ML20029B267
| ML20029B267 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1990 |
| From: | Leonard J LONG ISLAND LIGHTING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| SNRC-1788, NUDOCS 9103060336 | |
| Download: ML20029B267 (299) | |
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daarmaargesnur LONG ISLAND LIGHTING COMPANY unema=- SHOREH AM NUCLE AR POWER ST ATION P.0 BOX 010. NORTH COUNTRY RO AD
- W ADING RIVCR. N.Y.11792 JOHN D. LEONARD, JR.
v:ct PetStDENT = OMCC & CORPQAATE SEfMCES mo VICE PAESCENT 0Fmt OF NUCif AR SNRC-1788, MAR 1 1991 U. S. Nuclear Regulatory Commission u ATTN: Document Control Desk Washington, D.C. 20555 Semiannual Radioactive Effluent Release Report Shoreham Nuclear Power Station . Docket No. 50-322
-Reft (1) Facility Operating License NPF-82 (Shoreham).
(2) SNRC-1747 dated August 23, 1990 to U.S. Nuclear Regulatory Commission from John D. Leonard, Jr.; subject: Semiannual Radioactive Effluent Release Report. Gentlemen: Enclosed'is a copy of our Semiannual Radioactive Effluent Release Report; covering the third-and fourth calendar quarters of 1990. l This report-is in conformance with Technical Specification 6.9.1.7 end is consistent with. Sections 6.9.1.7 ani 6.15.1 of Part I of the Offsite Dose Calculation Manual (ODCM), as revised, and Sections 9.3.1 and 9.4 of the Process Control Program (PCP),
.as. revised, and was prepared in accordance with these documents.
This report includes information for each type of r,Olid waste shipped offsite during-the period and changes made ?uring the
. period'to the ODCM, On June 25, 1990 the NRC issued Amendment No. 5 to the Shoreham Nuclear Power Station (SNPS) Operating License (reference 1).
This amendment, among other th1ngs, made changes to the Administrative Controls section (Section 6) of the Technical Specifications, relocated existing procedural details involving radioactive effluent monitoring instrumentation, equipment requirements,;and control of radioactive liquid and gaseous effluents, and radiological monitoring and reporting details from b) the SNPS Technical Specifications to the ODCM. Additionally, the amendment relocated the requirements for radioactive solid waste l i from the Technical Snecifications to the PCP and added record retention requirements for changes to the ODCM and PCP, In - A]1 9103060336 901231 /' -
' I
>PDR ADOCK 05000322 l R PDR I].
, m p-SNRC-1788-Page_2' SNRC-1747 (reference 2;, we identified that these changes were only recently made-effective and, therefore, committed to , reporting these changes in the next Semiannual Radioactive Effluent Release Report. With the inclusion of revision 16 of the ODCM in this current report, this commitment has been ,> fulfilled. If you require additionel information, please contact this office.
.Very truly yours, s
/ -
Jr D. Ile r, r. [
. [Vi.e. President, Offic e of Corporate
&' Vice President,<Off ice of Nuclear Services
/ab L cc: S. Brown-T. T. Martin B. Norris 1
l l
SIMIIMu% RADICACTIVE 17Pw1Nr REIEA9E IEPOIR 3rd and 4th Quarters of 1990 , 1990 Meteorolcgical Stunry and Offsite Dono Assentumnt ! Facility: Shoreham Nuclear Pcper Station, Unit I l Licensee: Inng Island Lighting Caqxtny, Inc. t TABLE OP 00mnES Section Page Introduction 1 , A. Supplemntal Informtion 1 B. Gasecus Effluents 4 C. Liquid Effluents: 8 D. Solid Waste 11 E. ' Radiolcgical Inpact on Man 15 F. Meteorological Data 16
. G. CDCM Revisions, Ra!P Non Carpliardes 73 and Major Changes to Radioactive Waste Treatment Systems H. Miscellaneous Special Reports 74 l ..
a 1
.-,,I.--
- -l.--- ., , , - , . . , ,, - -m , -
nfPRODtCPION This Semiannual Padimetive Effluent Felease Peport, suhnitted in accordance with Technical Specification 6,9.1.7, Offsite Ibso Calculation Manual (orm) 6.9.1.7 and _6.15.1, and Prmess Control Prngram (PCP) 9.4, covers the period frrn July 1,1990 through Doccsubor 31, 1490 Meteorological data mmmries for
- the whole of 1990 are included as is an assusnment of offsite doses due to liquid and gaseous effluents for the Viole year. Dy contractual' agrecment with New York State,-the long Island Idghting Ccrpany (LIl&) will transfer the Shoreham Nuclear Dcwer Station to the Inng Islaryl Power Authority. LIIlX) cannot operate the plant in the interim. In order to ready the plant for doccomissioning and to protect plant systems, the fuel was transferred to the 1
spent fuel pool in August 1989, and plant layup activities began. Prior to d defueling, the plant was in a cold shutdcwn condition for alnrast two years. A. - SUPPIDU? PAL INFDPbRTION 1 Reaulatorv Limits i Shoreham's effluent regulatory limits are defined in Facility Operating j License NPF-82, Shoreham Nuclear Pcuer Station, Appendix A, Tochttical ! Specifications. ai Limits for gasecn.ls effluents and noble gases are cenered by Technical Specification 6.8.4 and 00CM Controls 3.11.2.1 and L 3.11.2.2. b&c) Indines and particulates with half-lives greater than 8 days in gaseous effluents are addressed in Technical Specification 6.8.4 and ODCM Control 3.11.2.3. d) Liquid effluent limits are described in Technical Specification j 6.8.4 and ODCM Controls 3.11.1.1 and 3.11.1.2. e) In addition, with Shoreham's sampling and analysis program the follcuing typical minimum detectable activities (BOA's) were l- achieved. .These FOA's are less than the required lower limits of' i detection (LID's): Liquid: p Ce-141 3.06 E-8 uCi/ml-Co-58 2.84 E-8 uCi/ml Cs-137 2.49 E-8 uCi/ml Mn-54 2.49 E-8 uCi/ml Mo-99 1,66 E-G uCi/ml Zn-65 6.50 E-9 uCi/ml Gasecus Cs-13' 5.65 E-14 uCi/cc I-131 8.71 E-14 uCi/cc I-133 7.29 E-13 uCi/cc Mn-54 5.50 E-14 uri/cc Xe-133 1.33 E-08 uC1/cc Zn-65 1.41 E-13 uC1/cc 1 l
.. _ _ _ - - . ._ ._ - - _ . - . .-- - --- _ - .- - - - - -~ l P. Maxinum Permissible Concentrationn a-d) Maxinun pemissible liquid effluent concentrations (FTC's) are those specified in 10 CPR 20, Appendix B, Table II, Column 2 If an_isotop3 is listed with values for SOIJELE and INSOLUBLE states, the more conservative value is utilized. For gaseous of fluents, FTC's were not used. Direct calculations of dose were uti'hed to satisfy the dose rate limitations of Technical Specification 6.8.4 and .0DCM Control 3.11.2.1. l l 1
- 3. Average Enertiv ;
No isotopes above mininun detectable activities were meamp:1 in gaseous effluents. 'Iherefore, there is no reportable average energy for this tino pericd.
- 4. Measuremnts and Approximtionn of Total Radioactivity a-d) Samples were collected in the nunner and with the frequency pmscribed in Technical Specificatinns Surveillance Requirarent 6 E.4 and CDCM Controls 4.11.1.1.1 and 4.11.2.1.2. Sanples were analyzed in accordance with OrrM Controls Tables 4.11.1.1.'l-1 and 4.11.2.1.2-1 regarding both type of analysis and level of sensitivitv. M,st samples were analyzoi by gantna spectroscopy with a GerTnanium det.ector. A liquid scintillation counter was used to analyze for H-3 and Fe-55 while Sr-89, -90 analyses were done by prop 3rtional counter. Sanples analyzed for iron and strontium underwent a chemical separation prior to ctamting.
Approved sample collection and analysis procedures were follo ni.- Analytical resul+m are examined to ensure that the minimum sensitivity leve ,, required by COCM Icwor limits of detection (LII>'s) have been met. Any identifiable peaks above background are quantifieri. The methods above were used for batch releases. The same metleds were used for continuous discharges, but were canbined with gross activity measurenents on process streams and total flcw for these - streams. No estimate of percent total error is provided in Table 1A and Table 2A because all values for gaseous and liquid offluents were determined to be less than required LLD's. 2
- 5. Batch Peleases a) Liquid 3ni qualter 4th Quarter
- 1. NtnTher of batches 1.50 E+1 2.60 E+1
- 2. Total Tire - (ninutes) 2.31 E+3 4.14 E+3
- 3. - Maxinta Tinn (r dnutes) 1.77 E+? 1.83 E+2
- 4. Average Tinn (n,inutes) 4 E+2 1,59 E+2
- 5. Mininin Tinn (ntinutes) 40 E+1 1.30 E+2
- 6. Average Ficw (gpn) 1.43 E+5 7.02 E+4 (Dilution) b) Gaseous - Nom
- 6. Abnormal Paleases -
a) Liquid - Nom b) Gaseous - None en 3
SEMINMIAL BAD 10NXIVE FEFIliENT RY1FASE PETO!G B - GASIXX1S EFFIl.1EN% o 3rd and 4th Quarters of 1990 All samples of gaseous effluents were analyzed and detennined to be at or below mininn detectable activities (MDA's) for all radionuclides listed in Shoreham's ODCM. These MDA'n were below the lower limits of detection required in (IXT4 Controls Table 4.11.2.1.2-1. In addition, no other radionuclides were identified. Therefore, no entries were made in Tables lA,1B or 1C that follow. Canposite sample results for the third and fourth quarters of this reporting period are all at or belcw !OA's. Similar results for the secd quarter, which were not included in the last Santannual Report because M unavailability then, are in ard showing levels at or below MDA's. 4
1 TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Ovaner Owarter Est. Total
, g E rror. %
3 A. Fission & activation gases ,
- 1. Total release Cl . E , E . E
- 2. Average release rate for penod pCi/see . E . E
- 3. Percent of Technical specification limit % . E . E_
B. lodines
- 1. Total iodine.131 Ci . E . E . E
- 2. Average release rate for period pCi/sec . E . E
+
- 3. Percent of techrutal specitication limit % . E . E C Particulates
- 1. Particulates with half. lives >8 days Ci . E . E , E
- 2. Average release rate for period pCi/sec . E . E
- 3. Percent of technical specification linut % . E . E
- 4. Gross alpha radicactmty Ci . E . E-D. Tritium
- 1. Total release Ci . E . E . E
- 2. Average release rate for period pCi/see . E . E
- 3. Percent of technical specification limit % . E , E 5
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990-GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE B ATCH MODE Nucien sei..wo u nit i ou.ner 3 ovenert ou ner 3 overier t
- 1. Fhslon gases krypton.85 Ci . E . E . E . E krypton 85m Ci . E . E . E . E krypton.87 Ci . E . E . E . E k rypt on.88 Ci E . E .
._ E , E L .
xenon.133 Ci . E . E . E . E
~
xen6n.135 Ci _ .
. E .
E_ . E . E xenon.135 m Ci . E . E . E . E xenon.138 Ci . E . E . E . E Others (specify) Ci . E . E . E . E Ci . E . E . E . E Ci . E . E . E _. E unidentified Cl . E . E . E . E Total for period Ci . E . E . E . E
- 2. lodines 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 Ci .
_E . E . E . E unidentified Ci . E . E . E . E 6
i TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 i GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES
=
CONTINUOUS MODE B ATC'H MODE Nuefida Retesw:1 Unit i Owartw3 Quarter 4 Qwm 3 Qwwtw4
- 1. Fission pses krypton.85 Ci . E , E . E . E kry pton45m Ci E E E E_
krypton 47 Ci . E . E . E . E krypton.68 Ci . E . E . E . E xenon.133 Ci . E . E . E . E l xenon.135 Ci . E . E . E . E xenon.135 m Ci . E . E . E . E xenon.138 C 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 .
El '
- 2. Iodines iodine.131 Ci E E E_ . E iodine 133 Ci . E . E . E . E iodine 135 C . E . E . E . E Total for period Ci . E . E , E . E
- 3. Particulates st rontium.89 Ci .
E_ . E . E . E I stmntium 90 Ci . E_ . E , E . E l cetium.134 Ci . E . E , E . E i cesium.137 Ci . E . E . E . E ba rium.tanthanum.140 Ci . E . E . E , E Others (specify) Ci . E . E . E . E l Ci E
. . E . E . E i
Ci . E . E . E . E unidentified Ci . E . E . E . E 1 7 9 l
~ . . . . . - . . .- .-. - , _ , .
SDCANNUAL RADIOAcrIVE ITFIJHWP ; REITA9E PTJWT C - LIQUID DTUDTP 3rd and 4th Chiarters of 1990 P All samples of liquid effluents were analyzed and'determtimd to be at or below minfrum detectable activities (MDA's) for all radionuclides listed in the 0004. These NDA's were below the ILD's required in 0001 Controls Table 4.11.1.1.1-1,- In addition, no other radionuclid.es were identified. '1herefore, no entries were
. made in' Tables 2A and 2B that follow.
Cmposito sample results for the third and fourth quartern of this reporting period are all at or below MDA's. - Results for the second quarter, which were rvrcincluded in the last Sentiannual floport because of unavailabilit,/ then, also are at-or below the MDA's.- .l_' s
?
l .8 f r p g .-p - 9 3 y ,r -am- .
TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quener Quanet Est. Totst 1 3 4 E rror. % A. Fission and activation products _ _ _
- l. Total release (not including tntium, gases, alpha) Ci . E . E . E
- 2. Average diluted concentration during period mci /ml . E . E
- 3. Percent of applicable limit % . E . E B. Tritium
- 1. Total release Ci . E . E . E l
- 2. Average diluted concentration ,
pCi/ml during period . E , E
- 3. Percent of appbcable limit % . E , E C. Dissolved and entrained gases -
- l. Total release Ci . E . E , E l 2 Average diluted concentration dunng period mci /ml . E , 'E
- 3. Percent of applicable limit 'k . E . E D. Gross alpha radioactidty
-l 1. Total telease l Cl l . E l .
El . E l E. Volume of waste released (prior to dilution) Liters . E . E , E F., Volume of dUution water used during period ~ !it ers . E . E . E l l 6 9
TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1990 LIQUID EFFLUENTS CONTINUOUS MODE 6ATCH MOOE Nuclides Released Unitg Overter4 Qua rte r Oswter a Overter 3 3 strontium.89 Ci . E . E . E . E Ci E E E E strontium.90 . . . . cesium.134 Ci . E , E . E . E' Ci E E E E eesium.137 . iodine.131 Ci . E . E . E . E cobalt.58 Ci ~
. E . E . E . E cobalt.ti) Ci . E . E . E . E-Ci E E E E iron 59 .
Ci E E E . E zine 65 . . . mmganese.54 Ci . E . E . E . E chromium 51. Ci . E . E . E . E zirconium. niobium.95 Ci E E . E . E molybdenum.99 Ci . E . E . E . E technetium 99m Ci . E , E . E . E barium. lanthanum 140 Ci . E E . E . E cerium.14 i Ci . E , E . E . E Other (specify) Ci . E . E , E . E_ Ci E . E . E . E Ci . E . E . E . E Ci . E . E , E E Ci . E . E , E- . E Ci E E E E unidentified . . , - Total for period (above) Ci E E E , E l . , , Ci E E E E xenon.133 Ci E E E . E xennn 135 . . . 10
.a Sn4IAhM1AL RADIOACTIVE TJTwmr PFJTASE REPORT D - SWED WG."E 1rd and -4th Quarters of .1990 Table 3 prtwides 'infonnation on shipmnts of solid waste for the third and fourth quarters of 1990. Rese shipmnts consisted of drwatered Class A Resifis, Class A Dry Active Waste (DAW), and Class A Irradiated Ccruponents. There vern no irre.diated fuel ahlpmnts. Se resins were shipped in 158.1 fta ter Spec 7A High Integrity Containers UIIC's), apprened by the South Carolina Departnent of Health and Environmental Conservation. DAW was shipped in 55 gallon dntms and the Irradiated Camponents were shipped in a lead-lined B-25 bax in a special bec<
. cash.
n .I '~ s 11
-- .. . . - - - . ~ . - . . . . - . - . . - . . - - - - . - -.
. . ~ - . . - . - . . -
TAILE 3
* *
- REGiff A'IORY GUIDE 1. 21 M: PORT * * *
- l SOLID IGSTE S!IIPPID OFTSITE FOR DISPOSAL '
** DURING PDUOD FPO4 ~1/1/90 to 12/31/90**
W STE STREAM: Resins, Filters, & Evaporator Dottcnm _ WSTE CASS _ CUBIC MNT:RS CURIES % DUOR (CI) f A 17.9 3.23E-03 125%
** ESTIMATES OF MAJOR NUCLIDES BY h76'TE CIASS & STPF#1 **
h%STE STPIAMt Rsins, Filters & Evaporator Botterns with .0% CUIDFF HASTE CASS NUCLIDE ARUtR W K'E CURIES A Co-60 25.144% 8.11E-04 Fe-55 21.932% 7.07E-04 Cr-51 18.134% 5.85E-04
'Co-58' 13.443% 4.34E-04 Zn-65 4.167% 1.34E-04 79-110m 3.336% 1.08E-04 N-241 3.333% 1.08E-04
!!-3 3.255% 1.05E 04 Mn-54 2.759% 8.90E-05 Fe-59 1.682% 5.42C-05 Ce-144 1.059% 3.42E-05 Ni-63 .990% 3.19E-05
-Cs-137 .341% 1.10E Nb 148% 4.77E-06 Sb-124 .127% 4.09E-06 Co-57 .102% 3.28E-06
- Co-141 .023% .7.49E-07 N1-59 .018% 5.69E-07 Sr-90 . 007% 2.31E Nb-94 .000% 1.18E-08 C-14 .000%- 4.51E-09 On-242 .000% 0.00E400 l~
I-129 .000% 0.00E+00 Tc-99 .000% 0.00E+00 o
-k l-12
TABLE 3 (Cnnt'd)
* *
- RPGIINIORY GUIDE 1. 21 RETORT * * *
- SO1JD KA.'?PE S11IPPED OFFSITF FOR DISPOSAL
** DURlNG PIRIOD FRCf4 7/1/90 to 12/31/00**
KASTE STREN4: Dry Active Waste NASTE CIASS CtmIC WTERS CTRTPS t ERROR (CI) A 6.4 8.01E-02 125%
** ESTIMATES OF MMOR NtCLIDES BY KAS'IE CIASS & STPrJet *
- 1@STE STRF14t: DIV Active Waste with .0% Ct.TIOPP RCTE CIASS NUCLIDE ABlNIVNCE CURIES A Mn-54 21.893% 1.91E-09 Co-60 22.855t 1.83E-02 Fe-55 18,640% 1.49F-02 Cr-51 15.398% 1.23E-02 Co-58 10.941% 0.77E-03 Zn-65 3.764% 3.02E-03 Ag-110M 3.069% 2.46E-03 Fe-59 1.311% 1.05E-03 Ni-63 .060% 4.80E-05 H-3 .045% 3.62E-05 Sb-124 .008% 6.48E-06 Co-57 .007% 5.24E-06 Zr-95 .005% 4.2BE-06 Cs-137 .003% 2.10E-06 Ni-59 .001% 9.16E-07 Co-141 .000% 1.52E-07 C-14 000% 1.13E-07 Am-241 .000% 5.00E-08 Sr-90 .000% 3.66E-08 Nb-94 .000% 1.85E-08 Ce-144 .000% 1.52E-08 Cm-24? .000% 0.00E+00 Pu-241 .000% 0.00E+00 I-129 .000% 0.00E+00
'IC-9 9 .000% 0.00E+00 13
TABLE 3 (Cont'd) l
* *
- PMII A'IORY GUIDE 1. 21 REPORP * * * * ,
-SOIJD h%STE SHIPPED OPPSITE FOR DISPOSAL l l
** DURIE PERIOD FRCN 7/1/90 to 12/31/90** -
I N TE STRFM4 Irradiated Conponents HMTE CASS - CUBIC METERS CIRIES % ERIOR (CI) A 2.8 8.19E-01 125%
** ESTIFMTES OF FATOR NUCLIDES BY WASTE CIASS & STREAM **
WASTE STRFR4: Irradiated Ca ponents with .0% CtfIOPP ESTE CIASS NUCLIDE ABUNIWCE CURIES A FE-55 66.426% 5.44E-01 Co-60 29,428% 2,41E Ni-63 2.235% 1.83E-02 Mn-54 1.893% 1.55E-02 Ni-59 . 015% 1.26E-04 C-14 . 003% 2.76E-05 Nb-94 .000% 2.60E-07 Pu'241 000% 6.78E-08 Pu239/40 .000% 4.62E-08 Pu-238 .000% 2.92E-08 Tc-99 000% 2.53E-10 Np-237 .000% 1.49E-10 Cm-242 .000% 3.52E-11 1m-241 .000% 2.60E-12 Cr-51 .000% 1.37E-12
- On243/44 .000% 4.29E-14 Pu-242 .000% 1.59E-14 An-243 000% 6.50E-15 Cs-137 .000% 0.00E+00 I-129 .000% -0.00E+00 Sr-5^ 000%. 0.00E+00 l
H-3 .000% 0.00E+00 l i
** SOLID WASTE DISPOSITION StPMTRY**
p NUMBER OF SHIPMEtTTS FDDE OF TRANSPORPATION DFSTIETICU 2 Trr.ck Barnwell r O Truck -Richland [ 0 Truck Beatty 0 Truck Other U-14
.y w
, _ - ~ . _ _ _ - _ .
SD!IANN(RL PADIGCPIVE EFFLIEff ! PT.IFASE REPORT E - RADIGOGICAL IMP /CT ON WW 1990 During 1990, there vore no radioactive isotopos identified within the limits of detection in any of the liquid or gaseous streams dischargod. Therefore, dose calculations were not performd. Direct radiation (as measured on quarterly TLD's) made no contribution to offsite doses based on a camparison of 1990 done rates with 1984 (preoperational) dose rates. 'Ihe highest dose neasured in 1990 was 5,0 mrem / standard mnth 'e .4 days) at indicator location 6Al campared to the 1984
- dose at the same max! s a location of 5.1 mtun/ standard month. Similarly, the 1990 average for-all_2 dicator locations was 3.6 mram/ standard month cmpared to a 1984.value of 3.9 mrem / standard mnth.
A
-a L 15 l
l.
SDiINNIAL PADIorcrIVE FEFIUDIT RDIASE PF2 ORT F - METDOROIIX;ICAL DATA 1990 TcN.as of ctanalative joint frequency distrihition of wind speed, wind direction, ard atnespheric stability are given by quarter for release heights of 33 feet and 150 feet. We joint. frequency distributions reflect all data that was determined to be valid by a mteorological consultant and _ are given in the tables that follow. Sane of the 33-foot level wind speed data was recovered from strip charts at the ; offsite tomr. The'offsite tower data are considered representative of the site aM this tower was used for the collection of the original licensing _ mteorological data bane, which han been reviewed and accepted by the NRC. Althcujh the calibration and maintenance of the strip chart incoders at the offsite tower is not included in the Plant's Surveillance Program, they are maintained by IJICO's Environmental Engineering Departent (DNED), in acconiance with DNED's procedtires. A quarterly calibration and maintainence program for the meteorological instruments,-including these recorders, is in effect and performed by TRC Environmntal Consultants.
%e percent recovery for joint wind speed, wind direction and delta ternperature was 93% for the year.
i 16 I L L . . _ _ _ _
.. .~ . = , . - . - . ~ . - - . . . . . .. - . . . . . -
i HOURS AT E ACH HIN0 $ PEED AND DIRECTION PERIOD OF DECOR 0 1/ 1/90 TO 3/31/90 STADILITY CLAS$t- A E LEVATION: 33 HIND LPEED IMPH) HIND 01RECf10N 1*3 4-7 6 12 13*16 19-24 >t4 TOTALS N 0 0 1 0 0 0 1 INE O O 1 1 0 0 t ilt 0 0 0 7 0 0 7 E HE O O O 2 0 0 t E O O O O O O O ELE- 0 0 0 0 0 0 0 LE O O O O O O O
. SDE. 0 0 0 1 0 0 1 5 _
0 0 1 5 0 0 6 53'4 0 0 0 4 0 0 4 LH 0- 0 0 1 0 0 1 6CH 0 0 0 0 0 0 0 H 0 0 -2 2 0 0 4
>#M 0 0 0 9 5 0 14 tM 0 0 1 -11 0 0 12 ftM 0 0 t 6 t 0 10 VARIABLE TOTAL 64 PER1003 0F CALH IHOUR$1 0 i
17
HOURS AT TACH HIND $ Pit 0 AND DIRECTION PERICO OF RECORD: 1/ 1/90 TO 3/31/90 STABILITY CLASS: B ELEVATION: 33 ~i HIND GP[t0 1NPHI 'l HIHD
}
DIRECTION 13 47 8 12 15 18 19+24 >t4 TOTALS ( N 0 0 0 0 0 0 0 i l#E O O O O O O O l![ 0 0 0 2 0 0 2 tilt 0 0 0 0 0 0 0 E O u O O O O 0 i ESE O O O D 0 0 0 i SE O O 1 1 0 0 t , SSE: 0 0 1 0 0 0 1 S 0 0 1 0 0 0 1 SCH 0 0 1 0 0 .0 1 SH 0 0. 1 0 0 0 1 HSH 0 0 0 0 0 0 0 H 0 0 0 1 0 0 1 HtM 0 0 1 5 3 0 9 tH - 0 0 2 4 0 0 6 PFH 0 0 1 2 0 0 5 VARIABLE TOTAL- 27 PfRIODS OF CALM IHOURSit 0 1 l 3 1 18
k HOURS AT EACH HIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/90 TO 3/31/ 90 STABILITY CL 4.33: C ELEVATIDHi 33 HIND SPEED (HPHI HINO DINECTIDH 13 4-7 8-12 13 16 19 24 >to TOTALS H 0 0 0 0 0 0 0 l#1E O O Z 0 0 0 t NE O O 2 0 0 0 t ENE O O O O O O O E- 0 0 0 0 0 0 0 ESE O O O O O 0 0 SE O O t 0 0 0 2 SSE O 0 1 0 0 0 1 S' O O O O 1 0 1
$$H^ 0 0 4 3 0 0 7 SH 0 0 1 0 0 0 1 FCH 0 0 1 0 0 0 1 H 0 0 1 1 1 0 3 &#Ai 0 0 2 1 2 0 5 NH 0 0 3 1 0 0 4 iC #4 0 0 2 1 0 0 3 VARIABLE TOTAL 32 PERIODS OF CALM IHOUR$lt 0 l
19 1
1 l 1
.O s
1 HOURS AT EACH HIND SPEED AND DIRECTION PERIOD OF RECORD 1/ 1/90 TO 3/31/90 LIABILITY CLASS: 0 ELEVATIDNt 33 HIND SPEED (HPH)- DIRECTION 1-3 4-7 6-12 13-18 19-24 >24 TOTALS N 1 14 15 7 1 0 38 tile 1 9 5 1 1 0 17 NE O 3 6 0 0 0 9 EtlE 0 3 5 1 0 0- 9 E D 3 4 4 0 0 11 ESE O 2 4 0 0 0 6 SE O 5 4 1 0 0 10 SSE O 4 5 0 0 0 9 S 0 9 16- 14 1 0 40
'SSH 0 10 27 29 9 0 75 SH. t $ 15 0 0 0 22 RSH 0 5 11 2 0 0 le H 0 5 16 20 1 0 - 42 ICH 0 13 39 17 7 0 76 tal 1 10 10 7 3 2. 33 t#H 1 12 7 6 4 1 31 VARIABLE TOTAL 446 PERIOOS OF CALH (HOURS): 0 b
l. y , 20
i HOURS AT E ACH NIND SPEED AND DIRECTION PERIOD OF RECORD: 1/ 1/90 TO 3/31/90 STABILITY CLASS: [ tLEVATIDN: 33 HIP 4D SPEED (MPHI HIND DIRECTION 13 4-7 6 12 13-16 19-24 >24 TOTALS H 5 4 9 9 7 0 34 t#4E 1 19 18 7 10 1 56 Nt 4 19 8 1 4 0 36 EtJE 7 17 8 15 0 0 47 E 1 13 13 1 0 0. 28 Est 5. 10 9 0 0 0 24 SE 3 8 10 3 1 0 25 SSE 1 7 5 0 0 0 13 S 5 34 76 ft 1 0 147 SSH 3 to 64 51 4 0 170
$H 4 34 29 2 0 0 69 IGH 4 16 23 1 0 0 44 H 3 9 45 21 0 0 78 RM 2 8 35 34 29 13 121 tN 4 14 10 19 21 10 86 t#N 2 10 15 23 16 4 70 VARIABLE TOTAL 1040 PER1003 0F CALM (HOURS): 0 I
i 1 21 1 i i
I i 1 WJR3 AT EACH HIND $ PEED AND tJRECTION PERIOD OF RICORD: 1/ 1/90 TO 3/31/90 STADILITY CLAC$t F E LEVATI0th 33
+
HIND SPEED IHPHI HIND OIRTCTICN 13 47 8 12 13 18 19-24 >24 TOTALS N 2 5 0 1 0 0 6
.'ac 0 3 1 0 0 0 4 NE 2 5 4 0 0 0 11 ENE 2 7 6 0 0 0 15 E 1 2 0 0 0 0 3 ESE 2 3 0 0 0 0 5 SE 2 3 1 0 0 0 6
$0E 3 20- 0 0 0 0 23
$ 4 24 12 1 0 0 41 00H 3 14 16 0 0 0 35 CH 1 16- 11'- 0 0 0. 26 BCH 3 7 2 0 0 0 12 H 3- 5 2 0 'J 0 10 RM 1 5 6 1 0 0 14 tal -5 3 2 0 0 0 8
. t# M 1 1 3 0 0 0 5 VARIABL.E TOTAL 226 PE RIODS C'r C ALH I HOUR $ h 1 22
.c
t
.)
I a I
'l 1
HOURS AT E ACH NIND SPEE0 AHO DIRECTIDH PERIOD OF RECORD 1/ 1/90 TO 3/31/90 STABILITY CLASS: 0 ELEVATION: 33 s HIPfD SPEED IMPHI -
- HIND DIRECTIDH 13 47 6 12 13 18 19-24 >t4 TOTALS H 0 2 0 0 0 0 t
##tt 0 1 0 0 0 0 1 NE O O 2 0 0 0 t EHE 1 0 1 0 0 0 t E O 1 0 0 0 0 1 ESE D 1 0 0 0 0 1 SE 1 0 0 0 0 0 1 i SSE 4 13 2 0 0- -0 19 S' 3' 13 11 0 0 0 27 SSH 7 22 3 0 0 0 32 SH 1 13 0= 0 0 0 14 HSH '3 3 0 0 0 0 6 H 0 0 0 0 0 0 0 FR 84 2 2 0 0 0 0 4 NH 0 1 0 0 0 0 1 t#81 0 1 0 0 0 0 1 VARIABLE TOTAL 114 PERIOOS OF CALN IHOURSI: 0 A
, 23 l
5 N , HOURS AT EACH HIND SPEE0 AND DIRECTION , PERIOD OF RECORD: 4/ 1/90 TD 6/30/90 STABILITY CLASS A Et,EVATIOth 33 HIND LPEE0 (HPHI HIrlD OIRECTION 13 47 a-12 13-18 1* 24 >24 TOTALS H 0 0 5 1 0 0 6 . t#lE O P 2 0 0 0 2 HE O O 4 0 0 0- 4 ENE o 0 2 0 0 0 2 E- 0 0 2 0 0 0 2 E3E O O 1 0 0 0 1 SE O O O O O 0 0 00E 0 0 1 4 0 0 5 6 0 0 4 10 0 0 14 SSH 0 0 8 6 0 0 14 SH 0 0 2 0 0 0 2 IGH 'O O 1 0 0 0- 1 H- 0 0 1- 2 0 0 3
T 0 0 0 11 0 0 11
>H 0 0 3 0 0 0 3 ttM 0 0 2- 0 0 0 2 VARIABLE k
TOTAL 72 PERI 000 #4F cal,H IHOURS): 0 k i t E' l l 24
A HOURS AT [ ACH HIND OP[to AND O!Rf CTION PERIOD OF PFCORD: 4/ 1/90 TO 6/30/90 I , STABILITY CLASS 1 B l
;LEVAT10th 33 * '
Hill 0 LPEED IHPH) HIND DIRECTION 1-3 4-7 6-12 13-10 19 24 >24 TOTALS N 0 0 1 0 0 0 1 t#lt 0 1 1 0 0 0 2 NE O O 3 0 0 0 3 tile O O O 0 0 0 0 E O 0 0 0 0 0 0 ESE O O 2 0 0 0 2 SE O O O O O O O 00t 0 0 0 0 0 0 0 S 0 0 6 1 2 0 9 00H 0 0 2 4 1 0 7 LH C 2 0 0 0 0 2 H-A 0 0 0 0 0 0 0 H 0 0 1 1 0 0 2
&# M 0 0 9 10 0 0 19 FM 0 0 3 1 0 0 4 ftM 0 0 1 0 0 0 1 VARIABLE TOTAL 52 PERIODS OF CAiH (HOURSI: 0 s
25
i i i HOURS At t ACH WIND f ettD MJD DIRECTION l'ta!DD OF PtCORD: 4/ 1/ t0 t o 6/10/90 , f,fatt!LITV CLA;3 C , titVATICHi 33 MitID SP!tO a trHI H!ilD ; DIRE CT10P1 1-3 4-7 6 12 13 18 19 24 mit TOTALS ; N 0 1 4 0 0 0 $ 19tt 0 t t 0 0 0 4 nt 0 0 0 0 0 0 0 ' t tit 0 0 0 0 0 0 0 t 0 0 0 0 0 0 0 ' tt! 0 0 0 0 0 0 0 Of 0 0 0 0 0 0 0 Ett 0 1 2 0 0 0 3 S O O 4 3 1 0 6 6LH 0 0 6 9 0 0 15 OW 0 1 0 0 0 0 1 H0H 0 0 0 1 0 0 1 N 0 0 3 0 0 0 $ b1M 0 0 10 0 0 0 10 IN 0 0 17 0 0 0 17 ftM 0 0 0 0 0 0 0
- VARIABLt ,
TDfAL 73 Fik!OD3 0F C ALM IHOURS): 0
+
26 p -.w--rr y-r-., -r, , , -y m , -w , , - , - . ,,,w,.,--,-.,v, r,--,, .- ,e.,-,,n,w,---,,,,.m-+...e.,,, y .,.- - - -w o,-m m m, -- v .,.m,,n.-- . . . - . . , . , ,..,mewm.----,.~-, ..n.n.,
, a .. ...-~._v.u- . . . ~ . . . . ~ . _ . - . - - ~ . . . _ . . . . . . - . - . _ . . _ . - - . . . , - . - - . . . - ...
I i L HOVt3 AT ( ACH N!tJD t.P(to AtdD Cl*1CTION PERIOD Of RECORD: 4/ 1/90 70 6/30/90 Stat!LITY CLA00: 0 ELtv&f! Celt 33 H!l40 arttD IMPHI H!tfD 13 47 6 12 15 16 19+t4 >t* TOTALS DI Pt C T10'.4 ... H 1 26 6 1 0 0 35 f t tt 0 lb 6 % 0 0 37 lit 0 17 4 10 0 0 31 f tif 0 t 1 4 0 0 7 t 0 1 7 1 0 0 9 L Ot . 1 1 1 0 0 0 3 Lt 0 + 4 1 0 0 11 L0t 0 13 29 4 1 0 .47 S 1 15 42 26 6 0 109-CSH 2 lb 19 21 10 0 68 0H 3 4 6 1 0 0 16 -' H0H 0 3 11 1 0 0 15 ; H O' 4 12 6 0 0 to , HH 1 16 $7 19 0 0 *$ fH 0 to 36 $ 0 0 69 ti!M 0 36 19 0 0 0 54 VARIABLt T0fAL 630 t'tP1003 Or cal.H t Houn 1: 0 i a h F 27 i I
_ . - ._ . . . - . - = _ _ . _ . . ... .._._ . . . ______..m__ . _ _ . _ . . . _ . . . _ _ _ . _ . . _ . .-___...__m _ _ . _ _ _ . _ . _ m i it0VR$ At tatH HIND SPt!D AtJD DIRECTICH PtPIOD GF RtCORD: 4/ 1/90 10 6/30/90 Li&BIL17Y CLALS: t (Ltvat!Dre: 33 HIPC trttp (HPHI Hit 0 D!RtCT!tN 13 47 61213161924 >t4 TOTALS N 3 11 19 11 2 2 40 ' telt 8 20 11 17 4 0 60 HI 10 35 ti 15 4 0 85 tt4 0 17 26 18 -0 0 61 (. 3 7 $ 1 0 0 16 Ett 2 12 5 2 0 0 21 St 2 16 4 1 0 0 25 001 3 35 22 6 1 0 67 S 8 8b 111 43 6 1 252 SOH 11 48 23 .30 4 5 121 LH 9 20 - 14 0 0 0 43 H*H 8 12 7 2 0 0 29 I H 4 23 12 3 0 0 42
' 6tM 12 to 11 13 0 0 56 PM 2 10 14 11 11 0 69 ftM 6 11 11 16 7 $ $6 VAR 1&BLE TOTAL' 1049 PtP1003 0F CatP IHOVRSI: 1 r
l t 28
- _. _ _ ._ .- - _ .~ . ._ _, ~ . _ . - _ . , _ _ , _ . . . _ _ _ _ _ _ . _ . . _ , . . . _
hWR!, At (f CH N11tD trtt0 AND 01ttCtitw4 FIRIOD OF RECORD: 4/ 1/*0 to 6/10/90 LTA0!LITY CLA03: F t t t V Allt"l a 31 HIND Lttt0 (HPH I H!Il0 01tttt104 13 47 01111181974 St4 TOTALS H t 0 4 0 0 0 6 ftJt 0 0 0 0 0 0 0 NE 1 0 0 0 0 0 1 tut 1 1 0 0 0 0 t i 1 0 0 0 0 0 1 Ett 0 0 0 0 0 0 0 LE 1 1 0 1 0 0 3 00t 4 4 3 0 0 0 11 0 9 24 to 1 0 0 64 LSH 4 12 2 0 0 0 16 OH 11 to 3 0 0 0 19 6CH $ 6 0 0 0 0 11 H $ $ 0 0 0 0 11 88 H 6 4 t 0 0 0 13 fM 3 1 4 0 0 0 9 ftM 4 6 1 1 0 0 12 VtRitBLE TOTAL 186 f t t'!ODS OF C ALM I HOUP.S I: 3 I 29 l .. . .
.. . _ = . .. - . . . . - - - - . . - . - . - - - . ~ . - . . . - . . . . . _ - . . . . . - . . . - . . _ . - - ~
l l l i 1 1 H7)R$ AT (ACH H!t3D trtLD AND 01 RECT 104 j PERIOD OF R(CORD: 4/ 1/90 TO 6/30/90
$1ABit!?Y ttAta O lit VAT 10:48 33 Hit 1D Spit 0 INPH)
HIllD DIRE CT!0tl 13 47 6 12 13 18 19 24 St4 TOTALS 0 ' H 0 0 0 0 0 0 telt 0 0 0 0 0 0 0 tit 0 0 0 0 0 0 0 th! 0 0 0 0 0 0 0 t 0 0 0 0 0 0 0 , L;t 0 0 0 0 0 0 0 .s Lt t 0 0 0 0 0 t ttt 1 5 2 0 0 0 6 S 2 14 1 0 0 0 17 OLH e to 1 0 0 0 ** LH 2 1t 2 0 0 0 17 DG4 9 2 0 0 0 0 12 H 2 1 0 0 0 0 3 4tal 2 0 0 0 0 0 t , lA4 1 1 0 0 0 0 2 t# At 0 0 0 0 0 0 0 VARIAttt TOTAL 92 PERIODO Cf CALM IHDUR$1: 2
+
30 _. ._ _ , . . . . _ - _ _ - ~ . - - . - , - _ , . . - . _ ,
g,,<, 3 7n.y i/y ,__ . ',l i E
,-7 [
i i r HOUR $ AT (ACH HIND SPllD AND DIRLCTION PER100 0F RICORot 7/ 1/90 TO 9/50/90 STABILITY CLASS: A ILivATIDH 55 HIND LPttD INPHI HIND 01Ritf!ON 13 4*7 6 12 13 16 19 24 St4. TOTALS H 0 0 0 4 0 0 4 int 0 9 1 1 0 0- 11 NE D 6 16 2 0 0 26 LHE O t 2 0 0 0 4 L 0 0 0 0 0 0 0 (St 0 1 0 0 0 0 2 St 1 2 0 0 0 0 8 ttt 0 t 8 0 0 0 10
$ 0 3 11 2 0 t 16 CCH 0 0 4 1 0 1 6
!.H 0 0 0 0 0 0 0 HSH '0 0 0 0 0 0 0 H 0 0 0 0 0 0 0 RH 0 0 1 0 0 0 1 tM 4 1 1 2 0 0 8 INH 0 2 1 0 0 0 3 VARIABLE TOTAL - 96 PERIODS OF C ALH IHOURS h 0 F
0 w l i 31
HOURS AT ( ACH HIND $Ptt0 AttD DIRttilpN PIRIOD OF RECOR0t 7/ 1/90 10 9/30/90 STABILITY CLA0$t b (LEVAT100: 33 HIND SPtt0 tHPHI HIllD DIRECTION 13 47 8 12 13 18 19 24 >to TOTALS H 0 0 0 1 0 0 1 t#11 0 3 0 0 0 0 3 tit 0 1 6 1 0 0 8 Itit 0 0 0 0 0 0 0 t O 3 0 0 0 0 3 [bt 0 0 0 0 0 0 0 Lt 0 0 0 0 0 0 0 SOE O O 2 0 0 0 t L 1 2 4 1 0 0 8 LLH 0 2 3 1 1 1 0 SH 0 0 0 0 0 0 0 HSH 0 0 0 0 0 0 0 N O O O O O O 1 HIM 0 0 1 0 0 0 3 iM 0 1 2 1 0 0 4 I?M 0 1 3 0 0 0 4 VARIADLE TOTAL 43 PtRIODS OF CALM iHOURS): 1 32
. . . . _ - . . ~
i
+
l HOURS AT t ACH HIND $ pct 0 AND 01RtCTICH PERIOD OF RECORD: F/1/90 TO 9/30/*0 i J STA01LITY CLA0$t C ELEVATION: 33 HIND $Ptt0 iHPHI H1tto DIRECTION 1-3 4-7 6 12 15+10 19 24 >t4 TOTALS N 0 4 1 0 0 0 $ t#d! O 3 1 0 0 0 4 ilt 1 4 3 0 0 0 6 E tit 0 4 0 0 0 0 4 t 1 1 0 0 0 0 t Ett 0 0 0 0 0 0 0 St- 0 0 0 0 0 0 0 Stt 0 1 3 0 0 0 4 0 0 4 5 1 -0 0 10 LtH 0 1 2 0 0 0 3 LH 0 3 0 0 0 0 3 6CH 0 0 1 0 0 0 1 H 1 0 0 0 0 0 1 HM 0 0 4 1 0 0 & 984 1 4 3 1 0 0 9 t#M 0 3 t 0 0 0 $ VARIABLE TOTAL 64 PERIODS OF CALH IHOURSli 0 t l l 33
.. _ _ .. __ _ _ _ .- _ -, . . ~ . . . _
.- - - . - . . - . . - -. - .. - ._ - - - - .. . . .. -.... ~ . ~ . - ~ . - . . _ - . . . . - . - _ ~
N I I l 1 i i 6
- HOUR $ AT ( ACH H2ND $PtLD AtlD 07RICT10N j PERIOD OF RICORD
- 7/ 1/90 TO 9/30/90 tiADIL11Y CLASS: D ,
(LivATION: 33 R1tlD SPELD IMPHI ' M1tlD DIRECTION 13 4.) 8 12 15+18 19 24 >t4 TOTALS H t t3 t 0 0 0 27 l#ft 9 15 6 -4 0 0 $1 IJE 3 19 17 3 1 0 45 tilt ! 13 5 1 0 0 21 ( 4 0 0 0 0 0 4 (St 1 4 0- 0 0 0 $ LE 4 8 2 0 0 0 11
$$t 0- to il 0 0 0 35 5 3 19 32 2 1 1 58 SCH 1 19 16 3 0 3 42 LH 1 10 0 0 0 0 11 ,
HSH 1 5 8 0 0 0 9 H 1 12 7 0 0 0 to HtM 3 29 29 4 2 0 66 i tal $ 49 10 & 0 0 65
#FM ll $9 2 4 0' O 78 YARIABLE TOTAL $28 PERIODS OF CALH IHOUR$1 1
+
4 s 34
. __ _ - _ . . . . _ . . . _ _._____.__:_.___.. .__..u, _ _ _ - - _ _ _ _ . . . . . _ . . _.. _ _ _. . u . .-
i i HOUR $ Af !LCH HIND SPEED AND DIRECT 1r,y PERIOD OF RECORD: 7/ 1/90 TO 9/50/90 STAD1LITY CLA0$t t EttVAT104: 31 Hitl0 $Ptto litPH) H!!JD DIRECTION 13 47 6-12 13 18 19 24 >t4 TOTALS H 5 11 8 8 1 0 34 t#JE 9 18 17 12 3 0 59 flE 14 37 49 34 2 0 136 E fit 20 25 30 t 0 0 78 E 10 6 1 0 0 0 19 Ett 23 9 0 0 0 0 St St 15 16 3 0 0 0 36
- LCE 14 40 18 0 0 0 el S 9 99 54 6 F 1 171 SOH 8 23 20 1 0 1 54 SH 4 7 2 0 0 0 14 H0li 11 11 0 0 0 0 23 H $ 22 6 1 0 0 35 6# 84 7 28 $ t 1 0 44 154 10 18 25 ? O O 62 6*M 6 23 16 11 1 0 $6 4RIABLE TOTAL 936 l'ERIODS OF C ALH IHOUR3 h 17 35
HOURS AT TACH HIttD Lott0 AtID 01RICT10t4 Pt kl0D OF Rf CORD: 7/ 1/90 10 9/30/90 LTABIL1tY CLALL: F I LE VATI0th 33 H1tJD LPit0 (HPHI H194D 0!hlCT10N 11 4-7 6 12 13 10 19 14 >t4 TOTALS H 0 4 1 0 0 0 6 IPJE O 1 0 0 0 0 3 til 1 0 0 0 0 0 1 (f at 2 1 0 0 0 0 3 L I C O O 0 0 t (Lt 3 0 0 0 0 0 4 Lt 3 1 0 0 0 0 7 LLE 10 $ 0 0 0 0 16
$ 10 60 4 0 0 0 74 LLH B T4 11 0 0 0 66 LH 12 14 1 0 0 0 31 mH 7 1 1 0 0 0 10 H 6 1 1 0 0 0 9 HtN 3 7 0 0 0 0 13 ft( 1 6 1 1 0 0 10 f#M t 4 2 0 0 0 9 VARIADLt TOTAL 244 T't R1005 0F CALM tSiOURSle 12 36
HOURS AT [ACH HIND SPt[0 AND DIRECT 10H PERIOD OF RECORD: 7/ 1/90 TO 9/30/90 STABILITY CLA$$1 0 ELEVAT10ti 33 HIND Spit 0 iHPHI HIltD DIRECT 10tl 1-3 47 Salt 13 18 19 24 >t4 TOTALS H 0 0 0 0 0 0 0
##JE O O O O O O- 0 lit 0 0 0 0 0 0 0 Etet 1 0 0 0 0 0 1 E O 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 St 7 3 0 0 0 0 11 LSE 5 15 0 0 0 0 20
.S 19 34 0 0 0 0 53 LLH 19 $$ 4 0 0 0 90 GH 21 8 0 0 0 0 30 s R$H 11 1 1 0 0 0 16 H t 0 0 0 0 0 3 Moi 1 0 0 0 0 0 3 184 0 0 0 0 -0 0 1 leM 0 0 0 0 0 0 0 VARIABLE TOTAL 229 P[R1005 0F CALH IHOUR$1 11
?
1 l-l I 37 l- .u 1
i l i l I HOURS AT EACH H!t4D SPttD Ato CIRtCTION PtRIOD OF PICORD: 10/ 1/90 TO 12/31/90 t STABILITY CLALL: A - (LEVAT10th 33 t hit 1D LPtt0 iMPHI Hit 3D ; DIRECTION 1+5 47 6 12 13 10 19 24 >tb TOTALS n 0 t 1 0 0 0 3 q t#1t 0 1 4 0 0 0 $ I!E O ? 4 0 0 0 4 E tJE O 2 1 0 0 0 1 t 0 1 1 0 0 0 t L0t 0 0 0 0 0 0 0 tt 0 0 0 0 0 0 0 LOC 0 $ 0 0 0 0 5 L 0 1 0 0 0 0 1 i~ LOH 0 '9 0 0 0 0 9 LH 0 0 0 0 0 0 l ICH 0 1 0 0 0 0 1 H 0 2 1 0 0 0 3
&# H 0 h 5 0 0 0 10 188 0 7 13 5 0 0 25 18 td 0 3 8 13. 0 0 24 VARIABLE total 95 PERIODS OF CALM f H7,93 8: 0 P
i 38
l HOVR3 at ( ACH HIND Spit 0 A'JD 01RICT204 )
' I PERIOD Of RICORD: 10/ 2 /00 TO !!/31/90
?TADILITY Ct&Out B (Liv &TICels 33
-HIffD Lftt0 IHPHI i H!im O!PLC11Cri 13 47 8 12 13 18 19 24 >t4 toteLS H 0 0 1 0 0 0 1 }
tDlt O. 0 1 0 0 0 1 ilt - 0 1 0 0 0 0 1 Illt . 0 0 0 0 0 0 0 t 0 0 1 0 0 0 1 ftt 0 0 0 0 0. 0 0 -( 5t 0 0 0 0 0 0- 0 SLt 0 1 0 0 0 0 1 S 0 t 3 0 0 0 $ LLH 0 1 1 2 0 0 4 . LH - 0 0 0 0 0 0 0 H0H 0 2 0 0 0 0 t
.0 H 0 0 -0 0 0 0 6tM 0 t 5 4 0 0 11 FM 0 1 2 1 0 0 4 trM 0 3 0 6 0 0 9 VARIADLL TOTAL 40-Ft k!ODS OF C ALH (HOURL I4 0
?
I 39
.- , ~ . . .-. . - . - . . . . . - , . - . ~ . . .. . . . . . . , . . . . - _ , - . , , . . . .
. ~ . - . , - , - - - . - , - . . . ..-
. - . . . . . .. m _. ._ . _ . _ - _ . ~ . . . - . , _ - . _ . - - . . . _
l HWR$ At t&CH HildD $ Pit 0 AND O!PICTION PERIOD OF RECORD: 10/ 1/*0 10 12/11/90 Lidt!LITY CLA03: C ( L LYAf!Dtil $3 HIND LPtt0 IMPHI Hitl0 O!PLCf!OH 1+3 67 6 12 11 18 19 16 pts TOTALS H 0 0 0 0 0 0 0
##4 0 0 0 0 0 0 0 ft 0 0 0 0 0 0 0 tilt 0 -0 0 0 0- 0 0 ,
t 0 1 0 0 0 0 -1 ^
!?! 0 0 0 0 0 0 0
- tt 0 0 0 0 0- 0 0 -;
L$t 0 1 0 0 0 0 1 0 0 5 1 0 0 -0 6-LSH 0- t 6 0 0 0 0 LH- 0 0 2 0 0 0 2 SCH 1 0 2 0 0 0 5 H 0 1 0 0 0 0 1 t#M - 0 -1 1 6 2 0 8 IM 0 6 2 2 0 0 8 18 64 0 1 6 2 0 0 7 i 469taDLt TOTAL 65 PtP1003 0F CALM IHOUR$1: 0 l
/
P r f. P 40 _ . . , - . _ - . . ~ . . _ _ _ . . - . . . - , _ ._._...._.___.....___.__1_._...-_-_,--..._ .______,,-_;
v i 4 t i H3)R3 AT ( ACH HIND $Pf tp UtD 0!RtCT10ri IERIOD OF RCCORD: 10/ 1/90 TO 12/31/90 ' OTA0!L17Y CLA03: D (Ltv&TIOril 33 i HIND C#EtD iHPHI W1HO DIRECTIOPd 13 47 8-12 13 18 19-24 *t4 TOTALS . H t 3 4 1 13 0 23 ; trit 3 6 3 16 9 0 37 i fit 0 5- 5 4 0 0 14 flit 0 t i 1 0 0 $ t t 11 3 0 0 0 16 [0E 4 4 0 0 0 0 8 Lt 2 3 3 0 0 0 6 LOL U 6 6 2 1 0 14 3 3 to 14 7 0 0 44 CCH . 2 14 21 0 0 0 37 D4 2 5 9 0 0 0 16 H5H 2 4 6 0 0 0 12 H 3 6 13 3 0 0 25 teal 6 15 19 26 9 0 75 484 3 6 10 15 2 0 36 tra4 1 5 7 29 7 5 54 VARIABLE ; total 424 FER10D3 0F CALH IHOURSI 0 1 1
~~
l-. . 41
_. , _g_._ . . . . . _ _ .. . . . - - - - - = - - l r o e HOUR $ AT L ACH H1ND LPtt0 AND O!RECTION # t PERIOD OF E'tCORD: 10/ 1/90 TO 12/31/90 i STADILITY CLA03: E ELtv& TION: 33 HIND opt t D I MPH I HIPID DIPtCTIDH 1-3 47 8 12 13 18 19-24 >t4 TOTALS N 0 3 22 10 2 0 38 telt 0 2 19 6 t Q 29 lit 1 0 1 A 0 0 7 + tilt . 3 6 0 0 0 0 9 E 13 13 1 0 0 0 27 [0E 11 14 10 $ 0 0 40 t SE 7 22 7 4 0 0 40 LOE 8 to Il 3 1 0 $$ 5- 11 91 39 10 0 0 151 LOH 10 $4 36 16 0 0 118 91 13 27 9 2 0 0 $1 FCH 5 14 10 1 0 0 31 H 4 14 20 8 0 0 46 6884 4 16 23 $1 19 0 113 13H t 10 27 38 11 0 69 tP&4 0- 3- 26 66 22 1 119 VARIABLE TOTAL 963 PERIOO3 Or CALM IHOURSI: 4 l l' 42
- - - , _ . . , . _ . . - _ . - . _ _ _ _ . _ - . - _ , . . . . _ - _ _ _ . . _ _ . ~ . , . - - - _ . _ _ . _ _ _ _ _ _ _ _ .
l 1 l l 1 1 l HOUR $ AT (ACH NIND $PitD AND O!PECT!ON , rikl0D or Wit 0DO: 10/ 1/ % /0 !!/31/90 ST Ah!LITY CL&O$t F t tt VAtJ 0til 33 HIHD SPt t 0 I HrM i ' N1fl0 - Of fitCt204 13 47 6 A t 13 16 19 14 >t4 TOTALS N 0 0 0 0 0 0 0 INE O O O O O O O HE 1 0 0 0 0 0 1 (tit t 0 0 0 0 0 t i 1 0 0 0 0 0 1 ttt 11 0 0 0 0 0 17 01 4 1 0 0 0 0 -6 L;t- 6 6 0 0 0 0 36 0 13 29 4 0 0 0 47 , LOH 9 16 1- t 0 0 79 LW 13 14 2 0- 0 0 St FCH- 3 3 0 0 0 0 6 H 1 t 0 0 0 0 3
. 6t H 0 1 0 0 0 0 1
- 164 0 0 0 0 0 0 0 IPM O' 0' 0 0 te 0 0 VARIABLt TOTAL 161 PtR1003 0F CALH IHOURS) 10 e
l l l 43
.. : . . . - , - . , - , . . . , . , , , , _ , . . . + , - . - _ . - - . - , , . - . . . . - . . - . . . . - . . - . - . - - . - _ . . - _ - - . . . , +
I f i HWRS AT ( ACH H2tfD Spit 0 AtlD OlPtCT10t4 L PERIDO 0F PtCORO: 10/1/90 TO 12/31/90 '^ $ fab!LITV CL&Oas G EttVATICP4: 33 N!!!O SPt!O INPH) I Hind O!PE C T104 1+3 47 6 18 13 16 19-24 >t* TOTALS N 0 O O 0 0 0 0 ettt 0 0 0 0 0 0 0 NC 0 0 0 0 0 0 0 t rit 0 0 0 0 0 0 0 t 0 0 0 0 0 0 0 10t 2 0 0 0 0 0 t CE 3 0 0 0 0 0 3 S:t 11 14 0 0 0 0 !$ L 24 24 0 0 0 0 68 C0H 33 47 0 0 0 0 SD
- 94 15 14 0 0 0 0 31 HtH 4 1 0 0 0 0 8 H 0 0 0 0 0 0 0 sch . 0 0 0 0 0 0 1 IM 0 0 0 0 0 0 0 ftM 0 0 0 0 0 0 0 VARIABLE TOTAL 198 PIPIODS OF CALM l HOUR $11 6 t
W 44
IICOR3 AT ( ACH HlHD LPILD AND O!RICTIDH Pip 100 0F DICORD 1/ 1/90 TO 5/11/90
$1 ADILITY C L AOS A (LivA1104: 1LO Hill 0 LPito lHPHI Nit 10 01P,1 C f 10'4 1*1 4*7 $*18 13-18 19*th >t4 TOTAlt
......... ... ... .... ..... ..... ... ...+..
H 0 0 t 3 0 0 L IP11 0 0 1 1 0 0 t fit 0 0 0 0 0 0 0 t elt 0 0 4 4 0 0 8 t 0 0 0 1 0 0 1 tti 0 0 0 0 0 0 0 Lt 0 0 0 0 0 0 0 L$t 0 0 0 0 0 0 0 L 0 0 0 2 0 0 t LLH 0 0 0 6 1 0 9 LH 0 0 0 0 0 0 0 HSH 0 0 0 2 0 0 t H 0 0 0 3 1 0 4 t#i>4 0 0 0 7 3 0 10 tal 0 0 3 6 1 0 10 iP M 0 0 t 9 1 0 12 VARIABLE 10TAL 6L PE RIODS OF C ALPt i HOUR $ h 0 45
j l 1 i
\
) i H URS AT ( ACH K1HD LPit0 At40 DI A[CTIDN ; PtRIOD OF RECORD: 1/ 1/90 TO 5/31/90
$TADILITY CLALS: ti ,
- ( Lt VAT 10f4
- 150 HIHD LPtt0 lHPH)
HIllD + DIRtCT10ti 1-3 47 6 12 15 10 19.t6 >t4 TOTALS-N . 0 0 0 1 0 0 1 iPit 0 0 0 0 0 0 0-
.. NE O O O O O O O ttal 0 0 1 1 0 0 t t 0 0 0 0 0 0 C ttt 0 0 0- 0 0 0 0 I Lt 0 0 0 0 0 0 0
$$t 0 0 1 2 0 0 3
$ 0 0 0 0 0 0 0 LLH 0 0 0 1 0 0 1
$H 0 0 0 1 0 0 3 PCN 0 0 1 0 0 0 1 H 0 0- 0 1 1 0 t Ht H 0- 0 1 4 0 0 $
tal 0 0 t t 8 0 7 1 t#M 0 0 2 1 1 0 4
'YARIABLE TOTAL F7 .
PERID0t. OF CALH IHOUR$18 0 i L 5 1 1 46
- 4-, . ,
wy .. -e,...--4 -uew ,.-..m_~ -,.t,.y..m.m,_ .._-.__,wmr,mw.,,----,y,.# , ,.e-,,--w..,.
HOURS AT ( ACH HIND $Ptt0 AtlD 01RICT!!N i PLRIOD Of RICORO: 1/ 1/90 70 3/31/90 STABILITY CLASS: C ELEVATION: 150 HIND $Ptt0 IttPH) HIND 0.*tCT!DN 13 4-7 6 12 13 18 19.te St4 TOTALS
-..,<...... ... ... .... ..... ...r.. ... ......
H 0 0 0 0 0 0 0 ta lt - 0 1 2 0 0 0 3 0 la 0 0 0 0 0 0
!!4 ' 0 0 1 1 0 0 t t 0 0 0 0. 0 0 0 (St 0 0 0 0 0 0 0 CL 0 0 3 0 0 0 3
$$t 0 0 b o 0 0 0 l S 0 0 0 0 0 0- 0 SSH 0 0 1 2 1 1 S SH 0 0 1 1 1 0 3 RSh - 0 0 0 7 0 0 3 H 0 0 1 0 1 0 t 60 64 0 0 3 0 1 0 t 154 0 0 4 1 2 0 7 t#64 0 0 1 1 0 0 t VARIABLE TOTAL 52 PERIOOS OF CALH IHOUR$14 0
?
I l 47 1
HOURS At t ACH HIHD $PEID AND 01RICTMH PERIOD OF RECORD 1/ 1/90 TO 3/31/v0 STABILITY CLALS: 0 EttVAT1&h 160 HIND LPttD ttFH1 HIND 0!Rttf1DH 13 47 B 12 13 16 19 14 >t4 TOTALS H 0 17 8 6 0 0 31 tatt 1 le 8 4 2 0 29 P4 2 4 0 0 0 0 6 [f tE O 6 9 1 0 0 16 t 1 2 6 1 1 0 11 (Lt 0 1 4 3 4 0 12 St 1 4 5 0 0 0 10
'J0t 0 t 2 1 0 0 $
S 0 3 5 1 0 0 9 LLH 0 4 20 34 11 10 79 LH 0 2 12 17 10 0 41 tCH 0 3 10 6 0 0 19 H 0 3 12 19 6 0 40 HN O 8 35 18 17 0 76 fH 1 11 12 3 9 0 36 leM 1 4 3 11 4 3 26 VARIABLE 10fAL 446 PERIODS OF CALH IHOURSli 0 48
HOUR $ AT taCp dIND $PilD AND D1RICTION PE RIOD OF PIC0kti 1/ 1/90 to 5/51/90 STABILITY CLALL: 1 (Liv & TION: 150 HIND LPEED IMPHI HilJD DIREC1131 13 47 6 12 13 18 19.L'4 >t4 TOTALS N 1 11 15 21 8 0 56 trit t 4 19 16 6 0 49 tit t t 16 5 3 0 20 tilt 0 12 ft 5 3 0 41 t 3 8 21 to 4 0 16 (St 1 It 15 5 0 0 31 Lt 1 8 12 1 0 0 !! SLE O 4 6 7 1 0 18 5 0 6 5 7 0 0 10 LLH 0 3 45 75 16 5 162 LH 0 6 !! 90 19 t 159 H3H 0 11 36 to 1 0 76 H 0 6 to 42 t 0 60
&#N 4 7 18 37 39 6 ill IM t 9 19 30 24 6 #2 tt M 0 5 tt f6 t1 6 00 VARIABLt TOTAL 1010 PERIODS Of C ALH IHOUR$1 0 G
49
NCt>R$ At t&CH HIND f,Pt!O UiD DIRitt10N PtRIOD OF AtCDPD: 1/ 1/90 TO 3/31/90
$TABILITY CL&tS: F ILtVkT1(24: 150 WIND CFttD IMPHI HIND' 01 RECT 10ti 13 47 6 12 Il 16 19 t4 >r4 TOTALS N 0 I -& 1 0 0 9 tPJC -0 1 0 0 0 0 1 Ht 0 1 7 0 0 0 4 tt:t 1 3 11 1 0 0 16 C .
0 6 6 5 0 0 15 (Lt 0 1 1 0 0 0 4 Lt 0 7 1 0 0. 0 6 00t 0 4 6 0 0 0 10
$ 0 4 13 4 0 0 21
.t0H 0 0 16 7 0 0 23 SH 0 6 8 16 0 0 30 H0H- 0 2 13 16 1 0 34 H 1 4 9 2 0 0 16 Ff M ' 0 3 6 2 0 0 11 tai 0 4 3 $ 0 0 12 t#M 1 ! 4 1 0 0 6 VARIABLt TOTAL ff6 PtP.1003 0F C&LH IHoudSI 0 50
1 l l 4 HDVR$ AT ( ACH HIND $Ptt0 AND DIRECTION i PtR100 0F RICORD: 1/ 1/90 TO 3/51/90 STADIL:TY CLAS$t C ELtVAT104: 160 i HIND LPEED lHPHI HIND 01RttT!DH 11 47 8 12 13+18 196t4 *t4 TOTALS i 0 5 0 0 0 0 5 H t#2 0 1 0 0 0 0 1 NE D 1 1 0 0 0 t 0 $ i INE D 1 4 0 0 L 0 1 1 0 0 0 t
!?! 0 1 1 0 0 0 t St 0 1 0 0 0 0 1 LSE D 5 6 2 0 0 13 t S 1 2 & 4 0 0 12
- LLM 0 5 6 7 0 0 14 9 8 0 0 21 l LW 0 w HSH 0 2 10 $ 0 0 17 H 1 6 1 0 0 0 t RM 3 6 2 0 0 0 11 '
PM 0 0 2 0 0 0 t 18 64 0 0 0 0 0 0 0 VARIABLE TOTAL 114 FERIODS OF CALH IHOURSI: 0 i I e f
" a
.P 51
__ . _ . . _ . . . _ _ _ _ . _ . _ _ . , , _ . . ~ _ , _ . - - - _ .
HOURL At t ACH HIND J,Ptt0 AtJD 01 REC 110H PIR10D OF RC*S*Ds 4/ 1/*0 10 6/30/90 STAB!(Ify CLAOS: & L L E VAT 10til 160 H1fl0 LPttD IHPHI H!tlD 01F E C110t4 13 6-7 6 12 13-16 19-24 >24 TOTALS H 0 0 3 2 0 0 $ trit 0 0 3 1 0 0 4 tit 0 1 1 0 0 0 2 ( tit 0 0 3 0 0 0 3 t 0 0 1 2 0 0 3 10t 0 0 1 0 0 0 1 Lt 0 0 1 0 0 0 1 L0t 0 0 1 1 0 0 2 5 0 0 0 8 0 0 8 LLH 0 0 2 14 3 0 19 LH 0 0 0 b 1 0 6 6 C.H 0 0 1 0 0 0 1 H 0 0 1 1 0 0 2 6tM 0 0 1 12 0 0 11 tal 0 0 0 1 0 0 1 frM 0 0 0 1 0 0 1 v&RIABLE TOTAL 72 PLR10D3 0F CALH tHOUR51: 0 A 52 e
- - . . . .. ._ .c.--.~,_-~.-.-- . . ~ . - . ~ . - . . . . . .
l l I 1 HOUR 5 at t &CH HitID LPit0 MiD 01 ALCT191
-1 PtP!00 0F PtCOR0s 4/ 1/90 10 6/30/90 l Ofan!L1tY CLA0h 6 i (LEVATIOh 150 H!HD LPit0 IMPN)
Wit 0 DIPICTION 18 4-7 0 1t 11 16 19 t4 *t4 TOTALS N O O- 0 0 0 0 0 telt 0 0 1 0 0 0 1 lit 0 1 4 0 0 0 b ( HI O J 0 0 0 0 : l 0 0 0 0 0 0 0 tti 0 0 2 0 0 0 t Lt 0 0 0 0 0 0 0 Ltt 0 0 0 0 0 0 0 L 0 0 0 1 0 0 1 1 LOH 0 0 2 9 4 0 lb LH 0 0 1 0 0 0 1 FCH 0 0 1 0 0 0 1 H 'O O O O O O O MM 0 0 5 14 2 0 21 161 0 0 3 1 0 0 4 lam ' O O 1 0 0 0 1 v&RIA0Lt T0fil $t P!RIODS OF CALM 1 HOUR 5ft 0 I; k P 1 l : l l I l' 53 _ _ -, .,.-._ - -- c _ . - _ _ , . . _ . _ . . - _ _ _ _ _, _ __
. m. - _ _ _ _ _ . - _ _ . _ _ _ _ . . . _ . . .
HOUR 3 AT E ACH HIHD SPEED AHD DIRECTIDH PERIOD OF RECORD: 4/ 1/90 TO 6/30/90 LTASILITY CLA05: C ELEVATION: 150 HIND LPEED (MPH ) HIND DIPECTION 1-3 47 4-12 11 18 19 1e 124 TOTALS H 0 0 2 0 0 0 2 tatt 0 0 2 1 0 0- 3 tit 0 4 1 0 0 0 5 EffE 0 0 0 0 0 C 0 E 0 0 0 0 0 0 0 ESE O O O O O O O OE O O 1 0 0 -0 1 SOE. 0 0 0 0 0 0- 0 S 0 0 1 1 0 0 2 00H 0 0 5 12 3 0 20 SH 0 0 1 2 1 0 4 6CH 0 0 0 0 0 0 0 N 0 0 1 4 1 0 6
&# H 0 0 15 8 1 0 24 PA4 0 0 9 0 0 0 9 frH 0 0 0 1 0 0 1 VARIABLE TOTAL 77 PER1033 0F CALN-4 HOUR 31: 0 L
l I l-54 T -
~~
HOURS AT CACH HIND OPEED AND DIRECT 10tl PERIOD 0/ RECORO: 4/ 1/90 TD 6/30/90 STABILITY CLAOS: D (LEYAT10H 150 HIND SPEED IMPH) H!tfD ' DIRECT 1 Del 1-3 4-7 8 12 13-18 19 24 >24 TOTALS N 0 15 9 1 0 0- 25 left 0 14 6 4 1 0 25 tR 0 22 5 0 0 0 27 t rJE o 9 13 11 3 0 36 E O 3 3 4 0 0 10 ttE 1 1 1 2 0 0 5 SE 0- 4 2 0 0 0 6 00t 0 6 19 4 -0 0 29
$ 0 5 29 6 1 1 42 GLH 0 6 54 38 30 3 131 SH 0. 4 17 14 2 1 38 FCH 0 3 10 6 3 0 22 H 0 3 -8 16 0 7 34 l#H 0 18 40 I4 5 0 97 las 0 29 30 5 2 0 66 70M 0 22 18 2 0 0 42
-VARIABLE TOTAL 635
.PER1000 0F CALM IHOUR31: 0 l.
55-i
HOUR $ AT E ACH HIND SPEE0 AND DIRECTION PERIOD OF RECORD: 4/ 1/90 TO 6/30/90 STABILITY CLA03: E E LEVATIctJ '150 HItto SPEED (HPH) HINO DIRECTION 13 4-7 6 12 13 18 19-24 >24 TOTALS
..~...... ... ... .... ... . ..... ... ......
N 0 5 12 21 3 2 43 l#lE 2 8 21 13 4 0 40 NE 1 19 19 17 7 0 63 ENE 4 19 .36 31 12 0 102 E 1 6 11 13 1 0 32 ESE O 9 14 2 0 0 25 CE 1 13 5 0 0 0 19 SSE O 15 27 to 2 1 55 S 0 15 51 20 3 2 91 LOH 3 8 79 114 36 7 247 O&t 1 9 32 29 3 1 75 HSH 1 10 12 10 1 0 34 H 0 8 24 9 1 0 42-RH 0 8 31 12 3 0 54 tal 1 7 19 le 8 0 53 taH 1- 12 20 26 12 0 71 VARIABLE TOTAL 1054 PERIODS OF CALH IHOUP,3); 9 l.. l-l- 1
~
L 56
- ~. - - . .
HOURS AT [ACH hit 40 LPEED Afl0 OIRECTIDH PEP 100 0F PICORD: 4/ 1/90 TO 6/30/90 LfABILITY CLAS?is F ELEVATION: . 150 HIllD SP[t0 (MPHI Hitt0 DIRECTIDH 13 47 8-17, 13-18 19 24 >24 TOTALS H 0 2 3 1 0 0 6 18 4 0- 0 0 3 0 0 3 tE O 3 0 0 0 0 3 EllE O 5 1 0 0 0 6 E O O O O 0 0 0 ELE O 1 0 0 0 0 1 St 0 3 2 0 0 0 5 LLE O 3 5 1 0 0 9 0 0 2 10 9 0 0 21 LLh 0 3 12 11 0 0 26 LH 0 2 16 7 0 0 25 vCH 1 4 12 7 0 0 24 H 0 2 16 1 0 0 19 6t H - 1 3 13 0 0 0 17 HH 0 2 6 2 0 0 10 t#M 1 1 5 3 1 0 11 VARIABLE TOTAL 106 l PERIODS Of CALM ! HOUR 311 0 I I l t 57
l l
.s HOURS AT LACH N111D CPLEO Atto DIRECTION 1 PERIOD OF PtCORO: 4/ 1/90 70 6/30/90 STABILITY CLAOS: 0 ELEVAT!0tle 150 HIND $PC10 iMPHI HitlD VIRECTION 13 4-7 8 12 .11 16 19 24 >t4 TOTALS N 0 0 0 0 0 0- O lift 0 1 0 0 0 0 1 tit 0 0 '
0 0 0 0 tut - 0 1 t, 0 0 0 1 L' O 1 0 0 0 0 1 (St 0 0 0 0 0 0 0 56 0 2 0 0 0 0 t LSE O 5 0 2 0 0 5 L 0 t 2 1 0 0 5 SOH 0 5 10 1 0 0 16 P4 0 0 9 1 0 0 10-tG4 0 5 15 6 0 0 26 H 0 3 10 2 0 0 15 60H 0 4 4 0 0 0 8 fH 0 1 0 0 0 0 1 tcH - 0 1 0 0 -0 -0 1 VARIABLE TOTAL 92 PERICO3 0F CAlti IHOURS h 0
.i i
d 58 1 T
m.. _ . . _ . . _. _ 1 HOURS AT E ACit HIND SPEED AND DIRECTION PERIOD OF RECORD: 7/ 1/90 10 9/30/90 STADILITY CLASS: A E LEVAT10th 150 HIND SPEED IMPHI HIND DIRECTION 1-3 47 8-12 13 18 19 24 >t4 TOTALS N 1 0 1 4 0 0 6 101E O O 1 1 0 0 4 tlE 0 5 8 2 0 0 15 [NE O 4 12 6 0 0 22 [ 0 0 2 0 0 0 2 ESE O 0 1 0 0 0 1 SE' O 2 1 0 0 0 3 SSE O O 1 4 0 0 5 S 0 0 7 5 0 0 12 SSH O O 6 7 0 0 13 SH 0 0 0 4 0 0 4 NOH 0 0 0 0 0 0 0 M 0 0 0 0 0 0 0 tit 4 0 2 0 1 0 0 3 tM 1 0 1 2 0 0 4 14 0 1 0 3 0 0 4 VARIABLE TOTAL 98 F'IRIODS OF CALH (HOURS I: 0 i i 1 1 59
HOVRS AT EACH HIND SPEE0 AND DIRECTIDH PERIOD OF RECORDI 7/ 1/90 TO 9/30/90 STABILITY CLASS: B ELEVAT10H: 1!" HIND SPEE0 (MPHl. Hit 40 DIRECTIt"4 13' 4-7 8-12 13-18 19 24 >24 TOTALS N 0 2 0 0 0 0 2 l#lt -1 1 0 1 0 0 3 11C 0 1 3 0 1 0 5 EllE O O 2 2 0 0 4 E 0 0 1 0 0 0 1 ESE O 1 1 0 0 0 2 SE D 0 0 0 0 0 0 SSE 0 0 2 0 0 0 2 , S 0 1 2 3 0 0 6 SSH 0 1 3 4 0 0 8 SH 0 0 1 1 1 0 3 H3H 0 0 0 0 0 0 0 N O 0 0 0 0 0 0
&DM 0 0 0 3 0 0 3 iM 0 0 3 0 0 0 3 l#M 0 1 1 2 0 0 4 VARIABLE TOTAL 46 PERIODS OF CALM (HOURS h 0 l
l l l l l l l l L 60
HOURS AT E ACH HIND SPEED AND DIRECTION PERIOD OF RECORO: 7/ 1/90 TO 9/30/90 STABILITY CLASS: .C ELEVATION: 150 MINO $ PEED (MPHI HIND DIRECTIDH 1-3 4-7 8 12 13-18 19-24 >24 TOTALS H 0 1 1 0 0 0 2 t#1E 1 4 3 0 0 0 8 Ilt 1 4 1 0 0 0 6 ENE O 2 6 1 0 0 9 E O 1 0 0 0 0 1 ESE O 1 0 0 0 0 1 SE O O O 0 0 0 0 SSE O O 2 1 0 0 3 S O' 1 1- 3 0 0 5 SSH 0 0 3 3 0 0 6 SH 0 0 5 1 0 0 6 HSH 0 0 1 0 0 0 1 H 0 0 1 1 0 -0 2 ftM 0 1 4 0 0 0 5 tai 0 3 3 1 0 0 7 t#81 1 2 1 1 0 0 5 VARIADLE
-TOTAL 67 PER1005 0F CALH IHOURSI: 0 t
61
. _ . . - - ~ ~ _ - , . , ..
HOURS AT EACH HIND SPEED ARD O!RECTION PERIOD OF RECORD - 7/ 1/90 TO 9/30/90 STABILITY Cf.AS$t 0 E LEVATIDN 150 HIND SPEED INPH) HIND DIRECT 10H .1-3 4-7 8-12 13-18 19-24 >24 TOTALS H 8 34 S 1 0 0 48 tDE 1 26 4 4 0 0 35 flE 2 14 9- 2 1 0 28 EffE 2 13 .25 7 1 0 43 E 1 4 2 1 2 0 10 ESE O 1 3 0 0 -0 4 SE 1 4 1 0 0 0 6
$5E O 7 19 3 0 0 29 S 0 4 16 10 0 0 30 SSH 0 5 22 23 0 0 50 SH 0 5 18 31 0 0 34 HSH 1 5 10 1 0 0 17 H I 4 17 12 0 0 34 Re4 . 2 10 38 25 0 0 75 tai 1- 43' 6 3 0 0 53 teoi 1- 42 1 4 0 0 40 VARIABLE
- TOTAL 549 PERIODS OF CALH IHOUR$lt 0 62
o HOURS AT EACH HIND $ PLED AND DIRECTION PERIOD OF RECORDt 7/ 1/90 TD 9/30/90 STABILITY CLASS: E ELEVATION: 150 HIND SPEED titPH) HIllD DIRECTIDH 1-3 4-7 6-12 13-16 19-24 >t4 TOTALS H 1 12 21 7 3 0 44 ftE 2 12 to 16 9 0 59 ilt 3 16 27 17 16 0 79 ENE 1 I2 36 51 le 0 Ito E 2 14 13 9 3 0 41 ESE 2 17 2 0 0 -0 21 SE 3 29 1 0 0 0 33 SSE 0- 13 33 12 0 0 58 S- O' 9 46- 20 0 0 75 SSH 0 5 .65 49 -0 0 119 SH 0 7 33 31 1 -0 72 FCH 0 7 4 3 0 0 19 H . O. 4 31 3 0 0 40
>0M 3 6 29 10 0 0 48 iM 4 10 17 17 2 0 50 tcH - 1 '9 17 24 3 0 54 VARIABLE TOTAL 940 PER100S of CALM IHOURS it 0 63
HOURS AT E ACH HIND SPIE0 AND DIRECTION PER100 0F RECOR0: 7/ 1/90 TO 9/30/90 STABILITY CLAS$r i ELEVATION: 150 HIND SPE E 0 I Hf H ) HIND DIRECTIDH 1-3 4-7 8-12 13-18 19 24 >24 TOTALS H 2 5 7 0 0 0 14 l#1E O 3 4 0 0 0 7 NE O 2 0 0 0 0 2
~ E NE O '1 0 0 0 0 1 E 1 7 1 0 0 0 9 ISE 0 1 0 0 0 0 1 SE . 1 2 0 0 0 0 3 SSE 1 2 S 0 0 0 8 S- 0 0 10 t 0 0 12 SSH 0 2 29 16 0 0 47 SH 0 1 16 49 0 0 46 HSH I 1 16 9 0 0 E7 H 1 4 10 0 1 0 16 &#N 1 2 13 1- 0 0 17 IDI '1 0 9 0 0 0 18 1854 1 6 '3 2 0 0' 12 VARIABLE TOTAL 240 PERIODS OF Calli (HOURSit 0 0
64
HOURS AT EACH HIND SPEED AND DIRECTIDH PERIOD OF RECORD: 7/ 1/9C TO 9/10/90 STABILITY CLASS: G ELEVATION: 150 HIND SPEED (HPH)
HIN0 DIRECTION 11 4-7 6-12 13 18 19-24 >24 TOTALS-H 2 1 0 0 0 0 3 t#ft 2 0 1 0 0 0 3 f1E 1 5 0 0 0 0 6 EHE 1 2 0 0 0 0 3 E 1 1 0- 0 0 0 2 ESE O 2 3 0 0 0 5 SE 2 4 3 0 0 0 9 SSE O 2 8 1 0 0 11 S 0 6 14 4 0 0 24 SSH 0 3 15 6 0 0 24 SH 0 7 24 11 0 0 42 HSH 0 0 17 7 0 0 52 H 1 6 13 1 0 0 21 ,
F#M - 0 10 3 0 0 0 13 FM 1 0 0 0 0 0 9 tRN 1 7 0 0 0 0 8 VARIABLE TOTAL 215 PERIDOS OF CALH (POUT 24 TOTALS H 0 0 2 1 0 0 3 IP!E O 1 3 0 0 0 4 NE O C 4 0 1 0 5 E tlE O C 4 1 0 0 5 E O O 2 1 0 0 3 E0E O 0 0 1 0 0 1 CE O O O O O O O COE O O 3 0 0 0 3
$ 0 0 2 0 0 0 2 SOH 0 0 1 0 0 0 1 GH 0 0 4 5 0 0 9 HSH 0 0 3 0 0 0 3-H 0 0 1- 3 0. 0 4 F# 54 0 0 9 0 0 0 9 t88 0 2 8 14 0 0 24 l# 54 0 -I 7 15 1 0 24 VARIABLE TOTAL 100 PERIOD 3 0F CALM IHOURS): O l
l' 66 l-l l
HOURS AT CACH HIND SPEED AND CIRECT104 PERIOD OF PtCORot 10/ 1/90 TO 12/11/90 LTAD'1LITY CLASS B ELEVATION: 150 i HIND OPEt0 (NPHI , H!fl0 j 01PECT104 1-3 47 6 12 13-16 19 24 >24 TOTALS ; H 0 0 3 2 0 0 $ ital 0 0 0 0 0 0 0 lit 0 0 1 0 0 0 1 Etit 0 0 0 0 0 0 0 t O O O O O 0 0 ELE O O 0 1 0 0 1 St 0 0 0 0 0 0 0 00t 0 0 0 0 0 0 0 L 0 0 1 0 0 0 1 00H 0 1 2 1 0 0 4 su 0 1 2 1 2 0 6 6CH 0 0 3 0 0 0 3 > H 0 0 1 0 0 0 1 6P H 0 0 1 1 4 2 8 tal 0~ 1 5 2 0 0 8 t7 84 - 0 1 0 t 't 0 $ VARIABLE TOTAL 43 PERIODS OF CALH IHOUR31 0 67
.-. .~ .n _ . - -. , _.
HOURS AT t&CH H1HD $Ptt0 APID OIRECTIDH PERIOD OF DICORD: 10/ 1/90 TO 12/31/90 OTABILITY CLA001 C EltvATION: 150 HIHO LPttD tMPHI HTH0 DIRECTION 1-3 4-7 6 12 13-16 19 24 >t4 TOTALS H 0 0 0 1 0 0 1 f."it 0 0 0 0 0 0 0 NE O O O O 0 0 0 (Hi 0 0 0 0 0 0 0 E O O 1 0 0 0 1 ESE O O O O O O O GE O O O O O O O CSE O O O O O 0 0 0 0 0 1 0 0 0 1 LOH 0 0 7 1 0- 0 8 r,H . 0 0 3 4 2 0 9
.lCH 0 0 0 2 0 0 2 H 0 0 2 1 1 0 4 leM 0 0 2 0 1 5 8
.f84 0 2 0 4 0 -0 6 IPM 0 1 3 1 3 0 0 VARIABLE TOTAL 48 FERIOD3 0F CALH IHOURSit. 0 6' 8 L
HOURS AT E ACH HIND SPEED ANO DIRECTION PERIOD OF RECORD: 10/ 1/90 70 12/31/90 LTABILITY CLASSi D ELEVATI0ti 150 HIND LPEED IHPH) HIPID DIRECTION 1-3 4-7 6-12 13+18 19 24 >24 TOTALS ti 1 4 3 5 12 23 48 tile - 0 6 0 1 '6 13 26 ilE O 6 4 8- 4 0 22 ENE 1 0 1 2 0 0 4 E O 0 4 4 0 0 8 E0E 1 2 1 8 0 0 12 tt 0 7 2 0 0 0 9 SOE o 1 1 6 0 0 8 5 0 1 9 1 2 2 15 00H 0 6 10 30 6 1 53 CH 0 3 9 16 2 -0 30 H;H 0 0 5 12 2 0 19 H 1 4 8 11 9 1 34 teH 1 5 13 6 15 14 54 tal 2 8 5 7 14 6 42 t##4 1 6 5 16 16 2 46 VARIABLE TOTAL 430 PERIODS OF CALH (HOUR 31 0 69
l l i HOURO AT EACH HIND LPEED ArtD DIRECTION PERIOD OF PECORD: 10/1/90 TO 12/31/90 LTALILITY CLALSt E i ELEVAT!0th 150 HIHO LPEED IMPHI , HIND DIRECTICH 13 47 8 12 13 18 19*24 >t4 10TALS N 0 2 5 47 to 3 75 tPlt 0 0 12 11 2 3 to ilE O O 4 4 1 0 9 EtlE D 0 6 0 1 0 7 E O 11 12 4 0 0 27 ESE 0 2 8 3 5 0 18 CE O 10 16 11 6 0 43 LOE O 7 26 14 2 1 50 S 0 4 14 15 3 4 38 LOH 0 6 49 72 15 7 150 LH 0 7 25 69 7 1 109 W>l 0 6 50 28 5 0 69 H 0 6 7 28 4 1 46 H?lH 0 2 10 21 30 21 84 IN 1 4 17 34 42 19 -117 MlH 0 3 12 39 50 5 109 VARIADLE TOTAL et9 PER1000 0F CALM iHOURS h 1-a k e i 70
HOUPS AT EACH HIND LPtto AND DIRECTION PER100 0F PCCCPO: 10/ 1/90 TO 12/31/90
$1 ADILITY CLAOSt F (LEVATICril 150 HillD OPCEO lHPH)
HIllD OIRCCTION 1-3 4-7 6 12 13 18 19-44 >24 TOTALS H 0 0 0 0 0 0 0 tale 0 1 1 0 0 0 2 NE O O O O O 0 0 Itti 0 3 2 0 0 0 5 E O 2 2 0 0 0 4 E0t 0 1 5 0 0 0 6 CE O 6 5 0 0 0 11 LGE O 1 1 1 0 0 3 S 0 0 8 7 0 0 15 GLH 0 0 11 6 2 0 29 OH 0 4 13 17 0 0 34 6CH 1 3 21 20. 0 0 45 H 0 0 8 1 0 0 9 M at 0 1 4 0 0 0 5 te! 0 1 2 0 0 0 3 N'M 2 1 0 0 0 0 3 VARIABLE TOTAL 174 PERIOOS OF CALM IHOURSI: 0 I I f i' 71
. -- . _ _ _ . . _ - . - . ,. . .. _ . ~. . _ . -
HOURS AT EACH HIND SPEED APID DIRECTION PERIOD OF RECORDr 10/ 1/90 TO 12/31/90 STABILITY CLASS: G ELEVATIDH: 150 V1 TID SPEED (HPHE HitlO DIRECTION 1-3 4-7 8 12 13-18 19 24 >24 TOTALS H 0 1 1 0 0 0 2 f.ilE 1 2 0 0 0 0 3 . HE 1 1 0 0 0 0 2 EtIE 1. 0 0 0 0 0 1 E O 1 0 0 0 0 1 E0E O 3 3 0 0 0 6 iE O 2 1 0 0 0 3 00E 1 3 4 0 0 0 8-
$ 1 7 11 9 0 0 28 CSH 0 10 11 14 0 0 35 LH- 2 7 22 19 0 0 50 6CH 1 7- 17 23 0 0 48 H I 2 8 -1 0 0 12 .lesf 0 2 0 0 0 0 2 IM 0 3 1 0 0 0 4 l#M 1 0 0 0 0 0 1 VARIABLE TOTAL 206 PER1003 0F CALH (HOURSI: 0
- 7. 2
._____._____l
SEM1ANNUE RADIO /CTIVE EITIUDR RE2.PASE REPOTC' G - ODCM RLVISIONS, RD@ tONMXfflJANCES NO
%70R CENGES 'IO RADIO 7CTIVE WASTE TREA'IFDR SYS'ITMS According to Technical Specification 6.14.c and OD04 Control 6.9.1.7, the Semiannual Radicactive Effluent Release Report shall include any changes to the Offsite Dose Calculation Manual (CDCM) mda during the reporting period.
A. Changes to the 0D04: There was a single revision to the Cini, Rev.16, that was mde during this reporting period. In this revision, the ODCM was brought into canpliance with the recmtendations of NRC Generic Letter 89-01, which recarmnded that procedural details of the Radiolcxjical Effluent Technical Specifications not associated with solid radioactive wastes be relocated to the ODCN. Portions of the Definitions and Administrative Controls Sections of the Technical Specifications (TS) have been relocated to the ODCM, and sam words of these sections of TS have been changed. All the changes are m to provide conformance with the reccmmndations of Generic Ictter 89-01.g Revision 16 to the TCM was approved by the Review of Operations Conmittee on July 26, 1990 and became effective on July 30, 1990. A copy of this revision is attached to this Semiannual Effluent Releace Report. Action Statement c of OD04 Control 3.12.1 and a and b of OD04 Control 3.12.2 require certain itans of RD@ nonccmpliance to be reported in the Semiannual Radioactive Effluent Release Report. B. There were no such RD4P noncorpliances during this reporting period. Technical Specification 6.15 and PCP 9.3.1 and 9.4.4 state that the Semiannual Radioactive Effluent Release Rep 3rt shall include major changes to radioactive waste treatment systats. C. There were no major changes to radioactive waste treatment systems during this reporting period. (1) NRC Generic Letter 89-01, "Implemntation of Progrannatic Controls for Radiological Effluent Technical Specifications in the Administrative Contrels Section of the Technical Specifications and the Relocation of Procedural Details of the RIES to the Offsite Dose Calculation Manual or to the Process Control Program," January 31, 1989. 73 i
-. ~. . . - .. .-- - - . - . - - - - . .
SDiINEAL RADICMPIVE EPPLUDTP R11 EASE REPORT
!! - MISCELIANEDUS SPICIAL REPORTS 3rd and 4th Quarters of 1990 The CDCM regttires ground water samples to be obtainM quarterly from one or tw sources hbl, Wb2. The required samples fran Wbl were obtained, hauver the sampler at hb2 were unavailable. 'Ib fulfill the requiranents of OD04 location Wb2, tha ODCM provides one waterborne sanplo location (13S2) . On Septanber 19, ,
1990 and December 6, 1990, the well at 13S2 was found dry and location 2A3 was subst.ltuted. This location, at a residence 0.3 miles NNE of the site, is not listed in cro! Table-5-4, Radiological Environmntal Monitoring Program Waterborne Monitoring Stations, but the sample provided ncets ODCM Controls Table 3.12.1-1 requirements for Wb2. l-i- l 74 l~ l
Submitted with SNRC-1788 OFFSITE DOSE CALCULATION MANUAL, REV. 16 SilOREllAM NUCLEAR POWER STATION i
M-wa** 5$$* Document No. h/7oco L Eff. Date 7D r/Sc RSv. No. is Reviewed By Date
'~'Eepared By Date k 7 IS f %
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APPROVALS
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h 0FFSITE DOSE CALCULATION PANUAL Revision 16 - July 1990 Insertion Instructions All pages, except Figures and Tables, have been renumbered. A new document is now being distributed. Please remove old pages and replace with new revision. O t 9 l
. . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ . . . . _ l
o 0FFSITE DJSE CALCULATION MANUAL
; List of Effective Pages (n)
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EP-1 Revision 16 - July 1990
OFFSITE DOSE CALCULATION MANUAL List of Effective Pages (Cont'd.) O Page, Table (T), Revision or Figure (F) _ Number 11.3.5-7 13 11.3.5-8 10 11.3.5-9 thru 11.3.5-10 13 11.3.5-11 thru 11.3.5-12 14 11.3.5-13 13 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 3.5-12, 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 g T.3.5-15, p. 1/1 15 y T.3.5-16, p. 1/1 3 T.3.5-17, p. 1/1- 14 11.3.6-1 16 F.3.6-1 1
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O LONG ISLAND LIGHTING COMPANY OFFSITE DOSE CALCULATION MANUAL 9 Revision 16 - July 1990
SNPS-1 ODCM h PLEASE NOTE Revision 1 - August 1983 of the LILCO, SNPS-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/or modifi-cations.)inengineering, design, methodology,etc. CHANGE BARS are not used for Errata (i.e., typos, format changes). CHANGE BARS are not useo in Part I Revision 16 since this material is entirely new to the ODCM. They are also not 9ted to indicate changed page numbers in Part 11 Revision 16 since all page numbers have had a II, appended to them. In addition, Part II changes are not labelled Revision 16 at the page bottom if the only change is a page number i appendage. DO NOT REMOVE - KEEP IN YOUR ODCM I h
$NPS-1 ODCM- i r PART 1 THERADIOLOGICALEFFLUENTCONTROLS(REC)
(]/ TABLE OF CONTENTS
, ODCM REC SECTION SECTION SUBJECT PAGF 1 - INTRODUCTION 1.1.0 2 1.0 DEFINITIONS !.2-0 3 3.0 and 4.0 CONTROLS AND SUREVEILLANCE 1.3-0 REQUIREMENTS 4 3.0 and 4.0 B,ASES BASES FOR SECTIONS 3.0 and 4.0 1,4-0 5 5.0 DESIGN FEATURES 1.5 0 6 6.0 ADMINISTRATIVE CONTROLS 1.6-0 b
t O
-BN1-11600.02-92 11 Revision 16 - July 1990
SNPS-1 ODCM PART 11 CALCULATIONAL METHODOLOGY AND PARAMETERS FOR COMPLIANCE WITH THE RADIOLOGICAL EFFLUENT CONTROLS TABLE OF CONTENTS Radiological Effluent Controls Section Subject Section Page 1 INTRODUCTION !!.1 1 2 SET POINTS !!.2.1-1 2.1 LIQUID 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 ." actor Building Salt Water Drain Tank 11.2.1-6 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RL-2':A.RE-238) High Alarm Set Points 11.2.1-7 2.2 GASEOUS EFFLUENT MONITOR SET POINTS 3.11.2.1 !!.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 for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Oose Rate 11.2.2-3 2.2.2 Main Condenser Offgas System Effluent Monitors (RE-6SA 8) High Alarm Set Point l'. 2.2 4 2.2.3 MainCondenserAirEjectorMonitors(RE-121,B) High Alarm Set Point for Non bypass Mode Operation 11.2.2-S 2.2.3.1 Initial Set Point for RE-12A.B Non-b/ pass Mode Operation 11.2.2-6 2.2.3.2 Subsequent AdjuGments of Set Points for RE-12A,8 in Non-bypass Mode Operation 11.2.2-7 O BN1-11600.02-92 iii Revision 16 - July 1990
SNPS-1 ODCM i TABLEOFCONTENTS(CONT'D) (mNJ 2.2,4 Main Condenser Air Ejector Menitors (RE-12A,B) High Alarm Set Point for Bypass Mode Operation 11.2.2-7 2.4.4.1 Initial Set Point for RE-12A,B in Bypass 1 Mode Operation 11.2.2-7 l 2.2.4.2 Subsequent Adjustments of Set Points for l RL-12A,B in Bypass Mode Operation !!.2.2-8 3 DOSE CALCULATION METHODS !!.3.0-1 3.1 LIQUID EFrLUENT, DOSE CALCULATION 3.11.1.2 11.3.1-1 3.1.1 Method 1: _ (ComputerizedMethod) 11.3.1-1 3.1.2 Method 2: (BackupMethod) !!.3.1-5 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS 3.11.1.3 11.3.2-1 1 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS !!.3.3-1 3.3.1 Method 1: (ComputerizedMethod) !!.3.3-1 3.3.1.1 Release Rate Estimation 3.11.2.1 !!.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 !!.3.3-3 3.3.1.4 Organ Dose Rate (1-131, 1-133 Tritium and Particulate Releases) 3.11.2.1 !!.3.3-4 3.3.2 Method 2: (BackupMethod) 11.3.3-5 il b' 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.1 3.11.2.1 11.3.3-b 11.3.3-6 3.3.2.2 Noble Ges Skin Dose Rate 3.3.2.3 OrganDoseRate(ParticulateReleases) 3.11.2.1 11.3.3-7 3.4 GASEOUS EFFLUENTS NOBLE GAS AIR DOSE 3.11.2.2 !!.3.4 1 3.4.1 Method 1: (ComputerizedMethod) 11.3.4 1 3.4.1.1 Release Lstimation 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 Noble' Gas Beta Air Dose 3.11.2.2 11.3.4-2 3.4.2 Method 2: (BackupMethod) 11.3.4-3 3.4.2.1 Noble Gas Ganna Air Dose 3.11.2.2 II.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 RADIO-10 DINES AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES WITH HALF-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 !!.3.5-2 k' BN1-11600.02-92 iv Revision 16-July 1990l
SNPS-1 ODCM TABLE OF CONTENTS (CONT'D) g,.s 3.5.1.3 Skin Dose 3.11.2.3 !!.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 !!.3.5-5 3.5.1.6 Infant Thyroie Dose Due to Inhalation and Ingestion of Goat Mill 3.11.2.3 11.3.5-7 3.5.2 Method 2: (Backupt'ethod) 11.3.5-11 3.5.2.1 Organ Doses 3.11.2.3 11.3.5-11 3.6 OPERATION OF VENTILATION EXHAUST TREATMENT SYSTEM 3.11.2.5 !!.3.6-1 3.7 TOTAL DOSE FOR THE URAN 1UM FUEL CYCLE 3.11.4 11.3.7-1 3.7.1 Sources of Ra'diation and Radioactivity !!.3.7-1 3.7.2 Radiological Impact of Generation of Electricity !!.3.7-1 4 METEOROLOGICAL AND HYOR0 LOGICAL PARAMETERS UTillZED lh THE CALCULATION OF DOSES 11.4 1
4.1 INTRODUCTION
4.2 PARAMETERS AND METHODOLOGY LSED IN THE t COMPUTERIZED METHOD 4.2.1 Meteorological Data 4.2.2 Long Term /Q and D/Q Values 4.3 PARAMETERS AND METHODOLOGY USED IN THE BACKUP RETHOD 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SANPLING LOCATIONS !!.5-1 6 INTEPLABORATORY COMPARISON PROGRAM 11.6-1 Appendix A DERIVATION OF A A-1 Appendix B DERIVATION OF p oj) B-1 BN1-11600.02-92 v Revision 16 - July 1990
SNPS-1 ODCM () V LIST OF TABLES Table T1tle 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(FishandInvertebrate) 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 ExposedIndividualinLNuofSite-SpecificData p g 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, In estion of Leafy and Stored 9dhe,tablesDoseRateConversonFactorsforchild 3.5-10 P Child Ingestion of Cow's Milk Dose Rate 8ddv,ersionfactors 3.5-11 P Child Ingestion of Goat's Milk Dose Rate 8ddv,ersionFactors 3.5-12 P , Child Ingestion of Meat Dose Rate Conversion Eddtors 3.5-13 P , Infant Irgestion of Cow's Milk Dose Conversion fddtors j, BN1-11600.02-92 vi Revision 16 - July 1990
SNPS-1 ODCM LIST OF 1 ABLES (CONT'D) Table Title 3.5-14 P , Infant Ingestion of Goat's Milk Dose Conversion Eddtors 3.5-15 P Child Inhalation and Ingestion of Leafy and Stored Vdhe,tablesDoseRateConversionFactors 3.5-16 P , Child Ingestion of Coat's Milk Dose Rate CJnversion Fddters 3.5-17 P , Infant Irjestion of Goat's Milk Dose Rate Conversion F$dtors 4-1 Critical Receptor Locations for Gaseous Effluent Calculstions 4-2 General Site - Specific Data 5-1 Radiological Environmental Monitoring Program - Sampling and Collection Frequency 5-2 Radiological Environmental Monitoring Program - Waterborne Monitoring Stations 5-3 Radiological Environmental Monitoring Program - Particulates and Radiciodine 5-4 Radiological Environmental Monitoring Program - Direct Radiation Monitoring Stations 5-5 Radiological Environmental Monitoring Program - Ingestion Monitoring Stations BN1-11600-92 vii Revision 16 - July 1990
$NPS-1 ODCM LIST OF FIGURES Fioure Title 2.1-1 Detector RE-13. Retponse vs. Gamma Energy 2.1 2 Detectors RE-23A RE 23B and RE-79, Response vs. Gama Energy 2.2 1 Detector RE-42, Efficiency vs. Average Beta Energy 2.2-2 Linearity Response Curve for Detector RE-42 2.2 3 Detectors RE-65A B. Generic Efficiency vs. Average Beta Energy 2.2 4 Generic L,inearity Response Curve for Detectors RE-65A,B 2.2-5 Detectors RE 12A,B, Efficiency vs. Gamma Energy 2.2 6 Generic Linearity Response Curve for Detector RE 12A B 3.1-1 Site Boundary for Liquid Effluents 3.1-2 Liquid Radwaste System Model 3.3-1 Gaseous Effluent Model 3.6-1 Ventilation Exhaust Treatment System 5-1 Onsite Sampling Locations - Radiological Environmentt Monitoring Program 5-2 Offsite Sampling Locations - Radiological Environmental Monitoring Program BN1-11600.02-92 viii Revision 16 - July 1990 t
SNPS 1 ODCM PART I SECTION 1 INTRODUCTION Procedural details of the Radiological Effluent Technical Specifications not associated with solid radioactive wastes which were previously located in the Station Technical Specifications (TS) have been relocated to the ODCM. Portions of the Definitions and Administrative Controls Seet. ion of the TS are , also being relocated to the ODCM, and some changes to the wrds of these sections of TS are being made. All the changes are made t conformancewiththerequirementsofGenericLetter89-01yggrovide O (1) HRC Generic Letter 89-01, " Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical S)ecification and the Relocation of Procedural Details of the RETS to tie Offsite Dose Calculation Manual or to the Process Control Program", January 31, 1989. ( 1.1-0 Revision 16 - July 1990 g
$NPS-1 ODCM PART I SECTION 2 i RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0
- DEFINITIONS I
b b O D 1.2 o R-4 4 1e . u ,1,,0
.-mr-,m.-r -, ,-, --c,y,.. w. , , . , - . . ---....e-m.,--.__ ,,.w,
INDEX _ DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 ACT10N........................................................ I.1-3 1.4 CHANNEL CALIBRATION........................................... I.1-3 1.5 CHANNEL CHECK................................................. I.1-3 1.6 CHANNEL FUNCTIONAL TEST....................................... I.1-3 1.9 DOSE EQUIVALENT I-131......................................... I.1-3 1.15 FREQUENCY NOTAT10N............................................ I.1-4 1.16 GASEOUS RADWASTE TREATMENT SYSTEM............................. 1.1-4 1.23 MEMBER (S) 0F THE PUBLIC....................................... I.1-4 1.250FFSITEDOSECALCULATIONMANUAL(0DCM)........................ I.1-4 1.26 OPERABLE - OPERABILITY........................................ 1.1-4 1.27 OPERATIONAL CONDITION - CONDIT 10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-4 ll h 1,32 PURGE - PURGING............................................... I.1-5 1.33 RATED THERMAL P0WER........................................... I.1-5 1.35 REPORTABLE EVENT.............................................. I.1-5 1,39 SITE B0VNDARY................................................. I.1-5 1.41 SOURCE CHECK.................................................. I.1-5 1.43 THERMAL P0WER................................................. I.1-5 1.46 UNRESTRICTED AREA............................................. I.1-5 1.47 VENTILATION EXHAUST TREATMENT SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . I.1-5 1.48 VENTING....................................................... I.1-6 l l l
' I l Revision 16 - July 1990 SHOREHAM - UNIT 1 1.2 1
- - _ . . . ~ . _ _ . . _ . _ . _ _ _ . _ _ _ _ _
d INDEX i j , LIST OF TABLES bv PAGE l TABLE < 1.1 SURVE!LLANCE FREQUENCY h0TATION................. I.1 7 1.2 OPERATIONAL CONDITIONS.......................... 1.1-8 4 o O SHOREHAM - UNIT ~1 1.2 2 Revision 16 - July 1990
l.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 required under designated conditions. CHANNEL CAllBRATION 1.4 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 CAllBRATION 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 1.5 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 parameWr. CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
- a. :.nalog 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 perfonned by any series of sequential, overlapping or total channel steps such that the entire channel is tested. DOSE EQUIVALENT l-131 1.9 DOSE EQUIVALENT l-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table 111 of TID-14044, " Calculation of Distance Factors for Power and Test Reactor Sites." SHOREHAM - UNIT 1 1.2-3 Revision 16 - July 1990
DEFINITIONS , FREQUENCY NOTATI.,0N, 1.15 The FREQUENCY NOTATION specified for the perfomance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. GASEOUS RADWASTE TREATMENT SYSTEM 1.16 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgeses from the primary system and providing for delay or holdup for the purpose of reducing the total radioactiv prior to release to the environment. MEMBER (S) 0F THE PUBLIC 1.23 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include 4 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, cccupational or other purposes not associated ~ with the plant. 0FFSITEDOSECALCULATIONMANUAL-QDCd
^ . 1.25TheOFFSITEDOSECALCULATIONMANUAL(00CM)shallcontainthemethodology and parameters used in toe calculation of offsite doses resulting from radioactive gaseous and liquid effluents,-in the calculation of gaseous ,
and liquid effluent monitoring Alarm / Trip Set)oints, and in the conduct ' of the Environmental Radiological Monitoring )rogram. The ODCM shall also contain (1) the Radiowtive Effluent Controls and Radiological
-Environmental Monitoring Programs required by Section 5.8.4 and (2) descriptions-of the-information that should be included in the Annual Radiological Environmental Operating and Semiannual-Radioactive Effluent
. Release Reports required by Specifications 6.9.1.0 and 6.9.1.7.
LOPERABLE - OPERABILITY 1~.26'A system, subsystem, train, component or device shall be OPERABLE or have ' 0PERABILITY when it is capable of performing its-specified function (s) and when all necessary attendant instrumentetion, controls, electrical
. Power,' cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device toperformitsfunction(s)arealsocapableofperformingtheirrelated
. support. function (s).
OPERATIONAL CONDITION - CONDITION
;1.27 An OPERATIONAL CONDITION, i.e., CONDITION, shall'be any one inclusive combination of mode switch position and average reactor coolant. i temperature as specified in Table 1.2. l
- SHOREHAM -~ UNIT 1 1.2-4 Revision 16 - July 1990
--________-------------__--_--_---___.__a
._ .-= _ _ _ _ _ _
DEFINITIONS PURGE - PURGING 1.32 PURGE or PURGING shall be the controlled process of discharging air oc gas from a confinement to maintain terrperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacernent air or gas is required to purify the confinement. RATED THERKAL POWER 1.33 RATED THERMAL POWER shall be a total re6ctor core heat transfer rate to the reactor coolant of 2435 MWt. REPORTABLE EVi.NT 1.35 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. 11,TE BOUNDARY 1.39 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. SOURCE CHECK 1,41 A SOURCE CHECK shall be the qualitative assessment of charnel response when the channel sensor is exposed to a radioactive source. THERMAL POWER 1.43 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. UNRESTRICTED AREA _ 1.46 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not cuntrolled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the $1TE BOUNDARY used for residential quarters or for industrial, comercial, institutional, and/or recreational purposes. VENTILATION EXHAUST TREATMENT SYSTEM 1.47 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to SHOREHAM - UNIT 1 1.2-5 Revision 16 - July 1990
I DEFINITIONS O the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atnospheric cleanup systems (e.g. RBSYS) are not considered to be d VENTILATION EXHAUST 7REATHENT SYSTEM components. VENTING 1.48 YENTING is the controlled process of discharging air or gas from a confinenent to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTlHG process. G Y %d
/G V
SHOREHAM - UNIT 1 1.2-6 Revision 16 - July 1990 l
DEFINITIONS TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION h0 TAT 10N 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. R At least once per 18 months (550 days). S/V Prior to each reactor startup. N/A Not applicable. P Completed prior to each release. SHOREHAM - UNIT 1 1.2-7 Revision 16 - July 1990 I
1 DEFIN!TIONS I 3 TABLE 1.2 0FERAT!0NAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITION POSIT!pN COOLANT TEMPERATURE
- 1. POWER OPERATION Run. Any temperature
- 2. - STARTUP Startup/ Hot $tandby Any temperature
- 3. HOT SHUTDOWN- Shutdowne*** >200'F l
- 4. COLD SHUTDOWN Shutdown # H*** 1200'F-
- 5. - REFUELING Shutdown or Refuel ** i 1140'F fThe reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified nwmber of the unit technical staff.
HThe reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor. pressure vessel per Specification 3.9.10.1 of the Technical Specifications.
- Fuel in the-reactor vessel with the vessel head closure bolts less.than fully tensioned or with-the head removed ,
**See Special Test Exceptions 3.10.1 and 3.10.3 of the Technical Specifications. [
***The reactor mode switch may be placed in'the Refuel position while a
- single-control rod is being recoupled provided that the one rod out.
interlock is OPERABLE. O : SHOREHAM - UNIT 1 1.2-8 Revision 16 - July 1990 F 4
*e-.4p y e. e ** r'm=-Tw-~e+m--**--' -' -a *e------'-1 ~'-r--t' +'*--v*nr--*rit-'sm--re-**-**-+'w-* w nw+=+w**+er-**+--*- w e u -' +-- -*-e+ ~ 4 ~ -e+ -iw'
$NPS-1 ODCM PART I SECTION 3 RADIOLOGICAL EFFLUENT CONTROLS SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS O
1,3-0 Revision 16 - July 1990 l
INDEX CONTROLS AND SURVEILLANCE REQUIREMENTS O SECTION- PAGE 3/4.0 APPLICABILITY......................................... 1,3-3 3/4.3 INSTRUMENTATION....................................... Radioactive Liquid Effluent Monitoring Instrumentation.................................. I.3-5 Radioactive Gaseous Effluent Monitoring Instrumentation.................................. 1.3-10 3/4.11 RADIOACTIVE EFFLUENTS I
-3/4.11.1 L10VID EFFLUENTS Concentration.................................... -I.3-15 Dose............................................. I.3-19 Liquid Radwe ste Treatment System. . . . . . . . . . . . . . . . . 1.3 20 -
3/4.11.2 GASEOUS EFFLUENTS
~ Dose Rate........................................ 1.3-22
-Dose-- Noble Gases............................... I.3-26
-Dose - lodine-131, lodine-133. Tritium, and Radionuclides in Particulate Form.............. 1,3-27 Gaseous Radwaste Treatment System................ I.3-28 Ventilation Exhaust Treatment System............. I.3-29 Containment Purging and Venting. . . . . . . . . . . . . . . . . . 1.3-31 p 3/ 4 .11. 4 . T OT AL D0 S E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.3-34~
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.................................... 1.3-35 3/4.12.2 LAND USE CENSUS....................................... 1.3-46 3/4.12.3 INTF.RLABORATORY COMPARISON PR0 GRAM.................... 1,3-47
- 1,3-l' Revision 16 - July 1990-
INDEX LIST OF TAELES h TABLE PAGE 3.3.7.10-1 RADI0 ACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION................................... I.3-6 4.3.7.10-1 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... I.3-8 3.3 7.11-1 RADIGACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION................................... I.3-11 4.3.7.11-1 RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... I.3-13 4.11.1.1.1-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PR0 GRAM........................................... 1.3-16 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE MONITORING, SAMPLING, AND ANALYSIS PR0 GRAM........................... 3 I.3-23 3.12.1 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..... 1.3-37 3.12.1-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.......................... I.3-42 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS.......................................... 1.3-43
, 9 I.3-2 Revision 16 - July 1990
3/4.0 APPLICABILITY CONTROLS f 3.0.1 Compliance with the Centrols contained in the succeeding controls is required during the OPERATIONAL CONDITIONS or other conditions specified thereint except that upon failure to meet the Controls for Operation, the associated ACTION requitwments shall be inct. 3.0.2 Noncompliance with e Control shall exist when the requirements of the Control associated ACTICW recuirements are not met within the specified time intervals. If the Control it restored prior to expiration of t1e specified time intervals, completion o'! the ACTION recuirements is not required. 3.0.3 When a Control is not m, except as provided in the associated ACTION requirements, within one hovr Mtion shall be initiated to place the unit in an OPERATIONAL CCNDITION in thich the Specification does not apply by placing it, as applicable, int '
- 1. At least STARTUP witMn the next 6 nours, 2, At least HOT SHUTL M vithin the following 6 hours, and
- 3. At least COLD $HUtiCW within the subsequent 24 hours.
Where corrective measuret, are cot.41eted that pennit operation under the ACTION requirements, the ACTION tray bt taken in accordance with the specified time limits as measured free the f.ime 9f failure to meet the Control. Exceptions to these requirements Fl 6t6tof in the individual Controls. /) ( This Control is not applicable in CPEPATIONAL CON'lTION u 4 or 5. 3.0.4 Entry into an OPU,ATIO ut. CONDITION or other specified condition shall not be made unless that cchditier.s for the Control are met without reliance on provisions containtd f1 the ACTION requirements. This provision shall not prevent passage throogt or to OPERATIONAL CONDITIONS as required to comply with ACTION requirenerts. Eu.ittions to these requirements are stated in the individual Controls. SHOREHAM - UNIT 1 1.3 3 Revision 16 - July 1990
APPLICABILITY SURVEILLANCE REQUIREMENTS g 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be perfonned within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveillance interval, but
- h. The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval. ,
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Control. Exceptions to these requirements are stated in the individual Controls. Surveillance Rer.,uirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable , condition shall not be made unless the Surveillance Requirement (s) associated with the Controls have been performed within the applicable surveillance interval or as otherwise specified, g SHOREHAM - UNIT 1 1.3-4 Revision 16 - July 1990 O
. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ . _ ~ . _ . _ _ _ _ . _ . _ . _ _ _
l INSTRUMENTATION RAv0 ACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION l CONTROLS 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels . shown in Table 3.3.7.10-1 shall be OPERABLE with their alam/ 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 detemined in accordance with theOffsiteDoseCalculationManual(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.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERAELE. take the ACTION shown in Table 3.3.7.10 1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified,
- c. The provisions of Controls 3.0.3 and 3.0.4 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 CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at - the frequencies shown in Table 4.3.7.10 1. 4.3.7;10.2 At least once per 4 hours at least one circulating 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. O SHOREHAM - UNIT 1 I.3-5' Revision 16 July 1990
TABLE 3.3.7.10-1 RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC ^
TEPJflHATION OF RELEASE
- a. Liquid Radwaste Effluent Line, RE-13 1 110 T
Y
- 2. GROSS RADI0 ACTIVITY MOMITORS PROVIDING ALARM BUT NOT PROVIDING AU10MATIC TERMINATION OF RELEASE
- a. RHR Heat Exchanger Service Water Outlet, RE-23A, RE-238 1 111
- b. Reactor Building Salt Water Drain Tank Outlet, RE-79 1 112
- 3. FLOW RATE HEASUREMEhT DEVICE
- a. Liquid Radwaste Effluent Line 1 113
? 1 1 8 . The detector associated with the operating RHR subsystem shall be OPERABLE E G D O O O O
W i TABLE 3.3.7.101(Continued) ACTION STATEMENTS ACTION 110.. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior t to initiating a release:
- a. At least two independent samples are analyzed in accordance 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 independently verify the release rate calculations and discharge line valvingt Otherwise, suspend release of radioactive effluents via this i pathway.
' ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requiren,ent, for the detector (s) associated with operating RHR loop (s) effluent releases via the(se) pathway (s)maycontinueforupto30daysprovidedthat, at least once per 12 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection of at O least 10* microcurie /mL.
ACTION 112 - With-the number of. channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours, grab samples are collected and analyzed t for radioactivity at a lower limit of detection of at least 10 ' microcurie /ml. ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, flow rate is estimated at least once per 4 hours during actual releases. Pump perfonnance curves generated in place may be used to estimate flow. O SHOREHAM - UNIT 1 1.3 7 Revision 16 - July 1990
I TABLE 4.3.7.10-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENATATION SUREVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
. a. Liquid Radwaste Effluent Line, RE-13 C(4) P R(3) Q(1)
Y w
- 2. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OR RELEASE
- a. RHR Heat Exchanger Service Water Outlet, RE-23A, RE-23B D M R(3) Q(2)
- b. Reactor Building Salt Water Drain Tank Outlet, RE-79 D M R(3) Q(2)
, 3. FLOW RATE MEASUREMENT DEVICE' "e
7 a. Liquid Radwaste Effluent Line D(4) N.A R Q
?
w b G b 8 O O O
) I t- ^ LABLE4.3.7.101(Continued) i l TABLE A0iAT!0NS l (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: I
- 1. Instrument indicates measured levels above the alann/ trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
i 4. Instrunnt cont.rols not set in operate mode. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control r00m alarm annunciation 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 mode. 4 (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the i ' referencestandardscertifiedbytheNationalBureauofStandards(NBS)or-using standards that have been obtained.from suppliers that participate in measurement assurance activities with NBS. These standards shall permit' calibrating _ the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used. (4) CHANNEL CHECK shall consist of verifying indication during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days when batch releases are made, e o SHOREHAM - UNIT 1 1.3-9 Revision 16 - July 1990 n a , - . ___,1 __ - _ _ -- .- - . _ _ .
._._____2.___ _ . ~ _ _ . - _ _ . . _ . _ _ _ _ _ .
l INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUPENTATION O CONTROLS 1 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels I shown in Table 3.3.7.11-1 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The i alam/ trip setpoints of these channels shall be determined in accordance with the ODCM. APPLICABILITY: As shown in Table 3.3.7.11-1 ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Co.itrol, inmediately suspend the release of radioactive gaseous effluents nionitored by the affected channel or declare the chant.el inoperable.
- b. With less than minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Semiannual Radioactive Effluent Release Report why th's inoperability was not corrected within the tirre specified,
- c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseou. effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCT10 Fat TEST operations at the
-frequencies shown in Table 4.3.7.11-1.
i SHOREHAM - UNIT 1 !.3-10 Revision 16 - July 1990
TABLE 3 7.11-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRIKfENT- CPERABLE APPLICABILITY ACTION 1.. MAIN CONDENSER OFFGAS.: TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM '
- a. Nobel Gas Activity Monitors - Alam, if ** 120 RE-65A, RE-65B
'2. (Not Used) .
- 3. STATION VENTILATION EXHAU ')MITORING SYSTEM
- a. Noble Gar. Activity Monitor, RE-42 1
- 120
.~ b. Iodine Sampler 1
- 122 Y
- c. Particulate Sampler 1
- 122
- d. Effluent System Flow Rate Monitor 1
- 123
- e. Sampler Flow Rate Monitor 1
- 123
- 4. CONDENSER AIR EJECTOR RADI0 ACTIVITY MONITOR PROVIDING ALARM (TERMINATION OF. BYPASS FLOW IS MANUAL) i
, a. Noble Gas Activity Monitors (prior to If *** 124
= input to holdup system), RE-12A, RE-12B i i r
o b i !- L. w b i O
i _ TABLE 3.3.7.11-1 (Continued) TABLE NOTATIONS
*At all times. **During main condent,er offgas treatment system operation. ***During operation of the main condenser steam jet air elector (s).
4 ,anitor connected to the operating offgas loop shall be OPERABLE. ACTION STATEMENTS ACTION 120 - Mth the number of channels OPERABLE less than required by the Minimum Ch'annels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab sa @ es are taken at least once pe* 8 hours and these samples are arislyzd for gross activity within 24 hours. ACTION 121 - (NotUsed) ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1. g ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. ACTION 124 - a. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the gases from the main coridenser may be released to the environment for up to 72 hours provided:
- 1. The offgas system is not bypassed, and
- 2. The offgas delay treatment system effluent activity monitor is OPERABLE; Otherwise, be in at least HOT SHUTDOWN within 12 hours,
- b. With the number of channels OPERABLE equal to the Minimum Channels OPERABLE requirement and the release exceeding the setpoint, terminate the bypass flow manually within 1 hour.
SHOREHAM - UNIT 1 1.3 12 Revi:: ion 16 - July 1990 l
. N l-TABLE 4.3.7.11-1
-RADI0 ACTIVE GASEOU', EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL 'MCDES IN WHICH' ;
CHANNEL SOURCE CHANNEL. ~ FUNCTIONAL' SURVEILLANCE INSTRUMENT -CHECK CHECK CALIBRATION : TEST- -REQUIRED
- 1. : MAIN CONDENSER OFFGAS TREATMENT
^*
SYSTEM EFFLUENT MONITORING SYT
- a. Noble Gas Activity Monitoi D M' R(2) Q(1) **
Alarm, RE-65A,'RE-65B
- 2. (NOT USED) ;
7 3. STATION VENTILATION EXHAUST MONITORING w SYSTEM
- a. Noble Gas Activity Monitor, D M R(2) Q(1)
- RE-42 :
- b. Iodine Sampler W N/A- N/A N/A *
- c. Particulate Sampler W N/A N/A N/A * ,
- d. Effluent System Flow Rate D N/A Q- N/A
- Monitor t
y e. Sampler Flor Rate Monitor D N/A Q. N/A *- g. [ 4. CONDENSER AIR EJECTOR :tADI0 ACTIVITY _ . MONITOR PROVIDING ALARM .-(TERMINATION OF BYPASS FLOW IS MANUAL)' i -; y a. Noble Gas Activity Monitors D M R(2) Q(1) *** q (prior to input to holdup _ -system),RE-12A,RE-12B '
'S O
TABLE 4.3.7.11-1(Continued) TABLE NOTATIONS
*At all times.
**During main condenser offgas treatment system operation.
***During operation of the main condenser steam jet air ejector (s).
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alann annunciation and/or indication occurs if any of the following conditions exists: ,
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(2) The initial CHANNEL CALIBRATION shall be performed using ane or more of l the reference standards certified by the National Bureau of Standards (NBS) or using s*andards that have been obtained from suppliers that participate in measurement 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 initial calibration shall be used. (3) (NotUsed) I SHOREHAM - UNIT 1 1.3-14 Revision 16 - July 1990
-3/4.11 RADI0 ACTIVE EFFLUENTS
- 3/4.11ilLIQUIDEFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 The concentration of radioactive material released in_ liquid effluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited to the -
concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2
' for radienucifdes other than dissolved or entrained noble gases. For dissolygd or_ entrained noble gases, the concentration shall be limited to-2,x 10' - microcurie /mL total activity.
APPLICABILITY: At all times. ACTIg{: With the concentration of. radioactive material released in liquid effluents - to UNRESTRICTED AREAS ecceeding the above limits,_immediately restore _the concentration: to within the above limits. i - SURVEILLANCE REQUIREMENTS l 4.11.1.1.1 Radioactive liquid wastes sh'all be sampled and analyzed according to the sampling and analysis' program of Table '4.11.1.1.1-1. 4'.11.1.1. 2 ' The results of:the radioactivity analyses shail be used in accordance with the methodology-and parameters in the ODCM to assure that the
-concentrations at-the point of release are maintained within the limits of
.Controli3.11.1.1.
p p }
;f3 t)
SHOREHAM - UNIT-1 I.3-15 Revision 16 - July 1990
TABLE 4.11.1.1.1-1 RADI0 ACTIVE L10U10 WASTE SAMFLING AND ANALYSIS PROGRAM O Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD) Type Frequency Frequency Analysis (uCi/mL)a A. Batch Waste P P Principal Gama e 5x10-7 Reler.seignks Each Batch Each Batch Emitters and Sumps
- 1. Discharge 1-131 Ot10-6 Waste Sample Tanks P*, M* Dissolved and 1x10-5 One Batch /M Entrained Gases
- 2. Recovery (GammaEmitters)
Sample Tanks 1x10-5 EacbBatch Compo$ited H-3 Gross Alpha 1x10-7 S. Yard Pip- 4 ind Drain P Q Sr-89, Sn90 5x10 d Surp Each Butch Composite Fe-55 1x10-6 Principal Ganca 5x10 N W B.Continuogs D d c Releases Grab Sample- Composite En.mi ters
- 1. RHR Heat Exchanger 1-131 1x10-6 Service Water M M Dissolved and 1x10-5 Outlet Grab Sample Entrained Gases (Ganna Emitters)
- 2. Reactor Building Salt Water D M H-3 1x10-5 d
Drain Tank Grab Sample Composite Gross Alpha 1x10~7 D Q Sr-89, Sr-90 5x10~8 d Grab Sample Composite - Fe.55 1x10-6
- If batdh is releaseo during the month.
1,3-16 Revision 16 - July 1990 O SHOREHAM - UNIT 1
TABLE 4.11.1.1.1-1-(Continued) TABLE NOTATION k ~
"The LLD_is defined. for purposes of the Controls, as the smallest Leoncentration of radioactive material in a sample that wili vield'a net
. count, above system background, _that will be detected with >5% 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-(-A6t_)
Where:. LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or_ volume, ssis the standard deviation of the background counting rate or of tne counting rate of a blank sample asl appropriate, as counts per minute, LE is the counting-efficiency. as counts per disintegration',- V is the sample size in units of mass or volume, 2.22 x 106 -is the number of disintegrations per minute per microcurie, i-Y 'is the fractional radiochemical-yield, when applicable, e A-is the radioactive. decay constant for the particular radionuclide.-and at for plant effluents-is the elapseo 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 <
-a_ posteriori (after the fact) limit for a- particular measurement.
bA batch rilease is the discharge of'11guid wastes of a-discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described-in.the ODCM to assure representative sampling. SHORLAM UNIT 1 1.3-17 Revision 16 - July 1990 l'
TABLE 4.11.1.1-1 (Centinued) TABLE NOTATIONS (Continued) C The principal gama emitters for which the LLD specification applies include the following radionuclides: Mn-54 Fe-59, 00-58, Zn-65, Mo-99, Cs-134 Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gama peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.7. d A 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 continous 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.
, O SHOREHAM - UNIT 1 1.3-18 Revision 16 - July 1990
_ - - . - . . - ..- _- - - -.~_--_ - -. - - -
-RADI0 ACTIVE EFFLUENTS.
DOSE
-CONTROL 3.11.1.2 The dose' or dose commitment to a MEMBER OF THE PUBLIC from .
radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.3-1) 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.
-APPLICABILITY: : At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials
,in liquid effluents exceeding any of the above limits. prepare and submit to the Comission 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 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 Controls.3.0.3 and 3.0.4 are not applicable.
' SURVEILLANCE REQUIREMENTS <
4.11.1.2' Cumulative dose contributions from -liquid effluents for the current calenda* quarter and the current calendar year shall be detennined in 1 accordance with.the methodology-and parameters in the ODCM at least once per-31 days. > o -SHORERAM - UNIT 1 1.3-19 Revision 16 - July 1990
RADIOACTIVE EFFLUENTS LIQUIDRADWASTETREATMENTSYSTp 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 lic,uid effluent, from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3-1) 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 6.9.2 a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability. -
(
- 2. Action (s) taken to restore the inopereble equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence, b .- The provisions of Controls 3.0.3 ano 3.0.4 are not applicable.
SURVEILLANCE 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. 4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. < 9 SHOREHAM - UNIT 1 1.3-20 Revision 16 - July 1990
1 RADIOACTIVE EFFLUENTS bV.-- 3.11.1.4 (NotUsed) 1 4 O S } O SHOREHAM - UNIT 1 I.3-21 Revision 16 - July 1990
RADIOACTIVE EFFLUENTS 3/4 11,2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 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 5.1.3-1) 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 mrems/yr to the skin, and
- b. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate forin with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s). SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. 4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1. l SHOREHAM - UNIT 1 1.3-22 Revision 16 - July 1990 l l l l l
TABLE 4.11.2.1.2-1 RADIDACTIVE GASEOUS WASTE MONITORING, SAMPLING AND ANALYSIS PROGRAM [') . q ,/ Lower Limit Minimum Type of of Detection Gaseous Release Sampling Analysis Activity Type Frequency Frequency Analysis (u(LLD)Ci/ml)a I A. Station Continuous' W I-131 1 x 10-12 Ventilation Charcoal Exhaust Sample I Continuous
- W Principal Gama 1 x 10~I1 Particulate b
. Sample Emitters 8
Continuous M Gross Alpha 1 x 10~11 Composite Particulate Sample Continuous' Q Sr-89, Sr-90 1 x 10~11 Composite Particulate Sample
- ,')
t U Continous' Noble Gas Noble Gases 1 x 10-6 Monitor Gross Beta or Gama c C Principal Gama 1 x 10~4 M M Grab Sample b Emitters c Mc .d M H-3 1 x 10-6 Grab Sample B. Containment MC '9 Mc .g Principal Gama 1 x 10 Atmoshere Grab Sample Emitters b H-3 1 x 10-6
/S V
SHOREHAM - UNIT 1 1.3-23 Revision 16 - July 1990 i
TABLE 4.11.2.1.2 1 (Continued) TABLE NOTATION a ihe 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 s b LLD = E . V. 2.22 x 106 . Y . exp ( AS t) Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sg is the standard deviation cf the background counting rate or of the counting rate of a blank sample as appropriate, as counts per 4 minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 100 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 radionuclide, and at for 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 reccgnized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measureEent system and not as
,a, posteriori (after the fact) limit for a particular measurement.
< O SHOREHAM - UNIT 1 I.3-24 Revision 16 - July 1990
TABLE 4.11.2.1.2-1(Continued) TABLE NOTATIONS (Continued) ( bThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, I-133, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gama peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.7. c Sampling and analysis shall also be perfonned following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1-hour period. - d ' Tritium grab samples shall be taken at least once per 7 days from the , ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
'The 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, 3.11.2.2, and 3.11.2.3.
I Samples shall be en vd at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler.
._ Sampling shall: also be performed at least once per 24 hours for at least 7 days following_ each shutdown, startup or THERMAL POWER change exceeding 15%
of RATED THERMAL p0WER in 1 hour and-analyses shall be completed within 48 hours of changing. When samples collected for,24 hours are analyzed, the This requirement does corresponding not apply.if (LLDs may_be increased by a factor of 10.1) analysis shows that the DOSE in the reactor coolant has not increased by more than a factor of -3; and (2)
- the noble gas monitor shows that effluent activity has not increased by more than a factor of,3.
9Sampling and analysis shall also be performed prior to \ENTING or-PURGING of-the containment drywell-and suppression chamber if- the purge lines _ bypassing the Containment Purge Filtration System are utilized or if the Containment
- Drywell- Filter Train Exhaust Radiation Monitor is inoperable.-
IO LJ Revision 16 - July 1990 SHOREHAM - UNIT 1 1.3-25 l i
3 t RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 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 5.1.3-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equoi 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 ganza 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 Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and 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 Cuntrols 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS _ 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current cf endar year for noble gases shall be determined in accordance with the methodo'ogy and parameters in the 3DCM at least once per 31 days, O SHOREHAM - UNIT 1 I.3-26 Revision 16 - July 1990 ,
. m. ._ . _ _ _ . - _ _ . _ . _ . _.. _ _ . - _ _ _.
i
,RAC10 ACTIVE EFFLUENTS l 90SE-10 DINE-131,10 DINE 133. TRIT!UM,ANDRADIONUCLIDESINPARTICULATEFORM CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine 131, iodine-133, 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 5.1.31) shall be limited to the foll_ owing: -
- a. During any calendar quarter: Less then or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to.15 mrems to any organ.
APPLICABILITY: At all times, ACTION:-
- a. ' With the calculated dose from the release of iodine-131, iodine-133. -tritium,- and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any Is of the above limits, )repare and submit to the Connission within 30 days, pursuant to Tecinical Specification 6.9.2, 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 proposCd Corrective actions to be taken to assure that subsequent releases will be in compliance wf h the above limits.
-b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVE1LLANCE REQUIREMENTS 4.11.2.3 Cumulative dose' contributions for the current calendar quarter and-current calendar year for iodine-131, iodine-133, tritium, and-radionuclides - in particulate fom with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the-0DCM at least once per 31 days. LO SHOREHAM - UNIT 1 1.3-27 Rt 11on 16 - July 1990 l i
RADIOACTIVE EFFLUENTS , GASE0US RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE and in operation. APPLICABILITY: Whenever the main condenser steam jet air ejector (evacuation) system is in operation. ACTION:
- a. With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable for more than
^
^$ys, prepare'and submit to the Commission within 30 days, w_.auant to Technical Specification 6.9.2, a Special Report d':h includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for 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.
g
- b. The provisions of Centrols 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.4 The GASE0US RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by verifying proper operation by checking relevant instrumentation at least once per 12 hours when the main condenser steam jet air ejec'.or (evacuation)systemisinoperation. Revision 16 - July 1990 O SHOREHAM - UNIT 1 1.3-28
RADIOACTIVE EFFLUENTS Q;, s VENTILATION EXHAUST TREATMENT SYSTEM CONTROLS 3.11.2.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) when averaged over 31 days would exceed 0.3 mrem to any organ in a 31-day period. APPLICABILITY: At all times. ACTION:
- a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following infonnation:
- 1. Identification of the inoperable equipment or subsystems, and (3 the reason for the inoperability.
\~)
- 2. Action (s)takentorestoretheinoperableequipmentto OPERABLE status, and
- 3. Sumary descriptions of action (s) taken to prevent a recurrence,
- b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMEhTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at
- and beyond the SITE B0UNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCH.
4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE Ly operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. g) V SHOREHAM - UNIT 1 1.3-29 Revision 16 - July 1990
RADIOACTIVE EFFLUENTS i EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOP OPERATION ~ 3.11.2.6 (NotUsed). PAD 10 ACTIVE EFFLUENTS MAIN CONDENSER - LIMITING CONDITION FOR OPERATION 3.11.2.7 (NotUsed). O SHOREHAM - UNIT 1 I.3-30 Revision 16 - July 1990 e! 1 1
, .- .- - . . - . - . . . - - . .-.- - - ~ . - -
RADI0 ACTIVE EFFLUENTS 7 CONTAINMENT PURGING AND VENTING-CONTROLS' 3.11.2.8 VENTING or PURGING of the containment drywell and suppression chamber shall be through:
-a.- The OPERABLE primary containment purge filter, or,
- b. The purge lines bypassing the primary containment purge filter.
The station ventilation exhaust monitor OE-42) shall be OPERABLE in this mode of operation. APPLICABILITY: Whenever;the drywell is vented or purged. , ACTION: . a.- 'With the requirements of the above specification not satisfied, I suspend all VENTING and PURGING of the drywell, b.- The provisions of Contrnis '3.0.3 and 3.0.4 are not_ applicable. d SURVEILLANCF REQUIREMENTS Q.
- 4.11.2.8.1 The containment drywell shall' be determined to be aligned for l VENTING or PURGING through the primary containment purge system within 4 '
hoursiprior to start-of and at least once per 12 hours during VENTING or PURGING'of the drywell. L4.11.2.8.?c The1 containment drywell shall:be analyzed per Table 4.11.2.1.2 of-iSpecification 3.11;2i1 within 8 hours prior to start of and at least once per ; 12 hours during VEliTING or PURGING of. the drywell if the containment purge filter is-bypassed or if the Containment Filter Train Exhaust Radiation , Monitorfis' inoperable.; 1
~
14.11.2.8.30-The primary containment purge system shall'be demonstrated OPERABLE: a' . . At least once ser. 31 days by initiating, .from the control room.- flo+through tie HEPA filters and charcoal adsorbers-and verifying that the system operates for at least 15 minutes'unless the system has been utilized to process gaseous effluents during the. previous-
?31' days.
- p:
X SH0REHAM -' UNIT 1 I.3-31 Revision 16 - July 1990;
RADIOACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) O
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone comunicating with the system by:
- 1. Verifying that with the system operating at a flow rate of 1200 cfm i 10% and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the subsystem bypass valve, is less than or equal to 1% when the system is tested by admitting cold DOP at the system intake.
- 2. Verifying that the system satisfies the in-place testing acceptance. criteria and uses the test procedures of Regulatory Positions C 5.a. C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978,_at a system flow rate of 1200 cfm 110%.
- 3. Verifying within 31 days after removal that a laboratory analysis of a respresentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52 Revision 2, March 1978.
- 4. Verifying a system flow rate of 1200 cfm 10% during subsystem operation when tested in accordance with ANSI N510-1975,
- c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal thet a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2 March 1978,
- d. At least once per 18 months by: j
- 1. Verifying that the pressure drop across the combined HEPA l filters and charcoal adsorber banks is less than 5.5 inches water gauge while operating the filter train at a flow rate of i 1200 cfm 110%. l l
- 2. Verifying that the filter train starts and isolation dampers open on manual initiation from the control room.
- e. After each complete or partial replacement of a HEPA filter bank by 4 verifying that the HEPA filter banks remove greater than or equal to 99.00% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 1200 cfm 10%.
( SHOREHAM - UNIT 1 1.3-32 Revision 16 - July 1990 O
RADI0 ACTIVE EFFLUENTS-
. SURVEILLANCE REQUIREMENTS (Continued) f.- After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than
. :99.00% of a=halogenated hydrocarbr' refrigerant test gas when they
-are tested in-place in accordance with ANSI NS10-1975 while
-operating the system at a flow rate'of 1200 cfm 210%.
i 4 RADI0 ACTIVE EFFLUENTS - 3/4.11.3 Not Used O SHOREHAM - UNIT 1 1.3-33 Revision 16 - July 1990-
RADICACTIVE EFFLUENTS 324.11.4 TOTAL DOSE CONTROLS 3.11.4 The annual (colencar year) dose or dose comitment 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 limited 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 Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, 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 conformance with the above limits. This Special 1 Report, as defined in 10 CFR 20.405c, shall include an anal;.is 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 end concentrations of radioactive material involved, and the cause of the exposure level:. or concentrations. If the estimated duse(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 Report 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 Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. 4.11,4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in ) accordance with the methodology and parameters in the ODCM. This requirement 1 is applicable only under conditions set forth in Control 3.11.4a. 1 SHOREHAM - UNIT 1 1.3-34 Revision 16 - July 1990 l l l
1 3/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING
/~N Q 3/4.12.1 MONITORING PROGRAM
. 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:
- a. . With the radiological environmental program not being conducted as specified in Table 3.12.101, prepare and submit to the Comission, in the Annual Radiological Environmental Op rating Report. required by Control 6.9.1.6, a description of the reasons for not conducting the program as 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 Sp(ecial Reportthat identif ,
A the corrective actions to be taken to reduce radioactive effluents > h so that the potential-annual-dose
- to A MEMBER OF THE PUBLIC fs 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 submitted if:
concentration'(11 + -concentration (2) + .. 11.0 t 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 Tl!E 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 31 ant-effluents; however, in such an event, the condition shall >e reported and described in the Annual Radiological Environmental Operating Report.
L -- *The methodology and parameters used to estimate the-potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. t SHOREHAM - UNIT 1 1.3-35 Revision 16 - July 1990
RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS (Continued) ACTION: (Continued)
- c. With milk or 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 6.9.1.7, ddentify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also it.clude in the- report a revised figure (s) and table for the ODCM reflecting thenewlocation(s),
- d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANU. REQUIREMENTS __ _ 4.12.1 The radiological environn' ental san'ples shall be collect ed pursuant to g Table 3.12.1-1 from the specific locations given in the table at d fig' 'rs in the 00CM, and shall be analyzed pursuant to the requirement of Table 3.12.1-1 and the detection capabilities required by 4.12.1-1. SHOREHAM - UNIT 1 I.3-36 Revision 16 - July 1990
. ,g n
\
.TABL .12.1-l'
_ RADIOL'0GICAL ENVIRONMENTAL MONITORING PROGRAM
- EXPOSURE PATHWAY NUMBER'0F REPRESENTATIVE SAMPLING'AND TYPE AND FREQUENCY' 8
AND/0R SAMPLE _5AMPLES AND SAMPLE COLLECTION COLLECTION FREQUENCY OF ANALYSIS D
- 1. DIRECT RADIATION '3s routine monitoring stations, Quarterly Gamma dose quarterly.
DRI-DR36, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously. - placed as follows:
- a. An inner ring of stations, one in each meteorological sector in the s general area of the. SITE BOUNDARY, u, DRI-DR16; d>
- b. An outer ring of stations, one in each meteorological sector. in the 6- to 8-km range from the site, DR17-DR25;
- c. The balance of'the ststions, DR26-D236,'to be placed in special iriterest areas such 'as population centers, nearby residences, schools, and in 1.or 2 areas to serve as control . sta tions.
5' o E
, The number, media, frequency, and location of samples may vary from site to site. This . table presents an c, acceptable minimum program for a ' site at which each entry is applie :_ .a. ' Local site characterisitics must be c, examined to determine if pathways not covered by this table may significantly contribute to an individual's dose
~
x and should be included in the. sampling program. 7> O
TABLE 3.12.1-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLES AND SAMPLE COLLECTION
- COLLECTION FREQUENCY OF ANALYSIS
- 2. AIRBORNE Radiciodine and Samples from 5 locations, Al-AS: Continuous sampler Radioiodine Cannister:
Particu!ates operation with sample I-131 analysis weekly. 3 samples, Al-A3* from close collection weekly, or t i the 3 SITE BOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sarnpler: highest calculated annual average loading. Gross beta radioactivity groundlevel D/Q. analysis folloging filter change; Gansna 1 sample, A4, from the vicinity isotopic analysis " of of a community having the highest corposite (by location) calculated annual average groundlevel quarterly.
." D/Q.
i' g 1 semple, A5, from a control location as for example 15-30 km distant and I" the least prevalent wind direction.c '
- 3. WATERBORNE
- a. Surface h I sample control, Wal Grab sample Gama isotopic analysis" (Long Island I sample o.' charge, Wa2 or Wa3 semiannually. and tritium analysis Sound) semiannually.
E. b. Ground Samples from 1 or 2 sources, Wbl, Quarterly. Gama isotopic" and g Wb2, only if likely to be affected.f tritium analysis, _ quarterly. m
' c. Sediment from I sample from downstream area with Semiannually. Gamma isotopic. analysis" y shoreline existing or potential recreational semiannually.
y
- value, Wdl. ~
o
$ *The first and second highest D/Q sectors have radiofodine mnd particulate ramples. The third highest D/Q sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector.
O O O
TADLE 3.12.1-1 (Continued) RADIOLOGICAL ENiflR0fMENTAL MONITORING PROGPAM* NUMBER OF REPRESENTATIVE a SAFILING AND TYPE AND FREtJUENCY EXPOSURE PAT}rdAY Of ANALYSIS SAMPLES AND SAMPLE COLLECTION _ COLLECTION FREQUENCY AND/0R SAMPLE
- 4. INGESTION Semimonthly when Gamma isotopic" and I-131
- a. Milk Samples fro = milking animals in location Ial, within 5 km distance animals are on analysis semimonthly when having the highest d3se potential. pasture, monthly at animals are on pasture; If there are none, then, I sample other times. renthly at otter tires.
from milking animals in each of 3 areas, Ial, between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr, or if there are none available within 8 km, then a location 8 to 17 km distant will be used.
- 1 sample from milking animals at a
[ e control location, Ia2, 15-30 km S distant, and not in a direction prevalently downwind from the Plant. I sample of each comercially and Sample in season Gan=a isotopic analysis"
- b. Fish and on edible pc-tions.
Invertebrates recreationally important spec es in or semiannually if vicinity of plant discharge area, they are not seasonal. Ibl-Ib2. I sample of sane species in areas not i influerced by plant discharge, Ib3.
- =
Samples of 3 different kinds of At time of harvest.I Gama isotopic" and I-131 3, c. FOOD PRODUCTS analysis.
; broad leaf vegetation grown nearest ,
o each of tw different offsite
" locations of highest pr*dicted annual E average ground-level D/Q, if milk e
sampling is not performed, Ic1 - Ic3. . ( 1 sample of each of the similar At time of harvest.' Gar:ma isotopic
- and 1-131 f- analysis.
- broad leaf vegetation grown 15-30 km E distant in the least prevalent wind E direction if milk sampling is not perform Ic3.
TA,BLE 3.12.1-1 (Continued) TABLE NOTATIONS 8 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 3.12.11 in a table ar.d figure in the ODCM. Refer to NUREG-0133,
- Preparation of Radiological Effluent Technical Specifi-cations for Nuclear Power Plants " October 1978. and to Radiological Assessment Branch Technical Position, Revision 1. November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtain-able 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 fror the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Controls 6.9.1.C. 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 question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Control 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reficcting the new location (s). One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may W used in place of, or in addition to, integrating dosimeters. For the surposes of this table, a thermoluminescent dosimeter (TLD) is considered to )e 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 radiatiun. 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 optimum dose information with minimal fading. C The purpose of this sample is to obtain background infomation. 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, d Airborne particulate sample filterr, shall be analyzed for gross beta radioactivity 24 hours or more after samp*ing 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 cont. 41 samples, gama isotopic analysis shall be perfomed on the individual .amples.
' Gamma isotopic analysis means the identification and quantification of gama-emitting radionuclides that n.ay be attributable to the effluents from the facility.
SHOREHAM - UNIT 1 1.3-40 Revision 10 - July 1990 O
TABLE 3.12.1-1(Continuedl TABLE NOTATIONS (Continued) I Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. 9The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. hT b " 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 lf harvest occurs more than once a year, sampling shall be performed during , each discrete harvest. If harvest occurs continously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root - food products. s O
=
(3 V SHOREHAM - UNIT 1 1.3 41 Revision 16 - July 1990 - a m.m W
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D i 1 2 O C O p F ( S E L P M - A S ) K L L L / A I i 3 0 0 0 T MCp 6 7 0 N 3 E ( M N O R I V N E N I ) t S e N w O 0 0 0 0 0 0 0 I H , 0 0 0 0 0 0 0 T s S g 0, 0, 0, 0, 0, 0, 0, 2 A l I k
- P e F / 0 0 0 0 0 1 2 1 T v i 3 1 3 1 2 N e C p
2 E L 1 C ( O N g 3 O n C i E t L Y r B T o p A I T V e I R E T T ) C A3 A L m 0 U / I C i D I c A R p R A ( P 9 P S D E E 0 0 0 F N S 1 2 R A S O G L B E R R V I O E A L G N I T R O ) P R L 0 0 0 0 0 0 0 2 0 0 0 E E / 0 0 0 0 0 0 0 3 5 0 R T i A 0, 0, 4 0, 3 3 4 2 W Cp 0 1 1 ( 3 0 S 5 4 I 9 1 O S - 4 7 - Y 4 9 8 0 5 b 1 3 3 a L 5 5 5 6 6 N 3 1 1 L A 3 - - - - - - I - - - N A H
- n e o o n r - s s a M F C C Z Z I C C B
[- O i Ey5 E - mkx *
'llI lll !i!! 1l l
i (~ b ( TABLE 4.12.1-1 U ab DETECTION CAPADILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)C AIRBORNE PARTICULATE OR GAS FISH MILK FDDD FRODUCTS SEDIMENTS WATER ANALYSIS (pCi/L) (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) (pCi/kg, dry) Gross Beta 4 0.01 H-3 3000 . Mn-54 15 130 Y C Fe-59 30 260 C0-58, 60 15 130
'Zn-65 30 260 Zr-95 30 Nb-95 15 m I-131 I d- 0.07 I 60 3
0.05 130 15 60 150 0' . Cs-134 15 . " 18 0.06 150 18 80 180 Cs-137 E i Ba-140 60 60
)
y' La-140 15 15 3 8
.r-
TABLE 4.12.1-1 (Continued) TABLE NOTATIONS - a This list does not mean that only these nuclides are to be considered. Other peaks that ere identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. b Required detecticn capabilities for thermoluminescent dosimeters used for environmental measurements are given in Re4ulatory Guide 4.13. C The LLD is defined, the purposes of these specifications, 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" sign.al. For a particular measurement system, which may include radiochemical separation: i LLD = 4.66 s b E . V . 2.22 . Y. exp (- Aat) g Where: LLD is the "a priori" lower limit of detection as defined above, os picocurie per unit mass or volume, s h 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 site in units of mass or volume, 2.22 is the number of transformations per minute per picoeurie, Y is the fractional radioche,'ical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and at for environiaental sampler is the elapsed time between sample collection, or end of the sample cc lection period, and time of counting. 4 Typical values of E, V, f, ene t shall be used in the calculations. SHOREHAM - UNIT 1 1.3-44 Revision 16 - July 1990
TABLE 4.12.1-1 (Continued) TABLE NOTATIONS (Continued) It should be recognized that the LLD is defined as an a prior (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter 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 Environnental Operating Report pursuant to Control 6.9.1.6. d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
%J O SHORfHAM - UNIT 1 1.3-45 Revision 16 - July 1990
l RADIOLOGICAL ENVIRONFENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location of each of the 16 meteorological sectorsofthenearestmi1Lanimal,ghenearestresidence,andthenearest garden of greater than 50 m2 (500 ft ) producing broad leef 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) thelocationsineachofthe16geteorologicalsectorsofallmilkanimalsand all gardens of greater than 50 m (500 ft ) 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, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7.
- 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 tha
! new location (s) to the radiological 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 af ter October 31 of the year in which this land use census was conducted. Pursuant to Control 6.9.1.7, identify the new location (s) in the next Semiannual 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 and 3.0.4 are not applicable.
SUREVE!LLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growth season at lesst 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 Control 6.9.1.6. 9 road 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 0/Qs 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 Revision 16 - July 1990
l RADIOLOGICAL ENVIRONMENTAL MONITORING , 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM (} CONTROLS 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaberatory 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 being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission i in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
- b. The provisions of Controls 3.0.'3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS O(s/ 4.12.3 The Interlaboratory Comparison Prngram 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 6.9.1.6. D O SHOREHAM - UNIT 1- 1.3-47 Revision 16 - July 1990
SNPS-1 CDCM t PART 1 & SECTION 4 W RADIOLOGICAL 1FFLUENT CONTROLS BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 4 O ; I.4-0 Revision 16 - July 1990 , O l
O . NOTE The BASES contained in succeeding pages w,:..arize 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. O 1.4-1 Revision 16 - July 1990 ,
INDEX BASES
- f O
S_ECTION PAGE INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION Radioactive Liquid Effluent Monitoring......... I.4-3 Instrumentation Radioactive Gaseous Effluent Monitoring........ I.4-3 Instrumentation 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration................................ I.4-3 D05e......................................... 1.4-4 Liquid Radwaste Treatment System............. 1.4-4 3/4.11.2 GASE0US EFFLUENTS Dose Rate.................................... I.4-5 Dose - Noble Gases........................... 1.4-5 Dose - Iodine-131, lodine-133, Tritium, and Radionuclides ir. Particulate Form.......... I.4-6 Gaseous Radwaste Treatment System............ I.4-6 Ventilation Exhaust Treatment System......... 1.4-7 Containment Purging and Venting.............. 1,4-7 3/4.11.4 TOTAL 00SE................................... I.4-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM........................... 1.4-8 3/4.12.2 LAND USE CENSUS.............................. 1.4-8 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM........... 1.4-9 SHOREHAM - UNIT 1 1.4-2 Revision 16 - July 1990 O
P INSTRUMENTATION BASE 5
-3/4.3.7 MONITORING INSTRUMENTATION ,
3/4.3.7.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to
- monitor and control, as applicable, the releases of radioactive material in t liquid effluents during actual or_ potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and 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. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60; 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.11 RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring. instrumentation is provided-to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual-or potential releases of gaseous effluents.
-The alarm / trip-setpoints for these -instruments. Shall be calcula+ed and 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 concentrations of potentially explosive gas mixtures in the main condenser offgas-treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to-10 CFR Part 50.
( 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This Control is provided to ensure.that the-concentration of radioactive materials-released in liquid waste effluents to UNRESTRICTED AREAS'will be . less.than;the concentration levels specified in 10 CFR Part 20, Appendix B,- 4 Table 11. Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in' exposure within (1) the Section ll.A design objectives of Appendix ,
-1, 10 CFR 20.106(e) to the population. The concentration limit for dissolved 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 International; "
Commission 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. .o
~
The require'd. 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-limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to E Radiochemistry," Anal-Chem. 40, 586 93 (1968), and Hartwell, J. K., Detection. [ ' Limits for Radionnalytical Counting)
. Techniques, Atlantic Richfield Hanford Company Report ARH.SA215-(June-1975 SHOREHAM - UNIT 1 1.4-3 Revision 16 - July 1990-
3/4.11 RADIDACTIVE EFFLUEATS BASES 3/4.11.1.2 DOSE This Control is provided to implenent the requirements of Sections ll.A. Ill.A and IV.A of Appendix 1, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A cf Apperdix ! to assure that the releases of radioactive material in liquid efflu nts will be kept "as low as reasonably achievable." The dose calculation rdodology and parameters in the ODCM implement the requirements in Section III.A of Appendix ! that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBt:R OF THE PUBLIC 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 mater 415 in liquid effluents cre consistent with the methodology provided ir; Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1 "
Revision 1, October 1977 and Regulatcry Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental ano Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. ( This Control applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radweste treatment systems, the liquid effluents from the shared system are proportioneo among the units sharing that system. 3/4.11.1.3 LIQUID RA0 WASTE TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid ef fluents require treatment prior to release to the environment. The requirement that the appropriate portions of-this system be used when specified provides assurance that the releases of radioactive materials in liquid ef fluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix 1 to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid redweste treatment system were specified as a suitable fraction of the done design objectives set forth in Section ll.A of Appendix 1, 10 CFR Part 50, for liquid effluents. 3/4.11.2 GASEOUS EFFLUENTS 1.4-4 Revision 16 - July 1990 O SHOREHAM - UNIT 1
RADIOACTIVE EFFLUENTS p BASE 5 V 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the dose at any time at and beyond the SITE BOUNDAPY 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 concentrations of 10 CFR Part 20, Appendix B Table 11 Column 1. These 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 the limits specified in Appendix B. Table 11 average of 10 CFRconcentrations Part 20 (10 CFRexceeding 20.106 (b)). For a MEMBER OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE pVBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER 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 also 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 required detection capabilities for radioactive materials in aseous wastesamplesaretabulatedinterms'ofthelowerlimitsofdetectionfLL0s).
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 and Quantitative Determination - Application for Radiochemistry," Anal. Chem 40,586-93(1968), and Hartwell, J. K., Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 3/4.11.2.2 DOSE - NOBLE GASES lhis Control is provided to implement the requirements of Sections II.B,
!!!.A and IV.A of Appendix I,10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I 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 ! that conformance with the guides of Appendix ! 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 substanially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide l
1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents- for the Purpose of Evaluating Compliance with 10 CFR Part 50, lA Q Appendix I, October 1977 and Regulatory Guide 1.111. " Methods for estimating SHOREHAM - UNIT 1 1.4 Revision 16 - July 1990
DCSE - NOBLE GASES (Continued)
! Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cocied Reactors," Revision 1 July 1977. The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.
3/4.11.2.3 __ DOSE - 10 DINE-131,10 DINE-133. TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of Sections !!.C. III.A and IV.A of Appendix 1, 10 CFR Part 50. The Controls are the guides set forth in Section !!.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the reovirements in Sestion ll!.A of Appendix ! that conformance with the guides for Appendix 1 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 substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Eveluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1. October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Geseous Effluents in Routine Releases from Light-Water. i Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, radionuclides in pnrticulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 3/4.11_.J 1 GASE0VS RADWASTE TREATMENT SYSTEM This Control is provided to ensure the operation of the GASE0US RADWASTE TREATMENT SYSTEM whenever the main condenser air ejector system is in opera tier,. Implementation of this requirement provides reasonable assurance that the releases of radioactive materials in gaseous ef fluents will be kept
'a* b a3 is reasonably achievable." This Control implements the rw.tements of 10 CFR 50.36.a. General Design Criterion 60 of Appendix A to 10 LFR Part 50, and the design objectives set forth in Sections ll.B 6nd 11.0 of Appentix 1 to 10 CFR Part 50 for gaseous effluents.
I SHOPEHAM - UNIT 1 1.4-6 Revision 16 - July 1990
RADICACTIVE EFFLUENTS BASEE _ _ 3/4.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM The OPERABILITY of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10 CFR Part 50, and the design objective!, given in Section II.D of Appendix ! to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose cesign objectives set forth in Sections !!.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents. 3/4.11.2.8 CONTAINMENT PURGING AND VENTING This Control provides reasonable assurance that releases from drywell purging and venting operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. _3 / a .11. 4 TOTAL DOSE
/N This Contol is provided to meet the dose limitations of 40 CFR Part 190 i' that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated' doses from plant-generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites
'containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER Of THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if tne 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 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated 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 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other require-ments for dose limitation of 10 CFR Part 20. as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during
/~ any period in which he/she is engaged in carrying out any operation that is j k part of the nuclear fuel cycle.
l SHOREHAM - UNIT 1 1.4-7 Revision 16 - July 1990 I
. - - - ~ ,. - ,.. . - . . . . . . ,-.- . -
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 the station operation. This monitoring program implements Section IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the radiological effluent monitorin; 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. l Guidance for this monitoring program is provided by the R6diological i Assessment Branch Technical Position on Environmental Monitoring. The i initally specified monitoring program will be effective for at least the first 3 years of commercial operational experience. Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms 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 LtD is defined as an a, priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) .imit 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 and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K.,
" Detection Limits for Radioanalytical Countin Hanford Company Report ARH-SA-215 (June 1975)g Techniques," Atlantic Richfield 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 (ER2.5.3.2). 3/4.12.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at or beyond the SITC BOUNDARY are identified and that modifications to the monitoring program are made if required by 'he results of this census. The best survey information from the door-to-do .* 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 ! 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 l SHOREHAM - UNIT 1 1.4-8 Revision 16-July 1990l l .
RADIOLOGICAL ENV!RONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS (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 garden size, the following assumptions were used, (1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage),and(2)avegetationyieldof2kg/squaremeter. 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 quality 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 1 to 10 CrR Part 50. l') V O SHOREHAM - UNIT 1 1.4-9 Revision 16 - July 1990
i i i 1 !1 e SNPS 1 CDCM PART I SECTION 5 F e i RADIOLOGICAL EFFLUENT -l CONTROLS ! SECTION 5,0 i 1 l DESIGN FEATURES I t f : i l ! I 1 4
< 9 1.5-0 Revision 16 - July 1990
i ) i i i 1 l INDEX j - DESIGN FEATURES ! SEC'l10N PAGE 1 1 5.1 SITE i SITE BOUNDARY for Radioactive Gaseous and Liquid
- Effluents.......................................... 1.5 3 i
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i i INDEX LIST OF FIGURES l FIGURE PAGE l 1 5.1.3-1 SITE BOUNDARY FOR RADIOACTIVE GASEOUS l And LIQUID EFFLUENT 5.............................. 1.5-4 l l i j r i 9 i i i 1.5-2 Revision 16 - July 1990 g 4
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_ = . ._ _ __ i l SNPS-1 ODCM PART I SECTION 6 RADIOLOGICAL EFFLUENT CONTROLS . SECTION 6.0 l ADMIN!$TRATIVE CONTROLS l l I i 4 J l i : i , h (
?
t ( 1.6-0 Revision 16 - July 1990 ; l. _ __j
ADMINISTRATIVE CONTROLS SECTION DAGE 6.9 REPORTIN3 REQUIREMENTS 6.9.1 ANNUAL RADIOLOGICAL ENYlRONMENTA6 OPERATING REPORT..... 1.6-2 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT......... 1.6 2 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)..................... I.6-3 6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID, AND GASEOUS, WASTE TREATMENT SY5TEMS............,. 7......................... l.6-4 < O
- l O
I.6-1 , Revision 16 - July 1993 '
ADMINISTRATIVE CONTROLS . ) ~ ANNUAL RADIOLOGICAL ENV7RONMENTAL OPERATING REPORT 6.9,1.6 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of ecch year. The initia) report shall be submitted prior to May 1 of the fellowing year following initial criticality. The Annual Radiological Environmental Operating Reports shal) 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 ant) an assessment of the observed impacts of the plant operation on the environcent. The reports shall also include the results of land use censuses required by Control 3.12.2. The Annual Radiological Environmental-Operating Reports shall include the results of analysis of all radioivgical environmentai samples of all environmental radiation measurements taken during tt ) period pursuant to the locations specified in the table and figures in the 00CM, as well as
.,atinarized 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 sone individual results are not available for inclusion with the report, the report inall-be submitted noting and explaining the reasons for the missing results. The missing data thall be submitted as soon as possible in a supplementary report.
v-The reports shall also include the following: o sunnary description of the radiological environmental monitoring program at least two legible maps
- covering all sarapling 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 r9 quired by Table 4.12-1 was not behievable.
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 Routine Semiannual Rad'oactive Effluent Release Peports covering the operation-of the unit during th> previous 6 months of operatten shall be ' submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality. The Semiannual 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 Reicases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, wf th data summarited on a _ quarterly basis following the format of Appendix 8 ther0'. (G) T 0ne map shall cover stations near the SITE BOUNDAU ; a second shall include the more distant stations. SHOREHAM - UNIT 1- 1.6-2 Revision 16 - July 1990
,.n. . . , - , , . . , ,, - .,,n-. n ~ , - - ., - ,,__r.-
ADMINISTRATIVE CONTROLS SEMI ANNUAL RADIOACTIVE EFFLUENT RELE/3E REPORT (Continued) The Semiannual Radioactive Ef fluent Seitase Report to be submitted 60 days after January 1 of each year shall inc;ude en annual su mary of hourly meteorological data collected over the pre 91cu yecr. This annual Su m:ry nioy t be either in the form of an hour-by hour listing . f wind need, wind L. - direction, atmospheric stability, and precipitelmn (if reasured) on magnetic or oe. Or in ;he form of joint freq;en y Jtstribut w. of windspeed, wind s direct m ahl atmospheric stabi.iy.** This sarne aport shall include an 1 assesment uf the radiatM doses due to the radicatt!ve liquid and gaseous j effluents eleased from the unit or station durin1 the previous calendar year, r This same r 'purt shall also include an assessroent'of tht radiation doses from
, raoicacti'e ' Quid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their '
activities .5' ide the SITE BOUNDARY (Figure 5.1.34 ) during the report period. All assumptio, s useo in trakir..; these assessments (i.e., specific activity. I exposure tirv tr0 location) shall be included in these reports. The ' 'eteorologic(. cont'tions concurrent with the time of release of radioactise f 'terials if i iscous ef fluents (as determined by sampling f requency and rement) Jall be used for determining the gaseous athway doses. The 3,,es wett of radiation doses shall be performed b acc & nce with the methodology and parameters in the OFFSITE DOSE CALCULATib N'eUAL (ODCM). The Semiannual Radioactive Effluent Release Report to be vx: ' ted 60 days . after Jannry 1 of each year shall also include an assessment o radiation doses tD nCy uranium fuel cycle sources (including doses fre crimary effluent pathn;6 and direct radiation) for the previous calend6" p ar to show " conf onn acs witt 40 CFR Part 190. Environmental Radiation Protfcuar St: inca rds rat Nuclo Pones ?peration. Acceptable rnethods for calcu1 Hing in iiose contributich frov Iquid and gaseous effluents are given in RegulaS q Guide 1.109, Rev.1, Oc c bor 1977. The Semiannual hdioactive Effluent Release Reperts shall include r list and description of unplanned releases from the site to UNRESTRICTED ArCAS of s radioactive materials in gaseous and liquid effluents made during the reporting Mriod. The Semirann i Radioactive Effluent Release Reports shall include any changes L ma4 'fl.'P the reporting period to the OFFSITE DOSE CALCULATION MANUAL
@DCM), k oli as listing of new locations for dose calculations and/or environmenbr Nnitoring identified by the land use census pursuant to Control 3.12.2.
6M OFFSITE DOSE gr.ULAlyN MANUAL (00CM1 See Technical Spd 'cotion 6.14. L **In lieu of submission witt he Se11ernual Radioactive Effluent Release Report, the ifcensee has the ption of retaining this summary of required meteorological data on file, iT a file that shall 5e provided to the NRC upon ( request. Sr4P EHAM - UNIT 1 1.6-3 Revision 16 - July 1990 m E _ _ _ . . . _ _
q ADMINISTRATIVE CONTROLS d - =- 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID AND GASEOUS Wl.STE TREATMENT SYSTEMS 6.15.1 Licensee-initiated major changes to the radioactive waste treatment system (liquidandgasecus):
- a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Review of Operations Comnittee. The discussion of each change shall contain:
- 1. A suemary 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 benefit of additional or supplemental infmnation; g 3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;
- 1. An evaluation of the change which shows the predicted releases
= of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license
, application and amendments thereto; t
V 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 thereto;
- 6. A comparison of the predicted releasas of radioactive materinis, in liquid and gasecas 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 persennel as a result of the change; and
- 8. Documentation of the fact that the change was reviewed and found acceptable by the Review of Operations Committee,
- b. Shall' become effective upon review and acceptance by the P0C.
()h L. SHOREHA!i - UNIT 1 1.6-4 Revision 16 - July 1990 l
_ m%g - 4 SNPS-1 ODCM PART !! 3 SECTION 1 INTRODUCTION The purpose of this manual is to show the calculational methodology and parameters i used to comply with the Radiological Effluent Controls (REC, Part I) of the ODCM. I Section 2 establishes and the Gaseous methods Effluent Monitortoset calculate points inthe Liquid order Effluent to comply Monitor with set point l REC Sections 3.11.1.1 and 3.11.2.1, respectively. Section 3 establishes dose calculational methods for liquid and gaseous effluents. The liquid effluents dose calculation methods are used to show compliance with REC l Sections 3.11.1.2 and 3.11.1.3. For liquid pathways, the dilution factor of 8.85 used in Section 3.1 is a calculated value based on a submerged, multiport diff, user with a port discharge velocity of 12 fps, a 300 f t radius mixing zone, and 4 circulating water pumps discharging. If only service water pumps are discharging, the dilution factor is one (1.0). The paseot.. effluent dose calculation methods are used to show compliance with REC l Sections 3.11.2.1, 3.11.2.2, and_3.11.2.3. The atmospheric dispersion and deposi-tion factors used in calculation methods were calculated based on onsite meteor-ological data for th) 2-year period of October 1, 1973 through September 30, 1975. ( Regulatory Guide 1.119. Rev. 1 (October 1977), Methodology and Parameters, with the exception of the dil:ition factor of 8.85, when circulating water flow exists, were used in Method 2 (th> Backup hethod,' 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, i BN1-11600.02-92 11.1-1 Revision 16 - July 1990 l 4
i-L SNPS-1 ODCM O V PART 11 ! SECTION 2 SET POINTS 2.1 LIQUID EFFLUENT MONITOR SET POINTS (Compliance with Section 3.11.1.1 of the l RadiologicalEffluentControls(REC,Part1oftheODCM). The radionuclide concentrations released vic liquid ef fluents to unrestricted areas shall be limited to' the concentrations snecified in 10CFR20, Appendix B, Table II.- Column 2 for radionuclides- other than dissoiva d or entrained noble gases. For disgolved or entrained noble gases, the total conc:intration shall be limited to 2 x 10' C1/ml.. The set points of the effluent monitors e e depent' ant on circulating or service water as follows:- 1.- a. circulating With the circulating water flowwater sy(stem rate the (a once-through circulating water system system) in use,ofthe is composed four pumps and circulates sea water at a rate of 574,000 gpm).
- b. The service water flow rate, if the circulating water system is not in use but service water is in use. (The service water system is composed of Lfour reactor building service water pumps, each having a capacity of.8600 gpm and three turbine building service water-pumps each having a capacity
_-h
- %./ - .
of8000gpm.)
- 2. Flow rates 'of effluents from tanks and/or from the RHR heat exchanger service water outlet, and/or yard piping drain sump.
- 3. Individual concentrations of gamma emitters- (other than . dissolved or entrainedinoble gases) and :Sr-89, Sr-90,- Fe-55, and H-3; and - the. total concentration of -dissolved or entrained noble gases and gross concen-tration of the alpha emitters -in the liquids to be discharged.
- 4. Maximum allowable concentration of 2 x'10~4 pCi/ml.for the total concen=
tration= of dissolved or entrained noble gasen ind--maximum permissible-
- concentrations (MPCs) of other gamma - emitters, Sr-89. Sr-90, Fe-55, H-3, -
and alpha emitters in:the effluents as:specified in 10CFR20,4 Appendix B. Table II, Column 2 for an unrestricted area. 1 NOTE: iPrecautions should be taken to assure that.the circulating-water system flow rate or the service - water system flow rate -- used -in determining ' the -set point remains constant during the period of discharge. If the circulating or service water- flow rate during 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.
' Service water via- the RHR heat exchanger service water outlet will be released- /i .
continuously to the environment when the RHR heat exchanger is in operation.
- Reactor building salt' water drain tank contents may be released to the environment cither as Da ibatch - process or continuously. The discharge - waste ': aple tanks, t
recovery sample tanks, and yard piping drain sump contents will shays be released to-the environment as batch processes. BN1-11600.02-92 11.2.1-1 Revisien 16 - July 1990-
SNPS-1 ODCM 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. Spec-ifically, the analysis program will include the determination of gross alpha concentration of the alpha emitters. in addition, it will include isotopic anal-ysis for determination of individual concentrations of principal gama emitters, and the spec.fic radionuclides, Sr-89. Sr-90, Fe-55, and H-3. It will also include the determination of total concentration of the dissolved and entrained noble gases (gama emitters) in the liquids. The concentrations of individual gamma emitters are determined by gama spectral analysis of 1) the batch sample prior to its release for the batch releases and 2) the weekly composite sample for continuous releases. For gross alpha and the specific radionuclides Sr-89, Sr-90, Fe-b5, and H-3, if analysis cannot be performed prior to discharge, chen the following concen-trations are used in the monitor set point calculations: Gross Alpha and H-3 Gross alpha concentration and H-3 concentrations as determined by analysis of the previous monthly composite sample. Sr-89, Sr-90, Fe-55 Individual concentrations are determined by analysis of the previous quarterly composite sample for batch releases. Representative Samples ( Representative composite samples utilized in determining the concentrations of H-3, Sr-89, Sr-90, Fe-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 for obtaining such samples in the REC Table 4.11.1.1.1-1. The tank contents are retirculated prior to obtaining samples for analysis. The minimum recirculation time rt shall be: t = 2v r 7r wtere: v = the volume of liquid in the tank to be sampled f r= the recirculation flow rate being used to mix the tank contents. For the yard drain sump, the above methodology will be used unless it cin b; determined that there has been no condensate storage tank overflow events since the last batch release. Although designated a batch release, tnere may be times when non-contaminated yard drain runoff to the sump will occur during the discharge period. This input will not increase the discharge concentration.
, O ,
BN1-il600.02-92 11.2.1-2 Revision 16 - July 1990
b SNPS-1 ODCM The above methodology will-ensure that a representative sample will be obtained for batch releases. Set Point Philosophy. - 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 i C 4 j1 WC WG
= C a+ C b + ..... +
C n + C e, Cg b a %
'+
C-3 ,Ct +CFe <1 (2.1.1) where: W G. K MPCp y ~ ' CaCb ,......C n = Concentration of the. individual ganna emitting i radionuclidesidentified(pCi/ml) h: 'C. = The gross alpha concentration-(uCi/ml) G C- g = The total concentration of -dissolved 'or entrained ncble gases (UCi/ml)
=
C 3 The Sr-89-and Sr-90 concentrations (uCi/ml)
=
.Ct- TheH-3 concentration (UCi/ml).
C, p
= The Fe-55 concentration (pCi/mi)
MPC = 4 MPC,, MPC b ....., MPC , nMPC , a MPC ,GMPC ,3MPC ,.MPCFe t
=l the m6ximum permissible concentration-of the ~ respective radio-
' isotope i-(pCi/ml) from-10CFR20, Appendix B, Table 11 Column 2.--
For dissolved or entrained noble' gases. the maximum allowable will be ~ 2.00E (uC1/ml). For. gross concentration: alpha, the :: ' assu (MPC@)ed will be 3.00E-08 (pCi/mi). 4 If1 the: C/MPC calculated- is- se than - 1, then no release is possible. The normalization factor-(as definea in Section 2.1.1) must be greater than 1 to permit-releases. JTo permit releases, this factor can be increased to-a value greater;than-
- 1~ by ; increasing _ dilution flow F pumps in the. applicable 1dischartructure),-- f s.(by _ running more_ circulating or service flow water-
- and/or decreasing the effluent
- rates f , . f , f f defined in Section 2.1.1), -and recalculate C/MPC
-using-nbC S in h,atik.- 2.1-1. etc.
4 O BN1-11600.02 11.2.1-3 , Revision 8 - February 1986 l
SNPS-1 00CM 2.1.1 Radiation Ef fluent Monitor (RE-13) High/ Trip Alarm Set Point for Discharle Waste Sample Tanks, Recovery Sample Tanks, or YARD Fiping Drain Sump 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 tenninate the release. A sample is taken from any of the following tanks or sump which is to be discharged along with any ctreams which are in the process of being discharged.
- 1. Discharge waste tanks
- 2. Recovery sample tanks
- 3. v ard piping drain sump
- 4. Reactor building salt water drain tank
- 5. Residual heat removal nut exchanger service water Only one of the first three items above is discharged at any one time, which can be combined with releases from item 4 and/or 5.
I Obtain the circulating or service water flow rate from the control room (see NOTE in Section 2.1). Define Normalizing factor [fD*IHA + IHB + s
+ (F c ~
HA ' IHB)) g
*0.8 (C Di ID f f
+ C gjg HA + C HiB HB + C 3$ 3)
I E~ MPC 3 i An isotopic analysis of each sample is performed. This analysis includes isotopic analysis for gamma emitters; gross alpha emitters; total dissolved or entrained noble gases; and Sr-89, Sr-90, Fe-55, and H-3. This should be done for all moni-tors. 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 con-sidered as zero) for detector RE-13 is calculated as: N (cpm) S 13 3 F* I C 0i *E 4 i=1 ( BN1-11600.02-92 11.2.1-4 Revision 8 - February 1986
l SNPS-1 ODCM where: C = concentration of radioisotope (i) (nCi/ml) in any of the following tanks Di or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump f = Discharge flow rate (gpm) from any of the following tanks or sunip that is D
to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump.
(Maximum design discharge flow rate = 150 gpm) C = Reautor building salt water drain tank concentration of radioisotope (i) 34 (uCi/ml) CHIA = RHR heat exchanger service water outlet concentration of radioisotope (i) (UCi/ml) from loop A. RHR heat exchanger service water outlet concentration of radioisotope (i) CHiB = (pCi/ml) from loop B. em f3 = Reactor building salt water drain tank discharge flow rate (gpm). (Maximum design discharge flow rate = 100 gpm) f HA
= RHR heat exchanger service water outlet discharge flow rate (gpm) from loop A (Maximum design discharge flow rate = 9340 gpm) f HB
= RHR heat exchanger service water outlet discharge flow rate (gpm) from loop B (Maximum design discharge flow rate 9340 gpm)
F C
=
Total circulating or service water flow rate (gpm) (this includes FHA and fHB) E 4
= Gamma counting efficiency of RE-13 for radionuclide (i) (cpm /uCi/ml).
Figure 2.1-1 shows the energy response. For non-gamma emitters, E4=0. 0.8 = Safety factor MPC is defined in Section 2.1. The above calculation is made for each batch to be i 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 i advertent release cccur. I BN1-11600-02-92 11.2.1-5 - Revision 8 - February 1986 l
SNPS-1 ODCM 2.1,2 Radiation Effluent Monitor (RE-79) High Alarm Set Point for Reactor Building Sait 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 seit 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 st;n p
- 4. Residual heat removal heat exchanger service water In the case of continuous release, samples will be taken as per requirement REC Table 4.11.1.1.1-1.
t Obtain the circulating or 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: L$3 ,1 C33Eg] (cpm) 579 _ F* where: Eg= Gamma counting efficiency of RE-79 for radionuclide i (cpm /pCi/ml). Figure 2.1-2 shows the energy response. For non-gamma emitters, E$=0 All other parameters are as defined in Section 2.1.1. When the tank operates in a batch mode, ti'e aueve calculation is made for each batch to be released. Af ter each batch release or continuous release teriod, 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 II.2.1-6 Revision 16 - July 1990
_ . . _ _ . . . ~ _ _ _ . . _. m SNPS-1 00CM 2 .1". 3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A, RE-23B) High Alarm Set Points ' The function of this ronitor set point is to ensure'that the sum =of the ratios of the discharge concentrations to the MPCs of the corresponding tadionuclides 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. Monitors .RE-23A and -RE-238 are independent. Each is dedicated to monitor its respective RHR loop. A sample will; be taken from the RHR heat exchange service water outlet (A and/or B).- along with individual samples of any of the following streams which may be in , the process.of-be.ing discharged:
- 1. Discharge waste sample-tanks
- 2. Recovery sample tanks .
3 '. - Yard piping drain' sump
- 4. Reactor building salt water drain. tank discharge Obtaint the circulating or service water flow rate from the control room (see NOTE 1 in Section 2.1).
The' set-points for RE-23A'and RE-23B are calculated as follows: N-S23A < F * [j{3 Cgjg E4 j) N S 23B I 11 gggC EiB) swhere:: E = ' iA Gamaicounting Figure 2.1-2 shows efficiency
-the gama energy of RE-23AL response.for For radionuclide-i non-gama emit- . (cpm /
=_0-ters -EiA ,
J
=
E iB Gama. counting efficiency Figure 2.1-2'showsithe gama energy- of RE-238 response.forFor radionuclide non-gamma emit-. 1 (' cpm ters, EiB =10 Al_1 other parameters -are as defined in Section.2.1. BN1-11600.02-92 11.2.1-7 . Revision 13 - November 1988
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+ nortmlized to 1 Ji noton/disintegrat_im DFFSITE DOSE CALCULATION MANUAL e e Revision 14 - Janu 1089
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- FICURE 2.1-2 SOURCE:
l I C-RPD-490, Rev. O vtau;1uG RE-23A, RE-23B ard RE 79 RETCrG VS. GtMM DERGY SFORENAM NUCLEAR POWER STATION-UNIT 1
+ nor1Talized to 1 photon /disinttv; ration OFFSITE DOSE CALCULATION MANUAL Revision 14 - January 1989
SNPS-1 00CM 2.2 GASE0US EFFLUENT MONITOR SET POINTS (Compliance with Section 3.11.2.1 of the RFC) l 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: Less than or equel to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. The set point for this monitor will be determined based on the lower 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. The high alarm set points for the Main Condenser Offgas System Effluent Monitors (RE-65A, B) is based on the MPC limit specified in 10CFR20 Appendix B, Table II, Column 1 which is in conformance with the dose rate limits specified above. The high alarm set point for the Main Condenser Air Ejector Monitor (RE-12A, B) in normal operation is based on the REC limited total noble gas (beta and gama) release rate at the main condenser air ejector, which is 244,000 ECi/sec at 30 minutes delay. The high alarm set point for the Main Condenser Air Ejector Efflu-ent Monitors in the bypass mode (RE-12A, B in the bypass mode) are based on 25 percent of the limit specified above. I~ For all the above monitors, the initial set points are based or expected release rates (Ci/ year) for radionuclides given in the Safety Evaluatic Report (SER) for l Shoreham (NUREG-420, April 1981, Table 11-2). An effective initial concentration, C (pC1/cc) for each radionuclide, i, is obtained from the release rate, Q,(Ci/yr) fdr the radionuclide and the appropriate flow rate V(cc/se:) as follows: l i C 4 (pCi/cc) = 9 1 (Ci/yr)
- 10 12(h)
- 1 1 7 3.15
- 10 Isec) yr Y(cc sic )
When the mechanical vacuum pump is in operation, the release rate Q mechanical vacuum pump exhaust will be cused assuming that the medOn(ical vacuumCi/yr pump operates for 100 hours or 3.6 x 10" seconds per year. The effective initial concentration C l in operation, id c(alculated as:pCi/cc) for radionuclide, i, when the mechanical vacuu 1 C $ (pCi/cc) = gim (Ci/yr)
- 10 12(h)
- 1 5
3.6
- 10 Isec) yr YIcc sec )
Once operation has begun, the concentration, C obtair,ed as the measured value from a grab sampid., for each radionuclide, will be l BN1-11600.02-92 11.2.2-1 Revision 16 - July 1990
SNPS-1 ODCM O 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 or 2.2-4 will be made. 2,2.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) 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
- 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic r.omposition and concentration, C4. Before startup.
C$ will be calculated as noted in Section 2.2.
- 2. At the time of sampling, the net count rate (excluding background), CR (cpt ), of the Station Ventilation Exhaust Noble Gas Radiation Monitor will be recorded. Before startup, the estimated CR is calculated as:
CR = 10'0 * ( ,) C4 *E4 ) (cpm) l where: E 4
= detector efficiency (cpm /pC1/cc) for RE-42 for radio-nuclide, i, as provided in Figure 2.2-1. The linearity response for RE-42 is shown in Figure 2.2-2.
- 3. .The noble gas total body dose rate is calculated using the following equation:
= (mrem /yr)'
f DR$ X/Q*V*(f0FB*C) j 4 where: DR
= predicted dose rate based on gas sample for isotope i (mrem /yr),
x/Q = annual average X/Q (sec/m3) at 366 meters NNE due to releases via the station ventilation exhaust point (6.6E-07'sec/m3), DFBj= total body dose rate conversion factor (mrem /yr/pCi/m3), from Table 2.2-1, C 4
= sampled isotope release concentration (pCi/cc),
V = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate = 1.73E*08 cc/sec (3.66E+05 cfm).) i k l i BN1-11600.02-92 11.2.2-2 . Revision 3 - December 1983
SNPS-1 ODCM g 4 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 B 500/fDRg
- 5. From the above, the set point (see NOTE in Section 2.1.1) based on total body dose rate can be calculated as follows:
8
$ 42j0.8*FB
- CR (cpm) where:
0 5 2
= high alarm set point that results in a total body dose rate of less than 500 mrem /yr, F
g
= normalization factor (unitiess),
CR = station ventilation exhaust noble gas radiation monitor count rate (cpm), and 0.8 = safety factor. The above procedure and format will be used to calculate the set point for RE-4 when the mechanical vacuum pump is in operation or during containment purge. Under I these conditions, the short term atmospheric dispersion factor at 366 meters NNE (3.60E-06 sec/m3) shall be used instead of the annual average value. 2.2.1.2 Gaseous Effluent Monitor Hich Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate
- 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C 4
. Before startup, C4 will be calculated as noted in Section 2.2.
- 2. At the time of sampling, the net count rate (excluding background), CR (cpm), of the station ventilation exhaust noble gas radiation monitor will be recorded. Before startup, CR is calculated as noted in Section 2.2.1,
- 3. The noble gases beta and ye.,c..ia skin dose rate is calculated using the i following equation: !
E (mrem /yr) X/Q
- V *8 (f Kdm *C)
DR = 4 $ $ where: DR
= predicted dose rate based on ga:, sample for isotope i l (mrem /yr),
BN1-11600.02-92 II.2.2-3 Revision 3 - December 1983 l l
.a i
LSNPS-1 ODCM'- , X/Q ' = annual average X/Q (sec/m8):at 366 meters NNE due to releases t via the station ventilation exhaust point,L(6.6E-07 sec/m3)' , K,4,= skin- dose rate conversion factu (mrem /yr/pCi/m3). from Tat ie 2.2-1, C-j a sampled isotope release concentration (pci/cc), F
~
V = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate =1.73E+08_cc/sec(3.66E+05cfm).) ,
;4.- The isotopic release! activity concentration is normalized to a skin- dose -
rate of 3000 mrem /yr by multiplying by the following normalizing factor: , F3=3000/fDR4
- 5. Fromtheabove,thealarmsetpoint(seeNOTEin-SectionL2.1.1),basedon skin dose rate can be-calculated as follows:
(cpm) Sf2 J 0.8
- F3 '* CR where:
b S42 = ,high alarm. set point that results- in: a skin dose rate of O(_f .less than 3000'mrom/yr (cpm), F 3-
=. normalization. factor _'(unitiess),
CR a- station ventilation-: exhaust - noble _ gas radiation monitor _ l count _ rate (cpm),:and ;
-08 = ~ safety, factor. ~i The; above ~ procedure and format will- be used to calculate- the -. set?pointJ for RE-42
. when the mechanical-' vacuum pump is inL operation or durir(containment! purge. Under these conditions, the short term atmospheric dispersior, factor'_ at 366 meter: NNE:
_(3.60E-06sec/m3)shallbe:usedinstead.of:theannual.averagevalue, il 12.2.2 Main Condenser Offgas System Effluent Monitors (RE-65A,B) High Alarm 5et Point LThe Main Condenser Offgas System Effluent Monitorthas two chambers (65A, 65B) in series. Each chamber' constitutes a separate -independent output channel ~containing-
.a detector 1 composed of 13 GM tubes whose output is- summed. The monitor : set ooint.
will:be based on a release rate which results in 0.1 MPC at_ the site boundary. The
- set point calculated shall be-divided by a factor of 3 to account for the case when-
- only one-GM tube per chamber .is functional.
L V BN1-11600.02-92 II.2.2-4 Revision 3 - December 1983
, , , . . , ,, , . . . - . _ _ ~ . .~.-- , . - _ - - . .- - -
SNPS-1 ODCM
- 1. During operation, a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C'. $
Before startup, C4 will be calculated as noted in Section 2.2.
- 2. At the time of sampling, the net count rate (excluding background), CR (cpm), of the monitor will be recorded. Before startup, the estimated count rate CR (cpm) due to concentration, C 4
, is calculated as:
N (cpm) CR=10-6*($[3 C4 *E) 4 where: E = detector efficiency (cpm /pCi/cc) for '.E-65A,B for radio-4 nuclide, 1, as provided in Figure 2.2-3. The generic linearity response for RE-65A,B is shown in Figure 2.2-4
- 3. The sum of the ratios of the released isotopic concentrations to MPC is normalized to 0.1 at the site boundary by multiplying by the following factor:
0 F=
, c.'l Y
(iul )* V
- X/Q
- 3.0 MPc; where:
V = Main condenser offgas system ventilation flow rate (m3/sec) (Maximum flow rate = 1.18E-02 m3/sec (25 cfm) . ) X/Q = annual average meteorological dispersion factor at 366 meters hNE (6.6E-07 sec/m)) due to releases via the station ventilation exhaust point. 3.0 = Safety factor in case of 2 out of 3 GM tube failures.
- 4. From the above, the high alarm set point for RE-65A,B (see NOTE in Section 2.1.1) is calculated as follows:
(cpm) 565 < 0.8
- F
- CR 2.2.3 Main Condenser Air Ejector Monitors (RE-12A,B) High Alarm Set Point for Non-Bypass Mode Operation (Normal Oneration)
The Main Condenser Air Ejector Monitor System has two detectors looking at one chamber. The alarm will be set off by a signal from either detector. O BN1-11600.02-92 11.2.2-5 Revision 3 - December 1983
, _ _ . .-- . .~ .. . - = - - -. - . . _. _ - .
SNPS-1 ODCM 2.2.3.1 Initial Set Point for RE-12A,8 Non-bypass More Operation
- 1. Decay the t=0 GE noble gas spectrum for off-gas system release rate prior to treatment (GE document 22A2703B Rev. 3, Table V) for 201 seconds. l Scale it to the Shoreham REC (3.11.2.7) limit of 244,000 pCi/sec at 30 minutes decay by multiplying by 2.44. Divide it by the desuperheater condenser exhaust maximum flow rate (4.8E+04 cc/sec) to obtain the limiting concentrations C4 (UCi/cc) of each radioisotope 1.
- 2. Using the isotopic concentrations C 4 (ICi/cc), defined above and the effective gamma energy per disintegration, E (MeV/ dis) calculate the specific gamma activity, A MeV the following gamma ray bins: erNr(gy /cc-sec),
0-0.4, 0.4-0.8, 0.8-1.3,for1,3-he1.i-th 7, isoto 1.7-2.2, 2.2-2.5, and 2.5-3.5 (MeV). Thus: A4g=K* Egg *C j where E 3 g is the total gama energy (MeV) emitted per disintegration of the i-tn isotope by gamma rays be1onging 4 to the t-th energy bin defined above. The factor K = 3.7 x 10 (dis /sec/pci) is introduced for unit conversion, q The total specific gamma activity, At (MeV/cc-sec), for each gamma energy Q bin, t, is calculated by summing the specific gama activity, A 4g, for bin E, over all isotopes. N A t=4{1 Ag 4
- 3. Using the response curve for RE-12A,B given in Figure 2.2-5, calculate the dose rate. The generic linearity response curve for RE-12A B is shown in Figure 2.2-6.
7 DR = g[3 CFt
- Ag -(mrem /hr) where:
CFt is the efficiency ( mrem /hr
) at the L-th energy group (MeV) MeV/cc-sec
- 4. The high alarm set point (see NOTE in Section 2.1.1, but note the back-ground unit is in mrem /hr) for RE-12A,B in the non-bypass mode will be:
S < 0.8
- DR 12 (mrem /hr)
?
BN1-11600.02-92 11.2.2-6 Revision 6 - August 1985 l _
SNPS-1 ODCM 2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-Bypass Mode Operation
- 1. During operation, a gaseous sample from the monitor will be taken and analyzed for noble gases isotopic composition and concentration, C (uC1/cc). The concentrations should be corrected for elapsed decay tide, between sampling and measurement. In addition, computed concentrations should be obtained for short lived isotopes. Before startup, C will be 4
calculated as noted in Section 2.2.
- 2. At the time of sampling, the net dose rate reading (excluding background) of the monitor will be recorded, DR (mrem /hr).
- 3. The isotopic release activity concentrations, C , are sumed and multi-plied by the desuperheater condenser exhaust ffow rate, V (cc/sec)* to l obtain the noble gas release rate in VCi/sec.
4 The release rate in step 3 is normalized to the REC Section 3.11.2.7 release limit of 2.44E+05 UCi/sec at t=30 minutes as follows: y , 2.44E+05 (IC4 )
- V i
- 5. From above, the high alarm set point (see NOTE in Section 2.1.1, but note l the background is in mrem /hr) based on a release rate of 2.a4E+05 uCi/sec at t=30 minutes can be calculated as follows:
5 1 0.8
- F
- DR (mrem /hr) 12 2.2.4 Main Condenser Air Ejector Monitor (RE-12A,B) High Alarm Set Point for Bypass Modelperation 2.2.4.1 Initial Set Point for RE-12A,B in Bypass Mode Operation
- 1. Same as steps 1, 2, and 3 in Section 2.2.3.1. However, set the desuper-heater condenser exhaust maximum flow rate to 5.3E+05 cc/sec.
- 2. The offsite total body dose rate D corresponding T
to the above concentra-tion is calculated as: D = T 10+6
- X/Q
- V * ({ DFB *C) 4 4 and the beta and gamma skin dose rate is calculated as:
10+6
- X/Q
- V *sim([ *C)
D = s K 4
- Note: If flow rate increases, the setpoint must be recalculated. If the flow rate decreases, recalculation of setpoint is optional.
BN1-11600.02-92 11.2.2-7 Revision 6 - August 1985
. .- . - . . . . - .. - --.. -. ~-- - - . - . - . . . . . - . . - . - ..-. .
SNPSJ1 00CM' where: D'T
= predicted-total body dose rate..(mrem /yr);
D = predicted beta and gama skin dose rate (mrem /yr) 3 , X /Q = - annust averaoo atmospheric dispersion factor at '366 meters NNE- (6.6E-07= sec/m3) : due 'to releases -via the station-ventilation exhaust point V = desuperheater condenser maximum exhaust flow rate (cc/sec) ~
='
- 5.3E+05 cc/see DFBj' = ' total body dose rate conversion factor (mremhr)i from
- Table 2.2 pCi/m3-g skin dose rate conversion factor (mrem /yr) from Table
'KSI" =: - 2.2 pCi/m3 3.- The : normalizing factor F is chosen to be.' the smaller -of- th'e two (to-comply with 25 percent;of the REC (3.11;2.1) . dose rate-limit): J p . ,-
125 mrem /yr' T v T p_ ,, 750-mrem /yr S 0 s
~
F: a: the smaller of FT or F3 (unitiess)
- 4i _ The high alarm-set: point (see NOTE in Section 2.1.1., but note the' back-
? ground-is ,in -mrem /hr) RE-12A,B -in bypass -mode Lis set at: ,
t 12 0.8* F
- DR-(mrem /hr) 2.2;4.2 Subsequent Adjustments o'f- Set Points for RE-12A,B in- Bypass Mode -
Operations 1.. A gaseous sample from the monitor will be taken and analyzed for, isotopic;
-composition and concentration, Cj -(UCi/cc)
~
- 2. - At the time of_ sampling. the net dose rate reading,-DR (mrem /hr), of the 4
monitor will be recorded. . 3. Follow- procedures 2, :3, and 4 of Section 2' 2.4.1- to get the' high alarm set point for RE-12A,B in bypass' mode. BN1-11600,02-92 II.2.2-8 - Revision 16 - July 1990 6
,--m- .g y ip - g , y,i, .- w s%. y r r --a w
SNPS-1 ODCM TABLE 2.2-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES K. } Ksim
. (5) . si nu e B-Air ( ) (DFbg ) B-SkinI2) (DFSg ) Y-Air I (DF ) Y-Body (2) (DFBg ) Skin Dose (2) Skin 90se(2)
Kr-83m 2.88E-04(3) --- 1.93E-05 7.56E- 08 1.5E-05 2.1E-05 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E- 03 2.4E-03 2.8E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E- 05 1.4E-03 1.4E-03 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E- 03 1.5E-02 1.7E-02 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E- 02 1.4E-02 1.9E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E- 02 2.4E-02 2.9E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E- 02 2.0E-02 2.5E-02 Xe-131m 1.11E-03 4.76E-04 1.56E-04 9.15E- 05 6.0E-04 6.5E-04 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E- 04 1.2E-03 1.43-03 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E- 04 5.8E-04 7.0E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E- 03 3.3E-03 4.4E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E- 03 3.4E-03 4.0E-03
~
Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E- 03 1.3E-02 1.4E-02 BN1-11600.02-93 1 of 2 Revision 10 - August 1987 O O O
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SNPS-1 ODCM-(J
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TABEE 2.2-1_(CO'IT'D) Ksi(4) Ksim
- (5) ,
1 de 8-AirIII (DFbg ) B-Skin (2) (DF59 ) Y-AirII) (DF ) Y-Body fDFBy ) Skin Dose ( ) Skin Dose ( } Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E- 03 1.1E-02 1.4E-02 Ar-41 3.28E 2.69E-03 9.30E-03 8.84E- 03 9.9E-03 1.3E-02 (1) mead-m3 pCi-yr (2) mrem-m 3 pCi-yr (3) 2.88E-04 = 2.88
- 10-4 (4) K si = (0.7
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- EBERt.INE INST, CORP - Cat,4R ATION OF (8f4LINE EXTERNAA PRQat Qas.5
=<== lDC AL CURVg C AllSM ATION CAff. 02/22/45 e ACTUAL DATA flGURE 2.2 6 i GENERIC LINE ARITY CURVE
\ FOR DETECTORS RE 12 A,0 SHOCEHAM NUCLE AR POWER STATION-UNIT I Off SITE OCSE CALCULATION WANU AL REVill0W 7 OCT 4ISIS
SNkS-1 0DCM PART 11 SECTION 3 . DOSE CALCULATION METHODS , ) This section presents the calculational specifics required to demonstrate compli- :4 chce with the follnwing Radiological Effluent (catrols (REC, Part I of the ODCM) sections: a 3.11.1.2 - Liquid Effluent Dcse Calculation d
/
311.1.3 - Operation of Liquid Radwaste Treatment System 3.11.2.1 - Gaseous Effluent Dose Rate I 3.11.2.2 - heble Gas Air Dose l 3.11.2.3 - Gaseous Effluent Cose From R.*deiodines, Tritium, A.( Padionuclides in Particulate corm 3.11.2.5 - t ceration of Ventilation Exhaugt Trestre! Systn , Calculation methods are based on the equation and calculational methon describe in Regulatory Guide 1.109, "Celculation of Annual Doses to Man from Routine Re least s of Remtor Effluents for the Purpose of Evaiubting Ctmoliance with 10CFR50, Appendix !. Two methods at3 provided for each Analysis. The first method is the method used by the cmputer; zed radiation nonitocir6 System. Method 2 is a backup hand calcula-tictul method to be used oniy if the computer is not functionol. Ihs Semi-Annual Effluent Release Report is produced and the land use census is evalua:ed.using NRC codes which implement Regulat.ory Guide 1.109. O BN1-11600.02 9? !!.3.0-b Revision 16 - July 1990 1
$NPS-1 ODCM
( 3.1 LIQU!O EFFLUENT, DOSE CALCUL8, TION To comply with Section 3.11.1.2 of the REC, the liquid e"#1uents released to unrestricted areas shall be limited:
- 1. During any calencar Quarter to less than or equal to 1.5 mren to the total body and to less than or equal to 5 mrem to any orgen.
- 2. During any calendar year to less than or equal to 3 mrem to the total body and to Ins than ur equal to 10 mrem to any organ.
The site boundary for liquid effluents is shown in Figure 3.1-1. The liquid radweste system model is shown in Figure 3.1-2. 3.1.1 Method 1: (Computerited Pethod) The 64uations which follow are used by the computer software t- calculate the offsite Joses 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 numoer of circulating 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: p) V Og = 3.785 x 10'3 ' og where: Og =- total inventory of isotope i in the liquid to be released (Ci) a concentration of isotope i in the liquid to be discharged (as q, treasured in laboratory) (UCi/cc) V = volume of liquid to be discharged (gallons) 3.785 x 104 = [(Ci/pci) (cc/ gal)] The dose equations which follow are from Regulatory Guide 1.109, with minor modif-ications. They are employed for the computation of dose from any single batch discharge (contir.uous discharges are handled as batch discharges in the com-puterized method). Weekly and quarterly cumulative doses are also calculated and stored in data files for reporting. (a) Organ Dose Oue to Incestlet ?,f Salt }later Fish R g fish = 0.389 U 5(1/K)I S DFI
-24 i for cire, water g Qg B e p
part+1 lja 5 R g fish
- 57.4/(K2 + 0.930 K3) V a Oi 6 DFl Qq ija* I
/ \ for service water V
BN1-11600.02-92 !!.3.1-1 Revision 16 - July 1990 j
SNPS 1 ODCM R ing fish ja = dose to organ j of individual in age group 'a due to ingestion of fish contaminated with particulates and radiciodines (mrem) (Ref. Reg. Guide 1.109, with the following special values:
- F (flow rate of liquid effluent) is represented by product K *F f t8/sec), where K is the number of pumps of 59stemM*8 D sir [atingandF Tstheflowrateperunit pump. Forthecirculati8%aTersystem,m=1;forthereactor building service water system, m=2; for the turbine building
, service water systs,m m=3 1.435x10 gpm)=319.7[ft3/sec)
- F "*P ' l == 8,600, g un = 19.16 ;ft3/sec
*FP
' fpump.2 = 8,000 gpm = '7.8 ,ft8/sec
- M @iking ratio at the point of exposure) = 0.113 = (1/8.85) i circulating water is in use;
= 1.0 if service water is in use.
*D a (see below)
' t $ ra(dose ns
= 24 [hr)factor) = DFleEposure)it (see pg 1.109-12 time require of the Regulatory Guide)
V fb = fish consumption rate by individual in age group a [kg/yr) (from Table E-5 of the Guide, for maximum individual)
, K, = number of pumps of system m operating 1 Og = total activity of isotope i released [Ci), from above
= Bioaccumulation factor for saltwater fish [(pC1/kg)/ ;
(pCi/ liter))(fromTableA-1oftheGuide) DFI 4ja
= 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 g a radionuclidedecaycunstant[hr~1)(fromTable3.1-1) 0.389 = 1100 Mp/F pump,1 e 1100x0.113/319.7[(pCi/t)/(Ci/yr))for cire water 57.4 = 1100/F pump,2 = 1100/19.16[(pCi/t)/(Ci/yr))forreactor building service water 0.930 pump.3/Fpump,2
= F part+1 = 68 particulates and 5 iodines in the summation sign (b) Organ Dose Due to ingestion of Salt Water Invertebrate 9I" 0.389Vf"p(1/K)I V
Q4 B "V p DFl ija R = e i for cire, water g R 9 I"Y = V 57.4/(K2+0.930K)(P 3 art +1 P 08 for service water BN1-11600.02-92 11.3.1-2 Revision 8 - February 1986 4 .. .
A d SNPS-1-ODCM where: R 9 I"*
- dose to organ j of individual in age group a due to the ingestion of saltwater invertebrate contaminated with 1 radioactive particulates and : iodines [ mrem] (Ref.: Reg.
Guide 1.109 Eq. A-3 with the special values identified in the fish ingestion equation above) I#- BI "P
=
Bioaccumulation factor for saltwater invertebrate * [(pCi/kg)/(pCi/ liter)) (from Table A-1 of the Guide) Vf"Y p
= _ invertebrate consumption rate by individual in age group _a
[kg/yr) (from Table E-5 of the Guide, for maximum ' individual) (c) Total Body Dose From Shoreline Deposits l R -e = 0.561 Ushore(1/K) p I 03 0FGg ) (i.e-tb q for cire, water part+1 < 4
-t ore
= 82.9/(K2+0.930K)Ufp 3 I Q4 0FG4 ) (1 eA b i) service water ,
part+1 4 where: R$ ,aore
.= total body dose to individual in age group a from shoreline de- !
O posits (nirem] (Ref.: Reg. Guide 1.109 Eq. A-7 with the follow. in special values:
*g(flowrateofliquideffluent)isrepresentedbythe F
L product K *F' g i operatingpuE$P7s[ystemmandFft8/sec),whereK 6 m is the flow rate is per tu number pump.m , unit pump for the circulating water system, m=1; for the reactor build. ing service water system, m=2; for the turbine building service water system
*F 1.435 x 10 5*[g*3pm]=319.7[ft8/sec)
*F PU*P I = 8,600 ;gpm] = 19.16 ft3/sec5
'Mpu7ggjingratio}gpm;=17.82,;ft8/sec)Fpum = 0.113 if cire, water is in use P
= 1.0 if service water is in use
'W(shore-width-factorthatdescribesthegeometryofthe
-- exposure) = 0.5 for ocean site (from Table A-2 of the
- guide). .
t (transit time from source to shoreline) = 0'(see Reg. G81depg1.109-69, for Eq._A-7) . 0.693/(24Aq ) wh re
*: 0.693T4 (radionuclide
- 109 2 and Ag _ half life, days) =is the decay constant in '[
- D,qp3 = _DFG,4) (seebelow)
= shoreline exposure time for individual in age group a [hr/yr] ,
(from' Table E 5 of the Guide, for maximum individual) O BN1-11600.92 11.3.1-3 ' Revision 8 - February 1986 y ,+-w- ,- - rw-+W T'**- *Y' 7 71 #T=-*-r'"'J'"'t**"*'-d-"*'"*F---- '"
*-+r'*E'-t'-*'rv-*"-- 't"i**f "-#N"Y'f--*"*--'"~-'Yr'tw-8'v"v'r"*' "'"'"'W"fw'-*Y -t' 8"'- # 'ev revv e v= w- vw' e-**F*w wt-+-e-D
SNPS 1 ODCM ' K = number of pumps of system m operating m Q 4
- totalactivityofisotopeireleased[C1),fromabove DFG 3 )
= total body conversion factor for standing on contaminated ground (shore) [(mrem /hr)/(pC1/mt)) (f rom Table E 6 of the guide) tb =
tin periog over which accumulation is evaluated (15 years, or
- 1. 14 x 10 hours) 0.561 =
110,000 M p W (T 44A )/ Fpump.1[(pCi/1)/(Ci/yr))
= 110,000 x 0.113 x 0.5 x (0.693/24)/ 319.7 for cire, water 82.9 =
110,000W 4(7 xj) Fppp.2[(pCi/t)/(C1/yr))
=
110,000 x 0.5 x (0.693/24)/19.16 for reactor building aervice water 0.930 = F pump.3/Fpump,2 part+1 = 68 particulates and 5 iodines in the sunrnation sign (d) Skin Dose From Shoreline Deposits shore ~t A t R = 0.561 Ushore (1/K ) I Q DFGg p _-e 1 b 1) for cire, water part+1 A g
=
82.9/(K 2+0.930K)(p"l' 3 pa r;;+ 1 Q DFGi2 (1-e bi g 1
,4 for service water where:
shoce R skin,a
= skin dose to individual in age group a from shoreline deposits
[ mrem);(Ref.: Reg. Guide 1.109 Eq. A-7 with the $5ecial values listed for the total body dose) DFG i2
= skin dose conversion factor for standing on '..c',aminated ground (shore) [(mrem /hr)/(pC1/mt)) (from Table E-6 0/ 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 surrned in the following way for the computation of total doses: g , ning inv ja 3aning fish , 3a p , shore wb a hb.aingfish,hb.ainginy,hbsa p , p sbore skin,a skin.6 BN1-11600-92 11.3.1 4 Revision 8 - February 1986
$NpS 1 ODCM where:
R ja
=
total dose to organ j (exclusive of the total body) of individ-ual in age group a due to the ingestion of fish and invert- I ebrate(mrem) R 4'3
=
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 skin,a
= total dose to the skin of an individual in age group a from j shoreline deposits (Frem). !
i 3.1.2 Method 2: (Backup Method) l 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:
$ C4 gFt ]
07=3,3-Bg7g[3 ott (3.1 1) where: Dr = the cumulative dose or dose commitment to the total body or an organ A from the liquid effluents for the total release period gg 6t g (mrem), 4tg = the' length of the Ath release period 'over which C 4g and F g are averaged for all liquid released. (minutes). C gg a the avtrage concentration of radionuclide C i in undiluted liquid effluent during release period att fromanyliquidrelease(pCi/cc). A g7 = the' site-related ingestion ' dose or dose commitment factor to the-total body or any organ for each identified principal gamma and beta , emitter listed in Table 3.1-2 (mrem / min per pCi/cc), see Appendix A for derivation
= Undiluted liquid effluent flow rate Ft Fe/Mp F
c
= total circulating water flow rate with the number of circulating pumps in use
= total service water flow rate if the circulat'ng water is not in use HP (Mixing factor) = 0.113 if circulating wat+r is in use;
= 1.0 if service water only ic 4. use L BN1-11600-92 11.3.1-5 Revision 8 - February 1986
SNPS-1 ODCM The total dose from liquid effluents from all discharges Diotal' 15 O' Diotal
- UtD + 0,p + Dtg + D7 3 + D, p l where:
D = Dose contribution from discharge waste sample tanks as calculated in TD Equation 3.1-1 j 1 D TR
= Dose contribution from recovery sample tanks as calculated in I Equation 3.1-1 I l
0 7g = Pose contribution from RHR heat exchanger, service water as calculated in Equation 3.1-1 0,7'
= Dose contribution from reactor building salt water drain tank as calculated in Equation 3.1-1 D
7p
= 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 l REC Section 3.11.1.2. l < O O BN1-116DD.02-92 11.3.1-6 - Revision 16 - July 1990
1 i SNPS-1 ODCM TABLE 3.1-1 DECAYCONSTANTS(1/hr) ' l Radio- Radio- l nuclide Constant nuclide Constant i H-3 6.408E-06 Ru-103 7.300E-04 i' 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 i Mn-56 2.700E-01 Te-127 7.400E-02 . Fe-55 2.930E-05 Te-129m 8.600E-04 Fe-59 6.480E-04 Te-129 5.900E-01 Co-58 4.068E-04 Te-131m 2.300E-02 Co-60 1.501E-05 Te-131 1.700E+00 Ni-63 8.600E-07 Te-132- 8.900E-03 hi-65 2.700E-01 1-130 5.600E-02 Cu-64 5.400E-02 1-131- 3.593E-03
.Zn-65 1.184E-04 1-132 3.000E-01 Zn-69 7.296E-01 1-133 3.334E-02 Br-83 2.900E-01 1-134 7.900E 01 ,- Br-84 1.300E+00 1-135 1.100E-01
(]- Br-85 Rb-86 1.449E+01 1.500E-03 Cs-134 Cs-136 3.852E-05 2.203E-03 Rb-88 2.400E+00 Cs-137 2.635E-06 Rb-89 2.700E+00 Cs-138 1.300E+00 Sr-89 5.724E-04 Ba-139 5.000E-01 Sr-90 2.776E-06 Ba-140 2.257E-03 Sr-91 7.300E 02 Ba-141 2.300E+00 Sr-92 2.600E-01 Ba-142 3.900E+00 Y-90 1.100E-02 La-140 1.700E-02 Y-91m 8.300E-01 La-142 4.500E-01 Y-91 4.900E-04 Ce-141 8.892E-04 Y-92 2.00E-01 Ce-143 2.100E-02. Y 6.800E Ce-144 1.019E-04
'Zr-95 4.392E-04 Pr-143 2.100E-03 Zr-97 4.100E-02 Pr-144 2.400E+00 Nb-95 8.200E-04 Nd-147 2.600E-03 Mo-99 1.000E-02 W-187 2.900E-02 Tc=99m 1.200E-01 Np-239 1.200E-02 Tc-101 2.900E+00 O
BN1-11600-112 1 of 1 - Revision 3 - December 1983
m M M N M et M N M N et N N e=4 N M M e==8 @ OMMONNNNONN 00 e=e C00000000000000000 OOOOOOMOCOO m
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6
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e qp L3 et et M N M N M M M *=e N m M M 0*> m ett M *=4 m m e-4 N 03 Ln CO M M N
.Q b
V (P O I MM M e.e NN M s OO C O OO 4 + t e ++ C bi WW W W W hJ O C @N O N N@ a r*
- s e e e e e e gn J et et i N IM i i M CD 1 1 4 4 1 e i i t I l I i e t 6 1 i t i **
0
> /
e C
**= ~2
*C Z
* =% M *=e M NMM OMC *=*
^ Ca. A OO O OOO OOO O e* 0 e+ a e+ t + + + 8 w Z C kJ LJ Ld kJ W LJ L.J W W La J A O t. @N m o et m *1 @ M M Cz: . e e e e e e e e e e e O H M 92 et i N 1NMmI I 4 e i i NmN I t i I I e t I e i I I e-g F-= W^
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- M N M m N CC M c=e N @ N N ** M N e=8 N tt N Ln e=e LA N N M N e-o e EC CL Q
W MM M tt N M N M O M M ett *=e M C O N 00 OO OCOOOOOOC.JOO O O L. + 4 + t + , 4 ++ e e++ + # 0 kJ Ld W Ld kJ LU W W kJ kl W kJ kJ kJ Ld LJ LM
> @N m@ N @ CO *=e CO CO @ N @ ** M CQ M
== e e e e e e e e e e e e e e e e e J ett et iNM i M ** m M m N m @ Ch 03 M i i mI 8 4 4 4 i i i i CJ NmMLA NM NM MO MMMMNNomMM C000 00 00 00 00000e*O000
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- ~
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- C000000MO000000 %
M N O i ++ 4 + i+ 1 + + + 0 + 4 + a e L WWWWWWWWWWWWWWW o e M h MOMmMMCMONOMvvM e x e e e e e e e e e e e e e e e N M H l i f i l l l lMMNMmNMMNWMMMNmI l l e t i i l 4 6 $ 1 ( m W l W M H h OMvMMOMOMOMomMOOMO4MONNNNmMOMmM4MM COCOOOOOOOOOOONOCOOOMOOOOMOOOOOOOO
+ e e 4 4 + + + e+ e+ e e s+ e+ s e e e+++ 8 e+ 4 I e 6 4 6 WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW e @e Me eM W 4e eM e eN eTeOe N eM e eWe Ve me v e Me eNaOe N eM e e@ m O N N. M W-e W Ne-o e M MeNe m e e @e m H WNM4NMMMMMMmN@m4MNNMNWMNMMMNMNMWVMV MOOm NNOOMOMMCOMOWMmNNMNmONMMNOON L
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V EMm@O4mNNmmMMN 4@NmmOONMMcM M
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$NPS-1 ODCM TABLE 3.1-2 (CONT'D)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ND-147 6.1E-02 7.1E-02 4.2E-03 - 4.1E-02 - 3.4E+02 W-187 7.5E-02 6.3E-02 2.2E-02 - - - 2.1E+01 NP-239 4.3E-04 4.ZE-05 2.3E-05 - 1.3E-04 - 8.7E+00 III The dash (-) indicates insufficient data or that the dose factor is <1.0E-20. BNI-11600-Il6 3 of 3 Revision 3 - December 1983 O O O
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SNPS 1 ODCM 3.2 OPERATION OF L10VID WASTE TREATMENT SUBSYSTEMS The dose projection analysis will be performed UF ino t1e methodology described in Section 3.1 with the exception that the calculated dotts 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 0.2 mrem to any organs in a 31 day period. A model of the liquid radwaste treatment subsystems is shown on Figure 3.12. Although the- RHR Service Water Discharge. RBSWDT. and yard piping drain sump systems are not part of the radweste treatment subsystems, they are included in Figure 3.12 because they represent locations of potentially radioactive dis-charges. t c' O BN1-11600.02-92 !!.3.2-1 . Revision 16 - July 1990
SNPS-1 ODCM 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS To comply with Section 3.11.2.1 of REC, the dose rate at any time in the un-restricted area for noble gas dose and for organ dose due to radioactive materials in gaseous effluer.ts released via the station ventilation exhaust duct shall be limited to the following values:
- 1. For noble gases: Less than or equal to 500 mrem /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 rechnuclides in particulate form with half lives greater than 8 days: Less than or eaual to 1500 mrem /yr to any organ.
The geseous effluent model is shown in Figure 3.3-1. 3.3.1 Method 1: (Computerized Methodi 3.3.1.1 Release Rate Estimation Dose rate estir.ction is performed every 15 minutes by making use v' 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 i 0 3 3 where:
F' = 4 k y,3 F,(j) bngI3) Al f3 = 10-6 44 (t) /Cng(T) k = 2.832 x 104 (cc/ft)) F(j) 3
= vent flow during t ma interval j (cfm) i b (j) = .itor count rate during time interval n9 jnoble (cpm c)as ef fluent t =
time interval (=1 minute) qg
= concentration of isotope i in the effluent as measured in the lab at time T (uti/cc)
F' = 15-minute average of the flow and countrate product (for dose rate estimation every 15 minutes) assumed t, apply fora 60-minuteinterval[(cc/hr)(cpm)) 4 x 15 = number of t intervals per hour (1/hr) 1 BN1-11600.02-92 !!.3.3-1 Revision 10 - July 1990
1 SNPS-1 ODCM , G ! Q 3 . 3 .1. 't Total Bod.y Dose Rate eloud inh D = D + D + Dground , wb wb wb wb j i where:
' 4 CI "
D wb IX/0)$Y F 2.22 x 10 nbbles f DFB i 4
' I h 4 D =
(X/0)sa 7 3.17 x 10 R ad paht+1 f iDFA ij,ad I1 l i (D/Q) F 7 x 10 p{rt+1 #1DFG jg[1-e-tAbij/q
=
D(ound 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 gamma (X/Q) and the DFB 4 insteadofDF{doseconversion D h = total bod dose (j = total body) due to inhalation [ mrem /hr) y(Ref.: Reg. Guide 1.109. Eqs. C-3 and C-4, for an adult) - D(ound
= total body dose due to particulate and iodine radio-activity depositing- on the ground [ mrem /hr) (Ref.: Reg.
i Guide C1 and C-2 with the product 8760 1.109 (1/A ) Eqs.[yr) replaced by 4(1/A ) [hr] and parameter {h/yr 4 r.0 repr sented by the (D/0)) DFB = gamma dose to body conversion factor [(mrem /yr)/(pCi/m2)) 4 (from Table B-1 of the guide) DFA a dose conversion factor for nuclide i to organ j of an ij'ad adult individual [ mrem /pCi inhaled] (from Tables E-7 through E-10 of Reg. Guide 1.109) DFG = total body conversion factor for standing on contaminated 44 ground [(mrem /hr)/(pCi/m8)] (from Table E-6 of Reg. Guide 1.109) (X/Q)88 = concentrationdispersionfactor(sector-averagemodel)for the period of release (site boundary only) (sec/m8) (X/0)$8 y
= gama (X/Q) (finite cloud sector-average model) for the period of release (site boundary only) (sec/m8)
(D/Q) = particulate deposition rate (site boundary only) (1/me ) F' f = 4 Q4(Ci/hr)(asdefinedinSection3.3.1.1) l f l . BN1-11600-02-92 -11.3.3-2 Revision 3 - December 1983
l 1
$NPS-1 ODCM R
ad
= adult breathing rate (m8/yr) (from Table E 5 of the Guide)
A
= radionuclide decay constant (hr*I) '
4
=
t b time period over which the acgumulation is evaluated, which is 15 years (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 4 3.17x10 = 10 12(8760x3600)[(pCi/C1)(yr/sec))
/
4 2.2x10 = 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 1.10') Table E-15) 12 7x10 ll = 10 x 0.7, where 0.7 is the shielding factor and 10 12 43 the number of PCi per Ci (see Eqs. C 1 and C-2 of the guide) part+1 = 68 particulates and 5 iodines in the summation sign 3.3.1.3 Skin Dose Rate
= eloud + Dground D D skin skin skin I where:
DCI 1.11 x 0.7 ( VQ)Sa F' 3,17 x 104 jud noblesf i DF}
=
3 y l 4 (X/Q)S" F' 3.17 x 10 nbblesf iDFS 4
+
l
=
II I DQnd (D/Q) F' 7 x 10 phrtH #1 DFG12[1-e b1]/A 4 l O cloud = skin dose due to direct gama radiation from the skin radioactive cloud (first component of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud ireersion) [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B 9; also similar to Eq. B-7 if one makes use of the gama (X/Q)) Dground = sk.n dose due to particulate and iodine radioactivity kin depositing on the ground [ mrem /hr] (Ref.: Reg. Guide 8760 hr/yr 1.109l (1/A 4 C-1 [Eqs and C-2 with 4 the productyr) replaced by ( represented by the (D/Q)) DF{
= gamma dose to air conversion factor [(arad/yr)/(pCi/m8)]
(from Table B-1 of the Guide) ! DFS = beta dose to skin conversion factor [(mrem /yr)/(pCi/m8)] 4 (from Table B-1 of the Guide) BN1-11600-02-92 11.3.3-3 Revision 3 - December 1983
$NPS-1 ODCM DFG = skin dose conversion factor for standing on contaminated 32 ground [(mrem /hr)/(pCi/me )) (from Table, E-6 of Reg. Guide 1.109) 1.11
- average ratio of tissue to air energy absorption coefficient (from Reg. Guide 1.109, pg 1.109 6) 0.7 = shielding dose reduction factor (see pg 1.109-60 of the Guide) y = radionuclidedecayconstant[hr'I]
3.3.1.4 Organ Dose s Rate (1-131. 1 133 Tritium and particulate Release) nh s 4 D , ( g a F' 3.17 x 10 R,)ph.;fDFA33, g where; inh a dose to organ j of individual in age grou a due to D ja inhalation of airborne radioactivity [ mrem /hr)p(Ref.: Reg. Guide 1.109. Eqs. C-3 and C 4.) f'T DFA = dose conversion factor for nuclide i to organ j of g ija individual in age group a [ mrem /pCi inhaled) (from Tables E-7 through E-10 of the Guide) R = breathing rate of individual in age group a [m8/yr) (from a Table E 5 of Reg. Guide 1.109, for the maximum individ-ual s.) The analysis in site boundary is the limited to the sector downwind computation of the of for the period thyroid dose (i.e., the release to a child at the l j = thy-roid, a a child). O BN1-11600 02-92 11.3.3-4 - Revision 3 - December 1983
SNPS-1 ODCM 3.3.2 Method 2: (Backup Method) 3.3.2.1 Noble Gas Total Body Dose Rate DT,
=
0.7
- yJ0)
- IlDFB3 *(C3 )*V) - C12 *V2-C43 *V)3 3
+ 0.7 *V 2 *X0* 2 [DFBj *Ci2)
+ 0.7 *V 3 *VQ*fWB 3 4 *C43]
(mrem /yr) During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following: DT = (mrem /yr) 3 0.7
- V) ' X/0)
- I[DFB4
- C$ )]
If main condenser air removal is performed by the mechanical vacuum pump and the l sampling is performed at the Station Vent, the following equation should be used: DT = (mrem /yr) 3 0.7
- Y)
- X/02
- I[DFB4
- C4 )]
where: DT = total body dose rate from all radionuclides releases (mrem /yr), 3 DFB4= the total body dose rate factor due to garrrna emissions for each identified noble gas radionuclide (mrem /yr per pCi/m3) (Table 2.2-1),
= the station ventilation exhaus', duct release concentration of C)j radionuclide, i, (pCi/ce) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),
C = the air removal pump ventilation exhaust auct release concentration 12 of radionuclide, i, (pC1/cc) (from the isotopic analyses performed on the the air removal pump discharge monitnr) gaseous sample taken from C 13
= the containment drywell purge ventilation exhaust concentration of radionuclide, i, (pCi/cc) obtained from a sample taken during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.),
O BN1-11600-02-92 II.3.3-5 Revision 9 - May 1987
SNPS-1 ODCM (] V 3
= 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct V ventilation exhaust flow rate, V
2
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventila-tion exhaust flow rate, V
3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate.
X/Q3 = long term dispersion factor due to release via the station ventila- p, , 9 tion exhaust point; refer to Table 4-1, cells Al and A3, is X/Q2 = short term dispersion factor due to air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells Al and AS, X/03 = short term dispersion factor due to containnient drywell purge via the station ventilation exhaust point; refer to Table 4-1, cells Al and A7, 0.70 = shielding factor that accounts for dose reduction due to shielding from residential structures. 3.3.2.2 Noble Gas Skin Dose Rate
^
*(Cj )
- V) - C12 *Y2-C33
- V3 ))
DS X/0) * [K 3j (v) 3
+V2 (X/02 *7i EE si *C12) + Y3
- X/03 * $ [K 34 *C i3 J (mmm/yr)
During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the , tollowing: DS 3
=
V)
- X/Q)
- j [K 34
- C4 )) (mrem /yr)
If main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following equation should be used: 05 3
=
V)
- X/02 IK si
- Cg )] (crem/yr) where:
DS 3
= skin dose rate from all radionuclides released (mrem /yr),
f\ J. BN1-11600.02-92 11.3.3-6 Revision 13 - November 1988
SNPS-1 ODCM K gj
= the skin dose factor due to beta and gama emissions for each O identified noble gas radionuclide (mrem /yr per pC1/m8) from Table 3 2.2-1 ' '
C 41
= the station ventilation exhaust duct release concentration of radionuclide, i. (pCi/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhavst monitor),
C i2
= the air removal pump ventilation exhaust duct release concentration of radionuclide,1, (pCi/cc) (from the isotopic analyses performed on the the cir removal pump discharge monitor) gaseous sample taken from ,
C 33
= the containment drywell purge ventilation exhaust concentration of radionuclide, 1 (pC1/cc) obtained from a sample taken during a filtered release or from tho containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.),
V i
= 1.73E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilo-2 tion exhaust flow rate, i V 3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation O exhaust flow rate, 3
X/Q3= long term dispersion factor due to release via the station ventila- 4, tion exhaust point; refer to Table 4-1, cells Al and A3, '" X/Qp= short term dispersion factor due to air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells Al and AS, X /Q3= short term dispersion factor due to containment drywell purge via the station ventilation exhaust point; refer to Table 41, cells Al and A7 3.3.2.3 Organ Dose Rate (Particulate Releases)
*P gj
- X/Q) * (C 3) V) - C12 V2-C33 V)
=
D 33 }(106*R 3 3
+V 2 *
[106
- R,
- P j )
- X/Q 2 *C12)
+V 3 *f[106
- R,
- P gj
- X/03 *Cg3] (mrem /yr)
During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following:
= (mrem /yr)
D)3 V) * { 106*Rg* P )
- X/Q)
- C )
4 $ BN1-11600.02 92 11.3.3 7 Revision 13 - November 1988
SNps 1 ODCM () If main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following ecuation should be used:
= 106.y .g * */02
- IP ij *C)) (mrem /yr)
O g 1 a 4 where:
= total dose rate to organ, j, mrem /yr.
D) 3
- the inhalation dose conversion factor, for radionuclides 04er than P'd noble gases, i, and organ, j, in mrem per pCi from Table ,*1.6 3.
The dose factor p is based on the critical individual organ for theChildgroup,wMchismostrestrictive. Inhalation dose factorb for other age groups are given in Tables 0.5 1, 3.5 2, anc 3.5-4 R,
= inhalation rate (m8/yr), from Table 3.5 5.
C N
= the station ventilation exhaust duct release concentration of radionuclide, i, (UCi/cc) (from the isotopic analyses performed on the filter paper and charcoal cartridge taken from the station ventilation exhaust monitor),
C
- the air removal pump ventilation exhaust duct release concentration i2 of radionuclide, i, (uCi/cc) (from the isotopic analyses performed O on the iodine and particulate filters taken from the air removal
() pump discharge monitor), C a the containment dr purge ventilation exhautt concentration of 33 radionuclide, i, (ywelluC1/cc) obtained from the iodine and particulate filters during a filtered release or from the containment drywell atmosphere inonitor with the purge lines bypassing the primary containment purge filter (The concentration is obteined from the isotopic enalyses performed on the iodine and particulate filters.),
= 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct V) ventilation cxbast flow rate, V = 5.70D05 cc/sec (1200 cfm), air removal pug exhaust duct ventila-2 tion exhaust flow rate, i.
= 5.70E+05 ccisec (1200 cfm), containment drywell purge ventilation r exhaust flow rate, X/Cg* long term dispersion factor due to releases via the station ventila- o84 tion exhaust point; refer to Table 4<1, cells A2 and A4, X/0 2 e short term dispersion factor due to condenser air removel pump releese via the station ventilation exhaust point; refer to Table 4-1, cells A2 and A6, n
U X/Q3* short term dispersion factor due to containment drywell purge via the station ventilation exhaust point; refer to Table 41, cells A2 g and AB. u SN1-11600.02-92 11.3.3-8 Revisior 13 - November 1988 4
- m. .
m
7 2 8 g1 , T 4 M
- @,~ at>{du
- U - 7 a8 . NL 8 a- LIOA
.= s5 ii J 91 s6
- . z EATW
=
eE RR
. - 1i DT A OSM T MRN z, tO US E TwI O T G
. _ E LA A NP U
- U RU w L ALC -
F EA 0
. F C'.C 1 1EeE U
- c. -
. . PS N 7 _
m 3, SM O e 3 UA D OI Z..
. EOHE S c REET I I
- - :_ . US O H FS V GAHF E A
a I FGSO R u ~, .
,ii-1 p __
E _ 1 pa_ y [ _, , 1 I a l l w
.s 4
.8 m
- vD
=l I v
c.
-- _ W
_ ... .t _f c A8
- _ t 22 1
- 4 . t il i e.
EE RR t( .
= _ .
A Y m e p
=
p-
,l g -
1 g n_ y .
. . g g nU gn g
- m .
.nv
- = _ . .
=
SNPS-1 ODCM 3.4 GASEOUS EFFLUENTS NOBLE 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 gamma 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 gamma radiation and less than or equal to 20 mrads for beta radiation. ,4 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 Fstimation Dose estimation is performed every nour 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):
=
Qi F' f 4 8 where: k F F' = k 3,g 3(j) b ng Id) Ot f 4
=
10-6 q(7)7[ng j IT) 4 k = 2.832 x 10 .(cc/ft8) F(j) s
= vent fl w rate during interval j (cfm) b"9(j) = noble gas effluent monitor count rate during interval j j (cpm).
At = time interval (= 1 minute) q$
= concentration of isotope i in the effluent as measured in the lab at time T (uCi/cc)
F' = 60-minute avera of the flow and count-rate product [(cc/hr) (cpm)) ge 60 = number of at intervals per hour (1/hr) O BN1-11600.02-92 11.3.4-1 Revision 16-July 1990!
SNPS-1 00CM g 3.4.1.2 Noble Gas Garrna Air Dose 4 D Y,a i r
=
(X/Q)5 F' 3.17 X 10 nobles f i DQ where Dy,,$r
= ganna dose to air at the site boundary in the downwind sector during the period of release (mrad /hr) (Ref.: Reg.
Guide 1.109 Eos. B-4 and B-5, and also Eq. B-1 with the substitution of (X/Q)y (X/0)sa = finite-cloud sector-average 'ganna' dilution f actor at the downwindsite-boundary [sec/m3] 0Fj = genna dose to air conversion factor (from Table B-1 of Reg. Guide 1.109)[(mrad /yr)/(pCi/m3)) F'f 4 = Q4 (Ci/hr) (5?e Section 3.4.1.1) 4 3.4.1.3 Noble Gas Beta Air Oose 08, air = (X/0)sa p. 3.17 x 10 4 nobles f iDF 38 where 0 = in the downwind
- 3'347 beta sectordose to air during theatperiod the siteofboundary release [ mrad /hr) (Ref.:Reg.
Guide 1.109 Eqs. B-4 and B-5) DFj
= beta dose to air conversion factor (from Table B-1 of Reg.
Guide 1.109)[(mrad /yr)/(pC1/m3)] F'f 4
=
Qg(Ci/hr)(seeSection3.4.1.1) (X/Q)sa = sector-average concentration dilution factor at the site boundaryduringtheperiodofrelease[sec/m3) i e BN1-11600.02-92 11.3.4-2 - Revision 3 - December 1903 l l
P SNPS 1 00CM , 3.4.2 Method 2: (Bacipp Method) t 3,4,2.1 Noble Gas Garrta Air Dose . The general equation is: 2 12*Ci3 V 3 t)3
=
D g3 3.17E08X/0)*f[M3 *(C3 ) V) t) - 012 V
+ 3.17E 08 *V 2 *t 2 *C i2 3
- x/02 'f IMi
+ 3,17E 08 *V *t *x/Q 3 *t [M) *Cg3 J (mrad) 3 3 During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following:
O g3 a
*C))
g (mrad) 3.17E-08'V)*t)*x/0*{(M 3 3 If main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following equation should be used: 1 D, g
=
3.17E-08 *V) *t2 X /0*[IN 2 i *C3 )) (mrad) O where Dg = the total ganrna air dose from the releases (mrad), 3.17E 08 = the inverse of number of seconds in a year, Mg = the air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad /yr per UC1/m*) from Table =3.4 1, tg = 7.88E+06 sec for quarterly dose calculation.
- 3.15E+07 see for yearly dose calculation ,
t 2
= release period (sec) for condenser air removal pump 1
3
= release period (sec) for containment drywell purge exhaust C
Il
=
the station ventilation exhaust duct release concentration of - radionuclide, i, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), C = the air removal pump ventilation exhaust duct release i2 concentration of radionuclide,1. (uCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor), O BN1-11600.02-92 11.3.4 3 , Revision 9 - May 1987
SNPS-1 DDCM C g3
= the containment drywtl1 purge vertilation exhaust concentration O of radionuclide, i, (uCl/cc) obtained from a sample taken during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtainets from the isotcpic analyses performed on the gaseous sample taken.),
V 3
= 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V
2
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V
3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventila-tion exhaust flow rate,
= long term dispersion factor due to relesse via the station X/Q I ventilation exhaust point; refer to Table 4-1, cells B1 and 83, (7 X/Q 2 = shurt term dispersion factor due to condenser air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells B1 and B5, X/0 3 = short term dispersion factor due to containment drywell purge 3 release via the station ventilation exhaust releese refer to Table 4-1, cells B1 and B7. point;h
{ 3.4.2.2 gb1? Gas Beta Air Oose The general equation is:
=
Og 3.17E-08
- X/Q)
- I [N4 * (C4 ) V) t) - C12 Y 2 t2-C43 3 t)))
V
+ 3.17E-08
- X/Q2
- V 2 *t 2
- I [N 4 *C 12 l '
+ 3.17E-08
- X/Q3
- V 3 *t 3 *{[N *C43) 3 (mrad)
During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the ;Aove formule reduces to the following:
=
Og 3.17E-08
- X/Q)
- V) *t) g* I [N 4 *C))
j (mrad) If the main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following equation should be used:
,f ,
=
D 3.17E-08
- V)
- t2
- X/02
- f EN i
- C4 )] (mrad)
( B' O BN1-11600.02-92 11.3.4-4 Revision 13 - November 1908
p SNPS-1 ODCM where: Dg = beta air dose from 411 radionuclides released (mrad),
- f. Ng = the air dost facto, due to beta emissions for each i-idet.Mied ne ble ga radionuclide (mrad /yr per uCi/9) :
\
from Table 3 A1,
.17E-08 = the inverse of m,mber of seconds in a year, ')
t g
= 7.8BE+06 sec for quarterly dose calculation.
= 3.15E+07 see for yearly dose calculation, t = release period (sec) for condenser air removal pump, 2
t = release period (sec) for containment drywell purge 3 exhaust, C gy = the station ventilation exhaust duct release concentration of radionuclide, i. (uCt/cc) (from the isotopic analyses performed on the geseous sample taken from the station ventilation exhaust monitor), C = the air removal pump ventilation exhaust duct release i2 concentration of radionuclide, i. (uti/cc) (from the q isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor). C = the containment dryweil purge ventilation exhaust coticen-43 tration .of radionuclide, i. (uCi/cc) obtained from a l sample taken during a filtered release or from the con-tainment drywell atmosohere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.), V = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation 3 exhaust duct ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct 2 ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfm), containment drywell purge 3 ventilation exhaust flow rate, X/Q g = long term dispersion factor due to release via the station ventilation exhaust point; refer to Table 4-1, cells B1 fy , and B3, X/Q 2 = Ahort term dispersion factor due to condenser air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells B1 and B5, X /0 3 = short term dispersion factor due to containment drywell purge release via the station ventilation exhaust point; refer to Table 4-1, c-ells B1 and B7. BN1-11600.02-92 11.3.4-5 Revision 13 - November 1988
~ . . -
I SNS 4 ODCM TABLE 3.4-1 h N0B LP. GAS DOSE FACTORS , Gamma Air Beta Air Oose Factor Dose Factor ,: l H H 1sotope (mrad /yi' peh DCi/m8) (mradlyr p$r' Ki/m3) Kr - 83m 1.9E+01 2.9E+02 Kr 85m 1.2E+03 2.0E+03 Kr - 85 1.7E+01 2.0E+03 Kr - 87 6.2E+03 1.0E+04 Kr - 88 1.5E+04 2.9E+03 Kr - 89 1.7E+04 1.1E+04 Kr - 90 1.6E+04 7.8E+03 Xc - 131m 1.6E+02 1.1E+03 Xe - 133m 3.3E+02 1.5E+03 g Xe - 133 3.5E+02 1.1E+03 Xe - 135m 3.4E+03 7.4E+02 Xe - 135 1.9E+03 2.5E+03 Xe - 137 1.5E+03 1.3E+02 Xe - 138 9.2E+03 4.8E+03 Ar - 41 0.3E+03 -3.3E+03
, O BN1-11600.02-112 1 of 1 -
Revision 1 - August 1983
SNPS-1 ODCM 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RAD 1010 DINES ALD RADIOACTIVE
. MATERIALS IN PARTICULATE FOTM AND RADIONUCLIDES (other than '
Noble Gases) WITH HALF-LIV'.S 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 radioiodines and particulates releases via the station ventilation exhaust point shall he limited to the following: ,
- 1. During any calencar 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: (Computerized Meth W ) 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 Q4 4 where:
F' = g0 F (j) b (j) At k 4 ,, , 3 ng
= -6 f
3 10 q4(T) / C ng IT) k = 2.832__t '04 (cc/ft% F(j) s
= vent flow rate during interval J (cfm)
C ng(j) = noble gas effluent monitor _ count rate during interval j x (cpm) At = time interval (= 1 minute) q4
= concentration of, isotope i in the effluent as measured in the lab at time T (pCi/cc)
F' = 60-minute avera of the flow and count-rate product [(cc/hr)(cpm)]ge 60
= number of f.t intervals per hour (1/hr) 4, BN1-116CO.02-112 11.3.5-1 Revision 16 - July 1990
.m i
i SNPS-1 ODCM 3.5.1.2 Total Body Dose
= eloud +
inh + Dgr und 9 D D wb wb
'wb wb where:
, (gg)sa F' 2.22 x 10 4 f DFB 4
/doud no les i 0
h , (gg)sa p. 3,17 x 3g4 g ad p t+1 f iDFA ij,ad I1 D(ound
=
(D/Q) F' 7 x 10 par I F 4 DFG $ ) [1 - e-tb i]/ A4 eloud a total body dose due to direct radiation from the D wb radioactive cloud [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. 3-8;alsosimilar}toEq.B-6ifonemakesuseofthegamma (X/Q) and the DFB instead of dose conversion factor) , i D inh = total body dose (j = total body) due to inhalation Il wb (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4, for [ mrem /hr an adult D, ground = total body dose due to particulate- and iodine radioactivity depositing on the ground [ mrem /hr] (Ref.: Reg. Guide 1.109, thr/yr)(1/A ]Eqs. C-1 yr replaced and )C-2 by [1/A [hr]withand the product 8760 parameter 6 (r,6) reprds)e[nte( of the (D/Q)) $ 3 DFB j = gamma dose to body conversion factor [(mrem /yr)/(pCi/m3)] (from Table B-1 of the Reg. Guide) DFA = dose conversion factor for nuclide i to organ j of en ij,ad adult individual [ mrem /pCi inhaled] (from Table E-7 of Reg. Guide 1.109)
= total body conversion factor for standing on contaminated DFG4 ) ground [(mrem /hr)/(pCi/m2)] (from Table E-6 of Reg. Guide 1.109)
(x/Q)sa
= concentration dispersion factor (sector-average model) for the period of rclease (site boundary only) (sec/m3)
O BN1-11600.02-112 11.3.5-2 - Revision 10 - August 1987
=. . - - --
SNPS-1 ODCM (y/Q)Say
= gamma (X/Q) (finite cloud sector-average model) for the r'} =
period of. release (site boundary only) (sec/m3) particulate deposition rate (site boundart only) (1/mt) (D/Q) F' f j = Q4 (Ci/hr) (as defined in Section 3.5.1.1) R ad
= adult breathing rate (m3/yr) (from Table E-5) q = radionuclidedecayconstant(1/hr) t b
=
time period over which the accuylation is evaluated, which is 15 years (1.314 x 10 hours) (Reg. Guide
, pg 1.109-24) 4 3.17x10 = 10 12 / (8760 x 3600) ((pCi/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 1.109 Table E-15) 7x10 ll = 10 12 x 0.7, where 0.7 is the shielding factor and 10 I2 is the number of pCi per Ci (see Eqs. C-1 and C-2 of the guide) part+1 = 68 particulates and 5 iodines in the summation sign
'a Note that the total " total body" dose as computed above is used only fcr hou;'ly asussment of plant operation within the specification limits. The reports pre-paret' by the dose sof tware-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 gas 7:s, even though this section addresses only the iodines and particulates.
3.5.1.3 Skin Dose
= eloud + Dground 0 D skin skin skin where:.
4 CI D jud = 1.11 x 0.7 - ( Y/Q)30 F' 3.17 x 10 nohlesf i DFf , 4
+(X/Q)sa F' 3.17 x 10 noblesf iDFS $ l O -V BN1-11600.02-112 II.3.5-3 -
Revision 3 - December 1983
SNPS-1 ODCM ll D[n" = (D/Q) F' 7 x 10 par b I i DFG 12 [3 ,g-tbi]/A 4 D eloud = skin dose due to direct ganina radiation from the skin radioactive cloud (first component of the equation with finite cloud modeling) and beta radiation (second compon-ent, semi infinite cloud immersion) [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Eq. B-7 if one makes use of the gamma (X/0))
= skin dose due to particulate and iodine radioactivity D]und " depositing on the ground [ mrem /hr) (Ref.: Reg. Guide 1.109, Eqs. C-1 ond C-2 with the product 8760[hr/yr]
(1/A )[yr] replaced by (1/A )[hr] 4 9 and parameter 6 4 (r,0) represented by the (D/Q)) DF Y = amma dose to air conversion factor [(mrad /yr)/(pCi/m3)] 3 from Table B-1 of the Guide) DFS = beta dose to skin conversion factor [(mrem /yr)/(pCi/m3)] (from Table B-1 of the Guide) l DFG = skin dose conversion factor for standing on contaminated 12 r )] (from Table E-6 of Reg. Guide ground [(mrem /hr)/(pCi/m 1.109) 1.11 = average ratio of tissue to air ent.rgy absorption coeffici-ent (from Reg. Guide 1.109, pg 1.109-6) 0.7 = shieldin dose-reduction factor (from Reg. Guide 1.109, pg 1.109-68 and the remaining parameters are as defined above in Section 3.6.1.2. 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 particulates. O BN1-11600.02-112 II.3.5-4 Revision 3 - December 1983
i SNPS-1 ODCM 3.5.1.4 Organ Doses Due to inhalation n h
'~'
D , (gg)sa F' 3.17 x 10 4 R, p,fg;f4 DFA ijh where: h = D dose to organ j of individual in age grou a due to inhalation of airborne radioactivity [ mrem /hr)p(Ref.: Reg. Guide 1.109 Eqs. C-3 and C-4) DFA jj,
= dose conversion factor for nuclide i to organ j of 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 [m8/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/m2] 3.5.1.5 Organ Dose Due to Ingestion of Leafy Vegetably I i I i Dja"9 = (Dja"9) part + (D "9) ja iodines + (D "9)C14 ja 73 Q where: l
= 0 l
(D 9) part (D/Q) F' 1.1 x 10 part U f i DFl ija O iv 0.2 3 e'24i
+
xE2 ( A g + 0.0021) 240 A 7 (D 9) iodines
=
(D/0) P 5.5 x 10 iodinesUa Ii DFl ija O 1.0 + iv e"24Ai x{2(Ag + 0.0021) 240A ) 4 7 (D ,"9)C14. = (X/Q)sa F' 5.5 x 10 0 fC14 DFI C14,ja 7
= (X/Q)sa p. (,1.2x10)Ukf H3 DF1 (D 9)H3 H3,ja BN1-11600.02-112 11.3.5-5 ,
Revision 3 - December 1983 L l i l
SNPS-1 ODCM
= dose to organ j of individual in age group a due to t
(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 of the Guide)
't (time period that crops are exposed to l
c8ntaminationduringgrowingseason)= [ hrs]
't s stime period (14 which the accumulation is evaluated) = [h rt j j 'th (time delay between harvest of vegetation or cropsandingestion)=24[ hrs]
l
*Yy (agricultural productivity) = 2 [kg/m8]
- P (soil effective surface density) = 240 [kg/mr ]
+ 0.0021 [hr*I] (Ref.: Reg. Guide 1.109,
*xh=1.kb9-4and1.109-69) p
*6 4 (r,0) = (0/Q) [m'2]
- f r. (fraction of leafy vegetables growing in garden of interest) = 1.0 1
I (D"9) = dose to organ j of individual in age group a due to Ja todines 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) I = dose to organ j of individual in age group a due to l-(D"U9) d C14 ingestion of leafy ve Carbor-14 [ mrem /hr] getables (Ref.: Reg.exposed to airborne Guide 1.109, Eqs. 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) l
= dose to organ j of individual in age group a due to (0)a"9)H3 ingestion of leafy vegetables exposed to airborne tritium [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-9 and C-13 for leafy vegetables only) t BN1-11600.02-112 11.3.5-6 Revision 3 - December 1983 ;
..___m .._ _ ._ . . _ . . _ _ . _ . _ . . _ _ _ _ . _ _ _ . _ . . .
ey - n; y SNPS-1 ODCM . U L '= _ ingestion rate of leafy v'egetables by . individual _in age a roup a ' _ kg/yr) (from Table E-5 of the Guide, maximum individual)
'B '=- concentration factor for uptake of radionuclide i from IV -
parts . of crops [(pct /kg)(wet - weight)/. soil.' (pCi/kg by) (edibledry soil))? (Ref.: - Reg. Guide 1.109, Table E-1 and included on Table 3.5-6) DFI kja
= dose conversion factor for nuclide i to organ j-of Sdividual food [ mrem in/pCiingested age group]a(from due Tables to ingestion of contam:aated E-11 through E-14 of '
tae Guide).
-DFI C14.ja = CFl ija for Carbon-14
=
DFI H3.ja DFI$ ), for tritium
'F '~ f C14 i. for Carbon-14 (see Section 3.5.1.1 above) f
- f for tritium H3 i H = absolute humidity of the atmosphere at the ' location 'of. '
interest [g/m8)(See_ Table 3.5-7)-
, (X/Q)8 = . concentration-dispersionLfactor-(Sector - Average model) -
for the - eriod of release (nearest . garden and' nearest' residence [sec/m8]
.(D/Q) =- -particulate deposition rate'(nearest garden and nearest residence)[1/m2]
3.5.1.6 Infant-Thyroid-Dose-Due to Ingestion of--Goat Milk and Inhalation- {<et. ej Infant thyroid dose equation:
- 1
=- inh _. milk D
thy,inf Dthy,inf. , D thy,inf where:- milk milk ~-- +' milkt thy,inf " y -D IEhy,inf)~part t IDthy,inf)-iodines h:, + (D inf.) C14 IE inf)H3:
> .3
+ I
- 4 D
t ,inf _ X/Q)38 ( F' 3.17 x 10 _Rinfpdt+1 f i DFAi , thy,inf m O -BN1-11600.0E-112 11.3.5-7 Revision 13 - November 1988
SNFS-1 ODCM 0 (0 inf) part = (0/Q) F' 1.1 x 10 part Ujnf f i 0Fli , thy,inf 0.2 + siv 3e-24AI x6F,9[0.7tA + 0.0021) 240x i i 7 (D inf) iodines
=
(D/Q) 5.5 x 10 iod nes O nf i f DFl i thy,inf 1.0 B
)e'24A i 4 iv x 6 F*i b 0.7(A j + 0.0021) 240A 4 7
(D inf)C14
=
@/0) P 2.2 x 10 f'nf 4 I C14 DN C14, thy,inf x6fm,C14 **PI'24'C14) 7 milk =
m (Othy,inf}H3 (X/Q)sa F,[1.2x10_)Vinf H3 f 0 H3, thy,inf x6F m,H3 exp(-24A H3) inh = infant thyroid dose due to inhalation of airborne D thy.inf radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109, ( Eqs. C-3 and C-4) (gilk = infant thyroid dose due to ingestion of milk contam-thy inf)part inated 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 1.109-68 of the Guide)
*t (time period that crops are exposed to c8ntaminationduringgrowingseason)= [ hrs]
*th (time period over which accumulation is evaluated) = Lhrs]
*t
=h0 ([hrs](seepg time delay 1.109-69 for ingestionof Reg.ofGuide) forage by animals)
Y mXn(agricultural pathway) = 0.7productivity, [kg/m2] (Reggrass-animal-Guide 1.109, Rev.milk-0)
- P (soil effective surface density) = 240 [kg/m2]
i BN1-11600.02-112 11.3.5-8 Revision 10 - August 1987
.. . .~ - - . . . . - . _ . . . .._-...~ ~. _ .. - .. - - _ - - - . . _
t SNPS-1 ODCM Ai + 0.0021 [hr'I) (sce pgs 1.109-4 and
*A Ei =
,O- 1.109-69)
- 0; a6 (r e) = _ (D/Q) [m-2)
- p. ,,,
t, feed (average into thetransportmilk andtime of receptor to the activity)from; data the jg ' listed in Table 4-2
- f (fraction of the year that animals graze on
~
h .,' pEsturebasedonsurveydata);datalistedinTable 'I 4-2
- f when(fraction g,,
the animalofgrares daily feed that isbased on pasture pasture on grass survey ,t data);datalistedinTable4 milk = infant thyroid dose due to ingestion of milk contam-(0 thy.inf) iodines inatedwithradio-iodines [ mrem /hr)(Ref.: Reg. Guide Eqs. C-5, C-7, C-10. C-11, and C-13 for milk; similar to -the infant- thyroid -dose due to the ingestion of particulates given above, with the exception of a
= different multiplying--factor and r = 1.0) a : infant thyroid dose due to ingestion of milk contam-(D* thy,inf)C14 inated with C14:[ mrem /hr) (Ref.: Reg. Guide 1.109, pf 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 8 as given above for the
'partictflated, milk- = infant thyroid dose due to ingestion of milk contam-
-(Dthy.inf)H3 _inated 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 3 given above for the particulates)
R = infant breathing rate [m3/yr)c(from Table- E-5 of the inf Guide, for maximum individual) DFA i ,th#'inf
= dose conversion factor for nuclide i to the infant thyroid due -to inhalation [ mrem /pCi inhaled) (from Table E-10 of theLGuide)
DFl~i , thy'inf
= dose conversion. factor for nuclide -1 to the infant thyroid due to ingestion -[ mrem /pCi ingested] (from Table E-14 of the. Guide) l DM C14, thy.inf =
p 091, thy,inf for Carbon-14 i, thy,inf for tritium
; 0FI = DFl H3, thy,inf L
BN1-11600.02-112 11.3.5-9 . Revision 13 - November 1988
1 SNPS-1 ODCM F C14
" f ifor Carbon-14 (see Section 3.5.1.1 above)
F H3 'i for tritium ,
= milk ingestion rate by infant [ liters /yr] (Ref.: Reg.
nf Guide 1.109, Table E-5, max ind.) F*$
= average fraction of the animal's daily intake of radionuclide i which appears in each liter of r ilk
[ days / liter] from Table E-2 of the Guide, with F, = F,4,forgoat) i B = concentration factor for uptake of radionuclide i iv from soil by edible parts of crops [(pCi/kg) (wet weight)/(pCi/kg)(drysoil)](fromTableE1ofthe Guide and included on Table 3.5-6) H = absolute humidity] ofinterestLg/m8 of Table (See the 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, Q p factor) ( y/Q)sa
= concentration dispersion factor (Sector - Average model) for the of release (nearest goat location)[sec/m3] period
( (D/Q) = particulate deposition rate (nearest goat location) ll/m2] I i BN1-11600.02-112 11.3.5-10 Revision 13 - November 1988
SNPS-1 ODCM 3.5.2 Method 2: (Backup Method) I . (> 3.5.2.1 Organ Doses: D)
=
3.17E-08*j[(106 *R a
- P3 ) *X/Q3 + Pg4) *D/Q) g
*(C 4j *V 3 *ti-C12 *Y 2 *t2 -C43 *V 3 *t)) 3
+ 3.17E-08 *V 2 *t 2 *j[(106 *R,
- P 4) *X/Q2 + P g43 *D/Q)*Ci2) 2
+ 3.17E-08 *V 3 *t 3 *{[(106 *R,
- Pjj *X/Q2 + P og) *D/Q3 ) *C13)
(mrem) (3.5.2-1) During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: , D) = 3.17E-08 *V) *ty *j[(106 *R 3 *P jj *X/01 + P o$j *D/Qg )*C33] (mrem) (3.5.2-2) If main condenser air removal is performed by the mechanical pump and the sampling is performed at the Station Vent, the following equation should be used: D j = 3.17*10'8 *V) *t 2 *{[(106 *R, *P4 ) *X/Q2 + P g4) *D/Q2 ) *C$3] (mrem) (3.5.2-3) where: D J
* * **I d S* * '9'" d (**)'
P = the inhalation dose conversion factor for- redionuclides, i, (other
$d than noble gases), and organ j, (mrem per pCi inhaled) from Table '
3.5-4. P values listed in Table 3.5-17 are the dose rate conversion fNtors for tritium and carbon-14 from ingestion of goat's milk. 13 V BN1-11600.02-112 11.3.5-11 Revision 14 - January 1989
SNPS-1 ODCM Note: For short term releases such as from condenser air removal ( pump or containment drywell purge P for C 'l must be adjusted (see note in Table 3.5-17) 43 R a
= inhalation rate (m3/yr) from Table 3.5-5, P the dose conversion factor for radionuclides, other than noble ng) = r gases, i, and organ j, for goat milk in m (mrem /yr per uCi/sec) from Table 3.5-14.
The dose factors P P are based on the critical individual organ for the infanth,rouhsince this group is most restrictive. t g
= 7.88E+06 sec for quarterly dese calculation
= 3.15E+07 see for yearly dt.'e calculation, t = release period (sec) for condenser air removal pump, 2
t 3
= release period (sec) for containment drywell purge exhaust, C
II
= the station ventilation exhaust duct release concentration of radionuclide, i, (uCi/cc) (from '.he isotopic analyses performed on the iodine and filter cartridge taken from the station ventilation exhaust monitor),
C 12
= the air removal pump ventilation exhaust duct release concentration
( of radionuclide, i, (uti/cc) (from the isotopic analyses performed on the iodine and particulate filters taken from the air removal pump discharge monitor), C = the containment dr 13 radionuclide, i, (ywell purge uCi/cc) ventilation obtained exhaust from the iodineconcentration of and particulate filters during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the iodine and particulate filters.), V = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct i ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct 2 ventilation exhaust flow rate, V 3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge 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, short term dispersion factor due to condenser air removal pump X/Q2= release via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C5. BN1-11600.02-112 11.3.5-12 . Revision 14 - January 1989
SNPS-1 ODCM short term dispersion factor due to containment drywell purge via '$6 X/Q3= (q g the station ventilation exhaust point; refer to Table 4-1, cells C1 and C7, d long term deposition factor due to releases via the station D/Q3= ventilation exhaust point; refer to Table 4 1, cells C1 and C9, D/Q2 = short term deposition factor due to condenser air removal pump releases via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C11 D/Q3= short term deposition factor due to containment drywell purge exhaust via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C13,
- 3. DE-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) t' P used in Equation 3.5.2-1 will include the values in Tables 3.5-10 through 3N14,ifthosepathwaysexist. 0 At each location, the following P6thways must be considered and dose (dose rates) reevaluated if any hctual pathway edits:
- 1. inhalation,
- 2. leafy vegetables (fresh),
- 3. stored vegetables,
- 4. goat's or cow's milk (if both exist choose the one resulting in the higherdose),and
- 5. deposition on grounc.
Since a person will always be present, pathways 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 0/Q at the updated critical location must be used.
O V BN1-11600.02-112 11.3.5-13 Revision 13 - November 1988
i SNPS-1 ODCM TABLE 3.5-1 INHALATION DOSE FACTORS FOR ADULTS i (mrem per pCi inhaled) l Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI=LLI ! 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 1.28E-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 fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 . Co-58 No Data 1.98E.07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 l Co-60 No Data 1.44E-On ' 85E-06
. No Data no Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.03E-06 1.8?E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.ltE-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 8.62E-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 Sr-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 V-90 2.61E-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 - August 1987 e G
~ .
G
V V SNPS-1 ODCM-TABLE 3.5-1 (CONT'D) Radio-nuclide 8one Liver T. Body Thyroid Kidney Lung GI-LLI Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09. 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 No Data 3.89E-11 No. Dita 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.2SE-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 1 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 '2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 i I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NJ Data 6.56E-07 4 Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 . Cs-138 4.14E-05 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 , Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 BN1-11600.02-99 2 of 3 Revision 1 - August 1983 3
t SNPS-1 ODCM TABLE 3.5-1 (CONT'D) l L_ung GI-LLI Thyroid Kidney Ra dio-. T. Body Bone Liver 1.50E-05 7.83E-07 4.52E-05 fnuclide 1.69E-06 1.91E-07 No Data 7.60E-09 9.97E-06 2.83E-05 2.49E-06 1.91E-09 No Data 9.72E-04 1.02E-04' fCe-141 2.33E-08 1.72E-08 2.30E-05 No Data 1.06E-04 3.51E-05 2.50E-05
- Ce-143 4.29E-04 1.79E-04 No Data 2.70E-07 2.69E-18 Ce-144 4.69E-07 5.80E-08 8.81E-13 1.27E-07 1.17E-06 1.91E-13 No Data 2.76E-05 2.16E-05 l Pr-143 3.76E-12 1.56E-12 No Data 4.45E-07 l'.94E-05 l Pr-144 7.62E-07 4.56E-08 No Data 3.63E-06 j Nd-147 6.59E-07 .3.10E-10 No Data 4.70E-06 1.49E-05 1.06E-09 8.85E-10 No Data 8.75E-09
) W-187 2.82E-09 1.55E-09 fNp-239 2.87E-08 l l l l I i 1 i Revision 1 - Ausst 1983 3 BN1-11600.02-99 9
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SNPS-1 ODCM TABLE 3.5-2 (CONT *D) Radio-auclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 ho Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.?1E-05 Mo-99 No Data 2.11E-08 4.08E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03F-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-!1 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 5.96E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.14E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.1.1E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Dato 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 , BN1-11600.02-100 2 of 3 Revision 1 - August 1983 6 9 9
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I k_)m k_ SNPS-1 ODCM TABLE 3.5-2 (CONT'D) Radio-nuclide Bone Liver .T. Body ' Thyroid Kidney Lung G1-LLI Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No. Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05 l Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-05 l I BN1-11600.02-100 3 of 3 Revision 1 - August 1983 i 1
SNPS-1 ODCM TABLE 3.5-3 I INHALATION DOSE FACTORS FOR CHILD (mrem per pCi inhaled) Radio- Lung GI-LLI nuclide Bone Liver T. Body Thyroid Kidney 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 H-3 No Data 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 C-14 9.70E-06 4.35E-06 4.35E-06 l Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 P-32 7.04E-04 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Cr-51 4.26E-04 6.19E-06 1 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Mn-56 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-55 1.28E-05 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 Fe-59 5.59E-06 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-58 No Data No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Co-60 1.71E-06 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 7.99E-11 4.44E-11 No Data No Data 2.21E-06 2.27E-05 Ni-65 8.08E-10 9.92E-06 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 Cu-64 4.41E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Zn-67 1.81E-11 No Data No Data 1.28E-07 No Data No Data No Data <l.00E-24 Br-83 <1.00E-24 No Data No Data 1.48E-07 No Data No Data No Data Br-84 No Data <1.00E-24 Br-85 No Data No Data 6.84E-09 No Data No Data No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-86 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-88 5.IIE-10 No Data 9.33E-08 7.83E-08 No Data No Data No Data Rb-89 4.52E-05 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 Sr-89 9.28E-05 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 Sr-90 4.70E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Sr-92 7.24E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91m 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-91 V-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Y-93 5.04E-08 BN1-11600.02-101 1 of 3 Revision 1 - August 1983 O O O i
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d a SNPS-1 00tM TABLE 3.5-3 (CONT'D) Radio- Lung nuclide Bone Liver T. Body Thyroid Kidney GI-tLI 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-95 5.13E-05
-7.34E-09 4.32E-09 No Data 1.050-08 3.06E-05 9.49E-05 Zr-97 5.07E-08 1.00E-05 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 Nb-95 3.42E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data I.06E-07 3.66E-05 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-99m 4.81E-13 4.41E-09 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 Tc-101 1.21E-05 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 Ru-103 2.69E-05 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 Ru-105 1.16E-04 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 Ru-106 2.71E-05 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 A9-110m 9.13E-06 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-0A Te-125m 1.93E-05 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 Te-127m 1.52E-05 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 Te-127 4.91E-05 5.19E-06 1.85E-06 8.22E.07 1.71E-06 1.36E-05 4.76E-04 Te-129m 6.89E-06 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 Te-129 8.32E-05 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 Te-131m 3.63E-08 5.55E-07 3.60E-07 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 Te-132 1.30E-07 1
4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 l 1-130 2.21E-06 7.68E-07 1.30E-05 7.37F-06 4.39E-03 2.13E-05 No Data 1-131 1.30E-05 8.65E-07 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-05 No Data l I-132 No Data 1.48E-06 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 L.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-134 3.17E-07 1.20E-06 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 Ne Data I-135 3.27E-05 1.04E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-136 1.76E-05 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-137 2.45E-04 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-OS Cs-138 1.71E-07 2.66F-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-139 4.98E-10 2.75E-US 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 Ba-140 7.44E-08 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 Ba-141 7.41E-10 Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 La-140 1.74E-07 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 La-142 BN1-11600.02-101 2 of 3 Rcvi'sion 1 - August 1983 l ___m
SNPS-1 ODO4 TABLE 3.5-3 (CONT'D)
. Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data .2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22F-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Dats 1.11E-05 2.16E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 BN1-11600.02-101 3 of 3 Revision 1 - August 1983 O O O
j SNPS-1 ODCM TABLE 3.5-4 INHALATION DOSE FACTORS FOR INFANT (mrem per pCi inhaled) Radio- Lung GI-LLI nuclide Bone Liver T. Body Thyroid Kidney 1 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 l H-3 No Data 3.79E-06 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 Na-24 7.54E-06 1.15E-05 8.03E-05 5.53E-05 No Data No Data No Data P-32 1.45E-03 2.55E-07 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 Cr-51 7.14E-04 5.04E-06 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Mn-56 No Data 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-55 1.41E-05 1.77E-05 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 Fe-59 7.95E-06 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 Co-58 2.28E-05 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 ! Ni-63 2.42E-04 3.58E-05 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 Ni-65 6.64E-06 1.07E-05 Co-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-65 1.38E-05 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Zn-69 No Data <1.00E-24 Br-83 No Data No Data 2.72E-07 No Data No Data No Data 2.86E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data No Data 1.46E-08 No Data No Data No Data <1.00E-24 Br-85 2.17E-06 No Data 1.36E-04 6.30E-05 No Data No Data No Data Rb-86 2.42E-07 No Data 3.98E-07 2.05E-07 No Data No Data No Data Rb-88 4.87E-08 No Data 2.29E-07 1.47E-07 No Data No Data No Data Rb-89 4.57E-05 f Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 Sr-90 2.92E-02 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 Sr-91 6.83E-08 1.70E-05 1.00E-04 Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-90 2.35E-06 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91m 2.91E-10 No Data 1.12E-05 No Data No Data 1./SE-03 5.02E-05 Y-91 4.20E-04 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-92 1.17E-08 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Y-93 1.07E-E7 1 of 3 Revision 1 - August 1983 BN1-11600.02-102
SNPS-1 ODCM TABLE 3.5-4 (CONT'D) Radio-nuclide Bone Liver T. Body Thyrcid Kidney Lung GI-LLI Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.8SE-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E'-03 2.36E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Date 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-l' 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-OL 6.38E-08 1.89E-07 1.42E-04 8.51E-05 le ' 4 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 T -132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 7.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.<4E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.3"r-05 1.49E-06 No Data 9.21E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2. 74 E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 BRI-11600.02-102 2 of 3 Revision 1 - August 1983 O O O
,e D %J J SNPS-1 ODCM TABLE 3.5-4 (CONT'D)
Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Le-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.59E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 .8.30E-05 3.55E-45 Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04' Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 - Pr-144 3.42E-11. 1.32E-Il 1.72E-12 No Data 4.80E 1.15E-06 3.06E-06 Nd-147 5.67E-06' 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 '9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4 25E-05 1.78E-05 BN1-11600.02-102 3 of 3 Revision 1 - August 1983
SNPS-1 ODCM TABLE 3.5-5 g RECOMMENDED VALUES FOR U,p TO BE USED FOR THE MAXIMUM EXPOSED p INDIVIDUAL IN LIEU OF SITE-SPECIFIC CATA Pathway Infant Child Teca Adult Fruits, vege-g/ r) N/A I7) 520 630 520 Leafy vege-tables (kg/yr) (1) N/A 26 42 64 i Milk (t/yr)II) 330 330 400 310 Meat &p%try (kg/yr) N/A 41 65 110 l Fish (fresh or salt) (kg/yr)(3) N/A 6.9 16 21 , Otherseg{9od ( (kg/yr) N/A 1,7 3,9 5 , 4 Drinkinp4yater (t/yr) 330 510 510 730 Shoreline rec-reation[4) (hr/yr) N/A 14 67 12
' Inhalation f (m3/yr) 1400s5) 3700(6) 8000(6) 8000(5)
II) Consumption rate obtained from Reference 19 for average ir.dividual and age prorated and maximized using techniques contained in Reference 10 of Regula-tory Guide 1.109, Rev 1, Oct. 1977. (2) Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain,
~ ; O BN1-11600,02-112 1 of 2 Revision 3 - December 1983 a
l l SNPS-1 00CM TABLE 3.5-5(CONT'0) ' 53) Consumption rate for adult obtained by averaging data frori References 10 and 21-24 of Regulatory Guide 1.109 Rev. 1, Oct. 1977 and age-prorated using techniques contained in Reference 10. (4) 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, Oct. 1977. (6) Inhalation rate derived from '9ta rro'ided in Reference 20 of Regulatory Guide 1.109, Rev.1, Oct.19U, II) N/A indicates m t applicable, f 1 ("h V 1
) ,
O BN1-11600.02-112 2 of 2 Revision 3 - December 1983
SNPS-1 ODCM TABLE 3.5-6 STABLE ELEMENT TRANSFER DATA (1) 8 F (Cow) F E_l ement Veg/ Soil Milk (d/11 Meat (d/kg) 4.8E+00 1.0E-02 1.2E-02 Hf2 C 5.5E+00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02 O) 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 5.2E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.76-02 8.0E-04(3) 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 2r 1.7E-04 S.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 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 Ag 1.3E-01 1.5E-01 1.0E-02 5.0E-02 1.5E-03 1.7E-02 W Te 1.3E-00 1.0E-03 7.7E-02 1 2.0E-02 6.0E-03 4) 2.9E-03 Cs 1.0E-02 1.2E-02 ' 4.0E-C? Ba 5.0E-03 4.0E-04 3.2E-03 La- 2.5E 03 2.0E-04 Ce 2.5E-03 5.0E-06(3) 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E 06 3.3E-03 W 1.8E-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. Meat and milk coefficients are based on specific activity considerations. From Reference 15 of Regulatory Guide 1.109. Rev. 1, Oct. 1977, h'4}
) See text (Regulatory Guide 1.109, Rev.1, Oct.1977).
From Reference 13 of Regulatory Guide 1.109, Rev.1, Oct.1977 l Ol
- BN1-11600-112 1 of 1 , Revision 1 - August 1983 l
l .
SNPS-1 ODCH TABLE 3.5-7 (~ CP HUMIDITY PARAMETERS AT RECEPTORS , i Monthly Average Absolute Humidity (om/m8) January 3.06 February 3.09 March 3.83 4 April 5.71 May 8.19 June 12.62 July 15.53 August 14.52 September 11.68
~
October 8.11 November 5.37
. ember 3.73 5
h () BN1-11600-112 1 of 1 Revision 1 - August 1983 q .-
,,,,-.----g -n ,- , - - - , , - . v .n - e - -n- .- - -,-
SfPS-1 A TfRE 3.5-8 L0rEI&l & fUMST iESIDDfI, VEET7aE C/@Df, SITE BoltDWY,40 MILK 4GR BY SELT101
~
Nearest tieamst Nearrst th,t Site Bourdary Pec i43re(+) VeTtable Gmien(+) Milk f# 1(*+) Distance
- Elevation ** DistanoE' avation** Distance
- Elevatim** Distance
- Devatim**
h ter (Meten) (Meters) (Meters) s.eters) (Meters) %ters) (Meters) (fttm) N 4% 6.1 - - - - - - r!E 366 6.1 458 12.2 - - - - l fE 332 6.1 SM 12.2 - - - - ETE 311 6.1 1050 12.2 1895 32.0 - - E 346 6.1 1097 12.2 1212 17.4 - - ESE 457 6.1 889 12.2 1323 1C.2 - - t SE 1105 26.0 1007 19.8 1260 21.3 - - SSE 876 30.0 789 30.8 1920 51.4 - - S 610 25.9 1170 41.1 1837 57.9 - - < SSW 457 22.0 1487 62.5 14 % 62.5 - - SW 533 17.0 497 21.3 2C46 45.7 WSW 457 15.0 1694 38.4 IE67 53.3 - - W 360 6.1 1408 33.5 2273 40.2 3058 41.5(Goats) WM 354 6.1 664 25.9 - - - - PM 4?9 6.1 - - - - - - t/M 4% 6.1 - - - - - - Ntes: Distances are given trun tie mactor centerline out to 8)16 neters. . Elevations givm are refers atow rnean sea level - higtest elevation betxui reactor aru! receptrar pirit.
- Milkiry gaats are airo located at 3862 neters frun STPS, at elevation 42.7 neters, in this section.
Ikwmm per tre Milk Animal Sursey, these gmts are on 10fr. irriuor-stored, om-local co crtial feet. (*) Pesults of 19P3 Lard (Pa Survey. (++) Results of 1989 Milk Ir.iral Survey I Fevisim 15 ,. 1990
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O O SMPS-1 CDCM O TABLE 3.5-9 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Eung GI-LLI PR-143 1.4E+05 4.2E+04 6.EE+03 - 2.3E+04 - 1.5E+08 PR-144 1.8E+03 1.8E+03 1.8E+03 1.8E+03 1.8E+03 1.8E+03 1.6E+03 ND-147 8.5E+06 8.5E+06 8.4E+06 8.4E+06 8.4E+06 8.4E+06 9.5E+07 W-187 2.5E+06 2.4E+06 2.4E+06 2.4E+06 2.4E+06 2.4E+06 7.6E+06 NP-239 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.5E+07 l The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. I i d 4 BNI-11600-117 3 of 3 Revision 3 - December 1983 4 y - - - , - . _
SNPS-1 ODCM TABLE 3.5-10 P ggj CHILD INGESTION OF COW'S MILK DOSE RATE CONVERSION FACTORS m2 (mrem /yr/uCi/sec) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI r2 3.5E-03 - 3.9E-04 - - - 1.0E-04 hn-24 4.3E+06 4.3E+06 4.3E+06 4.3E+06 4.3E+06 4.3E+06 4.3E+06 P-32 3.7E+10 1.7E+09 1.4E+09 - - - 1.0E+09 CR-51 -(1) - 4.6E+04 2.5E+04 7.0E403 4.6E+04 2.4E+06 MN-54 - 1.1E+07 2.9E+06 - 3.0E+06 - 9.0E+06 MN-56 - 6.2E-03 1.4E-03 - 7.5E-03 - 9.0E-01 FE-55 5.8E+07 3.1E+07 9.5E+06 - - 1.7E+07 5.7E+06 FE-59 5.4E+07 8.8E+07 4.4E+07 - - 2.5E+07 9.IE+07 C0-58 - 5.6E+06 1.7E+07 - - - 3.3E+07 CO-60 - 2.3E+07 6.9E+07 - - - 1.3E+08 NI-63 1.8E+10 9.8E+08 6.2E+08 - - - 6.6E+07 NI-65 9.5E-01 8.9E-02. 5.2E-02 - - - 1.lE+01 CU-64
- 3.7E+04 2.3E+04 -
9.1E+04 - 1.8E+06 IN-65 2.4E+09 6.5E+09 4.1E+09 - 4.1E+09 -- 1.1E+09 - ZN-69M 2.5E+04 3.6E+04 3.3E+03 - 2.2E+04 - 2.2E+06 BR-83 - - 2.3E-01 - - - - RB-86 - 4.0E+09 2.4E+09 - - - 2.5E+08 SR-89 3.0E+09 - 8.6E+07 - - - 1.2E+08 SR-90 6.6E+10 - 1.7E+10 - - - 8.9E+08 SR-91 6.2E+04 - 2.4E+03 - - - 1.4E+05 SR-92 1.1E+00 - 4.2E-02 - - - 2.0E+01 Y-90 1.5E+02 - 4.1E+00 - - - 4.4E+05 Y-91M 1.5E-19 - - - - 2.9E-16 ; Y-91 1.8E+04 - 4.8E+02 - - - 2.4E+06 ) Y-92 1.2E-04 - 3.5E-06 - - - 1.4E+02 ' Y-93 5.1E-01 - 1.4E-02 - - - 7.6E+03 ZR-95 1.8E+03 3.9E+02 3.5E+02 - 5.6E+02 - 4.IE+05 ZR-97 9.0E-01 1.3E-01 7.7E-02 - 1.9E-01 - 2.0E+04 f i BN1-11600-11B 1 of 3 Revision 3 - December 1983 e O O
O O ShPS-1 ODCM O TABLE 3.5-10 (CONT *D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI NB-95 1.4E+05- 5.5E+04 3.9E+04 - 5.2E+04 - 1.0E+08 M0-99 - 3.9E+07 9.7E+06 - 8.4E+07 - 3.2E+07 TC-99M 6.5E+00 1.3E+01 2.1E+02- - 1.8E+02 6.4E+00 7.2E+03 RU-103 1.9E+03 - 7.4E+02 -- 4.8E+03 - 5.0E+04 RU-105 1.9E-03 - 6.8E-04 . 1.6E-02 - 1.2E+00 RU-106 4.9E+04 - 6.1E+03 - 6.6E+04 - 7.6E+05 AG-110M 1.1E+08 7.6E+07 6.1E+07 - 1.4E+08 - 9.0E+09 56-124 1.3E+07 2.4E+05 5.0E+06 3.0E+04 - 9.8E+C6 3.6E+08 TE-125M 3.8E+07 1.0E+07 5.1E+06 1.1E+07 - - 3.7E+07 TE-127M 1.3E+08 3.4E+07 1.5E+07 3.0E+07 3.6E+08 - 1.0E+08 TE-127 1.5E+03 4.0E+02 3.2E+02 1.0E+03 4.,c+03 - 5.8E+04 TE-129M 1.3E+08 3.6E+07 2.0E+07 4.2E+07 3.8E+08 - 1.6E+08 TE-129 7.8E-10 2.2E-10 1.8E-10 5.5E-10 2.3E-09 - 4.8E-08 TE-131M 7.9E+05 2.7E+05 2.9E+05 5.6E+05 2.6E+06 - 1.1E+07 TE-132 5.0E+06 2.2E+06 2.7E+06 3.2E+06 2.1E+07 - 2.2E+07 I-130 4.2E+05 8.6E+05 4.4E+05 9.4E+07 1.2E+06 - 4.0E+05 1-131 3.1E+08 3.1E+08 1.8E+08 1.0E+11 5.1E+08 - 2.7E+07 1-132 1.6E-01 2.8E-01 1.3E-01 1.3E+01 4.4E-01 - 3.4E-01 1-133 '4.1E+06 5.1E+06 1.9E+06 9.5E+08 8.5E+06 - 2.1E+06 I-134 2.0E-12 3.7E-12 1.7E-12 8.5E-11 5.7E-12 - 2.5E-12 1-135 1.3E+04 2.3E+04 1.1E+04 2.1E+06 3.6E+04 - 1.8E+04 CS-134 1.2E+10 1.9E+10 4.1E+09 - 6.0E+09 2.2E+09 1.0E+08 C5-136 4.6E+08 1.3E+09 8.2E+08 - 6.7E+08 1.0E+08 4.4E+07 C5-137 1.8E+10 1.7E+10 2.6E+09 - 5.7E+09 2.0E+09 1.IE+08 BA-139 1.1E-07 5.7E-11 3.1E-09 - 5.0E-11 3.4E-11 6.2E-06 BA-140 5.4r_+07 4.7E+04 3.IE+06 - 1.5E+04 2.8E+04 2.7E+07 LA-140 9.4E+00 3.3E+00 1.0E+00 - - - 9.1E+04 LA-142 2 0E-11 6.3E-12 2.0E-IZ - - - 1.2E-06 CE-141 r,.7E+03 4.8E+03 7.2E+02 - 2.IE+03 - 6.0Et06 CE-143 9.0E+01 4.9E+04 7.1E+00 - 2.1E+01 - 7.ZE+05 CE-144 8.2E+05 2.6E+05 4.4E+04 - 1.4E+05 - 6.7E+07 PR-143 3.3+02 9.8E+01 1.6E+01 - 5.3E+01 - 3.5E+05 BN1-11600-118 2 of 3 Revision 3 - December 1933
h SNPS-1 ODCM TABLE 3.5-10 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ND-147 2.lE+02 1.7E+02 1.3E+01 - 9.lE+01 - 2.6E+05 W-187 1.4E+04 8.3E+03 3.7E+03 - - - 1.2E+06 NP-239 8.3E+00 6.0E-01 4.2E-01 - 1.7E400 - 4.4E+04 II) The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. BN1-11600-118 3 of 3 Revision 3 - December 1983 O O O
O O SMPS-1 ODCM O i TABLE 3.5-11 i l P,9)
' CHILD INGESTION OF GOAT'S MILK DOSE RATE CONVERSION FACTORS m 2 (mrem /yr/pCi/sec) i i
! Nuclide Bone Liver T. Body thyroid Kidney Lung GI-LLI F-18 3.0E-04 - 3.3E-05 - - - 8.8E-06 NA-24 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 j P-32 4.4E+10 2.1E+09 1.7E+09 - - - 1.2E+09 CR-51 -(1) - 5.5E+03 3.1E+03 8.3E+02 5.6E+03 2.9E+0c MN-54 - 1.3E+06 3.4E+05 - 3.6E+05 - 1.1r oo MN-56 - 7.5E-04 1.7E-04 - 9.0E-04 - 1.1E-01 3 FE-55 7.5E+05 4.0E+05 1.2E+05 - - 2.3E+05 7.4E+04 FE-59 7.0E+05 1.1E+06 5.7E+05 - - 3.3E+05 1.2E+06 CO-58 - 6.8E+05 2.1E+06 - - - 3.9E*06 C0-60 2.8E+06 8.2E+06 1.5E+07 NI-63 2.2E+09 1.2E+08' 7.4E+07 - - - 7.9E+06 4 NI-65 1.1E-01 1.1E-02 6.2E-03 - - - 1.3E+00 l' 64 - 4.2E+03 2.5E+03 - 1.0E+04 - 2.0E+05
- ZN-65 2.9E+08 7.8E+08 4.9E+08 -
4.9E+08 - 1.4E+08 ZN-69M 3.0E403 4.3E403 3.9E+02 - 2.6E+03 - 2.7E+05 BR-83 - - 2.8E-02 - - - - RB-86 4.7E+08 2.9E+08 - - - 3.1E+07 SR-89 6 .3E+09 - 1.8E+08 - - - 2.4E+08 SR-90 1.4E+11 - 3.5E+10 - - - 1.9E+09
; SR-91 1.3E+05 -
4.9E+03 - - - 2.9E+05 j SR-92 2.2E+00 - 8.9E-02 - - - 4.2E+01 ] Y-90 1.9E+01 - 5.0E-01 - - - 5.3E+04
- Y-91M -
1.8E - - - - 3.4E-17 l Y-91 2.1E+03 - 5.7E+01 - - - 2.9E+05 i Y-92 1.5E-05 - 4.2E-07 - - - 1.7E+01 i Y-93 6.1E-02 - 1.7E-03 - - - 9.1E+02 i ZR-95 2.1E+02 4.7E+01 4.2E+01 - 6.7E+01 - 4.9E+04 ZR-97 1.1E-01 1.6E-02 9.2E-03 - 2.2E-02 - 2.4E+03 BN1-11600-119 I of 3 Revision 3 - December 1983 1
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g . n/ w. SNPS-1 ODCM o TABLE 3.5-12 (CONT'D) Nuclide Bone T. Body-Liver Thyroid Kidney M GI-LLI HB-95 1.4E+C6 5.4E+05 3.8E+05 - 5.0E+05 - 9.9E+08 M0-99 - 5.6E+04 1.4E+04 - 1.2E+05 - 4.6E+04 TC-99M - - 1.1E-19 - - - 3.8E-18 RU-103 7.0E+07 - 2.7E+07 - 1.8E+08 - 1.8E+09 RU-106 2.3E+09 - 2.9E+08 - 3.2E+09 - 3.6E+10 AG-110M 4.5E+06 3.CE+06 2.4E+06 - 5.7E+06 - 3.6E+08 SB-124 3.4E+06 6.4E+04 1.3E+06 8.2E+03 - 2.6E+06 9.6E407 TE-125M 3.0E+08 8.0E+07 3.9E+07 8.3E+07 - - 2.9E+08 TE-127M 1.1E+09 2.9E+08 1.3E+08 2.6E+08 3.1E+09 - 8.7E+08 TE-127 2.0E 5.5E-11 4.4E-11 1.4E-10 5.8E-10 - 8.0E-09 1 TE-129M 8.6E+08 2.4E+08 1.3E+08 2.8E408 2.5E+09 - 1.0E+09 i TE-131M 3.5E+02 1.2E+02 1.3E+02 2.5E+02 12E+03 - 4.9E+03 TE-132 1.0E406 4.6E+05 5.5E+05 6.6E+05 4.2E+06 - 4.6E+06 I-130 8.7E-07 1.7E-06 9.0E-07 1.9E-04 2.6E-06 - 8.2E-07 I-131 3.9E406 3.9E+06 2.2E+06 1.3E+09 6.4E+06 - 3.5E+05 I-133 1.4E-01 1.7E-01 6.6E-02 3.2E+01 2.9E-01 - 7.0E-02 , 1-135 1.6E-17 2.BE-17 1.3E-17 2.5E 15 4.3E-17 - 2.1E-17 i CS-134 4.8E+08 7.9E+08 1.7E+08 - 2.5E+08 8.8E+07 4.3E+06 CS-136 7.3E+06 2.0E+07 1.3E+07 - 1.1E+07 1.6E+06 7.0E+05
- CS-137 7.5E+08 7.2E+08 1.1E+08 -
2.4E+08 8.5E+07 4.5E+06 BA-139 - - - - - - - i BA-140 2.0E+07 1.8E+04 1.2E+% - 5.7E+03 1.0E+04 1.0E+07 ! LA-140 2.8E-02 9.6E-03 3.0E-03 - - - 2.7E+02 l CE-!41 9.9E+03 4.9E+03 7.3E+02 - 2.2E+03 - 6.1E+06 CE-143 1.5E-02 8.4E+00 1.2E-03 - 3.5E-03 - 1.2E+02 CE-144 1.2E+06 3.7E+05 6.2E+04 - 2.0E+05 - 9.5E+07 l PR-143 1.5E+04 4.6E+03 7.6E+02 - 2.5E+03 - 1.6E+07 4 i BN1-11600-120 2 of 3 Revision 3 - Decenber !" 1
- w -9
SNPS-1 00CM TABLE 3.5-12 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ND-147 5.4E+03 4.4E+03 3.4E+02 - 2.4E+03 - 6.9E+G6 W-187 1.6E-02 9.7E-03 4.4E-03 - - - 1.4E+00 NP-239 2.1E-01 1.5E-02 1.1E-02 - 4.4E-02 - 1.1E+03 (1) The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. BN1-11600-120 3 of 3 Revision 3 - December 1983 O O O
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~3 14 i CC E E W W Q Q e=* M D E E N CD CE C2 1 6 4 6 4 CE E E W E Ch. W E E ha. W W W E E U N N CC CC m m"mNmN>= >= >= >- >= N CD e , . -
.---.-y...p-.m- . - - ~ - - . --w m -m,:-.m - -. - . ,,. w- s --. - - - ,s-- - , - , - -
iNPS-1 ODCM TABLE 3.5-13 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ZR-97 1.9E400 3.3E-01 1.5E-01 - 3.3E-01 - 2.1E+04 NB-95 2.6E405 1.1E+05 6.3E+04 - 7.8E+04 - 9.2E+07 M0-99 - 1.0E+08 2.0E+07 - 1.5E+08 - 3.3E+07 TC-99M 1.3E401 2.8E+01 3.6E+02 - 3.0E+02 1.5E+01 8.1E+03 RU-103 3.9E+03 - 1.3E+03 - 8.1E+03 - 4.7E+04 RU-105 3.9E-03 - 1.3E-03 - 2.9E-0^ - 1.6E+00 RU-106 1.0E+05 - 1.3E+04 - 1.2E+0S - 7.6E+05 AG-110M 2.1E+08 1.5E+08 1.0E+08 - 2.2E+08 - 7.8E409 58-124 1.3E+07 2.4E+05 5.0E+06 3.0E+04 - 9.8E+G6 3.6E+08 TE-125M 7.8E+07 2.6E+07 1.1E+07 2.6E+07 - - 3.7E407 TE-127M 2.5E+08 8.4E+07 3.1E+07 7.3E+07 6.3E+08 - 1.0E+08 TE-127 3.2E403 1.1E403 6.8E+02 2.6E+03 7.7E+03 - 6.7E404 i TE-129M 2.7E+08 9.2E+07 4.1E+07 1.0E+08 6.7E+08 - 1.6E+08 ! TE-129 1.6E-09 5.7E-10 3.8E-10 1.4E-09 4.1E-09 - 1.3E-07 TE-131M 1.7E+06 6.7E+05 5.5E+05 1.4E+06 4.6E+06 - 1.1E+07 TE-132 1.0E+07 5.1E+06 4.8E+06 7.5E+06 3.2"+07 - 1.9E+07 I-130 8.7E+05 1.9E+06 7.7E+05 2.2E+08 2.1E*06 - 4.1E+05 I-131 6.4E+08 7.5E+08 3.3E408 2.5E+11 8.8E+08 - 2.7E407 I-132 3.2E-01 6.5E-01 2.3E-01 3.1E+01 7.3E-01 - 5.3E-01 ' I-133 8.7E+06 1.3E*07 3.7E+06 2.3E+09 1.5E407 - 2.2E+06 I-134 4.1E-12 8.5E-12 3.0E-12 2.0E-10 9.5E-12 - 8.8E-12 I-135 2.7E+04 5.4E404 2.0E+04 4.8E+06 6.0E+04 - 1.9E+04 CS-134 1.9E+10 3.6E+10 3.6E+09 - 9.2E*09 3.8E+09 9.7E+07 CS-136 9.0E+08 2.6E+09 9.9E+08 - 1.1E+09 2.2E+08 4.0E407 CS-137 2.9E+10 3.4E+10 2.4E+09 - 9.1E+09 3.7E+09 1.1E+08 BA-139 2.3E-07 1.5E-10 6.6E-09 - 9.1E-11 9.1E-11 1.4E-05 BA-140 1.1E408 1.1E+05 5.7E+06 - 2.6E+04 6.8E+04 2.7E+07 LA-140 2.0E+01 7.7E+00 2.0E+00 - - - 9.1E+01 LA-142 4.1E-11 1.5E-11 3.6E-12 - - - 2.6E-06 CE-141 1.9E+04 1.2E+04 1.4E+03 - 3.6E+03 - 6.1E+06 CE-143 1.9E+02 1.3E+05 1.4E401 - 3.7E+01 - 7.4E+05 CE-144 1.2E+06 4.8E+05 6.6E+04 - 1.9E+05 - 6.7E+07 PR-143 6.8E+02 2.SE+02 3.4E+01 - 9.4E+01 3.6E+05 BNI-11600-121 2 of 3 Revision 3 - Decenber 1983 0 9 9
O O SNP5-1 000s O TABLE 3.5-13 (CONT *D) Nuclide Bone Liver T. Body Thyroid Kidney y GI-LLI 2.6E+01 1.6E+02 - 2.6E+05 ND-147 4.1E+02 4.2E+02 - 7.1E+03 - - 1.2E+06 W-187 2.9E+04 2.1E+04 - 8.9E-01 3.1E+00 - 4.6E+04 NP-239 1.8E+01 1.6E+00 - (1) The dash (-) indicates insufficient data or that the dose factor is <l.0E- 20.
)
i 3 of 3 Revision 3 - December 1983 BNI-Il600-121
i l. ! ll !llllilj) i){ll1fl fl ' 3 I 659551466760595 000000000000000 789514651343 000000100000 8 9 1 r O L - ++++ - +++ + + + + + + + + + + + ! - + - + + + e L EEEEEEEEEEEEEEE EEEEEEEEEEEE b 159214299065 m I 8125875144911.I2 . e c G 891281713172219 - 321355125142 e D 3 n 5 4 55 o 0 0 00 i s
+ + ++
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+ OCQQQQCOOOMQQQQQQMOMOMOOOMOQQ
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*
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SNPS-1 ODCM TABLE 3.5-14 (CONT'D) T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone Liver 1.lE+01 - 4.3E+04 PR-143 8.1E+01 3.0E+01 4.0E+00 - I.9E+0I - 3.2E+04 ND-147 4.9E+01 5.0E+01 3.1E+00 -
,8.5E+02 - - - 1.4E+05 W-187 3.5E+03 2.5E+03 5.SE+03 1.9E-01 I.IE-01 - 3.8E-01 -
NP-239 2.1E+00 1.0E- 20. (1) The dash (-) indicates insufficient data or that the dose factor is 3 of 3 Revision 3 - December 1983 UN-11600-122 O O O
SNP. CM TABLE 3.5-15 P gj CHILD INHALATION AND INGESTION OF LEAFY AND STORED VLGETABLES DOSE RATE CONVERSION FACTORS (mrem per pCi) T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone Liver 1.4E-6 1.4E-6 1.4E-6 1.4E-6 1.4E-6 1.4E-6 H-3 - 1.9E-4 9.6E-4 1.9E-4 1.9E-4 1.9E 4 1.9E-4 1.9E-4 C-14* 1 l Pite:
- or short term releases such as from air removal pumn or from contain:nent dryweil purge vent C-14 values should be multiplied by 2.
1 l 1 of 1 Revision 15 - January 1990 BNI-II600-123 _
SNPS-1 ODCM IABLE 3.5-16 P yj CHILD INGESTION OF GOAT'S MILK DOSE RATE CONVERSION FACTORS (mrem per pCi) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 - 8.6E-7 8.6E-7 8.6E-7 8.6E-7 8.6E-7 8.6E-7 C-14* 4.7E-4 8.9E-5 8.9E-5 8.9E-5 8.9E-5 8.9E-5 8.9E-5
*See Note in Table 3.5-15 j
BN1-11600-125 1 of 1 Revision 3 - December 1983 9 e 9 9
U O
~
~O SNP5-1 ODCM TABLE 3.5-17 P
gy INFANT INGESTION OF GOAT'S MILK DOSE RATE CONVIRSION FACTORS (a: rem per pCi) Nuclide Bone Liver T. Body Thyroid Kidney Lung GT-LLI H-3 - 3.5E-12 3.5E-12 3.5E-12 3.5E-12 3.5E-12 3.5E-12 C-14* 2.4E-9 4.9E-10 4.9E-10 4.9E-10 4.9E-10 4.9E-10 4.9E-10 Note: .i *For the short term releases such as from air removal p>mp or from containment drywell purge vent. ' I C-14 values should be raitiplied by 2. i i BN1-11600-128 1 of 1 Revision 14 - January 1989
. - ._. _ _ ._ ~
SNPS-1 ODCM 3.6 OPERATION OF VENTILATION EXHAUST TREATMENT SYSTEM The Ventilation Exhaust Treatment System (see Figure 3.61) shall be used to reduce O radioactive materials in gaseous waste prior to their discharge as specified in REC Section 3.11.2.5. The dose analysis will be perfomed as described in Sections l 3.5.1 or 3.5.2. If the calculated doses exceed the limits specified above consult l REC Section 3.11.2.5. s i,
< O s
a Revision 16 - July 1990 9 BN1-11600.02-112 11.3.6-1 l_________________
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i STATiest VEteT81.ATIOmr (
- ExmAUST l CMEN. L ASOR ATORY _EXMaOST MEPA 4300 CFEB J >
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TREATesERT [ SYSTEtB OFFSAS TRE ATWEleT EXmAUST 25 CFM ; 8C"*"CO*L3 O MEPA = FsLTER I t 1 i FIGURE 3.6-1 VENTILATION EXHAUST TREATMENT SYSTEM 1 - , > i l BHORENAM NUCLEAR POWER STATION - UNIT-1 - ! t
- OFFSITE DOSE CALCULATtON MANUAL :
r feEVIS90881- AUGUST 1985 ^ I
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_ . - - ~
$NPS-1 ODCM 3.7 TOTAL DOSE FOR THE URAN!UM FUEL CYCLE g 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 member of the public, due to releases vf 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 mrem, or less), over any 12 consecutive months. 3./.1 Sources of Radiation and Radioactivity _ lhe uranium fuel cycle is defined in 40CFR190 to ine'lude:
- a. operations of milling of uranium ore,
- b. chemical conversion of uran 1um, !
- c. isotopic enrichment of uranium,
- d. fabrication of uranium f uel,
- e. generation of electricity by a nu; lear power plant using uranium fuel, and
- f. reprocessing of spent uranium fuel.
The maximum individual doses due to each of the processing f acilities 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 nuclear power plant using uranium fuel is more than 75 kilometers away. 3.7.2 R,adioloaical Impact of Generation of Electricity The generation of 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 The direct radiation measuring devicesTLD (plant s can be determined by measurement.Environmental Monitoring Program (REMP) and areystems) are provided listed in Tables by the Radiological 5-1 and 5-4 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 determilie the total body dere due to all sources of radiation in the uranium fuel cycle, O BN1-11600.02-112 11.3.7 1 Revision 16 - July 199') s
SNPS-1 ODCM SECTION 4
- (]
v NETEOR0 LOGICAL 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 metsorological methodology and parameters utilized in the com-puterized method for atmospheric release, t 'itical locations for receptors and their respective dispersion and depositia factors are provided for the backup method for atmospheric releases. For liquid effluent pathways a calculated dilution factor of 8.85 is used if circulation water is utilized. If service water is in use the dilution factor is Me (1.0). 4.2 PARAMETERS AND METHODOLOGY USED IN THE COMPUTERIZED METHOD 4.2.1 Meteoroloaical Data Hourly overage values (based upon 60 one-minute values) of temperature, wind speed, wind direction and temperature difference from the 33- and 150-ft levels of the Shoreham meteorological towers are used in the computerited method, to determine X/Q and 0/Q values at the locations (~] y given in Table 3.5.-8. 4,2.2 g g-Term gQ and D/Q Values
' Sector-average atmospheric cor dispersion factors ()/Q)bA g3mma dispersion factors (X/Q) gntrationand relative deposition factors (0/Q}
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 Sof tware (Rev. B.1)" (Entech Engineering Inc., P104-R3, Section 2.0 M y 1983, by J. N. Hamawi). General site specific data values that may be required for the calculation of dispersior, parameters are given in Table 4-2. The basic methodology used to obtain the (X/Q) and D/Q values is the straight-line trajectory model with Gaussian dispersion - described in Regulatory Guide 1.111, Rev. 1. The list of selected optios and varia-tions from the Regulatory Guide is as follows: i- (a) Plume depletion due to dry and wet deposi tions , as well as to enroute radioactive decay is consere tively ignored. O V BN1-11600.02-112 11.4 1 Revision 8 - February 1986 l 8
- , , ,---n
ENPS-1 ODCM (b) Plume recirculation is accounted for by making use of the conservative open-terrain recirculation correction factors in Revisinn 0 of Reg. Guide 1.111, which are also used in the X0%00 computer code (NUREG/CR-2919, Au0ust 1982). (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', (USEFA, Publication AP-26,1970) and has the additional capability of predicting the entire range of ef fects f rom 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 reletses 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 prevaili..g wind during the period of inter-est. At the Shoreham station, 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 X00D0Q computer code (NUREG/CR-2919. August 1982); the same relationship is used to 3 f replace missing wind speed data at either the 'ower or upper instrument W 1evels of the meteorological towers. (f) Sector- average ( >;/Q)S# values are not permitted to exceed the plume centerline 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 described in item (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 o zvalues are limited to a maximum value of 1000 m.
. O BN1-11GCO,02 112 !!.4 9 Revision 4 - August 1984
.I 1
1 SNPS-1 ODCM j
-(h)-LSitespecific. sector-anddistance-der.endentterrainheightsareemployed Q in connection with elevated releases. These terrain heights (as given in V Table 3.5-8) represent the maximum heights between the release point .and :1 the locations where the concentrations.are being calculated. in accord-
-ance with Regulstory luide.1.111 Rev. 1.
O) Relative ' deposition factors (D/Q) are calculated using the relative deposition' mtes_ given in Regulatory Guide - 1.111 Rev. 1 in graphical j form; the height-dependent curves in the guide are used as follows: > Calculated Effective Applicability Regulatory Height Range-(m) Guide 1.111 Rev. 1 Curve 0 - 15 Ground-level releases 15 - 45 30-m releases 45 - 80 60-m releases
> 80 100-m releases In addition to_ the atmospheric dispersion -factors the computerizeYA method also computes certain " effective gamma dispersion factors" -(X/0) which permit evaluation of external air and whole body Moses from figte clouds of multi-energetic gamma sources. . The basic defini ;" 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 y/Q. The gama spectrum is representative of the actual nuclide mix in the effluent. The finite cloud model is employed for both ground-level and elevatedireleases. Recirculation correction and inversion layer reflec-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.E m rgy 1968',-USAEC TID-24190, 1968, Sec. 7-5.2.2).
4.3 ~ PARAMETERS!ANDi VETh00 LOGY USED IN THE BACKUP METHUD For- gaseous eiflu nt pathways, Table 4-1 lists the critical locations _ for receptors -and tttir respective dispersion and deposition factors. The. atmospheric disp:csion and'. deposition factors were calculated utilizing Shoreham onsite r ateorological data for the 2-year period of October 1,-1973 through -September' 30,-1975,. Regulatory Guide 1.111 Rev. _0, March 1976,-- and
~
- 1. July- 1977 Rev. Several X/Q values _ were -obtained from the FinalJ Environmental Statement, NUREG-0285, dated _ October 1977, docket No. 50-322 -
Jee1 Table 4-1), O U BN1-11600-112 11.4-3 Revision 4 - August 1984 1: l a , a. . - . - - -- -- -------------
94P. JOi . TABLE 4-1 CRITICfL RECEP1TR LOCATIO6 FOR CASEOUS EFFLUEhT Cft01ATIO6 S E E E Technical Specification 3.11.2.1 3.11.2.2 3.11.2.3 3.1i2.5 Section Sections in this Manual 3.3 3.4 3.5 3.6 Limiting Criteria Instantaneous Dosa Pate to Quarterly and Annual Air Quarterly and Annual Dose to any onpn de to itole Body and Skin due to Doses die to Gama and Dose d;e to radionuclides other tran ikble Gas and dose to any onpn Beta radiatim radimutlids other than fible Gas for 31-day due to radionuclides otler than tkble Ces period tkble Gas Distarce and Direction of 1 Noble Gas: 366 neters, ifE 457 neters, ESE 3058 meters, W 3058 neters, W Peceptor frun the Plant 2 Organ: 3058 cetas, W Description of Location Location of Highest Dose Location of Highest Dose location of Highest Dose Locatic
- of Highest Dose -
Rate Long Term (Amual Average) 3 6.6E-07 sec/m3(I) 8.44E-07 sec/m 3 (2) 3.73E-03sec/m3 3./JE-GG =c/m3 (3) . Atmospheric Dispersion 4 3.73E-03sec/m3(3) Factor for Station \entila-tion ExhaustT/Q3 Short Tenn Atnospheric 5 3.6F-06 sec/m3 1.83E-06 sec/m3 (2) 1.ZE-07 sec/m3(3) 1.79E-07 sec/d (3) l Dispersion Factor for Air 6 1.79E-07 sec/m3
)
Rsova1 Pmp 7/0 2 Short Term Atnospheric 7 3.6E-06 sec/m3 1.83E-06 sec/m3(2) 1.79E-07 sec/m3 (3) 1.79E-07 sec/m3(3) Dispersim Factor for 8 1.79E-07 sec/m3
)
Cmtairment Drywell Pung 7/Q3 Bril-11600.02-109 1 of 2 Revision 15 - Janmry 1990 0 0 0
~
O O Sl@S-1 GXM - O TABLE 4-1 (Cont'd.) ,. A .B. C D. 3)' & Long Term Relative. 9 . WA. WA- 4.10E-10[I3) 4.10E-10 m
. Deposition Factor for: 10 4.10E-10m-2(3)
Station Ventilation Exhaust D/Q3 . (3)~ 1.95E-09 m -2.(3) Short Term Relative 11 ' WA - 'WA 1.952-09 m
" Deposition Factor for Air 12 1.95E-09 m
-2(3)
Remal Rap D/Q 2 WA 1.95E-09 m
-2I3) -
'1.95E-09 m (3)-
Short Term Relative 13.1 WA~ :
.s ,(3)
Deposition Factor for . '14- 1.95E-09 m Contaiment Drywell Ibrge D/03 (I lug Island Lighting Capany, Shoreham Nrlear Station -~ Unit Ore, FIML ENVIlufGTAL STATDOT, MKG 0285,~ Oober 1977, Docket 50-322.' I2) "Cmpliance With 10CFRSO Appendix I," Shorehan Nuclear Power Station - thit One, Lmg Island Lighting Capany, Docket 50.-322, SEC-119, July 30,1976._, . (3) Based on Stone & Webster calculation 19.6A-6-118,'Rev. O, and ffD calculation C-RFD-473, Rev. O. BN1-11600.02-109 2 of 2 Revision 13 - Noveter 1508
- - -- .- .---- ---1-- - - - --
~
4 SNPS-1 00CM TABLE 4-2 h GENERAL SITE SPECIFIC DATA PARAMETER VALUE Elevation of upper-level met. instru::.ents II) 33 ft above ground level Elevation of upper-level met, instruments (2) 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 m2 Station vent equivalent diameter 2.664 m May.imum effective plume height allowed 400 m Height of inversion layer aloft 600 m ( Maximum plume vertical standard deviation o = 1000 m t r*.
'l Fraction of the year that animals graze on pasture f = 1.0 p
Fraction of dhily feed that is pasture grass when f = 0.84 s the animal grazes on pasture Average transport time of activity from the feed *d into the milk and to the receptor tf = 24 hours d (1) Onnite 10 M meteorological tower (2) Offsite 400 f t meteorological tower V i BN1-11600-112 1 of 1 - Revision 13 - November 1988
SNPS-1 ODCM PART II (] V SECTION 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The purpose of this section is to identify those sampling locations from which the radiological environmental monitoring samples shall be collected pursuant to Radiological Effluent Controls 3/4-12 (Part I of the ODCM). Table 5-1, 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, locatior, and frequency of sample collection and the required analyses. The Shoreham-specific implementation of the program is given in Tables 5-2, 5-3, 5-4 and 5-5, 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. I w/ V' BN1-11600.02 11.5-1 Revision 16 - July 1990
SNPS-1 ODCM TABLE S-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM * (TYPICAL SAMPLING AND COLLECTION FREQUENCY) EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a AND/OR SAMPLE SAMPLES AND SAMPLE LOCATION COLLECTION FREQUENCY OF ANALYSIS b
- 1. DIRECT RADIATION 36 routine monitoring stations, Quarterly. Gamma dose quarterly.
DR1-DR36, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
- a. An inner ring of stations, one in-each meteorological sector in the general area of the SITE BOUNDARY, DR1-DR16;
- b. An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site, DR17-DR25;
- c. The balance of the stations, DR26-DRJ6, to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
- The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's' dose and should be included in the sampling program.
BN1-11600.02-113 1 of 5 Revision 10 - August 1987 9 O O
> ~SNPS-1 ODCM.
TABLE 5-1 (CONT'D)- SAMPLING AND TYPE AND FREQUENCY. EXPOSURE PATHWAY NUMBER OF. REPRESENTATIVE a. COLLECTION FREQUENCY l 0F ANALYS5 AND/OR. SAMPLE- SAMPLES AND' SAMPLE LOCATION
-2. AIRBORNE Samples from 5 locations, Al-AS: Continuous sampler Radiciodine Cannister:
Radiciodine and ' operation with sample 1-131 analysis weekly. Particulates, 3 samples, Al-A3* from close collection weekly, or.
.to the 3 SITE BOUNDARY.. locations, more frequently if
' in different sectors, of the required by dust : Particulate Sampler: loading. Gross beta radioactivity-highest calculated annual average groundlevel D/Q. analysisfollowjng. filter change; Gansna isotopic analysis" 1; sample,'A4, from the vicinity
~
of a community having the highest l of composite (by calculated annual average groundlevel location) quarterly. l D/Q. I sample, AS, from a. control location.
. as for example .15-30 km distant and in the least prevalent wind direction. c 1
- 3. WATERBORNE h Grab sample semi- Gamma isotopic analysis' l
- a. Surface I sample control, WAl (Long Island 'l sample discharge, WA2 or WA3 annually. ,and tritium analysis
.semiannnally.
Sound)
' Gamma isotopic" and
- b. Ground Samples from 1 or.2 sources, Wbl, Quarterly.
tritium analysis Wb2,- only if' likely to be affected.f , J quarterly. 1 sample from downstream area with Semiannually. Gamma isotopic analysis'
- c. Sediment' form semiannually.
shoreline existing or, potential ' recreational value, Wdl.
.l -*The first and second highest D/Q sectors have radioiodine and particulate samples. The third highest D/Q sector at the SITE B0UNDARYuis approximately 150 ft from the first highest sector. l 2 of 5 Revision 4 - August-1984 BN1-11600.02-113 _
l l u
SNPS-1 ODCM TABLE 5-1 (CONT'D) EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a AND/0R SAMPLE SAMPLES AND SAMPLE LOCATION COLLECTION FREQUENCY OF ANALYSE
- 4. INGESTION
- a. Milk Samples from milking animals in Semimonthly when Gamma isotopic" and I-131 location, Ial, within 5 km distance animals are on analysis semimonthly when having the highest dose potential. pasture, monthly at animals are on pasture; If there are none, then, I sample other times. monthly at other times.
from milking animals in each of 3 areas, Ial, between 5 to 8 km distant where doses are calcu-lated to be greater than 1 mrem per yr, or if there are none available within 8 km, then a i location beused.gto17kmdistantwill I sample from milking animals at a control location, Ia2, 15-30 km distant, and not in the least prevalent wind directions.
- b. Fish and 1 sample of each commercially and Sample in season or Gamma isotopic analysis" Invertebrates recreationally important species in semiannually if they on edible por+ ions.
vicinity of plant discharge area, are not seasonal. Ib1 - Ib2. I sample of same species in areas not influenced by plant discharge, Ib3.
- c. Food Products Samples of 3 different kinds of broad Gamma Isotopic" and leaf vegetation grown nearest each of Attimeo{
harvest. I-131 analysis. two different offsite locations of highest predicted annual average ground-level D/Q, if milk sampling is not performed, Ic1 - Ic3. I sample of each of the similar broad Ganna Isotopic" and leaf vegetation grown 15-30 km distant Attimeo{ harvest. I-131 analysis. in the least prevalent wind direction if milk sampling is not performed. BN1-11600.02 ,3 3 of 5 Revision 4 - Anoust 14R4
7 s _. 7y g N] SNPS-1 ODCM
-NY TABLE 5-1 (CONT'D)
TABLE NOTATION 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 "
~
HUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 19/8, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling sche <iule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunc-tion 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 REC 6.9.1.6. 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 question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to REC 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semi-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). b 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 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 optimum dose information with minimal fading. C 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 r.ay be substituted. BN1-11600.01-113 4 of 5 Revision 1 - August 1983
m rm - - 1 SNPS-1 ODCM l I TABLE 5-1 (CONT'D) l ( TABLE NOTATION 1 1 d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more 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 perfonned on individual samples.
- Ganma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. 9 The dose shall be calculated for the maximum organ and age group, using the 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 continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. 5 of 5 Revision 4 - August 1984 BN1-11600.01-113 O O O
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- hi ni:: SNPS-1 ODCM-
-n , p 1; i TABLE.5-2 y .
y A .i RADIOLOGICAL ENVIRONMENTAL-1 N i- MONITORINGPROGRAM-(REMP) - DIRECT' RADIATION MONITORING-STATIONS Functional-
' Designation Location Code--
;(NUREG-0473) _(Shoreham REMP) location Description DR1 1S1 -Beach east:of intake, 0.3 mi. N-
'DR2 2A2- West:end of. Creek Road, 0.2 mi. NNE DR3: 3S1 Site Boundary. 0.1 mi. NE-DR4 451= Site Boundary 0.1 mi.-ENE
.DR5
- -SS2 Site Boundary. 0.1 mi. E DR6- 652 Site Boundary, 0.1 mi. ESE; DR7 :7A2 - North Country Road. 0.7 mi. SE DR8' 8A3- North Country Road..0.6 mi. SSE JDR9: 951 Service Road SNPS, 0.2 mi. S DR10 10A1 ' North Country Road. 0.3 mi. SSW-DR11D 11A1 Site Boundary 0.3 mi.'SW .
;DR12. 12A1 Meteorological = Tower, 0.9 mi, WSW DR13; 13S3 Site Coundary, 0.2 mi..W _ t
-DR14 14S2 St. Josephis Villa,: 0.4 -mi WNW:
DR15- -15S1 Beach west :of intake, 0.3 mi. NW
~ ( 'DR16L 1652 Site Boundary 0.3 mi..NNW
- DR17 - SE2 Calverton, 4.5 mi. E .
DR18. .FE1 .LILC0 R0W,: 4.8 mi . ESE 1DR19 7El- Calverton.f4.9-mi.--SE DR20 8E1 Calverton,'4.4 mi.-SSE __ 4 DR21 9El -Brookhaven National Laboratory, t 5.0=mi. S-110El' , Ridge' Substation,: 4.0 mi . .SSW DR22 s DR2, 11El -LILCO R0W. 4.7 mi. SW lDR24: '12011> North Shore Beach Substation, -
. 3.7 miu WSW :
!DR25 E13E1- Sound Way Drive 4.5 mi. W
,DR26 501- Wildwood-State Park,'3.4 mi.-E-
- UR27 SF3: Dairy Farm, 7.8 mi 'E-
'DR28 7B1- OverhilliRoad, 1.4 mi.1SE
- DR29- 12G2 Flowerfield-Substation, 15.4 mi'.iWSW 3DR30! <12G1 Central Islip Substation, 19.9 mi. WSW
'DR31: 11G1- -MacArthur Substation 16.6 mi. SW DR32 8G1 Wading River Road,.10.1 mi~.-SSE' - .
'DR33: 6G11 -Hampton Bays Substation, 19.0 mi. ESE DR34 '6Al Sound-Road, 0.7 mi.'ESE-DR35- 2A3 Nearest' Residence, 0.3 mi. NNE DR36' 952- . East Gate SNPS, 0.3 mi. S:
BN1-11600.02-112 1 of 1 Revision 14 - January 1989'
SNPS-1 00CM TABLE 5-3 . 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) (PARTICULATESANDRAD1010 DINE Functional Designation Location Code _(NUREG-0473) (Shoreham REMP) location Description A1 6S2 Site Boundary, 0.1 mi. ESE A2 2A2 West end of Creek Road 0.2 mi. NNE A3 3S1 Site Boundary 0.1 mi. NE A4 7B1 Overhill Road, 1.4 mi. SE A5 11G1 MacArthur Substation, 16.6 mi. SW < G
< e' BN1-11600.02-112 1 of 1 . Revision 10 - August 1987
SNPS-1 ODCM TABLE 5-4
- gL
\~/ RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM (REMP)
WATERBORNE MONITORING STATIONS Functional Designation Location Code (NUREG-0473) (Shoreham REMP) QcationDescription WA1 13G2 Surface. background area, 13.2 mi. W WA2 14C1 Surface, outfall area, 2.1 mi WNW WA3 3C1 Surface, outfall area, 2.9 mi. NE Wbl 251 Potable Water, well on site, 0.1 mi NNE Wb2 13S2 Pot-51e Water, well on site, 0.2 mi. W Wdl 2A4 Seonnent, beach, 0.4 mi NNE f) l G l \ () BN1-11600.02-112- 1 of 1 . Revision 10 - August 1987
SNPS-1 ODCM TABLE S-S 4 RADIOLOGICAL ENVIRONMENTAL ' MONITORING PROGRAM (REMP) INGESTION MONITORING STATIONS Functional Designation Location Code (ShorehamREMP) location Description (NUREG-0473J le 13B1 "4',k, Goat Farm 1.90 Mi W Ia2* 10F1 Milk, Goat Farm, 9.2 Mi. SSW ; 8G2 Dairy (Cow), 10.8 Mi. SSE lb1 3C1 Fish and Invertebrates, Outfall Area, 2.9 Mi NE Ib2 14C1 Fish and Invertebrates, Outfall Area 2.1 Mi, WNW Ib3 13G2 Fish and Invertebrates, Background, 13.2 Mi, W q Ic1 881 Food Product, Local Farm, 1.2 Mi, SSE Ic2 6B21 Food Product, Condzella's Farm, 1.8 Mi, ESE Ic3 12H1 Food Products, Background Farm, 26 Mi. WSW
- Samples will be obtained fror one of the locations listed as available. Priority will be given to the first of the two locations listed. If samples are unavail-able from that location, substitution will be made from the second location listed.
O BN1-11600.02-112 1 ;f 1 Revision 15 - January 1990
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ONSITE SAMPLING LOCATIONS RADIOLOGICAL ENVIRONMENTAL -
" * MONITORING PROGRAM i . ,
SHOREHAM NUCLEAR POWER STATION -UNIT 1 l SCALE - MILts l l OFFSITE DOSE CALCULATION MANUAL. l REVISION 10 - AUGUST 1987
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SHOREHAM NUCLEAR FOWER STATIOM-UNITI OFFSITE DOSE CALCULATION MANUAL Revision 15 - Jr.nuary 1990 0 0 . O
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![v ') SNPS-1 ODCM-SECTION 6 INTERLABORATORY COMPARISON 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 p (EPA) environmental radioactivity laboratory intercomparison studies (cross-check) progre.m. Our participation code is "CJ".
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(.) 11.6-1 Revision 3 - December 1983 BN1-11600.02-112
SNPS-1 ODCM APPENDIX A DERIVATION OF A 4 O ~ A (mrem / min per Ci/cc) is the dose conversion factor for the combined fish plus shafoodpathwaysduetoaliquidradwastesystemdischarge. The doses to an organ, due to ingestion of fish and seafood (contribution from shoreline deposit is considered insignificant) containing isotope, i, were calculated by a computer code based on Regulatory Guide 1.109, Rev. 1 methodology and default parameters. The computer isotopic dose rates output were nomalized to unit intake concentra-tion with the following equation: Aq =OFi + Ds4 Cg /F
- =
where: D g4 = Calculated fish ingestion dose rate (mrem / min) to an organ, from isotope, i, (Ref. Reg. Guide 1.109 Eq. (A-3) assuming a dilution factor of 8.85.
=
( D si Calculated seafood ingestion dose rate (mrem / min) to an organ, from g isotope, i, (Ref. Reg. Guide 1.109, Eq. (A-3)) assuming a dilution factor of 8.85. C = Discharge concentration of isotope, i ( Ci/cc) 4 F = Near field dilution factor, 8.85 (unitiess) 1 O BN1-11600.02-112 A-1 Revision 15 - January 1990
I SNPS-1 ODCM APPENDIX B i DERIVATION OF P ojj , m . mrem /yr P ojj ( HC1/sec
)is the dose conversion factor due to combined effect of ingestion of leafy vegetables, ~ ingestion of stored vegetables (fruits, vegetables, andgrains),andcontaminatedgroundpathways.
The- dose delivered to organ, j due to the ccmbined effect of the 3 pathways were ' calculated for each radioisotope,1, using a computer code based on Regulatory . Guide 1.109 Rev. 1 methodology and default parameters. The computer _-isotopic dose rates output were normalized to unit isotopic release rate and-deposition factor with the equation: p , Dcij + Dtjj + D343 3.17*10-2
- C4
- D/Q where:
D = 1culated contaminated ground dose to organ, j from isotope, cij
- D Lij
= Calculated leafy vegetable ingestion dose to organ, j, from isotope, 1, 0 = Calculated sorted vegetables dose to organ, j, from isotope, 1 34)
C = Gaseouseffluentreleaserate-ofisotope,i,(Ci/yr) > 4 D/Q = eposition. factor (m-2) as used in calculation of Dcij, OLij, sij. 3.17*10-2 = Thenumberofyearg)persecond(3.17x10-8)tbesthenumb of 9C1 per C1 (10 . I l-l l. k - BN1-11600.02-112' B-1 Revision 3 - December 1983
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