RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 12, Radiation Protection
Text
REFERENCE LEGEND FOR SECTION 12.1 FIGURES PLANT RADIATION ZONE DESIGNATIONS Zone Color Code DescriptionDose Rate (mRem/hr)I Uncontrolled No restrictions on occupancy expected
< 1.0 mRem/hr II Controlled Unlimited access, 40 hrs/week
< 2.5 mRem/hr III Controlled Limited access, 6 to 40 hrs/week < 15.0 mRem/hr IV Limited access for short periods, 1 to 6 hrs/week
< 100 mRem/hr V Controlled, High Radiation Area Occupancy averages less than one
hour per week
> 100 mRem/hr Notes For Layout Drawings Showing Radiation Color Code Figures 12.1-12, 12.1-13, 12.1-17 and 12.1-18 The solid color of the cross-hatched areas represents t he radiation zone designations during a shutdown/refueling period while the RHR system is not in operation. The cross-hatched color repr esents the radiation zone designations during a shutdown/refueli ng period while the RHR system is in operation.
Figure 12.1-16 The solid color of the cross-hatched areas represents t he radiation zone designations during a shutdown/refueling period while the refueling canal and the region above the reactor vessel are flooded.
The cross-hatched color represents the radiation zone designations during a shutdown/refuelin g period while the refueling canal and the region above the reactor vessel are not flooded.
Figure 12.1-0 Amendment 02-01 May 2002
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TABLE 12.2-1 CALCULATED AIRBORNE CONCENTRATIONS (1) Isotope Reactor Building Concentrations (2) (Ci/cc) Auxiliary Building Concentrations (Ci/cc) Letdown Heat Exchanger Room Concentrations (3) (Ci/cc) Turbine Building Concentrations (Ci/cc) H-3 8.7 x 10-4 1.4 x 10-8 2.0 x 10-7 3.0 x 10-10 Kr-85m 1.3 x 10-6 2.1 x 10-9 2.9 x 10-7 1.1 x 10-14 Kr-85 9.6 x 10-6 1.6 x 10-10 2.2 x 10-8 8.2 x 10-16 Kr-87 4.3 x 10-7 2.1 x 10-9 3.2 x 10-7 1.2 x 10-14 Kr-88 1.6 x 10-6 3.8 x 10-9 5.4 x 10-7 2.1 x 10-14 Xe-131m 3.0 x 10-5 1.1 x 10-9 1.5 x 10-7 5.4 x 10-15 Xe-133m 2.5 x 10-6 3.4 x 10-10 4.7 x 10-8 1.8 x 10-15 Xe-133 1.1 x 10-4 6.9 x 10-9 9.5 x 10-7 3.6 x 10-14 Xe-135m 8.2 x 10-8 1.4.x 10-9 2.5 x 10-7 1.0 x 10-14 Xe-135 1.2 x 10-5 9.6 x 10-9 1.3 x 10-6 5.1.x 10-14 Xe-137 5.3 x 10-9 1.6 x 10-10 3.9 x 10-8 2.1 x 10-15 Xe-138 7.0 x 10-8 1.2 x 10-9 2.3 x 10-7 9.5 x 10-15 Br-84 2.1 x 10-11 1.6 x 10-12 2.6 x 10-10 3.4 x 10-16 I-131 1.6 x 10-8 5.4 x 10-12 7.4 x 10-10 1.1 x 10-14 I-132 1.2 x 10-9 2.6 x 10-11 3.7 x 10-9 1.6 x 10-14 I-133 6.6 x 10-9 1.7 x 10-11 2.4 x 10-9 2.8 x 10-14 I-134 7.3 x 10-10 3.8 x 10-11 5.8 x 10-9 1.2 x 10-14 I-135 4.1 x 10-9 3.3 x 10-11 4.5 x 10-9 3.6 x 10-14 02-01 (1) Based upon the assumptions given in Sections 12.2.3 and 12.2.6. (2) Concentrations at the end of interval between purges and without operation of the reactor building charcoal cleanup system.
(3) Concentrations are based upon the assumption that one-half of the auxiliary building leakage occurs in the letdown heat exchanger room.
12.2-19 Reformatted Per Amendment 02-01 TABLE 12.2-2 AIR FLOW RATES AND APPROXIMATE NET FREE VOLUMES SERVED BY VENTILATION SYSTEMS System System Exhaust Flow Rate Approximate Net Free Volume Served (ft
- 3) Control Room Ventilation System 21,270 cfm/emergency system fan 226,040 Controlled Access Area Exhaust
System 16,000 cfm/fan 73,890 (1) Spent Fuel Pool Area Ventilation
System 27,000 cfm/fan 629,260 (1) Auxiliary and Radwaste Area
Ventilation Systems 123,800 cfm, total 1,890,000 Turbine Building Ventilation S ystems 1,500,000 cfm, total 3,700,000 Reactor Building Charcoal Cleanup
System 24,000 cfm, total 1,800,000 RN 02-048 RN 02-048 RN 02-048 RN 01-119 (1) Original Licensing / Construction Estimates 12.2-20 Reformatted Per Amendment 02-01 TABLE 12.2-3 AIRBORNE RADIOACTIVITY MONITORS MONITOR FUNCTION DETECTORS POWER SOURCE RM-A1 Control Room Supply Air Monitors ventilation air supplied to control room 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus B (1) RM-A2 Reactor Building Air
Sample Line Monitors sample taken
from containment 1. Particulate-Beta, 5.5 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2.6 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus B (1) RM-A3 Main Plant Vent Exhaust Monitors effluent from
auxiliary building 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2.6 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus A (1) RM-A4 Reactor Building Purge Exhaust Monitors effluent from containment during purge 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus A (1) RM-A6 Fuel Handling Building Exhaust Monitors ventilation discharge from fuel handling building 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus B (1) RN 03-011 12.2-21 Reformatted Per Amendment 02-01 TABLE 12.2-3 (Continued) AIRBORNE RADIOACTIVITY MONITORS MONITOR FUNCTION DETECTORS POWER SOURCE RM-A7 Sampling Rooms Monitors air sample
from sampling room.
Movable unit - may be used for other areas as
required. 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 480 volt outlets RM-A8 Spent Fuel Area Monitors local air
sample. Movable unit - may be used for other areas as required. 1. Particulate-Beta, 4.7 x 10
-11 to 10-7 Ci/cc, Cs-137 2. Iodine-Gamma, 2 x 10
-11 to 2 x 10
-7 Ci/cc, I-131
- 3. Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 480 volt outlets RM-A9 Condenser Air Removal Monitors effluent of condenser off-gas discharge Gas-Gamma, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Xe-133 Bus B RM-A10 Waste Gas Discharge Monitors discharge of waste gas-provides backup to decay tank
analysis Gas-Gamma, 2 x 10
-4 to 2 Ci/cc, Xe-133 Bus B RM-A11 Auxiliary Building
Ventilation Sequentially monitors
various auxiliary building ventilation
exhaust ducts Gas-Beta, 2 x 10
-6 to 2 x 10
-2 Ci/cc, Kr-85 Bus B (1) 02-01 RN 03-011 12.2-22 Reformatted Per Amendment 02-01 Reformatted Per Amendment 02-01 TABLE 12.2-3 (Continued) AIRBORNE RADIOACTIVITY MONITORS MONITOR FUNCTION DETECTORS POWER SOURCE RM-A12 Movable Particulate Unit Provides local
particulate monitoring
and iodine sampling Particulate-Beta, 10
-11 to 10-7 Ci/cc, Cs-137 120 volt outlets RM-A13 Main Plant Vent Exhaust, High Range Gas Discharge Effluent High Range Gas Monitor Ion Chamber - Gamma
0.1 to 10 7 mr/hr (10-2 to 10 5 Ci/cc, Xe-133)
Bus A RM-A14 Purge Exhaust Effluent, High Range Effluent High Range
Gas Monitor Ion Chamber - Gamma
0.1 to 10 7 mr/hr (10-2 to 10 5 Ci/cc, Xe-133)
Bus A RM-G19 A, B, C
Steam Line Steam Line High Range Gamma Monitor Ion Chamber - Gamma
0.1 to 10 7 mr/hr Bus B RN 02-002 RN 03-011 12.2-23 (1) Associated sample pump powered from diesel backed 480 volt bus.
TABLE 12.2-4 ESTIMATED DETECTION TIME FOR I-131 AND Cs-137 IN THE FUEL HANDLING BUILDING Fuel Handling Building Area (1) Exhaust Flow (cfm) Dilution Factor Detection Time (Minutes)
I-131 Cs-137 Spent Fuel Area 15,320 0.567 0.8 0.7 General Flow Area 1,840 0.068 7.0 5.5 Railroad Area 3,020 0.112 4.3 3.4 Personnel Cleanup (2) 242 0.009 53.6 42.0 Emergency Personnel Hatc h 1,750 0.065 7.4 5.8 412 South West 1,470 0.054 8.8 6.9 Decontamination 1,120 0.041 11.6 9.1 Excess Waste Holdup Tank 950 0.035 13.6 10.7 Decontamination Pit
Collection Tank 686 0.025 18.9 14.8 RN 01-119 Notes: 1. Small areas, access to whic h is controlled due to potentia lly high activity levels, are not included since access is under administrative control.
- 2. The personnel cleanup area is listed although it is not considered as a source of activity.
12.2-24 Reformatted Per Amendment 02-01 GENERAL NOTES: 1.<:=DENOTES AIR FLOW.2.....DENOTES FILTER REMOVAL.3.TAG NO.XAA-29A-AH.
4.TAG NO.XAA-29B-AH
- 5.SAFETY CLASS-2b.6.MAXIMUM UNIT CAPACITY 21,000 CFM.7.OPERATING WT.28,149 LB.8.SHIPPING WT.21,714 LB.9.THIS DESIGN IS PRELIMINARY ONLY.THE FINAL DESIGN MAY DEVIATE FROM THIS ARRANGEMENT.
- 10.ALLOW 42" CLEARANCE ABOVE FOR CHARCOAL FILLING.0 11.DblE TO HEIGHT LIMITATIONS FLOOR SLOPE WILL BE APPROX.1/2" IN 11'-0".o..0 3t"*-c, 0:-Iff>-I-",@c ,./0 r-S t@,LIGHT ASSY.(TYP.8 PLACES)COMP DR.a"cvI.
CR.(T"rP-4.PL.)18'-0..0 (}-9...0 0'2.'-102-3 ROUGHING FILTER 3H X 5W@2000 CFM EA.---HECAŽ(2" CHARCOAL/BED)'
_____---.11 BEDS@2000 CFM EA.----------HEPA FILTER-r-T:'_g=--
i-f......".-+!--r-r::;-o"'i-'------=-t-"'-,--,3H X 5W@1500CFMEA.
cr ():: SOUTH CAROLINA ELECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Control Room Emergency Charcoal Filter Plenum Figure 12.2 c 1 l..---.;
CONTROL BUILDINGRAD MAINT.
BLDGHOT MACH.SHOPEAST/WEST PENETRATION RM A13 RM A39000 CFM4000 CFM52200 CFMCONTROLLED ACCESSCHARCOAL EXH. FILT.16000 CFMSAMPLING ROOMSAMPLE & LAB.
HOODS MISC. CLEAN AREAS RM A1 RM A7 PLANT VENT 238,188 CFMFUEL HANDLING BUILDINGFUEL HANDLING BUILDINGCHAR. EXH.FILTERS30000 CFM MISC. AREASSPENT FUEL AREA RM A8 RM A615320 CFM575 CFMHOT MACH.SHOP3000 CFMAUXILIARY BUILDINGAUX. BLDG.
HEPAFILTERS39375 CFMAUX. BLDG.HEPA &CHAR. FILT.45680 CFMAUX. BLDG.HEPA &CHAR. FILT.42695 CFMMISC.CONTROLLED AREASMISC.CONTROLLED AREASMISC.CONTROLLED AREASACCESS &CORRIDORSSUPPLY RM A12 RM A11SOUTH CAROLINA ELECTRIC & GAS CO.VIRGIL C. SUMMER NUCLEAR STATIONAirborne Activity MonitoringASSOCIATED WITH FSAR FIGS9.4-4, 9.4-7, 9.4-8, 9.4-9,9.4-10a, 9.4-11, 9.4-26a Figure 12.2-2 Rev. 2SUPPLYRN 01-119June 2006 RN 13-011 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Buildup of Predominate Particulates in Reactor Building From 1 gpm Reactor Coolant Leak as a Function of Time After Leakage Begins Figure 12.2
-3 1.E-081.E-071.E-061.E-050.1 1101001000PARTICULATE CONCENTRATION IN RB (TIME (HOUR)1 GPM PRIMARY COOLANT LEAKAGE IN REACTOR BUILDING PRIMARY COOLANT CONCENTRATIONS PER SECTION 12.2.4.4 PARTITION FACTOR = 0.3 1000 CFM CONTINUOUS PURGE OF REACTOR BUILDING RN 13-011 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Buildup of Xe
-133 in Reactor Building From 1 gpm Reactor Coolant Leak as a Function of Time After Le akage Begins Figure 12.2
-4 1.E-061.E-051.E-041.E-030.1 1101001000 XE-133 CONCENTRATION IN RB (Ci/cc)TIME (HOURS
)1 GPM PRIMARY COOLANT LEAKAGE IN REACTOR BUILDING Xe-133 PRIMARY COOLANT CONCENTRATION OF 5.1 x 10
-5 Ci/gm Xe-133 PARTITION FACTOR = 1 1000 CFM CONTINUOUS PURGE OF REACTOR BUILDING
NOTE FIGURE 12.3-1 Figure 12.3-1 is being retained for historical purposes per NEI 98-03, Revision 1.Vice PresidentNuclear OperationsGeneral ManagerNuclear Plant OperationsManagerHealth Physics ServicesSupervisorCount RoomSupervisor ALARASupervisorField Operations SupervisorRadwasteStaff Health PhysicistsHealth Physics SpecialistsSupervisorHealth Physics Support ServicesSupervisorRadiological Analytical Services 00-01 00-01 SOUTH CAROLINA ELECTRIC & GAS CO, VIRGIL C. SUMMER NUCLEAR STATION Amendment 00-01 Decmeber 2000 Health Physics Organization Chart Figure 12.3-1