structures / systems / components status
TRANSCRIPT
San Onofre 2&3 UFSAR
(DSAR)
RADIOACTIVE WASTE MANAGEMENT
November 2016 11-1 Rev 3
11. RADIOACTIVE WASTE MANAGEMENT
Plant Radioactive Waste Management Systems are described in this chapter in three separate
areas: Plant Area, South Yard Area, and North Industrial Area (NIA). Monitoring and sampling
of the radiological process and effluent for each area is discussed in detail in Section 11.4.
Not all subsystems of the Radioactive Waste Management Systems are required to support
permanent plant shutdown or defueled operations. The status of these subsystems is listed in the
table below. Design Basis, Licensing Basis, and operational information contained in this
chapter / section has been updated to reflect the current status. Although the subsystems
removed or partially removed from service no longer support operation, they may still contain
fluids, gases, or other hazards such as energized circuits, compressed air, radioactive material,
etc. Equipment may not have been physically removed from the plant. See General
Arrangement Drawings, P&IDs, and One Line diagrams for the current plant configuration.
STRUCTURES / SYSTEMS / COMPONENTS STATUS
Plant Area Radwaste Management Systems
Liquid Radwaste Partially Removed from Service
Gaseous Radwaste Partially Removed from Service
Solid Radwaste Removed from Service
South Yard Area Radwaste Management Systems
Liquid Radwaste Partially Removed from Service
Gaseous Radwaste Removed from Service
Solid Radwaste Available
North Industrial Area Radwaste Management Systems
Liquid Radwaste Available
Gaseous Radwaste Removed from Service
Solid Radwaste Removed from Service
San Onofre 2&3 UFSAR
(DSAR)
RADIOACTIVE WASTE MANAGEMENT
November 2016 11-2 Rev 3
11.1 PLANT AREA RADWASTE MANAGEMENT SYSTEMS
11.1.1 LIQUID RADWASTE
The liquid waste systems consisted of four subsystems:
STRUCTURES / SYSTEMS / COMPONENTS STATUS
Coolant Radwaste System (CRS) Removed from Service
Coolant and Boric Acid Recycle System (CBARS) Removed from Service
Miscellaneous Liquid Waste System (MLWS) Partially Removed from Service
Mixed Waste Processing (MWP) Unit Removed from Service
The equipment that remains powered and in-service includes sumps and tanks to facilitate
storage until a processing skid is obtained and placed in service to allow more routine
processing:
Radwaste sump and pumps
Outlying radioactive sumps and pumps
Chemical Waste Tank (T064) and one pump (P180)
Condensate Monitor Tanks (T075, T076) and one pump
Radwaste Primary Tanks (T065, T066, T067, T068)
Interconnecting piping for above
Discharge to Unit 2 Outfall via Salt Water Dilution System and associated Radiation
Monitor (2/3RE7813)
A future processing skid that will meet the ODCM requirements
11.1.1.1 Design Basis of MLWS
The principal design objectives of the MLWS liquid waste system are:
A. Collection of all liquid wastes generated during plant shutdown which may contain
radioactive nuclides.
B. Sufficient processing capability so that liquid waste may be discharged to the
environment at concentrations below the regulatory limits of 10CFR20 and consistent
with the As Low As Reasonably Achievable (ALARA) guidelines set forth
in 10CFR50.
San Onofre 2&3 UFSAR
(DSAR)
RADIOACTIVE WASTE MANAGEMENT
November 2016 11-3 Rev 3
The auxiliary building radwaste area equipment layout is presented in General Arrangement
Drawings 40000 through 40003. The seismic and quality group classifications for the liquid
waste components and piping are provided in Controlled Document 90034, “Q-List” and in
Controlled Drawings.
Special equipment design provisions have also been incorporated for consideration of ALARA,
reduce maintenance, equipment downtime, liquid leakage, or gaseous releases of radioactive
materials to the building atmosphere. Where practicable, welded connections are used in lieu of
flanged ones. Butt welds are used where justified in the liquid waste systems to reduce crud trap
formation. Pumps are provided with mechanical seals to minimize leakage. The frequency of
equipment maintenance is minimized by utilizing corrosion-resistant materials wherever feasible.
Diaphragms in some radwaste tanks are provided to prevent release of tritium and dissolved
noble gases to the building atmosphere, and prevent air from dissolving into the liquid.
Tanks receive liquid until processing begins or until tank liquid volume reaches a predetermined
level. The tank is then isolated from the feed while its contents are stored until processed.
Appropriate alarms are utilized to alert operators of tank high or low level. Overflow lines are
connected to the radwaste sump via a loop seal. Table 11.1-1 provides a list of potentially
radioactive tanks and describes the design provisions to prevent and control tank overflow.
The function of the MLWS liquid waste systems is to collect and process radioactive liquid
wastes generated during plant shutdown and to reduce their radioactivity and chemical
concentrations to levels acceptable for discharge.
11.1.1.2 System Description of MLWS
The MLWS, in permanently shutdown configuration, consists of sumps, seven tanks (T064,
T065, T066, T067, T068, T075, and T076) and associated pumps.
The future processing skid will consist of ion exchangers and supporting sample and process
equipment to allow processing of waste water from the Miscellaneous Waste Evaporator
Condensate Monitor Tanks (T075 and T076) to prepare for discharge. The pumping action is
provided by the condensate monitor tank pump, P188. The future processing system will be
capable of reducing activity to meet the isotopic limits in 10CFR20 App B, and discharge per the
Offsite Dose Calculation Manual.
Some of the components from the CRS, CBARS, and MLWS have been repurposed since plant
shutdown and are listed in Table 11.1-2 which describes equipment sizes and/or capacities,
process flowrates, storage capabilities, design temperatures, and design pressures. Design codes
and standards are listed in Table 11.1-3.
Features and procedures used to prevent inadvertent releases to the environment from the liquid
waste systems include automatic discharge pump shutoff, administrative procedures, Certified
Fuel Handler training, and discharge radiation monitors which provide alarms.
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November 2016 11-4 Rev 3
Table 11.1-1
RADIOACTIVE TANK OVERFLOW PROTECTION
Radioactive Tanks
Outside
Containment Location Level Monitoring Potential Overflow Alarm Method for Containing Overflow
Radwaste Primary Tanks
T 065 Radwaste Building EL-9' Local (LI 7585A) Overflow would accumulate in lower
levels and the drain is piped to the
radwaste building area sump. Sump
is then pumped to chemical waste
tank (T064).
T 066 Radwaste Building EL-9' Local (LI 7586A)
T 067 Radwaste Building EL-9' Local (LI 7587A)
T 068 Radwaste Building EL-9' Local (LI 7588A)
Spent Fuel Makeup Tanks
T 055 (Unit 3) Radwaste Building EL-9' Local (3LI 7133A)
Control Room /
Command Center
CDAS
Control Room /
Command Center CDAS
Same
T 056 (Unit 2)
(see Chapter 9)
Radwaste Building EL-9' Local (2LI 7133A)
Control Room /
Command Center
CDAS
Control Room /
Command Center CDAS
Chemical Wastes Tank
T 064 Radwaste Building EL-9' Local (LI 7401) Control Room /
Command Center CDAS
Same
Miscellaneous Waste Evaporator Condensate Monitor Tanks
T 075 Radwaste Building EL-9' Local (LI 7459) Same
T 076 Radwaste Building EL-9' Local (LI 7458)
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RADIOACTIVE WASTE MANAGEMENT
November 2016 11-5 Rev 3
Table 11.1-2
MLWS EQUIPMENT DESCRIPTIONS
Component Quantity Size/Capacity For Each
Component Material
Design Press/Temp
(psig / °F)
Chemical waste tank, T-064 1 25,000 gal SS Atmospheric/180
Radwaste primary tanks T065, T066, T067 and
T068
4 60,000 gal SS Atmospheric/180
Misc. wastes evaporator condensate monitor tanks,
T-075 and T-076
2 25,000 gal SS Atmospheric/180
Chemical waste tank pumps, P-180 2 65 gal/min
@ 180 psig
SS 200/180
Misc. wastes evaporator condensate monitor tank
pump (Nuclear condensate tank pump, P-188)
2 100 gal/min
@ 113 psig
SS 140/180
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November 2016 11-6 Rev 3
Table 11.1-3
EQUIPMENT DESIGN CODES, LIQUID RADWASTE SYSTEM (Sheet 1 of 2)
CODES
EQUIPMENT Design and Fabrication Materials(a)
Welder
Qualifications and
Procedure
Inspection and Testing
Tanks, Atmospheric BTP ASME Code
Section(c)III, Class 3,
or API 620 and 650,
AWWA D-100
ASME Code(b)
Section II
ASME Code
Section IX
ASME Code(a) Section
III, Class 3 or API 620;
650 AWWA D-100
All Atmospheric Tanks
except Tanks
T-055 and T-056
SONGS 2 & 3 Design to API 620
Fabricate to API 650
ASME Code
Section II
ASME Code
Section IX
API 620 and API 650
Spent Fuel Pool
Make-up Tanks
(T-055, T-056)
See Chapter 9
(e) (e) (e) (e)
Tanks, Pressure BTP ASME Code Section
VIII, Div. 1
ASME Code
Section II
ASME Code
Section IX
ASME Code Section
VIII, Div. 1
SONGS 2 & 3 ASME Code Section
VIII, Div. 1
ASME Code
Section II
ASME Code
Section IX
ASME Code Section
VIII, Div. 1
Pumps BTP Manufacturer's(d)
Standards
ASME Code
Section II or
Manufacturers
Standard
ASME Code
Section IX (as
required)
ASME(c) Section III
Class 3; or Hydraulic
Institute
SONGS 2 & 3 Manufacturer's(d)
Standards
ASME Code
Section II
ASME Code
Section IX
Hydraulic Institute
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RADIOACTIVE WASTE MANAGEMENT
November 2016 11-7 Rev 3
Table 11.1-3
EQUIPMENT DESIGN CODES, LIQUID RADWASTE SYSTEM (Sheet 2 of 2)
CODES
EQUIPMENT Design and Fabrication Materials(a) Welder Qualifications
and Procedure
Inspection and
Testing
Piping and Valves BTP ANSI B31.1 ASTM or ASME
Code Section II
ASTM Code Section IX ANSI B31.1
SONGS 2 & 3 ANSI B31.1 ASTM ASTM Code Section IX ANSI B31.1
MLWS (Sump
subsystem)
SCE and vendor Commercial B31.1 or
Commercial
ASTM Code Section IX ANSI B31.1
(a) Material Manufacturer's certified test reports should be obtained whenever possible.
(b) Fiberglass reinforced plastic tanks may be used in accordance with Part M, Section 10, ASME Boiler and Pressure Vessel
Code, for applications at ambient temperature.
(c) ASME Code Stamp and material traceability not required.
(d) Manufacturer's standard for the intended service. Hydro testing should be 1.5 times the design pressure.
(e) The Spent Fuel Pool Makeup Tanks (formerly Primary Plant Make-up Storage Tanks) meet Seismic Category I requirements.
These tanks have been analyzed to withstand the effects of tornado depressurization.
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November 2016 11-8 Rev 3
The piping and instrumentation diagrams for the MLWS, including process flow, are shown in
Controlled Drawings 40137B, 40137C, 40137D, 40138A, 40138B, 40138C, 40139A, 40139B,
40129A, and 40129B. Miscellaneous liquid wastes are piped into the chemical waste tank
(T064). In addition, liquid waste from the radwaste sump is normally pumped into chemical
waste tank (T064). The miscellaneous liquid waste system normally collects, stores, and
processes liquids from the following major sources:
A. Radioactive chemical laboratory drains (chemical waste tank)
B. Floor drains (miscellaneous wastes tank or chemical waste tank)
From the chemical waste tank (T064), the chemical waste passes through a duplex strainer in the
suction line of the chemical waste pump (P180). The chemical waste tank can then be pumped
to the condensate monitor tanks (T075 and T076). If sampling results so dictate, the chemical
waste tank and / or condensate monitor tanks can be pumped to the Radwaste Primary Tanks
(T065, T066, T067, and T068). Wastes are discharged to the Unit-2 outfall in accordance with
Offsite Dose Calculation Manual (ODCM) specification limits.
Fluid in the turbine plant area sumps is normally pumped to an oily waste holding sump and then
discharged to the Unit 2 Outfall via the Salt Water Dilution System in accordance with the
ODCM and the National Pollutant Discharge Elimination System (NPDES). Piping is also
provided to pump liquid from the turbine plant area sumps to the radwaste area sump. From
there, the turbine plant area sump water may be processed by the MLWS via the Chemical
wastes tank. Storage and processing by the MLWS may be done when the turbine plant area
sump water exceeds a predetermined specific activity (refer to Table 11.4-1).
11.1.1.3 Operation of MLWS
Operation of the MLWS consists of a series of automatic and operator-controlled operations.
Sump water collection can be accomplished automatically, and storage tank(s) and processing
paths, if needed, are selected by the operator.
The MLWS is normally utilized to process floor and equipment drains. The MLWS may also
receive wastes collected in the turbine building floor drains. The Chemical Waste Tank, T064,
receives waste from the radwaste sump as well as various drains from the chemistry laboratory,
decontamination shower, and other minor waste streams. From the chemical waste tank the
waste water is pumped to the Condensate Monitor Tanks, T075 and T076. These tanks are used
for processing water and preparing it for release. Water can be pumped from these tanks to a
future process ion exchange system for reduction of radioactive isotope activity. Once activity
levels are appropriately reduced, provisions are made for recirculation and sampling. The waste
is then batch released via a monitored pathway with appropriate dilution in a process controlled
by the ODCM to ensure compliance with 10 CFR 20, Appendix B, Table II, Column 2, and
10CFR50 App I.
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RADIOACTIVE WASTE MANAGEMENT
November 2016 11-9 Rev 3
If waste inventory exceeds the capacity of T075 and T076, the Radwaste Primary Tanks, T065,
T066, T067, and T068 have been repurposed from the retired Coolant Radwaste System. Waste
water from the MLWS can be stored in the primary tanks until it is appropriate to process and
release the waste water per the process described above.
The Condensate Monitor Tanks (T075, T076) are sampled and either discharged to the Unit 2
Outfall via the Salt Water Dilution System or stored for further processing.
The primary function of the Chemical Waste Tank, T064, is to receive water from the radwaste
sump. Area sumps where potentially contaminated liquids are routed to T064 as shown in
controlled drawings.
After filling a Miscellaneous Waste Evaporator Condensate Monitor Tank (T075 or T076), the
tank is isolated and the influent is routed to the other Miscellaneous Waste Evaporator
Condensate Monitor Tank. The contents of the isolated tank are analyzed for chemical and
radiochemical contamination and, depending upon analytical results and plant water
requirements, are either discharged offsite via a monitored path, or returned to the tank for
further storage or processing.
11.1.1.4 Radioactive Releases of MLWS
During liquid processing by MLWS, radioactivity is reduced to appropriate levels by a future
skid mounted ion exchanger before it is discharged to the environment. Before the liquid is to be
discharged, the activity level must be consistent with the discharge criteria of 10CFR20 and
10CFR50 in accordance with the ODCM. Treatment in these systems is such that these liquids
can be discharged from the plant while being monitored.
The expected average annual liquid releases from the liquid waste systems are based on the
following:
A. Direct discharge of Unit 2 East turbine building sump.
B. Discharge of MLWS effluents meeting 10CFR20 limits and dose objectives of 10CFR50,
Appendix I.
The doses resulting from these releases are discussed in Section 11.1.1.4.3.
11.1.1.4.1 Release Points
The release point of liquid radwaste is via the Unit 2 Outfall via the Salt Water Dilution System
as shown in Controlled Drawings. All discharges are either:
A. Continuously monitored through a monitored release path; or,
B. Batch released after activity levels are measured from samples taken.
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RADIOACTIVE WASTE MANAGEMENT
November 2016 11-10 Rev 3
11.1.1.4.2 Dilution Factors
Dilution factors are calculated per the ODCM and meet 10CFR20 limits.
11.1.1.4.3 Estimated Doses
The liquid radwaste system is designed to ensure that the design objectives of Section 11.1.1.1
are met. Estimates of the dose to the general public were calculated in accordance with
10CFR20, 10CFR50 and 40CFR190. Results for maximum whole-body dose to an individual,
maximum organ dose to an individual, and whole-body and organ doses to the population within
a 50-mile radius are tabulated in Table 11.1-4. Four possible pathways were used to determine
doses to the general public: ingestion of aquatic foods (fish and other seafood invertebrates),
sunbathing, boating, and swimming.
The dose as a result of ingestion of aquatic foods is due to concentrations of radionuclides in
aquatic foods due to release of contaminated liquid into the ocean and is directly related to the
concentration of the radionuclides in water. The individual consumption rate for fish was
assumed to be 21 kg/yr and seafood 5 kg/yr. Population doses resulting from ingestion of
aquatic foods were based on published catch data and the year 2020 population projections.
The dose received as a result of sunbathing is due to accumulation of radionuclides in shoreline
sediments that have been washed ashore and deposited on the beach. The individual sunbathing
occupancy time was based on the maximum age group usage (teenage) of 67 hr/yr. The
population dose usage factor was based on the year 2020 population projections within a 50-mile
radius of the facility.
The individual doses received from boating (water surface) were based on a usage time of 52
hrs/yr. The individual doses received as a result of swimming were based on usages of 100
hrs/yr and 8 oz/day for 150 days, respectively. The population doses were based on the
year 2020 population projections within a 50-mile radius of the facility.
Table 11.1-4
ANNUAL ESTIMATED DOSES DUE TO LIQUID RELEASES (PER UNIT)
Total Individual Dose Appendix I Limits Population Dose
Total Body 1.34 x 10-5 mrem 3 mrem 1.0 x 101 man-rem
Bone 9.37 x 10-6 mrem 10 mrem 3.5 x 10-2 man-rem
Thyroid 3.60 x 10-4 mrem 10 mrem 8.7 x 10-1 man-rem
GI Tract 2.34 x 10-5 mrem 10 mrem 4.4 x 10-2 man-rem
Skin 6.28 x 10-6 mrem 10 mrem 1.2 x 101 man-rem
11.1.2 GASEOUS RADWASTE
The Gaseous Waste Management systems are not required to support permanent plant shutdown
or defueled operations, with exceptions listed below. The operational information has been
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RADIOACTIVE WASTE MANAGEMENT
November 2016 11-11 Rev 3
removed from the UFSAR (DSAR) to indicate that the system performs no licensing bases or
design bases or safety function. Although the system does not support operation, the system may
still contain fluids, gases or other hazards such as energized circuits, compressed air, radioactive
material, etc. Equipment may not have been physically removed from the plant. See P&IDs,
One-Line diagrams, and General Arrangement Drawings for current plant configuration.
Radioactive waste gases are collected and processed through the following systems depending
upon their origin. These systems are:
STRUCTURES / SYSTEMS / COMPONENTS STATUS
High-activity reactor coolant gaseous radwaste system Removed from Service
Low-activity vent gas collection header Available
Main condenser evacuation system Removed from Service
Turbine gland seal system Removed from Service
Building ventilation systems Partially Removed from Service
11.1.2.1 Design Basis
The gaseous waste management systems collected and processed the radioactive noble gases,
airborne halogens, and particulates to reduce the anticipated annual releases and personnel
exposure in restricted and unrestricted areas to levels as low as is reasonably achievable.
The design objective of the remaining gaseous waste management systems is the collection of
potentially low-radioactive gaseous wastes. The equipment layout is presented as part of the
radwaste building equipment layout in General Arrangement Drawing 40000.
11.1.2.2 System Description
As shown on Controlled Drawings 40135A, 40135B, 40135C, 40175A, 40175ASO3, 40175B,
and 40175BSO3 and Figure 11.3-2, the vent gas collection system collects various low-activity
gases from potentially radioactive liquid storage tanks, thereby minimizing radiation doses to
plant operating personnel. These gases consist mainly of air collected in the vapor space above
storage tanks and ventilation discharges from plant sample hoods.
The sources for the vent gas collection header include the gases from:
A. Miscellaneous waste tank vent
B. Chemical waste tank vent
C. Miscellaneous waste evaporator condensate monitor tanks vents
D. Radwaste area sump
E Sampling system vent hoods
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November 2016 11-12 Rev 3
The vent gas collection system is shared between Units 2 and 3.
A continuous exhaust plenum is used to collect discharges from plant ventilation systems and
remaining components (via gas collection header) for monitoring before discharge.
11.1.2.3 Operation
Remaining plant components and systems are vented to a gas collection header. The header is
piped to the continuous exhaust plenum, where effluents are monitored. The HVAC systems
servicing these rooms are also directed to the continuous exhaust plenum. The HVAC system
operates continuously.
11.1.2.4 Radioactive Releases
11.1.2.4.1 Release Points
During normal operation, including transients associated with anticipated operational
occurrences, the potentially significant points of airborne radioisotope releases are:
STRUCTURES / SYSTEMS / COMPONENTS STATUS
Containment Purge Vent Stacks Removed from Service
Continuous Exhaust Vent Stacks Available
Turbine Buildings Removed from Service
Main Condenser Evacuation System Exhausts Removed from Service
Turbine Gland Seal System Exhausts Removed from Service
Continuous Exhaust Vent Stacks
Effluents from the fume hoods, laboratories, waste gas discharge and vent headers, fuel handling,
radwaste area, and safety equipment building and penetration buildings are routed to the
continuous exhaust plenum. The effluents are discharged to the atmosphere through the Unit 2
and Unit 3 Continuous Exhaust Plant Vent Stacks. The Continuous Exhaust Vent stacks are
located on the top of each containment structure. Each stack is 15 feet higher than the top of the
containment structure which is itself 160 feet above grade. The continuous exhaust vent and the
containment purge vent are included in a single stack with a divider down the middle. The
containment purge vent path is normally isolated. The combined stack on each containment is
sized to provide a minimum exit velocity of 3000 ft/min from each side at a temperature of
110°F.
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11.1.3 SOLID RADWASTE
The solid waste management system (SWMS) was designed to provide holdup, transfer,
solidification and packaging for radioactive wastes generated by plant operation, and to store
these wastes until they are shipped offsite. Shipment offsite may be to an intermediate processor
or directly to a licensed burial site depending on the method by which the wastes were packaged
on site. The processing system is no longer in service and has been removed from the radwaste
building. However, within the plant area, packaging, storing and shipping of solid radwaste is
still available.
Handling and Disposal
Packaging of radioactive materials (filters), dry active waste, and radioactive sources may be by
either encapsulation with an approved solidification agent (such as cement) in a liner or
placement into a High Integrity Container (HIC). The liner/HIC is then normally transferred to
the Multipurpose Handling Facility (MPHF), see Section 11.2.3, for temporary storage and is
ultimately shipped to a licensed burial site or alternate processor for disposal of final waste form
in an appropriate shielded shipping cask.
Packaging, Storage, and Shipment
All radioactive wastes will be prepared for shipment in containers which meet the requirements
of the U. S. Department of Transportation (DOT) regulations and the U. S. Nuclear Regulatory
Commission (NRC) regulations and burial site license requirements, as applicable.
Shipping containers will be stored in appropriate storage areas onsite. Solid radwaste is stored in
the high-level and low-level storage areas of the Auxiliary Building. In addition, solid radwaste
is also stored in the radwaste staging area which is a fenced off area located east of the Units 2
and 3 Auxiliary Building.
After the radioactive waste has been packaged it is normally sent to the MPHF for offsite
shipment. The MPHF has an in-process staging area for the accumulation of solid radwaste until
it is released for shipment.
Containers, solidification liners and HICs could be shipped promptly after filling, provided the
proper shielding is available, without exceeding DOT radiation limits. If 49CFR173 dose
limitations cannot be met with the available shielding, the containers (liners and/or HICs) are
stored and allowed to decay until the appropriate shielding is available.
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November 2016 11-14 Rev 3
11.2 SOUTH YARD AREA RADWASTE MANAGEMENT SYSTEMS
Radioactive waste management systems can be found in the South Yard Facility (Areas T10 and
T20) and in the Multipurpose Handling Facility, MPHF (Area T60).
The South Yard Facility is located on the south side of the plant outside the Protected Area. The
Radiological Work Area within the South Yard Facility includes the Radioactive Equipment and
Materials System (REMS) Rebuild Area, Mixed Waste Room and REMS Work Area. The SYF
also had a decontamination shop.
The MPHF consists of an office building, a staging building and an equipment pad. The facility
is surrounded by a chain link fence. The MPHF is located at the southern edge of the SONGS
owner controlled area.
Table 11.2-1 provides the allowable activity, quantity, and volume of radioactive waste allowed
to be stored at the MPHF.
Table 11.2-1
MPHF Allowable Limits
Waste Type Total Volume
ft3(a)
Total Activity
(Ci)
Spent Resin 5,175 16,120
Spent Resin (FFCPD) 7,935 225
Evaporator 20,227 86
Filter Water 4,301 18,269
Miscellaneous Waste 17,884 25
Total(b) 55,500 34,700 (a) Two-year waste generation. (b) Total volumes are rounded to the nearest 100 ft3 and 100 Ci.
SOUTH YARD AREA STATUS
South Yard Facility
Radiological Work Area Available
Decontamination Shop Removed from Service
Multipurpose Handling Facility (MPHF) Available
11.2.1 LIQUID RADWASTE
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November 2016 11-15 Rev 3
Currently no liquid radwaste is handled in the South Yard Area, except as discussed in 11.2.1.2
below for the MPHF area.
11.2.1.1 Design Basis
11.2.1.1.1 Mixed Waste Room of South Yard Facility Radiological Work Area
Mixed Waste is defined as a material that is both hazardous as defined by the EPA criteria in 40
CFR and by the State of California in 22 CCR, and radiologically contaminated with licensed
radioactive material per 10 CFR. The South Yard Facility is designed to process non-Resource
Conservation and Recovery Act (RCRA) mixed wastes, in particular used oil, generated by
SONGS. Other examples of mixed waste generated at SONGS are paints, solvents, caustics,
acids, and Freon. These wastes are collected at various satellite accumulation areas and brought
to the hazardous materials pad for consolidation and storage. As treatment or disposal
opportunities become available, these wastes are disposed of in accordance with all applicable
regulations.
11.2.1.1.2 MPHF
The MPHF is designed for low-level solid radwaste staging in accordance with federal, state, and
local permits for Class III combustible or non-combustible liquid radwaste staged in leak tight
containers.
11.2.1.2 System Description
The MPHF provides storage and staging areas only. Within the MPHF, liquid radwaste
containers are placed in either the High Specific Activity Waste area or the Low Specific Waste
area. Any liquid radwaste leakage will be collected through floor trenches and underground
drain lines within the building, sampled, processed, and disposed-of according to applicable site
procedures.
Liquid radwaste staged inside the MPHF must not be Class I flammable or Class II combustible.
Any Class I flammable or Class II combustible liquids staged inside the MPHF must be in U.L.
listed flammable liquid storage cabinets and be as far as possible from Class III combustible
liquids. In addition, if class I flammable or Class II combustible liquids are to be staged inside
the MPHF, an evaluation must be performed to demonstrate that fire protection features provided
are adequate to mitigate a potential fire.
11.2.1.3 Operation
These areas are for storage and staging only. No other operations are currently conducted.
11.2.1.4 Radioactive Releases
No radioactive liquid releases are made from the South Yard Area. Liquid radwaste
accumulated in the South Yard Area is transported to the plant for release.
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11.2.2 GASEOUS RADWASTE
There is no Gaseous Radwaste System in the South Yard Facility (SYF) and the MPHF. HVAC
systems in both buildings are capable of being monitored for radioactive effluent releases, via
RE-7904 (SYF) and RE-1956 (MPHF).
11.2.3 SOLID RADWASTE
11.2.3.1 Design Basis
Radioactive material may be decontaminated, processed, or worked on in the South Yard Facility
(SYF). The SYF is designed to have one potentially radioactive envelope with a monitored
effluent pathway. The SYF is designed with radiological controlled area (RCA) of the building
and has air samples taken in accordance with the ODCM when working with radioactive
materials. The limiting contamination level which would not cause the annual off-site Effluent
Concentration Limit to be exceeded is 3.66 x 1011 dpm/100 cm2. The source strength is based on
the SONGS dry active waste composite. The SYF surface contamination limit is based on the
decontamination of 1 square foot of material per second. The decontamination process is
assumed to be performed continuously for the entire year.
The MPHF is designed for solid radwaste staging in accordance with federal, state, and local
permits for Class III combustible or non-combustible liquid radwaste staged in leak tight
containers. The MPHF's HVAC system is designed such that there is only one release point. The
release point will be monitored when handling radioactive waste that could release to the
environment.
11.2.3.2 Operation
Operation conducted in the SYF include decontamination, processing, and working on
contaminated equipment. The SYF is designed to have one potentially radioactive envelope with
a monitored effluent pathway and has air samples taken in accordance with the ODCM when
working with radioactive materials.
The MPHF is designed for storage and staging of radioactive material. There are no other
operations conducted in the MPHF.
11.2.3.3 Radioactive Releases
The limiting contamination level is 3.66 x 1011 dpm/100 cm2 which would not cause the annual
off-site Effluent Concentration Limit to be exceeded. The source strength is based on the
SONGS dry active waste composite.
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The SYF surface contamination limit is based on the decontamination of one (1) square foot of
material per second. The decontamination process is assumed to be performed continuously for
the entire year.
11.3 NORTH INDUSTRIAL AREA RADWASTE MANAGEMENT SYSTEMS
The NIA is located north of Units 2&3 on the land previously occupied by Unit 1 (see plant
configuration drawing 40028). It is the present location for the Independent Spent Fuel Storage
Installation (ISFSI). There is a sump on the property which directs surface drainage from the
NIA and surrounding property to the Unit 2 outfall. On occasion, the sump also receives water
from sampling wells. Sump effluent is monitored via RE-2101.
11.3.1 LIQUID RADWASTE
11.3.1.1 Design Basis
Drainage and monitoring well water in the NIA sump could potentially be radioactive. Sump
effluent is monitored. Because remediation of Unit 1 is not complete, water from the soil or
drainage pipes could potentially be radioactive. Monitoring well effluent has contained trace
radionuclides, most notably tritium and Cs-137.
11.3.1.2 System Description
Effluent from the NIA sump is directed to the Unit 2 outfall. Radiation Monitor RE-2101
samples the NIA sump discharge flow. Upon detection of radiation RE-2101 trips the sump
pumps. Overflow of the NIA sump is contained within the NIA site. Compensatory measure
provide for batch release after sampling.
11.3.1.3 Operation
NIA pumps can be set in auto or manual. In auto they start and stop based on level. High
radiation will trip the pumps and alarm in the Control Room / Command Center.
11.3.1.4 Radioactive Releases
The presence of ionic radioactivity, principally Cs-137, would indicate contamination of the
normally non-contaminated rain water. Tritium has been detected in the ground monitoring
wells. See Section 11.3.1.1.
11.3.2 GASEOUS RADWASTE
There is no Gaseous Radwaste System in the NIA.
11.3.3 SOLID RADWASTE
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There is no Solid Radwaste System in the NIA. However, the NIA (Unit 1 Industrial Area) is
used from time to time for temporary staging of large contaminated equipment from Units 2
and 3 as it is decontaminated or prepared for shipment to an off-site facility for treatment and / or
disposal. Portions of NIA may be used to support SONGS 2/3 decommissioning activities.
Appropriate contamination control, spill prevention, and effluent control measures, based on the
activity, would be developed and implemented to prevent unplanned, unmonitored releases of
radioactive liquids and/or radioactive airborne material during temporary storage, treatment, and
packaging activities of the contaminated equipment.
11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING
SYSTEMS
STRUCTURES / SYSTEMS / COMPONENTS STATUS
Process Radiological Monitoring Removed from Service
Effluent Radiological Monitoring Partially Removed from Service
The effluent radiological monitoring system monitors and provides information to operators
concerning activity levels in selected plant effluents.
The system consists of permanently installed sampling and/or monitoring devices together with a
program and provisions for specific routine sample collections and laboratory analyses. The
overall systems are designed to assist the operator in evaluating and controlling the radiological
consequences of normal plant operation, anticipated operational occurrences, and postulated
accidents such that resultant radiation exposures and releases of radioactive materials in effluents
to unrestricted areas are maintained as low as reasonably achievable.
11.4.1 DESIGN BASES
11.4.1.1 Normal Operations
The effluent monitoring system is designed to perform the following functions in order to meet
the requirements of 10CFR20, 10CFR50, and follow the recommendations of Regulatory
Guide 1.21 during normal operations, including anticipated operational occurrences:
A. Provide continuous representative sampling, monitoring, and indication of liquid and
gaseous radioactivity levels, and, as a minimum, continuous representative sampling of
particulate and iodine radioactivity levels along principal effluent discharge paths.
B. Provide the capability, during the release of radioactive liquid wastes, to alarm and
automatically secure liquid waste releases before the limits of the ODCM specifications
are exceeded.
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C. Provide radiation level indication and alarm annunciation to the
Control Room / Command Center operators whenever ODCM specification limits for
release of radioactivity are approached or exceeded.
D. For continuous effluent paths, provide a means for collection and laboratory analysis of
required routine samples.
E. For batch releases, provide a means for collection and laboratory analysis of required
routine samples prior to release.
11.4.1.2 Postulated Accidents
Radiation monitoring systems are designed to perform the following functions in order to meet
the requirements of 10CFR50, for postulated accidents:
A. Effluent radiation monitors provide continuous gaseous monitoring during the remaining
Chapter 15 accidents and those conditions, as well as during normal operating
conditions, to quantify release rates for noble gases from all potential release points.
B. Effluent radiation monitors provide monitoring of particulate radionuclides collected by
absorption on sampling media, followed by laboratory analysis.
C. Area radiation monitors in the Fuel Handling Building provide an indication of
abnormal operating conditions (pool level, stored fuel damage, etc.).
11.4.2 SYSTEM DESCRIPTION
The requirements of the system design bases for continuous monitoring are satisfied by a system
of monitors, including independent detector channels with their associated sampling and
auxiliary equipment.
The following describes the features of the effluent radiation monitoring systems that apply to
both analog and digital radiation monitors.
1. All airborne particulate and iodine monitors and samplers, sample isokinetically in
accordance with the principles and methods of ANSI N13.1-1969, Guide to Sampling
airborne Radioactive Materials in Nuclear Facilities.
2. The particulate sampler collection efficiency is greater than 95% for 0.3µ particulates.
Table 11.4-1 is a tabulation of basic information describing each of the continuous effluent
radiation monitors and sampler, including monitor location, type of monitor and measurement
made, sampler and/or detector type, calibration isotope, range of activity concentrations to be
monitored and expected concentrations, alarm setpoint, provisions for power supplies, and
automatic actions initiated.
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Bases for the ranges of effluent monitors listed in Table 11.4-1 are as follows:
A. For effluent monitors, the ranges include:
1. Maximum calculated concentrations during normal operations and post-accident
conditions.
2. Minimum concentrations that must be detected in order to allow automatic and/or
manual actions to avoid exceeding ODCM specifications for the release of
radioactivity.
For effluent monitors, the setpoint is chosen as an appropriate fraction of the applicable ODCM
specification limit for the release of radioactivity in order to allow automatic and/or manual
actions to avoid exceeding the limit.
CDAS and Hallway Remote Monitors satisfy the redundancy, diversity, and independence
design bases for postulated accident in the permanently defueled condition.
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Table 11.4-1
CONTINUOUS EFFLUENT RADIATION MONITORING
Sampler/Monitor
Location Quantity Sampler Type Detector Type
Activity
Measured
Calibration
Isotope (f)(g)
Range
(µCi/cm3)
Expected
Concentrations
(µCi/cm3)(b)
Alarm(I)
Setpoint
(µCi/cm3)
Power
Supply(l)
Automatic
Actions
Initiated
Radwaste discharge
line (RDL.) monitor
(2/3RE7813; P&ID
40132C)(j)
1 Offline/liquid γ scintillation Gross β
Cs-137
Ba-133
Co-60
10-6-10-1
7.2x10-4
Cs-137
1.0x10-3
Cs-134
4.4x10-5 I-131
ODCM,
SP
Alarm and
secure radwaste
discharge to
outfall
Turbine plant sump
(TPS) monitor
(2RE7821; P&ID
40119A) (j)
1 Offline/liquid γ scintillation Gross γ
Cs-137
Ba-133
Co-60
10-6-10-1 < LLD ODCM,
SP
Alarm and
secure turbine
plant area sump
pumps
Plant vent stack
airborne (PVSA)
monitor
(2/3RE7808; P&ID
40175B)(j)
1 Offline/gas β solid state Gross β
Kr-85
Xe-133
Cl-36
Cs-137
10-6-10-1 5.4x10-4/
<LLD Kr-85 ODCM Alarm
Fixed paper &
charcoal cartridge
Detector not
used
Plant vent stack wide range (2RE7865-1 and 3RE7865-1; P&ID 40171C & 40171CS03)(j)
2 (1 per unit)
Offline/gas
Low range: plastic
scintillator Gross γ
Cl-36 Cs-137
10-7 to 10-1
(Xe-133)
5.4x10-4/ LLD Kr-85
ODCM Alarm
Mid-range: solid state
Gross γ Am-241 Cs-137 Ba-133
10-4 to 102
(Xe-133) < LLD
High range: solid state
Gross γ Cs-137 Am-241 Ba-133
10-1 to 105
(Xe-133) < LLD
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Table 11.4-1
CONTINUOUS EFFLUENT RADIATION MONITORING
Sampler/Monitor
Location Quantity Sampler Type Detector Type
Activity
Measured
Calibration
Isotope (f)(g)
Range
(µCi/cm3)
Expected
Concentrations
(µCi/cm3)(b)
Alarm(I)
Setpoint
(µCi/cm3)
Power
Supply(l)
Automatic
Actions
Initiated
Offline/isokinetic/ fixed particulate
filter No detector
Offline/isokinetic fixed charcoal
cartridge No detector
North Industrial
Area Yard Drain
Sump monitor
(2/3RE2101; P&ID
40119C)(j)
1 Offline/ liquid γ scintillation Gross γ Cs-137 10-6 to
10-1 < LLD
ODCM,
SP 2/3B58
Alarm and
initiate stop of
sump pumps
* These are initial setpoints, methodology to derive setpoints is found in the Unit 2, and 3 Offsite Dose Calculation Manual (a) Deleted. (b) LLD is less than the lower limit of detection. (c) Deleted (d) Deleted (e) Deleted (f) Ba-133 is the calibration isotope for I-131. (g) Kr-85 is the calibration isotope for Xe-133. (h) Deleted (i) This column represented initial alarm/trip setpoints, based upon design calculations N-4098-1 & N-720-3, (J-SPA-219 & J-SPA-329 digital monitors) used for
commencement of plant operations. Subsequent setpoints are established in accordance with 90010A and the Setpoint Program letter, dated March 28, 1994
(Docket 50-361 & 50-362) in response to 50.54(f) and/or the Offsite Dose Calculation Manual (ODCM), as appropriate, and administratively controlled per station
procedures. (j) Effluent Radiation Monitor. Setpoints are calculated per ODCM methodology. Alarm value provided is only indicative of range. (l) Power supplies are from common Cold & Dark Electrical System 2/3Q2005 (Dwg 38873 Sheet 2) except where noted.
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11.4.2.1 Gaseous Effluent Radiation Monitor Description
The effluent radiation monitoring system consists of Analog and Digital effluent monitors and
CDAS display panels.
11.4.2.1.1 Unit Specific Gas Effluent (Plant Vent Stack) Monitoring
The following two (2) monitor loops comprise unit specific gas effluent plant vent stack
radiation monitors: 2RE7865A1/B1/C1 and 3RE7865A1/B1/C1.
The monitoring equipment is designed to function properly under the following environmental
conditions:
An ambient temperature range of 40oF to 120oF
0% to 100% relative humidity
An external radiation field of 2.5 mR/hr (Co-60) [100 R/hr for wide range radiation
monitors]. 2RE7865-1 and 3RE7865-1 have been analyzed to 115 R/hr external radiation
field.
The following sections provide specific information for each effluent monitor.
Wide Range Radiation Monitors
Radiation monitors 2RE7865A1/B1/C1 and 3RE7865/A1/B1/C1 comprise the Wide
Range Gas Monitors (WRGM). Refer to Table 11.4-1 for monitor specifications.
The Plant Vent Stack is provided with wide range gas monitors. There are two sets of
isokinetic samplers provided for each stack. Each isokinetic sampler consists of two sets
of isokinetic nozzles, one for sampling during low concentration levels and one for
sampling during high concentration levels.
Each monitor has a flow transmitter that measures the total vent flow rate for each of the
vents being sampled. This signal is used to control the sample flow rate so as to maintain
true isokinetic sampling conditions. The vent flow rate signal also allows the operator to
display the effluent radiation level in units of µCi/cc (Xe-133).
The sample conditioning assembly is connected to the isokinetic samplers and provides
for both collection of particulate and iodine samples. There is one sample collector and it
is low range operation. Filter holders are connected via quick disconnect fittings to allow
rapid retrieval of particulate and iodine samples for isotopic analysis. Charcoal is used
during normal operation. Sampling conditioning is provided to prevent contamination of
the detection assembly by filtering out a major proportion of the iodine and particulate.
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The wide range effluent monitor draws a sample from isokinetic probes located at
elevation 152 ft. in the plant vent stacks. The isokinetic flow manifold, sample
conditioning and sample detection skid are located at elevation 63 ft. 6 in. of the
penetration area.
The function of this monitor is to supplement the capability of the plant vent stack
airborne monitor by providing high range capability (10-7 to 105 µCi/cc) for measuring
noble gas concentrations. The monitor functions to alarm when the preset level is
reached. The isokinetic nozzles sample properly with stack flows from 91,300 standard
ft3/min to 66,400 standard ft3/min (+10%, -20%) of the 83,000 standard ft3/min design
flow rate.
The detector assembly contains three radioactive gas detectors that monitor the sample
discharged from the sample conditioning assembly. Table 11.4-2 specifies the
arrangement of the individual detectors. The 12 decades of noble gas concentrations are
monitored by the three detectors with at least one decade overlap between ranges of the
individual detectors. The low-range detector utilizes a plastic scintillation detector. The
mid and high-range detectors are a solid state CdTe. Each detector has a
solenoid-actuated check-source to verify proper operation.
Table 11.4-2
Wide Range Radiation Monitors
Range Plant Vent Stack
Wide Range Radiation
Low Range 2RE7865A1
3RE7865A1
Mid Range 2RE7865B1
3RE7865B1
High Range 2RE7865C1
3RE7865C1
There are two flow paths through the detectors. During normal operation only the
low-range detector is used and the mid-range and high-range detectors are offline. As the
low-range detector reaches the concentration switch setpoint, the flow path is
automatically changed to the mid and high-range detectors and the low-range detector is
purged to prevent contamination of the low-range detector. Figure 11.4-3 and Controlled
Drawings 40171C, 40171CS03, 40152D, and 40152DS03 show the sample detection skid
flow diagram.
The detector assemblies are shielded with lead and are designed to detect over their
specified range in a 115 R/hr (Co-60) external field.
The monitor is operated by the Model RM-80 microprocessor located in the Control
Room / Command Center. A digital readout located in the Control Room / Command
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Center provides a display of all monitored parameters including channel activity and flow
rate, alarm status, check-source actuation, etc. The RM-80 also maintains history files of
channel activity that are available for recall. The stack effluent (µCi/sec) and each
detector output (µCi/cc) are continuously recorded.
11.4.2.1.2 Common Plant Vent Stack - PVS Monitor (2/3RE7808G)
The PVS channel samples for and monitors gaseous activity in the exhausted air and the
PVS monitor functions to alarm when the preset level is reached.
The PVS monitor is a one-channel off-line monitor for noble gas activity. It draws a
sample from and returns it to the ventilation duct leading to the plant vent stack,
downstream of the continuous exhaust plenum. The detector uses a beta-sensitive PIPS
detector located in a lead shielded sample chamber. The monitor is located in the
radwaste building at the 63 ft. 6 in. level. The detector skid contains the required piping,
sample pump, valves, and fittings to draw an off-line sample from the plant vent stack.
11.4.2.2 Liquid Effluent Radiation Monitoring Systems
The following three (3) monitors are included in digital liquid radiation monitoring
systems: 2/3RE7813, 2RE7821, and 2/3RE2101. Refer to Table 11.4-1 for monitor
specifications.
The digital liquid monitor detector configuration is off-line with the detector mounted in a lead
shield. The lead shielded assembly contains a gamma-sensitive NaI scintillation crystal and
photomultiplier tube. The scintillation detector is operated in the gross gamma detection mode.
The Field Units (FU) consist of the radiation detection unit (RU), the local processing unit
(LPU), the local display unit (LDU), and the remote display unit (RDU). This section describes
the components of the FU.
System equipment is designed to function properly under the following environmental
conditions:
An ambient temperature range of 36oF to 110oF
0% to 100% relative humidity
An external radiation field of 2.5 mR/hr (Cs-137).
Each radiation channel is designed to indicate full scale readings in the range from its normal
design range upper limit to a level 100 times this upper design limit.
The different types of detector assemblies used are described below.
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Radwaste Discharge Line (RDL) Monitor (2/3RE7813)
The RDL monitor is installed on a bypass sample line off the radwaste discharge line, upstream
of the radwaste discharge control valve. It is located at the 9-foot level. Sample low flow alarm
is provided in the Control Room / Command Center CDAS, via the 2/3RE7813 Failure alarm, to
indicate the sample flow rate in the sample line is below the specified setpoint, when the main
process flow is present.
During normal operation, the radwaste discharge line receives liquid from the miscellaneous
wastes condensate monitor tanks and discharges to the Unit-2 outfall. The RDL channel
continuously monitors this line for the presence of ionic radioactivity, principally Cs-137. The
presence of an abnormally high level of radioactivity in this line may indicate improper operation
of the radwaste system. The function of this monitor is to alarm on high - radiation level and to
terminate radwaste discharge to the Unit-2 Outfall by securing the operating pump.
Turbine Plant Sump (TPS) Monitor (2RE7821)
The TPS monitor is installed on a bypass sample line off the turbine plant sump pump discharge
line, upstream of the sump diverting valves to the oily waste separator and radwaste area sump.
The monitor is physically located in the Unit-2 turbine building at the 7-foot level, along the
west wall. Sample driving head is provided by sump pump discharge pressure in the main sump
discharge line. Sample low flow alarm is provided in the Control Room / Command Center
CDAS, via the 2RE7821 Failure alarm, to indicate the sample flow rate in the sample line is
below the specified setpoint, when the main process flow is present.
The turbine plant sump collects liquid leakage from various floor and equipment drains in the
turbine area of the plant. The sump pumps normally discharge to the oily waste holding sump,
and then to the Unit-2 Outfall. The TPS channel continuously monitors this discharge line to the
oily waste holding sump. The presence of ionic radioactivity, principally Cs-137, would indicate
the leakage of radioactive liquid from a normally nonradioactive system. The function of the
monitor is to alarm on high radiation level and to terminate sump discharge by automatically
securing the TSP discharge pump. Sump contents may then be diverted to the radwaste system
for processing, storage, or may be treated using appropriate local methods.
North Industrial Area Yard Drain Sump Monitor 2/3RE2101
The NIA Yard Drain Sump monitor is installed on a bypass sample line off the sump pumps
P1059 and P1060 discharge lines. The monitor is located on the roof of the sump. Sample
driving head is provided by the sump pump’s discharge pressure. Sample low flow alarm is
provided in the CDAS to indicate whether the flow rate in the sample line is below the specified
setpoint when the pumps are in operation.
The NIA Yard Drain Sump collects water from within the NIA and the surrounding areas via
Catch Basin (CB) 5. The sewage treatment plant overflow is routed to the sump. On occasion
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the sump receives effluent from ground monitoring wells located in the NIA. The sump
discharges to the Unit 2 outfall. Because portions of the area have a history of previous
contamination, the sump discharge is required to be continuously monitored. The presence of
ionic radioactivity, principally Cs-137, would indicate contamination of the normally non-
contaminated rain water. The function of the monitor is to alarm on high radiation level and to
terminate sump pump operation. The NIA Yard Sump monitor is comprised of an LPU and
LDU which displays alarms and displays on the CDAS.
11.4.2.3 Area Radiation Monitoring
Three Area radiation monitors are in service;
2RE7850 located in the Unit 2 Fuel Handling Building
3RE7850 located in the Unit 3 Fuel Handling Building
2/3RE7851 located in the Control Room / Command Center
All three area radiation monitors are standalone single channel area radiation monitors. They
provide local strobe and audio alarming in addition to remote CDAS indication, status and
alarming in the Control Room / Command Center.
11.4.3 CONTROL ROOM / COMMAND CENTER PANELS
The radiation monitoring system (RMS) instrumentation display and control equipment located
in Control Room / Command Center control panels listed below.
Control Room / Command Center Hallway Panels1
Panel 2L405 - Unit 2 RMS
2RI7865A1,B1,C1 Plant Vent Stack/ WR Rad
Panel 2/3L104 - Common RMS
2/3RIC7808G Plant Vent Stack Radiation
2/3RIC7813 Radwaste Discharge Line Rad
2RIC7821 Turbine Sump Discharge Radiation
Panel 3L405 - Unit 3 RMS
3RI7865A1,B1,C1 Plant Vent Stack WR Rad
1 NIA Yard Sump monitor 2/3RIC2101 is on the CDAS and not in hallway.
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11.4.4 RECORDERS
In-service radiation monitors output is displayed and trending data is on the
Control Room / Command Center Data Acquisition System (CDAS). CDAS provides trend
indications for the in-service radiation monitors.
11.4.5 INSPECTION, CALIBRATION AND MAINTENANCE
11.4.5.1 Maintenance
Plant radiation and effluent monitors are inspected, calibrated and maintained in accordance
plant procedures to ensure ODCM compliance.
11.4.5.2 Calibration and Inspection
Plant radiation and effluent monitors are inspected, calibrated and maintained in accordance
plant procedures to ensure ODCM compliance
Table 11.4-1 provides the isotopes used for calibration. For the initial calibration, additional
isotopes were used to verify the detector energy response. The calibration sources used,
duplicate to the extent practicable, the source to detector geometry expected during normal
operation.
11.4.6 ROUTINE SAMPLING
The requirements of the system design bases for routine continuous and discrete sampling of
radioactivity are satisfied by a system of liquid, gaseous, and airborne samplers, laboratory
equipment for sensitive radiochemical analyses, and a program of procedures for obtaining and
analyzing representative samples when and where appropriate in accordance with the
requirements of the Offsite Dose Calculation Manual (ODCM).
11.4.6.1 Sampling Equipment and Procedures
The following text discusses representative procedures to be used as needed to meet
requirements of the Offsite Dose Calculation Manual (ODCM). Actual procedures may vary
provided that ODCM-established control and accuracy commitments are maintained.
Sampling equipment and procedures are provided to assure that representative samples are
obtained. Prior to sampling, batch liquid tanks such as radwaste tanks are properly isolated,
recirculated, and sample lines purged to assure that individual samples are representative of the
effluent mixture prior to discharge to the outfall. For the NIA Yard sump, proportional samples
are taken manually from the sump itself. For continuous flowpaths, such turbine plant sump,
liquid proportional samplers are installed to assure that samples, representative of the effluent
mixture, are collected during discharge to the outfall. During initial crediting of the release point
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in the ODCM, a series of samples were taken during the interval of discharge to determine
whether any differences existed as a function of time and to assure that individual samples were
indeed representative of the effluent mixture. Polyethylene collection bottles are used to
preclude the loss of radioactive material by deposition on the walls of the sample container or
volatilization of potentially volatile material.
Plant Vent Stack ventilation stacks are continuously monitored for radioactive gases and sampled
isokinetically in accordance with ANSI N13.1-1969 for particulates and iodines. The particulate
and iodine samples are collected and analyzed once a week. Gas and tritium samples are
collected and analyzed once a week. South Yard Facility Work Area effluent ventilation stacks
are continuously monitored for particulates and sampled isokinetically in accordance with ANSI
N13.1-1969 for particulates and iodines (see Section 11.2). The particulate and iodine samples
are collected and analyzed weekly.
Liquid composite samples are collected in proportion to the volume of each batch of effluent
releases or in proportion to the rate of flow of the effluent stream. Prior to analysis, the
composite is thoroughly mixed so that the sample is representative of the average effluent
release. Gaseous particulate samples are mixed in proportion to the volume of release or in
proportion to the rate of flow from each effluent pathway. Samples are composited and analyzed
at an off-site facility in accordance with standard procedures.
11.4.6.2 Analytical Procedures
Samples of effluent gases and liquids are analyzed in accordance with plant procedures to meet
the requirements of the ODCM.