ML20245E024
| ML20245E024 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/28/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89221, NUDOCS 8905010271 | |
| Download: ML20245E024 (16) | |
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Log # TXX-89221 File # 10010, 912.2 i
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1 1UELECTRIC April 28, 1989 W.J.Cahm-Earcutive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk
-Washington,'D. C.
20555 L
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION ON CHAPTER 12 REF: TV Electric letter to the NRC logged TXX-89124 dated
. March 8, 1989 Gentlemen:
The attached response address the remaining NRC question on the CPSES FSAR Chapter 12.
Responses to the other questions were provided in the referenced letter. FSAR changes which may be needed as a result of this response will be incorporated in a future FSAR amendment.
Sincerely, i
21 William J. Cahill, Jr.
GLB/ddm Attachment Enclosure c - Mr. R. D. Martin, Region IV Mr. J. H. Wilson, NRR-0SP Ms. M. Malloy, NRR-0SP i
Resident Inspectors, CPSES (3) i 1
0%
8905010271'epo428 PDR ADOCK0500g5 4
4(X) North Olwe Street LB 81 Dallas, Texas 75201
1 Attschmsnt to TXX-89221 April 28, 1989 Page 1 of 6 RESPONSE TO NRC QUESTION - CHAPTER 12 RADIOACTIVE AIRBORNE CONCENTRATIONS QUESTION #2:
The following are several apparent discrepancies noted in the data presented in Table 12.2-26." Radioactive Airborne Contamination."
Verify the results listed in Table 12.2-26.
If the bases for the input data for the airborne concentration calculations is not NUREG-0017 - GALE code, then describe in detail the bases for the input parameters used.
a.
Table 12.2-26 sheets 6 through 14 contain calculated airborne concentrations for radionuclides in nine rooms and corridors in the safeguards building.
Although Table 12.2-25 lists very different calculational parameters for these areas, the results for each of these nuclides are the same for all nine areas (allowing for some round off error).
b.
The input parameters are listed in Table 12.2-25 sheets 14 and 15 for the turbine building basement and mezzanine, respectively.
Comparing these with the results of airborne Tritium (H3) for those areas (Table 12.2-26 sheets 16 and 17), seems to indicate that increasing the leak rate about 2.5 times (in rooms of about the same size and ventilation flow rate) increases the H3 airborne concentration by 37 orders of magnitude.
Also, justify it design that has.5 MPC of H3 on the turbine building mezzanine during normal operation.
c.
Table 12.2-26 sheets 23 through 31 have fifty-three (53) incorrectly listed as the atomic number for Br, Co, Rb, Sr, Mo, and Cs.
RESPONSE #2:
Potential airborne concentrations in buildings and various areas throughout the Comanche Peak plant have been calculated.
A discussion of the assumptions, key parameters (including those parameters that differ from NUREG-0017, Revision 1), methodology, and results follows.
Specific responses to Question items a, b, and c are addressed in the results section.
Calculations will be approved and available for review on site by May 20, 1989.
Attdchm:nt to TXX-89221 4
April 28, 1989
- Page 2 of 6 ASSUMPTIONS
-Leakage from the Chemical Volume and Control System (CVCS) is assumed to be the primary contributor to the radioactive airborne concentrations in the Safeguards and Auxiliary Buildings.
Leakage from the Residual Heat Removal System (RHRS) is also included for shutdown conditions when calculating airborne concentrations in rooms or areas.
Both the CVCS and RHRS are assumed to contain reactor coolant.
Since the leak rates provided for the auxiliary building in NUREG-0017 apply to both the Safeguards and Auxiliary Buildings at Comanche Peak, the leak rates have been prorated equally between the buildings for average building concentrations or among individual rooms for room concentrations based on the number and type of leakage sources (e.g. valves, pumps, flanges) (Enclosure, Table 1).
No purging, venting, or pressure relief of the Containment Building is assumed.
Prior to accessing the Containment Building for-brief periods during normal operation, the Containment Air Cleanup System may be operated and is designed to reduce airborne radioactivity levels.
Evaporation from sumps is assumed to be enveloped by releases from the primary system contributor to airborne concentrations.
PARAMETERS Release rates from NUREG-0017 were used to determine the leakage of iodines, noble gases, and particulate to the Auxiliary, Safeguards and Fuel Buildings.
Leak rates from NUREG-0017 were also used for the release of noble gases and iodines to the Turbine Building.
Noble gas and particulate leak rates from the Reactor Coolant System to the containment Building were assumed f x be one gallon per minute during normal operation, whi,3 is consistent with the NUREG-0017 value.
Iodine leak rates furing normal operation and shutdown were obtained from NURE0 <J17.
The NUREG-0017 leak rate for tritium was used in the calculations.
Forty curies of tritium are assumed to originate from liquid releases, based on 10CFR50, Appendix I, leakage assumptions.
Fifty percent of the
Att5 chm:nt to TXX-89221 L
April 28, 1989 Pase 3 of 6 l
remaining tritium is assumed to reside in the Fuel Building, 32 percent is prorated between the Auxiliary and Safeguards Buildings, and 18 percent is assumed to reside in the Containment Building.
During normal operation, the air density within containment is used to determine the effective concentration of tritium based on a relative humidity of 50 percent.
The shutdown concentration is the difference between the total and normal operation concentrations.
During refueling operations, the tritium concentration in the Fuel Building is assumed to be two times the normal operation concentration (NUREG/CR-0715).
Source terms for the reactor coolant and the secondary side activities were based on the "American National Standard Source Tern Specification" (ANS-18.1, ANSI N237-1976).
The decay of iodines to noble gases is included in the calculation of average building concentrations, which increases the noble gas concentrations.
Partition factors for iodines are included in the NUREG-0017 normalized release rates.
Partition factors for particulate are assumed to be included in the average of release rates presented in NUREG-0017.
The partition factor for noble gases is 1.0.
For particulate in containment, the removal factor was assumed to be 0.999.
This factor was obtained from the " Instrument Society of America Standard for Light Water Reactor Coolant Pressure Boundary Leak Detection" (ISA-S67.03, 1982).
Decontamination factors are assumed to be included in the leak rates obtained from NUREG-0017.
Volumes used in the calculation of average radioactive airborne concentrations in each building are as follows:
6 3
Containment Building 2.985x 0 t
Auxiliary Building 1.9x10 ft3 Safeguards Building 1.1x10 ft3 Fuel Building 1.3x10 ft 3 Turbine Building 2.8x10 ft Volumes in various rooms throughout the Safeguards and Auxiliary Buildings are provided in the Enclosure, Table 1.
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Att5chmsnt to TXX-89221 April 28, 1989 Page 4 of 6 Ventilation flow rates used in the calculation of average radioactive airborne concentrations in each building are as follows:
Containment Building 30,000 scfm (shutdown)
Auxiliary Building 90,600 scfm Safeguards Building 26,000 scfm Fuel Building 36,000 scfm Turbine Building 275,000 scfm During normal power operation, the Containment Building is not purged, the containment Air cleanup System is only operated prior to brief containment entries, and t'a pressure relief vent is used only as required.
Therefore,-a ventilation flow rate of zero is assumed for the containment Building.
~he Turbine Building ventilation flow rate could be as high as 613,000 scfm, if all of the wall ventilators are operating.
Ventilation flow rates in various rooms throughout the Safeguards and Auxiliary Buildings are provided in the Enclosure, Table 1.
METHODOLOGY Radioactive airborne concentrations were calculated assuming Comanche Peak Unit 1 operation.
Adjustment factors are provided for two unit operation.
Average building concentrations represent conservative estimates during normal operation and shutdown conditions for boC1 unrestricted and occupational access areas (Radiation Zones I and II).
Examples of these areas include corridors, mechanical or electrical equipment' areas, diesel generator rooms, or any area that is accessible 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week and 50 weeks / year.
These estimates are conservative, since leakage from rooms with potentially high airborne concentrations are assumed to mix with the low radioactive airborne areas to yield a net increase in the expected values.
Room or area concentrations are also provided for locations in the Auxiliary and Safeguards Buildings where potentially high airborne concentrations could exist during normal operation or shutdown.
Equili" tum concentrations are reported for the buildings and rowas.
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Atttchm nt to TXX-89221 April 28, 1989 Page 5 of 6 j
REST fS The average building concentrations and fractions of Maximum Permissible Concentrations (MPC) for both normal operation and shutdown are presented in the Enclosure, Tables 2 and 3, respectively.
For the Safeguards, Auxiliary, Fuel and Turbine buildings (and, hence, normally accessible areas),
the concentrations are a small fraction of MPC during normal operation.
In containment, the total MPC for normal operation is potentially much greater than 1.0 MPC.
Use of a self-contained breathing apparatus, if necessary, and the potential use of pressure relief (i.e., purge) in containment will greatly reduce the quantity of radioactive i
material inhaled by a worker when Containment Building entry is required.
During shutdown and refueling operations, the potential concentrations in the Auxiliary and Turbine Buildings are a small fraction of MPC.
The tritium concentration in the Containment and Fuel Buildings is the primary contributor to the MPC fraction.
Since these concentrations are based on conservative assumptions (i.e., spent fuel pool exhaust fans or other removal mechanisms were not assumed), the actual concentrations should also be a small fraction of MPC.
The primary contributors to the Safeguards Building MPC fraction are I-131 and I-133.
During normal operating and shutdown conditions, rooms with the highest potentially radioactive airborne concentrations include valve, heat exchanger, volume control tank, and pump rooms containing CVCS leakage and RHRS leakage (shutdown only).
Rooms with concentrations greater than 1.0 MPC are all in-Radiation Zone IV and V areas which have restricted access (if measured radiation levels are high), and ventilation flow is directed to the Primary Plant Ventilation System (PPVS).
All Radiation Zone IV or V rooms that were analyzed have ventilation flow paths directly to the PPVS, with the exception of Room 80.
Assuming that the radioactive airborne concentration is only due to the sources within the room, the potential concentration in Room 80 is greater than Room 31.
Since the ventilation flow path from Room 80 is to Room 81, the net concentration in Room 81 will increase.
This is the preferable flow path, since Room i
l 80 is a Radiation Zone IV room and Room 81 is a Radiation l
Zone V room.
The potential radioactive airborne concentration in Room 209 is less than 1.0 MPC and is in a i
Radiation Zcne III area where limited access is controlled (if measured radiation levels are high) and the ventilation flow path is directed to the PPVS.
The only normally occupied area with CVCS leakage (Corridor - Room 79) h&s potential radioactive airborne concentrations that are a very small fraction of the MPC,
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Atthch22nt'to TXX-89221 April 28, 1989 I
Page 6 of 6-The responses to Question items a, b, and c are as follows-l a.
Tables 12.2-25 and 12.2-26 will be replaced to provide revised assumptions, input parameters, and results.
b.
The tritium concentration in the Turbine Building has been recalculated and is a very small fraction of MPC.
c.
Table 12.2-26 will be replaced to provide revised Containment Building concentrations and correct any previous typographical errors.
.m.-_--,____
a 9
P ENCIDSURE TO TXX-89221 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION ON CHAPTER'12 TABLES 1 THROUGH 5 i
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Table 1 l
Ventilation and Leakage Data Area Area Air Exchange Leak Rate
- Area Flow Rate Volume Rate (cc/hr)
(c fm)
(cubic ft)
(/hr)
CVCS RHR Auxiliary Building **
90600 2.0E+06 2.718 Building 199 300 10059 1.789 37 200 300 7218 2.494 35 201 300 6495 2.771 37 203 1700 4131 24.691 324 209 1300 3906 19.969 36 213 5000 35787 8.383 2
230 6500 25543 15,268 116 Safeguards Building 26000 6.0E+05 2.600 Building 51 500 7049 4.256 3
52 200 2065 5.811 31 I
53 200 20E5 5.811 31 54 520 7049 4.426 2
66/62E 880 9102 5.801 1
187 67/62F 1250 9151 8.196 1
190 68 1000 12216 4.912 64 69 770 11880 3.889 64 76 300 3383 5.321 1
77A 2000 26246 4.572 23 36 77B 1200 26341 2.733 26 36 79 4780 12590 22.780 9
80 560 2547 13.192 63 81 560 2000 16.800 30 87 320 1875 10.240 62 88 2700 34918 4.639 1
89 370 5230 4.245 39 90 220 3641 3.625 60 91 380 1438 15.855 30 93 470 1600 17.625 30 99 200 1653 7./60 30 Totals 992 645.25 I
Assumed leak rates were used to prorate the source between the analyzed rooms.
l These leak rates are based upon the presence of valves, pumps, heat exchangers, and flanges in the room which are considered to be irtential radioactive leakage sources. The basic leakage assump" ions are:
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Pumps, heat exchangers, and associated flanges: 30cc/hr
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l Valves greater than or equal to 2" diameter:
3 cc/hr per inch of valve diameter Valves less than 2" diameter:
1 cc/br
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- Total building data was used in the calculation of everage airborne concentrations in the buildings. For these calculations, the releases to the
" Auxiliary Building" are assumed to be divided equally between the Auxiliary and Safeguards Buildings, j
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l TABLE 2 l
AVERAGE RADIOACTIVE AIRBORNE CONCENTRATIONS AND MAXIMUM PERMISSIBLE CONCENTRATION FRACTIONS *
(NORMAL OPERATION)
ISOTOPE TUEL AUXILIARY SAFEGUARD TURBINE CONTAINMENT ISOTOPE FUEL AUXILIARY SAFEGUARD TURBINE CONTAINMENT
- BLDG, BLDG.
- BLDG, BLDG.
BLDG.
BLDG.
BLDG.
- BLDG, BLDG, BLDG.
(UCI/ML) (UCI/ML)
(UCI/ML)
(UCI/ML)
(uC/cc)
(UCI/ML) (UCI/ML)
(UCI/ML)
(UCI/ML)
(uC/cc)
KR83M 1.8E-10 6.4E-10 9.0E-15 1.4E-07 RU103 7.1E-14 8.5E-15 3.0E-14 5.8E-18 9.6E-11 KR85M 9.0E-10 3.1E-09 4.4E-14 1.2E-06 RU106 1.1E-13 2.2E-15 7.7E-15 1.4E-18 3.8E-11 l
KR85 4.8E-11 1.6E-10 2.2E-15 2.0E-05 EB125 1.1E-13 1.4E-15 5.0E-15 1.0E-15 KR87 5.2E-10
'1.8E-09 2.4E-14 2.2E-07 CS134 3.2E-12 2.0E-13 7.0E-13 2.8E-15 1.0E-07 KR88 1.7E-09 6.0E-09 8.1E-14 1.5E-06 CS136 1.9E-17 1.8E-14 6.2E-14 1.6E-15 1.2E-08 KR89 1.0E-11 3.4E-11 8.5E-16 8.3E-10 CE137 5.0E-12 2.7E-13 9.3E-13 2,3E-15 7.9E-08 XE131H 4,0E-16 1.5E-10 5.2E-10 6.8E-15 1.3E-05 CS136 7.4E-11 2.6E-10 2.5E-15 3.2E-11 KE133M 8.0E-15 8.5E-10 3.0E-09 4.0E-14 1.3E-05 BA137M 7.5E-08 KE133 1.1E-13 4.1E-08 1.4E-07 1.8E-12 1.5E-03**
BA140 1.9E-17 1.5E-13 5.2E-13 2.8E-17 1.BE-10 XE135M 1.7E-12 7.6E-11 2.6E-10 4.6E-15 6.0E-07 CE141 8.2E-16 9.6E-15 3.4E-14 8.8E-18 1.3E-10 XE135 7.3E-13 2.7E-09 9.4E-09 1.2E-13 1.1E-05 CE143 3.8E-12 XE137 2.1E-11 6.9E-11 1.7E-15 1.8E-09 CE144 1.2E-10 XE138 2.4E-10 8.2E-10 1.5E-14 3.2E-08 TE125 7.4E-11 BR-83 3.6E-10 TE127M 8.9E-10 BR-84 4.4E-11 TE127 9.1E-10 BR-85 4.5E-13 TE12W1 2.6E-09 I-130 2.0E-13 7.3E-13 2.6E-12 1.3E-15 3.7E-11 TE129 1.7E
- I*131 2.5E-11 d.1E-11 3.2E-10 2.6E-13 7,1E-08 TE131M 2.2'
,J I-132 8.3E-12 3.2E-11 1.1E-10 1.0E-13 3.3E-10 TE131 4.9E 41 1-133 3.5E-11 1.3E-10 4.5E-10 2.8E-13 1.1E-08 TE132 6.0E-09 I-134 3.2E-12 1.3E-11 4.6E-11 5.7E-15 S.1E-11 LA140 2.0E-10 1-135 1.BE-11 6.6E-11 2.3E-10 9.5E-14 1.8E-09 PR143 4,9E-11 CR-51 3.4E-13 1.2E-13 4.1E-13 2.3E-16 3.1E-09 PR144 1.2E-10 RB-86 1.1E-10 Y90 4.0E-11 RB-88 7.8E-10 1.8E-09 2.3E-14 1.7E-06 Y91M 1.2E-11 RB-88 4.9E-12 1.1E-11 2.6E-16 8.3E-13 Y91 1.8E-10 MN-54 5.6E-13 2.9E-14 1.0E-13 5.6E-17 1.2E-09 Y93 1.0E-12 CO-58 3.9E-11 7.0E-13 2.5E-12 2.0E-15 4.4E-08 RH103M 3.6E-11 CO-60 1.5E-11 1.9E-13 6.6E-13 2.5E-16 8.2E-09 RH106 3.8E-11 FE-55 6.5E-09 M099 1.6E-08 FE-59 1.9E-17 1.8E-14 6.5E-14 1.4E-16 2.2E-09 TC99M 1.5E-08 SR-89 3.9E-12 2.8E-13 9.7E-13 5.8E-17 8.6E-10 NP239 1.9E-10 SR-90 1.5E-12 1.1E-13 3.7E-13 1.4E-18 4.2E-11 PU239 1.3E-15 SR 91 1.8E-11 H3 1.0E-06 1.6E-07 5.8E-07 1.7E-09 3.09E-05 ER-95 6.7E-15 3.7E-13 1.3E-12 8.6E-18 1.6E-10 E8-95 4.5E-12 1.1E-14 3.9E-14 8.6E-18 2.0E-10 TOTAL MPC NB-95M 1.1E-12 FER BUILDING: 0,211 0.056 0.200 0.0004 190
- Concentrations are provided for Unit 1 opera *,lon.
Adjustment factors for two unit operation are as follows:
Fuel Building 2.0 Auxiliary Building 2.0
- Based on the "American National Standard Radioactive Source Term for Normal Operation of Light Water Reactors" (ANSI /ANS-18.1-1-1984), reactor coolant concentrations for Xe-133 are a factor of 7 less than the "American National Standard Source Term Specification" (ANS-18.1, ANSI N237-1976). If this factor is applied to the reported Xe-133 concentration, the total building MPC would be significantly reduced.
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r, TABLE 3 AVERAGE RADI0 ACTIVE AIRBORNE CONCENTRATIONS AND MAXIM'JM I
PERMISSIBLE CONCENTRATION FRACTIONS * (SHUTDOWN AND REFUELING OPERATION)
ISOTOPE FUEL AUXILIARY SAFEGUARD TURBINE CONTAINMENT BLDG.
BLDG.
BLDG.
BLDG.
BLDG.
(UCI/ML)
(UCI/ML)
(UCI/ML)
(UCI/ML)
(UCI/ML) 1-130 1.9E-12 1.0E-11 3.6E-11 5.6E-16 7.5E-12 I-131 2.4E-10 1.3E-09 4.53-09 1.2E-13 9.9E-10 I-132 8.1E-11 4.6E-10 1.6E-09 4.6E-14 2.6E-10 1-133 3.4E-10 1.8E-09 6.4E-09 1.3E-13 1.4E-09 I-134 3.1E-11 1.9E-10 6.6E-10 2.6E-15 8.2E-11 1-135 1.7m-10 9.4E-10 3.3E-09 4.4E-14 6.4E-10 H3 2,1E-06 0.0 0.0 0.0 2.BE-06 TOTAL MPC PER BLDG.
0.465 0.221 0.769 0.00002 0.7270 Concentrations are provided for Unit i refueling. Ad,justment factors for one unit operating and one unit refueling are as follows:
Fuel Building 1.5 (Tritium) 1.1 (Iodines)
Auxiliary Building 1.1 l
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Table 4 Sheet 1 of 3 RADI0 ACTIVE AIRBORNE CONCENTRATIONS AND MAXIMUM FERMISSIB1.E CONCENTRATION FRACTIONS (Normal Operations)
Room Room Room Room Room Room Room Room Isotope 199 200 201 203 209 213 230 66/62E (uC1/ml)
(uC1/ml)
(uci/ml)
(uct/ml)
(uci/ml)
(uci/ml)
(uct/ml)
(uci/ml)
Kr-83m 3.85E-09 3.83E-09 4.10E-09 7.08E-09 1.03E-09 1.44E-11 6.57E-10 4.03E-11 Kr-85m 2.04E-08 1.97E-08 2.10E-08 3.40E-08 4.94E-09 7.05E-11 3.17E-09 1.99E-10 Kr-85 1.64E-07 1.55E-07 1.64E-07 2.53E-07 3.68E-08 5.32E-10 2.37E-08 1.51E-09 Kr-87 1.05E-08 1.07E-08 1.15E-08 2.08E-08 3.00E-09 4.18E-11 1.92E-09 1.16E-10 Kr-88 3.70E-08 3.62E-08 3,86E-08 6.44E-08 9.33E-09 1.33E-10 5.99E-09 3.72E-10 Kr-C3 1.51E-10 1.90E-10 2.20E-10 1.27E-09 1.71E-10 1.59E-12 9.81E-11 3.56E-12 Xe-131m 2.65E-08 2.51E-08 2.66E-08 4.11E-08 5.97E-09 8.62E-11 3.85E-09 2.45E-10 Xe-133m 4.40E-08 4.17E-08 4.41E-08 6.84E-08 9.94E-09 1.43E-10 6.40E-09 4.07E-10 Xe-133 3.75E-06 3.55E-06 3.76E-06 5.82E-06 8.45E-07 1.22E-08 5.45E-07 3.47E-08 Xe-135m 1.23E-09 1.40E-09 1.57E-09 4.32E-09 6.13E-10 7.59E-12 3.81E-10 1.95E-11 Xe-135 6.80E-08 6.51E-08 6.90E-08 1.09E-07 1.59E-08 2.2BE-10 1.02E-08 6.45E-10 Xe-137 3.14E-10 3.92E-10 4.51E-10 2.38E-09 3.22E-10 3.13E-12 1.88E-10 7.12E-12 Xe-138 4.12E-09 4.73E-09 5.28E-09 1.50E-08 2.13E-09 2.61E-11 1.32E-09 6.65E-11 I-130 1.54E-11
.1.47E-11 1.56E-11 2.45E-11 3.56E-12 5.12E-14 2.29E-12 1.49E-13 I-131 1.93E-09 1.83E-09 1.93E-09 2.99E-09 4.34E-10 6.27E-12 2.80E-10 1.83E-11 1-132 6.50E-10 6.41E-10 6.85E-10 1.16E-09 1.68E-10 2.38E-12 1.08E-10 6.84E-12 I-133 2.71E-09 2.56E-09 2.73E-09 4.27E-09 6.20E-10 8.93E-12 3.99E-10 2.60E-11 I-134 2.54E-10 2.63E-10 2.85E-10 5.49E-10 7.91E-11 1.09E-12 5.04E-11 3.0$E-12 1-135 1.37E-09 1.32E-09 1.40E-09 2.23E-09 3.24E-10 4.65E-12 2.09E-10 1.35E-11 Cs-134 4.51E-12 4.27E-12 4.51E-12 6.97E-12 1.01E-12 1.46E-14 6.53E-13 4.16E-14 Cs-136 4.00E-13 3.79E-13 4.01E-13 6.20E-13 9.00E-14 1.30E-15 5.80E-14 3.69E-15 Cs-137 6.01E-12 5.69E-12 6.01E-12 9.29E-12 1.35E-12 1.95E-14 8.70E-13 5.54E-14 Cr-51 2.67E-12 2.53E-12 2.67E-12 4.13E-12 6.00E-13 8.67E-15 3.87E-13 2.46E-14 Mn-54 6.52E-13 6.16E-13 6.52E-13 1.01E-12 1.46E-13 2.11E-15
- 8. aE-14 6.00E-15 Fe-59 4.18E-13 3.95E-13 4.18E-13 6.45E-13 0.38E-14 1.35f-15 6.04F-14 3.85E-15 Co-58 1.59E-11 1.50E-11 1.59E-11 2.45E-11 3.56E-12 5.1fE-14 2.30E-12 1.46E-13 Co-60 4.26E-12 4.03E-12 4.26E-12 6.5BE-12 9.57E-13 1.38E-14 6.16E-13 3.93E-14 Sr-89 6.20E-12 5.93E-12
- 6. 26L-12 9.68E-12 1.41E-12 2.03E-14 9.07E-13 5.77E-14 Sr-90 2.42E-12 2.29E-12 2.42E-12 3.74E-12 5.44E-13 7.86E-15 3.51E-13 2.23E-14 Sb-125-3.26E-14 3.08E-14 3.26E-14 5.03E-14 7.31E-15 1.0GE-16 4.71E-15 3.00E-16 Zr-95 8.35E-12 7.90E-12 8.35E-12 1.29E-11 1.88E-12 2.71E-14 1.21E-12 7.70E-14 j
Nb-95 2.50E-13 2.37E-13 2.51E-13 3.87E-13 5.63E-14 8.13E-16 3.63E-14 2.31E-15 j
Ru-103 1.92E-13 1.82E-13 1.92E-13 2.97E-13 4.31E-14 6.23E-16 2.78E-14 1.77E-15 Ru-106 5.01E-14 4.74E-14 5.01E-14 7.75E-14 1.13E-14 1.63E-16 7.25E-15 4.62E-16 Ba-140 3.34E-12 3.16E-12 3.34E-12 5.16E-12 7.50E-13 1.08E-14 4.83E-13 3.08E-14 Co-141 2.17E-13 2.05E-13 2.17E-13 3.36E-13 4.88E-14 7.04E-16 3.14E-14 2.00E-15 l
H-3 3.70E-06 3.50E-06 3.70E-06 5.73E-06 8.32E-07 1.20E-08 5.36E-07 3.41E-08 Total MPC 1.56E+00 1.4BE+00 1.56E+00 2.44E+00 3.55E-01 5.11E-03 2.28E-01 1.45E-02 Fer Room The room numbers used in this table are consistent with the numbers used in FSAR Figures 12.3-4 through 12.3-23.
i
Table 4 Sheet 2 og 3 RADIOACTIVE AIRBORNE CONCENTRATIONS AND MAXIMUM PERMISSIBLE CONCENTRATION FRACTIONS (Normal Operations)
. Room '
. Room Room Room Room Room Room Room Isotope 67/62F 77A 778 79 80 81 87 88 (uci/ml)
(uC1/ml)
(uci/ml)
(uct/ml)
(uci/ml)
(uci/ml)
'(uci/ml)
(uci/mi)
Kr-83m
- 2.89E-11 4.01E-10 7.19E-10 6.99E-11 4.13E-09 1.98E-09
.7,05E-09 1.29E-11 Kr-85m 1.41E-10 2.00E-09 3.68E-09 3.36E-10 2.00E-08.
9.53E-09 3.43E-08 6.44E-11 Kr-85'
'1.06E-09 1.53E-08 2.88E-08 2.50E-CD 1.50E-07 7.12E-08 2.57E 4.92E-10' Kr-87 8.35E-11 1.14E-09 2.01E-09 2.05E-10 1.20E-08 5.78E-09 2.0$E-08 3.69E-11 Kr-88 2.65E-10 3.72E-09 6.78E 6.36E-10 3.77E-08 1.80E-08 6.46E-08 1.20E-10 Kr-89 3.14E 3.04E-11 7.82E-11 1.22E-11 5.77E-10 3.08E-10 8.68E-10 9.89E-13 Xe-131m 1.72E-10 2.48E-09 4.67E-09 4.06E-10 2.42E-08 1.15E-08 4.17E-08 7.98E-11 Xe-133m ~
2.87E-10 4.12E-09 7.75E-09 6.76E-10 4.04E-08 1.92E-08 6.95E-08 1.33E-10 Xe-133 2.44E-08 3.51E-07 6.60E-07 5.75E-08 3.43E-06 1.64E-06 5.91E-00 1.13E-08 Xe-13 5m 1.51E 1.81E-10 2.73E-10 4.23E-11 2.35E-09
'1.16E-09' 3.85E-09' 5.87E-12 Xe-135 4.56E-10 6.50E-09 1.21E-08 1.08E-09 6.43E-08 3.07E-08 1.11E-07
-2.09E-10 Xe-137 6.19E-12 6.13E-11 7.84E-11 2.29E-11 1.11E-09 5.85E-10 1.69E-09 1.99E-12 Xe-138 5.19E-11 6.17E-10
.9.21E-10 1.47E-10 8.10E-09 4.02E-09 1.33E-08 2.00E-11 I-130 1.05E-11 4.5SE-12 2.81E-12 2.49E-13 1.48E-11 7.07E-12 2.55E-11 4.85E-14 I-131 1.29E-11 1.85E 10 3.49E-10 3.03E-11 1.81E-09 8.63E-10 3.12E-09 5.97E-12 I-132 4.89E-12
- 6. 83E-; 1 1.24E-10 1.18E-11 6.96E-10 3.33E-10 1.19E-09 2.20E-12 I-133 1.83E-11 2.63E-10
- 4.93E-10 4.33E-11 2.58E-09 1.23E-09 4.45E-09 8.47E-12 I-134 2,23E-12 2.99E-11 5.13E-11 5.55E-12 3.24E-10 1.56E-10 5.49E-10 9.66E-13 I-135 9.55E-12' 1.36E-10 2.52E-10 2.27E-11 1.35E-09' 6.44E-10 2.32E-09 4.38E-12 Cs-134 2.93E-14 4.21E-13 7.92E-13 6.89E-14 4.11E-12 1.96E-12 7.09E-12 1.35E-14
.Cs-136' 2.60E-15 3.74E-14 7 vee-14 6.12E-15 3.66E-13 1.74E-13 6.30E-13 1.20E-15 Cs-137 3.90E-14 5.615-13 1.06E-12 9.18E-14 5.49E-12 2.61E-12 9.45E-12 1.81E-14 Cr-51 1.73E-14 2.49E-13 4.69E-13 4.08E-!4 2.44E-12 1,16E-12 4.20E-12 8.03E-15 Hn-54 4.23E-15 6.08E-14 1,14E-13 9.95E-15 5.94E-13 2.83E-13 1.02E-12 1.96E-15 Fa-50 2.71E-15 3.89E-14 7.34E-14 6.38E-15 3.81E-13 1.81E-13 6.56E-13 1.25E-15 Co-58 1.03E-13 1.48E-12 2.79E-12 2.42E-13 1.45E-11 6.89E-12 2.49E-11 4.77E-14 Co-60 2.76E-14 3.97E-13 7.48E-13 6.50E-14 3.89E-12 1.85E-12 6.69E-12 1.28E-14 Sr-80 4.06E-14 5.84E-13 1.10E-12 9.56E-14 5.71E-12 2.72E-12 9.84E-12 1.88E-14 Sr-90 1.57E-14 2.26E-13 4'26E-13 3.70E-14 2.21E-12 1.05E-12 3.81E-12 7.27E-15 l
Sb-125 2.11E-16 3.04E-15 5.72E-15 4.97E-16 2.97E-14 1.42E-14 5.12E-14 9.78E-17 Er-95 5.42E-14 7.79E-13 1.47E-12 1.28E-13 7.62E-12 3.63E-12 1.31E-11 2.51E-14 Nb-95 1.63E-15 2.34E-14 4.40E-14 3.83E-15 2.29E-13 1.09E-13 3.94E-13 7.52E-16 Ru-103 1.25E-15 1.79E-14 3.37E-14 2.93E-15 1.75E-13 8.35E-14 3.02E-13 5.77E-16 Ru-106' 3.25E-16 4.67E-15 8.80E-15 7.65E-16 4.57E-14 2.18E-14 7.87E-14 1.51E-16 Ba-140 2.17E-14 3.11E-13 5.87E-13 5.10E-14 3.05E-12 1.45E-12 5.25E-12 1.00E-14 Co-141 1.41E-15 2.02E-14 3.81E-14 3.32E-15 1.98E-13 9.43E-14 3.41E-13 6.52E-16 H 2.40E-08 3.45E-07 6.51E-07 5.66E-08 3.38E-06 1.61E-06 5.82E-06 1.11E-08 e
Total MPC 1.02E-02 1.46E-01 2.75E-01 2.41E-02 1.44E+00 6.86E-01 2.48E+00 4.71E-03 Per Room i
e Since the ventilation exhaust from Room 80 is directed into Room 81, the concentrations in Room 81 would be higher than this calculated vslue.
I L':
H
'l t
i
' Table 4 Sheet 3 of 3 i
RADIOACTIVE AIRBORNE CONCENTRATIONS AND MAXIMUM PERMISSIBLE CONCENTRATION FRACTIONS (Normal Operations)
' Room Room Room Room Room Isotope.
89 '.
90-91 93 99 (uci/ml) - (uC1/mi)
(uct/ml)
(uC1/ml)
(uci/ml)
Kr-83m
'3.65E-09
'9.33E-09 2.91E-09 2.36E-09 5.38E-09 Kr-85m 1.83E-08 4.70E-08 1.40E-08 1.14E-08 2.64E-08 Kr-85 1.40E-07 3.62E-07 1.05E-07 8.48E-08' 1.99E-07
'Kr-87' 1.04E-08 2.64E-08 8.50E-09 6.89E-09 1.55E-08 Kr-88 3.40E-08.
8.71E-08 2.65E-08 2.15E-08 4.95E-08 Kr-89 2.63E-10 6.03E-10 4.42E-10 3.74E-10 5.46E-10 Xe-131m 2.27E 5.87E-08 1.70E-08 1.38E-08 3.23E-06 Xe-133m 3.77E-08 9.76E-08
.2.83E-08 2.29E-08 5.38E-08 Xe-133 3.21E-06 8.31E-06 2.41E-06 1.95E-06 4.58E-06 Xe-135m 1.62E-09 3.92E-09 1.69E-09 1.39E-09 2.74E-09 Xe-135 5.95E-08 1.54E-07 4.52E-08 3.65E-08 8.53E-08 Xe-137 5.33E-10 1.23E-09 8.42E-10 7.10E-10 1.08E-09 Xe-138 5.49E-09 1.33E-08 5.87E-09 4.82E-09 9.41E-09
'I-130 1.38E-11 3.56E-11 1.04E-11 8.43E-12 1.97E-11 I-131 1.70E.4.39E-09 1.27E-09 1.03E-09 2.42E-09 I-132 6.23E-10
.1.59E-09~
4.91E-10 3.97E-10 9.12E-10 I-133-2.41E-09 6.22E-09 1.81E-09 1.47E-09 3.44E-09 I-134 2.71E 6.83E-10 2.29E-10 1.86E-10 4.13E-10 I-135
- 1.24E 3.20E-09 9.48E-10 7.67E-10 1.79E-09 Co-134 3.86E-12 9.97E-12 2.89E-12 2.33E-12 5.49E Co-136 3.43E-13 8.86E-13 2.57E-13 2.07E-13 4.88E-13 Cs-137
>5.14E-12 1.33E-11 3.85E-12 3.11E-12 7.31E-12 Cr-51 2.28E-12 5.91E-12 1.71E-12 1.38E-12 3.25E-12 Hn 5.57E-13 1.44E-12 4.17E-13 3.37E-13 7.92E-13 Fe-59 3.57E-13 9.23E-13 2.67E-13 2.16E-13 5.08E-13 Co-58 1.36E-11 3.51E-11 1.02E-11 8.21E-12 1.93E-11
'Co-60 3.64E-12 9.42E-12 2.73E-12 2.20E-12 5.18E-12 Sr-89 5.35E-12 1.39E-11 4.01E-12 3.24E-12 7,62E-12 Br-90 2.07E-12 5.36E-12 1.55E-12 1.25E-12 2.95E-12 Eb 125 2.78E-14 7.20E-14 2.09E-14 1.69E-14 3.96E-14 Zr-95 7.14E-12.
1.85E-11 5.35E-12 4.32E-12 1.02E-11 Nb-95 2.14E-13 5.54E-13 1.60E-13 1.30E-13 3.05E-13 Ru-103 1.64E-13 4.25E-13 1.23E-13 9.94E-14 2.34E-13 Ru-106 4.28E-14 1.11E-13 3,21E-14 2.59E-14 6.10E-14 Ba-140 2.85E-12 7.38E-12 2.14E-12 1.730-12 4.06E-12 Co-141 1.86E-13 4.80E-13 1.30E-13 1.12E-13 2.64E-13 B-3:
3.17E-05 8.19E-06 2.37E-06 1.92E-06 4.51E-06 Total MPC 1.34E+00 3.47E+00 1.01E+00 8.17E-01 1.91E+00 Per Room ar=-___-__----_--___--__--__--_.-----______-_-_-_-_-_-_-__-.___--_--_.___-___-_._____________---_L_-_--_--____--_a
y_______,___ _ _ _ _
i 1
Ta-_4 5 Sheet 1 of 2 RADI0 ACTIVE AIRBORNE CONCENTRATIONS AND MAXIMUM PERMISSIBLE CONCENTRATION FRACTIONS *
(Shutdown and Refuelin8 Operations)
Room Room Room Room Room Room Room Room Isotope 199 200 P.01 203 209 213 230
$1 (uC1/ml)
(uC1/ml)
(uci/ml)
(uci/ml)
(uC1/ml)
(uC1/ml)
DC4/ml)
(uci/ml)
I-130 1.41E-10 1.35E-10 1.43E-10 2.24E-10 3.26E-11 4.69E-13 2.10E-11 6.99E-12 I-131 1.77E-08 1.67E-08 1.77E-08 2.74E-08 3.98E-09 5.74E-11 2.56E-09 8.61E-10 1-132 5.95E-09 5.87E-09 6.27E-09 1.06E-08 1.54E-00 2.18E-11 9.87E-10 3.16E-10 I-133 2.48E-08 2.36E-08 2.50E-08 3.91E-08 5.67E-09 8.18E-11 3.65E-09 1.22E-09 I-134 2.33E-09 2.41E-09 2.61E-09 5.02E-09 7.24E-10 9.94E-12 4.61E-10 1.38E-10 1-135 1.25E-08 1.21E-08 1.28E-08 2.04E-08 2.97E-09 4.2EE-11 1.91E-09 6.31E-10 Total MPC 3.00E+00 2.85E+00 3.01E+00 4.69E+00 6.81E-01 9.82E-03 4.38E-01 1.47E-01 1
Per Room Room Room Room Room Room Room Room Room Isotope
$2 53 54 66/62E 67/62F 68 69 76 i
(uct/ml)
(uci/ml)
(uci/ml)
(uci/ml)
(uci/ml)
(uct/ml)
(uct /ml)
(uci/ml)
I-130 1.81E-10 1.81E-10 4.4BE-12 2.50E-10 1.7WE-10 7.47E-11 9.67E-11 3.89E-12 I-131 2.23E-08 2.235-08 5.52E-10 3.07E-08 2.19E-08 9.19E-09 1.19E-08 4.78E-10 I-132 8.31E-09 8.31E-09 2.03E-10 1.15E-08 8.31E-09 3.40E-09 4.35E-09 1.78E-10 I-133 3.16E-08 3.16E-08 7.83E-10 4.36E-08 3.12E-08 1.30E-08 1.69E-08 6.80E-10 I-134 3.71E-09 3.71E-09 8.87E-11 5.12E-09 3.79E-09 1.50E-09 1.88E-09 7.89E-11 1-135 1,64E-08 1.64r-08 4.05E-10 2.26E-08 1.63E-08 6.75E-09 8.72E-09 3.52E-10 Total MPC 3.80E+00 3.80E+00 9.42E-02 5.24E+>0 3.75E+00 1.93E+00 2.03E+00 8.17E-02 Per Room
- Iodine concentrations increase due to maintenance.
The room numbers used in this table are consistent with the numbers used in FSAR Figures 12.3-4 through 12.3-23.
1 1
l
in s
-e..- :
L Table 5 Sheet 2 of 2 RADIOACTIVE AIRBORNE CONCENTRATIONS AND HAXIMUM PERMISSIBLE CONCENTRATION FRACTIONS *
(Shutdown and Refuelins Operations).
. Room Room Room' Room Roca Room Room Room Isotope 77A 775 79 80.
81 87 88 89 (uci/ml)-
(uC1/ml)
(uC1/ml)
(uC1/ml)
(uci/ml)
(uci/mi)
(uct/ml)
(uC1/ml)
I-130<
3.44E-11 5.97E-11 2.22E-12 1.32E-10 6.30Ea11 2.27E-10 4.32E-13 1.23E-10 I-131 4.23E-09 7.41E-09 2.70E-10 1.62E-08 7.69E-09 2.78E-08 5.32E-11 1.51E-08 I-132 1.56E 2.62E-09 1.0$E-10
'6.21E-09 2.97E-09 1.06E-08 1.96E-11 5.55E-09 I-133 6.01E-09 1.05E-08 3.86E-10 2.30E-08 1.10E-08 3.96E-08 7.55E-11 2.15E-08 I-134 6.84E-10 1.09E-09 4.95E-11 2.89E-09 1.39E-09
- 4.89E-09 8.60E-12 2.42E-09 I-135 3.11E-09 5.36E-09 2.02E-10 1.20E-08 5.74E-09 2.07E-08 3.90E-11 1.11E-08 t
en Total HPC 7.22E-01' 1.26E+00 4.63E-02 2.76E+00 1.32E+00 4.76E+00 9.07E-03 2.58E+00 Per Room Room Room Room Room Isotope.
90 91 93 99 (uci/ml)
(uC1/ml)-
(uci/ml)
(uC1/ml) 1-130 3.17E-10 9.28E-11 7.51E-11 1.76E-10
.I I-131 3.91E-08 1.13E-08 9.17E-09 2.15E-08 I-132' 1.42E-08 4.37E-09 3.54E-09 8,12E-09 I-133 5.55E-08 1.62E-08 1.31E-08 3.06E-08 I-134 6.09E-00 2.04E-09 1.66E-09 3.68E-09 I-135 2.86E-08 8.43E-09 6.84E-09 1.59E-08 Total MFC 6.67E+00 1.94E+00 1.57E+00 3.68E+00 Per Room
- Icdine concentrations increase due to maintenance.
- e Since the ventilation exhaust from Room 80 is directed into Room 81, the concentratient in Room 81 would be higher than this calculated valuc.
L_
- __ __