 253.0 day 6.00x10-8 6.00x10-5 W-187 23.9 hr 3.00x10-6 3.00x10-3 (1)
A 0.1% by weight carryover from reactor water to steam is assumed.
LGS UFSAR CHAPTER 12 12.2-16 REV. 13, SEPTEMBER 2006 Table 12.2-6 BASIC REACTOR DATA(1)
PARAMETERVALUE USED IN MODEL Reactor rated thermal power 3527 megawatts Overall average core power density 53.8 watts/cc Core power peaking factors:
At core center Pmax (axial) 1.5 PaveZ Pmax (radial) 1.4 PaveR At core boundary Pmax (axial) 0.5 PaveZ Pmax (radial) 0.7 PaveR Core volume fractions:
Density Volume Material gm/cc Fraction UO2 10.4 0.254 Zr 6.4 0.140 H2O 1.0 0.274 Void 0
0.332 Average water density between core and vessel and below the core 0.74 g/cc Average water-steam density above core:
In the plenum region 0.23 g/cc Above the plenum (homogenized) 0.6 g/cc Average steam density 0.036 g/cc (1)
This table represents the physical data required to form the reactor vessel model, which includes volume fractions, reactor power, and power distribution.
LGS UFSAR CHAPTER 12 12.2-17 REV. 13, SEPTEMBER 2006 Table 12.2-7 CORE REGION DESCRIPTION TO DETERMINE RADIAL FLUX DISTRIBUTION AT REACTOR CORE MIDPLANE REGION CUMULATIVE THICKNESS THICKNESS REGION DESCRIPTION (cm)
(cm)
MATERIAL Active fuel zone 237.60 237.60 Core Water 20.37 257.97 Water Core shroud 5.08 263.05 Stainless steel Water 58.26 321.31 Water Pressure vessel liner 0.476 321.786 Stainless steel Pressure vessel 16.354 338.14 Carbon steel Air 51.76 389.89 Air Steel liner (primary 1.27 391.16 Carbon shield) steel Concrete (primary 48.26 439.42 Magnetite/
shield)(1) ilmenite Steel liner (primary 3.81 443.23 Carbon shield) steel Air gap 418.78 862.01 Air Primary containment 195.58 1057.59 Ordinary concrete (1)
Ilmenite/magnetite aggregate mixture
LGS UFSAR CHAPTER 12 12.2-18 REV. 13, SEPTEMBER 2006 Table 12.2-8 MATERIAL COMPOSITION TO DETERMINE RADIAL FLUX DISTRIBUTIONS AT REACTOR CORE MIDPLANE ELEMENT MATERIAL (1024 atoms/cc)
STAINLESS CARBON ORDINARY CORE WATER STEEL-304 STEEL CONCRETE(1)
AIR CONCRETE H
1.83x10-2 4.89x10-2 3.66x10-3 7.84x10-3 O
2.26x10-2 2.44x10-2 4.51x10-2 1.12x10-5 4.41x10-3 Mo 5.93x10-4 U-235 1.24x10-4 U-238 5.46x10-3 Mg 9.69x10-4 1.43x10-4 A
1.32x10-3 2.39x10-3 Si 1.69x10-3 4.19x10-4 5.49x10-3 1.57x10-2 Ca 4.00x10-3 2.91x10-3 Ti 2.17x10-3 Mn 1.73x10-3 8.59x10-4 4.86x10-4 Fe 5.76x10-2 8.40x10-2 1.16x10-2 3.09x10-4 C
3.18x10-4 1.00x10-3 Cr 1.73x10-2 Ni 8.06x10-3 N
4.17x10-5 Na 1.05x10-3 K
6.91x10-4 S
5.30x10-5 (1) Magnetite/ilmenite mixture
LGS UFSAR CHAPTER 12 12.2-19 REV. 13, SEPTEMBER 2006 Table 12.2-9 CALCULATED GAMMA RAY AND NEUTRON FLUXES AT OUTSIDE SURFACE OF RPV Outside Vessel At Core Midplane(1)
GAMMA ENERGY GAMMA FLUX NEUTRON ENERGY NEUTRON FLUX (upper Mev)
(/cm2-sec)
(upper ev)
(/cm2-sec) 10.0 3.81e+07 1.50e+07 3.22e+05 8.0 1.16e+08 1.22e+07 1.10e+05 6.5 1.14e+08 1.00e+07 2.44+06 5.0 1.40e+08 8.18e+06 4.47+06 4.0 2.55e+08 6.36e+06 6.16e+05 3.0 1.90w+08 4.96e+06 4.43e+06 2.5 2.90e+08 4.06e+06 7.34e+06 2.0 2.50e+08 3.01e+06 8.45e+06 1.66 3.09e+08 2.46e+06 2.72e+06 1.33 4.03e+08 2.35e+06 1.67e+07 1.0 3.18e+08 1.83e+06 5.67e+07 0.8 3.87e+08 1.11e+06 1.62e+08 0.6 1.01e+09 5.50e+05 4.32e+08 0.4 6.26e+08 1.10e+05 3.06e+08 0.3 1.29e+09 3.35e+03 7.50e+07 0.2 1.73e+09 5.83e+02 6.42e+07 0.1 9.61e+07 1.01e+02 4.40e+07 0.05 1.77e+05 2.90e+01 2.88e+07 1.07e+01 3.19e+07 3.06e+00 2.01e+07 1.12e+00 1.56e+07 4.14e-01 1.61e+07 (1)
At 100% power. For geometry, See Table 12.2-7.
LGS UFSAR CHAPTER 12 12.2-20 REV. 13, SEPTEMBER 2006 Table 12.2-10 CALCULATED GAMMA RAY AND NEUTRON FLUXES AT OUTSIDE SURFACE OF PRIMARY SHIELD Outside Surface of Primary Shield at Core Midplane (1)
GAMMA ENERGY GAMMA FLUX NEUTRON ENERGY NEUTRON FLUX (upper Mev)
(/cm2 sec)
(upper ev)
(/cm2 sec) 10.0 1.23e+05 1.50e+07 8.32e+02 8.0 4.99e+05 1.22e+07 2.66e+03 6.5 4.88e+05 1.00e+07 5.59e+03 5.0 4.81e+05 8.18e+06 9.76e+03 4.0 7.02e+05 6.36e+06 1.28e+04 3.0 4.50e+05 4.96e+06 8.53e+03 2.5 5.61e+05 4.06e+06 1.06e+04 2.0 4.61e+05 3.01e+06 1.61e+04 1.66 5.36e+05 2.46e+06 7.88e+03 1.33 6.72e+05 2.35e+06 2.53e+04 1.0 5.06e+05 1.11e+06 5.63e+04 0.8 6.28e+05 5.50e+05 8.55e+04 0.6 1.28e+06 5.50e+05 1.18e+05 0.4 6.26e+05 1.10e+05 7.89e+04 0.3 7.22e+05 3.35e+02 2.53e+04 0.2 4.85e+05 5.83e+02 2.43e+04 0.1 1.33e+04 1.01e+02 2.17e+04 0.05 2.87e+01 2.90e+01 1.25e+04 1.07e+01 1.83e+04 3.06e+00 1.34e+04 1.12e+00 1.10e+04 4.14e-01 1.27e+04 (1)
At 100% power. For geometry, See Table 12.2-7.
LGS UFSAR CHAPTER 12 12.2-21 REV. 13, SEPTEMBER 2006 Table 12.2-11 TURBINE ENCLOSURE AND CONTROL STRUCTURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE(1)
THICKNESS ELEVATION DOMINANT SOURCE DENSITY IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 119 183 - 0 Offgas holdup piping 26" EBC-106 26" pipe x 0.00173 0.578 12.2-43 187 - 0 70' long 191 - 0 121 Offgas holdup piping 26" EBC-106 26" pipe x 0.00173 0.578 12.2-43 70' long 154 180 - 0 Offgas 10E127 33" vessel x 0.774 0.625 12.2-47 aftercondenser 9'-8" long Offgas 10S125 60" vessel x 0.154 1.1875 12.2-45 Recombiner 8'-6" high Offgas preheater 10E131 25" vessel x 0.575 0.500 12.2-44 9'-6" long 161 180 - 0 Condensate backwash 1BP159 6" pipe x 1.0 0.280 receiving tank 10' long 12.2-39 discharge pump 162 180 - 0 Condensate backwash 1AP159 6" pipe x 1.0 0.280 receiving tank 10' long 12.2-39 discharge pump 163 180 - 0 Condensate backwash 10T130 7.4' tank x 1.0 0.3125 receiving tank 28' long 12.2-39 165 180 - 0 Condensate backwash 1BP129, 1AP129, 2" pipe x 1.0 0.218 receiving tank area 1BP128, 1AP128 10' long 12.2-69 equipment and floor drain sumps 249 200 - 0 Offgas piping 4" HBC-262 4" pipe x 0.00173 0.237 208 - 0 100' long 12.2-43
LGS UFSAR CHAPTER 12 12.2-22 REV. 13, SEPTEMBER 2006 Table 12.2-11 (Contd)
EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE(1)
THICKNESS ELEVATION DOMINANT SOURCE DENSITY IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 253 200 - 0 RFPT exhaust ducting 61" duct x 0.000132 0.75 (plus sources in room 6' long 12.2-36
- 254) 254 200 - 0 Main condenser hotwells 1AE108, 1BE108, 40' well x 1.0 0.75 12.2-37 1CE108 4' long 255 200 - 0 Drain coolers 1AE107, 1BE107, 58" vessel x 1.427 0.50 12.2-34 (plus sources in 1CE107 25.25' long room #254) 256 189 - 0 Condensate pumps 1AP102, 1BP102, 36" pipe x 1.0 0.375 12.2-38 1CP102 44' long 259 200 - 0 Recombiner catalyst 10S125 4'-8" 0.529 0.0 element element x 2' -
12.2-46 10" high 264A-I 200 - 0 Condensate filter/
10" HBD-168 10" pipe x 1.0 0.365 12.2-39 demineralizer 100' long backwash piping 332 217 - 0 Moisture separators 1A1T104, 1B1T104, 12.5' vessel x 0.376 0.394 12.2-33 1C1T104, 1A2T104, 24' high 1B2T104, 1C2T104 333 217 - 0 Steam jet air ejector 1BE109 37.5" vessel x 0.718 0.375 12.2-41 20' long 334 217 - 0 Steam jet air ejector 1AE109 37.5" vessel x 0.718 0.375 12.2-41 20' long 337 217 - 0 Mechanical vacuum pump 10P105 10' pipe x 0.000216 0.365 12.2-42 20' long
LGS UFSAR CHAPTER 12 12.2-23 REV. 13, SEPTEMBER 2006 Table 12.2-11 (Contd)
EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE(1)
THICKNESS ELEVATION DOMINANT SOURCE DENSITY IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 339A-H 217 - 0 Condensate filter/
1AF106 through 72" vessel x 1.0 1.50 12.2-39 demineralizer 1HF106 70' high 340A-C 217 - 0 Reactor feed pump 1AS105, 1BS105, 10"pipe x 0.005803 0.365 12.2-36 turbines 1CS105 14' long 342 217 - 0 Condensate pumps 1AP102, 1BP102, 30" pipe x 1.0 0.63 12.2-38 1CP102 20' long 362A-D 200 - 0 H2 analyzers 3/8" BWG tubing 3/8" tube x 0.00173 0.375 12.2-48 20' long 438 239 - 0 Main steam piping 26" EBB-101 26" pipe x 0.036 0.928 12.2-1 through 200' long 12.2-5 439 239 - 0 Feedwater heaters 13CE103 74" vessel x 0.728 0.563 12.2-34 47.2' long 14CE104 69" vessel x 0.785 0.625 39.6' long 15CE105 68" vessel x 0.689 0.563 35.5' long 440 239 - 0 Feedwater heaters 13BE103 74" vessel x 0.728 0.563 12.2-34 47.2' long 14BE104 69" vessel x 0.785 0.625 39.6' long 15BE105 68" vessel x 0.689 0.563 35.5' long
LGS UFSAR CHAPTER 12 12.2-24 REV. 13, SEPTEMBER 2006 Table 12.2-11 (Contd)
EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE(1)
THICKNESS ELEVATION DOMINANT SOURCE DENSITY IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 441 239 - 0 Feedwater heaters 13AE103 74" `vessel x 0.728 0.563 12.2-34 47.2' long 14AE104 69" vessel x 0.785 0.625 39.6' long 15AE105 68" vessel x 0.689 0.563 35.5' long 544 269 - 0 Turbine deck piping 28" HP 28" vessel x 0.036 1.4 12.2-32 turbine inlet 15' long 42" HP 42" vessel x 0.00709 0.625 12.2-32 turbine exhaust 15' long 42" cross-42" vessel x 0.00610 0.625 12.2-32 around piping 15' long 545 69 - 0 Feedwater heater 16CE106 69" vessel x 1.144 1.125 12.2-34 34' long 546 269 - 0 Feedwater heater 16BE106 69" vessel x 1.144 1.125 12.2-34 34' long 547 269 - 0 Feedwater heater 16AE106 69" vessel x 1.114 1.125 12.2-34 34' long 551 269 - 0 Steam seal 10E128 80" vessel x 0.540 0.620 12.2-35 32' long 621 304 - 0 Turbine enclosure 1AF157, 1AF194, 15.306' filter x 0.00129 0.0 12.2-49 equipment compartment 1BF157, 1BF194, 11.5" thick exhaust air filters 1AF178, 1AF179, 1BF178, 1BF179
LGS UFSAR CHAPTER 12 12.2-25 REV. 13, SEPTEMBER 2006 Table 12.2-11 (Contd)
EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE(1)
THICKNESS ELEVATION DOMINANT SOURCE DENSITY IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 624 332 - 0 SGTS air filters 0AF170, 0BF170, 10.852' filter x 0.00129 0.0 12.2-50 0AF183, 0BF183, 11.5" thick 0AF169, 0BF169 252A 200-0 Spent resin tanks 1AT928, 1DT928 8'-0 vessel 1.0
.1875 12.2-101 7'-2" resin height 252B 200-0 Spent resin piping Various 3" x vessel 1.0
.12 12.2-101 lengths 252C 200-0 Resin Measuring tank 1OT930 4'-6" vessel 1.0
.250 12.2-101 8'-0" resin height 341 A to H 217-0 Deep bed vessels 1AT927, 1HT927 11'-0 bed 1.0 1.375 12.2-101 4"0" height 270A 200-0 Spent resin tanks 2AT928, 2DT928 8'-0 vessel 1.0
.1875 12.2-101 7'-2" resin height 270B 200-0 Spent resin piping Various 3" x vessel 1.0
.12 12.2-101 lengths 270C 200-0 Resin Measuring tank 2OT930 4'-6" vessel 1.0
.250 12.2-101 8'-0" resin height 354 A to H 217-0 Deep bed vessels 2AT927, 2HT927 11'-0 bed 1.0 1.375 12.2-101 4'-0" height (1)
"Effective source Density" is density of radiation source or combination of sources used in shielding design analyses.
LGS UFSAR CHAPTER 12 12.2-26 REV. 13, SEPTEMBER 2006 Table 12.2-12 REACTOR ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE THICKNESS ELEVATION DOMINANT SOURCE DENSITY(1)
IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 102 177 - 0 RHR heat exchanger, 1AE205 53.75" vessel 1.406 0.8125 12.2-24 pumps, and piping x 25.1' high 103 177 - 0 RHR heat exchanger, 1BE205 53.75" vessel 1.406 0.8125 12.2-24 pumps, and piping x 25.1' high 108 177 - 0 RCIC pump turbine 10S212 6" pipe x 0.0396 0.432 12.2-25 20' long 109 177 - 0 HPCI pump turbine 10S211 12" pipe x 0.0414 0.687 12.2-26 30' long 110 177 - 0 Core spray pump 1AP206 16" pipe x 1.0 0.375 12.2-87 20' long 113 177 - 0 Core spray pump 1CP206 16" pipe x 1.0 0.375 12.2-87 20' long 114 177 - 0 Core spray pump 1DP206 16" pipe x 1.0 0.375 12.2-87 20' long 114A 177 - 0 Pipe-way - RWCU backwash 2" HBC-113 2" pipe x 1.0 0.218 12.2-22 receiving tank to phase 20' long separator 115 177 - 0 Reactor enclosure
- 1BP225, 6" pipe x 1.0 0.280 12.2-69 equipment and floor
- 1AP225, 20' long drain sumps
- 1AP226, 1BP226 117 177 - 0 Core spray pump 1BP206 16" pipe x 1.0 0.375 12.2-87 20' long 203 201 - 0 RHR heat exchanger 1AE205 53.75" 1.406 0.375 12.2-24 vessel x 25.1' high 204 201 - 0 RHR heat exchanger 1BE205 53.75" vessel 1.406 0.8125 12.2-24 x 25.1' high
LGS UFSAR CHAPTER 12 12.2-27 REV. 13, SEPTEMBER 2006 Table 12.2-12 (Contd)
REACTOR ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE THICKNESS ELEVATION DOMINANT SOURCE DENSITY(1)
IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 209 201 - 0 Drywell equipment 4" HBD-162, 4" pipe x 1.0 0.237 12.2-15 and floor drain piping 4" HBC-115 15' long 296 201 - 0 Piping - RWCU backwash 2" HBC-113 2" pipe x 1.0 0.218 12.2-22 receiving tank to phase 15' long separator 297 201 - 0 HPCI turbine inlet 12" EBB-108 12" pipe x 0.0414 0.687 12.2-26 piping 30' long 298 201 - 0 RCIC turbine inlet 6" EBB-109 6" pipe x 0.0396 0.432 12.2-25 piping 15' long 306 241 - 3 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.076 12.2-2 through penetrations piping 3' long 12.2-5 307 241 - 3 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.076 12.2-2 through penetrations piping 3' long 12.2-5 309 217 - 0 HPCI turbine inlet piping 12" EBB-108 12" pipe x 0.0414 0.687 12.2-26 20' long 310 217 - 0 Spent fuel shipping cask Spent fuel, 0.5 7' cask x 1.00 Sufficient years decay 20' high for 10 mR/hr at 3 ft 401 253 - 0 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.07 12.2-2 through penetrations piping 40' long 12.2-5 403 253 - 0 Contaminated CRD mechanisms CRD filter 4" tube x 5.305 0.0 12.2-31 18" long 404 253 - 0 Decontaminated CRD CRD element 4" tube x 5.305 0.0 12.2-31 mechanisms 14'-1" long 405 253 - 0 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.076 12.2-2 through penetrations piping 40' long 12.2-5
LGS UFSAR CHAPTER 12 12.2-28 REV. 13, SEPTEMBER 2006 Table 12.2-12 (Contd)
REACTOR ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE THICKNESS ELEVATION DOMINANT SOURCE DENSITY(1)
IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 406 253 - 0 TIP and cable Activated TIP 0.213" cable 7.86 0.0475 12.2-90 through cable x 12' long 12.2-92 407 263 - 0 Main steam piping 26" EBB-101 26" pipe x 0.036 0.928 12.2-1 through 26' long 12.2-5 409 253 - 0 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.076 12.2-2 through penetrations piping 15' long 12.2-5 501 283 - 0 Streaming through drywell Reactor recirc 28" pipe x 0.73 1.076 12.2-2 through penetrations piping 2' long 12.2-5 502 283 - 0 RWCU backwash receiving 10T217 8' tank x 1.0 0.1875 12.2-22 tank 2.925' high 503 283 - 0 RWCU regenerative heat 10E207 16.25" vessel 2.104, 0.875 12.2-17, exchangers x 19.92' long 2.143, 12.2-18, 2.188 12.2-19 (3HX's) 504 283 - 0 RWCU nonregenerative 1BE208 17.25" vessel 1.777, 0.375 12.2-20, heat exchangers x 23' long 1.785 12.2-21 (2HX's) 505 283 - 0 RWCU nonregenerative 1AE208 17.25" vessel 1.777, 0.375 12.2-20, heat exchangers x 23' long 1.785 12.2-21 (2HX's) 507 283 - 0 RWCU recirculation pump 1AP221 4" pipe x 0.73 0.337 12.2-16 7.5' long 508 283 - 0 RWCU recirculation pump 1BP221 3" pipe x 0.73 0.300 12.2-16 7.5' long 509 283 - 0 RWCU recirculation pump 1CP221 3" pipe x 0.73 0.300 12.2-16 7.5' long
LGS UFSAR CHAPTER 12 12.2-29 REV. 13, SEPTEMBER 2006 Table 12.2-12 (Contd)
REACTOR ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE THICKNESS ELEVATION DOMINANT SOURCE DENSITY(1)
IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 510 283 - 0 Piping - RWCU backwash 2" HBC-113 2" pipe x 1.0 0.218 12.2-22 receiving tank to phase 20' long separator 511 283 - 0 Fuel pool cooling water
- 1AE202, 25.25" vessel x 1.55 0.375 12.2-29 heat exchangers
- 1BE202, 23' long 1CE202 518 279 - 0 Main steam piping 26" EBB-101 26" pipe x 0.036 0.928 12.2-1 through 35' long 12.2-5 522 296 - 0, Piping - RWCU backwash 2" HBC-113 2" pipe x 1.0 0.218 12.2-22 300 - 3 receiving tank to phase 20' long separator 523 295 - 3 Streaming through drywell 6" EBB-101 26" pipe x 0.036 0.928 12.2-1 through penetrations 2' long 12.2-5 599 283 - 0, Streaming through drywell 26" EBB-101 26" pipe x 0.036 0.928 12.2-1 through 287 - 0, penetrations 2' long 12.2-5 295 - 0 600A,B 313 - 0 RWCU filter/demineralizer 1AP223, 1BP223, 4" pipe x 1.0 0.237 12.2-22 holding pumps and 4" ECC-102 20' long 12.2-23 back wash piping 604 312 - 0 Spent fuel Spent fuel, 5.476 in² 2.236 0.0 12.2-14 2 days decay assy. x 150 inches
- long, 1224 assemblies 609A,B 313 - 0 RWCU filter/demineralizer
- 1AF203, 33" tank x 0.957 1.50 12.2-22 1BF203 5' high
LGS UFSAR CHAPTER 12 12.2-30 REV. 13, SEPTEMBER 2006 Table 12.2-12 (Contd)
REACTOR ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-SHIELDING EFFECTIVE (STEEL SOURCE THICKNESS ELEVATION DOMINANT SOURCE DENSITY(1)
IN UFSAR ROOM NO.
(Ft - In)
RADIATION SOURCE IDENTIFICATION SOURCE GEOMETRY (g/cc)
INCHES)
SOURCE TABLE 616 331 - 0 Reactor enclosure
- 1AF254, 15.918' filter 0.001293 0.0 12.2-30 equipment compartment
- 1AF258, x 11.5" thick exhaust air filters
- 1AF257, 1AF255 617 331 - 0 Reactor enclosure
- 1BF254, 15.918' filter 0.001293 0.0 12.2-30 equipment compartment
- 1BF258, x 11.5" thick exhaust air filters
- 1BF257, 1BF255 634 308 - 6 Spent fuel assembly Spent fuel, 5.476 in² 4.534 0.0 12.2-14 0.5 years decay assy. x 150" long (1)
"Effective source Density" is density of radiation source or combination of sources used in shielding design analysis.
LGS UFSAR CHAPTER 12 12.2-31 REV. 13, SEPTEMBER 2006 Table 12.2-13 RADWASTE AND OFFGAS ENCLOSURE SHIELDING DESIGN RADIATION SOURCE DESCRIPTION EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 123 162 - 0 Waste sludge tank 00T31 10.44' tank 1.0 0.5 12.2-76 x 21' long RWCU filter/demineralizer 2" HBC-113 2" pipe 1.0 0.216 12.2-22 backwash piping x 30' long 124 162 - 0 Waste sludge mixing 00P322 3" pipe x 1.0 0.216 12.2-76 pump 22' long 125 162 - 0 Condensate phase 1AT316, 1BT316 15' tank x 1.22 0.437 12.2-70 separators (Unit 1) 1.21' high
(+2 feet water to roof) 126 162 - 0 Condensate phase 10P332 6" pipe x 1.0 0.280 12.2-72 separator decant 15' long pump (Unit 1)
Equipment drain 6" HBC-36 6" pipe 1.0 0.280 12.2-54 filter backwash piping x 12' long 127 162 - 0 Condensate phase 10P331 4" pipe x 1.0 0.237 12.2-71 separator decant 15' long pump (Unit 1) 128 162 - 0 Condensate phase 2AT316, 2BT316 15' tank x 1.22 0.4375 12.2-70 separator (Unit 2) 1.21' high
(+2 feet water to roof) 129 162 - 0 Condensate phase 20P331 4" pipe x 1.0 0.237 12.2-71 separator sludge pump (Unit 2) 15' long
LGS UFSAR CHAPTER 12 12.2-32 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 130 162 - 0 Condensate phase 20P332 6" pipe x 1.0 0.280 12.2-72 separator decant 15' long pump (Unit 2) 131 162 - 0 Equipment drain 00T302 20' tank x 1.0 0.4375 12.2-51 collection tank 8.5' high Fuel pool filter/
6" HBC-7 6" pipe 1.0 0.280 12.2-28 demineralizer backwash x 30' long piping 132 162 - 0 Equipment drain 00P301 4" pipe x 1.0 0.237 12.2-51 collection tank pump 20' long Fuel pool filter/
6" HBC-7 6" pipe x 1.0 0.280 12.2-28 Demineralizer 11' long backwash piping 133 162 - 0 Floor drain collection 00P309, 00P313, 4" pipe x 1.0 0.237 12.2-57, tank pump and sample 00P314 20' long 12.2-59, tank pumps 12.2-60 Equipment drain filter 6" HBC-36 6" pipe 1.0 0.280 12.2-54 backwash piping x 56' long 134 162 - 0 Floor drain collection 00T306, 00T307, 15' tank x 1.0 0.4375 2.2-57, nk and sample tanks 0T308 2.7' high 2-59, 12.2-60 Floor drain filter 6" HBC-37 6" pipe 1.0 0.280 12.2-61 backwash piping x 10' long 136 162 - 0 Chemical waste tank 00T314 10' tank x 1.0 0.1875 12.2-64 10.21' high RWCU filter/demineralizer 2" HBC-10 2" pipe 1.0 0.216 12.2-22 backwash piping x 25' long
LGS UFSAR CHAPTER 12 12.2-33 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 137 162 - 0 Chemical waste tank 00P321 3" pipe x 1.0 0.120 12.2-64 pump 20' long RWCU filter/demineralizer 2" HBC-10 2" pipe 1.0 0.216 12.2-22 backwash piping x 5' long 138 162 - 0 Floor drain spent 00P323 3" pipe x 1.0 0.216 12.2-63 resin pump 10' long Equipment drain filter 6" HBC-36 6" pipe 1.0 0.280 12.2-54 backwash piping x 20' long 139 162 - 0 Equipment drain spent 00P317 3" pipe x 1.0 0.216 12.2-56 resin pump 10' long Equipment drain filter 6" HBC-36 6" pipe 1.0 0.280 12.2-54 backwash piping x 13' long 140 162 - 0 Equipment and floor 00T323, 00T324 6' tank x 1.0 0.1875 12.2-55, drain spent resin tanks 3.274' high 12.2-62 141 162 - 0 RWCU phase separator 0BT318 11.5' tank x 1.22 0.1875 12.2-73 4.3' high
(+2 feet water to roof) 142 162 - 0 RWCU phase separator 00P336 1.5" pipe x 1.0 0.200 12.2-75 decant pump 6' long RWCU filter/demineralizer 2" HBC-10 2" pipe 1.0 0.216 12.2-22 backwash piping x 13' long 143 162 - 0 RWCU phase separator 0AT318 11.5' tank x 1.22 0.1875 12.2-73 4.3' high
(+2 feet water to roof)
LGS UFSAR CHAPTER 12 12.2-34 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 144 162 - 0 RWCU phase separator 00P334 3" pipe x 1.0 0.216 12.2-74 sludge pump 15' long 146 162 - 0 Equipment and floor 0AP337, 0BP337, 2" pipe x 1.0 0.218 12.2-69 drain sumps and pumps 0AP338, 0BP338 10' long 147 162 - 0 Equipment drain sample 0AP305, 0BP305 4" pipe x 1.0 0.120 12.2-53 tanks pumps 20' long 148 162 - 0 Equipment drain sample 0AT303, 0BT303 16' tank x 1.0 0.1875 12.2-53 tanks 13.3' high 216 181 - 2 Charcoal filter 1AS371 10.76' vessel x 0.545 1.44 12.2-81 28' high 217 195 - 0 Charcoal filter 1CS371, 1DS371, 9.75' vessel x 0.545 0.865 12.2-81 1ES371, 1FS371 14.5' high 218 195 - 0 Charcoal filter 1GS371 See Room 217 0.545 0.865 12.2-81 219 195 - 0 Charcoal filter 1BS371 See Room 216 0.545 1.44 12.2-81 220 195 - 0 Charcoal filter 2BS371, 2DS371, See Room 217 0.545 0.865 12.2-81 2FS371, 2HS371 221A 195 - 0 Guard bed 10S370 2.92' vessel x 0.545 0.5 12.2-80 2.92' high 221B 195 - 0 Guard bed 20S370 See Room 221A 0.545 0.5 12.2-80 222 195 - 0 Charcoal filter 2AS371 See Room 216 0.545 1.44 12.2-81 223 191 - 0 Charcoal filter 2CS371, 2ES371, See Room 217 0.545 0.865 12.2-81 2GS371, 2IS371 224A 191 - 0 Outlet HEPA filter 10F371 1.08' cylinder 0.0013 0.432 12.2-82 x 4.5' high
LGS UFSAR CHAPTER 12 12.2-35 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 224B 195 - 0 Outlet HEPA filter 20F371 See Room 224A 0.0013 0.432 12.2-79 226A 195 - 0 Cooler condenser 10E377 8" pipe x 1.0 0.322 12.2-79 (drain pot) 0.672' high 226B 195 - 0 Cooler condenser 20E377 See Room 226A 1.0 0.322 12.2-79 (drain pot) 227 191 - 0 RWCU backwash 2"
2" pipe x 1.0 0.218 12.2-22 piping HBC-213 10' long 228 191 - 0 Laundry drain tanks, 0AT311, 0BT311, 7' tank x 1.0 0.4375 12.2-67, pumps, and filter 00F313, 00T312, 6.25' high 12.2-68 0AP318, 0BP318, 0AP319, 0BP319 230 191 - 0 Evaporator feed tank 00T320, 00T321 11' tank x 1.0 0.1875 12.2-64, and evaporator distillate 8.44' high 12.2-66 sample tank (abandoned) 231(2) 191 - 0 Evaporator feed tank pumps OAP326, OBP326 1.5" pipe x 1.0 0.145 12.2-64 (abandoned) 20' long 232(2) 191 - 0 Evaporator distillate pump 00P327 2" pipe x 1.0 0.1875 12.2-66 (abandoned 20' high 233(2) 191 - 0 Radwaste evaporator 00T322 10' tank x 1.0 0.1875 12.2-77 concentrate storage tank 6.81' high (abandoned)
RWCU phase separator 1.5" HBC-14 1.5" pipe 1.0 0.200 12.2-74 discharge piping x 27' long 234(2) 191 - 0 Concentrate storage tank 00P328 1" pipe x 1.0 0.133 12.2-77 discharge and mixing pump 15' long (abandoned) 235A 191-0 RWCU phase separator 1.5" HBC-14 1.5" pipe 1.0 0.200 12.2-74 discharge piping 19' long
LGS UFSAR CHAPTER 12 12.2-36 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 236 191 - 0 Fuel pool filter/
00P340, 10P340, 6" pipe x 1.0 0.280 12.2-28 demineralizer holder
- 20P340, 10' long pumps and backwash piping 6" 0 HBC-103 237 191 - 0 Floor drain filter
- 00P312, 6" pipe x 1.0 0.280 12.2-61 holding pump and 6" 0 HBC-28 15' long backwash piping 238 191 - 0 Equipment drain
- 00P304, 6" pipe x 1.0 0.280 12.2-54 filter holding pump 6" 0 HBC-25 15' long and backwash piping 239A 191 - 0 Fuel pool filter/
10F311 3' tank x 1.0 0.4375 12.2-28 demineralizer 5' high 239B 191 - 0 Fuel pool filter/
00F311 3' tank x 1.0 0.4375 12.2-28 demineralizer 5' high 239C 191 - 0 Fuel pool filter/
20F311 3' tank x 1.0 0.4375 12.2-28 demineralizer 5' high 240A 191 - 0 Floor drain filter 00F307 3' tank x 1.0 0.4375 12.2-61 5' high 240B 191 - 0 Floor drain 00F306 6' tank x 1.0 1.5 12.2-62 demineralizer 3.274' high (3/4" for roof) 241A 191 - 0 Equipment drain 00F301 6' tank x 1.0 1.5 12.2-55 demineralizer 3.275' high (3/4" for roof) 241B 191 - 0 Equipment drain filter 00F302 3' tank x 1.0 0.4375 12.2-54 5' high
LGS UFSAR CHAPTER 12 12.2-37 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 242(2) 191 - 0 Radwaste evaporator SKID A 7.5' tank x 1.0 0.1875 12.2-65 and condenser (abandoned) 3.33' high RWCU phase separator 1.5" HBC-14 1.5" pipe 1.0 0.200 12.2-74 discharge piping x 19' long 243(2) 191 - 0 Radwaste evaporator SKID B 7.5' tank x 1.0 0.1875 12.2-65 and condenser (abandoned) 3.33' high RWCU phase separator 1.5" HBC-14 1.5" pipe 1.0 0.200 12.2-74 discharge piping x 19' long 245 191 - 0 Equipment drain surge 00T304, 00T309 32' tank x 1.0 0.4375 12.2-52, tank and floor drain 9.97' high 12.2-58 surge tank 247 191 - 0 Floor drain surge 00P310 4" pipe 1.0 0.237 12.2-58 tank pump 20' long 248 191 - 0 Equipment drain surge 00P302 4" pipe x 1.0 0.237 12.2-52 tank pump 20' long 421 217 - 0 HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 activity resin x 5' high 421A 217 - 0 HSA sludge transfer 1.5" 1.5" pipe x 1.0 0.200 12.2-74 piping HBC-14 20 ft long 421B 217 - 0 HIC with low specific LSA-HIC 6'-0" container 0.72 0.0 12.2-102 activity resin x 6' in. high 421C 217 - 0 HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 activity resin x 5' high 421M 228 - 6 &
HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 237 - 0 activity resin x 5' high
LGS UFSAR CHAPTER 12 12.2-38 REV. 13, SEPTEMBER 2006 Table 12.2-13 (Cont'd)
EQUIPMENT SELF-EFFECTIVE SHIELDING SOURCE (STEEL UFSAR ROOM ELEVATION DOMINANT SOURCE DENSITY THICKNESS SOURCE NO.
(FT - IN)
RADIATION SOURCE(S)
IDENTIFICATION SOURCE GEOMETRY (g/cc)(1)
IN INCHES)
TABLE 422A 217 - 0 High specific activity 1.5" 1.5" pipe x 1.0 0.200 12.2-74 sludge transfer piping HBC-14 17' long 422B 217 - 0 HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 activity resin x 5' high 422C 217 - 0 HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 activity resin x 5' high 423 217 - 0 HIC with high specific HSA-HIC 4'-6" container 0.72 0.0 12.2-101 activity resin x 5' high 469 237 - 0 High specific activity 1.5" 1.5" pipe x 1.0 0.200 12.2-74 sludge transfer piping HBC-14 20' long 470 237 - 0 Centrifuge OAS313 1'-0" tank 0.86 1.0 12.2-103 x 4' long 471 237 - 0 Centrifuge OBS813 1'-0" tank 0.86 1.0 12.2-103 x 4' long 485 237 - 0 Radwaste enclosure 0BF355, 0BF354 18.766' 0.001293 0.0 12.2-78 equipment compartment filter x 0.9583' exhaust air filters thick 486 237 - 0 Radwaste enclosure 0AF355, 0AF354 18.766' 0.001293 0.0 12.2-78 equipment compartment filter x 0.9583' exhaust air filters thick 515 257 - 0 Centrifuge air filters OAF380, OAF383 18.8' cylinder 0.00129 0.0 12.2-78 x 0.9583' long 516 257 - 0 Centrifuge air filters OBF380, OBF383 18.8' cylinder 0.00129 0.0 12.2-78 x 0.9583' long (1)
"Effective Source Density" is density of radiation source or combination of sources used in shielding design analyses.
(2)
These rooms contain components associated with the abandoned radwaste evaporator system. Installation of these components was not completed for plant operation (Section 11.2.2.1.3).
LGS UFSAR CHAPTER 12 12.2-39 REV. 16, SEPTEMBER 2012 Table 12.2-14 SPENT FUEL ASSEMBLY SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
SPENT FUEL STORAGE POOL(4)
Specific Specific Specific Activity Activity Activity Isotope(6)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Kr-85m 2.38E-04 Ru-105 8.62E-04 Pr-143 2.42E+00 Kr-85 1.81E-02 Ru-106 9.99E-04 Pr-144 2.19E+00 Kr-87 3.00E-12 Rh-103m 2.61E+00 Pr-145 6.79E-03 Kr-88 7.82E-06 Rh-105m 2.07E-04 Nd-147 9.96E-01 Xe-133m 1.76E-02 Rh-105 6.81E-01 Nd-149 6.03E-09 Xe-133 3.02E+00 Rh-106 9.99E-01 Pm-147 4.08E-01 Xe-135m 6.88E-03 Rh-109 3.41E-15 Pm-149 5.14E-01 Xe-135 1.83E-01 Pd-107 7.07E-12 Pm-151 1.03E-01 I-131 1.45E+00 Pd-109 5.11E-02 Sm-153 2.74E-01 I-132 2.19E+00 Sb-127 1.23E-01 Eu-156 2.75E-01 I-133 6.88E+00 Sb-129 2.46E-04 Sm-151 8.66E-06 I-134 4.29E-16 Te-127 1.09E-01 Sm-147 1.48E-14 I-135 2.20E-02 Te-129m 1.03E-03 Nd-144 3.46E-18 Rb-88 8.76E-06 Te-129 8.74E-04 Cs-135 9.12E-10 Sr-89 1.46E+00 Te-131m 8.99E-02 Xe-131m 1.05E-13 Sr-90 4.36E-07 Te-131 1.65E-02 I-129 1.48E-11 Sr-91 6.04E-02 Te-132 2.12E+00 Te-127m 4.10E-04 Sr-92 9.65E-06 Te-133m 9.73E-018 Ag-109m 5.11E-02 Y-90 1.86E-07 Te-133 1.32E-18 Pd-109m 3.69E-15 Y-91 1.91E+00 Te-134 8.94E-21 Tc-99 1.01E-07 Y-92 6.87E-04 Ba-139 1.24E-10 Nb-98 5.69E-19 Y-93 9.80E-02 Ba-140 2.70E+00 Nb-97m 3.79E-01 Zr-95 2.76E+00 La-140 2.96E+00 Nb-95m 1.72E-02 Zr-97 4.08E-01 La-141 5.78E-04 Zr-93 1.87E-09 Nb-95 2.81E+00 La-142 1.26E-09 Nb-93m 3.62E-13 Nb-97 4.39E-01 Ce-141 2.78E+00 Y-91m 3.91E-02 Mo-99 4.56E+00 Ce-143 9.44E-01 Y-89m 1.46E-04 Tc-99m 4.35E+00 Ce-144 2.19E+00 Rb-87 2.29E-15 Ru-103 2.66E+00
LGS UFSAR CHAPTER 12 12.2-40 REV. 16, SEPTEMBER 2012 Table 12.2-14 (Cont'd)
SPENT FUEL SHIPPING CASK(5)
Specific Specific Specific Activity Activity Activity Isotope(6)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Kr-85 1.76E-02 Rh-106 7.10E-01 Pm-147 3.68E-01 Xe-133 1.54E-10 Pd-107 7.07E-12 Eu-156 8.11E-05 I-131 2.60E-07 Sb-127 1.15E-15 Sm-151 1.24E-05 I-132 3.53E-17 Te-127 4.44E-04 Sm-147 1.29E-12 Sr-89 1.36E-01 Te-129m 2.62E-05 Nd-144 2.56E-16 Sr-90 4.31E-07 Te-129 1.68E-05 Cs-135 9.81E-10 Y-90 4.31E-07 Te-132 3.43E-17 Xe-131m 4.90E-07 Y-91 2.27E-01 Cs-137 7.96E-07 I-129 2.03E-11 Zr-95 4.09E-01 Ba-140 1.53E-04 Te-127m 4.46E-04 Nb-95 7.91E-01 La-140 1.76E-04 Tc-99 2.79E-07 Mo-99 1.25E-19 Ce-141 5.90E-02 Nb-95m 8.66E-03 Tc-99m 1.20E-19 Ce-144 1.40E+00 Zr-93 1.94E-09 Ru-103 1.11E-01 Pr-143 2.53E-04 Nb-93m 4.63E-11 Ru-106 7.10E-01 Pr-144 1.40E+00 Y-89m 1.36E-05 Rh-103m 1.09E-01 Nd-147 1.21E-05 Rb-87 2.29E-15 (1) Based on EOL assembly (1000 days irradiation).
(2) Assumes reactor to have been operating at 3323 MWt. Expect shielding to be sufficient for approximate 6% power increase to 3515 MWt.
(3) Assumes 764 assemblies per core.
(4) Assumes 2 days decay, when earliest fuel transfer from core to storage pool is expected.
(5) Assumes 0.5 years decay, when earliest offsite transport is expected.
(6) Isotopes with specific activities less than 1.0x10-20 are not listed.
Note: This table applies to the assumed spent fuel shipping cask, and not to the Independent Spent Fuel Storage Installation (ISFSI) Transfer Cask which will have significantly lower activities due to increased decay period of the ISFSI fuel.
LGS UFSAR CHAPTER 12 12.2-41 REV. 13, SEPTEMBER 2006 Table 12.2-15 DRYWELL EQUIPMENT AND FLOOR DRAIN SUMPS SHIELDING DESIGN SOURCE TERMS(1)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(2)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 5.25x10-8 Tc-99m 9.80x10-7 Ce-144 1.23x10-10 Br-84 9.45x10-8 Tc-101 4.90x10-7 Pr-143 1.33x10-10 Br-85 5.95x10-8 Ru-103 6.65x10-11 Nd-147 4.90x10-11 I-131 4.55x10-8 Ru-106 9.10x10-12 Np-239 8.40x10-7 I-132 4.20x10-7 Te-129m 1.40x10-10 Na-24 2.00x10-9 I-133 3.12x10-7 Te-132 1.72x10-7 P-32 2.00x10-11 I-134 8.40x10-7 Cs-134 5.60x10-10 Cr-51 5.00x1010 I-135 4.55x10-7 Cs-136 3.85x10-10 Mn-54 4.00x10-11 Sr-89 1.09x10-8 Cs-137 8.40x10-10 Mn-56 5.00x10-8 Sr-90 8.05x10-10 Cs-138 6.65x10-7 Co-58 5.00x10-9 Sr-91 2.42x10-7 Ba-139 5.60x10-7 Co-60 5.00x10-10 Sr-92 3.85x10-7 Ba-140 3.15x10-8 Fe-59 8.00x10-11 Zr-95 1.40x10-10 Ba-141 5.95x10-7 Ni-65 3.00x10-10 Zr-97 1.12x10-10 Ba-142 5.95x10-7 Zn-65 2.00x10-12 Nb-95 1.47x10-10 Ce-141 1.37x10-10 Zn-69m 3.00x10-11 Mo-99 7.70x10-8 Ce-143 1.23x10-10 Ag-110m 6.00x10-11 W-187 3.00x10-9 (1) Assumes 100% of specific activity in reactor water, less activation gases (Tables 12.2-2, 12.2-3, and 12.2-5).
(2) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-42 REV. 13, SEPTEMBER 2006 Table 12.2-16 RWCU SYSTEM RECIRCULATION PUMPS SHIELDING DESIGN SOURCE TERMS (1)(2)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(3)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 3.82x10-8 Ba-141 4.27x10-7 Y-89m 5.27x10-13 Br-84 6.84x10-8 Ba-142 4.23x10-7 Xe-135 1.25x10-10 BR-85 3.94x10-8 Ce-141 9.96x10-11 Xe-135m 1.86x10-9 I-131 3.32x10-8 Ce-143 8.94x10-11 Xe-133m 4.92x10-13 I-132 3.07x10-7 Ce-144 8.94x10-11 Xe-133 8.58x10-12 I-133 2.27x10-7 Pr-143 9.71x10-11 Xe-131m 3.44x10-15 I-134 6.10x10-7 Nd-147 3.58x10-11 Kr-85m 4.60x10-11 I-135 3.32x10-7 Np-239 6.13x10-7 Kr-85 2.79x10-19 Sr-89 7.92x10-9 Ag-110 2.93x10-13 Kr-83m 1.01x10-10 Sr-90 5.88x10-10 Zn-69 1.12x10-13 N-13 2.84x10-8 Sr-91 1.76x10-7 Pu-239 1.40x10-17 N-16 2.48x10-6 Sr-92 2.81x10-7 Pm-147 7.62x10-18 N-17 6.37x10-11 Zr-95 1.02x10-10 Pr-144 1.51x10-12 O-19 2.79x10-7 Zr-97 8.17x10-11 La-142 1.36x10-9 N-18 2.91x10-9 Nb-95 1.07x10-10 La-141 5.44x10-10 Na-24 1.46x10-9 Mo-99 5.62x10-8 La-140 2.80x10-12 P-32 1.46x10-11 Tc-99 7.15x10-7 Te-129 2.79x10-13 Cr-51 3.65x10-10 Tc-101 3.50x10-7 Rh-106 2.95x10-12 Mn-54 2.92x10-11 Ru-103 4.85x10-11 Rh-103m 2.42x10-13 Mn-56 3.64x10-8 Ru-106 6.64x10-12 Tc-99 1.90x10-18 Cu-58 3.65x10-9 Te-129m 1.02x10-10 Nb-97m 1.93x10-11 Cu-60 3.65x10-10 Te-132 1.25x10-7 Nb-97 6.45x10-14 Fe-59 5.84x10-11 Cs-134 4.09x10-10 Nb-95m 1.11x10-16 Ni-65 2.19x10-10 Cs-136 2.81x10-10 Y-92 3.88x10-10 Zn-65 1.46x10-12 Cs-137 6.13x10-10 Y-91 2.51x10-13 Zn-69m 2.19x10-11 CS-138 4.81x10-7 Y-91m 6.05x10-10 Ag-110m 4.38x10-11 Ba-139 4.07x10-7 Y-90 4.79x10-14 W-187 2.19x10-9 Ba-140 2.30x10-8 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) Pumps are assumed to be 25.4 seconds downline from the reactor recirculation loop.
(3) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-43 REV. 13, SEPTEMBER 2006 Table 12.2-17 RWCU SYSTEM REGENERATIVE HEAT EXCHANGER - FIRST-STAGE SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Br-83 5.96x10-3 1.22x10-3 La-141 1.36x10-4 2.27x10-4 Br-84 1.06x10-2 1.99x10-3 La-140 7.04x10-7 1.30x10-6 Br-85 5.78x10-3 3.55x10-4 Te-129 7.01x10-8 1.27x10-7 I-131 5.18x10-3 1.09x10-3 I-129 3.06x10-1 95.94x10-19 I-132 4.77x10-2 9.89x10-3 Rh-106 6.34x10-7 2.18x10-7 I-133 3.55x10-2 7.44x10-3 Rh-103m 6.09x10-8 1.09x10-7 I-134 9.48x10-2 1.86x10-2 Ic-99 4.79x10-1 8.84x10-13 I-135 5.18x10-2 1.08x10-2 Nb-97m 4.47x10-6 2.45x10-6 Sr-89 1.24x10-3 2.60x10-4 Nb-97 2.17x10-8 1.18x10-7 Sr-90 9.17x10-5 1.93x10-5 Nb-95m 2.81x10-1 5.18x10-11 Sr-91 2.75x10-2 5.75x10-3 Y-92 9.98x10-5 1.78x10-4 Sr-92 4.37x10-2 8.99x10-3 Y-91 6.35x10-8 1.23x10-7 Zr-95 1.59x10-5 3.36x10-6 Y-91m 1.52x10-4 2.71x10-4 Zr-97 1.27x10-5 2.67x10-6 Y-90 1.21x10-8 2.23x10-8 Nb-95 1.67x10-5 3.52x10-6 Y-89m 1.02x10-7 2.60x10-8 Mo-99 8.77x10-3 1.84x10-3 Xe-135 3.15x10-5 5.67x10-2 Tc-99m 1.11x10-1 2.32x10-2 Cs-135 4.73x10-1 2.73x10-14 Tc-101 5.39x10-2 8.72x10-3 Xe-135m 4.64x10-4 7.96x10-1 Ru-103 7.57x10-6 1.59x10-6 Xe-133m 1.24x10-7 6.68x10-4 Ru-106 1.04x10-6 2.18x10-7 Xe-133 2.16x10-6 1.16x10-2 Te-129m 1.59x10-5 3.36x10-6 Xe-131m 8.66x10-1 1.98x10-5 Te-132 1.95x10-2 4.11x10-3 Kr-85m 1.12x10-5 1.01x10-4 Cs-134 6.38x10-5 6.71x10-5 Kr-85 1.11x10-1 6.13x10-12 Cs-136 4.38x10-5 4.61x10-5 Kr-83m 2.53x10-5 1.60x10-2 Cs-137 9.57x10-5 1.01x10-4 N-13 4.34x10-3 6.30x10-3 Cs-138 7.46x10-2 7.00x10-2 N-16 8.69x10-2 6.22x10-15 Ba-139 6.34x10-2 1.28x10-2 N-17 7.82x10-7 negligible Ba-140 3.59x10-3 7.55x10-4 O-19 3.01x10-2 3.10x10-5 Ba-141 6.60x10-2 1.13x10-2 F-18 4.54x10-4 9.23x10-4 Ba-142 6.49x10-2 9.76x10-3 Na-24 2.28x10-4 4.77x10-5 Ce-141 1.55x10-5 3.28x10-6 P-32 2.28x10-6 4.79x10-7 Ce-143 1.39x10-5 2.93x10-6 Cr-51 5.69x10-5 1.19x10-5 Ce-144 1.40x10-5 2.94x10-6 Mn-54 4.56x10-6 9.58x10-7 Pr-143 1.51x10-5 3.19x10-6 Mn-56 5.68x10-3 1.16x10-3
LGS UFSAR CHAPTER 12 12.2-44 REV. 13, SEPTEMBER 2006 Table 12.2-17 (Cont'd)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Nd-147 5.58x10-6 1.17x10-6 Co-58 5.69x10-419x10-4 Np-239 9.57x10-2 2.01x10-2 Co-60 5.69x10-5 1.19x10-5 Ag-110 6.11x10-8 1.87x10-8 Fe-59 9.11x10-6 1.91x10-6 Zn-69 2.83x10-8 5.06x10-8 Ni-65 3.41x10-5 6.99x10-6 Pu-239 3.53x10-1 6.55x10-1 Zn-65 2.28x10-7 4.79x10-8 Pm-147 1.92x10-1 3.56x10-1 Zn-69m 3.41x10-6 7.15x10-7 Pr-144 3.77x10-7 6.30x10-7 Ag-110m 6.83x10-6 1.43x10-6 La-142 3.39x10-4 5.22x10-4 W-187 3.42x10-4 7.17x10-5 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) Tube side is reactor water with 37.5 seconds decay accumulated for 6.98 seconds at 341.7 gpm at 0.757 g/cc; shell side is filtered and demineralized reactor water with 353.81 seconds decay accumulated for 14.7 seconds at 310 gpm at 0.834 g/cc.
(3) Shell side assumes a decontamination factor of 10 across the filter/demineralizer (except for Cs and Rb, which have a DF of 2, and gases, which have a DF of 1).
(4) Shell side includes noble gases generated by particulate parents accumulating on filter/demineralizer resins.
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-45 REV. 13, SEPTEMBER 2006 Table 12.2-18 RWCU SYSTEM REGENERATIVE HEAT EXCHANGER - SECOND-STAGE SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Br-83 6.41x10-3 1.28x10-3 La-141 1.72x10-4 2.29x10-4 Br-84 1.14x10-2 2.09x10-3 La-140 8.91x10-7 1.31x10-6 Br-85 6.06x10-3 3.94x10-4 Te-129 8.87x10-8 1.27x10-7 I-131 5.58x10-3 1.14x10-3 I-129 3.88x10-1 5.95x10-19 I-132 5.13x10-2 1.04x10-2 Rh-106 7.49x10-7 2.28x10-7 I-133 3.82x10-2 7.79x10-3 Rh-103m 7.70x10-8 1.10x10-7 I-134 1.02x10-1 1.95x10-2 Tc-99 6.06x10-1 8.87x10-13 I-135 5.57x10-2 1.13x10-2 Nb-97m 5.45x10-6 2.56x10-6 Sr-89 1.33x10-3 2.72x10-4 Nb-97 3.04x10-8 1.17x10-7 Sr-90 9.87x10-5 2.02x10-5 Nb-95m 3.56x10-1 5.20x10-11 Sr-91 2.96x10-2 6.02x10-3 Y-92 1.24x10-4 1.78x10-4 Sr-92 4.70x10-2 9.43x10-3 Y-91 8.04x10-8 1.23x10-7 Zr-95 1.72x10-5 3.51x10-6 Y-91m 1.92x10-4 2.72x10-4 Zr-97 1.37x10-5 2.80x10-6 Y-90 1.53x10-8 2.24x10-8 Nb-95 1.80x10-5 3.69x10-6 Y-89m 1.16x10-7 2.72x10-8 Mo-99 9.44x10-3 1.93x10-3 Xe-135 3.99x10-5 5.91x10-2 Tc-99m 1.20x10-1 2.43x10-2 Cs-135 7.05x10-1 2.20x10-14 Tc-101 5.77x10-2 9.24x10-3 Xe-135m 5.86x10-4 8.43x10-1 Ru-103 8.15x10-6 1.67x10-6 Xe-133m 1.57x10-7 7.00x10-4 Ru-106 1.12x10-6 2.28x10-7 Xe-133 2.73x10-6 1.22x10-2 Te-129m 1.72x10-5 3.51x10-6 Xe-131m 1.10x10-9 2.07x10-5 Te-132 2.10x10-2 4.30x10-3 Kr-85m 1.40x10-5 1.06x10-4 Cs-134 6.86x10-5 7.03x10-5 Kr-85 1.64x10-1 5.67x10-12 Cs-136 4.72x10-5 4.83x10-5 Kr-83m 3.20x10-5 1.68x10-2 Cs-137 1.03x10-4 1.05x10-4 N-13 4.64x10-3 6.72x10-3 Cs-138 8.01x10-2 7.37x10-2 N-16 4.64x10-2 2.83x10-14 Ba-139 6.82x10-2 1.34x10-2 N-17 2.54x10-7 Ba-140 3.86x10-3 7.90x10-4 O-19 2.72x10-2 4.65x10-5 Ba-141 7.07x10-2 1.20x10-2 F-18 4.88x10-4 9.68x10-4 Ba-142 6.93x10-2 1.04x10-2 Na-24 2.45x10-4 5.00x10-5 Ce-141 1.67x10-5 3.44x10-6 P-32 2.45x10-6 5.02x10-7 Ce-143 1.50x10-5 3.07x10-6 Cr-51 6.13x10-5 1.25x10-5 Ce-144 1.50x10-5 3.07x10-6 Mn-54 4.90x10-6 1.00x10-6 Pr-143 1.63x10-5 3.34x10-6 Mn-56 6.11x10-3 1.22x10-3
LGS UFSAR CHAPTER 12 12.2-46 REV. 13, SEPTEMBER 2006 Table 12.2-18 (Cont'd)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Nd-147 6.00x10-6 1.23x10-6 Co-58 6.13x10-4 1.25x10-4 Np-239 1.03x10-1 2.11x10-2 Co-60 6.13x10-5 1.25x10-5 Ag-110 7.13x10-8 1.96x10-8 Fe-59 9.80x10-6 2.01x10-6 Zn-69 3.57x10-8 5.09x10-8 Ni-65 3.66x10-5 7.34x10-6 Pu-239 4.47x10-1 6.57x10-1 Zn-65 2.45x10-7 5.02x10-8 Pm-147 2.43x10-1 3.57x10-1 Zn-69m 3.67x10-6 7.49x10-7 Pr-144 4.77x10-7 6.35x10-7 Ag-110m 7.35x10-6 1.51x10-6 La-142 4.27x10-4 5.29x10-4 W-187 3.68x10-4 7.51x10-5 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) The tube side is reactor water with 44.48 seconds decay accumulated for 7.52 seconds at 317.0 gpm at 0.815 g/cc; the shell side is filtered and demineralized reactor water with 338.41 seconds decay accumulated for 15.4 seconds at 294 gpm at 0.879 g/cc.
(3) The shell side assumes a DF of 10 across the filter/demineralizer (except for Cs and Rb, which have a DF of 2, and gases, which have a DF of 1).
(4) The shell side includes noble gases generated by particulate parents accumulating on filter/demineralizer resins.
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-47 REV. 13, SEPTEMBER 2006 Table 12.2-19 RWCU SYSTEM REGENERATIVE HEAT EXCHANGER - THIRD-STAGE SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Br-83 6.95x10-3 1.37x10-3 La-141 2.17x10-4 2.33x10-4 Br-84 1.23x10-2 2.24x10-3 La-140 1.12x10-6 1.33x10-6 Br-85 6.38x10-3 4.46x10-4 Te-129 1.12x10-7 1.29x10-7 I-131 6.05x10-3 1.22x10-3 T-129 4.90x10-1 6.03x10-19 I-132 5.57x10-2 1.10x10-2 Rh-106 8.79x10-7 2.43x10-7 I-133 4.14x10-2 8.30x10-3 Rh-103m 9.71x10-8 1.12x10-7 I-134 1.10x10-1 2.09x10-2 Tc-99 7.65x10-1 9.01x10-13 I-135 6.04x10-2 1.20x10-2 Nb-97m 6.60x10-6 2.71x10-6 Sr-89 1.44x10-3 2.90x10-4 Nb-97 4.22x10-8 1.18x10-7 Sr-90 1.07x10-4 2.15x10-5 Nb-95m 4.49x10-1 5.28x10-11 Sr-91 3.21x10-2 6.41x10-3 Y-92 1.56x10-4 1.81x10-4 Sr-92 5.10x10-2 1.00x10-2 Y-91 1.02x10-7 1.25x10-7 Zr-95 1.85x10-5 3.74x10-6 Y-91m 2.42x10-4 2.77x10-4 Zr-97 1.49x10-5 2.98x10-6 Y-90 1.93x10-8 2.28x10-8 Nb-95 1.96x10-5 3.93x10-6 Y-89m 1.31x10-7 2.90x10-8 Mo-99 1.02x10-2 2.06x10-3 Xt-135 5.04x10-5 6.26x10-2 Tc-99m 1.30x10-1 2.59x10-2 Cs-135 1.03x10-1 1.61x10-14 Tc-101 6.22x10-2 9.97x10-3 Xt-135m 7.38x10-4 9.08x10-1 Ru-103 8.85x10-6 1.78x10-6 Xe-133m 1.98x10-7 7.45x10-4 Ru-106 1.21x10-6 2.43x10-7 Xe-133 3.45x10-6 1.29x10-2 Te-129m 1.86x10-5 3.74x10-6 Xe-131m 1.38x10-9 2.20x10-5 Te-132 2.28x10-2 4.58x10-3 Kr-85m 1.74x10-5 1.12x10-4 Cs-134 7.45x10-5 7.48x10-5 Kr-85 2.38x10-1 5.19x10-12 Cs-136 5.12x10-5 5.14x10-5 Kr-83m 4.03x10-5 1.79x10-2 Cs-137 1.12x10-4 1.12x10-4 N-13 4.99x10-3 7.29x10-3 Cs-138 8.67x10-2 7.89x10-2 N-16 2.36x10-2 1.43x10-13 Ba-139 7.39x10-2 1.43x10-2 N-17 7.55x10-8 Ba-140 4.19x10-3 8.41x10-4 O-19 2.45x10-2 7.24x10-5 Ba-141 7.64x10-2 1.29x10-2 F-18 5.29x10-4 1.03x10-3 Ba-142 7.46x10-2 1.12x10-2 Na-24 2.66x10-4 5.32x10-5 Ce-141 1.81x10-5 3.66x10-6 P-32 2.66x10-6 5.34x10-7 Ce-143 1.63x10-5 3.27x10-6 Cr-51 6.65x10-5 1.34x10-5 Ce-144 1.63x10-5 3.27x10-6 Mn-54 5.32x10-6 1.07x10-6 Pr-143 1.77x10-5 3.55x10-6 Mn-56 6.62x10-3 1.30x10-3
LGS UFSAR CHAPTER 12 12.2-48 REV. 13, SEPTEMBER 2006 Table 12.2-19 (Cont'd)
ACTIVITY (Ci)
ACTIVITY (Ci)
ISOTOPE(5)
Tube Side Shell Side ISOTOPE Tube Side Shell Side Nd-147 6.52x10-6 1.31x10-6 Co-58 6.65x10-4 1.34x10-4 Np-239 1.11x10-1 2.24x10-2 Co-60 6.65x10-5 1.34x10-5 Ag-110 8.26x10-8 2.08x10-8 Fe-59 1.06x10-5 2.14x10-6 Zn-69 4.51x10-8 5.18x10-8 Ni-65 3.97x10-5 7.82x10-6 Pu-239 5.65x10-1 6.67x10-1 Zn-65 2.66x10-7 5.34x10-8 Pm-147 3.07x10-1 3.63x10-1 Zn-69m 3.99x10-6 7.98x10-7 Pr-144 6.00x10-7 6.49x10-7 Ag-110m 7.98x10-6 1.60x10-6 La-142 5.36x10-4 5.42x10-4 W-187 3.99x10-4 7.99x10-5 (1) Based upon shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) The tube side is reactor water with 52.0 seconds decay accumulated for 8.15 seconds at 292.4 gpm at 0.885 g/cc; shell side is filtered and demineralized reactor water with 322.01 seconds decay accumulated for 16.4 seconds at 278 gpm at 0.929 g/cc.
(3) The shell side assumes a DF of 10 across the filter/demineralizer (except for Cs and Rb, which have a DF of 2, and gases, which have a DF of 1).
(4) The shell side includes noble gases generated by particulate parents accumulating on filter/demineralizer resins.
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-49 REV. 13, SEPTEMBER 2006 Table 12.2-20 RWCU SYSTEM NONREGENERATIVE HEAT EXCHANGER - FIRST-STAGE SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(3)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 1.30x10-2 Ba-142 1.34x10-1 Xe-135 1.58x10-4 Br-84 2.28x10-2 Ce-141 3.40x10-5 Cs-135 5.40x10-17 Br-85 1.04x10-2 Ce-143 3.05x10-5 Xe-135m 2.27x10-3 I-131 1.33x10-2 Ce-144 3.05x10-5 Xe-133m 6.17x10-7 I-132 1.04x10-1 Pr-143 3.31x10-5 Xe-135 1.08x10-5 I-133 7.76x10-2 Nd-147 1.22x10-5 Xe-131m 4.32x10-9 I-134 2.05x10-1 Np-239 2.09x10-1 Kr-85m 5.08x10-5 I-135 1.13x10-1 Re-187 3.57x10-20 Kr-85 1.18x10-12 Sr-89 2.70x10-3 Ag-110 1.81x10-7 Kr-83m 1.25x10-4 Sr-90 2.01x10-4 Zn-69 1.40x10-7 N-13 8.95x10-3 Sr-91 6.01x10-2 Po-239 1.76x10-11 N-16 1.26x10-3 Sr-92 9.53x10-2 Pm-147 9.58x10-12 N-17 3.38x10-10 Zr-95 3.49x10-5 Pr-144 1.85x10-6 O-19 1.90x10-2 Zr-97 2.79x10-5 La-142 1.64x10-3 F-18 9.87x10-4 Nb-95 3.66x10-5 La-141 6.67x10-4 Na-24 4.98x10-4 Mo-99 1.92x10-2 La-140 3.51x10-6 P-32 4.98x10-6 Tc-99m 2.44x10-1 Te-129 3.48x10-7 Cr-50 1.25x10-4 Tc-101 1.13x10-1 I-129 1.54x10-18 Mn-54 9.97x10-6 Ru-103 1.66x10-5 Rh-106 2.00x10-6 Mn-56 1.24x10-2 Ru-106 2.27x10-6 Rh-103m 3.02x10-7 Co-58 1.25x10-3 Te-129m 3.49x10-5 Tc-99 2.39x10-12 Co-60 1.25x10-4 Te-132 4.27x10-2 Nb-97m 1.71x10-5 Fe-59 1.99x10-5 Cs-134 1.40x10-4 Nb-97 1.79x10-7 Ni-65 7.42x10-5 Cs-136 9.60x10-5 Nb-95m 1.39x10-10 Zn-65 4.98x10-7 Cs-137 2.09x10-4 Y-92 4.86x10-4 Zn-69m 7.47x10-6 Cs-138 1.60x10-1 Y-91 3.19x10-7 Ag-110m 1.46x10-5 Ba-139 1.38x10-1 Y-91m 7.53x10-4 W-187 7.47x10-4 Ba-140 7.85x10-3 Y-90 6.01x10-8 Ba-141 1.40x10-1 Y-89m 2.65x10-7 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) Reactor water with 85.75 seconds decay accumulated for 15.29 seconds at 277.5 gpm at 0.931 g/cc.
(3) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-50 REV. 13, SEPTEMBER 2006 Table 12.2-21 RWCU SYSTEM NONREGENERATIVE HEAT EXCHANGER - SECOND-STAGE SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(3)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 1.32x10-2 Ba-141 1.41x10-1 Y-90 7.13x10-8 Br-84 2.30x10-2 Ba-142 1.35x10-1 Y-89m 2.73x10-7 Br-85 9.93x10-3 Ce-141 3.46x10-5 Xe-135 1.88x10-4 I-131 1.15x10-2 Ce-143 3.11x10-5 Cs-135 7.46x10-17 I-132 1.06x10-1 Ce-144 3.11x10-5 Xe-135m 2.68x10-3 I-133 7.90x10-2 Pr-143 3.37x10-5 Xe-133m 7.32x10-7 I-134 2.08x10-1 Nd-147 1.24x10-5 Xe-133 1.28x10-5 I-135 1.15x10-1 Np-239 2.13x10-1 Xe-131m 5.12x10-9 Sr-89 2.75x10-3 Re-187 4.23x10-20 Kr-86m 5.86x10-5 Sr-90 2.04x10-4 Ag-110 1.89x10-7 Kr-85 1.60x10-12 Sr-91 6.11x10-2 Zn-69 1.66x10-7 Kr-83m 1.49x10-4 Sr-92 9.69x10-2 Pu-239 2.09x10-11 N-13 8.95x10-3 Zr-95 3.55x10-5 Pm-147 1.14x10-11 N-16 2.88x10-4 Zr-97 2.84x10-5 Pr-144 2.18x10-6 N-17 2.66x10-11 Nb-95 3.73x10-5 La-142 1.92x10-3 0-19 1.34x10-2 Mo-99 1.95x10-2 La-141 7.87x10-4 F-18 1.00x10-3 Tc-99m 2.48x10-1 La-140 4.16x10-6 Na-24 5.07x10-4 Tc-101 1.14x10-1 Te-129 4.12x10-7 P-32 5.07x10-6 Ru-103 1.69x10-5 T-129 1.83x10-18 Cr-51 1.27x10-4 Ru-106 2.30x10-6 Rh-106 2.12x10-6 Mn-54 1.01x10-5 Te-129m 3.55x10-5 Rh-103m 3.58x10-7 Mn-56 1.26x10-2 Te-132 4.35x10-2 Tc-99 2.83x10-12 Cu-58 1.27x10-3 Cs-134 1.42x10-4 Nb-97m 1.89x10-5 Cu-60 1.27x10-4 Cs-136 9.77x10-5 Nb-97 2.32x10-7 Fe-59 2.03x10-5 Cs-137 2.13x10-4 Nb-95m 1.65x10-10 Ni-65 7.55x10-5 Cs-138 1.62x10-1 Y-92 5.76x10-4 Zn-65 5.07x10-7 Ba-139 1.40x10-1 Y-91 3.79x10-7 Zn-69m 7.60x10-6 Ba-140 7.99x10-3 Y-91m 8.91x10-4 Ag-110m 1.52x10-5 W-187 7.60x10-4 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) Reactor water with 101.04 seconds decay accumulated for 15.57 seconds at 272.5 gpm at 0.948 g/cc.
(3) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-51 REV. 13, SEPTEMBER 2006 Table 12.2-22 RWCU SYSTEM FILTER/DEMINERALIZER AND BACKWASH RECEIVING TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(5)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 5.92 Cs-138 1.43x10+1 Rh-103m 2.92x10-1 Br-84 2.01 Ba-139 3.21x10+1 Tc-99 2.08x10-5 Br-85 6.96x10-2 Ba-140 1.26x10+2 Nb-97m 7.48x10-2 I-131 1.65x10+2 Ba-141 6.85 Nb-97 8.05x10-2 I-132 4.68x10+2 Ba-142 3.93 Nb-95m 5.63x10-3 I-133 2.66x10+2 Ce-141 1.59 Y-92 4.42x10+1 I-134 2.98x10+1 Ce-143 1.65x10-1 Y-91 6.95 I-135 1.28x10+2 Ce-144 5.82x10-1 Y-91m 5.83x10+1 Sr-89 4.97x10+1 Pr-143 5.75x10-1 Y-90 2.12 Sr-90 3.85 Nd-147 1.91x10-1 Y-89m 4.97x10-3 Sr-91 9.86x10+1 Np-239 1.73x10+3 Cs-135 4.76x10-7 Sr-92 4.37x10+1 Rd-187 7.21x10-13 Na-24 1.26 Zr-95 6.47x10-1 Ag-110 3.70x10-3 P-32 8.16x10-1 Zr-97 8.03x10-2 Zn-69 1.75x10-2 Cr-51 2.20 Nb-95 7.00x10-1 Pu-239 6.03x10-4 Mn-54 1.90x10-1 Mo-99 1.77x10+2 Pm-147 5.03x10-4 Mn-56 5.36 To-99m 4.01x10+2 Sm-147 2.14x10-17 Co-58 2.32x10+1 Tc-101 4.26 Pr-144 5.80x10-1 Co-60 2.39 Ru-103 3.00x10-1 Nd-144 1.56x10-18 Fe-59 3.64x10-1 Ru-106 4.33x10-2 La-142 4.61 Ni-65 3.22x10-2 Te-129m 6.26x10-1 Te-129 3.97x10-1 Zn-65 9.49x10-3 Te-132 4.32x10+2 I-129 2.40x10-10 Zn-69m 1.75x10-2 Cs-134 2.67 Rh-106 4.33x10-2 Ag-110m 2.85x10-1 Cs-136 1.56 W-187 3.01 Cs-137 4.02 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Filter/demineralizer is assumed to be 154.11 seconds downline from the reactor recirculation loop.
(3) Filter/demineralizer resins are assumed to accumulate all nongaseous isotopes in reactor water for 6.8 days at 135 gpm at 0.957 g/cc.
(4) Backwash volume for the receiving tank is assumed to be 1100 gallons.
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-52 REV. 13, SEPTEMBER 2006 Table 12.2-23 RWCU SYSTEM FILTER/DEMINERALIZER HOLDING PUMPS SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(5)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 4.91x10-9 Ba-140 3.01x10-9 Y-90 7.29x10-14 Br-84 8.12x10-9 Ba-141 4.71x10-8 Y-89m 1.04x10-13 Br-85 1.83x10-9 Ba-142 4.18x10-8 Xe-135 2.22x10-7 I-131 4.35x10-9 Ce-141 1.31x10-11 Xe-135m 3.34x10-6 I-132 3.96x10-8 Ce-143 1.17x10-11 Xe-133m 2.67x10-9 I-133 2.97x10-8 Ce-144 1.17x10-11 Xe-133 4.64x10-8 I-134 7.53x10-8 Pr-143 1.27x10-11 Xe-131m 7.90x10-11 I-135 4.32x10-8 Nd-147 4.69x10-12 Kr-85m 4.01x10-10 Sr-89 1.04x10-9 Np-239 8.03x10-8 Kr-85 1.20x10-17 Sr-90 7.70x10-11 Ag-110 7.46x10-14 Kr-83m 6.43x10-8 Sr-91 2.30x10-8 Zn-69 1.66x10-13 N-13 2.72x10-8 Sr-92 3.61x10-8 Pu-239 2.14x10-17 N-16 1.40x10-17 Zr-95 1.34x10-11 Pm-147 1.16x10-17 O-19 5.96x10-10 Zr-97 1.07x10-11 Pr-144 2.10x10-12 F-18 3.71x10-9 Nb-95 1.41x10-11 La-142 1.77x10-9 Na-24 1.91x10-10 Mo-99 7.36x10-9 La-141 7.56x10-10 P-32 1.91x10-12 Tc-99m 9.30x10-8 La-140 4.25x10-12 Cr-51 4.78x10-11 Tc-101 3.68x10-8 Te-129 4.15x10-13 Mn-54 3.83x10-12 Ru-103 6.36x10-12 Rh-106 8.70x10-13 Mn-56 4.68x10-9 Ru-106 8.71x10-13 Rh-103m 3.59x10-13 Co-58 4.78x10-10 Te-129 1.34x10-11 Tc-99 2.88x10-18 Co-60 4.78x10-11 Te-132 1.64x10-8 Nb-97m 9.61x10-12 Fe-59 7.66x10-12 Cs-134 2.68x10-10 Nb-97 3.66x10-13 Ni-65 2.81x10-11 Cs-136 1.84x10-10 Nb-95m 1.69x10-16 Zn-65 1.91x10-13 Cs-137 4.02x10-10 Y-92 5.82x10-10 Z-69m 2.86x10-12 Cs-138 2.86x10-7 Y-91 3.98x10-13 Ag-110m 5.74x10-12 Ba-139 5.14x10-8 Y-91m 8.90x10-10 W-187 2.86x10-10 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) Pumps are assumed to be 295.01 seconds downline from the reactor recirculation loop.
(3) A DF of 10 is assumed across the filter/demineralizer (except for Cs and Rb, which have a DF of 2, and gases, which have a DF of 1).
(4) Includes noble gases generated by particulate parents accumulating on filter/demineralizer resins.
(5) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-53 REV. 13, SEPTEMBER 2006 Table 12.2-24 RHR SYSTEM SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(4)
(Ci/g)
ISOTOPE (Ci/g)
ISOTOPE (Ci/g)
Br-83 1.66x10-8 Ba-141 5.78x10-11 Y-90 3.63x10-11 Br-84 5.06x10-10 Ba-142 1.61x10-13 Y-89m 1.08x10-12 I-131 4.49x10-8 Ce-141 2.43x10-10 Xe-135 9.45x10-8 I-132 2.42x10-7 Ce-143 1.13x10-10 Cs-135 5.48x10-18 I-133 2.72x10-7 Ce-144 1.22x10-10 Xe-135m 9.38x10-8 I-134 3.43x10-8 Pr-143 1.33x10-10 Xe-133m 3.48x10-10 I-135 3.00x10-7 Nd-147 4.85x10-11 Xe-133 6.16x10-9 Sr-89 1.08x10-8 Np-237 8.00x10-7 Xe-131m 2.64x10-12 Sr-90 8.05x10-10 Ag-110 7.80x10-13 Kr-85m 3.64x10-10 Sr-91 1.81x10-7 Zn-69 2.46x10-11 Kr-85 3.35x10-15 Sr-92 1.38x10-7 Pu-239 1.06x10-14 Kr-83m 2.10x10-8 Zr-95 1.40x10-10 Pm-147 5.89x10-15 N-13 2.24x10-15 Zr-97 9.51x10-11 Pr-144 1.22x10-10 F-18 8.78x10-10 Nb-95 1.47x10-10 La-142 1.33x10-8 Na-24 1.66x10-9 Mo-99 7.39x10-8 La-141 2.44x10-8 P-32 1.98x10-11 Tc-99m 6.44x10-7 La-140 2.09x10-9 Cr-51 4.98x10-10 Tc-101 3.39x10-12 Te-129 8.15x10-11 Mn-54 4.00x10-11 Ru-103 6.63x10-11 Rh-106 9.10x10-12 Mn-56 1.70x10-8 Ru-106 9.10x10-12 Rh-103m 6.14x10-11 Co-58 4.99x10-9 Te-129m 1.40x10-10 Tc-99 1.21x10-15 Co-60 5.00x10-10 Te-132 1.65x10-7 Nb-97m 8.86x10-11 Fe-59 7.98x10-11 Cs-134 5.60x10-10 Nb-97 9.04x10-11 Ni-65 1.02x10-10 Cs-136 3.82x10-10 Nb-95m 8.49x10-14 Zn-65 2.00x10-12 Cs-137 8.40x10-10 Y-92 1.23x10-7 Zn-69m 2.45x10-11 Cs-138 3.80x10-9 Y-91 3.46x10-10 Ag-110m 6.00x10-11 Ba-139 7.53x10-8 Y-91m 1.11x10-7 W-187 2.67x10-9 Ba-140 3.12x10-8 (1) Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2) RHR system is assumed to begin operation 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after shutdown.
(3) Assumes no cleanup of reactor coolant after shutdown.
(4) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-54 REV. 13, SEPTEMBER 2006 Table 12.2-25 RCIC SYSTEM SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(4)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 4.16x10-11 Ba-140 1.25x10-12 Xe-137 1.17x10-8 Br-84 7.48x10-11 Ba-141 2.36x10-11 Xe-138 6.93x10-9 Br-85 4.71x10-11 Ba-142 2.36x10-11 Xe-139 2.18x10-8 I-131 3.60x10-11 Ce-141 5.40x10-15 Xe-140 2.33x10-8 I-132 3.33x10-10 Ce-143 4.85x10-15 Xe-141 1.87x10-8 I-133 2.47x10-10 Ce-144 4.85x10-15 Xe-142 5.66x10-9 I-134 6.65x10-10 Pr-143 5.27x10-15 Xe-143 9.35x10-10 I-135 3.60x10-10 Nd-147 1.94x10-15 Xe-144 4.36x10-11 Sr-89 4.30x10-13 Np-239 3.33x10-11 N-13 2.77x10-10 Sr-90 3.19x10-14 Kr-83m 2.65x10-10 N-16 1.98x10-6 Sr-91 9.56x10-12 Kr-85m 4.75x10-10 N-17 7.92x10-10 Sr-92 1.52x10-11 Kr-85 1.56x10-12 O-19 3.17x10-8 Zr-95 5.54x10-15 Kr-87 1.56x10-9 F-18 1.58x10-10 Zr-97 4.44x10-15 Kr-88 1.56x10-9 Na-24 7.92x10-14 Nb-95 5.82x10-15 Kr-89 1.01x10-8 P-32 7.92x10-16 Mo-99 3.05x10-12 Kr-90 2.18x10-8 Cr-51 1.98x10-14 Tc-99m 3.88x10-11 Kr-91 2.57x10-8 Mn-54 1.58x10-15 Tc-101 1.94x10-11 Kr-92 2.57x10-8 Mn-56 1.98x10-12 Ru-103 2.63x10-15 Kr-93 7.68x10-9 Cu-58 1.98x10-13 Ru-106 3.60x10-16 Kr-94 1.79x10-9 Cu-60 1.98x10-14 Te-129m 5.54x10-15 Kr-95 1.63x10-10 Fe-59 3.17x10-15 Te-132 6.79x10-12 Xe-131m 1.17x10-12 Ni-65 1.19x10-14 Cs-134 2.22x10-14 Xe-133m 2.26x10-11 Zn-65 7.92x10-17 Cs-136 1.52x10-14 Xe-133 6.38x10-10 Zn-69m 1.19x10-15 Cs-137 3.33x10-14 Xe-135m 2.02x10-9 Ag-110m 2.38x10-15 Cs-138 2.63x10-11 Xe-135 1.71x10-9 W-187 1.19x10-13 Ba-139 2.22x10-11 (1)
Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2)
Inlet steam to RCIC turbine, with conditions of 1120 psig and 575F.
(3)
No decay is assumed in transit from the RPV steam nozzles.
(4)
Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-55 REV. 13, SEPTEMBER 2006 Table 12.2-26 HPCI SYSTEM SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(4)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 4.35x10-11 Ce-141 5.65x10-15 Xe-144 4.55x10-11 Br-84 7.82x10-11 Ce-143 5.07x10-15 N-13 2.90x10-10 Br-85 4.93x10-11 Ce-144 5.07x10-15 N-16 2.07x10-6 I-131 3.77x10-11 Pr-143 5.51x10-15 N-17 8.28x10-10 I-132 3.48x10-10 Nd-147 2.03x10-15 0-19 3.31x10-8 I-133 2.58x10-10 Np-239 3.48x10-11 F-18 1.66x10-10 I-134 6.96x10-10 Kr-83m 2.77x10-10 Na-24 8.28x10-14 I-135 3.77x10-10 Kr-85m 4.97x10-10 P-32 8.28x10-16 Sr-89 4.49x10-13 Kr-85 1.63x10-12 Cr-51 2.07x10-14 SR-90 3.33x10-14 Kr-87 1.63x10-9 Mn-54 1.66x10-15 Sr-91 1.00x10-11 Kr-88 1.63x10-9 Mn-56 2.07x10-12 Sr-92 1.59x10-11 Kr-89 1.06x10-8 Co-58 2.07x10-13 Zr-95 5.80x10-15 Kr-90 2.28x10-8 Co-60 2.07x10-14 Zr-97 4.64x10-15 Kr-91 2.68x10-8 Fe-59 3.31x10-15 Nb-95 6.09x10-15 Kr-92 2.68x10-8 Ni-65 1.24x10-14 Mo-99 3.19x10-12 Kr-93 8.03x10-9 Zn-65 8.28x10-17 Tc-99m 4.06x10-11 Kr-94 1.87x10-9 Zn-69m 1.24x10-15 Tc-101 2.03x10-11 Kr-95 1.71x10-10 Ag-110m 2.48x10-15 Ru-103 2.75x10-15 Xe-131m 1.22x10-12 W-187 1.24x10-13 Ru-106 3.77x10-16 Xe-133m 2.36x10-11 Te-129m 5.80x10-15 Xe-133 6.67x10-10 Te-132 7.10x10-12 Xe-135m 2.12x10-9 Cs-134 2.32x10-14 Xe-135 1.79x10-9 Cs-136 1.59x10-14 Xe-137 1.22x10-8 Cs-137 3.48x10-14 Xe-138 7.25x10-9 Cs-138 2.75x10-11 Xe-139 2.28x10-8 Ba-139 2.32x10-11 Xe-140 2.44x10-8 Ba-140 1.30x10-12 Xe-141 1.95x10-8 Ba-141 2.46x10-11 Xe-142 5.92x10-9 Ba-142 2.46x10-11 Xe-143 9.77x10-10 (1)
Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2)
Inlet steam to HPCI turbine, with conditions of 1120 psig and 560F.
(3)
Decay is assumed in transit from the RPV steam nozzles.
(4)
Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-56 REV. 13, SEPTEMBER 2006 Table 12.2-27 FPCC SYSTEM SHIELDING DESIGN SOURCE TERMS (1)(2)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(3)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 1.05x10-10 Tc-99m 1.96x10-9 Ce-144 2.45x10-13 Br-84 1.89x10-10 Tc-101 9.80x10-10 Pr-143 2.66x10-13 Br-85 1.19x10-10 Ru-103 1.33x10-13 Nd-147 9.80x10-14 I-131 9.10x10-11 Ru-106 1.82x10-14 Np-239 1.68x10-9 I-132 8.40x10-10 Te-129m 2.80x10-13 Na-24 4.00x10-12 I-133 6.23x10-10 Te-132 3.43x10-10 P-32 4.00x10-14 I-134 1.68x10-9 Cs-134 1.12x10-12 Cr-51 1.00x10-12 I-135 9.10x10-10 Cs-136 7.70x10-13 Mn-54 8.00x10-14 Sr-89 2.17x10-11 Cs-137 1.68x10-12 Mn-56 1.00x10-10 Sr-90 1.61x10-12 Cs-138 1.33x10-9 Cu-58 1.00x10-11 Sr-91 4.83x10-10 Ba-139 1.12x10-9 Cu-60 1.00x10-12 Sr-92 7.70x10-10 Ba-140 6.30x10-11 Fe-59 1.60x10-13 Zr-95 2.80x10-13 Ba-141 1.19x10-9 Ni-65 6.00x10-13 Zr-97 2.24x10-13 Ba-142 1.19x10-9 Zn-65 4.00x10-15 Nb-95 2.94x10-13 Ce-141 2.73x10-13 Zn-69m 6.00x10-14 Mo-99 1.54x10-10 Ce-143 2.45x10-13 Ag-110m 1.20x10-13 W-187 6.00x10-12 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
Reactor water (less gases) diluted to 0.2%, with no decay (this corresponds to a gross specific activity of 1.6x10-2 Ci/cc).
(3)
Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-57 REV. 13, SEPTEMBER 2006 Table 12.2-28 FPCC SYSTEM FILTER/DEMINERALIZER SHIELDING DESIGN SOURCE TERMS(1)(2)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(3)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 2.32x10-2 Cs-138 6.54x10-2 I-129 2.21x10-12 Br-84 9.19x10-3 Ba-139 1.41x10-1 Rh-106 2.75x10-4 Br-85 5.45x10-4 Ba-140 7.42x10-1 Rh-103m 1.81x10-3 I-131 9.31x10-1 Ba-141 3.27x10-2 Tc-99 1.44x10-7 I-132 2.32 Ba-142 2.00x10-2 Nb-97m 3.24x10-4 I-133 1.60 Ce-141 9.90x10-3 Nb-97 3.49x10-4 I-134 1.33x10-1 Ce-143 7.37x10-4 Nb-95m 4.46x10-5 I-135 5.57x10-1 Ce-144 3.69x10-3 Y-92 1.91x10-1 Sr-89 3.10x10-1 Pr-143 3.42x10-3 Y-91 4.48x10-2 Sr-90 2.45x10-2 Nd-147 1.11x10-3 Y-91m 2.52x10-1 Sr-91 4.28x10-1 Np-239 8.22 Y-90 1.62x10-2 Sr-92 1.91x10-1 Re-187 4.97x10-15 Y-89m 3.10x10-5 Zr-95 4.05x10-3 Ag-110 2.34x10-5 Cs-135 3.19x10-9 Zr-97 3.49x10-4 Zn-69 7.59x10-5 Na-24 5.49x10-3 Nb-95 4.44x10-3 Pu-239 4.58x10-6 P-32 4.83x10-4 Mo-99 8.64x10-1 Pm-147 4.43x10-6 Cr-51 1.35x10-2 Tc-99m 1.83 Sm-147 2.80x10-19 Mn-54 1.20x10-3 Tc-101 2.09x10-2 Pr-144 3.68x10-3 Mn-56 2.36x10-2 Ru-103 1.86x10-3 Nd-144 1.46x10-20 Cu-58 1.45x10-1 Ru-106 2.75x10-4 La-142 2.00x10-2 Cu-60 1.52x10-2 Te-129 3.86x10-3 La-141 3.27x10-2 Fe-59 2.26x10-3 Te-132 2.15 La-140 5.91x10-1 Ni-65 1.41x10-4 Cs-134 6.01x10-5 Te-129 2.45x10-3 Zn-69m 7.59x10-5 Cs-136 9.22x10-3 Ag-110 1.80x10-3 Cs-137 2.56x10-2 W-187 1.31x10-2 Ag-110m 1.80x10-3 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
Fuel pool water (Table 12.2-27) accumulated for 10 days at 280 gpm.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
(4)
For shielding design of associated piping, backwash volume to waste sludge tank is 1925 gallons.
LGS UFSAR CHAPTER 12 12.2-58 REV. 13, SEPTEMBER 2006 Table 12.2-29 FUEL POOL HEAT EXCHANGER SHIELDING DESIGN SOURCE TERMS(1)
ACTIVITY ISOTOPE(2)
(Ci)
Na-24 2.25x10-2 P-32 2.25x10-4 Cr-51 5.63x10-3 Mn-54 4.50x10-4 Mn-56 5.63x10-1 Co-58 5.63x10-2 Co-60 5.63x10-3 Fe-59 9.00x10-4 Ni-65 3.38x10-3 Zn-65 2.25x10-5 Zn-69m 3.38x10-4 Ag-110m 6.75x10-4 W-187 3.38x10-2 (1)
Corrosion (noncoolant activation) products in reactor water (given in Table 12.2-5) with no decay were normalized to yield a contact dose rate of 200 mR/hr for one fuel pool heat exchanger.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-59 REV. 13, SEPTEMBER 2006 Table 12.2-30 REACTOR ENCLOSURE EQUIPMENT COMPARTMENT EXHAUST AIR FILTERS SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ISOTOPE(3)
(Ci)
I-131 1.90x10-2 I-133 7.95x10-3 Co-60 9.37x10-3 Co-58 1.64x10-4 Cr-51 3.29x10-5 Mn-54 2.03x10-3 Fe-59 7.18x10-5 Zn-65 1.25x10-3 Zr-95 3.55x10-4 Sr-89 6.50x10-5 Sr-90 1.73x10-5 Sb-124 1.64x10-4 Cs-134 1.19x10-2 Cs-136 5.68x10-5 Cs-137 1.90x10-2 Ba-140 7.08x10-5 Ce-141 4.49x10-5 La-140 7.08x10-5 Y-90 1.71x10-5 Y-89m 6.50x10-9 Nb-95 3.46x10-4 Nb-95m 7.08x10-6 (1)
Based on NUREG-0016, Revision 0, table 1-1 (Reference 12.2-1) release rates, with fission products adjusted to 0.35 Ci/cc offgas release rate at 30 minutes decay.
(2)
Assumes a one year accumulation of all these isotopes at 40,000 cfm.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-60 REV. 13, SEPTEMBER 2006 Table 12.2-31 CONTROL ROD DRIVE MECHANISM SHIELDING DESIGN SOURCE TERMS(1)
CONTAMINATED CRD MECHANISM FILTER(2)
CONTAMINATED CRD MECHANISM BODY(3)
DECONTAMINATED CRD MECHANISM BODY(4)
Activity Activity Activity Isotope(5)
(Ci)
Isotope(5)
(Ci)
Isotope(5)
(Ci)
Na-24 2.32x10-2 Na-24 4.35x10-2 Na-24 2.18x10-3 P-32 2.32x10-4 P-32 4.35x10-4 Pa-32 2.18x10-5 Cr-51 5.79x10-3 Cr-51 1.09x10-2 Cr-51 5.44x10-4 Mn-54 4.63x10-4 Mn-54 8.70x10-4 Mn-54 4.35x10-5 Mn-56 5.79x10-1 Mn-56 1.09 Mn-56 5.44x10-2 Co-58 5.79x10-2 Co-58 1.09x10-1 Co-58 5.44x10-3 Co-60 5.79x10-3 Co-60 1.09x10-2 Co-60 5.44x10-4 Fe-59 9.26x10-4 Fe-59 1.74x10-3 Fe-59 8.70x10-5 Ni-65 3.47x10-3 Ni-65 6.53x10-3 Ni-65 3.26x10-4 Zn-65 2.32x10-5 Zn-65 4.35x10-5 Zn-65 2.18x10-6 Zn-69m 3.47x10-4 Zn-69m 6.53x10-4 Zn-69m 3.26x10-5 Ag-110m 6.95x10-4 Ag-110m 1.31x10-3 Ag-110m 6.53x10-5 W-187 3.47x10-2 W-187 6.53x10-2 W-187 3.26x10-3 (1)
Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2)
Specific activity of corrosion products in the reactor coolant concentrated in the filter to yield a contact dose rate of 50 R/hr.
(3)
Specific activity of corrosion products in the reactor coolant concentrated in the body to yield a contact dose rate of 10 R/hr.
(4)
Specific activity of corrosion products in the reactor coolant concentrated in the body to yield a contact dose rate of 0.5 R/hr.
(5)
Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-61 REV. 13, SEPTEMBER 2006 Table 12.2-32 TURBINE OPERATING DECK SHIELDING DESIGN SOURCE TERMS(1)(2)
DECAY TIME AVERAGE IN TRANSIT AVERAGE DENSITY N-16 SPECIFIC ACTIVITY SOURCE (seconds)
(g/cc)
(Ci/cc)
Main steam piping to high pressure 3.27 3.78x10-2 1.38 turbine High pressure turbine exhaust piping 3.63 7.44x10-3 2.61x10-1 Cross-around piping to combined 6.43 6.41x10-3 1.71x10-1 intercept valves (1)
Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2)
Assumes a total rated flow of main steam from the RPV of 14,140,500 lb/hr.
LGS UFSAR CHAPTER 12 12.2-62 REV. 13, SEPTEMBER 2006 Table 12.2-33 MOISTURE SEPARATOR SHIELDING DESIGN SOURCE TERMS(1)
VAPOR REGION IN MOISTURE SEPARATOR BODY (2)
Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 6.42E-04 La-143 1.35E-06 N-17 5.60E-03 Br-84 1.15E-03 Cs-142 2.10E-02 O-19 4.38E-01 Br-85 7.16E-04 La-142 2.41E-07 F-18 2.44E-03 I-131 5.57E-04 Cs-141 1.59E-02 Na-24 1.23E-06 I-132 5.14E-03 La-141 8.84E-08 P-32 1.23E-08 I-133 3.81E-03 Cs-140 1.57E-02 Cr-51 3.06E-07 I-134 1.03E-02 La-140 4.35E-10 Mn-54 2.44E-08 I-135 5.57E-03 Cs-139 1.86E-03 Mn-56 3.06E-05 Sr-89 6.64E-06 Cs-135 9.14E-16 Co-58 3.06E-06 Sr-90 4.93E-07 Rb-95 3.91E-04 Co-60 3.06E-07 Sr-91 1.49E-04 Sr-95 2.90E-05 Fe-59 4.90E-08 Sr-92 2.60E-04 Y-95 6.96E-08 Ni-65 1.84E-07 Zr-95 8.57E-08 Nb-95m 1.76E-14 Zn-65 1.23E-09 Zr-97 6.85E-08 Rb-94 5.83E-03 Zn-69m 1.84E-06 Nb-95 8.99E-08 Sr-94 2.17E-14 Ag-110m 3.67E-08 Mo-99 4.71E-05 Y-94 2.62E-07 W-187 1.84E-06 Tc-99 5.99E-04 Rb-93 2.38E-02 Kr-83m 4.08E-03 Tc-101 2.99E-04 Sr-93 1.15E-04 Kr-85m 7.34E-03 Ru-103 4.07E-08 Y-93 4.13E-09 Kr-85 2.40E-05 Ru-106 5.57E-09 Rb-92 1.04E-01 Kr-87 2.40E-02 Te-129m 8.57E-08 Y-92 6.31E-08 Kr-88 2.40E-02 Te-132 1.05E-04 Rb-91 1.49E-02 Kr-89 1.53E-01 Cs-134 3.43E-07 Y-91 3.94E-11 Kr-90 3.05E-01 Cs-136 2.36E-07 Y-91m 9.47E-08 Kr-91 2.85E-01 Cs-137 5.15E-07 Rb-90 5.94E-03 Kr-92 1.35E-01 Cs-138 5.88E-04 Y-90 7.48E-12 Kr-93 2.37E-02 Ba-139 3.43E-04 Rb-89 5.47E-04 Kr-94 2.80E-03 Ba-140 1.93E-05 Y-89m 1.22E-10 Kr-95 1.05E-04 Ba-141 3.95E-04 Rb-88 7.35E-05 Xe-131m 1.80E-05 Ba-142 4.65E-04 Rb-87 5.20E-20 Xe-133m 3.49E-04 Ce-141 8.35E-08 Ag-110 5.98E-11 Xe-133 9.85E-03 Ce-143 7.49E-08 Zn-69 1.76E-11 Xe-135m 3.12E-02 Ce-144 7.49E-08 Pu-239 2.18e-15 Xe-135 2.64E-02 Pr-143 8.13E-08 Pm-147 1.19e-15 Xe-137 1.78E-01
LGS UFSAR CHAPTER 12 12.2-63 REV. 13, SEPTEMBER 2006 Table 12.2-33 (Cont'd)
VAPOR REGION IN MOISTURE SEPARATOR BODY(2)
Activity Activity Activity Isotope(4)
(Ci Isotope (Ci)
Isotope (Ci)
Nd-147 3.00E-08 Te-129 4.35E-11 Xe-138 1.07E-01 Np-239 5.14E-04 Rh-106 5.74E-10 Xe-139 3.12E-01 Cs-144 4.92E-04 Rh-103m 3.78E-11 Xe-140 2.94E-01 Ba-144 9.75E-05 Tc-99 2.96E-16 Xe-141 4.34E-02 La-144 3.36E-06 Nb-97m 3.38E-09 Xe-142 1.03E-02 Pr-144 2.37E-10 Nb-97 4.95E-12 Xe-143 6.02E-04 Cs-143 2.28E-03 N-13 4.26E-03 Xe-144 4.68E-04 Ba-143 6.79E-04 N-16 1.94E+01 0.00E+00
LGS UFSAR CHAPTER 12 12.2-64 REV. 13, SEPTEMBER 2006 Table 12.2-33 (Cont'd)
LIQUID REGION IN MOISTURE SEPARATOR DRAIN TANK(3)
Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 4.37E-03 Cs-137 3.50E-06 Nb-97m 5.15E-08 Br-84 7.83E-03 Cs-138 2.76E-03 Nb-97 1.12E-10 Br-85 4.75E-03 Ba-139 2.32E-03 Nb-95m 2.76E-13 I-131 3.79E-03 Ba-140 1.31E-04 Y-92 9.65E-07 I-132 3.50E-02 Ba-141 2.45E-03 Y-91 6.22E-10 I-133 2.60E-02 Ba-142 2.44E-03 Y-91m 1.50E-06 I-134 6.97E-02 Ce-141 5.68E-07 Y-90 1.18E-10 I-135 3.79E-02 Ce-143 5.09E-07 Y-89m 1.66E-09 Sr-89 4.52E-05 Ce-144 5.09E-07 Cs-135 2.88E-19 Sr-90 3.34E-06 Pr-143 5.54E-07 N-16 2.03E+00 Sr-91 1.00E-03 Nd-147 2.04E-07 Na-24 8.32E-06 Sr-92 1.60E-03 Np-239 3.50E-03 P-32 8.32E-08 Zr-95 5.82E-07 Ag-110 8.57E-10 Cr-51 2.09E-06 Zr-97 4.66E-07 Zn-69 2.79E-10 Mn-54 1.66E-07 Nb-95 6.11E-07 Pu-239 3.49E-14 Mn-56 2.07E-04 Mo-99 3.20E-04 Pm-147 1.90E-14 Co-58 2.09E-05 Tc-99 4.07E-03 Pr-144 3.76E-09 Co-60 2.09E-06 Tc-101 2.02E-03 La-142 3.39E-06 Fe-59 3.33E-07 Ru-103 2.77E-07 La-141 1.36E-06 Ni-65 1.25E-07 Ru-106 3.79E-08 La-140 6.94E-09 Zn-65 8.32E-09 Te-129m 5.82E-07 Te-129 6.92E-10 Zn-69m 1.25E-07 Te-132 7.14E-04 Rh-106 6.39E-09 Ag-110m 2.50E-07 Cs-134 2.33e-06 Rh-103m 6.02E-10 W-187 1.25E-05 Cs-136 1.61e-06 Tc-99 4.72E-15 (1)
Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2)
Main steam with 3.63 seconds decay accumulated for 2.185 seconds at rated flow per moisture separator.
(3)
All particulates and 20% of N-16 that enter the moisture separator accumulated for 14.85 seconds at rated flow per moisture separator drain tank.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-65 REV. 13, SEPTEMBER 2006 Table 12.2-34 FEEDWATER HEATERS AND DRAIN COOLER SHIELDING DESIGN SOURCE TERMS(1)(2)
N-16 ACTIVITY IN SHELL SIDE OF FEEDWATER HEATERS Vapor Region Liquid Region (3)
Total Equipment (Ci)
(Ci)
(Ci)
Feedwater Heater No. 106 5.54 3.71 9.25 Feedwater Heater No. 105 3.84 2.88 6.72 Feedwater Heater No. 104 1.41 5.31 6.72 Feedwater Heater No. 103 1.61 3.04 4.65 Feedwater Heater No. 102 5.89x10-1 2.23 2.82 Feedwater Heater No. 101 3.45x10-1 2.22 2.57 Feedwater Heater Drain cooler 5.41x10-1 5.41x10-1 (1)
Based on shielding source terms given in Table 12.2-4.
(2)
All data are based on "Valve Wide Open" flow conditions.
(3)
Assumes 20% of N-16 in steam that condenses enters the liquid region.
LGS UFSAR CHAPTER 12 12.2-66 REV. 13, SEPTEMBER 2006 Table 12.2-35 STEAM SEAL EVAPORATOR SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ACTIVITY ACTIVITY Isotope(3)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 2.69x10-5 Ba-143 3.23x10-5 N-16 4.80x10-1 Br-84 4.82x10-5 La-143 2.07x10-7 N-17 9.77x10-5 Br-85 2.93x10-5 Cs-142 2.83x10-4 O-19 1.60x10-2 I-131 2.33x10-5 La-142 2.51x10-8 F-18 1.02x10-4 I-132 2.15x10-4 Cs-141 6.64x10-4 Na-24 5.12x10-8 I-133 1.60x10-4 La-141 8.71x10-9 P-32 5.12x10-10 I-134 4.29x10-4 Cs-140 1.23x10-3 Cr-51 1.28x10-8 I-135 2.33x10-4 La-140 4.00x10-11 Mn-54 1.02x10-9 Sr-89 2.78x10-7 Cs-139 1.61x10-4 Mn-56 1.28x10-6 Sr-90 2.06x10-8 Cs-135 8.38x10-17 Co-58 1.28x10-7 Sr-91 6.32x10-6 Rb-95 4.63x10-6 Co-60 1.28x10-8 Sr-92 1.25x10-5 Sr-95 1.78x10-6 Fe-59 2.05x10-9 Zr-95 3.59x10-9 Y-95 1.25x10-8 Ni-65 7.68x10-9 Zr-97 2.87x10-9 Nb-95m 1.62x10-15 Zn-65 5.12x10-11 Nb-95 3.77x10-9 Rb-94 9.33x10-5 Zn-69m 7.69x10-10 Mo-99 1.97x10-6 Sr-94 1.57x10-5 Ag-110m 1.54x10-9 Tc-99m 2.51x10-5 Y-94 5.38x10-8 W-187 7.69x10-8 Tc-101 1.24x10-5 Rb-93 6.96x10-4 Kr-83m 1.71x10-4 Ru-103 1.70x10-9 Sr-93 1.13x10-5 Kr-85m 3.07x10-4 Ru-106 2.33x10-10 Y-93 1.09x10-9 Kr-85 1.01x10-6 Te-129m 3.59x10-9 Rb-92 3.59x10-3 Kr-87 1.01x10-3 Te-132 4.39x10-6 Y-92 6.28x10-9 Kr-88 1.01x10-3 Cs-134 1.43x10-8 Rb-91 1.09x10-3 Kr-89 6.29x10-3 Cs-136 9.86x10-9 Y-91 3.61x10-12 Kr-90 1.14x10-2 Cs-137 2.16x10-8 Y-91m 8.72x10-9 Kr-91 8.09x10-3 Cs-138 3.35x10-5 Rb-90 5.06x10-4 Kr-92 1.72x10-3 Ba-139 1.45x10-5 Y-90 6.84x10-13 Kr-93 1.81x10-4 Ba-140 8.12x10-7 Rb-89 4.95x10-5 Kr-94 1.17x10-5 Ba-141 1.90x10-5 Y-89m 9.91x10-12 Kr-95 2.10x10-7 Ba-142 2.23x10-5 Rb-88 6.73x10-6 Xe-131m 7.56x10-7 Ce-141 3.50x10-9 Ag-110 5.06x10-12 Xe-133m 1.46x10-5 Ce-143 3.14x10-9 Zn-69 1.61x10-12 Xe-133 4.13x10-4 Ce-144 3.14x10-9 Pu-239 2.00x10-16 Xe-135m 1.30x10-3 Pr-143 3.41x10-9 Pm-147 1.09x10-16 Xe-135 1.11x10-3
LGS UFSAR CHAPTER 12 12.2-67 REV. 13, SEPTEMBER 2006 Table 12.2-35 (Cont'd)
ACTIVITY ACTIVITY ACTIVITY Isotope(3)
(Ci)
Isotope (Ci)
Isotope (Ci)
Nd-147 1.26x10-9 Te-129 3.99x10-12 Xe-137 7.33x10-3 Np-239 2.15x10-5 Rh-106 4.93x10-11 Xe-138 4.45x10-3 Cs-144 1.46x10-5 Rh-103m 3.46x10-12 Xe-139 1.19x10-2 Ba-144 7.64x10-6 Tc-99 2.72x10-17 Xe-140 9.69x10-3 La-144 7.04x10-7 Nb-97m 3.00x10-10 Xe-141 2.57x10-4 Pr-144 2.16x10-11 Nb-97 5.97x10-13 Xe-142 4.88x10-5 Cs-143 2.08x10-5 N-13 1.77x10-4 Xe-143 1.20x10-6 Xe-144 1.29x10-5 (1) Based upon shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Main steam with 6.59 seconds decay accumulated for 7.49 seconds at 3929 gpm at 0.0138 g/cc.
(3) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-68 REV. 13, SEPTEMBER 2006 Table 12.2-36 REACTOR FEED PUMP TURBINE SHIELDING DESIGN SOURCE TERMS(1)(2)
RFPT INLET STEAM(3)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
N-13 4.03x10-11 Nd-147 2.84x10-16 Xe-144 4.02x10-12 N-16 1.62x10-7 Np-239 4.87x10-12 Cs-144 4.42x10-12 N-17 4.27x10-11 Na-24 1.16x10-14 Ba-144 1.19x10-12 O-19 4.02x10-9 P-32 1.16x10-16 La-144 5.32x10-14 F-18 2.32x10-11 Cr-51 2.90x10-15 Pr-144 2.85x10-18 Br-83 6.09x10-12 Mn-54 2.32x10-16 Cs-143 1.50x10-11 Br-84 1.09x10-11 Mn-56 2.90x10-13 Ba-143 7.33x10-12 Br-85 6.75x10-12 Co-58 2.90x10-14 La-143 2.00x10-14 I-131 5.28x10-12 Co-60 2.90x10-15 Cs-142 1.58x10-10 I-132 4.87x10-11 Fe-59 4.64x10-16 La-142 3.01x10-15 I-133 3.62x10-11 Ni-65 1.74x10-15 Cs-141 1.57x10-10 I-134 9.74x10-11 Zn-65 1.16x10-17 La-141 1.08x10-15 I-135 5.28x10-11 Zn-69m 1.74x10-16 Cs-140 1.84x10-10 Sr-89 6.30x10-14 Ag-110m 3.48x10-16 La-140 5.25x10-18 Sr-90 4.67x10-15 W-187 1.74x10-14 Cs-139 2.21x10-11 Sr-91 1.41x10-12 Kr-83m 3.87x10-11 Rb-95 2.77x10-12 Sr-92 2.55x10-12 Kr-85m 6.96x10-11 Sr-95 3.31x10-13 Zr-95 8.12x10-16 Kr-85 2.28x10-13 Y-95 1.06x10-15 Zr-97 6.50x10-16 Kr-87 2.28x10-10 Rb-94 4.58x10-11 Nb-95 8.53x10-16 Kr-88 2.28x10-10 Sr-94 2.60x10-12 Mo-99 4.47x10-13 Kr-89 1.45x10-9 Y-94 4.13x10-15 To-99m 5.69x10-12 Kr-90 2.81x10-9 Rb-93 2.19x10-10 To-101 2.83x10-12 Kr-91 2.46x10-9 Sr-93 1.48x10-12 Ru-103 3.86x10-16 Kr-92 9.40x10-10 Y-93 6.87x10-17 Ru-106 5.28x10-17 Kr-93 1.41x10-10 Rb-92 1.01x10-9 Te-129m 8.12x10-16 Kr-94 1.35x10-11 Y-92 7.72x10-16 Te-132 9.95x10-13 Kr-95 3.74x10-13 Rb-91 1.72x10-10 Cs-134 3.25x10-15 Xe-131m 1.71x10-13 Y-91 4.72x10-19 Cs-136 2.23x10-15 Xe-133m 3.31x10-12 Y-91m 1.14x10-15 Cs-137 4.88x10-15 Xe-133 9.34x10-11 Rb-90 7.06x10-11 Cs-138 6.03x10-12 Xe-135m 2.95x10-10 Y-90 8.99x10-20 Ba-139 3.26x10-12 Xe-135 2.51x10-10 Rb-89 6.57x10-12 Ba-140 1.83x10-13 Xe-137 1.68x10-9 Y-89m 1.43x10-18 Ba-141 3.88x10-12 Xe-138 1.01x10-9 Rb-88 8.86x10-13 Ba-142 4.65x10-12 Xe-139 2.90x10-9 Ag-110 7.09x10-19
LGS UFSAR CHAPTER 12 12.2-69 REV. 13, SEPTEMBER 2006 Table 12.2-36 (Contd)
RFPT INLET STEAM(3)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Ce-141 7.92x10-16 Xe-140 2.64x10-9 Zn-69 2.12x10-19 Ce-143 7.11x10-16 Xe-141 2.37x10-10 Te-129 5.24x10-19 Ce-144 7.11x10-16 Xe-142 5.19x10-11 Rh-106 6.83x10-18 Pr-143 7.72x10-16 Xe-143 2.14x10-12 Rh-103m 4.56x10-19 Nb-97m 4.05x10-17 Nb-97 6.35x10-20
LGS UFSAR CHAPTER 12 12.2-70 REV. 13, SEPTEMBER 2006 Table 12.2-36 (Cont'd)
RFPT EXHAUST STEAM(4)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
N-13 9.14x10-13 Pr-143 1.75x10-17 Xe-142 1.18x10-12 N-16 3.67x10-09 Nd-147 6.44x10-18 Xe-143 4.85x10-14 N-17 9.68x10-13 Np-239 1.10x10-13 Xe-144 9.12x10-14 O-19 9.12x10-11 Na-24 2.63x10-16 Cs-144 1.00x10-13 F-18 5.26x10-13 P-32 2.63x10-18 Ba-144 2.70x10-14 Br-83 1.38x10-13 Cr-51 6.58x10-17 La-144 1.21x10-15 Br-84 2.48x10-13 Mn-54 5.26x10-18 Pr-144 6.45x10-20 Br-85 1.53x10-13 Mn-56 6.57x10-15 Cs-143 3.40x10-13 I-131 1.20x10-13 Co-58 6.58x10-16 Ba-143 1.66x10-13 I-132 1.10x10-12 Co-60 6.58x10-17 La-143 4.53x10-16 I-133 8.19x10-13 Fe-59 1.05x10-17 Cs-142 3.58x10-12 I-134 2.21x10-12 Ni-65 3.94x10-17 La-142 6.82x10-17 I-135 1.20x10-12 Zn-65 2.63x10-19 Cs-141 3.56x10-12 Sr-89 1.43x10-15 Zn-69m 3.95x10-18 La-141 2.45x10-17 Sr-90 1.06x10-16 Ag-110m 7.89x10-18 Cs-140 4.16x10-12 Sr-91 3.20x10-14 W-187 3.95x10-16 La-140 1.19x10-19 Sr-92 5.78x10-14 Kr-83m 8.78x10-13 Cs-139 5.01x10-13 Zr-95 1.84x10-17 Kr-85m 1.58x10-12 Rb-95 6.28x10-14 Zr-97 1.47x10-17 Kr-85 5.17x10-15 Sr-95 7.51x10-15 Nb-95 1.93x10-17 Kr-87 5.16x10-12 Y-95 2.41x10-17 Mo-99 1.01x10-14 Kr-88 5.17x10-12 Rb-94 1.04x10-12 To-99m 1.29x10-13 Kr-89 3.28x10-11 Sr-94 5.89x10-14 To-101 6.41x10-14 Kr-90 6.38x10-11 Y-94 9.36x10-17 Ru-103 8.75x10-18 Kr-91 5.58x10-11 Rb-93 4.97x10-12 Ru-106 1.20x10-18 Kr-92 2.13x10-11 Sr-93 3.36x10-14 Te-129m 1.84x10-17 Kr-93 3.19x10-12 Y-93 1.56x10-18 Te-132 2.26x10-14 Kr-94 3.05x10-13 Rb-92 2.29x10-11 Cs-134 7.37x10-17 Kr-95 8.47x10-15 Y-92 1.75x10-17 Cs-136 5.06x10-17 Xe-131m 3.88x10-15 Rb-91 3.89x10-12 Cs-137 1.11x10-26 Xe-133m 7.50x10-14 Y-91 1.07x10-20 Cs-138 1.37x10-13 Xe-133 2.12x10-12 Y-91m 2.59x10-17
LGS UFSAR CHAPTER 12 12.2-71 REV. 13, SEPTEMBER 2006 Table 12.2-36 (Cont'd)
RFPT EXHAUST STEAM(4)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Ba-139 7.38x10-14 Xe-135m 6.69x10-12 Rb-90 1.60x10-12 Ba-140 4.15x10-15 Xe-135 5.68x10-12 Rb-89 1.49x10-13 Ba-141 8.78x10-14 XE-137 3.81x10-11 Y-89m 3.25x10-20 Ba-142 1.05x10-13 Xe-138 2.29x10-11 Rb-88 2.01x10-14 Ce-141 1.80x10-17 Xe-139 6.57x10-11 Ag-110 1.61x10-20 Ce-143 1.61x10-17 Xe-140 5.97x10-11 Te-129 1.19x10-20 Ce-144 1.61x10-17 Xe-141 5.37x10-12 Rh-106 1.55x10-19 Rh-103m 1.03x10-20 Nb-97m 9.17x10-19 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Based on cross-around steam 6.0 seconds from RPV nozzles.
(3) Cross-around steam conditions of 104.8 psia and 1196.3 Btu/lb.
(4) Cross-around steam with RFPT exhaust conditions of 5.17" Hg (abs) and 994.0 Btu/lb.
(5) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-72 REV. 13, SEPTEMBER 2006 Table 12.2-37 MAIN CONDENSER HOTWELL SHIELDING DESIGN SOURCE TERMS(1)
CARRYOVER COMPONENT(2)
Specific Specific Specific Activity Activity Activity Isotope(6)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Br-83 1.05x10-9 Tc-99m 9.80x10-10 Ce-144 1.23x10-13 Br-84 1.89x10-9 Tc-101 4.90x10-10 Pr-143 1.33x10-13 Br-85 1.19x10-9 Ru-103 6.65x10-14 Nd-147 4.90x10-14 I-131 9.10x10-10 Ru-106 9.10x10-15 Np-239 8.40x10-10 I-132 8.40x10-9 Te-129m 1.40x10-13 Na-24 2.00x10-12 I-133 6.23x10-9 Te-132 1.72x10-10 P-32 2.00x10-14 I-134 1.68x10-8 Cs-134 5.60x10-13 Cr-51 5.00x10-13 I-135 9.10x10-9 Cs-136 3.85x10-13 Mn-54 4.00x10-14 Sr-89 1.09x10-11 Cs-137 8.40x10-13 Mn-56 5.00x10-11 Sr-90 8.05x10-13 Cs-138 6.65x10-10 Co-58 5.00x10-12 Sr-91 2.42x10-10 Ba-139 5.60x10-10 Co-60 5.00x10-13 Sr-92 3.85x10-10 Ba-140 3.15x10-11 Fe-59 8.00x10-14 Zr-95 1.40x10-13 Ba-141 5.95x10-10 Ni-65 3.00x10-13 Zr-97 1.12x10-13 Ba-142 5.95x10-10 Zn-65 2.00x10-15 Nb-95 1.47x10-13 Ce-141 1.37x10-13 Zn-69m 3.00x10-14 Mo-99 7.70x10-11 Ce-143 1.23x10-13 Ag-110m 6.00x10-14 W-187 3.00x10-12 NITROGEN COMPONENT(3)(4)
Specific Activity Isotope(6)
(Ci/cc)
N-16 8.59x10-7
LGS UFSAR CHAPTER 12 12.2-73 REV. 13, SEPTEMBER 2006 Table 12.2-37 (Cont'd)
FALLOUT COMPONENT(5)
Specific Specific Specific Activity Activity Activity Isotope(6)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Cs-144 7.16x10-10 Cs-140 3.59x10-8 Rb-93 3.58x10-8 Ba-144 2.35x10-10 Ba-140 8.39x10-14 Sr-93 3.06x10-10 La-144 1.27x10-11 La-140 9.67x10-19 Y-93 1.71x10-14 Ce-144 7.76x10-19 Cs-139 4.41x10-9 Rb-92 1.71x10-7 Cs-143 1.90x10-9 Ba-139 2.19x10-12 Sr-92 6.70x10-11 Ba-143 1.32x10-9 Cs-138 4.38x10-10 Y-92 1.04x10-14 La-143 4.51x10-12 Cs-137 1.50x10-15 Rb-91 3.32x10-8 Ce-143 4.51x10-12 Rb-95 3.73x10-10 Sr-91 2.54x10-12 Cs-142 2.20x10-8 Sr-95 6.24x10-11 Y-91 3.47x10-19 Ba-142 2.35x10-10 Y-95 2.46x10-13 Y-91m 8.39x10-16 La-142 1.02x10-13 Zr-95 6.89x10-20 Rb-90 1.40x10-8 Cs-141 2.73x10-8 Rb-94 6.60x10-9 Sr-90 4.00x10-17 Ba-141 9.26x10-11 Sr-94 5.06x10-10 Rb-89 1.32x10-9 La-141 1.31x10-14 Y-94 9.83x10-13 Sr-89 7.06x10-16 Rb-88 1.78x10-10 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Reactor water activities with a water/steam carryover factor of 0.02 by weight for halogens and 0.001 for others (coolant activation gases and noble gas fission products are excluded).
(3) Assumes a 5.815 second transit time from the RPV steam nozzles to the main condensers.
(4) Assumes 20% of the N-16 in the steam that condenses enters and accumulates in the hotwell for 2 minutes at the rated flow of 2,659,391 lb/hr.
(5) Noble gas daughters created during the 7 second transit time from the RPV steam nozzles to the condensers noncondensables exhaust.
(6) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-74 REV. 13, SEPTEMBER 2006 Table 12.2-38 CONDENSATE SYSTEM SHIELDING DESIGN SOURCE TERMS(1)(2)
CARRYOVER_COMPONENT(3)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Br-83 1.04x10-9 Cs-136 3.85x10-13 Rh-103m 1.55x10-15 Br-84 1.81x10-9 Cs-137 8.40x10-13 Nb-97m 7.80x10-14 Br-85 7.50x10-10 Cs-138 6.37x10-10 Nb-97 1.06x10-15 I-131 9.10x10-10 Ba-139 5.51x10-10 Nb-95m 7.19x10-19 I-132 8.32x10-9 Ba-140 3.15x10-11 Y-92 2.50x10-12 I-133 6.22x10-9 Ba-141 5.51x10-10 Y-91 1.65x10-15 I-134 1.64x10-8 Ba-142 5.25x10-10 Y-91m 3.87x10-12 I-135 9.07x10-9 Ce-141 1.37x10-13 Y-90 3.10x10-16 Sr-89 1.08x10-11 Ce-143 1.22x10-13 Y-89m 1.08x10-15 Sr-90 8.05x10-13 Ce-144 1.23x10-13 Na-24 2.00x10-12 Sr-91 2.41x10-10 Pr-143 1.33x10-13 P-32 2.00x10-14 Sr-92 3.82x10-10 Nd-147 4.90x10-14 Cr-51 5.00x10-13 Zr-95 1.40x10-13 Np-239 8.37x10-10 Mn-54 4.00x10-14 Zr-97 1.12x10-13 Ag-110 7.54x10-16 Mn-56 4.96x10-11 Nb-95 1.47x10-13 Zn-69 7.20x10-16 Co-58 5.00x10-12 Mo-99 7.70x10-11 Pm-147 4.93x10-20 Co-60 5.00x10-13 Tc-99m 9.77x10-10 Pr-144 9.45x10-15 Fe-59 8.00x10-14 Tc-101 4.44x10-10 La-142 8.31x10-12 Ni-65 2.97x10-13 Ru-103 6.65x10-14 La-141 3.41x10-12 Zn-65 2.00x10-15 Ru-106 9.10x10-15 La-140 1.81x10-14 Zn-69m 2.99x10-14 Te-129m 1.40x10-13 Te-129 1.79x10-15 Ag-110m 6.00x10-14 Te-132 1.71x10-10 Rh-106 8.53x10-15 W-187 3.00x10-12 Cs-134 5.60x10-13
LGS UFSAR CHAPTER 12 12.2-75 REV. 13, SEPTEMBER 2006 Table 12.2-38 (Cont'd)
FALLOUT COMPONENT(4)
Specific Specific Specific Activity Activity Activity Isotope(5)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Ba-144 2.84x10-13 Ba-140 1.62x10-12 Rb-92 2.62x10-14 La-144 1.79x10-11 La-140 5.80x10-16 Sr-92 1.58x10-10 Ce-144 1.38x10-16 Cs-139 3.81x10-9 Y-92 1.01x10-12 Pr-144 6.17x10-18 Ba-139 7.02x10-11 Rb-91 1.06x10-8 Ba-143 1.66x10-12 Cs-138 4.20x10-10 Sr-91 4.95x10-11 La-143 2.56x10-11 Cs-137 1.50x10-15 Y-91 2.08x10-16 Ce-143 4.52x10-12 Sr-95 1.47x10-11 Y-91m 4.91x10-13 Pr-143 3.20x10-16 Y-95 4.77x10-12 Rb-90 8.70x10-9 Ba-142 2.75x10-10 Zr-95 4.72x10-17 Sr-90 1.10x10-15 La-142 4.43x10-12 Sr-94 2.69x10-10 Y-90 2.36x10-19 Cs-141 8.54x10-10 Y-94 3.12x10-11 Rb-89 1.21x10-9 Ba-141 6.41x10-10 Rb-93 1.27x10-14 Sr-89 2.38x10-14 La-141 3.07x10-12 Sr-93 6.03x10-10 Y-89m 1.94x10-18 Ce-141 3.90x10-17 Y-93 1.43x10-12 Rb-88 1.65x10-10 Cs-140 1.02x10-8 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Assumes 2 minutes decay in transit through the condenser hotwell.
(3) Reactor water activities with a water/steam carryover factor of 0.02 by weight for halogens and 0.001 for others (coolant activation gases and noble gas fission products are excluded).
(4) Noble gas daughters created during the 7 second transit time from the RPV steam nozzles to the condensers noncondensables exhaust.
(5) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-76 REV. 13, SEPTEMBER 2006 Table 12.2-39 CONDENSATE SYSTEM FILTER/DEMINERALIZER AND BACKWASH RECEIVING TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
CARRYOVER COMPONENT(4)
Activity Activity Activity Isotope(6)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 3.54 Cs-138 4.81x10-1 Rh-103m 1.40x10-2 Br-84 1.35 Ba-139 1.07 Tc-99 1.12x10-6 Br-85 5.00x10-2 Ba-140 5.72 Nb-97m 2.50x10-3 I-131 1.43x10+2 Ba-141 2.31x10-1 Nb-97 2.69x10-3 I-132 4.31x10+1 Ba-142 1.34x10-1 Nb-95m 3.44x10-4 I-133 1.79x10+2 Ce-141 7.63x10-2 Y-92 1.47 I-134 2.00x10+1 Ce-143 5.67x10-3 Y-91 3.46x10-1 I-135 8.56x10+1 Ce-144 2.85x10-2 Y-91m 1.95 Sr-89 2.39 Pr-143 2.64x10-2 Y-90 1.25x10-1 Sr-90 1.89x10-1 Nd-147 8.56x10-3 Y-89m 2.39x10-4 Sr-91 3.29 Np-239 6.33x10+1 Cs-135 4.92x10-7 Sr-92 1.46 Re-187 3.83x10-14 Na-24 4.22x10-2 Zr-95 3.12x10-2 Ag-110 1.81x10-4 P-32 3.73x10-3 Zr-97 2.69x10-3 Zn-69 5.85x10-4 Cr-51 1.04x10-1 Nb-95 3.43x10-2 Pu-239 3.54x10-5 Mn-54 9.30x10-3 Mo-99 6.66 Pm-147 3.42x10-5 Mn-56 1.80x10-1 Tc-99m 1.41x10+1 Sm-147 2.16x10-18 Co-58 1.12 Tc-101 1.45x10-1 Pr-144 2.84x10-2 Co-60 1.17x10-1 Ru-103 1.43x10-2 Nd-144 1.13x10-19 Fe-59 1.75x10-2 Ru-106 2.12x10-3 La-142 1.54x10-1 Ni-65 1.08x10-3 Te-129m 2.98x10-2 La-141 2.52x10-1 Zn-65 4.64x10-4 Te-132 1.66x10+1 La-140 4.55 Zn-69m 5.84x10-4 Cs-134 1.31x10-1 Te-129 1.89x10-2 Ag-110m 1.39x10-2 Cs-136 7.10x10-2 I-129 1.71x10-11 W-187 1.01x10-1 Cs-137 1.97x10-1 Rh-106 2.12x10-3
LGS UFSAR CHAPTER 12 12.2-77 REV. 13, SEPTEMBER 2006 Table 12.2-39 (Cont'd)
FALLOUT COMPONENT(5)
Activity Activity Activity Isotope(6)
(Ci)
Isotope (Ci)
Isotope (Ci)
Ba-144 5.54x10-7 La-140 3.22x10-1 Zr-93 1.65x10-9 La-144 2.24x10-4 Cs-139 8.38x10-1 Nb-93m 1.03x10-12 Ce-144 3.90x10-5 Ba-139 9.90x10-1 Rb-92 7.68x10-9 Pr-144 3.90x10-5 Cs-138 3.17x10-1 Sr-92 6.07x10-1 Ba-143 3.29x10-6 Cs-137 3.53x10-4 Y-92 6.13x10-1 La-143 8.33x10-3 Cs-135 5.22x10-10 Rb-91 2.56x10-1 Ce-143 2.18x10-1 Sr-95 2.22x10-4 Sr-91 9.72x10-1 Pr-143 7.30x10-2 Y-95 1.48x10-3 Y-91 1.02x10-1 Cs-142 4.30x10-20 Zr-95 1.61x10-4 Y-91m 5.74x10-1 Ba-142 7.02x10-2 Nb-95 1.50x10-5 Rb-90 5.62x10-1 La-142 8.09x10-2 Nb-95m 1.77x10-6 Sr-90 6.67x10-4 Cs-141 5.22x10-3 Rb-94 7.33x10-17 Y-90 4.41x10-4 Ba-141 2.77x10-2 Sr-94 7.53x10-3 Rb-89 4.33x10-1 La-141 2.97x10-1 Y-94 2.33x10-2 Sr-89 5.91x10-2 Ce-141 5.57x10-2 Rb-93 4.37x10-9 Y-89m 5.91x10-6 Cs-140 2.25x10-1 Sr-93 1.16x10-1 Rb-88 6.84x10-2 Ba-140 4.04x10-1 Y-93 1.39x10-1 Rb-87 2.96x10-14 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Assumes 2.25 minutes decay in transit through condenser hotwell and piping to filter/demineralizer.
(3) Backwash volume for the receiving tank is assumed to be 9000 gallons.
(4) Carryover component of condensate accumulated for 10 days at 4314 gpm at 1.0 g/cc.
(5) Fallout component of condensate accumulated for 10 days at 4314 gpm at 1.0 g/cc.
(6) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-78 REV. 13, SEPTEMBER 2006 Table 12.2-40 FEEDWATER SYSTEM SHIELDING DESIGN SOURCE TERMS(1)
CARRYOVER COMPONENT(2)
Specific Specific Specific Activity Activity Activity Isotope(4)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Br-83 1.04x10-10 Cs-134 2.80x10-13 Ni-65 2.97x10-14 Br-84 1.81x10-10 Cs-136 1.92x10-13 Zn-65 2.00x10-16 Br-85 7.50x10-11 Cs-137 4.20x10-13 Zn-69m 2.99x10-15 I-131 9.10x10-11 Cs-138 3.18x10-10 Ag-110m 6.00x10-15 I-132 8.32x10-10 Ba-139 5.51x10-11 W-187 3.00x10-13 I-133 6.22x10-10 Ba-140 3.15x10-12 Ag-110 7.54x10-17 I-134 1.64x10-9 Ba-141 5.51x10-11 Zn-69 7.20x10-17 I-135 9.07x10-10 Ba-142 5.25x10-11 Pm-147 4.93x10-20 Sr-89 1.08x10-12 Ce-141 1.37x10-14 Pr-144 9.45x10-16 Sr-90 8.05x10-14 Ce-143 1.22x10-14 La-142 8.31x10-13 Sr-91 2.41x10-11 Ce-144 1.23x10-14 La-141 3.41x10-13 Sr-92 3.82x10-11 Pr-143 1.33x10-14 La-140 1.81x10-15 Zr-95 1.40x10-14 Nd-147 4.90x10-14 Te-129 1.79x10-16 Zr-97 1.12x10-14 Np-239 8.40x10-11 Rh-106 8.53x10-16 Nb-95 1.47x10-14 Na-24 2.00x10-13 Rh-103m 1.55x10-16 Mo-99 7.70x10-12 P-32 2.00x10-15 Nb-97m 7.80x10-15 Tc-99m 9.77x10-11 Cr-51 5.00x10-14 Nb-97 1.06x10-16 Tc-101 4.44x10-11 Mn-54 4.00x10-15 Nb-95m 7.19x10-20 Ru-103 6.65x10-15 Mn-56 4.96x10-12 Y-92 2.50x10-13 Ru-106 9.10x10-16 Co-58 5.00x10-13 Y-91 1.65x10-16 Te-129m 1.40x10-14 Co-60 5.00x10-14 Y-91m 3.87x10-13 Te-132 1.71x10-11 Fe-59 8.00x10-15 Y-90 3.10x10-17 Y-89m 1.08x10-16
LGS UFSAR CHAPTER 12 12.2-79 REV. 13, SEPTEMBER 2006 Table 12.2-40 (Cont'd)
FALLOUT COMPONENT(2)
Specific Specific Specific Activity Activity Activity Isotope(4)
(Ci/cc)
Isotope (Ci/cc)
Isotope (Ci/cc)
Ba-144 2.84x10-14 Cs-140 5.09x10-9 Y-93 1.43x10-13 La-144 1.79x10-12 Ba-140 1.62x10-13 Rb-92 1.31x10-14 Ce-144 1.38x10-17 La-140 5.80x10-17 Sr-92 1.59x10-11 Pr-144 6.17x10-19 Cs-139 1.91x10-9 Y-92 1.01x10-13 Ba-143 1.66x10-13 Ba-139 7.02x10-12 Rb-91 5.23x10-9 La-143 2.56x10-12 Cs-138 2.10x10-10 Sr-91 4.95x10-12 Ce-143 4.52x10-13 Cs-137 7.50x10-16 Y-91 2.08x10-17 Pr-143 3.20x10-17 Sr-95 1.47x10-12 Y-91m 4.91x10-14 Ba-142 2.75x10-11 Y-95 4.77x10-13 Rb-90 4.35x10-9 La-142 4.43x10-13 Zr-95 4.72x10-18 Sr-90 1.10x10-16 Cs-141 4.27x10-10 Sr-94 2.69x10-11 Y-90 2.36x10-20 Ba-141 6.41x10-11 Y-94 3.12x10-12 Rb-89 6.03x10-10 La-141 3.07x10-13 Rb-93 6.36x10-15 Sr-89 2.38x10-15 Ce-141 3.90x10-18 Sr-93 6.03x10-11 Y-89m 1.94x10-19 Rb-88 8.23x10-11 NOBLE GAS GENERATION COMPONENT(3)
Xe-135 4.67x10-9 Xe-133 9.78x10-10 Kr-85m 1.35x10-11 Xe-135m 7.02x10-8 Xe-131m 2.14x10-12 Kr-85 3.17x10-17 Xe-133m 5.59x10-11 Kr-83m 1.36x10-9 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Based on condensate activity, Table 12.2-38, with appropriate DFs applied:
2 for Cs and Rb, and 10 for others.
(3) Noble gases generated by particulate parents accumulating on filter/demineralizer resins.
(4) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-80 REV. 13, SEPTEMBER 2006 Table 12.2-41 SJAE CONDENSER SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
CS-144 1.23x10-3 Y-95 4.99x10-7 O-19 1.19 Ba-144 4.42x10-4 Zr-95 1.52x10-13 F-18 7.12x10-3 La-144 2.61x10-5 Nb-95m 1.70x10-18 Kr-83m 1.19x10-2 Ce-144 1.73x10-12 Rb-94 1.07x10-2 Kr-85m 2.14x10-2 Pr-144 2.04x10-15 Sr-94 9.44x10-4 Kr-85 7.00x10-5 Cs-143 2.91x10-3 Y-94 2.01x10-6 Kr-87 6.99x10-2 Ba-143 2.37x10-3 Rb-93 6.16x10-2 Kr-88 7.00x10-2 La-143 9.01x10-6 Sr-93 5.89x10-4 Kr-89 4.42x10-1 Ce-143 1.37x10-10 Y-93 3.58x10-8 Kr-90 8.37x10-1 Pr-143 1.19x10-14 Rb-92 2.98x10-1 Kr-91 6.79x10-1 Cs-142 3.50x10-2 Sr-92 1.30x10-4 Kr-92 2.05x10-1 Ba-142 4.37x10-4 Y-92 2.20x10-8 Kr-93 2.58x10-2 La-142 2.08x10-7 Rb-91 6.22x10-2 Kr-94 1.99x10-3 Cs-141 4.85x10-2 Sr-91 5.13x10-6 Kr-95 4.14x10-5 Ba-141 1.80x10-4 Y-91 9.08x10-13 Xe-131m 5.26x10-5 La-141 2.77x10-8 Y-91m 1.83x10-9 Xe-133m 1.02x10-3 Ce-141 7.75x10-14 Rb-90 2.66x10-2 Xe-133 2.87x10-2 Cs-140 6.77x10-2 Sr-90 8.17x10-11 Xe-135m 9.05x10-2 Ba-140 1.70x10-7 Y-90 6.82x10-16 Xe-135 7.70x10-2 La-140 7.58x10-12 Rb-89 2.51x10-3 Xe-137 5.14x10-1 Cs-139 8.38x10-3 Sr-89 1.45x10-9 Xe-138 3.10x10-1 Ba-139 4.48x10-6 Y-89m 1.46x10-14 Xe-139 8.68x10-1 Cs-138 8.35x10-4 Rb-88 3.40x10-4 Xe-140 7.58x10-1 Cs-137 2.86x10-9 Rb-87 2.40x10-19 Xe-141 3.97x10-2 Cs-135 4.23x10-15 N-13 1.24x10-2 Xe-142 8.04x10-3 Rb-95 5.86x10-4 N-16 3.44x10+1 Xe-143 2.37x10-4 Sr-95 1.15x10-4 N-17 1.02x10-2 Xe-144 1.10x10-3 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Main steam (activation and fission gases only) with 7.0 seconds decay accumulated for 1.0 second at rated flow.
(3) Assumes a 20% washout of N-16 in the main condensers.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-81 REV. 13, SEPTEMBER 2006 Table 12.2-42 MECHANICAL VACUUM PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(4)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 3.22x10-9 Cs-140 1.84x10-7 Sr-90 1.47x10-14 Br-84 5.74x10-9 Ba-140 1.57x10-11 Y-90 2.08x10-18 Br-85 2.47x10-9 La-140 3.94x10-15 Rb-89 5.20x10-8 I-131 2.87x10-9 Cs-139 9.96x10-8 Sr-89 4.67x10-13 I-132 2.63x10-8 Ba-139 9.96x10-10 Y-89m 3.17x10-17 I-133 1.96x10-8 Cs-138 2.04x10-8 Rb-88 8.44x10-9 I-134 5.18x10-8 Cs-137 6.36x10-14 Kr-83m 2.09x10-8 I-135 2.86x10-8 Sr-95 6.05x10-11 Kr-85m 3.77x10-8 Cs-135 1.09x10-19 Y-95 1.44x10-11 Kr-85 1.24x10-10 Cs-144 8.96x10-13 Zr-95 1.17x10-16 Kr-87 1.22x10-7 Ba-144 1.80x10-11 Rb-94 6.49x10-19 Kr-88 1.23x10-7 La-144 2.16x10-10 Sr-94 1.02x10-9 Kr-89 5.42x10-7 Ce-144 9.03x10-16 Y-94 9.27x10-11 Kr-90 1.76x10-7 Pr-144 2.95x10-17 Rb-93 4.72x10-13 Kr-91 9.19x10-10 Ba-143 1.50x10-11 Sr-93 2.15x10-9 Kr-92 2.38x10-17 La-143 8.23x10-11 Y-93 4.21x10-12 Xe-131m 9.31x10-11 Ce-143 4.36x10-14 Rb-92 1.72x10-12 Xe-133m 1.80x10-9 Pr-143 1.18x10-18 Sr-92 6.25x10-10 Xe-133 5.08x10-8 Ba-142 9.20x10-10 Y-92 3.31x10-12 Xe-135m 1.49x10-7 La-142 1.25x10-11 Rb-91 1.13x10-7 Xe-135 1.36x10-7 Cs-141 4.87x10-9 Sr-91 3.42x10-10 Se-137 6.74x10-7 Ba-141 2.12x10-9 Y-91 1.08x10-15 Xe-138 5.14x10-7 La-141 8.31x10-12 Y-91m 2.56x10-12 Xe-139 3.00x10-7 Ce-141 8.82x10-17 Rb-90 2.22x10-7 Xe-140 1.66x10-8 Xe-144 7.86x10-13 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-2.
(2) Assumes all fission gases and halogens in main steam at 100% reactor power.
(3) Assumes a transit time of 109 seconds from the RPV steam nozzles to the mechanical vacuum pump, at 3% reactor power.
(4) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-82 REV. 13, SEPTEMBER 2006 Table 12.2-43 OFFGAS PIPING SHIELDING DESIGN SOURCE TERMS (1)(2)(3)(4)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(5)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
N-13 3.99x10-7 Kr-89 1.45x10-5 Xe-135m 2.91x10-6 N-16 2.28x10-3 Kr-90 3.13x10-5 Xe-135 2.46x10-6 N-17 1.14x10-6 Kr-91 3.69x10-5 Xe-137 1.68x10-5 O-19 4.56x10-5 Kr-92 3.69x10-5 Xe-138 9.97x10-6 F-18 2.28x10-7 Kr-93 1.11x10-5 Xe-139 3.13x10-5 Kr-83m 3.81x10-7 Kr-94 2.58x10-6 Xe-140 3.36x10-5 Kr-85m 6.84x10-7 Kr-95 2.35x10-7 Xe-141 2.68x10-5 Kr-85 2.24x10-9 Xe-131m 1.68x10-9 Xe-142 8.15x10-6 Kr-87 2.24x10-6 Xe-133m 3.25x10-8 Xe-143 1.34x10-6 Kr-88 2.24x10-6 Xe-133 9.18x10-7 Xe-144 6.27x10-8 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Main steam (activation and fission gases only) with no decay (at RPV nozzles).
(3) Assumes a 20% washout of N-16 in the main condensers.
(4) Credit for decay is taken for shielding various segments of the offgas piping.
(5) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-83 REV. 13, SEPTEMBER 2006 Table 12.2-44 OFFGAS PREHEATER SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Cs-144 2.50x10-4 Zr-95 6.70x10-7 N-17 1.86x10-3 Ba-144 4.35x10-5 NB-95 6.67x10-7 0-19 3.49x10-1 La-144 2.54x10-5 NB-95m 1.34x10-8 F-18 2.17x10-3 Ce-144 1.84x10-5 Rb-94 2.09x10-4 Kr-83m 3.63x10-3 Pr-144 1.84x10-5 Sr-94 3.77x10-5 Kr-85M 6.52x10-3 Cs-143 2.72x10-5 Y-94 3.54x10-5 Kr-85 2.14x10-5 Ba-143 6.10x10-6 Rb-93 1.97x10-3 Kr-87 2.13x10-2 La-143 3.85x10-6 Sr-93 5.02x10-4 Kr-88 2.13x10-2 Ce-143 3.85x10-6 Y-93 4.99x10-4 Kr-89 1.34x10-1 Pr-143 3.85x10-6 Zr-93 3.41x10-10 Kr-90 2.46x10-1 Cs-142 9.81x10-4 Nb-93m 1.19x10-11 Kr-91 1.83x10-1 Ba-142 1.47x10-4 Rb-92 1.73x10-2 Kr-92 4.16x10-2 La-142 1.46x10-4 Sr-92 4.23x10-3 Kr-93 4.27x10-3 Cs-141 1.32x10-3 Y-92 4.23x10-3 Kr-94 2.52x10-4 Ba-141 7.42x10-4 Rb-91 1.96x10-2 Kr-95 3.68x10-6 La-141 7.42x10-4 Sr-91 1.56x10-2 Xe-131m 1.60x10-5 Ce-141 7.42x10-4 Y-91 1.55x10-2 Xe-133m 3.10x10-4 Cs-140 2.27x10-2 Y-91m 9.18x10-3 Xe-133 8.75x10-3 Ba-140 1.77x10-2 Rb-90 2.20x10-2 Xe-135m 2.76x10-2 La-140 1.77x10-2 Sr-90 7.21x10-4 Xe-135 2.35x10-2 Cs-139 2.13x10-2 Y-90 7.16x10-4 Xe-137 1.56x10-1 Ba-139 2.07x10-2 Rb-89 1.08x10-2 Xe-138 9.45x10-2 Cs-138 7.53x10-3 Sr-89 1.06x10-2 Xe-139 2.58x10-1 Cs-137 4.15x10-4 Y-89m 1.06x10-6 Xe-140 2.14x10-1 Cs-135 6.33x10-10 Rb-88 1.71x10-3 Xe-141 5.89x10-3 Rb-95 4.25x10-6 Rb-87 3.59x10-1 Xe-142 1.08x10-3 Sr-95 7.58x10-7 N-13 3.01x10-3 Xe-143 2.11x10-5 Y-95 6.72x10-7 N-16 8.86 Xe-144 2.93x10-4 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Main steam (activation and fission gases only) with 9.1 seconds decay accumulated for 0.305 seconds at rated flow (includes an 18 month buildup of 1% of the particulate daughters of gases).
(3)
Assumes a 20% washout of N-16 in the main condensers.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
Note: Since the short term activity reaches equilibrium within a few days after startup, extending the refueling cycle to 24 months does not contribute a significant amount to the total dose from the system.
LGS UFSAR CHAPTER 12 12.2-84 REV. 13, SEPTEMBER 2006 Table 12.2-45 OFFGAS RECOMBINER SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Cs-144 1.89x10-3 Y-95 7.36x10-5 N-16 1.81x10+1 Ba-144 3.15x10-3 Zr-95 7.34x10-5 N-17 3.65x10-3 La-144 3.22x10-3 Nb-95 7.31x10-5 O-19 7.44x10-1 Ce-144 2.36x10-3 Nb-95m 1.47x10-6 F-18 4.70x10-3 Pr-144 2.36x10-3 Rb-94 2.97x10-3 Kr-83m 7.85x10-3 Nd-144 6.10x10-19 Sr-94 4.02x10-3 Kr-85m 1.41x10-2 Cs-143 2.62x10-4 Y-94 4.03x10-3 Kr-85 4.62x10-5 Ba-143 4.13x10-4 Rb-93 5.06x10-2 Kr-87 4.62x10-2 La-143 4.22x10-4 Sr-93 5.88x10-2 Kr-88 4.62x10-2 Ce-143 4.22x10-4 Y-93 5.88x10-2 Kr-89 2.89x10-1 Pr-143 4.22x10-4 Zr-93 4.02x10-8 Kr-90 5.26x10-1 Cs-142 1.15x10-2 Nb-93m 1.40x10-9 Kr-91 3.80x10-1 Ba-142 1.67x10-2 Rb-92 4.45x10-1 Kr-92 7.86x10-2 La-142 1.67x10-2 Sr-92 5.15x10-1 Kr-93 7.56x10-3 Cs-141 8.29x10-2 Y-92 5.15x10-1 Kr-94 4.09x10-4 Ba-141 8.61x10-2 Rb-91 1.98 Kr-95 5.34x10-6 La-141 8.61x10-2 Sr-91 2.00 Xe-131m 3.47x10-5 Ce-141 8.61x10-2 Y-91 2.00 Xe-133m 6.70x10-4 Cs-140 2.27 Y-91m 1.18 Xe-133 1.89x10-2 Ba-140 2.30 Rb-90 2.58 Xe-135m 5.97x10-2 La-140 2.38 Sr-90 9.43x10-2 Xe-135 5.08x10-2 Cs-139 2.70 Y-90 9.37x10-2 Xe-137 3.37x10-1 Ba-139 2.71 Rb-89 1.40 Xe-138 2.04x10-1 Cs-138 9.83x10-1 Sr-89 1.40 Xe-139 5.52x10-1 Cs-137 5.46x10-2 Y-89m 1.40x10-4 Xe-140 4.52x10-1 Cs-135 8.34x10-8 Rb-88 2.22x10-1 Xe-141 1.01x10-2 Rb-95 5.00x10-5 Rb-87 4.74x10-12 Xe-142 1.79x10-3 Sr-95 7.33x10-5 N-13 6.51x10-3 Xe-143 3.06x10-5 Xe-144 6.07x10-4 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Main steam (activation and fission gases only) with 9.51 seconds decay accumulated for 0.66 seconds at rated flow (includes an 18 month buildup for all the particulate daughters of gases).
(3)
Assumes a 20% washout of N-16 in the main condensers.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
Note: Since the short term activity reaches equilibrium within a few days after startup, extending the refueling cycle to 24 months does not contribute a significant amount to the total dose from the system.
LGS UFSAR CHAPTER 12 12.2-85 REV. 13, SEPTEMBER 2006 Table 12.2-46 OFFGAS RECOMBINER CATALYST ELEMENT SHIELDING DESIGN SOURCE TERMS(1)
ACTIVITY ISOTOPE(2)
(Ci)
Ce-144 2.35x10-3 Pr-144 2.35x10-3 Nd-144 6.12x10-19 Ce-143 2.57x10-4 Pr-143 4.17x10-4 La-142 3.92x10-7 La-141 1.27x10-3 Ce-141 8.47x10-2 Ba-140 2.17 La-140 2.27 Ba-139 1.81x10-5 Cs-138 3.41x10-14 Cs-137 5.46x10-2 Cs-135 8.34x10-8 Zr-95 7.26x10-5 Nb-95 7.31x10-5 Nb-95m 1.47x10-6 Y-93 1.19x10-2 Zr-93 4.02x10-8 Nb-93m 1.41x10-9 Sr-92 1.11x10-3 Y-92 1.63x10-2 Sr-91 3.59x10-1 Y-91 1.98 Y-91m 2.32x10-1 Sr-90 9.43x10-2 Y-90 9.38x10-2 Sr-89 1.38 Y-89m 1.38x10-4 Rb-87 4.74x10-12 (1)
Particulate activity in recombiner (Table 12.2-45) with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-86 REV. 13, SEPTEMBER 2006 Table 12.2-47 OFFGAS AFTERCONDENSER SHIELDING DESIGN SOURCE TERMS (1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Cs-144 1.11x10-2 Y-95 7.88x10-8 N-17 3.00x10-2 Ba-144 8.63x10-3 Zr-95 1.25x10-13 O-19 2.92x10+1 La-144 2.38x10-3 Nb-95 2.71x10-19 F-18 2.93x10-1 Ce-144 8.91x10-10 Nb-95m 5.16x10-20 Kr-83m 4.89x10-1 Pr-144 5.69x10-12 Rb-94 1.05x10-3 Kr-85m 8.81x10-1 Cs-143 5.23x10-5 Sr-94 2.76x10-4 Kr-85 2.89x10-3 Ba-143 4.65x10-5 Y-94 2.94x10-6 Kr-87 2.88 La-143 9.44x10-7 Rb-93 2.91x10-2 Kr-88 2.88 Ce-143 7.98x10-11 Sr-93 1.23x10-3 Kr-89 1.68x10+1 Pr-143 4.87x10-16 Y-93 3.79x10-7 Kr-90 2.17x10+1 Cs-142 5.00x10-3 Zr-93 6.32x10-20 Kr-91 7.38 Ba-142 1.87x10-4 Rb-92 4.72x10-1 Kr-92 4.47x10-1 La-142 4.27x10-7 Sr-92 1.00x10-3 Kr-93 2.67x10-2 Cs-141 2.20x10-2 Y-92 8.76x10-7 Kr-94 9.22x10-4 Ba-141 3.25x10-4 Rb-91 1.85 Kr-95 7.59x10-6 La-141 2.31x10-7 Sr-91 6.35x10-4 Xe-131m 2.17x10-3 Ce-141 5.92x10-13 Y-91 4.22x10-10 Xe-133m 4.19x10-2 Cs-140 3.11 Y-91m 1.02x10-6 Xe-133 1.18 Ba-140 3.19x10-5 Rb-90 1.95 Xe-135m 3.67 La-140 1.75x10-9 Sr-90 2.32x10-8 Xe-135 3.18 Cs-139 6.94x10-1 Y-90 8.33x10-13 Xe-137 1.98x10+1 Ba-139 1.41x10-3 Rb-89 2.67x10-1 Xe-138 1.26x10+1 Cs-138 9.45x10-2 Sr-89 5.70x10-7 Xe-139 2.50x10+1 Cs-137 3.09x10-7 Y-89m 1.87x10-11 Xe-140 1.28x10+1 Cs-135 4.86x10-13 Rb-88 3.88x10-2 Xe-141 2.91x10-2 Rb-95 9.15x10-6 Rb-87 2.75x10-17 Xe-142 4.41x10-3 Sr-95 3.76x10-6 N-13 3.97x10-1 Xe-142 4.35x10-5 N-16 2.61x10+2 Xe-144 1.09x10-2 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Main steam (activation and fission gases only) with 10.45 seconds decay accumulated for 41.25 seconds at rated flow.
(3) Assumes a 20% washout of N-16 in the main condensers.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-87 REV. 13, SEPTEMBER 2006 Table 12.2-48 H2 ANALYZERS SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)(5)(7)
SPECIFIC ACTIVITY ISOTOPE(6)
(Ci/cc)
N-13 3.04x10-7 N-16 1.01x10-4 N-17 6.84x10-11 O-19 1.82x10-5 F-18 2.27x10-7 Kr-83m 3.80x10-7 Kr-85m 6.84x10-7 Kr-85 2.25x10-9 Kr-87 2.23x10-6 Kr-88 2.24x10-6 Kr-89 1.25x10-5 Kr-90 1.38x10-5 Kr-91 3.41x10-6 Kr-92 5.96x10-8 Kr-93 1.29x10-9 Kr-94 1.19x10-11 Kr-95 1.65x10-14 Xe-131m 1.69x10-9 Xe-133m 3.26x10-8 Xe-133 9.20x10-7 Xe-135m 2.83x10-6 Xe-135 2.47x10-6 Xe-137 1.48x10-5 Xe-138 9.72x10-6 Xe-139 1.65x10-5 Xe-140 7.04x10-6 Xe-141 8.19x10-10 Xe-142 7.63x10-11 Xe-143 9.47x10-14 Xe-144 4.84x10-9 Cs-144 4.84x10-9 Ba-144 4.84x10-9 La-144 4.84x10-9 Ce-144 4.84x10-9 Pr-144 4.84x10-9 Cs-143 9.47x10-14 Ba-143 9.47x10-14 La-143 9.47x10-14 Ce-143 9.47x10-14 Pr-143 9.47x10-14
LGS UFSAR CHAPTER 12 12.2-88 REV. 13, SEPTEMBER 2006 Table 12.2-48 (Cont'd)
SPECIFIC ACTIVITY ISOTOPE(6)
(Ci/cc)
Cs-142 7.63x10-11 Ba-142 7.63x10-11 La-142 7.63x10-11 Cs-141 8.17x10-10 Ba-141 8.17x10-10 La-141 8.17x10-10 Ce-141 8.17x10-10 Cs-140 7.04x10-6 Ba-140 7.04x10-6 La-140 7.04x10-6 Cs-139 1.65x10-5 Ba-139 1.65x10-5 Cs-138 9.72x10-6 Cs-137 8.96x10-6 Cs-135 2.28x10-11 Rb-95 1.65x10-14 Sr-95 1.65x10-14 Y-95 1.65x10-14 Zr-95 1.65x10-14 Nb-95 1.65x10-14 Nb-95m 3.31x10-16 Rb-94 1.19x10-11 Sr-94 1.19x10-11 Y-94 1.19x10-11 Rb-93 1.29x10-9 Sr-93 1.29x10-9 Y-93 1.29x10-9 Zr-93 2.39x10-14 Nb-93m 1.30x10-14 Rb-92 5.96x10-8 Sr-92 5.96x10-8 Y-92 5.96x10-8 Rb-91 3.41x10-6 Sr-91 3.41x10-6 Y-91 3.41x10-6 Y-91m 2.01x10-6 Rb-90 1.38x10-5 Sr-90 8.75x10-6 Y-90 8.75x10-6 Rb-89 1.25x10-5 Sr-89 1.25x10-5
LGS UFSAR CHAPTER 12 12.2-89 REV. 13, SEPTEMBER 2006 Table 12.2-48 (Cont'd)
SPECIFIC ACTIVITY ISOTOPE(6)
(Ci/cc)
Y-89m 1.25x10-9 Rb-88 2.24x10-6 Rb-87 1.29x10-15 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Assumes a 20% washout of N-16 in the main condensers.
(3)
Based on activity at outlet of offgas recombiner aftercondenser.
(4)
Assumes an 18.6 second holdup pipe between aftercondenser outlet and analyzer cells.
(5)
Assumes a flow rate of 0.3 scfm of offgas through the analyzer tubing (includes a 40 year buildup of particulate daughters of gases).
(6)
Isotopes with specific activities less than 1.0x10-20 are not listed.
(7)
Based on sum of radiation sources in analyzer cells.
LGS UFSAR CHAPTER 12 12.2-90 REV. 13, SEPTEMBER 2006 Table 12.2-49 TURBINE ENCLOSURE EQUIPMENT COMPARTMENT EXHAUST AIR FILTERS SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ISOTOPE(3)
(Ci)
I-131 2.12x10-2 I-133 8.89x10-3 Co-60 1.87x10-3 Co-58 1.64x10-4 Cr-51 1.43x10-3 Mn-54 4.07x10-4 Fe-59 8.97x10-5 Zn-65 1.25x10-4 Zr-95 8.87x10-5 Sr-89 4.34x10-3 Sr-90 6.91x10-5 Sb-124 2.47x10-4 Cs-134 8.91x10-4 Cs-136 9.47x10-6 Cs-137 2.08x10-3 Ba-140 1.95x10-3 Ce-141 2.70x10-4 La-140 1.95x10-3 Y-90 6.85x10-5 Y-89m 4.34x10-7 Nb-95 8.66x10-5 Nb-95m 1.77x10-6 (1)
Based on NUREG-0016, Revision 0, table 1-1 (Reference 12.2-1) release rates, with fission products adjusted to 0.35 Ci/sec offgas release rate at 30 minutes decay.
(2)
Assumes a one year accumulation of all these isotopes at 63,000 cfm.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-91 REV. 13, SEPTEMBER 2006 Table 12.2-50 SGTS AIR FILTERS SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ISOTOPE(3)
(Ci)
I-131 4.66x10-3 I-133 1.61x10-2 Co-60 7.97x10-5 Co-58 4.77x10-6 Cr-51 2.38x10-6 Mn-54 2.39x10-5 Fe-59 3.18x10-6 Zn-65 1.59x10-5 Zr-95 1.11x10-5 Sr-89 2.51x10-6 Sr-90 1.40x10-7 Sb-124 5.57x10-6 Cs-134 1.12x10-4 Cs-136 8.28x10-6 Cs-137 1.54x10-4 Ba-140 1.10x10-5 Ce-141 2.78x10-6 La-140 9.02x10-7 Y-90 7.79x10-9 Y-89m 2.51x10-10 Nb-95 4.50x10-8 Nb-95m 8.37x10-9 (1)
Assumes untreated airborne release rate from drywell during purging to be 7 times that from reactor enclosure during normal operation, from NUREG-0016, Revision 0, tables 1-1 and 2-11 (Reference 12.2-1).
(2)
Based on drywell purge for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> at 11,000 cfm.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-92 REV. 13, SEPTEMBER 2006 Table 12.2-51 EQUIPMENT DRAIN COLLECTION TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 1.94x10-1 Cs-137 1.14x10-2 Tc-99 2.11x10-8 Br-84 7.91x10-2 Cs-138 5.64x10-1 Nb-97m 1.11x10-3 Br-85 4.70x10-3 Ba-139 1.22 Nb-97 1.05x10-3 I-131 6.03x10-1 Ba-140 4.21x10-1 Nb-95m 1.75x10-6 I-132 3.12 Ba-141 2.82x10-1 Y-92 1.25 I-133 3.45 Ba-142 1.72x10-1 Y-91 6.85x10-3 I-134 1.15 Ce-141 3.60x10-3 Y-91m 1.20 I-135 3.47 Ce-143 1.47x10-3 Y-90 7.44x10-4 Sr-89 1.47x10-1 Ce-144 1.67x10-3 Y-89m 1.47x10-5 Sr-90 1.09x10-2 Pr-143 1.80x10-3 Zn-69 2.77x10-4 Sr-91 2.17 Nd-147 6.53x10-3 Cs-135 1.82x10-10 Sr-92 1.58 Np-239 1.06x10+1 Na-24 2.06x10-2 Zr-95 1.89x10-3 Pu-239 2.17x10-7 P-32 2.68x10-4 Zr-97 1.19x10-3 Re-187 4.12x10-16 Cr-51 6.73x10-3 Nb-95 1.99x10-3 Pm-147 1.23x10-6 Mn-54 5.42x10-4 Mo-99 9.79x10-1 Pr-144 1.61x10-3 Mn-56 1.96x10-1 Tc-99m 7.50 La-142 1.72x10-1 Fe-59 1.08x10-3 Tc-101 1.81x10-1 La-141 2.49x10-1 Co-58 6.76x10-2 Ru-103 8.97x10-4 La-140 4.20x10-2 Co-60 6.77x10-3 Ru-106 1.23x10-4 Te-129 1.05x10-3 Ni-65 1.17x10-3 Te-129m 1.89x10-3 I-129 4.64x10-14 Zn-65 2.71x10-5 Te-132 2.21 Ag-110 1.06x10-5 Zn-69m 3.03x10-4 Cs-134 7.59x10-3 Rh-106 1.23x10-4 Ag-110m 8.12x10-4 Cs-136 5.15x10-3 Rh-103m 7.81x10-4 W-187 3.42x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Equipment drains (17.9% of reactor water less gases) accumulated for 0.5157 days at 26.93 gpm.
(3) This activity is in 20,000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-93 REV. 13, SEPTEMBER 2006 Table 12.2-52 EQUIPMENT DRAIN SURGE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 2.00x10-1 Cs-137 3.41x10-2 Rh-103m 2.52x10-3 Br-84 7.91x10-2 Cs-138 5.64x10-1 Tc-99 1.13x10-7 Br-85 4.70x10-3 Ba-139 1.22 Nb-97m 2.18x10-3 I-131 1.73 Ba-140 1.23 Nb-97 2.29x10-3 I-132 7.00 Ba-141 2.82x10-1 Nb-95m 1.47x10-5 I-133 7.19 Ba-142 1.72x10-1 Y-92 1.64 I-134 1.15 Ce-141 1.32x10-2 Y-91 4.23x10-2 I-135 4.70 Ce-143 3.47x10-3 Y-91m 2.01 Sr-89 4.39x10-1 Ce-144 4.99x10-3 Y-90 6.11x10-3 Sr-90 3.27x10-2 Pr-143 5.35x10-3 Y-89m 4.38x10-5 Sr-91 3.44 Nd-147 1.90x10-2 Zn-69 5.45x10-4 Sr-92 1.65 Np-239 2.74x10+1 Cs-135 2.10x10-9 Zr-95 5.64x10-3 Pu-239 1.78x10-6 Na-24 3.88x10-2 Zr-97 2.35x10-3 Re-187 3.00x10-15 P-32 7.83x10-4 Nb-95 5.97x10-3 Pm-147 1.08x10-5 Cr-51 1.99x10-2 Mo-99 2.60 Sm-147 1.02x10-19 Mn-54 1.62x10-3 Tc-99m 1.10x10+1 Pr-144 4.93x10-3 Mn-56 2.03x10-1 Tc-101 1.81x10-1 La-142 1.72x10-1 Fe-59 3.21x10-3 Ru-103 2.67x10-3 La-141 2.82x10-1 Co-58 2.02x10-1 Ru-106 3.69x10-4 La-140 3.25x10-1 Co-60 2.03x10-2 Te-129m 5.60x10-3 Te-129 3.43x10-3 Ni-65 1.22x10-3 Te-132 5.95 I-129 4.60x10-13 Zn-65 8.11x10-5 Cs-134 2.27x10-2 Ag-110 3.16x10-5 Zn-69m 5.53x10-4 Cs-136 1.51x10-2 Rh-106 3.69x10-4 Ag-110m 2.43x10-3 W-187 7.47x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Equipment drains (17.9% of reactor water less gases) accumulated for 1.547 days at 26.93 gpm.
(3) This activity is in 60,000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-94 REV. 13, SEPTEMBER 2006 Table 12.2-53 EQUIPMENT DRAIN SAMPLE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 1.94x10-4 Cs-137 5.69x10-4 Tc-99 2.11x10-11 Br-84 7.91x10-5 Cs-138 2.82x10-2 Nb-97m 1.11x10-6 Br-85 4.70x10-6 Ba-139 1.22x10-3 Nb-97 1.05x10-6 I-131 6.03x10-4 Ba-140 4.21x10-4 Nb-95m 1.75x10-9 I-132 3.12x10-3 Ba-141 2.82x10-4 Y-92 1.25x10-3 I-133 3.45x10-3 Ba-142 1.72x10-4 Y-91 6.85x10-6 I-134 1.15x10-3 Ce-141 3.60x10-6 Y-91m 1.20x10-3 I-135 3.47x10-3 Ce-143 1.47x10-6 Y-90 7.44x10-7 Sr-89 1.47x10-4 Ce-144 1.67x10-6 Y-89m 1.47x10-8 Sr-90 1.09x10-5 Pr-143 1.80x10-6 Zn-69 2.77x10-7 Sr-91 2.17x10-3 Nd-147 6.53x10-6 Cs-135 9.10x10-12 Sr-92 1.58x10-3 Np-239 1.06x10-2 Na-24 2.06x10-5 Zr-95 1.89x10-6 Pu-239 2.17x10-10 P-32 2.68x10-7 Zr-97 1.19x10-6 Re-187 4.12x10-19 Cr-51 6.73x10-6 Nb-95 1.99x10-6 Pm-147 1.23x10-9 Mn-54 5.42x10-7 Mo-99 9.79x10-4 Pr-144 1.61x10-6 Mn-56 1.96x10-4 Tc-99m 7.50x10-3 La-142 1.72x10-4 Fe-59 1.08x10-6 Tc-101 1.81x10-4 La-141 2.49x10-4 Co-58 6.76x10-5 Ru-103 8.97x10-7 La-140 4.20x10-5 Co-60 6.77x10-6 Ru-106 1.23x10-7 Te-129 1.05x10-6 Ni-65 1.17x10-6 Te-129m 1.89x10-6 I-129 4.64x10-17 Zn-65 2.71x10-8 Te-132 2.21x10-3 Ag-110 1.06x10-8 Zn-69m 3.03x10-7 Cs-134 3.79x10-4 Rh-106 1.23x10-7 Ag-110m 8.12x10-7 Cs-136 2.57x10-4 Rh-103m 7.81x10-7 W-187 3.42x10-5 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Activity in equipment drain collection tank with DFs applied for filter and demineralizer (DF for Cs and Rb = (0.5)(0.1) = 0.05 and DF for others =
(0.1)(0.01) = 0.001).
(3) This activity is in 20,000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-95 REV. 13, SEPTEMBER 2006 Table 12.2-54 EQUIPMENT DRAIN FILTER SHIELDING DESIGN SOURCE TERMS(1)(2)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(3)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 2.00x10-1 Cs-137 2.41x10-2 Rh-103m 1.75x10-3 Br-84 7.91x10-2 Cs-138 5.64x10-1 Tc-99 6.85x10-8 Br-85 4.70x10-3 Ba-139 1.22 Nb-97m 1.83x10-3 I-131 1.24 Ba-140 8.76x10-1 Nb-97 1.89x10-3 I-132 5.38 Ba-141 2.82x10-1 Nb-95m 7.53x10-6 I-133 5.90 Ba-142 1.72x10-1 Y-92 1.61 I-134 1.15 Ce-141 8.88x10-3 Y-91 2.48x10-2 I-135 4.48 Ce-143 2.70x10-3 Y-91m 1.81 Sr-89 3.09x10-1 Ce-144 3.50x10-3 Y-90 3.16x10-3 Sr-90 2.31x10-2 Pr-143 3.79x10-3 Y-89m 3.08x10-5 Sr-91 3.12 Nd-147 1.36x10-3 Cs-135 1.05x10-9 Sr-92 1.65 Np-239 2.06x10+1 Na-24 3.32x10-2 Zr-95 3.99x10-3 Re-187 1.63x10-15 P-32 5.58x10-4 Zr-97 1.97x10-3 Ag-110 2.23x10-5 Cr-51 1.41x10-2 Nb-95 4.21x10-3 Zn-69 4.65x10-4 Mn-54 1.14x10-3 Mo-99 1.93 Pu-239 9.19x10-7 Mn-56 2.03x10-1 Tc-99m 1.01x10+1 Pm-147 5.42x10-7 Co-58 1.42x10-1 Tc-101 1.81x10-1 Pr-144 3.45x10-3 Co-60 1.43x10-2 Ru-103 1.89x10-3 La-142 1.72x10-1 Fe-59 2.27x10-3 Ru-106 2.60x10-4 La-141 2.79x10-1 Ni-65 1.21x10-3 Te-129m 3.97x10-3 La-140 1.72x10-1 Zn-65 5.72x10-5 Te-132 4.38 Te-129 2.38x10-3 Zn-69m 4.78x10-4 Cs-134 1.60x10-2 I-129 2.24x10-13 Ag-110m 1.72x10-3 Cs-136 1.07x10-2 Rh-106 2.60x10-4 W-187 6.02x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Equipment drains (17.9% of reactor water less gases) accumulated for 1.09 days at 26.93 gpm.
(3) Isotopes with activities less than 1.0x10-20 are not listed.
(4) For shielding design of associated piping, backwash volume to waste sludge tank is 1925 gallons.
LGS UFSAR CHAPTER 12 12.2-96 REV. 13, SEPTEMBER 2006 Table 12.2-55 EQUIPMENT DRAIN DEMINERALIZER AND SPENT RESIN TANK SHIELDING DESIGN SOURCE TERMS (1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 2.00x10-2 Cs-138 2.82x10-1 Ag-110 1.18x10-4 Br-84 7.91x10-3 Ba-139 1.22x10-1 Rh-106 1.41x10-3 Br-85 4.70x10-4 Ba-140 1.48 Rh-103m 6.50x10-3 I-131 1.38 Ba-141 2.82x10-2 Tc-99 9.45x10-7 I-132 2.26 Ba-142 1.72x10-2 Nb-97m 2.80x10-4 I-133 1.00 Ce-141 3.32x10-2 Nb-97 3.01x10-4 I-134 1.15x10-1 Ce-143 6.41x10-4 Nb-95m 3.15x10-4 I-135 4.80x10-1 Ce-144 1.88x10-2 Y-92 1.65x10-1 Sr-89 1.22 Pr-143 7.18x10-3 Y-91 1.92x10-1 Sr-90 1.32x10-1 Nd-147 2.01x10-2 Y-91m 2.18x10-1 Sr-91 3.70x10-1 Np-239 7.47 Y-90 1.25x10-1 Sr-92 1.65x10-1 Pu-239 3.44x10-5 Y-89m 1.22x10-4 Zr-95 1.68x10-2 U-235 2.74x10-15 Zn-69 6.54x10-5 Zr-97 3.01x10-4 Th-231 2.60x10-15 Cs-135 9.37x10-8 Nb-95 2.17x10-2 Pa-231 1.07x10-19 Na-24 4.73x10-3 Mo-99 8.11x10-1 Re-187 3.06x10-14 P-32 1.03x10-3 Tc-99m 1.64 Pm-147 6.86x10-4 Cr-51 4.16x10-2 Tc-101 1.81x10-2 Sm-147 3.22x10-16 Mn-54 6.13x10-3 Ru-103 6.64x10-3 Pr-144 1.88x10-2 Mn-56 2.03x10-2 Ru-106 1.41x10-3 Nd-144 4.76x10-19 Fe-59 8.49x10-3 Te-129m 1.30x10-2 La-142 1.72x10-2 Cu-58 6.16x10-1 Te-132 2.11 La-141 2.82x10-2 Cu-60 8.13x10-2 Cs-134 4.47x10-1 La-140 1.47 Ni-65 1.22x10-4 Cs-136 9.58x10-2 Te-129 8.33x10-3 Zn-65 3.01x10-4 Cs-137 6.89x10-1 I-129 5.49x10-11 Zn-69m 6.54x10-5 Ag-110m 9.07x10-3 W-187 1.13x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Filtered equipment drains (DF of 2 for Cs and Rb and DF of 10 for others) accumulated for 62.6 days at 26.93 gpm.
(3) This activity is in 85 ft3 of spent resin.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) The equipment drain spent resin tank will not be used for initial plant operation (Section 11.4.2.1.1).
LGS UFSAR CHAPTER 12 12.2-97 REV. 13, SEPTEMBER 2006 Table 12.2-56 EQUIPMENT DRAIN SPENT RESIN TANK PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
I-131 7.90x10-3 Ce-141 9.27x10-3 Te-129 2.47x10-3 I-132 5.75x10-6 Ce-143 4.72x10-17 I-129 1.05x10-10 Sr-89 5.55x10-1 Ce-144 1.62x10-2 Ag-110 1.00x10-4 Sr-90 1.32x10-1 Pr-143 3.40x10-4 Rh-106 1.26x10-3 Zr-95 8.92x10-3 Nd-147 4.69x10-4 Rh-103m 2.27x10-3 Nb-95 1.48x10-2 Np-239 1.50x10-7 Tc-99 9.80x10-7 Mo-99 2.58x10-7 Pu-239 3.64x10-5 Nb-95m 1.89x10-4 Tc-99m 2.47x10-7 U-235 8.56x10-15 Y-91 9.58x10-2 Ru-103 2.32x10-3 Th-231 8.41x10-15 Y-90 1.32x10-1 Ru-106 1.26x10-3 Pa-231 1.27x10-19 Y-89m 5.55x10-5 Te-129m 3.85x10-3 Re-187 3.13x10-14 Cs-135 9.51x10-8 Te-132 5.58x10-6 Pm-147 8.77x10-4 P-32 5.61x10-5 Cs-134 4.23x10-1 Sm-147 1.23x10-15 Cr-51 9.33x10-3 Cs-136 4.60x10-3 Pr-144 1.62x10-2 Mn-54 5.34x10-3 Cs-137 6.87x10-1 Nd-144 1.30x10-18 Fe-59 3.41x10-3 Ba-140 5.74x10-2 La-140 6.60x10-2 Co-58 3.44x10-1 Co-60 7.96x10-2 Zn-65 2.54x10-4 Ag-110m 7.71x10-3 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Equipment drain spent resin with 60 days decay.
(3) This activity is in a 1500 gallon slurry.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) The equipment drain spent resin tank and pump will not be used for initial plant operation (Section 11.4.2.1.1).
LGS UFSAR CHAPTER 12 12.2-98 REV. 13, SEPTEMBER 2006 Table 12.2-57 FLOOR DRAIN COLLECTION TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 4.28x10-2 Cs-138 1.21x10-1 Tc-99 2.57x10-8 Br-84 1.69x10-2 Ba-139 2.62x10-1 Nb-97m 4.76x10-4 Br-85 1.01x10-3 Ba-140 2.74x10-1 Nb-97 5.01x10-4 I-131 3.86x10-1 Ba-141 6.04x10-2 Nb-95m 3.43x10-6 I-132 1.55 Ba-142 3.69x10-2 Y-92 3.52x10-1 I-133 1.57 Ce-141 2.96x10-3 Y-91 9.66x10-3 I-134 2.46x10-1 Ce-143 7.65x10-4 Y-91m 4.35x10-1 I-135 1.01 Ce-144 1.12x10-3 Y-90 1.42x10-3 Sr-89 9.81x10-2 Pr-143 1.20x10-3 Y-89m 9.81x10-6 Sr-90 7.32x10-3 Nd-147 4.24x10-3 Zn-69 1.19x10-4 Sr-91 7.43x10-1 Np-239 6.07 Cs-135 4.88x10-10 Sr-92 3.53x10-1 Pu-239 4.12x10-7 Na-24 8.44x10-3 Zr-95 1.26x10-3 Re-187 6.92x10-16 P-32 1.75x10-4 Zr-97 5.12x10-4 Pm-147 2.52x10-6 Cr-51 4.46x10-3 Nb-95 1.34x10-3 Sm-147 2.48x10-20 Mn-54 3.63x10-4 Mo-99 5.76x10-1 Pr-144 1.10x10-3 Mn-56 4.36x10-2 Tc-99m 2.38 La-142 3.69x10-2 Fe-59 7.19x10-4 Tc-101 3.87x10-2 La-141 6.03x10-2 Co-58 4.51x10-2 Ru-103 5.96x10-4 La-140 7.52x10-2 Co-60 4.55x10-3 Ru-106 8.26x10-5 Te-129 7.68x10-4 Ni-65 2.60x10-4 Te-129m 1.25x10-3 I-129 1.08x10-13 Zn-65 1.81x10-5 Te-132 1.32 Ag-110 7.08x10-6 Zn-69m 1.20x10-4 Cs-134 5.09x10-3 Rh-106 8.26x10-5 Ag-110m 5.44x10-4 Cs-136 3.36x10-3 Rh-103m 5.64x10-4 W-187 1.64x10-2 Cs-137 7.64x10-3 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drains (14.3% of reactor water less gases) accumulated for 1.616 days at 7.22 gpm.
(3) This activity is in 16,800 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-99 REV. 13, SEPTEMBER 2006 Table 12.2-58 FLOOR DRAIN SURGE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 4.28x10-2 Cs-137 2.73x10-2 Rh-103m 1.99x10-3 Br-84 1.69x10-2 Cs-138 1.21x10-1 Tc-99 1.36x10-7 Br-85 1.01x10-3 Ba-139 2.62x10-1 Nb-97m 5.97x10-4 I-131 1.16 Ba-140 8.78x10-1 Nb-97 6.42x10-4 I-132 3.49 Ba-141 6.04x10-2 Nb-95m 3.42x10-5 I-133 2.12 Ba-142 3.69x10-2 Y-92 3.53x10-1 I-134 2.46x10-1 Ce-141 1.09x10-2 Y-91 4.67x10-2 I-135 1.03 Ce-143 1.30x10-3 Y-91m 4.67x10-1 Sr-89 3.41x10-1 Ce-144 3.97x10-3 Y-90 1.31x10-2 Sr-90 2.61x10-2 Pr-143 3.98x10-3 Y-89m 3.41x10-5 Sr-91 7.92x10-1 Nd-147 1.33x10-2 Zn-69 1.40x10-4 Sr-92 3.53x10-1 Np-239 1.31x10+1 Cs-135 3.13x10-9 Zr-95 4.41x10-3 Pu-239 3.74x10-6 Na-24 1.01x10-2 Zr-97 6.42x10-4 Re-187 4.67x10-15 P-32 5.66x10-4 Nb-95 4.75x10-3 Pm-147 2.95x10-5 Cr-51 1.51x10-2 Mo-99 1.33 Sm-147 1.06x10-18 Mn-54 1.29x10-3 Tc-99m 3.12 Pr-144 3.95x10-3 Mn-56 4.36x10-2 Tc-101 3.87x10-2 La-142 3.69x10-2 Fe-59 2.49x10-3 Ru-103 2.05x10-3 La-141 6.04x10-2 Co-58 1.58x10-1 Ru-106 2.94x10-4 La-140 5.63x10-1 Co-60 1.62x10-2 Te-129m 4.29x10-3 Te-129 2.71x10-3 Ni-65 2.60x10-4 Te-132 3.21 I-129 1.39x10-12 Zn-65 6.44x10-5 Cs-134 1.81x10-2 Ag-110 2.51x10-5 Zn-69m 1.40x10-4 Cs-136 1.08x10-2 Rh-106 2.94x10-4 Ag-110m 1.93x10-3 W-187 2.38x10-2 (1) Based upon shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drains (14.3% of reactor water less gases) accumulated for 5.769 days at 7.22 gpm.
(3) This activity is in 60,000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-100 REV. 13, SEPTEMBER 2006 Table 12.2-59 FLOOR DRAIN SAMPLE TANK NO. 1 SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 4.28x10-3 Cs-137 3.82x10-3 Tc-99 2.57x10-9 Br-84 1.69x10-3 Cs-138 6.04x10-2 Nb-97m 4.76x10-5 Br-85 1.01x10-4 Ba-139 2.62x10-2 Nb-97 5.01x10-5 I-131 3.86x10-2 Ba-140 2.74x10-2 Nb-95m 3.43x10-7 I-132 1.55x10-1 Ba-141 6.04x10-3 Y-92 3.52x10-2 I-133 1.57x10-1 Ba-142 3.69x10-3 Y-91 9.66x10-4 I-134 2.46x10-2 Ce-141 2.96x10-4 Y-91m 4.35x10-2 I-135 1.01x10-1 Ce-143 7.65x10-5 Y-90 1.42x10-4 Sr-89 9.81x10-3 Ce-144 1.12x10-4 Y-89m 9.81x10-7 Sr-90 7.32x10-4 Pr-143 1.20x10-4 Zn-69 1.19x10-5 Sr-91 7.43x10-2 Nd-147 4.24x10-4 Cs-135 2.44x10-10 Sr-92 3.53x10-2 Np-239 6.07x10-1 Na-24 8.44x10-4 Zr-95 1.26x10-4 Pu-239 4.12x10-8 P-32 1.75x10-5 Zr-97 5.12x10-5 Re-187 6.92x10-17 Cr-51 4.46x10-4 Nb-95 1.34x10-4 Pm-147 2.52x10-7 Mn-54 3.63x10-5 Mo-99 5.76x10-2 Pr-144 1.10x10-4 Mn-56 4.36x10-3 Tc-99m 2.38x10-1 La-142 3.69x10-3 Fe-59 7.19x10-5 Tc-101 3.87x10-3 La-141 6.03x10-3 Co-58 4.51x10-3 Ru-103 5.96x10-5 La-140 7.52x10-3 Co-60 4.55x10-4 Ru-106 8.26x10-6 Te-129 7.68x10-5 Ni-65 2.60x10-5 Te-129m 1.25x10-4 I-129 1.08x10-14 Zn-65 1.81x10-6 Te-132 1.32x10-1 Ag-110 7.08x10-7 Zn-69m 1.20x10-5 Cs-134 2.54x10-3 Rh-106 8.26x10-6 Ag-110m 5.44x10-5 Cs-136 1.68x10-3 Rh-103m 5.64x10-5 W-187 1.64x10-3 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drain collection tank activity with DFs applied for the filter (DF = 2 for Cs and Rb, DF = 10.0 for other isotopes).
(3) This activity is in 16,800 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-101 REV. 13, SEPTEMBER 2006 Table 12.2-60 FLOOR DRAIN SAMPLE TANK NO. 2 SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 4.28x10-5 Cs-137 3.82x10-4 Tc-99 2.57x10-11 Br-84 1.69x10-5 Cs-138 6.04x10-3 Nb-97m 4.76x10-7 Br-85 1.01x10-6 Ba-139 2.62x10-4 Nb-97 5.01x10-7 I-131 3.86x10-4 Ba-140 2.74x10-4 Nb-95m 3.43x10-9 I-132 1.55x10-3 Ba-141 6.04x10-5 Y-92 3.52x10-4 I-133 1.57x10-3 Ba-142 3.69x10-5 Y-91 9.66x10-6 I-134 2.46x10-4 Ce-141 2.96x10-6 Y-91m 4.35x10-4 I-135 1.01x10-3 Ce-143 7.65x10-7 Y-90 1.42x10-6 Sr-89 9.81x10-5 Ce-144 1.12x10-6 Y-89m 9.81x10-9 Sr-90 7.32x10-6 Pr-143 1.20x10-6 Zn-69 1.19x10-7 Sr-91 7.43x10-4 Nd-147 4.24x10-6 Cs-135 2.44x10-11 Sr-92 3.53x10-4 Np-239 6.07x10-3 Na-24 8.44x10-6 Zr-95 1.26x10-6 Pu-239 4.12x10-10 P-32 1.75x10-7 Zr-97 5.12x10-7 Re-187 6.92x10-19 Cr-51 4.46x10-6 Nb-95 1.34x10-7 Pm-147 2.52x10-9 Mn-54 3.63x10-7 Mo-99 5.76x10-4 Pr-144 1.10x10-6 Mn-56 4.36x10-5 Tc-99m 2.38x10-3 La-142 3.69x10-5 Fe-59 7.19x10-7 Tc-101 3.87x10-5 La-141 6.03x10-5 Co-58 4.51x10-5 Ru-103 5.96x10-7 La-140 7.52x10-5 Co-60 4.55x10-6 Ru-106 8.26x10-8 Te-129 7.68x10-7 Ni-65 2.60x10-7 Te-129m 1.25x10-6 I-129 1.08x10-16 Zn-65 1.81x10-8 Te-132 1.32x10-3 Ag-110 7.08x10-9 Zn-69m 1.20x10-7 Cs-134 2.54x10-4 Rh-106 8.26x10-8 Ag-110m 5.44x10-7 Cs-136 1.68x10-4 Rh-103m 5.64x10-7 W-187 1.64x10-5 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drain sample tank No. 1 activity with DFs applied for the demineralizer (DF=10 for Cs and Rb, DF=100 for others).
(3) This activity is in 16,800 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-102 REV. 13, SEPTEMBER 2006 Table 12.2-61 FLOOR DRAIN FILTER SHIELDING DESIGN SOURCE TERMS(1)(2)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(3)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 4.27x10-2 Cs-137 4.35x10-3 Rh-103m 3.14x10-4 Br-84 1.69x10-2 Cs-138 1.21x10-1 Tc-99 1.14x10-8 Br-85 1.01x10-3 Ba-139 2.62x10-1 Nb-97m, 3.55x10-4 I-131 2.26x10-1 Ba-140 1.59x10-1 Nb-97 3.62x10-4 I-132 1.02 Ba-141 6.04x10-2 Nb-95m 1.16x10-6 I-133 1.13 Ba-142 3.69x10-2 Y-92 3.37x10-1 I-134 2.46x10-1 Cs-141 1.56x10-3 Y-91 4.04x10-3 I-135 9.24x10-1 Ce-143 5.07x10-4 Y-91m 3.61x10-1 Sr-89 5.58x10-2 Ce-144 6.33x10-4 Y-90 4.89x10-4 Sr-90 4.17x10-3 Pr-143 6.85x10-4 Y-89m 5.58x10-6 Sr-91 6.28x10-1 Nd-147 2.47x10-4 Cs-135 1.55x10-10 Sr-92 3.52x10-1 Np-239 3.81 Na-24 6.48x10-3 Zr-95 7.21x10-4 Re-187 2.58x10-16 P-32 1.01x10-4 Zr-97 3.82x10-4 Ag-110 4.03x10-6 Cr-51 2.56x10-3 Nb-95 7.61x10-4 Zn-69 9.04x10-5 Mn-54 2.07x10-4 Mo-99 3.56x10-1 Pu-239 1.43x10-7 Mn-56 4.35x10-2 Tc-99m 2.05 Pm-147 8.29x10-8 Co-58 2.58x10-2 Tc-101 3.87x10-2 Pr-144 6.22x10-4 Co-60 2.59x10-3 Ru-103 3.42x10-4 La-142 3.69x10-2 Fe-59 4.11x10-4 Ru-106 4.71x10-5 La-141 5.91x10-2 Ni-65 2.60x10-4 Te-129m 7.18x10-4 La-140 2.70x10-2 Zn-65 1.03x10-5 Te-132 8.06x10-1 Te-129 4.25x10-4 Zn-69m 9.39x10-5 Cs-134 2.90x10-3 I-129 3.37x10-14 Ag-110m 3.10x10-4 Cs-136 1.95x10-3 Rh-106 4.70x10-5 W-187 1.15x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drains (14.3% of reactor water less gases) accumulated for 0.92 days at 7.22 gpm.
(3) Isotopes with activities less than 1.0x10-20 are not listed.
(4) For shielding design of associated piping, backwash volume to waste sludge tank is 1925 gallons.
LGS UFSAR CHAPTER 12 12.2-103 REV. 13, SEPTEMBER 2006 Table 12.2-62 FLOOR DRAIN DEMINERALIZER AND SPENT RESIN TANK SHIELDING DESIGN SOURCE TERMS (1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPES (Ci)
ISOTOPE (Ci)
Br-83 4.28x10-3 Cs-138 6.04x10-2 Rh-103m 7.10x10-4 Br-84 1.69x10-3 Ba-139 2.62x10-2 Tc-99 7.21x10-8 Br-85 1.01x10-4 Ba-140 2.37x10-1 Nb-97m 5.99x10-5 I-131 2.59x10-1 Ba-141 6.04x10-3 Nb-97 6.44x10-5 I-132 4.81x10-1 Ba-142 3.69x10-3 Nb-95m 2.61x10-5 I-133 2.14x10-1 Ce-141 3.81x10-3 Y-92 3.53x10-2 I-134 2.46x10-2 Ce-143 1.37x10-4 Y-91 1.89x10-2 I-135 1.03x10-1 Ce-144 1.59x10-3 Y-91m 4.67x10-2 Sr-89 1.25x10-1 Pr-143 1.12x10-3 Y-90 9.10x10-3 Sr-90 1.07x10-2 Nd-147 3.40x10-3 Y-89m 1.25x10-5 Sr-91 7.92x10-2 Np-239 1.60 Zn-69 1.40x10-5 Sr-92 3.53x10-2 Pu-239 2.53x10-6 Cs-135 1.48x10-9 Zr-95 1.65x10-3 U-235 7.06x10-17 Na-24 1.01x10-3 Zr-97 6.44x10-5 Th-231 6.10x10-17 P-32 1.58x10-4 Nb-95 1.91x10-3 Re-187 2.38x10-15 Cr-51 5.04x10-3 Mo-99 1.73x10-1 Pm-147 3.60x10-5 Mn-54 5.19x10-4 Tc-99m 3.51x10-1 Sm-147 5.72x10-18 Mn-56 4.36x10-3 Tc-101 3.87x10-3 Pr-144 1.59x10-3 Fe-59 8.96x10-4 Ru-103 7.26x10-4 La-142 3.69x10-3 Co-58 5.96x10-2 Ru-106 1.19x10-4 La-141 6.04x10-3 Co-60 6.64x10-3 Te-129m 1.48x10-3 La-140 2.23x10-1 Ni-65 2.60x10-5 Te-132 4.49x10-1 Te-129 9.46x10-4 Zn-65 2.58x10-5 Cs-134 3.69x10-2 I-129 2.11x10-12 Zn-69m 1.40x10-5 Cs-136 1.50x10-2 Ag-110 1.01x10-5 Ag-110m 7.75x10-4 Cs-137 5.60x10-2 Rh-106 1.19x10-4 W-187 2.43x10-3 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Filtered floor drains (DF of 2 for Cs and Rb and DF of 10 for others) accumulated for 23.7 days at 7.22 gpm.
(3) This activity is in 85 ft3 of spent resin.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) The floor drain spent resin tank will not be used for initial plant operation (Section 11.4.2.1.1).
LGS UFSAR CHAPTER 12 12.2-104 REV. 13, SEPTEMBER 2006 Table 12.2-63 FLOOR DRAIN SPENT RESIN TANK PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
I-131 4.03x10-2 Ce-143 2.57x10-9 Nb-97m 3.98x10-14 I-132 4.54x10-3 Ce-144 1.51x10-3 Nb-97 4.60x10-14 I-133 4.42x10-9 Pr-143 3.78x10-4 Nb-95m 2.77x10-5 Sr-89 9.40x10-2 Nd-147 8.79x10-4 Y-91 1.51x10-2 Sr-90 1.07x10-2 Np-239 2.71x10-3 Y-91m 3.75x10-18 Sr-91 5.81x10-18 Pu-239 2.95x10-6 Y-90 1.07x10-2 Zr-95 1.31x10-3 U-235 2.37x10-16 Y-89m 9.40x10-6 Zr-97 4.27x10-14 Th-231 2.25x10-16 Zn-69 7.44x10-17 Nb-95 1.75x10-3 Re-187 2.54x10-15 Cs-135 1.54x10-9 Mo-99 7.94x10-4 Pm-147 6.43x10-5 Na-24 3.77x10-14 Tc-99m 7.59x10-4 Sm-147 2.66x10-17 P-32 5.56x10-5 Ru-103 4.97x10-4 Pr-144 1.51x10-3 Cr-51 2.94x10-3 Ru-106 1.14x10-4 Nd-144 4.16x10-20 Mn-54 4.94x10-4 Te-129m 9.55x10-4 La-140 8.46x10-2 Fe-59 6.45x10-4 Te-132 4.41x10-3 Te-129 6.12x10-4 Co-58 4.83x10-2 Cs-134 3.62x10-2 I-129 5.01x10-12 Co-60 6.59x10-3 Cs-136 5.02x10-3 Ag-110 9.50x10-6 Zn-65 2.43x10-5 Cs-137 5.59x10-2 Rh-106 1.14x10-4 Zn-69m 6.93x10-17 Ba-140 7.35x10-2 Rh-103m 4.87x10-4 Ag-110m 7.31x10-4 Ce-141 2.42x10-3 Tc-99 7.94x10-8 W-187 7.19x10-10 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Floor drain spent resin with 21.6 days decay.
(3) This activity is in a 1500 gallon slurry.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) The floor drain spent resin tank and pump will not be used for initial plant operation (Section 11.4.2.1.1).
LGS UFSAR CHAPTER 12 12.2-105 REV. 13, SEPTEMBER 2006 Table 12.2-64 CHEMICAL WASTE TANK AND EVAPORATOR FEED TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 6.91x10-4 Cs-138 1.95x10-3 Tc-99 1.83x10-9 Br-84 2.73x10-4 Ba-139 4.22x10-3 Nb-97m 9.59x10-6 Br-85 1.62x10-5 Ba-140 1.25x10-2 Nb-97 1.03x10-5 I-131 1.68x10-2 Ba-141 9.75x10-4 Nb-95m 4.33x10-7 I-132 5.24x10-2 Ba-142 5.96x10-4 Y-92 5.70x10-3 I-133 3.40x10-2 Ce-141 1.53x10-4 Y-91 6.44x10-4 I-134 3.97x10-3 Ce-143 2.04x10-5 Y-91m 7.54x10-3 I-135 1.66x10-2 Ce-144 5.55x10-5 Y-90 1.68x10-4 Sr-89 4.79x10-3 Pr-143 5.66x10-5 Y-89m 4.79x10-7 Sr-90 3.65x10-4 Nd-147 1.91x10-4 Zn-69 2.25x10-6 Sr-91 1.28x10-2 Np-239 1.99x10-1 Cs-135 4.25x10-11 Sr-92 5.70x10-3 Pu-239 4.80x10-8 Na-24 1.63x10-4 Zr-95 6.19x10-5 Re-187 6.23x10-17 P-32 8.06x10-6 Zr-97 1.03x10-5 Pm-147 3.64x10-7 Cr-51 2.13x10-4 Nb-95 6.65x10-5 Sm-147 1.12x10-20 Mn-54 1.81x10-5 Mo-99 2.00x10-2 Pr-144 5.53x10-5 Mn-56 7.03x10-4 Tc-99m 4.90x10-2 La-142 5.96x10-4 Fe-59 3.50x10-5 Tc-101 6.24x10-4 La-141 9.75x10-4 Co-58 2.22x10-3 Ru-103 2.89x10-5 La-140 7.46x10-3 Co-60 2.27x10-4 Ru-106 4.11x10-6 Te-129 3.82x10-5 Ni-65 4.20x10-6 Te-129m 6.04x10-5 I-129 1.69x10-14 Zn-65 9.02x10-7 Te-132 4.79x10-2 Ag-110 3.52x10-7 Zn-69m 2.25x10-6 Cs-134 2.54x10-4 Rh-106 4.11x10-6 Ag-110m 2.71x10-5 Cs-136 1.54x10-4 Rh-103m 2.80x10-5 W-187 3.79x10-4 Cs-137 3.81x10-4 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Chemical wastes (2% of reactor water less gases) accumulated for 5.0 days at 0.833 gpm.
(3) This activity is in 6000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) Installation of the abandoned evaporator feed tank was not completed for plant operation (Section 11.2.2.1.3).
LGS UFSAR CHAPTER 12 12.2-106 REV. 13, SEPTEMBER 2006 Table 12.2-65 RADWASTE EVAPORATOR SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE
((Ci)
Br-83 7.04x10-13 Ce-143 4.87x10-6 Nb-97 5.95x10-7 I-131 3.71x10-2 Ce-144 9.06x10-4 Nb-95m 1.45x10-5 I-132 3.94x10-2 Pr-143 2.22x10-4 Y-92 1.76x10-8 I-133 2.96x10-3 Nd-147 5.87x10-5 Y-91 8.18x10-3 I-135 9.46x10-6 Np-239 1.06x10-1 Y-91m 4.73x10-5 Sr-89 5.04x10-2 Re-187 1.58x10-15 Y-90 6.56x10-3 Sr-90 6.67x10-3 Ag-110 5.70x10-6 Y-89m 5.04x10-6 Sr-91 7.32x10-5 Zn-69 6.53x10-8 Cs-135 9.62x10-10 Sr-92 5.75x10-11 Pu-239 1.81x10-6 Na-24 5.82x10-6 Zr-95 7.22x10-4 U-235 2.24x10-16 P-32 3.20x10-5 Zr-97 5.52x10-7 Th-231 2.16x10-16 Cr-51 1.52x10-3 Nb-95 9.95x10-4 Pm-147 3.92x10-6 Mn-54 2.98x10-4 Mo-99 1.33x10-2 Sm-147 2.93x10-18 Mn-56 2.72x10-12 Tc-99m 1.27x10-2 Pr-144 9.06x10-4 Co-58 2.67x10-2 Ru-103 2.61x10-4 Nd-144 3.64x10-20 Co-60 4.09x10-3 Ru-106 6.91x10-5 La-142 5.95x10-18 Fe-59 3.43x10-4 Te-129m 4.97x10-4 La-141 2.66x10-9 Ni-65 1.49x10-14 Te-132 3.83x10-2 La-140 4.90x10-2 Zn-65 1.45x10-5 Cs-134 4.45x10-3 Te-129 3.19x10-4 Zn-69m 6.08x10-8 Cs-136 5.88x10-4 I-129 3.66x10-12 Ag-110m 4.38x10-4 Cs-137 6.96x10-3 Rh-106 6.91x10-5 W-187 4.85x10-5 Ba-139 8.76x10-19 Rh-103m 2.56x10-4 Ba-140 4.46x10-2 Tc-99 4.90x10-8 Ce-141 1.26x10-3 Nb-97m 5.14x10-7 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Chemical wastes (2% of reactor water less gases) accumulated for 91.575 days at 0.833 gpm, with 3 days decay.
(3) This activity is in 1100 gallons of concentrate.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) Installation of the abandoned radwaste evaporator system was not completed for plant operation (Section 11.2.2.1.3).
LGS UFSAR CHAPTER 12 12.2-107 REV. 13, SEPTEMBER 2006 Table 12.2-66 EVAPORATOR DISTILLATE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (ci)
Br-83 7.04x10-16 Ba-140 1.07x10-6 Y-92 1.76x10-12 I-131 1.30x10-5 Ce-141 1.48x10-8 Y-91 7.10x10-8 I-132 2.60x10-5 Ce-143 4.49x1010 Y-91m 4.74x10-9 I-133 2.91x10-6 Ce-144 5.51x10-9 Y-90 2.79x10-8 I-135 9.46x10-9 Pr-143 5.00x10-9 Y-89m 4.60x10-11 Sr-89 4.60x10-7 Nd-147 1.58x10-9 Zn-69 6.51x10-12 Sr-90 3.65x10-8 Np-239 8.21x10-6 Cs-135 5.24x10-15 Sr-91 7.34x10-9 Pu-239 7.89x10-12 Na-24 5.79x10-10 Sr-92 5.75x10-15 Pm-147 7.41x10-11 P-32 6.97x10-10 Zr-95 6.00x10-9 Pr-144 5.51x10-0 Cr-51 1.98x10-9 Zr-97 5.48x10-11 La-141 2.66x10-13 Mn-54 1.79x10-9 Nb-95 6.61x10-9 La-140 1.02x10-6 Mn-56 2.72x10-16 Mo-99 9.46x10-7 Te-129 3.64x10-9 Fe-59 3.34x10-9 Tc-99m 9.06x10-7 I-129 3.65x10-17 Co-58 2.15x10-7 Ru-103 2.74x10-9 Ag-110 3.49x10-11 Co-60 2.27x10-8 Ru-106 4.09x10-10 Rn-106 4.09x10-10 Ni-65 1.49x10-18 Te-129m 5.69x10-9 Rn-103m 2.69x10-9 Zn-65 8.94x10-11 Te-132 2.52x10-6 Tc-99 2.34x10-13 Zn-69m 6.07x10-12 Cs-134 2.53x10-8 Nb-97m 5.10x10-11 Ag-110m 2.68x10-9 Cs-136 1.33x10-8 Nb-97 5.90x10-11 W-187 4.70x10-9 Cs-137 3.81x10-8 Nb-95m 7.67x10-11 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Activity in evaporator feed tank with 3.0 days decay and DFs applied for the evaporator (DF of 1000 for I and Br and DF of 10,000 for others).
(3) This activity is in 6000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) Installation of the abandoned evaporator distillate tank was not completed for plant operation (Section 11.2.2.1.3).
LGS UFSAR CHAPTER 12 12.2-108 REV. 13, SEPTEMBER 2006 Table 12.2-67 LAUNDRY DRAIN COLLECTION TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ISOTOPE(4)
(Ci)
Mn-54 5.48x10-6 Co-58 2.18x10-5 Co-60 4.94x10-5 Zr-95 7.62x10-6 Nb-95 1.09x10-5 Ru-103 7.60x10-7 Ru-106 1.31x10-5 Ag-110m 2.41x10-6 I-131 3.15x10-6 Cs-134 7.12x10-5 Cs-137 1.31x10-4 Ce-144 2.74x10-5 Pr-144 2.69x10-5 Ag-110 3.13x10-8 Rh-106 1.31x10-5 Rh-103m 7.02x10-7 Nb-95m 1.33x10-8 (1)
Based on untreated detergent waste activities presented in NUREG-0016, Revision 0, Tables 2-31 and 2-32 (Reference 12.2-1).
(2)
Laundry drains accumulated for 1.0 days at 0.625 gpm.
(3)
This activity is in 900 gallons.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-109 REV. 13, SEPTEMBER 2006 Table 12.2-68 LAUNDRY DRAIN SAMPLE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ISOTOPE(4)
(Ci)
Mn-54 1.09x10-5 Co-58 4.35x10-5 Co-60 9.88x10-5 Zr-95 1.52x10-5 Nb-95 2.18x10-5 Ru-103 1.51x10-6 Ru-106 2.62x10-5 Ag-110m 4.81x10-6 I -131 6.05x10-6 Cs-134 1.42x10-4 Cs-137 2.63x10-4 Ce-144 5.47x10-5 Pr-144 5.42x10-5 Ag-110 6.25x10-8 Rh-106 2.62x10-5 Rh-103m 1.43x10-6 Nb-95m 4.99x10-8 (1)
Based on untreated detergent waste activities presented in NUREG-0016, Revision 0, tables 2-31 and 2-32 (Reference 12.2-1).
(2)
Laundry drains accumulated for 2.0 days at 0.625 gpm.
(3)
This activity is in 1800 gallons.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-110 REV. 13, SEPTEMBER 2006 Table 12.2-69 REACTOR, TURBINE, AND RADWASTE ENCLOSURES EQUIPMENT AND FLOOR DRAIN SUMPS SHIELDING DESIGN SOURCE TERMS(1)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(2)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 5.25x10-10 Tc-99m 9.80x10-9 Ce-144 1.23x10-12 Br-84 9.45x10-10 Tc-101 4.90x10-9 Pr-143 1.33x10-12 Br-85 5.95x10-10 Ru-103 6.65x10-13 Nd-147 4.90x10-13 I-131 4.55x10-10 Ru-106 9.10x10-14 Np-239 8.40x10-9 I-132 4.20x10-9 Te-129m 1.40x10-12 Na-24 2.00x10-11 I-133 3.12x10-9 Te-132 1.72x10-9 P-32 2.00x10-13 I-134 8.40x10-9 Cs-134 5.60x10-12 Cr-51 5.00x10-12 I-135 4.55x10-9 Cs-136 3.85x10-12 Mn-54 4.00x10-13 Sr-89 1.09x10-10 Cs-137 8.40x10-12 Mn-56 5.00x10-10 Sr-90 8.05x10-12 Cs-138 6.65x10-9 Co-58 5.00x10-11 Sr-91 2.42x10-9 Ba-139 5.60x10-9 Co-60 5.00x10-12 Sr-92 3.85x10-9 Ba-140 3.15x10-10 Fe-59 8.00x10-13 Zr-95 1.40x10-12 Ba-141 5.95x10-9 Ni-65 3.00x10-12 Zr-97 1.12x10-12 Ba-142 5.95x10-9 Zn-65 2.00x10-14 Nb-95 1.47x10-12 Ce-141 1.37x10-12 Zn-69m 3.00x10-13 Mo-99 7.70x10-10 Ce-143 1.23x10-12 Ag-110m 6.00x10-13 W-187 3.00x10-11 (1) Assumes 1% of specific activity in reactor water, less activation gases (Tables 12.2-2, 12.2-3, and 12.2-5).
(2) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-111 REV. 13, SEPTEMBER 2006 Table 12.2-70 CONDENSATE PHASE SEPARATORS SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
CARRYOVER COMPONENT Activity Activity Activity Isotope(5)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 2.48x10+1 Cs-138 3.36 Te-129 3.19x10-1 Br-84 9.44 Ba-139 7.51 I-129 8.73x10-10 Br-85 3.50x10-1 Ba-140 7.54x10+1 Rh-106 4.17x10-2 I-131 1.59x10+3 Ba-141 1.62 Rh-103m 2.41x10-1 I-132 3.17x10+2 Ba-142 9.37x10-1 Tc-99 2.59x10-5 I-133 1.25x10+3 Ce-141 1.28 Nb-97m 1.75x10-2 I-134 1.40x10+2 Ce-143 4.00x10-2 Nb-97 1.88x10-2 I-135 5.99x10+2 Ce-144 5.57x10-1 Nb-95m 9.43x10-3 Sr-89 4.26x10+1 Pr-143 3.59x10-1 Y-92 1.03x10+1 Sr-90 3.79 Nd-147 1.07x10-1 Y-91 6.49 Sr-91 2.30x10+1 Np-239 4.68x10+2 Y-91m 1.36x10+1 Sr-92 1.02x10+1 Re-187 8.51x10-13 Y-90 3.31 Zr-95 5.69x10-1 Ag-110 3.53x10-3 Y-89m 4.26x10-3 Zr-97 1.88x10-2 Zn-69 4.10x10-3 Cs-135 1.05x10-5 Nb-95 6.68x10-1 Pu-239 9.19x10-4 Na-24 2.96x10-1 Mo-99 5.08x10+1 U-235 3.15x10-14 P-32 5.09x10-2 Tc-99m 1.03x10+2 Th-231 2.80x10-14 Cr-51 1.68 Tc-101 1.01 Pa-231 1.42x10-18 Mn-54 1.82x10-1 Ru-103 2.46x10-1 Pm-147 1.42x10-3 Mn-56 1.26 Ru-106 4.17x10-2 Sm-147 2.76x10-16 Co-58 2.05x10+1 Te-129m 5.00x10-1 Pr-144 5.57x10-1 Co-60 2.34 Te-132 1.32x10+2 Nd-144 6.37x10-18 Fe-59 3.05x10-1 Cs-134 2.60 La-142 1.08 Ni-65 7.54x10-3 Cs-136 9.58x10-1 La-141 1.77 Zn-65 9.04x10-3 Cs-137 3.95 La-140 7.23x10+1 Zn-69m 4.09x10-3 Ag-110m 2.72x10-1 W-187 7.09x10-1
LGS UFSAR CHAPTER 12 12.2-112 REV. 13, SEPTEMBER 2006 Table 12.2-70 (Cont'd)
FALLOUT COMPONENT Activity Activity Activity Isotope(5)
(Ci)
Isotope (Ci)
Isotope (Ci)
Ba-144 3.88x10-6 La-140 5.11 Y-93 9.72x10-1 La-144 1.57x10-3 Cs-139 5.86 Zr-93 3.44x10-8 Ce-144 7.64x10-4 Ba-139 6.93 Nb-93m 6.38x10-11 Pr-144 7.64x10-4 Cs-138 2.22 Rb-92 5.38x10-8 Ba-143 2.31x10-5 Cs-137 7.06x10-3 Sr-92 4.25 La-143 5.83x10-2 Cs-135 1.05x10-8 Y-92 4.29 Ce-143 1.54 Rb-95 1.43x10-19 Rb-91 1.79 Pr-143 1.14 Sr-95 1.56x10-3 Sr-91 6.81 Cs-142 3.01x10-19 Y-95 1.04x10-2 Y-91 1.91 Ba-142 4.91x10-1 Zr-95 2.93x10-3 Y-91m 4.02 La-142 5.66x10-1 Nb-95 7.21x10-4 Rb-90 3.93 Cs-141 3.65x10-2 Nb-95m 4.87x10-5 Sr-90 1.33x10-2 Ba-141 1.94 Rb-94 5.13x10-16 Y-90 1.17x10-2 La-141 2.08 Sr-94 5.27x10-2 Rb-89 3.03 Ce-141 9.42x10-1 Y-94 1.63x10-1 Sr-89 1.05 Cs-140 1.58 Rb-93 3.06x10-8 Y-89m 1.05x10-4 Ba-140 5.33 Sr-93 8.09x10-1 Rb-88 4.79x10-1 Rb-87 5.93x10-13 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Condensate with 2.25 minutes decay accumulated for 28.6 days at 30,200 gpm.
(3) Assumes a 2.25 minute transit time through the hotwell to the filter/demineralizers.
(4) This activity is in 1600 gallons of sludge (spent resin).
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-113 REV. 13, SEPTEMBER 2006 Table 12.2-71 CONDENSATE PHASE SEPARATOR SLUDGE MIXING AND DISCHARGE PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
CARRYOVER COMPONENT Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci)
I-131 1.43x10+2 Ce-144 5.20x10-1 Tc-99 2.80x10-5 I-132 3.38x10-1 Pr-143 8.72x10-2 Nb-97m 2.22x10-14 I-133 1.36x10-7 Nd-147 1.86x10-2 Nb-97 2.57x10-14 Sr-89 2.95x10+1 Np-239 1.20x10-1 Nb-95m 8.96x10-3 Sr-90 3.78 Re-187 8.96x10-13 Y-91 4.79 Sr-91 2.81x10-20 Ag-110 3.27x10-3 Y-91m 1.81x10-20 Zr-95 4.23x10-1 Zn-69 9.73x10-18 Y-90 3.78 Zr-97 2.39x10-14 Pu-239 1.04x10-3 Y-89m 2.95x10-3 Nb-95 5.91x10-1 U-235 1.08x10-13 Cs-135 1.09x10-5 Mo-99 4.72x10-2 Th-231 1.04x10-13 Na-24 8.95x10-15 Tc-99m 4.51x10-2 Pa-231 1.53x10-18 P-32 1.31x10-2 Ru-103 1.51x10-1 Pm-147 2.40x10-3 Cr-51 8.37x10-1 Ru-106 3.96x10-2 Sm-147 1.32x10-15 Mn-54 1.71x10-1 Te-129m 2.83x10-1 Pr-144 5.20x10-1 Co-58 1.57x10+1 Te-132 3.28x10-1 Nd-144 1.83x10-17 Co-60 2.32 Cs-134 2.53 La-140 1.91x10+1 Fe-59 2.00x10-1 Cs-136 2.32x10-1 Te-129 1.81x10-1 Zn-65 8.36x10-3 Cs-137 3.94 I-129 2.07x10-9 Zn-69m 9.06x10-18 Ba-140 1.65x10+1 Rh-106 3.96x10-2 Ag-110m 2.52x10-1 Ce-141 7.11x10-1 Rh-103m 1.48x10-1 W-187 2.45x10-9 Ce-143 2.97x10-8
LGS UFSAR CHAPTER 12 12.2-114 REV. 13, SEPTEMBER 2006 Table 12.2-71 (Cont'd)
FALLOUT COMPONENT Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci)
Ce-144 7.14x10-4 Cs-137 7.04x10-3 Nb-93m 1.94x10-10 Pr-144 7.14x10-4 Cs-135 1.05x10-8 Y-91 1.41 Nd-144 2.51x10-20 Zr-95 2.18x10-3 Sr-90 1.33x10-2 Ce-143 1.14x10-6 Nb-95 1.48x10-3 Y-90 1.33x10-2 Pr-143 3.15x10-1 Nb-95m 4.62x10-5 Sr-89 7.29x10-1 Ce-141 5.25x10-1 Y-93 2.28x10-20 Y-89m 7.29x10-5 Ba-140 1.18 Zr-93 3.52x10-8 Rb-87 5.93x10-13 La-140 1.35 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Condensate phase separator sludge decayed for 28 days.
(3) This activity is in a 13,000 gallon slurry.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-115 REV. 13, SEPTEMBER 2006 Table 12.2-72 CONDENSATE PHASE SEPARATOR DECANT PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(3)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 7.88x10-12 Cs-136 7.68x10-14 Rh-103m 6.71x10-15 Br-84 5.11x10-12 Cs-137 1.68x10-13 Tc-99 7.01x10-20 Br-85 1.14x10-17 Cs-138 3.66x10-11 Nb-97m 2.00x10-14 I-131 9.07x10-12 Ba-139 6.78x10-11 Nb-97 9.45x10-15 I-132 7.08x10-11 Ba-140 6.29x10-12 Nb-95m 4.29x10-18 I-133 6.02x10-11 Ba-141 1.18x10-11 Y-92 1.21x10-11 I-134 7.55x10-11 Ba-142 2.72x10-12 Y-91 1.37x10-14 I-135 8.20x10-11 Ce-141 3.19x10-14 Y-91m 1.54x10-11 Sr-89 2.17x10-12 Ce-143 2.40x10-14 Y-90 1.85x10-15 Sr-90 1.61x10-13 Ce-144 2.45x10-14 Y-89m 2.17x10-16 Sr-91 4.50x10-11 Pr-143 2.66x10-14 Na-24 3.82x10-13 Sr-92 5.96x10-11 Nd-147 9.77x10-15 P-32 3.99x10-15 Zr-95 2.80x10-14 Np-239 1.66x10-10 Cr-51 9.99x10-14 Zr-97 2.15x10-14 Ag-110 1.56x10-16 Mn-54 8.00x10-15 Nb-95 2.94x10-14 Zn-69 3.02x10-15 Mn-56 7.64x10-12 Mo-99 1.52x10-11 Pu-239 5.42x10-19 Co-58 1.00x10-12 Tc-99m 1.76x10-10 Pm-147 2.96x10-19 Co-60 1.00x10-13 Tc-101 5.03x10-12 Pr-144 2.23x10-14 Fe-59 1.60x10-14 Ru-103 1.33x10-14 La-142 9.88x10-12 Ni-65 4.58x10-14 Ru-106 1.82x10-15 La-141 7.37x10-12 Zn-65 4.00x10-16 Te-129m 2.80x10-14 La-140 1.08x10-13 Zn-69m 5.71x10-15 Te-132 3.40x10-11 Te-129 8.13x10-15 Ag-110m 1.20x10-14 Cs-134 1.12x10-13 Rh-106 1.82x10-15 W-187 5.83x10-13 (1) Based on shielding design source terms given in Tables 12.2-1 through 12.2-5.
(2) Activity is 0.02% of reactor water with one hour decay.
(3) Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-116 REV. 13, SEPTEMBER 2006 Table 12.2-73 RWCU SYSTEM PHASE SEPARATOR SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(5)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 2.11x10+1 Ba-139 1.28x10+2 Rh-106 1.45 Br-84 7.95 Ba-140 1.58x10+3 Rh-103m 6.81 Br-85 2.52x10-1 Ba-141 2.69x10+1 Tc-99 9.70x10-4 I-131 1.48x10+3 Ba-142 1.53x10+1 Nb-97m 3.00x10-1 I-132 2.42x10+3 Ce-141 3.48x10+1 Nb-97 3.22x10-1 I-133 1.07x10+3 Ce-143 6.84x10-1 Nb-95m 3.26x10-1 I-134 1.18x10+2 Ce-144 1.93x10+1 Y-92 1.77x10+2 I-135 5.12x10+2 Pr-143 7.65 Y-91 1.99x10+2 Sr-89 1.27x10+3 Nd-147 2.15 Y-91m 2.33x10+2 Sr-90 1.36x10+2 Np-239 8.01x10+3 Y-90 1.28x10+2 Sr-91 3.94x10+2 Re-187 3.14x10-11 Y-89m 1.27x10-1 Sr-92 1.74x10+2 Ag-110 1.22x10-1 Cs-135 1.92x10-5 Zr-95 1.75x10+1 Zn-69 7.01x10-2 Na-24 5.06 Zr-97 3.22x10-1 Pu-239 3.53x10-2 P-32 1.10 Nb-95 2.24x10+1 U-235 2.68x10-12 Cr-51 4.38x10+1 Mo-99 8.69x10+2 Th-231 2.54x10-12 Mn-54 6.32 Tc-99m 1.76x10+3 Pa-231 1.05x10-16 Mn-56 2.15x10+1 Tc-101 1.67x10+1 Pm-147 6.97x10-2 Co-58 6.40x10+2 Ru-103 6.95 Sm-147 3.11x10-14 Co-60 8.36x10+1 Ru-106 1.45 Pr-144 1.93x10+1 Fe-59 8.87 Te-129m 1.37x10+1 Nd-144 4.68x10-16 Ni-65 1.29x10-1 Te-132 2.26x10+3 La-142 1.84x10+1 Zn-65 3.11x10-1 Cs-134 9.21x10+1 La-141 3.02x10+1 Zn-69m 6.99x10-2 Cs-136 2.04x10+1 La-140 1.57x10+3 Ag-110m 9.36 Cs-137 1.42x10+2 Te-129 8.75 W-187 1.21x10+1 Cs-138 5.67x10+1 I-129 5.48x10-8 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
Reactor coolant (less gases) accumulated for 60 days at 708 gpm at 0.73 g/cc.
(3)
Assumes a 3 minute transit time from reactor vessel to phase separator.
(4)
This activity is in 700 gallons of sludge (spent resin).
(5)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-117 REV. 13, SEPTEMBER 2006 Table 12.2-74 RWCU SYSTEM PHASE SEPARATOR SLUDGE DISCHARGE AND MIXING PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
I-131 8.46 Ce-141 9.72 Te-129 2.59 I-132 6.15x10-3 Ce-143 5.04x10-14 I-129 1.08x10-7 I-133 4.79x10-19 Ce-144 1.66x10+1 Rh-106 1.30 Sr-89 5.76x10+2 Pr-143 3.63x10-1 Rh-103m 2.38 Sr-90 1.35x10+2 Nd-147 5.01x10-2 Tc-99 1.01x10-3 Zr-95 9.28 Np-239 1.61x10-4 Nb-95m 1.97x10-1 Nb-95 1.53x10+1 Re-187 3.22x10-11 Y-91 9.96x10+1 Mo-99 2.77x10-4 Ag-110 1.03x10-1 Y-90 1.35x10+2 Tc-99m 2.65x10-4 Pu-239 3.74x10-2 Y-89m 5.76x10-2 Ru-103 2.43 U-235 8.67x10-12 Cs-135 1.95x10-5 Ru-106 1.30 Th-231 8.51x10-12 P-32 5.97x10-2 Te-129m 4.04 Pa-231 1.24x10-16 Cr-51 9.82 Te-132 5.97x10-3 Pm-147 9.02x10-2 Mn-54 5.51 Cs-134 8.71x10+1 Sm-147 1.25x10-13 Co-58 3.57x10+2 Cs-136 9.81x10-1 Pr-144 1.66x10+1 Co-60 8.18x10+1 Cs-137 1.41x10+2 Nd-144 1.32x10-15 Fe-59 3.56 Ba-140 6.12x10+1 La-140 7.04x10+1 Zn-65 2.62x10-1 Ag-110m 7.95 W-187 8.93x10-18 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
RWCU system phase separator sludge decayed for 60 days.
(3)
This activity is in a 5600 gallon slurry.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-118 REV. 13, SEPTEMBER 2006 Table 12.2-75 RWCU SYSTEM PHASE SEPARATOR DECANT PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)
SPECIFIC ACTIVITY SPECIFIC ACTIVITY SPECIFIC ACTIVITY ISOTOPE(3)
(Ci/cc)
ISOTOPE (Ci/cc)
ISOTOPE (Ci/cc)
Br-83 1.06x10-13 Ba-139 6.63x10-15 Nb-97 9.07x10-14 I-131 8.35x10-11 Ba-140 5.97x10-11 Nb-95m 9.40x10-16 I-132 2.86x10-10 Ce-141 7.11x10-13 Y-92 1.74x10-11 I-133 2.75x10-10 Ce-143 1.48x10-13 Y-91 2.66x10-12 I-134 7.77x10-18 Ce-144 2.44x10-13 Y-91m 5.59x10-11 I-135 7.55x10-11 Pr-143 2.62x10-13 Y-90 3.90x10-13 Sr-89 2.14x10-11 Nd-147 9.20x10-14 Y-89m 2.14x10-15 Sr-90 1.61x10-12 Np-239 1.25x10-9 Cs-135 1.44x10-19 Sr-91 8.65x10-11 F-18 8.96x10-16 Na-24 1.32x10-12 Sr-92 1.66x10-12 Ag-110 1.56x10-15 P-32 3.81x10-14 Zr-95 2.77x10-13 Zn-69 1.93x10-14 Cr-51 9.75x10-13 Zr-97 8.42x10-14 Pu-239 1.13x10-16 Mn-54 7.98x10-14 Nb-95 2.94x10-13 Pm-147 6.88x10-17 Mn-56 1.57x10-13 Mo-99 1.20x10-10 Pr-144 2.44x10-13 Co-58 9.90x10-12 Tc-99m 2.31x10-10 La-142 3.32x10-15 Co-60 1.00x10-12 Ru-103 1.31x10-13 La-141 1.36x10-12 Fe-59 1.58x10-13 Ru-106 1.82x10-14 La-140 2.07x10-11 Ni-65 9.14x10-16 Te-129m 2.74x10-13 Te-129 1.76x10-13 Zn-65 3.99x10-15 Te-132 2.77x10-10 Rh-106 1.82x10-14 Zn-69m 1.80x10-14 Cs-134 1.12x10-12 Rh-103m 1.28x10-13 Ag-110m 1.20x10-13 Cs-136 7.32x10-13 Tc-99 6.85x10-18 W-187 2.99x10-12 Cs-137 1.68x10-12 Nb-97m 7.84x10-14 (1)
Based on shielding design source terms given in Tables 12.2-2 through 12.2-5.
(2)
Reactor water decayed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a phase separation partition factor of 0.2%.
(3)
Isotopes with specific activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-119 REV. 13, SEPTEMBER 2006 Table 12.2-76 WASTE SLUDGE TANK AND DISCHARGE AND MIXING PUMP SHIELDING DESIGN SOURCE TERMS(1)(2)
FIRST COMPONENT(3)
Activity Activity Activity Isotope(5)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 2.00x10-1 Cs-137 9.62x10-2 I-129 3.72x10-12 Br-84 7.91x10-2 Cs-138 5.64x10-1 Rh-106 1.04x10-3 Br-85 4.70x10-3 Ba-139 1.22 Rh-103m 7.10x10-3 I-131 4.35 Ba-140 3.21 Tc-00 4.44x10-7 I-132 1.40x10+1 Ba-141 2.82x10-1 Nb-97m 2.76x10-3 I-133 9.71 Ba-142 1.72x10-1 Nb-97 2.96x10-3 I-134 1.15 Ce-141 3.86x10-2 Nb-95m 9.89x10-5 I-135 4.80 Ce-143 5.68x10-3 Y-92 1.65 Sr-89 1.21 Ce-144 1.40x10-2 Y-91 1.59x10-1 Sr-90 9.22x10-2 Pr-143 1.44x10-2 Y-91m 2.18 Sr-91 3.69 Nd-147 4.91x10-3 Y-90 3.87x10-2 Sr-92 1.65 Np-239 5.41x10+1 Y-89m 1.21x10-4 Zr-95 1.57x10-2 Re-187 1.50x10-14 Cs-135 1.03x10-8 Zr-97 2.97x10-3 Ag-110 8.88x10-5 Na-24 4.69x10-2 Nb-95 1.68x10-2 Zn-69 6.50x10-4 P-32 2.06x10-3 Mo-99 5.38 Pu-239 1.11x10-5 Cr-51 5.43x10-2 Tc-99m 1.38x10+1 Pm-147 8.10x10-6 Mn-54 4.56x10-3 Tc-101 1.81x10-1 Sm-147 2.18x10-19 Mn-56 2.03x10-1 Ru-103 7.33x10-3 Pr-144 1.39x10-2 Co-58 5.61x10-1 Ru-106 1.04x10-3 Nd-144 2.39x10-20 Co-60 5.72x10-2 Te-129m 1.53x10-2 La-142 1.72x10-1 Fe-59 8.87x10-3 Te-132 1.28x10+1 La-141 2.82x10-1 Ni-65 1.22x10-3 Cs-134 6.40x10-2 La-140 1.78 Zn-65 2.28x10-4 Cs-136 3.96x10-2 Te-129 9.67x10-3 Zn-69m 6.51x10-4 Ag-110m 6.83x10-3 W-187 1.08x10-1
LGS UFSAR CHAPTER 12 12.2-120 REV. 13, SEPTEMBER 2006 Table 12.2-76 (Cont'd)
SECOND COMPONENT(4)
Activity Activity Activity Isotope(5)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 1.27x10-3 Cs-137 1.30x10-2 Rh-106 1.41x10-4 Br-84 1.90x10-9 Cs-138 1.65x10-8 Rh-103m 9.80x10-4 I-131 6.02x10-1 Ba-139 5.65x10-4 Tc-99 6.13x10-8 I-132 1.86 Ba-140 4.42x10-1 Nb-97m 3.40x10-4 I-133 1.26 Ba-141 3.17x10-14 Nb-97 3.93x10-4 I-134 1.38x10-5 Ce-141 5.43x10-3 Nb-95m 1.23x10-5 I-135 2.89x10-1 Ce-143 7.95x10-4 Y-92 8.65x10-2 Sr-89 1.64x10-1 Ce-144 1.89x10-3 Y-91 2.29x10-2 Sr-90 1.25x10-2 Pr-143 1.98x10-3 Y-91m 2.10x10-1 Sr-91 3.26x10-1 Nd-147 6.77x10-4 Y-90 4.92x10-3 Sr-92 1.54x10-2 Np-239 7.67 Y-89m 1.64x10-5 Zr-95 2.13x10-3 Re-187 2.04x10-15 Cs-135 1.47x10-9 Zr-97 3.65x10-4 Ag-110 1.21x10-5 Na-24 5.47x10-3 Nb-95 2.28x10-3 Zn-69 7.84x10-5 P-32 2.84x10-4 Mo-99 7.61x10-1 Pu-239 1.42x10-6 Cr-51 7.41x10-3 Tc-99m 1.18 Pm-147 9.72x10-7 Mn-54 6.19x10-4 Tc-101 6.31x10-18 Sm-147 1.99x10-20 Mn-56 1.62x10-3 Ru-103 9.99x10-4 Pr-144 1.89x10-3 Co-58 7.62x10-2 Ru-106 1.41x10-4 La-142 1.71x10-4 Co-60 7.76x10-3 Te-129m 2.09x10-3 La-141 7.31x10-3 Fe-59 1.21x10-3 Te-132 1.80 La-140 2.37x10-1 Ni-65 9.52x10-6 Cs-134 8.68x10-3 Te-129 1.34x10-3 Zn-65 3.09x10-5 Cs-136 5.44x10-3 I-129 4.38x10-13 Zn-69m 7.30x10-5 Ag-110m 9.27x10-4 W-187 1.45x10-2 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) This activity is in 13,475 gallons of sludge slurry.
(3) Equipment drains accumulated for 4.36 days at 26.93 gpm, with no decay.
(4) Floor drains accumulated for 2.76 days at 7.22 gpm, with 0.51 days decay.
(5) Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-121 REV. 13, SEPTEMBER 2006 Table 12.2-77 RADWASTE EVAPORATOR CONCENTRATE STORAGE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)(5)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Br-83 7.04x10-13 Ce-141 1.47x10-3 Tc-99 1.80x10-7 I-131 3.71x10-2 Ce-143 4.89x10-6 Nb-97m 5.14x10-7 I-132 3.95x10-2 Ce-144 2.53x10-3 Nb-97 5.95x10-7 I-133 2.96x10-3 Pr-143 2.24x10-4 Nb-95m 2.31x10-5 I-135 9.46x10-6 Nd-147 5.88x10-4 Y-92 1.76x10-8 Sr-89 7.14x10-2 Np-239 1.06x10-1 Y-91 1.22x10-2 Sr-90 2.41x10-2 Pu-239 6.67x10-6 Y-91m 4.74x10-5 Sr-91 7.34x10-5 U-235 2.97x10-15 Y-90 2.40x10-2 Sr-92 5.75x10-11 Th-231 2.95x10-15 Y-89m 7.14x10-6 Zr-95 1.13x10-3 Pa-231 1.21x10-19 Zn-69 6.53x10-8 Zr-97 5.52x10-7 Re-187 5.75x10-15 Cs-135 3.50x10-9 Nb-95 1.76x10-3 Pm-147 1.47x10-4 Na-24 5.82x10-6 Mo-99 1.33x10-2 Sm-147 4.43x10-16 P-32 3.24x10-5 Tc-99m 1.27x10-2 Pr-144 2.53x10-3 Cr-51 1.69x10-3 Ru-103 3.26x10-4 Nd-144 3.86x10-19 Mn-54 8.41x10-4 Ru-106 2.03x10-4 La-142 5.95x10-18 Mn-56 2.72x10-12 Te-129m 5.88x10-4 La-141 2.66x10-9 Fe-59 4.54x10-4 Te-132 3.84x10-2 La-140 4.94x10-2 Co-58 4.36x10-2 Cs-134 1.45x10-2 Te-129 3.77x10-4 Co-60 1.42x10-2 Cs-136 5.94x10-4 I-129 2.00x10-11 Ni-65 1.49x10-14 Cs-137 2.51x10-2 Ag-110 1.54x10-5 Zn-65 3.88x10-5 Ba-139 8.76x10-19 Rh-106 2.03x10-4 Zn-69m 6.08x10-8 Ba-140 4.49x10-2 Rh-103m 3.19x10-4 Ag-110m 1.18x10-3 W-187 4.85x10-5 (1) Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2) Chemical wastes (2% of reactor water less gases) with 3.0 days decay accumulated for 33 days at 0.833 gpm.
(3) This activity is in 4000 gallons.
(4) Isotopes with activities less than 1.0x10-20 are not listed.
(5) Installation of the abandoned evaporator concentrate tank was not completed for plant operation (Section 11.2.2.1.3).
LGS UFSAR CHAPTER 12 12.2-122 REV. 13, SEPTEMBER 2006 Table 12.2-78 SOLID RADWASTE CENTRIFUGE AIR FILTERS AND RADWASTE ENCLOSURE EQUIPMENT COMPARTMENT EXHAUST AIR FILTERS SHIELDING DESIGN SOURCE TERMS(1)(2)
ACTIVITY ISOTOPE(3)
(Ci)
I-131 1.11x10-2 I-133 4.21x10-3 Co-60 1.69x10-1 Co-58 2.46x10-3 Cr-51 1.98x10-3 Mn-54 4.07x10-2 Fe-59 5.38x10-3 Zn-65 1.87x10-3 Zr-95 8.87x10-5 Sr-89 6.50x10-4 Sr-90 2.07x10-3 Sb-124 8.23x10-5 Cs-134 2.67x10-2 Cs-136 1.71x10-4 Cs-137 6.23x10-2 Ba-140 3.54x10-5 Ce-141 2.34x10-3 La-140 3.54x10-5 Y-90 2.05x10-3 Y-89m 6.50x10-8 Nb-95 8.66x10-5 Nb-95m 1.77x10-6 (1)
Based on NUREG-0016, Revision 0, table 1-1 release rates, with fission products adjusted to 0.35 Ci/sec offgas release rate at 30 minutes decay. All isotopes are multiplied by 2 to account for two reactors.
(2)
Assumes a one year accumulation of all these isotopes at 53,000 cfm.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-123 REV. 13, SEPTEMBER 2006 Table 12.2-79 CHARCOAL TREATMENT SYSTEM COOLER CONDENSER SHIELDING DESIGN SOURCE TERMS(1)
COOLER CONDENSER DRAIN POT COMPONENT(3)
COOLER CONDENSER HEAT EXCHANGER BODY COMPONENT(4)
Activity Activity Activity Isotope(2)
(Ci)
Isotope (Ci)
Isotope (Ci)
La-144 1.26x10-11 Zr-95 9.60x10-7 N-13 3.30x10-2 Ce-144 6.46x10-7 Nb-95 2.35x10-10 O-19 9.59x10-9 Pr-144 4.30x10-7 Nb-95m 4.48x10-11 F-18 6.97x10-2 La-143 1.10x10-2 Sr-94 2.45x10-6 Kr-83m 1.16x10-1 Ce-143 2.38x10-4 Y-94 3.33x10-2 Kr-85m 2.26x10-1 Pr-143 1.52x10-7 Sr-93 1.17x10-1 Kr-85 7.87x10-4 Ba-142 8.61x10-2 Y-93 1.48x10-2 Kr-87 6.45x10-1 La-142 4.48x10-2 Zr-93 2.64x10-13 Kr-88 7.19x10-1 Cs-141 9.86x10-17 Nb-93m 2.86x10-19 Kr-89 8.02x10-2 Ba-141 4.00x10-1 Sr-92 2.81x10-1 Kr-90 5.72x10-8 La-141 5.79x10-2 Y-92 2.70x10-2 Xe-131m 5.90x10-4 Ce-141 1.50x10-5 Rb-91 6.69x10-5 Xe-133m 1.13x10-2 Cs-140 3.62x10-5 Sr-91 2.82x10-1 Xe-133 3.22x10-1 Ba-140 1.36x10-2 Y-91 3.27x10-5 Xe-135m 3.99x10-1 La-140 1.06x10-4 Y-91m 5.27x10-2 Xe-135 8.59x10-1 Cs-139 8.95x10 Rb-90 3.16x10-1 Xe-137 1.86x10-1 Ba-139 5.63x10 Sr-90 3.32x10-5 Xe-138 1.50x10 Cs-138 5.84x10+1 Y-90 1.54x10-7 Xe-139 2.71x10-6 Cs-137 1.14x10-4 Rb-89 2.84x10+1 Xe-140 4.78x10-15 Cs-135 6.65x10-10 Sr-89 1.11x10-2 Sr-95 7.61x10-11 Y-89m 1.10x10-6 Y-95 1.77x10-3 Rb-88 2.61x10+1 Rb-87 3.43x10-14 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
(3)
This particulate activity is assumed to be uniformly distributed throughout the 0.78 ft3 volume of condensate in the drain pot.
(4)
This gaseous activity is assumed to be uniformly distributed throughout the 1.54x105 cc volume of the entire (homogenized) cooler condenser heat exchanger body.
LGS UFSAR CHAPTER 12 12.2-124 REV. 13, SEPTEMBER 2006 Table 12.2-80 CHARCOAL GUARD BED SHIELDING DESIGN SOURCE TERMS(1)(3)
(Unit 1)
Activity Activity Activity Isotope(2)
(Ci)
Isotope (Ci)
Isotope (Ci)
Xe-131m 9.87 Cs-140 2.32 Y-93 1.29x10-2 Xe-133m 3.14x10+1 Ba-140 2.30 Zr-93 2.38x10-7 Xe-133 1.26x10+3 La-140 2.30 Nb-93m 1.30x10-7 Xe-135m 2.65x10+2 Cs-139 1.34x10+1 Rb-92 9.74x10-2 Xe-135 8.22x10+2 Ba-139 1.34x10+1 Sr-92 9.64x10-2 Xe-137 1.08x10+2 Cs-138 3.71x10+2 Y-92 9.64x10-2 Xe-138 3.73x10+2 Cs-137 6.45x10+1 Rb-91 9.93x10-1 Xe-139 1.34x10+1 Cs-135 7.53x10-3 Sr-91 9.85x10-1 Xe-140 2.32 Kr-83m 2.48x10+1 Y-91 9.85x10-1 Xe-141 2.29x10-2 Kr-85m 3.85 Y-91m 5.81x10-1 Xe-142 5.42x10-3 Kr-85 7.49x10-2 Rb-90 8.08 Xe-143 3.99x10-4 Kr-87 1.12x10+1 Sr-90 5.09 Xe-144 1.43x10-3 Kr-88 1.15x10+1 Y-90 5.09 Cs-144 1.43x10-3 Kr-89 3.19x10+1 Rb-89 3.16x10+1 Ba-144 1.43x10-3 Kr-90 8.13 Sr-89 3.16x10+1 La-144 1.43x10-3 Kr-91 9.95x10-1 Y-89m 3.16x10-3 Ce-144 1.41x10-3 Kr-92 9.74x10-2 Rb-88 1.14x10+1 Pr-144 1.41x10-3 Kr-93 1.30x10-2 Rb-87 6.44x10-9 Nd-144 1.59x10-17 Kr-94 1.49x10-3 N-13 8.75x10-2 Cs-143 3.99x10-4 Kr-95 6.97x10-5 N-16 2.38x10+1 Ba-143 3.99x10-4 Rb-95 6.97x10-5 N-17 4.41x10-3 La-143 3.99x10-4 Sr-95 6.96x10-5 O-19 1.83 Ce-143 3.95x10-4 Y-95 6.91x10-5 F-18 6.15x10-2 Pr-143 3.95x10-4 Zr-95 6.90x10-5 Br-83 2.28x10+1 Cs-142 5.42x10-3 Nb-95 6.90x10-5 Br-84 8.52 Ba-142 5.42x10-3 Nb-95m 1.38x10-6 Br-85 2.97x10-1 La-142 5.38x10-3 Rb-94 1.49x10-3 I-131 1.61x10+3 Cs-141 2.29x10-2 Sr-94 1.49x10-3 I-132 1.71x10+2 Ba-141 2.29x10-Y-94 1.48x10-3 I-133 1.15x10+3 La-141 2.27x10-2 Rb-93 1.30x10-2 I-134 1.27x10+2 Ce-141 2.27x10-2 Sr-93 1.29x10-2 I-135 5.54x10+2
LGS UFSAR CHAPTER 12 12.2-125 REV. 13, SEPTEMBER 2006 Table 12.2-80 (Cont'd)
CHARCOAL GUARD BED SHIELDING DESIGN SOURCE TERMS(1)(3)
(Unit 2)
Activity Activity Activity Isotope(2)
(Ci)
Isotope (Ci)
Isotope (Ci)
Xe-131m 9.87 Cs-140 2.25 Y-93 1.24x10-2 Xe-133m 3.14x10+1 Ba-140 2.22 Zr-93 2.30x10-7 Xe-133 1.26x10+3 La-140 2.22 Nb-93m 1.25x10-7 Xe-135m 2.64x10+2 Cs-139 1.31x10+1 Rb-92 9.41x10-2 Xe-135 8.22x10+2 Ba-139 1.30x10+1 Sr-92 9.32x10-2 Xe-137 1.06x10+2 Cs-138 3.70x10+2 Y-92 9.31x10-2 Xe-138 3.71x10+2 Cs-137 6.36x10+1 Rb-91 9.60x10-1 Xe-139 1.31x10+1 Cs-135 7.53x10-3 Sr-91 9.53x10-1 Xe-140 2.25 Kr-83m 2.45x10+1 Y-91 9.53x10-1 Xe-141 2.21x10-2 Kr-85m 3.34 Y-91m 5.62x10-1 Xe-142 5.24x10-3 Kr-85 7.22x10-2 Rb-90 7.69 Xe-143 3.85x10-4 Kr-87 9.66 Sr-90 4.84 Xe-144 1.38x10-3 Kr-88 9.90 Y-90 4.84 Cs-144 1.38x10-3 Kr-89 2.80x10+1 Rb-89 2.77x10+1 Ba-144 1.38x10-3 Kr-90 7.74 Sr-89 2.77x10+1 La-144 1.38x10-3 Kr-91 9.63x10-1 Y-89m 2.77x10-3 Ce-144 1.37x10-3 Kr-92 9.41x10-2 Rb-88 9.80 Pr-144 1.37x10-3 Kr-93 1.26x10-2 Rb-87 5.53x10-9 Nd-144 1.54x10-17 Kr-94 1.44x10-3 N-13 8.69x10-2 Cs-143 3.85x10-4 Kr-95 6.73x10-5 N-16 2.30x10+1 Ba-143 3.85x10-4 Rb-95 6.73x10-5 N-17 4.27x10-3 La-143 3.85x10-4 Sr-95 6.72x10-5 O-19 1.78 Ce-143 3.81x10-4 Y-95 6.67x10-5 F-18 6.15x10-2 Pr-143 3.81x10-4 Zr-95 6.66x10-5 Br-83 2.28x10+1 Cs-142 5.24x10-3 Nb-95 6.66x10-5 Br-84 8.50 Ba-142 5.24x10-3 Nb-95m 1.33x10-6 Br-85 2.92x10-1 La-142 5.20x10-3 Rb-94 1.44x10-3 I-131 1.61x10+3 Cs-141 2.21x10-2 Sr-94 1.44x10-3 I-132 1.71x10+2 Ba-141 2.21x10-2 Y-94 1.43x10-3 I-133 1.15x10+3 La-141 2.19x10-2 Rb-93 1.26x10-2 I-134 1.27x10+2 Ce-141 2.19x10-2 Sr-93 1.25x10-2 I-135 5.54x10+2 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
LGS UFSAR CHAPTER 12 12.2-126 REV. 13, SEPTEMBER 2006 Table 12.2-81 CHARCOAL MAIN BED SHIELDING DESIGN SOURCE TERMS This table lists the shielding design source terms for the various components that comprise the charcoal main bed. The table is divided into the following parts:
- a. First Half of Adsorber Number 1 (Unit 1)
- b. Second Half of Adsorber Number 1 (Unit 1)
- c. Adsorber Number 2 (Unit 1)
- d. Adsorber Number 3 (Unit 1)
- e. Adsorber Number 4 (Unit 1)
- f. Adsorber Number 1 (Unit 2)
- g. Adsorber Number 2 (Unit 2)
- h. Adsorber Number 3 (Unit 2)
- i. Adsorber Number 4 (Unit 2)
- j. Adsorber Number 5 (Unit 2)
LGS UFSAR CHAPTER 12 12.2-127 REV. 13, SEPTEMBER 2006 Table 12.2-81(a)
FIRST HALF OF ADSORBER NUMBER 1 (UNIT 1)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 1.72x10+1 Cs-135 3.21x10-2 Rb-91 2.29x10-3 Xe-133m 2.06x10+2 Kr-83m 8.68x10+1 Sr-91 9.87x10-3 Xe-133 8.12x10+3 Kr-85m 2.28x10+2 Y-91 9.86x10-3 Xe-135m 1.25x10+1 Kr-85 1.03 Y-91m 5.83x10-3 Xe-135 3.51x10+3 Kr-87 3.89x10+2 Rb-90 2.96x10-1 Xe-137 3.13x10-3 Kr-88 6.32x10+2 Sr-90 2.05x10-1 Xe-138 4.03x10+1 Kr-89 3.79x10+1 Y-90 2.05x10-1 Ce-144 1.41x10-5 Kr-90 2.46x10-1 Rb-89 3.82x10+1 Pr-144 1.41x10-5 Kr-91 6.89x10-6 Sr-89 3.79x10+1 Nd-144 1.59x10-19 Kr-92 1.36x10-18 Y-89m 3.79x10-3 La-143 2.21x10-7 Sr-95 6.64x10-8 Rb-88 6.31x10+2 Ce-143 3.93x10-6 Y-95 6.28x10-7 Rb-87 2.22x10-7 Pr-143 3.95x10-6 Zr-95 6.90x10-7 N-13 5.37 Ba-142 1.34x10-6 Nb-95 6.90x10-7 N-16 1.76x10+1 La-142 3.95x10-5 Nb-95m 1.38x10-8 N-17 1.32x10-3 Ba-141 2.44x10-5 Sr-94 3.74x10-6 O-19 7.84 La-141 2.06x10-4 Y-94 1.43x10-5 F-18 5.73 Ce-141 2.27x10-4 Rb-93 1.89x10-13 Br-83 2.28x10-1 Cs-140 2.50x10-18 Sr-93 1.04x10-4 Br-84 8.52x10-2 Ba-140 2.30x10-2 Y-93 1.29x10-4 Br-85 2.89x10-3 La-140 2.30x10-2 Zr-93 2.38x10-9 I-131 1.61x10+1 Cs-139 2.00x10-3 Nb-93m 1.30x10-9 I-132 1.71 Ba-139 9.37x10-2 Rb-92 6.47x10-13 I-133 1.15x10+1 Cs-138 4.20x10+1 Sr-92 9.60x10-4 I-134 1.27 Cs-137 6.47x10-1 Y-92 9.66x10-4 I-135 5.54 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout the first half of adsorber number 1, which is composed to two parallel units, 1AS371 and 1BS371.
LGS UFSAR CHAPTER 12 12.2-128 REV. 13, SEPTEMBER 2006 Table 12.2-81(b)
SECOND HALF OF ADSORBER NUMBER 1 (UNIT 1)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 1.33x10+1 Kr-85 1.03 Sr-90 2.05x10-3 Xe-133m 5.59x10+1 Kr-87 4.17x10+1 Y-90 2.05x10-3 Xe-133 4.68x10+3 Kr-88 2.30x10+2 Rb-89 7.91x10-6 Xe-135m 1.64 Y-95 1.10x10-15 Sr-89 3.78x10-1 Xe-135 1.54 Zr-95 6.89x10-9 Y-89m 3.78x10-5 Ce-144 1.40x10-7 NB-95 6.90x10-9 Rb-88 2.30x10+2 Pr-144 1.40x10-7 Nb-95m 1.38x10-10 Rb-87 2.61x10-8 Ce-143 4.61x10-9 Y-94 3.43x10-11 O-19 1.10x10-8 Pr-143 3.49x10-8 Sr-93 1.39x10-15 F-18 5.23 La-141 2.38x10-14 Y-93 9.94x10-7 Br-83 2.13x10-3 Ce-141 2.08x10-6 Zr-93 2.38x10-11 Br-84 6.23x10-4 Ba-140 1.82x10-4 Nb-93m 1.30x10-11 Br-85 1.05x10-6 La-140 2.04x10-4 Sr-92 3.38x10-6 I-131 1.61x10-1 Cs-137 6.47x10-3 Y-92 7.40x10-6 I-132 1.59x10-2 Cs-135 3.64x10-4 Sr-91 7.37x10-5 I-133 1.15x10-1 Kr-83m 1.90x10+1 Y-91 9.86x10-5 I-134 1.05x10-2 Kr-85m 1.20x10+2 Y-91m 4.74x10-5 I-135 5.41x10-2 N-13 1.98 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout the second half of adsorber number 1, which is composed of two parallel units, 1AS371 and 1BS371.
LGS UFSAR CHAPTER 12 12.2-129 REV. 13, SEPTEMBER 2006 Table 12.2-81(c)
ADSORBER NUMBER 2 (UNIT 1)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 8.93 Kr-85 1.11 Y-90 2.05x10-5 Xe-133m 1.39x10+1 Kr-87 4.56 Rb-89 1.30x10-12 Xe-133 2.36x10+3 Kr-88 8.73x10+1 Sr-89 3.77x10-3 Xe-135m 8.60x10-1 Zr-95 6.88x10-11 Y-89m 3.77x10-7 Xe-135 1.54x10-1 Nb-95 6.90x10-11 Rb-88 8.74x10+1 Ce-144 1.38x10-9 Nb-95 1.38x10-12 Rb-87 2.87x10-9 Pr-144 1.38x10-9 Y-94 8.05x10-17 N-13 7.33x10-1 Ce-143 5.39x10-12 Y-93 7.55x10-9 O-19 1.28x10-17 Pr-143 2.84x10-10 Zr-93 2.38x10-13 F-18 4.80 Ce-141 1.90x10-8 Nb-93m 1.30x10-13 Br-83 1.99x10-5 Ba-140 1.45x10-6 Sr-92 1.19x10-8 Br-84 4.56x10-6 La-140 1.65x10-6 Y-92 4.40x10-8 Br-85 3.86x10-10 Cs-137 6.46x10-5 Sr-91 5.50x10-7 I-131 1.61x10-3 Cs-135 4.77x10-6 Y-91 9.85x10-7 I-132 1.47x10-4 Kr-83m 4.29 Y-91m 3.55x10-7 I-133 1.14x10-3 Kr-85m 6.64x10+1 Sr-90 2.05x10-5 I-134 8.70x10-5 I-135 5.28x10-4 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 2, which composed of two parallel units, 1CS371 and 1DS371.
LGS UFSAR CHAPTER 12 12.2-130 REV. 13, SEPTEMBER 2006 Table 12.2-81(d)
ADSORBER NUMBER 3 (UNIT 1)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 7.23 Kr-85m 3.03x10+1 Y-90 2.05x10-7 Xe-133m 4.61 Kr-85 9.73x10-1 Rb-89 9.51x10-20 Xe-133 1.47x10+3 Kr-87 4.00x10-1 Sr-89 3.76x10-5 Xe-135m 4.63x10-1 Kr-88 2.73x10+1 Y-89m 3.76x10-9 Xe-135 2.48x10-6 Zr-95 6.86x10-13 Rb-88 2.74x10+1 Ce-144 1.37x10-11 Nb-95 6.90x10-13 Rb-87 2.58x10-10 Pr-144 1.37x10-11 Nb-95m 1.38x10-14 N-13 2.73x10-1 Ce-143 8.79x10-15 Y-93 5.62x10-11 F-18 4.50 Pr-143 2.37x10-12 Zr-93 2.38x10-15 Br-83 1.85x10-7 Ce-141 1.76x10-10 Nb-93m 1.30x10-15 Br-84 3.33x10-8 Ba-140 1.19x10-8 Sr-92 3.88x10-11 Br-85 1.38x10-13 La-140 1.37x10-8 Y-92 2.24x10-10 I-131 1.61x10-5 Cs-137 6.46x10-7 Sr-91 4.02x10-9 I-132 1.37x10-6 Cs-135 1.57x10-6 Y-91 9.84x10-9 I-133 1.13x10-5 Kr-83m 8.15x10-1 Y-91m 2.59x10-9 I-134 7.18x10-7 Sr-90 2.05x10-7 I-135 5.15x10-6 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
(3)
Based on 150 scfm main condenser air inleakage.
(4)
This activity is assumed to be uniformly distributed throughout adsorber number 3, which is composed to two parallel units, 1ES371 and 1FS271.
LGS UFSAR CHAPTER 12 12.2-131 REV. 13, SEPTEMBER 2006 Table 12.2-81(e)
ADSORBER NUMBER 4 (UNIT 1)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE Ci)
Xe-131m 3.08 Kr-85m 9.53 Sr-90 2.05x10-9 Xe-133m 9.71x10-1 Kr-85 4.86x10-1 Y-90 2.05x10-9 Xe-133 5.14x10+2 Kr-87 3.63x10-2 Sr-89 3.76x10-7 Xe-135m 1.36x10-1 Kr-88 6.52 Y-89m 3.76x10-11 Xe-135 8.23x10-2 Zr-95 6.85x10-15 Rb-88 6.53 Ce-144 1.36x10-13 Nb-95 6.90x10-15 Rb-87 2.33x10-11 Pr-144 1.36x10-13 NB-95m 1.38x10-16 N-13 5.99x10-2 Ce-143 1.43x10-17 Y-93 4.34x10-13 F-18 2.04 Pr-143 1.97x10-14 Zr-93 2.38x10-17 Br-83 1.73x10-9 Ce-141 1.63x10-12 Nb-93m 1.30x10-17 Br-84 2.41x10-10 Ba-140 9.81x10-11 Sr-92 1.45x10-13 Br-85 4.53x10-17 La-140 1.12x10-10 Y-92 1.17x10-12 I-131 1.60x10-7 Cs-137 6.46x10-9 Sr-91 3.05x10-11 I-132 1.27x10-8 Cs-135 7.69x10-7 Y-91 9.83x10-11 I-133 1.12x10-7 Kr-83m 1.39x10-1 Y-91m 1.97x10-11 I-134 5.89x10-9 I-135 5.02x10-8 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
(3)
Based on 150 scfm main condenser air inleakage.
(4)
This activity is assumed to be uniformly distributed throughout adsorber number 4, which is composed of one unit, 1GS371.
LGS UFSAR CHAPTER 12 12.2-132 REV. 13, SEPTEMBER 2006 Table 12.2-81(f)
ADSORBER NUMBER 1 (UNIT 2)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 1.71x10+1 Cs-135 3.20x10-2 Rb-91 2.82x10-3 Xe-133m 2.06x10+2 Kr-83m 8.96x10+1 Sr-91 9.58x10-3 Xe-133 8.12x10+3 Kr-85m 2.40x10+2 Y-91 9.57x10-3 Xe-135m 1.25x10+1 Kr-85 1.10 Y-91m 5.66x10-3 Xe-135 3.50x10+3 Kr-87 3.97x10+2 Rb-90 4.47x10-1 Xe-137 3.09x10-3 Kr-88 6.59x10+2 Sr-90 2.96x10-1 Xe-138 4.01x10+1 Kr-89 4.08x10+1 Y-90 2.96x10-1 Ce-144 1.37x10-5 Kr-90 3.95x10-1 Rb-89 4.10x10+1 Pr-144 1.37x10-5 Kr-91 3.64x10-5 Sr-89 4.06x10+1 Nd-144 1.54x10-19 Kr-92 3.36x10-16 Y-89m 4.06x10-3 La-143 2.13x10-7 Sr-95 9.07x10-8 Rb-88 6.59x10+2 Ce-143 3.80x10-6 Y-95 6.20x10-7 Rb-87 2.27x10-7 Pr-143 3.82x10-6 Zr-95 6.66x10-7 N-13 5.31 Ba-142 1.29x10-6 Nb-95 6.66x10-7 N-16 1.70x10+1 La-142 3.81x10-5 Nb-95m 1.33x10-8 N-17 1.27x10-3 Ba-141 2.35x10-5 Rb-94 3.17x10-20 O-19 7.61 La-141 1.99x10-4 Sr-94 4.44x10-6 F-18 5.70 Ce-141 2.19x10-4 Y-94 1.39x10-5 Br-83 2.28x10-1 Cs-140 2.42x10-18 Rb-93 3.57x10-12 Br-84 8.49x10-2 Ba-140 2.22x10-2 Sr-93 1.04x10-4 Br-85 2.85x10-3 La-140 2.23x10-2 Y-93 1.25x10-4 I-131 1.61x10+1 Cs-139 1.94x10-3 Zr-93 2.30x10-9 I-132 1.71 Ba-139 9.12x10-2 Nr-93m 1.25x10-9 I-133 1.15x10+1 Cs-138 4.18x10+1 Rb-92 1.44x10-11 I-134 1.27 Cs-137 6.38x10-1 Sr-92 9.29x10-4 I-135 5.54 Y-92 9.34x10-4 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 1, which is composed of one unit, 2AS371.
LGS UFSAR CHAPTER 12 12.2-133 REV. 13, SEPTEMBER 2006 Table 12.2-81(g)
ADSORBER NUMBER 2 (UNIT 2)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 1.06x10+1 Kr-87 3.38x10+1 Y-90 2.96x10-3 Xe-133 4.88x10+1 Kr-88 1.95x10+2 Rb-89 3.71x10-6 Xe-133 3.84x10+3 Y-95 3.39x10-16 Sr-89 4.05x10-1 Xe-135m 1.68 Zr-95 6.65x10-9 Y-89m 4.05x10-5 Xe-135 1.70 Nb-95 6.66x10-9 Rb-88 1.95x10+2 Ce-144 1.35x10-7 Nb-95 1.33x10-10 Rb-87 2.16x10-8 Pr-144 1.35x10-7 Y-94 1.79x10-11 N-13 2.01 Ce-143 4.44x10-9 Sr-93 2.99x10-16 0-19 1.09x10-8 Pr-143 3.37x10-8 Y-93 9.41x10-7 F-18 5.40 La-141 2.28x10-14 Zr-93 2.30x10-11 Br-83 2.13x10-3 Ce-141 2.01x10-6 Nb-93m 1.25x10-11 Br-84 6.23x10-4 Ba-140 1.76x10-4 Sr-92 3.02x10-6 Br-85 1.06x10-6 La-140 1.97x10-4 Y-92 6.92x10-6 I-131 1.61x10-1 Cs-137 6.38x10-3 Sr-91 7.00x10-5 I-132 1.59x10-2 Cs-135 3.36x10-4 Y-91 9.57x10-5 I-133 1.15x10-1 Kr-83m 1.59x10+1 Y-91m 4.51x10-5 I-134 1.05x10-2 Kr-85m 1.02x10+2 Sr-90 2.96x10-3 I-135 5.41x10-2 Kr-85 8.91x10-1 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 2, which is composed of two parallel units, 2BS371 and 2CS371.
LGS UFSAR CHAPTER 12 12.2-134 REV. 13, SEPTEMBER 2006 Table 12.2-81(h)
ADSORBER NUMBER 3 (UNIT 2)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 8.73 Kr-85 8.91x10-1 Xe-133m 1.77x10+1 Kr-87 4.93 Rb-89 2.76x10-12 Xe-133 2.50x10+3 Kr-88 8.17x10+1 Sr-89 4.05x10-3 Xe-135m 8.45x10-1 Zr-95 6.64x10-11 Y-89m 4.05x10-7 Xe-135 1.60x10-1 Nb-95 6.66x10-11 Rb-88 8.18x10+1 Ce-144 1.34x10-9 Nb-95m 1.33x10-12 Rb-87 3.04x10-9 Pr-144 1.34x10-9 Y-94 1.32x10-16 N-13 7.08x10-1 Ce-143 8.42x10-12 Y-93 7.42x10-9 O-19 7.16x10-18 Pr-143 2.88x10-10 Zr-93 2.30x10-13 F-18 4.79 Ce-141 1.87x10-8 Nb-93m 1.25x10-13 Br-83 1.98x10-5 Ba-140 1.47x10-6 Sr-92 1.23x10-8 Br-84 4.51x10-6 La-140 1.68x10-6 Y-92 4.41x10-8 Br-85 3.47x10-10 Cs-137 6.38x10-5 Sr-91 5.44x10-7 I-131 1.61x10-3 Cs-135 4.82x10-6 Y-91 9.57x10-7 I-132 1.47x10-4 Kr-83m 4.26 Y-91m 3.51x10-7 I-133 1.14x10-3 Kr-85m 5.90x10+1 Sr-90 2.96x10-5 I-134 8.64x10-5 Y-90 2.96x10-5 I-135 5.27x10-4 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 3, which is composed of two parallel units, 2DS371 and 2ES371.
LGS UFSAR CHAPTER 12 12.2-135 REV. 13, SEPTEMBER 2006 Table 12.2-81(i)
ADSORBER NUMBER 4 (UNIT 2)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 7.20 Kr-85 8.51x10-1 Rb-89 2.06x10-18 Xe-133m 6.45 Kr-87 7.08x10-1 Sr-89 4.04x10-5 Xe-133 1.62x10+3 Kr-88 3.32x10+1 Y-89m 4.04x10-9 Xe-135m 4.55x10-1 Zr-95 6.63x10-13 Rb-88 3.32x10+1 Xe-135 1.69x10-1 Nb-95 6.66x10-13 Rb-87 4.35x10-10 Ce-144 1.33x10-11 Nb-95m 1.33x10-14 N-13 2.64x10-1 Pr-144 1.33x10-11 Y-93 5.86x10-11 F-18 4.49 Ce-143 1.59x10-14 Zr-93 2.30x10-15 Br-83 1.85x10-7 Pr-143 2.44x10-12 Nb-93m 1.25x10-15 Br-84 3.29x10-8 Ce-141 1.74x10-10 Sr-92 4.99x10-11 Br-85 1.24x10-13 Ba-140 1.23x10-8 Y-92 2.59x10-10 I-131 1.61x10-5 La-140 1.42x10-8 Sr-91 4.22x10-9 I-132 1.37x10-6 Cs-137 6.37x10-7 Y-91 9.55x10-9 I-133 1.13x10-5 Cs-135 1.59x10-6 Y-91m 2.72x10-9 I-134 7.13x10-7 Kr-83m 1.15 Sr-90 2.96x10-7 I-135 5.14x10-6 Kr-85m 3.27x10+1 Y-90 2.96x10-7 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 4, which is composed of two parallel units, 2FS371 and 2GS371.
LGS UFSAR CHAPTER 12 12.2-136 REV. 13, SEPTEMBER 2006 Table 12.2-81(j)
ADSORBER NUMBER 5 (UNIT 2)(1)(3)(4)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(2)
(Ci)
ISOTOPE (Ci)
ISOTOPE (Ci)
Xe-131m 6.01 Kr-85m 1.99x10+1 Sr-90 2.96x10-9 Xe-133m 2.36 Kr-85 8.92x10-1 Y-90 2.96x10-9 Xe-133 1.06x10+3 Kr-87 1.14x10-1 Sr-89 4.03x10-7 Xe-135m 2.31x10-1 Kr-88 1.49x10+1 Y-89m 4.03x10-11 Xe-135 1.67x10-1 Zr-95 6.62x10-15 Rb-88 1.49x10+1 Ce-144 1.32x10-13 Nb-95 6.66x10-15 Rb-87 6.98x10-11 Pr-144 1.32x10-13 Nb-95m 1.33x10-16 N-13 9.29x10-2 Ce-143 3.02x10-17 Y-93 4.67x10-13 F-18 3.98 Pr-143 2.06x10-14 Zr-93 2.30x10-17 Br-83 1.72x10-9 Ce-141 1.63x10-12 Nb-93m 1.25x10-17 Br-84 2.38x10-10 Ba-140 1.03x10-10 Sr-92 2.11x10-13 Br-85 4.08x10-17 La-140 1.19x10-10 Y-92 1.49x10-12 I-131 1.60x10-7 Cs-137 6.37x10-9 Sr-91 3.32x10-11 I-132 1.27x10-8 Cs-135 1.54x10-6 Y-91 9.55x10-11 I-133 1.12x10-7 Kr-83m 3.53x10-1 Y-91m 2.14x10-11 I-134 5.85x10-9 I-135 5.01x10-8 (1) Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2) Isotopes with activities less than 1.0x10-20 are not listed.
(3) Based on 150 scfm main condenser air inleakage.
(4) This activity is assumed to be uniformly distributed throughout adsorber number 5, which is composed of two parallel units, 2HS371 and 2IS371.
LGS UFSAR CHAPTER 12 12.2-137 REV. 13, SEPTEMBER 2006 Table 12.2-82 OUTLET HEPA FILTER SHIELDING DESIGN SOURCE TERMS(1)(3)
UNIT 1 Activity Activity Isotope(2)
(Ci)
Isotope (Ci)
Xe-131m 2.03x10-4 Zr-93 2.41x10-19 Xe-133m 5.27x10-5 Nb-93m 1.31x10-19 Xe-133 3.17x10-2 Sr-92 8.94x10-16 Xe-135m 2.88x10-3 Y-92 8.49x10-15 Xe-135 2.06x10-3 Sr-91 2.68x10-13 Ce-144 1.37x10-15 Y-91 9.92x10-13 Pr-144 1.37x10-15 Y-91m 1.73x10-13 CE-143 5.79x10-20 SR-90 2.07x10-11 Pr-143 1.81x10-16 Y-90 2.07x10-11 Ce-141 1.58x10-14 Sr-89 3.79x10-9 Ba-140 8.98x10-13 Y-89m 3.79x10-13 La-140 1.03x10-12 Rb-88 2.04x10-2 Cs-137 6.53x10-11 Rb-87 2.54x10-13 Cs-135 2.68x10-8 N-13 1.14x10-3 Kr-83m 4.29x10-4 F-18 4.99x10-2 Kr-85m 1.28x10-2 Br-83 1.68x10-11 Kr-85 7.60x10-4 Br-84 2.07x10-12 Kr-87 3.20x10-5 Br-85 8.62x10-20 Kr-88 7.96x10-3 I-131 1.62x10-9 Zr-95 6.91x10-17 I-132 1.23x10-10 Nb-95 6.97x10-17 I-133 1.12x10-9 Nb-95m 1.39x10-18 I-134 5.40x10-11 Y-93 3.85x10-15 I-135 5.00x10-10
LGS UFSAR CHAPTER 12 12.2-138 REV. 13, SEPTEMBER 2006 Table 12.2-82 (Cont'd)
OUTLET HEPA FILTER SHIELDING DESIGN SOURCE TERMS(1)(3)
UNIT 2 Activity Activity Isotope(2)
(Ci)
Isotope (Ci)
Xe-131m 2.03x10-4 Zr-93 2.33x10-19 Xe-133m 5.28x10-5 Nb-93m 1.27x10-19 Xe-133 3.17x10-2 Sr-92 8.64x10-16 Xe-135m 2.05x10-3 Y-92 8.20x10-15 Xe-135 2.09x10-3 Sr-91 2.60x10-13 Ce-144 1.32x10-15 Y-91 9.63x10-13 Pr-144 1.32x10-15 Y-91m 1.68x10-13 Pr-143 1.75x10-16 Sr-90 2.99x10-11 Ce-141 1.53x10-14 Y-90 2.99x10-11 Ba-140 8.70x10-13 Sr-89 4.06x10-9 La-140 1.00x10-12 Y-89m 4.06x10-13 Cs-137 6.44x10-11 Rb-88 2.06x10-13 Cs-135 3.49x10-8 Rb-87 7.23x10-13 Kr-83m 4.25x10-4 N-13 6.71x10-4 Kr-85m 1.27x10-2 F-18 4.75x10-2 Kr-85 7.60x10-4 Br-83 1.62x10-11 Kr-87 3.20x10-5 Br-84 1.75x10-12 Kr-88 7.95x10-3 Br-85 1.46x10-20 Zr-95 6.68x10-17 I-131 1.62x10-9 Nb-95 6.73x10-17 I-132 1.19x10-10 Nb-95m 1.34x10-18 I-133 1.12x10-9 Y-93m 3.71x10-19 I-134 4.87x10-11 I-135 4.94x10-10 (1)
Based on shielding design source terms given in Tables 12.2-1 and 12.2-4.
(2)
Isotopes with activities less than 1.0x10-20 are not listed.
(3)
Based on 150 scfm main condenser air inleakage.
LGS UFSAR CHAPTER 12 12.2-139 REV. 13, SEPTEMBER 2006 Table 12.2-83 CONTROL ROOM SHIELDING DESIGN SOURCE TERMS - PRIMARY CONTAINMENT ACTIVITY (CURIES) AT TIME POST-LOCA(1)(2)(3)(4)
ISOTOPE 0.0 HR
.50 HR 1.00 HR 2.00 HR 4.00 HR 8.00 HR 16.00 HR 24.00 HR 96.00 HR 240.00 HR 720.00HR I-131 2.22E+07 2.21E+07 2.21E+07 2.20E+07 2.18E+07 2.15E+07 2.09E+07 2.03E+07 1.54E+07 8.92E+06 1.44E+06 I-132 3.30E+07 2.84E+07 2.43E+07 1.79E+07 9.67E+06 2.83+06 2.42E+05 2.07E+04 5.14E-06 3.15E-25 0.00E+00 I-133 5.11E+07 5.03E+07 4.94E+07 4.77E+07 4.46E+07 3.89E+07 2.95E+07 2.24E+07 1.90E+06 1.36E+04 9.56E-04 I-134 5.95E+07 3.99E+07 2.67E+07 1.20E+07 2.43E+06 9.87E+04 1.64E+02 2.71E-01 2.58E-26 0.00E+00 0.00E+00 I-135 4.65E+07 4.42E+07 4.19E+07 3.77E+07 3.07E+07 2.02E+04 8.78E+06 3.81E+06 2.10E+03 6.40E-04 1.21E-25 I-136 2.37E+07 6.88E+00 2.00E-06 1.69E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 3.89E+06 3.37E+06 2.92E+06 2.18E+06 1.22E+06 3.88E+05 3.87E+04 3.86E+03 3.75E-06 3.55E-24 0.00E+00 Br-84 7.02E+06 3.64E+06 1.90E+06 5.11E+05 3.71E+04 1.97E+02 5.52E-03 1.55E-07 0.00E+00 0.00E+00 0.00E+00 Br-85 9.84E+06 9.44E+03 9.04E+00 8.30E-06 7.01E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-83m 1.59E+07 1.33E+07 1.09E+07 7.52E+06 3.57E+06 8.02E+05 4.05E+04 2.04E+03 4.38E-09 2.00E-32 0.00E+00 Kr-85m 3.97E+07 3.67E+07 3.39E+07 2.90E+07 2.11E+07 1.13E+07 3.20E+06 9.12E+03 1.11E+01 1.63E-09 0.00E+00 Kr-85 1.35E+06 1.35E+06 1.35E+06 1.35E+06 1.35E+06 1.35E+06 1.35E+06 1.34E+06 1.32E+06 1.28E+06 1.15E+06 Kr-87 7.63E+07 5.80E+07 4.42E+07 2.55E+07 8.55E+06 9.58E+05 1.20E+04 1.51E+02 1.17E-15 0.00E+00 0.00E+00 Kr-88 1.06E+08 9.38E+07 8.29E+07 6.48E+07 3.95E+07 1.47E+07 2.03E+06 2.82E+05 5.24E-03 1.82E-18 0.00E+00 Kr-89 1.40E+08 2.00E+05 2.87E+02 5.85E+07 2.45E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 5.19E+06 5.15E+06 5.12E+06 5.05E+06 4.93E+06 4.67E+06 4.21E+06 3.79E+06 1.49E+06 2.28E+05 4.44E+02 Xe-133 2.04E+08 2.03E+08 2.02E+08 2.01E+08 1.99E+08 1.95E+08 1.86E+08 1.77E+08 1.18E+08 5.19E+07 3.39E+06 Xe-135m 5.49E+07 1.45E+07 3.80E+06 2.63E+05 1.26E+03 2.90E-02 1.53E-11 8.09E-21 0.00E+00 0.00E+00 0.00E+00 Xe-135 1.92E+08 1.85E+08 1.79E+08 1.65E+08 1.42E+08 1.05E+08 5.70E+07 3.10E+07 1.31E+05 2.29E+00 3.28E-16 Xe-137 1.84E+08 8.69E+05 4.13E+03 9.30E-02 4.72E-11 1.22E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 1.81E+08 5.48E+07 1.66E+07 1.54E+06 1.32E+04 9.67E-01 5.20E-09 2.79E-17 0.00E+00 0.00E+00 0.00E+00 (1)
Assumes the reactor to have been operating for 1000 days at 3458 Mw(t) at time of LOCA.
(2)
Assumes 100% of noble gases and 25% of halogens in core are released to primary containment atmosphere.
(3)
Assumes 0.5% per day leak rate from primary to secondary containment.
(4)
This activity is assumed to be uniformly distributed throughout the free air volume of primary containment, including the drywell and wetwell.
This volume is 404,000 ft3.
LGS UFSAR CHAPTER 12 12.2-140 REV. 13, SEPTEMBER 2006 Table 12.2-84 CONTROL ROOM SHIELDING DESIGN SOURCE TERMS - REACTOR ENCLOSURE ACTIVITY (CURIES) AT TIME POST-LOCA(1)(2)(3)(4)(5)(6)
ISOTOPE 0.0 HR 50 HR 1.00 HR 2.00 HR 4.00 HR 8.00 HR 16.00 HR 24.00 HR 96.00 HR 240.00 HR 720.00 HR I-131 0.00E+00 1.88E+03 3.09E+03 4.39E+03 5.14E+03 5.23E+03 5.08E+03 4.93E+03 3.74E+03 2.17E+03 3.50E+02 I-132 0.00E+00 2.40E+03 3.40E+03 3.56E+03 2.27E+03 6.86E+02 5.89E+01 5.04E+00 1.24E-09 7.66E-29 0.00E+00 I-133 0.00E+00 4.25E+03 6.91E+03 9.51E+03 1.05E+04 9.44E+03 7.17E+03 5.46E+03 4.61E+02 3.29E+00 2.33E-07 I-134 0.00E+00 3.38E+03 3.74E+03 2.40E+03 5.70E+02 2.40E+01 3.98E-02 6.60E-05 6.27E-30 0.00E+00 0.00E+00 I-135 0.00E+00 3.74E+03 5.87E+03 7.53E+03 7.21E+03 4.91E+01 2.13E+0 9.27E+02 5.11E-01 1.56E-07 2.94E-29 I-136 0.00E+00 5.82E-04 2.80E-10 3.38E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 2.86E+02 4.08E+02 4.36E+02 2.89E+02 9.41E+01 9.39E+00 9.37E-01 9.11E-10 8.62E-28 0.00E+00 Br-84 0.00E+00 3.09E+02 2.65E+03 1.02E+02 8.74E+00 4.78E-02 1.35E-06 3.76E-11 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 7.99E-01 1.26E-03 1.65E-09 1.65E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-83m 0.00E+00 1.36E+03 2.23E+03 3.01E+03 2.73E+03 1.13E+03 9.86E+01 6.48E+00 2.15E-11 1.00E-34 0.00E+00 Kr-85m 0.00E+00 3.78E+03 6.92E+03 1.16E+04 1.62E+04 1.60E+04 7.81E+03 2.89E+03 5.46E-02 8.19E-12 0.00E+00 Kr-85 0.00E+00 1.39E+02 2.74E+02 5.39E+02 1.03E+03 1.91E+03 3.27E+03 4.24E+03 6.51E+03 6.43E+03 5.79E+03 Kr-87 0.00E+00 5.98E+03 9.01E+03 1.02E+04 6.56E+03 1.36E+03 2.93E+01 4.78E-01 5.76E-18 0.00E+00 0.00E+00 Kr-88 0.00E+00 9.67E+03 1.69E+04 2.59E+04 3.03E+04 2.08E+04 4.96E+03 8.91E+02 2.58E-05 9.13E-21 0.00E+00 Kr-89 0.00E+00 2.06E+01 5.84E-02 2.35E-07 1.88E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 0.00E+00 5.31E+02 1.04E+03 2.02E+03 3.78E+03 6.63E+03 1.03E+04 1.20E+04 7.33E+03 1.15E+03 2.23E+00 Xe-133 0.00E+00 2.09E+04 4.13E+04 8.05E+04 1.53E+05 2.75E+05 4.53E+05 5.62E+05 5.81E+05 2.61E+05 1.70E+04 Xe-135m 0.00E+00 1.49E+03 7.76E+02 1.05E+02 9.69E-01 4.11E-05 3.73E-14 2.58E-23 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 1.91E+04 3.63E+04 6.60E+04 1.09E+05 1.49E+05 1.39E+05 9.82E+04 6.43E+02 1.15E-02 1.65E-18 Xe-137 0.00E+00 8.96E+01 3.41E-01 3.72E-05 3.63E-14 1.73E-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 5.64E+03 3.40E+03 6.16E+02 1.01E+01 1.38E-03 1.26E-00 8.84E-20 0.00E+00 0.00E+00 0.00E+00
=____________________
(1)
Assumes the reactor to have been operating for 1000 days at 3458 Mw(t) at time of LOCA.
(2)
Assumes 100% of noble gases and 25% of halogens in core are released to primary containment atmosphere.
(3)
Assumes 0.5% per day leak rate from primary to secondary containment.
(4)
Assumes a secondary containment recirculation system flow rate of 60,000 cfm with a charcoal filter efficiency of 0.95 for halogens.
(5)
Assumes a SGTS flow rate of 2778 cfm with a charcoal filter efficiency of 0.99 for halogens.
(6)
This activity is assumed to be uniformly distributed throughout the free air volume of the secondary containment. This volume is 4,000,000 ft3, and includes the common refueling floor for both units.
LGS UFSAR CHAPTER 12 12.2-141 REV. 13, SEPTEMBER 2006 Table 12.2-85 CONTROL ROOM SHIELDING DESIGN SOURCE TERMS - TURBINE ENCLOSURE AND CONTROL STRUCTURE(1)(2)(3)(4)(5)(6)(7)
TOTAL INTEGRATED ACTIVITY (CURIES) RELEASED TO EXTERNAL ENVIRONMENT FROM SGTS (NO DECAY)
ISOTOPE 0 to 8 HRS 8 to 24 HRS 24 to 96 HRS 96 to 720 HRS I-131 7.56E-01 1.69E+00 6.47E+00 1.87E+01 I-132 3.54E-01 4.62E-02 4.08E-04 0.00E+00 I-133 1.52E+00 2.42E+00 3.03E+00 2.81E-01 I-134 1.94E-01 6.12E-04 0.00E+00 0.00E+00 I-135 1.03E+00 7.97E-01 1.88E-01 0.00E+00 I-136 1.10E-04 0.00E+00 0.00E+00 0.00E+00 Br-83 4.44E-02 6.75E-03 6.12E-05 0.00E+00 Br-84 1.07E-02 0.00E+00 0.00E+00 0.00E+00 Br-85 2.08E-04 0.00E+00 0.00E+00 0.00E+00 Kr-83m 7.30E+02 1.58E+02 7.14E-01 0.00E+00 Kr-85m 4.54E+03 5.63E+03 8.62E+02 0.00E+00 Kr-85 3036E+02 2.14E+03 1.76E+04 1.61E+05 Kr-87 1.94E+03 1.21E+02 0.00E+00 0.00E+00 Kr-88 8.12E+03 4.63E+03 1.63E+02 0.00E+00 Kr-89 7.06E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 1.21E+03 6.64E+03 3.18E+04 2.39E+04 Xe-133 4.93E+04 2.95E+05 1.92E+06 4.20E+06 Xe-135m 6.59E+01 0.00E+00 0.00E+00 0.00E+00 Xe-135 3.25E+04 8.95E+04 6.47E+04 3.06E+02 Xe-137 1.39E+01 0.00E+00 0.00E+00 0.00E+00 Xe-138 1.71E+02 0.00E+00 0.00E+00 0.00E+00 (1)
Assumes reactor to have been operating for 1000 days at 3458 Mw(t) at time of LOCA.
(2)
Assumes 100% of noble gases and 25% of halogens in core are released to primary containment atmosphere.
(3)
Assumes 0.5% per day leak rate from primary to secondary containment.
(4)
Assumes a secondary containment recirculation system flow rate of 60,000 cfm with a charcoal filter efficiency of 0.95 for halogens.
(5)
Assumes an SGTS flow rate of 2778 cfm with a charcoal filter efficiency of 0.99 for halogens.
(6)
Assumes turbine enclosure and control structure intake environs cloud immediately, allowing only for atmospheric dispersion.
(7)
Building wake atmospheric dispersion factors (X/Q) used are given by post-LOCA time period:
0 to 8 HRS 3.46x10-4 sec/m3 8 to 24 HRS 2.04x10-4 sec/m3 24 to 96 HRS 1.30x10-4 sec/m3 96 to 720 HRS 5.71x10-5 sec/m3
LGS UFSAR CHAPTER 12 12.2-142 REV. 13, SEPTEMBER 2006 Table 12.2-86 CONTROL ROOM SHIELDING DESIGN SOURCE TERMS - STANDBY GAS TREATMENT SYSTEM CARBON FILTER ACTIVITY (CURIES) AT TIME POST-LOCA(1)(2)(3)(4)(5)(6)
ISOTOPE 0.0 HR
.50 HR 1.00 HR 2.00 HR 4.00 HR 8.00 HR 16.00 HR 24.00 HR 96.00 HR 240.00 HR 720.00 HR I-131 0.00E+00 1.05E+00 3.68E+00 1.16E+01 3.18E+01 7.46E+01 1.57E+02 2.35E+02 7.48E+02 1.11E+03 5.66E+02 I-132 0.00E+00 1.34E+00 4.04E+00 9.45E+00 1.41E+01 9.80E+00 1.83E+00 2.41E-01 2.49E-10 3.91E-29 0.00E+00 I-133 0.00E+00 2.38E+00 8.21E+00 2.52E+00 6.48E+01 1.35E+02 2.22E+02 2.60E+02 9.20E+01 1.68E+00 3.75E-07 I-134 0.00E+00 1.89E+00 4.45E+00 6.34E+00 3.53E+00 3.42E-01 1.23E-03 3.15E-06 1.25E-30 0.00E+00 0.00E+00 I-135 0.00E+00 2.09E+00 6.98E+00 2.00E+00 4.46E+01 7.01E+01 6.61E+01 4.43E+01 1.02E-01 7.49E-08 4.75E-29 I-136 0.00E+00 3.25E-07 3.33E-13 8.96E-26 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 1.59E-01 4.86E-01 1.15E+00 1.79E+00 1.35E+00 2.91E-01 4.47E-02 1.82E-10 4.40E-28 0.00E+00 Br-84 0.00E+00 1.72E-01 3.15E-01 2.70E-01 5.41E-02 6.81E-04 4.15E-08 1.80E-12 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 4.46E-04 1.50E-06 4.39E-12 1.02E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (1)
Assumes the reactor to have been operating for 1000 days at 3458 Mw(t) at time of LOCA.
(2)
Assumes 100% of noble gases and 25% of halogens in core are released to primary containment atmosphere.
(3)
Assumes 0.5% per day leak rate from primary to secondary containment.
(4)
Assumes a secondary containment recirculation system flow rate of 60,000 cfm with a charcoal filter efficiency of 0.95 for halogens.
(5)
Assumes a SGTS flow rate of 2778 cfm with a charcoal filter efficiency of 0.99 for halogens.
(6)
This activity is assumed to be uniformly distributed throughout the SGTS carbon filter.
LGS UFSAR CHAPTER 12 12.2-143 REV. 13, SEPTEMBER 2006 Table 12.2-87 CONDENSATE STORAGE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
CARRYOVER COMPONENT Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 7.43x10-3 Cs-138 5.44x10-3 Re-187 7.09x10-18 Br-84 3.06x10-3 Ba-139 2.35x10-3 Ag-110 5.88x10-8 Br-85 1.16x10-4 Ba-140 2.22x10-3 Zn-69 8.17x10-7 I-131 6.15x10-2 Ba-141 5.30x10-4 Pu-239 4.88x10-9 I-132 6.51x10-2 Ba-142 3.08x10-4 U-235 1.81x10-20 I-133 2.20x10-1 Ce-141 2.43x10-5 Pm-147 3.43x10-9 I-134 4.46x10-2 Ce-143 5.45x10-6 Pr-144 9.14x10-6 I-135 1.54x10-1 Ce-144 9.24x10-6 La-142 3.32x10-4 Sr-89 8.07x10-4 Pr-143 9.76x10-6 La-141 4.95x10-4 Sr-90 6.09x10-5 Nd-147 3.41x10-6 La-140 8.10x10-4 Sr-91 5.38x10-3 Np-239 4.51x10-2 Te-129 6.29x10-6 Sr-92 3.03x10-3 Na-24 5.94x10-5 I-129 1.55x10-15 Zr-95 1.04x10-5 P-32 1.42x10-6 Rh-106 6.87x10-7 Zr-97 3.59x10-6 Cr-51 3.66x10-5 Rh-103m 4.63x10-6 Nb-95 1.11x10-5 Mn-54 3.02x10-6 Tc-99 2.36x10-10 Mo-99 4.33x10-3 Mn-56 3.76x10-4 Nb-97m 3.34x10-6 Tc-99m 1.83x10-2 Co-58 3.73x10-4 Nb-97 3.42x10-6 Tc-101 3.32x10-4 Co-60 3.78x10-5 Nb-95m 4.27x10-8 Ru-103 4.91x10-6 Fe-59 5.93x10-6 Y-92 2.66x10-3 Ru-106 6.87x10-7 Ni-65 2.25x10-6 Y-91 8.52x10-5 Te-129m 1.03x10-5 Zn-65 1.51x10-7 Y-91m 3.07x10-3 Te-132 1.00x10-2 Zn-69m 8.48x10-7 Y-90 1.70x10-5 Cs-134 2.12x10-4 Ag-110m 4.52x10-6 Y-89m 8.07x10-8 Cs-136 1.36 3.18x10-4
LGS UFSAR CHAPTER 12 12.2-144 REV. 13, SEPTEMBER 2006 Table 12.2-87 (Cont'd)
FALLOUT COMPONENT Activity Activity Activity Isotope(4)
(Ci)
Isotope (Ci)
Isotope (Ci Ba-144 2.50x10-9 Cs-139 9.64x10-3 Nb-93m 2.34x10-16 La-144 9.43x10-7 Ba-139 1.07x10-2 Rb-92 8.90x10-11 Ce-144 2.24x10-8 Cs-138 3.59x10-3 Sr-92 4.19x10-3 Pr-144 2.21x10-8 Cs-137 5.68x10-7 Y-92 3.67x10-3 Ba-143 1.45x10-8 Cs-135 8.40x10-13 Rb-91 2.96x10-3 La-143 3.16x10-5 Sr-95 1.03x10-6 Sr-91 7.71x10-3 Ce-143 1.43x10-5 Y-95 6.53x10-6 Y-91 1.22x10-4 Pr-143 9.49x10-7 Zr-95 1.02x10-7 Y-91m 4.40x10-3 Ba-142 3.21x10-4 Nb-95 2.70x10-9 Rb-90 6.50x10-3 La-142 3.46x10-4 Nb-95m 4.18x10-10 Sr-90 1.06x10-6 Cs-141 6.05x10-5 Rb-94 8.50x10-19 Y-90 2.95x10-7 Ba-141 2.84x10-3 Sr-94 4.02x10-5 Rb-89 4.96x10-3 La-141 2.60x10-3 Y-94 1.20x10-4 Sr-89 9.86x10-5 Ce-141 7.48x10-5 Rb-93 5.07x10-11 Y-89m 9.86x10-9 Cs-140 2.61x10-3 Sr-93 8.74x10-4 Rb-88 7.83x10-4 Ba-140 7.60x10-4 Y-93 7.24x10-4 Rb-87 4.77x10-17 La-140 2.77x10-4 Zr-93 1.27x10-12 (1)
Based on shielding design source terms listed in Tables 12.2-1 through 12.2-5.
(2)
Based on condensate activity with appropriate DFs applied: 2 for Cs and Rb; 10 for others.
(3)
Equilibrium activity of cleaned-up condensate flowing through a 200,000 gallon tank at 100 gpm.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-145 REV. 13, SEPTEMBER 2006 Table 12.2-88 REFUELING WATER STORAGE TANK SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
ACTIVITY ACTIVITY ACTIVITY ISOTOPE(4)
(Ci)
ISOTOPE (Ci)
ISOTOPE (ci)
Br-83 1.03x10-2 Cs-137 1.75x10-3 Tc-99 3.84x10-10 Br-84 4.92x10-3 Cs-138 1.75x10-1 Nb-97m 3.82x10-5 Br-85 2.92x10-4 Ba-139 7.25x10-2 Nb-97 3.05x10-5 I-131 1.87x10-2 Ba-140 1.30x10-2 Nb-95m 2.70x10-8 I-132 1.17x10-1 Ba-141 1.75x10-2 Y-92 4.06x10-2 I-133 1.17x10-1 Ba-142 1.07x10-2 Y-91 1.07x10-4 I-134 7.10x10-2 Ce-141 8.97x10-5 Y-91m 3.98x10-2 I-135 1.40x10-1 Ce-143 4.79x10-5 Y-90 1.16x10-5 Sr-89 4.51x10-3 Ce-144 5.10x10-5 Y-89m 4.50x10-7 Sr-90 3.35x10-4 Pr-143 5.53x10-5 Cs-135 1.72x10-12 Sr-91 8.14x10-2 Nd-147 2.02x10-5 Na-24 7.25x10-4 Sr-92 8.11x10-2 Np-239 3.37x10-1 P-32 8.27x10-6 Zr-95 5.82x10-5 Re-187 6.62x10-18 Cr-51 2.07x10-4 Zr-97 4.13x10-5 Ag-110 3.24x10-7 Mn-54 1.66x10-5 Nb-95 6.12x10-5 Zn-69 8.58x10-6 Mn-56 1.02x10-2 Mo-99 3.11x10-2 Pu-239 3.38x10-9 Co-58 2.08x10-3 Tc-99m 3.01x10-1 Pm-147 1.87x10-9 Co-60 2.08x10-4 Tc-101 1.12x10-2 Pr-144 4.75x10-5 Fe-59 3.32x10-5 Ru-103 2.76x10-5 La-142 9.94x10-3 Ni-65 6.11x10-5 Ru-106 3.79x10-6 La-141 1.12x10-2 Zn-65 8.32x10-7 Te-129m 5.81x10-5 La-140 6.64x10-4 Zn-69m 1.08x10-5 Te-132 6.95x10-2 Te-129 2.74x10-5 Ag-110m 2.50x10-5 Cs-134 1.17x10-3 I-129 6.16x10-16 W-187 1.14x10-3 Cs-136 7.96x10-4 Rh-103m 2.10x10-5 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
Filtered and demineralized fuel pool water (DF of 2 for Cs and Rb, DF of 10 for others) accumulated for 6.11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> at 1500 gpm.
(3)
This activity is in 550,000 gallons.
(4)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-146 REV. 13, SEPTEMBER 2006 Table 12.2-89 TRAVERSING INCORE PROBE MATERIALS DETECTOR REGION Material Weight (g) 304L stainless steel (Co 0.014%)
4.92 Commercially pure titanium 0.662 Alumina 0.885 Nickel/iron alloy 0.248 Copper 0.021 CABLE REGION Material Weight (g/inch)
AISI 304L stainless steel (Co 0.014%)
0.43 AISI 1070 carbon steel 2.16 Magnesium oxide (insulation) 0.0798
LGS UFSAR CHAPTER 12 12.2-147 REV. 13, SEPTEMBER 2006 Table 12.2-90 INTENTIONALLY LEFT BLANK
LGS UFSAR CHAPTER 12 12.2-148 REV. 13, SEPTEMBER 2006 Table 12.2-91 INTENTIONALLY LEFT BLANK
LGS UFSAR CHAPTER 12 12.2-149 REV. 13, SEPTEMBER 2006 Table 12.2-92 INTENTIONALLY LEFT BLANK
LGS UFSAR CHAPTER 12 12.2-150 REV. 13, SEPTEMBER 2006 Table 12.2-93 ESTIMATED IN-PLANT AIRBORNE RADIOACTIVE RELEASES(1)
(Ci/year)
TURBINE(2)
REACTOR RADWASTE(3)
ENCLOSURE ENCLOSURE ENCLOSURE ISOTOPE (PER UNIT)
(PER UNIT)
(PER PLANT)
H-3 4.1E+01 4.1E+0E Kr-83m Kr-85m 6.9E+01 6.1E+00 Kr-85 Kr-87 1.3E+02 6.1E+00 Kr-88 2.3E+02 6.1E+00 Kr-89 Xe-131m Xe-133m Xe-133 2.6E+02 1.3E+02 2.0E+01 Xe-135m 6.6E+02 9.4E+01 Xe-135 6.4E+02 6.9E+01 9.2E+01 Xe-137 Xe-138 1.4E+03 1.4E+01 I-131 1.9E-01 3.5E-01 1.0E-01 I-133 7.8E-01 1.4E+00 3.7E-01 Co-60 2.0E-03 2.0E-02 1.8E-01 Co-58 6.1E-04 1.2E-03 9.2E-03 Cr-51 1.3E-02 6.1E-04 1.8E-02 Mn-54 6.1E-04 6.1E-03 6.1E-02 Fe-59 5.1E-04 8.2E-04 3.1E-02 Zn-65 2.0E-04 4.1E-03 3.1E-01 Zr-95 1.0E-04 8.2E-04 1.0E-04 Sr-89 6.1E-03 1.8E-04 9.2E-04 Sr-90 2.0E-05 1.0E-05 6.1E-04 Sb-124 3.1E-04 4.1E-04 1.0E-04 Cs-134 3.1E-04 8.2E-03 9.2E-03 Cs-136 5.1E-02 6.1E-04 9.2E-04 Cs-137 6.1E-0E 1.1E-02 1.8E-02 Ba-140 1.1E-02 8.2E-04 2.0E-04 Ce-141 6.1E-04 2.0E-04 5.3E-03 (1)
BWR-GALE Computer Code (Reference 12.2-1).
(2)
Includes control structure releases.
(3)
Includes offgas enclosure releases.
LGS UFSAR CHAPTER 12 12.2-151 REV. 13, SEPTEMBER 2006 Table 12.2-94 ESTIMATED IN-PLANT DISTRIBUTION OF AIRBORNE RADIOACTIVITY RELEASES(1)
AIRBORNE RELEASE RELEASES FRACTION (%)
Turbine Enclosure(2)
Condenser areas 60.30 SJAE areas 7.00 Mechanical vacuum pump areas 3.50 Turbine hall areas 9.20 Other equipment areas(3) 20.00 100.00 Reactor Enclosure RWCU pump areas 23.65 RWCU filter/demineralizer areas 9.80 Refueling areas(4) 9.15 ECCS areas (RHR, HPCI, etc.)
7.40 Drywell areas 30.00 Other equipment areas(3) 20.00 100.00 Radwaste Enclosure(5)
Solids handling areas 8.40 Liquid waste handling areas 71.60 Other equipment areas(3) 20.00 100.00 (1)
Based on report for EPRI Research Project 274-1 (Reference 12.2-2).
(2)
Includes control structure equipment areas.
(3)
Assumes 80% of enclosure release by major areas listed and 20% by all other equipment areas within the enclosure.
(4)
All of reactor enclosure tritium is assumed to be released in the refueling area.
(5)
Includes offgas enclosure equipment areas.
LGS UFSAR CHAPTER 12 12.2-152 REV. 13, SEPTEMBER 2006 Table 12.2-95 REACTOR ENCLOSURE AIRBORNE SOURCE DESCRIPTIONS AREAROOM NOS. AND(1) TOTAL EXHAUST TOTAL ANNUAL(2)
DESIGNATION AREAS INCLUDED FLOW (cfm)
EXHAUST (cc/yr)
RWCU pump 503,504,505,507,508, 1.16x10+4 1.7x10+14 509,510,522 RWCU filter/demineralizer 502,600,609 2.63x10+3 3.9x10+13 Refueling 700 5.20x10+4 7.7x10+14 ECCS 102,103,108,109,203, 9.34x10+3 1.4x10+14 204,297,298,309 Drywell 400,400A,400B,400C, 1.10x10+4 1.3x10+13 400D,400E Others 115,209,296,399,402A, 3.26x10+4 4.9x10+14 403,406,407A,501,511, 518A,523,599,616,617, 618 (1) See drawings N-116, N-117, N-118, N-119, N-120, N-121, N-122, N-131, N-132, N-133, N-134, N-135, N-136, and N-137.
(2) Based on continuous release, 365 days per year except for drywell where release is assumed to occur entirely within 30 days.
LGS UFSAR CHAPTER 12 12.2-153 REV. 13, SEPTEMBER 2006 Table 12.2-96 TURBINE ENCLOSURE AIRBORNE SOURCE DESCRIPTIONS AREA ROOM NOS. AND(1)
TOTAL EXHAUST TOTAL ANNUAL(2)
DESIGNATION AREAS INCLUDED FLOW (cfm)
EXHAUST (cc/yr)
Condenser 253,254,255,256, 9.10x10+3 1.4x10+14 332,342,499 Steam jet air ejector 154,333,334 1.35x10+4 2.0x10+14 Mech vacuum pump 337 2.50x10+2 3.7x10+12 Turbine hall 544 2.40x10+4 3.6x10+14 Others 119,119A,119B,161, 4.85x10+4 7.2x10+14 162,163,165,249, 249A,259,264,299, 339,340,407,438, 439,440,441,498, 518,545,546,547, 551,621,624 (1) See drawings N-110, N-111, N-112, N-113, N-115, N-125, N-126, N-127, N-128, and N-130.
(2) Based on continuous release, 365 days per year.
LGS UFSAR CHAPTER 12 12.2-154 REV. 13, SEPTEMBER 2006 Table 12.2-97 RADWASTE AND OFFGAS ENCLOSURE AIRBORNE SOURCE DESCRIPTIONS AREA ROOM NOS. AND(1)
TOTAL EXHAUST TOTAL ANNUAL(2)
DESIGNATION AREAS INCLUDED FLOW (cfm)
EXHAUST (cc/yr)
Solid radwaste handling 123,124,125,126,127,128,129, 1.26x10+4 1.9x10+14 130,138,139,140,141,142,143, 144,233,234,422,423,470,471, 515,516 Liquid radwaste handling 131,132,133,134,136,137,147, 1.90x10+4 2.8x10+14 148,230,231,232,237,238,240, 241,242,243,245,247,248,472 Others 122,146,227,228,236,239,485, 1.29x10+4 1.9x10+14 486, offgas equipment areas (1) See drawings N-140, 141 and N-142.
(2) Based on continuous release, 365 days per year.
LGS UFSAR CHAPTER 12 12.2-155 REV. 14, SEPTEMBER 2008 Table 12.2-98 ESTIMATED AIRBORNE CONCENTRATIONS IN THE REACTOR ENCLOSURE(1)
DEMINERALIZER AREAS REFUELING AREAS ECCS EQUIPMENT AREAS DRYWELL AREAS OTHER EQUIPMENT AREAS NUCLIDE MPC(2)
Ci/cc Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC H-3 5.0E-06 5.2E-08 1.0E-02 Kr-83m 6.0E-06 Kr-85m 1.0E-06 8.5E-09 1.4E-04 1.5E-08 2.5E-04 7.2-10 1.2E-05 3.3E-09 5.4E-05 1.4E-07 2.4E-02 2.4E-09 4.1E-04 Kr-85 1.0E-06 Kr-87 1.0E-06 8.5E-09 8.5E-03 1.5E-08 1.5E-02 7.2E-10 7.2E-04 3.3E-09 3.3E-03 1.4E-07 1.4E-01 2.4E-09 2.4E-03 Kr-88 1.0E-06 8.5E-09 8.5E-03 1.5E-08 1.5E-02 7.2E-10 7.2E-04 3.3E-09 3.32E-03 1.4E-07 1.4E-01 2.4E-09 2.4E-03 Kr-89 1.0E-06 Xe-131m 2.0E-05 Xe-133m 1.0E-05 Xe-133 1.0E-05 1.8E-07 1.8E-02 3.4E-07 3.4E-02 1.5E-08 1.5E-03 7.0E-08 7.0E-03 3.1E-06 3.1E-01 5.4E-08 5.4E-03 Xe-135m 1.0E-06 1.3E-07 1.3E-01 2.3E-07 2.3E-01 1.1E-08 1.1E-02 5.0E-08 5.0E-02 2.1E-06 2.1E-01 3.9E-08 3.9E-02 Xe-135 4.0E-06 9.7E-08 2.4E-02 1.7E-07 4.3E-02 8.3E-09 2.1E-03 3.7E-08 9.2E-03 1.6E-06 4.1E-01 2.9E-08 7.1E-03 Xe-137 1.0E-06 Xe-138 1.0E-06 1.9E-08 1.9E-02 3.6E-08 3.6E-02 1.7E-03 1.7E-03 7.5E-09 7.5E-03 3.3E-07 3.3E-01 5.8E-09 5.8E-03 I-131 9.0E-09 4.8E-10 5.3E-02 8.7E-10 9.6E-02 4.1E-11 4.5E-03 1.8E-10 2.0E-02 8.0E-09 8.8E-01 1.4E-010 1.6E-02 I-133 3.0E-08 1.9E-09 6.5E-02 3.6E-09 1.2E-01 1.7E-10 5.8E-03 7.5E-10 2.5E-02 3.3E-08 1.1E+00 5.8E-010 1.9E-02 Co-60 9.0E-09 2.9E-11 3.2E-03 5.1E-11 5.7E-03 2.4E-12 2.7E-04 1.1E-11 1.2E-03 4.7E-10 5.2E-02 8.4E-012 9.3E-04 Co-58 5.0E-08 1.7E-12 3.5E-05 3.1E-12 6.1E-05 1.4E-13 2.9E-06 6.4E-13 1.3E-05 2.9E-11 5.7E-04 5.0E-013 1.0E-06 Cr-51 2.0E-06 8.5E-13 4.2E-07 1.5E-12 7.7E-07 7.2E-14 3.6E-08 3.3E-13 1.6E-07 1.4E-11 7.1E-06 2.4E-013 1.2E-07 Mn-54 4.0E-08 8.5E-12 2.1E-04 1.5E-11 3.8E-04 7.2E-13 1.8E-05 3.3E-12 8.2E-05 1.4E-10 3.6E-03 2.4E-012 6.1E-05 Fe-59 5.0E-08 1.1E-12 2.2E-05 2.0E-12 4.1E-05 9.7E-14 1.9E-06 4.3E-13 8.6E-06 1.8E-11 3.7E-04 3.4E-013 6.7E-06 Zn-65 6.0E-08 5.7E-12 9.5E-05 1.0E-11 1.7E-04 4.9E-13 8.2E-06 2.1E-12 3.6E-05 9.4E-11 1.6E-03 1.6E-012 2.7E-05 Zr-95 3.0E-08 1.1E-12 3.7E-05 2.0E-12 6.8E-05 9.7E-14 3.2E-06 4.3E-13 1.4E-05 1.8E-11 6.1E-04 3.4E-013 1.1E-05 Sr-89 3.0E-08 2.6E-13 8.5E-06 4.6E-13 1.5E-05 2.1E-14 7.1E-07 9.7E-14 3.2E-06 4.3E-12 1.4E-04 7.4E-014 2.5E-06 Sr-90 1.0E-09 1.4E-14 1.4E-05 2.6E-14 2.5E-05 1.2E-15 1.2E-06 5.4E-15 5.4E-06 2.3E-13 2.3E-04 4.2E-015 4.2E-06 Sb-124 2.0E-08 5.7E-13 2.9E-05 1.0E-12 5.1E-05 4.9E-14 2.4E-06 2.1E-13 1.1E-05 9.4E-12 4.7E-04 1.6E-013 8.2E-06 Cs-134 1.0E-08 1.1E-11 1.1E-03 2.0E-11 2.0E-03 9.7E-13 9.7E-05 4.3E-12 4.3E-04 1.8E-10 1.8E-02 3.4E-012 3.4E-04 Cs-136 2.0E-07 8.5E-13 4.2E-06 1.5E-12 7.7E-06 7.2E-14 3.6E-07 3.3E-13 1.6E-06 1.4E-11 7.1E-05 2.4E-013 1.2E-06 Cs-137 1.0E-08 1.5E-11 1.5E-05 2.9E-11 2.9E-03 1.3E-12 1.3E-04 5.9E-12 5.9E-04 2.5E-10 2.5E-02 4.6E-012 4.6E-04 Ba-140 4.0E-08 1.1E-12 2.8E-05 2.0E-12 5.1E-05 9.7E-14 2.4E-06 4.3E-13 1.1E-05 1.8E-11 4.6E-04 3.4E-013 8.4E-06 Ce-141 2.0E-07 2.9E-13 1.4E-06 5.1E-13 2.6E-06 2.4E-14 1.2E-07 1.1E-13 5.6E-07 4.7E-12 2.3E-05 8.4E-014 4.2E-07 (1) Based on gaseous releases given in BWR-GAL Computer Code (Reference 12.2-1).
(2) MPC is the maximum permissible concentration as defined in 10CFR20, Appendix B (pre-1994).
LGS UFSAR CHAPTER 12 12.2-156 REV. 13, SEPTEMBER 2006 Table 12.2-99 ESTIMATED AIRBORNE CONCENTRATIONS IN THE TURBINE ENCLOSURE(1)(2)
NUCLIDE MPC(3)
Ci/cc Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC Concen.
Ci/cc Fraction of MPC H-3 5.0E-06 1.7E-07 3.5E-02 1.4E-08 2.9E-03 3.9E-07 7.8E-02 1.0E-08 2.0E-03 1.1E-08 2.2E-03 Kr-83m 1.0E-06 Kr-85m 6.0E-06 3.0E-07 4.9E-02 2.4E-08 4.1E-03 6.5E-07 1.1E-01 1.7E-08 2.9E-03 1.9E-08 3.2E-03 Kr-85 1.0E-05 Kr-87 1.0E-06 5.7E-07 5.7E-01 4.6E-08 4.6E-02 1.2E-06 1.2E+00 3.4E-08 3.4E-02 3.7E-08 3.7E-02 Kr-88 1.0E-06 1.0E-07 1.0E+00 8.2E-08 8.2E-02 2.2E-06 2.2E+00 6.0E-08 6.0E-02 6.5E-08 6.5E-02 Kr-89 2.0E-06 Xe-131m 2.0E-05 Xe-133m 1.0E-05 Xe-133 1.0E-05 1.1E-06 1.1E-01 8.9E-08 8.9E-03 2.4E-06 2.4E-01 6.5E-08 6.5E-03 7.0E-08 7.0E-03 Xe-135m 1.0E-06 2.9E-06 2.9E-01 2.3E-07 2.3E-01 6.2E-06 6.2E+00 1.7E-07 1.7E-01 1.8E-07 1.8E-01 Xe-135 4.0E-06 2.8E-06 2.8E+00 8.2E-08 5.6E-02 6.1E-06 1.5E+00 1.6E-07 4.1E-02 1.7E-07 4.3E-02 Xe-137 1.0E-06 Xe-138 1.0E-06 6.1E-06 6.1E+00 5.0E-07 5.0E-01 1.3E-05 1.3E+01 3.7E-07 3.7E-01 4.0E-07 4.0E-01 I-131 9.0E-09 8.4E-10 9.3E-02 6.7E-11 7.5E-03 1.8E-09 2.0E-01 5.0E-11 5.6E-03 5.4E-11 6.0E-03 I-133 3.0E-08 3.4E-09 1.1E-01 2.8E-10 9.2E-03 7.3E-09 2.4E-01 1.9E-10 6.5E-03 2.1E-10 7.1E-03 Co-60 9.0E-09 8.8E-12 9.7E-04 7.1E-13 7.9E-05 1.9E-11 2.2E-03 5.2E-13 5.8E-05 5.7E-13 6.3E-05 Co-58 5.0E-08 2.7E-12 5.3E-05 2.1E-13 4.3E-06 5.8E-12 1.2E-04 1.5E-13 3.1E-06 1.7E-13 3.5E-06 Cr-51 2.0E-06 5.7E-11 2.9E-05 4.6E-12 2.3E-06 1.2E-10 6.1E-05 3.4E-12 1.7E-06 3.7E-12 1.8E-06 Mn-54 4.0E-08 2.7E-12 6.6E-05 2.1E-13 5.4E-06 5.8E-12 1.5E-04 1.5E-13 3.8E-06 1.7E-13 4.3E-06 Fe-59 5.0E-08 2.2E-12 4.5E-05 1.7E-13 3.5E-06 4.8E-12 9.6E-05 1.3E-13 2.7E-06 1.4E-13 2.9E-06 Zn-65 6.0E-08 8.8E-13 1.5E-05 7.1E-14 1.2E-06 1.9E-12 3.2E-05 5.2E-14 8.7E-07 5.7E-14 9.5E-07 Zr-95 3.0E-08 4.4E-13 1.5E-05 3.6E-14 1.2E-06 9.7E-13 3.2E-05 2.7E-14 8.8E-07 2.9E-14 9.5E-07 Sr-89 3.0E-08 2.7E-11 8.8E-04 2.1E-12 7.1E-05 5.8E-11 1.9E-03 1.5E-12 5.1E-05 1.7E-12 5.8E-05 Sr-90 1.0E-09 8.8E-14 8.8E-05 7.1E-15 7.1E-06 1.9E-13 1.9E-04 5.2E-15 5.2E-06 5.7E-15 5.7E-06 Sb-124 2.0E-08 1.3E-12 6.6E-05 1.0E-13 5.1E-06 2.9E-12 1.4E-04 7.9E-14 3.9E-06 8.5E-14 4.2E-06 Cs-134 1.0E-08 1.3E-12 1.3E-04 1.0E-13 1.0E-05 2.9E-12 2.9E-04 7.9E-14 7.9E-06 8.5E-14 8.5E-06 Cs-136 2.0E-07 2.2E-13 1.1E-06 1.7E-14 8.7E-08 4.8E-13 2.4E-06 1.3E-14 6.6E-08 1.4E-14 7.1E-08 Cs-137 1.0E-08 2.7E-12 2.7E-04 2.1E-13 2.1E-05 5.8E-12 5.8E-04 1.5E-13 1.5E-05 1.7E-13 1.7E-05 Ba-140 4.0E-08 4.8E-11 1.2E-03 3.9E-12 9.7E-05 1.0E-10 2.6E-03 2.9E-12 7.1E-05 3.2E-12 7.9E-05 Ce-141 2.0E-07 7.9E-12 3.9E-05 2.1E-13 1.1E-06 5.8E-12 2.9E-05 1.5E-13 7.7E-07 1.7E-13 8.7E-07 (1) Includes control structure areas.
(2) Based on gaseous releases given in BWR-GALE Computer Code (Reference 12.2-1).
(3) MPC is the maximum permissible concentration as defined in 10CFR20, Appendix B (pre-1994).
LGS UFSAR CHAPTER 12 12.2-157 REV. 13, SEPTEMBER 2006 Table 12.2-100 ESTIMATED AIRBORNE CONCENTRATIONS IN THE RADWASTE AND OFFGAS ENCLOSURES(1)
SOLID RADWASTE HANDLING AREAS LIQUID RADWASTE HANDLING AREAS OTHER EQUIPMENT AREAS MPC(2)
Concen.
Fraction Concen.
Fraction Concen.
Fraction NUCLIDE Ci/cc Ci/cc of MPC Ci/cc of MPC Ci/cc of MPC H-3 5.0E-06 Kr-83m 1.0E-06 Kr-85m 6.0E-06 Kr-85 1.0E-05 Kr-87 1.0E-06 Kr-88 1.0E-06 Kr-89 1.0E-06 Xe-131m 2.0E-05 Xe-133m 1.0E-05 Xe-133 1.0E-05 9.0E-09 9.0E-04 5.2E-08 5.2E-03 2.1E-08 2.1E-03 Xe-135m 1.0E-06 Xe-135 4.0E-06 4.1E-08 1.0E-03 2.3E-07 5.9E-02 9.7E-08 2.4E-02 Xe-137 1.0E-06 Xe-138 1.0E-06 I-131 9.0E-09 4.5E-11 5.0E-03 2.7E-10 2.9E-02 1.1E-10 1.2E-02 I-133 3.0E-08 1.6E-10 5.4E-03 9.4E-10 3.1E-02 3.9E-10 1.3E-02 Co-60 9.0E-09 8.2E-11 9.1E-03 4.7E-10 5.2E-02 1.9E-10 2.2E-02 Co-58 5.0E-08 4.1E-12 8.2E-05 2.3E-11 4.7E-04 9.7E-12 1.9E-04 Cr-51 2.0E-06 8.2E-12 4.1E-06 4.7E-11 2.3E-05 1.9E-11 9.7E-06 Mn-54 4.0E-08 2.8E-11 6.9E-04 1.5E-10 3.8E-03 6.4E-11 1.6E-03 Fe-59 5.0E-08 1.3E-11 2.7E-04 7.9E-11 1.6E-03 3.3E-11 6.5E-04 Zn-65 6.0E-08 1.3E-12 2.2E-05 7.9E-12 1.3E-04 3.3E-12 5.4E-05 Zr-95 3.0E-08 4.5E-14 1.5E-06 2.7E-13 8.8E-06 1.1E-13 3.7E-06 Sr-89 3.0E-08 4.1E-13 1.4E-05 2.3E-12 7.8E-05 9.7E-13 3.2E-05 Sr-90 1.0E-09 2.8E-13 2.8E-04 1.5E-12 1.5E-03 6.4E-13 6.4E-04 Sb-124 2.0E-08 4.5E-14 2.2E-06 2.7E-13 1.3E-05 1.1E-13 5.6E-06 Cs-134 1.0E-08 4.1E-12 4.1E-04 2.3E-11 2.3E-03 9.7E-12 9.5E-04 Cs-136 2.0E-07 4.1E-13 2.0E-06 2.3E-12 1.2E-05 9.7E-13 4.8E-06 Cs-137 1.0E-08 8.2E-12 8.2E-04 4.7E-11 4.7E-03 1.9E-11 1.9E-03 Ba-140 4.0E-08 9.0E-14 2.2E-06 5.2E-13 1.3E-05 2.1E-13 5.4E-06 Ce-141 2.0E-07 2.3E-12 1.2E-05 1.3E-11 6.6E-05 5.6E-12 2.8E-05 (1) Based on gaseous releases given in BWR-GALE Computer Code (Reference 12.2-1).
(2) MPC is the maximum permissible concentration, as defined in 10CFR20, Appendix B (pre-1994).
LGS UFSAR CHAPTER 12 12.2-158 REV. 13, SEPTEMBER 2006 Table 12.2-101 CONDENSATE SYSTEM DEEP BED/DEMINERALIZER, SPENT RESIN AND RESIN MEASURING TANKS SHIELDING DESIGN SOURCE TERMS(1)(2)(3)
CARRYOVER COMPONENT(4)
Activity Activity Activity Isotope(6 (Ci)
Isotope (Ci)
Isotope (Ci)
Br-83 3.38x10-1 Cs-138 3.99x10-1 Rh-103m 8.44x10-2 Br-84 1.35x10-1 Ba-139 5.76x10-1 Tc-99 7.05x10-6 Br-85 7.67x10-3 Ba-140 1.74 Nb-97m 2.48x10-3 I-131 2.37x10+1 Ba-141 1.55x10-1 Nb-97 2.55x10-3 I-132 4.39x10+0 Ba-142 2.67x10-2 Na-24 4.05x10-3 I-133 1.75x10+1 Ce-141 1.69x10-1 P-32 9.24x10-4 I-134 1.98x10+0 Ce-143 1.97x10-3 Cr-51 4.48x10-2 I-135 8.10x10+0 Ce-144 8.26x10-2 Mn-54 2.82x10-2 Sr-89 1.99 Pr-143 7.82x10-3 Mn-56 1.73x10-2 Sr-90 9.71x10-1 Nd-147 1.74x10-2 Co-58 1.13 Sr-91 6.76x10-1 Np-239 6.37x10+0 Co-60 5.50x10-1 Sr-92 3.11x10-1 Pr-144m 1.24x10-3 Ag-110m 3.78x10-2 Zr-95 2.89x10-2 Ag-110 5.67x10-4 W-187 9.74x10-3 Zr-97 2.55x10-4 Zn-69 5.56x10-5 Fe-59 1.15x10-2 Nb-95 4.55x10-2 Pu-239 2.69x10-4 Mo-99 6.85x10-1 Pm-147 5.05x10-3 Tc-99m 1.39x10+0 Ba-137m 4.73x10+0 Tc-101 1.57x10-2 Pr-144 8.26x10-2 Ru-103 8.46x10-3 Ba-136m 1.21x10-2 Ru-106 6.90x10-3 Ni-65 1.09x10-4 Te-129m 1.51x10-2 Zn-65 1.23x10-3 Te-132 1.80x10+0 Zn-69m 5.56x10-5 Cs-134 2.67x10+0 Te-129 9.56x10-3 Cs-136 8.09x10-2 I-129 5.68x10-10 Cs-137 5.00x10+0 Rh-106 6.90x10-3
LGS UFSAR CHAPTER 12 12.2-159 REV. 13, SEPTEMBER 2006 Table 12.2-101 (Cont'd)
FALLOUT COMPONENT (5)
Activity Activity Activity Isotope(6)
(Ci)
Isotope (Ci)
Isotope (Ci)
Ba-144 2.34x10-4 La-140 1.74x10+0 Zr-93 2.95x10-8 La-144 2.53x10-4 Cs-139 4.72x10-1 Nb-93m 1.03x10-9 Cs-144 1.34x10-4 Rb-92 1.45x10-1 Rb-91 3.64x10-1 Pr-144 8.26x10-2 Cs-143 6.33x10-4 Y-90 9.64x10-4 Ba-143 1.29x10-3 Y-92 3.11x10-1 Rb-88 3.55x10-2 La-143 1.43x10-3 Cs-135 2.82x10-6 Sr-95 8.11x10-5 Rb-95 2.63x10-5 Y-95 8.68x10-5 Y-91 6.75x10-1 Cs-142 6.92x10-3 Y-91m 3.85x10-1 Rb-90 4.01x10-1 Rb-88 3.55x10-2 La-142 2.67x10-2 Nb-95m 2.60x10-4 Cs-141 1.27x10-1 Rb-94 3.37x10-3 Sr-94 4.44x10-3 Rb-89 2.24x10-1 La-141 1.55x10-1 Y-94 4.48x10-3 Rb-93 3.92x10-2 Y-93m 1.72x10-2 Cs-140 4.40x10-1 Sr-93 4.41x10-2 Y-93 4.41x10-2 U-235m 2.69x10-4 NOBEL GAS GENERATION COMPONENT (7)
Activity Activity Activity Isotope(6)
(Ci)
Isotope (Ci)
Isotope (Ci)
Xe-135 8.10x10+0 Xe-133m 2.60x10-1 Kr-83m 3.38x10-1 Xe-135m 1.75x10+1 Kr-85m 7.65x10-3 Xe-133m 5.09x10-1 Kp-85 1.48x10-4 (1)
Based on shielding design source terms given in Tables 12.2-38.
(2)
Based on condensate activity with appropriate DF's applied: 2 for Cs, Rb, and 10 for others.
(3)
Resin source volume for the deep bed demineralizer and spent resin tanks is 364.4 cu.ft; resin measuring tank 85 cu.ft.
(4)
Carryover component of condensate accumulated for 180 days at 4114 gpm at 1.0 g/cc.
(5)
Fallout component of condensate accumulated for 180 days at 4114 gpm at 1.0 g/cc.
(6)
Isotopes with activities less than 1.0x10-12 are not listed.
(7)
Noble gases generated by particulate parents accumulating on deep-bed demineralizer resins.
LGS UFSAR CHAPTER 12 12.2-160 REV. 13, SEPTEMBER 2006 Table 12.2-102 DEWATERED LSA SPENT RESIN CAKE SHIELDING DESIGN SOURCE TERMS(1)(2)
Activity Activity Isotope(3)
(Ci)
Isotope(3)
(Ci)
Ag-110 3.27x10-3 Pr-143 5.22x10-1 Ag-110m 2.52x10-1 Pr-144 3.16x10-1 Ba-140 2.07x10+1 Pu-239 1.04x10-3 Ce-141 1.31 Rb-87 3.18x10-11 Ce-143 1.17x10-6 Re-187 8.96x10-13 Ce-144 5.22x10-1 Rh-103m 1.48x10-1 Co-58 1.57x10+1 Rh-106 3.96x10-2 Co-60 2.32 Ru-103 1.51x10-1 Cr-51 8.37x10-1 Ru-106 3.96x10-2 Cs-134 2.53 Sm-147 1.32x10-14 Cs-135 1.15x10-5 Sr-89 5.09x10+1 Cs-136 2.32x10-1 Sr-90 3.87 Cs-137 4.17 Sr-91 4.43x10-20 Fe-59 2.00x10-1 Tc-99 2.80x10-5 I-129 2.07x10-9 Tc-99m 4.51x10-2 I-131 1.43x10+2 Te-129 1.81x10-1 I-132 3.38x10-1 Te-129m 2.83x10-1 I-133 1.36x10-7 Te-132 3.28x10-1 La-140 2.38x10+1 Th-231 1.04x10-13 Mn-54 1.71x10-1 U-235 1.08x10-13 Mo-99 4.72x10-2 W-187 2.45x10-9 Na-24 8.95x10-15 Y-89m 5.09x10-3 Nb-93m 2.27x10-10 Y-90 3.87 Nb-95 5.93x10-1 Y-91 7.88 Nb-95m 9.01x10-3 Y-91m 2.32x10-20 Nb-97 2.57x10-14 Y-93 2.60x10-20 Nb-97m 2.22x10-14 Zn-65 8.36x10-3 Nd-144 1.84x10-17 Zn-69 9.73x10-18 Nd-147 1.86x10-1 Zn-69m 9.06x10-18 Np-239 1.20x10-1 Zr-93 4.13x10-8 P-32 1.31x10-2 Zr-95 4.25x10-1 Pa-231 1.53x10-18 Zr-97 2.39x10-14 Pm-147 2.40x10-2 (1)
Based on shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
This activity is in 235 ft3.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-161 REV. 13, SEPTEMBER 2006 Table 12.2-103 SOLID RADWASTE CENTRIFUGE SHIELDING DESIGN SOURCE TERMS(1)(2)
Activity Activity Isotope(3)
(Ci)
Isotope(3 (Ci)
Ag-110 1.03x10-1 Pm-147 9.02x10-2 Ag-110m 7.95 Pr-143 1.66x10+1 Ba-140 6.12x10+1 Pr-144 1.66x10+1 Ce-141 9.73 Pu-239 3.74x10-2 Ce-143 5.04x10-14 Re-187 3.22x10-11 Ce-144 1.66x10+1 Rh-103m 2.38 Co-58 3.57x10+2 Rh-106 1.30 Co-60 8.18x10+1 Ru-103 2.43 Cr-51 9.82 Ru-106 1.30 Cs-134 8.71x10+1 Sm-147 1.25x10-13 Cs-135 1.95x10-5 Sr-89 5.76x10+2 Cs-136 9.81x10-1 Sr-90 1.35x10+2 Cs-137 1.41x10+2 Tc-99 1.01x10-3 Fe-59 3.56 Tc-99m 2.65x10-4 I-129 1.08x10-7 Te-129 2.59 I-131 8.46 Te-129m 4.04 I-132 6.15x10-3 Te-132 5.97x10-3 I-133 4.79x10-19 Th-231 8.51x10-12 La-140 7.04x10+1 U-235 8.67x10-12 Mn-54 5.51 W-187 8.93x10-18 Mo-99 2.77x10-4 Y-89m 5.76x10-2 Nb-95 1.53x10+1 Y-90 1.35x10+2 Nb-95m 1.97x10-1 Y-91 9.96x10+1 Nd-144 1.32x10-15 Zn-65 2.63x10-1 Nd-147 5.01x10-2 Zr-95 9.28 Np-239 1.61x10-4 P-32 5.97x10-2 Pa-231 1.24x10-16 (1)
Based on the shielding design source terms given in Tables 12.2-2, 12.2-3, and 12.2-5.
(2)
This activity is in 400 ft3.
(3)
Isotopes with activities less than 1.0x10-20 are not listed.
LGS UFSAR CHAPTER 12 12.2-162 REV. 13, SEPTEMBER 2006 Table 12.2-104 RADIATION LEVELS FROM THE TIP DETECTORS AND CABLES(1)
DOSE RATE, R/hr DECAY TIME (DAYS)
DETECTOR(2)
CABLE(3) 0.0014 6.0 58 0.0035 5.0 57 0.021 4.0 50 0.042 3.4 44 0.083 2.6 34 0.17 1.5 19 0.50 0.18 2.4 1.00 0.014 0.10 2.00 0.0041 0.019 (1)
Based on 3 years of simulated use consisting of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of detector exposure in core semimonthly.
(2)
At 1 meter.
(3)
At 1 meter from the midpoint of the 12 foot length of irradiated cable adjacent to the detector.