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| number = ML20062C855 | | number = ML20062C855 | ||
| issue date = 10/26/1990 | | issue date = 10/26/1990 | ||
| title = Revised Draft Odcm | | title = Revised Draft Odcm | ||
| author name = | | author name = | ||
| author affiliation = PUBLIC SERVICE CO. OF NEW HAMPSHIRE | | author affiliation = PUBLIC SERVICE CO. OF NEW HAMPSHIRE | ||
Latest revision as of 19:31, 6 January 2021
| ML20062C855 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/26/1990 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20062C849 | List: |
| References | |
| NYN-90189, PROC-901026, NUDOCS 9011020195 | |
| Download: ML20062C855 (152) | |
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l I 1 l l l 1 l ODCM Part A l ~ h 1 1 l )
f-Parr A- 1 RADIOLOGICAL EFFLUENT MONITORING PROGRAMS
1.0 INTRODUCTION
i The purpose of Part A sf the ODCM (Of f-Site Dose Calculation Manual) is to describe the sampling and analysis programs conducted by the Station which provide input to the models in Part B for calculating ' liquid and gaseous i effluent concentrations, monitor setpoints, and off-site doses. The results of ' Part B calculations are used to determine compliance with the concentration and' ( dose requirements of Technical Specification 3/4.11. The Radiological Environmental Monitoring Program required as a minimum
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to be conducted -(per Technical Specification 3/4.12) is described in Part A, I with the identification of current locations of sampling stations- being. utilized
- to meet the program requirements listed in Part B. The information obtained-f rom the conduct of the Radiological Environmental Monitoring Program provides !
data on measurable levels of radiation and radioactive ~ materials in the environ-ment necessary to evaluate the relationship between quantities of radioactive materials released in effluents and resultant radiation dosec to individuals from principal pathways of exposure. The data developed in the. surveillance and monitoring programs described in Part A to the ODCM provide a means to confirm-that measurable concentrations of radioactive materials released as-a result of Seabrook Station operations are not significantly higher than expected based on-the dose models in Part B. ! Pending review and resolution of the staff's concerns regarding appl ed'~
;f[, lim persion parameters for Method I gaseous dose calculationjs,h :
hail be reduced by a factor of 10. This restjri ten will ensure com 1 nce with 10CFR20' Appendix B and.10CER$r Appendix 1. Upon satisfactory revte and resolution of theje netens regarding dispersion parameters with the se ODCM. this-rest terion will be deleted from the
- 2. Method 11 gaseous a quid dose calcuts ' one shall not be implemented until addi jtio a nformation is provided desc ng in sufficient detajl thw methodology used in Method II gaseous an quid dose calcu-ons. Upon review, approval and incorporation + of thi i hodology detail'in Part B of the ODCM, this restriction will be delete the O DCM.
4 l l l
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A.1 ; 0DCM ~ Rev.'4 L____________ e
2.0 RESPONSIBILITIES FOR PARt A All changes to Part A'of the ODCM shall be reviewed and approved by the / 'z Station Operations Review Committee (SORC) and the Nuclear Regulatory Comission prior to implementation. It shall be the responsibility of the Station Manager to ensure that the OOCH is used in the performance of the surveillance requirements and administrative :entrols of the appropriate' portions of the Technical l l Specifications. l l l kN
/
f l l l l l A.2-1 ODCM Rev. 4
3.0 LIOUl0 EFFtVENT SAMPLING AND ANALYSIS PROGRAM
?s ws Radioactive liquid wastes shall be sampled and analyzed in accordance
' Y with the program specified in Table.A.3-1 for Seabrook Unit 1. The risults of the radioactive analysis shall be used as appropriate with the methodology of , Part B of the 00CM to assure that the concentrations of liquid effluents at the point of release from the multiport diffuser of the circula. ting water system are maintained within the limits of Technical Sprc1fication 3.11.1.1 j for Unit 1. I i Radioactive ef fluent inforcation for li;Jids obtained f rom this-sampling and analysis program shall also be used in conjunction with the f j methodologies in Part B to demonstrate compliance with the dose objectives and ' surveillance requirements of Technical Specifications 3/4.11.1.2, 3/4.11.1.3, and 3/4.11.4. l si s, .' g-
/
j i A.3-1 ' I ODCM Rev. 4 li
TABL E A.3-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit Minimum Type of of Detection , Liquid Release Sampling Analysis Activity (LLD) (1) Type Frequency Frequency Analysis (uct/ml) P P Principal Gamma A. Liquid Emitters (3) 5x10-7 Radwaste Each Batch Each 3atch Test Tanks I-131 1x10-6 (Batch M Dissolved _and 1x10-5 Release)(2) P Entrained Gases
'One Batch /M (Ganuna Emitters)
L 1x10-5 di -p M(4) 11 - 3 Each Batch Composite Gross Alpha 1x10-7 Sr-89, Sr-90 5x10-8
-P Q(4)
Each Batch Composite Fe-55 1x10-6 W Principal Gansna B. Turbine Building .W Emitters (3) 5x10-7
' Sump Effluent (BJ Grab Sample.
1-131 1x10-6
'o 8
(Continuous M Dissolved and
- Release (5) W I 1x10-5 Grah Sample Entrained Gases I.
,E - (Gansna Emitters)
S c - ._ _ w., , , .. . . . _ . . ,
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T ABLE A.3-1 Radioactive Liquid Waste Sampilnq and Analysis Program (continued) Lower Limit Minimum Type of of Detection Liquid Sampling Analysis Activity (LLD) (1) Release Frequency Analysis (ucl/ml) Type Frequency M H -3 1x10-5 W Grab Sample Gross Alpha 1x10-7 Sr-89, Sr-90 5x10-8 W Q Grab Sample 1x10-6 Fe-55
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Y Principal Gamma W W C. ' Steam Generator Emitters (3) 5x10-7 Blowdown Flash Grab Sample Tank (6)(8) I-131 1x10-6 (Continuous M Dissolved and 1x10-5 Release)(5) 'W Grab Sample Entrained Gases (Gamma' Emitters) H-3 1x10-5 W M Grab Sample 1x10-7 o Gross Alpha
,8
- o Sr-89. Sr-90 5x10-8 W Q
- Grab Sample 1x10-6
.Ie-55
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.__S___- _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _
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TABLE A.3-1 Radioactive liquid Waste Sampling and Analysis Program l (continued) Lower Limit Liquid Minimum Type of of Detection Release Sampling Arialysis Activity (LLD) (1). Type Frequency Frequency Analysis (ucl/ml) W W Principal Gaavaa D. ' Service Water (7) Emitters (3) 5 x10-7 Grab Sample 1-131 1x10-6 W M Dissolved and Grab Sample Entrained Gases 1x10-5 (Gansna Emitters) W M H-3 1x10-5 Grab Sample p Gross Alpha 1 x10-7 Y Sr-89, Sr-90 5x10-8 W Q
. Grab Sample re-55 '1x10-6 P - Prior to Discharge-W - Weekly M - Monthly g Q - Quarterly n
'.E 2
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TABLE A.3-1 1 Notations _ j 7 l (1)The LLO is defined, for 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 percent i probability with only 5 percent probability of falsely concluding that a blank observation represents a 'real' signal, i For a particular measurement system, which may include radiochemical [ separation: 4.66 s b LLD = E x V x 2.22 x 106 x Y x exp (-Ac.t) f Where: l LLO = the 'a priori' lower limit of detection (microcurie per unit ' mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank samle as appropriate (counts per minute),
~
E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), ;
,j 2.22 x 10-6 = the number of disintegrations per minute per '
/ microcurie.
Y = the f ractional radiochemical yield, when applicable,
'A = the radioactive decay constant for the particular radionuclide (s-I), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and At should be used in the calculation. I
)
It should be recognized that the LLO is defined as an a_ oriori (before the I I fact) limit representing the capability of a measurement system and'not as an a costeriori (af ter the f act) limit for a particular measurement, r i (2)A batch release is the discharge of liquid wastes of a' discrete volume, i Prior to sampling for analyses, each batch shall be. isolated, and then thoroughly mixed to assure representative sampling. A.3-5 1 f ODCM Rev. 4
TABLE A.3-1 No*.ations (Entinued) V , (3)The principal gama emitters.for which the LLO specification applies . include the following radionuclides: Mn-54, Fe-59, Co-58,,Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only th(se nuclides are to be. considered. Other gama . peaks that- are i identifiable, together with those of the above nuclides, shall also be l analyzed and reported in t.he Semiannual Radioactive Effluent Release Isotopes Report which are not in accordance with Technical Specification 6.8.1.4.- detected should be reported as "not detected.' Values determined to be I below detectable levels are not used in dose calculations. i i (4)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. (5)A continuous release is the discharge of liquid wastes of a nondiscrete. volume, e.g., f rom a volume of a system that has an input flow during the continuous release. (6) Sampling and analysis is only required when Steam Generator Blowdown is < directed to the discharge transition structure. (7) Principal gama emitters shall be analyzed weekly in Service Water. 2 Sample and analysis requirements for dissolved and entrained gases, fv l tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gama' emitters exceeds the LLO. ; The following are additional sampling and analysis requirements: l l a. PCCW sampled and analyzed weekly for principal gama emitters.
- b. Sample Service Water System (SWS) daily for principti gama emitters i
whenever primary component cooling water (PCCW)_ activity exceeds 1x10-3 uC/cc. ,
- c. With the PCCW System radiation monitor inoperable, sample PCCW and'SWS daily f or: principal gamma emitters,
- d. With a confirmed PCCW/SWS leak and PCCW activity in excess of lx10-4' uC/cc, sample SWS every 12 hours for principal gama emitters.
- e. The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity to detect a PCCW/SWS leak is equal l
to or greater than that of en SWS radiation monitor located in the l unit's combined SWS discharge, with an LLO of 1x10-5 uC/cc. If this- l' sensitivity cannot be achieved, the SWS will be sampled once every-12 hours. , (8)lf the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be sampled and- analyzed' for Iodine-131 and principal gama emitters prior to release. A.3-6 l ! ODCM Rev. -
~
~
4.0 GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAN c3
".9
" Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table A.4-1 for Seabrook Unit 1. The results of the radioactive analyses shall be used as appropriate with the methodologies of Part B of the 00CM to assure that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond-the site boundary are within ,the limits of Technical Specification 3.11.2.1 for Unit 1.
Radioactive effluent information for gaseous wastes obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part B to demonstrate compliance with_the dose objectives and 4 1 surveillance requirements of Technical l Specifications 3/4.11.2.2, 3/4.11.2.3, 3/4.11.2.4, and 3/4.11.4. .. n Y?;!
/
1 l l . d (
' t A.4-1 i
ODCM Rev.s4-
1 l t TABLE A.4-1 Radioactive Gaseous Waste Sampling and Analysis Program Minimum lype of Lower Limit Gaseous Activity of Detection (l) Samp1tng Analysis Helease Analysis (LLD) (uC1/cc) Frequency Frequency Type Principal Ganssa Emitters (2) 1x10-4
- 1. Plant Vent M(3)(4) M Grab Sample 1x10-6 11 - 3 w(6) I-131 1 x10-12 Continuous (5)
Charcoal Sample
? Principal Gansna Emitters (2) 1x10-Il I Continuous (5) w(6)
. Pa rt Iculate Sample M Gross Alpha 1x10-Il' Continuous (5)
Compostte Part iculate Sample Sr-89, Sr-90 -1x10-Il Continuous (5) Q Composite Particulate
@ Sample 2 %'~ Principal Gansna Emitters 1x10-4
- M(7) M(7)
. 2. Condenser Air .
Removal Exhaust Grah Sample 1x10-6 ' c- 11 - 3 h
-, ,- - ,- .- -,- _. ..m.3 w . - -# -- .,,- , ._,-..-2 _-.m . . . c%,g,..-_ ,.mm..
N-TABLE A 4-1 Radioactive Gaseous Waste Sampling and Analysis Program (continued) s Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection (l) Type Frequency Frequency Analysis (LLD) (uC1/cc) ] Continuous W Principal Gamma Emitters (2) 1x10-Il
- 3. Gland Steam Packing Exhauster' Particulate '
Sample Continuous W I-131 1x10-12 . Charcoal Sample ? n Continuous M Gross Alpha lx10-Il & Composite Particulate Sample Continuous Q Sr-89, Sr-90 1x10-Il Composite Particulate Sample Principal Gansna Emitters (2) 1x10-4
- 4. Containment P(3) P Purge Each Purge Grab Each Purge 1x10-6 Sample 11-3 (exide) 9 E'
?
V'
-n.., .~. - . u. s - - ~ - - . . . . -- . . . , -
, ,n,,
TABLE A.a-1 [?
~
Notations (1)The LLD is defined, for purposes of these specifications, as the smallest , concentration of radioactive material in a sample that will yield a net l count, above system background, that will be detected with 95 percent ' probability with only 5 percent probability of falsely concluding that a blank obserustion represents a 'real' signal. For a particular measurement system, which may include radiochemical separation: 4.66 s b LLO = E x y x 2.22 x 106 , y , ,,p-(- h t) , Where: , LLD = the "a priori' lower limit of detecti,an (microcurie per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 'b 2d2 x 10-6 = the number of disintegrations per minute per i mic rocu rie', Y = the f ractional radiochemical yield, when applicable, h = the radioactive decay constant for the particular _radionuclide (s-l), and At = the elapsed time between the midpoint of sample collection and the time of counting (s). , 1 Typical values of E V, Y, and tt should be.used in the calculation. I ( It should be recognized that the LLD is defined as an a oriori (before the l fact) limit representing the capability of a measurement system and not as an g Dosteriori (af ter the f act) limit for a particular measurement. l l i l l l l A.4-4 l ODCM Rev, . 4 .
- TABLE A.4-1 Radioactive Gaseous laste Sa.mpling and Analysis Program (continued) l Notations I
(2)The principal gamma emitte'rs for which the LLD specification applies includes the folleving radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, I-131, Cs-134, Cs-137, Te-141, and co-144, in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4 Isotopes which are not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations. ( )Samp11*a and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unlessi 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a
, factor of 31 and 2) the noble gas activity monitor for the plant vent has not .
l y increased by more than a factor of 3. For containment purge, requirements i apply only when purge is in operation. ('} Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. 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 Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3. (6) Samples shall be changed at least once p r seven (7) days and analyses shall be completed within 48 hodra af ter changing, or af ter removal f rom samplet. Sampling shall also be performed at least once per 24 hours for j at least seven (7) days following each shutdown, startup, or THERMAL POWER l change exceeding 15 percent of RATED THERMAL POWER within a one-hour period ( and analyses shall be completed within 48 hours of changing. When samples ' collected for 24 hours are analyzed, the corresponding LLDs may be This requirement does not apply if (1) increased by a factor of 10. analysis shows that the DOSE EQUIVALENT _I-131 concentration in the reactor ' coolant has not increased more than a factor of 31 and (2) the noble gas monitor shows that effluent activity has not increased more than a factor' of 3. (7) Samples shall be taken prior to start-up of condenser air recoval system ! when there have been indications of a primary to secondary leak. A.4-5 ODCM Rev. 4 l _~
I 5.0 RADIOLOG'rAL ENv!RONMENTAL MONITORING 5.1 lamelino and Analysis procram The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of members of the public resulting from station operation. This monitoring program is required by Technical Specification 3.12.1. The monitoring program implements Section IV.B.2 of Appendix 1 to 10CFR, Part 50, and thereby supplements the radiological ef fluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of r;,diation are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways which have been incorporated into Part B of the 00CM. The initially specified monitoring program will be effective for at least the first three years of comercial operation. Following this period, program changes may be initiated based on operational experience. . In'accordance with Technical Specification surveillance requirements, 4.12.1, sampling and analyses shall be conducted as specified in Table A.5-1 for locations shown in Section 4 of Part B to the 00CM. Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown on Tables A.5-2 and A.5-3, respectively. , It should be noted that Technical Specification 3.12.1.C requires that if milk or fresh leafy vegetable samples are unavailable from one or more sample locations required by the REMP, new specific locations for obtaining replacement samples (if available) shall be added to the REMP within 30 days, and the specific locations, from which the samples are unavailable may then be deleted from the monitoring program, in this context, the term unavailable means that samples are no longer available to be collected now or in the future for reasons such as the permission from the owner to collect the samples has been withdrawn or he has gone out of business, thus causing the permanent lose of the sample location. A . 5 -1 ODCM Rev. 4
5.2 kgM Vse Census i
^
As part of the Radiological Environmental Monitoring Program Technical Specification 3/4.12.2 requires that a land use census be conducted annually during growing season to identify within a distance of 8 km the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest 2 residence, and the nearest garden of greater than 50 m producing broad leaf vegetation. - The land use census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modifications to the monitoring program and dose assessment models are made, if necessary. This census satisfies the requirements of Section IV.3.3 of Appendix I to 10CFR Part 50. For the purpose of conductino the land use census as required by Technical Specification 4.12.2, station personnel should determine what survey methods will provide the necessary results considering the type of inforn.ation to be collected and the use to which it will be put, such as the location of potential milk animal pathway for use in routine dose calculations. Land use
'O census results shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., ro'adside identification of locations), aerial surveys, or by consulting local agricultural authorities.
Technical Specification 3.12.2.b requires that new locations identified f rom the census that yield a calculated dose of dose comitment 20 percent , greater than at'a location f rom which samples are currently being obtained be added within 30 days to the REMP. These new locations required to be added to the sampling program shall only be those from which permission from the owner to collect samples can be obtained and sufficient sample volume is available. s A.5-2 ODCM Rev. 4
TABtE A.5-1 Radiological Environmental Monitoring Program Number of Representative Samples and s Sampling and Type and frequency Exposure Pathway a Collection frequency of Analysis and/or Sample Sample Locations b 40 routine monitoring stations Quarterly. Gamma dose quarterly,
- 1. DIREC1 RADIAT10N with two or more dosimeters placed as follows:
An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; . An outer ring of stations, one in each meteorological sector, generally in the 6 to 8-km r'.3ge ? from the site; s The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and control locations.
- 2. AIRBORNE Samples from five locationsd : Continuous sampler Radiolodine Cannister:
Radiolodine and operation with sample Particulates collection weekly, or I-131 analysis weekly, Three samples from close to the three SITE BOUNDARY locations, more frequently if Particulate Sampler: o in dif ferent sectors, of high required by dust calculated long-tene average loading. 8 Gross beta radioactivity
- ground-level D/Q. analysis following filter change C-One sample from the vicinity of Gamma isotopic analysis c
~ a community having the highest of composite (by location) #' calculated long-term average quarterly.
grour.d-level D/Q.
-h I }0 TADLE A.5-1 1
(Continued) Humber of l Representative Samples and Sampilng and Type and Frr:auency Exposure Pathway a x and/or Sample Sample locations Collection Frequency of Anrjysis One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.
- 3. WATERBORNE One sample in the discharge area. Monthly grab sample. Gamma isotopic analysis e
- a. Surface monthly. Composite for Dne sample from a control location.
tritium analysis quarterly. One sample f rom area with existing Semlannually. Gamma isotopic analysis'
- b. Sediment from semlannually.
from or potential recreational value. L shoreline
- 4. INGESTION Sem1 monthly when Gamma isotopic' and 1-131
- a. Milk Samples from milking animals in analysis on each sample.
three locations within 5 km milking animals are on distance having the highest dose pasture, monthly at potential. If their are none, other times. then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.f o 8 One sample from allking animals
- at a control location, as for w
example, 15-30 km distant and in the least prevalent wind 3
~
direction. z.
-, -w, - . - . + . ---e - ..,
TABLE A 5-1 Radiological Environmental Monitoring Program N (Continued) s Exposure Pathway Number of Representative Sgmples Sampling and Type and Frequency and/or Sample and Sample Locations Collection Frequency of Analysis
- b. Fish and One sample of each of three commer- Sample in season, or Gamma isotopic analysis
- Invertebrates cially and recreationally important semiannually if they on edible portions.
species in vicinity of plant are not seasonal. discharge area. One sample of similar species in areas not influenced by plant p- discharge. , t.n
$. c. Food Products Samples of three (if practical) Honthly, when Gamma isotopic
- and I-131 different kinds of broad leaf available. analysis.
vegetationE grown nearest each of two different off-site locations of highest predicted long-term avarsge ground-level D/Q if milk r,amr l ing is not performed. 0;4 sample of each of the siellar Monthly, when Gamma isotopic
- and I-131 broad leaf vegetationE grown at available. analysis.
a control location, as for example 15-30 km distant in the least prevalent wind direction, if milk , sampling.is not performed, o O O X W m 4 [m n '"
-- , r _ -
TABLE A.5-1 (Continued) Table Notation a) Specific parameters of distance and direction sector from the centerline of the Unit I reactor, and , additional description where pertinent, shall be provided for each and every sample location in Table B.4-1 in the 00CM, Part B. Deviations are permitted from the required sampling schedule if l specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations f rom the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. 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. Identify the cause of the unavailability of samples for that pathway and identify the new location (s), if available, for obtaining replacement samples in the next Semlannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for th: 00CM reflecting the new location (s). R ' 5Y b) A thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet i* are considered as two or more dosimeters. c) Airborne particulate sample filters shall be analyzed'for gross beta radioactivity 24 hours or more af ter sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times tbs yearly mean of control samples, gasuna isotopic analysis shall be performed on the individual samples.
- d) Optimal air sampling locations are based not only on D/Q but on factors such as population in the area, year-round access to the site, and availability of power.
c) Gamma isotopic analysis means the identification and quantification of gasuna-emitting radlonuclides that l may be attributable to the effluents from the facility. i ' 8 1he dose shall be calculated for the maximum organ and age group, using the methodology and parameters g f) in the 00CM, Part B. g) If broad leaf vegetation is unavailable, other vegetation will be sampled. z~
TABLE A.5-2 8 Detection Capab111tles for Environmental Sample Analysis .I 9 Lower Limit of Detection (LLD)b N Fish and Invertebrates Milk Food Products Sediment Water AirborneParticglata (pC1/kg. wet) (DCl /kg) (pC1/kg. wet) (pC1/kg. dry) Analysis (pC1/kg) or Gas (pC1/m ) Gross Beta 4 0.01 H -3 3,000 15 130 . Mn-54 30 260 Fe-59 15 130 Co-58, 60
- 3_
30 260 [ 2a-65 Zr-Nb-95 15C 1 608 i-131 15 0.07 , 130 15 60 150 Cs-134 15 0.05 18 80 180 18 0.06 150 Cs-137 15c d Ba-La-140 15c.d O 9
=
7 h qp w' n m-p y - a m -w- w , u ~-
I TABLE A.5-2 (Continued) Table Notation a) This list does not mean that only these nuclides are to be considered. l Other peaks that are ident',fiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological ' Environmental Operating Report, b) The LLD is defined, for 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 dttected 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 1 ll0
- E
- V ' 2. 2 2
- Y
- e x p (-Mt )
Where: , LLD is the "a priori' lower limit of detection as defined above, as picoeuries per unit mass or volume; ; ' W. l
%- 4.66 is a constant derived from the Kalpha and Kb eta values for l the 95% confidence level; j sb is the standard deviation of the background counting rate or of !
the counting rate of a blank sample as appropriate, as counts per minute; E is the counting efficiency, as counts per disintegration; V is the sample size in units of mass or volume; I 2.22 is the number of disintegrations per minute per picoeurie; Y is the fractional radiochemical yield, when applicable; ! h is the radioactive decay constant for the particular radionuclide as per second; and
~
6t for environmental samples is the elapsed time between sample collection and time of counting, as seconds. l Typical values of E. V, Y, and At should be used in the calculation. , t in calculating the LLD for a radionuclide detemined by gama ray spectrometry, the background shall include the typical contributions of l other radionuclides normally present in the samples (e.g., Potassium-40 in milk samples). A.5-8 l ODCM Rev. 4. _ i
TABLE A.5-2 (Continued) It should be recognized that the LLO is defined as an i oriori (before the , fact) limit representing the capability of a measurement system and not as an g posteriori (af ter the f act) limit f or a particular measurement. This does not preclude the calculation of an a costeriori LLO for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters such as decay while sampling and during analysis. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interf ering nuclides, or other uncontrollable circumstances may render r these LLDs unachievable. .In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. c) Parent only. , d) The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an eight-day period following collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an insignificant amour.t (at least 3.6% of its original value). The ingrowth equations will assume that the supported La-140 activity at the time of collection is zero. .. e) Broad leaf vegetation only, f) If the' measured concentration minus the three standard deviation uncertainty is found to exceed the specified LLO, the sample does not have to be analyzed to meet the specified LLO. g) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with recommendations of Regulatory Guide 4.13 Revision 1, July 1977. i A.5-9 ODCM Rev, 4
~
2
- - 3 'G .
8 TABLE A.5-3 Reporting levels for Radioactivity Concentrations in Environmental Samples Fish and Invertebrates Milk Food Products Water AirborneParticglate s (pC1/kg. wet) (DC1/kg) (pC1/kg. wet) Analysis (DC1/kg) or Gas (pC1/m 1 H-3 30,000 1,000 30,000 Mn-54 400 10,000 fe-59 1,000 30,000 Co-58 . 300 10,000 Co-60 20,0L Zn-65 300 o. Zr-Nb-95 400* J. o 100** 0.9 3 1-131 100 1,000 60 1,000 Cs-134 30 10 2,000 70 2,000 Cs-137 50 20 300* Ba-ta-140 200* kx-
- Parent only.
** Broad leaf vegetation only.
E V m u- _ ---..m---_.--._=---%- - , - -
~ y. - _
1 l , l i r I
]
1 l l l , 1 l l 5 ODCM Part U r I i 1 i i 1 . 1 1 I
1 l l l SEABROOK STATION ODCM r PART 8 RADIOLOGICAL CALCULATION METH005 AND PARAMETERS I l t i t 8691R ODCMRn. 5
- - - - - .. . . . . ,.....4,
, - - , .- , e
1.0 INTRODUCTION
Part B of the 00CM (Off-Site Dose Calculation Manual) provides formal and approved methods for the calculation of off-site concentration, off-site doses and effluent monitor setpoints..and indicates the locations of environmental monitoring stations in order to comply with the Seabrook Station Radiological Effluent Technical Specifications (RETS), Sections 3/4.3.3.9, 3/4.3.3.10, and 3/4.11, as well as the REMP detailed in Part A of the manual. The ODCM forms the basis for station procedures which document the off-site doses due to station operation which are used to show compilance with the numerical guides for design objectives of Section II of Appendix I to 10CFR Part 50. The methods contained herein follow accepted NRC guidance, unless otherwise noted in the text. 1.1 Responsibilities for Part B i All changes to Part B of the 00CM shall be reviewed and approved by the Station Operations Review Committee (SORC) in accordance with Technical Specification 6.13 prior to implementation. Changes made to Part B shall be submitted to the Commission for their information in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. l It shall be the responsibility of the Station Manager to ensure that the OOCH is used in the performance of in-plant surveillance requirements a'nd i administrative controls of the appropriate portions of the Technical-Specifications, and Effluent Control Prograii. detailed in Part A of the manual. The Production Services Manager shall be responsible to ensure that the Radiological Environmental Monitoring Program described in Section 4 of Part B is implemented in accordance with Technical Specification 3/4.12 and Part A of this manual. B.1-1 8683R 00CM Rev.-
I 1.2 Summary of Methods, Oose Factors, Limits, Constants, Variables and Definitions This section summarizes the Method I dose equations which are used as the primary means of demonstrating compilance kith RETS. The concentration , and setpoint methods are identified in Table B.1-2 through Table B.1-7. Where , more refined dose calculations are needed, the use of Method II dose i determinations are described in Sections 3.2 through 3.9 and 3.11. The dose factors used in the equations are in Tables B.1-10 through B.1-14 and the Regulatory Limits are summarized in Table 8.1-1. The variables and special definitions used in this 00CM, Part B, are in Tables B.1-8 and 8.1-9. -
/
4 4 4 4 B.1-2 : 8683R OOCH Rev. 4'
TABLE B.1-1 Summary of Radiological Effluent Technical Specifications and Implementing Equations ' t Technical Specification (1) Category Method I Limit 3.11.1.1 Liquid Effluent Total fraction of Eq. 2-1 Concentration MPC Excluding Noble i 1.0 Cases ' Total Noble Gas Eq. 2-2 1 2 x 10-4 pCl/mi Concentration 3.11.1.2 Liquid Effluent Total Body Dose Eq. 3-1 Dose 5 1.5 arem in a qtr. 1 3.0 mres in a yr. Organ Dose Eq. 3-2 1 5 arem in a qtr. 1 10 mrem in a yr. 3.11.1.3 Liquid Radwaste Total Body Dose Eq. 3-1 Treatment 1 0.06 mres in a no. Operabillty Organ Dose Eq. 3-2 1 0.2 arem in a mo. 3.11.2.1 Gaseous Effluents Total Body Dose Rate Eq. 3-3 1 500 mres/yr. Dose Rate from Hoble Gases Skin Dose Rate Eq. 3-4 1 3000 mres/yr. from Noble Gases Organ Dose Rate Eq. 3-5 1 1500 mres/yr. from I-131. I-133, , Tritium and Particulates with i T1/2 > 8 Days B.1-3 ' 8683R 00CM Rev. 4
i , ~~ l i l TABLE B.1-1 (Continued) Summary of Radiological Effluent Technical Specifications and Implementing Equations (1) Technical Specification Category Method I Limit 3.11.2.2 Gaseous Effluents Gamma Air Dose from Eq. 3-6 1 5 erad in a qtr. Dose from Noble Noble Gases Gases i 10 mrad in a yr. Beta Air Dose from Eq. 3-7 1 10 mrad in a qtr. 1 Noble Gases 1 1 20 mrad in a yr. 3.11.2.3 Gareous Effluents Organ Dose from Eq. 3-8 1 7.5 mrem in a qtr. !
, Dosa from I-131, Iodines, Tritium and l.
I-133 Tritium, Particulates with 1 15 mrem in'a yr. and P.rticulates T1/2 > 8 Days ; 3.11.2.4 Ventilatlos. Organ Dose Eq. 3-8 1 0.3 arem in a mo. Exhaust Treatment 3.11.4 Total Dose (from Total Body Dose Footnote (2). 1 25 mres in a yr. All Sources) Organ Dose 1 25 mres in a yr. Thyrold Dose 1 75 arem in a yr. i 3.3.3.9 Liquid Effluent ; Monitor Setpoint ' l.lquid Maste Test Alarm Setpoint Eq. 5-1 T.S. 3.11.1.1 Tank Monitor B.1-4
-8683R 00CM Rn. 4
TABLE B.1-1
- (Continued)
Summary of Radiological Effluent Technical Specifications and Implementing Equations (1) Technical Specification Category Method I Limit 3.3.3.10 Gaseous Effluent Monitor Setpoint Plant Vent Alare/ Trip Setpoint Eq. 5-9 T.S. 3.11.2.1 Hide Range Gas for Total Body Dose (Total Body)
- Monitors Rate Alare/ Trip Setpoint Eq. 5-10 T.S. 3.11.2.1 for Skin Dose Rate (Skin) 1 l
(1) More accurate methods may be available (see subsequent chapters). (2) Technical Specification 3.11.4.a requires this evaluation only if twice the limit of equations 3-1, 3-2, 3-12, 3-15 or 3-18 is reached. If. this occurs a Method,II-calculation, using actual release point parameters.wlth annual average or concurrent meteorology and identified pathways for a real Individual, shall be r de. B.1-5 8683R_ 00CM Rev. 4
1 i l TABLE B.1-2 Summary of Method I Ecuations to Calculate : Unrestricted Area Liould Concentrations Equation Number Category Ecuation , Cg 2-1 Total Fraction of MPC in ENG = Liquids. Except Noble Gases Fj g MPC g I' 2-2 Total Activity of Dissolved NG and Entrained Noble Gases C NG (m )={C I j i from all Station Sources 2E-04 i
/
l l l l l r l l 1 l l l l l i 1 l l B.1-6 8683R 00CM Rev. 4- j 1 1
i TABLE B.1 3 Summary of Method i Ecuations to Calculate i Off-Site Ooses from Licuid Releases Equation -
)
Number CateCory (Quation i 3-1 otal Body Otb(mrem) = k , Qg DFL itb 3-2 Maximum Organ Oose 0mo(mrem) = k
, Q iOFL Imo -
g h , B 1-7 8683R 00CM Rev. 4 l
TABLE B.1 4 Summary of Method i Ecuations to Calculat_t ' Oose Rates Equation Number Category Ecuation 3-3 Total Body Dose Rate gmrem) = 0.85
- EL(R)
- from Noble Gases [)tb yr h 1DFB 1 3-4 Skin Oose Rate from Noble Gases fskin (mrem) yr = EL(R)g
- hi DF'1 3-5 Critical Organ Oose .
Rate from Iodines, D,( e r'" '(N' * { 1 0FG gg, Tritium 1-and Particulates with T 1/2 Greater Than i Eight Days , I l i l 1 i B.1-8 8683R 00CM Rev.
v e t TABLE B.1-5 Summary of Method I Ecuations to Calculate Doses to Air from Noble Gates Equation Number Category Ecuation ; 3-6 Gama Dose to Air OY 2.7E-08
- EL(R)
- Qg 0F{
from Noble Gases air (mrad) g 3-7 Beta Dose to Air 0 0 0 air (mrad) = 2.6E-08
- EL(R)
- Qg 0F from Noble Gases g t
t , f i B .'l - 9 8683R 00CM Rev.
.y
TABLE B.1-6 Summary of Method I Ecuations to Calculate Oose to an Inotvidual from Tritium locine and Particulates Equation - Number Category Equation
,3 -8 Dose to Critical D Q1 DFG ico Organ from Iodines, co (mrem) - EL(R) * ,
Tritium and Particulates i I t i B.1-10 8683R 00CM Rev. m -
l I i TABLE B.1 7 l Summary of Methods for j Setootnt Determinatient Equation - 1 Number Category Eauttien > 5-1 Liould Effluents: ! Liquid Waste Test O Tank Monitor S setpoint ( uC1 "I
)= f; p"F I"
[C,g I ' (RM-6509)
~
Chhghk$Nm- RCs,-(gph) c = lx108 , ggy , Gaseous Effluents: Plant Vent Wide Range Gas , Monitors (RM-6528-1, 2, 3) ' I 5-5 Total Body 1 tb (pCl/sec) = 588 , 5-6 Skin 1 R skin (pC1/sec) = 3000 i l 1 l i l l l l l r l l B.1-11 8683R 00CM Rev. '!
I TABLE B.1-8 i Summary of Variables Variable Definttion Units l C = Concentration at point of discharge of pC1/ml l dissolved and entrained noble gas "1" in liquid pathways from all station sources
= Total activity of all dissolved and entralned uC1 C'f0 noble gases in liquid pathways from all mi i
station sources C = Concentration of radionuclide "i"'at the point pQ_t t dl of 11guld discharge ml > i
= Concentration of radionuclide "1" pCl/ml ,
C, C - Concentration, exclusive of noble gases, of uCi pg radionuclide "i" from tank "p" at point of j ml
+
discharge . 1 I C,9 = Concentration of radionuclide "1" in mixture pCi/ml at the monitor s
= Beta dose to air mrad Da fr
= Beta dose to air at Education Center mrad OfirE
= Beta dose to air.at " Rocks" mrad OfirR Gama dose to air mrad 0,Jr -
0 = Gama dose to air at Education Center . mrad Ir E < O = Gama dose to air at " Rocks" mrad , atr R O gg = Dose to the critical organ mrem O = Direct dose -mrem d O = Gama dose to air, corrected for. finite cloud mrad ffnite B.1-12 8683R 00CM Rev. 4.
--. - e 4
TABLE B.1-8 , (continued) Summary of Variables Variable Definition Units 0, = Dose to the maximum organ mrem 3 = Dose to skin from beta and gamma mrem 0 O = Dose to the total body mrem tb 0F = Dilution factor ratio DF Minimum allowable dilution factor ratio min DF' Composite skin dose factor mrem-sec C pCl-yr s
; = Total body gamma dose factor for nuclide "i"
*'"*~*3 0FB .pC -yr I
(Table B.1-10)
*~
DFB Composite total body dose factor j c OFL itb = Site-specific, total body dose factor for a mrem < liquid release of nuclide "1" (Table B.1-ll) pCi 0FLj , = Site-specific, maximum organ dose factor for a mrom 11guld release of nuclide "1" (Table B.1-11) pC- , DFG gCO = Site-specific, critical organ dose factor for a mrom gaseous release of nuclide "i" (Table B.1-12) pC1
= Site-specific, critical organ dose rate factor mrem-sec DFGlC0 for a gaseous release of nuclide "1" pCi-yr (Table B.1-12) mreum 3 0FS I
= Beta skin dose factor for nuclide "1" pCi-yr (Table 8.1-10) mrem-see DF' I
= Combined skin dose factor for nuclide "1" pCl-yr (Table B.1-10) mrad-m ~
DFY I
= Gamma air dose factor for nuclide "1" pCl-yr (Table B.1-10)
B.1-13 3683R 00CM Rev. 4 i
1 l TABLE B.1-8 (continued) Summary of Variables l .. l l Variable Definition Units 3 0 mrad-m ] 0F I Beta air dose factor for nuclide "1" pCi-yr (Table B.1-10) j l b CO Critical or an dose rate due to lodines yr and particu ates . Skin dose rate due to noble gases *' h skin r b . Total body dose rate due to noble gases *' tb r 0/Q = Deposition factor for dry deposition of I elemental radiolodines and other particulates 2 EL(R) - Ground level to vent stack elevation release Olmensionless point (R) correction factor F d
. Flow rate out of discharge tunnel gpm or ft 3/sec F, . Flow rate past liquid waste test tank monitor gpm F = Flow rate past plant vent monitor ce seC f;fII j 2 3 Fraction of total MPC associated with Dimensionless Paths 1, 2, and 3 Ff0
- Total fraction of MPC in 11guld pathways Olmensionless (excluding noble gases) ;
MPC g = Maximum permissible concentration for uC1 radionuclide "1" (10CFR20, Appendix B, cc Table 2. Column 2) Qg Release to the environment for curies, or radionuclide "1" pcuries Qg - Release rate to the environment for pC1/sec radionuclide "1" B.1-14 8683R 00CM Rev.
- , . , , - - - , - . , - , . , . . , . . - . , ,n,~
TABLE B.1-8 , (continued) i Summary of Variables I Variable Definitior! Units , R setpoint
= Liquid monitor response for the limiting pC1/ml concentration at the point of discharge d
R = Response of the noble gas monttor at the cpm, or skin limtting skin dose rate pC1/sec j R = Response of the noble gas monitor to cpm, or tb limiting total body dose rate pCl/sec l S = Shielding factor Dimensionless F S = Detector counting efficiency from the com - mR/hr 9 gas monitor calibration pC1/cc or pC1/cc S = Detector counting efficiency for noble com mR/hr pC1/cc or pct /cc 9I gas "1" Sj = Detector counting efficiency from the cos
, liquid monitor calibration pC1/mi 1 S ig - Detector counting efficiency for ces 'i radionuclide "1" pCl/ml '
i X/Q = Average undepleted atmospheric dispersion factor (Tabics B.7-4 and 8.7-5) if' m [X/Q]Y = Effective average gamma atmospheric dispersion factor (Tables B.7-4 and B.7-5) m
'f ;
SWF = Service Water System flow rate gph PCC -
- Primary component cooling water measured UCl/ml .
(decay corrected) gross radioactivity l concentration l B.1-15 8683R 00CM Rev.
1 1 TABLE B.1-9 Definition of Terms Critical Receptor - A hypothetical or real individual whose location'and behavior cause him or her to receive 'a dose greater than any other possible-real individual. ! Dose - As used in Regulatory Guide 1.109, the term " dose," when-applied to ; individuals, is used instead of the more precise term " dose' equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When app 1'ei to the evaluation of internal deposition or : radioactivity, the term " dose," as used here, includes the prospective dose-component arising from retention in the body beyond_the period of ' environmental exposure, i.e., the dose commitment. The' dose commitment is evaluated over a period of 50 years. The dose is measured in mrem to tissue I or mrad to air. Oose Rate - The rate for a specific averaging-time (i.e., exposure period) of dose accumulation, , i ! I Llauld Radwaste Treatment System - The components or subsystems which comprise the available treatment system as shown in-Figure B.6-1, a i i l I B.1-16 ,
~
8683R 00CM'Rev. 4
._. .. ._. . . . ~ - - . -- . - _ _ - - - .. - - - - _ _ - - _ - - - - . _ _ _ - -
TABLE B.1-10 Dose Factors Specific for Seabrook Station for Noble Gas Releases
, s Gamma Total Body 8 eta Skin Combined Skin Beta Air Gamma Air',
Oose Factor Dose Factor Dose Factor Oose Factor Dose Factor! 3 3 0 3 3-( oCl-yr ) DFS g (mrem-m Radionuclide DFB, (mrem-m oCI-yr ) 04 (mrem-sec) uCi-yr 0F, (mrad-mDCl-yr ) 0FJ(mrad-mDC l i Ar-41 8.84E-03* 2.69E-03 1.09E 3.28E-03 9.30E-03 l f l Kr-83m 7.56E-08 ----- 1.81E-05 2.88E-04' ~1.93E-05 i Kr-85m 1.17E-03 1.46E-03 2.35E-03 1-. 97 E-03 '1.23E-03'
- y Kr-85 1.61E-05 1.34E-03 1.11E-03 1.95E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 1,38E-02 1.03E-02 6.17E-03 i
Kr-88 1.47E-02 2.37E-03 1.62E-02 2.93E-03 1.52E Kr-89 1.66E-02 1.01E 2.45E-02 1.06E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 2.13E-02 7 . 8 3 E-O'.
. 1.63E-02. }
Xe-131m 9.15E-05 4.76E-04 5.37E 1.11E-03 1.56E-04 l ' Xe-133m 2.51E-04 9.94E-04 1.12E-03 1.48E-03' 3.27E ,
-t Xe-133 2.94E-04 3.06E-04 5.83E-04 1.05E-03 3.'53E-04 i Xe-135m 3.12E-03 7.11E-04 =3.74E-03 7.39E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 3.33E-03 '2.46E-03 1.92E Xe-137 1;42E-03 1.22E-02 1.14E-02 1.27E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 1.20E-02 4.75E-03 _9.21E-03 i
- 8.84E-03 = 8.84 x 10-3 I
l l. I ; B.1-17
-8683R 00CM Rev. !
l l 'l
__-__y I a TABLE B.1-11 Dose Factors Specific for Seabrook Station- , for Llauld Releases Total Body Maximum Organ-Dose Factor Oose Factor Oh ttb < mrem) ORg,o (mrem' Radionucilde uct uC1 H-3 3.02E-13 '3.02E-13 i' Cr-51 -1.83E-11 1.48E-09 Mn-54 5.15E-09 2.68E-08: ; Fe-55 1.26E-08. 7.67E-08 l , Fe-59 8.74E-08 6.66E-07 Co-58 2.46E-09 1.40E-08 Co-60 6.15E 9.22E-08 ! Zn-65 2.73E 5.49E-07 : Br-83 1.30E-14 1.89E-14 l. l Rb-86 4.18E-10 6;96E-10 Sr-89 2.17E 7.59E-09 ' Sr-90 3.22E-08 1.31E-07 Mo-99 3.'72E-11 2.67E-10 Tc-99m 5.22E-13 1.95E-12 Ag-110m 1.01E-08 6.40E-07 Sb-124 1.71E-09 9.89E-09 Sb-125 6.28E-09 8.31E-09 Te-127m 7.07E-08 1.81E-06 Te-127 3.53E-10' -9.54E-08 ! Te-129m 1.54E 3.46E-06 Te-129 7.02E-14 1.05E-13 l Te-131m 3.16E-08' 2.94E-06_ i' Te-132 9.06E-08 3.80E-06 I-130 2.75E-11 3.17E-09 ) I-131 2.30E-10 1.00E-07 r I-132 6.28E'11 6.36E-11 ' I-133 3.85E-11 1.15E-08 I-134 1.19E 1.41E-12 .; I-135 , 5.33E-11 4.69E ; Cs-134 3.24E-08 3.56E-08 i Cs-136 2.47E-09 3.27E-09 i i Cs-137 ~3.58E-08 4.03E-08 Ba-140 1.70E-10 3.49E-09 La-140 ' 1.07E-10 4.14E a Ce-141 .3.85E-11 9.31E 4' Ce-144 1.96E-10 6.46E-08 Other* 3.12E 1.58E-06 . Dose factors to be used in Method I calculation for any "other" detec'te'd gamma emitting radlonuclide which is not includeo in the above 11st. _; B.1-18 ! l 8683R 00CM Rev. j I
I TABLE B' 1 12. j Dose and Dose Rate Factors Soecific for Seabrook Sta* ion for Iodines, Tritium ani 7 articulate Releases j Critical Organ Critical Organ i Dose Factor Dose Rate Factor j
#'* 5'C OFG )'
Radionuclide ico (*uCi ) 0FG i ' coy- (*"'r*~uCi H-3 3.08E-10 9.71E-03' 0 Cr-51 8.28E-09' 2.91E-01 i Mn-54 1.11E-06 4.38E+01' Fe-59 1.06E-06 3.53E+01- -; Co-58 5.56E-07 2.00E+01-Co-60 l 1.21E-05 5.42E+02 i Zn-65 2.33E-06 7.82E+01 ! Sr-89 1.98E-05 6.24E+02 L Sr-90 7.21E-04' 2.27E+04. Zr-95 1.10E-06 3.63E+01 Nb-95 2.01E-06 6.,40E+01 1 Mo-99 1.63E-08 5.39E-01 Ru-103 Ag-110m 3.03E-06 9.62E+01 j 5.02E-06
~
1.80E+02-Sb-124 1.83E-06 6.15E+01 , I-131 1.47E-04 4.64E+03-I-l33 .1.45E-06 4.57E+01 : Cs-134 ' 5.62E-05 1.81E+03 Cs-137 5.47E-05 1.79E+03 Ba-140 1.55E-07 5.01E+00 ! Ce-141 2.65E-07 8.45E400 Ce-144 -6.09E-06 1.93E+02 1
', Other* 4.09E-06 1.29E+02' l
l Dose factors to be used in Method I calculations'for any "Other" detected gamma emitting radionuclide which is not included in the above list. i B.1-19 1 8683R - 00CM Rev. , l
i TABLE B.1-13 , Combined Skin Oose Factors SDecific for Seabrook Station Special Receptors \ for ; Noble Gas Release Education Center The " Rocks" ! Combined Skin Combined Skin Dose Factor Dose Factor ~ j Radlonuclide DFjE5 ') r DFlRI ') r Ar-41 1.57E-02 9.73E-02' Kr-83m 2.35E-05 1.07E-04 Kr-85m 3.84E-03 .3.16E-02 ' Kr-85 2.16E-03 2.29E-02 Kr-87 2.31E-02 2.00E-01 Kr-88 2.23E-02 1.25E Kr-89 3.73E-02 2.68E-01 Kr-90 3.15E-02 2.14E-01 - Xe-131m 9.52E-04~ 8.96E-03 Xe-133m 1.99E-03 1.87E-02 Xe-133 9.20E-04 7.16E-03 f Xe-135m 5.24E-03 3.07E-02 Xe-135 5.32E-03 4.23E-02 ' Xe-137 2.14E-02 .2.16E-01 ' Xe-138 1.78E-02 1.21E-01 (1) See Seabrook Station Unit 1 Technical Specification Figure 5.1-1. ; t i 4 i
'l
.i l
B.1-20 8683R 00CM Rev. '!
1 TA8LE B.1-14 Dose and Dose Rate Factors Specific for Seabrook Station- ! Special Receptorstl> for Iodine. '! Tritium, and Particulate Releases Education Center The " Rocks" Critical Organ Critical Organ Critical Organ' Critical Organ.- ~ Dose Factor Oose Rate Factor Oose Facter Oose Rate Factor. ' OFG F OFG,coE(mrem-see) DFG 0FG,coR(mrem-see Radionuclide lcoE(mrem uCi i uCt-yr icoR(mrom) uCi i uCi-yr I H-3 6.45E-11 2.03E-03 6.85E-10 2.16E-02. Cr-51 4.98E-09 2.12E-01 2.68E-08 1.07E+00 Mn-54 1.39E-06 6.24E+01 5.84E-06 2.55E+02 Fe-59 3.09E-07 1.29E+01 1.74E-06 6.78E+01 Co-58 3.89E-07 -1.72E+01 2'01E-06
. 8 llE+01 Co-60 2.17E-05 9.78E+02 8.83E-05 3.97E+03 ;
Zn-65 7.34E-07 3.31E+01 3.23E-06 1.37E+02 Sr-89 1.15E-07 3.63E+00 1.23E 3.88E+01 Sr-90 5.14E-06 1.62E+02 5.48E-05 1./3E+03: , Zr-95 3.38E-07 1.35E+01 2.22E f 8.14E+01 Nb-95 1.53E-07 6.43E+00 8.59E 3.37E+01- ; Mo-99 1.62E-08 5.58E-01 1.50E-07 "4.92E+00 ; Ru-103 1.30E-07 5.33E+00 7.74E-07 2.95E+01 1 Ag-110m 3.43E-06 1.55E+02 1. 54E-05 -- 6.47E+02: Sb-124 6.96E-07 2.89E+01 24.04E-06 1.56E+02 I-131 7.79E-07 2.47E+01 8.27E-06 2.61E+02 l I-133 1.84E-07 5.83E+00 '1.95E-06 -6.18E+01 Cs-134 6.83E-06 3.08E+02 2.78E-05 1.25E+03 Cs-137 1.03E-05 4.64E+02 4.19E-05 1.89E+03 Ba-140 1.14E-07 3.85E+00 1.10E-06 -3.56E+01 l' Ce-141 4.09E-08 1.45E+00 3.59E 1.'20E+01 Ce-144 6.95E-07 2.27E+01 7.02E-06 2.25E+02 - 1 Other* 2.26E-06 1.02E+02 9.56E-06. '4.16E+02
- Dose factors to be used in Method I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.. :
i i (1) See Seabrook Station Unit 1 Technical. Specification Figure 5.1-1. i B .' l -21 i 8683R 00CM Rev'. d
TABLE B.1-15 Ground Level to Vent Stack Elevation Release Point Correction Factor ;
~(
' Correction Factor. ;
, Receptor Point (R) Release Type- EL(R)
- 1. Maximum Off-Site a.- Noble Gases- 12.1-Receptor
- b. Iodine, Tritium, 12.5 i and Particulates i
- 2. The " Rocks" a. Noble Gases 9.4 a
- b. Iodine, Trituim, 9.4 .
and Particulates
- 3. The " Education a. . Noble Gases 14.3.
Center"
'b.. Iodine, Tritium. I14.3L i and Particulates . !
i l 1, i l l
)
f f B.1-22. 8683R. 00CM'Rev. ;
I F 2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS . , i Chapter 2 contains the basis for station procedures used to demonstrate compliance with Technical Specification 3.11.1.1, which limits the total fraction of MPC in liquid pathways, other than noble gases (denoted here as-F ENG) at the point of discharge from the station to the environment (see figure 8.6-1). F "O is limited to less than or equal to one, i.e., F ENG 1
- j, g i l
The total concentration of all dissolved and entrained noble gases at the point of discharge from the multiport' diffuser from all-station sources I combined, denoted C NU , is limited to 2E-04 pCl/ml, i.e;, I C"O 1 2E-04 Cl/ml. , 2.1 Method to Determine F ENG and C NG First, determine the total fraction of MPC (excluding noble gases), at the point of discharge from the station from all significant liquid sources , denoted FENG; and then separately determine the total concentration at
- the point of discharge of all dissolved and entrained noble gases from all.
station sources, denoted C NG , as follows: ENG = F 11. -(2-1) (uCl/ml) pC1/mi l l l and: l B.2-1
.8683R ODCM-Rev.
. .. . . _ _ . . . . - ~ - . . . - .- . . - _ - - . .
Cf - C < 2E-04
, (2-2)-
(pCl/mi) (pCl/ml) (pCi/mi) - l where: , i F - Total fraction-of MPC in liquids, excluding noble 'l l gases, at the point of discharge from the multiport diffuser-Cpt - Concentration at point of discharge-from the multiport , diffuser of radionuclide "1", except for dissolved and' i entrained noble gases, from-all tanks and other significant sources, p, from which a discharge may be made (including the-waste test tanks and any other significant source from which a discharge can be:made). Cpt is determined by dividing the product of the measured radionuclide concentration in , l 11guld waste test tanks.or effluent streams times their ' discharge flow rate by the total available dllution water H flow rate of circulating and service water at the time of l release (pC1/ml). ;I
.1 MPCt - Maximum permissible concentration of radionuclide "1" except i '
for dissolved and entrained.:oble gases from 10CFR20,
' Append 1x'B Table.II, Column 2 (pCl/ml)
Cf - Total concentration at point of discharge of all dissolved i and entrained noble gases'in liquids'from allistation sources (pCl/ml) , C - Concentration at point of discharge of dissolved and. entrained noble gas "l in liquids from all station- sources , (pC1/ml) 2.2 Method to Determine Radionuclide Concentration for Each Liculd ! Effluent Source-. 2.2.1 Waste Test Tanks C pj is determined for each radionuclide detected from the-activity in a representative grab sample of any of the waste test tanks'and'the predicted l flow at the point of discharge. l The batch releases are normally made from two 25,000-gallon capacity waste test tanks. These ts1ks normally hold 11guld-waste evaporator. B.2-2' 863.1R : 00CM Rev.
I distillate. The waste test tanks can also contain other waste such as 11guld taken directly from the floor' drain _ tanks when that liquid does not require j processing in the evaporator, distillate from the boron recovery evaporator
]
when the BRS evaporator is substituting for the waste evaporator, and' distillate from the Steam Generator Blowdown System evaporators and flash , steam condensers when that system must discharge liquid off-site. l l l If testing indicates that purification of.the waste test tank contents j is required prior to release, the-liquid can be circulated through the waste demineralizer and filter. The contents of the waste test tank may be reused in the Nuclear System if the sample test meets the purity. requirements. l Prior to discharge, each waste test tank is analyzed for principal l gamma emitters in accordance with the liquid sample and analysis program _ 1 outlined in Part A to the 00CM. j 2.2.2 Turbine Bu11dina Sump i
- The Turbine Building sump collects leakage from the Turbine Building floor drains and discharges the liquid unprocessed to the circulating' water i l
system. l 1 l Sampling of this potential source is normally done once per week for ) ! determining the radioactivity released to the environment (see Table A.3-1). 2.2.3 Steam Generator Blowdown Flash Tank , l The steam generator blowdown evaporators normally process the 11guld :l from the steam generator blowdown flash tank when there is primary to : secondary leakage. Olstillate from the evaporators can be sent to the waste test tanks or recycled to the condensate' system. When there is no primary to secondary leakage, flash tank, liquid:is processed through the steam generator j blowdown demineralizers and returned to the secondary side. j l S.2-3 1 86r.R 00CM Rev. 1
Steam generator blowdown is only subject to sampling and analysis when all or part of the blowdown liquid is being discharged to the environment instead of the normal recycling process (see Table A,3-1), l
.I
=!
l l t l l l 1
-1 l
I l l 8.2-4
-8683R =00CM.Rev;
~. _ _ . _ _ _ _ _ _ . - _ _- . _ _
3.0 0FF-SITE 00SE CALCULATION METH00S i l Chapter 3 provides the basis for station procedures required to meet .!' the Radiological Effluent Technical Specifications (RETS) dose and dose; rate requirements contained in Section 3/4:11 of the station operating Technical. Specifications. A simple, conservative method (called Method I)lis. listed in l Tables B.1-2 to B.1-7 for each of the requirements of the RETS. Each of the ! l Method I equations is presented in Sections-3.2 through 3.9. 'In addition, l those sections include more sophisticated methods (called Method II) for,use- . when more refined results are needed. This-chapter provides the-methods, data, and reference material with which the operator can calculate the needed-doses, dose rates and setpoints. The bases for the dose.and dose rate equations are given in Chapter 7.0. l l I The Semlannual Radioactive Effluent Release Report, to be filed after ] January I each year per Technical Specification 6.8.1.4, requires that 'l meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and l measurement, be used for determining the gaseous' pathway doses. For l continuous release sources (i.e., plant vent, condenser air removal-exhaust, I and gland steam packing exhauster), concurrent' quarterly average meteorology will be used in the dose calculations along _with the quarterly total radioactivity released. For batch releases or identifiable operational
- activities (i.e., containment purge or venting to atmosphere'of the Waste Gas System), concurrent meteorology during the period of release wil1 be used to determine dose if the total' noble . gas or iodine and particulates released in l
, the batch exceeds five percent of the total quarterly' radioactivity released from each unit; otherwise quarterly average meteorology will'be applied.
< Quarterly average meteorology will also be applied to batch. releases if the- l
- hourly met data for the period of batch release is unavailable.
l l l y l 8684R 00CM Rev. 4
=_ _ _ _
-i .
3.1 Introductory Concepts
- In part, the Radiological Effluent Technical 5,pecifications-(RETS) l limit dose or dose rate. The term " dose for . ingested or Inhaled radioactivity means the dose commitment, measured in mrem, which.results from- 1 the exposure to radioactive materials that, because of uptake and deposition ,
in the body, will continue to expose the body to radiation for some period'7f . time after the source of radioactivity is st@ ced. The time frame over which 0 the dose commitment is evaluated is 50 years. Inc chrases " annual dose" or dose in one year" then refers to the 50-year dose comitment resulting from ; exposure to one year's worth of releases. " Dose in a quarter" similarly-means' I the 50-year dose comitment resulting from exposure to one quarter's releases. The term " dose," with respect to external exposures, such as to' noble gas clouds, refers only to the doses received during the actual time. period of exposure to the radioactivity released from the plant. Once the- ( source of the radioactivity is removed, there is.no longer any addit;ional I accumulation to the dose commitment.
"Oose rate" is the total dose or dose comitment divided by exposure period. For example, an Individual who_ls exposed via the ingestion of_ milk ;
for one year to radioactivtty from plant gaseous effluents and receives a 50-year dose comitment of 10 mrem is said to have been exposed to a dose' rate 1 of 10 mrem / year, even though the actual dose received in-the year of exposure may be less than 10 mrem. In addition to limits on dose comitment, gaseous-effluents from thet j station are also controlled so that the maximum or peak dose rates at the site- , , boundary at any time are limited to the equivalentDannual do'se' limits of ; 10CFR, Part 20 to unrestricted areas (If it were assumed that the peak dose rates continued for one year). ' These dose-rate limits provide reasonable-assurance that members of the public,~elther inside^or.outside the site boundary, will not be exposed to a'nnual averaged concentrations exceeding the-limits specified in Appendix B. Table IILof'10CFR,.Part 20 (10CFR20.106(a)). 4
.B.3-2 8684R 00CM'Rev. 4
-l.
. ygw- h hye-+ +'ge gp w -+g I g g
1 ThequantitlesaDandbareintroducedtoprovidecalculable quantities, related to off-site doses or dose rates that demonstrate compilance with the RETS. Delta 0, denoted AD, is the quantity calculated by the Chapter 3, . Method I dose equations. It represents the conservative increment in dose. i The 40 calculated by Method I equations is not necessarily the actual dose received by a real individual, but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the selection and definition of critical receptors. The radionuclide. specific- i dose factors in each Method I dose equation represent the greatest dose to any organ of any age group. (Organ dose is a function of age because-organ mass : and intake are functions of age.) The critical receptor assumed by'" Method I" equations is then generally a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is higher than any real individual is likely to receive. Method II allows for a more exact dose-calculation for each individual if necessary. 0 dot,denotedb,isthequantitycalculatedintheChapter3doserate equations. It is calculated using the station's effluent monitoring system readingandanannualorlong-termaverageatmosphericdispersionfactor..b' I predicts the maximum off-site annual dose if the peak observed radioactivity release rate from the plant stack continued for one entire year' Since peak . e release rates, or resulting dose rates, are usually of short time duration on^ the order of an hour or less, this approach then provides assurance that 10CFR20.106 limits will be met. Each of the methods to calculate dose or dose rate are presented 'in separate subsections of Chapter 3, and are summarized in Tables B.1-1 to B.1-7. Each method has two levels of complexity and conservative margin called Method I and Method II. Method I has the greatest margin and is the-simplest; generally a linear equation. Method II is a more detailed analysis which allows use of site-specific factors and variable parameters to be se'ected to best fit the actual release. Guidance is provided, but.the appropriate margin and depth of analysis are determined.in each instance at the time of analysis under Method II. ! B.3 neoan- M ti
l 3.2 Method to Calculate the Total Body Dose from Liquid Releases Technical Specification 3.11.1.2 limits the total body dose commitment to a member of the public from radioactive material in 11guld effluents to 1 1.5 mrem per quarter and 3 mrem per y' ear per unit. Technical Specification 3.11.l'.3 requires liquid radwaste treatment when the total body dose estimate exceeds 0.06 mrem in any 31-day period. Technical
- Specification 3.11.4 limits the total body dose commitment to any real member of the public from all' station sources (including liquids) to 25 mrem in a year.
.i , Use Method I first to calculate the maximum total body dose from a.
liquid release from the station as it is simpler to execute and more conservative than Method II.
- t Use Method II if a more refined calculation of total body dose is needed, i.e., Method I indicates the dose might be greater than the Technical i Specification limits.
To evaluate the' total body dose, use Equation 3.1 to estimate the dose l from the planned release and add this to the. total body dose accumulated from f prior releases during the month. See Section 7.1.1 for basis. ;
+ 3.2.1 Method I The increment in total body dose from'a liquid release is:
O tb =k Qj OFL itb (3-1) I ; t (mrem) =( ) (pCl) ( *) where: ! 0FLitb = Site-specific-total' body dose factor (mrem /pC1) for a ! L liquid release. It is the highest of the four age groups. See Table 8.1-11. Qt - Total activity (pC1) released for radionuclide "l".- (For i ! strontiums, use the most recent measurement available.) l l l l B.3-4 _
"l l A684R _
00CM Rev. :4
. - . _ - . . . - .. ~_ _ - _ _ _ _
k L K = 918/Fd ; where Fd is the average (typically monthly average) dilution flow of the Circulating Water System at thg point of discharge from the multiport diffuser (in ftJ/sec). For normal operations with a cooling water flow , of 918 f t3 /sec, K is equal to 1. Equation 3-1 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multiport diffuser to: unrestricted _ areas '
(at the edge of the. initial mixing or_ prompt' dilution zone that i i corresponds to a factor of 10 dilution), and i
- 2. Any continuous or batch release over any time period. '
3.2.2 Method II I Method II consists of the models, input data and assumptions (bloaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide.1.109, Rev. T (Reference A), l except where site-specific data or: assumptions have been identified in the 00CM. The general equations (A-3 and A-7) taken from Regulatory ~ Guide 1.109, a*id used in the derivation of the simplified Method _I approach as described in the Bases section, are also applied to Method II assessments, except that dosec calculated to the'whole body from radioactive effluents are evaluated ' for each of the four age groups to determine the maximum whole body dose of an - age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors of Method II calculations As noted in. Section B.7.1, ' the mixing ratio associated with the edge of the 1 F~ surface isotherm above the multiport diffuser may be used in Method II calculations. l q B.3-5 - 8684R 00CM Rev., ! _ _ _ __ . .- _. - - -~ - ~
i 3.3 Method to Calculate Maximum Organ Oose from Licuid Releases , I Technical Specification 3.11.1,2 l'mits the maximum organ dose commitment to a Member of the Public from radioactive material in 11guld effluents to 5 mrem per quarter and 10 mrem per year per unit. Technical , Specification 3.11.1.3 requires liquid radwaste treatment when the maximum-organ dose projected exceeds 0.2 mrem in any 31 days (see Subsection 3.11 for I dose projections). Technical Specification 3.11.4 limits the maximum organ ; dose commitment to any real member of the public from all station sources l (including liquids) to 25 mrem in a year except for the thyrold, which is ; limited to 75 mrem in a year. i Use Method I first to calculate the maximum organ dose from a liquid release to unrestricted areas =(see Figure B.6-1) as it is simpler to execute i and more conservative than Method II. I Use Method II If a more refined calculation of organ dose 1s needed,. i.e. Method I indicates the dose may be greater than the limit. ! i Use Equation 3-2 to estimate the maximum organ dose from-individual or > combined liquid releases. See Section 7.1.2 for. basis. 3.3.1 Method I The increment in maximum organ dose from a liquid' release =ls: O g -k Qg 0FLg , (3-2) l (mrem) = ( ) (pCl) ( *) where: i 0FL'mo = Site-specific maximum organ dose.-factor (mrem / C1) for a liquid release. It is'the highest of the four age groups. See Table B.1-11. Qt - Total activity ( C1) released for radionuclide "1". (For strontiums, use the most recent measurement available.) 8.3-6 8684R 00CM Rev. 4 J i
.- -. _ . . -- . .- . _ . -~ .-
K = 918/Fd ; where Fd is the average (typically monthly , average) dilution flow of the Circulating Water System at the point of discharge from the multiport. diffuser (in 3 ft /sec).3 For normal of 918 ft /sec, operations K is equal.to 1. with a cooling. water flow j Equation 3-2.can be applied under the'following. conditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multipcrt diffuser to unrestricted areas (at the edge of the initial _ mtxing or prompt dilution < zone that-corresponds to a factor of-.10 dilution), and
- 2. Any continuous or batch release over any time period.
3.3.2 Method II Method II consists of the models, input data and assumptions # - t (bloaccumulation factors, shore-width factor, dose. conversion factors, and transport and buildup times) in Regulatory Guide l.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide-1.109, and used in the derivation of the simplified Method I approach as described in the Bases section. are also applied to Method II assessments, except that j doses calculated to critical organs from radioactive effluents are evaluated l for each of the four age groups to determine.the maximum critical organ of an l age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors for Method II calculations. As.noted in Section B.7.1, the mixing ratio associated with the edge of the 1 0F surface isotherm above the multiport diffuser may be used in Method II calculations. l
'l B.3-7 '
8684R 00CM Rev. l l
-j j ,
3.4 Method to Calculate the Total Body Dose Rate From Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the total body from noble gases at any location at or beyond the site boundary to 500 mrem / year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate. By limiting O to a rate equivalent to no more than-500 tb mrem / year, we assure that the total body dose accrued in any one year by any member of the general public is less than 500 mrem. , Use Method I first to calculate the Total Body Dose Rate from the peak I I release rate vla' the station vents . Method I applies at all release , rates. ' useMethodIIifamorerefinedcalculationofb tb is desired by the-station (i.e., use of actual release point parameters with annual or'a'ctual meteorology to obtain release-specific X/Qs) or'if Method I predicts a dose rate greater than the Technical Specification limit to determine if it had actually been exceeded during a short time.-interval. See-Section.7.2.1 for basis. Compliance with the dose rate limits for noble gases'are continuously
- demonstrated when effluent release rates are below the plant vent noble gas
', activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate:llmit, or a value below it. Determinations of dose rate for compliance-with Technical Specifications are performed when the effluent' monitor alarm setpoint is exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10, Table 3.3-10) when the monitor 1s Inoperable.
( i' (R The primary vent stack mix mode release X/Qs are assumed in the 00CM:
~
l j Method ~ I equations :when the correction' factor _ for ~ release point elevation, EL(R), is set at-1.0. L B.3-8 i 8684R 00CM Rev. o
.)
3.4.1 Method I j
-l The Total Body Dose Rate due to noble gases can be determined as l
follows: b = 0.85
- EL(R)
- hg 0FB g. (3-3)' i tb 1 3
(mrem) , (DC1-sec) ( ) ( f,,1,) (mrem-m ) yr pCl-m 3 sec pC1-yr where: EL(R) - Ground level to vent stack Elevation Releaso Point (R) correction factor (dimensionless).: For prinary-vent-stack releases, EL(STACK) equals 1.0. .For-ground level-releases, ; EL(GRO) equals 12.1 for.the maximum off-site receptor, as shown on Table B.1-15. , hg - The release rate at the station vents (uC1/sec), for each noble gas radionuclide, "1", shown in Tabie B.1-10. DFB g - Total body gamma dose factor (see Table B.1-10). -, Equation 3-3 can be applied under the follow'ing conditions'(otherwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via any station vent to the atmosphere.
3.4.2 Method II Method II consists of the model and input data (whole body-dose factors) in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the 00CM. The general equation (B-8) taken from Regulatory Guide -1.109', and used in the derivation of the simplified Method I approach as described in the Bases section, is also applied to a Method .II assessment. No credit for a shielding: B.3-9 8684R 00CM Rev.
.i
i factor (S p) associated with residential structures is assumed. Concurrent meteorology with the release period osy be utilized.for the gamma atmospheric dispersion factor identified in ODCM Ewa' ion 7-3 (Section-7.2.1), and , determined as indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. b i e A, j B.3-10 8684R 00CM Rev'. i
- i
1 3.5 Method to Calculate the Skin Oose Rate from Noble Gases I l Technical Specification 3.11.2.1 limits the dose rate at any time to
- the skin from noble gases at any location at or beyond the site boLndary to 3,000 mrem / year. The Technical Specif.1 cation indirectly limits peak release l rates by limiting the dose rate that is predicted from continued release at i the peak rate. By limiting Oskin to a rate equivalent to no more than l
1 3,000 mrem / year, we assure that the skin dose accrued in any one year by any member of the general public is less than 3,000 mrem. Since it can be ; expected that the peak niease rate on wnich Oskin is derived would not be exceeded without corrective action betrig taken to lower it, the -resultant j average release rate over the year is expected to be consid nubly.less than the peak release rate. Use Method I first to calculate the Skin Dose Rate from the peak' release rate via the station vents'I . ' Method I applies at all rele$se rates. Use Method II if a more refined calculation of O skin is desired by'the q station (i.e., use of actual release point parameters with. annual or actual f meteorology to obtain release-specific X/Qs) or if Method I predicts a dose rate greater than the Technical Specification limit to detarmine if it:had actually been exceeded during a short time interval. See Section 7.2.2 for basis. -l l Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by-virtue of the fact that the alarm setpoint I is based on a value which corresponds to the off-site dose rate limit, or'a. ( ' value below it. Determinations of dose rate for compilance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded.
'l l
(I) The primary vent stack mix mode release X/Qs are assumed in the 1 00CM Method I equations when the correction factor for release point' l evaluation, EL(R), is set equal to'l.0. -l 8.3-11 i l OOCH Rev. ; 8684R '
3.5.1 Method i The Skin Dose Rate due to noble gases is: bskin EL(R) hg Ofl (3-4)- 1 (mrem) ,( ) (uCl) (mrem-sec) yr sec pCl-yr where: EL(R) = Ground level to vent stack Elevation Release Point (R). correction factor (dimensionless). For-primary vent stack releases, EL(STACK) equals 1.0. For ground level releases, EL(GRO) equals-12.1 for the maximum off-site receptor,. as shown on Table B.1-IS. hg - The release rate at the station vents.(pCl/sec) for ach radionuclide, "1", shown in Table-B.1-10, OFj = combined skin dose factor (see Table B.1-10). Equation 3-4 can be applied under the following conditions (otherw'ise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via any station vent to the atmosphere.
3.5.2 Method II Method II consists of the model.and input data (skin dose factors).in Regulatory Guide 1.109, Rev. I (Reference A), except where site-specific data or assumptions have been identified in the ODCH. The general = equation (B-9) taken from Regulatory Guide 1.109, and used in the derivation of:the' simplified Method I approach as described.In the Bases .section, is also applied to a Method II assessment, no credit for a shielding factor.'(S p) B.3-12 . . 8684R OOCH Rev. l i
associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atinospheric dispersion ! factor and undepleted atmospheric dispersion factor identified in ODCM Equation 7-8 (Section 7.2.2), and determined as indicted in Sections 7.3.2 and 7.3.3 for the release point (either_ ground level or vent stack) from which-recorded effluents have been discharged. _. 1-l
-i i
I i i 1 i i
?
8.3-13 8684R 00CM Rev.
}
l 1 3.6 Method to Calculate the Critical Oraan Dose Rate from Iodines, Tritium-and Particulates with T1/2 Greater Than 8 Days l Technical Specification 3.11.2.1 limits the dose rate at any time to any organ from I3I I, 1337, 3H and radtonuclides in particulate form-with half lives greater than 8 days to 1500 mrem / year to any-organ. The Technical Specification indirectly limits peak release rates by limiting the dose rate ] that is predicted from continued release at the peak rate. By limiting O gg to a rate equivalent to no more than 1500 mrem / year, we assure that the j critical organ dose accrued in any one year by any-member of the general public is less than 1500 mrem. Use Method I first to calculate the Critical Organ Dose Rate from the i peak release rate via the station vents . Method I applies at all release j rates.
/ I UseMethodIIifamorerefinedcalculation~ofb co 1, lestred by the station (i.e., use of actual release point parameters .with annual or actual meteorology to obtain release-specific X/Qs) or if Method I predicts a' dose i rate greater than the Technical Specification limit to determine if it had l
actually been exceeded during a short time interval. See Section 7.2.3 for basis. l i 3.6.1 Method I The Critical Organ Oose Rate can be determined as follows: ; b co
- EL(R)
- hg DFGjco (3-5)
(mrem) ,( ) (uC1) (mrem-sec) yr sec pCl-yr (1) The primary vent stack mix mode release X/Qs are assumed in'the 00CM Method I equations when the correction factor'for release point elevation, EL(R), is set equal to 1.0. B.3-14 l 8584R 00CM Rev'. l
where:
.1 EL(R) - Ground level to vent stack Elevation Release Point (R) correction f actor (diriensionless). For primary vent stack releases, 1
E:.(STACK) equals 1.0.- For ground level releases,~EL(GRD) equa'.s 12.5 for the maximum off-site receptor, as shown I on Table B.I.15. l j DFGjco= Site-specificcriticalorgandoseratefactor(mrem-sec) . pC1-yr for a gaseous release. See Table B.1-12. hj = The activity release rate at the station vents of-radionuclide "1" in pC1/sec (i.e., total activity measured'of radionuclide "1" averaged over the time period for which the filter / charcoal samp.le collector was in the effluent stream). For 1 - Sr89 or Sr90, use the best estimates 4 (such as most recent measurements). Equation 3-5 can be applied.under the following conditions (otherwise, justify Method I or consider Method II): ,
- 1. Normal operations (not emergency event), and
- 2. Tritium, I-131 and particulate releases via monitored station vents-to-the atmosphere.
~ 3.6.2 Method II Method II consists of the models, input data and assumptions in , Appendix C of Regulatory Guide 1.109, Rev. 1 (Reference A), except-where l site-specific data or assumptions have been identified in the 00CM (see-Tables B.7-2 and 8.7-3). The critical organ dose rate will be determined based on the location (site boundary, nearest resident, or farm) of receptor pathways as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, j inhalation, ingestion of stored and leafy vegetables, milk, and meat) at an . off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release-point , B.3-15 00CM Rev. 8684R l l q
(either ground level or vent stack) from thich recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age .; groups independently, and take no credit for-a shielding factor (SF) ; associated with residential structures, i 1 i
-- k
-l i
Y t j 8,3-16 8684R OOCH Rev- <
i 3.7 Method to Calculate the Gamma Air Oose from Noble Gases Technical Specification 3.11.2.2 limits the gamma dose to air from noble gases at any location at or beyond the si,te boundary to 5 mrad in any l quarter and 10 mrad in any year per un.it. Dose evaluation is. required at ! least once per 31 days. Use Method I first to calculate the gamma air dose for the station vent (I) releases during the period. ] ; i Use Method II if a more refined calculation ~1s needed (i.e., use of j actual release point parameter with annual or actual meteorology to obtain release-specific X/Qs), or if Method I predicts a dose greater than the Technical Specification limit to determine.if it had actually been exceeded. , See Section 7.2.4 for basis. 1 l 3.7.1 Method I , The gamma air dose from station vent releases is: ; 0,{r - 2.7E-08
- EL(R)
- Q3 DFj . (3-6) 1 3
( ) (pC1) (mrad-m (mrad)=(U'~}) pCi-m pCl-yr where: Qg . total activity (pCl) released to the atmosphere via station ! vents of each radionuclide "1" during the period of interest. < i DF{ ' gamma dose factor to air for radionuclide "1". See Table B.1-10 , EL(R) Ground level to vent stack Elevation Release Point (R)- ; correction factor-(dimensionless). For primary vent stack releases, EL(STACK) equals 1.0. .For ground level releases, EL(GRD) equals 12.1 for the maximum off-ste receptor, as shown-on. Table B.1-15. (I) The primary vent stack mix mode release X/Qs are assumed in the' ODCM Method I equations when the correction factor for release point , elevation, EL(R), is set equal to 1.0. 'l B.3-17 acnao ODCW Reve .j
~ Equation 3-6 can be applied under the following conditions '.otherwise justity Method I or consider Method II):
- 1. Normal operations (nonetnergency event), and g
- 2. Noble gas releases via station vents to the atmosphere.
3.7.2 Method II Method II consists of ' models, input data (dose factors) and i assumptions in Regulatory Guit1 1.109. Rev. 1 (Reference A), except where { site-specific data or assumptions have been identified in the 00CM. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, ano used in , the derivation of the simplified Method I approach as described in the Bases Section 7.2.4 are also applied to Method II assessments. Concurrent I meteorology with the release period may be utilized for the gamma atmospheric dispersion factor identified in 00CM Equation 7-14, arid determined as indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. i I I i B.3-18 8684R 00CM Rev.
\
4 s m
r v ! 3.8 Method to Calcylate the se,tf, Air Oose from Noble Gases Technical Specification 3.11.2.2 limits the beta dose to air from noble
- gases at any location at or beyond the site boundary to 10 mrad in any quarter
; and 20 mrad in any year per unit. Oose evaluation is required at least once >
per 31 days. Use Method I first to calculate the beta air dose for the station vent U) stack releases during the period. Method I applies at all dose levels. Use Method II if a more refined calculation is needed (i.e., use of actual release point parameters with annual or actual meteorology to obtain release-specific X/Qs) or if Method I predicts a dose greater than the Technical Specification limit to determine if it had actually been exceeded. See Section 7.2.5 for basis. I 3.8.1 Method I The beta air dose from station vent releases is: D tr
- 2.6E-08
- EL(R)
- Qg 0Ff (3-7) i 3
(mrad) - (DCi-yr) ( ) ( Cl) (mrad-m ) pCl-m 3 pCl-yr where: Off . = Beta dose factor to air for radionuclide "1" (see Table B.1-10). i Qg . Total activity (pC1) released to the atmosphere,via' station vents of each radionuclide "1" during the period of interest. (I) The primary vent stack mix mode release X/Qs are assumed in tne 00CM Method I equations when the corrective factor for release point 3 elevation EL(R). is sat equal to 1.0. I B.3-19 , 8684R 00CM Rev.
EL(R) o Ground level to vent stack Elevation Release Point (R) correction factor (dimensionless). For primary vent stack releases, EL(STACK) equels 1.0. for ground level releases, j EL(GRD) equals 12.1 for the maximum off-site receptor, as shown on Table B.1-15. Equation 3-7 can be applied under the following conditions (otherwise ] justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via station vents to the atmosphere.
3.8.2 Method II Method II consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data er assumptions have been identified in the ODCM.- The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases ' Section 7.2.5, are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the atmospheric dispersion factor identified in ODCM Equation 7-15, and determined, as , indicated in Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. 1 F B.3-20
-ODCM Rev.
8684R
t l 3.9 Method to Calculate the Critical Organ Dese from Iodines, Tritium and l Particulates Technical Specification 3.11.2.3 limits the critical organ dose to ' member of the public from radioactive. iodines ' tritium, and particulates with , half-llves greater than 8 days in gaseous effluents to 7.5 mrem per quarter : and 15 mrem per year per unit. Technical Specification 3.11.4 limits the i total body and organ dose to any real member of the public from all station sources (including gaseous effluents) to 25 mrem in a year except for the thyrold, which is limited to 75 mrein in a year. I Use Method I first to calculate the critical organ dose from a vent , rel- a as it is simpler to execute and more conservative than Method !!. Use Method II if a more refined calculation of critical organ dose is t, needed (i.e., Method I indicates the dose is greater than the limit). See ' Section 7.2.6 for basis. + 3.9.1 Method I D eo
= EL(R)
- Qg 0FG ggo (3-8)
(mrem) = ( ) (pCl) ( *) Qg = Total activity (pCl) released to the atmosphere of radionuclide ,
"i" during the period of interest. For strontiums, use the most recent measurement.
OFGgco = Site-specific critical organ dose factor (mrem /pC1). For each radionuclide it is the age group and organ with the largest dose factor. See Table B.1-12. EL(R) = Ground level to vent stack Elevation Release Point (R) correction factor Mimensionless). e or primary vent stack releases, EL(STACK) equals 1.0. For ground level releases, EL(GRD) equals 12.5 for the maximum off-site receptor, as shown on Table B.1-15. B.3-21 8684R 00CM Rev. ,
Equation 3-8 can be applied under the fo?!cwing conditions (otherwise, justify Method I or consider Method II): ,
- 1. Normal operations (nonemergency event),
- 2. Iodine, tritium, and particulate releases via station vents to the atmosphere, and
- 3. Any continuous or batch release over any time period.
3.9.2 METHOD II Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the 00CM (see s Tables 8.7-2 and B.7-3). The critical organ dose will t determined based on the location (site boundary, nearest resident, or farm) of receptor pathways, as identified in the most recent annual land use census, or by conservatively , assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk and meat) at.an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in sccordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or L vent (tack) from which recorded effluents have been discharged. The maximum ; l l critical organ dose will consider the four age groups independently, and use a shielding factor (Sp ) of 0.7 associated with residential structures. . r s k B.3-22 8684R ODCM Rev. > l
l t 3.10 Method to Calculate Direct Dose from Plant Operation Technical Specification 3.11.4 restricts the dose to the whole body or any organ to any member of the public from all uranium fuel cycle sources (including direct radiation from station fact 11 ties) to 25 mrem in a calendar-year (except the thyroid, which is limited to 75 mrem). It should be noted that since there are no uranium fuel cycle facillites within 5 miles of the station, only station sources need be considered for determining compliance , with Technical Specification 3.11.4 3.10.1 Method The direct dose from the station will be determined by obtaining the dose from TLD locations situated on-site near potential sources of direct radiation, as well as those TLDs near the site boundary which are part of the environmental monitoring program, and subtracting out the dose contrJbution from background. Additional methods to calculate the direct dose may.also be used to supplement the TLD information, such as high pressure ton chamber measurements, or analytical design calculations of direct dose from identified sources (such as solid waste storage facilities). l 1 l The dose determined from direct measurements or calculations will be related to the nearest real person off-site, as well as those individuals on-site involved in activities at either the Education Center or the Rocks boat landing, to assess the contribution of direct radiation to the total dose limits of Technical Specification 3.11.4 in conjunction with liquid and gaseous affluents.
\
l B.3-23 , 8684R 00CM Rev.
. _ . ~,,._m_ -
. _ . _ , . . .. , , , __ , _ , . _ , _ , , . , , . . , , . , . _ . , , _ , _ , .,,.m ..._,, ,, ,
l
- 3.'1 Dose projections Technical Specifications 3.11.1.3 and 3.11.2.4 require that approorlate portions of liquid and gaseous radwaste treatment systems, respectively, be 1 used to reduce radioactive effluents.when it is projected that the resulting dose (s) would exceed limits which represent small fractions of the "as low as
, reasonably achievable" criteria of Appendix ! to 10CFR Part 50. The surveillance reautrements of these Technical Specifications state that dose projections be performed at least once per 31 days when the 11guld radwaste treatment systems or gaseous radwaste treatment systems are not being fully utilized. ' l Since dose assessments are routinely performed at least once per 31 days to account for actual releases, the projected doses shall be determined by comparing the calcu'ated dose from the last (typical of expected , operations) completed 31-day period to the appropriate dose limit fer.use of radwaste equipment, adjusted if appropriate for known or expected differences between past operational parameters and those anticipated for the next 31 days. 3.11.1 Liould Dose Projections The 31-day liquid dose projections are calculated by the following: (a) Determine the total body O tb and organ dose 0 ,(Equations 3-1 and 3-2, respectively) for the last typical completed 31-day , i period. The last typical 31-day period should be one without significant identified operational differences from the period being projected to, such as full power operation vs. periods.when the plant is shut down. ' l (b) Calcul*te the ratio (R )j of the total estimated volume of batch releases expected to be released for the projected period to that actually released in the reference period, , B.3-24 8684R 00CM Rev. t
,,e-- . ..r- , , - , , - - ----.--..--,-r.,-------,-----v- ---,-- - - - - - - - . - . ,-
i (c) Calculate the ratio (R 2) of the estimated gross primary coolist activity for the projected per!od to the average value in the reference period. Ute the most recent value of primary coolant activity as the projected value if no trend in decreasing or increasing. levels can be de.termined. ; I (d) Determine the projected dose from: Total Body: Dtb pr . Otb * "1 . R2 , Max. Organ: D e pr
- On.) .Rj.R2 3.11.2 Gaseous Dose Projections _
For the gaseous radwaste treatment system, the 31-day dose projections I are calculated by.the following: / ; (a)Determinethegammaairdose0,{r(Equation 3-6).andthebeta. air doseDft(Equation a 3-7)fromthelasttypical31-dayoperating period. (b) Calculate the ratio (R )3 of anticipated number of curies of noble I gas to be released from the hydrogen surge tank to the atmosphere )' l over the next 31' days to the number of curies released in the reference period on which the gamma and beta air doses are based. If no differences between-the reference period and the next 31 days can be identified, set R to 1. 3 l I (c) D'etermine the projected dose from: q Gamma Air: 0,{rpr.Dar.R3 l 4 Beta Air: Djr pr . Djr . R 3-B.3-25 l 8684R ODCM Rev. : I i
6 1 for the ventilation exhaust treatment system, the critical organ dose from lodines, tritium, and particulates are projected for the next 31 days by the following: (a) Determine the critical organ dose Oco (Equation 3-8) from the r last typical 31-day operating period. (b) falculate the ratio (R )4 of anticipated primary coolant dose . l equivalent 1-131 for the next 31 days to the average dose equivalent I-131 level during the reference period. Use the most current determination of DE I-131 as the projected value if no trend can be determined. . (c) Calculate the ratto (R )$ of anticipated primary system leakage rate to the average leakage rate during the reference period. Use the current value of the system leakage as an estimate of/the anticipated rate for the next 31 days if no trend can be determined. (d) Det,4rmine the projected dose from: 1 Critical Organ: D co pr =O,.R4.R$ g 2 B.3-26 u 8684R 00CM Rev.- l l l
4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring stations are listed in ' Table B.4-1. The locations of the stations with respect to the Seabrook Station are shown on the maps in Figures.B.4-l'to B.4-6.
- Olrect radiation measurements are analyzed at the station. .All other radiological analyses for environmental samples are performed at the Yankee '
Environmental Laboratory. The Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory , Intercomparison Studies Program for all the species and matrices routinely analyzed. Pursuant to Technical Specification 4.12.2, the land use census will be conducted "during the growing season" at. least once per 12 months. The growing season is defined, for the purposes of the land use census,,as the ., period from June 1 to October 1. The method to be used for conducting the census will consist of one or more of the following, as appropriate: door-to-door survey, visual inspection from roadside, aerial survey, or , consulting with local agricultural authorities. Technical Specification 6.8.1.3 requires that the results of the Radiological Environe.ntal Monitoring Program be summarized in the Annual Radiological Environmental Operating Report "in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, 1979." .The general table format will be used with one exception and one clarification, as follows. The mean and range values will be based not upon detectable measurements only, as specified in the NRC Branch Technical-Position, but upon allmeasurehnts. This will prevent thi positive bias associated with the calculation of the mean and range based upon detectable measurements only. Secondly, the Lower Limit of Detection column will specify the LLD required by 00CM Table A.5-2 for that radionuclide and sample medium. B.4-1 l, 8685R 00CM Rev. 4 i
_ TABLE B.4-1 Radiolooical Environmental Monitorino Stations (a) Distance From Exposure Pathway Sample location Unit 1 Otraction From and/or Sample and Designated Code Containment (km) the~ Plant
- 1. AIRBORNZ (Particulate and Radlolodine)
AP/CF-01 PSNH Barge 2.7 ESE Landing Area AP/CF-02 Hampton Marina 2.7 E i AP/CF-03 SW Boundary 0.8 SW 1 AP/CF-04 W. Boundary- 1.0 W AP/CF-05 Winnacunnet H.S.(b) 4.0 NNE AP/CF-06 Georgetown 24.0 SSH , Substation (Control)
- 2. WATERBORNE
- a. Surface WS-01 Hampton-Discharge Area 5.3 E WS-51 Ipswich Bay (Control) 16.9 f SSE ,
- b. Sediment SE-02 Hampton-Discharge Area (b) 5.3 -
E SE-07 Hampton Beach 3.1 E SE-08 Seabrook Beach (b) 3.2 ESE SE-52 Ipswich Bay (Control)(b) 16.9 SSE SE-57 Plum Island Beach 15.9 SSE
.(Control)(b)
- 3. INGESTION
- a. Milk TM-04 SA11sbury, MA 5.2 .SW TM-08 '.,ampton FalI s, NH 4.3 NNW
' Hampton Falls, NH , TM-10 4.8 WNW '
l TM-20 Rowley, MA (Control) 16.3 S
- b. Fish and Invertebrates (C)
FH-03 Hampton - Olscharge 4.5 ESE f Area FH-53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Olscharge 5.5 E Area HA-54 Ipswich Bay (Control)- 17.2 SSE MU-06 Hampton - 01scharge 5.2_. _E Area MU-56 Ipswich Bay (Control) 17.4 SSE [ B.4-2 8685R 00CM Rev. 4
, , , - . - - - . , , . - . - , , . - , e- - - - - - --
i l TABLE B.4-1 (continued) Radiolocical Environmental Monitoring StationsI ') Distance From ; Exposure Pathway Sample Location Unit i Direction From and/or Sample and Destanated Code Cortainment (km) the Plant
- 4. DIRECT RADIATION TL-1 Brimmer's Lane, 1.1 N Hampton Falls .
TL-2 Landing Rd., Hampton 3.2 NNE TL-3 Glade Path, Hampton '3.1 NE l Beach l TL-4 Island Path, Hampton 2.4 ENE Beach i TL-5 Harbor Rd., Hampton 2.7 E Beach TL-6 PSNH Barge Landing 2.7 'ESE 4 Area TL-7 Cross Rd., Seabrook 2.6 j SE , Beach 1 TL-8 Farm Lane, Seabrook 1.1 SSE TL-9 Farm Lane, Seabrook 1.1 S TL-10 Site Boundary Fence 1.0 SSW I TL-11 Site Boundary Fence 1.0- SW : Site Boundary Fence TL-12 1.0 WSW l TL-13 Inside Site Boundary 0.8 W TL-14 Trailer Park, Seabrook 1.1 WNW TL-15 Brlmmer's Lane, 1.4 .NW Hampton N ls ~ TL-16 Brimmr a Lane, 1.1 NNW Hampton Falls TL-17 South Rd., N. Hampton 7.9 N l TL-18 Mill Rd., N. Hampton 7.6 NNE l TL-19 Appledore Ave., 7.9 NE N. Hampton TL-20 Ashworth Ave., 3.4 ENE Hampton Beach TL-21 Route IA, Seabrook 2.7 SE
- l Beach TL-22 Cable Ave., 7.6 SSE i Salisbury Beach i TL-23 Ferry Rd., Salisbury 8.1 S l TL-24 Ferry Lots Lane, 7.2 SSW Salisbury 4 TL-25 Elm St., Arnsbury 7.6 SW j TL Route 107A, Amesbury 8.1 WSW ;
B.4-3 ! 8685R 00CM Rev. 4 ,
. - . -- -. . - - _ ~ - . _ _ . - - . . - . . - - . - . _ - -.
1 1 i TABLE B.4 1 (continued) Radiological Environmental MonitorinQ Stations'A' Distance From j Cxposure Pathway Sample Location Unit 1 Direction From and/or Sample and Designated Code Containment (km) the Plant TL-27 Highland St., 7.6 W S. Hampton . l TL-28 Route ISO, Kensington 7.9 WNW J TL-29 Frying Pan Lane, 7.4 NW Hampton Falls TL-30 Route 101C, Hampton. 7.9 NNW TL-31 Alumni Drive, Hampton 4.0 NNE TL-32 Seabrook Elementary School 1.9 5 TL-33 Dock Area, Newburyport 9.7 5 i TL-34 Bow St., Exeter 12.1 NW i TL-35 Lincoln Ackerman School 2.4 NNW i TL-36 Route 97, Georgetown 22 SSH (Control) TL-37 Plaistow, NH (Control) 26 WSW ! TL-38 Hampstead, NH (Control) 29 p W TL-39 Epping, NH (Control) 27 NW TL-40 Nowmarket, NH (Cantrol) 24 NNW TL-41 21 NNE Portsmouth,)NH (Control)(b I TL-42 Ipswich, MA (Control)(b) 27 SSE (a) Sample locations are shown on Figures B.4-1 to B.4-6. (b) This sample location is not required by monitoring program defined in Part A of-00CM; program requirements specified in Part A do not apply to samples taken at-this location. (c) Samples will be collected pursuant to 00CM Table A.5-1. Samples are not required from all stations listed during any sampling interval (FH = Fish; HA = Lobsters; HU = Mussels). Table A.5-1 specifies that "one sample of three commercially and recreationally important species" be collected in the vicinity of the plant discharge area, with similar species being. collected at a control location. (This wording is consistent with the NRC Final Environmental Statement for Soabrook Station.) Since the discharge area is off-shore, there is a great number of fish species that could be considered commercially or recreationally important. Some are migratory (such as striped bass) . making them less desirable as an Indicator of plant-related radioactivity. Some pelagic species (such as herring and mackerel) tend to school and wander throughout a large area, sometimes making catches of significant size difficult to obtain. Since the collection of all species would be difficult or impossible, and would provide unnecessary: redundancy in terms of monitoring important pathways to man, three fish and invertebrate species have been specified as a minimum requirement. Samples may include marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish, such as flounder or hake. Several similar species may be grouped together into one sample. if sufficient sample mass for a single species is not available after a reasonable effort has been made (e.g., yellowtail flounder and winter flounder). B.4 4 00CM Rev. 4 8685R _ _ _ _ _ _ _ _ _ _ _ _ _ . . ~ _ . _ ._ __ _ __ . _ _ _ . _
I I FIGURE 5.4-1
- P.ADIOLOGIf* A t- ENYTIONMENTAL McNITCtfMG LOCATIONS WITRIM 4 EILOMETERR OF STAngoog STATION N
[ k
~
w s s+g
- - . seAemos a /
, , - o -. -s e em-. A we.
~__
1(.08 I I
// e see sees
\
- lu
~ % y
,, ., . - ?
5.4-5 CDCM Rev. 6 : 4 tw-e .- - *,, ,--_...-.,,,-,,,,,....,,._.-,_,,,,,_,._,,,,_.,,.,.m..
i
. I 1 .
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FIGURE B.6 2 ' l s RADIOLOGICAL DIVIlolttENTAL HDMITORING LOCATIONS ' i RETVEEM 6 KILOMET m AND 12 KILONET m FROM SEA 1100E STATION .l .i t i #' i st upenes 4
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5.0 SETPOINT DETERMINATICNS Chapter 5 contains the methodology for the calculation of effluent monitor setpoints to implement the requirements of the radioactive effluent monitoring systems Technical Specifications 3.3.3.9 and 3.3.3.10 for liquids gases, respectively. Example setpoint calculations are provided for each of the required effluent monitors, r I I i 1 I 8.5-1 ! 8686R 00CM Rev.
5.1 Liould Effluent Instrumentation Setootnts Technical Specification 3.3.3.9 requires that the radioactive liquid effluent instrumentation in Table 3.3-12 of the Technical Specifications have alarm setpoints in order to ensure tttat Technical Specification 3.11.1.1 is not exceeded. Technical Specification 3.11.1.1 Ilmits the activity + concentration in 11guld effluents to the appropriate MPCs in 10CFR20 and a , total noble gas MPC. 5.1.1 Liould Waste Test Tank Monitor (RM-6509) The liquid waste test tank effluent monitor provides alarm and ; automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B Table II, Column 2 to the environment. It is also used to monitor discharges from various waste sumos to the environment. I 5.1.1.1 Method to Determine the Setootnt of the Liouid Waste Test Tank Moniter (RM-6509) l The instrument response (pC1/ml) for the limiting concentration at the point of discharge is the setpoint, denoted Rsetpoint, and is determined as follows: Rsetpoint
- Il C,g (5-1)
(pC1/ml) ()() [) where: 0F
=f=Dilutionfactor(dimensionless)' (5-2) m F, = Flow rate past monitor (gpm)
F. d
- Flow rate out of discharge tunnel (gpm)
DFmin Minimum allowable dilution factor (dimensionless) B.5-2 8686R ODCM Rev. 4 , f i
- - - +
. 1 - (f 2
- I 3); where f) is the fraction of the total f) contribution of MPC at the discharge point to be associated with the test tank effluent pathway and, f2 and f3 are the similar fractions for Turbine Building symp and steam generator blowdown pathways, respectively:' (f) + f2*I3 I II' 0F min *
{C,9 (5-3) g IWC g MPC g . MPC for radionuclide "1" from 10CFR20 Appendix B. Table II, Column 2 (pC1/ml). In the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should b2 based on the most restrictive HPC for an " unidentified" mixture given in 10CFR20 Appendix B, notes. , 1 I C,g - Activity concentration of radionuclide "1" in mixture at the ! monttor (pC1/ml) 5.1.1.2 Liould Waste Test Tank Mcntter Setootnt Example The activity concentration of each ladionuclide, C,g, in the waste test tank is determined by analysis of a representative grab sample obtained at the radwaste sample sink. This setpoint extmple is based on the following data' ! l 1 C,g (pCl/ml) MPCg (pCl/ml) ll
.Cs-134 2.15E-05 9E-06 Cs-137 7.48E-05 2E-05 Co-60 2.56E-05 3E-05 .
C,g - 2.15E-05 + 7.48E-05 + 2.56E-05 1 (h) (h) (h) (h)
= 1.22E-04 )
I i B.5-3 . , 8686R ODCM Rev.
i
- i i
0.c min
" (5-3) g uCl-ml !
gmi-pCl) ,
- 2.15E-05 + 7.48E-05 +
2.56E-05 9E-06 2E-05 3E-05 uCl-ml uCl-ml uCl-ml , (mi-pCI) (ml-pCl) (ml-pCl) DFmin " 7 d i The minimum dilution factor, OFmin, needed to discharge the mixture of radionuclides in this example is 7. The release rate of the waste test tank , d is between 10 and 150 gpm. The circulating water discharge flow can vary from 10,500 to 412,000 gpm of dilution water. With the dilution flow taken as 412,000 gpm and the release rate from the waste test tank taken as 150 gpm, the DF is: r 1 0F . [F m l (qom). (5-4) (gpm) 412.000 com 150 gpm
= 2750 1 P
B.5-4 8686R 00CM Rev. 4
Under these conditions, and with the fraction f of total MPC to be ! j associated with the test tank selected as 0.6, the setpoint of the liquid radwaste discharge monitor is: Rsetpoint * #1 0 Cml (5-1) r 4 min i h ( )( ) (,
. 0.6 2 0 1.22E-04
- ()() (,h ,
I
- 2.87E-02 pCl/mi or pCl/cc '
In this example, the alarm of the 11guld radwaste discharge monitorishould be set at 2.87E-02 pCl/cc above background. ' 5.1.2 Turbine Buildino Drains L1 auld Effluent Monitor (RM-6521) The Turbine Building drains liquid effluent monitor continuously monitors the Turbine Building sump effluent line. The only sources to the. - Sump Effluent System are from the secondary steam sys'- . Activity is , expected in the Turbine Building Sump Effluent System only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, with reduced activity from , decay and dilution. The Turbine Building drains ,lguld effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. The alarm setpoint for this monitor will be determined using the same method as
- that of the liquid waste test tank monitor if the total sump activity is greater than 10 percent of MPC. If the total activity is less.than 10 percen't of MPC, the setpoints of RM-6521 are calculated as follows:
B.5-5 8686R 00CM Rev. 1
-cc .*,,4 - , - - -
. . - - - ,...-.w.- , ~ . - - ,-vv-.
High Trip Monitor .f2 (Dr') (1.0E-07 pC1/ml) (5-21) Setoolnt (pCl/ml) . i where: Circulating water flow rate (opm) OF' . , Flow rate post-monttor (gpm) ! 1.0E-07 pct /ml most restrictive MPC value for an unidentified mixture given in 10CFR20, Appendix B, Note 3b. f2 = 1 - (f) + f );3 where the f values are described j above. l l Warning Alarm .g High Trip (5-22) Monttor Setpoint Monttor Setpoint) (0'25) i (pCl/ml) / 5.1.3 Steam Generator Blowdown Lioutd Sample Monttor (RM-6519) The steam generator blowdown liquid sample monitor is used to detect abnormal activity concentrations in the steam generator blowdown flash tank liquid discharge. The alarm setpoint for the sitam generator blowdown 11guld sample monitor, when liquid is to be discharged from the site, will be' determined , using the same approach as the Turbine Building drains liquid' effluent' monitor. For any liquid monitor, in the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20, Appendix B notes. 5.1. 4 PCCW Head Tank Rate-of-Chance Alarm Setpoint ; A rate-of-change alarm on the liquid level In the Primary Component Cooling Water (PCCW) head tank will work in conjunction with the PCCW j radiation monitor to alert the operator in the Main Control Roon. of a leak to ! B.5-6 8686R -00CM Rev.
the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint is selected based on detection of an activity level equivalent to 10-8 Cl/mi in the discharge of the Service Water System. The activity in the PCCW is determined in accordance with the liquid sampling and analysis program described in Part A, Table A.1-1 of the'00CM and is used to determine the setpoint. The rate-of-change alarm setpoint is calculated from: RC set lx10-8 SWF . h (5-23)
. (p>
<4> i i where: I I RC set . The setpoint for the PCCW head tank rate-of-change alarm (in gallons per hour). 1x10-8 The minimum detectable activity level in the Service Water System due to a PCCW to SWS leak (pCl/ml). SWF - Service Water System flow rate (in gallons per hour). l e PCC - Primary Component Cooling Water measured (decay corrected) gross radioactivity level (pC1/ml). As an example, assume a PCCW &ctivity concentration of lx10-5 pC1/mi with a service water flow rate of only 80 percent of.the normal flow of 21,000-gpm. The rate-of-change setpoint l' then: RCset lx10-8 - 1.0x100 gph (1/lx10-5_ ) 1000 gph RCset B.5-7 8686R ODCM Rev. As a result, for other PCCW activities, the RC set which would also j relate to a detection of a minimum service water concentration of Ix10'8 pCl/ml can be found from: . I RCset " C ($' } l l I i i L l , B,5-8' ODCM Rev- , 8686R . i I 4 l ! I 5.2 Gaseous Ef'luent Instrumentation Setootnts i Technical Specification 3.3.3.10 requires that the radioactive gaseous effluent instrumentation in Table 3.3-13 of the Technical Specifications have their alarm setpoints set to insure that Technica' 7pecification 3.11.2.1 is not exceeded. , i 5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1,2 and 3) The plant vent wide-range gas monitors are shown on Figure B.6-2. , 5.2.1.1 Method to Determine the Setootnt of_the Plant Vent Wide Range Gas . Monitors (RM-6528-1.2 and 3) The maximum allowable setpoint for the plant vent wide-range gas monitor (readout response in pCl/sec) is set by limiting the off-site noble gas dose rate to the total body or to the skin, and is denoted R setpoint' R setpoint is the lesser of: l-R tb = 588 (5-5) 3 mr pC1/sec . (yrem-uCI-m pCI-sec }( oCl-yr}3 mrem-m e and: i R = 3,000 (5-6) skin uCl pCl/see (*"'*) yr (mrem secyr ) i where: ; t R tb = Response of the monitor at the limiting total body dose rate (pCl/sec) 3 500 588 - (mrem-uC1-m ) (1E+06) (8.5E-07) yr-pCl-sec 8.5-9 _ _ -._ _ _ , . ] 1 i 500 Limiting etal body dose rate (mrem /yr)- IE+06 - Number of PCI per pCi (pCl/pCl) 8.5E-07=(X/QF,maximumoff-sitelong-termaveragegamma. atmospheric dispersion factor for' primary vent stack releases (:ec/m3 ) ! 1 3 DFB c - Composite total body dose factor (mrem-m /pC1-yr) i hg0FBg = (5-7) I hg hg = The release rate of noble gas "1" in the mixture, for:each , noble gas identified in.the off-gas (pCl/sec) I 3 OFB g = Total body dose. factor (see Table B.1-10) (mrem-m /pCl-yr) R skin = Response of the monitor at the limiting skin ~ dose rate. (pC1/sec) 1 3,000 = Limiting skin dose rate (mrom/yr) OF' = Compostte skin dose factor' (mrem-sec/pCl-yr)- j i hgDFj I = (5-8)~ hg
- 1 O F ,'
= Combined skin dose factor (see Table B.1-10): (mrem-sec/pCl-yr) i ,B 9-10 . ; 8686R 00CM Rev. . s y r . e 5.2.1.2 Plant Vent Wide Range Gas Monitor Setpoint Example ! The following setpoint example for the plant vent wide range gas monitors demonstrates the use of equations 5-5 and 5-6 for determining. ; setpoints. . This setpoint example is based on the following data (see Table B.1-10 for 0FBq and DF ): i h, GFB j OFj 3 j (uCl) see (mrem-m oC1-yr ) (mrom-sec) vCl-yr Xe-138 1.03E+04 S.83E-03 1.20E-02 y Kr-87 4.73E+02 5.92E-03 1.38E-02 Kr-88 2.57E+02 1.47E-02 1.62E-021-Kr-85m 1.20E+02 1.17E 2.35E ., I Xe-135 3.70E+02 1.81E-03 3.33E-03 ( Xe-133 - 1.97E+01 2.94E 5.83E-04 1 hg 0FB g 0FB c" . (5-7)- Qj 1 l hg 0FBg - (1.03E+04)(8.83Ea03) +-(4.73E+02)(5.92E-03) + (2.57E+02)(1.47E-02) + (1.20E+02)(1~.17E-03)' q t +-(3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) 1 3 = 9.83E+01 (pCl-mrem-m /sec-pCl-yr) hg = 1.03E+04 + 4.73E+02'+ 2.57E+02 I i i B.5-11 8686R 00C. Rev. - - - -- _a . - - -- - ~ - - - - - . - - . - - - a a s + 1.20E+02 + 3.70E+02 + 1'.97E+01 i = 1.15E+04 pC1/see t = 9.8"~+01 0FB q
- 1.15E+04 3
= 8.52E-03 (mrem-m /pCl-yr) 1 Rg = 588 py- ( 5-5 )- C - (588) (8.52E-03) . 'I 6.90E+04 pC1/sec and next; I hg 0Fj OF' = d (5-8)- ! ht I + (4.73t:+02)(l;38E-02). i hi 0F{ = (1.03E+04)(1.20E-0M + (2.57E+02)(1.62E-02) 4 (1.20E+02)(2.35E-03)- i e + (3.70E+02)(3.33E-03) ( (1.97E+01)(6.83E-04)- = 1.38E+02 (pCl-mrem-sec/sec-pCl-yr)- - i 0F' = 1.36E+02 1.15E+04 = 1.18E-02 (mrem-sec/pCl-yr) l 1 R skin = 3,000 h _ -(5-6) c 1 1 B.5-12 J '8686R :00CM Rev. .! l ' l 1 , .l = (3,000) ( 1.18 E-02) . 2.54E+05 pCl/sec ] l The setpoint, Rsetpoint, is the. lesser of'R tb and R skin. For the noble gas mixture in this example'R tb is less than Rskin, indicating that -- the total body dose rate is more restrictive. Therefore, in'this example the plant vent wide-range-gas monitors should each be set at no more than 6.90E+04 pC1/sec above background, or at some administrative. fraction of the above , value. In the event that no activity-is expected to be released, or can be measured in the system to be vented, the gaseous monitor setpoint should be based on Xe-133.
- I.
- i i
I l B.5-13 . -8686R 00CM Rev. s .-..... . .. - - - -. . - . .. . . . - , . 'h 6.0 LIQUIO AND GASEOUS EFFLUENT STREAMS, RADIATION HONITORS AND RADWASTE TREATHENT SYSTEMS , Figure B.6-1 shows the liquid effluent streams,' radiation monitors and ; the appropriate Liquid Radwaste Treatment System. Figure-B'.6-2 shows the gaseous effluent streams, radiation monitors and the appropriate Gaseous ' Radwaste Treatment System. [ For more detailed information concerning the above, refer to the Seabrook Station Final Safety Analysis Report, Sections ll.2 (Liquid-Waste . System), 11.3 (Gaseous Waste System) and 11.5 (Process and Effluent [ Radiological Monitoring and Sampling System). a The turbine gland seal .ondenser exhaust.is an unmonitored release- .; path. The lodine and particulate gaseous releases will be determined by continuously sampling the turbine gland seal condenser .aaust. The noble gas releases will be determined by the noble gas released via the: main condenser air evacuation exhaust and ratioing them to the turbine gland seal condenser exhaust by use of the flow rates. l I e i l i i 1 L C 1 B.6-1 [ ~8687R OOCH Rev. :4 ., .t h - .- - . - . - -.-. .-- . . - . . . - . . - . . . . ~ . - - - _ . . _ _ . - _ - - _ - - --- - _ _ - - - - - _ - _ - - - - - - _ _ _ . 1 I 1 -l l l ~1 M l 8 WAEEup ; MAKEUF SfosAGE 1 i StomaGE pas. TANE- J TANE pas UNIT,1
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1P ,j i ! tr AUMILIAAY SUILDINC VGNT AIR k = L 1 3 LacsNO A* j r M . MGPA FILit A '}. = C - CMA ACCAL FILTER === XH-RADIATIott SU7LDINC' MONITOR * ,4 . Figure B.6-2~ Caseous E! fluent Streams, Radiation' Monitors, and Radwasta' ; Treatment System at Seas, rock Station y p i i 1' , 'l l B '. 6 ] 00CM Rev. A ' te c( 1 1 7.0 BASES FOR DOSE CALCULATICN METH005 7.1 Liould Release Oose Calculations ~ This section scrves: (1)'to document the development and conservative , nature of Method I equations to provide background:information to Method I ) users, and (2) to identify the general. equations, pararneters and approaches to' l Method II-type dose assessments. Method I may be used to show that the Technical Specifications which-limit off-site total body dose from liquids (3,11.1.2 and 3.11.1.3) .have been met for releases'over the appropriate periods. .The quarterly and annual dose 1 limits in Technical Specification 3.ll.l.2.are based on the ALARA design , objectives in 10CFR50, Appendix I Subsection II A'. The. minimum dose values noted in Technical Specification 3.11.1.3 are '.' appropriate fractions," as determined by the NRC, of the design objective to ensure-that radwaste-equipment is used as required to keep off-site doses ALARA. - Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" .(10CFR50,- Appendix I). The definition, below, of a single " critical receptor" (a-hypothetical or real individual whose behavior results in a maximum potential-dose) provides part of the conservative margin to the calculation of total
- body dose in Method.I. Method II allows that actual; Individuals, associated j with identifiable exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method-II
- analysis'for a critical ,
I receptor assuming all principal . pathways present instead of any real individual. That analysis was called the base cas'e;" It 'was then ' reduced to form Method I. The general equations used in:the base case analysis:are also used as the starting point in' Method II evaluations. The base case, the. 4 method of reduction, and.the assumptions and data used are presented below. , The staps performed in tne Method I derivation follow. First,-the dose impact to the critical receptor [in the form of dose factors DFl itt 'j (mrem /pC1)] for a unit activity release of.each radioisotope in: liquid ~ effluents was derived. The base case analysis uses the general: equations,- methods,. data and assumptions in Regulatory Guide 1.109-(Equations A-3 and: B -' 7-1 . . . I 8688R L OOCM Rev . ' 4 ' . ' I . m __ A-7, Reference A). Vne 11guld pathways contributing to an' individual dose are due to consumption of fish and invertebrates, shoreline activities, and swimming and boating near the discharge point. A normal operating plant discharge flow rate of 918 ft 3/sec was used with a mixing ratio of 0.10. , The mixing ratio of 0.10 corresponds to the minimum expected prompt dilution ! or near-field mixing zone created at the ocean surface directly above the multiport diffusers. (Credit for additional dilution to the outer edge of the prompt mixing zone which corresponds to the 1 F surface isotherm (mixing r?tio .025) can be applied in the Method II calculation. The edge of this isotheia typically does not reach the shoreline receptor points during the tidal cycle ) The location of the critical receptor is assumed to'be the edge of the r!xing zone at the ocean surface. The transit time used for the c 'ocd oathway was 24 hours and for shoreline activity 0.0 hours. T av t . ,-l outlines the human consumption and use factors used in the-analysis. The resulting, site-specific, total body dose factors appear in Table 8.1-11. , 7.1.1 Dose to the Total Body For any liquid release, during any period, the increment in total body dose from radionuclide "1" is: DFl (7-I) AD " 01 tb itb o (mrem) ( ) (pC1) (*['*) where: , DFLitb - Site-specific-total. body dose' factor (mrem /pC1) for a : liquid release. It is the highest of the four age groups. See Table B.1-11. Qt - Total activity (pC1) released for'radionuclide."1". . K - 918/fd (dimensionless); where'Fd is the average dilution flowoftheCirculatingWaterSystematthegointof discharge from the multiport diffuser (in ft-/sec). Method I is more conservative than Method'II in the region of the Technical Specification limits because the dose factors CFlitb used in Method I were chosen for the base case to be the highest of the four age B.7 . ODCM'Rev, '8688R i l' t groups (adult, teen, child and infant) for that radionuclide, fn effect each radionuclide is conservatively represented by its own critical-age group. j i 7.1.2 Dose to the Critical Organ The methods to calculate maximum organ dose parallel to the total body. dose methods (see Section 7 1.1). For each radionuclide, a dose factor (mrem /pCi) was determined for.each of seven organs ar.d four age groups. The largest of these was chosen to be the maximum organ dose factor (0FL g ,g) for that-radionuclide. OFLj ,3 also ih-cludes the external dose contribution to the critical organ, i For any liquid release, during any period, the increment in dose from : radionuclide "1" to the maximum organ is: l -k Qj DFl igo (7-2) . AD,g (mrem) ( ) (pC1) (*['*) where: OFl imo - Site-specific maximum organ dose-factor (mrem /pC1) for a liquid release. See Table B.1-il. .; Q1 = Total activity (pC1) released for radionuclide "1". K = 918/fd (dimensionless); where Fd is_the average dilution ' flow of the Circulating Hater < System at'the point of discharge'from the multiport diffuser (in ft3/sec). , i t - J -B.7-3 00CM Rev.. 8688R . i [ TABLE B.7-1 usage Factors for Various Liquid Pathways at Seabrook Station (from Reference A, Table E-5*, except as noted. Zero where no pathway exists) ~ i AGE RG. LEAFY MI'LK MEAT. FISH INVERT. POTABLE SHORELINE SWIM 41NG* *
- BOATING ***
VEG. WATER i (KG/YR) (KG/YR) (LITER /YR) (KG/YR) (KG/YR) (KG/YR) (LITER /YR) (HR/YR) (HR/YR) (HR/YR) k Adult' 0.00 0.00 0.00 0.00 21.00 5.00 0.00 334.00 " 8.00 52.00 l i Teen- 0.00 0.00 0.00 0.00 16.00 3.80 0.00 67.00 45.00 52.00 ChIid :0.00 0.00 0.00 0.00 6.90 1.70 0.00 14.00 28.00 29.00 l - : Infant- 0.00 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- Regulatory-Guide 1.109
** Regionalishoreline'use associated with mudflats - Maine Yankee Atomic Power. Station Environmental Report ~ i ._ "***' HERMES; "A Digital Compinter Code.for Esti:r.ating Regional Radiological Effects from Nuclear Power Industry," '
- HEDL. December 1971. Note,-for Method II.' analyses, these pathways need not be evaluated since they represent
~ ? [ only..a small fraction'of-the total. dose' contribution associated with the other pathways. i 4 4 j B.7-4 , 8688R OOCH Rev. ,- c, . ~:.- . . , - . ~ - - .-- _ . , - . . -.e. - .- - .. - . , _ - _ ~ . - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - . . _ _ . _ _ _ _ - . l 7.2 Gaseous Release Oose Calculations 'f l I 7.2.1 Total Body Dose Rate From Noble Gases 1 This section serves: (1) to document the development of the Method I , equation, (2) to provide background information to Methoc t. users, and (3).to identify the general equations, parameters and approaches to Method II-type -i dose rate assessments. ! Method I may be used to show that the_Te:hnical Specification which ' limits total body dose rate from noble gases released to-the atmosphere (Technical Specification 3.ll.2.1)-has been met for the peak noble gas ' release I rate. -i l Method I was derived
- rom general-equation B-8 in Regulatory Guid'e !
1.109 as follows: i -L b tb = 1 +06 U/Q hj OFB j (7-3)- 1 (mrem) , (gCl,) (sec) yr pCl (g) (mrom-m pC1-yr 3 ) ,3 sec where: CX/Q1Y = Maximum.off-site receptor location long-term average gamma ; atmospheric dispersion factor. = 8.SE-07 (sec/m3 ). l hg , = Release rate tb the environment of noble gas "1" (pC1/sec). OFB g = Gammatotalbodydosefactor,(]"y ). See Table B.1-10. (Regulatory Guide 1.109, Taole B-1). Equation 7-3 reduces to: I 0.85
- EL(R) *Lp O = 0FB tb Qg I (3-3)
~{ (mrem) , (oCI-sec)_( yr 3 ) (g) sec (mrem-m 3 pct-yr ) y 1 C1-m ' 4 8688R' 00CM Rev. 'i t The selection of critical receptor, outlined in Section 7.3 is inherect in the derived Method I, since the maximum expected off-site lon'g-term average atmospheric dispersion factors were used for a primary vent stack release . The EL(R) term is added to the above equation as a dimensionless correction ; factor to be applied when calculating the impact from ground level release points. For primary vent stack releases, this correction factor is equal to 1.0 since the dose conversion factors are based on meteorological dispersion parameters derived for this release point. For release points other than the-primary vent stack, the correction factor reflects-the difference between ground level dispersion and that associated with the primary vent stack. 1. l ; noble gases in Table B.1-10 should be considered. A Method II analysis.could include the use of actual. concurrent meteorology..to assess the dose rates as the re d t of a specific release. 7.2.2 Skin Dose Rate From Noble Gases -j This section serves: (1) to document the development of the-Method I equation, (2) to provide background information to Method I users, and-(3)'to identify the general equations parameters and approaches to. Method II-type ' dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Only the differences are presented here. ' Hethod I may be used to show that the Technical Specification M.ich limits skin dose rate from noble' gases released to the atmosphere (Technical Specification 3.11.2.1) has.been met for the peak noble gas release rate. The annual skin dose limir 1s-3,000 mrem (from NBS Handbook 69, Reference 0, pages 5 and 6, is 30 rem /10).- 'The factor of 10 reduction'is to account Jor nonoccupational. dose 1Imits. It is the skin dose commitment to the critical,-or most'llmiting, off-site receptor assuming long-term site average meteorology and that the release rate reading remains constant over the. entire year. B.7-6: 8688R 00CM Rev. 1 l Method-I was derived from the general- equation 8-9 in Regulatory Guide - 1.109 as follows: l 3 D - 1.11 0 + 3.17E+04 Qg (X/Q) DFSj (7-4) tr 1 3 mrem pCl-yr (mrem) yr , (mrad) (mead) yr C_1 m ) (mrem-m ) (Cl-sec) yr (3 3 pCi-yr - q where: 1.11 = Average ratio of tissue to air absorption coef'ficients '(will- ! convert mrad in air to mrem in: tissue). OFS1 - Beta skin dose factor for'a semi-infinita-cloud of i radionuclide "1" which includes the attenuation by 'the outer- " dead" layer of the-skin. 0 tr = 3.17E+04 Qj CX/Q) 0F j Y - (7-5) 1 DCl-yr 3 C (mrad) (yr)J (sec) mrad-m yr (C1-sec) - ,3 pCl-yr DF{=Gammaairdosefactorforauniformsemi-infinitecloudof ;
- radionuclide "1".
i- , Now it is assumed for the definition of (X/QY) from
Reference:
B that: i O ftnite = 0 Ir (X/QlT/(X/Q) (7-6). ; i 3 ; (mrad) yr ' (mrad) yr (see) (msec)
,3 .
3 i and Q=j 31.54 Qg (7-7) ( C1 (yr) ,,.(Cl-sec) j . pCl-yr (uC1) sec : 8.7-7 8688R 00CM'Rev. -i l
l so: b = 1.11 1E+06[X/QN hg 0Fj (7-8) skin 1 3 (mrem) , (mrem) (p2) ( s e_c ) (uCl) (mred-m ) yr mrad pCl ,3 sec pC1-yr ,
+ 1E+06 X/Q hg 0FS g 1
3 (pg) -see pH (mrem-m ) , pCl ,3 sec pCl-yr substituting 3 [X/Q)Y = 8.5E-07 sec/m 3 X/Q = 8.2E-07 sec/m ! t (7-9)' gives b = 0.94 hg 0.82 hg OFS g skin 1 0F{- + 1 l 3 3 (mrem) ,goCi-sec-mrem)(uCl)(mrem-m )(DCl-sec)(uC1)(yem-m ) yr sec pC1-yr sec pd -yr l Cl-m3-mrad Cl-m 3 4
= hg[0.940F{+0.820FS1 g
.(7-10)
I t define DFj=0.940F{+0.820FSg (7-11) -> o then:.b skin - EL(R)
- hg . OFj (3-4) !
1 (mrem) , (- ) (uC , ( mrem-sec) yr sec pCi-yr l The EL(R). term is added to the above equation as a'dimensionless correction factor be applied-when calculating the impact from ground level release points. For-i 8.7-8 8688R. -00CM Rev. j l
primary vent stack releases, this correction factor is equal to 1.0 since the dose conversion factors are based on meteorological dispersion parameter derived for this release point. For release points other than-the primary vent stack, the correction factor reflects the difference between ground level dispersion and thai associated with the primary vent stack. - - The selection of critical receptor. outlined in Section 7.3, is inherent in-l the derived Method I, as it is based on the determined maximum expected off-site j
- atmospheric disperston factors. All noble gases in- Table B.1-10 must be l considered.
l 7.2.3 Critical Oroan Oose Rate From Iodines, Tritium and Particulates With Half-Lives Greater Than Elaht Days , l This section serves: (1) to document the development of the Method I equation, (2) to provide background information to Method I users, gnd (3) to identify the general equation's parameters and approached to Method II type dose rate assessments. The methods to calculate skin dose rate parallel the ' total body dose rate methods in Section 7.2.1. Only the differences are l l presented here. Method I may be used to show that the Technical Specification which limits organ dose rate from iodines, tritium and radionuclides in particulate . , form with half lives greater than 8 days released to the atmosphere (Technical I Spectfication 3.11.2.1)-has.been met for the peak above-mentioned release-rates. The annual organ dose limit is 1500 mrom (from NBS; Handbook 69, Reference 0, pages 5 and 6). It is evaluated by looking at the critical organ dose commitment to the most limiting off-site receptor assuming long-term site
- average met'eorology.
Theeaationforb co is derived by modifying EcuaM on 3-8 from Section 3.9 as follows: l O " # 0 10FG jg, (3-8) co 1 (mrem) (; ) (pCl). ( *)- l L . i' B.7-9 ' 00CM Rey, 8686R- : i
-i ET e - - ___________s a __+__ _ _ - _ _ . _ _ - _______-__s. _ _ _ - - - _ m _.. .-_m__ -_
t applying the conversion factor, 3.154E+07 (sec/yr) and converting Q to hinpCl/secyields ! b co
- 3.154E+07
- EL(R)
- hg 0FG jen (7-12)
(mrem) , (Leg) ( ) _(uCl) (mrem) yr yr sec pct Eq. 3-8 is rewritten in the form: b eo EL(R)
- hg 0FGjen (3-5)
(mrem) yr < ) (uC1) sec (mrem-sec) pC1-yr. 4 ;
- where f.
DFGjeg = 3.lS4E+07- 0FG U-I3' ico gmrem-sec) , e
< jiec,) (mrom) pCl-yr yr pCl I
- In the case of the dose rate conversion factor (DFG1co), the dose conversion
- factors for lodine and particulate exposure pathways-(DFG1co) are derived with the Shielding Factor (SF) for ground plane exposure set equali to 1.,0.
For. accumulated doses over extended periods, the 0FG 1co are calculated with' SF = 0.7, as referenced in-Regulatory Guide 1.109. The select 1.on of critical receptor, outlined in Section.7.3 isl. inherent in 3 Method I, as are the may bum expected off-stte atmospheric: dispersion factors. Should Method.II.be needed, the analysis'for critical receptor, critical; pathway (s) and atmospheric dispersion factors may be; performed with concurrent meteorology and latest land use census-data to!!dentify existing-pathways. - B.7-10 M
, , '8688R 00CM'Rev. 1 q
J. l 1
- x. _.. ... .
i 7.2.4 Gamma Dose to Air From Noble Gases This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I : users, and (2) to identify the gener.al, equations, parameters and approaches to Method II-type dose assessments. -t Method I may be used to show that-the Technical Specification 3.11.2,1 ; which limits off-site gamma air dose from gaseous effluents has been met for' , releases over appropriate periods. This Technical. Specification.1s based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated gamma air dose in off-site unrestricted areas. ; For any noble gas release, in any period, the Increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide. l.109 with the added assumption that Ofinite = O D /Q]Y / g/g); f 40,Jr = 3.17E+04 (X/Q]Y Qg DFY (7 14) 1
# 3 (mrad) = ( ec) (sec/m ) (Cl) ( )
e where:
, 3.17E+04 = Number of pCl per Cl divided by the number of seconds per year.
[X/Q]Y = Maximum off-site long-term average gamma atmospheric dispersion factor for the primary vent stack release point.
= 8.5E-07 (sec/m3 )
( - Qg = Number of curies of noble gas "1" released. l I 0F{ = Gamma air dose factor for.a uniform. semi-infinite cloud of radlonticlide "1". l B.7-11 ' 8688R 00CM Rev. .I
c l which leads to: D ar
- 2.7E-08
- EL(R) '
Qj OF{ (3-6) "i i I d
) ('pC l )~ ( )'
(mrad) =(D'*I3)pC1-m ( , As done above, the EL(R) correction factor has been addcd to allow for , the determination of dose-Impacts from ground level release points utilizing
~
the same dose equation as used for the primary vent stack. The major difference between Method I'and Method II is that Method II would use actual or concurrent meteorology with a' specific noble gas release spectrum to determine-(X/Q)Y rather than use the site'.s long-term average , meteorological dispersion values. I 7.2.5 Beta Dose to Air From %ble G0ses- ! This section avrvos: (1) to document the development.and conservative nature of Metnod I % eations to provide' background information-to Method.'I -l i users, and (2) to identify the general equations, parameters .and. approaches 'to- ; Method II-type dose assessments. Method I may be used to show that Technical Specification 3.11.2.1, which limits off-site beta air dose from gaseous effluents,~ has:been met for- l releases over appropriate periods. This Technical Specification is based on } the objective in 10CFR50, Appendix I, Subsection B'.1,'which limits the , estimated beta air dose in off-s1te unrestricted;areaLlocations. q q For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory-Gulde 1.109:~ ' 8.7-12
-8688R 00CM Rev. ,
k i
;)
_.u-. _
- . . . , .._ n. . . _ _ . . . _ _ _ _ ____1.______..._.____!
1 -) . 0 a0 fir = 3.17E-02 X/0 1 Q{ OF (7-15) l (mrad) = ( c) ( ) (pCl)'( d
) ]
~
l'. 1 where: l Off-Betaairdosefactorsforauniformsemi-inftnttecloud_of-radionuclide "1". substltuting X/Q = Maximum off-site long-term average undepleted atmospheric , dispersion factor for the primary vent. stack release point. t
= 8.2E-07 sec/m3 .
We have /- Ofir - 2.6E-08
- EL(R)
- Qg 0F0 ' .( 3-7)
,1 3
(mrad) - (pCl-yr )-( ) ( Cl) (mrad-m ) pCl-m 3 pCl-yr As done above, the EL(R) correction factor bas been added to. allow for
' the determination of dose impacts from ground level release points utilizing
~
the same. dose equation as used for the primary vent stack. l- 7.2.6 Dose to Critical Oraan From'Ic.11nes, Tritium and Particulates' With- 1 1 . Half; Lives Greater Than Elaht Oa'ys I i l This section serves: .(1) to document the-development and conservative' l l l nature of Method I equations to provide background Information to Method I , users, and (2) to identify the general equations, para'4ters and approaches to -j Hethod II-type dose assessments. i B.7 8688R '00CM'Rev; ; 4 y -- , , , _
. - = - . . -- . - - .
L Method I may be used to show that the Technical Specifications thich
$imit off-site organ dose from gases (3.11.2.3 and 3.11.4) have been met for.
releases over the appropriate periods' Technical Specification 3.11.2.3 is based on the ALARA objectives in 10CFR50, Appendix I, Subsection II C. Technical Specification 3.11.4 is based on Environmental Standards for Uranium fuel Cycle in.40CFR190, which applies to direct radiat on as well as liquid and gaseous effluents. These methods apply only to lodine, trittum, and , particulates in gaseous effluent contribution. ! 1 Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use below of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis of a critical' receptor assuming all pathways present. That analysis was called the " base case"; it was then reduced to form Method I. The. base case, the method o' reduction, and the assumptions and data used are presented below. The steps performed in the Method I derivation follow. - First, the dose impact to the critical receptor [in the form of dose factors DFGgco (mrem /pC1)] for a unit activity release of each iodine, tritium,-and i particulate radionuclide with half lives greater than eight days to gaseous i effluents was derived. Six exposure pathways (ground plane, inhalation, stored vegetables, leafy vegetables, milk, and meat ingestion) were assumed to exist at the site boundary (not over water or marsh areas) which exhibited the highest long-term X/Q. Doses were.then calculated to six organs.(bone, liver, kidney, lung, GI-LLI, and thyroid), as well as for the whole. body and skin for four age groups (adult, toer.ager, child, and infant) due to the seven combined exposure pathways. For each radionuclide, the highest dose per unit activity release for any organ (or whole body) and age group was then selected to
- become the Method I site-specific dose factors. The base case, or Method I analysis, uses the general equations methods, data, and assumptions in Regulatory Guide 1.109 (Equation C-2 for doses-resulting from direct exposure to contaminated ground plane; Equation C-4 for doses B.7-14 8688R 00CM Rev.
l
Meth)d I may be used to show that the Technical Specifications which limit off-!!te organ dose from gases (3.11.2.3 and 3.11.4) have been met for releases over the appropriate periods. Technical Specification 3.11.2.3 is based on the Al. ARA objectives in 10CFR50, Appendix I.. Subsection II C. Technical Specification 3.11.4 is based on Environmental Standards' for Uranium fuel Cycle in 40CFR190, which applies to direct radiation as well as. liquid and gasecut effluents. These methods apply only to lodine, tritium, and particulates in gaseous effluent contribution. Method I was developed such that "the actual exposure of an-individual ... Is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use celow of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ dose in Method I. Method II allows that actual' individuals, associated with identiflable exposure pathways, be taken into account for any given release. In fact, Method. I was based on a-Method II analysis of a critical receptor assuming all pathways-present. That analysis was called the " base case"; it
~
was then reduced to form Method I. The base case, the method of reduction, and the assumptions and data used are presented below. The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor (in the form of. dose factors.0FG gc3 (mrem /pCl)] for a unit activity release of each todine, tritium, and
~
particulate radionuclide with half lives greater than eight days to gaseous effluents was derived. Seven exposure, pathways (ground E ane, inhalation, stored vegetables, leafy vegetables, milk, and meat-Ingestion) were assumed to exist at the site boundary-(not over water or marsh' areas) which exhibited the highest long-term X/Q. Doses were then calculated to six organs (bone, liver, kidney, lung, GI-LLI, and thyroid), as well' as' for the whole body and skin for four age groups (adult, teenager, child, and. infant) due to'the seven combined exposure pathways. For each radionuclide, the highest dose per unit activity release for any organ (or whole body) and age group was then selected to-become the Method I site-specific dose factors. The base case, or Method I-analysis, uses the general equations methods data, and assumptions in-Regulatory Guide 1.109 (Equation C-2 for doses resulting from direct' exposure to contaminated ground plane: Equation C-4 for doses' s B.7-14 8688R' 00CM Rev.
associated with inhalation of all radionuclides to different organs of Individuals of different age groups; and Equation C-13 for doses to organs of-Individuals in different age groups resulting from ingestion of radionuclides in produce, milk, meat, and leafy vegetables in Referenca A). Tables B.7-2 and B.7-3 outline human consumption and environmental par eeters used in the ! analysis. It is conservatively assume'd that the critical receptor lives at' { the " maximum off-site atmospheric dispersion factor location" as defined in Section 7.3. 1 The resulting site-specific dose factors are for the maximum organ ' which combine the limi_ ting age group with the highest dose factor for any organ with each nuclide. These critical organ, critical age dose factors are given in Table B.1-12. For any lodine, tritium, and particulate gas release, during'any- , period, the increment in dose from radionuclide "1" is: f I (7-16) 1 ADico " O l0FGico where OFGge,is the critical dose factor for radlonuclide "1" and Qp is_ the activity of radionuclide "1" released in microcuries. 7.2.7 Special Receptor Gaseous Release Oose Calculations Technical Specification 6.8.1.4 requires that the doses to individuals involved in recreational activities within the site boundary are to be determined and reported in the annual Semlannual. Effluent Report The gaseous dose. calculations for the special receptors parallel t'_ , bases of the gaseous dose rates and doses in Sections 7.2.1 through 7.2.~ Only the differences are presented here. The special recaptor XQs are given in Table B.7-5. 7.2.7.1 Total Body Dose Rate From Noble Gases, Method I was derived from Regulatory Guide 1.109'as.follows: l
-B.7 8688R C red Rev. q l
l
.- . . . . . . - = . - _ . --..- , . - . i l l l 0FBg (7-3) btb = IE+06 (X/Q]Y l General Equation (7-3) l- then multiplied by an Occupancy Factor (OF) -1 to account for the time an individual will be at- the on-site receptor locations during the year. For the Education Center, and the " Rocks", the'0Fs -
)
are: l 1 Education Center - j = 0.0014 -1 The " Rocks" - 6
- 0.0076 substituting
[X/Q]Y = 1.lE-06 sec/m3 (Education Center) for primary vent stack releases. -
- 5.0E-06'sec/m3 (The " Rocks") for primary vent' stack releases.
4 multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
1 and adding the release point correction'i' actor EL(R) gives: btbE = 0.0015
- EL(R)i
- b.OFR, (mrem /yr) (7-17)
* (mrem /yr) (7-18) btbR = 0.038
- EL(R)1 hg- 0FB g 1
(I)Taken from Seabrook Station Technical Specifications (Figure 5.1-1). B.7-16 i 8688R 00CM Rev.. l
.1 e , , - ,wr
t where: htbE,andhtbR = Total body dose rates due to noble gases to an Individual at the Education Center and the " Rocks" (recreational, site), respectively. Qj = Oefined previously. l OFB, = Defined previously. EL(R) = Defined previously. 7.2.7.2 Skin Dose Rate From Noble Gates Method I was derived from Equation (7-8):- I (7-8) bskin = 1.11IE+06 [X/Q]Y .h,OF{ + i DFS j lE+06 ):/Q t substituting l
' [X/Q)Y = 1.lE-06 sec/m3 -(Education Center) for primary vent stack releases.
- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.
l X/Q = 1.6E-06 sec/m3 (Education Center) for primary vent stack releases.
= 1.7E-05 sec/m3 (The." Rocks") for primary vent stack releases, multiplying by OF = 0.0014 (Education Center) .
B.7-17 8688R 00CM Rev.
7 i f 0.0076 (The " Rocks") gives bskinE - 0.0014 hj (1.22 DFJ + 1.60 0FSg] (mrem /yr) bskinR 0.0076 hg C5.550F{+17.00FS](mremg /yr) t and with the addition of the release point correction factor EL(R), the equations can be written: bskinE = 0.0014
- EL(R)
- hj OFjE'(mrem /yr)
I bskinR 0.0076
- EL(R) h30FlR (mrem /yr) where:
b skinE andbskinR = The skin dose rate due to noble gases to an individual at the Education Center and the " Rocks," respectively, hg = Defined previously. EL(R) = Defined previously.
"1" DF'1E and 0F'IR = The combined skin dose factors for radionuclide '
f^r the Educattor Center, and the " Rocks", respectively (see Table 8.1-13).. 1 i i B.7-18 8688R 00CH Rev.
7.2.7.3 Crltical Organ Dose Rate From Iodines, Tritium and Particulates With Half-Lives Greater Than Eloht Days Theequationsforb are derived in the same manner as in
, co Section 7.2.2, except that the occupan'cy factors are also included. Therefore:
* (7-21) bcoE = 0.0014
- EL(R) hj OFGjcoE(mrem /yr)
(7-22) bcoR = 0.0076
- EL(R)
- h30FG lcoR (mrem /yr)
I where: b coE andbcoR = The critical organ dose rates to an individual at the Education Center and the " Rocks", respectively. hg = Oefined previously. EL(R) = Oefined previously. OF'icoE and 0F'gcog The critical organ dose rate factors fcr radionuclide "1" for the Education Center ,. I and the " Rocks," respectively (see Table B.1-14). 7.2.7.4 Gama Dose to Air From Noble Gases t Method I was derived from Equation (7-14):-
'9 1 (7-14F 0F{
0[r = 3.17E+04 (X/Q]Y B.7-19 8688R 00CM Rev. ; i I
i substituting (X/Q]Y = 1.lE-06 sec/m3 (Education Center) for primary vent stack releases. 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases. multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
and 1E-06 C1/pC1, plus adding the release point correction factor EL(R) gives / O trE - 4.88E-11
- EL(R)
- Qg 0F{ (mrad)
(7-23) 1 0 irR - 1.20E-09
- EL(R)
- Qg 0F{ (mrad)
(7-24) l 1 where: i l 0 trE and 0 irR - The gamma air doses to an Individual at the Education Center and the " Rocks," respectively. Qg - Total activity (pC1) released to the atmosphere via the station ; vents of each radionuclide "i". OF{,DF{,andEL(R)=Oefinedpreviously. 8.7-20 8688R 00CM Rev. w ---
l 7.2.7.5 Beta ~ Dose to Air From Noble Gases i Method I was derived from Equation (7-15): O tr 3.17E+04 X/Q 9Off1
-(7-15)-
substituting X/Q = 1.6E-06 sec/m3 (Education Center) for primary vent stack releases.
.1
- 1.7E-05 sec/m3 (The " Rocks") for primary vent stack releases. ;
multiplying by 1 0F - 0.0014 (Education Center) ' [
= 0.0076 (The " Rocks")
and IE-06 Cl/pCl, plus adding the release point correction factor EL(R) gives
, OfirE-7.1E-11*EL(R)* Q,OFf (mrad) (7-25) 1 OftrR.=4.1E-09*EL(R)* Qg 0Ff (mrad) (7-26) i 1
-i I
B.7 8688R OOCH Rev, i
where: 0 0 alrE andOfirR=Thebetaairdosesto'anIndividualattheEducation Center and the " Rocks," respectively. Og - Total activity (pCl) relea' sed to the atmosphere via the station vents of each radionuclide "1". Off,Off,andEL(R)=Oefinedpreviously; i 7.2.7.6 Critical Organ Dose From Iodines, Tritium and Particulates With l Half-Lives Greater Than Elcht Days . Method I was derived in the same manner as Equation (3-8): O co
- EL(R)
- Qg 0FG lco (3-8) 1 multiplying by:
OF = 0.0014 (Education Center) 0.0076 (The " Rocks") ; i l and IE-06 C1/pCl; plus substituting the location specific 0FGs gives Q 0FG (mrem) (7-27); OcoE - 0.0014
- EL(R)
- 1
$ lcoE ,
Q3 0FG lcoR (mrem) (7-28) OcoR = 0.0076
- EL(R)
- 1 i
S.7-22 8688R 00CM Rev.
where: D and O coR
= The critical organ doses of an individual at the:
coE Education Center and the " Rocks," respectively. Qg - The total activity (pCl) released to the l , atmosphere of radionuclide "1". DFG lcoE and DFGlcoR = The critical organ dose' factors (mrem /pCl) for the Education Center and the " Rocks," respectively for each radionuclide "1". The factors represent ; the age group and organ with the largest dose factor (see Table B.1-14). EL(R) = Oefined previously. The special receptor equations can be applied under the follo, wing conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event).
l
- 2. Applicable radionuclide releases via the station vents to the l atmosphere.
l l If Method I cannot be applied, or if the Method I dose exceeds this limit, or if a more refined calculation is required, then Method II may be applied. j B.7-23 8688R 00CM Rev- . i
i TABLE B.7-2 l i Environmental Parameters for Caseous Effluents at Seabrook Station (Derived rrom Reference A)* Vegetable <, Cow Milk Goat Milk Meat Variable - Stored. Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural (Kg/M2 ) 2. 2. 0.70- 2. 0.70 2. 0.70 2. l" Product 1v1ty P Soll Surface Density (KG/M 2) 240. 240. 240. 240. 240. 240. 240. 240. T Transport Tina io User (HRS) 48. '48. 48. 48. ;30 480. IB Soll ExPasure Tlee(I) (HRS) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 131400. t TF Crop Er.posure Tlw (HRS) 1440. 1440. 720. 1,440. 720. 1,440. 720. to Plume 1.440.l TH Holdup After Harvest (HRS) 1440. 24. O. 2160. O. 2160. O. 2160. . QF Animals Daily Feen (KG/ DAY) ,
- 50. 50. 6. 6. . 50. 50.
FP fractton of Year. 0.50 0.50 0.50 ' on Pasture (2) FS Fraction Pasture 1. 1. 1. when on Pasture (3) . FG Fraction of Stored 0.76 Veg. Grown in' Garden FL Fraction of Leafy 1.0 Veg. Grown in Garden FI Fraction Elemental Iodine - 0.5 H Absolute (ge/M3 ) Humidtty - 5.60(4)- <
- Regulatory Guide 1.109. Rev. I B.7-24 8688R- 00CM Rev.
b.
, . , . ,,.....a-. ~ -
- . . . _ _ . . , . - . . , _ _..,.s. . . , _ . ,
l TABLE B.7-2 . (Continued) Notes: (1) for Method II dose / dose rate analyses of identified radioactivity releases of less than one year, the soll , exposure time for that release may be set at 8760 hours (1 year) for all pathways. l (2) for Method II dose / dose rate analyses performed for releases occurring during the first or fourth calendar quarters, the fraction of time animals are assumed to be on pasture is zero (nongrowing season). For the second and third calendar quarters, the fraction of time on pasture (FP) will be set at 1.0. FP may also be adjusted for specific farm locations if this information is so identifled and reported as part of the land use census. (3) for Method II analyses, the fraction of pasture feed while on pasture may be set to less than 1.0 for specific '
~ farm locations if this information is so identified and reported as part of the land use census.
(4) for all Method II analyses, an absolute humidity value equal to 5.6 (ge/m3) shall be used to reflect conditions in the Northeast (
Reference:
Health Physics Journal, Vol. 39 (A *st), 1980; Page 318-320, Pergammon Press). l i l 1 ! 1-B.7-25 8688R. ODCH Rev.
. . . ~ .-. . - _. _. -
P 1 TABLE B.7-3 Usage Factors for Various Gaseous Pathways at Seabrook Station (from Reference A Table E-5)* f Maximum Receptor: Age Leafy Group Vegetables Vegetables Milk Meat Inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr) Adult 520.00 64.00 310.00 110.00 8000.00 Teen 630.00 42.00 400.00 65.00 8000.00 Child 520.00 26.00- 330.00 41.00 3700.00 Infant 0.00 0.00 330.00 0.00 1400.00 I I The " Rocks" and Education Center: Age Leafy Group Vegetables Vegetables Milk Meat . Inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr) Adult 0.00 0.00 0.00 -0.00 8000.0 , Teen 0.00 0.00 0.00 0.00 8000.0 Child 0.00 0.00 0.00 0.00 3700.0 Infant 0.00 0.00 0.00 0.00- 1400.0
- Regulatory Guide 1.109 B.7-26 8688R 00CM Rev.
7,3 Receptor Points and Average Atmospheric Dispersion Fac? ors for Important E;posure Pathways The gaseous effluent dose equations (Method I) have been simplified by assuming an individual whose behavior and living habits inevitably lead to a higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:
- 1. Direct exposure to contaminated air;
- 2. Direct exposure to contaminated ground;
- 3. Inhalation of air;
- 4. Ingestion of vegetables;
- 5. Ingestion of goat's milk; and !
- 6. Ingestion of meat.
1 Section 7.3.1 details the selection of important-off-site and on-site locations and receptors. Section 7.3.2 describes the atmospheric model used i to convert meteorological data into atmospheric dispersion factors. Section 7.3.3 presents the maximum atmospheric dispersion factors calculated at each l of the off-site receptor locations, f i 7.3.1 Receptor Locations The most limiting sitt boundary location in which individuals are, or likely to be located as a place of residence was assumed to be the receptor for all the gaseous pathways considered. This provides a conservative estimate of the dose to an individual from existing and potential gaseous pathways for the Method I analysis. B'7-27 8688R ODCM Rev.
i t This point is the west sector, 974 meters from the center of the reactor units for undepleted, depleted, and gamma X/Q calculations, and the northwest section, 914 meters for ca.culations with D/Q the dispersion parameter. The site boundary in the NNE through SE sectors is located over tidal marsh (e.g., over water), and consequently are not used as locations for determining maximum off-sita receptors (Reference NUREG 0133). Two other locations (on-site) were analyzed for direr,t s.sund' plane exposure and inhalation only. They are the~" Rocks" (recreational site) and the Education Center shown on Figure 5.1-1 of the Technical Specifications. I l l l B.7-28 8688R OOCH Rev.
\
7.3.2 Seabrook Station Atmospheric Dispersion Model I The time average atmospheric dispersion factors for use in both Method I and Method II are computed for routine releases using the AEOLUS-2 i Computer Code (Reference B). l AE0LUS-2 produces the following average atmospheric dispersion factors for each location:
- 1. Undepleted X/Q dispersion factors for evaluating ground level concentrations of noble gases; -
i
- 2. Depleted X/Q dispersion factors for evaluating ground level concentrations of iodines and particulates; t
( 3. Gamma X/Q dispersion factors for evaluating gamma' dose rates from a sector averaged finite noble gas cloud (multiple energy undepleted source); and l
- 4. D/Q deposition factors for evaluating dry deposition of elemental radiolodines and other particulates.
Gamma dose rate is calculated throughout this 00CM using the finite
' cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5. That model is implemented through the definition of an effective gamma atmospheric dispersion. factor, [X/QY ) (Reference B, Section '
6), and the replacement of X/Q in infinite cloud dose equations by the (X/QY ), 7.3.3 Average Atmospheric 01spersion Factors for Receptors The calculation of Method I and Method II atmospheric diffusion factors
- (undepleted CHI /Q, depleted CHI /Q, 0/Q, and gamma CHI /Q values) utilize a methodology generally consistent with US NRC Regulatory Guide 1.111 (Revision 1) criteria and the methodology for calculating routine release diffusion factors as represented by the X0QDOQ computer code (NUREG/CR-2919).
B.7-29 00CM Rev. 8688R i
The primary vent sted is treated as-a " mixed-mode" release, as defined in , Regulatory Guide 1.111. Effluents are considered to be part-time ground-level /part-time elevated releases depending on the ratio of-the primary vent stack effluent exist velocity relative to the speed of the prevailing wind. All other release points (e.g., lurbine Building and Chemistry lab hoods) are considered ground-level releases. . , In addition, Regulatory Guide 1.111 discusses the concept that constant mean wind direction models like AEOLUS-2 do not describe spatial and temporal variations in airflow such as the recirculation of airflow which can occur during arolonged periods of atmospheric stagnation. For sites near large bodies of water like Seabrook, the onset and decay of sea breezes can also ' results in airflow reversals and curved trajectories. Consequently, Regulatory Guide 1.111 states that adjustments to constant mean wind direction model outputs may be necessary to account for such spatial and temporal variations in air flow trajectories. Recirculation correction factors have been applied to the diffusion factors. The recirculation correction factors used are compatible to the " default open terrain" recirculation correction factors used by the XOQOOQ computer code. The relative deposition rates, D/Q values, were derived using the relative deposition rate curves presented in Regulatory Guide 1.111 (Revision 1). These curves provide estimates of deposition rates as a
' function of plume height, stability class, and plume travel distance.
l Receptor Locations l l For ground-level releases, the downwind location of "The Rocks" (244m NE/ENE) and the Ed Center (406m SW) were taken as the distance from-the nearest point on the Unit 1 Administrative Building / Turbine Building complex. For the site boundary, the minimum distances from the nearest point on the Administration Building / Turbine Building complex to the site boundary within a 45-degree sector centered on the-compass direction of interest as measured from FSAR Figure 2.1-4A were used (with the exception that the NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations). B.7-30 8688R ODCM Rev.
l l l l For primary vent stack releases, the distances from the Unit 1 primary vent stack to "The Rocks" (244m NE) and the Ed Center (488w SW) as measured from a recent site aerial photograph were used. For the site boundary, the minimum distances'frcm the Unit I primary vent stack to the site boundary within a 45-degree sector centered on the compass direction of interest as measured from FSAR Figure 2.1-4A were used (with the exception that ths > NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their > over-water locations). Meteorological Data Bases for "The Rocks" and Ed Center receptors, the diffusion factors represent six-year averages during the time period January 1980 through December 1983 and January 1987 through December 1988 (with the exception that, ; because of low data recovery, April 1979 and May 1979 were substituted for April 1980 and May 1980). For the site boundary receptors, both sim-year average growing season (April through September) and year-round (January through December) diffusion factors were generated, with the higher of.the two chosen to represent the site boundary. The meteorological diffusion factor used in the development of the 00CM Method I dose models are summarized on Tables B.7-4 through B.7-6. i i I B.7-31 8688R 00CM Rev.
^
r TABLE B.7-4 Seabrook Station Dilution Factors
- Primary Vent Stack Dose to j Critical Dose Rate to Individual Dose to Air Organ Total Body Skin Critical Organ Gamma Beta Tnyroid X/Q depleted (S'3) - -
7.5E-07 - - 7.SE-07 m X/Q undepleted (**3) - 8.2E-07 - - 8.2E-07 - m D/Q ( ) - - 1.SE-08** - - 1.5E-08 m 8.5E-07 8.SE-07 - 8.5E-07 - - X/QY m(503)
- Hest site boundary, 974 meters from Containment Building
** Northwest site boundary, 914 meters from Containment Building i
B.7-32 8688R 00CM Rev.
. ~ . . , , . - -
TABLE B.7-5 Seabrook Station Ollution Factors for Special (On-Site) Receptors Primary Vent Stack Dose to Critical Dose Rate to Individual Dose to Air Organ Total Body Skin Critical Organ Gamma Beta Thyroid Education Center: (SH - 488 meters) X/Q depleted (5'3) - -
.5E-06 - -
1.5E-06 t X/Qundepleted(y) - 1.6E-06 - - 1.6E-06 - i a 2.7E-08 D/0(h). X/QY (5 ) 1.1E-06 1.lE-06 - 1.1E-06 - - m. The " Rocks" (ENE - 244 .eters) X/Q depleted (5'C) - - 1.6E-05 - - 1.6E-05 m X/Q undepleted (S'C) - 1.7E-05 - - 1.7E-05 - D/Q ( ) - - 1.lE-07 ' X/QY (SOC)' 5.0E 5.0E-06 - 5.0E-06 - - m
~~
8688R OOCH Rev. __ . - = - , . . - .
! TABLE B.7-6 Seabrook Station
- l Atmospheric Olffusion and Deposition Factors Ground-Level Release Pathway RECEPT 0R (a) "
Diffusion Factor Tne Rocks Ed Center Site Boundary-Undepleted CHI /Q, sec/m3 1.6 x 10-4 2.3 x 10-5 1.ox 1o-5 (244m ENE) (406m SW) (823m W) Depleted CHI /Q, sec/m3 1.5 x 10-4 2.1 x 10-5 g.4 x lo-6 (244m ENE) (406m SW) (823m W) 0/Q, m-2 5.1 x 10-7 1.0 x 10-7 5.1 x 10-8 (244m ENE) (406m SW) (823m W) , Gamma CHI /Q, sec/m3 2.6 x 10-5 5.3 x 10-6 3.4 x.10 (244m ENE) (406m SW) (823m W)_ l l l i 1 1 (a) The highest site boundary diffusion and deposition factors occurred during the April through September growing' season. Note that for the primary vent stack release pathway, none of the off-site receptor diffusion and deposition factors (located at 0.25-mile increments beyond- the site boundary) exceeded the site boundary-diffusion and deposition factors. 8.7-34 8688R 00CM Rev.-
4 8.0 BASES FOR LIQU!O AND GASEOUS MONITOR SETPOINTS 8.1 Basis for the liquid Waste Test Tank Monitor Setpoint TheliquidwastetesttankmonitorsetpointmustensurethatTechnical Specification 3.3.3.9 1s not exceeded for the appropriate-in-plant pathways. The liquid waste test tank monitor is placed upstream of the major source of dilution flow. The derivation of Equation 5-1 begins with the general equation for the response of a radiation monitor:
- R =
C,g S ig (8-1) 1 (cps) = (h) (C {*) l I where: R = Response of the monitor (cps) 4 S yg = Detector counting efficiency for radionuclide "1" (eps/(pCl/ml)) C,j = Activity concentration of radionuclide "1" in mixture at the monitor (pCl/ml) The detector calibration procedure for the liquid waste test tank monitor at Seabrook Station establishes a counting efficiency by use of a known calibration source standard and a linearity response check; Therefore, in Equation 8-1 one may substitute 5 3 for S j[, where Sj is the detector counting efficiency determined from the calibration procedure. :Therefore, Equation 8-1 becomes: R = S j C,3 (8-2) , 1 (cos) = (C {*) (h) B.8-1 , 8689R _00CM Rev. 5-
The MPC for a given radionuclide must not be exceeded at the point of , discharge. When a mixture of radlonuclides is present.10CFR20 specifies that the concentration at the point of discharge shall be limited'as follows: i {CMPC I I 1 d1 1 (8~3} i (uC1-ml) mi-pC1 ! i whefe: { C dl
- Activity concentration of radionuclide "1" in the mixture at (
i the point of discharge (pCl/ml) MPCg MPC for radionuclide "1" from 10CFR20, Appendix 8. Table II, Column 2 (pCl/mi) f 3 The activity concentration of radionuclide "1" at the point of discharge is ; related to the activity concentration of radionuclide "i" at the monitor as ' follows: l j C dl
=
C,g [F (8 4) ' d 1 (b)=($)(E) mi mi gpm where:
~
Cdl = Activity concentration of radionuclide ".1" in the mixture at the , point of discharge (pC1/ml) I F, = Flow rate past monitor (gpm) F d
= Flow rate out of discharge tunnel (gpm) ;
B.8-2 l l 8689R OOCH Rev. 4 l
l Substituting the right half of Equation 8-4 for C dt in Equation 8-3 and solving for F d F, yields the minimum dilution factor needed to comply with Equation 8-3: DFmin I 1 M (8-5) m (gpm) uCl-ml (mi-pCl) where: > F d Flow rate out of discharge tunnel (gpm) F, = Flow rate past monitor (gpm) C,j = Activity concentration of radionuclide "1" in mixture at the monitor (pCl/mi) 1 MPC g - MPC for radionuclide "1" from 10CFR20, Appendix B. Table II, Column 2 (pCl/ml) If F d/F, is less than OFn.in, then the tank may not be discharged until either Fd or F,or both are adjusted such that: l ' [Fm 1 0F min (E) gpm Usually Fd /F,is greater than DFmin (i.e., there is more dilution than necessary to comply with Equation 8-3). The response of the 11guld waste test tank monitor at the setpoint is therefore: l l Rsetpoint " Il 3 C ,g (8-6) 0 1 ) min 1 , i HC.!, ,( ) ( ) uC1 mi (cos-ml) pC1 (ml ) B.8-3 8689R OOCH Rev. 4
where f) is equal to the fraction of the total contribution of MPC at the discharge potr,t to the environment to be associated with the test tank effluent pathway, such that the total sum of the fractions for the three 11guld discharge pathways is equal to or less than one (f) + f2+I3 I I The monitoring system is designed to incorporate the detector efficiency. 5 , into its software. 3 This results in an automatic readout in pC1/cc or pC1/ml for the monitor response. Since this procedure for converting cps to pCl/ml is inherently done by .the system sof tware, the monitor response setpoint can be calculated in terms of the total waste test tank activity concentration in pC1/ml determined by the laboratory analysis. Therefore, the setpoint calculation for'the liquid waste test tank is: R setpoint "I IO C,g (5-1) I min 1 (",) ( )( ) (h) 8.2 Basis for the Plant Vent Wide Range Gas Monitor Setpoints The setpoints of the plant vent wide range gas monitors must ensure that Technical Specification 3.11.2.1.a is not exceeded. Sections 3.4 and 3.5 show that Equations 3-3 and.3-4 are acceptable methcds for determining compliance with that Technical Specification. Which equation (i.e., dose to l total body or skin) is more limiting depends on the noble gas mixture. l Therefore, each equation must be considered separately. The derivations of l Equations 5-5 and 5-6 begin with the general equation for the response R of a radiation monitor: R - S C ,j (8-D gg 3 (cpm) . (cp m) (uC ) em B.8-4 8689R '00CM Rev. 4
l where: l R Response of the instrument (cpm) l 3 Sgj = Detector counting efficiency for noble gas "1" (cpm /(pC1/cm )) I Cgj - Activity concentration of noble gas "1" in the mixture at the noble gas activity monitor (pC1/cm3) l C,j, the activity concentration of noble gas "1" at'the noble gas activity monitor, may be expressed in terms of Qj by dividing by F, the appropriate flow rate. In the case of the plant vent noble gas activity monitors the l l appropriate flow rate is the plant vent flow rate. Cg = hg h I
.(8-8) i
( ) (b) I' (sec) '
;m Cm 4 where: ,
h5= the release rate of noble gas "1" in the mixture, for each noble
- gas list.ed iti Table B.1-10.
' F = Appropriate flow rate (cm3/sec)
Substituting the right half of Equation 8-8_into Equation 8-7 for C,3 yields: (8-9) R = S gj hg h l (cpm) (C *) ( )(8'j) Cm As in the case before, for the liauld waste test tank monitor, the-plant vent wide range gas monitor' establishes.he detector counting efficiency by use of a calibration source. Therefore, Sg can be substituted for S gj B.8 8689R 00CM Rev. 4-
in Equation 8-9, where S is the detector counting efficiency determined g from the calibration procedure. Therefore, Equation 8-9 becomes: R - S g h Qg , (3 10) (cpm)-(CD*]*) (S'C) ( ). Cm The total body dose rate due to noble gases is determined with Equation 3-3: i
)
b
- tb
- 0.85
- EL(R) Qg DFBg- (3-3).
I J 3 Imrem' " (DCl-sec uCl - yr 3 sec mrom-m pCl-yr ) Cl-m I l where: . l 1 O - total body dose rate (mrem /yr) I tb [ i- 3 l 0.85 - (1.0E+06) x (8.5E-07) (pCl-sec/pCl-m3 ) f IE+06 number of pCl per pCl (pC1/pC1) ! 8.5E-07 - CX/Q)Y, maximum off-site average gamma atmospheric ! 3 dispersion factor (sec/m ) for primary vent stack releases EL(R) - Release point correction factor 1= 1.0 for' primary vent i I
- l. stack {
i
)
l Qg As defined above. ! L i i I 0FB g - total body dose factor (see Table B.1-10) ! 3 (mrem-m /pCl-yr) j l i i B 8-6 8689R -00CM Rev. e l
r A ccmposite total body gari.ma dose factor, OFBc, may be defined such that: OFB e t h=g i hg DFB g (8-11) l J 3 3 mrem-m (uCl) , (g) (mrem-m ) pCl-yr sec sec PCI-yr Solving Equation 8-11 for DFB c yleids: hg0FB g
' (5-7) 0FB = i hg !
1 l l rechnical Spectftcation 3.'1.2.1.a limits the dose rate to the total .j body from noble gases at any location at or beyond the site boundary to 500 l mrem /yr. Bysettingh equal to 500 mrem /yr and substituting 0FBc for DFB 3 tb l In Equation 3-3 .one may solve for [ Qg at the limiting whole body / noble gas' l I dose rate:
\
t C. , l
/_ Qi-I 588 g c (8-12) ;
3 (gql,) , < mrem-uCl-m ) <pci-yr ) see yr-pCl-sec mrem-m 3 i f Substituting this result for [ hg in Equation 8-10 yields Rtb, the response s I of the monitor at the limiting noble gas. total body dose rate: 4 1 1 R - 588 S p 18-W tb g 3 c ,c,3 (cpm') = (mrem-uCl-m yr-pCl-sec I ,,C1 p
' <see'3 (DC1-vr3 ' 0 a
cm mrem-m The skin dose rate due to noble gases is determined'with Equation 3-4: b - EL(R)
- Qg 0Fj (3-4) skin 1 (mrem)yr
,( ) (g) sec (mrem-sec) pCl-yr B.8-7 8689R 00CM Rev.
t where: EL(R) 1.0 for primary vent stack release (dimensionless) bskin Skin dose rate (mrem /yr) hg As defined above. OFj = Combined skin dose factor (see Table B.1-10) (mrem-sec/pCl-yr) A composite combined skin dose factor, DFj, may be defined such that:' DFj hg - h; 0Fj (8-14)- , t i gmrem-sec) pC1-yr (g) sec
, gg) (mrem-sec) sec pC1-yr-SolvingEquation8-14forOFjyields: i L
bg DFj OF' = (5-8) hg 1 Technical Specification 3.11.2.1.a limits the dose . rate to the skin-l from noble gases at any location at or beyond the site boundary to 3,000 mrem /yr. Bysettingb skin equal to 3,000 mrem /yr and substituting 0Fj for OFj in Equation 3-4 one may solve for [ Qg at the limiting skin noble gas dose rate: ) 1 l I hg 3,000 h c (8-15) ! (pCJ.) uCl sec (mrem) yr < mrem sec yr ) l l Substituting this result for [ hg in Equation 8-10 yields Rskin, the response I of the monitor at the limiting noble gas skin dose rate: i l B.8-8 8689R 00CM Rev. l
J 3,000 S h (8-16) Rskin g 0 l (cpm) ( *y'r ' * ) (CD*~#* ) (3 E ) (m" sec rem# ) l pCl cm 4 As with the liquid monitoring s'ystem, the gaseous monitoring system-is also designed to incorporate the detector efficiency S g
. Into its software. The monitor also converts the response output to a release rate (pCl/sec) by using a real time stack flow rate measurement input. Therefore,.
multiplying by the stack flow rate measurement-(F), the Equations 8-15 and 8-16 become, t i R tb
- 588 h C (5-5) !
3 (uCl) , (mrem-uC1-m ) (oCl-yr ) sec yr-pCl-sec mrem-m 3 i
- 3000 (5-6)
R skin h.C (uCl) , (mrem) uCl sec yr (mrem yr ) sec 8.3 Basis for PCCW Head Tank Rate-of-Change Alarm Setootnt. ( l The PCCW head tank rate-of-change alarm will work in conjunction with-l the PCCW radiation monitor to alert the operator in the Main Control Room of a leak to the Service Water System from.the PCCW System. For the rate-of-change alarm, a setpoint based on detection of an activity level of.10-8pC1/cc in i the discharge of the Service Water System has been selected. This activity-level was chosen because it is the minimum detectable level of a service water monttor if such a montter were installed. The use of rate-of-change alarm with information obtained from the 11guld sampling and analysis commitments described in Table A.3-1 of Part A ensure that potential releases- from the B.8-9 8689R 00CM Rev.
?
, .,,--e -
/
Cervice Water System are known. Sampling and analysis requirements for the Service Water System extend over various operating ranges with increased sampling and analysis at times when leakage from the PCCW to the service water-is occurring and/or the activity level in the PCCW is high. , e f l l 1 l l t i i B.8-10 8689R 00CM Rev.
REFERENCES A. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compilance with 10CFR50, Appendix !", U.S. Nuclear Regulatory Commission, Revision 1, October 1977. - B. Hamawl, J. N., "AEOLUS A Computer Code for the Determination of Continuous and Intermittent-Release Atmospheric Olspersion and Deposition of Nuclear Power Plant Effluents in Open-Terrain Sites, Coastal Sites, and Deep-River Valleys for Assessment of Ensuing Doses and Finite-Cloud Gamma Radiation Exposures," Entech Engineering, Inc., March 1988. C. Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Olspersion of Gaseous Effluents in Routine Releases From Light-Water Cooled Reactors", U.S. Nuclear Regulatory Commission, March 1976. D. National Bureau of Standards, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure", Handbook 69 June S, 1959. E. Slade. D. H., " Meteorology and Atomic Energy - 1968", USAEC, July 1968. F. Seabrook Station Technical Specifications. ' 1 i
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