ML20063L359
| ML20063L359 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1993 |
| From: | LONG ISLAND POWER AUTHORITY |
| To: | |
| Shared Package | |
| ML20063L356 | List: |
| References | |
| NUDOCS 9403040266 | |
| Download: ML20063L359 (391) | |
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,.- i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l For the Year of 1993 i Facility: Shoreham Nuclear Power Station, Unit 1 l Licensee: Long Island Power Authority ;
i TABLE OF CONTENTS ,
t Section Pace Introduction 1 A. Supplemental Information 1 B. Gaseous Effluents 4 )
C. Liquid Effluents 11 :
D. Solid Waste 16 i E. Radiological Impact on Man 29 F. Meteorological Data 37 l t'
G. ODCM Revisions, REMP Location Changes 102 and Major Changes to Radioactive Waste Treatment Systems H. Miscellaneous Special Report 104 l Appendix A i
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 INTRODUCTION This Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specification 6.8.1.4, Offsite Dose Calculation Manual (ODCM)
Administrative Control Section 6.8.1.4 and Sections 8.3.1 and 8.4 of the Process Control Program (PCP), covers the nominal period from January 1,1993 through December 31,1993. During the period covered by this report, substantial progress j has been made in the decommissioning of the Shoreham Nuclear Power Station. This includes removal of the Reactor and Turbine Building Liquid Radwaste and Fuel Pool Cooling and Cleanup system piping; decontamination of the RPV bottom bowl; completion of the Turbine, Reactor and Radwaste buildings hydrolyazing; and ,
completing 18 of the total 33 irradiated fuel shipments.
A. SUPPLEMENTAL INFORM ATION
- 1. Reoulatorv Limits Shoreham's effluent regulatory limits are defined in the Possession Only License NPF-82, Shoreham Nuclear Power Station, Appendix A, i Technical Specifications.
a) Limits for gaseous effluents and noble gases are covered by Technical Specification 6.7.4 and ODCM Controls 3.11.2.1 and :
3.11.2.2. I 3
b&c) Tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents are addressed in i Technical Specification 6.7.4 and ODCM Control Sections 3.11.2.1 and 3.11.2.3.
d) Liquid effluent limits are described in Technical Specification 6.7.4 -
and ODCM Controls 3.11.1.1 and 3.11.1.2. ;
, t e) In addition, with Shoreham's sampling and analysis program the following average minimum detectable activities (MDAs) were ,
achieved or exceeded in 1993. These MDAs are less than the required lower limits of detection (LLDs): :
Liquid: ,
Ce-141 3.70 E-8 uCi/ml l Ce-144 1.67 E-7 uCi/mi !
Co-58 3.59 E-8 uCl/mi ,
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I Co-60 6.05 E-8 uCi/mi -
Cs-134 4.40 E-8 uCi/rrd :
. Cs-137 4.04 E-8 uCi/ml 'i Mn-54 3.59 E-8 uCi/mi Mo-99 1.92 E-8 uCi/mi !
Zn-65 8.09 E-8 uCi/mi ;
l Gaseous:
' Cs-137 3.04E-11 uCi/cc i Cs-134 1.76E-14 uCi/cc !
Co-60 1.19E-14 uCi/cc Mn-54 8.36E-15 uCi/cc ;
Xe-133 7.16E-08 uCi/cc Zn-65 1.68E-14 uCi/cc l Ce-144 2.65E-14 uCi/cc j
- 2. Maximum Permissible Concentrations ,
a-d) Maximum permissible liquid effluent concentrations (MPCs) are those specified in 10 CFR 20, Appendix B, Table 11, Column 2. If 'j an isotope is listed with values for SOLUBLE and INSOLUBLE i states, the more conservative value is utilized. For gaseous j effluents, MPCs were not used. Direct calculations of dose were j utilized to satisfy the dose rate limitations of Technical <
I Specification 6.7.4 and ODCM Control 3.11.2.1.
- 3. Averaae Enerov No isotopes above minimum detectable activities were measured in -
gaseous effluents. Therefore, there is no reportable average energy for this time period.
- 4. Measurements and Anoroximations of Total Radioactivity a-d) Samples were collected in the manner and with the frequency prescribed in Technical Specification 6.7.4 and ODCM Controls 4.11.1.1.1 and 4.11.2.1.2. Samples were analyzed in accordance with ODCM Controls Tables 4.11.1.1.1-1 (liquid) and 4.11.2.1.2-1 (gaseous) regarding both type of analysis and level of sen ;itivity. Most samples were analyzed by gamma I spectroscopy with a High Purity Germanium HPGe detector. A l liquid scintillation counter was used to analyze for H-3 and Fe-55 i
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.- ANNUAL RADIOACTIVE EULUENT RELEASE REPORT
. . I while Sr-89, Sr-90 analyses were done by proportional counter.
Samples analyzed for iron and strontium underwent a chemical l separation prior to counting. Approved sample collection and analysis procedures were followed. ,
Analytical results are examined to ensure that the minimum.
sensitivity levels required by ODCM lower limits of detection !
(LLDs) have been met. Any identifiable peaks above background '
are quantified.
The methods above were used for batch releases. The same methods were used for continuous discharges, but were combined i with gross activity measurements on process streams and total .
flow for these streams. l No estimate of percent total error is provided in Table 1 A because ,
all values for gaseous effluents were determined to be less than required LLDs. Basis for the estimated percent total error for entries in Table 2A is given in Section C.
- 5. Hatch Releases .
I a) Liquid 1" Quarter 2* Quarter 3'dQuarter 4* Quarter- [
- 1. Number of batches 35 30 16 18'
- 2. Total Time (minutes) 5,223 4,768 2,471 2,659 ;
- 3. Maximum Time (minutes) 177 341 176 173
- 4. Minimum Time (minutes) 15 13 78 74' 1
- 5. Average Time (minutes) 149 159 154 148
- 6. Total Volume Discharged (gal) 6.12E + 5 5.41 E + 5 2.91 E + 5 3.15E + 5
- 7. Total Dilution Water (gal) 4.49E + 7 4.10E + 7 2.13E + 7 2.29E + 7 ,
- 8. Average Flow (gpm) 8.72E + 3 8.71 E + 3 8.72E + 3 8.72E + 3 j b) Gaseous - None }
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- 6. Abnormal Releases a) Liquid - None ;
b) Gaseous - None 1
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
.l B - GASEOUS EFFLUENTS j j
1993
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I All samples of gaseous effluents were analyzed and determined to be at or below minimum detectable activities (MDAs) for all radionuclides listed in Shoreham's ODCM. These MDAs were below the lower limits of detection required in ODCM ,
Controls Table 4.11.2.1.2-1. In addition, no other radionuclides were identified, Therefore, no entries were made in Tables 1 A,18 or 1C that follow. '
.1 Composite sample results for the four quarters of this reporting period are all at or below MDAs.
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1 A ANNUAL REPORT 1993 ;
EFFLUENT AND WASTE DISPOSAL l
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter O us m r Est. Total Enor, % l 1 1 2 A. Fision & activation gases Ci . E . E . E l
- 1. Total release pCi/sec E . E
- 2. Average release rate for period .
- 3. Percent of Technical specification limit % . E . E B. Iodines Ci . E . E . E
- 1. Total iodine.131 pCi/sec E . E
.2. Average release rate for period .
% E . E
- 3. Percent of techttical speci0 cation limit .
C. Particulates :
Ci E E . E
- 1. Particulates with half. lives >8 days . .
- 2. Average release rate for period pCi/see . E . E __
- 3. Percent of technical specification limit % . E . _E Ci . E . E
- 4. Gross alpha radioactivity D. Tritiurn Ci . E . E . E
- 1. Total release pCi/sec E . E
- 2. Average release rate for period .
- 3. Percent of technical specificationlimit % . E . E 6
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-- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1 A (cont *.)
EFFLUENT AND WASTE DISPOSAL ! ANNUAL REPORT 199,3 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total
- Enor. % .
3 3 4 A. Fission & activation gases
- 1. Total release Ci . E . E . E
- 2. Average release rate for period yCi/sec . E . E
- 3. Percent of Technical specification limit % . E . E B. Todines Cl E . E . E
- 1. Totat ydine.131 .
.2. Aserage release rate for period pCi/sec . E . E ,
- 3. Percent of technical specification limit % . E . E C. Particulates
- 1. Particulates with half. lives >8 days Ci . E . E . E !
- 2. Average release rate for period pCi/see . E . E
- 3. Percent of technical specification limit % . E . E
- 4. Gross alpha radioactivity Ci . E . E D. Tritium Ci E E . E
- 1. Total release . .
- 2. Average release rate for period pCi/sec . E . E
- 3. Percent of technical specification limit % . E . E
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l i
TABLE 1B EFFLUENT AND WASTE DISPOSAL . ANNUAL REPORT 1993 GASEOUS EFFLU$NTS-ELEVATED RELEASE CONTINUOUS MODE B ATCH MODE j Nuclides Released - U nitg* Quarter Quarter 2 Quarter y 'Ouaner 2 3
- 1. Fission gases .
krypton-85 Ci . E . E . E . E !
krypton.85m Ci . E . E . E . E__ l krypton.87 Ci . E . E . E . E krypton.88 Ci . E . E . E . E Cl E E E E xenon.133 . . . .
Ci E E E E xen6n.135 . . . .
Ci E E E E -
i xenon.135m . . . .
Ci E E E E xenon.138 . . . .
Others (specify) Ci . E . E . E . E Ci . E . E . E . E_ _
Ci . E . E . E . E Ci E E E E unidentified . . . .
Total for period Ci . E . E . E . E
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- 2. Iodines iodine.131 Ci . E . E . E . E iodine.133 Ci . E . E . E . E iodine.135 Ci . E . E . E . E Total for period Ci . E . E . E . E
- 3. Particulates
- 7. -
strontium-89 Ci . E . E . E . E
. strontium.90 Ci . E . E . E . E cesium 134 Ci . E . E . E . E cesium 137 Ci . E . E . E . E Ci E E E E barium. lanthanum.140 . . . .
Others (specify) Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E . E Ci E E E E unidentified . . . .
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l l
TABLE 18 (cont-)
EFFLUENT AND WASTE DISPOSAL . ANNUAL REPORT 199 3 GASEOUS EFFLUENTS-ELEVATED RELEASE
' CONTINUOUS MODE B ATCH MODE Nuclides Released -
U nit 1 Ouaner3 Quanw4 Quan" 3 Ouenn4 I. Fission gases l
krypton.85 Ci . E . E . E . E krypton.85m Ci . E . E . E . E krypton.87 Ci . E . E . E . E .
krypton.88 Cl . E . E . E . E xenon.133 Ci . E . E . E . E_
xen6n.135 Ci . E .. E . E . E xenon.135m Ci . E . E . E . E -
xenon.138 Ci . E . E . E . E Others (specify) Ci . E . E . E . E Ci . E . S . E . E !
Ci . E . E . E . E ,
unidentified Ci . E . E . E . E Total for period Ci . E . E . E . E
- 2. Iodines -
iodine 131 Ci . E . E . E . E .
iodine.133 Ci . E . E .' E . E iodine 135 Ci . E . E . E . E Total for period Ci . E . E . E . E '
- 3. Particulates strontium.89 -
Ci . E . E . E . E strontium.90 Ci . E . E . E . E -
cesium.134 Ci . E . E . E . E cesium 137 Ci . E . E . E . E barium. lanthanum.140 Ci . E . E . E . E Others (specify) Ci . E . E . E . E ;
Ci . E . E , E . E l l
Ci . E . E . E . E unidentified Ci . E . E . E . E 8- i l
_ : __ - . _ _ _ l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C EFFLUENT AND WASTE DISPOSAL ' ANNUAL REPORT 1993 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES i i
CONTINUOUS MODE BATCH MODE Nuefides Reisews Unit Quaner Ousne'2 Quaneri Quanw2 t , 3 I. Fission gases i
krypton.85 Ci . E . E . E . E I krypton.85m Ci . E . E . E . E krypton.87 Ci . E . E . E . E !
krypton.88 Ci . E . E . E . E i xenon.133 Ci . E . E . E . E xenon.135 Ci . E . E . E . E xenon 135m Ci . E . E . E . E xenon.138 Ci . E . E . E . E Others (specify) Cl . E . E . E . E j Ci . E- . E . E . E Ci . E . E . E . E unidentified Ci . E . E . E . E Total for period Ci . E . E . E . EI
- 2. Iodines lodine.131 Ci . E . E . E . E iodine.133 Ci . E . E . E . E iodinc.135 Ci . E . E . E . E Total for period Ci . E . E . E . E
- 3. Particuhte strontium.89 Ci . E . E . E . E strontium.90 Ci . E . E . E . E cetium.134 Ci . E . E . E . E cesium.137 Ci . E . E . E . E barium. lanthanum.140 Ci . E . E . E . E Others (specify) Cl . E . E . E . E Ci . E . E . E . E -
Ci . E . E . E . E unidentified .
Cl . E . E . E . E
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C GanQ ,
EFF1.UBJT AND WASTE DISPOSAL ANNUAL REPORT ig3 OASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE B ATCH MODE Nuclidn Releases Unit i Quanw3 Ousner 4 Quartw 3 09wtw4
- 1. Fission pues kryptor>45 Ci . E . E . E . E krypton 45m Ci . E . E . E . E krypton 47 Ci . E . E . E . E krypton 46 Ci . E . E . E . E xenon.133 Ci . E . E . E . E xenon.135 Ci . E . E . E . E xenon.135m Ci . E . E . E . E xenon.138 Ci . E . E . E . E Others (specify) Cl . E . E . E . E __
Ci . E- . E . E . E Ci . E . E . E . E unidentified Ci . E . E . E . E Total for period Ci . E . E . E . EI
- 2. Iodines iodine.131 Ci . E . E . E . E iodine 133 Ci . E . E . E . E iodine.135 Ci . E . E . E , E Total for period Ci . E . E . E . E
- 3. Particulates erontiurn49 Ci . E . E . E . E strontium.90 Ci . E . E . E . E cedum.134 Ci . E . E . E . E cedum 137 Ci . E . E . E . E barium 4:nthanum 140 Ci . E . E . E . E Others (specify) Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E . E unidentified , Ci . E . E . E . E
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-C - LIQUID EFFLUENTS 1993 t
i All samples of liquid effluents were analyzed according to ODCM requirements and, except for three instances as noted below, determined to be at or below minimum -
detectable activities (MDAs) for all radionuclides listed in the ODCM. These MDAs -
were below the LLDs required in ODCM Controls Table 4.11.1.1.1-1. In addition, no other radionuclides that are not specified in the aforementioned ODCM Table were identified. .
Except for the three cases noted below, composite sample results from batch and '
continuous discharges in this reporting period for tritium, gross alpha, noble gases, Sr-89, Sr-90, and all other nuclides, including those listed in the categories of principal gamma emitters and dissolved and entrained gases, are all at or below MDAs.
In the first quarter of 1993, trace levels of Fe-55 at 5.97E-8 pCi/mi were found in the '
composite sample for the continuous liquid release when both Reactor Building Salt Water Drain Tank pumps were routinely started and tested. -
in the second quarter, trace levels of Sr-89 at 1.20E-8 Ci/ml were identified in the l quarterly batch composite sample.
In the fourth quarter, a gamma spectroscopic analysis of a batch sample showed unidentified low level peaks near the usual positions for the Co-60 signature peaks.
It was conservatively reanalyzed, assuming they were indeed Co-60 activity indications. A level of 3.3E-8 pCl/ml was determined by manual calculations.
The maximum whole body doses and organ dose commitments from nuclides i identified in these three cases were all below regulatory limits. Section E prese'nts the ,
analyses in detail and shows the total results to be of insignificant impact to the '
public. j The total error percentage entered into Table 2A for liquid measurement was estimated from the tank sampling error and from counting error at values close to minimum detectable activities. This overall error is estimated to be approximately SOE ;
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
TABLE 2A l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES.
Unit Ousner Quener Est. Total g,,,,,g 1 1 2 l
A. Fision and actintion products l
- 1. Total release (not including tritium, :
gases, alpha) Ci 1.i.3 E-8 2.4 E-5 .$.o E+1 !
- 2. Average diluted concentration 4 l during period pCi/ml 5.97E-8 1.56 E-10 !
- 3. Percent of appucable limit % 7 46 E-3 5 2 E-3 B. Tritium
- 1. Tot al release Ci . E . E . E l
- 2. Average diluted concentration during period pCi/m! . E . E l 3. Percent of appucable limit % . E . E C. Dissolved and entrained goes
- 1. Total release C E E E l )
2 Average dduled concentration j during period pCi/ml . E . 'E ,
1
- 3. Percent of applicable limit % . E . E D. Gross alphs radioactivity El l 1. Total release l Ci l . E l . . E l l
i E. Volume of waste releued (prior to dilution) liters 2.32 E+6 2.oyE+6 1. o E+.t. l 1
F. Voliune of dilution water used during period liters 1.7o E+8 .i.55E+8 2. o E+1 )
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- No dilution volume was added during this small continuous release.
Total volume discharged in the one minute run was 50 gallons, or 189.25 liters.
ANNU.AL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A (c.<nr.)
EFFLUENT AND WASTE DISPOSAL . ANNUAL REPORT 1993 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Ousrter Quaner Est. Total 1 3 4 Error, %
A. Fission and activation products
- 1. Total release (not inciuding intium, gases, alpha) Ci . E 1.33 E-6 8.0 E41
- 2. Average diluted concentration during period pCi/ml . E 4.49 E-10
- 3. Percent of applicable limit % . E J. . y E-3 .
B. Tritium
- 1. Total release Ci . E . E . E l
- 2. Average diluted concentration during period pCi/ml . E . E
- 3. Percent of appbcable limit % . E . E C. Dissolnd and entrained gases
- 1. Total release Ci . E . E . E l
- 2. Average dduted concentration during period pCi/ml . E . *E i
- 3. Percent of applicable limit 'A . E . E I D Gross 31pha radioactivity I 1. Total release l Ci l . E l .
El . E l l E. Volume of waste released (prior to dilution) liters 1.lo Et6 1.1.9 Et6 1. O E +1 F. Volume of dilution water used during period liters 8 06 E+'l g. 67E+7 2.o E+.1 l
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- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 28 i l
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nucl des Released Ouarter i Ousn" 2 Quenerg l Quanu 2 Unit 3 strontium 49 Ci . E . E . E 2 46 E-5 Ci E E . E . E strontium.90 . .
Ci E E . E . E cesium 134 . .
Ci E E . E . E cesium.137 . .
Ci E E . E . E iodine 131 . .
Ci E E . E . E cobalt 58 . .
Ci E E . E . E cobali.60 . .
Ci E E . E . E iron-59 . .
Ci E E . E . E zinc.65 . .
Ci E E . E . E !
mang:nese.54 . .
Ci E E . E . E Aromium.51 . .
Ci E E . E . E zirconium niobium.95 . .
Ci E E E . E molybdenum 99 . . .
E E E E technetium.99m Ci . . . .
Cl E E . E . E barium. lanthanum.140 . .
Ci E . E . E . E cerium.141 .
E E l Other (specify) Ci . E . E . .
E E i ron -35 Ci i .13 E-8 . E . . i Ci . E . E . E . E
- Ci . E . E . E . E !
Ci . E . E . E . E l C E . E . E . E unidentified .
i Total for period (above) Ci 1.13 E-8 . E . E 2.% E-5 Ci E E . E . E xenon.133 . .
Ci E . E . E . E xenon.135 .
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
TABLE 28 ( cmt.)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS CONTINUOUS MODE S ATCH MODE 1
Nuclides Retsamed Umt j Quenst4 Owne'3 Quenu 4 Oustier 3 strontium 89 Ci . E . E . E . E __ l strontium.90 Ci . E . E . E . E_
cesium.134 Ci . E . E . E . E cesium.137 Ci . E . E . E . E iodine.131 Ci . E . E . E . E 1
cobait.58 Ci . E . E . E . E cobalt 60 Ci . E . E . E 1.33 E-6 i iron 59 Ci . E . E . E . E Ci E E E E zinc.C . . . .
raanga nere.54 Ci . E . E . E . E
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cluomium 51 Ci E E E . E l
E E E__ ;
zirconium. niobium.95 Ci . E . . .
molybdenum.99 Ci . E . E . E . E :
technetium.99m Ci . E . E . E . E barium. lanthanum.140 Ci . E . E . E . E cerium.141 Ci . E . E . E . E Other (specify) Ci . E . E . E . E Ci . E . E . E . E E E E i Ci . E . . .
E E E !
Ci . E . . .
Ci . E . E . E . E Cs E E E . E unidentified . . .
Total for period (above) . Ci . E . E . E 1 33 E-6 senon.133 Ci . E . E . E . E ac.nnn.135 Ci . E . E . E . E f 1
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT D - SOLID WASTE 1993 There was one shipment of solid waste offsite to a burial site during the year of 1993. l There were also six shipments of solid waste to a volume reduction vendor's ;i processing site, in addition,18 shipments of Shoreham's 'slightly irradiated fuel !
bundles were made during 1993. These shipments were made by barge from ,
Shoreham to Philadelphia Electric Company's Eddystone Station in Philadelphia then by train to its Limerick Generating Station for reuse. !
The entries in Table 3 represent the volume and curie content of solid waste shipped l from Shoreham to both types of sites during 1993. l i
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, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION 1993 WASTE STREAM: Resins, Filters, & Evaporator Bottoms WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
A 31.6 7.68E-1 i 25 %
ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Resins, Filters & Evaporator Bottoms with 1.0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES A Fe-55 59.6 % 4.58 E- 1 Ni-63 33.1 % 2.54 E-1 Co-60 5.8% 4.46E-2 Zn-65 1.5 % 1.17E-2 l.
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f ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
i SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION 1993 !
WASTE STREAM: Dry Active Waste s
WASTE CLASS CUBIC METERS CURIES % ERROR (Cl) i A 119.6 8.51 E-2 25 % '
ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM -l WASTE STREAM: Dry Active Waste with 1.0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES i A Ni-63 65.1 % 5.54E-2 f
Co-60 18.7 % 1.59E-2 Fe-55 14.0 % 1.19E-2
, 2n-65 2.2% 1.89E-3 1
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. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION
- 1993 ;
WASTE STREAM: Irradiated Components l
WASTE CLASS CUBIC METERS CURIES % ERROR (Cl) t N/A 0.0 0.0 N/A ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM i WASTE STREAM: Irradiated Components with .0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES !
N/A N/A N/A N/A ,
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ,
i TABLE 3 (Cont.)
SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION l
l 1993 )
f WASTE STREAM: Other Waste I
WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
N/A 0.0 0.0 N/A ,
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ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM i
WASTE STREAM: Other Waste with .0% CUTOFF I
WASTE CLASS NUCLIDE ABUNDANCE CURIES l l
N/A N/A N/A N/A i I
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
TABLE 3 (Cont.)
l SOLID WASTE SHIPPED OFFSITE FOR VOLUME REDUCTION ;
i 1993 WASTE STREAM: Sum of All Categories WASTE CLASS CUBIC METERS CURIES % ERROB_iCil i A 151.2 8.53E- 1 1 25 %
ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Sum of All Categories with 1.0% CUTOFF i WASTE CLASS NUCLIDE ABUNDANCE CURIES A Fe-55 55.06 % 4.70E-1 i Ni-63 36.26 %- 3.09E-1 '
Co-60 7.09 % 6.05E-2 Zn-65 1.59 % 1.36E-2 ' l SOLID WASTE VOLUME REDUCTION SHIPMENT
SUMMARY
i NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 6 Truck SEG (Oak Ridge, TN) i e
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. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL 1993 WASTE STREAM: Resins, Filters, & Evaporator Bottoms WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
N/A 0 0.0 N/A ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Resins, Filters & Evaporator Bottoms with .0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES N/A N/A N/A N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.) 1 SOLID WASTE SHIPPED OFFSITE FOR BURIAL _
1993 WASTE STREAM: Dry Active Waste -i l
i WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
N/A O 0.0 N/A ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Dry Active Waste with .0% CUTOFF ,
WASTE CLASS NUCLIDE ABUNDANCE CURIES N/A N/A N/A N/A i l
l 1
1
)
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. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL .
1993 9
WASTE STREAM: Irradiated Components ;
WASTE CLASS CUBIC METERS fd)BLEiS % ERROR (Cl)
B 0.41 190.0 i 25 %
ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Irradiated Components with 1.0% CUTOFF ,
WASTE CLASS NUCLIDE ABUNDANCE CURIES B Fe-55 49.1 % 9.32E + 1 .;
Co-60 47.6 % 9.05E + 1 Ni-63 2.7% 5.22E + 0 1
l j
1 l
i l
l l
p 2 4 J J ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
SOLID WASTE SHIPPED OFFSITE FOR BURIAL 1993 WASTE STREAM: Other Waste WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
N/A 0 0.0 N/A 1 ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM WASTE STREAM: Other Waste with .0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES N/A N/A N/A N/A
m
'1
- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Coni.) l SOLID WASTE SHIPPED OFFSITE FOR BURIAL
-1 1993 WASTE STREAM: Sum of All Categories i
WASTE CLASS CUBIC METERS CURIES % ERROR (Cl)
B 0.41 190.0 i 25 %
ESTIMATES OF MAJOR NUCLIDES BY WASTE CLASS & STREAM .i WASTE STREAM: Sum of All Categories with 1.0% CUTOFF WASTE CLASS NUCLIDE ABUNDANCE CURIES B Fe-55 49.1 % 9.32E + 1 Co-60 47.6% 9.05E + 1 Ni-63 2.7% 5.22E + 0 I
i
)
i
- _ _ . .i
-l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
SOLID WASTE SHIPPED FOR OFFSITE BURIAL DISPOSAL 1993 53 LID WASTE OFFSITE BURIAL DISPOSITION
SUMMARY
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1 Truck Barnwell, SC
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3 (Cont.)
IRRADIATED FUEL SHIPMENTS 1993 NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 18 Barge / Train Limerick Generating Station /PA l
l l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT E - RADIOLOGICAL IMPACT ON MAN 1993
- 1. Doses from Direct Radiation 9
Direct radiation (as measured quarterly with TLDs) made no significant contribution to offsite doses based on a comparison of 1993 dose rates with 1984 (pre-operational) dose rates. The highest average monthly dose in 1993 was 6.8 mrem / standard month (30.4 days), obtained in the fourth quarter at indicator location 9S1, compared to the 1984 dose at location 6A1 of 5.1 i mrem / standard month. Although this maximum value is about 30% higher than l the pre-operationalfigure, the average monthly reading for all indicator locations in the fourth quarter (4.2 mrem /std. month) is less than 8% higher over the control location average (3.9 mrem /std. month). The 1993 average for all indicator locations was 3.5 mrem / standard month compared to a 1984 value of 3.9 mrem /Ondard month. On the annual average basis therefore, there is :
no statisticaily significant contribution from the direct radiation component.
- 2. Doses from Liquid Effluent Discharges Throughout 1993, there were only three positive radioisotopic identifications in the liquid radioactive effluent release streams from Shoreham.
Concentrations of the radioisotopes identified in the liquid release streams were ;
all below the Lower Limits of Detection (LLD) as required by the ODCM. The very sensitive detection instruments at their Minimum Detectable Activity (MDA) levels however, were able to detect levels of concentrations that are well below the required LLDs. The three detected activities and their associated LLDs and concentrations are: i Release isotooe LLD Concentration Release Mode Period ( Ci/ml) ( Ci/ml) 2/22- Fe-55 1 x10'8 5.97x10'8 Continuous Liquid 2/28/93 (SWDT/RHR Service Water) 3/29- Sr-89 5x10~8 1.2x10 8 Batch Liquid !
6/27/93 (#93D-036 through !
- 93D-066) ;
12/17/93 Co-60 5x104 3.3x10~8 Batch Liquid
(#93D-097)
1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;
The Fe-55 release was through the running of the Reactor Building Salt Water Drain Tank (RBSWDT) pumps as part of the routine testing and maintenance requirements for the pumps. During the last week in February,1993, Pump A registered a 0.7-minute run time while Pump B, a 0.3-minute run time. Total volume released was 50 gallons at a 50-gpm flow rate. These were the only continuous liquid discharges in the first quarter of 1993. ;
The Sr-89 release was detected from a composite sample for the second quarter Batch Releases. The sample analysis was performed offsite by Scientech Laboratories in Gaithersburg, MD; and the measured level was 1.2E-8 pCi/ml. Scientech is a QA certified vendor that routinely analyzed quarterly ,
composite samples from Shoreham for Sr-89, Sr-90, and Fe-55. Twice a year, i Shoreham sent Scientech samples to be analyzed for Sr-89, Sr-90, and Fe-55 l for cross checking; and previous cross check results have been acceptable. Sr-89 has a half-life of 50.52 dcys. The last reactor criticality at Shoreham was i January 5,1989. Due to the number of half-lives that have elapsed since the last criticality date, it is physically impossible to have induced Sr-89 from Shorehare.. The sample was shipped to Scientech prior to fuel packaging and prior to the shipping cask's arrival on site, in order to be conservative j however, the Sr-89 result is assumed to be valid and therefore the dose results I I
were calculated and are included here.
The Co-60 release came from a batch release from the Discharge Storage Tank A on December 17,1993. A sample was obtained from the tank prior to the release of a total of 10,686 gallons of its contents. The 4096 multi-channel gamma spectrum analysis of the sample reported no gamma peaks identified with one sigma error at the 95% confidence level. However, there were two peaks measured but not identified and therefore, not included in the report.
Both were outside the normal i1.0 kev energy window set for the identification of the two prominent Co-60 peaks. To be conservative on this sample analysis, Co-60 was assumed present and a hand calculation was performed. A Co-60 concentration of 3.3E-8 Ci/mi was obtained, which was confirmed by running the spectrum analysis with a double-width energy window of i2.0 kev for the Co-60 peaks.
Following are the dose calculation inputs and results for each of the above three releases:
l
I
~
j
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- 1) Dose from Fe-55 in Continuous Liquid release between 2/22/93 and 2/28/93:
1 A). Input Data (from SNPS Continuous Liquid Radwaste Discharge l Summary, First Quarter of 1993):
l
- a. Discharge Flow Rate (gallons per minute): 50
- b. Release Duration (minutes):
RBSWDT Pump A: 0.7 RBSWDT Pump B: 0 3 l Total (Pump A + Purap B): 1.0
- c. Volume of Dilution W2.ter used: none
- d. dffluent Volume Discharged (gallons): 50
- e. Effluer't isotopic Concentration, i undiluted ( Cirml): 5.97E-8
- f. Total Activity Released (Ci): 1.13E-8 B). ?. sumptions and Methodology:
i Dose commitments were calculated using the backup method described in ODCM for computing doses from liquid effluent l discharges. A spreadsheet developed in-house from a LILCO calculation (#C-RPD-489, Rev. O) was employed to aid the -l computations.
It is assumed that doses to the public are primarily due to the ingestion of fish and seafood removed from the Long Island Sound. Doses due to other liquid pathways (shoreline deposits and land-based food chain) are assumed to be negligible from SNPS' Appendix I study and the fact that water from the Sound is not used for irrigation purposes.
1 Other assumptions and generic input data are taken consistently from SNPS Station procedures SP74X.020.12 (Rev. 0),
SP74X.020.02 (Rev. 0), and SP74X.020.10 (Rev. 0), in addition i to those specified in the ODCM (LIPA Rev.1). They are described -
in details in calculation #C-RPD-489, Rev.O.
C). Summary of Fe-55 Release Results:
f Because the primary pathway considered is through internal exposure, the doses calculated are dose commitments. Dose commitments to a member of the public for the surveillance period 2/22/93 through 3/28/93, encompassing the release period, are presented below: '
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Dose Commitments from Fe-55 in the Continuous Liouid Release mrem Organ Adult Teen Child W-Body 4.9 E-8 5.2E-8 7.OE-8 Bone 2.9E-7 3.0E-7 4.OE-7 Liver 2.0E-7 2.2E-7 2.2 E-7 Thyroid 0.0E-0 0.OE-0 0.OE-O Kidney 0.0E-0 0.0E-O 0.0E-0 Lung 1.1 E-7 1.4E-7 1.2E-7 GI-LLI 1.1 E-7 9.3E-8 4.0E-8 The maximum whole body and organ c'ose commitments are:
9 Dose Critical (mrem) Groun Organ W'iole Body Dose 7.0E-8 Child -
Organ Dose 4.0E-7 Child Bone Comparing these to the ODCM limits (Q: 1.5 mrem WB/5.0 mrem Organ; A: 3.0 mrem WB/10.0 mrem Organ), the. are well within the allowable limits:
Fraction of the ODCM Limits Quarteriv Annual Whoic Body Dose 4.7E-8 2.3E-8 Organ Dose 8.0E-8 4.0E-8
- 2) Dose from Sr-89 in Batt.5 Liquid releases during 2nd quarter of 1993 (3/29/93 - 6/27/93):
A). Input Data (from SNPS Batch Liquid Radwaste Discharge ;
Summary, Second Quarter of 1993):
- a. Release Start Time' (first batch): 4/01/93
- b. Release Stop Time (last batch): 6/23/93
- c. Release Duration (total run time, min): 4,768
- d. Effluent Volume Discharged (gallons): 5.41 E + 5
- e. Effluent Isotopic Concer.;tation, 1 undiluted ( Ci/ml): 1.20E-8 .
- f. Total Activity Released (Ci): 2.46E-5 '
' For conservatism, it was assumed that all the 30 batches in the second quarter were released with the same Sr-89 level of activity as identified in the quarterly batch composite samples.
1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT B). Assumptions and Methodology:
The assumptions and methodology used for analyzing the offsite dose commitments frorn the Sr-89 activities in the second quarter batch liquid releases of 1993 are identical to those used for the Fe-55 dose commitment estimates for the first quarter continuous liquid release, as given earlier under 2.1 B in this section.
C). Summary of Sr-89 Release Results:
Dose commitments to a member of the public from exposure in the second quarterly period (3/29/93 through 6/27/93), are presented below:
Dose Comraitments from SR-89 in 2nd Quarter Liauid Batch mrem Organ Adult Teen Child W-Body 1.73E-6 1.95E-6 2.43E-6 Bone 6.07E-5 6.67E-6 8.86E-5 Liver - - -
Thyroid - - -
Kidney - - -
Lung - - -
GI-LLI 9.89 E- 6 7.91 E-6 3.46E-6 The maximum whole body and organ dose commitments calculated for both quarters are:
Dose Critical (mrem) Grouc .Qraan Whole Body Dose 2.43E-6 Child -
Organ Dose 8.86E-5 Child Bone Comparing these to the ODCM limits, they are well under the allowable limits:
Fraction of the ODCM Limits Quarteriv Annual Whole Body Dose 1.6E-6 8.1 E-7 Organ Dose 1.8E-5 8.9E-6 I
1
,7 ,,
i n
[ j
1
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT b
- 3) Dose from Co-60 in Batch #93D-097 Liquid release during 4th quarter of 1993 (12/17/93; Discharge Storage Tank A):
Since Co-60 peaks were identified in the sample of this batch only and not in any of the subsequent batches, the following dose commitments are calculated for exposure to this batch on'y.
A). Input Data (from SNPS Batch Liquid Radwaste Discharge Permit for batch #93D-097,12/17/93):
- a. Release Start Time: 20:40 12/17/93
- b. Release Stop Time: 22:10 12/17/93 '
- c. Release Duration (total run time, min.): 90
- d. Effluent Volume Discharged (gallons): 10,686
- e. Effluent isotopic Concentration, Co-60 undiluted ( Ci/ml): 3.3E-8
- f. Total Activity Released (Ci): 1.33E-6 B). Assumptions and Methodology: ,
The assumptions and methedology used for analyzing the offsite dose commitments from the Co-60 activities in this fourth quarter batch liquid releases of 1993 are identical to those used for the Fe-55 dose commitment estimates for the first quarter continuous liquid release, as given earlier under 2.1).B) in this section.
C). Summary of Co-60 Release Results: -
Dose commitments to a member of the public from _ exposure to the Co-60 activities in the batch release are presented below:
Dose Commitments frqm_Cq-Spin Liould Batch #93D-097 Release 3 mrem Organ Adult Teen Child W-Body 2.6E-6 2.6E-6 2.9E-6 Bone - - -
1 Liver 1.1 E-6 1.1 E-6 9.6E-7 Thyroid - - - ;
Kidney - - - 1 Lung - - -
GI-LLI 2.2 E-5 1.5 E-5 5.4E-6 1
1 i
, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The maximum whole body and organ dose commitments calculated for both quarters are:
Dose Critical (mrem) Grouc Oroan Whole Body Dose 2.9E-6 Child -
Organ Dose 2.2E-5 Adult GI LLI Comparing the above results to the ODCM limits, they are well under the allowable limits:
Fraction of the ODCM Limits Quarteriv Annual -
Whole Body Dose 1.9E-6 5.8 E-7 Organ Dose 4.4E-6 2.2E-6 Conclusion on Liauid Effluent Discharaes:
The total calculated maximum whole body dore commitments due to the 4 above three liquid releases in the first, second, and fourth quarters, respectively, of Fe-55, Sr-89, and Co-60 are conservatively added up to yield the following conclusions:
Dose Critical (mrem) Grouo Oraan Whole Body Dose 5.4E-6 Child -
Organ Dose 8.9E-5 Child Bone Comparing these to the ODCM limits:
Fraction of the ODCM Limits Quarterly Annual Whole Body Dose 3.6E-6 1.8E-6 Organ Dose 1.8E-5 8.9E-6 -
> Both the maximal whole body and the organ dose commitments are below either the quarterly or the annual Technical Specification limits, and are approximately 0.002% or lower of the allowable limits. The total radiologicalimpact from these liquid releases to the general public is thus negligible.
g -
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT r
- 3. Doses from Gaseous Effluent Discharges j During 1993, there were no radioactive isotopes identified a'oove the lower limits of detection in any of the gaseous streams discharged. Therefore, no dose calculation was performed and the associated radiologicalimpact on the ;
general public from the gaseous effluents is none. -l l
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i t
i i
I p - , _ - ,. , - -
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT F - METEOROLOGICAL DATA 1993 Tables of cumulative joint frequency distribution of wind speed, wind direction, and ,
atmospheric stability are given by quarter for measuring heights of 33 feet and 150 feet for each stability class, in the following pages. The joint frequency distributions, as presented in the tables that follow, reflect all parameters that were reviewed by a meteorologist and were determined to be valid.
The average data recovery rate for 1993, notwithstanding the many winter storms during the first quarter, was excellent such that no recovery was needed from the backup analog strip charts. The offsite tower is considered to be representative of the I site and as such, was used for the collection of the original licerding meteorological database, which has been reviewed and accepted by the NRC. Although the calibration and maintenance of the strip chart recorders at the offsite tower is not included in the Plant's Surveillance Program, they are however, maintained by LILCO's Environmental Engineering Department (EED), in accordance with approved i procedures. A quarterly calibration and maintenance program for the meteorciogical instruments, including the recorders, was in place and executed until the end of the third quarter, whereupon it was reduced to a semiannual frequency in accordance with Technical Specification 3/4.1.1.3.
The 1993 raw meteorological data as recorded and averaged by the RMS Computer, was sent to a project meteorologist for review at regular intervals throughout the year.
The reviews, conducted in compliance with SNPS USAR Section 38-123 commitment to NRC Regulatory Guide 1.23, consisted of examining each hourly parameter along with onsite data logs, records of events, and activities for the meteorological systems.
Data of questionable quality were singled out and manually excluded from the database as though they were " missing". A set of mainframe programs were then called upon to generate the required joint frequency distributions.
For the four quarterly periods in 1993, the amount of flagged " missing" hours at the 33-foot level was 331, versus that of 510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br /> for the 150-foot level. Out of the 331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />, only 6 hourly average data sets were incomplete and treated as " lost" as a result of the RMS data acquisition process, with remaining all attributable to unacceptable or questionable instrumentation readings; whereas the 510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br /> for the 150-foot case were all falling in the later case.
As a result, for the 1993 reporting period, an annualjoint recovery rate of 96.2% was achieved for the 33-foot wind speed / wind direction / delta temperature combination, and a 94.2% recovery rate for the 150-foot level combination. Thus the requirement by Regulatory Guide 1.23 of meeting a minimum joint recovery rate of 90% is met.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;
l l
l l
1 l
l HOURS AT EACH WIND SPEED AND DIRECTION 9
PERIOD O'r RECORD: 1/ 1/93 TO 11/31/93 STABILITY CLASS: A ELEVATIDN 33 i
WIND SPEED (MPH) !
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N O 3 7 it 9 0 12 NHE O O 8 8 8 0 0 NE e 1 6 0 9 0 9 ENE O O 2 8 8 0 2 E 9 0 0 0 0 0 0 ESE e 0 0 0 0 0 8 SE O O 6 0 0 0 8 SSE 8 9 1 0 0 0 1 S 0 0 0 0 0 0 0 SSW D 1 0 2 0 0 3 SW 0 1 2 0 0 8 3 WSW 9 1 2 0 0 W
8 3 4 0 0 8 0 0 0 WNW 4 0 19 9 0 NW 0 28 8 3 25 7 8 8 35 HNW 0 0 4 2 0 0 6 i VARIABLE ,
1 TOTAL 102 PERIODS OF CALM (HOURSI: 0 6
l i
e I l
l l
l e
- l a
0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/95 STABILITY CLASS: 8 ELEVATION: 35 WIND SPEED (HPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 8 8 9 1 8 8 1 HNE O 1 0 e e e 1 NE O 1 1 4 8 0 2 ENE 8 8 8 8 e e e E e e e e e e e ESE O O 8 8 0 0 0 SE e 8 0 8 e e e
$$E 4 0 $ e e e e S 0 0 0 0 8 0 0 SSW G 0 8 2 0 8 2 SW 0 0 2 0 0 0 2 WSW 0 2 6 1 0 0 3 W 0 0 0 0 0 0 0 '
WHW 0 1 18 2 4 4 21 HW 0 3 2 3 0 0 8 HNW 9 3 4 1 l 0 6 2 VARIABLE i l
TOTAL 42 PERIODS OF CALM (HOURS): I 0 !
9 l
1 l
l 1
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4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT m
HOURS AT EACH WIND SPEED AND DIRECTIDN PERIOD OF RECORD: 1/ 1/93 TO 3/31/95 STABILITY CLASS: C ELEVATION: 33 WIND SPEED (MPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H e 0 1 8 0 0 1 HNE O 1 0 0 0 8 1 NE O 1 8 9 0 0 1 ENE 0 0 8 8 9 9 e E O O e e e o 0 ESE 8 0 0 0 9 0 0 SE 8 0 0 0 0 0 4 SSE 8 9 1 0 0 0 1 S e 0 2 8 8 8 2 SSW 0 0 1 2 0 0 3 SW 8 8 0 0 0 0 *O WSW 0 0 1 1 0 0 2 W 0 0 4 1 0 0 5 WNW e 1 16 13 0 0 30 HW 4 0 4 0 0 0 4 NNW 8 2 1 9 8 0 3 VARIABLE TOTAL 53 PERIODS OF CALM (HOURS): 8 S
9 e
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION A
PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 STABILITY CLASS: D ELEVATION: 33 WIND SPEED (HPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 1 21 3 5 8 8 30 HNE e 23 5 0 0 0 28 NE o 28 30 1 0 0 59 ENE 1 15 7 0 0 0 23 E O 8 3 0 0 8 11 ESE 1 7 3 0 0 0 11 SE 1 5 0 0 9 4 6 SSE 1 9 2 0 0 8 12 S 0 6 6 4 0 0 16 SSW 0 4 4 4 0 0 12 SW 1 4 4 2 0 0 11 WSW 8 5 10 8 8 0 15 W 0 5 19 4 6 0 34 WRW 0 15 35 24 3 0 77 NW 1 23 17 7 0 0 48 HNW 2 12 2 19 0 0 35 VARIABLE TOTAL 428 PERIODS OF CALM (HOURS): 0 4
0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
i e
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 '
l STABILITY CLASS: E ELEVATIDH 33 l
WIND SPEED (MPHI WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 10 31 19 1 0 9 61 HNE 7 33 21 8 0 4 61 NE 7 35 25 e e e 67 ENE 2 33 13 12 2 0 62 E 3 31 2 0 0 0 36 ESE S 17 2 0 0 0 24 SE 9 17 8 8 0 0 26 SSE 4 11 8 8 8 9 15 S 3 18 4 2 8 9 29 ;
SSW 2 13 le 14 8 0 39 SW 1 22 13 9 4 4 36 WSW 4 27 22: 1 0 0 54 W 3 25 49 19 1 0 97 WNW 6 45 98 50 3 0 194 HW 5 27 58 3 0 8 93 NNW 6 27 lt 3 0 0 55 VARIABLE TOTAL 949 PERIODS OF CALM (HOURS): $
I I
3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;
~
l i
HOURS AT E4CH WINO SPEED AND DIRECTION !
~
PERIOD OFiRECORD: 1/ 1/93 TO 3/31/93 -'
[
STABILITY CLASS: F
- ELEVATIDN: 33 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24- TOTALS N 6 6 1 e e e 14 ;
NNE 5 4 1 e e e le NE l 1 2 4 e e 8 7 ENE e 2 2 e 1 0- 5 :'
E 4 1 2 e e 8 7 ESE 2 4 8 e e e 6 >
SE 3 3 3 e e e 9 SSE l 3 8 e a e e 11 ;
S 5 le 2 1 e e 18 SSW 12 2e e e e e 32 SW 13 16 5 e e e 34 i WSW .6 le 1 e e e 17 !
W 7 5 4 1 e e 17 ,
WNW 11 2 8 8 0 e 13 l NW 5 3 .e 0 0 0 8 '
HHW $ 3 e 8 0 0 3 VARIABLE '
TOTAL 216 '
. PERIODS OF CALM (HOURS): 1 I R
(
i
- 43 i
\. _t l
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- l l
l s
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 -*
- STABILITY CLASS: 0 '
ELEVATION: 35 WIND SPEED INPN)'
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS ;
N 1 1 e 0 0 ~0 2 +
NNE e 1 e e e e 1 NE 1 1 1 e e e 3 j ENE e 1 2 e e e 3
~
E 2 e 4 e e 8 6 ESE 1 1 e e e e 2 !
SE 8 0 1 e e e 1
$$E 4 4 1 e e e 9
$ 6 le e e l e e 16 SSW- 12 6. e e e e 18 '
SW 28 22- e e e e 5e WSW 5 6 2 e e e 13 r W e e 8 8 e e 8 :
WNW 1 e e e e e 1 :
HW 2 e e e . 0 2 ;
NuW 1 e e e e e 1 1 VARIABLE I TOTAL 128 PERIODS OF CALM (HOURS): e i
I
- L I
e 4L4 I
~
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l l
l l
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF' RECORD: 1/ 1/93 TO 3/31/93 '
STABILITY CLASS: ALL' ELEVATION: 35 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 18 62 31 9 8 8 121 NHE 12 63 27 0 0 0 102 NE 9 69 69 1 4 8 148 ENE 3 51 26 12 3 e 95 E 9 48 11 0 0 0 60 ESE 9 29 5 8 8 0 43 SE 13 25 4 8 9 e 42 SSE 12 32 5 0 0 e 49 S 14 44 16 7 0 0 81 SSW 26 44 15 24 8 0 109 SW 43 65 26 2 0 0 136 WSW 15 51 38 3 8 0 107 W 10 35 76 25 7 0 153 WNW 18 64 178 98 6 0 364 NW 13 59 106 28 8 8 198 HNW 14 45 26 25 0 0 110 VARIABLE TOTAL 1918 PERIODS OF CALH (HOURS): 1 HOURS OF HISSING DATA: 242 p
-i:.. ;
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
~
-r i
HOURS AT EACH WIND SPEED AND DIRECTION :
PERIOD OF RECORD: 4/ 1/93 TD 6/30/93 STABILITY CLASS: A ,
i ELEVATION: 35 WIND SPEED IMPHI ;
WIND '
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS j N 0 8 4 7 1 e e a NNE .i S 3 6 1 4 e 10 i HE 3 le 4 4 8 0 21 l ENE 1 5 18 8 e e 24 .i E 1 1 4 0 0 0 5 !
ESE 1 3 3 0 0 0 7
SE 2 15 9 8 8 4 26 E
$$E 1 13 9 5 8 8 28 *
$ 8 12 30 4 4 8 46 '
SSW 8 7 57 16 8 8 80 SW 8 4 9 .1 e e 14 ;
WSW 8 4 0 0 0 8 4 W 8 0 2 0 0 0 2 .
WNW 9- 1 11 1 0 0 13 i HW G 4 8 8 8 e 12 .l HNW 9 4- 2 0 $ $ 2 -l VARIABLE
- TOTAL 303 ~
PERIODS OF CALM (HOUR $1: 4 *
'i 9
1 1
.i 46-
..y m , , - ,,w-
l 1
1 1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
HOURS AT EACH WIND SPEED AMD DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/95-STABILITY CLASS: B ELEVATION: 33 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 0 0 0 0 '
8 4 4 HNE O 1 8 9 0 0 1 NE 1 8 1 0 8 0 10 ENE # 4 2 8 0 0 6 E 2 1 0 0 e e 3 ESE 8 8 1 0 8 9 1 SE 9 1 0 1 0 0 2 SSE 9 3 1 e e t 9 L 8 8 4 2 8 9 6 SSW 0 1 5 2 e e 8 SW 0 1 1 0 0 8 2 WSW D 1 6 0 e e 1 W e # 0 e e e a WNW 0 1 7 0 0 0 8 4 NW G 1 3 0 0 0 4 NNW 8 0 8 0 0 0 0 VARIABLE ,
TOTAL 56 PERIODS OF CALM (HOURS): 8 l
1
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
l l
t HOURS AT EACH WIND SPEED AND DIRECTIDH ,
PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: C ELEVATION: 35 WIND SPEED (HPH)
WIND DIRECTION 1-3 4-7 6-12 13-18 19-24 >24 TOTALS H 8 8 8 8 0 0 0 NNE 8 1 1 0 0 0 2 NE O 4 1 9 8 9 5 ENE O 2 1 0 0 8 3 E o 0 1 0 0 0 1 ESE 4 0 2 8 0 0 2 SE O e e e e e e SSE e 1 1 8 8 9' 2 5 1 5 4 1 8 8 11 SSW D 3 4 1 0 G 8 SW 0 4 1 0 0 0 5 WSW e 3 1 0 8 0 4 W 0 e 1 0 e 0 1 WNW 0 3 4 2 0 0 9 HW 9 2 8 8 0 0 2 HNW 0 8 0 0 0 0 0 VARIABLE TOTAL 55 PERIODS Of CALM IHOURS): 8 9
f r
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/38/93 STABILITY CLASS: D ELEVATIDN 33 WIND SPEED (MPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 5 27 0 e e e 32 NNE 9 37 3 0 0 0 49 NE 2 40 1 e e e 43 ENE 5 12 5 8 8 0 22 E o 5 5 0 0 e 10 ESE 1 11 1 4 0 0 13 SE 1 18 4 e e 8 23 SSE 1 24 12 la e e 47 S 2 23 IS 8 8 3 48 SSW e 25 30 13 0 0 68 SW 5 13 8 0 0 0 26 WSW 2 11 1 0 0 0 14 W 0 17 24 3 8 0 3e WNW 1 61 91 6 0 0 159 HW 3 45 16 4 8 8 68 HNW 0 24 8 0 8 8 24 VARIABLE TOTAL 685 PERIODS OF CALM (HOURS): 0 4
9 l
_ _ _ -. ._. . . - - _ _ _ - _ j
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/3s/93 STABILITY CLASS: E ELEVATION: 33 WIND SPEED (HPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 9 19 1 0 0 9 29 HNE 9 15 2 0 9 8 26 NE 5 12 2 0 0 0 19 EHE 5 13 3 0 0 8 21 ,
E 2 5 1 0 0 0 8 ESE 1 11 5 0 6 6 17 SE 4 6 3 4 0 8 13 SSE 5 le 3 4 S e 18 S 3 30 30 2 0 8 65 SSW 4 60 63 12 4 6 139 SW 4 22 7 8 8 0 35 WSW 3 12 2 8 0 0 17 W 3 38 26 6 8 8 73 WHW 7 101 43 4 0 0 155 HW 14 60 13 0 8 8 87 HNW 5 29 2 8 0 0 36 VARIABLE TOTAL 756 PERIODS OF CALM (HOURS): 0 k
4 e
I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: F ELEVATIDH: 33 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 15-18 19-24 >24 TOTALS N 9 1 0 0 0 0 10 NNE 5 8 8 0 0 0 5 NE 1 2 8 8 0 0 3 ENE 6 0 0 0 0 0 8 E 1 0 0 0 8 0 1 ESE O 2 0 0 0 0 2 SE 8 0 0 0 0 0 0 SSE 5 3 0 e 0 0 8 S 1 le 8 8 0 0 11 SSW 4 29 0 0 0 0 33 ,
SW 6 19 0 0 0 8 25 WSW 4 6 0 0 0 0 10 W 15 le 1 0 0 0 26 WNW 7 15 0 0 0 0 22 HW 6 10 0 0 e e 16 HNW 5 9 0 0 0 0 14 VARIABLE r
TOTAL 186 PERIODS OF CALM IHOURS): 0 5
i h
l l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/93 TO 6/30/93 STABILITY CLASS: G ELEVATIDH: 33 WIND SPEED INPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N e 1 e e e e 1 HNE 3 8 e e e e 3 NE 9 0 0 0 0 e e ENE O e e e 8 0 0 E O e e e e o e ESE 2 0 e e 8 e 2 SE 8 0 0 8 0 0 0 SSE e 1 e e e 0 1 S 3 0 0 0 0 0 3 SSW 3 12 1 0 0 0 16 SW 7 23 0 0 0 0 30 WSW 19 2 0 0 0 0 21 W 10 1 0 0 0 0 11 WNW 5 1 0 0 0 0 6 HW 2 8 8 0 0 0 2 NHW 9 0 0 0 0 8 8 VARIABLE TOTAL 96 PERIODS OF CALH (HOURSI: 0 4
1 W__
~
1 1
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l 1
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93
STABILITY CLASS: ALL ELEVATIDN 33 WIND SPEED (HPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 23 48 8 1 8 8 80 HNE 26 57 12 1 0 0 96 NE 12 76 13 0 0 0 101 ENE 11 36 29 e e s 76 E 6 12 11 e e 8 29 ESE S 27 12 0 0 0 44 SE 7 40 16 1 0 0 64 SSE 12 55 26 15 0 0 108 5 10 80 83 17 8 8 190 SSW 11 137 160 44 0 0 352 SW 22 86 26 1 0 0 135 WSW 28 39 4 0 0 0 71 W 28 61 54 9 9 0 152 WNW 20 183 156 13 0 0 372 NW 25 122 40 4 8 8 191 HNW 10 62 4 0 0 8 76 VARIABLE TOTAL 2137 PERIODS OF CALM (HOURS): 8 HOURS OF HISSING DATA: 47 G
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 7/ 1/93 TO 9/30/93 STABILITY CLASSt A ELEVATIDH: 33 -
a WIND SPEED (NPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TDTALS ~I N 9 2 0 8 0 0 2 NNE e 7 8 e e a 7 NE e 21 2 e e e 23 ENE 1 9 1 e e 4 11 E e 1 2 8 8 8 3 ESE e 1 e e e e 1 SE O 3 2 0 0' 8 5 SSE 8 1 2 8 8 4 3 S 8 5 20 0 9 9 25 SSW 0 8 39 4 3 e 47 SW 4 8 4 e 6 c. 4 WSW 8 9 1 0 0 0 *1 W 9 8 2 8 0 0 2 WNW 8 3 30 8 0 0 33 NW 8 16 7 4 0 0 25 '
HNW 4 4 4 8 9 e g VARIABLE TOTAL 198 >
PERIODS OF CALH (HOURS): 0 O
r 1
+
l
)
)
f ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/93 TO 9/38/93 STABILITY CLASS: 8 ELEVATION: 33 WIND SPEED (HPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 8 2 8 0 0 0 2 HNE e 5 0 0 8 8 5 NE e 9 e 0 0 0 9 ENE 8 1 0 e e e 1 E 1 1 0 8 0 0 2 ESE O e 8 8 0 0 0 SE 8 4 1 8 8 e 5 SSE e 2 1 8 e e 3 S 8 1 1 8 0 0 2 SSW 8 3 3 8 8 8 6 SW 6 0 2 8 8 e 2 WSW D 1 1 0 0 0 2 W $ 0 2 0 0 0 2 WNW 9 9 7 0 0 0 16 HW 8 4 8 0 8 8 4 NNW 8 3 0 0 0 0 3 VARIABLE TOTAL 64 PERIDOS OF CALM (HOURS): 8 4
I l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECO2D: 7/ 1/93 TO 9/38/93 STABILITY CLASS: C ELEVATION: 35 WIND SPEED (MPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H e 5 e e 8 9 5 HNE 8 4 0 0 e e 4 NE 9 4 4 0 0 0 4 ENE e 1 8 e e e 1 E e 8 8 e e e e ESE o 2 1 0 0 0 3 SE O 2 8 0 0 8 2 SSE e 1 0 8 0 8 1 S 0 5 4 0 0 8 9
$$W 9 0 8 0 0 0 8 SW 0 1 3 0 0 0 4 WSW 1 0 0 8 0 0 1 W 8 0 2 0 0 0 2 WFTW G 8 5 0 0 0 15 HW G 12 0 8 0 NHW 8 12 9 7 1 0 0 0 8 VARIABLE TOTAL 77 PERIODS OF CALH (HOUR $1 4 e
. . _ . .- . . . . . - - m - . . _ _ - - . -__
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT '
i i
h HOURS AT EACH WIND SPEED AND DIRECTION ;
PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 '
STABILITY CLASS: D '
ELEVATION: 33 :
WIND SPEED (NPH) -i WIND i
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 4 46 1 0 0 0 51 HNE i 3 19 8 8 8 8 22 !
HE 1 18 0 8 8 e 19 i ENE 2 17 5 e 8 e 24 l E 1 8 8 e e t 9 !
ESE O 15 8 8 8 8 15 SE 8 24 5 8 8 8 29 .
SSE 3 36 2 e e 8 41 '
S 1 44 22 0 0 8 67
$$W 2 33 51 1 0 8 87 SW e le 5 0 8 8 15 WSW 2 10 1 0 0 0 13 W 1 11 12 0 e s 24 ;
WNW 8 50 15 8 0 0 65 :
HW 5 32 7 8 0 0 44 NNW l 2 50 2 0 0 0 54 ,
VARIABLE TOTAL 579 PERIODS OF CALM (HOURS): 0 s
+
l l
[
h
+
i
[
~
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -
i
(
HOURS AT EACH WIND SPEED AND DIRECTION l
PERIOD OF RECORD: 7/ 1/93 TO 9/30/93
- STABILITY CLASS: E ELEVATION: 33 I t
WIND SPEED (MPM) ;
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS t N 4 36 4 0 0 0 44 'h NNE 1 35 0 8 0 0 36 ;
NE 6 38 5 0 0 0 41 !
ENE 3 43 18 0 e e 64 J E 1 13 8 8 8 9 14 i ESE 2 le 0 0 t 0 12 8 SE 4 21 4 8 8 0 29 I SSE le 37 6 8 8 8 .53 S 11 70 24 1 {
0 0 106
$$W 12 88 62 2 0 '
0 164 SW 13. 2s 2 e e e 35 1 WSW 18 8 4 e e e so W .;
5 22 8 8 0 0 35 WNW 10 i 32 18 2 0 0 62 I NW 1. 24 1. . . . 44 !
NNW 3 34 14 0 4 4 51 ,
VARIABLE t
TOTAL 820. !
PERIODS OF CALM (HOURSit 8 i
i 1
i I
-[ .
l 4
5
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
l i
I HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 STABILITY CLAS$t F i
ELEVATION: 33
- r WIND SPEED (MPH 3 WIND ,
DIRECTION 1-3 4-7 8-12 13-18 19-24. > 28, ioTALS
......... ... ... .... ..... ..... ... ...... j N 3 2 8 8 8 8 5 I HNE 3 3 e e 9 e 6 ,
NE 3 0 0 0 4 8 3 ENE 2 8 8 0 $
3 e 2 i E 1 4 e e e e 1 ESE 2 8 8 0 0 8 2 SE 5 3 0 0 !
e e 8
-SSE 5 3 e e 4 0 8 S le 37 9 0 0 0 47 SSW 6 47 o o e s 53 Sif 18 16 0 4 e e 34 WSW 14 6 8 0 0 0 20 W 8 20 0 0 0 0 28 ;
WNW 9 8 1 0 0 8 18 .i NW 10 7 0 0 4 8 17, NNW j 13 1 0 $ 8 e 14 VARIABLE TOTAL 266 PERIODS OF CALM (HOURS): 8 >
i q k I
.t
-t i
e
?
i
.i
- - ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j t
i i
i HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 '
STABILITY CLASS: O' '
ELEVATION: 33 l
- (
WIND SPEED IMPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 0 0 0 0 0 0 8 HNE 8 0
-i 0 0 0 0 0 !
HE 8 0 0 -0 0 0 0 ENE t 8 0 0 0 0 0 0 E 9 0 0 0 0 0 0 !
ESE e 0 0 0 0 0 0 .!
SE 1 0 0 0 -0 0 1 ,
SSE 2 1 0 0 0 0 3 i S 3- 12 0 0 0 0 15 i SsW 11 11 0 0 0 0 22 :
SW 37 28 0 0 0 0 65 t WSW 48 4 0 0 0 0 52 W 22 2 0 0 0 0 24 i WNW 7 0 0 0 0 0 7 ,
NW 4 -0 0 0 0 0 4 '
MW 3 0 0 0 0 0 l' VARIABLE '
TOTAL 194 r PERIODS OF CALM (HOURS): 0 f t
Y t
I E
i
- )
I
~h
.t L
l 8
. l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
~
t i
HOURS AT EACH WIND SPEED AND DIRECTION :
PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 STABILITY CLASS: ALL :
ELEVATIDNr 33 '
WIND SPEED (MPH) ;
WIND
- DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 11 95 5 0 0 0 109 HNE 7 73 8 0 8 8 80 NE le 82 7 8 0 0 99 ,
ENE 8 71 24. 8 8 8 103 E 4 23 2 [
0 0 0 29 :
ESE 4 28 1 8 8 0 33 SE le 57 12 0 6 e 79 SSE 20 81 11 0 0 8 112 S 25 174 71 1 8 0 271
$$W 31 190 163 3 8 0 387 SW 68 7F. 16 4 8 e 159 t WSW 83 29 7 8 0 0 119 W 36 55 26 8 8 0 117 WPW 26 110 76 2 8 8 214 i NW 29 95 24 8 8 e 148 NHW 19 99 21 0 0 0 139 l VARIABLE i
TOTAL 2198 PERIODS OF CALM (NOURSI: 0 'l HOURS OF MISSING DATA: 10 i
0 ,
l 1
l l
1
1 i
ANNU AI. RADIOACTIVE EFFLUENT RELEASE REPORT !
l l
H00R3 AT EACH WIND SPEED AND DIRECTION PERIOD OF REC 0h0? 10/ 1/93 TO 12/31/93 STABILITY CLASS: A ,
ELEVATION ' 33 l
[
WIND SPEED (MPHI WIND DIRECTIDN 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 8 3 1 8 8 9 4 NNE 8 1 0 8 8 9 1 NE e 2 3 8 8 8 5 ;
ENE 5 4 3 0 0 '
e 7 E 8 9 1 e e e 1 ESE 8 8 9 9 e e e SE 9 8 9 0 8 8 9
- SSE 8 0 4 4 8 8 e
$ e e e e e e s SSW e 1 3 e e e 4 SW 8 1 3 1 e e 5 WSW e 8 0 8 9 e a W 6 0 1 0 0 0 1
WNW 8 4 4 0 0 0 8 HW 8 9 15 8 8 e 24 HNW 8 3 2 8 8 9 5 VARIABLE TOTAL 65 PERIODS OF CALM IHOURS): 0 9
-1 k
t
, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j i
HOURS AT EACH WIND SPEED AND DIRECTION
, t PERIOD OF RECORD: 10/ 1/93 TO 12/31/95 STABILITY CLASS: 8 ELEVATIDN: 35 WIND SPEED (MPH)
WIND l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS ;
M e 2 1 8 0 0 3 ,
NNE 8 0 e 4 e e e NE e 2 1 e e e 5 ENE 9 8 e e C e e ;
E e 1 e a e e 1 i ESE e e 0 e e e e SE e 8 0 e a e e !
SSE 8 8 e e e 0 0 S
e 1 e e e e 1 SSW e 1 4- e 8 e 5 '
SW e 2 4 4 e e 6 .-
WSW 8 0 e e e e e P W e 0 1 e e e 1 WNW 8 9 5 e 8- e 5 HW 9 3 2 8 e e 5 HNW 8 4 1 e e 8 5 VARIABLE TOTAL 35 PERIODS OF CALM IHOURS): 8 i'
O e
t
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i i
t 9
HOURS AT EACH WIND SPEED AND DIRECTION -
PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 !
STABILITY CLAS$s C ELEVATIDN 33 WIND SPEED (MPH) t WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS ,
N 4 0 1 0 0 0 1 NNE 8 1 0 0 9 0 1 NE 8 4 0 0 0 0 4 ENE 8 2 8 0 0 8 2 E e 1 8 8 0 0 1 ESE e 0 0 0 8 0 0 SE 8 0 0 0 8 8 0 SSE 8 8 9 0 0 e e ;
5 e e s e e e e !
SsW e 3 8 1 e e 12 SW 8 2 6 0 4 0 8 l WSW 8 1 2 8 e e 3 W 8 1 1 1 8 0 3 WNW e 4 7 e e e 11 NW 0 6 3 1 0 0 10 ;
NNW 8 0 2 8 8 0 2 '
VARIABLE TOTAL 58 PERIODS OF CALM (HOURS): 0 l
o i
P i
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
l r
HOURS AT EACH WIND SPEED AND DIRECTION i e
PERICD OF RECORD: 19/ 1/93 TO 12/31/93 i STABILITY CLASS: D i ELEVATION: 33 ;
i WIND SPEED (HPH) I WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS ;
N e 18 5 e e e 23 ,
NNE 1 12 6 e t 8 19 HE 1 12 6 8 0 0 19 ;
ENE 1 7 3 8 8 8 11 i E 9 5 4 8 0 8 9 ESE 1 12 8 2 0 8 25 SE 1 6 2 0 0 0 9 ;
SSE e 4 2 e e e 6 5 1 15 4 2 8 8 22 ;
SSW 1 16 30 1 0 0 48 SW 8 11 12 2 0 9 25 f WSW 2 6 9 3 4 0 20 -
W 1 8 21 24 8 0 54 1 WHW 2 18 le 14 e e 44 HW 5 27 14 5 0 0 51 HNW 3 19 19 3 0 8 44 VARIABLE !
1 TOTAL 427 PERIODS OF CALH (HOURS): 8 e
-I t
i F
v i
?
1 i
. .. . - -, , .~. .
t ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 9
1 i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/95 STAB!tITY CLASS 6 E ELEVA TION: 33 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 6 25 7 3 8 0 41 HNE 4 43 26 1 8 8 74 NE 3 23 59 12 0 0 97 ENE 4 12 23 0 0 8 39 E 5 30 21 8 0 0 56 ESE 9 27 13 2 0 0 51 SE 3 18 2 9 0 0 32 SSE 15 12 9 2 2 8 40 S 3 24 28 5 0 8 60 SSW 7 44 58 2 0 0 111 SW 5 73 28 3 0 8 109 WSW 8 36 9 11 0 0 64 W 7 17 36 9 9. 8 69 WNW 3 29 47 34 1 0 114 HW 8 28 48 22 0 0 98 i NNW 1 30 37 11 0 0 79 VARIABLE TOTAL 1134 PERIODS OF CALH (HOURS): 8 l
1 9
i e
1 I
l i
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
.6 l
l l
i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 l STABILITY CLASS: F ELEVATION: 33 l WIND SPEED (NPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS !
N 1 0 1 0 0 0 2 NNE 2 0 0 0 0 0 2
- NE 8 0 0 0 0 0- 8 ENE O O 9 0 0 0 0 E 4 3 0 0 0 0 7 ESE 6 7 0 0 0 0 13 SE 2 12 0 0 0 0 14 SSE 15 7 0 0 0 0 22 ,
S 11 15 0 0 0 0 26 '
$$W 11 24 0 0 0 0 35 SW 9 35 0 0 0 0 44 WSW 6 17 0 0 0 0 23 W 3 3 1 0 0 0 7 WNW 5 3 0 0 0 0 8 NW 2 2 0 0 0 0 4 NNW 1 1 0 0 0 0 2 VARIABLE TOTAL 209 PERIODS OF CALM (HOURS): 0 4
i s
s h
I W
-t
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ,
i HOURS AT EACH WIND SPEED AND DIRECTION ,
~
PERIOD OF RECORD: 18/ 1/93 TO 12/31/93 STABILITY CLASS: G ELEVATION: 33 WIND SPEED (MPH) i WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 0 0 '
0 0 0 0 4 HNE 8 0 0 0 0 e e NE 8 8 8 8 8 8 8 ENE e e 4 8 0 e e E 8 0 8 0 0 0 8 ESE 1 2 8 8 0 e 3 SE 3 1 0 0 e e 4 SSE $ 8 8 e e e 13 S le 29 0 8 e e 39 SSW 23- 29 9 e e e 52 :
SW 50 65 0 0 8 9 115 '
WSW 9 8 0 0 0 0 17 W 3 1 0 8 0 0 4 WNW 1 4 0 9 0 0 1 HW 0 0 0 0 0 0 0 .
NNW G G 4 0 $ $ 0 VARIABLE TOTAL 248 PERIODS OF CALM (HOURS): 6 I
'l i
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/95 STABILITY CLASS: ALL ELEVATION: 33 WIND SPEED (HPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 7 48 16 3 e e 74 NHE 7 57 32 1 8 0 97 NE 4 43 69 12 0 0 128 ENE 5 25 29 0 8 8 59 E 9 40 26 0 0 0 75 ESE 17 48 21 4 0 0 90 SE 9 37 4 9 0 0 59 SSE 35 31 11 2 2 0 81 S 25 84 32 7 0 0 148 SSW 42 118 103 4 0 0 267 SW 64 189 53 6 8 0 312 WSW 25 68 20 14 0 0 127 W 14 30 61 34 8 0 139 WNW 11 58 73 48 1 0 191 NW 7 75 82 28 8 0 192 NHW 5 57 61 14 8 0 137 VARIABLE TOTAL 2176 PERIODS OF CALM (NOURS): 9 HOURS OF HISSING DATA: 32 S
i
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/95 TO 5/31/95 STABILITY CLASS: A ELEVATION: 150 WIND SPEED (MPH) ,
W1ND DIRECTION 1-5 4-7 8-12 15-18 19 24 >24 TOTALS N 8 1 2 2 5 0 le NNE 6 0 1 8 e e 1 NE 8 0 0 4 2 8 6 ENE 9 9 C 2 e e 2 E e 0 0 e e e e ESE O 8 0 0 e e o SE 8 0 e e 0 0 0 SSE e 4 1 e e e 1 S 8 8 8 8 8 9 0 SSW 9 0 0 0 0 0 0 SW 8 0 1 1 0 0 2 WSW 8 0 1 2 0 0 5 W 0 0 0 P 0 0 0 WNW 8 0 6 4 7 0 17 NW 0 0 5 12 3 0 20 NfN 0 0 4 6 5 7 20 VARIABLE TOTAL 82 '
PERIODS OF CALM IHOURS): 8 t
4
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 STABILITY CLASS: B ELEVATION: 158 WIND $ PEED (MPM)
WIND DIRECTION 1-3 4-7 8-12 I3-18 19-24 >24 TOTALS N 0 8 1 8 9 1 2 NNE O 8 1 6 8 9 1 NE O 1 0 6 8 0 1 ENE 8 0 0 1 0 0 1 E~ 0 0 e e e e e ESE 8 0 0 8 0 8 0 SE 9 0 0 0 0 0 0 SSE e o e e e e e S 0 0 0 0 6 8 8 SSW 0 8- 0 0 -0 0 0 SW 8 0 1 1 0 0 2 WSW 8 0 2 1 0 e 3 W D 0 0 8 0 8 8 WNW 0 0 4 le 1 8 15 NW e e 3 1 0 0 4 NNW 8 1 1 1 2 2 7 VARIABLE TOTAL 36 PERIODS OF CALM (HOURS): 8 G
S ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
l t
?
HOURS AT EACH WIND SPEED AND DIRECTION ,
PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 STABILITY CLASS: C i ELEVATION: 15e ,
WIND SPEED (MPH) j WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS j N 8 1 # 1 1 0 3 NNE D 1 8 8 8 8 1 NE 9 1 8 8 8 8 1 .
ENE 8 8 8 0 0 8 8 1
.E e s 8 8 0 0 8 ESE 8 8 8 8 0 0 0 r SE 9 0 0 8 8 -G G SSE 8 8 0 1 8 8 1 S 8 'S 1 1 0 0 2 ;
SSW 8 8 0 0 9 0 0 SW G S e 8 8 8 8 WSW 9 8 9 1 8 8 1 ;
W 8 9 1 1 1 8 3 WNW 9 8 11 10 8 8 29 NW G 0 8 2 1 1 4 NNW 8 8 1 1 1 8 3 VARIABLE ,
I TOTAL 48 PERIODS OF CALM (HOURS): 0 n
P l
i
.i
(
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/95 STABILITY CLASS: D ELEVATI0H 150 WIND SPEED (HPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 2 8 4 3 9 6 32 HNE 8 23 12 4 1 8 49 NE 8 17 7 9 17 8 50 ENe- 0 11 le 12 8 8 33 E 9 6 6 2 0 8 14 ESE e 8 4 8 8 8 12 SE O 3 1 0 0 0 4 SSE o 4 5 2 8 8 11 5 0 0 8 3 1 8 12 SSW e 0 2 2 4 1 9 SW 8 1 1 3 2 8 7 WSW 0 0 3 9 0 0 '12 W 8 1 10 5 1 0 17 WNW 8 4 19 35 12 4 74 HW 0 18 5 9 2 1 27 HNW 8 7 6 5 13 9 40 VARIABLE TOTAL 394 PERIODS OF CALM (HOURS): 8 9
+
i
)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- ;
- i i
-I HOURS AT EACH WIND SPEED AND DIRECTION-PERIOD OF RECORD: 1/ 1/93 TO 3/31/93
- STABILITY CLASS: E ELEVATION: 159 i
WIND SPEED (MPN)
WIND l DIRECTION 1-3 .!
4-7 8-12 13-18 19-24 >24 TOTALS ~'
... ... .... ..... ..... ... ...... 1, N 0 7 24 18 13 8 62 NNE i 8 8 33 23 9 8 73 NE 8 i 9 29 19 4- 0 61. !
ENE 1 12 22 19 8 2 64 I E 1 30 19 2 5 4 61 1 ESE e 12 le 1 0 0 23 !
SE e 11 6 0 $ s. 17 _i SSE e 6 9 1 =0 e' 16 Ji S e 1 9 3 e e 13 i SSW 8 3 9 5 11 5 33 i SW 8 2 le 15' 1 0 28 I WSW 8 3 21 12 8 8 36' -!'
W 8 5 29 39 2 1 76 WNW 8 7 23 60 43 3 136 !
NW D 5 38 28 38 le 111 NNW G 4 17 31 19 8 71 VARIABLE l
TOTAL 881 PERIODS OF CALM (HOURS): s' 1
i I
'I l
1 l
l i
' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
-i i
l HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 .
STABILITY CLASS: F
{
ELEVATION: 150 ,
WIND SPEED (MPH)
WIND t DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS' I
[
N. 9 4 8 1 0 8 13' !
NNE 9 7 4 2 1 0 14 !
HE 8 2 8 4 0 0 14 ENE 1 3 8 2 0 1 7 !
E 1 5 4 4 8 9 14 -
8 5 I ESE e e e e 13 SE 1 2 4 0 0 0 7 i SSE e 1 5 0 8 8 6 S 8 6 3 2 0 8 11 ,
SSW D 1 9 2 0 0 12. :
SW 8 4 14 5 0 0 23 WSW 8 7 6 5 0 0 -18 I W 8 3 9 3 0 0 15 !
WNW . 0 3 7 0 0 0 10' i NW 1 4 8 0 8 0 5~ l HNW 1 2 2 8 8 8 5 '!
VARIABLE TOTAL 187-PERIODS OF CALM IHOURS): e t
l
.i I
i b
l 4
1
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
HOURS AT EACH WIND SPEED AND DIRECTION ,
I PERIOD OF RECORD: 1/ 1/93 TO 3/31/93 STABILITY CLASS: C ELEVATION: 150 I
WIND SPEED INPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 1 2 3 8 8 0 3 ME 1 1 2 1 3 8 5 NE e 1 g 8 0 e 1 ENE e e 1 4 0 0 5 E O 3 0 4 0 0 7 ESE o 3 8 0 0 0 3 SE 1 e 1 8 0 0 2 SSE 1 2 3 0 0 0 6 S 8 5 6 1 0 8 12 +
SSW 1 2 6 2- 0 0 11 SW 1 3 11 5 0 0 20 WSW 2 3 9 6 0 0 20 W 1 3 2 0 0 8 6 WNW 0 4 1 0 e e 5 -
NW 6 1 0 0 0 0 1 WW 8 1 0 9 e g g VARIABLE TOTAL 108 PERIODS OF CALM IHOURS): 3 l i
l
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT '
l 1
i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD of RECORD: 1/ 1/93 TO 3/31/95 STABILITY CLASS: ALL ELEVATION: 150 WIND SPEED (MPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 3 23 39 25 28 7 125 NNE 1 40 53 30 11 0 135 NE 8 31 44 36 23 0 134 ENE 2 26 33 40 8 3 112 E 2 44 29 12 5 4 96 ESE 9 31 19 1 0 0 51 SE 2 16 12 0 0 0 30 SSE 1 13 23 4 0 0 41 S 0 12 27 le 1 0 50 SSW 1 6 26 11 15 6 65 SW 1 10 38 30 3 0 82 WSW 2 13 42 36 0 0 95 W 1 12 51 48 4 1 117 WNW 0 18 71 119 71 7 286 NW 1 20 51 52 36 12 172 HNW 1 15 31 44 38 18 147 VARIABLE TOTAL 1736 PERIODS OF CALM (HDURS): 0 HOURS OF HISSING DATA: 424 9
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: A ELEVATI0H 158 WIND SPEED (MPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H e 0 8 4 2 1 7 HNE 4 0 3 2 4 3 12 NE 8 0 7 0 0 4 7 ENE 9 9 14 13 1 0 37 E e 1 1 2 1 0 5 ESE 8 1 6 0 0 0 7 SE 1 7 15 1 8 0 24 SSE 1 2 18 5 2 3 31 3 8 4 13 19 3 e 39 SSW G 2 17 47 21 1 88 SW e 1 3 9 1 0 '14 WSW 8 1 2 0 0 0 3 W 8 0 1 1 0 0 2 WNW e 8 1 3 2 9 6 HW 0 0 4 8 2 0 14 NHW 9 0 2 5 0 0 7 VARIABLE TOTAL 303 PERIODS OF CALM IHOURS): 8 O
S l
i l
l l
1 l
l
i 1
1 1
- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT '
r, ;i 1
l
+
1 I
}
HOURS AT EACN WIND SPEED AND DIRECTION i
PERIOD OF RECORD: 4/1/95 TO 6/30/95 .
STABILITY CLASS: 5 l ELEVATION: 15e WIND SPEED (NPN) !
WIND DIRECTION 1-3 4-7 8-12 13-Is 19-24 >24 TOTALS
......... ... ... .... ..... ..... ... ...... l N e e e e a e e +
NNE e e e e e e 4 -!
HE e. 2 2 e 4 4 4 ENE e 5 8 e e e 13 '~i E e 3 e ESE e e .4- 3 l e e e 1 e e 1 .l SE e 2 e e e 4 2 SSE e e 2. 1 S
1 3 4' i e e 2 2 1
e 5 SSW e 1 e 3 4 e a l SW e e 1 2 e "
e- 3 WSW e 1 e e e e 1- !
W e- e e a e e e ;
WNW e. e 1 3 e g HW 4 .]
e e 1 7 4 e a j NNW e e e e e g e
VARIABLE i
TOTAL- 56 !
PERIODS OF CALM (HOURS): e i
i e ,
9 s
0 i
e 6
4 1
y .,- .s,
l
^
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;
l i
1 HOURS AT EACH WIND SPEED AND DIRECTIDH e
PERIOD OF RECORD: 4/ 1/93 TO 6/30/95 STABILITY CLASS: C ELEVATION: 150 WIND SPEED IMPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 8 8 0 0 0 4 4 NNE S 8 0 8 1 8 1 NE 8 0 4 1 0 0 5 ENE 8 0 2 1 1 0 4 E O O O 1 8 e 1 ESE 8 0 1 1 8 8 2 SE 8 8 8 8 0 0 0 SSE O 2 1 1 0 4 4 S 0 2 5 1 0 0 8 SSW 8 1 2 3 1 1 8 SW 9 0 4 2 8 8 6 WSW D 1 3 0 0 0 4 W 0 0 0 1 0 0 1 WNW 8 1 3 2 1 0 7 NW 8 8 4 8 0 8 4 HNW 8 0 0 0 0 0 9 VARIABLE TOTAL 55 PERIODS OF CALM (HOURS): 0
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: D ELEVATION: 150 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 1 19 8 3 0 8 31 HNE 4 18 5 8 3 0 30 NE 3 39 17 8 8 9 59 ENE 4 14 15 6 e t 39 E 6 5 7 3 8 9 13 ESE 1 5 8 1 0 0 15 SE 8 13 5 9 0 8 18 SSE O 10 22 7 8 3 50 S 0 2 20 11 18 0 43 SSW 1 6 22 27 17 2 75 SW 8 4 14 8 @ 9 26 WSW 0 5 6 0 8 9 11 W 0 3 11 10 1 0 25 WNW 1 19 77 40 8 8 145 HW 4 27 22 18 4 4 75 HNW 1 12 12 5 0 0 33 VARIABLE TOTAL 685 PERIODS OF CALM (HOURS): 9 4
J
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: E CLEVATION: 150 WIND SPEED (HPH)
WIND DIRECTIDH 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 2 25 12 2 2 HNE 0 43 1 13 10 6 0 0 30 HE 1 4 13 7 0 0 25 ENE e 5 12 3 0 0 20 E 9 9 5 2 0 0 16 ESE 1 8 15 2 1 0 27 SE 1 4 6 8 8 8 11 SSC 0 5 6 3 0 8 14 S 0 4 14 16 2 0 36 SSW 1 2 33 85 24 2 147 SW 0 2 22 26 0 0 50 WSW D 2 12 3 0 0 17 W 0 4 28 7 0 0 39 WNW 0 14 68 44 9 8 135 NW 1 18 34 23 6 8- 82 NNW 1 18 28 15 2 8 64 VARIABLE TOTAL 756 PERIODS OF CALH (HOURS): 9 4
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: F ELEVATION: 150 WIND SPEED (MPH)
WIND DIRECTIDH 1-3 4-7 6-12 13-18 19-24 >24 TOTALS
, H 8 8 7 2 8 8 17 HNE 8 4 4 8 8 8 8 NE 2 3 2 0 0 8 7 ENE 1 2 0 0 0 0 3
. E O 4 3 8 0 0 7 ESE 1 2 1 8 4 4 4
' SE 8 4 8 8 8 8 4 SSE O 3 5 1 0 9
5 0 1 2 8 0 3 SSW 0 7 5 25 0 37 SW 6 1 6 16 8 23 WSW 0 1 3 5 4 9 W 6 2 6 1 0 t 9 WNW 1 3 9 0 4 4 13 NW D 4 8 1 8 0 13 NHW e 8 7 5 e 8 20 VARIABLE TOTAL 186 PERIODS OF CALN (HOURS): 8 i
1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/ 1/93 TO 6/30/93 STABILITY CLASS: O ELEVATION: 150 WIND SPEED INPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 8 3 8 8 9 0 3 HNE 1 1 1 8 9 0 3 i HE 1 2 8 0 0 4 3 ENE 0 8 0 t e e e E e 1 1 8 0 0 2 ESE 8 2 8 8 0 0 2 SE e 2 2 8 9 0 4 SSE e 1 1 e s 8 2 S 8 1 0 1 e e 2 SSW 0 1 5 6 0 0 12 SW 8 5 6 15 8 0 26 WSW 0 2 4 4 0 0 10 W 0 3 5 8 e e a WNW 1 5 0 0 0 0 6 HW 1 8 1 0 0 0 10 NIN 9 2 1 0 0 0 3 VARIABLE TOTAL 96 PERIODS OF CALM (HOURS): 8 O
p-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT '
9 i
HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 4/ 1/93 70 6/30/93 ,
- l i
STABILITY CLASS: ALL i
ELEVATION: 158 '
f t
WIND SPEED (HPH)
- WIND 1
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24' TOTALS N 3 55 27 11 4 1 191 NNE 6 36 23 8 j 8 3 84
- HE 7 50 45 8 8 8 110 ',
ENE 5 35 51 23 2 e 116 E 8 21 17 i 8 1 8 47 '
ESE 3 18 31 5 1 8 58 SE 2 32 28 1 0 0 63 SSE 1 23 55 18 11 6 114 S e 14 56 i 58 16 e 136
$$W 2 20 84 196 (
67 6 375 SW e 13 56 78 1 8 148 '
WSW 8 13 30 12 8 0 55
- W 9 12 51 20 1 0 84 WNW 3 42 159 92 20 0 316 NW 2 57 74 57 12 4 206 HNW 2 40 58 30 2 8 124
'?ARIABLE [
TOTAL 2137 PERIODS OF CALM (HOURS): 4 HOURS OF MISSING DATA: 47
~
e
[
r i
e i
'(
?
ANNUAL RADIOACTIVE EFFLUENT' RELEASE REPORT -
HOURS AT EACH WIND SPEED AND DIRECT 10N +
PERIOD OF RECORD: 7/ 1/93 TO 9/38/93 STABILITY CLASS: A ELEVATION: 158
~
WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 8 1 1 1 8 8 3 NNE 8 1 2 0 0 0 3 NE 6 5 14 1 8 8 20 ENE o 3 13 2 0 0 la E o 2 2 1 0 8 5 ESE O 1 0 8 8 0 1 .
SE O 8 2 8 '
0 8 2
$$E O 8 6 0 0 8 6 5 8 0 12 8 0 8 20 '
SSW 0 0 13 34 2 SW 0 49 0 0 0 7 8 e 7 WSW 0 0 8 1 0 0 1 W e 0 1 1 0 0 2 WNW e 1 20 12 0 0 33 HW 8 2 9 1 NHW 0 0 12 8 0 8 8 8 0 16 VARIABLE TOTAL 198 PERIODS OF CALH (HOURS): 8 h
6 i
i l
1 1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECT 10N PERIOD OF RECORD: 7/ 1/93 70 9/30/93 I STABILITY CLASS: B ELEVATIDH: 150 WIND SPEED (MPH)
. WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N & 2 1 e e 3 3 NNE 8 2 1 8 0 0 3 NE O 6 4 e e e 10 ENE 9 2 2 0 8 8 4 E O 1 0 e e 3 1 ESE e 1 1 e e e 2 SE e 2 1 0 0 e 3 SSE e e 3 e e 0 3 S 0 0 1 1 e a 2 SSW e 8 2 3 8 4 5 SW 0 2 0 2 0 0 4 WSW 8 0 0 2 0 8 W 2 8 0 1 8 0 8 1
WNW 0 3 12 1 8 8 16 NW 8 2 2 0 0 0 4 HNW 0 1 e e o e 1 VARIABLE TOTAL 64 PERIODS OF CALM (HOURS): 0 1
4 F
l l
I
ANNUAL RADIC ACTIVE EFFLUENT RELEASE REPORT '
a i
MOURS AT EACH WIND SPEED AND DIRECTION PERIOD Of RECORD: 7/ 1/93 TO 9/38/95 '
STABILITY CLASS: C ELEVATION: 1s0 !
r WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTALS !
N e s 1 . . . 6 NNE e 6 1 !
e e 8- 7 HE 8 3 0 e :
e e 3 ENE 8 1 1 0 8 8 2 !
E 9 0 2' 8 8 4 ESE e 2
a 1 e e L SE 4 1 8 2 0 0 0 8- ~
SSE e 2
8 8 8 4
$ e e I 0 1 7 2 6 8 10 '
SSW 8 1 2 6 9 4 9 SW 8 1 j 0 3 0 0 WSW D 4
0 0 1 4 W 8 8 4 -1 8 1 6 0 WNW 8 1 1 18 2 0 4 HW 8 13 !
8 2 8 4 0 HnW e le 4 1 1 e e VARIABLE 6 :
TOTAL 77 PERIODS OF CALM IHOURS): 0 a
I i
I' l
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/93 TO 9/38/93 STABILITY CLASS: D !
ELEVATION: 158 !
WIND SPEED (MPH) -;
, WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS- ;
N 1 33 2 2 8 8 38 26 12 f
NNE 1 1 0 0 40 "
NE 2 14 7 1 0 0 24 ENE 1 8 18 5 0 0 32 >
E 3 8 7 8 8 8- 18 ESE 1 8 4 0 0 8 13 SE 8 19 9 2 0 0 30 SSE 1 28 20 8 e e 41 S 1 6 38 11 1 0 57 SSW 1 4 32 48 4 8 89 ;
SW 6 4 6 12 9 0 22 WSW 8 7 6 3 8 9 16- [
W 6 7 s 20 e 7 4 '
WNW 8 19 28 7 8 8 54 NW 8 28 11 3 8 9 42 i NNW 1 31 1 10 0 8 43 l VARIABLE TOTAL 579 PERIODS OF CALM (HOURS): 0 _;
- i i
e 1
- .. - ,. r
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 '
STABILITY CLASS: E ELEVATION: 150 WIND SPEED (MPH)
WIND DIRECTIDN 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 3 2 28 28 2 8 61 NHE 1 8 27 18 8 8 54 NE 8 2 29 18 1 8 58 ENE 8 14 31 25 8 8 70 E 1 7 14 8 8 8 22 ESE 4 9 18 8 8 8 19 SE 1 18 12 3 8 8 26 SSE 1 8 24 6 8 S
8 39 8 14 45 21 1 8 81 SSW 2 11 73 97 3 0 186 SW 1 9 21 12 8 8 45 WSW 8 11 9 5 8 W
8 25 8 4 15 5 0 0 24 WNW 2 7 18 16 4 NW 8 47 1 18 12 12 8 8 35 NNW 1 8 11 21 3 8 44 VARIABLE TOTAL 826 PERIODS OF CALM (HOURS): 6 I
f I
1 l
r 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;
I i
'i
?
HOURS AT EACH WIND SPEED AND DIRECTIDN i 7/ 1/93 TO 9/30/93 PERIOD OF RECORD:
STABILITY CLASS: .F '
ELEVATION: 150 WIND SPEED (MPH)
, WIND f
!!!!CI!?N };} $;J );}2;}g }};2) 323 Jg}A(} l N e 9 2 e e 9 11 NNE 9 8 8 e e e 16 NE e 4 e 1 e e s . ENE e 3 4 e e e 7 ' E e 3 3 e e e 6 > ESE e 3 e e 0 0 3 l SE e 9 2 e e e 11
$$E e 2 5 e e e 7 i S e 9 18 12 0 0 39 SSW 9 8 33 12 e e .53 '
SW e 2 18 14 4 4 34-WSW e 6 7 2 e e 15 W 1 4 11 e 0 0 16 + WNW e 2 12 0 0 0 14 i NW e 4 11 1 0 0 16 ! NNW e 4 8 1 0 0 13 , VARIABLE TOTAL 266 PERIODS OF CALM (HOURS): 0 l I I 2 h i 4 0 9 i 7 -,.-.+-r,
r- i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECT 1DN PERIOD OF RECORD: 7/ 1/93 TO 9/30/95 4 STABILITY CLASS: C ELEVATION: ISO WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 2 4 0 0 0 0 6 HNE e 4 0 0 0 0 4 NE 2 1 0 0 0 0 3 ENE O 3 2 0 0 0 5 E e 5 3 0 0 0 8 ESE O 6 1 0 0 0 7 SE 2 1 2 0 0 0 5 SSE O 4 5 0 0 0 9
$ 2 6 3 3 0 0 14 SSW 0 7 15 5 0 0 27 SW 1 11 21 10 0 0 43 WSW G 9 14 2 0 0 25 W 0 4 9 0 0 0 13 WHW 9 9 2 0 0 0 11 HW 1 6 0 0 0 0 7 HNW 9 6 1 0 0 0 7 VARIABLE TOTAL 194 PERIODS OF CALM (HOURS): 0 h
9 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/93 TO 9/30/93 STABILITY CLASS: ALL ELEVATION: 150 WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 6 56 27 31 2 9 128 NNE 2 55 51 19 4 0 127 NE 4 35 55 20 1 0 ' 115 ENE 1 34 71 32 0 0 138 E 4 26 31 1 0 0 62 ESE 1 28 17 6 0 0 46 SE 3 43 28 5 0 0 79 SSE 2 34 63 6 0 0 105 S 3 36 124 58 2 9 223
$$W 3 31 170 205 9 8 418
- SW 2 29 66 60 0 0 157 WSW 8 33 36 16 0 e '85 W 1 18 44 14 8 8 77 WNW 2 42 102 38 4 8 188 HW 2 60 47 17 0 0 126 HNW 2 54 30 41 3 e 130 VARIABLE TOTAL 2204 PERIODS OF CALM (HOURS): 6 HOURS OF HISSING DATA: 4 6
h l
f ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l r ~! i i e i HOURS AT EACH WIND SPEED AND DIRECTION I PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 STABILITY CLASS: A ELEVATION - 150 ' WIND SPEED (MPH) WIND DIRECTIDN 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 9 9 4 2 0 8 6
- NNE 4 8 1 0 0 8 1 4 NE 9 0 0 3 0 0 5 EHE 9 8 7 2 8 9 9 E 8 9 1 0 0 9 1 i ESE 8 8 8 8 8 0 0 SE e 8 8 0 0 4 8 SSE 8 8 8 0 e e e i S e 0 0 8 8 9 0 SSW 4 0 1 0 1 0 2 SW 4 0 1 3 3 4 7 i WSW 8 9 1 0 8 8 1 I W 8 8 0 9 0 0 '
0 WNW G S 1 2 0 0 3 HW' S 9 11 4 0 0 15 NHW 8 0 6 le 1 0 17 VARIABLE TOTAL 65 ' PERIODS OF CALM (HOURS): 4 I f
?
f I i i I
+. l l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i f i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 . I STABILITY CLASS: 8 , ELEVATION: 150 WIND SPEED (MPM) : WIND , DIRECTION 1-3 4-7. 8-12 13-18 19-24 >24 TOTALS N 0 2 1 3 0 0 6 ' ME 8 0 2 e e 8 2 I NE e 1 1 8 1 e 3 ' ENE 8 8 8 .6 0 0 0 E 8 8 1 9 4 4 1 ' ESE 8 e e e 8 0 0 SE 6 0 8 8 4 e e t SSE 6 0 0 0 0 0 0
$ e 0 0 9 4 6 8 SSW G 8 2 2 1 0 5 :
SW e 1 2 .2 2 wSW e 7 .' e e e a e e O- -' w e e 0 0 -e e e WNW G e 1 2 8 -i 0 3 HW 9 0 4 2 8 8 6 HPW 8 9 1 1 0 0 2 VARIABLE , TOTAL 35 PERIODS OF CALM (HOURS): 0 l O I i I i
--.e- m e -w,4 ,- g .-- . .<rs , , - - , , , . ,n , , 9 m =,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTIDN PERIOD OF RECORD: 10/1/93 TO 12/31/95 STABILITY CLASS: C ELEVATION: 150 WIND SPEED (MPH) WIND DIRECTION 15 47 8-12 13 18 19-24 >24 TOTALS N 0 $ e 2 g 8 2 HNE e s 8 4 0 0 0 NE O 1 1 e e 9 2 ENE 8 8 5 0 0 0 5 E e 0 1 0 g g i ESE O e e 8 0 e e SE O O O 8 0 0 t
$$E 8 0 0 e e e e S 0 0 0 0 0 0 8 SSW e 1 2 4 1 0 8 SW 9 1 5 5 0 0 11 WGW e 8 4 6 s e 4 W 0 9 1 1 g 9 2 WNW 9 0 2 5 0 e 7 NW e e 7 1 0 9 a NNW e e- 2 4 2 e a VARIABLE TOTAL 58 PERIODS OF CALM (HOURS): e 0
)
l a e i i
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . j F 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: IS/ 1/93 TO 12/31/93 ; STABILITY CLASS: D ELEVATION: 150 WIND SPEED (MPM)
. WIND.
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 2 9 7 7 3 3 31 HNE e 12 4 4 5 2 27 NE 8 11 2 4 2 0 19 ENE 1 6 6 4 2 e 19 E 8 4 4 8 8 9 16 ESE 1 7 2 7 1 e 18 SE e 4 1 e e G 5 , SSE 1 1 4 1 e a 7 S e 7 6 2 2 0 17 SSW 8 3 17 14 3 0 37 - SW e 6 13 14 5 0 38 WSW 9 3 5 9 e e 17 W e 7 6 9 16 0 38 WNW 1 4 8 12 18 6 49 HW 1 14 11 4 1 3 34 ' NHW 8 16 11 12 15 1 55 ! VARIABLE i TOTAL 427 PERIODS OF CALM (HOURS): 8 l E l I i e 5
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 STABILITY CLASS: E ELEVATION: 150 WIND SPEED (HPHI WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 1 5 19 35 10 6 76 NHE 9 9 26 37 15 2 89 HE 1 6 14 33 32 11 97 ENE 3 3 2 19 13 0 40 E 1 8 28 31 4 0 72 ESE 3 14 17 14 3 0 51 SE 1 13 3 7 3 0 27 SSE 1 9 8 8 2 3 31 S 0 3 10 19 8 1 41 SSW 0 9 21 60 6 0 96 SW 9 8 42 58 2 2 112 WSW 8 9 40 11 13 2 75 W D 6 16 17 0 1 40 WNW 2 4 14 31 29 14 94 NW 9 3 21 31 15 6 76 NHW 1 5 23 38 30 20 117 VARIABLE TOTAL 1134 PERIODS OF CALH (HOURS): 0 l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l HOURS AT EACH WIND SPEED AND DIRECTIDN PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 . STABILITY CLASS: F ELEVATION: 150 WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13*18 19-24 >24 TOTALS H 8 4 1 0 8 8 g NNE 1 4 0 0 0 1 6 NE O 4 0 $ 3 g ENE 4 O 4 1 g g 8 E 5 1 5 9 1 0 0 ESE 16 e 3 11 0 0 0 SE 14 8 10 5 0 e 8 15 SSE 1 8 2 0 0 g gg S 8 6 le 2 0 0 18 SSW 1 6 9 7 0 0 25 SW D 5 17 17 8 0 39 WSW 9 1 14 9 0 6 24 W 8 1 9 1 0 0 11 WNW 8 5 5 HW 1 e a gg 8 2 1 8 0 NNW e 3 g g 3 g g g VARIABLE TOTAL 209 PERIODS OF CALN (HOURS): 8 b O e i j
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i I HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/ 1/93 TO 12/31/93 ' STABILITY CLASS: G ELEVATION: 158 - WIND SPEED (MFn) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTALS N 1 1 8 9 8 0 2 HNE O 1 0 0 0 e 1 NE 2 3 0 0 0 0 5 ENE o 4 1 0 0 0 5 E e 4 2 0 e s 6 ESE O 6 4 0 0 0 10 SE 2 7 3 0 0 0 12 SSE e 6 6 8 8 0 12 S 1 15 23 2 8 0 41 SSW 9 3 19 16 8 0 38 SW 1 5 17 16 0 0 39 WSW e 7 21 14 8 0 42 W e 4 6 0 0 0 10 WNW 0 4 7 0 0 0 11 NW 3 1 1 8 0 0 5 HNW 2 3 1 8 8 8 6 VARIADLE TOTAL 245 PERIODS OF CALM (HOURSI: 8 r h 4
- 100 -
i
. . .- . - ..- . .. . ,. ,~ ,.
'I l
l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l l
'l l
l
?
l t HOURS AT EACH WIND SPEED AND DIRECTION
, 1 PERIOD OF RECORD: 18/ 1/93 TO 12/31/93 STABILITY CLASS: ALL ELEVATION: 158 ,
WIND SPEED INPN) WINO DIRECTIDH 1-3 4-7 8-12 13-18 19-24
........w ... ...
>24 TOTALS N 4 21 32 49 13 9 128 NNE 1 26 33 41 24 5 126 NE 3 26 18 40 35 11 133 ENE 4 17 22 25 15 0 83 E 2 21 46 40 4 8 113 ESE 4 38 34- 21 4 0 95 SE 3 34 .;
12 7 3 8 59 SSE 3 24 28 9 2 3 61 S 1 31 49 25 le 1 117 i SSW 1 22 71 183 12 0 209 .i SW 3 26 97 115 12 12 - 253 WSW G 20 85 43 13 2 163 , W 9 18 38 't 28 16 1 101 WNW 3 17 38 i 53 47 28 178 NW 4 20 56 42 16 9 147 NNW 3 25 47 .! 65 48 21- 209 VARIABLE TOTAL 2175 PERIODS OF CALM (HOURS): 8 HOURS OF HISSING DATA: 35 , t i
.i l
~
^
I
- 101 - ,
l l
t
' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT .
i G - ODCM Revisions, REMP Location Changes and Major ; Changes to Radioactive Waste Treatment Systems 1993 t i Revisions were made to both the ODCM and PCP in 1993. Copies of the revised ! documents are attached as Appendix A. '
- 1. Changes to the ODCM ;
In 1993, the ODCM was revised to:
)
a) Reflect Amendment No.10 to License NPF-82 dated July 14,1993, which revised the SNPS Defueled Technical Specifications by relaxing the requirements from Semi-Annual Radioactive Effluent Release Reports to Annual
)
Radioactive Effluent Release Reports, in accordance with the revision to 10CFR 50.36a; b) Reduce the frequency of Land Use Census from annually to once every 2 years and delete the requirement for milk animals from further census taking; c) Delete reference to plant instrumentation and systems that have been removed as part of the decommissioning process; d) Incorporate the use of the RBSWDT in the batch release mode for the final draining of the SFSP after all fuel has been shipped offsite; e) Incorporate the changes associated with the planned phased decommissioning ' of the Liquid Radwaste System.
- 2. REMP Location Changes There were no REMP location changes during the report period.
- 3. Changes to the PCP in 1993, the PCP was revised to:
a) Reflect Amendment No.10 to License NPF-82 dated July 14,1993, which revised the SNPS Defueled Technical Specifications by relaxing the requirements from Semi-Annual Radioactive Effluent Release Reports to Annual Radioactive Effluent Release Reports, in accordance with the revision to 10CFR
-102 -
c ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT b) Reflect the current plant radwaste operations / conditions and incorporate the-Plan for the Phased Decommissioning of the Liquid Radwaste System submitted to the NRC in LSNRC-2004, Attachment 1, dated January 5,1993. I s i l
- 103 -
f
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT H - MISCELLANEOUS SPECIAL REPORT 1993 On November 20,1993, Gaseous Effluent Release Radiation Monitor PNL-41 was declared inoperable due to a low sample flow. The plant entered LCO#A93-40 to take necessary action LAW ODCM Table 3.3.7.11-1. Maintenance Work Request 93-53 i was issued to repair the pump. The pump was determined not to be repairable and PO#S9302763 was written to purchase a new pump. The manufacturer no longer had the exact type of pump needed so an Engineering Change Report (ECR) was initiated for the use of a similar pump that the manufacturer had available. Upon , arrival, the new pump was installed and tested. On January 4,1994, PNL-41 was i returned to service and the LCO lifted. Since more than 30 days has elapsed before PNL-41 was returned to an operable status, this explanation is included in this Annual Radiological Effluent Release Report , per requirement of ODCM Section 3.3.7.11, Action Statement (b). ; i l l l l
- 104 -
F ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 4
/
Appendix A i r i L s i
}
. + , +
4 1 g
. satana 4 - .
SWPC-001 "p Document No. j " i ~ Effective Date 9/1/93 Rev. 1
%e.
Prepared By Date Re g ed By Date hs ( ff] CONTROL COPY APPROVALS , Z$g Title / Dept. Sgnature Date Nuclear Analysis Section Head r/&8/E / Nuclear Engineering Division Manage 1
! 17 O )
SRC Chairman $2'fU . TITLE OF DOCUMENT SOLID WASTE PROCESS CONTROL PROGRAM t CONTROLLED i AUG~311993 N011YB
- j
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, SOLID WASTE '\ PROCESS CONTROL PROGRAM FOR SHOREHAM NUCLEAR POWER STATION - UNIT 1 REVISION 1 LONG ISLAND POWER AUTHORITY t
February,1993 . , L I Prepared by: \ . Date: : l Nuclear Engineering Division l Reviewed by: Date: ' N - SRC Chairman r [ Approved by: J Date: '
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Resident Manager , j
i TABLE OF CONTENTS l PAGE#, 1.0 Purpose 1 2.0 Radioactive Waste Sources 1 2.1 Floor Drain Filter 1 2.2 Radweste Filter 2 2.3 Spent Resin Tank 3 2.4 Cartridge Filters 3 2.5 Trash Compactor 3 2.6 Mdile Filter and/or Demineralizer 3 3.0 Radioactive Waste Streams 4 1 3.1 Spent Resin Tank Waste 4 3.2 Funda Filter Generated Waste 4 3.3 Floor Drain Filter Generated Waste 4 3.4 Dry Active Waste (DAW) 4 3.5 Filter Cartridges 4 3.6 Radioactive!y Contaminated Liquids and Solids 4 3.7 Mobile Filter and/or Demineralizer Waste 4 4.0 in-House Dewatering 5 5.0 Mobile Solidification, Dewatering, Filtration 5 nd Demineralization Services 6.0 Solidification Process Control Parameter Determination 6 7.0 Solidification and Dewatering Process Contro! 6 'i 7.1 Sampling and Analysis 6 7.2 Conditioning 7 7.3 Batch Test Solidification 7 ' 7.4 Waste Classification 8 7.5 Container Control 9 L 7.6 Decontamination 9 7.7 Records and Inventory Control 9 'l 8.0 Administrative Controls 10 8.1 Responsibilities 10 8.2 Changes to the Process Control Program 11 8.3 Major Changes to Radioactive Solid Waste Systems '11 ; 8.4 Annual Radioactive Effluent Release Report 14 i
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l TABLE OF CONTENTS (Cont'd)
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90 References 13 9.1 UPA Operating Procedures 13 9.2 Mobile Services Contractor Documents 14 9.3 General References 15 i FIGURE 1 Solid Radweste System . 16 FIGURE 2 Logic Diagram for the Phased Shutdown and 17 i Decommissioning of the Shoreham Radweste Facility l Appendix A Solidification Record Sheet 18 ) Appendix B Dewatering Record Sheet 21 Appendix C Definitions 23 Appendix D Controls and Surveillance Requirements 24 ' Appendix E Bases 28 Appendix F Plan for the Phased Decommissioning of the Uquid 29 Radwaste System 2 L
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Page 1 of 53 ( 1.0 PURPOSE The Shoreham Nuclear Power Station (SNPS) Process Contro! Program (PCP) describes the administrative and process controls which provide reasonable assurance of a consistent quality radioactive waste product which is acceptable for shipment and burial. Implementation of this PCP will be in accordance with Appendix D and will: o Provide assurance that waste types produced at SNPS will be classified satisf actorily in accordance with the requirements of 10CFR61. o Provide assurance that the requirements of 10CFR61 and specific disposal site criteria for Class A unstable waste to be solidified are met by the use of a mobile solidification system supplied by a qualified contractor. o Provide assurance that the waste form stability requirements of 10CFR61 for Class B and C wastes are met. This will be accomplished through the use of a mobile solidification system supplied by a qualified contractor or use of approved High integrity Containers (HICs) with approved overpacks. The contractor's Process Control Programs are referenced in the " Mobile Service Contractor Documents
- Section of this document. SNPS management shall ensure that the contractor's waste processing operations are performed in accordance with procedures, o Provide assurance that dewatered Class A, B or C waste products meet the applicable burial site criteria for free standing water.
o Provide assurance that the processing and packaging of solid radioactive wastes meet the requirements of federal and state regulations and disposal site criteria. o Ensure that the quality assurance requirements delineated in 10 CFR 71.101, 71.103 and 71.105 are met. , 1 2.0 RADIOACTIVE WASTE SOURCES j Low-level radioactive wastes are produced es a result of decommissioning activities at SNPS. The major contributing sources of radioactive waste are discussed in the fo!!owing subsections. As decommissioning progresses, the radioactive waste processing systems will be decontaminated and/or dismantled. This will occur in a phased manner, eliminating selected waste sources and the resulting waste streams in each phase as described in the " Plan for the Phased Decommissioning of the Liquid i Radweste System" (Appendix F). Figure 2 depicts a logic diagram of this phased approach to the decommissioning of these systems. 2.1 FLOOR DRAIN FILTER The filter is a horizontal traveling screen, precost type, designed for air drying and air aided discharge of the cake (without backflushing)into a shipping container for
Page 2 of 53 further dewatering. The waste may contain filter media auch as diatomaceous scrth or a powdered resin / fiber blend type material. The floor drain filter can be used to process the fo!!owing combined liquid radwaste streams: o Reactor Building Floor Drains I. o Turbine Building Floor Drains o Radwaste Building Floor Drains o Sample Tank Area Floor Drains o Turbine Building Decon Area Floor Drains o Condensate Storage and Transfer System Overflow Sump Pumps discharge. o Laundry Drains Tank Class A, B and C waste which is dewatered using irehouse equipment is . processed according to SP R3X710.02," Dewatering of Spent Radwaste Media". Waste which is dewatered by the contractor's mobile equipment will be processed according to his procedures (see
- REFERENCES" Section).
1 2.2 RADWASTE FILTER The Radweste Filter is used to process the fo!!owing combined liquid radwaste streams: o Low Conductivity Equipment Drains o Reactor Building Equipment Drains, Drywell Equipment Drains, Radwaste Building Equipment Drains, and Turbine Building Equipment Drains l c Radweste Filters displacement and profiltration liquid l l o Decanted liquid from the Phase Separator and the Spent Resin Tank o Blowdown from the Fuel Pool Cooling and Clean-up System l The radweste filter units are sech composed of stacked horizontal filter discs assembled on an exia!!y located hotiow shaft. After deining the filter essel and air-drying the filter cake, the filter assemb!y is spun to renove the filter cake from the filter discs and discharged directly into a waste shipping container for dewatering and disposal. l
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- Page 3 of 53 The waste resulting from the filters may contain diatomaceous earth, Ecodex or similar powdered resin / fiber blend material. If Class A, B or C waste is being dewatered using in-house equipment itis processed according to SP R3X710.02, "Dawatering of Spent Radweste Media". All classes of waste may also be dewatered by the contractor using procedures referenced in the " REFERENCES" Section.
2.3 SPENT RESIN TANK (SRT) The Spent Resin Tank accepts the sludge from the backwash storage tank of the Fuel Pool Clean-up etched-disc type filter, in addition to spent bead resin from the fuel pool domineralizers, and the radwaste demineralizers. The resin is allowed to settle before excess water is decanted to the waste co!!setor tanks. Resin in the SRT can be transferred directly into a HIC from the SRT for dewatering by the in-house equipment or the contractors' Mobile unit using the procedures in the " REFERENCES" section of this PCP. 2.4 CARTRIDGE FILTERS The Control Rod Drive System uses a cartridge type filter for processing. Cartridge filters may also be used in mobile filtration systems. These cartridges may be imn obilized in a cement mixture which includes evaporator bottoms concentrates or spent resins. These may also be compacted as Dry Active Waste (DAW) usint SP R3XO75.01 (provided the filter cartridge is dry). Liners that contain solif objects era specifically identified. Liquid offluent from filtration of the laundry drains is not recovered. 2.5 TRASH COMPACTOR The drum compactor is used to compress low level dry waste such as r a g s , pap ar, shoe covers, floor sweepings, dry filters, HEPA filters, strainers and plastic glos es into 55 gallon steel drums for shipment offsite. Compaction force is rated at 1L.000 lbs for an approximate 4:1 compaction ratio. 2.6 MOBILt FILTER AND/OR DEMINERALIZER The mobile filter and/or demineralizer may be used to process the waste streams norma!!y treated by the floor drain filter or the radwaste filters (refer to sections 2.1 and 2.2 above). The filtration and/or demineralization media used mayinclude carbon-based media, oil-block media, bead resins, diatomaceous earth, ecodex and other acceptable vendor supplied media. Cartridge filters may also be used. After use, the filtration and/or demineralization medium is transferred to a waste container for in-house dewatering in accordance with SPR3X710.02,
- Dewatering of Spent Redwaste Media", or mobile dewatering or mobile solidification in accordance with contractor's procedures listed in the
- REFERENCES" Section.
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- Page 4 o' f 53 i 3.0 R ADIOACTIVE WASTE STREAMS 3.1 SPENT RESIN TANK WASTE This might be a mixture of the following:
3.1.1 Radwaste Domineralizar resins 3.1.2 Fuel Pool Domineralizer resins 3.1.3 Fuel Pool Cleanup (Vacco) Filter backwash sludges 3.2 RADWASTE (FUNDA) FILTER GENERATED WASTE 3.3 FLOOR DRAIN (FLAT BED) FILTER GENERATED WASTE 3.4 DRY ACTIVE WASTE (DAW) 3.4.1 Compactible 3.4.2 Non-Compactible 3.5 FILTER CARTRIDGES 3.5.1 HEPA Filters 3.5.2 CRD Filter cartridges 3.5.3 Mobile Filtration System Filter cartridges 3.6 RADIOACTIVELY CONTAMINATED L10UIDS AND SOLIDS Due to varying burial site regulations, each will be handled on a case by case basis in accordance with the burial site criteria and federal regulations. 3.6.1 Organics (including oils) 3.6.2 Charcoal (filters, charcoal beds) , 3.7 MOBILE FILTER AND/OR DEMINERAllZER WASTE This may include the following: 3.7.1 Carbon-based media 3.7.2 Oil-block media
Page 5 of 53 i 3.7.3 Bend resins 3.7.4 Diatomaceous Earth 3.7.5 Ecodex 3.7.6 Other acceptable vendor supplied media NOTE: ftems 3.7.1,3.7.2 and 3.7.6 can only be used if found acceptable under 3.6 and the 1 % oil test has been demonstrated successfully on ' those media. 4.0 IN-HOUSE DEWATERING As an altamative to solidification, Class A, B, and C dewaterable waste may be ' dewatered in High Integrity Containers (HIC). Non high integrity containers can be used for Class A waste. All of these containers are equipped with internal filters to which a pump may be attached. Pumping continues until burial site criteria for free standing non corrosive liquid are met. Dewatering is conducted in accordance with plant procedure SP R3X710.02, " Dewatering of Spent Radweste Medis," to assure a consistently , acceptable product. 5.0 MOBfLE SOLIDIFICATION. DEWATERING. FILTRATION AND DEMINER AlfzATION SERVICES 5.1 Wastes to be solidified must be transferred to the mobile solidification / dewatering equipment which is provided and operated by a qualified contractor. Class A, B or C dewatered wastes may be processed by the mobile services contractor or the in-house dewatering system at the discretion of the Radwaste Engineer. Class A solidified wastes shall be processed by the contractor. The mobile filtration and demineralization system may be operated by either contractor or properly trained SNPS Operators. 5.2 The " Mobile Services Contractor Documents" in the References Section have been used to prepare Station Procedures for use by the mobile services contractor and SNPS personnai to ensure that waste products meet all requirements for shipment and burial offsite. E3 Provisions have been made for the mobile solidification, filtration and demineralization equipment to be installed on Elevation 19' 6" of the Redwaste Building. This equipment will be installed and utilized as required. Spills are contained by installing the equipment in areas where sloping floors will carry liquids to floor drain sumps. The building ventilation system provides for filtering of particulate airborne contamination and monitoring of radiation before it enters the station vent. F
Page 6 of 53 6.0 sottDIFICATION PROCESS CONTROL PARAMETER DETERMINATION Solidification process control parameters are contained in the Mobile Services Contractor's Process Control Program. 7.0 SOLIDIFICATION AND DEWATERING PROCESS CONTROL 7.1 SAMPLING AND ANALYSIS 7.1.1 Samples shall be obtained and analyzed according to SP 72X002.18, "Radwaste Sampling for Disposal," prior to each solidification or dewatering operation and tested according to the contractor's procedures prior to solidification. 7.1.1.1 Sampling for Solidification
- 1. The waste tank to be sampled sha!! be recirculated for a minimum of three tank volumes prior to sampling, unless the tank had been on recirculation continuously since it began to be filled.
- 2. The waste tank sampfed shall remain isolated and in recirculation or agitation, as applicable, until the solidification process is started. If it becomes necessary to add material to the tank being processed, a new batch number will be initiated and a new sample will be taken after an appropriate mixing time.
- 3. Test solidification will be performed according to the schedule described in the " Batch Test Solidification" Section.
7.1.1.2 Sampling for Dewatering Funda, Spent Resin Tank and flat bed filter wastes must be sampled from the liner. These will not be mixed prior to sampling. 7.1.2 The following applies to both Dewatering and Solidification.
- 1. Samples will be analyzed for pH and gamma emitters.
- 2. Oil content will be verified to be less than 1 % by volume prior to shipment. ,
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- 3. The analysis number will be added to the Solidif*mation or ~ -
Dewatering Record Sheet which is prepared for'sach'weste container (liner or HIC)..
- 4. For waste streams that could potentially contain c h e ie tin g !
' gents, a a determination will be made as to whether the waste .;
contains greater that .1% cheletes by weight and if so, the.. j percent of chelate will be determined. 7.2 CONDITIONING ! l 7.2.1 Weste conditioning for solidification is required when any of the ; following conditions exist
- 1. The pH is outside of the acceptable range according to the.
contractor's PCP. l
- 2. Liquid content of the batch is above or below the acceptable ;
envelope for solidification as indicated in the Contractor's PCP in i the " REFERENCES" Section documents. ; 7.2.2 pH 'shall be determined on the decanted liquid from each container which has been dewatered. If pH is less than 4 or greater than 11 it , will.be determined on's case-by-case basis if any further action is l required prior to shipment. ! 7.3 BATCH TEST SOLIDIFICATION 7.3.1 Test solidification shall be performed according to the following i schedule: 1
- 1. One sample initially from each type of wet waste, and then from !
every tenth batch of each type of wet waste. }
.s NOTE: Balsh is defined as the total volume of waste _
contained in a waste mixing tank that has been prepared for solidification.
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- 2. When sample analyses fall outside the acceptable envelope) established by the mobile services contractor, indicating a' ,
change in the waste type. 7.3.2 If any test specimen fails to solidify, the solidification of the batch ' under test.shall be deferred until such time as additional test l specimens can be obtained, altamative solidification parameters con be determined, and a subsequent test verifies solidification. ; i i f f s
Page 8 of 53 Solidification of the batch may then be performed using the a!temative solidification paramsters determined. Representative samples shall be obtained and tested from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The contractor shall modify his own PCP as necessary to accommodate unusual waste streams. 7.3.3 The test specimen shall be }udged to have solidified successfully if, when its container has been removed, it remains a free standing monolith with no visible free liquid. 7.3.4 if a cement and water mixture (without waste) is used to s olidif y misce!!aneous objects,this mixture will be tested for solidification prior to use. 7.4 WASTE CLASSIFICATION 7.4.1 in compliance with 10 CFR 20.311, wastes are classified as Class A, B or C, or greater than Class C, based on the presence of particular radionuclides and their activities as specified in 10 CFR 61.55. Plant procedures SP R1X001.02, "10CFR61 Compliance Program", and SP R2X713.06, " Calculations for Radwaste Curie Content" or SP R3X713.02 "RADMAN Computer Program" provide the methodology for this determination as used at SNPS. 7.4.2 Waste streams will be sampled based upon the Branch Technical Position requirements (or more frequently,if plant parameters indicate a change in waste characteristics) and analyzed for fission and activation products, including transuranics. Scaling factors will be developed from these complete analyses if detectable results are obtained, and will be used with gamma spectra from each batch of waste to infer the concentrations of non-gamma emitting radionuclides. 7.4.3 When complete sample analyses do not yield detectable results, radionuclide concentrations will be used based on scaling factors determined in accordance with "RADMAN - Data Base Analysis Report". 7.4.4 The curie content of waste streams (such as trash) for which representative sampling is difficult may be inferred based on gamma analysis of representative smears and extemal dose rate measurement (SP R2X713.06 or SP R3X713.02).
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Page 9 of 53 7.5 CONTAINER CONTROL 7.5.1 A quality assurance program shall be established to inspect the container to be used for dewatering (and solidification) using SP R2X713.30, "Radweste Container Control". 7.5.2 This program shall assure that prior to use, the containers to be used for dewatering ars iritect and free of any visual damage that would prevent the dowatering of waste to required limits. 7.6 DECONTAMINATION Prior to shipment, containers will be swiped for removable contamination and examined for general condition. Decontamination will be conducted as necessary to meet shipping requirements. 7.7 RECORDS AND INVENTORY CONTROL 7.7.1 Solidification
- 1. A Solidification Record Sheet (Appendix A) shall be completed for each liner filled for solidification. [
- 2. If more than one liner results from a batch, then the initiallinars will not be shipped until all liners for that batch are verified as being solidified. Those liners will be identified by a common analysis number.
7.7.2 Dewatering Radiochemistry Analysis Sheet and Post Dewatering Survey Sheet (see , Appendix B and Appendices 12.4 and 12.5 of SP R3X710.02) shall ! be completed for each container filled with dewatered waste. 7.7.3 Solidification and Dewaterire
- 1. The Solidification or Dewatering Record Sheets and the attached
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isotopic analysis shall be forwarded to the Radwaste Engi:,eer for retention until such time as the liner identified on the Record Sheet is shipped for final disposition.
- 2. When the identified liner is shipped and then verified received, the Solidification or Dewatering Record Sheets and other documents concerning the shipment shall be forwarded to Records Management for permanent record storage. j
Page 10 of 53 8.0 ADMINISTRATIVE CONTROLS 8.1 RESPONSIBILITIES The fol. swing outlines departmental responsibilities and interfaces to implement and aus., art all activities associated with the SNPS PCP. NOTE: All service contractor procedures implementing the PCP which will be used at SNPS, prior to their utilization and implementation, must be approved by the Site Review Committee as per SNPS Tech. Spec. 6.7.1.h. 8.1.1 NOC Policy 25 (Management of Low Level Radioactive Waste) identifies the following orgsnizations as having direct responsibilities for the implementation, maintenance, licensing and regulatory interf ace of the SNPS PCP.
.1 Nuclear Engineering Division, as described in NED 1X02.
.2 Operations and Maintenance Department, as described in SP R1 X001.01.
.3 Licensing and Regulations Compliance Department (LRCD)
.4 Nuclear Quality Assurance Department (NOAD) as described in the QA Manual, Section 1.
.5 Independent Review Panel (IRP) as also described in the
" Independent Review Panel Charter".
See NOC Policy 25 for more details. 8.1.2 Procedure NED 6XO4, " Change Control", in conjunction with the LRCD6X, " Control of License Documents" shall be used to review, approve, control and disposition proposed changes and revisioas to the SNPS PCP. 8.1.3 NED is restonsibia for preparing and maintaining the PCP current per NED Procedures 6XO4 and 6X01. 8.1.4 The Site Review Committee (SRC) is responsible to review and find acceptable any changes to this program and the associated l implementing procedures.
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8.1.5 The Resident Manager's approva! shall be obtained for every PCP revision. i i
Page 11 of 53 i 8.1.8 SRC and Resident Manager approval signatures shall be indicated on the cover page of the PCP. 8.1.7 PCP implementation is accomplished through station procedures and is the responsibility of the Radiological Controls and Operations Divisions. 8.2 CHANGES TO THE PROCESS CONTROL PROGRAM Any changes to the Solid Waste Process Control Program for the Shoreham Nuclear Power Station shall be reviewed and found acceptable by the Site Review Committee and approved by the Resident Manager as specified in Technical Specifications. 8.3 MAJOR CHANGES TO RADIDACTIVE SOLID WASTE SYSTEMS 8.3.1 Licensee-initiated major changes to the radioactive waste treatment systems (solid):
.1 Shall be reported to the Commission in the nnual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Site Review Committee. The discussion of each change shall contain:
.1 A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
.2 Sufficient detailed information to totally support the reason for the change without the benefit of additional or supplementalinformation;
.3 A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;
.4 An evaluation of the change which shows the predicted releases of radioactive materials in or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
.5 An evaluation of the change which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREAS and to the general population that differ from those previously estimated in the license application and amendments therato; i
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.6' A comparison of the predicted releases of radioactive materials, in solid waste, to the actual releases for the period prior to when the changes are to be made;
.7 An estimate of the exposure to plant operating personnel as a result of the change; and
.8 Documentation of the fact that the change was reviewed and found acceptable by the Site Review Committee.
.2 Shall become effective upon review and acceptance by the SRC.
8.4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT r 8.4.1 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted annually, and the time between submission of the reports must be no longer than 12 months. 8.4.2 The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the ' format of Appendix B thereof. 8.4.3 The Annual Radioactive Effluents Release Reports shall include the following information for each type of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
.1 Container volume
.2 Total curie quantity (specify whether determined by measurement or estimate),
.3 Principal radionuclides (specify whether determined by measurement or estimate),
.4 Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste,
.5 Type of container (e.g., LSA box, HIC, steel liner, 55 gallon drum), and
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.6 Solidification agent (e.g., cement, bitumen, Dow media). ;
8.4.4 The Annual Radioactive Effluent Release Reports shallinclude major changes to radioactive solid waste treatment systems.
9.0 REFERENCES
9.1 LIPA OPERATING PROCEDURES 9.1.1 SP 23X710.01, Low Conductivity Liquid Radweste 9.1.2 SP R3X710.02, Dewatering of Spent Radwaste Media 9.1.3 SP 23X711.01, High Conductivity Liquid Radweste 9.1.4 SP 23X712.01, Regenerant Chemical Liquid Radwaste 9.1.5 SP 23X718.01, Liquid Radwaste Spent Resin 9.1.6 SP R2X713.06, Calculations of Radwaste Curie Content 9.1.7 SP R2X713.24, Sampling, Treatment and Disposal of Radioactive Waste Oil 9.1.8 SP R2X713.30, Radwaste Container Control 9.1.9 SP R2X713.35, Storage of Packaged Radwaste Liners and DAW 9.1.10 SP 72X002.18, Radw::ste Sampling for Disposal t 9.1.11 SP R3X713.02, RADMAN Computer Program 9.1.12 SP R3XO75.01, Sorting, Compaction and Handling of Contaminated Waste , 9.1.13 SP R1X020.01, Liquid Radwaste Process Control 9.1.14 SP R1X001.01, Radwaste Program - Policy and Objectives 9.1.15 SP R1X001.02,10CFR61 Compliance Program 9.1.16 SP S2X001.02, SNPS Decontamination Program 9.1.17 SP S2X002.01, Dilute Chemical Decontamination Equipment Setup, Operation and Demobilization
Page 14'of 53 ( 9.1.18 TP R3X713.04, Setup and Operating Procedure for Dewatering Resins using the RDS-1000 Unit 9.1.19 TP R3X713.05, Setup and Operating Procedure for Dewatering Fdter Media using the RDS-1000 Unit 9.2 MOBlLE SERVICES CONTRACTOR DOCUMENTS 9.2.1 DM-OP-008, Rev. D, " Operating Procedure for the Loading of 24* Pressure Vessels with Resins or Activated Carbon" 9.2.2 DM-OP-015, Rev. D, " Operating Procedure for CNSI Domineralization Systems Employing the Pressure Vessel Skid" 9.2.3 DM-OP-022, Rev. B,
- Process Control Program for the CNSI Demineralization Systems" 9.2.4 DM-OP-028, Rev C, " Operating Procedure for UMO Filter Vessels with Replaceable Filter Cartridges" 9.2.5 FO-OP 022, Rev. E, "Ecodex Precost/ Powder /Solka Floc /
Diatomaceous Earth Dewatering Procedure for CNSI 14-215 or Small Liners" 9.2.6 FO-OP-023, Rev. G, ' Bend Resin / Activated Carbon Dewatering Procedure for CNSI 14-215 or Smaller Liners" 9.2.7 FO-OP-025, Rev. A,
- Dewatering Procedure for CNSI 24-inch Diameter Pressure Vessels" Datew?
9.2.8 SD-OP-003, Rev. U, Pressure Control Program for CNSI Cement Solidification Units" 9.2.9 SD-OP-050, Rev. C, " Operating Procedure for the Mobile Cement Solidification Unit NO. 221 (MSU-C 221)" 9.2.10 SD-OP-051, Rev. A," Assembly and Disassembly Procedure for the Mobil Cement Solidification Unit No. 221 (MSU-C 221)" 9.2.11 FO-OP-032, Rev. H " Setup and Operating Procedure for the RDS-1000 Unit" 9.2.12 FO-OP-032, Rev. E, " Setup and Operating Procedure for Dewatering Pre Coat Media in a 21-300 Liner Using the RDS-1000" 9.2.13 CNSI Proprietary Topical Report RDS 1000 Radiosetive W este Dewaterine System. RDS-25506-01-NP-A, Revision 1, March 1988
Page 15 of 53 9.2.14 DT SH-01, Diversified Technologies Operating Procedure for the Temporary Spent Fuel Pool Domineralizer 9.2.15 . DT-SH-02, Diversified Technologies Operating Procedure for the Portable Radwaste Procesa Skid 9.3 GENERAL REFERENCES 9.3.1 NRC Standard Review Plan 11.4, " Solid Waste Management Systems" (NUREG-0800) 9.3.2 NRC Branch Technical Position ETSB 11-3, " Design Guidance for Solid Weste Management Systems Installed in Ught-Water Cooled Nuclear Power Reactor Plants", July 1981 9.3.3 Code of Federal Reguistions, Title 10, Part 61, "Ucensing Requirements for Land Disposal of Radioactive Waste" 9.3.4 Code of Federal Regulations, Title 49,
- Transportation
- 9.3.5 South Carolina Department of Health and Environmental Control, Radioactive Material License No. 097, as amended.
9.3.6 NRC Special Nuclear Material License No.12-13536-01, as amended, for Barnwell, SC 9.3.7 ANSI /ANS 55.1/1979, American National Standard for Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants. 9.3.8 AIF/NESP-027, Methodologies for Classification of Low-Level Radioactive Wastes form Nuclear Power Plants, impell Corporation, January 1984. 9.3.9 NRC Low-Level Waste Licensing Branch, Final Wasta Classification Technical Position Paper, May 11,1983 9.3.10 RADMAN-Data Base Analysis Report - Shoreham Nuclear Power Station - Weste Management Group, Inc., August,1985 9.3.11 QA Manual , App. K, " Packaging and Transport of Radioactive Material *. 9.3.12 NRC Low-Level Waste Management Branch Technical Position on Waste Form (Revision 1), January,1991. i
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,. I DRuu CoerACTOR l' ucSILE O FILTRATION OR DEMINERALIZATION RA WAST FLOOR DRAIN FILTER R l SHIPrime FILTERS u
JL ' ~ ^' ~ m.m l' 1' WDt!LE SMIPFING 90LIDIFICAtleu 5$ GAL SM P 2NO CONTAINEP DRuW CONTAINERS J L_ B
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/ PROCESS L10U80 RADWASTE
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4- n - i r- +44-Page 18 of 53 Appendix A Page 1 of 3 - SOUDIFICATION RECORD SHEET PARTI Sampling and Pre-Solidification Analysis
- 1. Type of Waste ;
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- 2. Waste tank placed on recirc. !
Date1 Time
- 3. Waste Tank sampled analysis ID#
Date/ Time
- 4. Waste Stream pH 7
- 5. Oil Content _ % by volume ,
e
- 6. Isotopic Analysis Attached Check
- 7. Estimated Curie content (SP R2X713.06) . uci/cc
- 8. Test Solidification Required ,
Yes No
- 9. Acceptable Test Solidification performed (if required) '
Initials
- 10. The above waste tank has been analyzed and is acceptable for solidification.
?
Radiochemistry Engineer Date or designes i
i Page 19 of 53 l t Appendix A Page 2 of 3 sot.fDIFICATION RECORD SHEET PART tl Contractor System Preparation and Processing
- 1. Container ID Number Type
- 2. Applicable conntetions made to liner for transferring waste ad cement to liner initials
- 3. Connections made to liner for mixing contents,if applicable initials .
- 4. Process parameters Waste to be added to liner cf Cement to be added to liner cf Water to be added to liner cf
- 5. Authorization to commence processing Radwaste Supervision Date Time
- 6. Time processing started
- 7. Time processing stopped
- 8. Waste Class Class A Class B Class C
- 9. Container checked for free standing water initials Time /Date
- 10. Liner capped Date Time
- 11. Liner Weight lbs.
8
)
Page 20 of 53 l i Appendix A Page 3 of 3 ) I SOLIDIFICATION RECORD SHEET PART 111 Filled Liner Data
- 1. Filler Liner Radiation Levels
- a. Contact Dose Rate 1 Meter Dose Rate mR/hr mR/hr
- b. Smearable Activity beta-camma alpha 4 Quadrants 1 dpm/100 cm' 1 dpm/100 cm' (Use actual 2 dpm/100 cm' 2 dpm/100 cm8 number) 3 dpm/100 cm8 3 dpm/100 cm 8 4 dpm/100 cmr4 dpm/100 cm'
- c. Liner decon performed Yes/No
- d. Smearable activity after decon (if performed) dpm/100cm'
- e. Liner ready for shipping or transfer to storage Health Physics Supervision Date Time
- 2. Storage Location Radwaste Supervision
i Page 21.of 53 Appendix B Page 1 of 2 DEWATERING RECORD SHEET t RADIOCHEMISTRY ANA1.YSIS SHEET
- 1. Type of Waste
- 2. Waste Tank (or Uner) Sampled Analysis IDF Date/ Time
- 3. pH of Decant
- 4. Oil ;>ntent % by volume
- 5. Isotopic Analysis of filter media and or bead resin attached Check
- 6. The above waste tank / container has been sampled and found to contain the isotopes and properties as indicated on the attached data sheets.
t Radiochemistry Supervision Date
Page 22 of 53 > Appendix 8 : Page 2 of 2 . DEWATERING RECORD SHEET , POST DEWATERfNG SURVEY SHEET
- 1. Container and Type ID#
- 2. Container Radiation Levels
- s. Contact Dose Rate mR/hr 1 Meter Dose Rate mR/hr
- b. Smearable Activity beta-osmma ahltha 4 Quadrants 1 dpm/100 cm' 1 dpm/100 cm 8 '
(Use actual 2 dpm/100 cm' 2 dpm/100 cm' number) 3 dpm/100 cm' 3 dpm/100 cm' 4 dpm/100 cm' 4 dpm/100 cm 8
- c. Container Decon Performed Yes/No l
- d. Smearable activity after washdown/decon dpm/100cm'
- e. Liner ready for shipping or transfer to storage Health Physics Supervision Date Time
- 3. Waste Class A B C initiets
- 4. Storage Location i
Radwaste Supervision l 4 1 J _.-1
. 1 r
Page 23 of 53 l Appendix C Page 1 of 1 DEFINfTIONS The defined terms appeer in capitalized type and shall be applicable throughout these Controls (Appendix D). ACTION 1.1 ACTION shall be that part of a Control which prescribes remedial measures required under designated conditions. DEFUELED MODE 1.2 The plant is in the DEFUELED MODE when all fuel has been removed from the reactor vessel and there is fuel in the spent fuel storage pool or in the new fuel storage vault. FUEL HANDLING OPERATIONS 1.3 FUEL HANDLING OPERATIONS shall be the movement of fuel over or within the Spent Fuel Pool. Suspension of FUEL HANDLING OPERATIONS shall not preclude completion of the movement of fuel to a safe conservative position. OPER ABLE - OPER ABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). PROCESS CONTROL PROGRAM 1.5 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging
~ of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste.
SOLIDIFICATION 1.6 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
Page 24 of 53 Appendix D Page 1 of 4 CONTROLS AND SURVEfLLANCE REQUIREMEM 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the Controf contained in the succesding Controls is required during the DEFUELED MODE specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with e Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 Commencement or continuation of FUEL HANDLING OPERATIONS shall not be made when the conditions for the Control are not met and the associated ACTION requires suspension of FUEL HANDLING OPERATIONS if they are not met within a specified time interval. FUEL HANDLING OPERATIONS may be made in accordance with the ACTION requirements when conformance to them:
- 1. Permits continued FUEL HANDLING OPERATIONS for an unlimited period of time, or
- 2. Permits fuel to be moved to a safe, conservative position.
Page 25 of 53 Appendix D Page 2 of 4 APPLICABILITY SURVEILLANCE 4.0.1 Surveillance Requirements shall be met during the DEFUELED MODE or other APPUCABILITY conditions specified for individual Controls. 4.0.2 Each Surveillance Requirement shall be performed within the specified survel!!ance interval with a maximum allowable extension not to excesd 25 % of the surveillance interval. 4.0.3 Failure to perform a Survei!!ance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. Survei!!ance Requirements do not have to be performed on inoperable equipment. 4.0.4 FUEL HANDLING OPERATIONS shall not occur or continue unless all Surveillance Re quirement(s) associated with the Control have been performed within the applicable surveillance interval. This provision shali not prevent passage through or to conditions as required to comply with ACTION requirements. 1
Page 26 of 53 Appendix D Page 3 of 4 I RADIOACTIVE EFFLUENTS ! 3/4.11.3 SOLID R ADIO ACTIVE WASTE CONTROLS 3.11.3 Radioactive wastes shall be SOLIOlFIEO or dowatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal alte. APPLICABILITY: At all times. , ACTION:
- a. With SOLIO!FICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM,the procedures, and/or the solid wasta system as necessary to prevent recurrence.
- b. With SOLIDIFICATION or dews'tering not performed in accordance with the PROCESS CONTROL PROGRAM, (1) test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and (2) take appropriate administrative action to prevent recurrence.
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at al'sst every 1 tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM.
- a. . If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
i l
l l Page 27 of 53. ! Appendix D - Page 4 of 4 !
- b. If the initial test specimen from a batch ~of waste fails to verify ;
SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the > collection and testing of represent 6tive test specimens from each consecutive - batch of the same type of wet waste until at least three consecutive initial test e specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM I shall be modified as required, as provided in Section 9.2 of the PCP to assure SOLIDIFICATION of subsequent batches of waste.
- c. With the installed equipment incapable of meeting Control 3.11.3 or declared ,
inoperable, restore the equipment to OPERABLE status or provide for contract l capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements. : i t l f n i
Page 28 of 53 Appendix E Page 1 of 1 BASES 3/4.11.3 SOLID RADf 0 ACTIVE WASTE t This Controlimplements the requirements of 10 CFR 50.36a and General Design Criterion 80 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times. i n n 5 0
4
" ~ ~
Page 29 ef 53
.- Appendix F I Page 1 of 25 '
1 FZAN FOR TEE FEASED DScobetISs!CErIBG OF SEB LtgeIs RanenwzE srstuu suomrnax wocLEAR PCerER STATICE xmo ISLAND PouxR AtmsonIrr January 5, 1993 (
.,. .= . . ,,
t Decommissioning cf the Page 30 of 53 i
.- . ' shershan I.iquid maeuxto system Appendix F ' ',
Page 2 of 25 r r r TART.2 0F CONTENTS t ascrIm nascRIrtzcs pass 30. , I zwrmococrzas 3 II srsrax casem2rtscs s III esOONN!ssIDsISC PsAsts 6 IV Post-psoonxzsszonIno ImposrRIAI,WhsTE 15 f wArra srstax , y arrEngscas 16 . VI zz.z.usinArrous n ; e f i-i i e f r O e I i 4 i l' i i 3 O s ~- ,
Page 31 of 53 i Dee m icsioning cf the Shorr. ham Liquid Radwasto System Page 3 of 25
- 1. INTR 00DCRICE i
The Liquid Radwaste System (011) has been identified la the Decommissieming Plan as a contaminated system which will be dismantled and removed. Per LENRC-1859, LTPA Resnonsa 10, a descripties of the phased decommissieaLag of the Lipid Radweste System was provided. In this response, LIPA stated that "a phased shutdown methodology has been developed which minimicos the mood for temporary equipment". LIPh also stated that *1asta11ed plant epigment will be utilised to the maximum artent possible to hold, ree!Jresiste, saeple ' and process liquid radioactive waste water. Temporary filtration satte er domineralisers will caly be used La the event of equipment malfsmettaa er during periods when installed epipseat is soeured for echeduled malatenanos, ! radiological surveys or other such evolutieas". A more-sangrebensive review , of our plane.for decommissieming the liquid radwaste system indiented that l the use of temporary filitraties amits er d==f==ealisere, as system i decommission 1ag activities ,a::f, is most advantageons. &IPh 1stando en using a mobile radwaste filter /demineraliser skid, as a planned evoleties, to i process liquid radwaste during the final stages of system decommissieslag j when certain equipment is secured for removat purposes. In accorda=== with , the Decommissioning order condities # 3, this plan provides a detailed { description for the shutdown, dismantlement, and reuoval of the Liquid i - Radweste System and describes how 11guid radwaste will continue to be . , processed during system decommissieming. l In addition, L8NRC-1859, LIFA.Ramannaa_10, states that *the laundry draia , j subsystem will he decontaminated and prepared for eventual see as an - ! industrial waste processing facility". LIPA has subsequently deter =tand that it would be preferable, from a schedule and most viewpolat, to decommission the Laundry Drain Sub-system. Instead, the Regeneraat Liquid and Evaporater Peed Tank subsystem and possibly other selected radweste components will he + decontaminated, modified, or replaced, to be used as the post-decommissicalag ' l Industrial waste water System. L5NRC-1859, LIPA Response 10 also states that the remaining Phase 3 components will be decommissioned following the draining of the SPSP. These ' coeponents may be decommissioned prior to the draining of the SPSP if the offsite pose calculation Manual (CDCN) is amended to pesimit draiaing of the SFSF to the Salt Water Draia Tank. 1 Indirectly related to the phased decomatosioning of the liquid radwaste system is the potential use of temporary filter /d==t==raliser equipment to : maintain the quality of the water la the Spent Fuel Storage Pool (SPSP). This l will facilitate removal of the Fuel pool Clean Op (641) System La parallel ; with the continued storage of the fuel assemblies la the SPSP sat 11 shipment. { t I 3 I
,. 3 ;
i
.l l
W
i
._.y. . _ . . . .
Decommicciening cf the Page 32 cf 53
. Shoreham Lipid Radw=to system Appendix F ,
Page 4 of 25 t section II provides a description of the tip id Radwaste system as it new . exists and also describes how it is being operated La the surrent plant , condition to collect, process and discharge 11p id redwaste. section III details the phased decosmsissientag activities, describing in seguential ~ order the isolation, diamantlement er decontanimaties, of sub- ; systems and componente. The preregioites to begia the respoetive phases are given, as are the temporary modificatione repired which will keep the systen functional. Additionally, the collection, processing, campling and discharge espabilities after sempletisa of each of the phases is provided. ' l
~ '
section IV provides a descripties of the proposed Industrial Waste Water system which will be stilised to Sollect, held, process, eseple, and discharge waste water after the Terminaties Survey is sempleted. Portimes of ; this new system ~may be placed Late servios prior to 11oense teaminaties to collect and transfer " clean
- water to the radwaste erstem. ,
i P e e [ t t 6
?
I f i h l d . h
~~ ~
es sw a e ~ peramaicsioning at the Pa0e 33 of 53
- shorwham Lipid Radw=to System Appendix F Paes 5 of 25
- 31. SYSTEN DESCRIFTEM 4
In the surrent configurattee, the Lipid Radwaste System saa collect, prosess and discharge radioactive waste water sollected from building fleer and equipment drains. Lipid radwaste is transported from these sollection pointe via the 6" floor drain header (high conductivity)'er the 4" equipment drain header (low sonductivity) to see of three pairs of tanks in the Radwaste Building. These tanks are the Floor Draia collector Tanks (FDCT's) TE-061&/Si the Regenerant Liquid and Svaporator Feed Tanks (REFT's) TE-060&/S; and the I waste collector Tanks (WCT's) TE-010&/S. Each tank has a espasity of 25,000 gallons. Bach of these sollecties tanks has a pair of bees which reciresiste and discharge the liquid to na appropriate sub-system for processiat. The i sub-systems are the Waste (I-043) lad the Regeneramt (B-044) Svaporators, the Floor Draia Filter (FL-012), and the. Radwasta pilters (FL-014&/3) ~S Domineralisers (DE-001h/3). The Svaporater sub-system to not used. Omtrestly, the sollected liquid radwaste is saly processed through the filter .sub-systems. After processing,~ the liquid radwaste 'to then east to ese of tue ! pairs of discharge and holding taaks. These tanks are the Discharge Waste sample Tanks (DNST's) TE-06SA/S and the. Recovery Sample Tanks (RST's) TR-069A/8. Each of these tanks has a capacity of 25,000 galleas. Each tank has : its own pump which re-circulates and than discharges the sampled liquid to . the condensate storage Tank (cst), circulating Water Discharge Tunnel, er - l back to one of the sub-systems for further processing. , Normal system alignment routes the floor desta' effluent to see of the tuo, FDCT's. The equipment draia effluent is normally routed to ese of the tuo . .. WCT's. The third pair of liquid radwaste collection. tanks are the REFT's. * ] These tanks collect high conductivity chemical liquid waste resulting from 1 the regeneration of the condensate dominera11sers which are new shut down and i designated for removal. These tanks have acid and caustic Lajection lines which permit the neutralisation of the collected liquid radweste. Additionally, the high conductivity liquid waste from the 6" fleer drais , discharge header may be diverted to the REFT's should neutralisation he required. Depending upon certain conditions, the liquid waste is processed through the -; i Floor Drain Filter or the Radwaste Filters & Domineralisers. Processed water is then transferred to the DWST's er the RST's where it is recireulated,. > sampled and discharged to the circulating water Discharge Tunnel or recycled back to the CST. During the discharge process, the radioactivity level is ' monitored by an existing radiation element (1D11-R3-013). A high radiaties t level or a loss of power at the sampling panel (FEL-013) will alars and slese the waste discharge valve (ADV-150).
-l i
5 e
' Plan f:r The Phased - Page 34 of 53 Demmicsioning cf the shor: ham Liquid madwste system gg p Page 6 of 25 III. nsecnottssrostas ramass
( . The following describes the major seepenests and sub-systems of the Liquid Radwaste system skish will be either removed or deoentaminated. Esisting equipseat a portions of piping systems may be decontaminated and re-seed as combinaties with new piping s sempenests for eartala temporary modifiestions. '] It aise describes the prerequisites required to begia the sospoetive phases ; et deceamissiemias, temporary modiftsatsens required to hoop the remalaing ! portions of the system faaetiamal, and a descriyttom of the ramalaing ersten j espabilities after semplottom of ensk of.the phaeos. j l A. Phase I
- 1. Deecercissionine /Di==ntline activit t aa j
- s. Isolate and decontaminata Phase separator Tanks TK-107 Aas, !
remove all associated piping and compeaants.
- b. Isolate Reaporater sub-eystem. Decontaminate evaporators, remove all associated piping and oosponents up to active j system interfaces. ,
- c. Laundry Drain Tanks TK-020 &&s; pumps, piping and , :
coeponents will be isolated and removed back up to all ' i interfaces with active portiene of the erstem. This also includes the removal of the ratwaste washer red dryer.
- d. Radwaste solidification system (P63); isolated only, this l system is not designated as oc staminated, and will not be ;
removed.
- 2. Prerecuisitas
- a. 30 influent into Laundry Drains sub-tystem.
- 3. Tarecrarv Modificatiana
- a. Beme. .
- 4. tiould Radwasta Processine Canabilities '
- s. With exception of the Laundry Draias sub-eystem, full l system process espabilities remain as described in secties I
21. f i i l c \ 4
'~ ~ ~
, De:emaic[io M Cf the Page 35 of 53
. shoreham Lipid RadwW System Appendix F Page 7 of 25 .
D. Phase IIA - (. '
- 1. Decommissionina/Dimmantline Activitima ,
The following op ipment will be decontaminated or removed ;
- s. Turbine Duilding' Floor Drain sump TK-053A, along with its.
associated pumps, piping and components up to eennection to ~ ! the 4* floor draia discharge header. i
- b. Turbine Duilding ' Floor Drain sump TK-0533, along with all :
incoming floor _drata lines, pumps, piping and componente up ! to the interface with d* .11ae at the ' discharge from the Deoon Area Drain Sump TK-012. Dete: Turbine Duilding sump i Pumps and associated portions of discharge piping for TE- l 053 Ass'will be'decontamtmated, if possible, and retained for future see.
- c. Decon. Area Drain sump TK-013, along with ' all Laseming floor draia lines, pumps, piping and components up to the :
interface with 4* floor draia discharge header. !
- d. Raposed floor draia piping in Turbine Duilding
- e. Drywell spipment Drain Tank TK-049, pumps, ecolor, all piping _ and componente up to the d' op ipment drata ', l discharge header i
- f. Reactor Building Equipment Drain suspe TK-050 Ass, along with all incoming lines, pumps, piping and components up to l the 4* equipment drain discharge. header.
~
- g. Esactor Building Floor Drain Sump TK-056C along with all .
incoming floor drains, pumps, piping and components up to the 6* floor draia discharge header.
- h. Recovery sample Tank TK-069st pumps, piping and components l will be isolated and removed up to. active portions of the !
eystem. t
- 1. Radweste Dominera11aer D3-0013, along with all associated' i piping and components up to interfeoes with active portions i of the system.
l i
- j. _ Discharge Waste sample Tank TK-0643; pumps, piping and -
components will be isolated and removed up to. active. portions of the system. ,
- k. Floor Draia collector Tanks TK-061 Ass, pumps, Lafluent and offluent ' piping and componente up to the common system connections to the Floor Drain Filter, Radwaste Filters a Domineralisers, and the svaporator sub-system. '
1 7 I
, - - m ., - -e. - - . - , v \ , - , . - r _ _ ,
secamascotontag cr
- Page 36 of 53
. Chercham Liquid Radwzete System Appendix F Page 8 of 25
- 1. 6" floor draia discharge header from ADV-245 (located la Reacter Building) to FE-397 (located la Radwaste Building) will he isolated and decentaminated for post- ,
decommiseloning servies. Note: This header may have to be j
' partially removed to provide access for deoontaminaties and ;
ourvey activities. If it to demonstrated that this header : cannot he deoentaminated in 'a timely manner, it will he ' removed and replacement p,iping lasta11ed as needed. , Notes Turbine Building Floor Draia Sump TK453h will he returned to service during this phase of decommissioning as a *elsaa* emb- ! erstem. Discharge wilt he routed to the Radwaste Squipment Brain i sump TK-071 er the Asid & Cauette Waste Suey (1721-TE-110) .via e' l Temporary Modificaties (qN). This gu will remaia la effect until ' i the 6' floor drata header has been desentaminated er replaced. '
=
- 2. Prerepuisitam
- a. Mechanical decontamination (hydrolastag) and radiologiest. I survey of embedded piping is complete for Turbine Building :
Floor Drain sumps TK-053 A&R and Reactor. Building Fleer Drain sump TK-056c.
- b. Mechanical leolaties of Low conductivity Draia (P71) System ,
sumps TK-186 A&B pump discharge piping eennections to d' [ equipment draia discharge header ocuplete (for item 1.1 '
, above).
- c. No radioactive influent from the Chem. Lab (for item 1.c..- i above) Notes Liquid drains from the saisting them. Lab are [
directed to Decon Area Drain Suey TK-012. The entire Chem. ~ Lab may he relocated or a separate
- hot
- 1ab set up La a -
different location to prevent the continued flew of ; radwaste to Decon. sump TK-012. This sould allow the " cold * ! lab to remaia la the existing locaties with a new draia line installed to direct *elean* liquid discharge to the Turbine Building Floor Drain susp TK-053&.
- d. ,,,ro,ri.te ratio .re du,s. r. vie.d to incorpo, ate ;
.hanges to . 1 q
I ( 5 3 i
.' i l
1
~
plan f:r The Phased P;ge 37 of 53
'Decommicsionias cf the ._ Shoreham Lipid Radw:sta system Appendix F Page 9 of 25 1
- 3. Temnerary Modificatiman
- a. Install eress-tie to direct Radweste Building Fleer Draia Sump TK-054 discharge to the Radwaste Building Equipment Brain Sump TK-071.
- h. Zastall pump discharge piping from Turbine Building' Floor Drain Sump TK-053A te- Radwaste Building Equipment Drain Sump TK-071 or the Acid a caustic Waste suse (1P21-TK-118). ;
(after sempletion of item 2.a above)..
- e. Install temporh draia lines from the Chem. Eeb and '
station air sempressors to Terbias Building Floor train Sump TE-053&.
- d. Install temporary line from d' radwaste equipment drain discharge' header to Regenerant Liquid and Braporater Feed ,
Tank TK-060s. A manual isolation valve will be Lastalled in lieu of valve ADF-384.
- 4. Linuid Radwasta Processing canabilitian With deecemaissioning of the Floor Drain Collector Tanks TK-061 ,
Ass' and the 6' floor draia discharte header, all liquid unste : collected in the Reactor Building, Turbine Building, and the " Radwaste Building sumps will be transferred to the Waste Collector Tanks TK-010 A&S or the Regenerative Evaporative Food. l Tanks TK-060 A&R via the 4" equipment drain discharge header. l This waste will be processed in the normal manner utilising the j Floor Drain Filter FL-012, the Radwaste Filters FL-014 &&B and the remaining Radwaste Domineraliser DR-001A._ Processed liquid will be sampled and discharged stilising the remaining Discharge Waste sample Tank TK-06&A and the Recovery Sample Tank TR-069A. j C. Phase 115
- 2. peccanissionina/Diamantline Activitian The following equipment will be dooontaminated er removed
- a. Reactor Building Floor Drain Suey TK-0563, along with all !
incoming floor drain lines, pumps, piping and componente up : to the floor drata discharge header.
- b. . Regenerant Liquid and Evaporator Feed Tanks TK-060 A&B, l along with their associated pumps, piping and eesponente up ta' interfaces with active portions of the system.- ;
- c. Waste collector Tank TK-0108, along with its associated l pumps, piping and componente up to interfaces with active portions of the system.
9
!i e
, s-
i Flan Err The Phased
,Decommiteirning cf the Page 38 cf 53
- Shoreham Liquid Radwaste system Appendix F i Pa0s 10 of 25 l k
- d. Discharge Waste Sample Tank TK-066&, along . with its associated pump, piping and components up to active portions of the system.
- e. Radweste Filter FL-0143, along with all associated valves, piping and components up to interfaces with active partless of the system. ,-
- f. Floor Drain Filter FL-012, along with all associated valves, piping and components up to interfaces with active portions of the eystem. .
- 3. Prereculaites
- a. Mechanical decontamination (hydrolasing) and radiological eurvey of all embedded piping is complete for maaster Building Floor Drain sung TK-OS$3.
- b. Radwaste system Lafluent has decreased to an acceptable ,
level for processlag at a reduced espacity.
- c. Appropriate Operations Procedures revised to incorporate changes to system. ,
- 3. Townerary Modificattena
. I
- a. Contingent - Connect the acid and caustic neutralising ;
lines which are currently connected to the REFT's to the Waste Collector Tank TK-010A via a Temporary Modification. l This will provide direct neutralisation capability of the Waste Collertor Tank TK-0101. J
- 4. Licruid Radwante Processina e.auhilittaa After completion of this phase, liquid radwaste sollected by the remaining operattag sumps will be sent to Waste collector Tank TK-010A and processed through Radweste Filter FL-014A and .
Domineraliser DE-001A. The processed water will be sampled and ! discharged utilising the Recovery Sample Tank : TK-069A and-l existing flowpaths. After completica of this phase, the i Regenerant Liquid and Evaporator Food Tanks TK-060 A&E will he l decontaminated and the pumps, piping, and components replaced for Ll future collection and processing of '*elean" industrial waste l water. 10 I I
^
Flan f r The phased Page 39 of 53 Derommiecioning ci the . . shoreham Liquid Radw:ste Sy: tem Appendix F Page 11 of 25
- 3. Phase IIC
- 2. Deconuri s a [onine /Di ==a nt i lne activit tem The following equipment will he decontaminated er removed ,
- s. Reactor Building Floor Drain suey TK-05&h, along with all incoming floor drata lines, pumps, piping and components up_
- to the floor draia discharge header.
~
- h. Drywell Floor Drain Tank TE-057, along with its associated pumpe, piping and sosponente . up to the steer drata discharge header.
- c. Radwaste Filter FL-0144, along with all assoaisted piping and components.
- d. Radwaste Dominera11ser DB-0011, along with all associated '
piping and componente.
- e. spent Resin Tank TK-062, along with associated piping, valves and components up to other system interfaces.
- 2. Prerecuisites
- a. Mechanical decontamination (hydrolasing) and radiological surysy of influent piping (embedded drains, downcomers, etc.) is complete for Reactor puilding Floor Drain sump TR-0561.
- b. No liquid radwaste from Reactor Duilding or Turbine Building (i.e. Termination Survey complete in all areas).
i
- c. Esisting Fuel Pool Clean WP (841) System Damtnatalisers l empty.
- d. Appropriate Operations procedures revised to incorporate changes to system.
f I 9
.mmme 11
e
- - - ... e wa -
. shorcham Lipid madwa::ta system hfo of53 ;
- Appendix F- ;
Page 12 of 25 i j Notes. To facilitate the decommissioning of the Fuel pool clean Up (641) system, temporary filter /demineraliser epigment may , be wood to elean the water la the spent Puol Storage Pool l
,(arsF) until the nuclear fuel la removed. i
- e. Enc approval roosived . for see of mobile radweste- i desinoraliser/ filter opipment. Mobile epigment will meet repirements of Reg. Guide 1.143. Esisting lipid redweste '
system process connections specifically designed for
&asta11ation of a mobile filter /demineraliser will be mood. !
& change ' to the process control program (pcP) any be .i repired to add vendor operettag -maanal if other thaa ,
surrently refessmood. : h j
- 3. Temnorary Modificatiana
- s. Insta11stice or mobile Radweste Filter /Demineraliser {
*Wipment. ;
- b. contingent - Install temporary submersible pump (e) La !
decontaminated Reactor Building Floor Drain Sumpe. ; Notes If Reactor Building Floor Drain Sump TK-056c new discharge piping .; installation has been eompleted for ' clean" servios, this cump* , may be returned to servios during this phase of decommissieslag. - It will temporarily discharge into the 4* - epigment ~ drain i discharge header until the 6' floor drain discharge header is - . l ready for service.
- 4. Litruid Radwaste Processino canabllittaa l
After completion of this . phase, . lipid waste water will be ' collected by the operating sumpe and directed - to the Waste .{ collector Tank TK-010A via the 4" epigment draia discharge j header. With both Radwaste Filters and Domineralisers ; decommissioned, a mobile filter /demineraliser will be used to : procese collected lipid radwaste. The mobile epipment will be !
~
connected to existing system prece'es connections desigeod specifically for this purpose. The mobile filter /demineraliser - will discharge the processed lipid.to mesevery sample Tank TK-069A for sampling and discharge. s
-l l
i 12 l t i l l
. - _ . - _ _ _ _ . . _ _ _ . . . ~ . - -, _ . . ... , . , , ,
~
Decomuni::sioning cf the - .PB9e 41'of 53
. IShoreham Lipid Radw:ste System Appendix F ;
Page 13 of 25 l
+
[\ 5. Phase 113
- 1. De e enre i s s i on i ne /D i ama nt l i ne Ret ivit ion i The following ep ipment will he deoostaminated or removed: !
pote: .The Recovery sample Tank TE-069& and the mobile Radweste f Filter /Demineraliser, skid will be the last componente , removed in this phase of work; this will enable processing and discharge of water sollected bymeans other than design i flowpaths (e.g. _wot vacuums, temporary pumpe, etc.)
- s. complete removal of 4* epipment drata diesberge header.
- h. Radwaste Building spigment Draia sump WK-071, along with all incoming floor drains, pumps, piping and - n- - a a up.
~
i to interfaces with the remaimias portions of the system. ,
- c. Radwaste Building plear Drain Sump TE-054, along with all incoming floor drains, pumps, piping and esoponente up to interfaces with the remaining portions of the system.
- d. Waste collector Tank TE-0104, along with all pumps, piping and components up to interfaces with active portions of the . ,
system. . ,
- e. Recovery sample Tank TK-069A, along 'with all remainlag ,
pumps, piping and. oomponents op to interfaces with the Domineralised Water (F11) System immediately before entering the discharge tunnel.
- f. All remaining piping and components will he removed er -
decontaminated la place la preparation for the operational and termination surveys of the madwaste Building.
- 2. Frereculaites
- a. Mechanical decontamination (hydrolasing) and radiological ,
survey of all embedded drata piping is complete for. ' Radwaste su11 ding Drain sumps TE-054 a TE 471.
- b. No lipid radwaste belag discharged into Radwaste Building ,
Drain sumps TE-054 & TE-071. i 13 , a
. . . + - . - . - - . - - - , , -
. . ~ . _. . - .- - .
~ ~
-ENamisaiEingofthe Page 42 of 53 !
-
- Sniercham Lipid Radvisto System Appendix F Page 14 of 25
- e. All suelear feel has been removed from the Spent puel Storage pool (SF8F). The SFSF has been drained prior to removal of the d' op ipment draia discharge header. This prerequisite may not be required it the offeite Does calculation Waaval (cDcat) is amended to permit draining of ,
the SF8F to the Roseter Building Salt Water Drain Tank TK-190. ,
- d. Appropriate operatione procedures revised to Ameerparate shanges to system
- 3. Tearmorary blodificatiana
- s. Woes.- ,
- d. Lieuld Radwante Freessefne Emmabilittan l With decontamination activities (hydrolasing) completodi there ,
should be no liquid radioactive waste streams. After the Redwasta Suilding Floor Drain and Equipent Drain Sumps TK-054 & TK-071 have been pumped down to vaste collector Tank TK-010&, this water may be processed and discharged utilising the mobile j filter /demineraliser equipent and the saisting eseple and ' discharge flowpaths from the Recovery Sample Tank TK-049A. During - this final phase of decommissioning, Waste collector Tank TK-010A will be decommissioned .-first leaving the mobile filter /demineraliser equipment and the Recovery Sample Tank TK-069A for processing, sampling and discharging any-lip ids which may result from decontamination of Waste collector Tank TK-010&. l i These liquids may be collected from portable pumps or " wet vaes", and pumped directly to the Recovery Sample Tank TK-049A -for : process, sample and discharge. The normal discharge flowpath from the Recovery Smsple Tank TK-069A to the circulating Water Discharge Tunnel will remain intact with all required semponente such as radiation element 1D11-28-013 and- 40V-154 fully functional (see Sectica II for, descriptima of discharge : flowpath). Upon process and discharge of this last batch of water, the remaining parts of the system will be dismantled and -! removed. The mobile Radwaste Filter /Demineraliser equipment will be broken down and shipped back to the supplier for disposal. ; i 4 l 14
_ -. ~ . Plan f2r The Phased- De d 53
. Ds:comissientag af the
. Shoreham Liquid Radwaste System Appendix F.
Pope 15 of 25 IV. Phase III - Post Deceanissioning Industrial Waste Water Systas {s A. Phase III sempletes the lasta11ation and testing of the Industrial
~ Waste Water System. Phase III does set involve any actual decommissioning setivities. This work has been identified as a Phase of the Radweste Decommission 1ag Plan for the purpose of maintaining '
oontinuity of the overall project simos this phase of work must be - ooordinated with decommissienlag activities. . f I note: Termination ' surveys shall- he satisfactorily ocepleted for all systems and structures in arsae where liquid waste selleetten fleer drains are returned to seresse. . . The Industrial Waste Water System will be partially septemented via a series of Temporary Modifications as the phased deocamissioning of the Liquid Radwaste System progresses. New floor drais piping 4 semponente, , sump pumps - and discharge piping a components, and other piping a components associated with the sollection and discharge tanks will be installed. The collection and discharge tanks are the decontaminated Regenerant Liquid and Evaporator Food Tanks TK-060 &&B. Final tie-las, faitial eheck-out, and operational tests will' he completed prior to placing the entire Industrial Waste Water System La service. 4 l
\
l i 15 . 6
?
1 raan cor roe rasses ~ ~~~ Decommic:Loning Et the O'
.- 'sikireham Livoid madw:ste systes Appendix F Page 16 of 25 i g
- v. marsamecas l l
- 1. usume letter dated June 11, 1992 to L.M. sill from s.u. arewar i subjects Order Approving the Decommissioning Plan and Authorialmg l Decommissioning of the shorshna Ruclear Power staties, Smit 1.
- 2. Iong Island Power Authority (s. 311mberg) letter LSNRO-1859 dated November 27,1571 46 8' 8. Nuclear Regulatory commissies,(Document control Desk); subjects Additional Raformation la support of the Decommissioning Plan for shoreham. .
- 3. Offsite Dose Calculatjan Mamual (CDCM)
- 4. Process control Fregram (PCF) ,
B. Flow Diagrams, Mrst-17 (A-F)
- 5. Flow Diagrams, NFSK-46 (A-D)
- 7. Regulatory Suide 1.143 o
9 8 e a m P en 16 h
~ , , - _.
PaE' 45 53
- S* emamiccioning et the .. Shor: ham Lipid Radwncto System Appendix F Page 17 of 25
. VI. ILLusraArIass ,
- 2. Figure 1 - Raisting Lipid Radwasta System - 311
- 2. Figurs 3 - Lipid Radwaste System Mter completten of Phase 1
- 3. Figure 3 - Lipid Radwaste System Mter completion of Phase IIA
- 4. Figure 4 = Lipid Radwaste System After Completion of Phase IES
- 5. Figure 5 - Lipid Radwaste System After Onepleties of Phase 210
- s. Pieure s - Proposed Nethed of Dewaterlag Spest Fuel storage Pool - Utilising Esisting Discharge Flowpath-
- 7. Figure 7 - Alternate Nethed of Dewatering Spent Fuel Sterego Pool . (repires shaage to Opet)
- 8. Figure S - Proposed Industrial Waste Water System configuratien !
+
+
4 m 11 9
'
- Page 46 of 53 Appendix F Page 18 of 25 i
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DCN No. 93X024 w.nd DOCUMENT CHANGE NOTICE ; Poww Sheet 1 of 1 i SHOREHAM ODCM REV.1 (2) DCR No. 93XO39 (1) AFFECTED DOCUMENT (s): (3) DESCRIPTION OF CHANGE: (4) EFFECTIVE DATE: /[/f9//
- 1) Page 1.3-46, Para. 3.12.2, Line 2: [ .y,,mn ,y, y g ge
~
Delete phrase "the nearest milk animal,"
- 2) Page 1.3-46, Para. 3.12.2, Line 6:
Delete phrase "all milk animals and".
- 3) Page 1.3-46, Para. 4.12.2, Line 2:
Replace '12' with '24'.
- 4) Page 1.3-46, Para. 4.12.2, Line 5:
Replace " pursuant to control 6.8.1.4" with "for the year in which such census was taken, pursuant to control 6.8.1.3".
- 5) Page 1.6-2, Para. 6.8.1.3, Line 9:
Insert phrase ", when conducted within the year, as" between ' censuses' and ' required'. CONTROLLED
\
DliC 2 91993 _, { 1 _a. (7) APPROVAL (s) (5) ORIGINATOR pATE: Ap QATE: h lli 2 Q3 S E T)l O al y IIlz4lf1 (6) REVIEW ) DATE: NED A AGE DATE:
.. % I/W41 //hi!.D ,
E OMD MANAGER DATE: DD MANAGER ATE: . SRC CHAIRMAN DATE:
/z f b 0.E./V.P. (r
\\ l i
DATE: sos 4x -v
l l l 1
~
y }}j '" " ' Document No. X417002
% :1")lg
=
w.m aur,,
. eJ4 s Effective Date 9/1/93 Rev. 1 Prepared By Date Reviewed By Date
#7 39D 1., . Les CONTROL copy APPROVALS
- s. 159 Title / Dept. Opgnature .
Date NUCLEAR ANALYSIS SECTION HEAD [ pdb [L , .y 6/Y/f3 NUCLEAR ENGINEERING DIVISION MANAGER hfaw,! ,4(t (,/qf 93 [/sy/ SRC CHAIRMAN , f,- , , 3.{ TITLE OF DOCUMENT OFFSITE DOSE CALCULATION MANUAL (ODCM) CONTROLLED AUG 3 l 1993 N011XB
l l l LONG ISLAND POWER AUTHORITY OFFSITE DOSE CALCULATION MANUAL i EFFECTIVE DATE - 9/1/93 4 I i t I LIPA Revision 1 - February 1993
l l OFFSITE DOSE CALCULATION MANUAL LIPA Revision 1 - February 1993 1 - Insertion Instructions Revision 18 of LILCO's Shoreham ODCM became Revision O of LIPA's Shoreham ODCM upon license transfer, via the issue of a LIPA Procedure incorporation Notice to the document on ' March 8,1992. Upon that day all pages became LIPA Revision O. However, to keep from' ' losing the historical perspective of the LILCO Revision numbers at the bottom of each page,
- no change was made to pages which did not otherwise change.
For this revision of LIPA's Shoreham ODCM, pages which change shall be noted as 'LIPA Revision 1 - Feb.1993' to clearly identify the revised pages and to avoid any confusion with ; LILCO Revision 1 pages which may still remain.
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OFFSITE DOSE CALCULATION MANUAL l List of Effective Paaes : I Page, Table (T), Revision ; or Fioure (F) Number EP-1 LIPA Rev.1 EP-2 LIPA Rev.1 , EP-3 LIPA Rev.1 i thru ii 16 LIPA Rev.1 iii thru viii l.1-0 17 1,2-0 16 l 1.21 thru l.2.3 .18 ; 1.2-4 LIPA Rev.1 1.2-5 18 1.2-6 17 , 1.2-7 thru 1.2-8 18 l 1.3-0 16 l 1.3-1 17 l.3-2 16 l.3-3 thru 1.3-4 18 1.3 5 thru 1.3-8 LIPA Rev.1 1.3-9 16 1.3-10 LIPA Rev.1 1.3-11 thru l.3-15 17 l 1.3-16 LIPA Rev.1 1.3-17 16 1.3 18 LIPA Rev.1 , l.3-19 and 1.3-20 18 1.3-21 16 1.3-22 thru 1.3-23 17 f.3-24 16 1.3-25 LIPA Rev.1 , 1.3-26 and 1.3-27 18 , 1.3-28 and 1.3-29 17 1.3-30 16 'l 1.3-31 thru l.3 33 17 ; 1.3-34 18 1.3 35 and 1.3 36 LIPA Rev.1 ; 1.3-37 thru 1.3-39 17 ; 1.3-40 LIPA Rev.1 1.3-41 thru 1.3-43 17 ; i.3-44 thru l.3-47 LIPA Rev.1 l 1.4-0 and 1.4-1 16 j l.4-2 17 j i
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EP-1 LIPA Revision 1 - February 1993 , I
, OFFSITE DOSE CALCULATION MANUAL ! List of Effective Paaes (Cont'd.) Page, Table (T), Revision or Fioute (F) Number 1.4-3 thru 1.4 5 16 1.4-6 thru 1.4-8 17 , 1.4-9 16 l 1.5-0 thru 1.5-1 16 ! 1.5-2 and 1.5-3 LIPA Rev.1 1.5-4 16 1.6-0 16 1.6-1 thru 1.6-4 LIPA Rev.1 l1.1 1 LIPA Rev.1
- 11. 2 . 1 - 1 LIPA Rev.1
- 11. 2 . 1 2 17 11.2.1-3 thru 11.2.1-7 LIPA Rev.1 ,
F2.1 - 1 14 F2.1 -2 LIPA Rev.1
- 11. 2 . 2 - 1 17 II.2.2-2 thru 11.2.2-4 LIPA Rev.1 T2.2-1, pp.1/2 thru 2/2 10 F.2.2-1 3 F.2.2-2 1 F.2.2 3 thru F.2.2 6 17 Deleted
!!.3.0-1 1.lPA Rev.1
- 11. 3 . 1 - 1 LIPA Rev.1 11.3.1-2 thru 11.3.1-6 LIPA Rev.1 T.3.1-1 3 T.3.1-2, pp.1/3 thru 3/3 3 T.3.1-3, pp.1/3 thru 3/3 LIPA Rev.1 !
F.3.1 1 thru F.3.1-7 A LIPA Rev.1 F.3.1-2 17 Deleted ,
!!.3.2-1 LIPA Rev.1 F.3.2-1 14 Deleted
- 11. 3 . 3 1 16 11.3.3-2 thru 11.3.3-4 3 11.3.3-5 thru 11.3.3-8 17 F.3.3-1 17
- 11. 3 . 4 - 1 16
- 11. 3 . 4 - 2 3 11.3.4-3 thru 11.3.4-5 17 '
T.3.4-1 1
- 11. 3 . 5 - 1 17 11.3.5-2 10 11.3.5-3 thru 11.3.5-6 3
- 11. 3 . 5 - 7 13 :
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OFFSITE DOSE CALCULATION MANUAL List of Effective Paaes (Cont'd.) Page, Table (T), Revision : or Fiaure (F) Number
- 11. 3 . 5 - 8 10 ,
11.3.5-9 thru ll.3.5-10 13 ' II.3.511 thru 11.3.5-13 17 T.3.5-1, p.1/3 10 ; T.3.5-1, pp. 2/3 thru 3/3 1 T.3.5-2, pp.1/3 thru 3/3 1 T.3.5-3, pp.1/3 thru 3/3 1 T.3.5 4, pp.1/3 thru 3/3 1 T.3.5-5, pp.1/2 thru 2/2 3
- T.3.5-6, p.1/1 1 T.3.5-7, p.1/1 1 T.3.5-8, p.1/1 15 T.3.5 9, pp.1/3 thru 3/3 3 T.3.5-10, pp.1/3 thru 3/3 3 T.3.5-11, pp.1/3 thru 3/3 3 T 3.512, pp.1/3 thru 3/3 3 T 3.5-13, pp.1/3 thru 3/3 3 T.3.5-14, pp.1/3 thru 3/3 3 T.3.5-15, p.1/1 15 T.3.5-16, p.1/1 3 T.3.5-17, p.1/1 14 II.3.6-1 17 F.3.6-1 17 Deleted
- 11. 3 . 7 - 1 13
- 11. 4 - 1 LtPA Rev.1 ;
ll.4 2 13 II.4-3 4 T.41, pp.1/2 thru 2/2 17 T.4-2, pp.1/1 18
- 11. 5 - 1 17
' T.5-1, ( Rev. O thru 16 Deleted ) 17 T 5-2 thru T.5-5 renumbered as T.5-1 thru T.5-4 17 F.5-1 thru F.5-2 17 11.6-1 3 A-1 15 B-1 3 :
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l EP-3 LIPA Revision 1 - February 1993
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$NPS-1 DDCM 1 i PLEASE NOTE' ;
Revision 1 - August 1983 of the LILC0, $NPS-1 Offsite Dose Calculation Manual has been totally revised from the Original - March 1983 Submittal - , Therefore. Revision 1 - August 1983 has_ no change _ bars. CHANGE BARS have been used in subsequent revisions to locate a change (additions, deletions and ; cations)inengineering, design,sethodology,/ormodifi-- etc. CHANGE BARS are not used for Errata (i.e., typos, forinat changes). CHANGE BARS are not used in Part i Revision 16 since' this r.aterial is entirely new to the ODCM. They are also not used to indicate changed page numbers in Part !! Revision 16- : since all page numbers have had a !!. appended to them. : In addition, Part Il changes are not labelled Revision 16 at the page bottom if the only change is a page number ' appendage. b DO NOT REP.0VE - KEEP IN YOUR ODCM t i i Revision 16_- July 1990 BN1-116DO.02-92 i t i
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SNPS-1 ODCM PART I THE RAD 1OLOGICAL EFFLUENT CONTROLS (REC) . TABLE OF CONTENTS ODCM REC SECTION SUBJECT PAGE SECTION 1
- INTRODUCTION I.1-0 2 1.0 DEFINITIONS 1.2-0 3 3.0 and 4.0 CONTROLS AND SUREVEILt.ANCE I.3-0 REQUIREMENTS 4 3.0 and 4.0 BASES BASES FOR SECTIONS 3.0 and 4.0 1.4-0 5 5.0
- DESIGN FEATURES I.5-0 6 6.0 ADM]NISTRATIVE CONTROLS I.6-0 I
i EN1-1160D.02-92 11 Revision 16 - July 1990
I SNPS-1 ODCM , 4 PARTll CALCULATIONAL METHODOLOGY AND PARAMETERS FOR COMPLIANCE WITH THE RADIOLOGICAL EFFLUENT CONTROLS TABLE OF CONTENTS Radiological Effluent Controls , Section . Subiect Section EfLqa
- 11. 1 - 1 1 INTRODUCTION 2 SET POINTS 11.2.1-1 2.1 LIQUlO EFFLUENT MONITOR SET POINTS 3.11.1.1 11. 2 . 1 - 1 2.1.1 Radiation Effluent Monitor (RE-13) High/ Trip Alarm Set Point for Discharge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping Drain Sump 11. 2 . 1 - 4 2.1.2 Radiation Effluent Monitor (RE-79) High Alarm Set Point for Reactor Building Salt Water Drain -
Tank 11. 2 . 1 6 i 2.1.3 No Longer in Use l1.2.1 7 l 2.2 GASEOUS EFFLUENT MONITOR SET POINTS 3.11.2.1 11. 2 . 2 1 2.2.1 Gaseous Effluent Monitor High Alarm Set Point ; for Station Ventilation Exhaust Monitor (RE-42) 11. 2 . 2 - 2 2.2.1.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Total Body Dose Rate 11.2.2 2 2.2.1.2 Gaseous Effluent Monitor High Alarm Set Point j for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate 11. 2 . 2 - 3 I; 4 BN1-11600.02-92 iii LIPA Revision 1 - February 1993 l
SNPS-1 ODCM TABLE OF CONTENTS (CONT'D) Radiological Effluent Controls Section Subieet Section EADA 3 DOSE CALCULATION METHODS 11. 3 . 0 - 1 3.1 LlOUID EFFLUENT, DOSE CALCULATION 3.11.1.2 11. 3 . 1 - 1 3.1.1 Method 1: (Computerized Method) 11. 3 . 1 - 1 3.1.2 Method 2: (Backup Method) 11.3.1-5 3.2 OPERATION OF LIQUID WASTE TREATMENT 3.11.1.3 11. 3 . 2 - 1 , SUBSYSTEMS 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS 11. 3 . 3 - 1 3.3.1 Method 1: (Computerized Method) 11.3.3-1 3.3.1.1 Release Rate Estimation 3.11.2.1 II.3.3-1 3.3.1.2 Total Body Dose Rate 3.11.2.1 11.3.3 2 3.3.1.3 Skin Dose Rate 3.11.2.1 l1.3.3-2 3.3.1.4 Organ Dose Rate (1-131,1-133, Tritium and Particulate Releases) 3.11.2.1 11. 3 . 3 - 4 3.3.2 Method 2: (Backup Method) II.3.3-5 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.1 11. 3 . 3 - 5 3.3.2.2 Noble Gas Skin Dose Rate 3.11.2.1 11. 3 . 3 - 6 3.3.2.3 Organ Dose Rate (Particulate Releases) 3.11.2.1 11. 3 . 3 - 7 3.4 GASEOUS EFFLUENTS NOBLE GAS AIR DOSE 3.11.2.2 11.3.4-1 3.4.1 Method 1: (Computerized Method) 11. 3 . 4 - 1 3.4.1.1 Release Estimation 3.11.2.2 11. 3 . 4 - 1 3.4.1.2 Noble Gas Gamma Air Dose 3.11.2.2 11. 3 . 4 - 2 3.4.1.3 Notle Gas Beta Air Dose 3.11.2.2 11. 3 . 4 - 2 3.4.2 Method 2: (Backup Method) 11. 3 . 4 - 3 3.4.2.1 Noble Gas Gamma Air Dose 3.11.2.2 11. 3 . 4 - 3 3.4.2.2 Noble Gas Beta Air Dose 3.11.2.2 11. 3 . 4 - 4 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RADIOACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES WITHHALF-LIVES GREATER THAN 8 DAYS 3.11.2.3 11. 3 . 5 - 1 3.5.1 Method 1: (Computerized Method) 11.3.5-1 3.5.1.1 Release Estimation 3.11.2.3 11. 3 . 5 - 1 3.5.1.2 Total Body Dose 3.11.2.3 11. 3 . 5 2 BN1-11600.02 92 iv LIPA Revision 1 - February 1993
SNPS-1 ODCM l TABLE OF CONTENTS (CONT'D) Radiological Effluent Controls Section Subject Section EA2R 3.5.1.3 Skin Dose 3.11.2.3 11. 3 . 5 3 3.5.1.4 Organ Doses Due to inhalation 3.11.2.3 11. 3 . 5 5 3.5.1.5 Organ Doses Due to ingestion of Leafy Vegetables 3.11.2.3 11. 3 . 5 - 5 3.5.1.6 Infant Thyroid Dose Due to inhalation and Ingestion of Goat Milk 3.11.2.3 11. 3 . 5 - 7 3.5.2 Method 2: (Backup Method) 11.3.5 11 3.5.2.1 Organ Doses 3.11.2.3 11.3.5 11 3.6 [No Longer in Use) !!.3.6 1 3.7 TOTAL DOSE FOR THE URANIUM FUEL CYCLE 3.11.4 11. 3 . 7 1 3.7.1 Sources of Radiation and Radioactivity 11. 3 . 7 - 1 3.7.2 RadiologicalIrnpact of Generation of Electricity ll.3.7-1 4 METEOROLOGICAL AND HYDROLOGICAL PARAMETERS UTILIZED IN THE CALCULATION OF DOSES 11. 4 1 INTRODUCTION 11. 4 - 1 4.1 4.2 PARAMETERS AND METHODOLOGY USED IN THE COMPUTERIZED METHOD l1.4-1 4.2.1 Meteorological Data l1.4-1 4.2.2 Long Terrn X/O and D/O Values 11. 4 - 1 4.3 PARAMETERS AND METHODOLOGY USED IN THE BACKUP METHOD l1.4-3 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
- 11. 5 - 1 INTERLABORATORY COMPARISON PROGRAM 11. 6 - 1 6
Appendix A DERIVATION OF A A-1 App.ndix B DERIVATION OF P4 B-1 BN1-11600.02 92 v LIPA Revision 1 - February 1993
SNPS-1 ODCM PART 11 - LIST OF TABLES i Table Illla 2.2-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases 3.1-1 Decay Constants 3.1-2 Adult Dose Rate Conversion Factors, A for (Fish and invertebrate) Ingestion Pathway 3.4-1 Noble Gas Dose Factors 3.5-1 inhalation Dose Factors for Adults 3.5-2 inhalation Dose Factors for Teenager 3.5-3 inhalation Dose Factors for Child 3.5-4 inhalation Dose Factors for Infant 3.5-5 Recommended Values for U, to be Used for the Maximum Exposed Individualin Lieu of Site-Specific Data 3.5-6 Stable Element Transfer Data 3.5-7 Humidity Parameters at Receptors 3.5-8 Location of Nearest Residence, Vegetable Garden, and Site Boundary by Sector 3.5-9 P,, Contaminated Ground, Ingestion of Leafy and Stored Vegetables Dose Rate Conversion Factors for Child 3.5-10 P , Child Ingestion of Cow's Milk Dose Rate Conversion Factors 3.5-11 P4, Child Ingestion of Goat's Milk Dose Rate Conversion Factors 3.5 12 Po, Child Ingestion of Meat Dose Rate Conversion Factors 3.5-13 P , infant ingestion of Cow's Milk Dose Conversion Factors - i BN1-11600.02 92 vi LIPA Revision 1 - February 1993
SNPS-1 ODCM PART ll - LIST OF TABLES (CONT'D) Tabte Ill!A ' 3.5-14 P , infant ingestion of Goat's Milk Dose Conversion Factors 3.5-15 P., Child Inhalation and Ingestion of Leafy and Stored Vegetables Dose Rate Conversion Factors , 3.5-16 P., Child Ingestion of Goat's Milk Dose Rate Conversion Factors 3.5-17 P., Infant ingestion of Goat's Milk Dose Rate Conversion Factors 4-1 Critical Receptor Locations for Gaseous Effluent Calculations 4-2 General Site - Specific Data 5-1 Radiological Environmenta! Monitoring Program - Direct Radiation Monitoring Stations 5-2 Radiological Environmental Monitoring Program - Airborne Monitoring Stations 6-3 Radiological Environmental Monitoring Program - Waterborne Monitoring Stations 5-4 Radiological Environmental Monitoring Program -Ingestion Monitoring . Stations BN1 11600-92 vii LIPA Revision 1 - February 1993
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SNPS 1 ODCM PART 11 - LIST OF FIGURES j Froute Titic 2.1-1 Detector RE-13, Response vs. Gamma Energy 2.1 2 Detector RE-79, Response vs. Gamma Energy 2.21 Detector RE-42, Efficiency vs. Average Beta Energy 2.2-2 Linearity Response Curve for Detector RE-42 , i 3.1-1,1 A Existing Liquid Radwaste System - G11 j 3.1 2,2 A G-11 System after Completion of Decommissioning - Phase 1 3.1 -3,3 A G-11 System after Completion of Decommissioning - Phase llA 3.1 -4,4 A G-11 System after Completion of De ommissioning - Phase llB 3.1 5,5 A G-11 System after Completion of Decommissioning - Phase llc ; 3.1 -6,6 A G-11 System after Completion of Decommissioning - Phase llD-1 3.1 -7,7 A G-11 System after Completion of Decommissioning - Phase llD-2 ; 3.3-1 Gaseous Effluent Model 5-1 Onsite Sampling Locations - Radiological Environmental Monitoring Program , 5-2 Offsite Sampling Locations - Radiological Environmental Monitoring Program F BN1-11600.02-92 viii LIPA Revision 1 - February 1993 l
55PS-1 ODCM l PART I SECTION 1 INTRODUCTION Procedural details of the Radiological Effluent Technical Specifications not associated with solid radioactive vastes which were previously located in the Station Technical Specifications (TS) have been relocated to the ODCH. , Portions of the Definitions and Administrative Controls Section of the TS are also being relocated to the ODCM, and some changes to the words of these sections of TS are being made. All the changes are made tgggravide conformance with the requirements of Generic Letter 89-01 Additional changes to the Radiological Effluent Controls (Part 1. Section.3) of the ODCM have been cade to reflect the isotopic inventory and the radiological effluent monitoring requirements appropriate to a defueled operating condition with fuel stored in the Spent Puel Fool. The Plant may not be returned to an operational state or fuel moved back into the reactor vessel without codifying this ODCH. Additional changes to this document may be required for decor =issioning activities. (1) liRC Generic Letter 89-01, " Implementation of Progra==stic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specification and the Relocation of Procedural Details of the RITS to the Offsite Dose Calculation Manual or to the Process Control Progra ", January 31, 1989. 4 i 1 I.1-0 Revision 17 - May 1991 l 1
SNPS-1 DDCM PART I SECTION 2 ( RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 DEFINITIONS 1,2-0 Revision 16 - July 1990
INDEX DEFINITIONS SECTION PAGE I.0 DEFINITIONS I.2-3 1.1 ACTION........................................................ I.2-3
- 1. 2 CRANNEL C AL I B RAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
I.2-3 1.3 CHANNEL CHECK................................................. I.2-3 1.4 CHANNEL FUNCT I ON AL TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I.2-3 1.5 DEFUELED M0DE................................................. I.2-4 1.6 FREQUENCY N0TATION............................................ 1.2-4 1.7 FUEL HANDLING OPERATIONS...................................... 1.2-4 1.8 MEMBER ( S) 0F THE P UBL I C . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . (0DCM)........................ 1.2-4 1.9 0FFSITE DDSE CALCULATION MANUAL 0PE'RABILITY........................................ I.2-4 1.10 OPERABLE - I.2-5 1.11 REPORTABLE EVENT.............................................. 1.2-5 1.12 SITE B0VNDARY................................................. I.2-5 1.13 SOURCE CHECK.................................................. I.2-5 1.14 UhRESTRICTED AREA............................................. l i
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i 1.2 1 Revision 18 - May 1991 SHOREHAM - UNIT 1
INDEX LIST OF TABLES i PAGE TABLE 1.1 SURVEILLANCE' FREQUENCY NOTATION................. 1.2 7 k 1.2-2 Revision 18 - May 1991 SHOREHAM - UNIT 1
I.0 DEFINITIONS The defined terms appear in capitalized type and shall be applicable throughout these Controls. ACTION 1.1 ACTION shall be that part of a Control which prescribes remedial measures to be taken under designated conditions. CHANNEL CALIBRATION 1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. - CHANNEL FUNCTIONAL TEST 1.4 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested. DEFUELED MODE 1.5 The plant is in the DEFUELED MODE when all fuel has been removed from the reactor vessel and there is fuel in the spent fuel storage pool or in the new fuel storage vault. . I.2-3 Revision 28 - May 1991 SHOP.EHAv. - UNIT 1
DEFINITIONS ( FREQUENCY NOTATION 1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. FUEL HANDLING OPERATIONS 1.7 FUEL HANDLING OPERATIONS shall be the movement of fuel over or within the Spent Fuel Pool. Suspension of FUEL HANDLING OPERATIONS shallnot preclude completion of the movement of fuel to a safe conservative position. MEMBER (S) OF THE PUBLIC 1.8 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated n:th the plant. This category does not include employees of the utility,its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.9 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.0 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specification Section 6.0, OPER ABLE - OPER ABILITY 1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, , train, compoaent or device to perform its function (s) are also capable of performing _ their related support function (s). SHOREHAM - UNIT 1 1.2-4 LIPA Revision 1 - Feb 1993 i
DEFINfTIONS REPORTABLE EVENT 1.11 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. SITE BOUNDARY 1.12 The SITE BOUN'aRY shail be that'11ne beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. SOURCE CHECK 1.13 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. , UNRESTRICTED AREA 1.14 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. - 1.2-5 Revision 18 - May 1991 SHDREHAM - UN]T 1 l i
DETINITIONS I. THIS PAGE LETT BLANK SHORIEAM - L317 1 1.2-6 Revision 17 - May 1991
'i DEFIN2TIONS ,
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TABLE 1.1 i _ . i SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY' S At least once per 12 hours.- .
'D At least once per 24 hours. .
W At least once per 7 days. . M At least once per 31 days'. Q At least once per 92 days. SA At least once per 184 days. ; A At least once per 366 days. j R Atleastonceper18 months (550 days). N/A Not applicable. f P Completed prior to each release.
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i SHOREHAM - UNIT 1 1.2-7 Revision 18 - May 1991 -
l DEFINITIONS THIS PAGE LEFT BLANK 1.2-8 Revision 18 - May 1991 SHOREHAM - UNIT 3
$NPS-1 ODCM 1L PART I-I SECTION 3 RADIOLOGICAL EFFLUENT CONTROLS SECTIONS 3.0 and 4.0 CONTROLS .
AND SURVEILLANCE REQUIREMENTS i
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1 i I 1 1.3-0 Revision 16 - July 1990 I
INDEI CONTROLS AND SURVEILLANCE REQUIRDENTS f SECTION PACE
, 3/4.0 APPLICABILITY.....................s................... I.3-3 3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring In5trucentation.................................. I.3-5 Radioactive Gaseous Effluent Monitoring Instrumentation.................................. I.3-10 3/4.11 RADI0 ACTIVE ETTLUENTS 3/4.11.1 LIQUID ETTLUENTS Concentration.................................... I.3-15 Dese............................................. 1.3-19 Liquid Radvaste Treatment System................. 1.3-20 3/4.11.2 GA$EOUS ETTLUENTS Dose Rate........................................ 1.3-22 Dese - Noble Ca5es............................... 1.3-26 Dese - Tritiu=, and Radienuclides in Particulate Form............................ I.3-27 3/4.11.4 TOIAL D0SE............................................ I.3-34 3/4.12 RADIOLOGICAL EhTIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.................................... I.3-35 3 /4 .12 . 2 L AND U S E C EN SU S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I.3-46 3/4.12.3 INTERLABORATORY COMPARISON PR00 RAM.................... I.3-47 I.3-1 Revision 17 - May 1991
1NDEK LIST OF TABLES PAGE TABLE 3.3.7.10-1 RADIOACTIVE LIQUID EFFLUENT MONITORING 1RSTRUKENTATION................................... I.3-6 4.3.7.10-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING I.3-8 IRSTRUMENTATION SURVEILLANCE REQUIREKENTS......... 3.3.7.11-1 RADIDACTIVE EASEOUS EFFLUENT MONITORING I.3-11 INSTRUMENTATION................................... 4.3.7.11-1 RADI0ACT!YE GASEOUS EFFLUENT MONITORING I.3 13 I NST RUMENT ATION SURVEILLANCE REQUI REKENTS . . . . . . . . . 4.11.1.1.1-1 RAD 10ACT'!VE LIQUID WASTE SAMPLING AND ANALYSIS 1.3-16 PR0 GRAM........................................... RADIOACTIVE GASEOUS WASTE MONITORING, SAMPLING, 4.11.2.1.2-1 I.3-23 AND ANALYSIS PR0 GRAM.............................. 1.3-37 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..... 3.12.1-2 REPORTING LEVELS FOR RADIDACTIVITY CONCENTRATIONS I.3-42 Ih ENVIRONMENTAL 5AMPLES.......................... 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONKENTAL SAMPLE 1.3-43 AfiALY515.......................................... I.3-2 Revision 16 - July 1990
3/4.0 APPLICABfLITY CONTROLS 3.0.1 Compliance with the Controls contained in the succeeding Controls is required during the DEFUELED MODE specified therein; exce>t that upon failure to meet the Controls the associated ACTION requirements s tall be met. 3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 Commencement or continuation of FUEL HANDLING OPERAT!dNS shall not be made when the conditions for the Controls are not met and the associated ACTION requires suspension of FUEL HANDLING OPERATIONS if they are not met, within a specified time interval. FUEL HANDLING OPERATIONS may be made in accordance with the ACTION requirements when conformance to them:
- 1. Permits continued FUEL HANDLING OPERATIONS for an unlimited period of time or,
- 2. Perr.its fuel to be moved to a safe, conservative position.
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].3-3 Revision 18 - May 1991 SHDREHAM - UNIT I 1
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l APPLICABILITY . SURVEILLANCE REQUIREMENTS
-f 4.0.1 Surveillance Requirements shall be met during the DEFUELED MODE or other APPLICABILITY conditions specified for individual Controls.
4.0.2 Each Surveillance Requirement shall be performed within the specified , surveillance interval with a reximum allowable extension not to exceed 25% of the specified surveillance interval. 4.0.3 Failure to perform a Surveillance Requirement with'in the allowed surveillance interval, defined by Specification 4.0.2 shall constitute noncompliance with the OPERABILITY requirements for a Control. The time ' limits of the ACTION requirements are applicable at the time it is identified-that a Surveillance Requirement has not been performed. Surveillance Requirements do no have to be performed on inoperable equipment. 4.0.4 FUEL HANDLING OPERATIONS shall not occur or continue unless all Surveillance Requirement (s) associated with the Control have been performed within the applicable surveillance interval. This provision shall not prevent passage through or to conditions as required to comply with ACTION renuirements. 4 SHDREHAM - UNIT 1 1.3-4 Revision 18 - May 1991
l lNSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.10 The radioactive liquid offluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM). APPLICABILITY: At all times. ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably ,
conservative,
- b. With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement of Table 3.3.7.10-1, take the ACTION shown in Table 3.3.7.10-1. Restore the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Annual Radiological Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS ; 4.3.7.10.1 Each radioactive liquid effluent monitoring instrumentation channel shall be : demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies i shown in Table 4.3.7.10-1. 4.3.7.10.2 At least once per 4 hours at least one service water pump shall be determined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive effluent concentration limits of Control 3.11.1.1. i SHOREHAM - UNIT 1 1.3-5 LIPA Revision 1 - February 1993 a
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> TABLE 3.3.7.10-1 K
RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION s-1 a MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE g a. Uguid Radwaste Effluent Lie, RE-13 1 110 5 2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. No Longer in use
- b. Reactor Building Salt Water Drain Tank Outlet, RE-79 1 112 3 3. FLOW RATE MEASUREMENT DEVICE E a. Liquid Radwaste Effluent Line 1 113 5.
6' a a e E 5
i E TABLE 3.3.7.10-1 (Continued) ;
-, ACTION STATEMENTS
( j ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this ; pathway may continue provided that prior to initiating a release:
- s. At least two independent samples are analyzed in accordance l with Controls 4.11.1.1.1 and 4.11.1.1.2, and
- b. At least two technically qualified members of the Station Staff l independently verify the release rate calculations and diacharge line l volving, ,
1 Otherwise, suspend release of radioactive effiuents via this pathway. ACTION 111 - No Longer in Use. j l ACTION 112 - Wi" '.6 number of channels OPERABLE less than required by the ; Minimum ':nannels OPERABLE requirement, affluent releases via this l pathmv rany continue provided that, at least once per 12 hours, grab samp!es are collected and analyzed for radioactivity at a lower limit of ! detection of at least 5x10 4microcurie /mL. 1 I ACTION 113 - With the number of channels OPERABLE less than required by the- ; Minimum Channels OPERABLE requirement, effluent releases via this i ! pathway may continue provided that, flow rate is estimated at least once ; per 4 hours during actual releases. Pump performance curves generated in ; place may be used to estimate flow. ! i i
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.1 SHOREHAM - UNIT 1 1.3-7 LIPA Revision 1 - February 1993 i ~. -- - __ -- -- -. _ -- , . . _ . - - -.
8 g TABLE 4.3.7.10-1 { RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e a CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. GROSS RADIOACTIVITY MONITORS PROVID!NG ALARM AND AUTOMATIC TERMINATION OF RELEASE g a. Liquid Radweste Effluent Line, RE-13 D(4) P R(3) O(1)
A 2. GROSS RADIOACTIVITY MONITORS PROVIDlNG ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. No Longer in Use.
- b. Reactor Building Salt Water Drain Tank Outlet, RE-79 D M R(3) O(2) g 3. FLOW RATE MEASUREMENT DEVICE l
k a. Liquid Radweste Effluent Line D(4) N.A. R O 8 1 ,
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l TABLE 4.3.7.10 1 (Continued) TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation and/or indication occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarr/ trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm ar.nunciation and/or indication occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mude.
(3) The initial CFANNEL CALIERATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or usir.g standards that have been obtained from suppliers that participate in ressure ent assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initiel calibration shall be used. (4) CHANNEL CHECK shall consist of verifying indicatinn during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days ; when batch releases are e.ade. , t SHDREHAM - UNIT 1 1.3-g Revision 16 - July 199n
INSTRUMENTATION t R ADIOACTIVE GASEOUS EFFLUENT MONITORtNG INSTRUMENTATION , CONTROLS 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM. APPLICABILITY: At all times. ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Control, immediately ,
suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative. 9 b. With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement of Table 3.3.7.11-1, take the ACTION shown in Table 3.3.7.11-1. Restore the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radiological Ef fluent Release Report why the inoperability was not corrected in a timely manner, f
- c. The provisions of Control 3.0.3 are not applicable. ;
SURVE!LLANCE REQUIREMENTS ; 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be f demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK,- CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1. i t i i l l l l SHOREHAM - UNIT 1 1.3-10 LIPA Revision 1 - Feb 1993 l
E TABLE 3.3.7.11-1 8 g RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION D E C z a MINIMUM
-o CHANNELS INSTRUMENT OPERABLE ACTION
- 1. [No Longer in Usel
- 2. [No Longer in Usel
- 3. STATION VENTILATION EXHAUST MONITORING SYSTEM
- a. Noble Gas Activity Monitor, RE-42 1 120
- b. [No Longer in Usel
" c. Particulate Sampler 1 122
- d. Effluent System Flow Rate Monitor 1 123
- e. Sampler Flow Rate Monitor 1 123
- 4. [No Longer in Usel E
s. E. , O d. 4 G S
TABLE 3.3.7.11-1 (Continued) i ' TABLE NOTATIONS ACTION STATEMENTS ACTION 120 - With the number of channels OPERA 3LE less than required by the Minimum Channels OPERABLE requirement, affluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 121 [NoLongerinUse] l ACTION 122 - Vith the number of channels OPERA 3LE less than required by the , Minimum Channels OPERABLE requirement, affluent releases via this pathway may continue provided samples are continuously collected starting within 8 hours of discovery, with auxiliary sampling equipment as required in Table 4.11.2.1.2-1. ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERA 3LE requirenent, affluent releases via this pathway may continue provided the flow rate is estimated I at least once per 12 hours. ACTIOS 124 - [No Longer in Usel n SEDREEAM - L'517 1 1.3-12 Revision 17 - May 1991
TABLE 4.3.7.11-1 o RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS T 5> i f CHANNEL C CHANNEL SOURCE CHANNEL FUNCTIONAL
$ INSTRUMENT CHECK CHECK CAllBRATION TEST
- 1. [No Longer in Usel .
- 2. [No longer in Usel
- 3. STATION VENTILATION EXHAUST MONITORING SYSTEM
- a. Noble Gas Activity Monitor, RE-42 D M R(2) O(1)
- b. [No Longer in Use]
'i' c. Particulate Sampler W N/A N/A N/A
- d. Effluent System Flow Rate Monitor D N/A Q N/A
- e. Sampler Flow Rate Monitor D N/A Q N/A
- 4. [No Longer in Use]
I s. a S _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ . . , . . . _ - . . . . - - . . - . ~ . . ._ _. - _ , _ . - . . ._. .._. - . _ , . _ _ _ _ _ _ _ _
TABLE 4.3.7.11-1 (Continued) l l l i TABLE NOTATIONS , (1) The CHANNEL TUNCTIONAL TEST shall also demonstrate that control room alarn annunciation and/or indication occurs if any of the following conditions exists' .
- 3. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
Instrument indicates a devnscale failure.
- 3. ,
- 4. Instrument controls not set in operate moda.
(2) The initial CRANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NES) or using standards that have been obtained from suppliers that . l participate in reasurecent assurance activities with NBS. These standards shall permit calibrating the system over its intended range of , energy and ceasurcrent range. For subsequent CHARNEL CALIBRATION, sources that have been related to the initial calibration shall be used. ' (3) [No Lenger in Use] i i i
-i
.1 1.3-14 Revision 17 - May 1991 .
SEDREHAM - UNIT 1
I 3/4.11 RAD 20 ACTIVE EFTLUENTS 3/4.11.1 LIQUID EFFLUENTS > ! CONCENTRATION CONTROLS ; 3.11.1.1 The concentration of radioactive material released in liquid - af fluents to UNRESTRICTED AREAS (see Figure 5.1.3) shall be limited to the concentrations specified in 10 CTR Part 20, Appendix B. Table II, Column 2 i for radionuclides other than dissolved or entrained ncble gases. For dissolvgd or entrained noble gases, the concentration shall be limited to
~
2 x 10 microcurie /mL total activity. r APPLICABILITY: At all times. ACTION: . With the concentration of radioactive material released in liquid affluents to UNRISTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. j SUR7EILLANCE REQUIREMENTS i f 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11.1.1.1-1. 6 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the cethodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1. , b b b b i
- l l
l 1.3-15 Revision 17 - May 1991 l SHDREHAM - UNIT 1 \
TABLE 4.11.1.1.1-1 , RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of arnpHng Y " Liquid Release Type An ysi Analysis Frequency (LLD) Frequency (uCi/mt)" A. Batch Waste P P Principal 5x107 Release Tanks Each Batch Each Batch Gamma and Sumps' Emitters'
- 1. Discharge P' M' Dissolved and 1x10 4 Waste One Batch /M Entrained Gases Sample (Gamma Tanks Emitters)
- 2. Recovery P' M' H-3 1x10 4 d
Sample Each Batch Composite Tanks Gross Alpha 1x10'
- 3. Yard Piping P' O Sr-89, Sr-90 5x10 4 Drain Sump Each Batch Composite d ..
p
- 4. Reactor Bldg Salt Water Drain Tank' B. Continuous M# M# Principal Gamma 5x107 Releases
- Grab Sample' Grab Sample' Emitters *
- 1. No Longer in se Dissolved and 1x10 4 Entrained Gases (Gamma Emitters)
- 2. Reactor Building Salt H-3 1x104 Water Drain Tank Gross Alpha 1 x10
O## Or# Sr-89, Sr-90 Ex10* Grab Sample' Grab Sample' Fe-55 1x10 4 If batch is released during the month.
** If batchis released during the quarter. # If flow is released during the month. ## If flow is released during the quarter. .
SHOREHAM - UNIT 1 1.3-16 LIPA Revision 1 - February 1993 f
TABLE 4.11.1.1.1-1 (Continued) TABLE NOTATION I "The LLO is defined, for purposes of the Controls, as the smallest - concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability withonly5%grobabilityoffalselyconcludingthatablankobservation represents a real" signal. For a particular measurerent system, which may include ridiochemical separation: 4.66 s LLD = 6 E . V . 2.22 x 10 . Y . exp (-Aat ) Ehere: LLD is the "a priori" lower limit of detection as defined above, as e.icrocuries per unit mass or volume, sg is the standard deviation of the background counting rate or of tr;e counting rate of a blank sample as appropriate, as counts per minute. E is the counting efficiency, as counts per disintegration, V is the serple size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable. A is the radioactive decay constant for the particular radienuclide, and 4t fer plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. Typical values of E. V, Y and at should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measureEent system and not as aposteriori(afterthefact)Ifmitforaparticularmeasurement. bA batch release is the discharge of liquid wastes of a discrete volume. Prior to sarpling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. 1.3-17 Revision 16 - July 1990 SOF.EMM - LINIT I
f TABLE 4.11.1.1-1 (Continued) s TABLE NOTATIONS (Continued) cThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Co-60, Zn-65, Cs-134 and Cs-137. Ce 144 shall also be measured, but with an LLD of 5x10pCi/mL. This list does not mean that only these nuclides are to be , considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall aNo be analyzed and reported in the Annual Radioactive Ef fluent Release Report pursuant to Contro! 6.8.1.4. dA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
I lf the alarm setpoint of the effluent monitor, as determined by the method presented in the ODCM, is exceeded, the frequency of sampling shall be increased to daily until the alarm , condition no longer exists. Frequency of analysis shall be increased to daily for principal gamma emitters and on incident composite for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 prepared and analyzed. . 0When the final draining of the Spent Fuel Storage Pool is performed (after removal of all > spent fuel from Pool),it shall be considered a batch release of the contents of the SFSP with j mixing and sampling requirements as defined in the ODCM for batch releases. This is despite its transit through the limited volume of the Reactor Building Salt Water Drain Tank to the Long Island Sound through the continuous release path via 1D11-PNL-079. The actual details of the release times, flowrates, and duration will be determined when the release is to take place, in accordance with the applicable requirements of the ODCM. Final draining of the SFSP shall be the only occasion for use of the Salt Water Drain Tank in a batch release mode. i SHOREHAM - UNIT 1 1.3-18 LlPA Revision 1 - February 1993
l l l RADIDACTIVE EFFLUENTS DOSE CONTROL l 3.11.1.2 The dose or dose comitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.3) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than.or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICAEILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materi,;1s in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 6.0, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREFENT5 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be detemined in accordance with the methodology and parameters in the ODCM at least once per 31 days. SHOREHAM - UNIT 1 1.3-19 Revision 18 - May 1991
i RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3) would exceed 0.06 mrem to the total body or 0.2 mrem to any organs in a 31-day period. APPLICABILITY: At all times. ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Comission within 30 days pursuant to Technical Specification Section 6.0, a Special Report that includes the following information:
- 1. Explanation of why. liquid radweste was being discharged without treattrent,~ identification of any inoperable equipment or subsystems, and the reason for the inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Sumary description of action (s) taken to prevent a recurrence,
- b. The provisions of Control 3.0.3 are not applicable.
SUPTE1LLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCM. 4.11.2.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. 1.3-20 Revision 18 - May 1991 SHOREHAM - UNIT 1
RAD 20 ACTIVE EFFLUENTS 1 3.11.1.4 (NotUsed)' ; l l
.i I
l l l l l I l l l l l
}
SHDF.EKAM - Uti1T 1 1.3-21 Revision 16 - July 1990
RADI0 ACTIVE ETTLUENTS 3/4 11.2 CASIOUS ETTLUENTS DOSE RATE CONTROLS i 3.11.2.1 The dose rate to areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the site (see Figure 5.1.3) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total ,
body and less than or equal to 3000 mrams/yr to the skin, and
- b. For tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 cre=s/yr to any organ.
APPLICA3ILITY: At all times. ; ACTION: With the dose rate (s) exceedink the above limits, immediately restore the release rate to within the above 11=it(s). SrRVIILLANCE REorIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous affluents shall be ' determined to be within the above limits in accordance with the methodology and para eters in the ODCM. 4.11.2.1.2 The dose rate due to tritium and all radionuclides in particulate for with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology r and para =eters in the ODCM by obtaining representative saeples and performing analyses in accordance with the sampling and analysis program specified in , Table 4.11.2.1.2-1. f a l I.3-22 Revision 17 - May 1991 SHORIRAM - UNII 1
TABLE 4.11.2.2.2-1 RADIDACTIVE GASEOUS WASTE MONITORING, SAMPLING AND ANALYSIS PROGRAM i Lower Limit Minimum
- Type of of Detection Gaseous Release Sampling Analysis Activity (LLD)
' Frequency (uC1/mL),
Type Frequency Analysis, A. Station Continuous' M Principal Gamma 1 x 10~II b Ventilation Particulate b Exhaust Sample Emitters Continuous' M Gross Alpha 1 x 10"Il b Particulate Sample .
-11 Continuous
- Q Sr-89, Sr-90 ~1 x 10 Composite Particulate
' Sample
-6 Centinous' Noble Gas Noble Gases 1 x 10 Menitor Gross Beta or Gam =a M M Principal Ga==a 1 x 10 Grab Sa:ple b
-6 M
d M E-3 1 x 10 Grab Sa:ple B. [No Longer in Usel i i I
\
. l l
i 1.3-23 Revision 17 - May 1991 SHOKEFJ.M - UNIT I
TABLE 4.11.2.1.2-1 (Continued) T BLE NOTATION
- The LLD is defined, for purposes of these Controls as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical - separation: 4.66 sb , LLD = 6 E . V. 2.22 x 10 . Y . exp ( Mt) Where: LLD is the "a priori" lower limit of detection as defined above, as micrecuries per unit mass or volume, s is the standard deviation of the background counting rate or of , thecountingrateofablanksampleasappropriate,ascountsper minute, , E is the counting efficiency, as counts per disintegration, V is the ssrple size in units of mass or volume, l 2.22 x 106 is the number of disintegrations per minute per microcurie, j Y is the fractional radiochemical yield, when applicable. l 1 is the radioactive decay constant for the particular radichuclide, and at for plant effluents is the elapsed time between the midpoint of sarple collection and the time of counting. Typical values of E. V, Y, and at should be used in the i calculation. It should be recognized that the LLD is defined as an a priori (before the ~ fact) limit representing the capability of the measure?ent system and not as a posteriori (after the fact) limit for a particular measurement.w% supb ( t th. l SHDFEH!y. - UNIT 1 1.3-24 Revision 16 - July 1990
T ABLE 4.11.2.1.2-1 (Continued) j TABLE NOTATIONS (Continued) bThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Co-60, 2n-65, Cs-134, Cs-137 and Ce-144 in particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.8.1.4. c[No Longer in Usel dTritium grab samples shall also be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuelis in the spent fuel pool, until stable tritium release levels (5 consecutive samples) can be demonstrated. eThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1 and 3.11.2.3. . f lNo Longer in Use) DINo Longer in Usel i t l SHOREHAM - UNIT 1 1.3-25 LIPA Revision 1 - February 1993 l
RADIDACTIVI EFFLUENTS DOSE - NOBLE GASE5 CONTROL 5 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrads for gama radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times. ACTION:
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Com.ission within 30 days, pursuant to Technical Specificati'on Section 6.'0, a Special Report which identifies the ,
cause(s) for exceeding the limit (s) ard defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calender year for noble gases shall be detennined in accordance with the rnethodology and parameters in the ODCM at least once per 31 days. SHOREHAM - UNIT 1 1.3-26 Revision IB - May 1991 ; i
l l RAD 70ACT!YE EFFLUENTS DOSE-TRITIUMANDRADIONUCLIDES15PARTICULATEFORM l 1 CONTROLS 1 1 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate fom with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond , the SITE BOUNDARY (see Figure 5.1.3) shall be limited to the following:
~
- a. During any calendar quarter: Less than or equal to 7.5 arems to -
any organ and,
- b. During any calendar year: - Less than or equal to 15 mrems to any organ. '
APPLICABILITY: At all times. 1 ACTION: i
- a. With the calculated dose from the release of tritium and radionuclides in particulate form with half-lives greater than 8 ,
days, in gaseous effluents exceeding any of the above limits, ', prepare and submit to the Commission within 30 days, pursuant to , Technical Specification Section 6.0, a Special Report that # identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above Ifmits.
- b. The provisions of Control 3.0.3 are not applicable. )
l SURVEILLANCE REOUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calender year for tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in'accordance with the methodology and parameters in the ODCM at least once per 31 days. . i
~
l SHOREHAM - UNIT 1 ].3-27 Revision 18 - May 1991
[ RADI0 ACTIVE ETn.tTNTS 1 i GASEOUS RADVASTE TRT.ATMENT SYSTEM CONTROLS 3.11.2.4 [No Longer in Use] \ SURVEILIANCE REQUIREMEh7S 4.11.2.4 (No Longer in Use) I.3-28 Revision 17 - May 1991 SHORIPE - UNIT I
I I j RADICACTh'I EMUENTS VEhTILATION IIRAUST TREA7 MENT SYSTEM CONTROLS 3.11.2.5 [No Longer in Use] SURVEILLANCE REQUIRDEh7S 4.11.2.5.1 [No Longer in Use] 4.11.2.5.2 [No longer in Use) I i 1 l l l I.3-29 Revision 17 - May 1991 ; SHORIHAM - UNIT I !
RADIDACTIVE EFFLUEhTS EXPLO5IVE GAS MIXTURE i LIMITING CONDITION F0P OPERATION
~ 3.11.2.6 (NotUsed).
RADIOACTIVE EFFLUEh7S MAIN CONDENSER LIMITING C0NtIT10N FOR OPERATION 3.11.2.7 (Not Used). l SH REHAP. - Uti!T 1 1.3-30 Revision 16 - July 1990
RADI0 ACTIVE ETTLUEh7S CONTAINMENT PURCING AND VENTING C0h7ROLS 3.11.2.8 [No Longer in Use] SURVIILIJLNCE REQUIREMENTS 4.11.2.8.1 [No Longer in Use] 4.11.2.8.2 [No Longer in Use] 4.11.2.8.3 (No Longer in Use] 1 1 d l 1 a SHOREHAM - UNIT 1 1.3-31 Revision 17 - May 1991 I
i RADI0 ACTIVE EFTLUEh7S SURVIILLANCE REQUIRDENTS This page intentionally left blank. , l l l i i t 1 P 9 t 1,3-32 Revision 17 - May 1991 , SHOREHAM - UNIT 1 1
1 RADICACTIVE EFFLUENTS SURVIILLANCE RIQUIREKENTS
' I i
l 1 l RADI0 ACTIVE EFFLUENTS 3/4.11.3 [No Longer in Use) SHOREPm - USIT 1 I.3-33 Revision 17 - May 1991
RADf0 ACTIVE EFFLUENTS 3/4.!!.4 TOTAL DOSE CONTROLS 3.11.4 The annual (calendar year) dose or dose connitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from unranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be Ifmited to less than or equal to 75 mrems. APPLICABILITY: At all times. ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,
3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of If such is the case, prepare Control 3.11.4 have been exceeded. and submit to the Commission within 30 days, pursuant to Technical Specification Section 6.0, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving confomance with the above limits. This Special Repert, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special R'eport shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents accordance with Controls 4.11.1.2, 4.11.2.2, and shall be determined 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. l j 4.11.4.2 Cutulative dose contributions from direct radiation from the l reactor units and from radwaste storage tanks shall be detemined in This requirement accordance with the methodology and parameters in the ODCM. i is applicable only under conditions set forth in Control 3.11.4a. Revision 18 - May 1991 SHDREHAM - UNIT 1 1.3-34
3/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGR AM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1. , APPLICABILITY: At all times. , ACTION: _ f
- a. With the radiological envirj anmental program not being conducted as specified in Table 3.12.15'1, prepare and submit to the Commission, in the Annual ,
Radiological Environmental Operating Report required by Controf 6.B.1.4, a description of the reasons for not conducting the program es required and the plans for preventing , a recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission, within 30 days, pursuant to Technical Specification 6.9.2, a Special <
Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose * , to A MEMBER OF THE PUBLIC is less than the calendar year limits of Controls
- 3.11.1.2,3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table '
3.12.1-2 are detected in the sampling medium, this report shall be submit concentration (1) + concentration (2) + ..) .0
~
reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A ,
MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 3.11.1.2,3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however,in such an event, the condition shall be reported and descrioed in the Anr.ual Radiological Environmental Operating Report,
~ 'The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report, r
SHOREHAM - UNIT 1 1.3-35 LIPA Revision 1 - Feb 1993
l l l RADIOLOGICAL ENVIRONMENTAL MONITORING i CONTROLS (Continued) ACTION: (Continued)
- c. With fresh leafy vegetable samples discontinued from one or more of '
the sample locations required by Table 3.12.1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may than be deleted from the monitoring program. Pursuant to Control 6.8.1.4, identify the cause of the unavailability of samples and identify the new location (s) for obtaining repla^ement samplesin the next Annual Radioactive Effluent Release Report and also incluoe in the report a revised figure (s) and table for the ODCM reflecting the , new location (s).
- d. The provisions of Controls 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM, and shall be analyzed pursuant to the requirement of Table 3.12.1-1 and the detection capabilities required by 4.12.1-1. b F 1 : SHOREHAM - UNIT 1 1.3-36 LIPA Revision 1 - Feb 1993
d
~ ,..
TABLE 3.12.1-1 . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION
- COLLECTION FREQUENCY OF ANALYSIS
- 1. DIRECT RADIATION 18 routine monitoring stations, DR1- Quarterly Gamma dose quarterly.
DR16, DR30-DR31 either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
- a. A ring of stations, one in enci:
meteorological sector in the
- general area of the SITE y BOUNDARY, DR1-DR16; O
- b. The remaining two. stations, DR-30 and DR31 serve as control locations.
l 1 5. 8 i x e
TABLE 3.12.1-1 IContinued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATHWAY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION
- COLLECTION FREQUENCY OF ANALYSIS
- 2. AIRBORNE ,
Gross Beta and Samples from 5 locations, A1-A5: Continuous sampler Particulate Samoler: Gamma Isotopics operation with sample Gross beta radioactivity 3 samples, Al-A3" from close to the 3 collection weekly, or more analysis following filter SITE BOUNDARY locations, in different frequently if required by change;d Gamma isotopic sectors, of the highest calculated annual dust loading. analysis' of composite (by average groundlevel D/O. location) quarterly. 1 sample, A4, from the vicinity of a community having the highest i' calculated annual average groundlevel
$ D/O.
4 1 sample, AS, from a contro! location as for example 15-30 km distant and,in the least prevalent wind direction.'
- 3. WATERBORNE 5
Surfaceh (Long 1 sample control, Wa1 Grab sample semiannually. Gamma isotopic analysis' h a. 1 sample discharge, Wa2 or Wa3 and tritium analysis 7 Island Sound) 5 semiannually. O b. Not Used i 1 sample from downstream area with Semiannually. Gamma isotopic analysis' g: c. Sediment from existing or potential recreational value, semiannually.- x shoreline G Wd 1.
*The first and second highest D/O sectors have particulate samples. The third highest D/O sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector. . _ _ _ _ _ __ _ _ _ _ _ _ - _ _ _ _ e = - w + =g-w n
- w q e -o.c g- %
v . , ,_m_, .g
TABLE 3.12.1-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM" EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION' COLLECTION FREQUENCY. OF ANALYSIS 4 INGESTION
- a. Not Used
- b. Fish and 1 sample of each commercially and Sample in season or Gamma isotopic analysis' invertebrates recreationally important species in semiannually if they are not on edible portions.
vicinity of plant discharge area, Ib1-lb2. seasonal. 1 sample of same species in areas not influenced by plant discharge, Ib3. Y w
- c. FOOD Samples of 3 different kinds of broad At time of harvest.' Gamma isotopic
- analysis.
PRODUCTS leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground-level D/Q, Ic1 - Ic2. m { 1 sample of each of the similar broad leaf vegetation grown 15-30 km distant At time of harvest.' Gamma isotopic
- analysis.
8 in the least prevalent wind direction,
- ic3.
u I h x b _ ._ _ _ . . . _ - . _. . - . . . ~ . _ . . _ . . ._ . . _ . , . . . . - _ . . . . _ . _ . .
, TABLE 3.12.1-1 (Continued) t e
TABLE NOTATIONS
- Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the ODCM. Refer to NUREG-0133, " Preparation of Radiological l
Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from i the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal ' unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report : pursuant to Controls 6.8.1.4. It is recognized that, at times,it may not be possible or practicable , to continue to obtain samples of the media of choice at the most desired location or time. In these ; instances suitable alternative media and locations may be chosen for the particular pathway in i question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Control 6.8.1.4, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next ! Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table l for the ODCM reflecting the new location (s).
"One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of ,
this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optinmm dose information with minimal fading.
'The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
' Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more i after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
' Gamma isotopic analysis means the identification and quantification of gamma- emitting radionuclides that may be attributable to the effluents from the facility. >
t l SHOREHAM - UNIT 1 1.3-40 LIPA Revision 1 - Feb 1993 .
+
TABLE 3.12.1-1 (Continued) TABLE NOTATIONS (Continued) < I Not Used IThe dose shall be calculated for the maximum organ and age group, using the t methodology and parameters in the ODCM. h The " control" sample shall be taken at a distance beyond significant influence of the discharge. The " discharge" sample shall be taken in an area beyond but near the mixing zone. I If harvest occurs more than once a year, sampling shall be performed during. each discrete harvest. If harvest occurs continously, sampling shal1~ be , monthly. Attention shall be paid to including samples of tuberous and root food products. t i
)
i q i SHDREHAM - UNIT I I.3-41 Revision 17 - May 1991 , i 1
6 TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reportina levels WATER AIRBORNE PARTICULATE FISH FOOD PRODUCTS ANALYSIS (pCi/L) OR GASES (pCi/m') (pCi/kg, wet) (pCi/kg, wet) H-3 30,000 Mn-54 1,000 30,000 s Co-60 300 10,000 w Zn-65 300 20,000 h Cs-134 30 10 1,000 1,000 Cs-137 50 20 2,000 2,000 W
;i a
8 0 i ; Y x e S ,
- 1. .
-~
TABLE 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS *6 LOWER LIMIT OF DETECTION (LLD)* A " ^ ^ FISH FOOD PRODUCTS - SEDIMENTS WATER
^"# ' OR ^ (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)
(pCi/L) Ci Gross Beta 4 0.01 H-3 3000 Mn-54 15 130 Co-60 15 130 Zn-65 30 260 [ Cs-134 15 0.05 130 60 150 h Cs-137 18 0.06 150 80 180 5
;l a
8 I w e 2 _ma._.u._ -..a-_._-..-.__m ._m__-_..-mm_a__ .-m__._____________.m ._m _ --J- *L_ ^ w s-i M g -W y- ge > -*+s % e- er. m w+ q -s- .e w s.
i TABLE 4.12.1-1 (Continued) TABLE NOTATIONS i
"This list does not mean that only these nuclides are to be considered. Other peaks that are ' identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.8.1.4. l l ' Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. ,
i The LLD is defined, for the purposes of these specifications, as the smallest concentration of radioactive materialin a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding j that a blank observation represents a "real" Signal. For a particular measurement system, which may include radiochemical separation: 4.66s3 E V2.22 Y exp (-AA c) , Where: LLD is the "a priori" lower limit of detection as defined above, as picocurie per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency (as counts per transformation), V is the sample size in units of mass or volume, 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t for environmental sampler is the elapsed time between sample collection, or end i of the sample collection period, and time of counting. l Typical values of E, V, Y, and t shall be used in the calculations. ~ 1 l l 1 SHOREHAM - UNIT 1 1.3-44 LIPA Revision 1 - Feb 1993 ; l
TABLE 4.12.1-1 (Continued) i. TABLE NOTATIONS _(Continued) It should be recognized that the LLD is defined as an a pigr (before the fact) limit ' representing the capability of a measurement system and not as an a costeriori (after the ' fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interferring nuclides, or other - uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Contro! 6.8.1.4. t 4 SHOREHAM - UNIT 1 1.3-45 LIPA Revision 1 - Feb 1993
RADIOLOGICAL ENVIRONMENTAL MONITORING i 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location of each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 (500 ft) producing broad leaf vegetation.' For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 8 km (5 miles) the locations in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 m2 (500 ft2) producing broad leaf vegetation. APPLICABILITY: At all times. ACTION: ;
- a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3. idernify the new location (s) in the next Annual Radioactive Effluent Release Report, pursuant to Control 6.8.1.4. !
- b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) to tha e adiological environmental monitoring program within 30 days. The sampling location (s), excluding the ,
control station location, having the lowest calculated dose or dose commitment (s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Control 6.8.1.4, identify the new location (s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
- c. The provisions of Controls 3.0.3 are not applicable.
SUREVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growth season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Contro! 6.8.1.4.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the ;
highest predicted D/Os in lieu of the garden census. Specifications for broad leaf ' vegetation sampling in Table 3.12.1-1, item 4.c., shall be followed, including analysis of control samples. SHOREHAM - UNIT 1 1.3-46 LIPA Revision 1 - Feb 1993
RADIOLOGIC AL ENVIRONMENTAL MONITORING q 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM j 1 CONTROLS i 3.12.3 Analyses shat: be performed on radioactive materials supplied as part of an j interlaboratory Comparison Program that has been approved by the Commission, that . corresponds to samples required by Table 3.12.1-1. -{ APPLICABILITY: At all times. ; ACTION: ,
- a. With analyses not beMg performed as required above, report the corrective i actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 6.8.1.4.
- b. The provisions of Controls 3.0.3 are not applicable. t T
SURVEILLANCE REQUIREMENTS 4 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.8.1.4. t r I SHOREHAM - UNIT 1 1.3-47 LIPA Revision 1 - Feb 1993 , 5 b
l l SNPS-1 ODCM l PART I < l SECTION 4 I RADIOLOGICAL EFFLUENT C0hTROLS BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMEhTS 1.4-0 Revision 16 - July 1990
MOTE The BASES contained in' succeeding pages sumarize the reasons for the Controls in Sections 3.0 and 4.0, but in accordance with 10 CFR 50.36 are not part of these Controls. l I.4-1 Revision 16 - July lego
1 1 1 1 INDEI BASES FACE SECTION . i J INSTRUMINTATION I
.J 3/4.3.7 MONITORING INSTRUMENTATION .
Radioactive Liquid Effluent Monitoring......... I.4-3 l i Instrumentation Radioactive Caseous Effluent Monitoring........ I.4-3 Instrumentatics 3/4.11 RADI0 ACTIVE EFTLUDiTS 3/4.11.1 LIQUID ETTLUEh75 Concentration................................ I.4-3 j Dose......................................... 1.4-4 . I.4-4 l Liquid Radvaste Treatment System............. 3/4.11.2 CASEOUSEFFLUEkTS
.I.4-5 Dose Rate....................................
?
I.4-5 t Dose - Noble Cases........................... Dose - Tritiu: and Radionuclides in I.4-6 Particulate Fors........................... , I.4-7 3/4.11.4 TOTAL D0SE................................... 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM........................... I.4-8 I.4-8 ; 3 / 4 .12 . 2 LAND U SE CEN SU S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 4-9 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM. . . . . . . . . . . . 1 l i J l 1.4-2 Revision 17 - May 1991 l SHORIHAM - UNIT 1 I
l l INSTRUMENTATION BASES 3/4.3.7 MONITORlhG . INSTRUMENT AT ION 3/4.3.7.10 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive material The in liquid effluents during actual or potential releases of liquid effluents. alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCri The to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60; 63 and 64 of Appendix A to 10 C Part 50, 3/4.3.7.11 RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATI Ine racioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials The alarm / trip setpoints for these instruments shall be ca adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the contentrations of potentially explosive gas mixtures in the The OPERABILITY and use of this main condenser offges treatment system. instrumentation is. consistent with 60, 63, anc 64 of Appendix A to 10 CFR Part 50. 3/4.11.1 L10UID EFFLUENTS 3/4.11.1.1 C0f CENTRATION Inis Control 1s provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the contentration levels specified in 10 CFR Part 20 . A Table 11, Column 2. levels of radioactive materials in bodies of water in UNRESTRI result in exposure within (1) the Section II.A design objectives of Appen I,10 CFR 20.106(e) to the population. or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC air (submersion) was converted to an equivalent concentration in water using the methods described in Internat Comission on Radiological Protection (ICRP) Publication 2. This Control applies to the release of radioactive materials in liquid effluents from all reactor units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs) Detailed discussion of the LLD, and other detection li for Qualitative Detection and Quantitative DeterminationK., - Application Detection toand Ha Radiochemistry,* Anal-Chem. 40, 586-93 (1958), Limits for Radicar.alytical Counting) Techniques, Atlantic Richfie Company Report ARH-5A215 (June 1975 . Revision 16 - July 1990 1.4-3 SHOREHAM - UM T 1 .
. i 3/4.11 RAD 10 ACTIVE EFFLUEh75 l
BASES _ 3/4.11.1.2 DOSE . This Control is provided to implement the requirements of Sections II.A. - The Control implements the III.A and IV.A of Appendix I,10 CFR Part 50. The ACTION statements provide guides set forth in Section II.A of Appendix I.the required operating flexibili , set forth in Section IV.A of Appendix I to assure that the releases of ) radioactive material in liquid effluents will be kept "as low as reasonably , achievable." The dose calculation methodology and parameters in the ODCM ' implement the requirements in Section III.A of Appendix ! that confomance with the guides of Appendix I be shown by calculational procedures based on - ; models and data, such that the actual exposure of a MEMBER OF THE PUBLIC l through appropriate pathways is unlikely to_be substantially underestimated. ' The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, ;
"forCalculation of Annual Doses to Man from Routine Releases of Reactor Effll the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," i Revision 1, October 1977 and Regulatory Guide 3.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.
l This Control applies to the release of radioactive materials in liquid j For units with shared radweste effluer.ts from each reactor at the site. i treatment systems, the liquid effluents from the shared system are i proportioned among the units sharing that system, 3/4.11.1.3 L100!D EADi'ASTE TREATMENT SYSTEM The OPERAEILITY of the liquid radweste treatment system ensures that this syster will be available for use whenever liquid effluents The requirement require that the treatment appropriate prior to release to the environment. portions of this system be used when specified provides assurance that the releases cf radioactive materials in liquid effluents will be kept as low a is reasonably achievable." 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and The the design objective given in Section 11.0 of Appendix ! to 10 CFR Part 50. specified limits governing the use of appropriate portions of the liquid radweste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents. ' 3/4.11.7 GASEOUS EFFLUENTS 1.4-4 Revision 16 - July 1990 4 SHOREHAM - Uf;IT 1
RADf 0ACTfVE EFFLUENTS . BASE 5 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the dose at'any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the These concentrations of 10 CFR Part 20, Appendix B. Table IL, Column 1. - limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding of10CFRPart20(10CFR20.106b)). For a MEMBER(theOFlimits specified THE PUBLIC in Appendix who may at B. Ta times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusicn factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding game and beta dose rates above background to a HEMSER OF THE PUBLIC at or beyond the SITE BOUNDARY, to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits diso restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year. This Control applies to the release of radioactive materials in gaseous effluents from all, reactor units at the site. The re:;uired detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detectiora (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASLProceduresManual,HASL-300(revisedannually), Currie,L.A.," Limits for Qualitative Detection and Quantitative Determination - Application for K., Detection Radiochemistry," Anal. Chem 40, 556-93 (19EB), and Hartwell, J. Limits for Radicanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 3/4.11.2.2 DOSE - NDELE GASES This control is proviceo to implement the requirements of Sections II.B. III.A and IV. A of Appendix 1,10 CFR Part 50. The Control implements the The ACTION statements provide guides set forth in Section II.B of Appendix I. the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantally underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual relea.e rates of radioactive noble gases in gaseous , effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Eff1 vents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appencix 1, October 1977 and Regulatory Guide 1.111, " Methods for estimating . 1.4-5 Revision 16 - July 1990 SHOREHAv. - UhlT I . i
DOSE - NOBLE CASES (Cantinusd) Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. The ODCM equations provided for determining the air doses at the SITE 50UNDART are based upon the historical average atmospheric conditions. 3/4.11.2.3 DOSE - TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of Sections II.C, 111.A and IV.A of Appendix I, 10 CFR Part 50. The controls are the guides set forth in Section 11.C of Appendix 1. Ihe ACTION statements provide the required operating flaxibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive
^
materials in gaseous affluents vill be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance.
' Requirements implement the requirements in Section III.A of Appendix I that
- conformance with the guides for Appendix I be shown by calculational procedures based on models and data, such thet the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underesticated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the nethodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Co:pliance with 10 CTR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical sysrage atmospheric conditions. The release rate specifications for radionuclides in particulate form and tritium are dependent on the existing radionuclide pathways to man, !
in the unrestricted area. The pathways which were examined in the dev.elopment cf these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumptien by man, (3) deposition onto grassy areas where milk animals and nest producing animals graze with consumption of the milk and l test by can, and (4) deposition on the ground with subsequent exposure of man. l 3/4.11.2.4 {Ko Longer in Use) I 1.4-6 Revision 17 - May 1991 SEORERAM - UNIT 1 i I i l
RADI0 ACTIVE ITTLUENTS BASES 3/4.11.2.5 (No Longer in Use] 3/4.11.2.8 (No Longer in Use] - 3/4.11.4 TOTAL DOSE This Contol is provided to meet the dose limitations of 40 CTR Part 190 that have been incorporated into 10 CTR Part 20 by 46 TR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses from plant-generated radioactive affluents and direct radiation exceed 25 mrees to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mress. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MIMBER OF THE PUBLIC vill exceed the dos: limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within 40 CTR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose com=iteent to the MEMBER OF THE FUBLIC frem other uranium fuel cycle sources is' negligible, with the exception that dose contributions ~ fro: other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any HIN3ER OF THE PUBLIC is esticated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CTR Part 190 have not already been corrected), in accordance with the provisions of 40 CTR 190.11 and 10 CFR 20.405c, is considered to be a ticely request and fulfills the requirements of 40 CFR Part 190 until ERC staff action is completed. The variance only relates to the limits of 40 CTR Part 190, and does not apply in any way to the other require-ments for dose licitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEM3fR OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. SHOREHAM - UNI! 1 I.4-7 Revision 17 - May 1991
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of individuals resulting from station decontamination. This monitoring program implements Section IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. . The required detection cepabilities for environmental sample analyses are tabulated in tems of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a
~
particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection enc Quantitative Detemination - Application to Radiochemistry," Anal. Chem. 40,586-93(1958), and Hartwell, J. K.,
" Detection Limits for Racioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-5A-215 (June 1975).
Composite sampling and drinking water requirements are not applicable. No public drinking water supplies could be affected by the plant's discharge since groundwater drainage is to the north into Long Island Sound (ER 2.5.3.2). 3/4.12.2 LAND USE CENSUS This Control is provided to ensure that change: in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the The monitoring program are made if required by the results of this census. best survey information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements' of Section IV.B.3 of Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum 1.4-8 Revision 17 - May 1991 SHOREHAM - UNIT I
RADIOLOGICAL ENVIRONMENTAL MONITORING f BASES' . 3/4.12.2 LANDUSECENSUS'(Continued) . required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum gardensize,thefollowingassumptionswereused.(1)that20%ofthegarden. was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ square meter. 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and. accuracy of the measurements of radioactive material in environmental sample - matrices are performed as part of the Ruality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.
+
1.4-9 Revision 16 - July 1950 SHOREHAM - U'07 2 , . . . _ .- - - . .u
i.
$NPS-1 DDCM PART I. ,
SECTION 5 RADIOLOGICAL EFFLUENT CONTROLS SECTION 5.0 DESIGN FEATURES 4 I.5-0 Revision IE - July 1990
INDEX DESIGfi FEATURES PAGE SECTION 5.1 SITE SITE BOUNDARY for Radioactive Gaseous and Liquid I.5-3 Effluents.......................................... 1.5-1 Revision 16 - July 1990
INDEX LIST OF FIGURES FIGURE PAGE 5.1.3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS A N D U QUI D E FFLU E NTS. . ......... ......................... ...... l.5-4 l I l l I I y SHOREHAM - UNIT 1 1.52 UPA Revision 1 - February 1993 l _j
1 5.0 DESIGN FEATURES
-( L .j 5.1 SITE l
5.1.1 (Not Used) 5.1.2 (Not Used) , SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 The SITE BOUNDARY for radioactive gaseous and liquid affluents shall be as shown in Figure 5.1.3.
.l t
1 i i! 9 SHOREHAM - UNIT 1 1.5-3 LIPA Revision 1 - February 1993 , i l I
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SNPS-1 ODCM 7 PART I SECTION 6 i RADIOLOGICAL EFFLUENT C0hTROLS SECTION 6.0 ADMINISTRATIVE CONTROLS i 1.6-0 Revister. 16 - July 1990
INDEX ADMINISTRATIVE CONTROLS , h SECTION PAGE 6.8 REPORTING REQUIREMENTS i 6.8.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT............ l.6-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT............................. 1.6-2 ! i 6.13 OFFSITE DO S E C ALCUL ATIO N M A NU A L (ODCM)...................... ............. l.6-3 , i t t 6.15 MAJOR CHANGES TO RADIOACTIVE Lf 0UID. AND GASEOUS. WASTE TR E AT M E NT SY ST E M S . . . . . . . ... ... .. . ... .. ... . .. . . . . ... . ........... ....... .. l.6-4 1 1 t 4 i 1.6-1 LIPA Revision 1 - Feb 1993 i
ADMINISTR ATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 Routine Annual Radiological Environmental Operating Reports covering the operation 1 of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial. report shall be submitted prior to May 1 of the following year following initial criticality. The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Control 3.12.2. The Annual Radiological Envi onmental Operating Reports shallinclude the results of analysis of all radiological environmental samples of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as , well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological ; environmental monitoring program; at least two legible maps' covering all sampling locations , keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Control - 3.12.3: discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted annually, and the time between submission of the reports must be no longer than 12 months. : The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio- active Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis folbwing the format of Appendix B thereof. l
'One map shall cover stations near the SITE BOUNDARY; a second shallinclude the more distant stations.
f.6-2 LIPA Revision 1 - February 1993 SHOREHAM - UNIT 1 1 1
- =.
ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELE ASE REPORT (Continued) . The Annual Radioactive Effluent Release Report shallinclude an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in , the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of windspeed, wind direction and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include ' an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1.31) during the report period. All assumptions used in making these assessments (i.e., specific ~ activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents . (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). ; The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977. The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Annual Radioactive Effluent Release Reports shallinclude any changes made dur{ng the l i reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as fet ng of new locations f or dose calculations and/or environmental monitoring identified by the land use census pursuant to Control 3.12.2. 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM) See Technical Specification 6.13.
* 'In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on file,in a file that shall be provided to the NRC upon request.
SHOREHAM - UNIT 1 1.6-3 LIPA Revision 1 - Feb 1993
ADMINISTRATIVE CONTROL.S ( 6.15 M AJOR CH ANGESTO R ADIOACTIVE UQUID AND G ASEOUS WASTETREATMENT SYSTEMS 6.15.1 Licensee-initiated major changes to the radioactive waste treatment system (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release !
Report for the period in which the evaluation was reviewed by the Site Review Committee. The discussion of each change shall contain:
- 1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2. Sufficiert detailed information to totally support the reason for the change without benefit of additional or supplementalinformation;
- 3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;
- 4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from r those previously predicted in the license application and amendments thereto;
- 5. An evaluation of the change which shows the expected maxirnum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREAS and to the general population that differ from those previously estimated in the license application and amendments thereto; ,
- 6. A comparison of the predicted releases of radioactive materials,in liquid ,
and gaseous effluents, to the actual releases for the period prior to when the changes are to be made; ,
- 7. An estimate of the exposure to plant operating personnel as a result of the change; and
- 8. Documentation of the fact that the change was reviewed and found acceptable by the Site Review Committee. -
t
- b. Shall become effective upon review and acceptance by the SRC.
, SHOREHAM - UNIT 1 1.6-4 LIPA Revision 1 - February 1993
SNPS-1 ODCM ! PART il SECTION 1 INTRODUCTION The purpose of this manualis to show the calculational methodology and parameters used to comply with the Radiological Effluent Controls (REC, Part I) of the ODCM. Section 2 establishes methods to calculate the Liquid Effluent Monitor set point and the Gaseous Effluent Monitor set points in order to comply with REC Sections 3.11.1.1 and 3.11.2.1, respectively. Section 3 establishss dose calculational methods for liquid and gaseous effluents. The liquid of fluents dose calculation methods are used to show compliance with REC Sections 3.11.1.2 and 3.11.1.3. Fer liquid pathways, the dilution factor is one (1.0) (only service water pumps are discharging), The gaseous effluent dose calculation methoos are used to show compliance with REC Sections 3.11.2.1, 3.11.2.2, and 3.11.2.3. The atmospheric dispersion and deposition factors used in calculation methods were calculated based on onsite meteorological data for the 2-year period of October 1,1973 through September 30,1975. Regulatory Guide 1.109, Rev.1 (October 1977), Methodology and Parameters, were used in Method 2 (the Backup Method) dose rate and dose conversion factors. Tables 3.5-10,3.5-12 and 3.5-13 are incorporated only for future use if there is a change in the land use census which requires considering any combination of cow's milk and meat pathways. Section 4 identifies the receptor locations which represent critical pathway locations, water dilution, atmospheric dispersion, and deposition factors used in calculation Method 2. Table 4-1 summarizes the above factors for the gaseous effluent pathways. Section 5 indicates locations at which environmental sampling may be conducted. Section 6 addresses the Interlaboratory Comparison Program. BN1-11600.02 92 11. 1 - 1 LIPA Revision 1 - February 1993
SNPS-1 ODCM PART ll SECTION 2 ' SET POINTS 2.1 LIQUID EFFLUENT MONITOR SET POINTS (Compliance with Section 3.11.1.1 of the Radiological Effluent Controls (REC, Part 1 of the ODCM). The radionuclide concentrations released via liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration shall be limited to 2 x 10 pCi/ml. The set points of the effluent monitors are dependent on service water as follows:
- 1. The service water flow rate with the service water system composed of one ,
reactor building service water pump, having a capacity of 8600 gpm.
- 2. Flow rates of effluents from tanks and/or yard piping drain sump. '
- 3. Individual concentrations of gamma emitters (other than dissolved or entrained .
noble gases) and Sr-89, Sr-90, Fe-55, and H-3; and the total concentration of dissolved or entrained noble gases and gross concentration of the alpha emitters in the liquids to be discharged.
- 4. Maximum allowable concentration of 2 x 10-' Ci/ml for the total concentration of dissolved or entrained noble gases and maximum permissible concentrations (MPCs) of other gamma emitters, Sr-89, Sr-90, Fe-55, H-3, and alpha emitters ,
in the of fluents as specified in 10CFR20, Appendix B, Table II, Column 2 for an unrestricted area. NOTE. Precautions should be taken to assure that the service water system l flow rate used in determining the set point remains constant during the period of discharge. If the service water flow. rate during l discharge becomes less than the flow rate that was used in calculating the discharge set point, the discharge must be terminated and a new set point calculated. Reactor building salt water drain tank contents are released to the environment continuously.' The discharge waste sample tanks, recovery sample tanks, and yard piping drain sump contents will always be released to the environment as batch processes.
- The final release and draining of the water in the Spent Fuel Storage Pool through the Reactor Building Salt Water Drain Tank via the continuous release path and 1D11-PNL-079 to the Long Island Sound shall be considered a batch release and treated as such. Final draining of the SFSP shall be the only occasion for use of the Salt Water Drain Tank in a batch release mode.
BN1-11600.02-92 11. 2 . 1 - 1 LIPA Revision 1 - February 1993 [
l gNPS-1 ODCM l For batch as well as continuous releases, the sampling and analysis program shall be in accordance with the minimum requirements of REC Table 4.11.1.1.1-1. gpec. ! ifically, the analysis program will include the determination of gross alphs concentration of the alpha emitters. In addition, it will include isotopic anal-ysis for determination of individurl concentrations of principal samma amitters. I and the specific radionuclides, Sr-89, Sr-90. Fe-55, and E-3. It will also include the determination of total. concentration of 'the dissolved and entrained noble gases l (gassna emitters) in the liquids. The concentrations of individual samma emitters l are determined by gamma spectral analysis of 1) the batch sample prior to its , release for the batch releases and 2) the monthly grab sample for continuous i releases._ For gross alpha and the specific radionuclides Sr-89, Sr-90 Fe-55, and , E-3, if analysis cannot be performed prior to discharge, then the following concen-trations are used in the monitor set point calculations i Cross Alpha and E-3 i Cross alpha concentration and E-3 concentrations as determined by analysis of the i previous senthly composite sample for batch releases. For continuous releases gross alpha and E-3 concentrations are determined by analysis of previous sonthly . I grab sample. Sr-89. Sr-90, Te-55 ; Individual concentrations are determined by analysis of the previous quarterly composite sa:ple - f or batch releases. For continuous releases the individual concentrations are determined by analysis of the previous quarterly grab sample. Representative Samples Representative co:posite sa=ples utilized in determining the concentrations of E-3, St-89, Sr-90, Te-55, and the gross alpha concentration both for batch and contin-uous releases,and in determining the concentrations of gamma emitters (excluding dissolved and entrained noble gases) for continuous releases are obtained in accordance with the method stated f or obtaining such samples in the RIC Table 4.11.1.1.1-1. The tank contents are recirculated prior to obtaining samples for analysis. The minimum recirculation time t, shall be , t r* 2_v - I r , where: v = the volume of liquid in the tank to be sampled j f, = the recirculation flow rate being used to mix the tank contents. ] For the yard drain sump, the above methodology - vill be used unless it can be determined that there has been no condensate storage tank overflow events since the last batch release. Although designated a batch release, there' may be times when non-centacinated yard drain runof f to the sump will occur during the discharge period. This input vill not increase the discharge concentration. bel-11600.02-92 11.2.1-2 Revision 17 - May 1991 i
SNPS-1 ODCM ! ! The above methodology will ensure that a representative sample will be obtained for batch releases. Set Point Philosoohv The philosophy of the set points will be based on the sum of the ratios of isotopic concentrations to MPCs being less than 1 for discharges into unrestricted areas. Specifically: C=NE C3 HPC j.1 MPC3
- b n * + C
= + +,,,,,+ +
MFC, MPCy MPC, MFC, HPCa (2.1.1) i, C* Ct Cre
+ + . 31 MFC, MPCt MPC, p where:
C ,. 3C ,...... C = Concentration of the individual gamma emitting radionuclides identified ( Ci/ml) C, = The gross alpha concentration (pCi/ml) Ca = The total concentration of dissolved or entrained noble gases (gCi/ml) C. = The Sr-89 and Sr-90 concentrations (gCi/ml) C, = The H-3 concentration (pCi/ml) C,, = The Fe-55 concentration ( Ci/ml) MPC, = MPC,, MPC, ....., MPC,, MPC,, MPCa, MPC,, MPC,, MPC,, i
= the maximum permissible concentration of the respective radioisotope i (gCi/ml) from 10CFR20, Appendix B, Table il Column 2. For dissolved or entrained noble gases, the maximum allowable concentration (MPCo) will be 2.00E-04 ( Ci/m!). For gross alpha, the MPC assumed will be 3.00E-08
( Ci/ml). If the C/MPC calculated is greater than 1, then no release is possible. The normalization factor (as defined in Section 2.1.1) must be greater than 1 to permit releases. To permit releases, this factor can be increased to a value greater than 1 by increasing dilution flow F. (by running more service water pumps in the applicable discharge structure), and/or decreasing the ef fluent flow rates fo, f , etc. (defined in Section 2.1.1), and recalculate C/MPC using new C,in Equation 2.1-1. l BN1-11600.02-92 11. 2 . 1 - 3 LIPA Revision 1 - February 1993 i
SNPS-1 ODCM 2.1.1 Radiation Effluent Monitor (RE 13) Hioh/ Trio Alarm Set Point for Discharoe Weste Samole Tanks. Recovery Samole Tanks. or YARD Picino Drain Sumo The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges,if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will terminate the release. A sample is taken from any of the following tanks or sump which is to be discharged along with any streams which are in the process of being discharged.
- 1. Discharge waste tanks
- 2. Recovery sample tanks
- 3. Yard piping drain sump
- 4. Reactor building salt water drain tank Only one of the first three items above is discharged at any one time, which can be combined with releases from item 4.
Obtain the service water flow rate from the control room (see NOTE in Section 2.1). Define Normalizing factor F = Ifo + f, + F.)
*0.8 N
I (Cafo + C,f,) i=11 1 MPC, An isotopic analysis of each sample is performed. This analysis includes isotopic analysis for gamma emitters; gross alpha emitters: total dissolved or entrained noble gasi A; end Sr-89, Sr-90, Fe-55, and H-3. This should be done for all monitors. Then the set point (NOTE: the background (cpm),if it can be determined, is also added to the , set point value. If, however, it cannot be determined, it is considered as zero) for detector i RE-13 is calculated as: N l Su s F 'I C 3* E, (cpm) i=1 BN1-11600.02-92 11. 2 . 1 - 4 LIPA Revision 1 - February 1993 )
SNPS-1 ODCM where: i C. = concentration of radioisotope (i) (uCi/ml) in any of the following tanks or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump !
fo = Discharge flow rate (gpm) from any of the following tanks or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump.
(Maximum design discharge flow rate = 150 gpm) C = Reactor building salt water drain tank concentration of radioisotope (i) ( Ci/ml) fs = Reactor building salt water drain tank discharge flow rate (gpm). (Maximum design discharge flow rate = 100 gpm) Fe
= Total service water flow rate (gpm)
E, = Gamma counting efficiency of RE 13 for radionuclide (i) (cpm /pCi/ml). Figure 2.1-1 shows the energy response. For non-gamma emitters, E,=0. 0.8 = Safety factor MPC,is defined in Section 2.1. The above calculation is made for each batch to be released. After each batch release, the high alarm set point should be reset as close to the background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. BN1-11600-02 92 11. 2 . 1 5 LIPA Revision 1 - February 1993
l SNPS-1 ODCM 2.1.2 Radiation Effluent Monitor (RE-79) Hiah Alarm Set Point for Reactor Buildina Salt Water Drain Tank The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges,if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will alarm in the control room. A sample will be taken from the reactor building salt water drain tank discharge, along with individual samples of any of the following streams which may be in the process of being discharged:
- 1. Discharge waste sample tanks
- 2. Recovery sample tanks
- 3. Yard piping drain sump
- 4. Spent Fuel Storage Pool in the case of continuous release, samples will be taken as per requirement REC Table 4.1 1.1.1.1 - 1.*
Obtain the service water flow rate from the control room (see NOTE in Section 2.1). The set point for continuous or batch release (see NOTE in Section 2.1.1) will be calculated as follows: ~ - N S n :s F ' I C, E,
.i=1 .
(cpm) where: E, = Gamma counting efficiency of RE-79 for radionuclide i(cpm /pCi/ml). Figure 2.1-2 shows the energy response. For non-gamma emitters, E, = 0 , All other parameters are as defined in Section 2.1.1. 1 When the tank operates in a batch mode, the above calculation is made for each batch to be , released.' J The final release and draining of the water in the Spent Fuel Storage Pool through the Reactor Building Salt Water Drain Tank via the continuous release path and 1D11-PNL-079 to the Long Island Sound shall be considered a batch release and treated as such. Final draining of the SFSP shall be the only occasion for use of Salt Water Drain Tank in a batch release mode. BN1-11600-02-92 11. 2 . 1 - 6 LIPA Revision 1 - February 1993 [ , l
SNPS-1 ODCM i After each batch release ar continuous release period, the high alarm set point should be reset as close to the background as prac.tical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. ; 2,1.3 [No Longer in Use] 4 I I a BN1-11600.02-92 11. 2 . 1 - 7 LIPA Revision 1 - February 1993 l
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i SNPS-1 ODCM i 1 2.2 GASEOUS EFFLUENT MONITOR SET POINTS (Compliance with Section 3.11.2.1 of the REC) The high alarm set point for the Station Ventilation Exhaust Monitor (RE-42) is set in accordance with the dose rate limit for noble gases at the site boundary spec- , ified in Section 3.11.2.1 of the REC: ) l Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. 1 The set point for this monitor vill be determined based on the lover of the two set points calculated for: 1) the total body dose rate and 2) the skin dose rate, calculated respectively in Sections 2.2.1 and 2.2.2. BN1-11600.02-92 11.2.2-1 Revision 17 - May 1991 t
I l SNPS 1 ODCM _g The methodology of multiplying the observed cpm by the calculated scale factor will be used to obtain the set point in the range where the detector response is linear with changes in nuclide concentration. In the non-linear region, appropriate correction as derived from Figures 2.2-2 will be made. 2.2.1 Gaseous Effluent Monitor Hioh Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) 2.2.1.1 Gaseous Effluent Monitor Hioh Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Total Body Dose Rate
- 1. The net count rate (excluding background), CR (cpm), of the Station Ventilation Exhaust Noble Gas Radiation Monitor is given by:
CR = 108* C(Kr-85)
- E(Kr-85) (cpm) ,
where: E(Kr-85) = detector efficiency (cpm /pCi/cc) for RE-42 for Kr-85 as l provided in Figure 2.2-1. The linearity response for , RE-42 is shown in Figure 2.2-2. (
- 2. The noble gas total body dose rate is calculated using the following equation: l DR(Kr-85) = X/O
- V
- DFB (Kr-85)
- C (Kr-85) (mrem /yr) where:
DR(Kr-85) = predicted dose rate for (Kr 85) (mrem /yr), X/O = annual average X/O (sec/m*) at 366 meters NNE due to releases via the station ventilation exhaust point (6.6E-07 sec/m8), DFB(Kr-85) = total body dose rate conversion factor (mrem /yr/pCi/m*), ! from Table 2.2-1, t I C(Kr 85) = isotope release concentration (pCi/cc) " sampling not required", , i V = station ventilation exhaust rate (cc/sec). (Maximum exhaust I rate = 1.73E + 08 cc/sec (3.66E+05 cfm).) l l BN1-11600.02-92 11. 2 . 2 - 2 LIPA Revision 1 - February 1993
l l SNPS 1 ODCM
- 3. The isotopic release activity concentration is normalized to a total body dose rate of 500 mrem /yr by multiplying by the following normalizing factor:
F. = 500/ DR (Kr-85)
- 4. From the above, the set point (see NOTE in Section 2.1.1) based on total body dose rate can be calculated as follows:
S'u s 0.8
- F,
- CR = 0.8
- 500
- E(Kr-8 5)
- 10 8 (cpm)
X/O
- V
- DFB(Kr-85) where:
S) = high alarm set point that results in a total body dose rate of less than 500 mrem /yr, F. = normalization factor (unitiess), CR = station ventilation exhaust noble gas radiation monitor count rate (cpm), and 0.8 = safety factor. , 2.2.1.2 Gaseous Effluent Monitor Hiah Afarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate
- 1. The net count rate (excluding background), CR (cpm), of the station ventilation .
exhaust noble gas radiation monitor is given as noted in Section 2.2.1.
- 2. The noble gases beta and gamma skin dose rate is given the following equation:
DR(Kr-85) = X/O
- V
- K(Kr-85)* C(Kr-85) tmW/) >
sim . where: DR(Kr-85) = predicted dose rate for Kr-85 (mrem /yr), i 1 l l BN1-11600.02-92 11. 2 . 2 - 3 LIPA Revision 1 - February 1993
i SNPS-1 ODCM X/O - = annual average X/O (sec/m') at 366 meters NNE due to releases via the station ventilation exhaust point, (6.6E 07 sec/m'), - K(Kr-85) = skin dose rate conversion factor (mram/yr/pCi/m'), from < sim Table 2.2-1, C(Kr 85) = isotope release concentration (pCi/cc) sampling not required,' j V '= station ventilation exhaust rate (cc/sec). (Maximum exhaust rate' = 1.73E+08 cc/sec (3.66E+05 cfm).)
- 3. The isotopic release activity concentration is normalized to a skin dose rate of 3000 mrem /yr by multiplying by the following normalizing factor:
F = 3000/ DR(Kr-85)
- 4. From the above, the alarm set point (see NOTE in Section 2.1.1), based on skin dose rate, can be calculated as follows:
- . l S4 s 0.8
- F,
- CR = 0.8
- 3000
- EfKr-85)
- 104 (cpm) !
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- V
- K. (Kr-85)
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== = =- = 10EAL CURVE FIGURE 11-1 t CALIBRATION CURVE (DATA CON 5tSTENT WITH LINEARITY RESPONSE CURVE FOR riouRE a.: u . DETECTOR RE-42 i l
SHOREHAM NUCLE AR POWER STATION-UNIT 1 OFFSITE DOSE CALCULATION W ANUAL l REVISION 1-AUGUST 1983 I i 1 1
SNPS-1 ODCM PART 11 SECTION 3 DOSE CALCULATION METHODS This section presents the calculational specifics requn ed to demonstrate compliance with the , following Radiological Effluent Controls (REC, Part I of the ODCM sections. 3.11.1.2 - Liquid Effluent Dose Calculation 3.11.1.3 - Operation of Liquid Radwaste Treatment System 3.11.2.1 - Gaseous Effluent Dose Rate f 3.11.2.2 - Noble Gas Air Dose 3.11.2.3 - Gaseous Effluent Dose From Radiciodines, Tritium, and , Radionuclides in Particulate Form Calculation methods are based on the equation and calculational methods described in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of i' Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1." Two methods are provided for each analysis. The first method is the method used by the computerized radiation monitoring system. Method 2 is a backup hand calculational method to be used only if the computer is not functional. The Annual Effluent Release Report is produced and the land use census is evaluated using ( NRC codes which implement Regulatory Guide 1.109. . i t i BN1-11600.02 92 11. 3 . 0 - 1 LIPA Revision 1 - Feb 1993 l
l l l l l SNPS-1 ODCM l ( 3.1 1.lOUID EFFLUENT, DOSE CALCULATION To comply with Section 3.11.1.2 of the REC, the liquid effluents released to unrestricted J areas shall be limited:
- 1. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 mrem to any organ.
- 2. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrem to any organ.
The site boundary for liquid effluents is shown in Part i Figure 5.1-3. The liquid radwaste system modelis shown in Figure 3.1-1 with corresponding flow diagram shown in Figure 3.1-1 A. The proposed liquid radwaste system models are shown in Figures 3.1-2 thru 3.1-7 with their corresponding flow diagrams given in Figures 3.1-2A thru 3.1-7A. Details of the propsoed phases of the decommissioning changes are defined in Table 3.1-3. 3.1.1 Method it (Comouterized Method) The equations which fo!!ow are used by the computer software to calculate the offsite doses due to release of liquid radwaste. For this dose calculation the actual concentration to be discharged by isotope,.the total volume of liquid to be discharged, and the number of service water pumps running, supplied by the operator, shall be used. The software computes the isotopic releases by multiplying the lab measurements by the volume of the liquid to be released: O, = 3.785 x 10-8 V q, where: O, = totalinventory of isotope lin the liquid to be released (Ci) q, = concentration of isotope iin the liquid to be discharged (as measured in laboratory) (gCi/cc) V = volume of liquid to be discharged (gallons) 3.785 x 10'8 = [(Ci/pCil (cc/ gal)] The dose equations which follow are from Regulatory Guide 1.109, with minor modifications. They are employed for the computation of dose from any aingle batch discharge (continuous discharges are handled as batch discharges in the computerized method). Weekly and quarterly cumulative doses are also calculated and stored in data files for reporting. (a) Oroan Dose Due to incestion of Saft Water Fish R'* * = 57.4/(K2 + 0.930 K3 ) U" I O, B* DFI,,e 8*
*
- part +1
- for service water BN1-11600.02-92 11. 3 . 1 - 1 LIPA Revision 1 - Feb.1993 l
l I SNPS-1 ODCM where: R** '*
* = dose to organ j of individual in age group a due to ingestion of fish contaminated with particulates and radioiodines (mrem) (Ref. Reg. Guide 1.109, with the following special values:
- F (flow rate of liquid effluent) is represented by product K.
- F ,,,
Ift*/sec), where K,is the number of pumps of system m operating and F ,,,, is the flow rate per unit pump. For the reactor building service water system, m = 2;
- F . = 8,600 [gpm] = 19.16 [ft*/sec)
- F ,, = 8,000 [gpml = 17.82 [ft*/sec)
- M,(mixing ratio at the point of exposure)
= 1.0 if service water is in use.
- Og (dose factor) = DFI,(see below)
- t,(transit time required for nuclides to reach the point of exposure) = 24 [hr)(see pg 1.109-12 of the Regulatory Guide)
U" = fish consumption rate by individual in age group a Ikglyr) (from Table E-5 of the Guide, for maximum individual) K. = r$ umber of pumps of system m operating Q, = total activity of isotope i released ICil, from above
= Bioaccumulation factor for saltwater fish [(pCi/kg)/ (pCi/ liter)I (from Table A-1 of the Guide)
DF1, = dose conversion factor for nuclide i to organ j of individual in age group a due to ingestion [ mrem /pCi ingested) (from Tables E-11 through E-14 of the Guide) A, = radionuclide decay constant [hrd ) (from Table 3.1-1) 57.4 = 1100/F ,3
= 1100/19.16 [(pCi/f)/(Ci/yr)) for reactor building service water O.930 = F ,3/Fm, part +1 = 68 particulates and 5 iodines in the summation sign (b) Oroan Dose Due to inoestion of Salt Water Invertebrate R'* *" = 57.4/(K2 + 0.930 K 3) U'" I Q, B6 " DFI,e2 *
*
- pad +1
- for service water II.3.1-2 1. IPA Revision 1 - February 1993 BN1-11600.02-92
SNPS-1 ODCM where: R* * = dose to organ j of individual in age group a due to the
> ingestion of saltwaterinvertebrate contaminated with radioective particulates and iodines [mram] (Ref.: Reg. Guide 1.109 Eq. A-3 with the special values identified in the fish-ingestion equation above)
B* = Bioaccumulation factor for saltwater invertebrate
* [(pCi/kg)/(pCi/ liter)] (from Table A-1 of the Guide)
U* = invertebrate consumption rate by individual in age group a
* [kglyr) (from Table E-5 of the Guide, Gor maximum individual)
(c) lotal Body Dese From Shoreline Denosits R***. = 82.9/(K, + 0.930 K 3) U*** I O, DFG, .1 e 4 b'i. service water
**
- part +1 A, where:
R*** = tctal body dose to individual in age group a from shoreline de-
"' posits [ mrem] (Ref.: Reg. Guide 1.109 Eq. A-7 with the follow-ing special values:
- F(flow rate of liquid effluent) is represented by the product K,*Fm,, [ft*/sec], where K,is the number of operating pumps of system m and Fm,,is the flow rate per unit pump For the reactor building service water system, m = 2;
- F,,, = 8,600 [gpm) = 19.16 [ft*/sec]
- M, (mixing ratio) = 1.0 if service water is in use
- W (shore-width factor that describes the geometry of the ,
exposure) = 0.5 for ocean site (from Table A-2 of the guide)
- t, (transit time from source to shoreline) = 0 (see Reg.
Guide pg 1.109-69, for Eq. A-7)
- T (radionuclide half life, days) = 0.693/(24A,) where 0.693 = log,2 and A,is the decay constant in [hr']
- D, = DFG, (see below)
= shoreline exposure time for individual in age group a [hr/yr] (from Table E-5 of the Guide, for maximum individual)
BN1-11600-92 11. 3 . 1 - 3 LIPA Revision 1 - February 1993 i l l
SNPS-1 ODCM K. = number of pumps of system m operating 0, = total activity of isotope i released ICil, from above DFG, = total body conversion factor for standing on contaminated ground (shore) [(mrem /hr)/(pCi/m')] (from Table E 6 of the guide)
- t. = time period over which accumulation is evaluated (15 years, or 1.314 x 10 5hours) 82.9 = 110,000W (T,4.) F [(pCi/t)/(Ci/yr)]
= 110,000 x 0.5 x (0.693/24)/19.16 for reactor building service water 0.930 = F3/Fm part + 1 = 68 particulates and 5 lodines in the summation sign (d) Skin Dose From Shoreline Deoosits R*** = 82.9/(K + 0.930 K ) U*** I Q, DFGa .1-e 'b'i.
"*
- part +1 A, for service water where:
R*** = skin dose to individual in age group a from shoreline deposits
"" [ mrem]; (Ref.: Reg. Guide 1.109 Eq. A-7 with the special values listed for the total body dose)
DFGa = skin dose conversion factor for standing on contaminated ground (shore) ((mrem /hr)/(pCi/m8)) (from Table E-6 of the Guide) Other parameters are as defined earlier for the total body dose from shoreline deposits. (e) Total Doses ) The individual dose components described in items (a), (b), (c), and (d' above are summed in the following way for the computation of total doses: R, = RN " + R*
- R, = R"5 " + R* * + R***
. 4. .
R, = R*** e. BN1-11600-92 11. 3 . 1 4 LIPA Revision 1 - February 1993 4
SNPS-1 ODCM where: R, = total dose to organ j (exclusive of the total body) of individual in age group a due to the ingestion of fish and invertebrate (mrem) R, = total dose to the total body of individual in age group a due to the ingestion of fish and invertebrates, and direct radiation from shoreline deposits and R, = total dose to the skin of an individual in age group a from shoreline deposits (mrem). 3.1.2 Method 2: (Backoo Method) The dose contributions for the total release period shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression: N M D, = I ( A, ,.,iat, C ,F,] (3.1-1) i=1 . where: Dr = the cumulative dose or dose commitment (mrem) to the total body or an organ from the liquid effluents for the total release period M E At, f=1 At, = the length of the f. release period over which C, and F, are averaged for all liquid released (minutes), ) C,, = the average concentration of radionuclide Ci in undiluted liquid effluent during release period At, from any liquid release (pCi/cc), A,, = the site-related ingestion dose or d%f mrkr,'itment factor to the total body or any organ for each identifid?, principait ;amma and beta emitter listed in Table 3.1-2 (mrem / min per pCi/cc), see Appendix A for derivation F, = Undilated liould effluent flow rate ' F/M, F, = total service water flow rate M, (Mixing factor) = 1.0 if service water only is in use BN1-11600-92 11. 3 . 1 - 5 LIPA Revision 1 - February 1993 l
l SNPS-1 ODCM , The total dose from liquid affluents from all discharges, Dru,is: Dru = D,o + D, + D, + D, l whors: D,o = Dose contribution from discharge waste sample tanks as calculated in Equation 3.1-1 . D, = Dose contribution from recovery sample tanks as calculated in Equation 3.1-1 , D,. = Dose contribution from reactor building salt water drain tank as calculated in Equation 3.1-1 D ,,, = Dose contribution from yard piping drain sump as calculated in Equation 3.1-1. If the calculated total dose exceeds the limit specified in Section 3.1, consult REC Section , 3.11.1.2.
.t 1
r h i BN1-11600.02-92 11.3.1-6 LIPA Revision 1 - February 1993
SNPS-1 ODCM
- TABLE 3.1-1 DECAYCONSTANTS(1/hr)
Radio- Radiol nuclide Constant nuclide Constant - H-3 6.40BE-06 Ru-103 7.300E-04
.C-14 1.379E-08 Ru-105 1.600E-01 Na-24 4.600E-02 Ru-106 7.800E-05 P-32 2.000E-03 Ag-110m 1.100E-04 Cr-51 1.044E-03 Te-125m 5.000E-04 Mn-54 9.252E-05 Te-127m 2.600E-04 Mn-56 2.700E-01 Te-127 7.400E-02 2.930E-05 Te-129m 8.600E-04 Fe-55 6.480E-04 Te-129 5.900E-01 Fe-59 4.06BE-04 Te-131m 2.300E-02 Co-58 1.501E-05 Te-131 1.700E+00 Co-60 -
B.600E-07 Te-132 B.900E-03 Ni-63 5.600E-02 Ni-65 2.700E-01 1-130 5.400E-02 1-131 3.593E-03 Cu-64 1.184E-04 1-132 3.000E-01 2n-65 3.334E-02 2n-69 7.295E-01 1-133 2.900E-01 1-134 7.900E-01 Br-83 1.100E-01 1-135 Br-84 1.300E+00 1.449E+01 Cs-134 3.852E-05 Br-85 2.203E-03 Rb-86 1.500E-03 Cs-136 2.400E+00 Cs-137 2.635E-06 Rb-BB 2.700E+00 Cs-138 1.300E+00 Rb-89 5.724E-04 Be-139 5.000E-01 Sr-89 2.257E-03 Sr-90 ~ 2.776E-06 Ba-140 7.300E-02 Ba-141 2.300E+00 Sr-91 3.900E+00 Sr-92 2.600E-01 Ba-142 1.100E-02 La-140 1.700E-02 Y-90 B.300E-01 La-142 4.500E-01 Y-51m 4.900E-04 Ce-141 B.892E-04 Y-91 2.100E-02 Y-92 2.00E-01 Ce-143 6.800E-02 Ce-144 1.019E-04 Y-93 2.100E-03 2r-95 4.392E-04 Pr-143 i 4.200E-02 Pr-144 2.400E400 Zr-97 2.600E-03 B.200E-04 Nd-147 Nb-95 2.900E-02 Mo-99 1,000E-02 W-187 1.200E-01 Np-239 1.200E-02 Tc.99m Tc-101 2.900E+00 1 of 1 . Revision 3 - December 1983 BN1-11600-312
S,-. 3-1 ODCM TABLE 3.1-2 ADULT DOSE RATE CONVERSION FACTORS"', A, FOR (FISH AND INVERTEBRATE) INGESTION PATHWAY
. (mrem / min per pCi/cc)
Nuclide Bone Liv _gt T. Body Thyroid Kidney LUDn GI-LLI H-3 -(1) 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.7E + 01 C-14 2.4E + 02 4.7E + 01 4.7E + 01 4.7E + 01 4.7E +01 4.7E + 01 F-18 1.2E-05 - 1.4E-06 - - - 3.7E-07 NA 24 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 P-32 2.6E + 05 1.6E + 04 1.0E + 04 - - - 3.0E + 04 CR-51 - - 9.0E-02 5.3E-02 2.0E-02 1.2E-01 2.2E + 01 MN-54 - 1.2E + 02 2.2E + 01 - 3.4E + 01 - 3.5E+02 MN-56 - 4.6E-03 8.1 E-04 - 5.9E-03 - 1.4E-01 FE-55 8.3E + 02 5.8E + 02 1.4E + 02 - - 3.2E+02 3.3E + 02 FE-59 1.3E + 03 3.1 E + 03 1.2E + 03 - - 8.6E + 02 1.OE + 04 CO-58 - 9.8E + 00 2.2E + 01 - - - 2.0E + 02 CO-60 - 2.8E + 01 6.3E + 01 - - - 5.4E +02 NI-63 8.1 E + 02 5.6E + 01 2.7E + 01 - - - 1.2E + 01 NI65 4.8E-03 6.2E-04 2.9E-04 - - - 1.6E-02 CU-64 - 9.6E-01 4.5E-01 - 2.4E + 00 - 8.2E + 01 ' ZN-65 2.7E + 03 8.4E + 03 3.8E + 03 - 5.6E+03 - 5.3E+03 - ZN-69M 1.7E + 00 3.3E + 00 2.2E-01 - 2.1 E + 00 - 4.9E-01 BR-83 - - 1.1 E-06 - - - 1.6E-06 BR 84 - - 2.7E- 17 - - - RB-86 - 9.8E + 00 4.6E + 00 - - - 1.9E + 00 SR-89 8.1 E + 01 - 2.3E + 00 - - - 1.3E + 01 SR-90 2.0E + 03 - 5.0E + 02 - - - 5.8E + 01 2.6E-01 1.0E-02 - - - 1.2E + 00 SR-91 - SR-92 1.2E-03 - 5.3E-05 - - - 2.4E-02 Y-90 7.6E-02 - 2.1 E-03 - - - 8.2E + 02 Y-91 M 1.9E-12 - 7.2E-14 - - - 5.4E- 12 Y-91 1.4E + 00 - 3.9E-02 - - - 8.0E +02 Y-92 7.9E-05 - 2.3E-06 - - - 1.4E + 00 Y-93 5.4E-03 - 1.5E-04 - - - 1.8E + 02 ZR-95 2.6E-01 ' 8.3E-02 5.6E-02 - 1.3E-01 - 2.6E+ 02 BN1-11600-118 1 of 3 - Revision 3 - December 1983
M NwCNNOMMNumQu@mCamOmmNNO CQ@mNmNNNN @ w OOOOOOOOOOOOOOONOOOQQwCO s+++++++++ a+ a+ e+ e+ ONCOOOOOOO
+ 8 s++ e++++
m e W +++ s e 4 W WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW L s wewe Ce Ne O e m e eNeNeN v.C.o.m eO w m eNe w Neae @e eNe O e eNe Oe emg Oe ewe M e eM m w @ m o 4 m e e W C MNMNNN*mmmMNNN@mWwmWWmmwmMMmmWWammw U m O nom @ON M C O OQQwmo e + +++ e e e C D W W me WWWWWW mMNNMW D C We e e e e e e e M 3 - J 4 8 Sm8 8 I BM 4 I t 8 I 4 8 0 1 8 8 0 9 $NMNmMn8 8 8 8 8 9 > W K MOOwONum mmmmkommmowommmmmmON NMmN h 0C000000 0C000CmOQ00000000mmO e+ e+ s+ e+ e+ e e+++ a s e 0000 e e e e W e++ e+ e++ ++ WWWW C WWWWWWWW WWWWWWWWWWWWWWWWWWWW WmMm t e
@CNN@mwN e e e e o e e e wN.ONmmNNmmNNNM@wNNwm e e e e e e e e e e e e e e e e e e o e e e M mvMm@wmv 9mMm@m@mmNCmmNamN@mmm 8 tamNN m
.O g5W O w t NOONOCOmOwmNNMO M O
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~
p b COOOOOO"e+OOOOOO a++ e+ WWWWWWWWWWWWWWW e+ + + e+ 4 + b Q m m e h *CMCamOmONmmewM e e o e e e e e e e e e e o e N L 2 . E M W l 4 4 0 8 l i e. GmwNamNm-NwmmmNme S I S 4 0 0 8 0 0 8 8 m . W 4 m l C W h wC=w=MC=O*OMOmmOOmOw-ONN-NemOMmMwam t COCOOOOOOOOOOOONOQQCQwCCComOOCCOOOO e + e e e s+++ e+ a+ a e s+ e+ e e e s+++ e+ e e e e e e C e C WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW
. @e em -e Cewe eM Ne w C.N.a.w.w.m.w =eN
. e Oe eNeme me eme O e eNeNe M wewe Ne M m N m.@.m.
e e W WNMwNmMwwwmmN@mwmNNmNwMNMmMNmNMwwmW MOOm -NCOMOCMOO*CwmmNNmNmONMMNCON COCO COOOOOOONQQOCOOOOCCmwCOCOCOO L' e++ +e++ e+ e e e+ 4 + s e e e+++ e e a e e e++ e 0 WWWW e WWWWWWWWWWWWWWWWWWWWWWWWWWWW
> -O@m weme m e ememe @e eCewe w eN e O e eNeMe @ o eweme N w o o m.N @eNNwN@ e e e e e w e e e e W wwmM 8 0 INQmMWmm@mmmwMmmWNwNNmM@mMwmM MO mom-* CONwmOmomOTmONNmNWNmN@NMON OC OOOOO C00000mO000CmO00CmO0000000 e+++ e+
e+ e+ s++ ++e+ e+ 8 + 8 + 4 e e e e a e s + a W WW WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW mmmmWNMMNWMNmmmmmm@m@NNmOmm C c w. N. Me N e. @ @e e e e e e e e e e e e e e e e e e e e e e e e e e e o m mN 8mmMNNwMCNmNamNmMmmmMmmmMENmNmWNm @ m m e 8 e r xx x x @ t w Emm@QwmNNommmN Nmm&OOO-NNNNNNMMMOmNMwmMMMMMwwwwwww wcNmmOONmMwM = a m mgmmmmmmmmmw=mmmmMMMMMMmmmmmmmmmmmm
- 8 U e e e e 8 8 I O O I 8 0 t 6 8 8 8mmmmmm 9 4 0 9 9 0 0 8 4 4 4 0 E E
O McCWOOOCCWWWWWWWW NzErggECmWWWWWWWWmm""amWWWW@mWWWWUh 8 8 e 8 8 $mmmMCCCCWWWE C
SNPS-1 ODCH TABLE 3.1-2 (CONT'D) Nuc11de Bone liver T. Rody Thyroid Kidney Lung GI-LLI ND-147 6.lE-02 7.lE-02 4.2E-03 - 4.lE-02 - 3.4E+02 W-IR7 . 7.5E-02 6.3E-02 2.2E-02 - - - 2.lE+01 NP-239 4.3E-04 4.2E-05 2.3E-05 - 1.3E-04 - 8.7E+00 (1) The dash (-) indicates insufficient data or that the dose factor is <l.0E-20. m RM1-Il600-Il6 3 of 3 Revision 3 - December 1983
Page 1 of 3 I Table 3.1-3 This Table summarizes the activities of system G-11 (Liquid Radwaste System) decommissioning as a function of the proposed decommissioning phases and relates the decommissioning pha.,e (at its completion) to a representative ODCM figure. Phases ilD-1 and ilD-2 also show the tie-in of the G11 system to the G41 system (Fuel Pool cool and clesnup). Details of the proposed phases (with the exception of decom phase 0 and the corresponding ODCM Figures 3.1-1 and 3.1-1 A are subject to change. The corresponding figures are, therefore, to be regarded as 'For information Only'. ODCM DECOM FIGURE PHASE MAJOR COMPONENTS TO BE DECOMMISSlQRED. 3.1-1 0 This figure shows the existing G-11 Liquid Radwaste System 3.1-1 A 3.1-2 1 1. Phase Separator Tanks (TK-107 A & B) 3.1 -2A 2. Evaporator Sub-system: Waste and Regenerant Evaporators
- 3. Laundry Drain Tanks (TK-020 A & B) 3.1 3 IIA 1. TB Floor Drain Sumps (TK-053 A & B) 3.1-3 A 2. Decontamination Area Sump (TK-012)
- 3. Drywell Equipment Drain Tank (TK-049)
- 4. Rx Equipment Drain Sumps (TK-050 A & B)
- 5. Rx Floor Drain Sump (TK-056C)
- 6. Recovery Sample Tank B (TK-069 B)
- 7. Redwaste Demineralizer B (DE-OO1 B)
- 8. Discharge Waste Sample Tank B (TK-068 B)
- 9. Floor Drain Collector Tanks (TK-061 A & B) 3.1-4 IIB 1. Rx Floor Drain Sump B (TK-056 B) 3.1-4 A 2. Regenerant Evaporator Feed Tanks (TK-060 A & B)
- 3. Waste Collector Tank B (TK-010 B)
- 4. Discharge Waste Sample Tank A (TK-068 A)
- 5. Radwaste Filter B (FL-014 B)
- 6. Floor Drain Filter (FL-012) 3.1-5 llc 1. Rx Floor Drain Sump A (TK-056 A) 3.1-5 A 2. Drywell Floor Drain Tank (TK-049)
- 3. Radwaste Filter A (FL-014 A)
- 4. Redwaste Demineralizer A (DE-001 A)
- 5. Spent Resin Tank (TK-062) 3.1-6 IID 1. Radwaste Equipment Drain Sump (TK-071) 3.1-6A 2. Radwaste Floor Drain Sump (TK-054)
- 3. Recovery Sample Tank A (TK-069 A)
- Discharge sampling function is shifted to the remaining Waste Co!!ector Tank (TK-010 A) and 1011-PNL-013 (RE-013) in operation LIPA Revision 1 - February 1993
Page 2 of 3 I Table 3.1-3 [ Cont'd) ODCM DECOM flGURE PHASE MAJOR COMPONENTS TO BE DECOMMISSIONED 3.1-7 IID-2 Alternate path to Phase llD-1: 3.1-7A 1. Radweste Equipment Drain Sump (TK-071) *
- 2. Radwaste Floor Drain Sump (TK-054)
- 3. Recovery Sample Tank A (TK469A) *
- 4. Waste Collector Tank A (TK-010A)
Discharge sampling function is shifted to Salt Water Drain Tank (TK-190) and 1011-PNL 079 (RE 079)in operation. r I i l l l LIPA Revision 1 - February 1993 l
+
I Page 3 of 3 Table 3.1-3 (Cont'd] ' l LIQUID RADWASTE TREATMENT CAPABILITY AT COMPLETION OF VARIOUS l I PHASES OF G-11 SYSTEM DECOMMISSIONING
- ExJsting capability before G-11 decommissioning PHASES O & 1* PHASE IIA PHASEffC PHASE flD PHASE I!B COLLECTION Floor Drain Cottector Tcnks (TK 061 A&B)
Regenerant Liquid Regenerant Uguid Evaporator Feed Evaporator Feed Tanks Tanks (TK-060 A&B) (TK-060 A&B) Waste Collector Waste Collector Recovery Sample Waste Cettector Waste Collector Tanks Tcnks (TK-010 A&B) (TK-010 A&B) Tank A (TK-010 A) Tank A (TK-010 A) Tank A (TK-089 A) (Decommissioned at and of Phase 110) TOCESSING daste Evaporator (E-043) Regenerant Mobile Filter and Mobile Fitter and Evaporator Demineralizer Demineralizer (E-044) (Dismantled at end of Phase llD) Floor Drain Fitter Floor Drain Fitter (FL-012) (FL-012) Radwaste Fitters Radwaste Fitters Radwaste Fitter A (FL-014 A&B) (FL-014 A&B) (FL-014 A) Radwaste Demin. Radwaste Demin. A Radwaste Demin. (DE-001 A&B) (DE401 A) A (DE 001 A) DISCHARGE Discharge Waste Discharge Waste Sample Tanks Sample Tank A (TK-068) A&B) (TK 068A) Recovery Sample Recovery Sample Tank Recovery Sample Recovery Sample Recovery Sample Tanks (TK-069 A&B) A (TK-069 A) Tank A (TK-069 A) Tank A (TK-069 A) Tanks A (TK-069 A) (Decommissioned at end of Phase IID) UPA Revision 1 - February 1993 1
FLOOR DRAIN FLOOR DRAIN COLLECTOR TANK FILTER MOBILE FILTER /DEMIN. [ MFD) CIRCULATING WATER TUNNEL WASTE l l DISCHARGE EVAPORATOR WASTE TANK RE 13 o WASTE RADWASTE RECOVERY COLLECTOR DEMINERALIZER/ SAMPLE TANK FILTER TANK YARD PIPING DRAIN SUMP REGENERANT
~
EVDORATOR 55hACTOR BUILDING SALT WATER DRAIN TANK (RBSWDT) RE-79 TO FIGURE 3.1-1 SOUN LIQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL LIPA REVISION 1, FEB.1993
r - i - i - i . i , . i ~ i . i, o w- gj q--- 7 I I
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UQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STATON, UNIT 1 OFFSITE DOSE CALCULATION MANUAL UPAREVISION 1.FEB.1993
. c.
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SALT WATER DRAIN TANK , t (RBSWDT) RE-70 , TO FIGURE 3.1-2 sOUN , LIQUID RADWASTE SYSTEM MODEL ; SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL ; LIPA REVISION 1, FEB.1993 i
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ii. l ii. I!I ll i -~ - , FIGURE 3.1-2A UQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STATON, UNIT 1 OFFSITE DOSE CALCULATON MANU'- , UPA REVISION 1. FEB.19931 i
FLOOR DRAIN FILTER . , MOBILE
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/
WASTE RADWASTE RECOVERY SAMPLE COLLECTOR DEMINERAllZER/ TANK FILTER *A' TANK 'A' i 1 l YARD PIPING DRAIN SUMP i REACTOR BUILDING ..! SALT WATER _ y DRAIN TANK i (RBSWDT) . RE 70 , i TO. .I
~ LONG ISLAND i FIGURE 3.1-3 SOUND- ,
LIQUID RADWASTE SYSTEM MODEL ; SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL 'l LlPA REVISION 1 FEB.1993 -l . l l l et , - - - , .---m ..w.., . y -, -. . . _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _
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[ ,q -,l - fi .
^
Eg i l g _ IlP 1.1 gjg
= gl i _
I di- e _ n g. _y Ia a, l <
~~
g I I l - Idi- d7 l -il l gl t I di- EL_l,_ li = " I I . l p i!
. :=l E ; 7 "
i .
t t Il "B Is i 4i elgi ll-2 j, ll C ei- ).
a[ [l 9, ein - 4 i c> 1 l 6
- I $I" Dl
< i ei. e lll: !l w l
w l1 i 0
- l _ }
li r i g . t a l _
. _ r - - l - -- -- - 7 .
I ll l et! I _ a L - - r- - i
< < > ill l !
m l l = l
. I j i I
- I i
's- 1 i r ---- j---E il -
i i I, 1
- it.
l llil- - I .I"I s - I li , ll i _ FIGURE 3.1-SA UQUID RADWASTE SYSTEM MODEL
- - . SHOREHAM NUCLEAR POWER STATON, UNIT 1 OFFSITE DOSE CALCULATION MANUAL UPA REVISIO'N 1, FEB.1995 1 e
^
( MOBILE FILTER /DEMIN. (MFD) CIRCULATING WATER TUNNEL RE-18 o WASTE RADWASTE RECOVERY
. COLLECTOR DEMINERALIZER/ SAMPLE i TANK 'A' FILTER *A' TANK 'A' ,
YARD PIPING DRAIN SUMP I l REACTOR BUILDING'- SALT WATER I DRAIN TANK (RBSWDT) RE 70 To FIGURE 3.1-4 sOUN ,, j LIQUID RADWASTE SYSTEM MODEL ! SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL LIPA REVISION 1, FEB.1993 -) 1 i
r r -- i - i i .
. . i- i . m w- gr .
, il --
ll rl 1
. i t
=
t . \, - - l E ,y 8 id 11 f . In L lI -
)
11 I = X i _ v ', ,,. c lli .Ig -
-Illb- I,
=
i .
.g Il 3 l 1 1-I -ilIH lj ls,la i
= ;.
= . l =
3: l i l . l
. E.l.
l . sis it "l' l: il Os v is eIIj _
'k i n.
[i( i i - ). I
. 31u D
Idi - oc>lg . 55 E
' t w-
! y l g I ! g . __._f__,__.__., 3
. ! 11 i .4 i =
o i l t
-_.r---q l
-,iill l i s I I. '
l . I I l I l . 1 i!li l-fi] i r----h- iji Ili l
=
=:IIiil! _T'j 1 FIGURE 3.1-4A UQUID RADWASTE SYSTEM MODEL SHOREHAM NUCt. EAR POWER STATON, UNIT 1 OFFSITE DOSE CALCULATON MANUAL ,
~
. UPAREVISION1 FEB.1993 l
MOBILE .
!- 1 FILTER /DEMIN.
4 (MFD] ; CIRCULATING WATER TUNNEL RE 18 h WASTE RECOVERY
, COLLECTOR SAMPLE TANK 'A' TANK 'A' .s YARD PIPING DRAIN SUMP REACTOR BUILDING -
8 ALT WATER - DRAIN TANK (RBSWDT) RE 79 FIGURE 3.15 son , LIQUID RADWASTE SYSTEM MODEL , SHOREHAM NUCLEAR POWER STATION UNIT 1 ' OFFSITE DOSE CALCULATION MANUAL LIPA REVISION 1, FEB.1993 l .. ;
i- i . , r - i - i , i < . . . !
- e- gi ,
, i} --
I,I r 'i_I.. .... ,
!lI L
al lI tg L i
,l -
tl
= _
e lg i ai. = i .
- [ -illF- l,g ay -
g i t-i lj :. 1 -illH i
=
l ,. l., [ li l - n- 1
'in%
gb it I-j! e ll i n. - er
. *au -
o 55
$5 .
w U o _ y I
. _. _ . _ _ . ._ f ._ _ g .- . ._ _ . q 3
! il l .if i :
l l- - - - -4 : -__.p_.__. l l . I j i t 1 I
~
* ~I i I
i r----j ' -" II - Il l Il
- I '-
k I3 l' -[
- 1, l'ill i
)
FIGURE 3.1-5A ) UQUID RADWASTE SYSTEM MODEL : f SHOREHAM NUCLEAR POWER STATION, UNIT 1 OFFSITE DOSE CALCULATON MANUAL i
- - UPA REVISION 1,FEB.1993 1
l
MOBILE FILTER /DEMIN. (MFD] CIRCULATING WATER TUNNEL
, RE 18 MOBILE FILTER /DEMIN,
[M FD-G41] WASTE
' COLLECTOR TANK'N SPENT FUEL STORAGE POOL YARD PIPING DRAIN SUMP REACTOR BUILDING SALT WATER DRAIN TANK (RBSWDT) RE M TO WNG '
FIGURE 3.1-6 sOUN LIQUID RADWASTE SYSTEM MODEL l SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL UPA REVISION 1. FEB.1993 i
1, ri - t a l' t , t . . , , .
- ~c- g ,
, il --
= l[t . r I
- I ,y w 1 f A
- a[ _
< A. .
gE g l ,1 v3 - l _ II I - O- ! _ g _ k HllH-
- l. g _
Nar- lij l il i ltl R .: .I
.- I I - ~
E
. gr
~
i s!= -4'
- s . -
li o ,g i _ i, -
. 4 ,
h t -
. g
- i. .__.__.__._.7,__,
.q .
I I ilI .il i o l - ._ 7 _ EM li! ! !
~
Ml , l i i j g
< ii slI ll ll' i
FIGURE 3.1-6A UQUID RADWASTE SYSTEM MODEL
- SHOREHAM NUCt. EAR POWER STATON, UNIT 1
, OFFSITE DOSE CALCULATON MANUAL ,
UPA REVIS!ON 1.FEB.1993
l
'I l
CIRCULATING
. WATER TUNNEL e
i MOBILE FILTER /DEMIN. (MFD.G41] I !' P
. SPENT FUEL STORAGE POOL j'
REACTOR BUILDING SALT WATER _ 1 DRAIN TANK (RBSWDD RE-70 TO. FIGURE 3.1-7 ""so'UN LIQUID RADWASTE SYSTEM MODEL i SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL LIPA REVISION 1, FEB.1993 , 6 4 4
~
r' t- t t , ~1 . t t' n 17 nj'
< i ,
< . . ija l I I d - l I l
!L I
I i h s . II
~
U g l < l f
'. l I l l I i ! i !
- i I l
\ "' s . W l : ll -
f cqi ;
. l ; ,
e g i i a b h I i 67g . g l i I d /~'s v i 1 I e I
~
go I el
- ,9 /
x e i I l i o t-pl l~ l
/ \ I gi i e ! 'i
- 'E I e
/ I ! -
i a.. i.
!,=1
;1 l " -
Il ' g
,\ I l-
[* \ l [ _ N 5 s t (g j .
, l I
\' .
z= i \ l i o
~
' s. ' s l \ l -
i N I I s- 1 I " I i . \\ 11 1 i l
/
Il 1 N ._. / I ' L*_.____.__.__.__.__.__.__.__.__.__.-I . FIGURE 3.1-7A - UQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STA5)N, UNIT 1 ; OFFSITE DOSE CALCULATION MANUAL l
-, UPAREVISION 1.FEB.1993 l I
SNPS-1 ODCM \ 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS The dose projection analysis will be performed using the methodology described in Section 3.1 with the exception that the calculated doses will be compared with the limits specified in REC Section 3.11.1.3. The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or O.2 mrem to any organs in a 31-day period. . Models of the liquid radwaste treatment subsystems, as presently envisioned, are shown on Figure 3.1-1 through 3.1-7. As a result of the on-going decommissioning process and in accordance with the descriptions , provided in LSNRC-2004 and LSNRC 2019, the Liquid Radwaste System and the Fuel Pool Cool and Cleanup System are in a state of transition. It is intended that a phased decommissioning of the G11 system will allow the systematic removal of various components and eventually, the entire system without disrupting the collection, processing, sampling, and discharging capability of the system. Some of the decontaminated components may be re- ; used in the proposed Industrial Waste Water System. The decommissioning of the G41 system includes the isolation of G41 from the Spent Fuel I Storage Pool with the installation of a temporary portable demineralizer/ filter pump to maintain water purity while relying on alternate sources for makeup capability. The ultimate disposal of the water in the SFSP will be, (after the removal of all the spent fuel from the pool) through temporary connection with the Salt Water Drain Tank as a batch release via 1D11-PNL-079 and the continuous release path to the Long Island Sound. (Figure 3.1-7) The shift to use of Monitor RE-79 instead of RE-13 will not occur until the final release of the water in the Spent Fuel Storage Pool. Final draining of the SFSP shall be the only occasion for use of the Salt Water Drain Tank in a batch release mode. BN1-11600.02.-92 l1.3.2-1 LIPA Revision 1 - February 1993 ,
$NPS-1 DDCM 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS 1
To comply with Section 3.11.2.1 of REC, the dose rate at an} time in the un- ~ restricted area for noble gas dose and for organ dose due to radioactive materials in gaseous effluents released via the station ventilation exhaust duct shall be limited to the following values: -
- 1. For noble gases: Less than or equal to 500 erem/yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- 2. For 1-131. 1-133 tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
The gaseous effluent model is shown in Figure 3.3-1. 3.3.1 Method 2: (Computerized Method) 3.3.1.1 Release Rate Estimation Dese rate estimation is perfomed every 15 minutes by making use of the atmospheric dispersion calculation made every hour from meteorological data taken every minute (see Section 4), and of the following equation for the release rate (Ci/hr): ,
= T' f Og 4 where:
F' = 4k 15 F (j) bng(j) At j=1 3 f 4
= 10-6 q j(T)j{ngIT) k = 2.832 x 104 (cc/ft8 )
F,(j) = vent flow during time interval j (cfm) bng(j) = noble as effluent monitor count rate during time interval j (cpm t = timeinterval(=1 minute) qI
= concentration of isotope i in the effluent'as measured in the lab at time T (pC1/cc)
F' = 15-minute average of the flow and countrate product (for dose rate estimation every 15 minutes) assumed to apply fora 60-minuteinterval[(cc/hr)(cpm)J 4 x 15 = number of t intervals per hour (1/hr) B 1-11600.02-92 11.3.3-1 - Revision 16 - July 1990
SN'PS-1 DDCM 3.3.1.2 Total Body Dose Rate CIoud h , round - D . = D , p 4 b where:
' 4 Dfb
= (x/Q)5"Fy 2.22 x 10 ,{bles f DFB i 9 4
D[ = (x/Q)5' F 3.17 x 10 Rad paht+1 I iDFA ij.ad
= (D/Q)F 7x10II {rt+1 #1DFG gj[1-a-tb ij/Ag D[ound p eloud = total body dose due to direct radiation from the radio-D wb active cloud [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B-8; also similar to Eq. B-6 if one makes use of the gama (x/Q)andtheDFBg insteadofDF{doseconversion
= total body dose (j = total body) due to inhalation D*i"h [ mrem /hri Reg. Guide 1.109. Eqs. C-3 and C-4, for an adult} (Ref.:
D,3ground = total body dose due to particulate and iodine radio-activity depositing on the ground [ mrem /hr) (Ref.: Reg. Guide and C-2 with the product 8760 [h/yr 1.109,) (1/A Eqs. C-1[yr)replacedby(1/A)[hr]andparameter g 6 r ,0 reprsentedbythe(0/Q)) 4 DFE g = gama dose to body conversion factor [(mrem /yr)/(pCi/m8)] (f rom Table B-1 of the guide) DFL = dose conversion factor for nuclide i to organ j of an id'8d adult individual [ mrem /pti inhaled) (from Tables E-7 through E-10 of Reg. Guide 1.109)
= total body conversion factor for standing on contaminated DFGg ) ground [(erem/hr)/(pC1/mt)) (from Table E-6 of Reg. Guide 1.109)
= concentration dispersion factor (sector-average model) for (X/Q)58 the period of release (site boundary only) (sec/m8) .
(X/0, j 8 = gama (X/Q) (finite cloud sector-average model) for the periodofrelease(siteboundaryonly)(sec/m8) (D/Q) = particulatedepoiitionrate(siteboundaryonly)(1/mt) F' f g = Qg(Ci/hr)(asdefinedinSection3.3.1.1) Efil-11600-02-92 11.3.3-2 Revision 3 - December 1983 l l
$NPS-1 DDCM R = adult breathing rate (m2/yr) (from Table E-5 of the Guide) ad radionuclidedecayconstant(hr*I) :
=
Ag
= time period over which the acgumulation is evaluated, t
b which is 15 years- (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 3.17x10 4 = 1012/(8760 x 3600) [(pC1/C1) (yr/sec)] 3.17 x 10 x 0.7, where 0.7 is the shielding factor which 4 4
=
2.2x10 accounts for the dose reduction due to the shielding
- effects of residential structures during occupancy (Ref.:
Reg. Guide 1.109TableE-15) 12 g, 7x10 II = 1012 x 0.7, where 0.7 is the shielding factor and 10 the number of pCi per C1 (see Eqs. C-1 and C-2 of the guide) part+1 - 68 particulates and 5 iodines in the sumation sign 3.3.3.3 Skin Dose Rate eloud + Dground D = D skin skin skin where:
= 1.11 x 0.7 (y/Q)sa F' 3.17 x 10 noblesY i DF}
Dfg[0
+ (X/Q)sa p. 3.17 x 104nZbles #1 DF5 3
Dy[r.d , (pfn) 7 7 x 10IIpI rt+1 #1 DFG12 [1 - e bi)/A g el = skin dose due to direct game radiation from the D5 "oud
" radioactive cloud (first component of the equation cloud modeling) and beta radiation with finite imersion)
(second component, semi-infinite cloud B-9; also Eq. [ mrem /hr) (Ref.: Reg. Guide 1.109 similar to Eq. B-7 if one makes use of the gama (X/Q)) Dground = skin dose due to particulate and iodine radioactivity skin depositing on the ground (mrem /hr] (Ref.: Reg. Guide 1.109, [Eqs. C-1 and C-2 with the product 8 (1/A) yr)replacedby(1/A)[hr]andparameter6 4 g representedbythe(D/Q)]
= cama dose 'to air conversion factor [(mrad /yr)/(pC1/m3))
DF} Ifrom Table B-1 of the Guide)
= beta dose to skin conversion fatter [(mrem /yr)/(PCi/m8)3 DFS I (from Table B-1 of the Guide) 11.3.3-3 Revision 3 - December 1983 Bi;1-11600-D2-92 1
1
$NPS-1 DDCM ;
DFG = skin dose conversion factor for standing on contaminated ! i2 ground [(mram/hr)/(pC1/m*)] (from Table E-6 of Reg. Guide
'1.109) !
1.11 = average ratio of ' tissue to air energy absorption ' .l coefficient (fromReg. Guide 1.109,pg1.109-6). , D.7 = shielding dose-reduction factor (see pg 1.109-68 of the i Guide)
= radionuclide decay constant [hr"I]
39 3.3.1.4 Organ Dose Rate (1-131, 1-133. Tritium and Particulate Release) ] D h , gg sa F' 3.17 x 104 R,)p[rt+1 #1DFAg ), where: inh = dose to organ j of individual in age grou a due to D ja inhalation of airborne radioactivity [ mrem /hr)p(Ref.: Reg.
- Guide 1.109.Eqs.C-3andC-4.)
DFA = dose i:enversion factor for nuclide' i to organ j of
- id" individual in age group.a [ mrem /pCi inhaled) (from Tables E-7 through E-10 of the Guide)
R = breathing rate of individual in age group a [m3/yr) (from. a Table E-5 of Reg. Guide 1.109, for the maximum individ-- unis) . The analysis is limited to the computation of the thyroid dose to a child at the r site boundary in the dodnwind sector for the period of the release (i.e., j = thy-- roid, a = child). , t EK1-11600-02-92 11.3.3-4 - Revision 3 - December 1983 t
= e =m. , . . _ . _ my ., +
. . . . . . _ ~ - -. .
$NPS-1 DDCM 3.3.2 Method 2: (Backup Method) 3.3.2.1 Noble Gas Total Body Dose Rate -
The following equation should be used: - (arem/yr) DT,
= 0.7
- Vj
- I/Qj
- I[DFB,
- Cg ))
where: DT,
= total body dose rate from all radionuclides releases (arem/yr).
3FBq= the total body dose rate factor due to gama emissions for each identified noble gas radionuclide '(mrem /yr per pCi/m8) (Table . 2.2-1), C g3 = the station ventilation. exhaust duct release concentration of radionuclide,1 (pCi/cc) (from the isotopic analyses perfonned on the gaseous sample taken from the station ventilation exhaust monitor), 1 -t 11.3.3-5 Revision 17 - May 1991 BN1-11600-02-92
SNPS-1 ODCM V = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct 3 ~ ventilation exhaust flow rate. - . X/Q3 = long tem dispersion factor due to release via the station ventila-tien exhaust point; refer to Table 4-1 cells Al and A3 0.70 = shielding factor that accounts for dose reduction due to shielding from residential structures. 3.3.2.2 Noble Gas Skin Dose Rate The following equation should be used: (mrem /yr) DS,
= V)*X/Qj*j[K,9
- C4 )]
where: D5
= skin dose rate from all radionuclides released (mrem /yr).
3
. l l
l l l i 11.3.3-6 Revision 17 - May 1991 BN1-11600.02-92 i
SNPS-1 ODCM f K,9
= the skin dose factor due to beta and gamma emissions for each identified noble gas radionuclide (mrem /yr per pC1/m8) from Table 2.2-1 .
C = the station ventilation exhaust duct release concentration of l il radionuclide 1. (pti/cc) (from isotopic analyse; performed on the gaseous sample taken from the station ventilation exhaust monitor). V 3
= 1.73E+08 cc/sec (3.66E+05 cfm). station ventilation exhaust duct ventilation exhaust flow rate.
2/03 = long term dispersion factor due to release via the station ventila-tion exhaust point; refer to Table 4-1, cells Al and A3 3.3.2.3 Orcan Dose Rate (Particulate Releases) ; The following equation should be used:
= 106*R *P y
- X/Qj
- Cy ) (mrem /yr)
D) 3 V)
- l l
l l l l BN1-11600.02-92 11.3.3-7 Revision 17 - May 1991 l l
i SNFS-1 DDCM where:- ( D,3
= total dose rate to organ, j, ares /yr. .
P = the inhalation dose conversion factor, for radionuclides other than Id noble gases.1, and organ, j a in arem per pCi from Table 3.5-3. The dose factor F is based on the critical individual organ for the Child group M ch is most restrictive. Inhalation dose factors I for other age groups are given in Tables 3.5-1, 3.5-2, and 3.5-4. i R, = inhalation rate (m*/yr), from Table 3.5-5. ] Cgg = the station ventilation exhaust duct release concentretion of ! radionuclide,- 1, (uci/ce) (from the isotopic analyses performed on-the filter paper and charcoal cartridge taken from the station ventilation exhaust monitor), i Vg = 1.70E+08 cc/sec (3.60E+05 cfs), station ventilation exhaust duct ventilation exhaust flow rate, I/Q 3 = long term dispersion factor due to releases via the station ventila-tion exhaust point; refer to Table 4-1, cells A2 and A4, i h I i l i 1I.3.3-8 Revision 17 - May 1991 B51-11600.02-92 , h m-, - , , , - - , _ . . _ . , ~ . , , _ _ m. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ _ _ _ _ _
~
o 1 J i 4 m es m a e . e m ,se ... 11 m _
- s - -. m .s. rgi la J
===c= == =e=
U LU -
==vwti, us sm.essie. .,
vesi. evinssesse MC42 M $ b_
- i ean r.e
- weevuerem . vomosos eerwees _gg 1
" " " U U wees e seawe b
Ls ,j , W SWGFlt I m Pee pas 9A.mm89W Sefwees
,,gg 39, Q - -
mes==m seawe=e monumb 99efttattes gg FIGURE 3.3-1 GASEOUS EFFLUENT MODEL-
- SHOREMAN NUCLEAR Potter STATION-UNIT 1
- OFFSITE DOSE CALCULATION MANUAL REVISION 17 - MAY 1991 .
O
. _ _E_ m - _ _ _ _ . _ _ ____ ..i__..E_.____.____
m.___ _ . _ _ _ . _ _ . _ _ _-- _ u_____________ __ m_ _ . _ _ _ ____ __y_. .________ _ _ _ + . . . *
- _.- . _ . _ , _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ .
SNPS-1 ODCM 3.4 GASEOUS EFFLUENTS NDBLE GAS AIR DOSE To comply with Section 3.11.2.2 of the REC. the air dose in' unrestricted area location due to releases via the station ventilation exhaust point shall be limited to the following: ,
- 1. During any calendar quarter: Less than or equal to 5 mrads for gama radiation and less than or equal to 10 mrads for beta radiation. .
- 2. During any calendar year: Less than or equal to 10 mrads for gama radiation and less than or equal to 20 mrads for beta radiation.
3.4.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.4.1.1 Release Estimation Dese estimation is performed every hour by making use of the atmospheric dispersion calculation made every hour from meteorological data taken every minute (see Section 4), and of the following equation for the release rate (C1/hr):
= F' f g Qi where:
6 F' = k )g ,) F,(j) b ng (j) at f 4
=
10~6 q,(t)/bng(t) k = 2.832 x 104 (cc/ft3) , F,(j) = vent flow rate during interval j (cfm) -
= n ble gas effluent monitor count rete during interval j Cng(j) (cpm)
At = time interval (= 1 minute)
= concentration of isotope i in the effluent as measured in qI the lab at time t (uti/cc)
F' = 60-minute avera of the flow and count-rate product [(cc/hr) (cpm)) ge 60 = number of 4t intervals per hour (1/hr) 1 BN1-11600.02-92 11.3.4-1 Revision 16 - July 1990
SNPS-1 DDCM 3.4.1.2 Noble Gas Gama Air Dose 4 -
=
DY, air (X/0)58 F' 3.17 X 10 no les #1 DFJ where . Dy' air
= gama dose to air at the site boundary in the downwind ,
sector during the period of release (mrad /hr) (Ref.: Reg. l Guide 1.109. Eqs. B-4 and B-5, and also Eq. B-1 with the substitutionof(X/Q)y ]
= finite-cloud sector-average 'gama' dilution factor at the I (X/Q)}a downwind site-boundary [sec/m83 . ;
= gama dose to air conversion factor (from Table B-1 of ,
DF} Reg. Guide 1.109) [(mrad /yr)/(pti/m8)] l F'f = 4 09(C1/hr)(seeSection3.4.1.1) 3.4.1.3 Noble Gas Beta Air Dese 4 0 DB , air
= (X/Q) F' 3.17 X 10 no les fi DF 4 where
= in the downwind Dg,g r beta sectordose to air during theatperiod the site ofboundary release [ mrad /hr] (Ref.: Reg.
Guide 1.109 Eqs. B-4 and B-5) DFB = beta dose to air conversion factor (from Table B-1 of Reg. Guide 1.109) [(mrad /yr)/(pti/m2))
=
F'f g Qg(Ci/hr)(seeSection3.4.1.1)' (X/0)58 = sector-average concentration dilution factor at the site l boundaryduringtheperiodofrelease[sec/m8] l l
)
BN1-11600.02-92 11.3.4-2 . Revision 3 - December 1983 I
l l
$NPS-1 ODCM 3.4.2 Method 2: (Backup Method) 3.4.2.1 Noble Gas Gama Air Dose . l The following equation should be used:
Dg3 = 3.17E-08 'Vj *t j
- X/Q3
- I [Mg *C,j] (erad) 1 where:
Dg5 = the total gama air dose from the releases (trad), 3.17E-08 = the inverse of number of seconds in a year, M = the air dose factor due to gama emissions for each identified
~
4 noble gas radionuclide (mrad /yr perpti/m2) from Table 3.4-1, ty = 7.BBE+06 see for quarterly dose calculation,
= 3.15E+07 see for yearly dose calculation C
$3
= the station ventilation exhaust duct release concentration of C1 radionuclide,1, on the gaseous %samp/cc) le taken (from the station from the isotopicventilation analyses perform
, exhaust monitor),
me BN1-11600.02-92 11.3.4-3 Revision 17 - May 1991
SNTS-1 DDCM
=
V g 1.73E+0B cc/sec (3.66E+05 cfm). ' station ventilation exhaust i duct ventilation exhaust flow rate. X/03 = long term dispersion factor due to release' via the station ventilation exhaust point; refer to Table 4-1 cells 81 and B3, 3.4.2.2 Noble Gas Beta Air Dose The following equation should be used:. . Dg = 3.17E-08
- X/Qj
- Vj *t)
- I [Ng *Cyj) (arad) s 1 I
1 l a i i i f I i 9 j 1 l
)
BN1-11600.02-92 11.3.4-4 Revision 17 - May 1991 'l l
1
$NPS-1 DDCM wheres i D 33
= beta air dose from all radionuclides released (arad).
Ng = the air dose factor due to beta- emissions for each l identified noble gas radionuclide (arad/yr per uCi/a') i f rom Table 3.4-1, - l 3.17E-08 = the inverse of-number of seconds in a year,
.)
tg = 7.88E+06 sec for quarterly dose calculation.
= '3.15E+07 sec for yearly dose calculation,.
Cgg = the station ventilation exhaust duct release concentration' of radionuclide, 1 (uci/ce) (from the isotopic. analyses performed en the gaseous aanple taken from the station ventilation exhaust monitor), i Vg a 1.73E+08 cc/see (3.66E+05 - efs), station' ventilation exhaust duct ventilation exhaust flow rate, j I/Q 3 = long term dispersion factor due ' to release via the station' i ventilation exhaust point; refer to Table 4-1, cells 31 and B3, a 1
+
E51-11600.02-92 II.3.4-5 Revision 17 - May 1991 - e
$NPS-1 ODCM TABLE 3.4-1 .
s i NOBLE GAS DOSE FACTORS . Gama Air Beta Air Dose Factor Dose Factor' M N
!sotope (mrad /yrpefWCi/m8) (mrad /yr por WC1/m8)
Kr - 83m 1.9E+01 '2.9E+02 Kr - 85m 1.2E403 2.0E+03 Kr - 85 1.7E+01 2.0E+03 1 Kr - 87 6.2E+03 1.0E+04 Kr - 88 1.5E+04 2.9E+03 Kr - 89 1.7E+04 1.1E+04 1.6E+04 7.BE+03 Kr - 90 , 1.6E+02 1.1E+03 Xe - 131m 3.3E+02 1.5E+03 Xe - 133m , 3.5E+02 1.1E+03 i Xe - 133 3.4E+03 7.4E+02 Xe - 135m 1.9E+03 2.5E+03 Xe - 135 1.5E+03 1.3E+02 xe - 137 4.BE+03 : xe - 138 9.2E403 9.3E403 3.3E+03 Ar - 41 a t ,r f
=i i
1 ef 1 - Revision 1 - August 1983 Bf;1-11600.02-112
SNPS-1 ODCM 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES (other than Noble Gases) WITH HALF-LIVES GREATER THAN 8 DAYS To comply with Section 3.11.2.3 of the Radiological Effluent Controls, the organ dose to maximum individual in unrestricted area due to particulate releases via the station ventilation exhaust point shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
3.5.1 Method 1: (ComputerizedMethod) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.5.1.1 Release Estimation , Dose estimation is performed every hour by making use of the atmospheric dispersion calculation made every hour from meteorological data taken every minute (see Section 4), and of the following equation for the release rate (Ci/hr):
= F' f Qg 4 .
where: F' = k 1 F (j) dng(j) at 3,3 3 f 4 10-6 jg(7)j[ng IT) k = 2.832 x 104 (cc/ft3) F (j) = ventflowrateduringintervalj(cfm) 3 d ng (j) = noble gas effluent monitor count rate during interval j (cpm)
~
4t = timeinterval(=1' minute)
= concentration of isotope i in the effluent as measured in qi thelabattimet(pC1/cc)
F' = 60-minute avera count-rate product [(cc/hr) (cpm)] ge of the flow and 60 = number of At intervals per hour (1/hr) BN1-11600.02-112 11.3.5-1 Revision 17 - May 1991
l SNPS-1 ODCM 3.5.1.2 Total Body Dose i CIoud h D = D , p + D9 "" 4 b where: . CIoud 4 D b (pg)sa p. 2.22 x 10 no les # DFBy 1 D h = ( W )sa p. 3.17 x 104 Radpaft+1 I iDFA ij,ad A g II D,round = (D/Q) F' 7 x 10 par 1 gF DFG)[1-e-tb i]/1 g 9 D el ud = total body dose due to direct radiation from the
# radioactive cloud [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq.
B-B; also simila to Eq. B-6 if one makes use of the gama (X/Q)andtheDFB insteadofdoseconversionfactor) D h = total dose (j = total body) due to inhalation [erem/hr body (Ref. : Reg. Guide 1.109. Eqs. C-3 and C-4, for en adult D,9[ound = total body dose due to particulate and iodine radioactivity depositing on the ground [ mrem /hr) (Ref.: Reg. Guide 1.109. Eqs. C-1 and C-2 with the product 8760 6[hr/yr'l 1 (r.el r(e/A ) [yr) replaced by)[1/A pr$sentedbythe(D/Q) g
) [hr] and parameter 4
DFB g a gen a dose to body conversion factor [(mrem /yr)/(pti/m8)] (from Table B-1 of the Reg. Guide) DFA = dose conversion factor for nuclide i to organ j of an ij,ad adult individual Reg. Guide 1.109) [ mrem /pti inhaled] (from Table' E DFG = total body conversion factor for standing on contaminated Il ground [(mrem /hr)/(pCi/m8)] (from Table E-6 of Reg. Guide - 1.109)
= concentrationdispersionfactor(sector-averagemodel)for i (X/Q)5 theperiodofrelease(siteboundaryonly)(sec/m8) .l 11.3.5-2 - Revision 10 - August 1987 Stil-12500.02-112 l
l
SNPS-1 DDCM ( y/Q)'y" = gama (y/Q) (finite cloud sector-average model) for the periodofrelease(siteboundaryonly)(sec/m8) (D/Q) = particulate deposition rate (site b'oundar) only) (1/mr } F' f 4
= Qg (C1/hr) (as defined in Section 3.5.1.1) .
R = adult breathing rate (m8/yr) (from Table E.5) ad
= radionuclidtdecayconstant(1/hr) g t = time period over which the accuylation is evaluated, b which is 15 years (1.314 x 10 hours) (Reg. Guide pg1.109-24) 3.17x10" = 10 12(8760x3600)L(pti/C1)(yr/sec))
/
2.22x10 4 = 3.17 x 104 x 0.7, where 0.7 is the shielding factor which accounts for the dose reduction due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109TableE-15) 12 7x10 II = 1012 x 0.7, where 0.7 is the shielding factor and 10 4, the number of pC1 per ti (see Eqs. C-1 and C-2 of the guide) part41 = 68 particulates and 5 iodines in the sumation sign . Note that the total total body" dose as computed above is used only for hourly assessment of plant operation within the specification limits. The reports pre-pared by the dose software include the total body dose due to inhalation as a separate parameter. Also note that the equation conservatively includes the dose due to the airborne noble gases, even though this section addresses only the iodines and particulates. 3.5.1.3 Skin Dose
= eloud + Dground D
skin D skin skin where: Dfgfn d = 1.11 x 0.7 (y/Q)sa p. 3.17 x 10 4 nohlesf i DFf 4 *
+ (X/Q)S" F' 3.17.x 10 no les i f DFS g BN1-11600.02-112 11.3.5-3 - Revision 3 - December 19E3
$NPS-1 DDCM A
D[n"
= (D/Q)F'7x10 II parb# 1 DFG 12 [g , ,-tb i]q el d skin dose due to direct gama radiation from the D$ a radioactive cloud (first component of the equation with '
finite cloud modeling) and beta radiation (second compon- ' ent semi-infinite cloud imersion) [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Eq. 8-7 if one makes use of the gama (X/Q)) , i
= skin dose due to particulate and iodine radioactivity D$und "
depositing on the . ground [ mrem /hr) (Ref.: Reg. Guide 1.109 Eq (1/A,$[yr)s. C-1by replaced and C-2 with the product 1/A)[hr]andparameter6 8760[hr/y g (r,8)- 4 reprdsented by the (D/Q)() 4 DFT = gamma dose to air conversion' factor [(mrad /yr)/(pCi/m3)]~ (fromTableB-1oftheGuide) i DFS = beta dose to skin conversion factor [(erem/yr)/(pC1/m8)] ' 9 (from Table B-1 of the Guide) i DFG = skin dose conversion factor for standing on contaminated I2 ground [(mrem /hr)/(pti/m8)] (from Table E-6 of Reg. Guide 1.109) . F 1.11 = average ratio of tissue to air energy absorption coeffici-ent(fromReg. Guide 1.109,pg1.109-6)
= shielding dose-reduction factor (from Reg. Guide 1.109, pg !
0.7 1.109-68) i and the remaining parameters are as defined above in Section 3.5.1'.2. Note that the total skin dose as described here includes the contribution of airborne noble gases, even though this section addresses only the iodines and t particulates. , 11.3.5-4 . Revision 3 - December 1983 EN1-136DD.02-))2 r 4
, -. . --- v - - .- .,
- , - - , - - - r . -
I l SNPS-1 ODCM i 3.5.1.4 Organ Doses Due to Inhalation D h , (gg)sa p. 3.17 x 104 R, g f 'DFAg3; 4 where: .
= in age grou a due to D dose to organ j of 'individualinhalation of airborne radioact Guide 1.109 Eqs. C-3 and C-4)
DFA a dose conversion factor for nuclide i to organ j of g3, individual in age group a [ mrem /pci inhaled] (from Tables E-7 through E-10 of the Guide) R,
= breathing rate of individual in age group a [m2/yr] (from Table E-5 of Reg. Guide 1.109, for the maximum individuals)
( y/Q)sa = concentration dispersion factor (Sector-Average model) for the period of release (nearest garden and nearest residence)[sec/m8] 3.5.1.5 Orcan Dose Due to Ingestion of Leefy vegetables
= M D .
(D3 , ) part
- IU Ifodines
- IU )C14 ,
where: 0
=
(D/Q) F' 1.1 x 10 p,Irt U, 19 DFI g3, (Dy9)part
+ 8 *24 0.2 1v e 1 240 A )
xE2 ( A4 + 0.0021) g 7 (D 9) iodines
=
(D/Q) F' 5.5 x 10 iofinesOa Ii DFI gy,
+ I *24A 1.0 xE(Ag + 0.0021) 2 iv 240A 9
3e 1 7
= (X/Q)" F' 5.5 x 10 U, fC14 DFI C14.ja '
(D 9)C14 7
=
(X/Q)" F' (1.2 x 10 ) U, fH3 DFI H3.ja (D 9)H3 Revision 3 - December 1953 ! BN1-11600.02-II2 11.3.5-5 . i
SNPS-1 ODCM
= dose to organ j of individual in age group a due to (Dh"9) part -
ingestion of leafy vegetables contaminated with ' particulateradioactivity(mrem /hr](Ref.: Reg. Guide 1.109. Eqs. C-5, C-6 and C-13 for leafy vegetables only, with the following:
' r(fraction of deposited activity retained on crops)
= 0.2 (see pg 1.109-68 oftheGuide)
*tc6n(time period that crops are exposed to[ hrs) taminationduringgrowingseason)=
*t (time riod over which the accumulation is ekaluated =
[ hrs]
*t D (time Alay between harvest of vegetation or
- c. ops a- ngestion)=24[ hrs]
' Y, (agricultural productivity) = 2 [kg/mt)
*P(soileffectivesurfacedensity)=240[kg/m] r
+0.0021'[hr*I](Ref.: Reg. Guide 1.109,
- xh =1.$b9-4 and 1.109-69) p
*6 4(r.0)=(D/Q)[m-2) _
- ft (fraction of leafy vegetables growing in garden of interest) = 1.0 (D0 9) = dose to organ j of individual in age group a due to iodines ingestion of leafy vegetables contaminated with radiciodines [ mrem /hr] (Ref.: Reg. Guide 1.109 Eqs.
C-5 C-7 and C-13 for leafy vegetables only; similar to the organ dose 'due to particulate radioactivity given above but with r = 1.0 and different multiply - ing constant) 9 = dose to organ j of individual in age group a due to (D]"a)C14 ingestion of leafy ve Carbon-14 [ mrem(Ref.: /hr) getables exposed toEqs. airborneRe C-8 and C-13 for leafy vegetables only, with p (the ratio of the total annual release time to the total annual time during which photosynthesis occurs) = 1) i9 = dose to organ j of individual in age group a due to (Dj "a )H3 ingestion of leaf tritium [ mrem /hr) y vegetables (Ref.: exposed Reg. Guide 1.109, Eqs.toC-9 airborne and C-13 for leafy vegetables only) Bt:1-11600.02 112 11.3.5-6 - Revision 3 - December 19S3
i I SNPS-1 DDCM ( a ' ingestion rate of leafy vegetables by individual in age group Lkg/yr ]a (from Table E-5 of the Guide, maxieum individua i B = concentration factor for uptake of radionuclide i from 4V soil by edible par.ts of crops [(pC1/kg)(wet weight)/ (pti/kg) (dry soil)] (Ref.: Reg. Guide 1.109. Table E-1 andincludedonTable3.5-6) DFI kja = dose conversion factor for nuclide i to organ j of individual in age group a due to ingestion of contaminated food [ mrem /pti ingested) (from Tables E-11 through E-14 of theGuide) DFIC14.ja = DFIgy,forCarbon-14
=
DFI H3.ja DFIg ), for tritium F C14
- I tfor Carbon-14 (see Section 3.5.1.1 above) f * # for tritium H3 1 H = absolute humidity of the atmosphere at the location of interest [g/m8](SeeTable3.5-7)
(x/Q)sa = concentrationdispersionfactor(Sector-Averagemodel) for the period of release (nearest garden and nearest . residence)[sec/m3] (D/Q) = perticulate deposition rate (nearest garden and nearest residente)[1/m] r 3.5.1.6 Infant Thyroid Dese Due to incestion of Goat Milk and Inhalation Infant thyroid dose equation: inh
- milk O O O thy inf thy,inf thy,inf where:
- I D inf
* (0 inf) part inf) iodines
*
- ID '
ID inf)C14 inf) H3 D i = (X/Q) F' 3,17 x 10 R 4 f DFA 1 . thy,inf t ,inf inf pa t+1 i BN1-11500.02-112 11.3.5-7 Revision 13 - November 1988
SNPS-1 DDCM 8 ID h inf)part = (D/Q)F'1.1x10 par nf I tDF11 .t % inf 0.2 + Biv
*0I mi )e-241 0.7LA + 0.0021) 240x ,
1 ~1 7 ID inf) iodines
=
(D/Q)F'5.5x10 iod nes nf Yi DFli . thy,inf 1.0 , 8,4 3 ,-24kg x 6 F"I E 0. mag + 0.0021) 240Ag I DFI C14. thy inf (D inf)C14
- 4/Q)" F' 2.2 x 107 (nf C14 x6fm C14 **PI'2* C14)
I DFI H3. thy,inf (D inf)H3
= (x/Q) F'[ ] (nf H3 x 6 Fm,H3 **PI~2 H3 I
ih = infant thyroid dose due to inhalation of airborne ' Dt "hy inf radioactivity [ mrem /hr) (Ref.: Reg. Guide 1.109 Eqs. C-3 and C-4)
= infant thyroid dose due to ingestion of milk contam-(gH kthy,inf)partinsted with radioactive particulates [ mrem /hr) (Reg.
Guide Eqs. C-5, C-6, C-10. C-11 and C-13) for milk, with the following:
- r (fraction of deposited activity retained on crops) = 0.2 (see pg 1.109-6B of the Guide)
*tc$n(time period that crops are exposed to[ hrs) tamination during growing season) =
*t time period over which accumulation is eIa(luated)=l, hrs) ,
*t=h (time delay for ingestion of forage by animals )
0[ hrs)(seepg 1.109-69 of Reg. Guide)
*Ymin (agricultural productivity, grass-animal- milk-pathway)=0.7[kg/mt)(RegGuide1.109.Rev.
0) r
*P(soileffectivesurfacedensity)=240[kg/m]
Revision 10 - August 1987 BN1-11600.02-112 11.3.5-8 l l
SNPS-1 ODCH ' *1 gg = 11 + 0.0021 [hr*I) (see pgs 1.109-4 and 1.109-69)
*6 9(r,8)*(D/Q) [m*2]
- t,feed(average into thetransport milk andtime of receptor to the activity)from the
; data listed in Table 4-2
*f (fractionoftheyearthatanimalsgrazeon PIsture based on survey data); data listed in Table 4-2
*fwee (fractionofdailyfeedthatispasturegrassn the anima data); data listed in Table 4-2 ik = infant thyroid dose due to ingestion of milk contam-(Dfhy,inf) iodines instedwithradio-iodines [ mrem /hr)(Ref.: Reg. Guide Eqs. C-5, C-7, C-10, C-11, and C-13 for milk; similar to the infant ttyroid dose due to the ingestion of particulates given above, with the exception of a differentmultiplyingfactorandr=1.0) .
infant thyroid dose due to in estion of milk contam-1k = (Dfhyinf)C14
- inated with C14 [erem/hr) (R f.: Reg. Guide 1.109 -
Eqs. C-8, C-10, C-11 and C-13 for milk, with p (the ratio of the total annual release time to the total annual time during which photosynthesis occurs) = 1 and t, f and f 3 as given above for the particiflates3
= infant thyroid dose due to ingestion of milk contam.
(D"Ih J 'i"I)H3 insted with tritium [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-9, C-10. C-11, and C-13 for milk, with t f, f , pand f, as given above for the particulates) R
= infantbreathingrate[m8/yr)(fromTableE-5ofthe inf Guide, for t.aximum individual)
DFA
= dose conversion factor for nuclide i to the infant i, thy,inf thyroid due to inhalation [ mrem /pti inhaled] (from Table E-10 of the Guide)
= dose conversion factor for nuclide i to the infant DF]1 thy,inf thyroid due to ingestion [ mrem /pti ingested] (from TableE-14oftheGuide) <
DII C14, thy.inf
- 1 thy,inf for Ca don 14 DFI H3,
- O
- 1. thy.inf for tritium thy,inf 11.3.5-9 Revision 13 - November 19E0 Bt;1-11600.02-112 .
SNPS-1 ODCM g F
- Ti for Carbon-14 (see Section 3.5.1.1 above)
C14 F H3
- T1 for tritium ,
= milk ingestion rate'by infant (liters /yr] (Ref.: Reg.
knf Guide 1.109.TableE-5.maxind.) l F,3
= average fraction of the' animal's daily intake of radionuclide 1 ~ which appears in each liter. of milk I, days / liter) from Table E-2 of the Guide, with F, =
,9.forgoat)
B gy = concentration factor for uptake of radionuclide i from soil by edible parts of crops [(pCi/kg) (wet weight)/(pC1/kg)(drysoil))(fromTableE-1ofthe Guide and included on Table 3.5-6) H = a
'ofinterestLg/m*
bsolute humidity]of (See Tablethe atmosphere 3.5-7) at the location 6 = amount of feed consumed by a goat per day [kg/ day] ; (from Table E-3 of the Guide. O p factor) (y/0)sa = concentration dispersion factor (Sector - Average model) for the of release (nearest goat ; location)(sec/mS) period (D/Q) = particulatedepositionrate(nearestgoatlocation) [1/m3 i l
'l l
.-ge=
1' EN1-126DD.02-132 11.3.5-10 Revision 13 - November 1988
. 'l x 1
SNPS-1 DDCH
~
i 3.5.2 Method 2: (Backup Method) 3.5.2.1 Organ Doses: , The following equation should be used: Dj = 3.17E-DB *V3 *t 3j[(106
*R, *P g3 *2/Q3 + P,9y *D/Q)*C 3 g33 (erem)
(3.5.2-1) where: Dj = total dose to organ j (arem), P the inhalation dose conversion factor for radionuclides,1. (other 43 = than noble gases), and organ j, (mrem per pCi inhaled) from Table 3.5-3. P values listed in Table 3.5-15 and 3.5-16 res ectively are the dNe rate conversion factors for tritium an carbon-14 from inhalation and ingestion of leafy and stored vegetables and ingestion of goat's milk. 1 I l i i BN1-11600.02-112 11.3.5-11 Revision 17 - May 1991 l
$NPS-1 ODCH )
t R, = inhalationrate(m8/yr)fromTable3.5-5 l P,9) = the dose' conversion factor for radionuclides, other than noble gases 1. and organ j. for contaminated ground, ingestion of leafy I and stored vegetables in m8(mrem /yr per uti/sec) from Table 3.5-9. The dose factors P P are based on the critica1' individual organ for the child houpiNince this group is most restrictive, ty = 7.BBE+06 see for quarterly dose calculation
= 3.15E+07 see for yearly dose calculation.
C yg = the station ventilation' exhaust duct release concentration of radionuclide.1. (uti/cc) (from the isotopic analyses performed on the filter cartridge taken from the station ventilation exhaust monitor). V = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct 3 ventilation exhaust flow rate. X/Q3 = long term dispersion factor due to releases via the station ventila-tion exhaust point; refer to Table 4-1 cells C1 and C3
)
BN1-11600.02-112 11.3.5-12 Revision 17 - May 1991
SNPS-1 DDCM
~
D/03 = long term deposition. factor due to releases via the station . ventilation exhaust point; refer to Table.4-1 cells C1 and Cg, 3.17E-08 = inverse of 3.15E+07 sec/yr, and NOTE: If the land use census (see Table 3.5-8) changes, the critical location; i.e.. the location where an individual would be exposed .to the highest dose, must be reevaluated using Equation 3.5.2-1 for each of the following locations:
- 1. nearest residence.
- 2. nearest vegetable garden, and -
- 3. nearest milk cow or goat.
P used in Equation 3.5.2-1 will include the values in Tables 3.5-10 through 3?N14,ifthosepathwaysexist. , At each location, the following pathways must be considered and dose (dose rates) ' reevaluated if any actual pathway exists:
- 1. inhalation.
- 2. leafy vegetables (fresh). .
- 3. stored vegetables, ,
3 4. goat's or cow's milk (if both exist choose the one resulting in the -i higherdose),and
- 5. deposition on ground.
since a person will always be present, pLthways 1 and 5 must always be evaluated. Once the location of the critical individual is determined and found to be other than the one listed in Table 4-1 (cell C1), the values of X/Q and D/Q at the updated critical location must be used. 4 BN1-11600.02-112 11.3.5-13 Revision 17 - May 1991 i
SNPS-1 ODCM TABLE 3.5-1 INHALATION DOSE FACTORS FOR ADUtTS (mrem per pCI inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung Gi=tti H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.2SE-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 . No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 te-59 1.47E-06 3.47E-06 1.32E-06' No Data No Data 1.27E-04 2.35E-05 00-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 00-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.03E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 N1-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data B.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data. 1.00E-24 Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21
$r-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.M E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 ' No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-05 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 BN1-11600.02-99 1 of 3 Revision 10 - Augest 1987
i l l SMP5-1 00CM TABLE 3.5-1 (CONT'D) Radio- Kidney GI-LLI Thyrold nuclide Bone Liver T. Body Lung f-4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-95 1.34E-05 6.54E-05 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 Zr-97 6.31E-05 1.30E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 7 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Mo-99 No Data 5.20E-07 l 1.79E-13 3.64E-13 4.63E-12 No Data. 5.52E-12 9.55E-08 Tc-99m 1.35E-13 4.99E-08 1.36E-21 No Data' l Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data R.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-103 1.91E-07 6.02E-06 l No Data 3.89E-11 No Data 1.27E-10 1.37E-06 Ru-105 9.88E-11 1.14E-04 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 Ru-106 5.79E-04 3.78E-05 Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 le-125m 4.27E-07 1.87E-05 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 Te-127m 1.58E-06 7.17E-06 1.75E-10 8.03E-11 3.81E-11 1.32E-10 6.37E-10 8.14E-07 Te-127 1.45E-04 4.79E-05 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-129 6.22E-12 1.82E-05 6.95E-05 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-131 1.39E-12 6.37E-05 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 Te-132 3.25E-08 No Data 9.61E-07 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data. 7.85E-07 1-131 3.15E-06 No Data 5.08E-08 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 1-133 1.08E-06 1.26E-10 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1-134 8.05E-08 No Data 6.56E-07 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-134 4.66E-05 1.46E-06 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 Cs-136 9.40E-06 1.05E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 4.14E-05 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-1) Cs-138 4.70E-07 1.12E-07 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-140 4.88E-06 ~ 6.13E-09 1.45E-17 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 na-141 1.96E-26 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 Ra-142 5.73E-05 4.30E-08 2.17E-08 5.73E-09 No Data No Data. 1.70E-05 La-140 7.91E-07 2.64E-07 La-142 ~B.54E-11 3.88E-11 9.65E-12 No Data No Data 2 of 3 Revision 1 - August 1983 8N1-11600.02-99
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SNPS-1 00CM , TABLE 3.5-2 - IN!!ALATION DOSE FACTORS FOR TEENAGER (mrrm per pCl inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney tg GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Ma-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.6BE-04 1.19E-05 00-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05
- Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Nt-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.6BE-06 In-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.01E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data <1.00E-24 Hr-84 No Data No Data 5.41E-08 No Data No Data No Data - < 1.00E-24 Br-85 No Data No Data 2.29E-09 No Data No Data No Data <1.00E-24 Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-09. No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 5r-91 1.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.45C-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 l
l BN1-11600.02-100 1 ol' 3 Revfsion 1 - Aogust 1983 r
~
SMPS-1 $ nrm TABEE 3.5-2 (COMT'D) Radio-nuclide Bone Liver T. Dody Thyroid Kidney L222 GI-llI Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data Zr-97 1.72E-08 8.42E-06 3.36E-04 1.86E-05 3.40E-09 1.57E-09 No Data 5.15E-09 Wh-95 2.32E-06 1.29E-06 1.62E-05 7.88E-05
- 7. ORE-07 No Data 1.25E-06 Mo-99 No Data 2.11E-08 9.39E-05 1.21E-05 4.08E-09 No Data 5.14E-08 1.92E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 3.36E-05 No Data 7.20E-12 1.44E-07 7.66E-07 '
Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data Ru-103 1.90E-13 8.34E-08 1.09E-16 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 Re-105 1.40E-10 No Data 9.79E-05 1.36E-05 5.42E-11 No Data 1.76E-10 2.27E-06 Ru-106 1.23E-05 No Data 1.55E-06 1.13E-05 Ag-110m No Lata 2.38E-05 2.01E-03 1.20E-04 1.73E-06 1.64E-06 9.99E-07 No Data te-125m 6.10E-07 3.13E-06 8.44E-04 3.41E-05 2.80E-07 8.34E-08 1.75E-07 No Data Te-127m 2.25E-06 1.02E-06 6.70E-05 9.38E-06 2.73E-07 5.4BE-07 8.17E-06 2.07E-04 Te-127 2.51E-10 1.14E-10 5.520-11 1.99E-05 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 Te-131m 6.18E-12 3.32E 4.12E-07 2.02E-07 1.23E-08 7.51E-09 5.03E-09 9.05E-09 Te-131 1.97E-12 5.49E-08 2.97E-05 7.76E-05 1.04E-12 6.30E-13 1.55E-12 7.72E-12 Te-132 4.50E-08 2.92E-07 1.89E-09 3.63E-08 2.74E-08 3.07E-08 2.44E-07 l-130 7.80E-07 2 ~~R-06 5.61E-05 5.79E-05 8.96E-07 1.86E-04 3.44E-06 No Data l-131 4.43E-06 0.Inf.06 3.30E-06 1.14E-06 l-132 1.83E-03 1.05E-05 No Data 8.11E-07 1.99E-07 5.4iE-07 1.97E-07 1.89E-05 l-133 1.52E-06 8.65E-07 No Data' 1.59E-07 2.56E-06 7.7BE-07 3.65E-04 4.49E-06 l-134 1.11E-07 No Data 1.29E-06 2.90E-07 1.05E-07 4.94E-06 4.58E-07 l-135 4.62E-07 1.18E-06 No Data 2.55E-09 4.36E-07 7.76E-05 1.86E-06 No Data Cs-134 6.28E-05 1.41E-04 6.86E-05 8.69E-07 Cs-136 No Data 4.69E-05 1.83E-05 1.22E-06 6.44E-06 2.42E-05 1.71E-05 No Data l Cs-137 8.36E-05 1.38E-05 2.22E-06 1.36E-06 1.06E-04 3.89E-05 No Data 3.80E-05 i Cs-138 5.82E-08 1.07E-07 1.51E-05 1.06E-06 5.58E-08 No Data 8.28E-08 9.84E-09 l Ba-139 1.67E-10 1.18E-13 4.87E-12 3.38E-11 Ba-140 No Data 1.11E-13 8.08E-07 8.06E-0Z l 6.84E-06 8.38E-09 4.40E-07 No Data l Da-141 1.78E-11 2.85E-09 2.54E-04 2.86E-05 1.32E-14 5.93E-13 No Data 1.23E-14
- Ba-142 4.62E-12 - 4.63E-15 4.11E-07 9.33E-14 2.84E-13 No Data 3.92E-15 2.39E-07
- La-140 5.99E-08 2.95E-08 7.82E-09 5.99E-20 l La-142 No Data No Data 2.68E-05 6.09E-05 1.20E-10 5.31E-11 1.32E-11 No Data
! No Data 1.27E-06 1.50E-06 BMI-11600.00-100 2 of 3 Revision 1 - August 1983
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SNPS-1 ODCM TABLE 3.5-5 RECOMMENDED YALUES FOR U,p TO BE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway infant Child Teen Adult Fruits, vege- - r)I N/A III 520 630 520 Leafy vege-tablesII) (kg/yr) N/A 26 42 64 Milk (1/yr)III 330 330 400 310 Meat &p%try (kg/yr) N/A 41 65 110 Fish [ fresh or salth (kg/yr)I3) . N/A 6.9 16 21 Other segged (kg/yr) N/A 1.7 3.8 5 Drinkingster 510 510 730 (t/yr) 330 Shoreiinerec-reationgg) (hr/yr) N/A 14 67 12 n ) 1400 I6) 3700(6) 8000(6) 8000(5) III Consumption rate obtained from Reference 19 for average individual and age prorated and maximized using techniques contained in Reference 10 of Regula-tory Guide 1.109. Rev 1. Oct. 1977. (2) Consists (including of thevegetables leafy following),(on anda24% ussgrain. basis): 22% fruit. 54% vegetables BN1-11600.02-112 1 of 2 Revision 3 - December 1983
. .-_ -_ =. . . - . . . _ . . - _ - -- - .
$NPS-1 ODCM l i- TABLE 3.5-5(CONT'D)
I3) Consumption rate for adult obtained by averaging data from References 10 and , 21-24 of ' Regulatory Guide 1.109. Rev.1. Oct.1977 and age-prorated using : techniques contained in Reference 10. . : I4) Data obtained directly from Reference 10 of Regulatory Guide 1.109. Rev.1 ! Oct. 1977. ; (5) Data obtained directly from Reference 20 of Regulatory Guide 1.109. Rev.1 i Oct. 1977. j II) inhalation rate derived from data provided in, Refeitnce 20 of Regulatory Guide 1.109. Rev. 1. Oct. 1977. III N/A indicates not applicable. 1 i 1 l i I i EN1-11600.02-112 2 of 2 Revision 3 - Decernber 1983 , I
SNPS-1 ODCM TABLE 3.5-6 STABLEELEMENTTRANSFERDATA(1) B F (Cow F - Element Veo/ Soil Milk (d/)1) Meat (d/kg) H 4.BE+00 1.0E-02 1,2E-02 C 5.5E+00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02 I3)- 3.0E-02 P 1.1E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 - 8.0E-04 Fe 6.6E-04 1,2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 2n 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 8.0E-04 I3) 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 2r 1.7E-04 5.0E-06 3.4E-02 hb 9.4E-03 2.5E-03 2.8E-01 Ho 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E-01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E-00 1.0E-03 7.7E-02 1 2.0E-02 6.0E-03 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-36 2.0E-04 Ee 2.5E-03 1.0E-04 I3) 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 K 1.BE-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04(5) II) Data presented in this table is from Reference 1 of Regulatory Guide 1.109 Rev. 1. Oct. 1977. ' III Meat and milk coefficients are based on specific activity considerations. From Reference 15 of Regulatory Guide 1.109. Rev. 1. Oct. 1977. Seetext(RegulatoryGuide1.lf".:e.Rev.1.Oct.1977). From Referen:e 13 of Regulatory Guide 1.109. Rev. 1. Oct. 1977. EN1-11600-312 1 of 1 . Revision 1 - August 1983
SNPS-1 DDCM TABLE 3.5-7 HUMIDITY PARAVITERS AT RECEPTORS Monthly Average Absolute Humidity fem /m8) January 3.06 February 3.09 March 3.83 April 5.71 May 8.19 June 12.62 July 15.53 August 14.62
, September 11.68 October 8.11 November 5.37 December 3.73 l
l I Bf:1-116DD-112 1 of 1 Revisien 1 - ?ugust 1983
^
O-I SP05-1 GDI '+ TMLE 3.5-8 LOCATI(M OF Pt#f37 ftSiftMT, E(ETMLE (MtOf, SITE mwmy, no Mitt mm. m sEtTiet Meerest Mrerst inwrest fleerest Site Bounrbry PesiMce(+) Veytable ra*n(+) Milk khe1(++) ' Distance
- Elevottae* Distance
- Elevattae* . Distance
- Elevattore* Distarue Elevetist" -
Settre (&ters) (Nters) (Sim) (*tm) (&ters) (%ters) (Meters) , (Meters) ; M 436 6.1 - - - - - - 10E 366 6.1 45R 12.2 - - - - PC 332. 6.1 504 12.2 - - - ' - - l1E 311 6.1 1071 12.2 IPJ5 32.0 - - E 346 6.1 1997 12.2 1212 17.4 - -
.EK 457 6.1 m9 12.2 1323 18.2 - -
SE 1105 26.0 1007 19.S 12E0 21.3 - - 55C 84 30.0 709 30.8 1920 51.4 - -
- S 610 25.0 IIMI 41.1 1837 57.9 - -
SSW 457 22.0 1487 62.5 1496 62.5 - - ; 9d 533 17.0 497 21.3 2006 . 45.7 *** ** IGl 457 15.0 1694 38.4 1867 53.3 - - - W 3E0 6.1 1808 33.5 2273 40.2 3X5 41.T(thets) leel 354 6.1 664 25.9 - - - - - led 419 6.1 - - - - - - leal . 436 6.1 - - - - - - Mutes:
- litstances are given from the tractor centerifne cut to IDI6 seters. .
" Elevations afwn are seters aime seen see level - highest elevation betnesi reactor and vroepter point. .
*" Milkirus gnets are also located at 3862 neters fWm SMPS, at elevetion 42.7 meters, in this section.
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+ C 000000b0000020000000000-Om000000++++++++++*O++++++++++++++++++++C + + +
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Mucilde Bone liver T. Rody Thyroid Kidney g GI-LLI PR-143 1.4E405 4.2E404 6.RE403 - 2.3E404 - 1.5E+08 PR-144 1.8E*03 1.8E403 1.R0403 1.8E*03 1.8E403 1.BE+03 1.8E*03 NO-147 8.5E+06 8.5E406 8.4E*06 8.4E*06 8.4E+06 8.4E406 9.5E407 . W-187 2.5E406 2.4E*06 2.4E*06 2.4E406 2.4E406 2.4E406 7.6E406 NT'-239 1.7E406 1.7E406 1.7E*06 1.7E*06 1.7E*06 1.7E+06 1.5E+07 (1) The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. RN1-11600-117 3 of 3 Revision 3 - Decem6er 1983
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Nucilde Bone liver T. Body Thyroid Kidney tg GI-LE! HD-147 2.1E*02 1.7E402 1.3E*01 - 9.lE+01 - 2.6E+05 W.In? 1.4E*04 8.3E*03 3.7E*03 - - - 1.2E+06 HP-239 8.3E*00 6.0E-01 4.7E-01 - 1.7E+00 - 4.4E+04 III The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. e BN1-11600-118 3 of 3 Revisfon 3 - December 1963 D
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SNPS-1 DDCM 3.6 [No Longer in Usel i d P F W b i EN1-11600.02-112 21.3.6-1 Revision 17 - May 1991
?
i l SNpS.-1 DDCM j 3.7 TOTAL DOSE FOR THE URANIUM FUEL CYCLE ( To comply with Section 3.11.4 of the REC which implements 40CFR190, radiation doses shall be limited as follows: The dose or dose commitment to a membpr of the public, due .to releaset Jf radioactivity and radiation, from uranium fuel cycle sources shall be limited to 25 mrem, or less, to the total body and/or any organ (except the thyroid, which shall be limited to 75 arem, or less), over any 12 consecutive months. 3.7.1 Sources et Radiation and Radioactivity 1he uranium fuel cycle is defined in 40CFR190 to include: 1
- a. operations of milling of uranium cre,
- b. chemical conversion of uranium,
- c. isotopic enrichment of uranium,
- d. fabrication of uranium fuel,
- e. generatien of electricity by a nuclear power plant using uranium fuel, and
- f. reprocesstng of spent uranium fuel.
The maximum individual doses due to each of the processing facilities for items a, b, c. d, and f above are required to be less than 10CFR20 limits. Therefore, the dose contribution to any person living in the Shoreham service area due to the above facilities, which are all more than 125 kilometers distance away, is expected to be negligible compared to 40CFR190 limits. The only radiological source of concern will be due to item e above. The nearest i nuclear power plant using uranium fuel is more than 75 kilometers away. 3.7.2 Rediologicel lesset of Generation of Electricity The generation cf electricity using a nuclear power plant results in radioactivity released in gaseous and liquid effluents. The dose rate assessment of these is done in Section 3.3. The radiological impact of direct radiation (including skyshine) from the plant can be detemined by measurement. The direct radiation measuring devices (TLD s Monitoring Program (REMP) ystems) and are listed inare provided Tables by 5-4. 5-1 and the Radiological Environmental Dose registered by the TLDs will be added to the doses calculated in Sections 3.1.1 (Dose From Liquid Effluent) and 3.5.1 (dose to maximum individual due to inhalation and ingestion from gaseous effluents) to detemine the total body dose due to all sources of radiation in the uranium fuel cycle. St:3-31600.02-112 11.3.7 1 Revision 16 - July 1900 t
SNPS-1 ODCM SECTION 4 METEOROLOGICAL AND HYDROLOGICAL PARAMETERS UTILIZED IN THE CALCULATION OF DOSES
4.1 INTRODUCTION
This section specifies the liquid pathway dilution factor and the dispersion and deposition factors utilized for atmospheric releases. A description is given of the meteorological methodology and parameters utilized in the computerized method for atmospheric rsiease. Criticallocations for receptors and their respeetive dispersion and deposition factors are provided for the backup method for atmospheric releases. For liquid effluent pathways the dilution factoris one (1.0) (only service wateris used). 4.2 PARAMETERS AND METHODOLOGY USED IN THE COMPUTERIZED METHOD 4.2.1 Meteoroloaical Dets Hourly average values (based upon 60 ene-minute values) of temperature, wind speed, wind direction and temperature difference from the 33- and 150-ft levels of the Shoreham mete orological towers are used in the computerized method, to determine X/O and D/O values at the locations given in Table 3.5.-8. 4.2.2 Lono-Term /0 and D/O Vsfues Sector average atmospheric concentration dispersion factors (X/Q)", gamma dispersion factors (X/0)" and relative deposition factors (D/0) are calculated every hour using 60 one-minute meteorological data values obtained from the meteorological towers. The methodology utilized is described in the report "Shoreham Nuclear Power Station EMSP Software (Rev. B.1)* (Entech Engineering Inc., P104-R3, Section 2.0, l July 1983, by J. N. Hamawi). General site specific data values that may be required for the calculation of dispersion parameters are given in Table 4-2. The basic methodology used tri obtain the (X/Q)" and D/O values is the straight 4ine trajectory model with Gaussian dispersion described in Regulatory Guide 1.111, Rev.
- 1. The list of selected options and variations from the Regulatory Guide is as follows:
(a) Plume depletion due to dry and wet depositions, as well as to enroute i radioactive decay is conservatively ignored, j l BN1-11600.02-112 11. 4 - 1 LIPA Revision 1 - February 1993 l
SNPS-1 DDCM (b) Plume recirculation is accounted for by making use of the conservative open-terrain recirculation correction factors in Revision 0 of Reg. Guide 1.111, which are also used in the X0QD0Q computer code (NUREG/CR-2919, 1 August 1982). l l (c) The atmospheric dispersion equations employed include terms to account for the plume eddy reflections between the ground and an inversion layer aloft. The reflection model was based on Turner's ' Workbook of Atmos-pheric Dispersion Estimates', (USEPA, Publication AP-26,1970) and has the additional capability of predicting the entire range of effects from J no reflection to the attainment of uniform vertical concentration result-ing from multiple reflections. (d) According to Regulatory Guide 1.111 Rev.1, effluents can be considered to be ground-level releases, elevated releases, or mixed-mode releases depending on (a) the elevation of the release point above grade relative to the height of adjacent buildings, and (b) the effluent exit velocity ' relative to the speed of the prevailing wind during the period of inter-est. At the Shoreham staticn, vent releases are assumed to be either at ground level or totally elevated. Conditions leading to a mixed mode release under Regulatory Guide 1.111 Rev. I criteria are conservatively assumed to result in a ground level release in the computerized method. (e) The wind speed at the release height is computed by subjecting the wind speed measured at the upper instrument level of the meteorological tower to the height-dependent wind speed relationship in the X0QD0Q computer code (NUREG/CR-2919. August 1982); the same relationship is used to replace missing wind speed data at either the lower or upper instrument levels of the meteorological tower. (f) Sector- a'erage (X/Q)Ik values are not permitted to exceed the plume centerlir.e values corresponding to the same atmospheric conditions, plume centerline values are computed using the equations in Regulatory Guide 1.145 Rev. I for non-meandering plumes, and the recirculation factor describedinitem(b)above. (g) Vertical plume standard deviations for Pasquill stability G(o (G)) are computed using the relationship between the stability classes
- F and G given in Reg. Guide 1.145. All 0 values 2
are limited to a maximum value of 1000 m. l BN1-11600.02-112 11.4-2 Revision 18 - May 1991
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(h) Site specific, sector-and distance-dependent terrain heights are employed in connection with elevated releases. These terrain heights (as given in , Table 3.5-8) represent the maximum heights between the release point and i the locations where the concentrations are being calculated, in accord. 1 ance with Regulatory Guide 1.111 Rev.1. l (1) Relative deposition factors (D/Q) are calculated using the relative deposition rates given in Regulatory Guide 1.111 Rev.1 in graphical form; the height-dependent curves in the guide are used as follows: Calculated Effective Applicability Regulatory Heicht Range (m) Guide 1.111 Rev. 1 Curve 0 - 15 Ground-level releases ab - 45 30-m releases 45 - 80 60-m releases
> 80 100-m releases In additfor. to the atmospheric dispersion factors, the computerize [A method also computes certain " effective gamma dispersion factors" (X/Q) which permit evaluation of external air and whole body doses from fiQte clouds of multi-energetic gamma sources. The basic definition of the X/Q was derived by expressing the finite-cloud dose rate equations in Regulatory Guide 1.109 in a form identical to the standard dose rate equation for semi-infinite clouds. It includes the I function of Appendix F of Regulatory Guide 1.109, and for large plume standard deviations its numerical value reduces to that of the standard X/Q. The gama spectrum is representative of the actual nuclide rix in the effluent. The finite cloud model is employed for both ground-level and elevated releases. Recirculation correction and inversion 1ayer reflec-
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tion are accounted for, and sector-average finite cloud values are not allowed to exceed corresponding plume center-line values computed in accordance with the three-dimensional Gaussian puff model described by Slade (' Meteorology and Atomic Energy 195B', USAEt TID-24190,1968, Sec. 7-5.2.2). 4.3 FARAMETERS AND METHODOLOGY USED IN THE BACKUP METHDD For gaseous effluent pathways. Table 4-1 lists the critical locations for receptors and their respective dispersion and deposition factors. The atmospheric dispersion and deposition factors were calculated utilizing Shoreham onsite eeteorological data for the 2-year period of October 1,1973 through September 30, 1975 Regulatory Guide 1.111 Rev. O. March 1976, and Rev. 1 July 1977. Several x/Q values were obtained from the Final Environmental Statement NUREG-0285, dated October 1977, docket No. 50-322 1 (SeeTable4-1).
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4 SNPS-1 ODCM TABLE 4-1 CRITICAL RECEPTOR LOCATIONS FOR GASEOUS EFFLUENT CALCULATIONS C g a B 3.11.2.1 3.11.2.2 3.11.2.3 3.11.2.5 REC SECTION Manual 3.3 3.4 3.5 3.6 Section in this . Dose to any organ due t Limiting Criteria Instantaneous Dose Quarterly and Annual Quarterly and Annual ' Rate to Whole Body Air Dose due to Camma pose due to to radionuclides other and Skin due to Noble and Beta radiation radionuclides other than Noble Gas for 31-Cas and dose to any than Noble cas day period organ due to radionuclides other than Noble Gas 458 meters, NNE ,I 458 meters, NNE Distance and Direction of 1 Noble Cast 366 meters, NNE 457 meters, ESE Receptor from the Plant 2 organt 458 meters, NNE Location of Highest Location of Highest Location of Highest Location of Highest Description of Location Dose Dose Dose Dose Long Term ( Annual Average) 3 6.6E-07 sec/m' N 8.44E-07 sec/m'O 1.33E-06 sec/m'O) 1.33E-06 sec/mM) Atmospheric Dispersion 4 1.33E-06 sec/m'W i Factor for Station i ! Ventilation Exhaust X/Qg 1 f2 Revision 17.- May 1991 BN1-11600.02-109
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SNPS-1 ODCM TABLE 4-1 A E E R Long Term Relative 9 N/A N/A 5.16E-08 m-2 p) 5.16E-08 m-2 0) Deposition Factor for 10 5.16E-08 m-2 (3) Station Ventilation Exhaust D/Qg i i I Long Island Lighting Company, Shoreham Nuclear Station - Unit One, FINAL ENVIRONMENTAL STATEMENT, NUREG 0285, October 1977, Docker 50-322. 2 " Compliance With 10CFR50 Appendix I," Shoreham Nuclear Power Station - Unit One, Long Island Lighting company, Docker 50-322, SNRC-119, July 30, 1976. 3 Based on Stone & Webster calculation 19.6A-6-120, Rev. O and NED calculation CCI#039215, Rev. O. 1 2 2 of 2 Revision 17 - May 1991 BN1-11600.02-209 I
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$NPS-1 DDCM TABLE 4-2 GENERAL SITE SPECIFIC DATA PARAMETER ,
JALUE , 3 Elevation of lower-level met. instruments 33 ft above ground level Elevation of upper-level met. instruments 150 ft above ground level Temperature sensor separation 117 feet Release height for station vent 249 ft above MSL Station grade elevation 20 ft above MSL Reactor building height 65 m Reactor building cross-sectional area 2600 m8 Station vent equivalent diameter 2.664 m Maximum effective plume height allowed 400 m Height of inversion layer aloft 600 m Maximum plume vertical standard deviation c , = 1000 m Fraction of the year that animals graze on pasture fp = 1.0 Fraction of daily feed that is pasture grass when the animal grazes on pasture f* = 0.84 4 Average transport time of activity from the feed t fa 24 hours into the milk and to the receptor l l l I i I BN1-11600-312 1 of 1 Revision 18 - May 1991
SNPS-1 ODCM , a t A- PART II - SECTION 5
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-SAMPLING LOCATIONS The purpose of this section is to identify those sampling locations from which the i radiological environmental monitoring samples shall be collected pursuant to ;
! Radiological Effluent Controls 3/4-12 (Part I of the ODCM). l Table 3.12.1-1, (Page 1.3-37), based on NUREG 0473, defines an acceptable- :
Radiological Environmental Monitoring Program by providing guidelines for the ! sampling locations according to pathways. It specifies the number, location and ;
- frequency of ssmple collection and the required analyses. j The Shoreham-specific implementation of the program is given in Tables 5-1, 5-2. f 5-3 and 5-4, corresponding to the four pathways of direct, airborne, waterborne and :;
ingestion doses. The corresponding onsite and offsite sampling locations are shown . in Figures 5-1 and 5-2, respectively. .
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SNPS-1 ODCM TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM(REMP) ' DIRECT RADIATION MONITORING STATIONS Functional Designation Location Code . (NUREG-0473) (shoreham REMP) location Description - DR1 151 Beach east of intake. 0.3 mi. N DR2 2A2 West end of Creek Road. 0.2 mi. NNE DR3 351 Site Boundary. 0.1 mi. NE DR4 451 Site Boundary. 0.1 mi. ENE DR5 552 Site Boundary. 0.1 mi. E DR6 6S2 Site Boundary. 0.1 mi. ESE DR7 7A2 North Country Road 0.7 mi. SE DR8 BA3 North Country Road. 0.6 mi. SSE - DR9 951 Service Road SNPS, 0.2 mi. 5 DR10 10A1 North Country Road 0.3 mi. SSW DR11 11A1 Site Boundary. 0.3 mi. SW DR12 12A1 Meteorological Tower, 0.9 mi, WSW DR13 1353 Site Boundary. 0.2 mi. W DR14 1452 St. Joseph's Villa, 0.4 mi. WNW DR15 1551 Beach west of intake, 0.3 mi. NW DR16 1652 Site Boundary 0.3 mi. NNW DR30
- 12G1 Central Islip Substation.
19.9 mi. W5W DR31 11G1 MacArthur Substation, 16.6 mi. SW - BN1-11500.02-112 1 of 1 Revision 17 - May 1991
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$NPS-1 ODCM TABLE 5-2 RADIOLOGICAL ENVIRONFINTAL MONITORINGPROGRAM(REMP)
AIRBORNE MONITORING STATIONS t Functional ! Designation Location Code (NUREG-0473) (Shoreham REMP) Location Descriotion. , A1 652 Site Boundary. 0.1 mi. ESE A2 2A2 West end of Creek Road. 0.2 mi. NNE A3 351 Site Boundary. 0.1 mi. NE A4 781 Overhill Road, 1.4 mi. SE : A5 11G1 MacArthur Substation, 16.6 mi. SW ; 5 l t 3 1 i I Efil-11600.02-112 1 of 1 Revision 17 - May 1991 l l J
i SNPS-1 DDCH TABLE 5-3 RADIOLOGICAL ENVIRONMENTAL I MONITORINGPROGRAM(REMP) WATERBORNE MONITORING STATIONS - Functional Designation Location Code (NUREG-0473) (Shoreham REMP) Location Description WA1 13G2 Surface, background area.13.2 mi. W . WA2 14C1 Surface, outfall area. 2.1 mi. WNW WA3 3Cl Surface, outfall area. 2.9 mi. NE Wd! 2A4 Sediment, beach. 0.4 mi. NNE f I BN1-11600.02-112 1 of 1 Revision 17 - May 1991 l
SNPS-1 DDCM TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM(REMP) INGESTION MONITORING STATIONS Functional Designation Location Code _(NUREG-0473) (Shoreham REMP) Location Description Ia. Ia2 Not Used Ib1 3C1 Fish and Invertebrates. Outfall Area. 2.9 M1. NE Ib2 14C1 Fish and Invertebrates. Outfall Area 2.1 Mi. WNW Ib3 13G2 Fish and Invertebrates. Background. 13.2 Mi. W Ic1 831 Food Product. Local Farm,1.2 Mi. SSE Ic2 6B21 Food Product. Condzella Farm.1.8 Mi. ESE Ic3 12H1 or Food Products. Background Farm. 26 Mi. WSW 12H2 Food Products. Background Farm. 32.1 Mi WSW I i l l l l EN1-11600.02-112 1 of 1 Revision 17 - May 1991 ,
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$NPS-1 ODCM SECTION 6 INTERLABORATORY COMPARIS0N PROGRAM - ,
The laboratory performing the radiological environmental analyses shall ; participate in an interlaboratory comparison program which has been approved by the NRC. Currently this program is the Environmental Protection Agency - (EPA). environmental radioactivity laboratory intercogarison studies ! (cross-check) program. Our participation code is "CJ . k I 4 1 i I 1 BN1-11600.02-112 II.6-1 Revision 3 - December 1983 l 1 t _ _ _
y SNPS-1 DDCM 1 APPENDIX A DERIVATION OF A g A (mrem /minper C1/cc) is the dose conversion factor for the combined fish plus s afood pathways due to a liquid radwaste system discharge. The doses to an organ, due to ingestion of fish and seafood (contribution from shoreline deposit is considered insignificant) containing isotope, 1, were calculated by a computer code based on Regulatory Guide 1.109. Rev. I methodology and default parameters. The computer isotopic dose rates output were normalized to unit intake concentra-tion with the following equation: Ag =UF1
- Os1 Cg /F where:
D = Calculated fish ingestion dose rate (mrem / min) to an organ, frce Fi isotope,1, (Ref. Reg. Guide 1.109. Eq. (A-3) assuming a dilution factor of 8.85. D sg = Calcuiatedseafoodingestiondoserate(mrem / min)toanorgan,from isotope,1, (Ref. Reg. Guide 1.109. Eq. (A-3)) assuming a dilution factor of B.85. Cg = Dischargeconcentrationofisotope,1(Ci/cc) F = Nearfielddilutionfactor,8.85(unitless) BN1-11600.02-112 A-1 . Revision 15 January 1990
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SNPS-1 DDCM APPENDIX B i' DERIVATION OF P,93 , P,g) (at . trem/yr is
) the dose conversion factor due to combined effect of-WC1/sec .
ingestion of leafy vegetables, ingestion of stored vegetables. (fruits, vegetables, and grains). and contaminated ground pathways. The dose delivered to organ, j, due to the combined effect of the 3 pathways were calculated for each radioisotope,1. using a computer code based on Regulatory Guide 1.109, Rev. I methodology and default parameters. The computer isotopic dose rates output t*re normalized to unit isotopic release rate and deposition factor with the equation: p , Dgg) + Dggj + Dgg3 3.17*10-2
- Cy
- D/Q where:
D = 1culated contaminated ground dose to organ, j, frcen isotope, eg3 D gg)
= Calculated leafy vegetable ingestion dose to orgen, j, from isotope, 1 D = Calculated sorted vegetables dose to organ, j, from isctope,1 34)
C = Gaseous effluent release rate of isotope,1. (C1/yr) 4 D/Q = eposition factor (m-2) as used in calculation of Deg ), Dgg), sij. 0.17*10*2 = The number of y of 9C1 per Ci g)persecond(3.17x10~8)timesthenumber BN1-11600.02-112 B-1 Revision 3 - December 1983 -}}