ML20127M482
| ML20127M482 | |
| Person / Time | |
|---|---|
| Site: | Catawba, McGuire, 05000000 |
| Issue date: | 01/01/1985 |
| From: | Birch M, Hampton J, Stewart J DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20127M449 | List: |
| References | |
| PROC-850101, NUDOCS 8507010247 | |
| Download: ML20127M482 (11) | |
Text
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December 11, 1984 n-
SUBJECT:
Offsite Dose Calculation Manual Revision 6 The General Office Radwaste Engineering staff is transmitting to you this date, Revision 6 of the Offsite Dose Calculation Manual.
As this revision only affects Catawba Nuclear
- Station, the approval of other station managers is not necessary.
Please update your copy No.
1
, and discard affected pages.
REMOVE THESE PAGES INSERT THESE PAGES C-8 Rev. 4 C-8 Rev. 6 C-10 Rev. 4 C-10 Rev. 6 C-15 Rev. 4 C-15 Rev. 6 C-16 Rev. 4 C-16 Rev. 6 C-17 Rev. 4 C-17 Rev. 6 Table C5.0-1 Rev. 4 Table C5.0-1 Rev. 6 Table C5.0-2 Rev. 4 Table C5.0-2 Rev. 6
,]
Table C5.0-3 Rev. 4 Table C5.0-2 Rev. 6 V
NOTE:
As this letter contains "LOEP" information, please insert this in front of the September 7, 1984 letter.
Approval Date:
11/2/84 Approval Date:
11/16/3.1 Effective Date:
01/01/85 Effective Date:
01/n1/A r.
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j
,,f U d' G'f Mary L. mirc J. W. Hampton, Manager System Radwaste Engineer
. Catawba Nuclear Station If you have any questions concerning hevision 6, please call Jim Stewart at (704) 373-5444 Q-r/ter $
40 James M.
Stewart, Jr.
Associate Health Physicist Radwaste Engineering
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JUSTIFICATIONS FOR REVISION 6 Page C-8 Added/ changed words for clarification purposes; no change in meaning.
Page C-10 Decimal point was inadvertently _left in when converting 1.16E+02 t'
116; error resulted in a conservative radiation monitor setpoint cali-bration.
~
Page C-15 Incorrect units; the correct units for D/Q are m Page C-16 Incorrect _g/Q valve for location given; should be 5.8E-10 m Page C-16 Typo error; lower case "c" does not agree with upper case "C" used in equation.
-2 Page C-16 Incorrect units; the correct units for D/Q are m 3
Page C-16 Typo error; lower case "m" and "c" do not agree with upper case "M" and "C" used in equation.
Page C-16 Typo error; the word " performed" was misspelled.
Page C-17 Delete 3rd paragraph; groundwater samples are collected quarterly.
Special low level I-131 analyses are performed on bi-weekly drinking water and surface water composite samples in order to meet the 1 pCi/ Liter LLD for water samples.
For this same reason, special low level I-131 analyses are performed on groundwater samples collected quarterly.
Food products will be collected
- monthly, during harvest
- season, from a garden within a 5-mile radius of the station if a garden which is irrigated with water in which liquid plant effluents have been discharged is identified j
l during the annual land use census.
4 Location 9248; Piedmont Medical Center moved Table C5.0-1 to a new location - 7.0 miles SSE.
Tables C5.0-2 Revised Tables C5.0-2 and C5.0-3 are in response C5.0-3 to changes in requirements in the Catawba Nuclear Station Environmental radiological Monitoring Program Technical Specification.
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C3.0 RADIATION MONITOR SETPOINTS (V
Using the generic calculations presented in Section 2.0, final effluent l
radiation monitoring setpoints are calculated for monitoring as required by the Technical Specifications.
All radiation monitors for Catawba are off-line except EMF-50 (Waste Gas System) which is in-line. These monitors alarm on low flow; the minimum flow alarm level for both the liquid monitors and the gas monitors is based on the manufacturer's recommendations. These monitors measure the activity in the liquid or gas volume exposed to the detector and are independent of flow rate if a minimum flow rate is assured.
Radiation monitoring setpoints calculated in the following sections are expressed in activity concentrations; in reality the monitor readout is in counts per minute. Station radiation monitor setpoint procedures which correlate concen-tration and counts per minute shall be based on the following relationship:
c = 2.22 x 10"e V where:
c = the gross activity, in pCi/ml r = the count rate, in cpm 2.22 x 10s = the disintegration per minute per pCi s'
e = the counting efficiency, cpm /dpm V = the volume of fluid exposed to the detector, in ml.
For those occurrences when simultaneous releases of radioactive material must be made, monitor setpoints will be adjusted downward in accordance with Station Procedures to insure that instantaneous concentrations will not be exceeded.
C3.1 LIQUID RADIATION MONITORS C3.1.1 Waste Liquid Effluent Line As described in Section C2.1.1 on release rate calculations for the waste liquid effluent, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, the radiation monitor setpoint shall be set to terminate the release if the effluent activity should exceed that determined by laboratory analyses and used to calculate the release rate. A typical radiation monitor setpoint may be calculated as follows:
MPC x F c5 1 2.48E-05 pCi/mi g
where:
c = the gross activity in undiluted effluent, in pCi/ml
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f = the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be 100 gpm.
C-8 Rev. 6 1/1/85
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,(j C3.2 GAS MONITORS The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133 (Historical data shows that Xe-133 is most predominant isotope):
K(X/Q)Q1 < 500 (see Section C2.2.1)
D = 4.72E+02 C f (see Section C2.2.2) 1 g
C. < 116/f 1
where:
C
= the gross activity in undiluted effluent, in pCi/ml f
f
= the flow from the tank or building sources, in cfm 3
K
= from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m X/Q
= 3.1E-05, as defined in Section C.2.2.2 As stated in Section C2.2, the unit vent is the release point for the contain-ment purge ventilation system, the containment air release and addition system, the condenser air ejector, and auxiliary building ventilation.
For releases from the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows:
Cf < 116/f = 6.5E-04 where:
-f = 151,000 cfm (auxiliary building ventilation) + 28,000 cfm (containment purge) = 179,000 cfm For release from the containment air release and addition system, the waste gas decay tanks, the condenser air ejectors, and the auxiliary building ventilation, a typical radiation monitor setpoint may be calculated as follows:
Cg < 116/f = 7.7E-04 l
where:
f = 151,000 cfm (auxiliary building ventilation) bG C-10 Rev. 6 1/1/85
"D
'Q" C4.3.2.2 Radioiodines, Particulates, and Other Radionuclides with T 1/2 > 8 days For dose estimates, simplified dose estimates using the assumptions in C4.2.2.2 and source terms in the FSAR are presented below. Once operational source term data is available,'this information shall be used to revise these calculations, if necessary. 'These calculations further assume that the annual average dispersion / deposition parameter is used and that 95% of the dose is from Iodine-131 concentrated in goat's milk. The simplified dose estimate to the thyroid of an infant is:
D = 1.84E+04 w (Q)I-131 (1.05) where:
2 from Table C4.0-2 w = 7.3E-10 = D/Q for food and ground plane pathway, in m for location of nearest real goat (NW sector at 2.5 miles).
(D)y,737 = the total Iodine-131 activity released in pCi.
1.84E+04 = (3.17E-08)(R [D/Q])withtheappropriatesubstitutfonsfor goat's milk in the grass-cow-milk pathway factor, R.* [D/Q] for Iodine-131. See Section 3.1.2.2.
1.05 = factor derived from the conservative assumption (based on historical data) that 95% of the dose is contributed by I-131.
C4.3 FUEL CYCLE CALCULATIONS As discussed in Section 3.3.5, more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190. The fuel cycle dose assessments for Catawba Nuclear Station must include dose contributions from McGuire Nuclear Station, which is located upstream approximately thirty miles NNE of Catawba. For this dose assessment, the maximum exposed individual is conservatively assumed to live 5 miles NNE of Catawba and 5 miles SSW of McGuire; this individual eats fish caught in the discharge area at Catawba.
The dose contributions resulting from gaseous effluents are calculated using the methedology in Section 3.1.2:
D (g). <, 0.47 D (g) + 0.55 D (8}
g g
C Where:
3 D (g) = dose contribution from McGuire calculated using X/Q = 1.5E-07 sec/m g
l and D/Q = 3.8E-10 m2 The location is 5 miles SSW of McGuire.
0.47
= fraction of time the wind direction is out of NNE.
N C-15 Rev. 6 1/1/85 m
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h D (g) = dose contribution from Catawba calculated using X/Q = 3.3E-07 sec/m3 C
andD7Q = 5.8E-10 m2 The location is 5 miles NNE of Catawba.
0.55 = fraction of time the wind direction is out of SSW.
Using the methodology above and the assumption that each station releases their maximum Technical Specification dose limit, the gaseous effluent contribution to the fuel cycle calculation is but a small fraction (< 1/100) of the allowable dose. Therefore, fuel cycle calculations will not normally be performed unless either station exceeds their gaseous effluent Technical Specifications-by a factor of 10.
The dose contribution resulting from liquid effluents is calculated using the methodology in Section 3.1.1:
D (A) < 0.607 D (A) + D I )
g g
C Where:
.607 = 2670 cfs (average flow past Cowans Ford Dam) 4400 cfs (average flow past Lake Wylie Dam)
.D (A) = Dose contribution from McGuire via liquid effluents g
()
D ( ) = Dose contribution from Catawba via liquid effluents C
Using the methodology above and the assumption that each station releases its maximum Technical Specification dose limit, the liquid effluent contribution to.the fuel cycle calculation would be 48% of the allowable dose. Therefore, fuel cycle calculations will not normally be performed unless either station exceeds its liquid effluent Technical Specifications by a factor of 2.
In summary, Technical Specification 3.11.4 will be the deciding criteria for Catawba fuel cycle calculations since it is either equal to (liquid) or is more restrictive than (gaseous) the cases outlined above.
N C-16 Rev. 6 1/1/85
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C5.0 Radiological Environmental Monitoring The Radiological Environmental Monitoring Program shall be conducted in accordance with' Technical Specification, Section 3/4.12.
The monitoring program locations and analyses are given in Tables C5.0-1 through C5.0-3 and Figure C5.0-1.
q The laboratory performing the radiological environmental analyses shall parti-cipate in an interlaboratory comparison program which has been approved by the NRC. This program is the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparsion Studies (crosscheck)
Program, our participation code is CP.
The dates of the land-use census that was used to identify the controlling receptor locations was 10/26/82 - 10/28/82. These dates will not be changed unless a subsequent census changes a controlling receptor's location.
o O
C-17 Rev. 6 1/1/85 l
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f TABLE C5.0-1 (1 of 1).
CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)
SAMPLING LOCATION DESCRIPTION SAMPLING LOCATION DESCRIPTION 200 SITE BOUNDARY (0.7M NNE) 232.
4-5 MILE RADIUS (4.1M NE)'
201 SITE BOUNDARY (0.5M NE) 233 4-5 MILE RADIUS (4.0M ENE) 202 SITE BOUNDARY (0.6M ENE) 234 4-5 MILE RADIUS (4.5M E) 203 SITE BOUNDARY (0.5M SE) 235 4-5 MILE RADIUS (4.0M ESE)-
204 SITE BOUNDARY (0.5M SSW) 236 4-5 MILE RADIUS (4.2M SE) 205 SITE BOUNDARY (0.6M SW) 237 4-5 MILE RADIUS (4.8N SSE) 206 SITE BOUNDARY (0.7M WNW) 238-4-5 MILE RADIUS (4.2M S) 207 SITE BOUNDARY (0.8M NNW) 239 4-5 MILE RADIUS (4.6M SSW) 212 SPECIAL INTEREST (2.7M ESE) 240 4-5 MILE RADIUS (4.1M SW) 217 CONTROL (10.0M SSE) 241 4-5 MILE RADIUS (4.7M WSW) 222 SITE BOUNDARY (0.7M N) 242 4-5 MILE RADIUS (4.6M W) 223 SITE BOUNDARY (0.5M E) 243 4-5 MILE RADIUS (4.6M WNW).
224 SITE BOUNDARY (0.7M ESE) 244 4-5 MILE RADIUS (4.1M NW) 225 SITE BOUNDARY (0.5M SSE) 245 4-5 MILE RADIUS (4.2M NNW) 226 SITE BOUNDARY (0.5M S) 246 SPECIAL INTEREST-(8.1M ENE) 227 SITE BOUNDARY (0.5M WSW) 247 CONTROL (7.5M ESE) 228 SITE BOUNDARY (0.6M W) 248 SPECIAL INTEREST (7.0M SSE) l 229 SITE BOUNDARY (0.9M NW) 249 SPECIAL INTEREST (8.1H S) 230 4-5 MILE RADIUS (4.4M N) 250 SPECIAL INTEREST (10.3M WSW) 231 4-5 MILE RADIUS (4.2M NNE) 251 CONTROL (9.8M WNW)
Rev. 6 1/1/85-
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