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1.1 u 3/4.11.e+( Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below it's flammability limit provides assurance that the releases of radioactive materials will be controlled in confomance with the requirements of 10 CFR Part 50, Appendix A, General R Design Criterion 60. | 1.1 u 3/4.11.e+( Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below it's flammability limit provides assurance that the releases of radioactive materials will be controlled in confomance with the requirements of 10 CFR Part 50, Appendix A, General R Design Criterion 60. | ||
3 Changed by NRC letter dated April 26 1903 . | 3 Changed by NRC {{letter dated|date=April 26, 1903|text=letter dated April 26 1903}} . | ||
l CALVERT CLIFFS - UNIT 1 B 3/4 11-4 | l CALVERT CLIFFS - UNIT 1 B 3/4 11-4 | ||
| Line 2,154: | Line 2,154: | ||
" Detection Li ts for Radioanalytical Counting Techniqu s," Atlantic Richfield Ha ord Company Report ARH-SA-215 (June 1975). | " Detection Li ts for Radioanalytical Counting Techniqu s," Atlantic Richfield Ha ord Company Report ARH-SA-215 (June 1975). | ||
3/4.11.2. Dose - Noble Gases This s cification is provided to implement the requirements o 10 CFR , | 3/4.11.2. Dose - Noble Gases This s cification is provided to implement the requirements o 10 CFR , | ||
Part , Appendix I, Sections II.B. III.A and IV.A. The Limiti Condition for peration implements the guides set forth in Appendix I, Changed by NRC letter dated April 26, 1993 , | Part , Appendix I, Sections II.B. III.A and IV.A. The Limiti Condition for peration implements the guides set forth in Appendix I, Changed by NRC {{letter dated|date=April 26, 1993|text=letter dated April 26, 1993}} , | ||
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Latest revision as of 21:36, 25 September 2022
| ML20085D509 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/09/1995 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20085D493 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9506160255 | |
| Download: ML20085D509 (443) | |
Text
{{#Wiki_filter:1 i .. ATTACHMENT (1) i i l l UNIT 1 , TECIINICAL SPECIFICATIONS REVISED PAGES 1 1-6 1 3/43 3/43-51 3/4 11 3/4 11-19 j i 3/4 12 3/4 12-15 , 6 6-22 6-31 i B3/4 3-3 f B3/411 3/411-6 l B3/412-1 f B3/412-2 I i 9506160255 950609 PDR ADDCK 05000317 P PDR i l
l 1.0 DEFINITIONS ) I FREQUENCY NOTATION j 1.15 The FREQUENCY NOTATION specified for the perfomance of Surveillance l , Requirements shall correspond to the intervals defined in Table 1.2. ! GASE0US RADWASTE TREATMENT SYSTEM j 1 1.16 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and l installed to reduce radioactive gaseous effluent by collecting Primary. 1 Coolant System offgases from the Primary System and providing for delay or ! holdup for the purpose of reducing the total radioactivity prior to reieue I to the environment. ) IDENTIFIED LEAKAGE 1.17 IDENTIFIED LEAKAGE shall be: l
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted ,
to a sump or collecting tank, or l l
- b. Leakage into the containment atmosphere frca sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c. Reactor Coolant System leakage through a steam generator to the Secondary System.
MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not j occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. 0FFSITE DOSE CALCULATION MANUAL (0DCM) fl.1 Th 0FF TE SE ALC TI P UAL hal co ain(ha[urrdt l met odol gy dp ame ers sed n ec cul tio of fsiedc4es ue o ra ioac ive ase s a d li uid ffl ent in e 1cul tio of ase s id 1 uid eff1 ent oni rin a1 /t ip s tpo ts, and nt co due of he vir men 1 r diol gic me ito ing rog m.
$EPLACE M71 bSW Y CALVERT CLIFFS - UNIT . 1-4 Amendment No. 186
l INSERT "1.19" OFFSITE DOSE CALCULATION MANUAL (ODCM) i 1.19 'Ihe OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid emuents, in the calculation of gaseous and liquid emuent monitoring alarm and trip setpoints, and in the conduct of the radiological emironmentr.1 monitoring program. The ODCM shall also contain the radioactive emuent controls and radiological environmental monitoring activities and descriptions of the information that should be included 5 the Annual Radiological Environmental Operating, and Radioactive Emuent Release Reports requirco by Specifications 6.9.1.7 [6.6.2] and 6.9.1.8 [6.6.3]. i I
1.0 DEFINITIONS OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or I have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, nomal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that sre required for the system, subsystem, train, component or device to perfcnn its function (s) are also capable of ' perfoming their related support fonction(s). OPERATIONAL MODE 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combination l of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1. PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests perfomed to measure the l fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Comi ssion.
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PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator l tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall. NCE C0 R0 R0G4 LM CP
.2 Th PR ESS ONT OL P OG sh 1c tain the urr nt m a, l sa pli ,a lys , t.sts, and ete ,ina ons ob ma to ns e at he p oce ing nd cka ing fs id r dio tiv was s sed on emo tr ed '
roc sin of ctu or imu' ted 'et lid ast w 1b ac omp sh d i suc aw as to sur com ian wi 10 FR art 0, OC P t d Fe ral and tat and oca reg ati s 9 'ern ng e spo al te I r ioa tive was . DELETE l CALVERT CLIFFS - UNIT 1 1-5 Amendment No. 186 l l l l
1.0 DEFINITIONS PURGE - PURGING 1.25 PURGE or PURGING is the controlled process of discharging air or gas l j from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. i RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate l to the reactor coolant of 2700 MWt. REACTOR TRIP SYSTEM RESPONSE TIME 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism. l I REPORTABLE EVENT 1.28 A REPORTABLE EVENT shall be any of those conditions specified in l Section 50.73 to 10 CFR Part 50. I SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by l which the reactor is subcritical or would be subcritical from its present condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE B0UNDARY 1.30 The SITE B0UNDARY shall be that line beyond which the land is neither l owned, nor leased, nor otherwise controlled by the licensee. DIF AT N 31 $0 IF ATI s 1 th co ers on w w e n a t l mee s ppi an bur al ou re ir ient . DEL E TE Y CALVERT CLIFFS - UNIT 1 1-6 Amendment No. 186 l
-- _ _ _-___ _ ___ _ -_-___ _ __ ____ _ n
1 h 3/4.3 INSTRUMENTATION
/4.3.3 MONITORING INSTRUMENTATION
_ Radioactive Gaseous Effluent Monitorino Instrumenta on . LIMITI CONDITION FOR OPERATION 3.3.3.9 radioactive gaseous effluent monitoring inst mentation channels sh n in Table 3.3-12 shall be OPERABLE with t r alam/ trip setpoints set o ensure that the limits of Specificati 3.11.2.1 are not exceeded. and adjusted Thein lam / trip setpoints of these channels hall be detemined cordance with the methodology and arameters in the ODCM. g APPLICABILITY: As own in Table 3.3-12. ACTION: < a. With a radioac 've gaseous efflue monitoring instrumentation channel alam/tr setpoint less onservative than required by the above Specift tion, withou delay suspend the release of radioactive gaseous ffluents onitored by the affected channel, or declare the chann inope ble, or change the setpoint so it Z is acceptably conserva ve. == b. With less than the minim number of radioactive gaseous effluent g - monitoring instrumentat n hannels OPERABLE, take the ACTION H shown in Table 3.3-12. Exer best efforts to return the instruments to OPERA E statu within 30 days and, if unsuccessful, exala in the ne Semiannual Radioactive Effluent g Release Report w1y the inoperabi' 'ty timely manner. was not corrected in a H
- c. The provision of Specifications 3.0. and 3.0.4 are not 1, applicable, s
1 SURVEILLANCE RE REMENTS 4.3.3.9 Eac radioactive gaseous effluent monitoring instr entation channel sha be demonstrated OPERABLE by perfomance of the NEL CHECK, SOURCE CHE , CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST the freq ncies shown in Table 4.3-11. erations at CALVERT CLIFFS - UNIT 1 3/4 3-42 Amendment No. 199 l
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DELETE THIS PAGE . Q* G TABLE 3.3-12
'k*
g RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION w n C E MINIMUM CHANNELS Q INSTRUMENT !Q to OPERABLE APPLICA8ILITY ACTION " i . 1. WASTE GAS HOLDUP STEM E e 5
- a. Noble Gas Activity nitor - Providing Alam and Automatic T ination of 1 35 d Release E
- b. Effluent System Flow Rate Meas ng 1 36 Device
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor 1 37 Y
0 b. Iodine Sampler 1 38
- c. Particulate Sampler 1 38 i .
N I I a
.E i
3/4.3 INSTRUMENTATION TABLE 3.3-12 (Continued) , TABLE NOTATION At 1 times. ACTION STATENENTS ACTION 35 - With the number of channels OPERABLE ss than required by [ the M Ifmum Channels 0PERABLE requir nt, the contents of the tar (s) may be released to the nvironment:
- a. Using he main vent monitor a backup and recording RMS reading every 15 minutes ring the release, or
- b. Provided t t prior to i tiating the release, at least two indepen nt sample of the tank's contents are analyzed, an t leas two technically qualified members
@ of the Facilit Staf independently verify the release - rate calculation d two qualified operators verify the == discharge valve 1 eup.
Otherwise, suspend elea of radioactive effluents via this
% pathway.
ACTION 36 - With the numbe of channels
,"g the Minimum C annels 0PERABLE ERABLE less than required by quirement, effluent releases H via this pa way may continue p vided the flow rate is ; s estimated least once per 4 hou .
1 ACTION 37 - s With th number of channels 0PERABL less than required by 4 the Mi mum Channels OPERABLE require nt, effluent releases via is pathway may continue provided ither (1) grab Is . sam es are taken and anal ctivity at least A o per 24 hours, or (2) an yzed for grossmo itor is provided. equivalent ACTION 38 - ith the number of channels OPERABLE less tha required by the Minimum Channels OPERAELE requirement, ef ent releases via the affected pathway may continue provided ples are continuously collected as required in Table 4.11- with auxiliary sampling equipment. CALVERT CLIFFS - UNIT 1 3/4 3-44 Amendment No. 199 l l l
DELETE THIS PAGE J g TABLE 4.3-11 R.
.n n DI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANC C
q ES IN ze
.: CNANNEL Q
INSTRUMENT CHANNEL SOURCE CHANNEL FUNCTI SURVEILLANCE WHICH g e CHECK CHECK CALIBRATION m TE 5 _ REQUIRED 5 [ 1. WASTE GAS HOLDUP SYSTEM d E
- a. Noble Gas Activity Monitor -
Providing Alam and Automatic P P R)I3 SAU) Temination of Release w b. Effluent System Flow Rate D)U . 2, NA R Measuring Device NA
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor
- D M I3)
SAI2)
- b. Iodine Sampler W NA NA NA
- c. Particulate Sampler W NA NA NA N
E
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m _______.- _ _ ~ , - - -- - -w- - _ r -_ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ __
3/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued) , TABLE NOTATION At 1 times other than when the line is valved out a locked. III The C NEL FUNCTIONAL TEST shall also demonstrate he automatic isolatio of this pathway and/or Control Room ala annunciation occurs i he appropriate following condition (s) exists:
,s 1. Instrume indicates measure levels above he alarm / trip 1 setpoint.
- 2. Circuit fail e.
I
- 3. Instrument indi tes a downscale f lure.
% (2)
The CHANNEL FUNCTIONAL EST shall a o demonstrate that Control Room alann annunciation occu if any o the following conditions exists:
- 1. Instrument indicates m sur levels above the alarm setpoint.
- 2. Circuit failure.
H q 3. Instrument indicates downs le failure.
,' , I3)
The initial CNANNEL CAL RATION sha be perfonned using one or more 1 of the reference stan rds traceable o the National Bureau of Standards or using s ndards that have een obtained from suppliers H that participate in asurement assuran activities with NBS. These
;s standards shall p it calibrating the sy em within its intended 1 range of energy d measurement range. Fo subsequent CHANNEL w CALIBRATION, so rces that have been related the initial )-.
calibration c be used. 1 (4) The CHANNE HECK shall consist of verifying ind ation of flow during pe ods of release and shall be made at lea once per 24 hours on ays on which effluent relcases are made. l i I i CALVERT CLIFFS - UNIT 1 3/4 3-46 Amendment No. 199 l l
3 .3 INSTRUMENTATION - 3/4. 3 MONITORING INSTRUMENTATION kadioactive Liouid Effluent Monitorina Instrumentation - LINITING C ITION FOR OPERATION 3.3.3.10 The dioactive liquid effluent monitoring instrumen ion channels shown Table 3.3-13 shall be OPERABLE with their a rm/ trip setpoints set to sure that the limits of Specification 3.1.1.1 are not exceeded. The ala / trip setpoints of these channels shall e detennined i j and adjusted in acco ance with the methodology and param ers in the i 0FFSITE DOSE CALCULAT N MANUAL (0DCN). i APPLICABILITY: At all t es. ACTION:
- a. With a radioactive 1 uid effluent mo toring instrumentation channel alarm / trip se oint less con rvative than required by the above Specification without de y suspend the release of radioactive liquid efflu ts moni red by the affected channel, Z
or declare the channel in erabl , or change the setpoint so it is acceptably conservative.
- b. With less than the minimum n r of radioactive liquid effluent M monitoringinstrumentation/1an is OPERABLE, take the ACTION H
shown in Table 3.3-13. E# rt bes efforts to return the instruments to OPERABLE ;atus wit n 30 days and, if r' unsuccessful, explain the next Se f annual Radioactive Effluent A Release Report why th inoperability s not corrected in a "q timely manner. [ ,
- c. The provisions of pecifications 3.0.3 an 3.0.4 are not applicable.
1 SURVEILLANCE REQUI ENTS 4.3.3.10 Each r dioactive liquid effluent monitoring instrumen\ tion channel shall 4 demonstrated OPERABLE by performance of the CHAL L CHECK, SOURCE CHECK, :HANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST oper ions at the frequen es shown in Table 4.3-12. CALYERT CLIFFS - UNIT 1 3/4 3-47 Amendment No. 199 l
l l N/4.3 INSTRUMENTATION [ TABLE 3.3-13 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CNANNELS INSTRUMENT OPERABLE ACTION
- 1. GROSS RADI CTIVITY MONITORS PROVIDING ALARM AND At TIC TERMINATION OF RELEASE g" a. Liquid Radwa 'e Effluent Line 1 28
- b. Steam Generator lowdown Effluent 29 Line 1 I
- 2. FLOW RATE MEASUREMENT DE CES 4 a. Liquid Radwaste Effluen Line 1 30
- b. Steam Generator Blowdown E lu t 1 30
==
Line l M M 1 1 m 4 I CALVERT CLIFFS - UNIT 1 3/4 3-48 Amendment No. 199 l
1 N/4.3 INSTRUMENTATION
/
TABLE 3.3-13 (Continued) , ACTION STATEMENTS ACTION 28 - With the number of channels SPERABLE less than r quired by the Minimum Channels OPERABLE requirement, eff ent releases y continue provided that prior to inittatin a release:
- a. t least two independent samples are a lyzed in cordance with Specification 4.11.1. 1, and -
- b. At ast two technically qualified 1 Fact ty Staff independently vert bers of the the release rate calcu tions and two qualified erators verify the dischar valve line up. ,
ACTION 29 - With the numbe of channels OPE LE less than required by quirement, effluent releases h the Minimum Cha els OPERABLE via this pathway y continue rovided grab samples are analyzed for gross adioact' ity (beta or gama) at the 1 lower limit of detec ion d 'ined in Table 4.11-1: [ a. At least once per I hours when the specific activity of the secondary cool is greater than 0.01 M microcurie / gram E IVALENT I-131.
- b. At least once r 48 hou when the specific activity of
-s 1 the secondar coolant is 1 s than or equal to 0.01 - microcurie / am D0SE EQUIVA NT I-131.
N ACTION 30 - With the num r of channels 0PERAB less than required by g the Minimum hannels OPERABLE requir ent, effluent releases *
, via this p hway may continue provide the flow rate is estimate at least once per 4 hours du g actual releases.
N Pump pe ormance curves may be used to e imate flow. 1 m l l t 1 l 1 CALVERT CLIFFS - UNIT 1 3/4 3-49 Amendment No. 199 l l _ __. I
DELETE THIS PAGE ~ g _ TABLE 4.3-12 r-R a RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE RE b 7 CHANNEL AMEL h INSTRUMENT SOURCE CHANNEL FUNCTIONAL " CHECK CNECK CALIBRA TEST b 1. GROSS RADI0 ACTIVITY ITORS PROVIDING ALARM
} AND AUTOMATIC TERMINAT OF RELEASE h
- a. Liquid Radwaste Effluent g
e D P R(2) SAII)
- b. Steam Generator Blowdown Efflue Line D P R)
IZ SA(1)
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line D)I3 NA R NA h b. Steam Generator Blowdown Effluent Line D NA R NA i
a n M
, \
4/4.3 INSTRUNENTATION
,/
TABLE 4.3-12 (Continued) , TABLE NOTATION (1) The C NEL FUNCTIONAL TEST shall also demonstrate that'a omatic isolat of this pathway and/or Control Room alam ann ciation occur if he appropriate following condition (s) exists-
- 1. Inst t indicates measured levels above the am/ trip setpoint.
Circuit fai re. 2. L3
- 3. Instrument ind ates a downscale failure.
(2) h The initial CHANNEL of the reference standa ds traceable to t National Bureau of Standards or using stand ds that have en obtained from suppliers that participate in measu ent assura e activities with NBS. These IBRATION shall be p formed using one or more standards shall pemit cali ating t system within its intended range of energy and measure t ran . For subsequent CHANNEL CALIBRATION, sources that have ee related to the initial [ calibration can be used. H (3) CHANNEL CHECK shall consist of er ying indication of flow during 4 periods of release. CHANNEL ECK s all be made at least once per 24 hours on days on which e luent re ases are made. H 1 ' l
& i 1
m l l CALVERT CLIFFS - UNIT 1 3/4 3-51 Amendment No. 199 l
3/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.1 LIOUID EFFLUENTS Concentration I LIMITING ONDITION FOR OPERATION 3.11.1.1 T concentration of radioactive material releas in liquid effluents to hiRESTRICTED AREAS shall be limited to the c centrations specified in l' CFR Part 20, Appendix B. Table II, Colu 2 for radionuclides ot er than dissolved or entrained noble ses. APPLICABILITY: At 11 times. 1, ACTION: a. 4 With the conce ration of radioactiv material released in liquid effluents to UN TRICTED AREAS exc di'g limits. n the above limits, without delay res re the concentr tion to within the above
- b. The provisions of Spe ficati
=
applicable. s 3.0.3 and 3.0.4 are not buu m M
% SURVEILLANCE REQUIREMENTS ~
[ 4.11.1.1.1 Radioactive liqu according to the sampling wastes shall e samp?cd and analyzed d analysis progra of Table 4.11-1. H w 4.11.1.1.2 The results 1: ' the radioactivity ana ses shall be used in accordance with the me odology and parameters in he ODCM to assure that the concentrations at he point of release are main ined within the limits H of Specification 3.1.1.1. m r CALVERT CLIFFS - UNIT 1 3/4 11-1 Amendment No. IM
k3/4.11 RADI0 ACTIVE EFFLUENTS l TABLE 4.11-1 I RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i LOWER LIMIT 0F ! MINIMUM DETECTION LIQUID RELEAS SAMPLING ANALYSIS TYPE OF ACTI TY (LLD)* TYPE REQUENCY FREQUENCY ANALYS (pC1/ml) A. BatchWagte P P Principa[ Gamma 5x10-' Releases Eac Batch Each Batch Emitterf ' I-13][ 1x10-' Mo[9,Ce-144 2x10-' P M [3 1x10-5 % Each Batch Composite d [GrossAlpha 1x10-' Each Batch C sit Sr-89,Sr-90 5x10 4 , "" B. Turbine M Principal Gama 5x10-' Building Emitters
- DH Sump I-131 1x10-'
g Mo-99, Ce-144 2x10-8 H C. . l i 1 l 1 CALVERT CLIFFS - UNIT 1 3/4 11-2 Amendment No. 169 j
\
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION a The LD is defined, for purposes of these specification , as the smal' st concentration of radioactive material in a sa: le that will yield net count, above system background, that will se detected with 95 probability with only 5% probability of fa ely concluding that a bl k observation represents a "real" signa . For a parti lar measurement system, which may clude radiochemical
,, separation:
1 g too . EV-4 665 2 x 10' Y exp (-AA n LLD is the "a priori lower lim of detection as defined above, as microcuries per uni mass o volume, e s, is the standard deviat
- of the background counting rate or of the counting rate of a ank sample as appropriate, as counts
)H per minute, % E is the counting effi tency, a counts per disintegration, [" V is the sample siz in units of ss or volume,
-H 2.22 x 10' is th number of disintegr tions per minute per
- l s microcurie, Y is the fra ional radiochemical yield, ien applicable, I *.
A,is the 1 dioactive decay constant for the articular radionuc .de, and at is he clapsed time between sample collection or end of the samp collectica period, and time of counting. T ical values of E. V, Y, and At should be used in e 1culation. I should be recognized that the LLD is defined as an a prio efore the fact) limit representing the capabilit ment ystem and not as an a posteriori (after the fact)y of a measu limit for a particular measurement. I CALVERT CLIFFS - UNIT 1 3/4 11-3 Amendment No. 169 I
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION b Pri to sampling Reactor Coolant Waste and Miscellaneou Waste for anal es, each batch shall be isolated, and then thoro ly mixed to assure representative sampling. C The prin al gamma emitters for which the LLD spe fication applies exclusivel are the following radionuclides: Mn- , Fe-59. Co-58, Co-60, Zn-6 Cs-134 Cs-137 and Ce-141. This st does not mean
,, that only th e nuclides are to be considered. Other ganna peaks 1 that are ident table, together with those of he above nuclides, shall also be a lyzed and reported in the e f annual Radioactive Effluent Release port pursuant to Specif ation 6.9.1.8.
4 d A composite sample one in which the antity of liquid sampled is proportional to the q ntity of liquid aste discharged in which the method of sampling emp ed results a specimen that is representative of the li ids relea d. H H H M 1 1 ,
& l C -
l CALVERT CLIFFS - UNIT 1 3/4 11-4 Amendment No. 169
I l 5 3/4.11 _RADI0 ACTIVE EFFLUENTS
.11.1 LIOUID EFFLUENTS Dose !
LIMITIN ONDITION FOR OPERATION 3.11.1.2 T dose or dose commitment to a MEMBER 0F THE P LIC from ! radioactive terials in liquid effluents released to UN TRICTED AREAS shall be limit : I f'
- a. During y calendar quarter to less than o equal to 3.0 mrems to
-s the tota body and to less than or equal 10 mrems to any 1 organ, an
- b. During any ca endar year to less than r equal to 6 mrems to the total body and o less than or equal to 20 mrems to any organ.
APPLICABILITY: At all time w ACTION:
- a. With the calculated dos fr the release of radioactive
= materials in liquid effl s exceeding any of the above limits, prepare and submit to th 'ommission within 30 days, pursuant to H Specification 6.9.2, a ec q cause(s) for exceeding he 1 1it(s Rep) andortdefines that identifies the the corrective actions that have be taken t reduce the releases and the proposed corrective ctions to taken to assure that subsequent 1,s releases will be i compliance wi the above limits. M b. The provisions applicable. Specifications 3. 3 and 3.0.4 are nct
- 3 SURVEILLANCE REQU EMENTS 4~.11.1.2 Mont y cumulative dose contributions from liqui effluents for'
~
the current endar quarter and the current calendar year all be detemined accordance with the methodology and parameters the ODCM at least once er 60 days. CALVERT CLIFFS - UNIT 1 3/4 11-5 Amendment No. 169
4
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.1 LIOUID EFFLUENTS Licuid Radwaste Treatment System LIMITING ONDITION FOR OPERATION 3.11.1.3 Th Liquid Radwaste Treatment System shall be us to reduce the radioactive m erials in liquid wastes prior to their dis Marge when the calculated dose due to the liquid effluent to UNRESTRI ED AREAS exceeds 0.36 mrem to the otal body or 1.20 mrem to any organ a 92 day period.
3 APPLICABILITY: At 1 times. 1 ACTION: l l h
< a. With radioactiv liquid waste being scharged without treatment and in excess of he above limits, epare and submit to the Comission within 0 days pursuan to Specification 6.9.2 a Special Report that neludes the ollowing infonnation:
l l
- 1. Explanation of why liquid adwaste was being discharged without treatment, ent' ication of any inoperable l H equipment or subsyste and the reason for the H "" inoperability, HH "
g 2. Action (s) taken to estor the inoperable equipment to OPERABLE status, id 1 3. Sumary descri recurrence. ion of action taken to prevent a
==H
- s b. The provisions f Specifications 3.0.3 nd 3.0.4 are not 1 ,
applicable. SURVEILLANCE RE REMENTS 4.11.1.3 Mor ly doses due to liquid releases to UNRESTRIC AREAS shall be calculat at least once per 60 days in accordance with th methodology and parame rs in the ODCM. l CALVERT CLIFFS - UNIT 1 3/4 11-6 Amendment No. 169
INSERT "6.18" (continued)
- c. Determmation of cumulative and projected dose contributions from radioactive effluents 1 1
for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. f
- f. Limitations on the functional :apability and use of the Liquid Radw3ste Treatment System !
to ensure that appropriate portions of this system are used to reduce releases of 1 radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem j to the total body or 1.20 mrem to any organ in a 92 day period.
- g. Limitations on the functional capability and use of the Gaseous Radw3ste Treatment [
System and the Ventilation Exhaust Treatment System to ensure that appropriate portions of these systems am used to reduce releases of radioactivity when the calculated doses to : UNRESTRICTED AREAS exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period. I
- h. Limitations on the functional capability and use of the Ventilation Exhaust Treatment !
System to ensure that appropriate portions of this system are used to reduce releases of ; I radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED j i AREAS exceeds 1.8 mrem to any organ in a 92 day period. l I
- i. Limitations on the dose rate resulting from radioactive material released in gaseous i effluents to areas beyond the SITE BOUNDARY, to be limited: !
1
- 1. For noble gases: Less than or eqcal to 500 mrems/yr to the total body and less j than or equal to 3000 mrems/yT to the skin, and f i
- 2. For iodine-131 and for all radionuclides in particulate form with halflives greater !
than 8 days: Less than or equal to 1500 mrems/>T to any organ. f i
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.2 GASEOUS EFFLUENTS Dose Rate LIMI?ING NDITION FOR OPERATION 3.11.2.1 Th dose rate due to radioactive materials releas in gaseous effluents fro the site to areas at and beyond the SITE B (DARY (see Figure 5.1-1) s 11 be limited to the following:
- a. For nobl gases: Less than or equal to 500 rems /yr to the total body and ss than or equal to 3000 mrems/ to the skin, and b, '
- b. For iodine-1 and for all radionuclide in particulate fonn with half lives gr ter than 8 days: Less an or equal to 1500 mrems/yr to any rgan.
APPLICABILITY: At all times. ACTION:
- a. With the dose rate (s) ex redi the above limits, without delay
== restore the release rate . ithin the above limit (s). pH b. The provisions of Specifi at ns 3.0.3 and 3.0.4 are not applicable. M SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose ra due to noble gases in ga ous effluents shall be determined to be withi the above limits in accordan e with the methodology H and parameters in th DCM. a 4.11.2.1.2 The do e rate due to irline-131 and all radi uclides in particulate form ith half lives greater than 8 days in g eous effluents shall be determ ed to be within the .bove limits in actor ce with the methodology an parameters in the ODth by obtaining represen tive samples and performi _ analyses in accordance with the sampling and a lysis program spe fied in Table 4.11-2. CALVERT CLIFFS - UNIT 1 3/4 11-7 Amendment No. 169
DELETE THIS PAGE g TABLE 4.11-2 r-h R.
- RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 3 b P
M SAMPLING MINIMUM ANALYSIS LOWER L T OF g
$ GASEOUS RELEASE TYFT. h FREQUENCY FREQUENCY DETE N (LLD)* ~
TYPE OF ACTIVITY ANALYSIS pC1/ml) E o g 8 lank Ea Tank Each Tank Principal Gama Emittersb q Grab S le (Gaseous Emissions Only 1x10 4
- B. Containment Purge P m P
5 C. and Vent Main Vent Each Batch
- Grab Sample Each Batche
]l a s On{}b 1x104 ,E g
M Principal m a Emitters Grab Sample * (Gaseo issions Only) 1x10 4 w Continuous
- M N H-3 / 1x10*
Continuousd Charcoal Sampl 1x10-" Continuousd Parti te Princip Gama Emittersh , e (I-131,ot s) S le M Continuousd Pr$u !e Gr ss Alpha 1x10-" Sample N' q tinuous d ,tee Sr-89, Sr-90 p *{ x10-"
$ Sample & Continuouse Noble Gas Noble Gases Monitor Gross Beta or Gama 1x104 - D. Incin ed 011" P Principal Gama Emitters E Each Batchi P
Each Batcht Sx107 l
\
\ 3/4.11 RADI0 ACTIVE EFFLUENTS
,/
TABLE 4.11-2 (Continued) TABLE NOTATION Th LLD is defined, for purposes of these specifications as the smal j st concentration of radioactive material in a sam e that will yield net count, above system background, that will detected with 9 probability with only 5% probability of fal y concluding that a b nk observation represents a "real" signal l For a parti lar measurement system, which may i ude radiochemical separation: r s l l b 4.66s { EV- 22 x 10' Y exp (-M Where: h LLD is the "a priori lower limi of detection as defined above, as microcuries per un mass or olume, Z s, is the standard devia on f the background counting rate or of the counting rate of a ank sample as appropriate, as counts per minute, E is the counting effi ency, counts per disintegration, V is the sample size n units of ass or volume,
. .I 2.22 x 10' is the umber of disinteg tions per minute per % microcurie, Y is the frac onal radiochemical yield, hen applicable, i H " A is the r foactive decay constant for the articular
[ radionucl e, and O At for lant effluents .iru the elapsed time bet m n sample colle 'on or end of the sample collection perio and time of l cou ing. I ) T ical values of E, V, Y, and At should be used in e alculation. I should be reco before the fact)gnized that the LLDthe limit representing is defined capability asof anaameasu orfor J ent system and not as an a posteriori (after the fact) limit for a particular measurement. CALVERT CLIFFS - UNIT 1 3/4 11-9 Amendment No. 169
l l l
$ 3/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-2 (Continued)
TABLE NOTATION b principal gansna emitters for which the LLD speciff tion applies ex usively are the following radionuclides: Kr-87, -88, Xe-133, Xe- m Xe-135, and Xe-138 for gaseous emissions an Mn-54 Fe-59 Co-58, Co-60, Zn-65 Mo-99, Cs-134, Cs-137, Ce-141 nd Ce-144 for partic ate emissions. This list does not mean t t only these nuclides re to be considered. Other gamma peak that are identifia e, together with those of the above clides, shall also be analyze nd reported in the Semiannual Ra cactive Effluent
- s Release Repo pursuant to Specification 6.9 .8.
L C Sampling and an ysis shall also be perfo ed following shutdown, STARTUP, or a TH L POWER change excee ng 15 percent of RATED h THERMAL POWER with one hour unless (1 analysis shows that the D0SE EQUIVALENT I-131 co entration in the rimary coclant has not increased more than a " actor of 5, a (2) the noble gas activity monitor shows that eff' ent activit has not increased by more than a factor of 5. Z d The ratio of the sam)1e flo ra to the sampled stream flow rate H shall be known for tie time fod covered by each dose or dose rate H calculation made in accordan ith Specifications 3.11.2.1, 3.11.2.2 M and 3.11.2.3. Samples shall be changed t least ce per 7 days and analyses shall .s be completed within 48 ours after c nging, or after removal from i sampler. When sample ollection time s less than seven days, the corresponding LLDs m be increased by proportional factor. This H requirement does no apply if (1) analys shows that the DOSE 1y EQUIVALENT I-131 ncentration in the pri ry coolant has not increased more t n a factor of 5, and (2) e noble gas monitor shows that effl ent activity has not increas more than a factor of W
- 5. l I
Waste Gas D cay Tank samples shall be collected a analyzed for A oxygen on - per week on the in-service tank and fo owing tank isolatio . Waste Gas Surge Tank samples shall be co lected and i analyze daily during power escalation from MODE 6 th ugh MODE 3, and o e per week at all other times. i 9 Col ct sample and analyze daily for total Curie content r l S cification 3.11.2.6 when the Reactor Coolant System spec ic ' tivity of Xe-133 is greater than 150 Ci/ml. CALVERT CLIFFS - UNIT 1 3/4 11-10 Amendment No. 169
\ 3/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-2 (Continued)
TABLE NOTATION h , In nerated oil may be discharged via points other than e main vent (e.g Auxiliary Boiler). Releases shall be accounted r based on pre-r ease grab sample data, i Samples r incinerated oil releases shall be coll ed from and represent ive of filtered oil in liquid form. b C m VD mm M M 1 1 ' W I
\
f, i m i i CALVERT CLIFFS - UNIT 1 3/4 11-11 Amendment No. 169 i j
l 3/4.11 RADI0 ACTIVE EFFLUENTS 4.11.2 GASEOUS EFFLUENTS Dose - Noble Gases LIMITIN CONDITION FOR OPERATION 3.11.2.2 T air dose due to noble gases released in gaseo effluents to areas at and eyond the SITE BOUNDARY (see Figure 5.1-1) s 11 be limited to the followi :
- a. During y calendar quarter: Less than or e al to 10 mrads for gama ra ation and less than or equal to 2 mrads for beta g
radiation d, l
- b. During any c endar year: Less than or equal to 20 mrads for gama radiatio and less than or equa to 40 mrads for beta radiation.
APPLICABILITY: At all times. ACTION:
@ a. With the calculated air se rom radioactive noble gases in
[ gaseous effluents exceedi submit to the Commission any of the above limits, prepare and in 30 days, pursuant to M--q Specification 6.9.2, a S eci Report that identifies the cause(s) for exceeding he li 't(s) and defines the corrective actions that have bee taken to educe the releases and the proposed corrective etions to b taken to assure that subsequent
. .1.s releases will be i compliance wit the above limits.
- b. The provisions Specifications 3.0. and 3.0.4 are not applicable.
1 m SURVEILLANCE REQU EMENTS
~
4.11.2.2 Mont y cumulative dose contributions for the cu ent calendar quarter and rrent calendar year for noble gases shall be d ennined in accordance th the methodology and parameters in the ODCH at east once per 60 day . CALVERT CLIFFS - UNIT 1 3/4 11-12 Amendment No. 169
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.2 GASEOUS EFFLUENTS Dose - Iodine-131 and Radionuclides in Particulate Fo LIMITING ONDITION FOR OPERATION 3.11.2.3 Th dose to a HEMBER OF THE PUBLIC from fodine-131 nd all radionuclides n particulate fann with half lives greater an 8 days in gaseous effluen released to areas at and beyond the SIT B0UNDARY (see Figure 5.1-1) sh I be limited to the following:
- a. During an calendar quarter: Less than or ual to 15 mrems to
[ any organ a d,
- b. During any ca ndar year: Less than or qual to 30 mrems to any organ.
- c. Less than 0.1% of he limits of 3. .2.3(a) and (b) as a result of burning contamin ed oil.
APPLICABILITY: At all times. H ACTION: q a. With the calculated dose the release of iodine-131 and radionuclides in particu ate rm with half lives greater than 8 H days, in gaseous efflu ts exc ding any of the above limits, prepare and submit to he Commis ion within 30 days, pursuant to Specification 6.9.2, a Special Re rt that identifies the 1 cause(s) for excee ng the limit a defines the corrective q actions that have een taken to redu the releases and the
- proposed correc ve actions to be tak to assure that subsequent
[ releases will in compliance with the above limits. [( 1
- b. The provisi applicable s of Specifications 3.0.3 an 3.0.4 are not i
n . SURVEILLANCE QUIREMENTS 4.11.2.3 nthly cumulative dose contributions for the current alendar ! quarter d the current calendar year for iodine-131 and radionuc ides in particu te form with half lives greater than 8 days shall be dete ined in accor nce with the methodology and parameters in the ODCM at least ce per days. i CALVERT CLIFFS - UNIT 1 3/4 11-13 Amendment No. 169
3/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.2 GASEOUS EFFLUENTS GASE0US RADWASTE TREATMENT SYSTEM LIMITING ONDITION FOR OPERATION 3.11.2.4 Th GASE0US RADWASTE TREATMENT SYSTEM and the VENT TION EXHAUST TREATMENT SYS waste prior to eir shall be used to reduce radioactive materi s in gaseous discharge when the gaseous effluent r doses due to gaseous effluent eleases, to areas at and beyond the SI B0UNDARY (see Figure 5.1-1) exce s 1.20 mrad for gama radiation and .4 mrad for beta
"' r:diation in a 92 d period. The VENTILATION EXHAUS REATHENT SYSTEM shall be used to redu radioactive materials in gas us waste prior to their discharge when t calculated doses due to g eous effluent releases, to areas at and beyond e SITE BOUNDARY (see Fig e 5.1-1) exceeds 1.8 mrem to any organ in a 92 ay period.
APPLICABILITY: At all times ACTION: @ a. With gaseous waste bein disc rged without treatment and in H excess of the above limit epare and submit to the Commission H within 30 days, pursuant t pecification 6.9.2, a Special Report that includes the followi formation: H 1. Explanation of why aseous dwaste was being discharged without treatment identific ion of any inoperable ,"g equipment or sub stems, and t reason for the inoperability, i H
- 2. Action (s) ta n to restore the ino rable equipment to
[" OPERABLE s tus, and
- 3. Summary escription of action (s) taken o prevent a
- s recurr ce. 1
- b. The prov'sions of Specifications 3.0.3 and 3.0.
applic le. are not SURVEIL!A E REQUIREMENTS 4.11.2 Monthly doses due to gaseous releases shall be calculated a least nce per 60 days in accordance with the methodology and paramete the CM. in CALVERT CLIFFS - UNIT 1 3/4 11-14 Amendment No. 169
3/4.11 RADI0ACTIVEEFFLUINTS 3/4/,f), f M GASEOUS EFFLUENTS - L ' # Explosive Gas Mixture (Hydrogen rich systems not desi withstand a hydrogen explosion)gned to ' LIMITING CONDITION FOR OPE'tATION t 3, f), j, j " ' (gg The concentration of oxygen in the Waste Gas Holdup System shall e imited to less than or equal to 4% by volume. APPLICABILITY: At all times. . ACTION:
- a. With the concentration of oxygen in a waste gas decay tank greater than 4% by volume imediately suspend all additions of r waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not f applicable.
l SURVEILLANCE REQUIREMENTS i
- 1. 5 T c cen ti so ox en t Wa eG H duySy al e te ed be it t ab e i by e mp1 gro d rib in abl 4.1 2. /
<l
$EPLAcE WirH $NSER7 " Y. )). }. $ "
CALVERT CLIFFS - UNIT 1 3/4 11-15 Amendment No. 169
i INSERT "4.11.1.1" , 4.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall be determined to be within the above limit by collecting and analyzing a sample from the Waste Gas Decay Tank once per week on the in-service tank and following tank isolation. Waste Cu Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other i times. i
'l I
l l tt -,e
- 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11 GASEOUS EFFLUENTS Gas Storace Tanks LIMITING CONDITION FOR OPERATION
/ 3.11 h. The quantity of radioactivity contained in each gas storage tank 1* 2 shall be limited to less than or equal to 58,500 curies noble gases <
(consideredasXe-133). APPLICABILITY: At all times. ACTION:
- a. With the quantity of radioactive material in any gas storage tank exceeding.the above limit, imediately suspend all additions of radioactive material to that tank and within 48 hours reduce the tank contents to within the limit,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
- 1. 2 - 4.1M The quantity of radioactive material contained in the in-service >
gas storage tank shall be determined to be within the above limit at least once per 24 hours when the Reactor Coolant System specific activity of Xe-133 is greater than 150 pCi/ml.
- L CALVERT CLIFFS - UNIT 1 3/4 11-16 Amendment No. 169
/4.11 RADI0 ACTIVE EFTLUENTS 3 .11.3 SOLID RADI0 ACTIVE WASTE LIMIT CONDITION FOR OPERATION 3.11.3 T solid radwaste program shall be_used in accordan with a PROCESS C0 OL PROGRAM to process wet radioactive wastes t meet shipping and burial g und requirements.
APPLICABILITY: t all times. ACTION: [ a. With the visions of the PROCESS CONTR PROGRAM not satisfited,
- sussend s i nts of defectively proce ed or defectively pac'c aged so i radioactive wastes fr the site.
< b. The provision of pecifications 3.
applicable. and 3.0.4 are not [ SURVEILLANCE REQUIREMENTS H 4.11.3 The PROCESS CONTROL PROG sh 1 be used to verify the
' SOLIDIFICATION of at least one r resentbive test specimen from at least every tenth batch of each type f wet rad active waste (e.g., filter 1' sludges, spent resins, evapor or bottoms, ric acid solutions, and sodium sulfate solutions).
N 11 , ~ m = l CALVERT CLIFFS - UNIT.1 3/4 11-17 Amendment No. 169
4.11 RADI0 ACTIVE EFFLUENTS j 3/ 11.4 TOTAL D'0SE l l LIMITI CONDITION FOR OPERATION j 3.11.4 T annual (calendar year) dose or dose comitment to ny MEMBER OF THE PUBLIC e to releases of radioactivity and to radiation rom uranium fuel cycle so ces shall be limited to less than or equel 25 mrems to the total body r any organ, except the thyroid, which sh 1 be limited to less than or equ 1 to 75 mrems. APPLICABILITY: At 11 times. ACTION:
- a. With the calcu ted doses from the rel ase of radioactive h
materials in 11 id or gaseous efflu ts exceeding twice the Ifmits of Specifi tion 3.11.1.2.a. .11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2. .a. or 3.11.2. .b, calculations shall be made including direct ra tion contr utions from the reactor units and outside storage t ks to de mine whether the above limits g of Specification 3.11. have en exceeded. If such is the case, prepare and submit to th Co ission within 30 days, pursuant to g Specification 6.9.2, a Sp al Report that defines the corrective action to be taken to red subsequent releases to prevent M recurrence of exceeding e ove limits and includes the schedule for achieving onfo 1ce with the above Ifmits. This H Special Report, as de ned in 1- CFR 20.405c, shall include an analysis that estima s the radi ion exposure (dose) to a HEMBER 1s 0F THE PUBLIC from ranium fuel cy 'e sources, including all effluent pathways nd direct radiat n, for the calendar year that includes t release (s) covered this report. It shall also describe vels of radiation and ncentrations of 1 ' radioactive m ;erial involved, and the c se of the exposure levels or co centrations. If the estimat dose (s) exceeds the H above limi , and if the release condition esulting in violation [ of 40 CFR art 190 has not already been corr ted, the Special Report all include a request for a variance 'n accordance with the pr 1sions of 40 CFR Part 190. Submittal o the report is consi red a timely request, and a variance is g nted until staf action on the request is complete. l l
- b. T e provisions of Specifications 3.0.3 and 3.0.4 are at '
pplicable. CALVERT CLIFFS - UNIT 1 3/4 11-18 Amendment No. 169 i
4.11 RADI0 ACTIVE EFFLUENTS SUR ILLANCE REQUIREMENTS 4.11.4. Cumulative dose contributions from liquid and gaseous e uents shall be etermined in accordance with Specifications 4.11.1.2, .11.2.2, and 4.11. 3, and in accordance with the methodology and param ers in the ODCM. 4.11.4.2 Cum ative dose contributions from direct radiat n from the reactor units a outside storage tanks shall be detennin in accordance with the methodo gy and parameters in the ODCM. This r uirement is applicable only u er conditions set forth in Specific ion 3.11.4.a. C n 00 . H H bH M 1 1 , C l CALVERT CLIFFS - UNIT 1 3/4 11-19 Amendment No. 169
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 .12.1 MONITORING PROGRAM l LIMIT G CONDITION FOR OPERATION 3.12.1 radiological environmental monitoring program sh 1 be conducted specified in Table 3.12-1. ! l APPLICABILITY. At all times. ACTION:
,. s a. With the diological environmental moni ring progr u not being 1 conducted specified in Table 3.12-1, repare and s'Jbmit to the Commission, n the Annual Radiological nyfronmental Operating Report requir by Specification 6.9. 7, a descriptten of the % b.
reasons for no conducting the prog for preventing a ecurrence. With the level of as required and the plans dioactivity s the result of plant effluents in an environmental mple at specified location exceeding the reporting levels of T le 3. -2 prepare and submit to the
*== Comission within 30 da a er receiving the sample analysis, "" pursuant to Specificatio the cause(s) for exceedi .9.2, a Sp(ecial he limit s) and Report definesthat the identifies b--( corrective actions to b ta n Q
that the potential ann 1 dos ,to less than the calend year li ts of Specifications 3.11.1.2, reduce radioactive effluents so to a MEMBER OF THE PUBLIC is 3.11.2.2, and 3.11. 3. When mo e than one of the radionuclides 1, , in Table 3.12-2 ar detected in t sample this report shall be submitted if: H conc tration (1) . conce ration (2) s rep ting level (1) + ..> 1.0 reportin level (2) - N When radi . uclides other than those in Tab 3.12-2 are detected 1 and are e result of plant effluents. port shall be submit d if the potential annual dose,this to a BER OF THE PUBLIC is eq 1 to or greater than the calendar year 1 its of Spec ications 3.11.1.2, 3.11.2.2 and 3.11.2.3. his report is no required if the measured level of radioactivit was not the r ult of plant effluents; however, in such an even the ndition shall be reported and described in the Annu 1 t 1 Radiological Environmental Operating Report. [ The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. CALVERT CLIFFS - UNIT 1 3/4 12-1 Amendment No. 169
f -. 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING L ITING CONDITION FOR OPERATION (Continued) I With fresh leafy vegetable samples unavailable from on r more of the sample locations required by Table 3.12-1, ide ify locations for obtaining replacement samples and add em to the adiological environmental monitoring program withi 30 days. th e specific locations from which samples were un allable may be deleted from the monitoring program. Pu uant to Spe fication 6.9.1.7, identify the cause of th unavailability of sa les and identify the new location (s) f obtaining the replac nt samples in the next Annual Radio gical Environmental Operatin Report. 1 d. The provis ns of Specifications 3.0.3 a applicable. 3.0.4 are not Q SURVEILLANCE REQUIREMENTS y 4.12.1 The radiological environ tal collected pursuant to Table 3.12-1 r nitorf tg samples shall be H table and figure (s) in the ODCM, an the specific locations given in the H requirements of Table 3.12-1 and th hall be analyzed pursuant to the M Table 4.12-1. tection capabilities required by 1 1 , 1 m l CALVERT CLIFFS - UNIT 1 3/4 12-2 Amendment No. 169 l
DELETE THIS PAGE
$ TABLE 3.12-1 '/
2 RADIOLOGICAL ENVIR0 MENTAL MONITORING PROGRAM E P
.4 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE E 3 . AND/0R SAMPLE PLES AND SAMPLE LOCATIONS
- 0 EQUENCY -
COLLECTION FREQUENCY YSIS S c 1. DIRECT RADIATION b 23 ro ne monitoring stations At least Quarterly E G dose at least M (DR1-D either with two or arterly. more dosime s or with one $ .
- l instrument fo asuring and recording dose ra continuously, l ,
- placed as follows
- g I g
an inner ring of stat s. one ir. each meteorologic pl R
- sector in the general area the SITE B0UNDARY (DRI-DR9);
M l L an outer ring of station 4 one in each meteorol al g sector in the 6- t -km g a range from the s (DR10-DR18); the r ng stations g (DR19 23) to be placed in g sp al interest areas such g- population centers, nearby g residences, schools, and in r+ 1 area to serve as a control station. E e
DELETE THIS PAGE n g TABLE 3.12-1 (Continued)
/
i ca h p RADIOLOGICAL ENVIRONMENTAL MONITORING PRCCRfJ; E P M EXPOSURE PATHWAY Ul . AND/0R SAMPLE NUM8ER OF REPRESENTATIVE SAMPLING AND TYPE REQUENCY - E SAMPLES AND SAMPLE LOCATIONS *
- 2. AIRBORNE COLLECTION FREQUENCY 0 LYSIS 8
=
Z Radioiodine and Samples m 5 locations Continuous sampler c Particulates (Al-AS): Radiciodine Canister operation with sam I-131 analysis weekly. collection weekl , or g 3 samples (A ) from more frequent Particulate Sampler: close to the 3 if E required b ust Gross beta E BOUNDARY locations, loading radioactivity analysis R different sectors of following filter @
- highest calculated "
annual average ground- change;* Gama isotopic IG analysis' of composite ! a level 0/Q. (by location) quarterly. y 1 sample (A4) fr die g vicinity of a unity g having the . a est calculate annual averag round-level D/Q R g sample (AS) from a g- control location, as for g example 15-30 km distant-and in the least g prevalent wind direction. E
\
DELETE THIS PAGE
# TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
'/.
P
*;; EXPOSURE PATNWAY NUMBER 0F REPRESENTATIVE SAMPLING AND TYPE AND ENCY E
Q - AND/0R SAMPLE PLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY 0F LYSIS S
- 3. WATERBORNE R a
E 9 M a. Surface isotopic analysis d "
- I1sample a intake area (Wal) Composite samp'le over sample at charge area 1-month period monthly. Composite for (Wa2) tritium analysis $
y quarterly. g
- b. Sediment from I sample from downstream ea Semiannuall Gama isotopic analysisd shoreline with existing or potential semiannually. @
p { recreational value (Wb1).
~
x
=
R E, s
=
et F M n
\
DELETE THIS PAGE h TABLE 3.12-1 (Continued) '/ N 1
$ RADIOLOGICAL ENVIRONMENTAL MONITORTMS PROGRAM
'w N
P M EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND E AND/0R SAMPLE TYPE AND ENCY . SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ,_ SIS c 4. INGESTION z ~
% a. Fish and 3 samples f comercially 9 Sample in season. or ~
Invertebrates and/or recre ionally semiannually if they isptopic [ analysis on edible g important spec (2 fish are not seasonal. portions. species and 1 inv ebrate g o species) in vicinity plant discharge area (Ial-Ia3 ! t', 3 samples of same species in 5> areas not influenced by plant y discharge (Ia4-Ia6). l
- p
- b. Food Products Samples of 3 different ki Monthly E of broad leaf vegetati grown season. ng growing Gama isotopicd and g 1-131 analysis. m near the site bound at 2 different locatio of highest predicted annu average groundlevel Q (Ibl-Ib6).
R g 1 sam of each of the Monthly during growing Gama otopicdand l a 5 sim r broad leaf vegetation season. I-131 an sis. 1 E wn 15-30 km distant in the east prevalent wind direction g: (Ib7-Ib9). e
i
/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3.12-1 (Continued)
TABLE NOTATION a The ode in parenthesis, e.g., DR1, A1, defines generic ample locat ns in this specification that can be used to id tify the specif locations in the map (s) and table in the 00 . Specific paramete of distance and direction sector from th central point between t two containment buildings and additio description where pert ent, is provided for each sample loc . ion in Table 3.12-1 and in a table and figure (s) in t ODCM. Refer to NUREG-0133, " eparation of Radiological Effl t Technical Is . Specifications r Nuclear Power Plants. Oct er 1978", and to Radiological Ass sment Branch Technical Po tion, Revision 1, November 1979. D f ations are pennitted f om the required sampling h schedule if specime automatic sampling equ are unobtainable d to circumstances such as hazardous conditions, seasonal unavaila lity, and malfunction of nt. If spe mens are unobtainable due to sampling equipment malf ction, effo shall be made to complete ; corrective action prior t the end the next sampling period. All y deviations from the sampli sche le shall be documented in the Annual Radiological Environ ta Operating Report pursuant to " Specification 6.9.1.7. It is cognized that, at times, it may not be possible or practicable to tinue to obtain samples of the media H"q of choice at the most desire lo tion or time. In these instances suitable alternative media nd lo tions may be chosen for the particular pathway in quer ion and propriate substitutions made ,, within 30 days in the ra ological e fronmental monitoring program. 1 Pursuant to Specificati n 6.9.1.7, ide tify the cause of the unavailability of sam es for that path y and identify the new % location (s) for obt ing samples in the xt Annual Radiological 1* Environmental Oper ing Report and also in ude in the report a revised figure (s) nd table for the ODCM re ecting the new location (s). 1 C l CALVERT CLIFFS - UNIT 1 3/4 12-7 Amendment No. 169
/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3.12-1 (Continued)
TABLE NOTATION b One r more instruments, such as a pressurized ion cha er, for meas ing and recording dose rate continuously may be sed in place of, o in addition to, integrating dosimeters. For e purposes of this ta e, a themoluminescent dosimeter (TLD) is onsidered to be one phos or; two or more phosphors in a packet a considered as two or more do " meters. Film badges shall not be us as dosimeters for measuring d: ect radiation. The frequency of alysis or readout for >
,Ts. TLD Systems w 1 depend upon the characterist s of the specific system used an should be selected to obtain ptimum dose infomation with minimal fa g. Due to the geographi limitations, 9 sectors are monitored aro d the Calvert Cliffs N lear Power Plant.
C Airborne particulate ample filters sh radioactivity 24 hour or more after thoron daughter decay. be analyzed for gross beta pling to allow for radon and f gross bet activity in air particulate samples is greater than n times e yearly mean of control samples, gamma isotopic analysis sh I be rfomed on the individual samples. H d Gama isotopic analysis means e identification and quantification. H of gama-emitting radionuclid that may be attributable to the
) .H effluents fr.om the facility.
A composite sample is one n which e quantity (aliquot) of liquid
,, sampled is proportional o the quant y of flowing liquid and in 1
which the method of s ling employed esults in a specimen that is representative of the iquid flow. In is program, composite sample
-H aliquots shall be co ected at time inte als that are very short
- s (e.g., hourly) rel ive to the compositing eriod (e.g., monthly) in l., order to assure o aining a representative mple.
s 1 CALVERT CLIFFS - UNIT 1 3/4 12-8 Amendment No. 169
DELETE THIS PAGE g TABLE 3.12-2 G , g REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES f n M REPORTING 1FVELS c a. w . 5
=
r-i WATER BORNE PARTICULATE FISH & INVERTEBRATES g ANALYSIS (pci/1) ES (pC1/m') MILK M PRODUCTS E (pC1/kg, wet) (pci/1) / (pC1/kg, wet) U y H-3 20,000'
~
[ Mn-54 1,000 30,000 z Fe-59 o 400 10,000 l Co-58 1,000 30,000 m p Co-60 300 00 U ! a Zn-65 300 20,000 Q g Zr-Nb-95 400 lil m I-131 2 0.9 3 100
- Cs-134 30 1,000 60 1,000 N
g Cs-137 50 20 2,000 70 2,000 g Ba-La-140 200 a 300
& For drinking er samples. This is a 40 CFR Part 141 value. If no drinking water pathway e value of 30 0 pC1/1 may be used. ts, a i M l
DELETE THIS PAGE 9 r- TABLE 4.12-1
,[a DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS..b g ft LOWER LIMIT 0F DETECTION (LLD)*
a E B WATER AIRB0 PARTICULATE FISN & INVERTEBRATES E ANALYSIS (pC1/1) OR GAS (pC1/m3 ) (pC1/kg, wet) MILK F000 PRO 5 SEDIMENT .E (pC1/1) (pC1/ , wet) (pC1/kg. dry) 9 [ Gross Beta 4 0.01 H-3 2,000' g Mn-54 15 y 130 g ' Fe-59 39 0
- r-g Co-58,60 15 130 5 s
=j E Zn-65 30 -I 0
=
Zr-Nb-95 15
- I-131 I d
0.07 1 60 Cs-134 15 0.05 130 15 60 150 ( s Cs-137 18 6 150 18 80 180 $ Ba-La-140 15 15 [# If no drinki ater pathway exists, a value of 3000 pCi/1 may be used. 5
I l 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 4.12-1 (Continued) : TABLE NOTATION Th list does not mean that only these nuclides are t be con dered. Other' peaks that are identifiable, toget r with those of th above nuclides, shall also be analyzed and r orted in the Annual adiological Environmental Operating Report ursuant to Specifi tion 6.9.1.7. b Required d ection tapabilities for thennolumi scent dosimeters used
' for enviro tai m asurements shall be in ac rdance with the
[ recommendatio of Regulatory Guide 4.13. c The LLD is defin , for purposes of these pecifications, as the smallest concentra ion of radioactive m erial in a sample that will < yield a net count, ove system backgr nd, that will be detected with 95% probability ith only 5% pro ability of falsely concluding that a blank observati represents "real" signal . For a particular measurem t syst , which may include radiochemical Z separation: 4.66 M E V 2.22 - e (-Mt) H Where: " LLD is the "A pri i" lower limit f detection as defined above, y e as picocuries p unit mass or volu , [ s s, is the sta ard deviation of the ba ground counting rate or of the coun ng rate of a blank sample appropriate, as counts y per minute [ E is th counting efficiency, as counts per isintegration, V is e sample size in units of mass or volume
- 2. is the number of disintegrations per minute p r picocurie, is the fractional radiochemical yield, when applica le, A is the radioactive decay constant for the particular radionuclide, and CALVERT CLIFFS - UNIT 1 3/4 12-11 Amendment No. 169 l
T(3/4.12 RADIOLOGICAL ENVIRONNENTAL MONITOR !
,/
TABLE 4.12-1 (Continued) TABLE NOTATION At for environmental samples is the elapsed time tween sample 11ection, or end of the sample collection peri , and time of c nting. Typt 1 values of E, Y Y and at should be u d in the calcu' tion. ' I., It should be ecognized that the LLD is deff d as an a oriort ' (before the fa ) limit representing the ca bility of a measurement system and not an a posteriori (after t particular measur fact) limit for a ' nent. Analyses shall t perfonned in such a manner < that the stated LL will be achieved u er routine conditions. : Occasionally backgro d . fluctuations, avoidable small sample sizes, the presence of inter ring nuclides or other' uncontrollable h circumstances may rende these LLDs nachievable. In such cases, the contributing factors sha be ide ified and described in the Annual g Radiological Environmenta' Opera 6.9.1.7. ng Report pursuant to Specification
" "" d LLD for drinking water samp1 If no drinking water pathway exists,
)===4 the LLD of gamma isotopic a ly s may be used. ! H I
- -=<
$ s- ~ [ m , CALVERT CLIFFS - UNIT 1 3/4 12-12 Amendment No. 169
l l 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/ 2.2 LAND USE CENSUS LIMITI CONDITION FOR OPERATION 3.12.2 A nd use census shall be conducted and shall identif within a distance of km (5 miles) the location in each of the 9 met rological sector of th nearest milk animal, the nearest residence a the nearest garden; of grea er than 50 m (500 ft') producing broad lea vegetation. 2 (For elevated re ases as defined in Regulatory Guide 1. 1. Revision 1, July 1977, the la use census shall also identify with a distance of 5 km (3 miles) the ocations in each of the 9 meteorol gical sectors of all g milk animals and all ardens of greater than 50 m* pr ducing broad leaf vegetation). APPLICABILITY: At all t es. ACTION: h a. With a land use cens calculated dose or do identifyi a location (s) that yields a comitm t greater than the values g currently being calcula ed in ecification 4.11.2.3, identify the new location (s) in t n t Annual Radiological Environmental g Operating Report, pursuan Specification 6.9.1.7. M b. With a land use census i nt ing a location (s) that yields a H calculated dose or dose omit nt (via the same exposure pathway) 20 percent gr ater tha at a location from which samples
-s are currently being tained in a cordance with Specification 1 3.12.1, add the new ocation(s) to he radiological environmental monitoring progra within 30 days. hesamplinglocation(s),
excluding the co rol station locatio having the lowest T calculated dos or dose comitment(s), ia the same exposure
- pathway, may deleted from this monito ing program after 3 October 31 o the year in which this land se census was H conducted. Pursuant to Specification 6.9. 7, identify the new '[ location ( in the next Annual Radiological vironmental Operati Report and also include in the repo a revised figure ) and table for the ODCM reflecting the ewlocation(s).
- c. The . rovisions of Specifications 3.0.3 and 3.0.4 a e not ap icable.
Broad leaf vegetation sampling of at least three different kinds of vegetation may be perfomed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lie nf the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples. CALVERT CLIFFF - UNIT 1 3/4 12-13 Amendment No. 169
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING SU EILLANCE REQUIREMENTS 4.12. The land census shall be conducted during the growing seas n at l 1 east o e per 12 months using that information that will provid the best I results, uch as by a door-to-door survey, aerial survey, or by onsulting local agri 1ture authorities. The results of the land use c sus shall be included in he Annual Radiological Environmental Operating port pursuant to Specificat on 6.9.1.7. ' C m VD H M M 1 1 , 1 C- - CALVERT CLIFFS - UNIT 1 3/4 12-14 Amendment No. 169
1 I 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/ 2.3 INTERLABORATORY COMPARISON PROGRAM LIMITI CONDITION FOR OPERATION 3.12.3 An yses shall be performed on all radioactive materia , supplied as part of Interlaboratory Comparison Program that has be approved by the Comissio that correspond to samples required by Tabl 3.12-1. APPLICAEILITY: t all times. ACTION:
- a. With analys not being perfomed as requ ed above, report the corrective ac ions taken to prevent a r urrence to the Comission in e Annual Radiological vironmental Operating h
b. Report pursuant o Specification 6.9. 7. The provisions of applicable. ecifications 3 .3 and 3.0.4 are not r/2 SURVEILLANCE REQUIREMENTS H 4.12.3 The Interlaboratory Comp ison P gram shall be described in the ODCM. A sumary of the results btained a part of the above required Interlaboratory Comparison Pro am shall be neluded in the Annual 1 Radiological Environmental 0 rating Report p rsuant to q Specification 6.9.1.7. 1 R , CALVERT CLIFFS - UNIT 1 3/4 12-15 Amendment No. 169
6.0 ADMINISTRATIVE CONTROLS maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work l
. functions.
- b. The complete results of steam generator tube inservice i inspections performed during the report period (reference !
Specification 4.4.5.5.b) . i f t
- c. Documentation of all failures and challenges to the pressurizer i PORVs or safety valves.
l 1 MONTHLY OPERATING REPORT T 6.9.1.6 Routine reports of operating statistics and shutdown experience : shall be submitted on a monthly basis to the Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission, Washington, D.C. : 20555 ATTN: Document Control Desk, with a copy to the Regional f Administrator and to the NRC Resident Inspector, no later than the 15th of I each month following the calendar month covered by the report. : ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- I. 6 .7 Rou ne adi ogi 1E iro nt Op atin Rep ts veri g t l ;
o rat n th uni dur gt pr iou cal dar ar all es mit d j rio to y1 f ch y ar. ; T An al dio gic, En ro nta Oper ting epo ss 11 < clu ! es, nt ret ; ion', an an aly s of tren of he tsul o the ! radi logi al vir nt su eil ance cti ties for e or per d, ! in udi a pa son ith reo rati nal udi , w' ho at- nal l c tro as pp ria ,a wi pr tous nvi nme .al rye la e - epor s, d an sse men of eo erv imp cts t pl o rat n
- on ee tro nt. The epo ss 11 so clu th res ts 1 du ;
ce use req red yS cif atio 3.1 .2. i he nual adi ogi 1E iro ent 0p ati Re rts hal in ude he f , res ts an sis f ra ol cal nvi nme al pl s a of 11 e ro nta radi tior mea r :s t en rir the er dp sua t e lo tio sp if in he le nd F gur in e CM, as 1 Repkee A Insur "s.9.1.7*/ A single submittal may be made. CALVERT' CLIFFS - UNIT 1 6-19 Amendment No. 169 l
l INSERT "6.9.1.7" I i 6.9.1.7 The Annual I.adiological Emironmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological emironmental monitoring program for the reporting period. He material provided shall be consistent with the objectives outlined in the ODCM and 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. i The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological emironmental samples and of all emironmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. The report shall identify the TLD I results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. l l J
l
. 1 6.0 ADMINISTRATIVE CONTROLS riz and t ulat d res ts of hese alyse and asur ents thel at the ble the diol ical sess t Bra h Te nical siti n Rev sion . Nov ber 1 9. the ent t ts indi dual resu s are ot a 11abl for clust with he re rt, e rep t sha be ubmit d no ng an expl ing e rea ns for the ssing esults T miss g da shal be s itte as so as p sib in a upplem tary eport l
- 9. The epor shal also nelud the f lowin . a mmary escri fon the (X) ra plog al e fron tal itori g pro am; leas two le ble
. ps verin all s plin ocat ns ke d to tabl givin dist ces N nd d ecti s fro the ntral oint twee the t cont men M but ings; he r uits lice ee p ici tion the I erla rato
& Q Co paris viati Pro s fr the
,r utred y Spe fica on 3. .3; d cuss n of 11 31 1 sche eo able .12-1; nd d cus on of all a lyses n wh h t.1e LD re ired y Tab e 4.12 was at a leva e.
( Th Annu Radi ogica Envir nmen Oper ting R ort 11 i clude he i entif atio of th cause f un atlab ity o samp s (i any) and wi escri e the ocati s us for e re aceme samp es. e re rt wil i also nelu any rmane cha es i he sa le 1 atio whi could ap ar in he mo itori pro am, will nelu ar ised gure( and
% ~
t le f the CM r ecti g the .ew loc ion . 1 SEM NNUA RADIO TIVE FFLU RELE E RE RT** 13 y 9.1. Rout e Ra oact e Effl ent eas Repor cover g th N oper on o the it du ng th prev us 6 onth of ope tion all A sub tted ithi 0 da after Janu yI d Jul 1 of ch ye . e Ra oacti e Eff ent R ease epor sha inclu a su ary the s quant ies rad activ igu< and aseo efflue s an soli wast rel sed om th plant s ou iine in Re latory utde .21, eas ng, Ev uati , an Repor ng R ioac vity n Soli aste and eas of dica ive erial in quid nd G eous Ef uent from ght- ater-Cool Nucl r Pow Pla s," evisi 1. Ju 1974 with ata mar ed on quar rly b is f owi the ormat Appe ix B ere . WE -- k i h h 're aN En A single submittal may be made for Calvert Cliffs, since the Radwaste Systems are comon to both units.
%d;oadix fMIaenUelesse RepotI anc\
In lieu of submission with the(Semi-Annual RepordSr"fSr" analyses results may be submitted in a sup)1ementary report within 120 days afterfJanuary 1 and July 1 of eac1 yeg. 5%llb} ef the Radioachve EWLent Release Reporl' CALVERT CLIFFS - UNIT 1 6-20 Amendmerit No.169
INSERT "6.9.1.8" RADIOLOGICAL EFFLUENT RELEASE REPORT *
'6.9.1.8 De Radiological Effluent Release Repon covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. (i.e., time between submittal of the repons must be no longer than 12 months).** Le report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.I.
Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous, and solid) shall be reponed to the Commission in the Radioactive Effluent Release Repon for the period in which the modification to the waste system is completed. The discussion of each change shall contain:
- a. A description of the equipment, components and processes invoh ed.
- b. Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the POSRC.
l De report shall also include changes to the ODCM in accordance with Specification 6.17.2.c.
6.0 ADMINISTRATIVE CONTROLS The dioactive Effluent Release Report to be submitted within 60 days after anuary 1 of each year shall include an annual sumary of hourly meteoro gical data collected over the previous year. This annual sumary may be e her in the form of an hour-by-hour listing on magnetic tape of wind spee wind direction, atmospheric stability, and precipitation (if measured), in the form of joint frequenpy distributions of wind spee , wind directio and atmospheric stability. This same report shall include an ass sment of the radiation doses due to the radioactive 1 quid and gaseous eff ents released from the unit or station during the evious calendar year. assessment of radiation doses shall be perfo d in accordance with th methodology and parameters in the 0FFSITE DO CALCULATION MANUAL CM). l The Radioactive Effluen Release Report to be submitted 60 d s after January 1 of each year s 11 also include an assessment of adiation doses { .' g to the likely most expose MEMBER OF THE PUBLIC from reac r releases and other nearby uranium fuel c cle sources, including doses rom primary l h effluent pathways and direct adiation, for the previo calendar year to show conformance with 40 CFR rt 190, Environmental diation Protection Standards for Nuclear Power Ope tion. Acceptable ir hods for calculating the dose contribution from liqui and gaseous effl nts are given in Regulatory Guide 1.109, Rev.1, Oc ober 1977, and . UREG-0133, " Preparation { of Radiological Effluent Technical ecificatio for Nuclear Power Plants." H The Radioactive Effluent Release Report sh 1 include the following information for each class of solid waste as defined by 10 CFR Part 61) shipped offsite during the report period-
- a. Container volume, p b. Total curie quantity (spe ify whether etermined by measurement orestimate),
w
- J c. Principal radionucli s (specify whether d ermined by 11 measurement or esti te),
t d. Source of waste d processing employed (e.g., ewatered spent resin, compacte dry waste, evaporator bottoms), r s 1
- e. Solidificati agent or absorbent (e.g., cement).
The Radioactive Eff ent Release Reports shall include a list a description of unp anned releases from the site to UNRESTRICTED EAS of radioactive mate als in gaseous and liquid effluents made during e reporting perio . In eu of submission with the first half year Radioactive Effluent R ease Report, this summary of required meteorological data may be tained on site in a file that shall be provided to the NRC upon request. CALVERT CLIFFS - UNIT 1 6-21 Amendment No. 169 l i
1 ; 6.0 ADMINISTRATIVE CONTROLS [TeR ioa tiv Eff en Rel[asej[epor/ss 11 iclu e a c ng mde I ri th rep rti p iod ;o t(e PR FCES CON OL OG CP) a t he FFS ED E LCU TI JAL )DC ,a wel as 1 ti o ne WP loc to fo do ca cul to pu uan to pec fic io 3.1 2. ide ifi d b the ann 1 nd se en j 6.9.1.9 CORE OPERATING LIMITS REPORT l
- a. Core operating limits shall be established prior to each reload l cycle, er prior to any remaining portion of a reload cycle, and l shall be documented in the COLR for the following: l 2.2.1 -
i 3.1.1.1 ' l 3.1.1.2 3.1.1.4 3.1.3.1 3.1.3.6 3.2.1 3.2.2.1 3.2.3 3.2.5 3.9.1
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC; specifically, those described in the following documents:
(1) CENPD-199-P Latest Approved Revision, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LC0 Setpoint Methodology for Analog Protection Systems," January 1986 (2) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Themal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 (3) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Themal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (4) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Bolling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2 " March 1980 (5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 CALVERT CLIFFS - UNIT 1 6-22 Amendment No. 186
6.0 ADMINISTRATIVE CONTROLS [.17 cens ini ate ch ges ot ODC : Sh 1 be ub te to eC iss on i the emi nual dioac ve ffl nt lea Re rt f r th<f peri d in hich he ange ) sm ee ect e. his ubmi ;al all ntai :
- 1. uff ien inf at' n t sup' rt t e ra onal fo'r e hEptgg cha e. Info att su .itt sho dc sist fa acka of )
th e ges f th ODC to ch ged th e ch p e nu ere ' W/7"// a d pr vide. wit ac nge umb and rc nge te t geth ith p ana ses r ev luat ns j stif ng t e MSE#7 cha e(pro s) ria l %,f 7, p d . A ete ina on t at t e ch ge w 1n red et ac rac r re abi ty o dos cal lati ns o setp nt dete ina ons; and Do men tio of e fa th the hang has een evi ed ; a fo da ept le b the OSRC l b Sha be me fec ve u on r iew th POSR and ppr val f t Pla t Ge ral ana r. I6.1 MAIR Cf /NGES/f0 RA6I0AC[IVE IdOUldGASdVS d0 S0/fD W[STE/ TfEATMEfT SYTfEMS/ l
.18. Li nsee ini ated .ajor chan s to he dio tiv Wa e S ste, ggfg (lig d, seo an soli sh' 1 be epor ed t the omm si in the Sem nnu Ra oac ve E lue Rel ase port or ep io in ic th
; mo fic ion o tt was e sy em i comp eted Th dis ss no ea c ange hall con in:
- a. de ript on o the quip nt, ompo nts and ro ss inv ved.
. D cume atio of e fa 6 th the cha e clu ng he af y aly s wa rey wed df nd cep bl ay e SR ADD TNSER7' =
\
%.18" CALVERT CLIFFS - UNIT 1 6-31 Amendment No. 186 l
INSERT "6.17.2" ! l t 6.17.2 Licensee initiated changes to the ODCM:
- a. Shall be himmted and records of reviews performed shall be retamed This h>==tation shall contain: :
- 1. Sufficient information to support the change (s) together with the appropriate i i
analyses or evaluations justifying the change (s),
- 2. A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and !
10 CFR Past 50, Appendix I, and not adversely impact the accuracy or reliability , of effluent, dose, or setpoint calculations;
- b. Shall become effective after review and acceptance by the POSRC and the approval of the i Plant General Manager;
- c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of :
the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that ; was changed, and shall indicate the date (i.e., month and year) the change was i implemented.' l
INSERT "6.18" 6.18 RADIOACTIVE EFFLUENT CONTROLS PROGRAM This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the ! doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial : actions to be taken whenever the program limits are exceeded The program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring ' :
instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM. ,
- b. Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 2, :
Column 2.
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ,
ODCM. i
^
- d. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED l t
AREAS to be limited:
- 1. During any calendar quarter: Less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ, and
- 2. During any calendar year: Less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.
INSERT "6.18" (continued)
- e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.
- f. Limitations on the functional capability and use of the Liquid Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 mrem to any organ in a 92 day period.
- g. Limitations on the functional capability and use of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the calculated doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period.
- h. Limitations on the functional capability and use of the Ventilation Exhaust Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED AREAS exceeds 1.8 mrem to any organ in a 92 day period.
- i. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
- 1. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- 2. For iodine-131 and for all radionuclides in particulate form with halflives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
i l INSERT "6.18" (continued)
- j. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous emuents to areas beyond the SITE BOUND ARY, to be limited:
- 1. During any calendar quarter: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation, and
- 2. During any calendar year: Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.
- k. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131 and all radionuclides in particulate form with half-lives greater than 8 days in gaseous emuents released to areas beyond the SITE BOUNDARY, to be limited:
- 1. During any calendar quarter: Less than or equal to 15 mrems to any organ, and
- 2. During any calendar year: Less than or equal to 30 mrems to any organ.
- 3. Less than 0.1% of the limits of 6.18.k(l) and (2) as a result of burning contaminated oil.
- 1. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
3/4.3 ' INSTRUMENTATION BASES In the event more than four sensors in a Reactor Vessel Level channel are
- inoperable, repairs may only be possible during an extended COLD SHUTDOWN.
This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield ha:; been moved. If only one channel is inoperable, it should be restored to 0PERABLE status in accordance with the schedule outlined in a Special Report. If both channels are inoperable, the system shall be restored to 0PERABLE status in the next refueling outage. 3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is. required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
.3.3.9 Radioactive Gaseous Effluent Monitoring Instrumentation The ra active gaseous effluent instrumentation is provided to mo or and control, pp11 cable, the releases of radioactive materials gaseous effluents dur actual or potential releases of gaseous ef ents. The "T' alam/ trip setpo s for these instruments shall be cale ted and adjusted ,
Jun in accordance with methodology and parameters in e ODCM to ensure ' r that the alam/ trip wi, ccur prior to exceeding e limits of ; H Specification 3.11.2.1.a > d on average annu /Q. The OPERABILITY and use of this instrumentation onsistent the requirements of General Design Criteria 60, 63, and 64 o pen A to 10 CFR Part 50.
> 3/4.3.3.10 Radioactive Licuid E en nitorina Instrumentation The radioactive liquid eff nt instrumentati is provided to monitor and control, as applicable e releases of radioact materials in liquid
] effluents during ac or potential releases of liq effluents. The p alam/ trip setpo s for these instruments shall be cal ated and adjusted in accordanc th the methodology and parameters in the e to ensure """ that the m/ trip will occur prior to exceeding the limics o 10 CF rt 20. The OPERABILITY and use of this instrumentation co tent with the requirements of General Design Criteria 60, 63, 64 Appendix A to 10 CFR Part 50. CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 199 l
3/4.11 RADI0 ACTIVE EFFLUENTS sbS / 3/4. .1 LIOUID EFFLUENTS 3/4.11. 1 Concentration This speci cation is provided to ensure that the concentration of . radioactive terials released in liquid waste effluents to UNRE ICTED . AREAS will be ess than the concentration levels specified in I 10 CFR Part 20, ppendix B. Table II, Column 2. This limitati provides additional assur 1ce that the levels of radioactive material in bodies of - water in UNRESTRI4 ED AREAS will result in exposures wi. thin 1) the Section II.A design bjectives of 10 CFR Part 50, Appendix to a MEMBER OF THE PUBLIC and (2) t limits of 10 CFR 20.106(e) to the opulation. 1 The required detection pabilities for radioactive ma rials in liquid waste samples are tabula d in terms of the lower 11 ts of detection (LLDs). Detailed discussi of the LLD, and other tection limits can be
'..A., " Limits for found in HASL Procedures Ma al, HASL-300, Currie Qualitative Detection and Qua titative Determina on - Application to Radiochemistry," Anal. Chem. 4 586-93 (1968), nd Hartwell, J.K.,
" Detection Limits for Radioanal ical Countinc echniques," Atlantic Richfield Hanford Company Report H-SA-215 une 1975).
3/4.11.1.2 Dose H H This specification is provided to imp 1 nt the requirements of H" 10 CFR Part 50. Appendix I, Sections . III.A and IV.A. The Limiting Condition for Operation implements t e gu es set forth in Appendix I, N Section II.A. The ACTION statemen provi the required operating F flexibility and at the same time plement t guides set forth in [ Appendix I, Section IV.A to ass e that the re ases of radioactive material in liquid effluents t UNRESTRICTED AR will be kept "as low as H is reasonably achievable." T e dose calculation thodology and parameters
- in the ODCM implement the r utrements in Appendix , Section III.A that -
.1,,s, conformance with the guid of Appendix I be shown calculational y procedures based on mode and data, such that the ac al exposure of a HEMBER OF THE PUBLIC th ugh appropriate pathways is u 'ikely to be ) )-- l substantially underes , mated. The equations specified 1 - 1t- calculating the dose due to the actual release rates of dioactive the ODCM for materials in liqui effluents are consistent with the meth ology provided in Regulatory Gui 1.109, " Calculation of Annual Doses to > from Routine Releases of Rea or Effluents for the Purpose of Evaluating C pliance with 10 CFR Part 50 Appendix I," Revision 1, October 1977, Regulat Guide 1.113, stimating Aquatic Dispersion of Effluents from Ac idental and Routine eactor Releases for the Purpose of Implementing Appe ix I," April 1977 and NUREG-0133, " Preparation of Radiological Effluent chnical Specifica ions for Nuclear Power Plants". I l CALVERT CLIFFS - UNIT 1 B 3/4 11-1 Amendment No. 169 l 2 i
l 1
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3/4.11 RADI0 ACTIVE EFFLUENTS SES 3/ 11.1.3 Liouid Radwaste Treatment System The re irement that the appropriate portions of this system be use , when specifi , provides assurance that the releases of radioactive mat rials in liquid e luents will be kept "as low as is reasonably achievabl . This specificat n implements the requirements of 10 CFR 50.36a, of 10 CFR Part 0, Appendix A. General Design Criterion 60 and t design objective giv in 10 CFR Part 50, Appendix I, Section II.D. The specified
- limits governi the use of appropriate portions of the Liq d Radwaste Treatment System ere specified as a suitable fraction of le dose design objectives set fo h in 10 CFR Part 50, Appendix I, Sect n II.A for liquid effluents. The dos limits apply to the combined efflu t of the plant (e.g.,twounits). i
. .1.s .,
3/4.11.2 GASEOUS EFFLUMTS
\
I 3/4.11.2.1 Dose Rate This specification is provide to ensure that he dose at any time at and
% beyond the SITE BOUNDARY from will be within the annual dose l' its of I CFR Part 20 to UNRESTRICTED seous efflue s from all units on the site i
AREAS. The annual dose limits ar the do s associated with the concentrations of 10 CFR Part 20, A en x B, Table II, Column 1. These H limits provide reasonable assurance radioactive material discharged in H" gaseous effluents will not result in 'e exposure of a MEMBER OF THE PUBLIC l HH in an UNRESTRICTED AREA, exceeding e imits specified in 10 CFR Part 20, Q Appendix B, Table II (10 CFR 20.10' b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUND TY, the cupancy of that MEMBER OF THE F
,s PUBLIC will be sufficiently low o compensa for any increase in the {
1 atmospheric diffusion factor a ove that for t e SITE BOUNDARY. H The required detection capa lities for radioac 've materials in gaseous s waste samples are tabulat in tenns of the lower imits of detection 1i (LLDs). Detailed discus on of the LLD, and other etection limits can be w found in HASL Procedur Manual, HASL-300, Currie, L ., " Limits for
)- Qualitative Detection nd Quantitative Determination Application to 'T'i
- Radiochemistry," Ana . Chem. 40, 586-93 (1968), and Ha well, J.K.,
" Detection Limits r Radioanalytical Counting Technique " Atlantic Richfield Hanford ompany Report ARH-SA-215 (June 1975).
Cha ed by NRC letter dated April 26.1003 . l CALVERT CLIFFS - UNIT 1 B 3/4 11-2 l s
l 3/4.11 RADI0 ACTIVE EFFLUENTS i B S 3/4.1 2.2 Dose - Noble Gases This spe fication is provided to implement the requirements of 10 CF Part 50, pendix I, Sections II.B. III.A and IV.A. The Limiting Co ition for Operati implements the guides set forth in Appendix I, Sectio II.B. The ACTION s tements provide the required operating flexibility d at the same time imp ent the guides set forth in Appendix I, Section .A to i assure that the eleases of radioactive material in gaseous eff uents to UNRESTRICTED AR will be kept "as low as reasonably achieva e." The Surveillance Requ ements implement the requirements in Appe ix I, Section III.A that nfomance with the guides of Appendix be shown by calculational proced es based on models and data such th the actual
-y exposure of a MEMBER THE PUBLIC through appropriate p thways is unlikely 1 to be substantially und estimated. The dose calculat n methodology and parameters established i the ODCM for calculating th doses due to the actual release rates of ra ioactive noble gases in seous effluents are h
consistent with the methodo gy provided in Regula ry Guide 1.109,
" Calculation of Annual Doses o Man from Routine eleases of Reactor Effluents for the Purpose of E luating Complia e with 10 CFR Part 50, Appendix I," Revision 1, Octobe 1977 and Reg atory Guide 1.111, " Methods for Estimating Atmospheric Transp t and Dis rsion of Gaseous Effluents in Routine Releases form Light-Water- oled Re ctors," Revision 1 July 1977, and NUREG-0133 " Preparation of Radio ogic Effluent Technical Specifications for Nuclear Power Plan "
H The ODCM equations provided for dete n g the air doses at and beyond the SITE BOUNDARY are based upon the hi oric annual average atmospheric
- conditions. ,
3/4.11.2.3 Dose - Iodine-131 A Radionuclid In Particulate Form i This specification is provid to implement the quirements of 10 CFR
;1 3 Part 50, Appendix I, Sectio s II.C, III.A and IV. The Limiting Conditions for Operation e the guides set forth i Appendix I, !
7 Section II.C. The ACTIO statements provide the req red operating H flexibility and at the ame time implement the guides et forth in f Appendix 1 Section I .A to assure that the releases of adioactive materials in gaseou effluents to UNRESTRICTED AREAS wil be kept "as low as is reasonably a iievable." The ODCM calculational meth ds specified in the Surveillance equirements implement the requirements in ppendix I, Section III.A t t confomance with the guides of Appendix I e shown by calculational ocedures based on models and data, such that t e actual exposure of HEMBER OF THE PUBLIC through appropriate pathways s unlikely to be subst tially underestimated. The ODCM calculational meth ology and CALVERT CLIFFS - UNIT 1 B 3/4 11-3 Amendment No. 169 i
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3/4.11 RADI0 ACTIVE EFFLUENTS BASES rameters for calculating the doses due to the actual release rates of the s ect materials are consistent with the methodology provided in Reg tory Guide 1.109, " Calculation of Annual Doses to Man from Routi Relea of Reactor Effluents for the Purpose of Evaluating Complian with
. 10 CFR t 50, Appendix I," Revision 1, October 1977 Regulatory Guide 1.1 " Methods for Estimating Atmospheric Transport and D ersion 1 of Gaseous luents in Routine Releases from Light-Water-Cool Reactors,"
Revision 1, J 1977, and NUREG-0133, " Preparation of Radio gical Effluent Techni Specifications for Nuclear Power Plants". These
. equations also pro de for detemining the actual doses sed upon the - "T historical annual a age atmospheric conditions. Th elease rate A specifications for io e-131 and radionuclides in ticulate fonn with r half lives greater than days are dependent upon le existing radionuclide H
pathways to man, in the ar s at and beyond the TE BOUNDARY. The pathways that were examined the developmen of these calculations were: 1 "T a
- 1) individual inhalation of ai orne radio ides, 2) deposition of l i radionuclides onto green leafy y etatio ith subsequent consumption by l i man, 3) deposition onto grassy are w e milk animals and meat producing l animals graze with consumption of th ilk and meat by man, and i
, 3 4) deposition on the ground with s se ent exposure of man.
3/4.11.2.4 GASEOUS RADWASTE T ATHENT SYS The requirement that the ropriate portions these systems be used,
- when specified, provide reasonable assurance th the releases of radioactive materials n gaseous effluents will be pt "as low as is reasonably achievab "
This specifica n implements the requirements of 10 CFR .36a, 10 CFR Part , Appendix A, General Design Criterion 60 an he design objectives iven in 10 CFR Part 50, Appendix I, Section II.D. The specifie imits governing the use of appropriate portions of t systems were s cified as a suitable fraction of the dose design objectiv -set for in 10 CFR Part 50, Appendix I, Sections II.B and II.C for gas us e uents. The dose limits apply to the combined effluent of the pla ' e.g., two units). 1.1 u 3/4.11.e+( Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below it's flammability limit provides assurance that the releases of radioactive materials will be controlled in confomance with the requirements of 10 CFR Part 50, Appendix A, General R Design Criterion 60. 3 Changed by NRC letter dated April 26 1903 . l CALVERT CLIFFS - UNIT 1 B 3/4 11-4
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 12 a 3/4.11. $ Gas Storace Tanks The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly Y by another Technical Specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled k release of the tank's contents, the resulting total body exposure to a f HEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed 10 CFR Part 100 limits. gk
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Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed accident guidelines. 4.11.3 SOLID RADI0 ACTIVE WASTE This acification implements the requirements of 10 CFR 50.36a and 10 CFR t 50, Appendix A, General design Criterion 60. The pr ss parameters e included in the PROCESS CONTROL PROGRAM. 3/4.11.4 TOTAL SE F T' This specification is rovided to meet the dose li ations of 40 CFR A Part 190 that have been - corporated into 10 CF art 20 by 46 FR 18525. r The specification requires e preparation a submittal of a Special H Report whenever the calculate doses from ant generated radioactive effluents and direct radiation "y' eed mrems to the total body or any organ, except the thyroid, which s be limited to less than or equal to L 75 mrems. The Special Report wi d ribe a course of action that should 4 result in the limitation of t annual e to a MEMBER OF THE PUBLIC to
)
i within the 40 CFR Part 190 mits. For th urposes of the Special Report, b" it may be assumed that dose commitment t he HEMBER OF THE PUBLIC from other uranium fuel c e sources is negligible. O If the dose to y MEMBER OF THE PUBLIC is estimated exceed the l requirement 40 CFR Part 190, the Special Report wit request for a i====m' variance rovided the release conditions resulting in vio tion of i I 40 CF art 190 have not already been corrected), in accorda with the pro sions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is co "dered to a timely request and fulfills the requirements of 40 CFR Part ' CALVERT CLIFFS - UNIT 1 B 3/4 11-5 Amendment No. 169 l l
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3/4.11 RADI0 ACTIVE EFFLUENTS kES- _/ , unti NRC staff action is completed. The variance only relates to the limits f 40 CFR Part 190, and does not apply in any way to the other requir nts for dose limitation of 10 CFR Part 20, as addressed in Specific tons 3.11.1.1 and 3.11.2.1. An individual is not consider d a MEMBER OF (E PUBLIC during any period in which he/she is engaged ' carrying ou, any operation that is part of the nuclear fuel cycl : D m Cn H
-H DH +
p. c 1 , W C l CALVERT CLIFFS - UNIT 1 B 3/4 11-6 Amendment No. 169 i
4 3/4.12 liADIOLMICAL ENVIRONMENTAL MONITORING
% /
3/4. .I' MONITORING PROGRAM { The rad logical environmental monitoring program required by this specifica ton provider representative measurements of radiation and f ! radioactiv materials in those exposure pathways and for those-radionuclid that lead to the highest potential radiation expos s to ' MEMBERS OF Tl PUBLIC resulting from the plant operation. This nitoring i-program impi ts 10 CFR Part 50, Appendix I, Section IV.B.2 d thereby supplements the diological effluent monitoring program by v ifying that ; the measurable co entrations of radioactive materials and " vels of radiation are not her than expected on the basis of theAffluent ; measurements and the deling of the environmental expostre pathways. y,
" Guidance for this mon oring program is provided by the ,adiological Assessment Branch Tech cal Position on Environmental changes may be initiate ased on operational-experi ce.
nitoring. Program
< The required detection capa 111 ties for environmen I sample analyses are tabulated required byin Tableterms of the 4.12-1 arelo r limits of detecti n (LLDs). The LLDs sidered optimum or routine environmental measurements in industrial labo tories. It s uld be recognized that the LLD is defined as an a priori (b ore the fa limit representing the capability of a measurement system nd not an a Dosteriori (after the CC w
fact) limit for a particular measur nt. m -. Detailed discussion of the LLD and oth detection Ifmits can be found in y- HASL Procedures Manual, HASL-300 (rev annually), Currie, L. A., " Limits for Qualitative Detection and Quanti tiv Detemination - Application to
% Radiochemistry," Anal . Chem. 40, 5 -93 (1 ' ), and Hartwell, J.K.,
" Detection Limits for Radioanalyt' al Count: I,'
Techniques " Atlantic g Richfield Hanford Company Report (RH-SA-215 ne 1975). 3/4.12.2 LAND USE CENSUS [ s This specification is prov ed to ensure that chan s in the use of areas at and beyond the SITE B the radiological enviro ntal DARY are identified and t t modifications to 4 s monitoring program are ade if required by T.J the results survey, fromof this c sus. The best information from he door-to-door aerial > rvey or from consuiting with local gricuiturai m authorities shall b used. This census satisfies the req rements of 10 CFR Part 50 Appe ix I, Section IV.B.3. Restricting the nsus to gardens i_ of greater than m 2 provides assurance that significant ex sure pathways via leafy vege les will be identified and monitored since a arden of this size is " e minimum required to produce the quantity (26 / year) of leafy veget es assumed in Regulatory Guide 1.109 for consumpti child. To etermine by a this minimum garden size, the CALVERT CLIFFS - UNIT 1 B 3/4 12-1 Amendment No. 169 i
l
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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l kES foll ing assumptions were made: 1) 20% of the garden was used for broad af vegetation (i.e., similar to lettuce and cabbage), and 2)growi a i vegetat n yield of 2 kg/m". 3/4.12.3 TERLABORATORY COMPARISON PROGRAM The requireme for participation in an approved Interlaboratory mparison Program is pro ded to ensure that independent checks on the pr ision and accuracy of the asurements of radioactive material in enviro ntal sample matrices a perfonned as part of the quality assuran program for environmental mont ring in order to demonstrate that the r uits are valid for the purposes of CFR Part 50, Appendix I, Section IV .2. C m VD M 1 ll , W 1 C i l CALVERT CLIFFS - UNIT I B 3/4 12-2 Amendment No. 169 i
ATTACHMENT (2) UNIT 2 TECIINICAL SPECIFICATIONS REVISED PAGES 1 1-6 3/43 3/43-50 3/4 11 3/4 11-19 3/4 12 3/4 12-15 l i 6 6-22 6-31 B3/4 3-3 B3/411 B3/411-5 J B3/412-1 l B3/412-2 i
I 1.0 DEFINITIONS FREQUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance l Requirements shall correspond to the intervals defined in Table 1.2. GASE0US RADWASTE TREATMENT SYSTEM 1.16 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and l installed to reduce radioactive gaseous effluents by collecting Primary Coolant System offgases from the Primary System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. IDENTIFIED LEAKAGE 1.17 IDENTIFIED LEAKAGE shall be: l
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c. Reactor Coolant System leakage through a steam generator to the Secondary System.
MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l occupationally associated with the plant. This category does not include i employees of the utility, its contractors or vendors. Also excluded from j this category are persons who enter the site to service equipment or to i make deliveries. ! O SI D0 CAL LAT MA AL CM)
. Th 0FF TE EC CU ON NUA shal con in e cu ent l m hodo ogy dp amet su d in he 1cul ion fo site dose du to adio tive ase sa lig d ef uen ,i the alcu atio of seo a l liqu eff uent oni ring larrr trip etp nts and n th con et ft eny onm tal adio gic mon ori pro am. l REPUCE klITN INSEW "1.19l
CALVERT CLIFFS - UNIT 2 1-4 Amendment No. 163
INSERT "1.19" OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.19 'Ihe OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid emuents, in the calculation of gaseous and liquid emuent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain the radioactive emuent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Emuent Release Reports required by Specifications 6.9.1.7 [6.6.2] and 6.9.1.8 [6.6.3]. I
1.0 DEFINITIONS 1 OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or l have OPERABILITY when it is capable of performing its specified l function (s). Implicit in this definition shall be the assumption that all ! necessary attendant itstrumentation, controls, nomal and emergency i electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of perfonning their related support function (s). OPERATIONAL MODE 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combination l of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1. PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the l fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission. 1 PRESSURE BOUNDARY LEAKAGE _ 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator l tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall. ROCEdCONT/0LPR[ GRAM CP) 1.2 The ROCE CONT OL PR RAM all ontai the tren form a, l sa pling anal es, sts, d de ermin tion to be ade o en re th t the 4 p ocess- g an pack ing o soli radi acti was s ba d on emon rate l rocese ng o actu or s' ula >d we soli wast wil be a compi hed such way ., t o sure ompi nce th 1 CFR drt 2 , 10 FR P t 71 nd Fede 1 an Stat and 1 cal gula ons overn' g t dis sal the rad' acti was . I DELETE CALVERT CLIFFS - UNIT 2 1-5 Amendment No. 163
1.0 DEFINITIONS PURGE - PURGING 1.25 PUREL or PURGING is the controlled process of discharging air or gas l from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate l to the reactor coolant of 2700 Kdt. REACTOR TRIP SYSTEM RESPONSE TIME 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism. REPORTABLE EVENT 1.28 A REPORTABLE EVENT shall be any of those conditions specified in l Section 50.73 to 10 CFR Part 50. i SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shal! Se the instantaneous amount of reactivity by I which the reactor is subcritical or would be subcritical from its present condition essuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE B0UNDARY 1.30 The SITE B0UNDARY shall be that line beyond which the land is l neither owned, nor leased, nor otherwise controlled by the licensee. I S0t [DIFI dTIO /
.31 OLID ICAT N all et co ers no we was s to fo t t l meet shi ing d be ial rou re ire nts DEL ETE CALVERT CLIFFS - UNIT 2 1-6 Amendment No. 16
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4.3 INSTRUMENTATION l 3/4. 3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorina Instrumentation LIMITING C DITION FOR OPERATION 3.3.3.9 The dioactive gaseous effluent monitoring instrum tation channels shown n Table 3.3-12 shall be OPERABLE with their lam / trip setpoints set to nsure that the limits of Specification 3 1.2.1 are not exceeded. The al / trip setpoints of these channels sh I be determined and adjusted in act rdance with the methodology and par eters in the ODCH. I 4N APPLICABILITY: As sho n in Table 3.312. ACTION:
- a. With a radioactiv gaseous effluent rr nitoring instrumentation channel alam/ trip etpoint less co ervative than required by the above Specificat n, without ay suspend the release of H radioactive gaseous e luents mo tored by the affected channel, or declare the channel 'noperab e, or change the setpoint so it bb is acceptably conservati .
hd r b. Vith less than the minimum umber of radioactive gaseous effluent H monitoring instrumentatio c nnels OPERABLE, take the ACTION shown in Table 3.3-12. xert est efforts to return the instruments to OPERABL status ithin 30 days and, if "T' unsuccessful, explai in the nex Semiannual Radioactive Effluent A Release Report why e inoperabili was not corrected in a timely manner. H
- c. The provisions f Specifications 3.0.3 nd 3.0.4 are not
{s w applicable, l SURVEILLANCE REQ REMENTS O 4.3.3.9 Eac radioactive gaseous effluent monitoring instr . entation be demonstrated OPERABLE by perfomance of the - channel sha ANNEL CHECK, SOURCE CH , CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST erations at '
.the freq ncies shown in Table 4.3-11.
CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 176 l
DELETE THIS PAGE . g TABLE 3.3-12 f R G ^ g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 5d b MINIMUM CHANNELS q I UMENT OPERABLE APPLICABILITY CTION E m x
. 1. WASTE GAS HOLDUP SYST g c- >
5*
- a. Noble Gas Activity Moni r - Providing 1 35 ;"!
Alarm and Automatic Termin ion of E Release
- b. Effluent System Flow Rate Measurin 1
- 36 Device
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor 1 *
.37 Y
O b. Iodine Sampler
- 38
- c. Particulate Sampler 1
- 38 M
a E cn ____m_- -._ m __ - _ _ _ _ - _ _ _ _ _ .
1 I 4.3 INSTRUMENTATION / TABLE 3.3-12 (Continued) - l l TABLE NOTATION At al times. 1 ACTION STATEMENTS i I (gN ACTION 35 - With t a mmber of channels CPERABLE les than required by the Min um Channels OPERABLE requireme the tank may be released to the en ronment:
, the contents of j
- a. Using t main vent monitor as backup and recording RMS I readings very 15 minutes dur g the release, or
- b. Provided th prior to ini ating the release, at least two independe t samples o the tank's contents are H analyzed, and least o technically qualified members
' H of the Facility taff rate calculations n two qualified operators verify the dependently verify the release discharge valve li p. Otherwise, suspend r eas of radioactive effluents via this pathway. n m 1 n ACTION 36 - With the number channels 0 RABLE less than required by the Minimum Ch nels OPERABLE r quirement, effluent releases y via this path y may continue pr ided the flow rate is estimated a least once per 4 hou . n s 14 ACTION 37 - With the umber of channels OPERABLE ess than required by the Min .um Channels OPERABLE requirem nt, effluent releases via t s pathway may continue provided ther (1) grab l M samp s are taken and analyzed for gross ctivity at least onc per 24 hours, or (2) an equivalent mo itor is provided. ACTION 38 - th the number of channels OPERABLE less tha required by O the Minimum Channels OPERABLE requirement, eff ent releases w via the affected pathway may continue provided mples are continuously collected as required in Table 4.11- with auxiliary sampling equipment. 4 CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 176 l
DELETE THIS PAGE : g TABLE 4.3-11 h DI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 'w C mu E q CHANNEL SOURCE CHANNEL h H $
- CHANNEL FUNCTIONAL 5 EILLANCE g INSTRUM CHECK CHECK CALIBRATION TEST REQUIRED c
i'i
- 1. WASTE GAS HOLDUP SYSTEM y
- a. Noble Gas Activity Monitor P P R)I3 SAIll Providing Alann and Automatic Tennination of Release
- b. Effluent System Flow Rate D NA R NA m Measuring Device D 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor D M R)I3 SAI2)
- b. Iodine Sampler NA NA NA
- c. Particulate Sampler W NA NA NA a
M a .EF e,
I l ~ '
/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued) ,
TABLE NOTATION At al times other *% when the line is valved out and eked.
-w 1 (1) The CH L FUhtW'1, ..$T shall also demonstrate th automatic isolation f this pahay and/or Control Room alarm nunciation occurs if e appropriate following condition (s) e sts:
- 1. Instrumen indicates measure levels above th alarm / trip g 4N e
setpoint.
- 2. Circuit failu .
- 3. Instrument indic es a downscale fail re.
(2) The CHANNEL FUNCTIONAL ST shall also emonstrate that Control Room alann annunciation occurs if any of e following conditions exist: H H 1. Instrument indicates me ured evels above the alarm setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a d nse le failure.
(3)
-3 The initial CHANNEL CALIB TION shal be performed using one or more 1
of the reference standar s traceable the National Bureau of Standards or using sta ards that have een obtained from suppliers that participate in asurement assuranc activities with NBS. These
, standards shall pe t calibrating the sy em within its intended -5 range of energy an measurement range. For ubsequent CHANNEL 1 3 CALIBRATION, sour es that have been related calibration can e used.
the initial H -5 (4) The CHANNEL ECK shall consist of verifying ind ation of flow during peri ds of release and shall be made at lea t once per 24 1 hours on ys on which effluent releases are made. O CALVERT CLIFFS - UNIT 2 3/4 3-45 Amendment No. 176 l
- /4.3 INSTRUMENTATION 3 3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorino Instrumentation -
LIMITING NDITION FOR OPERATION 3.3.3.10 Th radioactive liquid effluent monitoring instrum ntation channels shown in Table 3.3-13 shall be OPERABLE with thei alam/ trip setpoints set t ensure that the limits of Specification .11.1.1 are not exceeded. The a m/ trip setpoints of these channels s 11 be detemined and adjusted in ac rdance with the methodology and pa meters in the ad( OFFSITE DOSE CALCU ION MANUAL (ODCM). <H APPLICABILITY: At all imes. ACTION:
- a. With a radioactive liquid effluent onitoring instrumentation channel alam/ trip tpoint less onservative than required by H the above Specificat n, withou delay suspend the release of radioactive liquid ef uents m nitored by the affected channel, H or declare the channel oper ble, or change the setpoint so it is acceptably conservati .
H
- b. With less than the minim . mber of radioactive liquid effluent monitoring instrumentat on ch nne?s OPERABLE, take the ACTION shown in Table 3.3-13 Exert st efforts to return the "r' instruments to OPE E status thin 30 days and, if L unsuccessful, exp1 n in the next emiannual Radioactive Effluent r Release Report wh the inoperabili was not corrected in a H timely manner.
T c. The provisio of Specifications 3.0.3 nd 3.0.4 are not
- applicable.
3 1 -s SURVEILLANCE R UIREMENTS _ 4.3.3.10 ch radioactive liquid effluent monitoring instru. ntation channel s 11 be demonstrated OPERABLE by perfomance of the NEL CHECK, SOURCE C CK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST o rations at the fr uencies shown in Table 4.3-12. l CALVERT CLIFFS - UNIT 2 3/4 3-46 Amendment No. 176 l
/4.3 INSTRUMENTATION
/
TABLE 3.3-13 , RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM - 5 CHANNELS 1 INSTRUMENT OPERABLE ACTION
- 1. GROSS RADI CTIVITY MONITORS PROVIDING ALARM AND AU MATIC TERMINATION OF RELEASE M
- a. Liquid Radwa e Effluent Line 1 28
- b. Steam Generator lowdown Effluent 1 29 Line
[ 2. FLOW RATE MEASUREMENT D CES H a. Liquid Radwaste Effluen Line 1 30 H b. eam Generator Blowdown f1 ent 1 30 + r 3 b, s m a CALVERT CLIFFS - UNIT 2 3/4 3-47 Amendment No. 176 l
4.3 INSTRUMENTATION
/
TABLE 3.3-13(Continued) . ACTION STATEMENTS l , 3 ACTION 28 - With the number of channels OPERABLE less than r utred by the Minimum Channels OPERABLE requirement, effl ent releases ] y continue provided that prior to initiatin a release:
- a. t least two independent samples are a lyzed in cordance with Specification 4.11.1. 1, and M
IN b. At Faci ast two technically qualified embers of the ty Staff independently veri y the release rate calcu tions and two qualified erators verify the dischar valve line up. ACTION 29 - With the numbe of channels OP BLE less than required by the Minimum Cha els OPERABLE equirement, effluent releases via this pathway ay contin provided grab samples are H analyzed for gross adioac vity (beta or gama) at the bd lower limit of dete ion efined in Table 4.11-1: hd r a. At least once per hours when the specific activity of H the secondary co a is greater than 0.01 microcurie / gram OSE UIVALENT I-131. "T' b. At least onc per 48 hou s when the specific activity of & the second y coolant is ss than or equal to 0.01 p microcuri gram DOSE EQUIY ENT I-131. ACTION 30 - With the n .ber of channels OPERA E less than required by "T the Minirr . Channels OPERABLE requi ement, effluent releases via thi pathway may continue provid the flow rate is 5 estima ed at least once per 4 hours e ing actual releases. Pump erfonnance curves may be used to timate flow. H ,. 3 a m CALVERT CLJffS - UNIT 2 3/4 3-48 Amendment No. 176 l
DELETE THIS PAGE
~
g TABLE 4.3-12 , r- a h DI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 'W CHANNEL SOURCE CHANNEL 0NAL q INSTRUMENT CHECK CHECK CALIBRATION TEST g I 1. GROSS RADI0ACTIVIT NITORS PROVIDING ALARM g g AND AUTOMATIC TERMINA 0F RELEASE g
- a. Liquid Radwaste Effluen ine D P R) I2 SAIII E
- b. Steam Generator Blowdown Effl t Line D P R) I2 SAII)
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line NA R NA
{
- b. Steam Generator Blowdown Effluent Line (3) NA R NA e
h 1 - E cn
4.3 INSTRUMENTATION TABLE 4.3-12 (Continued) , TABLE NOTATION (1) The C NEL FUNCTIONAL TEST shall also demonstrate that tomatic , s isolati of this pathway and/or Control Room alann an nciation 1 occur if he appropriate following condition (s) exist
- 1. Instrum t indicates measured levels above the larm/ trip setpoint.
I 4N 2. Circuit fai re.
- 3. Instrument in cates a downscale failur .
(2) The initial CHANNEL LIBRATION shall be erfonned using one or more of the reference stant ds traceable t the National Bureau of Standards or using stan rds that hav been obtained from suppliers that participate in meas ement ass ance activities with NBS. These H standards shall pennit cal rating he system within its intended b range of energy and measure nt r ge. For subsequent CHANNEL HH CALIBRATION, sources that hav en related to the initial r calibration can be used. M - (3) CHANNEL CHECK shall consist f ve ifying indication of flow during periods of release. CHAN, CHECK hall be made at least once per 24 hours on days on whic effluent r leases are made. M
- 1 s
s b s m CALVERT CLIFFS - UNIT 2 3/4 3-50 Amendment No. 176 l l
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.1 LIOUID EFFLUENTS Concentration LIMITING ONDITION FOR OPERATION '
n m 3.11.1.1 Th concentration of radioactive material release in liquid 1 effluents to RESTRICTED AREAS shall be limited to the co centrations specified in 1 CFR Part 20, Appendix B, Table II, Colum 2 for radionuclides at r than dissolved or entrained noble es. 4 APPLICABILITY: At a times. ACTION:
- a. With the concent ation of radioacti e material released in liquid effluents to UNRE RICTED AREAS e eeding the above limits, without delay rest e the concen ration to within the above H limits.
- b. The provisions of Spec 1 ica ons 3.0.3 and 3.0.4 are not applicable.
-H SURVEILLANCE REQUIREMENTS e y 4.11.1.1.1 Radioactive 1 uid wastes shall sampled and analyzed . according to the sampli and analysis progra. of Table 4.11-1. 5 14 4.11.1.1.2 The resul s of the radioactivity ana ses shall be used in accordance with the ethodology and parameters in he ODCH to assure that the concentrations at the point of release are main ined within the limits M e 8 of Specification .11.1.1. m
)
CALVERT CLIFFS - UNIT 2 3/4 11-1 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS I TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEAS' SAMPLING ANALYSIS TYPE OF ACTIV (LLD)* TYPE FREQUENCY FREQUENCY ANALYSIS (pci/al) A. Batch Waste P P Principal [ama 5x10-7 (M Releases b E h Batch Each Batch Emitters */ 4 I-131/ 1x10 Mo- k Ce-144 2x10-' P H H/ 1x10-s d Each Batch \ Composite /ross Alpha 1x10-7 Each Batch si Sr-89,Sr-90 5x10 4 B. Turbine M Principal Gama 5x10-7 ) Emitters' H Building Sump I-131 1x10-' Ho-99, Ce-144 2x10-' e M s, m J CALVERT CLIFFS - UNIT 2 3/4 11-2 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION I s a The L is defined, for purposes of these specificatio , as the I 1 smalle concentration of radioactive material in a s ple that will yield a et count, above system background, that wi be detected { with 95% robability with only 5% probability of f sely concluding i that a bla observation represents a "real" sig 1. ) g My For a particu r measurement system, which ma include radiochemical separation: 1 l 4.66s, LLD = ( t) E V 2. 2 x 10' Y exp (- Where: LLD is the "a priori" ower mit of detection as defined above, j )==H as microcuries per uni ma or volume, i s, is the standard devia n of the background counting rate or of the counting rate o a ank sample as appropriate, as counts per minute, 5 counts per disintegration, 1 1 E is the counting ficiency, V is the sample ize in units of ss or vcilume, l S 2.22 x 10' i the number of disinteg tions per minute per { 1 microcurie 1 Y is th fractional radiochen.; cal yield, hen applicable. l "T' 2 is he radioactive decay constant for the articular A rad nuclide, and O is the elapsed time between sample collectio or end of the an====. sample collection period, and time of counting. Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a pri i (before the fact) limit representing the capability of a mea rement system and not as an a posteriori (after the fact) Ifmit for a particular measurement. j 1 i CALVERT CLIFFS - UNIT 2 3/4 11-3 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued) TABLE NOTATION 3 b Prior o sampling Reactor Coolant Waste and Miscellaneo s Waste for 1 analyse , each batch shall be isolated, and then thor ghly mixed to assure r resentative sampling. c The princip 1 gama emitters for which the LLD sp ification applies exclusively e the following radionuclides: M '54, Fe-59, Co-58, <gq Co-60, Zn-65, s-134, Cs-137 and Ce-141. This ist does not mean that only these uclides are to be considere Other gama peaks l that are identif ble, together with those the above nuclides, shall also be ana zed and reported in th emiannual Radioactive Effluent Release Re ort pursuant to Spec ication 6.9.1.8. d A composite sample is ne in which th quantity of liquid sampled is proportional to the qua tity of liqu waste discharged in which the H method of sampling emplo d result in a specimen that is representative of the liq 'ds rel sed. H H r M b s m J CALVERT CLIFFS - UNIT 2 3/4 11-4 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.1 LIOUID EFFLUENTS Dose LIMITING NDITION FOR OPERATION 3.11.1.2 Th dose or dose comitment to a MEMBER OF THE PUI from radioactive ma erials in liquid effluents released to UNRE 'RICTED AREAS l shall be limite -
- a. During a calendar quarter to less than or qual to 3.0 mrems to g ody and to less than or equal t 10 mrems to any l gq the total organ, and i
- b. During any ca ndar year to less than r equal to 6 mrems to the total body and o less than or equal o 20 mrems to any organ.
APPLICABILITY: At all times. H Hy ACTION: HH
- a. With the calculated dose f om the release of radioactive materials in liquid effl ts exceeding any of the above limits, prepare and submit to t e mmission within 30 days, pursuant to Specification 6.9.2, Speci 1 Report that identifies the s cause(s) for exceedi the li t(s) and defines the corrective actions that have en taken to reduce the releases and the 1 proposed correcti actions to b taken to assure that subsequent releases will b in compliance wi the above limits.
l l s b. The provisio of Specifications 3.0. and 3.0.4 are not 1 s applicable. l
-s d SURVEILLANCE UIREMENTS 4.11.1.2 nthly cumulative dose contributions from liqui effluents for
= = = the curr t calendar quarter and the current calendar year all be determi d in accordance with the methodology and parameters 'n the ODCH at lea:t ce per 60 days.
\
/
CALVERT CLIFFS - UNIT 2 3/4 11-5 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.1 LIOUID EFFLUENTS Licuid Radwaste Treatment System LIMITING NDITION FOR OPERATION ' s 1 3.11.1.3 Th Liquid Radwaste Treatment System shall be use to reduce,the radioactive'ma erials in liquid wastes prior to their disc rge when the calculated dose due to the liquid effluent to UNRESTRIC AREAS exceeds 0.36 mrem to the otal body or 1.20 mrem to any organ i a 92 day period. i A APPLICABILITY: At a times. f ACTION:
- a. With radioactive liquid waste bein discharged without treatment and in excess of e above limits prepare and submit to the l
l Comission within days pursu t to Specification 6.9.2 a l H Special Report that cludes t _ following information: bd 1. Explanation of why iqu radwaste was being discharged hd without treatment, i e ification of any inoperable equipment or subsyst , and the reason for the inoperability,
- 3 2. Action (s) taken restor the inoperable equipment to OPERABLE statu , and 1
- 3. Summary des iption of action ) taken to prevent a recurrence
-3 s of Specifications 3.0. and 3.0.4 are not 1 3
- b. The provisi applicabl
{ M
- s
)
j SURVEILLANCE EQUIREMENTS D - l 9 4.11.1.3 onthly doses due to liquid releases to UNRESTRIC D AREAS shall be calc ated at least once per 60 days in accordance with t methodology and p ameters in the ODCH.
/
CALVERT CLIFFS - UNIT 2 3/4 11-6 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS Dose Rate LIMITING NDITION FOR OPERATION '
3 in gaseous 1 3.11.2.1 Th dose rate due to radioactive materials releas effluents from the site to areas at and beyond the SITE B0 DARY (see Fig"
- 5.1-1) s 11 be limited to the following:
- e. For nobl gases: Less than or equal to 500 rems /yr to the total j body and ss than or equal to 3000 mrems/ to the skin, and
- b. For iodine-1 and for all radionuclide in particulate fom with half lives gr ter than 8 days: Less an or equal to 1500 mrems/yr to an organ.
APPLICABILITY: At all times. H H ACTION: H
- a. With the dose rate (s) ex restore the release rate ing the above limits, without delay within the above limit (s).
M
- b. The provisions of Spec'ficat ns 3.0.3 and 3.0.4 are not
,". 3 applicable. 1 c SURVEILLANCE REQUIREMENT
- s 14 4.11.2.1.1 The dose te due to noble gases in seous effluents shall be detemined to be wi in the above limits in accor ce with the methodology and parameters in e ODCH.
"T 4.11.2.1.2 The ose rate due to iodine-131 and all ra ionuclides in
&-a particulate f . with half lives greater than 8 days in aseous effluents g shall be det ined to be within the above limits in acco dance with the methodology and parameters in the ODCM by obtaining repres tative samples
- and perfo ing analyses in accordance with the sampling and nalysis program pecified in Table 4.11-2. J CALVERT CLIFFS - UNIT 2 3/4 11-7 Amendment No. 149
DELETE THIS PAGE . g TABLE 4.11-2 , RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM h A LOWER 4 11 0F Q PLING HINIMUM ANALYSIS DET ON (LLD)* y
. GASEOUS RELEASE TYPE FR ENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pC1/ml) Q a t r ge
- Tank Each Tan Each Tank h1 9 n 1x10-*
Grab Sample m B. Containment Purge P P b 5 and Vent Each Batch
- E Batch" 1x10-4 Grab Sample a ns n C. Main Vent M ,, Principa ama Emitters h g-4 Grab Sample
- r. (Gase Emissions Only)
{ Continuous a M V 1x10* g Continuous d Charcoal Samp I- 1x10-'8 b Ipa tters Continuous d Part ate y 0the 1x10-" mple M Continuous d Gross Alpha 1x10-l' Pfr e Sample k Q d ontinuous Sr-89, Sr-90 1x10-" Pf0 r e E. Sample Noble Gas Noble Gases 2 Continuous d 1x10
.o Monitor Gross Beta or Gama
- D. Inci ated Oiln P i
P 5x10-' O Each Batch Each Batch' Principal Gama Emitters
i
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-2 (Continued)
TABLE NOTATION
-5 a The L is defined, for purposes of these specificatio , as the
( 1 smalle concentration of radioactive material in a s ple that will ! yield a t count, above system background, that wil be detected with 95% obability with only 5% probability of fi sely concluding that a bla observation represents a "real" sign . For a particu r measurement system, which may nelude radiochemical q separation: 1 4.66s, LLD = EV7.. x 10' Y exp (- t) Where: H LLD is the "a priori" ower 1 it of detection as defined above, Hy as microcuries per unit as or volume, bd" s, is the standard deviat of the background counting rate or M of the counting rate of b nk sample as appropriate, as counts per minute, w E is the counting ficiency, a counts per disintegration, 1 V is the sample ize in units of m s or volume, w 2.22 x 10' is he number of disintegr ions per minute per 1 ' microcurie, Y is the ractional radiochemical yield, en applica'ble, M 5 A is e radioactive decay constant for the articular 1 radi uclide, and ; O A for )lant effluents is the elapsed time betw n sample on or end of the sample collection period, and time of
- 11ect<
counting. Typical values of E, V, Y, and At should be used in t calculation. It should be recognized that the LLD is defined as an a prior (before the fact) limit representing the capability of a measur ment system and not as an a posteriori (after the fact) limit for a I a particular measurement. CALVERT CLIFFS - UNIT 2 3/4 11-9 Amendment No. 149 j
4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-2 (Continued) TABLE NOTATION 3 b The p "ncipal gamma emitters for which the LLD specific ion applies 1 exclust 'ely are the following radionuclides: Kr-87, -88, Xe -133, Xe-133m, e-135, and Xe-138 tor gaseous emissions an Mn-54, Fe-59, Co-58, Co 0, Zn-65 Mo-99, Cs-134, Cs-137, Ce-141 nd Ce-144 for particulat emissions. This list does not mean t t only these nuclides are to be considered. Other gama pea that are identifiable, ogether with those of the above uclides, shall also q be analyzed an reported in the Semiannual R ioactive Effluent j Release Report p suant to Specification 6. 1.8. { C Sampling and analy s shall also be perf ed following shutdown, STARTUP, or a THERMA POWER change exc ding 15 percent of RATED THERMAL POWER within e hour unless ) analysis shows that the DOSE EQUIVALENT I-131 concen ration in th primary coolant has not i' H increased more than a fa or of 5, nd (2) the noble gas activity HH monitor shows that efflue activ' y has not increased by more than a factor of 5. hd r d The ratio of the sample flow te to the sampled stream flow rate l ' shall be known for the time e 'od covered by each dose or dose rate
" calculation made in accor nce w h Specifications 3.11.2.1, 3.11.2.2
-3 and 3.11.2.3. I 8 Samples shall be chan d at least on per 7 days and analyses shall be completed within hours after ch ging, or after removal from sampl er. When sam e collection time i less than seven days, the w corresponding LLD may be increased by a reportional factor. This 1 , requirement doe not apply if (1) analysis shows that the DOSE EQUIVALENT I-1 concentration in the prima coolant has not increased mor than a factor of 5, and (2) t noble gas monitor H shows that fluent activity has not increase . ore than a factor of -5 5 f Waste s Decay Tank samples shall be collected an analyzed for O oxyge once per week on the in-service tank and fol wing tank iso tion. Waste Gas Surge Tank samples shall be co ected and an yzed daily during power escalation from HODE 6 thr gh MODE 3,
,d once per week at all other times.
9 Collect sample and analyze daily for total Curie content p Specification 3.11.2.6 when the Reactor Coolant System spec ic activity of Xe-133 is greater than 150 pCi/ml.
}
CALVERT CLIFFS - UNIT 2 3/4 11-10 Amendment No. 149 j
4.11 RADIOACTIVE EFFLUENTS TABLE 4.11-2 (Continued) TABLE NOTATION
'" Incin ated oil may be discharged via points other tha he main vent 15 (e.g., uxiliary Boiler). Releases shall be accounte for based on pre-rele e grab sample data, i Samples fo incinerated oil releases shall be col cted from and representati of filtered oil in liquid fonn,
<g N r/2 H H M H r $ w M 1 m I s l l CALVERT CLIFFS - UNIT 2 3/4 11-11 Amendment No. 149 !
l l 4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASE0US EFFLUENTS j Dose - Noble Gases LIMITING NDITION FOR OPERATION ' - w 1 3.11.2.2 Th air dose due to noble gases released in gaseo effluents to areas at and b and the SITE B0UNDARY (see Figure 5.1-1) s 11 be limited to the followin -
- a. During a calendar quarter: Less than or ual to 10 mrads for g mrads for beta gq gamma rad tion and less than or equal to radiation a d,
- b. During any ca ndar year: Less than o equal to 20 mrads for gamma radiation and less than or eque to 40 mrads for beta radiation.
APPLICABILITY: At all times. H Hy ACTION: hd a. With the calculated air from radioactive noble gases in gaseous effluents exceedi any of the above limits, prepare and submit to the Comissio wi in 30 days, pursuant to Specification 6.9.2, a the peci Re "3 cause(s) for exceedi li 't(port that identifies thes) and defines the actions that have b en taken to educe the releases and the 1 proposed correcti actions to bt. taken to assure that subsequent releases will be in compliance wit the above limits. ? w b. The provision of Specifications 3.0, and 3.0.4 are not 1 3 applicable. Mw 1 SURVEILLANCE R VIREMENTS 4.11.2.2 nthly cumulative dose contributions for the cu rent calendar - quarter a current calendar year for noble gases shall be tennined in accorda e with the methodology and parameters in the ODCM a least once per 60 ays.
}
CALVERT CLIFFS - UNIT 2 3/4 11-12 Amendment No. 149
i 1 4.11 RADI0 ACTIVE EFFLUENTS l 3/ 11.2 GASEOUS EFFLUENTS Dose - Iodine-131 and Radionuclides in Particulate Fo LIMITING NDITION FOR OPERATION .
-w 1 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-13 and all radionuclides particulate form with half lives greater an 8 days in gaseous effluen released to areas at and beyond the SIT BOUNDARY (see Figure 5.1-1) sha 1 be limited to the following:
- a. During an calendar quarter: Less than or qual to 15 mrems to q any organ a d,
- b. During any ca ;idar year: Less than o equal to 30 mrems to any organ.
- c. Less than 0.1% of he limits of 3.1.2.3(a) and (b) as a result of burning contamin ted 011.
hd APPLICABILITY: At all times. bd ACTION:
- a. With the calculated do e fro the release of iodine-131 and
," 3 radionuclides in par culate rm with half lives greater than 8 days, in gaseous ef uents exce ing any of the above limits, 1 prepare and submi to the Comiss on within 30 days, pursuant to Specification 6. 2, a Special Rep t that identifies the cause(s) for e eeding the limit an defines the corrective w actions that ye been taken to reduc the releases and the proposed cor ective actions to be take to assure that subsequent 1 ,
releases w' 1 be in compliance with the bove limits.
.0.4 are not H 5
- b. The pro sions of Specifications 3.0.3 and applic le.
e SURYEIL CE REQUIREMENTS 4.11. 3 Monthly cumulative dose contributions for the current lendar quar er and current calendar year for iodine-131 and radionuclide in pa iculate form with half lives greater than 8 days shall be dete ined in cordance with the methodology and parameters in the ODCH at least ce er 60 days. s 1 CALVERT CLIFFS - UNIT 2 3/4 11-13 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING NDITION FOR OPERATION , f w 1 3.11.2.4 Th GASEOUS RADWASTE TREATNENT SYSTEM and the VEN LATION EXHAUST TREATNENT SYS shall be used to reduce radioactive mater als in gaseous waste prior to eir discharge when the gaseous effluent ir doses due to gaseous effluent eleases, to areas at and beyond the 5 E B0UNDARY (see <jq Figure 5.1-1) exce s 1.20 mrad for gamma radiation a 2.4 mrad for beta radiation in a 92 d period. The VENTILATION EXHAU TREATMENT SYSTEM shall be used to redu e radioactive materials in g eous waste prior to their discharge when t calculated doses due to seous effluent releases, to areas at and beyond e SITE BOUNDARY (see Fi ure 5.1-1) exceeds 1.8 mrem to any organ in 92 day period. APPLICABILITY: At all time H ACTION: bd a. With gaseous waste bein di harged without treatment and in hd excess of the above limi within 30 days, pursuant prepare and submit to the Commission Specification 6.9.2, a Special Report that includes the follo ng infomation: -s 1. Explanation of w gaseous radwaste was being discharged 1 without treatm t, identifi tion of any inoperable equipment or bsystems, and he reason for the inoperabili , s 2. Action (s) taken to restore the i perable equipment to 1 OPERABL status, and
- 3. Sum y description of action (s) take to prevent a Ms e
rec rence. 1 b. The ovisions of Specifications 3.0.3 and 3. ap icable. 4 are not m SURVE LAMCE REQUIREMENTS .
- 4. .2.4 Monthly doses due to gaseous releases shall be calculate at ast 01ce per 60 days in accordance with the methodology and parame ers in he ODCM.
J CALVERT CLIFFS - UNIT 2 3/4 11-14 Amendment No. 149
)
3/4.11 RADI0 ACTIVE EFFLUENTS Jg,ff, f GASEOUS EFFLUENTS C,/ Explosive Gas Mixture (Hydrogen rich systems not desi withstand a hydrogen explosion)gned to i LIMITING CONDITION FOR OPERATION gjf j j [./M The concentration of oxygen in the Waste Gas Holdup System shall [ bed1mited to less than or equal to 4% by volume. APPLICABILITY: At all times. ACTION:
- a. With the concentration of oxygen in a waste gas decay tank greater than 4% by volume imediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS R rm be th ab 1 Rouce wa Insar "1.11.1.1 '
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1 CALVERT CLIFFS - UNIT 2 3/4 11-15 Amendment No. 149 l
l INSERT "4.11.1.1" 4.11.1.1 The concentration of oxygen in the Waste Gas lioldup System shall be determined to be within the above limit by collecting and analyzing a sample from the Waste Gas Decay Tank once per wwk on the in-senice tank and following tank isolation. Waste Gas Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other l times. l l 1 l l l l l
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ll 3/',.11 RADI0 ACTIVE EFFLUENTS 3/4.11[ GASEOUS EFFLUENTS j_ - Gas Storace Tanks LIMITING CON 0ITION FOR OPERATION [2 ' 3.11 shall
.6 The quantity of radioactivity contained in each gas storage tank limited to less than or equal to 58,500 curies noble gases (consideredasXe-133).
APPLICABILITY: At all times. ACTION:
- a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, imediately suspend all additions of radioactive material to that tank and within 48 hours reduce the tank contents to within the limit.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS L2-4.1Ih The quantity of radioactive material contained in the in-service gas storage tank shall be detemined to be within the above limit at least once per 24 hours when the Reactor Coolant System specific activity of Xe-133 is greater than 150 pCi/ml. CALVERT CLIFFS - UNIT 2 3/4 11-16 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.3 SOLID RADIOACTIVE WASTE LIMITI CONDITION FOR OPERATION 3.11.3 T solid radwaste program shall be used in accordance ith a r 3 PROCESS C0 R0L PROGRAM to process wet radioactive wastes to eet shipping 1 and burial g und requirements.
APPLICABILITY: t all times. ACTION:
- a. With the p visions of the PROCESS CONTR PROGRAM not satisfied, suspend ship ents of defectively proces d or defectively packaged soli radioactive wastes fro the site.
- b. The provision o Specifications 3.0 and 3.0.4 are not applicable.
H H SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROG s 11 be used to verify the SOLIDIFICATION of at least one presen ative test specimen from at least r 5 every tenth batch of each typ of wet ra ioactive waste (e.g., filter 1 r sludges, spent resins, evapo tor bottoms, boric acid solutions, and sodium sulfate solutions). H
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- N CALVERT CLIFFS t.IT 2 3/4 11-17 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS 3 .11.4 TOTAL DOSE LIMIT G CONDITION FOR OPERATION -
3.11.4 T annual (calendar year) dose or dose comitment to ny MEMBER OF -' THE PUBLIC ue to releases of radioactivity and to radiation rom uranium 1 fuel cycle s urces shall be limited to less than or equal 25 mrems to the total bod or any organ, except the thyroid, which sh I be limited to less than or e al to 75 mrems. APPLICABILITY: A all times. <gq ACTION:
- a. With the cal lated doses from the r ease of radioactive materials in 1
- quid or gaseous effl nts exceeding twice the limits of Speci ication 3.11.1.2. 3.11.1.2.b, 3.11.2.2.a.
3.11.2.2.b, 3.11. 3.a. or 3.11. 3.b, calculations shall be made [ including direct r diation cont ibutions from the reactor units H and outside storage anks to tennine whether the above limits of Specification 3.1 4 have een exceeded. If such is the case, H prepare and submit to he mission within 30 days, pursuant to Specification 6.9.2, a cial Report that defines the corrective action to be taken to r ce subsequent releases to prevent recurrence of exceedin th above limits and includes the . schedule for achievi conf ance with the above limits. This -w Special Report, as fined i 10 CFR 20.405c, shall include an analysis that est .ates the ra iation exposure (dose) to a HEMBER 1 , OF THE PUBLIC fr uranium fuel ycle sources, including all y effluent pathw s and direct radi tion, for the calendar year that includes he release (s) cover by this report. It shall 5 also descri levels of radiation a concentrations of 1 3 radioactiv material involved, and th cause of the exposure levels or concentrations. If the esti, ted dose (s) exceeds the ; above 1 its, and if the release conditi n resulting in violation i M' of 40 R Part 190 has not already been c rected, the Special Repo shall include a request for a varia e in accordance with l i 1 th provisions of 40 CFR Part 190. Submitta of the report is c sidered a timely request, and a variance i granted until O taff action on the request is complete. b The provisions of Specifications 3.0.3 and 3.0.4 e not applicable.
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1 l CALVERT CLIFFS - UNIT 2 3/4 11-18 Amendment No. 149
l 1 4.11 RADI0 ACTIVE EFFLUENTS SU EILLANCE REQUIREMENTS . 4.11.4 Cumulative dose contributions from liquid and gaseous eff ents shall b deternined in accordance with Specifications 4.11.1.2, 4. .2.2, and 4.11. 3, and in accordance with the methodology and paramet s in the ODCH.
-m 1 4.11.4.2 Cu lative dose contributions from direct radiatio from the reactor units d outside storage tanks shall be detennine in accordance with the method ogy and parameters in the ODCM. This re frement is applicable only u der conditions set forth in Specifica on 3.11.4.a.
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CALVERT CLIFFS - UNIT 2 3/4 11-19 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/ 12.1 MONITORING PROGRAM l LIMITI CONDITION FOR OPERATION . 3.12.1 Th radiological environmental monitoring program shall e 5 conducted a specified in Table 3.12-1, 1 APPLICABILITY: At~ all times. ACTION: l M a. With the diological environmental monitor ng program not being I q conducted a specified in Table 3.12-1, p pare and submit to the Comission, the Annual Radiological vironmental Operating Report requir by Specification 6.9.1 , a description of the reasons for not conducting the progr as required and the plans for preventing a ecurrence,
- b. With the level of dioactivity the result of plant effluents H in an environmental mple at specified location exceeding the Hy reporting levels of T le 3.1 2, prepare and submit to the Comission within 30 da s af er receiving the sample analysis, HH pursuant to Specificatio .9.2, a Special Report that identifies the cause(s) for exceedin the limit (s) and defines the M corrective actions to b ta en,to reduce radioactive effluents so that the potential ann 1 do to a MEMBER OF THE PUBLIC is
-3 less than the calend year 1 its of Specifications 3.11.1.2, 3.11.2.2, and 3.11. 3. When m e than one of the radionuclides 1 in Table 3.12-2 ar detected in e sample this report shall be submitted if: ? 3 conce ration (1) + concen ation (2) + ..> 1.0 ~
repor ing level (1) reporting level (2) 1' When radi nuclides other than those in T le 3.12-2 are detected and are he result of plant effluents. report shall be H r 5 submit ed if the potential annual dose,thi to MEMBER OF THE PUBLIC 1 is e al to or greater than the calendar yea limits of Spe ifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is O n required if the measured level of radioactis ty was not the esult of plant effluents; however, in such an ev nt, the condition shall be reported and described in the A ual Radiological Environmental Operating Report. l l l l
/ The methodology and parameters used to estimate the potential ann 1 dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
CALVERT CLIFFS - UNIT 2 3/4 12-1 Amendment No. 149 __- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ ~
4.12 RADIOLOGICAL ENVIR)NMENTAL MONITORING LI TING CONDITION FOR OPE'1ATION (Continued) . With fresh leafy vegetable samples unavailable from one more of the sample locations required by Table 3.12-1, ident y locations for obtaining replacement samples and add tt to the diological environmental monitoring program within 0 days.
- 5 T specific locations from which samples were unav lable may th be deleted from the monitoring program. Pur ant to Spec fication 6.9.1.7, identify the cause of the navailability of s les and identify the new location (s) fo obtaining the replac ent samples in the next Annual Radiol ical Environmental
<j q d. Operatin Report. The provisi ns of Specifications 3.0.3 a 3.0.4 are not applicable. uD SURVEILLANCE REQUIREMENTS bd 4.12.1 The radiological environ ntal .onitoring samples shall be pq collected pursuant to Table 3.12- fr m the specific locacions given in the r table and figure (s) in the ODCH, an shall be analyzed pursuant to the e etection capabilities required by H requirements of Table 3.12-1 and Table 4.12-1.
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,f CALVERT CLIFFS - UNIT 2 3/4 12-2 Amendment No. 149
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c TABLE 3.12-1 . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P E A EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND QUENCY ~
? AND/OR SAMPLE PLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF LYSIS S
, R
- 1. DIRECT RADIATION b 23 rout e monitoring stations At least Quarterly. Ga dose at least -
E (DR1-DR23 ither with two or arterly. 9
% more dosimet or with one ~ instrument for suring and E recording dose rat continuously. $
placed as follows: o E an inner ring of stati . E one in each meteorologica > t' sector in the general area
- the SITE BOUNDARY (DR1-DR9); !
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4, an outer ring of statio , one in each meteorol cal 5 sector in the 6- -km E range from the te (DR10-DR18); the r ning stations (DR19-g DR2 to be placed in special s a erest areas such as 's ' y population centers, nearby a residences, schools, and in Po 1 area to serve as a control g station. Z e
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/ ,O._ TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM N P SAMPLING AND TYPE AND 5 9 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE QUENCY ~
? AND/0R SAMPLE MPLES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF LYSIS g
- 2. AIRBORNE O
[ 2 9 Z Radiotodine and Samples fr . 5 locations Continuous sampler Radioiodine Canister N Particulates (Al-AS): operation with samp I-131 analysis weekly. @ collection week 1 or - 3 samples (Al- from more frequent if Particulate Sampler: close to the 3 5 required b ust Gross beta x BOUNDARY locations, loading radioactivity analysis @ different sectors of t following filter > t' highest calculated change *; dGama isotopic
" annual average ground- analysis of composite l M level D/Q. (by location) q 1, quarterly. o 1 sample (A4) fr the y vicinity of a munity a having the ghest calcula annual aver ground-level D/ .
i7 g 1 sample (A5) from a g control location, as for g example 15-30 km distant r and in the least g prevalent wind
- direction.
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DELETE THIS PAGE TABLE 3.12-1 (Continued) y p N k RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P SAMPLING AND TYPE AND b M EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE QUENCY Q AND/0R SAMPLE S LES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF LYSIS g [ 3. WATERBORNE k> z " Z a. Surface 1 sample at take area (Wal) Composite sample over 1- ama isotopic analysis d N 1 sample at dis arge area month period'. monthly. Composite for 3 (Wa2) tritium analysis y quarterly. g x
- b. Sediment from 1 sample from downstream a a Semiannual . Gama isotopic analysis d $
shoreline with existing or potential semiannually. > g recreational value (Wb1). E b R if a R E. ?. W
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DELETE THIS PAGE h TABLE 3.12-1 (Continued)
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2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P E M EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND ENCY O AND/OR SAMPLE S ES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF YSIS g
- 4. INGESTION O
[ m 9
% a. Fish and 3 samples of mercially Sample in season, or ma isgtopic [
N Invertebrates and/or recreati lly semiannually if they analysis on edible g important species fish are not seasonal. portions. g species and 1 inverte ate o species) in vicinity of ant E discharge area (Ial-Ia3). $ t' 3 samples of same species in
- areas not influenced by plant 5 g discharge (Ia4-Ia6). $
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- b. Food Products Samples of 3 differer.t nds Monthly dur growing Gama isotopied and $
of broad leaf vegeta on grown season. I-131 analysis, a near the SITE BOU RY at 2 different lo ions of highest pre ~ ted annual average undlevel D/Q p (Ibl- . g Monthly during growing Gama topicdand g sample of each of the season. I-131 ana sis. m similar broad leaf vegetation A grown 15-30 km distant in the z least prevalent wind direction - (Ib7-Ib9). W
4.12 RADIOLOGICAL ENVIRONNENTAL MONITORING . TABLE 3.12-1 (Continued) l l I TABLE NOTATION a The de in parenthesis, e.g., DR1, A1, defines generic ample "r' locat ns in this specification that can be used to id tify the 4m== specif locations in the map (s) and table in the CD . Specific saramete of distance and direction sector from th central point
)etween t two containment buildings and addition description where perti ent, is provided for each sample loc ion in Table 3.12-1, and in a table and figure (s) in t ODCM. Refer to (dN huREG-0133, " eparation of Radiological Effl nt Technical Specifications r Nuclear Power Plants, Oct er 1978", and to Radiological Ass sment Branch Technical P ition, Revision 1 November 1979. D iations are pennitted om the required sampling schedule if specime are unobtainable e to circumstances such as hazardous conditions, seasonal unavail 111ty, and malfunction of automatic sampling eq ment. If sp imens are unobtainable due to sampling equipment mal ction, eff t shall be made to complete corrective action prior the en of the next sampling period. All M deviations from the sampli sch ule shall be documented in the Annual Radiological Environ nt Operating Report pursuant to Specification 6.9.1.7. It i ecognized that, at times, it may not y be possible or practicable t antinue to obtain samples of the media m of choice at the most desir d 1 ation or time. In these instances suitable alternative medi and 1 ations may be chosen for the - 5 particular pathway in q stion an ppropriate substitutions made 1
within 30 days in the diological vironmental monitoring program. Pursuant to Specific ion 6.9.1.7, i ntify the cause of the unavailability of s ples for that pat ay and identify the new H
. location (s) for o aining samples in th next Annual Radiological "r*l-.
Environmental Op ating Report and also i clude in the report a revised figure and table for the ODCH r lecting the new
< location (s).
Mwr m i I 4 l 1 CALVERT CLIFFS - UNIT 2 3/4 12-7 Amendment No. 149 l
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4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3.12-1 (Continued) TABLE NOTATION b One more instruments, such as a pressurized ion chamb , for r 3 measu ng and recording dose rate continuously may be ed in place 1 of, or addition to, integrating dosimeters. For t. purposes of this tab , a thermoluminescent dosimeter (TLD) is c sidered to be one phosp r; two or more )hosphors in a packet ar considered as two or more dos eters. Film aadges shall not be use as dosimeters for measuring di et radiation. The frequency of a ysis or readout for TLD Systems w 1 depend upon the characteristi of the specific q system used and hould be selected to obtain ptimum dose infonnation with minimal fad g. Due to the geographic limitations, 9 sectors are monitored arou d the Calvert Cliffs Nu ear Power Plant. C Airborne particulate ample filters sha be analyzed for gross beta radioactivity 24 hours or more after mpling to allow for radon and thoron daughter decay. f gross bet activity in air particulate H samples is greater than t n times e yearly mean of control samples, gama isotopic analysis sh 1 be rfomed on the individual samples. Hy HH d Gamma isotopic analysis means of gama-enitting radionucli e identification and quantification that may be attributable to the effluents from the facility -3 A composite sample is on in which he quantity (aliquot) of liquid sampled is proportional o the quant'ty of flowing liquid and in 1 which the method of s >pling employed esults in a specimen that is representative of th liquid flow. In his program, composite sample aliquots shall be lected at time inte vals that are very short -5 (e.g., hourly) re tive to the compositin period (e.g., monthly) in 1 w order to assure taining a representative ampl e. M -3 , m l l CALVERT CLIFFS - UNIT 2 3/4 12-8 Amendment No. 149
e DELETE THIS PAGE - g TABLE 3.12-2 , h RE TING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES h N REPORTING LEVELS c 5 4 o r-m WATER AIR NE PARTICULATE FISH & INVERTEBRATES MILK 0 PRODUCTS E y i (pC1/1) S (pC1/m') (pC1/kg, wet) (pC1/l) (pC1/kg, wet) g ANALYSIS OR U H-3 20,000' / [ m := Mn-54 1,000 30,000 $ o Fe-59 400 10,000 l Co-58 1,000 30,00 Co-60 300 , 00 l
~ m a Zn-65 300 20,000 g Zr-Nb-95 400 E
I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 E 2,000 70 2,000 g Cs-137 50 20 , & 300 Ba-La-140 200 g g# For drinki water samples. This is a 40 CFR Part 141 value. If no drinking water pathway ex s, i a value 30,000 pCi/l may be used. b i \ l _ _ _ ._...__ _ _______.__. i __ _
DELETE THIS PAGE g TABLE 4.12-1 , DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS'b h LOWER LIMIT OF DETECTION (LLD)' { E a E
" 5
' FISH & INVERTEBRATES MILK F000 PR S SEDIMENT WATER AIRBORNE P ICULATE E ANALYSIS (pC1/1) OR GASES ( m') (pC1/kg, wet) (pci/1) (pCi , wet) (pC1/kg. dry) 9
[ Gross Beta 4 0.01 g H-3 2,000' @ Mn-54 15 130 "i I y Fe-59 30 2 N
- 3
=
g Co-58,60 15 13 E Zn-65 30 260 $
=
Zr-Nb-95 15 d I-131 I 0.07 1 60 l Cs-134 15 0. 130 15 60 150 l E Cs-137 18 0.06 150 18 80 180 Ba-La-140 15
$ 15 f# If no dri ng water pathway exists, a value of 3000 pC1/1 may be used.
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4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 4.12-1 (Continued) TABLE NOTATION
- This ist does not mean that only these nuclides are to
-5 consi red. Other peaks that are identifiable, togethe' with those 1 of the ove nuclides, shall also be analyzed and repo :ed in the Annual R iological Environmental Operating Report p suant to Specificat on 6.9.1.7.
b Required det tion capabilities for thennolumine ent dosimeters used g { gq for environmen al measurements shall be in acc dance with the recomendations f Regulatory Guide 4.13. I c The LLD is define for purposes of these ecifications, as the smallest concentrat n of radioactive ma rial in a sample that will yield a net count, a ve system backgro d, that will be detected with 95% probability w th only 5% pro ility of falsely concluding l [ that a blank observatio represents "real" signal . ( 1
, which may include radiochemical H For a particular measureme t syst separation:
l H LLD = E V 2.22 - exp Mt)
- 3 1 Where:
detection as defined above, LLD is the "A pr' ri" lower limit as picocuries r unit mass or volu.. , e m 1y s* is the st dard deviation of the ba ground counting rate or of the cou ing rate of a blank sample a appropriate, as counts per minut , b S E is t e counting efficiency, as counts per isintegration, Vi the sample size in units of mass or volum
.22 is the number of disintegrations per minute r picocurie, Y is the fractional radiochemical yield, when applic ble, A is the radioactive decay constant for the particular .
radionuclide, and s CALVERT CLIFFS - UNIT 2 3/4 12-11 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING TABLE 4.12-1(Continued) TABLE NOTATION t for environmental samples is the ela ed time be een sample
-S c 11ection, or end of the sample collec ion period and time of 1 co ting.
Typic values of E, V, Y and At should be us in the calcul ion. It should be cognized that the LLD is define as an a priori N (before the fa ) limit representing the cap flity of a measurement system and not a an a posteriori (after t fact) limit for a particular measur ent. Analyses shall b performed in such a manner that the stated LL will be achieved u er routine conditions. Occasionally backgro d fluctuations, avoidable small sample sizes, the presence of inter ring nuclides or other uncontrollable In such cases, the circumstances may rend these LLDs nachievable. H contributing factors sha 1 be ide ified and described in the Annual H Radiological Environmenta Opera ng Report pursuant to Specification 6.9.1.7. d LLD for drinking water sampl If no drinking water pathway exists, the LLD of gama isotopic al is may be used. i s m l
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 2.2 LAND USE CENSUS LIMITIN s. CONDITION FOR OPERATION . 3.12.2 A nd use census shall be conducted and shall identif within a distance of km (5 miles) the location in each of the 9 mete ological 15 sectory of th nearest milk animal, the nearest residence a the nearest garden of grea er than 50 m (500 ft') producing broad lea vegetation. 2 (For elevated re ases as defined in Regulatory Guide 1.1 , Revision 1 July 1977, the la use census shall also identify with a distance of 5 km (3 miles) the ocations in each of the 9 meteorol ical sectors of all g gq milk animals and all ardens of greater than 50 m pr ducing broad leaf vegetation). APPLICABILITY: At all t es. ACTION:
- a. With a land use cen s identifyi a location (s) that yields a H calculated dose or do e commitm t greater than the values currently being calcul ed in pecification 4.11.2.3, identify H the new location (s) in en t Annual Radiological Environmental Operating Report, pursuan o Specification 6.9.1.7.
- b. With a land use census i ent'fying a location (s) that yields a calculated dose or dos comi .ent (via the same exposure
- 3 pathway) 20 percent eater th at a location from which samples are currently being btained in ccordance with Specification 1 3.12.1, add the ne location (s) t the radiological environmental monitoring progr within 30 days. Thesamplinglocation(s), excluding the c trol station locati , having the lowest - w calculated do or dose comitment(s), via the same exposure 1 3 pathway, may e deleted from this monit ring program after October 31 f the year in which this lan use census was conducted Pursuant to Specification 6.9. 7, identify the new H 5 locatio s) in the next Annual Radiological nvironmental Operat g Report and also include in the rep t a revised 1 figur (s) and table for the ODCH reflecting th new location (s). O c. Th provisions of Specifications 3.0.3 and 3.0.4 re not - plicable. Broad leaf vegetation sampling of at least three different ki ds of vegetation may be perfor:ned at the SITE BOUNDARY in each of tw different direction sectors with the highest predicted D/Qs in eu of the garden census. Specifications for broad leaf vegetation
, sampling in Table 3.12-1.4b shall be followed, including analysis '
control samples. CALVERT CLIFFS - UNIT 2 3/4 12-13 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING SUR ILLANCE REQUIREMENTS . 4.12.2 The land census shall be conducted during the growing seas at least on e per 12 months using that infonnation that will provide he best ' results, ch as by a door-to-door survey, aerial survey, or by onsulting local agri 1ture authorities. The results of the land use ce us shall be included in he Annual Radiological Environmental Operating port pursuant !
"T' l A to Specificat n 6.9.1.7.
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l l CALVERT CLIFFS - UNIT 2 3/4 12-14 Amendment No. 149 i
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/ 12.3 INTERLABORATORY COMPARISON PROGRAM LIMITI CONDITION FOR OPERATION 3.12.3 An yses shall be performed on all radioactive material , supplied ,3 as part of Interlaboratory Comparison Program that has been pproved by that correspond to samples required by Table .12-1. 1 the Comissio APPLICABILITY: t all times. ACTION: <MN a. With analys not being performed as requi ed above, report the corrective a ions taken to prevent a re trence to the Comission in he Annual Radiological E ironmental Operating Report pursuant o Specification 6.9. 7.
- b. The provisions of ecifications 3 .3 and 3.0.4 are not applicable.
H HH HH SURVEILLANCE REQUIREMENTS 4 4.12.3 The Interlaboratory Camp ison ogram shall be described in the - 3 ODCH. A sumary of the result obtained s part of the above required 1 r Interlaboratory Comparison Pr ram shall b included in the Annual Radiological Environmental 0 erating Report ursuant to Specification 6.9.1.7. - w r w m m l 4 CALVERT CLIFFS - UNIT 2 3/4 12-15 Amendment No. 149
_ i l 6.0 ADMINISTRATIVE CONTROLS operations and surveillance, inservice inspection, routine ' maintenance, special maintenance -(describe maintenance), waste ; processing, and refueling. The dose assignment to various duty. . functions may be estimates based on pocket dosimeter TLD, or 2 film badge measurements. Small exposures totalling less than 20% i of the individual total dose need not be accounted for. In the ', aggregate, at least 80% of the total whole body dose. received 1 from external sources shall be assigned to specific major work i functions. '
- b. The complete results of steam generator tube inservice inspections perfomed during the report period (reference Specification 4.4.5.5.b).
l
- c. Documentation of all failures and challenges to the pressurizer PORVs or safety valves. !
1 MONTHLY OPERATING REPORT [ 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Inspection , and Enforcement .U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, ATTN: Document Control Desk, with a copy to the Regional i Administrator and to the NRC Resident Inspector, no later than the 15th of ! each month following the calendar month covered by the report. l i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.7 Routine)(adiologi 1 Envi ntal perati Repor[ covert the ,
opera on of th(unit du ng the evious lendar year sh 1 be s itted pri to May of each ar. e Annual adiologi 1 Envir mental perati Repor shall clude summaries interpr ations, nd an a lysis trend of the sults the i radiolo cal envi nmental surveil nce ac vities or the port pe od, I inclu g a com rison w h preop ation studie , with eration 1 cont is as ap opriat and wi previ s envi nmental urveill ce : re ts, and n asses" nt of e obse ed imp ts of e plant peration i o the envi nment. 'he rep ts sha also i clude t result of land se i ensuses quired Specif ation .12.2. The An al Radi ogical viron tal Op ating orts s 1 inclu the resul of an sis of 1 rad ogical nviro ntal s les and f all env nmenta radiati measu nts en dur g the riod pu ant to th locatio speci ed in e Table nd Fig es in t ODCM, well a marize and tab ated r uits o these alyses d measur nts i thh bace wn Imar %.9.ffJ A single submittal may be made. CALVERT CLIFFS - UNIT 2 6-19 Amendment No. 149
.m, - , , . , . . . . . , , , - , , .m ,
.m, . - . , , , - , m., . , . .-,e*, +--.r m
INSERT "6.9.1.7" 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological emironmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCM and 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. 1 The Annual Radiological Emironmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figmes in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. I i I
6.0 ADMINISTRATIVE CONTROLS o o the abl n R folo cal sse smen Bra ch T hni al [Po[tio,Re sio vem r 19 . t eve th t s in ivid al u1 are et a le ri ust wi h th rep rt, e r port shal s it d no ng de lai ng t e r sons for ea si res ts. The iss gd a sh 1b su tte as on pos ible n supp emen ary ~ re rt. ,
. e r port sha als inc de ef lowi g: s ry eser pti of e N rad" logi al e iro nta mon' ori p ram at 1 ast wo 1 gib1 map 04 co 3rin all p1 g lo tio .; ke dt at le vin dis nce and - d ect ns f om t cen al int etw nt two con i tb 1di s;
[ er uit of 1 ro am, ense par cip ion nt quir by peci cat n3 2.3 dis ssi of 11 via ons In ria rat yC pari on k fr the amp 1 g se edul of ble .12 ;a di uss no all nal ses i whic the r uire by able .12 wa not chi abl . he nual adio' gic Env ron ntal per ing epo wi in ud the ide ific fon th caus of nava abi ty s les (if y),and ill de ribe he 1 att s us d fo the ep1 eme sa les Th4 re rt v 11 .
}s a o in ude yp an t ct nges in t sa le cat ons 11c cou {
pear n th mon ori pr ram. It 11 clu e a evis d f ure ) d i 3 table or t e 00 ref ect g th new oca on( . SE ANN L RA 0AC VE FLU T RE ASEAEPO
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it' .9.1 Ro tine adi cti Eff ent el se )or co rin th W operi ion f th uni duri g th pre ou 6 mc itis fo rat on al be N sub tte with 60 days tfter Janu y and uly of ach yea .*** T Ra oact e flue Re1 ase por s s 11 clu e a umm ry t b ant les fr ioac ve 1 quid and ase se lue ts ds id as rele ed f om e p1 ta outl' ed nR ula ory uid 1. . as ing Eva atin , a Rep tin Radi act ity n S' id ast a Re as of Ra oact ye teri si Liqu d a Ga eous ffl ent fr Li t- ter C oled ucl r Po er P nts, Re sio 1, une 974 wi da a s ar ze na art ly b sis llow ng e f nna of pen x the eof I r s at . A single submittal may be made for Calvert Cliffs, since the Radwaste Systems are comon to both units.
&li lgical EF/uedgeese Tef r/
In lieu of submission with theCSemi-Annual ReportiP, SrTSr" analyses results may be submitted in_ a sup)lementary' report within 120 days __ after/ January 1 and July 1 of eac1 yea @
%b8al ef 8e Radtoleylealf/ flued %'elea.se Neyor/-
CALVERT CLIFFS - UNIT 2 6-20 Amendment No. 149
INSERT "6.9.1.8" RADIOLOGICAL EFFLUENT RELEASE REPORT
- 6.9.1.8 The Radiological Efiluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. (i.e., time between submittal of the reports must be no longer than 12 months)." The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. 'Ihe material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1, Section IV.B.I.
Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous, and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:
- a. A description of the equipment, components and processes involved.
- b. Documentation of the fact that the change, including the safety analysis, was resiewed and found acceptable by the POSRC.
The report shall also include changes to the ODCM in accordance with Specification 6.17.2.c.
0 ADMINISTRATIVE CONTROLS The adioactive Effluent Release Report to be submitted within 60. day after anuary 1 of each year shall include an annual sumary of hour y meteor ogical data collected over the previous year. This annual umary may be e ther in the form of an hour-by-hour listing on magnetic ape of wind spee wind direction, atmospheric stability, and precipit ion (if measured), r in the fom of joint frequency distributions of ind speed, "T' wind direct n, and atmospheric stability . This same repor shall ==d=== include an as .ssment of the radiation doses due to the rad active liquid and gaseous ef uents released from the unit or station d ing the previous calendar year. he assessment of radiation doses shall perfomed in accordance with t methodology and parameters in the FSITE DOSE </ N CALCULATION MANUAL ODCM). The radioactive Efflu t Release Report to be subm ted 60 days after January 1 of each year hall also include an ass sment of radiation doses to the likely most expos d HEMBER OF THE PUBLIC rom reactor releases and other nearby uranium fuel ycle sources, inc1 ing doses from primary effluent pathways and dire radiation, for e previous calendar year to show confomance with 40 CF Part 190, Envi onmental Radiation Protection Standards for Nuclear Power 0 ration. A eptable methods for calculating the dose contribution from liq 'd and ga eous effluents are given in H Regulatory Guide 1.109, Rev.1, ctobe 1977, and NUREG-0133, " Preparation of Radiological Effluent Technica Sp cifications for Nuclear Power H - Plants." M w The Radioactive Effluent Release epo s shall include the following infomation for each class of s id was e (as defined by 10 CFR Part 61) shipped offsite during the re rt period. r a. Container volume H - b. Total curie q ntity (specify wheth detemined by measurement or estimate)
< c. Principal adionuclides (specify whethe detemined by measurerr nt or estimate),
Sourc of waste and processing employed (e. , dewatered spent "T' d. res , compacted dry waste, evaporator bottom ,
- e. lidification agent or absorbent (e.g., cement)
The Rad active Effluent Release Reports shall include a lis and descri ion of unplanned releases from the site to UNRESTRICT AREAS of radi ctive materials in gaseous and liquid effluents made duri the rep ting period.
* [ In lieu of submission with the first half year Radioactive Efflu Release Report, this summary of required meteorological data may Tt h
retained on site in a file that shall be provided to the NRC upon request. CALVERT CLIFFS - UNIT 2 6-21 Amendment No. 149
6.0 ADMINISTRATIVE CONTROLS N . % IThe adio ctive fflu tR ease eport/shal inc de a ch ges de ! g d ing e rep ting eri to e PR(CESS NTRO PROG ( P), nd t i N e OFF ITE D EC ULA" ON UAL DCM) as w 1 as a li ing f ne ocat ns f dos calc / atio s idef(.ifie by t e an al 1 du cen purs nt t Spec icatfon3. .2. / 6.9.1.9 CORE OPERATING LIMITS REPORT
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
2.2.1 3.1.1.1 3.1.1.2 3.1.1.4 3.1.3.1 3.1.3.6 3.2.1 3.2.2.1 3.2.3 3.2.5 3.9.1
- b. The analytical methods used to detemine the core operating limits shall be those previously reviewed and approved by the NRC; specifically, those described in the following documents:
(1) CENPD-199-P, Latest Approved Revision, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," , January 1986 l (2) CEN-124(B)-P, " Statistical Combination of Uncertainties l Methodology Part 1: C-E Calculated Local Power Density and l Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I ; and II," December 1979 j (3) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Themal Margin Analyses for Calvert Cliffs Units 1 and 2 " January 1980 (4) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 l 1 (5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods I for Calvert Cliffs Units 1 and 2," December 1981 CALVERT CLIFFS - UNIT 2 6-22 Amendment No. 163
6.0 ADMINISTRATIVE CONTROLS
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6.17 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The ODCM shall be approved by the Connission prior to implementation. , kl7.2 icens initiat chang to the, CM: TEplAcE a. 11 be s mitted the C ission i the S nnual adioact e Eff1t t Rele Report r the p iod in ich the gg change was e effec ve. Thi submitt shall ntain: ;
- 1. uffici t info tion to pport t ratio e for t
[A/ SEAT chan . Info tion su tted s Id cons t of a ckage of the pages the OD to be c nged wi each p e number "f,f 7, [ g a provid with a ange n er and/ change ate tog ith app priate a lyses o evaluat ns just ying th er f y - change ;
- 2. A erminat n that e chan will no reduce e accur y reliabi ty of e cale tions o setpoin determi ions;
. Doc ntatio f the f ct that e chang as be reviewe
, a found eptabl y the P RC.
- b. Sh 1 beco effect e upon r few by e POSR and appr al of e Plan eneral anager.
kl MAJORC[NGEST DI0ACT LIOU GASE0[AND S0ldWASTE TREAIXENT SYSXMS 6.18.1 icens initiat major anges the Ra active ste Sys s (lig d, gas s and s id) sha be re ted to e Conni on in e Se annual dioacti Efflue Relea Report r the p iod in ich th
- 2. ch g al in 5 ..
- a. A scripti ) of th equipme , compo ts and ocesse volved
. Docur ntatio f the f t that e change neludi the s ety an ysis w review and fou accept e by t POSRC ADD
.TNsenr 6.18" , CALVERT CLIFFS - UNIT 2 6-31 Amendment No. 163 l
INSERT "6.17.2" 6.17.2 Licensee initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- 1. Sumcient infomtation to support the change (s) together with the appropriate analyses or evaluations justifying the change (s),
- 2. A determination that the change (s) maintain the levels of radioactive emuent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of emuent, dose, or setpoint calculations;
- b. Shall become effective after review and acceptance by the POSRC and the approval of the Plant General Manager;
- c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Emuent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was .
implemented. I l
l INSERT "6.18" 6.18 BADIOACTIVE EFFLUENT CONTROLS PROGRAM This program conforms to 10 CFR 50.36a for the control of radioactive emuents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive emuents as low as reasonably achievable. h program shal' be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. h program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM.
- b. Limitations on the concentrations of radioactive material released in liquid emuents to UNRESTRICTED AP.EAS conforming to 10 CFR Part 20, Appendix B, Table 2, Column 2.
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous emuents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the i
ODCM. 1 l
- d. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF Tile PUBLIC from radioactive materials in liquid emuents released to UNRESTRICTED AREAS to be limited
- 1. During any calendar quarter: Less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ, and
- 2. During any calendar year: Less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.
i i _ _ __. _ _ _ _ _ _ _ _ ____________________._._______.______________.___._____________J
1 INSERT "6.18" (continued)
- e. Determination of cumulative and projected dose contributions from radioactive effluents -
for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. {
- f. Limitations on the functional capability and use of the Liquid Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem ;
to the total body or 1.20 mrem to any organ in a 92 day period.
- g. Limitations on the functional capability and use of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the crJculated doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period.
- h. Limitations on the functional capability and use of the Ventilation Exhaust Treatment f
System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED AREAS exceeds 1.8 mrem to any organ in a 92 day period.
- i. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
- 1. For noble gases: Less than or equal to 500 mrems/>T to the total body and less than or equal to 3000 mrems/yr to the skin, and
- 2. For iodine-131 and for all radionuclides in particulate form with halflives greater than 8 days: Less than or equal to 1500 mrems/>T to any organ.
INSERT "6.18" (continued)
- j. Limitations on the annual and quarterly air doses resulting from noble gases released in :
gaseous efiluents to areas beyond the SITE BOUNDARY, to be limited: [ 1, During any calendar quarter: Less than or equal to 10 mrads for gamma radiation l and less than or equal to 20 mrads for beta radiation, and !
- 2. During any calendar year: Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.
- k. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from i iodine-131 and all radionuclides in particulate form with half-lives greater than 8 days in gaseous efiluents released to areas beyond the SITE BOUNDARY, to be limited:
l
- 1. During any calendar quarter: Less than or equal to 15 mrems to any organ, and
- 2. During any calendar year: Less than or equal to 30 mrems to any organ.
i
- 3. Less than 0.1% of the limits of 6.18.k(l) and (2) as a result of burning i
contaminated oil. I
- 1. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources to be j e
limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, t which shall be limited to less than or equal to 75 mrems. : i t i I
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3/4.3 INSTRUMENTATION BASES ! In the event more than four sensors in a Reactor Vessel Level channel are
- inoperable, repairs may only be possible during an extended COLD SHUTDOWN.
This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved. If only ' one channel is inoperable. It should be restored to 0PERABLE status in accordance with the schedule outlined in a Special Report. If both channels are inoperable, the system shall be restored to OPERABLE status in the next refueling outage. l 3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected , areas is required to provide detection capability until the inoperable ! instrumentation is restored to OPERABILITY.
.3.3.9 Radioactive Gaseous Effluent Monitorina Instrumentation i The ra ctive gaseous effluent instrumentation is provided to mo or and control, a plicable, the releases of radiactive materials aseous 1- 5 effluents dur actual or potentidi releases of gaseous ef" ents. The r alann/ trip setpo 1 for these instruments shall be calc ';ed and adjusted H
u in accordance with '. methodology and parameters in that the alam/ trip wil ccur prior to exceeding ' e limits of 00CM to ensure ! -' Specification 3.11.2.1.a ba on average annu /Q. The OPERABILITY and use of this instrumentation is nsistent the requirements of 10 CFR - 3 Part 50, Appendix A, General Desi ri a 60, 63, and 64. i b r 3 3/4.3.3.10 Radioactive Licuid Ef ent itorino Instrumentation 1 The radioactive liquid eff nt instrumentation control, as applicable provided to monitor and O e releases of radioactiv terials in liquid effluents during ac or potential releases of liqu ffluents. The =====. alarm / trip setpo s for these instruments shall be calcu ed and adjusted in accordanc th the methodology and parameters in the 0D ensure that the / trip will occur prior to exceeding the limits of CFR Part
- 20. T PERABILITY and use of this instrumentation is consistent the rec ements of 10 CFR Part 50, Appendix A. General Design Criteria 60, p ff 64.
CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. 176 l
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3/4.11 RADI0 ACTIVE EFFLUENTS , VSES / 1 3 .11.1 LIOUID EFFLUENTS 3/4. .1.1 Concentration This sp ification is provided to ensure that the concentration f radioact e materials released in liquid waste effluents to U STRICTED I AREAS will e less than the concentration levels specified i ! 10 CFR Part 0, Appendix B. Table II, Column 2. This limi tion provides additional as rance that the levels of radioactive mater' is in bodies of water in UNRES ICTED AREA 5 will result in exposures wit in (1) the Section II.A des n objectives of 10 CFR Part 50, Appe fx I to a MEMBER OF THE PUBLIC and (2 the limits of 10 CFR 20.106(e) to e population. ; The required detecti capabilities for radioactiv materials in liquid waste samples are tab ated in tenns of the lower imits of detection (LLDs). Detailed discu ion of the LLD, and ot r detection limits can be h found in HASL Procedures anual, HASL-300, Cur Qualitative Detection and uantitative Dete e, L.A., " Limits for nation - Application to Radiochemistry," Anal . Chem. 40, 586-93 (19 ), and Hartwell, J.K.,
" Detection Limits for Radica lytical Cou ng Techniques," Atlantic Richfield Hanford Company Repo ARH-SA- 5 (June 1975).
g 3/4.11.1.2 Dose This specification is provided to i lement the requirements of 10 CFR I M Part 50, Appendix'I, Sections II. , I ..A and IV.A. The Limiting Condition for Operation implements the gui s se. forth in Appendix I, Section II.A. H ; The ACTION statements provide e requir operating flexibility and at the , l -s same time implement the guide set forth Appendix I, Section IV.A to j 1 assure that the releases of adioactive mat rial in liquid effluents to UNRESTRICTED AREAS will be ept "as low as i reasonably achievable." The N dose calculation methodo1 gy and parameters i the ODCH implement the I g requirements in Appendi I, Section III.A that i nformance with the guides of Appendix I be show y calculational proced'.,r based on models and data, such that the tual exposure of a MEK3ER 0 THE PUBLIC through N appropriate pathway is unlikely to be substantiall underestimated. The equations specifi in the ODCM for calculating the ses due to the actual -1 release rates of adioactive materials in liquid efflu ts are consistent with the metho logy provided in Regulatory Guide 1.109, " Calculation of Annual Doses Man from Routine Releases of Reactor Eff ents for the Purpose of aluation Compliance with 10 CFR Part 50, Appe ix I," Revision 1 October 1977 Regulatory Guide 1.113. "Estimati Aquatic Dispersio of Effluents from Accidental and Routine Reactor R eases for the Pur se of Implementing Appendix I," April 1977, and NUREG 133, "Prepa tion of Radiological Effluent Technical Specifications r Nuclear Power Plants." CALVERT CLIFFS - UNIT 2 B 3/4 11-1 Amendment No. 149
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l S 3/4.11 RADI0 ACTIVE EFFLUENTS ASES 3 .11.1.3 Licuid Radwaste Treatment System The r utretuent that the appropriate portions of this system be ed, when specif d, provides assurance that the releases of radioactive aterials in liquid e 'luents will be kept "as low as is reasonably achiev le". This specifica'. on implements the requirements of 10 CFR 50.36a, 10 CFR Part 0, Appendix A, General Design Criterion 60 an the design objective gi n in 10 CFR Part 50, Appendix I, Section II . The specified limits govern the use of appropriate portions of the iquid Radwaste Treatment Syste were specified as a suitable fraction f the dose design , objectives set f th in 10 CFR Part 50, Appendix I, ction II. A for liquid l ef fluents. The do limits apply to the combined e luent of the plant I 1*: (e.g., two units). l 3/4.11.2 GASEOUS EFFL NTS 3/4.11.2.1 Dose Rate i h This specification is provi to ensure at the dose at any time at and beyond the SITE B0UNDARY from aseous ef uents from all units on the site q will be within the annual dose imits 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits a t doses associated with the i q concentrations of 10 CFR Part 20, endix B. Table II, Column 1. These limits provide reasonable assuranc hat radioactive material discharged in N gaseous effluents will not resul in he exposure of a MEMBER DF THE PUBLIC
-H in an UNRESTRICTED AREA, exceed g the limits specified in Appendix B, Table II of 10 CFR 20.106(b). or MEMB S OF THE PUBLIC who may at times ,
be within the SITE B0UNDARY, he occupan of that MEMBER OF THE PUBLIC 1 will be sufficiently low t compensate for ny increase in the atmospheric l diffusion factor above th for the SITE 801 DARY. 1 [ s The required detection apabilities for radioa ive materials in gaseous waste samples are tab ated in terms of the lowe limits of detection (LLDs). Detailed d cussion of the LLO, and othe detection limits can be 4( 1 found in HASL Proc ures Manual, HASL-300, Currie, . A. , "Limi ts for Qualitative Dete ion and Quantitative Detennination Application to Radiochemistry, Anal . Chem. 40, 586-93 (1968), and H twell, J.K. ,
" Detection Li ts for Radioanalytical Counting Techniqu s," Atlantic Richfield Ha ord Company Report ARH-SA-215 (June 1975).
3/4.11.2. Dose - Noble Gases This s cification is provided to implement the requirements o 10 CFR , Part , Appendix I, Sections II.B. III.A and IV.A. The Limiti Condition for peration implements the guides set forth in Appendix I, Changed by NRC letter dated April 26, 1993 , l r J - CALVERT CLIFFS - UNIT 2 B 3/4 11-2 ,
1 3/4.11 RADI0 ACTIVE EFFLUENTS BASES S tion II.B. The ACTION statements provide the required operating fle bility and at the same time implement the guides set forth in Appe fx I, Section IV.A to assure that the releases of radioacti materi 1 in gaseous effluents to UNRESTRICTED AREAS will be kep as low as reasona y achievable." The Surveillance Requirements impleme- the requir ts in Appendix I, Section III.A that conformance wi ,1 the guides of Appendi I be shown by calculational procedures based on dels and data such that t actual exposure of a MEMBER OF THE PUBLIC th ugh appropriate pathways is u likely to be substantially underestimated. he dose calculation me odology and parameters established in t ODCM for calculating the oses due to the actual release rates f radioactive noble gases in gaseous fluents are consistent with the hodology provided in "T' Regulatory Guide 1. 09, " Calculation of Annual Dose to Man from Routine Releases of Reactor ffluents for the Purpose of aluating Compliance with 10 CFR Part 50, Appen x I," Revision 1, October 977 and Regulatory Guide 1.111 " Methods Estimating Atmospheri Transport and Dispersion
< of Gaseous Effluents in utine Releases from ight-Water-Cooled Reactors,"
Revision 1, July 1977, an UREG-0133 "Prepa tion of Radiological Effluent Technical Specifications fo Nuclear Power ants". The 00CM equations provided fo detenni ng the air doses at and beyond the Z SITE B0UNDARY are based upon th histo cal annual average atmospheric conditions. H 3/4.11.2.3 Dose - Iodine-131 and ionuclides in Particulate Fonn
-H This specification is provided imp 1 ent the requirements of 10 CFR Part 50, Appendix I, Sections .C. III. and IV.A. The Limiting Conditions for Operation are .he guides s forth in Appendix I, 1* Section II.C. The ACTION s tements provi the required operating Q
flexibility and at the sa - time implement t guides set forth in Appendix I, Section IV.A o assure that the r eases of radioactive [ s materials in gaseous e luents to UNRESTRICTED EAS will be kept "as low as is reasonably achi able." The ODCM calculat nal methods specified in g-s the Surveillance Re f rements implement the requir ents 1 Appendix I, Section III.A that onfonnance with the guides of A endix I be shown by
,,1,,, calculational prc edures based on models and data, s h that the actual exposure of a M BER OF THE PUBLIC through appropriate athways is unlikely to be substant' ally underestimated. The ODCM calculati al methodology and parameters f calculating the doses due to the actual re ase rates of the '
subjact mat ials are consistent with the methodology prov ed in Rcgulator Guide 1.109, " Calculation of Annual Doses to Man rom Routine Releases f Reactor Effluents for the Purpose of Evaluating C pliance with 10 CFR art 50, Appendix I," Revision 1, October 1977. Regulat y Guide .111 " Methods for Estimating Atmospheric Transport and ' persion
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CALVERT CLIFFS - UNIT 2 B 3/4 11-3 Amendment No. 149
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T 3/4.11 RADI0 ACTIVE EFFLUENTS BASES Gaseous Effluents in Routine Releases from Light-Water-cooled Reactor , Re ion 1, July 1977, and NUREG-0133, " Preparation of Radiological Efflu t Technical Specifications for Nuclear Power Plants". These equatio also provide for detemining the actual doses based up the ; historical nual average atmospheric conditions. The release ate ' specificatio for iodine-131 and radionuclides in particul form with half lives grea than 8 days are dependent upon the exi ng radionuclide , pathways to man, the areas at and beyond the SITE B DARY. The : r pathways that were e ined in the development of tt e calculations were: l H
- 1) individual inhalati radionuclides onto green of airborne radionuclide , 2) deposition of afy vegetation with bsequent consumption by 1
"T' man, 3) deposition onto gra areas where animals and meat producing i
=&- animals graze with consumption f the mil nd meat by man, and I w 4) deposition on the ground with bse nt exposure of man. ;
3/4.11.2.4 GASEOUS RADWASTE TREA N YSTEM The requirement that the app riate portio of these systems be used, g when specified, provides r sonable assurance at the releases of radioactive materials i gaseous effluents will kept "as low as is
- reasonably achievabl .
This specificat' i implements the requirements of 10 CF 0.36a, 10 CFR ' Part 50, App 'x A, General Design Criterion 60 and the ign objectives given in 1 FR Part 50, Appendix I, Section II.D. The spect ed limits governi the use of appropriate portions of the systems were s cified as a sui le fraction of the dose design objectives set forth in 10 R Par 50, Appendix I, Sections II.B and II.C for gaseous effluents. e se limits apply to the combined effluent of the plant (e.g. two unit
- 11. Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the
,o concentration of oxygen below its flammability limit provides assurance
#ENuM3E4 that the releases of radioactive materials will be controlled in confomance with the requirements of 10 CFR Part 50, Appendix A. General Design Criterion 60.
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> L. 2.
3/4.11.fh+) Gas Storace Tanks The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the quantity that provides assurance that in the event of an Changed by NRC letter dated April 26.1903 . l CALVERT CLIFFS - UNIT 2 B 3/4 11-4
3/4.11 RADI0 ACTIVE EFFLUENTS BASES uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER 0F THE PUBLIC at the nearest SITE B0UNDARY will not exceed 10 CFR Part 100 limits. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed accident guidelines. 4.11.3 SOLID RADIOACTIVE WASTE This ecification implements the requirements of 10 CFR 50.36(a) 10 CFR rt 50, Appendix A. General Design Criterion 60. The pr ss paramete are included in the PROCESS CONTROL PROGRAM. 3/4.11.4 TO DOSE 3 This specificatio is provided to meet the dose limit ons of
'*T 40 CFR Part 190 tha have been incorporated into 10 FR Part 20 by P
46 FR 18525. The spe fication requires the pre ation and submittal of a Special Report whenever e calculated doses f plant generated H radioactive effluents and f rect radiation e eed 25 mrems to the total
; 3 body or any organ, except t thyroid, whi shall be limited to less than or equal to 75 mrems. The Sp al Repor will describe a course of action that should result in the limita "on the annual dose to a MEMBER OF THE 5
PUBLIC to within the 40 CFR Part , imits. For the purposes of the H
,3 Special Report, it may be assume THE PUBLIC from other uranium h
1 cyc the dose commitment to the MEMBER OF sources is negligible. l If the dose to any MEMBER THE PUBLIC is timated to exceed the 8 requirements of 40 CFR P t 190, the Special variance (provided th elease conditions resu ng in violation of port with a request for a
""" 40 CFR Part 190 hav not already been corrected), n accordance with the provisions of 40 R Part 190.11 and 10 CFR Part 2 . 05c, is considered to be a timely re st and fulfills the requirements of CFR Part 190 until NRC staff ac on is completed. The variance only relat to the limits of 40 CFR Par 90, and does not apply in any way to the oth requirements for dos imitation of 10 CFR Part 20, as addressed in Speci ations 3.11.1.1 and 3.11.2.1. An individual is not co' idered a MEM OF THE PUBLIC during any period in which he/she is engage sin c rying out any operation that is part of the nuclear fuel cycle.'
l CALVERT CLIFFS - UNIT 2 8 3/4 11-5 Amendment No. 149
l
, 3/1.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ES 3/ 12.1 MONITORING PROGRAM The r iological environmental monitoring program required by thi specif ation provides representative measurements of radiation nd of radioac ve materials in those exposure pathways and for those radionuc1 es that lead to the highest potential radiation e osures to MEMBERS OF E PUBLIC resulting from the plant operation. is monitoring program impi nts 10 CFR Part 50, Appendix I, Section IV. 2 and thereby supplements t radiological effluent monitoring program y verifying that the neasurable oncentrations of radioactive materials d levels of !
radiation are no higher than expected on the basis of the effluent measurements and e modeling of the environmental e osure pathways. ! [ Guidance for this m itoring program is provided by he Radiological Assessment Branch Te s nical Position on Environme al Monitoring. Program changes may be initiaiad based on operational ex rience.
< The required detection c abilities for envir mental sample analyses are tabulated in tenns of the wer limits of d ection (LLDs). The LLDs required by Table 4.12-1 ar considered opr mum for routine environmental measurements in industrial la oratories. ;t should be recognized that the LLD is defined as an a priori efore t fact) limit representing the
@ capability of a measurement sys m and ot as an a posteriori (after the H.H fact) limit for a particular meas e nt. >d pq Detailed discussion of the LLD an o her detection limits can be found in HASL Procedures Manual, HASL-300 rey ed annually), Currie, L. A., " Limits
% for Qualitative Detection and C antita ve Detennination - Application to Radiochemistry," Anal . Chem. M, 586-93 968), and Hartwell, J.K.,
" Detection Limits for Radioa lytical Cou ing Techniques," Atlantic
[ , Richfield Hanford Company port ARH-SA-21 (June 1975). -H
- s 3/4.12.2 LAND USE CENS 1 s This specification i provided to ensure that ch ges in the use of areas p at and beyond the S E BOUNDARY are identified anc that modifications to
-' the radiological vironmental monitoring program a made if required by 1 the results of t s census. The best infonnation fr the door-to-door survey, from ae al survey or from consulting with loc 1 agricultural authorities s 11 be used. This census satisfies the r uirements of 10 CFR Part 50, ppendix I, Section IV.B.3. Restricting the census to gardens of greater an 50 m provides assurance that significant posure pathways 2 via leafy egetables will be identified and monitored since garden of this si is the minimum required to produce the quantity (2 g/ year) of leafy getables assumed in Regulatory Guide 1.109 for l . CALVERT CLIFFS - UNIT 2 B 3/4 12-1 Amendment No. 149 i
3/1.12 RADIOLOGICAL ENVIRONMENTAL MONITORING , con ption by a child. To detemine this minimum garden size, the fall ing assumptions were made: 1) 20% of the garden was used for rowing broad eaf vegetation (i.e., similar to lettuce and cabbage), and a vegetat n yield of 2 kg/m'. 3/4.12.3 TERLABORATORY COMPARISON PROGRAM The requir t for participation in an approved Interlabor ory Comparison Program is pro ided to ensure that independent checks on e precision and accuracy of the asurements of radioactive material in vironmental sample matrices e perfomed as part of the quality a urance program for environmental moni ring in order to demonstrate that he results are valid [ for the purposes of 0 CFR Part 50, Appendix I, Sec on IV.B.2. m oo H H M M 1 Y ' b , l H 1 C j . CALVERT CLIFFS - UNIT 2 B 3/4 12-2 Amendment No. 149 i
1 T ATTACHMENT (3) OFFSITE DOSE CONTROL MANUAL DRAFT Revision 2, Change 0
r.. 4
'l 7 t2 00 .a OFFSITE DOSE CALCULATION MANUAL Revision 2, Change 0 For The Baltimore Gas And Electric Company Calvert Cliffs Nuclear Power Plant PREPARED BY: DATE:
RETS Program Manager REVIEWED BY: DATE: General Supervisor - Chemistry REVIEWED BY: DATE: Director Environmental Programs, Corporate Affairs Group REVIEWED BY: DATE: General Supervisor - Technical Services, Fossil Energy Division REVIEWED BY; DATE: General Supervisor - Nuclear Plant Operations REVIEWED BY: ' DATE: > General Supervisor Electrical And Controls . t REVIEWED BY: DATE: General Supervisor - Radiation Safety . l i REVIEWED BY: DATE: " POSRC Meeting Number APPROVED BY: DATE: l Plant General Manager j m l
. > I t3 1
I Offsite Dose Calculation Manual Page 3 cf 298 Revision 2, Change 0 PART 1.0 : PURPOSE AND APPLICABILITY / SCOPE t 9 { r a n i [ I
y , g a 7 o O JY lid ) ; OFFSITE DOSE CALCULATION MANUAL Revision 2, Change 0 For The Baltirnore Gas And Electnc Company Calvert Cliffs Nuclear Power Plant i i PREPARED BY: DATE: RETS Program Manager REVIEWED BY: DATE: General Supervisor - Chemistry i REVIEWED BY: DATE: Director Environmental Programs, Corporate Affairs Group REVIEWED BY: DATE: General Supervisor Technical Services, Fossil Energy Division REVIEWED BY: DATE: General Supervisor Nuclear Plant Operations REVIEWED BY: DATE: General Supervisor - Electrical And Controls REVIEWED BY: DATE: General Supervisor Radiation Safety REVIEWED BY: DATE: POSRC Meeting Number APPROVED BY: DATE: Plant General Manager D s k J - x
Offsit) Dose Cciculation Minull P gs2 of 298 Revision 2, Change 0 TABLE OF CONTENTS Part 1.0 Purpose and Applicability / Scope Part 2.0 Definitions and Referent.es Part 3.0 / 4.0 - Controls and Surveillance Requirements Part 5.0 Calculational Methodologies
Offsite Dose C:lculation Manual Page 3 cf 298 Revision 2, Change 0 PART 1.0 PURPOSE AND APPLICABILITY / SCOPE f l t
Offsit] Dose Calculation Minu:1 Page 4 of 298 Revision 2, Change 0 1.0 PURPOSE A. The ODCM lists the radiological effluent controls established at Calvert Cliffs Nuclear Power Plant (CCNPP) for the purpose of ensuring the amount of radioactive materials released to the environment are as low as reasonably achievable. B. The ODCM defines parameters and methodologies for calculating doses and dose rates resulting from the release of radioactive materials in liquid and gaseous effluents. C. The ODCM defines parameters and methodologies for calculating alarm and trip setpoints for Technical Specification related radiation effluent monitoring systems. D. The ODCM defines and establishes controls for the Radiological Environmental Monitoring Program. 2.0 APPLICABILITY / SCOPE A. The information presented in this procedure is applicable to any division, department, section, or unit within the Baltimore Gas And Electric Company (BG&E) which is either wholly or partly responsible for performing any of the activities listed in the PURPOSES section of this procedure. Responsible organizations include, but are not limited to, the following:
- 1. BG&E, Nuclear Energy Division (NED), CCNPP Department (CCNPPD),
Chemistry Section
- 2. BG&E, Corporate Affairs Group, Environmental Programs Section
- 3. BG&E, Fossil Energy Division, Technical Services Section, Chemistry Unit
- 4. BG&E, NED, CCNPPD, Electrical and Controls (E&C) Section
- 5. BG&E, NED, CCNPPD, Operations Section 1 6. BG&E, NED, CCNPPD, Radiation Safety Section l
B. This procedure is applicable to the determination of alarm and trip setpoints for the following radioactive gaseous effluent monitoring instrumentation:
- 1. 0-RE-2191
- 2. 1/2-RE-5415
- 3. 1/2-RE-5416 C. This procedure is applicable to the determination of alarm and trip setpoints for the following radioactive liquid effluent monitoring instrumentation:
- 1. 0-RE-2201 j
- 2. 1/2-RE-4014
- 3. 1/2-RE-4095 l
Offsite Dose Citculation Minual Pag 15 of 298 Revision 2, Change 0 D. This procedure is applicable to the determination of the offsite doses and/or offsite dose rates due to the following:
- 1. Radioactive material in gaseous waste discharged from CCNPP !
- 2. Radioactive material in liquid waste discharged from CCNPP
- 3. Radioactive material contained in outside storage tanks at CCNPP E. This procedure is applicable to the determination of the radiological affects on the environment due to the presence of Calvert Cliffs Nuclear Power Plant.
F. The ODCM is based on Technical Specifications, BG&E's interpretation of industry standards, and recommendations made by Combustion Engineering.
- _ , _ _ m __..__. m .
_ . - . ~ . _ . . .. . . - . . .. Offsite Dose Calculation MCnual Page 6 of 298 Revision 2, Change 0 l PART 2.0 l DEFINITIONS AND REFERENCES t I I a I a I i e s s i I i 1
l i Offsite Dose Calculation Manual Page 7 of 298 i Revision 2, Change 0 l 1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Controls. l Definitions linked to Technical Specification are designated by TS and the Technical Specification definition number it is linked to, e g. TS-1.0. ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE REI FASE: Any unplanned or uncontrolled release of radioactive material from the site boundary. ACTION: That part of a control or specification which prescribes remedial measures required under designated conditions. TS-1.2 CHANNEL FUNCTIONAL TESI:
- a. A analog CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signalinto the channel as close to the primary sensor as practicable to verify operability including alarm and/or trip functions. TS-1.7.a
- b. A bistable CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signalinto the channel sensor to verify operability including alarm and/or trip functions. TS-1.7.b BAICH RELEASE:
A BATCH RELEASE is the discharge of liquid (or gaseous) waste of a discrete volume. (NUREG-0133, page 14) CHANNEL CALIBRATION: A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensor and alarm and/or trip functg.n . .snd shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. TS-1.5 CHANNEL CHECK: A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. TS-1.6 COMPOSITE SAMPLE: A COMPOSITE SAMPLE is a combination of individual samples obtained at interva!s that are very short (e.g., hourly) in relation to the compositing time interval (e.g., monthly) to assure obtaining a representative sample. The sample volume should be proportionate to the volume of fluid, either liquid or gas, flovving through the system. CONTINUOUS RELEASE: A CONTINUOUS release is the discharge of liquid (or gaseous) wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the CONTINUOUS release. (NUREG-0133, page 14) CONTINUOUS SAMPLING: CONTINUOUS SAMPLING is sampling such that an interruption to sampling is normally less than one hour in duration. Best efforts shall be employed to retum the subject sampling equipment to service.
l l Offsite Dose C0lculation Manual Page 8 of 298 I Revision 2, Change 0 i DOMINANT RADIONUCLlDE: A DOMINANT RADIONUCLIDE is one whose activity is greater than 1% of the total activity found in a TYPICAL RELEASES of liquid or gaseous radwaste. DOSE EQUlVALENT LODINE-131: DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134, and 1-135 , actually present. The thyroid dose conversion factors used for this calculation shall be those listed in l Table til of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." TS 1.12 FREQUENCY NOTATION: The frequency notation specified for the performance of Surveillance Requirements shall correspond to l the intervals defined in the following Table TS-1.15. j Frecuency Notation Table TS-table 1.2 i l NOTATION FREQUENCY S At least once per 12 hours D At least once per 24 hours i W At least once per 7 days M At least once per 31 days ' Q Atleast once per 92 days SA At least once per 6 months R At least once per 18 months SIU Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling interval At least once per 24 months GAMMA ISOTOPIC ANALYSIS: A GAMMA ISOTOPIC ANALYSIS is a analytical method of measurement used for the identification and quantification of gamma-emitting radionuclides. GASEOUS RADWASTE TREATMENT SYSTEM: , A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. TS-1.16 LESS_ DOMINANT RADIONUCLIDE: l A LESS DOMINANT RADIONUCLIDE is one whose activity is less than 1% of the total activity found in TYPICAL RELEASES of liquid or gaseous radwaste.
Offsita Dose C:lculation Manual P;ge 9 of 298 Revision 2, Change 0 LOWER LIMIT OF DETECTION: The LLD, as defined by Technical Specifications, is the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. MEMBERS OF THE PUBLIC: MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries TS-1.18. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL: The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls (as specified by the Technical Specification section 6.5.5), (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specification 6.6.2 and 6.5.1. TS-1.19 OPERABILITY: A system, subsystem, train, component or device shall be operable or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subcomponent or device to perform its function (s) are also capable of performing their related support function (s). TS-1.20 OPERATIONAL MODE: An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in below. TS-1.21 Ooerational Modes TS-table 1.1
% RATED REACTIVITY THERMAL AVERAGE COOLANT MQDE CONDITION. Kg POWER
- TEMPERATURE POWER OPERATION 20.99 >5% 2300 *F STARTUP 20.99 55% 2300 *F HOT STANDBY <0.99 0 2300 *F HOT SHUTDOWN <0.99 0 300
- F > T ,, > 200
- F COLD SHUTDOWN <0.99 0 s200 *F REFUELING" 50.95 0 s140 *F Excluding decay heat.
Reactor vessel head unbolted or removed and fuelin the vesset. i
Offsite Dose Cclculation Manu 1 Pag)10 of 298 l Revision 2, Change O PROCESS CONTROL PROGRAM: PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal and State and Local regulations goveming the disposal of the radioactive waste. TS-1.24 PURGE OR PURGING: PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to punfy the confinement. RATED THERMAL POWER: Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt. TS-1.20 SIMULTANEOUS RELEASES: Simultaneous liquid releases are discharges of liquid radwaste which occur at the same time. Simultaneous gaseous releases are discharges of gaseous radwaste which occur at the same time. SITE BOUNDARY: The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. TS-1.30 (The SITE BOUNDARY is depicted on Attachment 18. " Environmental Monitoring Sites") SOURCE CHECK: A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. TS-1.32 ! THERMAL POWER: The THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. TS-1.34 TYPICAL RADWASTE RELEASES (OR TYPICAL RADWASTE EFFLUENTS): TYPICAL RADWASTE RELEASES are defined as (1) all releases conducted during any calendar quarter while either Unit 1 or Unit 2 is in mode 1, and also includes (2) all releases conducted during any calendar quarter following mode 1 operation of either Unit i or Unit 2. This definition of T(PICAL RADWASTE RELEASES is intended to ensure the concentrations of DOMINANT radionuclides represent realistic, maximum-expected values. This definition is also intended to ensure that the concentrations of DOMINANT radionuclides is not biased " low", as would be the case, if periods of extended outages-when the production of fission products is minimized-were included. This definition may be modified by the GSC, however, the new definition shall be documented in , accordance with the provisions outlined in the applicable section of the ODCM. (e.g., See the section which contains information related to documenting the fixed / adjustable setpoint.) UNRESTRICTED AREA: An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters of for industrial, commercial, institutional, and/or recreational purposes. TS-1.38
l Offsite Dose Calculation Manual PCge 11 of 298 Revision 2, Change 0 VENTILATION EXHAUST TREATMENT SYSTEM: A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or High Efficiency Particulate Air (HEPA) filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. TS-1.39 I VENTING: Ventir.g is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process. TS 1.40 WASTE GAS HOLDUP SYSTEM: See GASEOUS RADWASTE TREATMENT SYSTEM.
2.0 REFERENCES
A. Development References
- 1. NUREG-0133, " Preparation Of Radiological Effluent Technical Specification For Nuclear Power Plants", Boegli, J.3., R.R. Bellamy, W. L. Britz, and R. L.
Waterfield, (October 1978).
- 2. Regulatory Guide 1.109," Calculation Of Annual Doses To Man From Routine Release Of Reactor Effluents For The Purpose Of Compliance With 10 CFR Part 50, Appendix 1," Revision 1, (October 1977).
- 3. Regulatory Guide 1.111," Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors," Revision 1, (July 1977).
- 4. CCNPP System Description Number 148, " Reactor Coolant Waste Processing System Description."
- 5. Updated Final Safety Analysis Report, Chapter 11," Waste Processing And Radiation Protection."
- 6. CCNPP System Description Number 14D, " Miscellaneous Liquid Waste Processing System Description."
- 7. OI-17D, " Miscellaneous Waste Processing System"
- 8. OI-17C, " Reactor Coolant Waste Processing System"
- 9. Title 10 of the Code of Federal Regulations, Part 20
- 10. Title 10 of the Code of Federal Regulations, Part 50
- 11. Calvert Cliffs Nuclear Power Plant Semi-Annual Radiological Effluent Release Report (1986,1987,1988).
o Offsite Dose C:lculation Minuil Page 12 of 298 Revision 2, Change 0
- 12. Radioactive Decay Data Tables, David C. Kocher,1981. !
- 13. Radiological Health Handbook, Bureau of Radiological Health, Jan.1970,
- 14. TE-001, " Main Vent Stack Flow Measurement"
- 15. ETP-87-16, " Main Vent Stack Flow Measurement"
- 16. Verification And Validation Of The Gaseous Release Permit Portion Of The CCNPP EMS Computer Code, J. S. Bland And Associates, July 10,1990.
- 17. Land Use Survey in The Vicinity Of The Calvert Cliffs Nuclear Power Plant September 1991, (for the year 1990), Baltimore Gas And Electric Company, Environmental Programs Section, C. Key, B. E. Helbing
- 18. CP-607, Revision 1, "Offsite Dose Calculation Manual"
- 19. NO-1-201, Calvert Cliffs Operations Manual
- 20. TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites"
- 21. " Plant Data Book", BG&E CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1, Job 6750.
- 22. 50.59 Log No. 82-B-999-028-R00, Safety Analysis No. 2, FCR 82-1053, Supplement 1 (Component Cooling System) [B527]
- 23. 50.59 Log No. 90-0-074-011-R2, Activity MASE 90-7 (Plant Nitrogen System)
[B527]
- 24. 50.59 Log No. 90-0-029-045-R1, Activity MASE 90-6 (Plant Heating System)
[B527] 25, 50.59 Log No. 90-0-037-044-R1, Activity MASE 90-5 (Demineralized Water System) [B527]
- 26. 50.59 Log No. 90-B-012-043-R1, Activity MASE 90-4 (Service Water System)
[B527]
- 27. 50.59 Log No. 90-0-027-037-R2, Activity MASE 90-8 (Auxiliary Boiler System)
[B527]
- 28. Bechtel Power Corporation, Calculation Number M-90-20, " Allowable Radioactive Contamination Levels in the Plant Heating System" [B527]
- 29. Bechtel Power Corporation, Calculation Number M-90-18, " Allowable Radioactive Contamination Levels in the Nitrogen System Header" [B527]
- 30. Bechtel Power Corporation, Calculation Number M-90-04, " Allowable Radioactive Contamination Levels in Auxiliary Boiler Water" [B527]
- 31. Bechtel Power Corporation, Calculation Number M-90-21, " Allowable Radioactive Contamination Levels in the Demineralized Water System" [B527]
Offsite Dose Calculation Monual Page 13 of 298 < RGvision 2, Chenge 0 l
- 32. Bechtel Power Corporation, Calculation Number M-90-19, " Allowable Radioactive Contamination Levels in the Service Water System" [B527] ]
- 33. Bechtel Power Corporation, Job Number 11865, Calculation Number 7.4.3-15, l
" Allowable Radioactive Contamination Levels in the Condensate Storage Tank" l
[B527]
- 34. EN-1-100, Engineering Change Process Overview
- 35. Ol-8A, Blowdown System
- 36. NUREG-1301, "Offsite Dose Calculation Manual: Standard Radiological Effluent i Controls for Pressurized Water Reactors", W.W. Meinke, and T.H. Essig, (Published April 1991).
- 37. Radiological Environmental Monitoring Program Annual Report for the Calvert ;
Cliffs Nuclear Power Plant Units 1 and 2 January 1 - December 31,1991", Baltimore Gas And Electric Company, March 1992 38, 50.59 Log No. 90-B-037-120-R2, Activity MASE 90-11 (Condensate Storage . Tank) [B527] B. Performance References
- 1. TE-001, " Main Vent Stack Flow Measurement" r l
i I P e
' Offsite Dose Calculation Minu 1 Page 14 of 298 Revision 2, Change O PART 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS s
3
. .. = _ - . - - . . -- . .- ... .- .- - Offsite Dose Calculation Manual Pago 15 of 298 Revision 2, Change 0 3/4.0 APPLICABILITY CONTROLS
- _ - - - _ _ _ _ - - _ _ _ - . - _ ~ _ _ _ - - _ _ _ _ _ _ _ _ _ - . _ - _ .
3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: ,
- 1. At least HOT STANDBY within the next 6 hours,
- 2. At least HOT SHUTDOWN within the following 6 hours, and r
- 3. At least COLD SHUTDOWN within the subsequent 24 hours. ,
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. . 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications. 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable , solely because its emergency power source is inoperable, or solely because its normal power - source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding . normal or emergency power source is OPERABLE; and (2) all of its redunda4. system (s), subsystem (s), train (s), component (s) and device (s) k P h p_ , .. . y
Offsita Dose Criculition M:nual P:gs 16 of 298 Revision 2, Change 0 SURVEILLANCE 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. 4.0.3 Failure to perfctm a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements fer a Limiting Condition for Operation. The time lirnits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. However, this time of applicability may be delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not te made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operat'on have been performed within the stated surveillance interval or as othenvise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. I 1
1 1 Offsite Dose Oy.lculation M: null Paga 17 of 298 Revision 2, Change 0 , 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorina Instrumentation , CONTROLS 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table , 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of : Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be i det:"nined and adjusted in accordance with the methodology and parameters in the ODCM. APPLICABILITY: As shown in Table 3.3-12. ACTION: ,
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip ;
setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or chenge the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Exert best efforts to retum the instruments to OPERABLE status within 30 days , and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS : I 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11. l 1
Offsite Dose Calculation Manual Page 18 of 298 Revision 2, Change 0 TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION NilNIMUM CHANNELS INSTRUMENI CPERAB_LE APPLICABILITY ACTION
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor- Providing 1 35 Alarm and Automatic Termination of Release
- b. Effluent System Flow Rate Measuring 1 36 Device
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor 1 37
- b. lodine Sampler 1 38
- c. Particulate Sampler 1 39
.j
Offsite Dose C:lculation M:nu;l Paga 19 of 298 Revision 2, Change 0 TABLE 3.3-12 (Continued) TABLE NOTATION At all times. ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:
- a. Using the main vent monitor as a backup and recording RMS readings every 15 minutes during the release, or
- b. Provided that prior to initiating the release, at least two independent samples of the tank's contents are ana!yzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours, or (2) an equivalent monitor is provided. ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary sampling equipment.
Offsite Dose Calculation Manual Page 20 of 298 Revision 2, Change 0 TABLE 4.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MODES IN CHANNEL WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION IESI REQUIRED
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor- P P RW SAU)
- Providing Alarm and Automatic Termination of Release
- b. Effluent System Flow Rate D") NA R NA Measuring Device
- 2. MAIN VENT SYSTEM
- a. Noble Gas Activity Monitor D M RW SAA *
- b. lodine Sampler W NA NA NA
- c. Particulate Sampler W NA NA NA
1 Offsiu Dose C:lculation Manual Page 21 of 298 Revision 2, Chtnge 0 TABLE 4.3-11 (Continued) TABLE NOTATION At all times other than when the line is valved out and locked. The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation of this pathway and/or Control Room alarm annunciation occurs if the appropriate following condition (s) exists:
- 1. Instrument indicates measure levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used. . (4) The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours on days on which effluent releases are made.
Offsit2 Dose CIlculation Minual Paga 22 of 298 Revision 2 Change 0 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTAT!ON Radioactive Liauld Efiluent Mrnitorina Instrumentation CONTROLS ) l 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table , 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ' Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be ; determined and adjusted in accordance with the methodology and parameters in the OFFSITE > DOSE CALCULATION MANUAL (ODCM). ) i APPLICABILITY: At all times. ACTION: l
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without )
delay suspend the release of radioactive liquid effluents monitored by the ! affected channel, or declare the channel inoperable, or change the setpoint so it ' is acceptably conservative.
- b. With less than thc minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Exert best efforts to retum the instruments to OPERABLE status within 30 days ! and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS j 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequot 3 shown in Table 4.3-12. , I i i l _____.__-_a
Offsite Dose C:lculition M: null Page 23 of 298 Revision 2, Change 0 TABLE 3.3-13 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GROSS RADIOACTIVIT( MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line 1 28 l b. Steam Generator Blowdown Effluent Line 1 29
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line 1 30
- b. Steam Generator Blowdown Effluent Line 1 30 l
l i
Offsite Dose C:lculation Minual Page 24 of 298 Revision 2, Change 0 TABLE 3.3-13 (Continued) ACTION STATEMENTS ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with i Specification 4.11.1.1.1, and )
- b. At least two technically qualified members of the Facility Staff I independently verify the release rate calculations and two qualified operators verify the discharge valve line up.
ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the lower limit of detection defined in Table 4.11-1:
- a. At least once per 12 hours when the specific activity of the I secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131.
- b. At least once per 48 hours when the specific activity of the !
secondary coolant is less than or equal to 0.01 microcurie / gram ! DOSE EQUIVALENT l-131. ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual relesses. Pump performance curves may be used to estimate flow.
Offsste Dose Calculation Manual Page 25 of 298 q Revision 2, Change 0 TABLE 4.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENI CHECK CILEiCK CALIBRATION IESI
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line D P Rm SA("
- b. Steam Generator Blowdown Effluent Line D P RA SA(4
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line D(') NA R NA
- b. Steam Generator Blowdown Effluent Line D(') NA R NA l
l I
Offsib Dose Cdculation M nur! Page 26 of 298 Revision 2, Change 0 TABLE 4.3-12 (Continued) TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or Control Room alarm annunciation occur if the appropriate fol!owing condition (s) exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration can be used. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which effluent releases are made.
Offsit) Dose Calculation Minual Pag)27 of 298 Revision 2, Change 0 ' 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LlQUID EFFLUENTS Concentration CONTROLS I I 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. APPLICABILITY: At all times. ACTION;
- a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1. 1 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of -' release are maintained within the limits of Specification 3.11.1.1. I l i l
e Offsit] Dose Criculation Manu:1 Pag)28 of 298 Revision 2, Change 0 TABLE 4.11-1 BADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l l 1 i i I LOWER LIMIT ! OF MINIMUM DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)* l TYPE FREQUENCY FREQUENCY ANALYSIS (mci /mi) A. Batch Waste P P Principal Gamma 5x10 Releases
- Each Batch Each Batch Emitters
- l-131 1x10*
Mo-99, Ce-144 2x10* P M H-3 1x10* d Each Batch Composite Gross Alpha 1 x10 P Q d Each Batch Composite Sr-89,Sr-90 5x10-8 B. Turbine M M Principal Gamma 5x10 l l Building Emitters
- i Sump l l-131 1x10*
Mo-99, Ce-144 2x10+ I i l 1
-__- ___-________________________________________________________________-_________U
Offsite Dose C:lculation Minu;l Page 29 of 298 Revision 2, Change 0 TABLE 4.11-1 (Continued) TABLE NOTATION a 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 detected with 95% probability with only , 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = " E Ve 2.22 x 10' . Y exp(-AAt) Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, S b 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, 2.22 x 10' is the number of disintegrations per minute per microcurie, , Y is the FRACTIONAL radiochemical yield, when applicable, A, is the radioactive decay constant for the particular radionuclide, and , At is the elapsed time between sample collection, or end of the sample collection period, and time of counting. Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a pnori(before the fact) limit representing the capability of a measurement system and not as an a postenoIi (after the fact) limit for a particular measurement. l
Offsite Dose C"Icui tion Minuil Page 30 of 298 l Revision 2, Chmge 0 l l TABLE 4.11-1 (Continued) TABLE NOTATION b Prior to sampling Reactor Coolant Waste and Miscellaneous Waste for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. c The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137 and Ce-141. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Technical Specification 6.5.1. d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged in which the method of sampling employed results in a specimen that is representative of the liquids released. l l l l
I Offsite Dose Calculition Manual Page 31 of 298 Revision 2, Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS DDAt CONTROLS 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited:
- a. During any calendar quarter to less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ, and
- b. During any calendar year to less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective ACTIONS that have been taken to reduce the releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Monthly cumulative dose contributions from liquid effluents for the current calendar ! quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days. l l I
Offsite Dose Calculation Minuti Page 32 of 298 Revision 2, Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liauld Radwaste Treatment System CONTROLS 3.11.1.3 The Liquid Radweste Treatment System shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the calculated doses due to the liquid effluent to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 mrem to any organ in a 92 day period. APPLICABILITY: At all times. ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 a Special 7
! Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. ACTION (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of ACTION (s) taken to prevent a recurrence.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3 Monthly doses due to liquid releases to UNRESTRICTED AREAS shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM. I l
Offsite Dose Calculation Manual Paga 33 of 298 Revision 2, Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS Dose Rate , CONTROLS { 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site J to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 2) shall be limited l to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less !
t than or equal to 3000 mrems/yr to the skin, and
- b. For iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. -
APPLICABILITY: At all times. ! ACTION:
- a. With the dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ;
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. 4.11.2.1.2 The dose rate due to iodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative . samples and performing analyses in accordance with the sampling and analysis program j specified in Table 4.11-2. !
Offsite Dose Calculation Manual Page 34of 298 Revision 2. Change 0 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT OF SAMPLING MINIMUM ANALYSIS DETECTION (LLD)* GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pCi/ml) A. Waste Gas P P Principal Gamma Emitters
- 1 x 10" Storage' Tank Each Tank Each Tank (Gaseous Emissions Only)
Grab Sample B. Containment Purge P P Pnncipal Gamma Emitters" 1 x 10" and Vent Each Tank
- Each Tank * (Gaseous Emissions Only)
Grab Sample C 1 x 10" C. Main Vent M M Principal Gamma Emitters
- GrabSample (Gaseous Emissions Only) 4 Continuous' M H-3 1 x 10 42 Continuous' W l-131 1 x 10 Charcoal Sample
- Continuous
- W Principal Gamma Emitters
- 1 x 10-"
Particulate (1-131, others) Sample
- Continuous' M Gross Alpha 1 x 10-"
Composite Particulate Sample Continuous
- O Sr-89, Sr90 1 x 10-"
Composite Particulate Sample 4 Continuous
- Noble Gas Noble Gases 1 x 10 Monitor Gross Beta or Gamma D. Incinerated Oil' P P Principal Gamma Emitters 5 x 10 Each Batch" Each Batch"
Offsit) Dose C:lculition Minuil Page 35 of 298 Revision 2, Change 0 TABLE 4.11-2 (Continued) TABLE NOTATION a 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 detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = E o V e 2.22 x 10' e Y e exp (-lo t) Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, S bis 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, 2.22 x 10' is the number of disintegrations per minute per microcurie, Y is the FRACTIONAL radiochemical yield, when applicable, A. is the radioactive decay constant for the particular radionuclide, and , At for plant effluents is the elapsed time between sample collection or end of the sample collection period, and time of counting. Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a oriori(before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Offsite Dose Cdculltion Manual Page 36 cf 298 j Revision 2, Change 0 ! TABLE 4.11-2 (Continued) j TABLE NOTATION i b The principal gamma emitters for which the LLD specification applies exclusively , are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and , Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, ! Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that , are identifiable, together with those of the above nuclides, shall also be analyzed :' and reported in the Annual Radioactive Effluent Release Report pursuant to Technical Specification 6.5.1. Sampling and analysis shall also be performed following shutdown, STARTUP, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary coolant has not increased more ; than a factor of 5, and (2) the noble gas activity monitor shows that effluent : activity has not increased by more than a factor of 5. d 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 j accordance with Specifications 3.11.2.1,3.11.2.2 and 3.11.2.3. l
?
Samples shall be changed at least once per 7 days and analyses shall be f completed within 48 hours after changing, or after removal from sampler. When ] sample collection time is less than seven days, the corresponding LLDs may be t increased by a proportional factor. This requirement does not apply if (1) analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary j coolant has not increased more than a factor of 5, and (2) the noble gas monitor ; shows that effluent activity has not increased more than a factor of 5. l t i Collect sample and analyze daily for total Curie content per Specification , 3.11.2.6 when the Reactor Coolant System specific activity of Xe-133 is greater than 150 mci /ml. j 0 incinerated oil may be discharged via points other than the main vent (e.g., 1 Auxiliary Boiler). Releases shall be accounted for based on pre-release grab sample data. h Samples for incinerated oil releases shall be collected from and representative of filtered oil in liquid form.
l l Offsite Dose Calculation Manuil Page 37 of 298 ; l Revision 2, Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS pose - Noble Gases CONTROLS . . 1 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and l beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) shall be limited to l the following: H I
- a. During any calendar quarter: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation and, ;
- b. During any calendar year: Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.
APPLICABILIIY: At all times. . ACTION: 1
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective ACTIONS that have been taken to reduce the ,
releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits. i
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS . 4.11.2.2 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days. i
Offsit3 Dose C:Iculation M:nual Pag 3 38 of 298 Revision 2 Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS Dose -lodine-131 and Radionuclides in Particulate Form System CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131 and all radionuclides in particulate farm with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 15 mrems to any organ and,
- b. During any calendar year: Less than or equal to 30 mrems to any organ.
- c. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of buming contaminated oil.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of iodine-131 and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective ACTIONS that have been taken to reduce the releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Monthly cumulative dose contributions for the current calendar quarter and the current calendar year for iodine-131 and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.
Offsite Dose C:lculation Minu:1 Pag'a 39 of 298 Revision 2, Change 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS ; Gaseous Radwaste Treatment System . CONTROLS
+
3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous 1 waste prior to their discharge when the gaseous effluent air doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY BOUNDARY (see figure in UFSAR Chapter 2) exceeds 1.8 mrem to any organ in a g2 day period. APPLICABILITY: At all times. ACTION:
- a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report that includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without ,
treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. ACTION (s) taken to restore the inoperable equipment to OPERABLE ,
status, and
- 3. Summary description of ACTION (s) taken to prevent a recurrence,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 Monthly doses due to gaseous releases shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM. 3
Offsite Dose Calculation Minuil Page 40 of 298 Revision 2, Change 0
-3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE ' CONTROLS 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times. ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2.a.
3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days a Special Report that defines the corrective ACTION to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of i 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff ACTION on the request is complete,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2,4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a. l l
Offsite Dose Cilculation Minu 1 Page 41 of 298 ) Revision 2, Change 0 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS < 3.12.1 The radiological environmental monitoring program shall be conducted as specified in f Table 3.12-1. APPLICABILITY: At all times, j ACTION:
- a. With the radiological environmental monitoring program not being conducted as :
specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operati.,g Report required by Technical Specification ; 6.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. :
- b. With the level of radioactivity as the result of plant effluents in an environmental ,
sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission within 30 days after receiving the sample analysis a Special Report that identifies the cause(s) for exceeding the limit (s) : and defines the corrective ACTIONS to be taken to reduce radioactive effluents , so that the potential annual dose' to a MEMBER OF THE PUBLIC is less than l the calendar year limits of Specifications 3.11.1.2,3.11.2.2, and 3.11.2.3. When , more than one of the radionuclides in Table 3.12-2 are detected in the sample i this report shall be submitted if; j concentration (1) , concentration (2) + ..> 1.0 - reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12-2 are cletected and are the result of plant effluents, this report shall be submitted if the potential annual ; dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar : year limits of Specifications 3.11.1.2,3.11.2.2 and 3.11.2.3. This report is not i 1 required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. l I The methodology and parameters used to estimate the potential annual dose to a MEMBER OF : THE PUBLIC shall be indicated in this report. l I i
Offsite Dose C:lculation M; null Page 42 of 298 Revision 2, Change 0 1
- c. With fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement :
samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.6.2, identify the cause of the unavailability of samples and identify the new location (s) for obtaining the replacement samples in the next Annual Radiological Environmental Operating Report.
- d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. f 5 l
Offsde Dose Calculabon Manual Page 43 of 298 ' Revision 2. Change 0 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF ANALYSIS
- 1. DIRECT RADIATION" 23 routine monitoring stations (DR1 - DR23) At least Quarterly Gamma dose at least either with two or more dosimeters or with one quarterly.
instrument for measuring and recording dose rate continuously, placed as follow; an inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY (DR1 - DR09); , an outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the s;te (DR10 - DR09); the remaining stations (DR19 - DR23) to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 area to serve as a control station ___._.s__.____. _ _ _ ___ - - e . --
- v e% . - -- == 4 -. . ,_____m -,
Offsite Dose Calculation Manual Page 44 of 298 Revision 2. Change 0 TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY ANDIOR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
- 2. AIRBORNE Radiciodine and Samples from 5 locations (A1-AS): Continuous sampler operation with Radioiodine Canister Particulates sample collection weekly, or more I-131 analysis weekly.
3 samples (A1-A3) from close to the 3 frequently if required by dust loading. SITE BOUNDARY locations, in different Particulate Samoler sectors of the highest calculated annual Gross beta average ground-level D/Q. radioactivity analysis following filter 1 sample (A4) from the vicinity of a change;* Gamma isotopic community having the highest calculated analysisd of composite annual average ground-level D/Q. (by location) quarterly 1 sample (A5) from a control location, as for example 15-30 km distant and in the least prevalent wind direction.
onsite Dose caWW *""*' Page 45 of 298 Revision 2. Change O gE 3.121 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY ANDIOR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
- 3. WATERBORNE d
- a. Surface 1 sample at intake area (Wa1) Composite sample over 1-month Gamma isotopic analysis 1 sample at discharge are (Wa2) period
- monthly. Composite for tritium analysis quarterfy.
d
- b. Sediment from 1 sample from downstream area with existing Semiannually Gamma isotopic analysis shoreline or potential recreational value (Wb1) semiannually.
Offsite Dose Calculation Manual Page 46 of 298 Revision 2. Change 0 IABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY ANDIOR SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
- 4. INGESTION d
- a. Fish and 3 samples of commercially and/or Sample in season, or semiannually if Gamma isotopic analysis invertebrates recreationally important species (2 fish speces they are not seasonal. on edible portions.
and 1 invertebrate species) in vicinity of plant discharge area (la1-la3). 3 samples of same species in areas not influenced by plant discharge (la4-la6).
- b. Food Products Samples of 3 different kinds of broad leaf Monthly during growing season. Gamma isotopicd and l-vegetation grown near the site boundary at 2 131 analysis.
different locations of highest predicted annual average ground level D/Q (lb1-Ib6). 1 sample of each of the similar broad leaf Monthly duriag growing season. Gamma isotopic8 and l-vegetation grown 15-30 km distant in the least 131 analysis. prevalent wind direction (Ib7-Ib9). 1
. _ . .~ ~ - _ . __ . , . - . . - - - . - -- _ - . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - -
Offsite Dose Cdcuttion M; null Page 47 of 298 Revision 2, Change 0 TABLE 3.12-1 (Continued) TABLE NOTATION a The code in parenthesis, e.g., DR1, A1, defines generic sample locations in this specification that can be used to identify the specific locations in the map (s) and table in the ODCM. Specific parameters of distance and direction sector from the central point between the two containment buildings and additional description where pertinent, is provided for each sample location in Table 3.12-1, and in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978", and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment j malfunction, effort shall be made to complete corrective ACTION prior to the end l of the next sampling period. All deviations from the sampling schedule shall be ) documented in the Annual Radiological Environmental Operating Report 1 pursuant to Technical Specification 6.6.2. 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 eppropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Technical Specification 6.6.2, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining samples in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s). l i
l Offsite Dose CIlculation M:nu 1 Page 48 of 298 Revision 2, Change 0 [ TABLE 3.12-1 (Continued) TABLE NOTATION b One or more instruments, such as a pressurized ion chamber, for measuring and j recording dose rate continuously may be used in place of, or in addition to, l integrating dosimeters. For the purposes of this table, a thermoluminescent ' dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD Systenis will depend upon the characteristics of the specific ; system used and should be selected to obtain optimum dose information'with l minimal fading. Due to the geographicallimitations,9 sectors are monitored ' around the Calvert Cliffs Nuclear Power Plant. c Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If - gross beta activity in air particulate samples is greater than ten times the yearly riean of control samples, gamma isotopic analysis shall be performed on the ( individual samples. ' d l Gamma isotopic analysis means the identification and quantification of gamma- t emitting radionuclides that may be attributable to the effluents from the facility. , i e A composite sample is one in which the quantity (aliquot) of liquid sampled is l proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. l 1 i l
Offsde Dose Calculation Manual Page 49 of 296 Revision 2, Change 0 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMELES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH & INVERTEBRATES MILK FOOD PRODUCTS ANALYSIS (pCill) OR GASES (pCi/M3) (pCilkg, wet) (pCi/I) (pCilkg, wet) H-3 20,000" Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 i,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
" For drinking water samples. This is a 409 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCill may be used.
Offsite Dose Calculation Manual Page 50 of 298 Revision 2, Change 0 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS d LOWER LIMIT OF DETECTION (LLD)* WATER AIRBORNE PARTICULATE FISH & INVERTEBRATES MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCill) OR GASES (pCi/M') (pCilkg, wet) (pCi/I) (pCilkg, wet) (pCilkg, dry) Gross Beta 4 0.01 H-3 2,000' Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 d l-131 i 0.07 1 60 Cs-134 15 0.05 130 15 60 150 C:-137 18 0.06 150 18 80 180 Ba-La-140 15 15
" If no drinking water pathway exists, a value of 3000 pCi/I may be used.
i l Offsite Dose C:lculation Minuil P:g3 51 of 298 i Revision 2, Change 0 ; TABLE 4.12-1 (Continued) TABLE NOTATION i a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also : be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.6.2. b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. c 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 detected with 95% probability with only 5% probability of falsely concluding that a blank observation rsoments a "real" signal. For a particular measurement system, which may include radiochembt separation: S' LLD = EeVe 2.22
- Y e exp(-AA t)
Where: LLD is the "A priori" lower limit of detection as defined above, as picoeuries per unit mass or volume, sois the starWrd deviation of the background counting rate or of the counting rate rsi 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, 2.22 is the number of disintegrations per minute per picocurie, Y is the FRACTIONAL radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and l i
I i Offsite Dose Calculation M:nuil Page 52 of 298 Revision 2, Change 0 TABLE 4.12-1 (Continued) TABLE NOTATION l At for environmental samples is the elapsed time between sample collection, l or end of the sample collection period, and time of counting. j Typical values of E, V, Y and At should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) ! limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental ; Operating Report pursuant to Specification 6.6.2. i d i LLD for drinking water samples. If no drinking water pathway exists, the LLD of - gamma isotopic analysis may be used. q i i
\
Offsite Dose Calculation Minu:1 Page 53 of 298 Revisien 2, Change 0 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS - - - - _ - - .. . . _ - - - - .- - - -_-. 3.12.2 A land use census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 9 meteorological sectors of the nearestz milk animal, the 2 nearest residence and the nearest garden' of greater than 50 m (500 ft ) producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 9 meteorological sectors of all milk animals and all gardens of greater than 50 m* producing broad leaf vegetation). APPLICABILITY: At all times. ACTION:
- a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Specification 6.6.2.
- b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.6.2, identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2 The land census shall be conducted during the growing season at least tr.ce per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Envirotunental Operating Report pursuant to Specification 6.6.2.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the i
SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Os in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.
Offsite Dose Calculation Manual Page 54 of 298 Revision 2, Change 0 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/4.12.3 lNTERLABORATORY COMPARISON PROGRAM l l CONTROLS I ll l I 11 1 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1. APPLICABILITY: At all times. ACTION:
- a. With analyses not being performed as required above, report the corrective ACTIONS taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.6.2.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A semmary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Techn .al Specification 6.6.2. l
..l
Offsite Dose CCiculation Manual Page 55 of 298 RGvision 2, Change O PART 5.0 CALCULATIONAL METHODOLOGIES I l i l i
--__---__-_---____________--__________________________3
Offsite Dose Calculation Manual Page 56 of 298 Revision 2, Change 0 4.0 RADIOACTIVE LIQUID EFFLUENTS A. Release Pathways [B627]
- 1. Introduction a) Radioactive liquid waste generated as a result of operating the Calvert Cliffs Nuclear Power Plant (CCNPP) may be released to the Chesapeake Bay'.
b) - By design, there are four pathways by which all waste water, non-radioactive and radioactive, may be discharged from the site to the bay: (1) Outfall 001, (2) Outfall 002, (3) Outfall 003, (4) Outfall 004. A diagram which shows the location of each outfall is included as c) Attachment 1.
- 2. Outfall 001 :
a) Water from the Chesapeake Bay is pumped through the condensers and is discharged to the Chesapeake Bay through the circulating water discharge conduits, known as outfall 001. b) The liquid radioactive waste is mixed with and diluted by the circulating water prior to exiting the discharge conduit. c) The circulating water discharge conduit extends 850 feet into the ; Chesapeake bay. ; d) The circulating water discharg onduit may accept liquid radioactive waste from various sources. Sources which may contribute radioactive material to the circulating water discharge conduit are tabulated in Attachment 2.
- 3. Outfalls 002,003, and 004 a) There are three other potential patnways for the release of radioactive liquids to the bay. These pathways are designated outfall 002, outfall ,
003, and outfall 004. b) Sources which could potentially contribute radioactive material to each of these outfalls are tabulated in Attachment 3. 4 1 The federal controls and administrative limits associated with the release of radioactive materials from CCNPP are discussed elsewhere in this document. I
Offsete Dose Calculaton Manual Page 57 of 298 1 f Revision 2, Change O c) . No radioactive materials are expected to be discharged from outfall 002 ,
.i unless there is a primary to secondary leak, or unless there is an unforeseen and catastrophic failure of a condensate storage tank (CST). l d) No radioactive materials are expected to be released from outfalls 003 or
- 004 unless there is an unforeseen and catastrophic failure of a refueling ;
water tank (RWT). ]
- 4. Unmonitored release paths not shown on Attachment 3 should be evaluated and {
added to the ODCM as necessary. ;
- 5. Safety evaluations have been conducted for operating the following systems i after they have become contaminated: l a) component cooling water system (1) In accordance with applicable safety evaluations (Ref. 22), l i
continued operation of this system is allowed as long as the concentration of radionuclides in the component cooling water system is less than 3,000 MPCs. ; b) plant heating system (1) in accordance with applicable safety evaluations (Ref. 24 and Ref. ! 28), continued operation of this system is allowed as long as the '! concentration of radionuclides in the plant heating system is less i than 0.3 MPCs. j c) auxiliary boiler system (1) In accordance with applicable safety evaluations (Ref. 27 and Ref. ,
- 30) continued operation of this system is allowed as long as the !
concentration of radionuclides in the auxiliary boiler steam drum is ; less than 96 MPCs. ; , d) demineralized water system (1) In accordance with applicable safety evaluations (Ref. 25 and Ref. ! 31), continued operation of this system is allowed as long as the ; ' concentration of radionuclides in the domineralized water system , is less than 0.3 MPCs. t . e) service water system ) i . i ! (1) In accordance with applicable safety evaluations (Ref. 26 and Ref. l i 32), continued operation of this system is allowed as long as the ; concentration of radionuclides in the service water system is less l 4 than 0.1 MPCs. f) condensate storage tank 5 (1) In accordance with applicable safety evaluations (Ref 33), continued operation of this system is allowed as long as the i 1
. . , . -,- < - . . -- -, _ . . , . . - - . - - _ . , - - . , - , , _ . . , , . - - - e ,.
Offsde Dose Calculation Manual- Page 58 of 298 . Revision 2, Change O concentration of radionuclides in the condensate storage tank is less than 1.0 MPCs. B. Types of Liquid Releases 1.~ All liquid radwaste releases are classified as either BATCH RELEASES or CONTINUOUS releases.
- 2. The definition of " BATCH RELEASE"is included in the definitions section of the.-
ODCM.
- 3. The definition of " CONTINUOUS release" is included in the definitions section of
' the ODCM.
- 4. Liquid radweste discharges have been classified as CONTINUOUS or BATCH as shown on Attachments 2 and 3.
C. Processing Equipment
- 1. Simplified Flow Diagram a) An overview of the liquid waste processing system, including major equipment and (normal) flow paths, is outlined on Attachment 4.
b) There is no processing equipment for wastes discharged through outfalls . 002, 003, and 004; however, the waste shall be analyzed for radioactivity in accordance with the analysis frequencies contained in approved CCNPPD Chemistry Section procedures.
- 2. Modifications a) Major changes or modifications to the liquid waste processing system shall be reported to the Commission in the Annual Radioactive Effluent -
Release Report for the time interval in which the modification was completed (per Technical Specification 6.15.1). b) A " major" change or modification includes, but is not limited, to the removal or permanent bypass of any of the following: (1) degassifier (2) reactor coolant waste receiver tank (3) reactor coolant waste monitor tank (4) letdown filter I (5) reactor coolant waste ion exchanger (6) miscellaneous waste ion exchanger (7) miscellaneous waste filter (8) miscellaneous waste receiver tank
q Offsite Dose Calculation Monual Page 59 of 298 Revision 2. Change 0 j (9) miscellaneous waste monitor tank (10) evaporator
- 3. Detailed Description ,
a) A detailed description of the liquid waste processing system is beyond the scope of the ODCM. , b) For more information on the Miscellaneous Liquid Waste Processing , i System see System Description Number 14D," Miscellaneous Liquid Waste Processing System Description." c) For more information on the Reactor Coolant Waste Processing System
- see System Description Number 14B, " Reactor Coolant Waste Processing System Description."
d) For more information see the Updated Final Safety Analysis Report, Chapter 11,'" Waste Processing And Radiation Protection." D. Liquid Effluent Radiation Monitor Alarm and Trip Setpoints
- 1. Liquid Waste Discharge Radiation Monitor (0-RE-2201) a) General description (1) number of radiation elements: one -
type of radiation element: in-line scintillation detector ! (2) I (3) output: analog I (4) radiation indicator: 0-RI-2201 (5) units for radiation indicator: counts per minute (6) supplier: Westinghouse b) Functions of 0-RE-2201 (1) continuously measure the activity contained in liquid waste
- discharge line (Technical Specification 3.3.3.10)
(2) continuously indicate (via 0-RI-2201) the activity of liquids contained in liquid waste dischar0e line (Technical Specification : 3.3.3.10) . i (3) alarm (via 0-RI-2201) prior to exceeding 10 CFR 20, Appendix B, ' Table ll, Column 2 limits (per Technical Specification 3.11.1.1) (4) automatically terminate discharges from the liquid waste processing system by closing the discharge isolation valves (MWS-2201-CV, and MWS-2202-CV) whenever the radiation indicator (0-RI-2201) exceeds the fixed high radiation trip setpoint
, .-. . . ~ ... - _ .-
' Offsite Dose Calculation ManuCl ' Page 60 of 298
_ Revision 2, Change 0 1 c) OPERABILITY of 0-RE-2201 , I (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s) i (2) The functions of 0-RE-2201 are listed in paragraph (b) above. d) Monitors equivalent to 0-RE-2201 (1) There are no equivalent monitors for 0-RE-2201. e) Radiological effluent controls for 0-RE-2201 , (1) Liquid waste discharges via this pathway may continue if any one of the following two conditions are satisfied (per Technical Specification 3.3.3.10).
-(a) alarm and trip setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2, or (b) two independent sampit.s are analyzed in accordance with i Technical Specification 4.11.1.1.1; AND at least two ,
technically qualified members of the Facility Staff independently verify the release rate calculations; AND two qualified operators verify the discharge valve line up. f) Surveillances for 0-RE-2201 l (1) Technical Specification 4.3.3.10 reauires demonstrating the OPERABILITY of 0-RE-2201 by satisfying the checks, calibrations, and tests listed below: (a) CHANNEL CHECK within the past 24 hours i (b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months ,
-(d) CHANNEL FUNCTIONAL TEST within the past 6 six .
months . g) Setpoints for 0-RI-2201 (1) There are three radiation alarm setpoints associated with, or otherwise related to, the liquid waste discharge monitor. ! (a) 0-RI-2201 fixed high radiation alarm and automatic control trip setpoint (b) 0-RI-2201 adjustable plant computer high radiation alarm and manual control trip setpoint
+ - - , . , .
l
' Offsite Dose Calculation Manual Page 61 of 298 l Revtion 2, Change 0 (c) 0-Rl-2201 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, l and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:
(a) The 0-RI-2201 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint. ; , (b) The 0-RI-2201 adjustable plant computer high radiation alarm and manual control trip setpoint will be referred to as i the adjustable setpoint. .; (c) The 0-RI-2201 low radiation alarm setpoint will be referred , to as the low setpoint. (3) Each of these alarm setpoints is described below. h) Fixed setpoint for 0-RI-2201 (1) Generalinformation (a) This setpoint is considered to be a fixed setpoint. This i setpoint is not adjusted for each release. (b) Whenever the fixed setpoint is exceeded, discharges from ! the liquid waste processing system will be automatically l suspended. (c) The fixed setpoint corresponds to the maximum - concentration of radionuclides allowed in liquid waste discharged from the liquid waste processing system. l (d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. j (e) The CCNPP Alarm Manual refers to this alarm and trip j setpoint as the 0-RI-2201 Liquid Waste Discharge High l Alarm. ! l (f) The fixed setpoint is integral to the liquid release discharge : monitor, as purchased from the supplier. : (g) The fixed setpoint is administratively controlled by EN ; 100. 2 (h) The fixed setpoint shall be calculated as described below , ; 1 (2) Calculating the fixed setpoint for 0-Rl-2201 l l (a) The fixed alarm and trip setpoint for 0-Rl-2201 shall be calculated as follows:
- Per Specification 3.3.3.10. 1 t
.l I
. , + . - - - -. . . . . . _ -
Offsit2 Dose Calculsthn Manu 1 Page 62 of 298 Revision 2, Change 0 FIXED ALARM A'N TRIP SETPOINT FOR 0-RI-2201 e a Sra - 5 K r { ( Fo / F,) h [( Ai u )( c )] + Bkg } i Eq.1L Sr, = the fixed alarm and trip setpoint for 0-RI-2201 (cpn') 1 Kg = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to
. the 10 CFR 20 MPC limit (unitiess)
The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed i setpoint is always less than or equal to the limits of 10 CFR 20. r A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC. l A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs. it is recommended that a safety factor of 0.5 be used for calculating the fixed l setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. - The use of a " safety margin"is in accordance with the provisions of NUREG-0133, ! section 4.1.1, which states, "The alarm and trip setpoints . . should correspond to a { value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded." This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated ' fixed setpoint. 4 Fe
= the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED f AREAS t The dilution water flow rate is actually the sum of the minimum circulating water flow ;
rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow l rate. The dilution water flow rate shall be calculated in accordance with equation 2L. , DILUTION WATER FLOW RATE Fo
= Fe , + F., + F u Eq.-2L F,e
= the minimum circulating water system flow rate necessary to conduct liquid releases l A minimum of two circulating water pemps (one circulating water pump per conduit accepting radwaste) shall be operable when discharging liquid radwaste - via this monitor - to outfall 001,
- This formula has been derived from NUREG-0133, Addendum, page AA-1.
l
Offsite Dose Calculation Minu:1 Page 63 of 298 Revision 2, Change O Additional circulating water pumps may be required as specified in approved Chemistry Procedures. If a release of liquid radwaste is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, then the release shall not be allowed until a new setpoint has been calculated and entered into 0-Rl-2201, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. F. = the minimum salt water system flow rate necessary to release liquid radwaste i If the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint. l if a release of liquid radwaste is to be conducted using less than the minimum salt I' water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 0-Rl-2201, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. Fu = maximum undiluted radwaste flow rate (gpm) Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. l ! Since the flow rate of undiluted liquid waste (120 gpm maximum) is insignificant l relative to the circulating water flow rate (200,000 gpm per circulating water pump), the flow rate of undiluted liquid waste need not be considered when calculating the dilution water flow rate. 1 Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required-for the flow measuring device (0-FE-2199) in the effluent line-to verify compliance with Specification 3.3.3.10. Atn = specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table 11, Note 1 as described below; microcuries per milliliter). In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those DOMINANT AND LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP. Attachment 5 provides further guidance for determining the identity of those radionuclides, i, to be used to calculate a fixed setpoint. ( Values for Agn shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the collective total of all LESS DOMINANT l RADIONUCLIDES. I l L - - - - - - - - _ _ _ _
Offsite Dose Calculation Manual Page 64 of 298 Revision 2, Change O SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE i A,tn = ( f, ) ( A7tn ) Eq.3L f, = a FRACTION which represents the relative activity contribution of nuclide i to the average total effluent activity (unitiess) The average total effluent activity does not include tritium or dissolved and entrained noble gases. This value may be obtained using the guidance provided on Attachment 5. Artn = the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3) This value corresponds to 1 MPC. Artn shall be calculated as shown below. TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC h [(f,)( A7tn ) / Aiu ] = 1 Eq. 4L' Au i
= the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table 11, Column 2 (microcuries/cm3)
For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table ll, Column 2. For each of the LESS DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for Au i (per 10 CFR 20, Appendix B, Note 2).
=
1 the MPC limit (MPCs) for unrestricted areas This value is based on the MPC limit from 10 CFR 20, Table ll, Note 1. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collectad during calibration of the radiation monitor. Bkg = an approximation of the detector background prior to initiating the liquid release (cpm) Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. This formula has been derived from 10 CFR 20, Table 11, Notes 1,2, and 3.
,m. .. ~. -. . . . - . - -
~ 1 l Offsite Dose Calculation Manual Page 65 of 298 I Revision 2, Change 0 (3) Documenting the fixed setpoint for 0-RI-2201 . (a) Whenever the fixed setpoint is calculated, the specific I values chosen for each of the parameters shall be documented in accordance with EN-1-100. (4) ' Changing the fixed setpoint for 0-RI-2201 , e (a) If the fixed setpoint calculated in accordance with equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed alarm and trip setpoint for 0-RI-2201 may be i established at values lower than the maximum allowable setpoint, if desired. > (c) A setpoint change should be initiated whenever any of the parameters identified in equation 1L have changed. , (d) The fixed setpoint should not be changed unless one of the following occurs: ; i) the relative activity5of any radionuclide in TYPICAL .; LIQUID EFFLUENTS, f,i has changed by greater ; than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the minimum dilution water flow rate is not ! available for a liquid release, lii) the values listed in 10 CFR 20, Table 11, column 2 have changed, i iv) . the radiation monitor has been recently calibrated,- , repaired, or otherwise altered, or j the monitor is not conservative in its function (see : v)
" Functions of 0-RE-2201" earlier in this section).
(e) EN-1-100 contains the administrative controls associated with changing and approving the fixed setpoint. j i) The adjustable alarm and trip setpoint for 0-Rl-2201 (1) Generalinformation , (a) This setpoint is an adjustable setpoint. The adjustable l setpoint is calculated and adjusted prior to each release i' from the liquid waste processing system. As determined in accordance with Attachrnent 5.
I Offsite Dose Calculation ManuDI Page 66 of 298 - Revision 2, Change 0 , t (b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste , (as determined by radiochemical analysis per Specification 4.11.1.1.1). (c) Whenever the adjustable setpoint is exceeded, discharges from the liquid waste processing system will be manually ; suspended. ; (d) See 01-17C, " Reactor Coolant Waste Processing System", ; or Ol-17D, " Miscellaneous Waste Processing System," for , a full list of operator ACTIONS taken in response to this alarm. t (e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the liquid waste processing system. j The value for the adjustable setpoint is recorded on the i (f) liquid release permit in accordance with Chemistry section ' procedures. (g) This alarm is not integral to the liquid release discharge > monitor, as purchased from the supplier, j (h) This alarm is generated by the plant computer, which monitors output from 0-RI-2201, and provides an alarm to j plant operators when the adjustable alarm and trip setpoint has been exceeded j i (i) A value for the adjustable alarm and trip setpoint shall be i calculated prior to each release as shown below. (2) Calculating the adjustable setpoint for 0-RI-2201 (a) The adjustable setpoint is based on the specific activities of the radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Specification , 4.11.1.1.1), and shall be calculated as shown below. ADJUSTABLE SETPOINT FOR 0-RI-2201 Suj 5 1.50 [ h ( Aw ) ( e3 ) + Bkg ) Eq. 5L Sg; = the adjustable alarm and trip setpoint for 0-RI-2201 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuations in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical
L Offsite Dose Calculation Manual Page 67 of 298 Revaion 2, Change O fluctuations in_ disintegration rates, (3) statistical fluctuations in detector efficiencies, L (4) errors associated with sample analysis, or (5) errors associated with monitor calibrations.e . Au = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) ] i e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) J The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. i Bkg = an approximation of the detector background (cpm)
)
(3) Documenting the' adjustable alarm and trip setpoint for 0-RI-2201 l (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with approved chemistry j section procedures (e.g., CP-601). l
\
(4) Changing the adjustable alterm and trip setpoint for 0-RI-2201 .l { (a) ' in all cases, the adjustable alarm setpoint shall be set to a I value which is less than or equal to the fixed setpoint. { I I (b) If the adjustable alarm and trip setpoint exceeds the maximum range of the monitor, the setpoint shall be ! adjusted to a value which falls within the normal operating range of the monitor. (c) Chemistry section procedures (e.g., CP-601) contain administrative controls associated with calculating and approving an adjustable setpoint. (d) Whenever 0-RI-2201 is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release from the liquid waste processing system. l (e) Plant Operating instructions (e.g., OI-17C and 01-17D) contain administrative controls associated with entering the adjustable setpoint into the plant computer. j) The low radiation alarm for 0-RI-2201 l (1) This alarm is integral to the liquid release discharge monitor, as purchased from the supplier. l i The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality control limits. m___. _
Offsite Dose Calculation MCnuti Page 68 of 298 - Revision 2, Change 0 (2) The current value for the low alarm setpoint is specdied in the CCNPP Alarm Manual. (3) The low alarm setpoint may be used to determine the [. , OPERABILITY of this monitor (per Specification 4.3.3.10,
- j. CHANNEL FUNCTIONAL TEST).
!= (4) The alarm generated by the low alarm setpoint may be used to [ ' . terminate a release in the event 0-RE-2201 fails (i.e., downscale I failure or circuit failure) in accordance with Specification 4.3.3.10. (5) The low alarm setpoint calculations are not described in the ODCM. (6) Changes to the low alarm setpoint are controlled by EN-1-100.
- 2. Steam Generator Blowdown Effluent Radiation Monitors (1/2-RE-4095) a) General description of 1/2-RE-4095 (1) number of radiation elements: one per unit (2) Type of radiation elements: in-line scintillation detectors (3) output: analog (4) Designations for radiation indicators (a) 1-RI-4095 (b) 2-RI-4095 (5) units for radiation indicator: counts per minute l (6) supplier. Westinghouse b) Functions of 1/2-RE-4095 (1) continuously measure the activity contained in steam generator blowdown effluent line ( Specification 3.3.3.10)
(2) continuously indicate (via 1/2-Rl-4095) the activity of liquids contained in the steam generator blowdown emuent line ( Specification 3.3.3.10) (3) alarm (via 1/2-RI-4095) prior to exceeding 10 CFR 20, Appendix B, Table ll, Column 2 limits (per Specification 3.11.1.1) (Note: A technical evaluation shall be conducted to ensure compliance with ' UFSAR 10.2.2.4.) , (4) automatically terminate steam generator blowdown releases to UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4095) exceeds the fixed alarm setpoint ;
Offsite Dose Calculation Manual - Page 69 of 298 R v2 ion 2, Change O c) OPERABILITY of 1/2-RE-4095 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s). (2) The functions of this monitor are listed in section (b) above. (3) It should be noted that if the steam generator blowdown processing system heat exchangers are bypassed, it is possible for blowdown flow to bypass 1/2-RE-4095. If blowdown flow is allowed to bypass 1/2-RE-4095, the minimum channels operability requirement of Specification 3.3.3.10 may not be satisfied. d) Monitors equivalent to 1/2-RE-4095 (1) 1/2-RE 4014 is normally considered the PRIMARY MONITOR for measuring activity released via the steam generator blowdown processing system, and 1/2-RE-4095 is normally considered the l BACKUP MONITOR for measuring activity released via the steam l generator blowdown processing system. l (2) In the event PRIMARY MONITOR (1/2-RE-4014) is inoperable or otherwise unavailable, the BACKUP MONITOR (1/2-RE-4095) is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR. (3) 1/2-RE-4014, Steam Generator Blowdown Tank Radiation Monitor is considered to be " equivalent" monitor to 1/2-RE-4095 as : specified below. (4) 1/2-RE-4014, Steam Generator Blowdown Tank Radiation Monitor, is able to perform measurement, indication, alarm, and isolation functions (see " Functions of 1/2-RE-4014" earlier in this section) which limit the concentration of radioactive materials released to UNRESTRICTED AREAS in accordance with Specification 3.11.1.1 as long as the following conditions are satisfied: (a) the OPERABILITY of 1/2-RE-4014 must be demonstrated in accordance with Specification 4.3.3.10, Table 3.3.13(1b), and (b) the blowdown ion exchangers are isolated (or the decontamination factors for all radionuclides are verifed to be greater than or equal to one for the duration of the release), and (c) the specific activities of radionuclides in the blowdown tank radiation monitor are representative of the activities of the radionuclides in the blowdown effluent line. e) Radiological effluent controls for 1/2-RE-4095
Offsde Dose Colculation Manual ' Page 70 of 298 .
- Revision 2, Change 0 -
'(1) Steam generator blowdown releases via this pathway may continue if any one of the following two conditions are satisfed ,
(per Specification 3.3.3.10): l (a) A steam generator biowdown monitor (either 1/2-RE-4095 ! or 1/2-RE-4014) is OPERABLE (see " OPERABILITY of 1/2-RE-4095"; and " OPERABILITY of 1/2-RE 4014" earlier . In this section) AND the alarm and trip setpoint for this ! monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED ' AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table ll, Column 2, or , 1 (b) a grab sample is collected AND analyzed in accordance ; with the provisions described below: i) analysis shall determine EITHER the gross gamma activity or gross beta activity of the sample ; li) sampling and analysis shall be completed at least once per 12 hours if the specific activity of the steam generator blowdown is greater than 0.01 microcuries per gram LODINE DOSE EQUlVALENT iii) sampling and analysis shall be completed at least ; once per 48 hours if the specific activity of the , steam generator blowdown is less than or equal to -1 0.01 microcuries per gram IODINE DOSE : EQUIVALENT iv). the LOWER LIMITS OF DETECTION (LLDs) for j the gross gamma and/or gross beta analyses are in . -a accordance with the LLDs of Specification 4.11.1.1.1 f) Surveillances for 1/2-RE-4095 (1) Specification 4.3.3.10 requires demonstrating the OPERABILITY j of 1/2-RE-4095 by satisfying the checks, calibrations, and tests l listed below ; (a) CHANNEL CHECK within the past 24 houio l (b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months ] (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1/2-RI-4095 l 2 -r- ,- ye,, -
Offsite Dose Calculation Manual ' Page 71 of 298
, Revkion 2 Change 0 ,
-(1) There are three radiation alarm setpoints associated with the Steam Generator Blowdown Effluent Radiation Monitor. ;
(a) 1/2-Rl4095 fixed high radiation alarm and am matic ; control trip setpoint ; (b) 1/2-R14095 adjustable plant computer high radiation alarm i and manual control trip setpoint (c) 1/2-RI-4095 low radiation alarm setpoint (2) in order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows: (a) The 1/2-Rl4095 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint. , (b) The 1/2-Rl4095 adjustable plant computer high radiation , alarm and manual control trip setpoint will be referred to as ; the adjustable setpoint. (c) The 1/2-Rl4095 low radiation alarm setpoint will be , referred to as the low setpoint. (3) Each of these alarm setpoints are described below, h) The fixed setpoint for 1/2-Rl4095 , i (1) Generalinformation l I (a) This setpoint is considered to be a fixed alarm and trip setpoint. The fixed setpoint is not adjusted for each i release. , (b) Whenever the fixed setpoint is exceeded, discharges from , the steam generator blowdown processing system to UNRESTRICTED AREAS will be automatically suspended. l (c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste i discharged from thg steam generator blowdown i processing system , (d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. (e) The CCNPP Alarm Manual refers to this alarm and trip setpoint as the 1/2-RI-4095 Steam Generator Blowdown Recovery High Alarm. It should be noted that the UFSAR (section 10.2.2A) states, "the blowdown liquid monitor has an alarm setpoint selected to allow an annual average continuous blowdown past the monitor of 10 gpm without exceeding one curie discharged per year, excluding tritium." i I
Offsite Dose Calculation Manual Page 72 of 298 Revision 2, Change 0 (f) This setpoint is integral to the steam generator blowdown discharge monitor, as purchased from the manufacturer. (g) The fixed setpoint is administratively controlled by EN 100. (h) The fixed alarm gnd trip setpoint shall be calculsted as ; described below . (2) Calculating the fixed setpoint for 1/2-RI-4095 (a) The fixed alarm setpoint for 1/2-RI-4095 shall be calculated in accordance with equation 1L. , FIXED SETPOINT FOR 1/2-Rl-4095 Srx. 5 K.,{ ( F/Fu ) h [( Au )( e3 )) + Bkg } Eq.1L' Sn, = the fixed alarm and trip setpoint for 1/2-RI-4095 (cpm) K, = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20 MPC limit (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20. , A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC. A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs. It is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry. The use of a " safety margin"is in accordance with the provisions of NUREG-0133, section 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded." This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint. , l 1 l Per Specification 3.3.3.10. Equation 1L has been derived from NUREG-0133, Addendum, page AA-1. I l
Offsite Dose C:lculation M:nuil Pag)73 of 298 R;vtion 2, Ch:nge 0 Fe
= the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS the dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE Fo
= F + F,, + F u Eq.2L F. = the minimum circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit accepting radwaste) shall be operable when discharging liquid radwaste - via this monitor - to outfall 001.
The flow rate of esch circulating water pump is 200,000 gallons per minute. Additional circulating water pumps may be required as specified in approved chemistry section procedures. If a release of liquid radwaste from the steam generator blowdown system is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4095, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. F., = the minimum salt water system flow rate necessary to release liquid radwaste if the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint. The maximum flow rate for one salt water pump is listed on Attachment 2. If a release of liquid radwaste is to be conducted using less than the minimum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4095, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. Fu = maximum undiluted radwaste flow rate (gpm) Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. Since the steam generator blowdown flow rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump),
Offsite Dose Calculation Mar.ual Page 74 of 298 Revision 2, Change O the steam generator blowdown flow rate need not be considered when calculating the dilution water flow rate. Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required-for the flow measuring device in the effluent line-to verify compliance with Specification 3.3.3.10. A,tn = specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table 11, Note 1 as described below; microcuries per milliliter) In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those DOMINANT AND LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP. Attachment 5 provides further guidance for determining which radionuclides, i, should be used to calculate a fixed setpoint. Values for A it, shall be calculated, as described below, for each DOMINANT RADIONUCLIDE and for the collective total of all LESS DOMINANT RADIONUCLIDES. SPECIFIC ACTIVITY LIMIT FOR EACH RADIONUCLIDE i A,tn = ( f, ) ( A7tn ) Eq.3L f, = a FRACTION which represents the relative activity contribution of nuclide i to the average total effluent activity (unitiess) The average total effluent activity does not include tritium or dissolved and entrained noble gases. This value may be obtained using the guidance provided on Attachment 5. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. A7tn = the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3) This value corresponds to 1 MPC. Artn shall be calculated as shown below.
l l Offsite Dose Calculation M:nual Page 75 of 298 I R: vision 2, Ching3 0 TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC h [( f )( i Au ) / Au]i = 1 Eq. 4L'O A,u = the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table 11, Column 2 (microcuries/cm3) For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table 11, Column 2. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for Au i (per 10 CFR 20, Appendix B, Note 2). 1 = the MPC limit (MPCs) for unrestricted areas This value is based on the MPC limit from 10 CFR 20, Table 11, Note 1. l Bkg = an approximation of the detector background (cpm) instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. (3) Documenting the fixed setpoint for 1/2-RI-4095 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN-1-100. I (4) Changing the fixed setpoint for 1/2-RI-4095 (a) If the fixed setpoint calculated in accordance with equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the , normal operating range of the monitor. (b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired. 1 (c) A setpoint change should be initiated whenever any of the l parameters identified in equation 1L have changed. l 1 l (d) The fixed setpoint should not be changed unless one of l the following occurs: i) the relative activity" of any radionuclide in TYPICAL LIQUID EFFLUENTS has changed by This formula has been derived from 10 CFR 20, Table 11, Notes 1,2, and 3. As determined in accordance with Attachment 5. 1
I L- _
~ ! Offsde Dose Calculation Manual Page 76 of 298 :
Revision 2 Change 0 i greater than 10%, and the new radionuclide l mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ) l li) the minimum dilution water flow rate is not . available for a liquid release, ! iii) the values fated in 10 CFR 20, Table ll, column 2 have changed, iv) the radiation monitor has been recently calibrated, j repaired, or otherwise altered, or v) the monitor is not conservative in its function (see l
" Functions of 1/2-RE-4095" earlier in this section). ,
EN-1-100 contains the administrative controls associated ! (e) with changing and approving the fixed alarm and trip ; setpoint. l i) The adjustable alarm and trip setpoint for 1/2-RI-4095 ; i (1) Generalinformation ; , (a) This setpoint is an adjustable setpoint. The adjustable j setpo'nt is calculated and adjusted prior to each release ! from the steam generator blowdown processing system. ; (b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Specification 4.11.1.1.1). i (c) Whenever the adjustable setpoint is exceeded, discharges i
~
from the steam generator blowdown processing system will be manually suspended. j (d) See Ol-8A for a full list of operator ACTIONS taken in ! response to this alarm. j (e) The adjustable setpoint corresponds to the maximum h concentration of radionuclides anticipated or expected in I discharges from the steam generator blowdown processing system. l (f) The value for the adjustable setpoint is recorded on the ! liquid release permit in accordance with Chemistry section . procedures. ; I (g) This alarm is not integral to the steam generator blowdown l effluent monitor, as purchased from the supplier. ! (h) This alarm is generated by the plant computer which l monitors output from 1/2-RI-4095, and provides an alarm
Y i Offsite Dose Criculation M:nual Page 77 of 298 Revision 2, Change 0 l to plant operators when the adjustable alarm and trip - l setpoint has been exceeded. j (i) - A value for the adjustable ala"m and trip setpoint shall be calculated prior to each rolesse as shown below. (2) Calculating the adjustable setpoint for 1/2-RI-4095 l (a) The adjustable setpoint is t sed on the specific activities 1 ' of radionuclides in the undilt ad liquid waste (as determined by radiochemical analysis per Specification 4.11.1.1.1), and shall be calculated as shown below. ADJUSTABLE SETPOINT FOR 1/2-RI-4095
-f t
S,oj 5 1.50 [ h ( A,u )( e,) + Bkg ] Eq. SLs2 f Where, S adj = the adjustable alarm and trip setpoint for 1/2-RI-4095 (cpm) ! 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical i fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, , (4) errors associated with sample analysis, or (5) errors associated with monitor i calibrations.'8 l t Aiu = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per j milliliter) j e3
= absolute detecter efficiency for nuclide, I (cpm /microcuries per milliliter)
The detector efficiency for each radionuclide may be calculated from data collected ! during calibration of the radiation monitor. Bkg = an approximation of the detector background prior to nitiating the liquid release l (cpm) i (3) Documenting the adjustable setpoint,1/2-RI-4095 (a) Whenever the adjustable setpoint is calculated, the ! specific values chosen for each of the variables shall be !
'* This formula may be derived from NUREG-0133, Addendum, page AA-1.
The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality controllimits. l l
l Offsite Dose Calculation Manuel Page 78 of 298 l Revision 2 Change O documented in accordance with approved chemistry section procedures. (4) Changing the adjustable alarm and trip setpoint for 1/2-RI-4095 (a) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) in all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint. (c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint. (d) Whenever 1/2-RI-4095 is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release from the steam generator blowdown processing system. (e) Plant Operating instructions (e.g., Ol-8A) contain I administrative controls associated with entering the adjustable setpoint in the plant computer, j) The low setpoint for 1/2-RI-4095 (1) This alarm is integral to the steam generator blowdown effluent monitor, as purchased from the manufacturer. (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. (3) The low alarm setpoint may be used to determine OPERABILITY of this monitor (per Specification 4.3.3.10, CHANNEL FUNCTIONAL TEST). (4) The low alarm setpoint may be used to terminate a release in the i event 1/2-RE-4095 fails (i.e., downscale failure or circuit failure). ! (5) Changes to the low alarm setpoint are controlled by EN-1-100. l (6) The ODCM does not address the calculations associated with the low alarm setpoint.
- 3. Steam Generator Blowdov;n Tank Radiation Monitors (1/2-RE-4014) a) General description of 1/2-RE-4014 (1) number of radiation elements: one per unit (2) Type of radiation element: off-line scintillation detector (3) output; analog
Offsite Dose Calculation Manual Page 79 of 298 Revision 2, Change 0 l (4) Designations for radiation indicators ; (a) 1-RI-4014 ; (b) 2-RI-4014 - l I (5) units for radiation indicator: counts per minute (6) supplier: Westinghouse (7) A 3 gallon per minute sample is cooled, passed through the I detector, and pumped back into the steam generator blowdown , tank. b) Functions of 1/2-RE-4014 (1) continuously measure the activity contained in an off-line sample : of the steam generator blowdown tank ( Specification 3.3.3.10) (2) continuously indicate (via 1/2-RI-4014) the specific activity in an off-line sample of the steam generator blowdown tank ( Specification 3.3.3.10) (3) alarm (via 1/2-RI-4014) prior to exceeding the 10 CFR 20, i Appendix B, Table ll, Column 2 limits (per Specification 3.11.1.1) i (Note: A technical evaluation shall be conducted to ensure compliance with UFSAR 10.2.2.4.) (4) automatically terminate steam generator blowdown releases to UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4014) exceeds the fixed alarm setpoint. c) OPERABILITY of 1/2-RE-4014 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s) (2) The functions of this monitor are listed in section (b) above. d) Monitors equivalent to 1/2-RE-4014 (1) 1/2-RE-4014 is normally considered the PRIMARY MONITOR for - measuring activity released via the steam generator blowdown processing system, and 1/2-RE-4095 is normally considered the : BACKUP MONITOR for measuring activity released via the steam I generator blowdown processing system. (2) In the event PRIMARY MONITOR (1/2-RE-4014) is inoperable or l otherwise unavailable, the BACKUP MONITOR (1/2-RE-4095) is : able to fulfill the measuring, indicating, and alarming functions e normally provided by the PRIMARY MONITOR. j (3) 1/2-RE-4095, Steam Generator Blowdown Effluent Radiation - Monitor, performs measurement, indication, alarm, and isolation l r
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' Offsite Dose Calculation Mr.nual Page 80 of 298 i Revision 2, Change 0 j i
functions equivalent to 1/2-RE-4014 (see " Function of 1/2-RE-4014" earlier in this section), unless 1/2-RE 4095 is bypassed as l described below. .; (4) it should be noted that if the steam generator blowdown processing system heat exchangers are bypassed, it is possible : for blowdown flow to bypass 1/2-RE 4095 (the steam generator l blowdown effluent radiation monitor). If blowdown flow is allowed j to bypass 1/2-RE-4095, the minimum channels operability l requirement of Specification 3.3.3.10 may not be satisfed (unless
- 1/2-RE-4014 is operable). j i
e) Radiological effluent controls for 1/2-RE-4014 ! (1) Steam generator blowdown releases via this pathway may l continue if any one of the following two conditions are satisfed ; (per Specification 3.3.3.10): i (a) A steam generator blowdown monitor (either 1/2-RE-4095 ! or 1/2-RE 4014) is OPERABLE (see " OPERABILITY of 1/2-RE-4095"; and " OPERABILITY of 1/2-RE 4014" earlier in this section) AND the alarm and trip setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED ; AREAS are less than the concentrations specified in 10 l CFR 20, Appendix B, Table ll, Column 2, or j (b) a grab sample is collected AND analyzed in accordance with the provisions described below: ; i) - analysis shall determine EITHER the gross gamma j activity or gross beta activity of the sample li) sampling and analysis shall be completed at least ! once per 12 hours if the specific activity of the steam generator blowdown is greater than 0.01 , microcuries per gram IODINE DOSE EQUlVALENT ! I lii) sampling and analysis shall be completed at least l once per 48 hours if the specific activity of the i steam generator blowdown is less than or equal to , 0.01 microcuries per gram IODINE DOSE , EQUlVALENT iv) the LOWER LIMITS OF DETECTION for the grnss ; gamma and/or gross beta analyses are in i accordance with the LLDs of Specification ? 4.11,1.1.1 ! f) Surveillances for 1/2-RE-4014 ; i t
?
i i
- Offsite Dose Calculation Manual Page 81 of 298
' Revtion 2, Change 0 (1)- Specification 4.3.3.10 requires demonstrating the OPERABILITY of 1/2-RE-4014 by satisfying the checks, calibrations, and tests listed below (a) . CHANNEL CHECK within the past 24 hours (b) . SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months l
i g) Setpoints for 1/2-RI-4014 L (1) There are three radiation alarm setpoints associated with the Steam Generator Blowdown Tank Radiation Monitor f (a) 1/2-RI-4014 fixed high radiation alarm and automatic control trip setpoint (b) 1/2-RI-4014 adjustable plant computer high radiation alarm and manual control trip setpoint (c) 1/2-RI-4014 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will . refer to these setpoints as follows: (a) The 1/2-RI-4014 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint. (b) The 1/2-RI-4014 adjustable plant computer high radiation alarm and manual control trip setpoint will be referred to as the adjustable setpoint. (c) The 1/2-RI-4014 low radiation alarm setpoint will be referred to as the low setpoint. (3) Each of these alarms is described below. h) The fixed alarm and trip setpoint for 1/2-RI-4014 (1) General Information (a) This alarm and trip setpoint is considered to be a fixed setpoint. The fixed setpoint is not adjusted for each release. (b) Whenever the fixed setpoint is exceeded, discharges from j the steam generator blowdown processing system to UNRESTRICTED AREAS will be automatically suspended. 1
r Offsite Dose Calculation M:nual Page 82 of 298 Revision 2, Change 0 (c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the steam generator blowdown processing system." (d) The current value for the fixed alarm and trip setpoint is specified in the CCNPP Alarm Manual. (e) The CCNPP Alarm Manual refers to the fixed setpoint as the 1/2-RI-4014 Steam Generator Blowdown High Alarm. (f) The fixed setpoint is integral to the liquid release discharge monitor, as purchased from the manufacturer. (g) The fixed alarm and trip setpoint is administratively controlled by EN-1-100. (h) The fixed alarm and trip setpoint shall be calculated as described below'5 . (2) Calculating the fixed alarm and trip setpoint for 1/2-RI-4014 (a) The fixed alarm and trip setpoint for 1/2-RI-4014 shall be calculated as follows: s FIXED ALARM AND TRIP SETPOINT FOR 1/2-RI-4014 Sr, 5 Kg { ( Fa /uF ) h [( Au ) ( e;)] + Bkg } Eq.1 L'8 Where, Sr, = the fixed alarm and trip setpoint for 1/2 RI-4014 (cpm) Kg = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20 MPC limit (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20. A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC. A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs. E lt is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. It should be noted that the UFSAR (sectioa 10.2.2.4) states, "the blowdown liquid monitor has an alarm setpoint selected to allow an annual average continuous blowdown past the monitor of 10 gpm without exceeding one curie discharged per year, exc'ading tritium." . Per Specification 3.3.3.10.
" Equation 1L has been derived from NUREG-0133, Addendum, page AA-1.
i
)
Offsite Dose CIleulation Manual Page 83 cf 298 { Revision 2. Change 0 The use of a " safety margin"is in accordance with the provisions of NUREG-0133, SECTION 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded " This safety margin will prevent minor fluctuations in the nominal circulating water - flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint. Fe
= the dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE Fe
= F,, + F., + Fu E!q. 2L F, = the minimum circulating water system flow rate necessary to conduct liquid releases e ~{
A minimum of two circulating water pumps (one circulating water pump per conduit { accepting radwaste) shall be operable when discharging liquid radweste - via this monitor - to outfall 001. The flow rate of each circulating water pump is 200,000 gallons per minute. Additional circulating water pumps may be required as specified in approved chemistry section procedures. If a release of liquid redweste from the steam generator blowdown system is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4014, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. F, = the minimum salt water system flow rate necessary to release liquid radwaste if the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint. The maximum flow rate for one salt water pump is listed on Attachment 2. If a release of liquid radweste is to be conducted using less than the minimum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4014, or otherwise comply with the ACTION requirements of Specification 3.3.3.10. l 1 1 i
l 1 Offsite Dose CCiculation Manual Page 84 of 298 Revision 2, Change 0 Fu = maximum undiluted radwaste flow rate (gpm) Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. Since the steam generator blowdown flow rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the steam generator blowdown flow rate need not be considered when calculating the dilution water flow rate. Since the maximum undiluted radwaste flow rate is used for calculating the fixed - setpoint, a flow setpoint is not required-for the flow measuring device in the effluent line-to verify compliance with Specification 3.3.3.10. A itn = specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated in accordance with 10 CFR 20, Appendix B, Table ll, Note 1 as described below; microcuries per milliliter) In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those DOMINANT AND LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE RELEASES from CCNPP. Attachment 5 provides further guidance for determining which radionuclides, i, shouid be used to calculate a fixed setpoint. Values for Aitnshall be calculated, as described below, for each DOMINANT RADIONUCLlDE and for the collective total of all LESS DOMINANT RADIONUCLIDES. SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE, i Au = (f)(Ann) i Eq.3L f, = a FRACTION which represents the relative activity contribution of nuclide i to the average total effluent activity (unitiess) The average total effluent activity does not include tritium or dissolved and entrained noble gases. This value may be obtained using the guidance provided on Attachment 5. Ann = the sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3) This value corresponds to 1 MPC. Calculate the value of Ann as shown below. l
Offsit3 Dose Cilculation M nual Pags 85 of 298 Revision 2, Change 0 TOTAL SPECIFIC ACTIVITY CORRESPONDING TO 1 MPC AT THE SITE BOUNDARY h [ ( f )i ( Am ) / A iu ] = 1 Eq. 4L'7 Aul
= the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table ll, Column 2 (microcuries/cm3)
For all the DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table 11, Column 2. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 3E-8 microcuries per milliliter as the value for Au i (per 10 CFR 20, Appendix B, Note 2). 1 = the MPC limit (MPCs) for unrestricted areas This value is based on the MPC limit from 10 CFR 20, Table 11, Note 1. e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) i The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (cpm) instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. (3) Documenting the fixed setpoint for 1/2-Rl-4014 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be , documented in accordance with EN-1-100. (4) Changing the fixed setpoint for 1/2-RI-4014 (a) If the fixed setpoint calculated in accordance with equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed alarm setpoint may be established at values lower than the maximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenever any of the parameters identified in equation 1L (identified in this section of the ODCM) have changed.
" This formula has been derived from 10 CFR 20, Table 11, Notes 1,2, and 3.
I
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. Offsite Dose CalcUlstion Manu 1 Page 86 of 298 -
Revision 2, Change 0 (d) The fixed setpoint should not be changed unless one of ,
' the following occurs: ~!
i) the relative activity 1eof any radionuclide in , TYPICAL LIQUID EFFLUENTS has changed by ) greater than 10%, and the new radionuclide l' mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the minimum dilution water flow rate is not available for a liquid release, iii) the values listed in 10 CFR 20, Table 11, column 2 have changed, j iv) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or ; v) the monitor is not conservative in its function (see
" Functions of 1/2-RE-4014" earlier in this section).
(e) EN-1-100 contains the administrative controls associated I with changrg and approving the fixed setpoint. j l} The adjustable alarm and trip setpoint for 1/2-RI-4014 l 4 (1) Generalinformation l (a) This setpoint is an adjustable setpoint. The adjustable 1 setpoint is calculated and adjusted prior to each release i from the steam generator blowdown processing system.
.l I
(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste t (as determined by radiochemical analysis per ! Specification 4.11.1.1.1). j (c) Whenever the adjustable setpoint is exceeded, discharges ; from the steam generator blowdown processing system I will be manually suspended. l (d) See Ol-8A for a full list of operator ACTIONS taken in response to this alarm. l t (e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the steam generator blowdown ! processing system. l (f) The value for the adjustable setpoint is recorded on the , liquid release permit in accordance with Chemistry section l procedures. As determined in accordance with Attachment 5.
i Offsite Dose Calculation M:nu;l Page 87 of 298 -l Revision 2, Change 0
-(g) This alarm is not integral to the steam generator blowdown tank radiation monitor, as purchased from the supplier.
(h) This alarm is generated by the plant computer which monitors output from 1/2-RI-4014, and provides an alarm to plant operators when the 1/2-RI-4014 adjustable setpoint has been exceeded. (i) A value for the adjustable alarm and trip setpoint shall be , calculated prior to each release as shown below. . t (2) Calculating the adjustable setpoint for 1/2-RI-4014 (a) The adjustable alarm and trip setpoint is based on the specific activity of the radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Specification 4.11.1.'.1), and the alarm and trip setpoint is calculated as shown below. , ADJUSTABLE ALARM AND TRIP SETPOINT FOR 1/2-RI-4014 S,oj S 1.50 [ h ( A iu) ( e3 ) + Bkg ] Eq.SL" S,oj = the adjustable alarm and trip setpoint for 1/2-RI-4014 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor i response (unitless) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical i fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.20 A,o = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (cpm) (3) Documenting the adjustable setpoint for 1/2-RI-4014 " Equation SL has been derived from NUREG-0133, Addendum, page AA-1. The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality control limits. I
4 Page 88 of 298' Offsite Dose Calculation Manual l Revision 2, Change 0 (a) Whenever the adjustable setpoint is calculated, the ; specific values chosen for each of the variables shall be : documented in accordance with approved chemistry 1 section procedures. (4) Changing tho' adjustable setpoint for 1/2-Rl-4014 l (a) If the adjustable setpoint exceeds the maximum range of l the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) in all cases, the adjustable setpoint shall be set to a value ; which is less than or equal to the fixed setpoint. ; r (c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint. , r (d) Whenever 1/2-RI-4014 is operable, the calculated value for the adjustable setpoint shall be entered into the plant , computer prior to each release from the steam generator i blowdown and processing system. (e) Plant Operating instructions (e.g., Ol-8A) contain administrative controls associated with entering the adjustable setpoint in the plant computer.
]
j)' The low alarm setpoint for 1/2-Rl4014 ! i (1) This alarm is integral to the steam generator blowdown tank monitor, as purchased from the manufacturer. ; (2) The current value for the low alarm setpoint is specifed in the i CCNPP Alarm Manual. l (3) Changes to the low alarm setpoint are controlled by EN-1-100. ! (4) The ODCM does not address the calculations associated with the low alarm setpoint. I J E. Limits On Radionuclide Concentrations in Liquid Effluents i I
- 1. Introduction a) 10 CFR 20, Appendix B, specifies concentration limits associated with the release of radioactive materials to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls
)
i I
Offsite Dose Calculation Manual Page 89 of 298 Revision 2, Change O f a) The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases (per Specification 3.11.1.1). b) It should be noted that NUREG-0133 specifies that the concentration of radioactive materials in liquid effluents to UNRESTRICTED AREAS shall be limited to 2 E-4 microcuries per milliliter for dissolved or entrained noble gases, this control has not been incorporated into the CCNPP Technical Specifications, and as a result, the ODCM does not include calculations for same. c) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirements a) Routine surveillances for BATCH RELEASES (1) Sample each " BATCH" of radioactive liquid waste prior to its release (per Specification 4.11.1.1.1).
(2) Determine the concentrations of principle gamma emitters (including, but not limited to, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141,1-131, Mo-99, and Ce-144) in the
" BATCH" sample, prior to the " BATCH" release (per Specification 4.11.1.1.1).
(3) Determine the concentration of tritium contained in a monthly i COMPOSITE sample at least once per month (per Specification 4.11.1.1.1). , (4) Determine the concentrations of Sr-89 and Sr-90 contained in a quarterly COMPOSITE sample at least once per quarter (per Specification 4.11.1.1.1). (5) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Specification 4.11.1.1.2). ; b) Routine surveillances for CONTINUOUS releases i (1) Sample CONTINUOUS releases of radioactive liquid waste at least once per month (per Specification 4.11.1.1.1). l (2) Determine the concentrations of princide gamma emitters (including, but not limited to, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141,1-131, Mo-99, and Co-144) in the undiluted, CONTINUOUS waste stream sample (per Specification 4.11.1.1.1). (3) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Specification 4.11.1.1.2).
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Offsite Dose Calculation Manual Page 90 of 298 Revision 2, Change 0 .
- 4. Responsible Plant Organizations a) The Chemistry Section is responsible for performing the sampling, -
analysis, and calculations required by the above surveillances. b) The conditions which initiate the required surveillances are contained in the following section. ,
- 5. Initiating Conditions ' I a) The surveillances for BATCH RELEASES shall be performed prior to (
each BATCH RELEASE 2s and may be parformed more often as specified in approved chemistry section proce;dures. b) The surypillances for CONTINUOUS releaves shall be performed at least { monthly' (untilthe ONTINUOUS release has been terminated) and, if f activity is identified in the CONTINUOUS waste stream, the surveillances may be performed more often as specifed in approved , chemistry section procedures. l
- 6. Calculation Methodology !
i a) At CCNPP, there are two methodologies for calculating the : concentrations of radionuclides in the receiving waters, at the point of , release to UNRESTRICTED AREAS, resulting from the discharge of j liquid waste. : (1) The rigorous method shall be used IF a computer. system and the ! appropriate software are available. ; (2) The simplified method may be used IF a computer system and the j appropriate software are NOT available. I t (3) These methods, as well as additional supporting information, are presented in the following sections. , b) Rigorous method j (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software i are available. ! (2) If a computer system and the appropriate software are available, ensure the concentrations of radionuclides in UNRESTRICTED AREAS are less than one MPC by verifying the following inequality is true: LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS ! (RIGOROUS METHOD) 21 Per Specification 4.11.1.1.1. i 22 l Per Specification 4.11.1.1.1. f The LOWER LIMITS OF DETECTION shall conform to Specification 4.11.1.1.1, Table 4.11-1. l
-- - F -w 1
i Offsit] Dose C:lculation Minu:1 Page 91 cf 298 Revision 2. Change 0 ( Fu / F,) h ( A,u / Au i )51 Eq 6L24 F, = the actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate. The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE Fo
= F + F., + Fu Eq.2L F. = the actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.
F, = the salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. F, = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. 1-Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. f Au = the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table ll, Column 2 (microcuries/cm3) A,u = the specific activity of nuclide, i, in the undiluted liceid radwaste (microcuries per milliliter) 1 = the MPC limit (MPCs) for unrestricted areas This value is based on the MPC limit from 10 CFR 20, Table ll, Note 1. c) Simplified method (1) Whenever a computer system and appropriate software are unavailable to perform the rigorous calculations described in the l
" Equation 6L has been derived from 10 CFR 20, Appendix B. Table ll, Note 1
l l l Offsite Dose C7.lculation Manual P ga 92 of 298 R: vision 2, Cheng3 O previous section, erssure the concentrations of radionuclides in UNRESTRICTED Af TEAS are less than one MPC by verifying the following inequality is true. : LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (SIMPLIFIED METHOD) { Fu /[( Fo )( Anstu )( K.,) } } h Anu 51 Eq. 7L 2s F, = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. ! Fo = the actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate. DILUTION WATER FLOW RATE Fo
= Fe , + F., + F, Eq.2L F, e
= the actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.
F, = the actual salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Ansiu = the specific activity limit for 1-131 corresponding to the limiting concentration specified in 10 CFR 20, Appendix B, Table ll, Column 2 This value is 3E-7 microcuries per milliliter. A,, = the specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter) i '5 this equation has been derived from 10 CFR 20, Appendix B, Table ll, Note 1. l
Offsit) Dose Calculation M:nu;l Page 93 of 298 Revision 2. Change 0 K ,L = . a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to . the activity limit of 10 CFR 20, Appendix B, Table ll, Column 2, (unitiess) (per Specification 3.11.1.1) The safety factor chosen shall be less than or equal to 1.00. This ensures the activity is always less than or equal to the activity limit of 10 CFR 20, Appendix B, Table ll, Column 2. A safety factor of 1.00 will yield a activity which corresponds to the 10 CFR 20, Appendix B Table 11, Column 2 activity limit. A safety factor of 0.500 will yield an activity which corresponds to one-half the ; activity limit of 10 CFR 20, Appendix B, Table ll, Column 2. J lt is recommended that a safety factor of 1.0 be used for calculating the activity, i however, other values-not to exceed 1.00--may be used as directed by the General ! Supervisor Chemistry. ! The particular value selected for the safety factor is somewhat arbitrary, however a ! safety factor does provide plant personnelwith a degree of administrative control over the use of simplified equations for generating radioactive liquid release permits. . This administrative controlis designed to minim!ze the possibility of violating 10 CFR 20, Appendix B. Table ll, Column 2 limits whenever simplifying assumptions are used. i The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the j licensees should, "... in addition to complying with the limits set forth in this part [10 t CFR 20), make every reasonable effort to maintain radiation exposures, and > releases of radioactive materials in effluents to UNRE*TRICTED AREAS, as low as i is reasonably achievable." l
^
This safety factor has been included in equation 7L to account for any potential nonconservatism associated with applying the I-131 MPC limit to all radionuclides l identified in the liquid release. Such nonconservatism could conceivable be present ; whenever radionuclides which have an MPC value higher than the 1-131 MPC limit : are present in a liquid release. ; d) Once the rigorous or simplified calculations have been completed, the calculation results are compared to the applicable limits and corrective : ACTIONS are initiated as described below.
- 7. Corrective ACTIONS t
a) Chemistry Section surveillance procedures (e.g., CP-212) shall . contain/and or reference administrative and/or Technical Specification limits for concentration of radionuclides in liquid effluents and shall specify corrective ACTIONS to be initiated when these limits are ; exceeded. l t b) Refer to Specification 3.11.1.1 for ACTIONS to be taken in the event the ! concentrations of radionuclides in UNRESTRICTED AREAS exceed one - i MPC.
. _ . . -- , _ _. _ __ __ ~_ _ - . - _- ~
Offsite Dose Calculation Manu;l Page 94 of 298 Revision 2, Change 0 F. Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents
- 1. Introduction a) Appendix 1 to 10 CFR 50 specifies total body dose limits and organ dose limits associated with the release of radioactive liquids to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 3 mrems per calendar quarter and 6 mrems per calendar year ( Specification 3.11.1.2).
b) The organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 10 mrems per calendar quarter and 20 mrems per calendar year ( Specification 3.11.1.2). c) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirement (s) a) Cumulative total body doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the calendar quarter, the current calendar year, and the previous 92 days-shall be calculated, in accordance with equation BL, at least once per 60 days (per Specification 4.11.1.2 and 4.11.1.3).
b) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the current i calendar quarter, the current calendar year, and the previous 92 days- ! shall be calculated, in accordance with equation 8L, at least once per 60 days (per Specification 4.11.1.2 and 4.11.1.3).
- 4. Responsible Plant Organizations a) The Chemistry Section is responsible for performing the surveillances, i listed above, whenever the appropriate initiating conditions, listed below, l are present.
- 5. Initiating Conditions
)
a) Perform the surveillances, listed above, at least once per 60 days (per Specification 4.11.1.2).
Offsite Dose Calculation Manu;l Page M of 298 Revrion 2, Change 0 b) For BATCH RELEASES, perform the surveillances, listed above, prior to each BATCH RELEASE of radioactive liquid waste in accordance with approved chemistry section procedures. j c) For CONTINUOUS releases, perform the surveillances, listed above, at l least monthly (until the CONTINUOUS release has been terminated) and, if activity is identified ** in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved chemistry section procedures. d) Whenever the correct initiating conditions are present, the calculations required by the above mentioned surveillance (s) shall be completed in } accordance with the methodology listed in the next section. l
- 6. Calculation Methodology a) The cumulative total body dose and the cumulative organ doses (for the current calendar month, current calendar quarter, previous 92 days, and current calendar year) shall be calculated as follows:
CUMULATIVE TOTAL BODY OR ORGAN, o, DOSE FROM LIQUID RELEASES, r , I DTol
- UorEq.BL l
Drot = the sum total of the total body or organ, o, dose for allliquid releases discharged during the applicable time interval D, = the organ or total body dose resulting from release, r Calculate the values of Do, for each liquid release as described below. b) At CCNPP, two methods exist for calculating D , (i.e., the total body and organ doses resulting from any single release of radioactive liquid to an f UNRESTRICTED AREA). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous method
** The LOWER LIMITS OF DETECTION shall conform to Specification 4.11.1.1.1, Table 4.11-1.
Offsite Dose CCiculation Manual Page 96 of 298 Revision 2, Change 0 (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the dose commitments due to each release of radioactive liquid to an UNRESTRICTED AREA shall be calculated in accordance with the following equation: r DOSE TO THE TOTAL BODY OR ORGAN, o, FROM A LIQUID RELEASE (RIGOROUS EQUATION) De = { Vu / [ ( 60 )( Fd > i ) o < < ^,u ) < c ) > Ea.eL Where, Fo
= actual dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE Fa
= Fe , + F., + F u Eq.2L F, e
= actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.
F, = actual salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the Mtal dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used to equation 2L. 1 Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. V, = volume of undiluted radwaste (gallons) 27 Equation 9L has been derived from NUREG-0133,4.3. I
Offsite Dose C'iculation M:nu:1 Page 97 of 298 Revision 2, Change O A,, = specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter) Ce
= liquid release dose factor for nuclide, i, and organ, o (mrem /hr per microcurie /ml)
The liquid release dose factors for principal gamma and beta emitters are listed in Attachment 6. j The liquid release dose factors for principal gamma and beta emitters were obtained in accordance with the methodology of NUREG-0133, section 4.3.1 (for salt water sites). 60 = a constant, the number of minutes per hour , (3) In the event a computer system is unavailable, a simplified equation may be used to calculate the total body and organ dose , commitments due to individual liquid releases. (4) The simplified method is presented below. 1 d) Simplified methods i (1) Whenever a computer system is unavailable to perform the rigorous total body dose calculations described in the previous section, the totsl body dose commitments--due to each release of I radioactive liquid to an UNRESTRICTED AREA-may be l calculated in accordance with equation 10L i l (2) Whenever a computer system is unavailable to perform the lj rigorous organ dose calculations described in the previous section, the dose commitments-to the maximum exposed organ, l due to each release of radioactive liquid to an UNRESTRICTED ! AREA-may be calculated in accordance with equation 11L l I l TOTAL BODY DOSE FROM A LIQUID RELEASE (SIMPLIFIED EQUATION) De = { [ ( 58.6 ) ( Vu ) ) / [ ( Kg ) ( Fe ) ] } h A Eq.101.2s De = dose commitment, to the total body, due to each release of radioactive liquid to an UNRESTRICTED AREA 58.6 = a conversion constant which includes:
- 1) 1.33E4 mrem /hr per microcurie /mi (the dose factor for Cs-134 to the lower gastrointestinal tract)
- 2) 1.000 hr/60.00 min 2'
Equations 10L has been derived from NUREG-0133,4.3. l _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _______________________________________________________-__A
Offsite Dose Calculation Manual Page 98 of 298 Revision 2, Change 0 ) i
- 3) 1.000 gallons /3.785 liters i I
Vu = volume of undiluted radwaste (liters) l Kg = a constant, actually a safety factor, which is the ratio of the CCNPP total body dose I limit to the total body dose limit of Specification 3.11.1.2, (unitiess) ; The safety factor chosen shall be less than or equal to 1.00. This ensures the total body dose is always less than or equal to the total body dose limit of Specification i 3.11.1.2. A safety factor of 1.00 will yield a total body dose which corresponds to the total body dose limit of Specification 3.11.1.2. A safety factor of 0.500 will yield an total body dose which corresponds to one-half the total body dose limit of Specification 3.11.1.2. It is recommended that a safety factor of 1.0 be used for calculating the total body dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release permits. This administrative controlis designed to minimize the possibility of violating Specification 3.11.1.2 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." This safety factor has been included in equation 10L to account for any potential nonconservatism associated with applying the Cs-134 gastrointestinal dose conversion factor to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor greater than that of Cs-134 are present in a liquid release. Fe
= actual dilution water Cow rate (gpm) prior to the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.
The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE 1 Fa = F + F., + F u Eq.2L l
Offsite Dose Calcuttion Minu-J Page 99_cf 298 Revision 2, Change 0 F. = actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute. F, = actual salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm) If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. A,o = specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter) DOSE TO THE ORGAN, o, FROM A LIQUID RELEASE (SIMPLIFIED EQUATION) D, = { [( 449 )( Vu )) / [( K.,) ( Fo ) } } h A iu Eq.11L2s D, = the dose commitment to the maximum exposed ORGAN due to each release of radioactive liquid waste to an UNRESTRICTED AREA 449 = a conversion constant which includes:
- 1) 1.02E5 mrem /hr per microcurie /ml (the dose factor for 1-131 to the thyroid)
- 2) 1.000 hr/60.00 min
- 3) 1.000 gallons /3.785 liters V, = volume of undiluted radwaste (liters)
K, = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Specification 3.11.1.2, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the organ : dose is always less than or equal to the organ dose limit of Specification 3.11.1.2. ! A safety factor of 1.00 will yield a organ dose which corresponds to the organ dose limit of Specification 3.11.1.2. I l " Equations 11L has been derived from NUREG-0133,4.3. I
. , . . . . . - - -. .- - -. ~_ .- - - -
l l
. Offsite Dose Calculation Minual - Page 100 of 298 Revision 2, Change O A safety factor of 0.500 will yield an organ dose which corresponds to one-half the - '!
organ dose limit of Specification 3.11.1
- It is recommended that a safety factor of 1.0 be used for calculating the organ dose, l however, other values-not to exceed 1.00-may be used as directed by the General
. Supervisor Chemistry. ~j The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control j over the use of simplified equations for generating radioactive liquid release permits. -
This administrative control is designed to minimize the possibility of violating : Specification 3.11.1.2 when simplifying assumptions are used. ; The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effort to maintain radiation exposures, and , releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." . This safety factor has been included in equation 11L to account for any potential t nonconservatism associated with applying the 1-131 thyroid dose conversion factor , to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor , greater than that of I-131 are present in a liquid release. ! Fa
= dilution water flow rate (gpm) prior to the point of release to UNRESTRICTED ,
AREAS i The actual dilution water flow rate is the sum. of the circulating water flow rate, the , salt water flow rate, and the undiluted radwaste flow rate. i The dilution water flow rate shall be calculated in accordance with equation 2L. DILUTION WATER FLOW RATE Fa
= F , + F., + F. Eq.2L T t
F, = actual circulating water system flow rate : The flow rate of each circulating water pump is 200,000 gallons per minute. - F., = salt water system flow rate if the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L. The maximum flow rate for one salt water pump is listed on Attachment 2. Fu = actual undiluted radwaste flow rate (gpm)
Offsite Dose Calculation Manu;l Page 101 cf 298 Revision 2, Ch:nge 0 if the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L. Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachments 2 and 3. A,u = specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)
- 7. Corrective ACTIONS 1
Chemistry Section surveillance procedures (e.g., CP-212) shall l a) contain/and or reference administrative and/or Specification limits for ( cumulative total body doses or cumulative organ doses resulting from ' l liquid effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded. b) Refer to Specification 3.11.1.2 for ACTIONS to be taken in the event the calculated cumulative total body dose exceeds 3 mrem per calendar quarter or 6 mrem per calendar year. 1 c) Refer to Specification 3.11.1.2 for ACTIONS to be taken in the event the l calculated cumulative organ dose-for any organ-exceeds 10 mrem per ( calendar quarter or 20 mrem per calendar year. G. Limits For The Liquid Waste Processing System
- 1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the liquid waste processing system for the purpose of controlling effluents to the environment.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The liquid radwaste processing system shall be used to reduce the quantity of radioactive materials in liquid waste released to the environment whenever the total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 0.36 mrem for the previous 92 days (per Specification 3.11.1.3).
b) The liquid radwaste processing system shall be used to reduce the quantity of radioactive materials in liquid waste released to the environment whenever the organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 1.20 mrem for the previous 92 days (per Specification 3.11.1.3).
Offsite Dose Calculation Manual Page 102 of 298 Revision 2, Change 0 i c) The routine surveillances which are performed to verify compliance with' ! this radiological effluent controls are described below. I
- 3. Surveillance Requirement (s) !
a). The previous 92-day, cumulative, total body dose-to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-shall be calculated, as described in ; the ODCM, at least once per 60 days (per Specification 4.11.1.3). ! b) The previous 92-day, cumulative, organ doses-to MEMBERS OF THE : PUBLIC in UNRESTRICTED AREAS-shall be calculated, as described in i the ODCM, at least once per 60 days (per Specification 4.11.1.3). ; c) The CCNPP organization (s) responsible for performing these surveillances are identified in the next section. i
- 4. Responsible Plant Organization (s) a) The Chemistry Secuon is responsible for performing the surveillances, !
listed above, whenever the appropriate initiating conditions, listed below, ' are present.
- 5. Initiating Conditions l a) Perform the surveillances, listed above, at least once per 60 days (per i Specification 4.11.1.2). i b) For BATCH RELEASES, perform the surveillances, listed above, prior to !
each BATCH RELEASE of radioactive liquid waste in accordance with j approved c,hemistry section procedures. ; I c) For CONTINUOUS releases, perform the surveillances, listed above, at ; least monthly (until thg CONTINUOUS release has been terminated) and, i 8 if activityisidentified in the CONTINUOUS waste stream, the ' surveillances may be performed more often as specified in approved chemistry section procedures. , d) Whenever the correct initiating conditions are present, the calculations I required by the above mentioned surveillance (s) shall be completed in ; accordance with the methodology contained in the following section. , i
- 6. Calculation Methodology a) The cumulative total body dose and the cumulative organ doses for the previous 92 days shall be calculated in accordance with equation 8L j found in the section, " Limits On Cumulative Total Body Doses And i Cumulative Organ Doses For Liquid Effluents", found elsewhere in the l ODCM.
- 7. Corrective ACTIONS The LOWER LIMITS OF DETECTION shall conform to 4.11.1.1.1 Table 4.11 1.
l I l
. j Offsite Dose Calculation Manual Page 103 of 298 l I
Revtion 2, Change 0 a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification i limits for cumulative total body doses or cumulative organ doses resulting from liquid effluents and shall specify corrective ACTIONS to be initiated , when these limits are exceeded. i b) Refer to Specification 3.11.1.3 for ACTIONS to be taken in the event the calculated cumulative total body dose exceeds 0.36 mrem for the , previous 92 days. c) Refer to Specification 3.11.1.3 for ACTIONS to be taken in the event the ; calculated cumulative organ dose-for any organ--exceeds 1.2 mrem for the previous 92 days. l
Offsite Dose Calculation Manu:1 Paga 104 of 298 Revision 2, Change 0 i VI. RADIOACTIVE GASEOUS EFFLUENTS A. Release Pathways [B527] !
- 1. Introduction l I
a) Radioactive gaseous waste generated from operation of CCNPP may be released to the atmosphere. b) By design (i.e., in the absence of primary-to-secondary leaks), thea are , 2 pathways by which waste gas from the site may be discharged to t;'e t atmosphere. These pathways are listed below. Generalinformation related to each of these potential release pathways is contained on Attachment 7. (1) Unit 1 main vent stack (2) Unit 2 main vent stack c) Depending on plant conditions, (e.g., primary-to-secondary leaks) a potential exists for the release of radioactive materials from other pathways. These pathways are listed below. Generalinformation related to each of these potential release pathways is contained on Attachment 8. (1) auxiliary boiler deaerator (2) steam generator atmospheric steam dump system (3) plant nitrogen system (4) turbine building ventilation exhaust (5) emergency air lock (6) plant compressed air (7) main steam line penetrations d) All of these pathways are described below.
- 2. Unit 1 Main Vent Stack a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 1 main vent stack.
b) The radioactive gaseous waste is mixed with and diluted by the outside air and building exhausts prior to exiting the Unit 1 main vent stack. c) The Unit 1 main vent stack is secured to the Unit 1 reactor containment building.
Offsite Dose Calculation Manual Page 105 of 298 l Revision 2. Change O d) The top of the Unit 1 main vent stack is at elevation 203.5 feet (mean sea level, MSL), and as such is 10.1 feet above the top of the reactor l containment building dome. As a result, the Unit 1 main vent stg'ek does not qualify as a " free-standing" stack greater than 80 meters tall . e) The Unit 1 main vent stack is designed to accept gaseous radioactive waste from various sources. Sources which may contribute radioactive ; material to the Unit 1 main vent stack are tabulated in Attachment 7. 3
- 3. Unit 2 Main Vent Stack l a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 2 main vent stack. ,
b) The Unit 2 main vent stack is designed to accept radioactive gaseous ! waste from various sources. t c) The radioactive gaseous waste is mixed with and diluted by the outside air and building exhausts prior to exiting the Unit 2 main vent stack. d) The Unit 2 main vent stack is secured to the Unit 2 reactor containment building. l e) The top of the Unit 2 main vent stack is at elevation 203.5 feet (MSL), and as such is 10.1 feet above the top of the reactor containment building dome. As a result, the Unit 2 main vent stack does not qualify as a " free-standing" stack greater than 80 meters tall. f) The Unit 2 main vent stack is designed to accept gaseous radioactive ' waste from various sources. Sources which may contribute radioactive material to the Ur;t 2 main vent stack are tabulated in Attachment 7.
- 4. Auxiliary Boiler Demerator a) Radioactive gases may be vented from the auxiliary boiler deserator l during periods of primary to secondary leakage, b) Steam from the Moisture Separator Reheater (MSR) may be used in the deaerator. In the event of a primary to secondary leak, the MSR steam could become contaminated. Therefor, a potential exists for the release of radioactive gases in steam discharged from the auxiliary boiler .
deaerator. { ( c) The discharge of steam is accomplished via a relief vent,0-VBV-1891, which allows excess pressure to be vented to atmosphere. i d) In the event the auxiliary boiler deserator were to become contaminated, the amount of radioactivity released and the resulting doses / dose rates at i the site boundary can be estimated if the following parameters are l known: (1) the MSR steam activity obtained from a sample, " As defined by Regulatory Guide 1.111 l l l
- Offsite Dose Calculebon'ManualL Page 106 of 298 Revision 2, Change 0 l (2) the duration of the discharge, !
i (3) the estimated steam discharge flow rate, and ! (4) the measured or average annual meteorological conditions. .j e) in accordance with applicable safety evaluations32, continued operation of 1 this system is allowed as long as the concentration of radionuclides in the ! auxiliary boiler steam drum is less than 96 MPCs.
- 5. Steam Generator Atmospheric Steam Dump System a) Radioactive gases are not normally vented from this pathway, b) Radioactive gases may be vented from the steam generator atmospheric !
steam dump system during periods of primary to secondary leakage. c) If a primary to secondary leak is present and the steam dump valves are ! opened, the amount of radioactivity released and the resuiting ; doses / dose rates at the site boundary can be estimated if the following , parameters are known (per UFSAR,10.1.2.1): ' (1) the specific activity of a main steam sample as determined by ; GAMMA ISOTOPIC ANALYSIS, i (2) the duration of discharge, l (3) the estimated steam discharge flow rate, and : (4) the measured or average annual meteorological conditions. ! d) The total capacity of the atmospheric steam dump valve is 5 percent of ! steam flow with the reactor at full power (per UFSAR,10.1.2.1). ,
- 6. Plant Nitrogen System ,
l a) Radioactive gases are not normally vented from this pathway. , b) Nitrogen is supplied to various components which contain radioactive materials (e.g., VCT). . l c) In the event the plant nitrogen system were to become contaminated, the ! amount of radioactivity released and the resulting doses / dose rates at the : site boundary can be estimated if the following parameters are known: j (1) the specific activity of the gas in the plant nitrogen system as determined by GAMMA ISOTOPIC ANALYSIS, (2) the pressure of the nitrogen system, (3) the volume of the nitrogen system, and 8' See 50.59 Log No. 90-0-027-037-R1. l
- 1
s Offsite Dose Calculation Manu:1 Page 107 of 298 Revision 2, Change 0 , t (4) the measured or average annual meteorological conditions. d) It should be noted that the amount of radioactivity released could be estimated based on knowledge of other related parameters. e) In accordance with applicable safety evaluations88, continued operation of . this system is allowed as long as the concentration of radionuclides is less than 13,400 MPCs.
- 7. Turbine Building Exhaust a) Radioactive gases are not normally vented from this pathway.
b) In the event radioactive gases were to be released through the turbine , building exhaust, the amount of radioactivity released and the resulting i doses / dose rates at the site boundary can be estimated if the following parameters are known: (1) the specific activity of the turbine building air, r (2) the duration of the discharge, (3) the estimated flow rate during the discharge, and [ (4) the measured or average annual meteorological conditions.
- 8. Emergency Air Lock -
a) Radioactive gases are not normally vented from this pathway. b) In the event radioactive gases were to be released through the emergency air lock, the amount of radioactivity released and the resuP.:ng doses / dose rates at the site boundary can be estimated if the following parameters are known: (1) the containment air activity obtained from a sample, l (2) the volume of the air lock (9.558 cubic meters), (3) the measured or average annual meteorological conditions.
- 9. Plant Compressed Air a) Radioactive gases are not normally vented from this pathway, l
b) In the event the plant compressed air system were to become contaminated, the amount of radioactivity released and the resulting doses / dose rates at the site boundary can be estimated if the following l l parameters are known: ! (1) the specific activity of the compressed air system,
" See 50.59 Log No. 90-0-074-011-R1.
l
Offsite Dose Calculation Minu:1 Page 108 of 298 Revision 2 Change 0 (2) the pressure of the compressed air system, . l (3) the volume of the compressed air system, and (4) the measured or average annual meteorological conditions.
- 10. Main Steam Line Penetrations . 1 a) Radioactive gases are not normally vented from this pathway, b) This penetration is cooled by outside air.
-l c) Gases may be released to the atmosphere through safety vents to the -
roof at elevation 91.5 feet. i d) See UFSAR 9.8.2.3. 11.- Other unmonitored release paths should be evaluated and added to the ODCM as necessary. B. Types of Gaseous Releases
- 1. All gaseous radweste releases are classified as either BATCH RELEASES or CONTINUOUS releases. {
- 2. The definition of BATCH RELEASE is included in the definitions section of the ODCM.
- 3. The definition of CONTINUOUS release is included in the definitions section of the ODCM.
- 4. Gaseous radwaste discharges have been classified as CONTINUOUS or BATCH as shown on Attachments 7 and 8.
C. Processing Equipment
- 1. Simplified Flow Diagram a) An overview of the gaseous waste processing system, including major equipment and (normal) flow paths, is outlined on Attachment 9.
- 2. Modifications a) Major changes or modifications to the gaseous waste processing system shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the time interval in which the modification was completed (per Specification 6.18.1). ,
i 1 b) A " major" change or modification includes, but is not limited to, the - removal or permanent bypass of any of the following: ; (1) waste gas decay tank l (2) waste gas surge tank 1 i l I
i Offsite Dose Calculaton M:nual Page 109 of 298 Revision 2, Change 0
- 3. Detailed Description a) A detailed description of the gaseous waste processing system is beyond l the scope of the ODCM. j b) For more information on the Waste Gas System, see the CCNPP System Description Number 14A, " Waste Gas System."
c) For more information on the Waste Gas System, see the CCNPP ]' Updated Final Safety Analysis Report, Chapter 11, " Waste Processing And Radiation Protection." D. Gaseous Effluent Radiation Monitors And Setpoints j
- 1. Wide Range Gas Monitor (1-RE-5416) !
a) General description . (1) The Wide Range Gas Monitor (WRGM) contains 3 radiation elements (a) low-range noble gas detector I) Designation of radiation element: 1-RE-5416 ; ii) type of radiation element: Off-line scintillation iii) output: digital Radiation indicator.1-RIC-5415 : iv) l v) units for radiation indicator are user programmable and are normally set to microcuries per cubic centimeter vi) supplier. Sorrento Electronics (formerly General Atomics) (b) mid-range, noble gas detector i) Designation of radiation element: 1-RE-5417 ii) type of radiation element: Solid state l i lii) This noble gas monitor is used to measure the release of radioactivity from unit 1 main vent in the : event of an accident. (UFSAR, 11.2.3.2.12) iv) setpoints for the mid-range detector will not be addressed in the ODCM (c) high-range, noble gas detector i) Designation of radiation element: 1-RE-5418
Offsde Dose Calculation Manual Page 110 of 298 : Revision 2 Change 0 l t li) type of radiation element: Solid state -l lii) This detector is used to measure the release of ! radioactivity from unit 1 main vent in the event of i an accident. (UFSAR, 11.2.3.2.12) ! iv) setpoints for the high-range detector will not be , addresced in the ODCM i l (2)- The low range detector will be the only detector addressed further i in the ODCM. b) Functions of 1-RE-5416 (1) continuously measure the release rate of noble gases emanating ; from the Unit 1 main vent stack ( Specification 4.11.2.1.1 or j 4.11.2.1.2, Table 4.11-2) l (2) continuously indicate (via 1-RIC-5415) the release rate of noble 'f gases emanating from the Unit 1 main vent stack ( Specification j 4.11.2.1.1 or Specification 4.11.2.1.2, Table 4.11-2) (3) alarm (via 1-RIC-5415) prior to exceeding the site-boundary,- ! noble-gas, total-body-dose-rate limit of 500 mr/yr (per ! Specification 3.11.2.1.a) j (4) alarm (via 1-RIC-5415) prior to exceeding the site-boundary, noble-gas, skin-dose-rate limit of 3000 mr/yr (per Specification l 3.11.2.1.a) , l c) OPERABILITY of 1-RE-5416 i (1) This monitor shall be operable (or have OPERABILITY) when it is I capable of performing its specified function (s). i (2) The functions of this monitor are listed in section (b) above. l d) Monitors equivalent to 1-RE-5416 (1) 1-RE-5415 [the ' Westinghouse Plant Vent Stack Monitor] has the , capability of providing the measurement and alarm functions of 1- i RE-5416 during times when 1-RE-5416 is declared inoperable. l (2) 1-RE-5415 provides redundant monitoring [for 1-RE-5416] at the low end of the concentration ranges (UFSAR 11.2.3.2.12). (3) 1-RE-5415 is normally considered the PRIMARY MONITOR for measuring noble gas activity released via the Unit 1 Plant Vent Stack, and 1-RE-5416 is normally considered the BACKUP MONITOR for measuring noble gas activity released via the Unit 1 Plant Vent Stack. - i (4) in the event PRIMARY MONITOR (1-RE-5415) is inoperable or otherwise unavailable, the BACKUP MONITOR (1-RE-5416) is l 1
Offsite Dose Calculation Manual Page 111 cf 298 Revrion 2, Ch:nge 0 ; able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR. e) Radiological effluent controls for 1-RE-5416 (1) Specification 3.3.3.9 states that releases via the plant vent stack : may continue if any one of the following three conditions are satisfied: l (a) 1-RE-5415 is operable AND the alarm and trip setpoint(s) . t for 1-RI-5415 are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mr/yr to the skin (per Spacification 3.11.2.1.a), or (b) an " equivalent monitor" (see " Monitors Equivalent to 1-RE-5416" earlier in this section) is operable AND the alarm and trip sstpoint(s) for the " equivalent monitor" are set to t ensure annual dose rates due to noble gases at the SITE > BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Specification 3.11.2.1.a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours in accordance with Specifications 3.11.2.1.a,4.11.2.1.1, and 4.11.2.1.2 (per Specification 4.3.3.9, Table 3.3-12, ACTION 37). f) Surveillances for 1-RE-5416 (1) Specification 4.3.3.9 requires demonstrating the OPERABILITY of 1-RE-5416 by satisfying the checks, calibrations, and tests listed below: CHANNEL CHECK within the past 24 hours ! (a) (b) SOURCE CHECK within the past 31 days (c) CHANNEL CAllBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1-RIC-5415 , (1) Requirements and commitments (a) The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and - parameters of the ODCM. ( Specification 3.3.3.9) l (b) The method for calculating fixed or adjustable setpoints l l shall be provided in the ODCM (per NUREG-0133, 5.1.1). l
. _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - - _ __-_1
-~
Offsste Dose Calculation Manual Page 112 of 298 + Revision 2, Change 0 ; (2) There are three radiation alarm setpoints associated with, or otherwise related to, the WRGM. (a) 1-RIC-5415 fixed high-high radiation alarm setpoint (b) 1-RIC-5415 fixed high radiation alarm setpoint . (c) 1-RIC-5415 adjustable plant computer high radiation alarm setpoint , (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows The 1-RIC-5415 high-high radiation alarm setpoint will be . (a) ; referred to as the fixed high alarm setpoint . (b) The 1-RIC-5415 high radiation alarm setpoint will be referred to as the fixed alert setpoint (c) The 1-RIC-5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable setpoint l (4) Each of these alarm setpoints are described below, h) Fixed high alarm setpoint for 1-RIC-5415 (1) Generalinformation : (a) The high alarm setpoint is considered to be a fixed setpoint. The fixed high alarm setpoint is not adjusted for each release. (b) Whenever the fixed high alarm setpoint is exceeded, an alarm will be generated. ; (c) The current value for the fixed high alarm setpoint is l specified in the CCNPP Alarm Manual. The CCNPP Alarm Manual refers to the fixed high alarm I (d) setpoint as the Unit 1 Wide Range Noble Gas Radiation Monitor high alarm setpoint. (e) The fixed high alarm setpoint is integral to the WRGM, as l purchased from the supplier. (f) The fixed high alarm setpoint is administrative!y controlled by EN-1-100, (g) The fixed high alarm setpoint shall be calculated as described below. (2) Calculating the fixed high alarm setpoint for 1-RIC-5415 i
i Offsita Dose C:lculation M nu;l Pag)113 of 298 Revision 2, Change 0 j (a) The fixed high alarm setpoint for 1-RIC-5415 (WRGM) shall be calculated in accordance with equation 1G.* 1 J FIXED HIGH ALARM SETPOINT FOR 1-RIC-5415 l 5 Sunn <_ (c' / ( x/O ) ] [ Fox / ( Fe3 + Fe2 ) ] [ Artn ] Eq.1G i I
- Where, Sunn
= the fixed high alarm setpoint for 1-RIC-5415 (microcuries per second) c' = a conversion constant (1E6 cubic centimeters per cubic meter) x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) 38 Unit 1 main vent releases are considered "long-term" releases , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations.
The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) Fo, = the estimated main vent stack (diluted gaseous radwaste) flow rate for unit, x, (cubic meters ner second) The estimated main vent stack flow rates for Unit 1 and Unit 2 are defined below. F oi = the estimated main vent stack flow rate for Unit 1 (cubic metcrs per second) Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high setpoint. Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. This nominal main vent stack flow rate is based on the results of an approved 37 engineering test procedure
" The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9). " Equation 1G has been derived from NUREG-0133,5.2.1.
- NUREG-0133, 3.3 l
" See ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 1", completed in November 1987.
l i
i i Offsite Dose Calculation Manual . Page 114 of 298 l Revision 2, Change 0 I I The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (i 25%). The Test and Equipment Unit shall , be responsible for performing this test. The results of the main vent flow rate test ; shall be evaluated to ensure the main vent flow rates used in the ODCM are an - accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is , greater than the maximum discharge flow rates listed on Attachment 7.
]
= the estimated main vent stack (diluted gaseous radweste) flow rate for unit 2 (cubic Fe ;
meters per second) j Since the main vent stack flow rate will vary depending on the configuration of air ' dampers and the input gas streams, a conservative, nominal main vent stack flow ' rate is used to calculate the fixed high alarm setpoint. Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. This nominal main vent stagk flow rate is based on the results of an approved engineering test procedure ;. The main vent stack flow rate shall be determined, in accordance with approved i procedures, at least once per 6 months (t 25%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test : shall be evaluatcd to ensure the main vent flow rates used in the ODCM are an ; accurate reflection of the true main vent flow rates. The RETS Program Manager is ! responsible for modifying the (main vent flow rates used in the) ODCM in the event , the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is f greater than the maximum discharge flow rates listed on Attachment 7. ; t Ann = the sum of the total specific activities of all radionuclides found in TYPICAL i GASEOUS RADWASTE RELEASES (microcuries/cm3) i Calculate Ann in accordance with equation 2G. SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT ; h [(f )(i Ann )) / Au5 LMPC Eq. 2G , Where, f, = a FRACTION which represents the relative activity contribution of noble gas , radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value may be obtained using the guidance provided on Attachment 5. I
" See ETP-87-16, Revision 0,
- Main Vent Stack Flow Measurement - Unit 2", completed in November 1987.
" This equation has been derived from 10 CFR 20, Appendix B, Table 11, Note 1.
Offsite Dose Calculation M nual Page 115 of 298 Revision 2, Ch nge O Aa.:
= the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table ll, Column 1 (microcuries/cm3)
For all the DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table 11, Column 1. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E-14 microcuries per milliliter as the value for Au i (per 10 CFR 20, Appendix B, Note 2). LMPC = the site MPC limit (MPCs) for unrestricted areas The value chosen for Lupe in this equation is 2. The basis for this limit is 10 CFR 50.72. It has been shown" that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Specification 3.11.2.1(a). It should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Specification 3.11.2.1(a), a safety factor has been incorporated into equation 2G. An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4-hour NRC notification" (specified in 10 CFR 50.72) is required. (3) Documenting the fixed high alarm setpoint (a) Whenever the fixed high alarm setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN-1-100. (4) Changing the fixed high alarm setpoint for 1-RIC-5415 (a) If the fixed high alarm setpoint calculated in accordance with equation 1G exceeds the maximum range of the . monitor, the fixed high setpoint shall be adjusted to a value ! which falls within the normal operating range of the i monitor. (b) The fixed high alarm setpoint may be established at values lower than the maximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenever any of the parameters identified in the setpoint calculation equations (identified in this section of the ODCM) have changed. (d) The fixed high alarm setpoint should not be changed unless one of the following occurs:
- Addendum To Setpoint Calculations For WRGM Monitors 1-RIC-5415 and 2-RIC-5415, R.L.
i Conatser, December 10,1991. l
~ . - . . . .- . - .. . . . _ , . .-. -
Offsete Dose' Calculation ManurJ Page 116 of 298 Revision 2, Change 0
' i) the relative activityd ' of any radionuclide in l TYPICAL GASEOUS EFFLUENTS has changed by ;
greater than 10%, and the new radionuclide
~
mixture yields a fixed setpoint which is 10% (or . more) lower than the current fixed setpoint, l ii) the historical maximum annual average i' atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (Q) has changed, iv) the Unit 1 or Unit 2 main vent stack flow rate has changed by greater than or equal to 10%" , , v) the values listed in 10 CFR 20, Table 11, column 1 have changed, vi) the radiation monitor has been recently calibrated, repaired, or otherwise alteied, or vii) the monitor is not conservative in its function (see !
" Functions of 1-RE-5416" earlier in this section). l (e) EN-1-100 contains the administrative controls associated f with changing and approving fixed high alarm setpoint. i i) Fixed alert setpoint for 1-RIC-5415 !
(1) Generalinformation (a) The fixed alert setpoint is considered to be a fixed setpoint. The fixed alert setpoint is not adjusted for each release. (b) Whenever the fixed alert setpoint is exceeded, an alarm will be generated. ! (c) The CCNPP Alarm Manual does not reference this setpoint.
]
(d) The fixed alert setpoint is integral to the WRGM, as purchased from the supplier. - l (e) The current value for the fixed alert setpoint is specified in the CCNPP Setpoint File. (f) The fixed alert setpoint is administrative!y controlled by EN-1-100. ) (g) The fix alert setpoint shall be calculated as descritted below* As determined in accordance with Attachment 5. 42 As determined by analysis of the TE-001 and ETP-87-16 test results. l l
1 F Offsite Dose C",1culation Manuil Paga 117 of 298 Revision 2, Change 0 (2) Calculating the fixed alert setpoint for 1-RIC-5415 (a) The fixed alert setpoint for 1-RIC-5415 shall be calculated as described below: FlXED ALERT SETPOINT FOR 1-RIC-5415 i I Srixh <_ K., [ Svi,nn ] Eq.3G Where, Sri,n = the fixed alert setpoint for 1-RIC-5415 (microcuries per second) S,i,nn = the fixed high alarm setpoint for 1-RIC-5415 (microcuries per second) I K, = a constant, actually a safety factor, which is the FRACTION of the fixed high setpoint (unitiess). The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed alert setpoint is always less than or equal to the fixed high alarm setpoint. : A safety factor of 1.00 will yield a fixed alert setpoint which corresponds to the fixed ; high alarm setpoint. A safety factor of 0.100 will yield a fixed alert setpoint which corresponds to one-tenth the fixed high alarm setpoint. It is recommended that a safety factor of 0.1 be used for calculating the fixed alert setpoint, however, other values-not to exceed 1.00--may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a value less than 1.00 does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the ' possibility of violating either the 10 CFR 50.72 limit or the Specification 3.3.3.9 i limits. The use of the safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as l is reasonably achievable." The use of a " safety margin"is in accordance with the provisions of NUREG-0133 ; which states that ".... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous l release limit of Specification 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1). .
" The alarm and trip setpoints . . shall be determined and adjusted in accordance with the 4
methodology and parameters of the ODCM. (Technical Specification 3.3.3.9).
~. - . . . . -. -- .
. Offsite Dose Calculation Manud Page 118 of 298
- Revision 2, Change 0 I
This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated fixed alert setpoint.
.(3) Documenting the fixed alett alarm setpoint (a) Whenever the fixed alert alarm setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN 1-100.
(4) Changing the fixed alert alarm setpoint for 1-RIC-5415 (a) A setpoint change should be initiated whenever any of the parameters identified in equation 3G have changed. (b) The fixed ale:1 setpoint should be changed whenever the , fixed high setpoint is changed. (c) The fixed alert setpoint should be changed if the value of the safety factor is changed. (d) See EN-1-100 for a description of activities associated with setpoint changes and setpoint approvals. j j) Adjustable alarm setpoint for 1-RIC-5415 (1) Generalinformation (a) This setpoint is an adjustable setpoint. Whenever this radiation monitor is operable, the adjustable setpoint is 4 calculated and adjusted prior to each release of a WGDT, each containment vent, and each containment purge i discharged via the main vent. (b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable chemistry section procedures as required by Specification l 4.11.2.1.2). (c) Whenever the adjustable setpoint is exceeded, the WGDT, purge, or vent discharge via the main vent will be manually suspended. (d) Refer to the Alarm Manual for a full list of operator ACTIONS taken in response to this alarm. (e) The adjustable setpoint corresponds to the maximum , concentration of radionuclides anticipated or expected i 1 I
, _ -- _~ ~ - . - .. . -- .
' Offsite Dose Calculation M .nu:1 Page 119 of 298 Revision 2, Change 0 I
when discharging a WGDT, a containment vent, or a containment purge via the main vent. (f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable chemistry section procedures. (g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier. l (h) This alarm is generated by the plant computer which monitors output from 1/2-RIC-5415, and provides an alarm . to plant operators when the 1/2-RIC-5415 adjustable setpoint has been exceeded . (i) When this monitor is operable, a value for the adjustable alarm setpoint shall be calculated prior to each release of a WGDT, each containment vent, and each containment purge as shown below. (2) Calculating the adjustable setpoint for 1/2-RIC-5415 j (a) The adjustable alarm setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste i (as determined by radiochemical analysis per , Specification 4.11.2.1.2), and the alarm setpoint is calculated as shown below. l ADJUSTABLE ALARM SETPOINT FOR 1/2-RIC-5415 , S,oj 5 (1.50) ( Fe, ) ( c' ) { [ ( Fu / F , ) h ( Aw ) ( e3 ) ] + Bkg ) Eq. 29G" ! S,oj = the adjustable alarm setpoint for 1/2-RIC-5415 (microcuries per second) : 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess) This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with semple analysis, and (5) errors associated with monitor calibrations.d8 i Fu = maximum undiluted radwaste flow rate (cubic meters per second) Values of maximum undiluted radwaste flow rates for various waste streams are ; tabulated in Attachment 7. : t Equation 29G has been derived from NUREG-0133, Addendum, page AA-1. ! The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality controllimits. i i l 6 ______-____m_ _ _ - , - - v
Page 120 of 298 Offsite Dose Calculation Manual Revision 2 Change 0 Fdx = the estimated main vent stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second) Since the main vent stack flow rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the adjustable setpoint. Use the nominal main vent stack flow rate, for the appropriate unit, listed on Attachment 7. This nominal main vent stack flow rate is based on the results of an approved engineering test procedure". The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The Radiological Effluent Specifications (RETS) Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7. Aiu = specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or the containment building (microcuries per cubic centimeter) e4 = absolute detector efficiency for nuclide, I (microcuries Xe-133 equivalent per microcuries nuclide 1) The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (microcuries per cubic centimeter) ; c' = a conversion constant (1E6 cubic centimeters per cubic meter) I (3) Documenting the adjustable alarm setpoint for 1/2-RIC-5415 i I I (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with approved chemistry section procedures (e.g., CP-604). (4) Changing the adjustable alarm setpoint for 1/2-RIC-5415 (a) In all cases, the adjustable alarm setpoint shall be set to a value which is less than or equal to the fixed setpoint. i l " See ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 1", or ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 2, completed in November 1987. I
Offsde Dose Calculabon Manual Page 121 of 298 Revrion 2, Change 0 (b) If the adjustable alarm setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (c) Chemistry section procedures (e.g., CP-604) contain administrative controls associated with calculating and I approving an adjustable setpo',it. (d) Whenever this monitor is operable and this monitor is
)
performing the functions of the PRIMARY MONITOR (see
" Monitors Equivalent to 1-RE-5416" earlier in this section),
i the calculated value for the adjustable setpoint shall be entered into the plant computer prior to each release of a WGDT, a containment vent, or a containment purge via the main vent.
- 2. Wide Range Gas Monitor (2-RE-5416) i a) all information related to 1-RE-5416 is applicable to the Unit 2 WRGM
- with the following exceptions (s) l b) Monitors equivalent to 2-RE-5416 l (1) 2-RE-5415 (the " Westinghouse Plant Vent Stack Monitor") has the l
capability of providing the measurement and alarm functions of 2-l RE-5416 during times when 2-RE-5416 is declared inoperable 1 (2) 2-RE-5415 provides redundant monitoring [for 2-RE-5416] at the low end of the concentration ranges (UFSAR 11.2.3.2.12)
l Offsite Dose Calculation Manual Page'122 of 298 Revision 2, Change 0
- 3. Westinghouse Plant Vent Stack Monitor (1-RE-5415) -
a) The Westinghouse Plant Vent Stack Monitor contains 2 radiation elements (1)' 1-RE-5414 (a) particulate detector l (b) off-line scintillation detector (c)- analog output (d) supplies signals to radiation indicator 1/2-RI-5414 (e) values displayed by 1/2-RI-5414 are in units of counts per - minute (f) the detector manufacturer is Westinghouse (2) 1-RE-5415 (a) noble gas detector ; (b) off-line GM Tube (c) analog output (d) supplies signals to radiation indicator 1/2-RI-5415 (e) values displayed by 1/2-RI-5415 are in units of counts per -
' minute j (f) the detector manufacturer is Westinghouse .
b) Functions of 1-RE-5414 (1) The functions of 1-RE-5414 are mentioned here only as a basis ; for excluding this radiation element from the setpoint controls of- i Specification 3.3.3.g. i (2) This radiation element measures particulate activity contained on l a moving particulate filter which is 99% efficient for particle sizes , greater than 1.0 micron (UFSAR 11.2.3.2.1) ; (3) The activity contained on the particulate filter is representative of ~ e the particulate activity emanating from the Unit 1 Plant Vent Stack. (4) The ODCM will not address alarm setpoints for 1-RE-5414 i [ particulate monitor) since NUREG-0133, section 5.1.1 states, "It is not considered to be practicable to apply instantaneous alarm : and trip setpoints to integrating radiation monitors sensitive to ) I
I Offsite Dose Calculation Manual Page 123 of 298 l Revision 2, Change O L radioiodines, radioactive materials in particulate form and ,
- radionuclides other than noble gases." .;
i c) Functions of 1-RE-5415" .l (1) continuously measure the activity (CPM) of noble gases , emanating from the Unit 1 main vent stack ( Specification 4.11.2.1.2 Table'4.11-2)
+
(2) continuously indicate (via 1-RI-5415) the activity (CPM) of noble gases emenating from the Unit 1 main vent stack ( Specification i 4.11.2.1.2, Table 4.11-2) ; (3) alarm (via 1-RI-5415) prior to exceeding the site-boundary, noble- i gas, total-body-dose-rate limit of 500 mrlyr (per Specification : 3.11.2.1.a) i (4) alarm (via 1-RIC-5415) prior to exceeding the site-boundary, , noble-gas, skin-dose-rate limit of 3000 mr/yr (per Specifica'. son 3.11.2.1.a) d) OPERABILITY of 1-RE-5415 : (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s). (2) The functions of 1-RE-5415 are listed in section (c) above. : i e) Monitors equivalent to 1-RE-5415 (1) The Wide Range Gas Monitor (i.e.,1-RE-5416) has the capability r of providing the measurement and alarm functions of 1-RE-5415 during times when 1-RE-5415 is declared inoperable. . 4 (2) 1-RE-5415 provides redundant monitoring [for 1-RE-5416] at the i low end of the concentration ranges (UFSAR 11.2.3.2.12). (3) 1-RE-5415 is normally considered the PRIMARY MONITOR for ! measuring noble gas activity released via the Unit 1 Plant Vent i Stack, and 1-RE-5416 is normally considered the BACKUP ! MONITOR for measuring noble gas activity released via the Unit 1 Plant Vent Stack. i (4) in the event PRIMARY MONITOR (1-RE-5415) is inoperable or ; otherwise unavailable, the BACKUP MONITOR (1-RE-5416) is f able to fulfill the measuring, indicating, and alarming functions I normally provided by the PRIMARY MONITOR. l (5) The absence of a radiation element dedicated to measuring the ! particulate activity in the Wide Range Gas Monitor does not j preclude the use of 1-RE-5416 as a backup for 1-RE-5415. This - l
" This (radiation element) monitors noble gases. Other radiation elements monitor particulates in !
this waste stream ! t w , y y
,g.
4 - .w n --n-, - _..-.-,,.e-- ,v.. , -
Offsite Dose Calculation Manual Page 124 of 298 ' . Revision 2, Change 0
. is mentioned only as a basis for excluding 1/2-RE-5414 from the setpoint controls of Specification 3.3.3.9 (see " Functions of 1-RE- ;
5414" earlier in this section). f) Radiological effluent controls for 1-RE-5415
-(1) Specification 3.3.3.9 states that releases via the plant vent stack
. may continue if any one of the following three conditions are satisfied (a) 1-RE-5415 is operable AND the alarm and trip setpoint(s) for 1-RI-5415 are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are les,s than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Specification 3.11.2.1.a), or ,
(b) an " equivalent monitor" (see section (e) above) is operable - AND the alarm and trip setpoint(s) for the " equivalent monitor" are set to ensure annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Specification 3.11.2.1.a), or (c) grab samples are obtained and analyzed for gross activity at least once per 24 hours in accordance with Specifications 3.11.2.1.a. 4.11.2.1.1, and 4.11.2.1.2 (per - Specification 4.3.3.9, Table 3.3-12, ACTION 37). (2) specification 3.11.2.1.b (i.e., dose rates due to iodines and particulates at the SITE BOUNDARY) is not applicable to noble gas detector or to the setpoints related to the noble gas detector 1-RE-5415. As a result, the 1500 my/yr organ dose limit is not included as a radiological effluent control in this section of the ODCM. , g) Surveillances for 1-RE-5415 (1) Specification 4.3.3.9 requires demonstrating the OPERABILITY , of 1-RE-5415 by satisfying the checks, calibrations, and tests ; listed below: : I (a) CHANNEL CHECK within the past 24 hours (b) SOURCE CHECK within the past 31 days l (c) CHANNEL CALIBRATION within the past 18 months , i (d) CHANNEL FUNCTIONAL TEST within the past 6 six ) months h) Setpoints for 1-RI-5415 (1) Requirements and commitments
F Offsite Dose Calculation Manual Page 125 of 298 Revhion 2, Change 0 i i
-(a) The alarm and trip setpoints ... shall be determined and ,
adjusted in accordance with the methodology and parameters of the ODCM. ( Specification 3.3.3.g)- i (b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM. (NUREG-0133,5.1.1) P (2) There are three alarms associated with, or otherwise related to,1-RE-5415. (a) 1-RI-5415 fixed high radiation ala:m setpoint (b) 1-RI-5415 adjustable plant computer high radiation alarm setpoint , (c) 1-RI-5415 low radiation alarm setpoint (3) In order to simplify the setpoint terminology, eliminate ambiguity, ' and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows ; (a) The 1-RI-5415 fixed high radiation alarm setpoint will be ' referred to as the fixed setpoint. (b) The 1-RI-5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable setpoint. j (c) The 1-RI-5415 low radiation alarm setpoint will be referred , to as the low setpoint. l (4) Each of these alarm setpoints are described bebw. ; i) The fixed setpoint for 1-RI-5415 l (1) Generalinformation ; (a) This setpoint is considered to be a fixed setpoint. The . fixed setpoint is not adjusted for each release. (b) Whenever the fixed setpoint is exceeded, an alarm will be generated. (c) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. , I (d) The CCNPP Alarm Manual refers to this setpoint as the 1-RI-5415 High ksdiation Alarm Setpoint. (e) The fixed setpoint is integral to the Main Vent 6 (Westinghouse) RMS as purchased from the supplier. (f) The fixed setpoint is administratively controlled by EN 100. ._ _ ~ . . _ _ _ _ _ _ _ - _ _ _ __ - -
- Offsite Dose' Calculation Manual Page 126 of 298 Revision 2, Change 0 (g) The fix setpoint shall be calculated as described below" (2) Calculating the fixed setpoint for 1-RI-5415 (a) The fixed high radiation alarm setpoint for 1-Rl-5415 (plant vent stack monitor) shall be calculated in accordance with equation 4G.
THE FIXED HIGH At. ARM SETPOINT FOR 1-Rl-5415 SS 5 { K., / [ ( x/Q ) ( Foi + Fe2 ) ] } h [ ( e, ) ( Au ) ] Eq. 4G d? Su = the fixed radiation alarm setpoint for 1-Rl-5415 (counts per minute) K., = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, Lupc, used in equation 2G (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, Lupc, used in equation 2G. A safety factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit,- Lupc, in equation 2G. A safety factor of 0.500 will yield a fixed high setpoint which corresponds to one-half the MPC limit, Lupc, in equation 2G. It is recommended that a safety factor of 1.0 be used for calculating the fixed setpoint, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Specification 3.3.3.9 limits. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20], make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." The use of a " safety margin" is in accordance with the provisions of NUREG-0133, section 5.1.1, which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Specification 3.11.2.1(a) will not be exceeded." The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9). Equation 4G has been derived from NUREG-0133, 5.2.1, (the 500 mrlyr equation).
t Offsite Dose Calculation Minu;I Page 127 of 298 Revision 2, Change 0 This safety margin will prevent minor fluctuations in the nominal plant vent stack flow - rates, errors in detector efficiencies, and other statistical aberrations from adversely impacting the calculated fixed setpoint. x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) , Unit 1 and Unit 2 main vent releases are considered "long-term" releases' , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the l setpoint calculations. l The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for ; purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). Foi = the estimated main vent stack flow rate for Unit 1 (cubic meters per second) Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high setpoint. , Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. k flow rate is based on the results of an approved This nominal engineering testmain vent stap1. procedure < The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months ( 25%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an , accurate reflection of the true main vent flow rates. The RETS Program Manager is ! responsible for modifying the (main vent flow rates used in the) ODCM in the event , the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7. Fo2
= the estimated main vent stack flow rate for unit 2 (cubic meters per second)
Since the main vent stack flow rate will vary depending on the configuration of air dampers and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the fixed high setpoint. . Use the nominal Unit 1 main vent stack flow rate listed on Attachment 7. . This nominal main vent stack flow rate is based on the results of an approved s2 engineering test procedure , NUREG-0133, 3.3 See ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 1", completed in November 1987.
- Offsite Dose Calculation Manual Page 128 of 298 Revision 2, Change 0 The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (! 25%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test .
shall be evaluated to ensure the main vent flow rates used in the ODCM are an -
. accurate reflecticii of the true main vent flow rates. . The RETS Program Manager is .
responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is - greater than the maximum discharge flow rates listed on Attachment 7. , e, = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculateo .".rn data collected during calibration of the radiation monitor. Agtn = the specific activities of radionuclide, I, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated in accordance with 10 CFR 20, Appendix B, Table ll, Note 1 ' as described below; microcuries per milliliter) ' Calculate Auin accordance with equation SG. SPECIFIC ACTIVITY LIMIT FOR NUCLlDE I IN A RADIONUCLIDE MIXTURE Au = ( f,) ( Artn ) Eq.SG f, = a FRACTION which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value may be obtained using the guidance provided on Attachment 5. A TLn = the sum of the total specific activities of all noble gas radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3) Calculate A7tn in accordance with equation 2G. } l' SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT h [( f,)( ATLn )]/ Au S LMPC Eq. 2Gsa Lupe = the MPC limit : The value chosen for 4pc in this equation is 2. The basis for this limit is 10 CFR 50.72.
" See ETP-87-16, Revision 0, Main Vent Stack Flow Measurement - Unit 2", completed in November 1987.
" Equation 2G has been derived from 10 CFR 20, Appendix B, Table 11, Note 1.
-y-. .- ,
Offsite Dose Calculation Manu;l Page 129 of 298 Revision 2, Change 0 it has been shown" that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Specification 3.3.3.9. It should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Specification 3.11.2.1(a), a safety factor has been incorporated into equation 2G. The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-0133, Mion 5.1.1, which states that,."... in all cases, conservative assumptions may be racessary in establishing these setpoints to account for system variables, . . the variability in release flow, ... and the time lag between alarm and final isolation of radioactive effluents." i An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4-hour NRC notification" (specified in 10 CFR 50.72) is required. The use of a limiting specific activity equivalent to 2 MPCs is consistent with the provisions of 10 CFR 20.106(a). Au i
= the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table 11, Column 1 (micmcuries/cm3)
For all the DOMINANT RADIONUCLlDEs found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table ll, Column 1. For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E-14 microcuries per milliliter as the value for A i u (per 10 CFR 20 Appendix B, Note 2). (3) The low alarm setpoint for 1-Rl-5415 (a) The ODCM does not address the calculations associated with the low alarm setpoint. J (b) The low alarm setpoint is specified in the CCNPP Alarm Manual. (c) The low alarm setpoint may be used to determine l OPERABILITY of this monitor (in accordance with the provisions of Specification 4.3.3.9, Table 4.3-11, Note 2). ) (4) Adjusting the fixed setpoint for 1-RI-5415 (a) If the fixed setpoint calculated in accordance with equation 4G exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.
" Addendum To Setpoint Calculations For WRGM Monitors 1-RIC-5415 and 2alC-5415, R.L.
Conatser, December 10,1991.
Offsite Dose Calculation M nual Page 130 of 298 Revision 2, Change 0 (b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired. l ! (c) A setpoint change should be initiated whenever any of the l parameters identified in equation 4G have changed. (d) The fixed setpoint should not be changed unless one of the following occurs: i) the relative activity58of any radionuclide in l TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, li) the historical maximum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, iv) the estimated Unit 1 main vent stack flow rate or Unit 2 main vent stack flow rate has changed by greater than or equal to 10%68, v) the values listed in 10 CFR 20. Table ll, column 1 have changed, j l vi) the radiation monitor has been recently calibrated, l repaired, or otherwise altered, or ! vii) the monitor is not conservative in its function (see ; section " Functions of 1/2-RE-5415" earlier in this 1 section). (e) EN-1-100 contains the administrative controls associated with changing and approving fixed alarm setpoint. j) Adjustable alarm setpoint for 1/2-RI-5415 (1) Generalinformation (a) This setpoint is an adjustable setpoint. Whenever this radiation monitor is operable, the adjustable setpoint is calculated and adjusted57prior to each release of a As determined in accordance with Attachment 5. As determined by analysis of the TE-001 and ETP-87-16 test results. I 5' The adjustable setpoint may or may not be changed for each of the releases listed here. A determination of whether to change the setpoint would only be required when conducting simultaneous releases (i e., if a purge or a vent is conducted while a WGDT is also being released). In this case, two adjustable setpoints would be calculated (i e., one adjustable setpoint for the vent or purge and one adjustable setpoint for the WGDT). In the case of simultaneous {
Offsite Dose Calculation Manual Page 131 of 298 RevDion 2, Change 0 WGDT, each containment vent, and each containment purge discharged via the main vent. i (b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable chemistry section procedures as required by Specification ' 4.11.2.1.2). (c) Whenever the adjustable setpoint is exceeded, the WGDT, purge, or vent discharge via the main vent will be manually suspended. (d) Refer to the Alarm Manual for a full list of operator ACTIONS taken in response to this alarm. (e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT, a containment vent, or a containment purge via the main vent. (f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable chemistry section procedures. (g) This alarm is not integralio the main vent radiation monitor, as purchased from the supplier. (h) This alarm is generated by the plant computer which monitors output from 1/2-RI-5415, and provides an alarm to plant operators when the 1/2-RI-5415 adjustable setpoint has been exceeded. (i) When this monitor is operable, a value for the adjustable alarm setpoint shall be calculated prior to each release of a WGDT, each containment vent, and each containment purge as shown below. (2) Calculating the adjustable setpoint for 1/2-RI-5415 (a) The adjustable alarm setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Specification 4.11.2.1.2), and the alarm setpoint is calculated as shown below. ADJUSTABLE ALARM SETPOINT FOR 1/2-RI-5415 releases, the lower (more conservative) of the two adjustable setpoints should be input into the plant computer.
Offsite Dose Calculation Manus! Page 132 of 2C8 Revision 2, Change O S adj 5 1.50 ( F u
/ Fe, ) [ h ( Aiu ) ( ei) + Bkg ] Eq. 27Gse S,oj = the adjustable alarm setpoint for 1/2-RI-5415 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess)
This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, ("., Otistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.** Fu = maximum undiluted radwaste flow rate (cubic meters per second) Values of maximum undiluted radwaste flow rates for various waste streams are tabufated in Attachment 7. F, e
= the estimated main vent stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second)
Since the main vent stack , rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, a conservative, nominal main vent stack flow rate is used to calculate the adjustable setpoint. Use the nominal main vent stack flow rate, for the appropriate unit, listed on Attachment 7. This nominal main vent stack flow rate is based on the results of an approved engineering test procedure * . The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months ( 25%). The Test and Equipment Unit shall be responsible for performing this test. The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The Radiological Effluent Technical Specifications (RETS) Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vert flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7. A., = specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or containment building as applicable (microcuries per milliliter) e3 = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) " Equation 27G has been denved from NUREG-0133, Addendum, page AA-1. " The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality contro! limits. " See ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 1", or ETP-87-16, Revision 0, " Main Vent Stack Flow Measurement - Unit 2, completed in November 1987.
Offsne Dose Calculation Manual Page 133 of 298 Revtlon 2, Change 0 The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (cpm) )
)
(3) Documenting the adjustable alarm setpoint for 1/2-RI-5415
) ,
(a) Whenever the adjustable setpoint is calculated, the i l specific values chosen for each of the variables shall be documented in accordance with approved chemistry l section procedures (e.g., CP-604). (4) Changing the adjustable alarm setpoint for 1/2-RI-5415 (a) In all cases, the adjustable alarm s7boint shall be set to a value which is less than or equal to the fixed setpoint. ; (b) If the adjustable alarm setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a ! value which falls within the normal operating range of the l monitor. I (c) Chemistry section procedures (e.g., CP-604) contain !' administrative controls associated with calculating and approving an adjustable setpoint. l l (d) Whenever this monitor is operable and this monitor is performing the functions of the PRIMARY MONITOR (see i
" Monitors equivalent to 1-RE-5415" earlier in this section), ;
the calculated value for the adjustable setpoint shall be i entered into the plant computer prior to each release of a ; WGDT, a containment vent, or a containment purge via l the main vent. k) The low alarm setpoint for 1/2-RI-5415 1 (1) This alarm is integral to the main vent monitor, as purchased from I the supplier. t (2) The current value for the low alarm setpoint is specified in the : CCNPP Alarm Manual. ! i (3) The low alarm setpoint may be used to determine the OPERABILITY of this monitor (per Specification 4.3.3.9, ! CHANNEL FUNCTIONAL TEST). l (4) The alarm generated by the low alarm setpoint may be used to terminate a release in the event 1/2-RI-5415 fails (i.e., downscale failure or circuit failure) in accordance with Specification 4.3.3.9. . (5) The low alarm setpoint calculations are not described in the l ODCM. I i i
^
Offsite Dose Calculation M:nua! - Page 134 of 298 Revision 2, Change 0 (6) Changes to the low alarm setpoint are controlled by EN-1-100.
- 4. Westinghouse Plant Vent Stack Monitor (2-RE-5415) ;
a) All information related to 1-RE-5415 is applicable to the Unit 2 plant vent stack monitor with the following exception (s): , b) Monitors equivalent to 2-RE-5415 , t (1) 2-RE-5416 [the 'WRNGM"] has the capability of providin0 the . measurement and alarm functions of 2-RE-5415 during times when 2-RE-5415 is declared inoperable. (2) 2-RE-5415 provides redundant monitoring [for 2-RE-5416] at the low end of the concentration ranges (UFSAR 11.2.3.2.12).
- 5. Gaseous Radwaste Treatment System Radiation Monitor (0-RE-2191) a) General description i
(1) The GASEOUS RADWASTE TREATMENT SYSTEM Radiation Monitor (Waste Gas Decay Tank Radiation Monitor) contains 1 , radiation element. (2) It is a noble gas detector. The detector is an in-line GM tube (UFSAR, Table 11-10). (3) f (4) The radiation element is designated 0-RE-2191. i (5) The radiation indicators designated 0-Rl-2191. (6) The units for the radiation indicator are counts per minute. ) (7) The monitor was manufactured by Westinghouse. b) Functions of 0-RE-2191 (1) continuously measure the release rate of noble gases emanating from the waste gas decay tank discharge header ( Specification 4.11.2.1.2, Table 4.11-2) (2) continuously indicate (via 0-RI-2191) the activity (CPM) of noble gases emanating from the waste gas decay tank discharge header ( Specification 3.3.3.9 OPERABILITY requirement) , (3) alarm (via 1-RI-2191) prior to exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mrlyr (per Specification 3.11.2.1.a) (4) alarm (via 1-RI-2191) prior to exceeding the site-boundary, noble-gas, skin-dose-rate limit of 3000 mr/yr (per Specification 3.11.2.1.a) l
Offsite Dose Calculation Manual Page 135 of 298 Revision 2, Change O c) OPERABILITY of 0-RE-2191 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function (s). (2) For more information on the function (s) of this monitor, see
" Functions of 0-RE-2191" elsewhere in this section of the ODCM.
d) Monitors equivalent to 0-RE-2191 (1) There are no equivalent monitors associated with 0-RE-2191 since there are no other radiation monitors permanently installed in the waste gas discharge header, however, Specification 3.3.3.9 defines the plant vent stack monitor as a " BACKUP MONITOR." (2) 0-RE-2191 is designated the PRIMARY MONITOR for measuring noble gas activity released via the GASEOUS RADWASTE TREATMENT SYSTEM. (3) 1-RE-5415 (or 1-RE-5416) is designated the BACKUP MONITOR if the WGDT is discharged via the Unit 1 main vent. (4) 2-RE-5415 (or 2-RE-5416) is designated the BACKUP MONITOR if the WGDT is discharged via the Unit 2 main vent. (5) WGDTs are normally discharged through the Unit 1 main vent stack. (6) The BACKUP MONITOR has the capability of ensuring the noble gas activity released from the GASEOUS RADWASTE TREATMENT SYSTEM-to the plant vent stack-does not exceed Specification 3.11.2.1(a) at the SITE BOUNDARY ( Specification 3.3.3.9). (7) In the event PRIMARY MONITOR (0-RE-2191) is inoperable or otherwise unavailable, the designated BACKUP MONITOR (either 1-RE-5415,1-RE-5416,2-RE-5415, or 2-RE-5416) is able to fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR as long as plant operators record the BACKUP MONITOR readings every 15 minutes ( Specification 3.3.3.9, Table 3.3-12, ACTION 35a). e) Radiological effluent controls for 0-RE-2191 (1) Specification 3.3.3.9 states that releases via the GASEOUS RADWASTE TREATMENT SYSTEM may continue if ANY ONE of the following three conditions are satisfied: (a) 0-RE-2191 is operable AND the alarm and trip setpoint(s) for 0-RI-2191 are set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Specification 3.11.2.1.a), or
Offsite Dose Calculation Manual Page 136 of 298 Revision 2, Change 0 i (b) One " BACKUP MONITOR" (see section (e) above) is operable; AND the " BACKUP MONITOR" readings are recorded every 15 minutes during the release; AND the alarm and trip setpoint(s) for the " BACKUP MONITOR" are set to ensure the annual dose rates due to noble gases at ' the SITE BOUNDARY are less than 500 mrlyr to the total body and are less than 3000 mrlyr to the skin (per Specification 3.11.2.1.a), or (c) All three activities described below are completed prior to . the release; i) at least two independent samples of the waste gas decay tank's contents are analyzed, and i ii) at least two technically qualified members of the Facility Staff independently verify the release rate calculations, and iii) two qualified operators verify the discharge valve ; lineup. { f) Surveillances for 0-RE-2191 (1) Specification 4.3.3.9 requires demonstrating the OPERABILITY of 0-RE-2191 by satisfying the checks, calibrations, and tests i listed below (a) CHANNEL CHECK prior to each release (b) SOURCE CHECK prior to each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 0-Rl-2191 i (1) Requirements and commitments l (a) The alarm and trip setpoints .., shall be determined and l adjusted in accordance with the methodology and l parameters of the ODCM. ( Specification 3.3.3.9) (b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM. (NUREG-0133,5.1.1) (2) There are three radiation alarm setpoints associated with, or otherwise related to,0-RE-2191. (a) 0-RE-2191 fixed high radiation alarm and automatic control trip setpoint ;
L~ (
- Offsite Dose Calculation Manual Page 137 cf 298 Revision 2, Change 0 ;
(b) 4RE-2191 adjustable plant computer high radiation alarm l and manual control trip setpoint t (c) 0-RE-2191 low radiation alarm setpoint (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows l I (a) The 0-RE-2191 fixed high radiation alarm and automatic control trip setpoint will be referred to as the fixed setpoint. . (b) The 0-RE-2191 adjustable plant computer high radiation
- alarm and manual control trip setpoint will be referred to as ;
the adjustable setpoint. (c) The 0-RE-2191 low radiation alarm setpoint will be , referred to as the low setpoint. ; (4) Each of these alarm setpoints are described below. t h) Fixed setpoint for 0-RI-2191 l 4 (1) Generalinformation { (a) This setpoint is considered to be a fixed setpoint. The j fixed setpoint is not adjusted for each release. ! (b) The fixed setpoint is an alarm and trip setpoint. l I (c). Whenever the fixed setpoint is exceeded, an alarm will be j generated, and the WGDT release will be automatically .i suspended. ] (d) The fixed setpoint corresponds to the maximum . concentration of radionuclides aliowed (by equation 6G) in l gaseous waste discharged from the gaseous radwaste l processing system. (e) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual. (f) The CCNPP Alarm Manual refers to this setpoint as the O-RI 2191 High Radiation Alarm Setpoint. (g) The fixed setpoint is integral to the waste gas discharge monitor, as purchased from the supplier. (h) The fixed setpoint is administrative!y controlled by EN 100. l l
. Offsite Dose CCiculation Manual Page 138Cf 298 Revision 2, Change 0 (i) The fixed setpoint shall be calculated as described , below. (2) Calculating the fixed setpoint for 0-RI-2191 (a) The fixed alarm and trip setpoint for 0-RI-2191 (waste gas discharge monitor) shall be calculated as described below: FIXED ALARM AND TRIP SETPOINT FOR 0-RI-2191 Sr, 5 K., { { 1/ [ ( x/Q ) { Fu ) } } h [ ( e,) ( Aitn ) } + Bkg } Eq. 6Gs2 Where, K, = a constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, Lupc, used in equation 2G (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, Lupc, used in equation 2G. A safety factor of 1.00 is used for calculating the fixed setpoint. By setting the safety factor to 1, the safety factor is disabled. i Although it may appear that if this safety factor is set to 1.0, no safety margin exists, in actuality, another margin of safety has been incorporated into equation 2G (see definition of LuPc)- l A safety factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, Lupc, in equation 2G. . A safety factor of 0.500 will yield a fixed high setpoint which corresponds to one-half the MPC limit, Lupc, in equation 2G. Other values of safety factors-not to exceed 1.00-may be used for calculating the fixed setpoint as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a i value less than or equal to 1.0 does provide plant personnel with adequate time to i respond to changing plant conditions and to initiate corrective ACTIONS so as to i minimize the possibility of violating either the 10 CFR 50.72 limit or the Specification j 3.3.3.9 limits. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20], make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9). e2 Equation 4G has been derived from NUREG-0133,5.2.1, (the 500 mrlyr equation). ! l
I
!Offsite Dose C:lculation Manual Page 139 of 298 Ravhion 2, Ch:nge 0 The use of a " safety margin"is in accordance with the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous 7 release limit of Specification 3.11.2.1(a) will not be exceeded." _ (per NUREG-0133, !
5.1.1). This safety margin will prevent minor fluctuations in the nominal WGDT discharge l flow rates, errors in detector efficiencies, and other statistical aberrations from ! adversely impacting the calculated fixed setpoint. I Su = the fixed radiation alarm setpoint for 0-RI-21g1 (CPM) ! x/O = the highest calculated historical annual average relative concentration for any area , at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic , meter) , A waste gas decaygnk release via the Unit 1 or Unit 2 main vent is considered a "long-term" release , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations. i The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term , concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). , Fu = the estimated maximum flow rate of undiluted gases through the waste gas l discharge header (cubic meters per second) ; i Since WGDT pressure is the motive force for discharge of a WGDT, the waste gas flow rate will continually decrease as the release progresses (i.e., as tank pressure _j is decreased). Use the estimated maximum WGDT discharge flow rate, listed on Attachment 7, to calculate the fixed setpoint. ' ep = absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter) The detector efficiency for each radionuclide may be calculated from data collected , during calibration of the radiation monitor. j Aa.n
= the specific activities of radionuclide, I, found in TYP: CAL GASEOUS RADWASTE RELEASES (calculated in accordance with 10 CFR 20, Appendix B, Table ll, Note 1 as describe i below; microcuries per milliliter) ,
Calculate Au in accordance with equation SG. SPECIFIC ACTIVITY LIMIT FOR NUCLIDE I IN A RADIONUCLIDE MIXTURE {
** NUREG-0133,3.3 3 0
3 s u . - , Offsite Dose Calculation Manual Page 140 of 298 Revtion 2, ChDnge O Au = {f)(Ann) i Eq.5G f3
= a FRACTION which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess)
This value may be obtained using the guidance provided on Attachment 5. A7tn = the sum of the total specific activities of all noble gas radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3). Calculate Artn in accordance with equation 2G . SPECIFIC ACTIVITY OF NOBLE GASES AT THE SITE BOUNDARY h [( f )( i Ann )] / Au sLMPC i Eq. 2G"
- Where, Lupe = the MPC limit The value chosen for Lupc in this equation is 2. The basis for this limit is 10 CFR 50.72.
It has been shown est hat, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Specification 3.3.3.9. It should be noted that by using "2" as the MPC limit (10 CFR 50.72), instead of using the limits of Specification 3.11.2.1(a), a safety factor has been incorporated into equation 2G. The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-0133, section 5.1.1, which states that, " .. in all cases, conservative assumptions may be necessary in er.eblishing these setpoints to account for system variables, ... the variability in release now, . . and the time lag between alarm and final isolation of radioactive effluents."(NUREG-0133,5.1.1) An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the "4-hour NRC notification" (specified in 10 CFR 50.72) is required. Aiu = the specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table 11, Column 1 (microcuries/cm3) . 1 For all the DOMINANT RADidNUCLIDEs found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table ll, Column 1. " Equation 2G has been derived from 10 CFR 20, Appendix B, Table 11, Note 1. " Addendum To Setpoint Calculations For WRGM Monitors 1-RIC 5415 and 2-RIC-5415, R.L. Conatser, December 10,1991.
Offsit) Dose Cciculatbn Minu11 Page 141 cf 298 Revision 2, Chinge 0 -' For each of the LESS DOMINANT RADIONUCLIDES found in TYPICAL RADWASTE EFFLUENTS, use 2E-14 microcuries per milliliter as the value for Au i (per 10 CFR 20, Appendix B, Note 2). Bkg = an approximation of the detector background prior to initiating the gaseous release (cpm) Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired. (3) Documenting the fixed setpoint for 0-RI-2191 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented in accordance with EN-1-100. (4) Changing the fixed setpoint for 0-RI-21g1 (a) If the fixed setpoint calculated in accordance with equation 6G exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired. (c) A setpoint change should be initiated whenever any of the parameters identified in equations 2G, SG, or 6G have changed. (d) The fixed setpoint should not be changed unless one of the following occurs: i) the relative activity ** of any radionuclide in TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) the historical maximum annual average atmospheric dispersion factor has changed, lii) the MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, iv) values listed in 10 CFR 20 Table ll, column 1 have changed, v) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or As determined in accordance with Attachment 5.
)
Page 142 of 298 P Offsite Dose Calculation Manual - ; Revision 2, Change 0 ! vi) - - the monitor is not conservative in its function (see , section " Functions of 0-RE-2191" earlier in this - l section). l I (e) EN-1-100 contains the administrative controls associated with changing and approving fixed alarm setpoint. ; i) = Adjustable alarm setpoint for 0-RI-2191 (1) Generalinformation (a) This setpoint is an adjustable setpoint. Whenever this radiation monitor is oper9ble, the adjustable setpoint is calculated and adjusted' prior to each release of a WGDT. . (b) The adjustable setpoint is based on the specific activities of the radionuclides present in the WGDT. (The radionuclide concentrations are determined by radiochemical analysis in accordance with applicable i chemistry section procedures as required by Specification
- 4.11.2.1.2).
i (c) Whenever the adjustable setpoint is exceeded, the WGDT l discharge will be manually suspended. , (d) Refer to the radwaste Alarm Manual for a full list of operator ACTIONS taken in response to this alarm. ; (e) The adjustable setpoint corresponds to the maximum } concentration of radionuclides anticipated or expected J' when discharging a WGDT. (f) The value for the adjustable setpoint is recorded on the gaseous release permit in accordance with applicable t chemistry section procedures. (g) This alarm is not integral to the gaseous radwaste treatment system radiation monitor, as purchased from the supplier. , (h) This alarm is generated by the plant computer which l monitors output from 0-RI-2191, and provides an alarm to plant operators when the 0-RI-2191 adjustable setpoint has been exceeded.
" The adjustable setpoint may or may not be changed for each WGDT release. A determination of 1 whether to change the setpoint would only be required when conducting simultaneous releases (i.e., if a purge or a vent is conducted while a WGDT is also being released). In this case, two '
adjustable setpoints would be calculated (i.e., one adjustable setpoint for the vent or purge and one adjustable setpoint for the WGDT). In the case of simultaneous releases, the lower (more conservative) of the two adjustable setpoints should be input into the plant computer. y - 9 - - - - -
---w e- ,
Offsite Dose Calculation Manu;l Page 143 of 298 Rov?: ion 2, Change 0 (i) When this monitor is operable, a value for the adjustable alarm and trip setpoint shall be calculated prior to each release of a WGDT as shown below. (2) Calculating the adjustable setpoint for 0-RI-2191 (a) The adjustable alarm and trip setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Specification 4.11.2.1.2), and the alarm and trip setpoint is calculated as shown below. ADJUSTABLE ALARM AND TRIP SETPOINT FOR 0-RI-2191 S,oj 5 1.50 [ h ( A,u ) ( e4 ) + Bkg ] Eq. 28G'8 S , 33
= the adjustable alarm and trip setpoint for 0-RI-2191 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitiess)
This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.88 Fu = maximum allowed undiluted radwaste flow rate (cubic meters per second) The maximum allowed undiluted radwaste flow rate for a WGDT is tabulated in Attachment 7. A iu = specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) e4
= absolute detector efficiency for nuclide, I (cpm /microcuries per milliliter)
The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor. Bkg = an approximation of the detector background (cpm) (3) Documenting the adjustable alarm setpoint for 0-RI-2191 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be l " Equation 28G has been derived from NUREG-0133, Addendum, page AA-1. " The " analysis errors" and " calibration errors" refer to errors which are within established quality assurance and quality controllimits. l l l l 1
Offsite Dose Calculation Manual Page 144Cf 298 Revision 2, Change O documented in accordance with approved chemistry section procedures (e.g., CP-604). . (4) Changing the adjustable alarm setpoint for 0-RI-2191 I (a) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint. , (b) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor. (c) Chemistry section procedures (e.g., CP-604) contain administrative controls associated with calculating and approving an adjustable setpoint. (d) Whenever this monitor is operable, the calculated value for the adjustable setpoint shall be entered into the plant
- computer prior to each release of a WGDT via the main vent.
j) The low alarm setpoint for 0-Rl-2191 (1) This alarm is integral to the main vent monitor, as purchased from the supplier. (2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual. (3) The low alarm setpoint may be used to determine the OPERABILITY of this monitor (per Specification 4.3.3.9, CHANNEL FUNCTIONAL TEST). (4) The alarm generated by the low alarm setpoint may be used to terminate a release in the event 0-RI-2191 fails (i.e., downscale failure or circuit failure) in accordance with Specification 4.3.3.9. (5) The low alarm setpoint calculations are not described in the ODCM. (6) Changes to the low alarm setpoint are controlled by EN-1-100. E. Annual Total Body Dose Rate Due To Noble Gases in Gaseous Effluents
- 1. Introduction a) 10 CFR 20.105 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS. i b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.105.
1 c) These radiological effluent controls are described below.
l Offsite Dose C0lculation Manual Page 145 of 298 i Revision 2, Change 0
- 2. Radiological Effluent Controls a) The annual total body dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 500 mr/yr (per Specification 3.11.2.1).
b) The routine sunreillances which are performed to verify compliance with this radiological effluent control is described below.
- 3. Surveillance Requirement a) The annual total body dose rate, due to noble gases in all gaseous effluents discharged from the site, shall be determined in accordance with equation 7G (per Specification 4.11.2.1.1). ;
b) The results of the radioactive gaseous waste sampling and analysis program (required by Specification 4.11.2.1.2, and implemented by various CCNPP chemistry section procedures) are used to calculate the annual total body dose rate due to noble gases in gaseous effluents. c) The plant group (s) responsible for performing the required surveillances are identified below.
- 4. Responsible Plant Organization (s) a) The Chemistry Section is responsible for calculating the annual total body dose rate due to noble gases in gaseous effluents.
b) The CCNPP Chemistry Section calculates the annual total body dose rate whenever the appropriate initiating conditions are present. c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions a) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each release of a WGDT.
b) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each vent of a containment building. c) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each PURGE of a containment building, d) The annual total body dose rate due to noble gases in gaseous effluents is calculated at least weekly7 for CONTINUOUS discharges from plant vent stacks. " The frequency is controlled by the implernenting procedure, CP-612, and is based on plant conditions. Under no condrtions shall the frequency be less than once per month (Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).
Offsite Dose Calculation Manual Page 143 of 298 Revision 2 Change 0 e) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each discharge of combustion products resulting from the buming of contaminated oil, f) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE (as defined in CP-612). g) Whenever the correct initiating conditions are present, the annual total body dose rates shall be calculated as described below.
- 6. Calculation Methodology a) The annual total body dose rate, at the SITE BOUNDARY, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 7G."
i ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN ALL GAS RELEASES Doi
= hD Eq.tr 7G
= the site-boundary annual total body dose rate due to noble gases in all gaseous Doi effluents discharged (simultaneously) from the site (mrem / year)
= the site-boundary annual total body dose rate due to noble gases in release, r Der (mrem / year)
Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE would include the release of noble , gas radionuclides from the Unit 1 plant vent stack while also discharging noble t gases from the Unit 2 plant vent stack. An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. Calculate the values of Dirfor each SIMULTANEOUS RELEASE as shown below. b) At CCNPP, two methods exist for calculating Dir (i.e., annual total body dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9).
Offsde Dose Calculation Manual Page 147 of 298 Revision 2, Change 0 (2) . The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections, c) Rigorous method (1) Solution of the following equation may prove too rigorous for ' routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 8G. ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD) ( x/Q )[ h ( Ki )( Q,)) Eq.8G 72
~
D, = Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) 73 All releases are considered "long-term" releases , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) K, = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, I (mrem /yr per microcurie / cubic meter) The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.10g, Appendix B, Table B-1. The total-bo jy dose factors for various noble gas radionuclides are tabulated in Attachment 19. 72 Equations 8G has been derived from NUREG-0133,5.2.1, and Regulatory Guide 1.109 (Appendix B. Equation B-8 and Section C.2.e). 7' NUREG-0133, 3.3
Offsit) Dose C:lculation M:nuit Page 148 of 298 Revision 2, Change 0 Q,, = the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second). Calculate the values of Q,, for each SIMULTANEOUS RELEASE as shown below, i INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r Q,, = ( A,, ) ( F, ) ( c' ) Eq. 9G
- Where, A,, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter)
F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the
" Maximum Discharge Flow Rate" list?d on Attachments 7 or 8 may be used to calculate the annual total body dose rate.
Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method (1) If a computer system and the appropriate software are NOT available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 10G. ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD) D,i = [( x/Q )( Kug ) / ( Kg ) ] h Q,, Eq.10G"
- Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) ,
1 " Equations 10G has been derived from NUREG-0133,5.2.1, and historical, site-specific data. l
Offsite Dose Calculation M:nual Page 149 of 298 Revrion 2, Change O All releases are considered "long-term" releases78, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) K,, = the empirically derived, site specific, average, total body, dose factor due to gamma > emissions from TYPICAL GASEOUS EFFLUENTS (mrem /yr per microcurie / cubic ( meter) A site-specific, average, gamma total body dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data. The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11 (use section 3.4.5 of the old ODCM.) Refer to the table on Attachment 11 for the current value for the empirically derived, ; site specific, average gamma total body dose factor, j l Kg = a constant, actually a safety factor, which is the ratio of the CCNPP annual total j body dose rate limit to the annual total body dose rate limit of Specification 3.11.2.1, j (unitless) The safety factor chosen shall be less than or equal to 1.00. This ensures the annual total body dose rate is always less than or equal to the annual total body dose rate limit of Specification 3.11.2.1. l A safety factor of 1.00 will yield an annual total body dose rate which corresponds to l the annual total body dose rate limit of Specification 3.11.2.1. i A safety factor of 0.500 will yield an annual total body dose rate which corresponds to one-half the annual total body dose rate limit of Specification 3.11.7.1. I It is recommended that a safety factor of 1.0 be used for calculating the annual total body dose rate, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a ' safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Specification 3.11.2.1 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, ". . in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effort to maintain radiation exposures, and
" NUREG-0133, 3.3 l
l E - -- - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
, . .- . . _ . - ~ ~ . -- -- . -- . .- - . . - . .I_' y f
Offsite Dose Calculation MonuCl Page 150 of 298 - Revision 2, Change 0 - releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." This safety factor has been included in equation 10G to account for any potential , nonconservatism associated with applying the empirically derived total body gamma j dose factor, K.,,, to all radionuclides identified in the gaseous release. - Such nonconservatism could conceivable be present whenever radionuclides having a , total body gamma dose factor greater than K.,, are present in a gaseous relecse. j Q,i = the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second) l Calculate the values of Q,, for each SIMULTANEOUS RELEASE in accordance with -i equation 9G. } INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q ir = ( A,, ) ( F, ) ( c' ) Eq.9G Where. : A,, = the specific activity of noble gas radionuclide, i, in (simultaneous) release, r ! (microcuries/ cubic centimeter) ; F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) ! If the discharge flow rate is unknown (e.g., the release has not been conducted), the
" Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to ,
calculate the annual total body dose rate. , Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in l approved chemistry section procedures (e.g., CP-601 and CP 604). '! c' = a conversion constant (1E6 cubic centimeters per cubic meter) l t e) Radiation monitoring system algorithms 1 (1) The plant vent stack radiation monitoring systems display values which are proportional to the annual total body dose rates due to ; noble gases emanating from the plant vent stacks.' l (2) The values displayed by the plant vent stack radiation monitoring ! syrtems are not used for the purpose of effluent accountability per ; se, but the values displayed can provide a gross approximation of ' annual total body dose rate (see Specification 3.3.3.9). l 1
l Offsite Dose Calculation Manual Page 151 of 298 Revision 2, Change 0 (3) The Westinghouse Main Vent Noble Gas Monitor,1/2-RE-5415, is j an analog system and does not employ instrument algorithm to ! determine noble release rates. { (a) It is possible to approximate the noble gas release rates ); for the Unit i and Unit 2 main vents based on output from 1/2-RI-5415. (b) These calculations are described elsewhere in the ODCM. (See equation 4G in the section " Calculating the Fixed Setpoint for 1/2-RI-5415.") (4) The Sorrento WRNGM,1/2-RE-5416, is a digital radiation monitoring system which employs an instrument algorithm to determine noble release rates (microcuries per second). , (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415. (b) These calculations are described elsewhere in the ODCM. (See equation 1G in the section " Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.") , (c) The instrument algorithms and the (data base) values accessed by the instrument algorithms are controlled by EN-1-100. f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are , initiated as described below.
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for annual total body dose rates for gaseous effluents and shall specify corrective ACTIONS to be initiated when these limits are ,
exceeded. b) Refer to Specification 3.11.2.1 for ACTIONS to be taken in the event the calculated annual total body dose rate due to noble gases in gaseous effluents exceeds 500 mrlyr. F. Annual Skin Dose Rate Due To Noble Gases in Gaseous Effluents
- 1. Introduction a) 10 CFR 20.105 specifies dose rate limits associated with the release of !
radioactive materials to UNRESTRICTED AREAS. b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.105. l
Offsite Dose Calculation Manud Page 152 of 298 i Rev2 ion 2, Change 0 l c) . These radiological effluent controis are described below.
- 2. Radiological Effluent Controls a) The annual skin dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 3000 mr/yr (per Specification 3.11.2.1).
b) The routine surveillances which are performed to verify compliance with ) this radiological effluent controls are described below. J
- 3. Surveillance Requirement a) The annual skin dose rate at the SITE BOUNDARY, due to noble gases in all gaseous effluents discharged from the site, shall be determined in accordance with equation 11G (per Specification 4.11.2.1.1).
b) The results of the radioactive gaseous waste sampling and analysis program (required by Specification 4.11.2.1.2, and implemented by various CCNPP chemistry section procedures) are used to calculate the annual skin dose rate due to noble gases in gaseous effluents. c) The plant group (s) responsible for performing the required surveillances are identified below.
- 4. Responsible Plant Organization (s) i a) The Chemistry Section is responsible for calculating the annual skin dose rate due to noble gases in gaseous effluents.
b) The CCNPP Chemistry Section calculates the annual skin dose rate whenever the appropriate initiating conditions are present. c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions ,
a) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each release of a WGDT. b) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each vent of a containment building. c) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each PURGE of a containment building. l l l l
-t Offsste Dose Calculation Manual Page 153 of 298 i
-_ Revision 2, Change 0 i d) The annual skin dose rate due to noble gases in all gaseous effluents l 78 discharged from the site is calculated at least weekly for CONTINUOUS l discharges from plant vent stacks. ,
e) The annual skin dose rate due to noble gases in all gaseous effluents l discharged from the site is calculated for each discharge of combustion products resulting from the burning of contaminated oil. ; i f) The annual skin dose rate due to noble gases in all gaseous effluents ! discharged from the site is calculated for each ABNORMAL AND/OR : UNANTICIPATED RADIOACTIVE GAS RELEASE (as defined in CP- l 612). j l g) Whenever the correct initiating conditions are present, the annual skin : dose rates shall be calculated es described below. ;
- 6. Calculation Methodology i i
a) The annual skin dose rate, at the SITE BOUNDARY, due to noble gases in all gaseous effluents discharged simultaneously from the site to . UNRgSTRICTED AREAS shall be calculated in accordance with equation j 11G. ; ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN ALL SIMULTANEOUS GAS RELEASES, r D,o = h D , Eq.11G
)
D,o = the annual skin dose rate at the SITE BOUNDARY due to noble gases in all simultaneous discharges of gaseous radwaste from the site (" Unit 0") 1 D., = the annual skin dose rate at the SITE BOUNDARY due to noble gases in release, r i Sum for all releases, r, which are discharged simultaneously. 5 An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging noble ; gases from the Unit 2 plant vent stack. An example of a SIMULTANEOUS RELEASE would include the release of noble ' gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. Calculate the values of D., for each SIMULTANEOUS RELEASE as shown below. ; i
" The frequency is controlled by the implementing procedure, CP-612, and is based on plant l conditions. Under no conditions shall the frequency be less than once per month (Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2). ,
" The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9). i i
i
Offsite Dose Calculation Manual Page 154 of 298 Revision 2, Change 0 b) At CCNPP, two methods exist for calculating D,7 (i.e., annual total skin dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. 4 (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the annual skin dose rate due to noble gases in gaseous release, r, discharged from the site to UNRESTRICTED AREAS shall be calculated in accordance with equation 12G. ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD) D er = ( x/Q ) h { [ L i+ ( 1.1 ) { M,)] ( Q,) } Eq.12G"
- Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)
All releases are considered "long-term" releases", and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for
- purposes of routine, lor,g-term concentrations (e.g., routine noble gas releases)
(UFSAR, 2.3.6.3) , The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) " Equation 12G has been derived from NUREG-0133,5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B-9 and Section C.2.f). " NUREG-0133,3.3 l l l
4 Offsite Dose Calculation Manual Page 155 of 298 i Revision 2, Change 0 ; L-i = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i i (mrem /yr per microcurie / cubic meter) The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The beta skin dose factors for various noble gas radionuclides are tabulated in
- Attachment 10.
M, = the air dose factor due to gamma emissions for each identified noble gas radionuclide, I (mradlyr per microcurie / cubic meter) The gamma air dose factors have been obtained from Regulatory Guide 1.109, i Appendix B, Table B-1. The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10. 1.1 = The conversion constant,1.1 mrem / mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose. Q,, = the release rate of noble gas radionuclide, I, in (simultaneous) release, r > (microcuries/second). , This value shall be calculated in accordance with equation 9G. - INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLlDE i IN GASEOUS RELEASE r i Q,, = ( A,, ) ( F, ) ( c' ) Eq.9G A,, = the specific activity of noble gas radionuclide, I, in (simultaneous) release, r l (microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) ;
. If the discharge flow rate is unknown (e.g., the release has not been conducted), the i
" Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to l calculate the annual skin dose rate. ;
Whenever possible, the actual discharge flow rate determined from actual release l conditions (e.g., initial pressure, volume, and temperature of a WGDT along with : final pressure and temperature) shall be used in equation 9G. Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method
Offsite Dose Cciculation M: nut! Paga 156 of 298 R:; vision 2, Ching3 0 (1) If a computer system and the appropriate software are NOT available, the annual skin dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED l AREAS may be calculated in accordance with equation 13G. ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD) D., = [ ( x/O ) / ( K ,) ) [ Las + ( 1.1 ) ( Mas)) Q,, Eq.13G 80
- Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) si All releases are considered "long-term" releases , and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.
The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3) The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3) K., = a constant, actually a safety factor, which is the ratio of the CCNPP annual skin dose rate limit to the annual skin dose rate limit of Specification 3.11.2.1, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the annual skin dose rate is always less than or equal to the annual skin dose rate limit of Specification 3.11.2.1. A safety factor of 1.00 will yield an annual skin dose rate which corresponds to the annual skin dose rate limit of Specification 3.11.2.1. A safety factor of 0.500 will yield an annual skin dose rate which corresponds to one-half the annual skin dose rate limit of Specification 3.11.2.1. It is recommended that a safety factor of 1.0 be used for calculating the annual skin dose rate, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control 1 over the use of simphfied equations for generating radioactive gaseous release ; 1 " Equation 12G has been derived from NUREG-0133,5.2.1, and Regutalory Guide 1.109 (Appendix B. Equation B-9 and Section C.2.f). " NUREG-0133,3 3 l l
Offsite Dose Calculation M:nu:1 Page 157 of 298 Revision 2, Change O permits. This administrative controlis designed to minimize the possibility of violating Specification 3.11.2.1 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, ". . in addition to complying with the limits set forth in this part [10 CFR 20], make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." This safety factor has been included in equation 13G to account for any potential nonconservatism associated with applying the empirically derived skin beta dose factor, L,y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a skin beta dose factor greater than L,y are present in a gaseous release. L,y = the empirically derived, site specific, average, skin dose factor due to beta emissions from TYPICAL GASEOUS EFFLUENTS (mrern/yr per microcurie / cubic meter) A site-specific, average, beta skin dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data. The calculation of this site-specific, average, beta skin dose factor is presented on Attachment 11. Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average beta skin dose factor. M,y = the empirically derived, site specific, average, air dose factor due to gamma emissions from T(PICAL GASEOUS EFFLUENTS (mradlyr per microcurie / cubic meter) A site specific, average, gamma air dose factor for TYPICAL MSEOUS EFFLUENTS has been calculated from historical data. The calculation of this site-specific, average, gamma air dos s. ctor is presented on Attachment 11. Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma air dose factor. 1.1 = The conversion constant,1.1 mrem / mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose. O,, = the release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second) This value shall be calculated in accordance with equation 9G. INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r Q,, = { A,, ) ( F, ) ( c' ) Eq.9G
Offsde Dose Calculation Manual Page 158 of 298 - Revtion 2 Change O A, = the specific activity of noble gas radionuclide, I, in (simultaneous) release, r
.(microcunes/ cubic centimeter) ;
F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) , if the discharge flow rate is unknown (e.g., the release has not been conducted), the
" Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to ,
calculate the annual skin dose rate. Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with ! final pressure and temperature) shall be used in equation 9G. : Additional guidance for calculating discharge flow rates may be contained in j approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) l e) Radiation monitoring system algorithms ! (1) The plant vent stack radiation monitoring systems display values i which are proportional to the annual skin dose rate due to noble ~; gases emanating from the plant vent stacks. ; (2) The values displayed by the plant vent stack radiation monitoring ! systems are not used for *s purpose of effluent accountability per se, but the values dispF - an provide a gross approximation of ! annual skin dose rate , ~ pecification 3.3.3.9). j (3) The Westinghouse Main Vent Stack Noble Gas Monitor,1/2-RE- , 5415, is an analog system and does not employ instrument sigorithm to determine noble release rates. , (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from ; 1/2-Rl-5415. I (b) These calculations are described elsewhere in the ODCM. (See equation 4G in the section " Calculating the Fixed : Setpoint for 1/2-Rl-5415.") > (4) The Sorrento WRNGM,1/2-RE-5416, is a digital radiation ; monitoring system which employs an instrument pigorithm to ! determine noble release rates (microcuries per second). ! i (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415. (b) These calculations are described elsewhere in the ODCM. (See equation 1G in the section " Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.")
Offsite Dose Calculation M:nual Page 159 of 298 l Revision 2, Change 0 (5) The instrument algorithms and the (data base) values accessed , by the instrument algorithms are controlled by EN-1-100. i f) Once the calculations above have been completed, tne calculation results J are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-213) shall I contain/and or reference administrative and/or Technical Specification limits for annual skin dose rate for gaseous effluer's and shall specify corrective ACTIONS to be initiated when these limus are exceeded.
1 b) Refer to Specification 3.11.2.1 for ACTIONS to be taken in the event the calculated annual skin dose rate exceeds 3000 mrlyr. 1 G. Annual Organ Dose Rates Due To lodines And Particulates In Gaseous Effluents
- 1. Introduction I
a) 10 CFR 20.105 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS. b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.105. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The annual organ dose rates, due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 1500 mr/yr (per Specification 3.11.2.1).
b) The rou'.ine surveillances which are performed to verify compliance with this radiological effluent controls are described below.
- 3. Surveillance Requirements a) The chemistry section's sampling and analysis procedure (s) (e.g., CP-504, CP-604) shall describe the CCNPP radioactive gaseous waste sampling and analysis program (required by Specification 4.11.2.1.2 b) The results of the radioactive gaseous waste sampling and analysis program are used to calculate the annual organ dose rates due to iodines and particulates in gaseous effluents.
c) The plant group (s) responsible for performing the required surveillances are identified below.
- 4. Responsible Plant Organization (s) l j
Offsite Dose Calculation Manual Page 160 of 298 - Rev'fion 2, Change 0 a) The Chemistry Section is respcnsible for calculating the annual organ dose rates due to iodines and particulates in gaseous effluents. b) The CCNPP Chemistry Section calculates the annual organ dose rates whenever the appropriate initiating conditions are present. c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions a) The annual organ dose rate-for each organ and at the SITE BOUNDARY-due to iodines and particulates in gaseous effluents is a2 calculated at least weekly for CONTINUOUS discharges from plant vent stacks.
b) The annual organ dose rate-for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated for each discharge of combustion products resulting from the buming of contaminated oil. c) The annual organ dose rate-for each organ and at the SITE BOUNDARY-due to iodines and particulates in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED 83 RADIOACTIVE GAS RELEASE d) Whenever the correct initiating conditions are present, the annual organ dose rates shall be calculated as described below.
- 6. Calculation Methodology a) The annual organ dose rate, at the SITE BOUNDARY, due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS shall be calculated in accordance with equation 14G."
ANNUAL ORGAN, o , DOSE RATE DUE TO IODINES AND PARTICULATES IN ALL SIMULTANEOUS GASEOUS RELEASES, r FROM THE SITE, O Doo
= h D ,Eq.14G o
Do o
= the site-boundary annual organ dose rate due to iodine and particulate radionuclides in all gaseous effluents discharged simultaneously from the site (" Unit 0")
The frequency is controlled by the implementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Technical Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2). " See the definition of ABNORMAL 1 UNANTICIPATED GAS RELEASE in the DEFINITIONS section of the ODCM. " The alarm and trip setpoints . . shall be determined and adjusted in accordance with the methocology and parameters of the ODCM. (Specification 3.3.3.9).
l Offsit2 Dose C;lculation M:nus! Page 161 of 298 Rev2 ion 2, Change O D,o = the site-boundary annual organ dose rate due to iodine and particulate radienuclides I in release, r i Sum for all releases, r, which are discharged simultaneously. An example of a SIMULTANEOUS RELEASE would include the release of iodines and particulate radionuclides from the Unit 1 plant vent stack while also discharging iodines and particulate radionuclides from the Unit 2 plant vent stack. An example of a SlMULTANEOUS RELEASE would include the release of iodine and particulate radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank. Calculate the values of Do, for each SIMULTANEOUS RELEASE as shown below. b) At CCNPP, two methods exist 'or calculating Do,(i.e., the annual organ dose rates due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) Tne simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the annual organ dose rates due to iodines and particulates in gaseous effluents released to an UNRESTRICTED AREA shall be calculated in accordance with equation 15G. ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (RIGOROUS METHOD) D,o
= ( x/Q ) h ( P i )( Q,,) Eq.15G 85
- Where, x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)
" Equation 15G has been derived from NUREG-0133,5.2.1. I I
Offsite Dose C:lculation M: null Page 162 of 298 Revision 2, Change 0 All releases are considered "long-term" releases *8, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (UFSAR,2.3.6.3). l lI The maximum annual average on-shore concentrations occur in the southeast i sector at a distance of 1300 meters for purposes of routine, long-term ) concentrations (UFSAR, 2.3.6.3). Pi = the maximum organ inhalation pathway dose parameter for iodine and particulate radionuclides, i, for the most restrictive (i.e., child) age group (mrem / year per microcurie / cubic meter) The inhalation pathway dose parameters have been obtained in accordance with I NUREG-0133, 5.2.1.1. The pathway dose factor specified in NUREG-0133, 5.2.1.b, specifies calculating the exposure to the "lNFANT" age group, where the exposure is due to a combination of three separate pathways.
- 1) inhalation,
- 2) ground plane, and
- 3) food.
i The latest NRC guidance has deleted the requirement to include the ground plane ; and food dose contributions when calculating maximum organ doses, therefor no l pathway dose factors are calculated for the ground plane or food pathways.
- The latest NRC guidance has changed the critical receptor age group from " infant" to " child." l The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12.
It should be noted that the dose parameters, P,, (listed in Attachment 12) calculated in accordance with NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the " Inhalation Pathway Factors," K, calculated in accordance with NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and K,. , l Q,i = the release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous ! release, r (microcuries/second). I Calculate the values of Q,,for each SIMULTANEOUS RELEASE in accordance with equation 9G. NUREG-0133. 3.3 I l _______-_-_-___-__-________-_\
l Offsit) Dose Calculation Minuti Page 163 of 298 Revision 2, Change 0 INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Q,, = ( A;, ) ( F, ) ( c' ) Eq.9G 1 A,, = the specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) l F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the
" Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.
Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) d) simplified method (1) If a computer system and the appropriate software are NOT available, the annual organ dose rate due to iodines and particulates in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated in accordance with equation 16G. ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (SIMPLIFIED METHOD) Der = ( il K ,) ( x/Q ) ( Pma ) h Q,, Eq.16Gs7
- Where, K., = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose rate limit to the organ dose rate limit of Specification 3.11.2.1, (unitiess)
The safety factor chosen shall be iess than or equal to 1.00. This ensures the organ dose rate is always less than or equal to the organ dose rate limit of Specification 3.11.2.1. A safety factor of 1.00 will yield an organ dose rate which corresponds to the organ dose rate limit of Specification 3.11.2.1. A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose rate limit of Specification 3.11.2.1. " Equation 16G has been derived from NUREG-0133,5.2.1.
Offsite Dose Calculation Manu11 Page 164 of 298 Revision 2, Change 0 ft is recommended that a safety factor of 1.0 be used for calculating the organ dose rate, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release , pe,mits. This administrative controlis designed to minimize the possibility of violating Specification 3.11.2.1 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 ; CFR 20], make every reasonable effort to maintain radiation exposures, and 4 releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." , This safety factor has been included in equation 16G to account for any potential nonconservatism associated with applying the dose parameter, P.,, to all , radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a dose parameter greater than P., are present in a gaseous release. i x/O = the highest calculated annual average relative concentration for any area at or i beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases **, and as such, the highect , historical annual average dispersion factor, (x/Q), is used in the dose rate ! calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) - (UFSAR, 2.3.6.3). The maximum ar nual average on-shore concentrations occur in the southeast ; sector at a distance of 1300 meters for purposes of routine, long-term , concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). , P., = the most restrictive dose parameter which would be reasonably anticipated for the ! inhalation pathway, child age group, thyroid organ, and 1-131 radionuclide (mrem / year per microcurie / cubic meter) The inhalation pathway dose parameters have been obtained in accordance with ! NUREG-0133, 5.2.1.1. l The pathway dose factor specified in NUREG-0133, 5.2.1.b, specifies calculating the f exposure to the " INFANT" age group, where the exposure is due to a combination of three separato pathways.
- 1) inhalation,
- 2) ground plane, and NUREG-0133, 3.3 ,
l
Offsite Dose Calculation Manual Page 165 of 298 Revtion 2, Change 0
- 3) food.
The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefor no pathway dose factors are calculated for the ground plane or food pathways. l. The latest NRC guidance has changed the critical receptor age group from " infant" to " child." The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12. It should be noted that the dose parameters, Pi , (listed in Attachment 12) calculated in accordance with NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the " Inhalation Pathway Factors," Ki , calculated in accordance with NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and K.i Q, = the release rate of iodine or particulate radionuclide, I, in (simultaneous) gaseous release, r (microcuries/second). Calculate the values of Q, for each SIMULTANEOUS RELEASE in accordance with equation 9G. INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r l Q, = ( A,) ( F r) { c' ) Eq.9G A, = the specific activity of lodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/ cubic centimeter) F, = the discharge flow rate for (simultaneous) release, r (cubic meters per second) If the discharge flow rate is unknown (e.g., the release has not been conducted), the
" Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.
Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). c' = a conversion constant (1E6 cubic centimeters per cubic meter) e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS 1
_________________________j
Offsite Dose Calculation Manual Page 166 of 298 -
- Revision 2, Change 0 a). Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for annual organ dose rates for gaseous emuents and shall specify corrective ACTIONS to be initiated when these limits are exceeded b) - Refer to Specification 3.11.2.1 for ACTIONS to be taken in the event the
.\' calculated annual organ dose rate to any organ exceeds 1500 mr/yr. H. Cumulative Gamma Air Doses Due To Noble Gases in Gaseous Emuents
- 1. Introduction a) Appendix 1 to 10 CFR 50 specifies cumulative gamma air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.
b) Radiological emuent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. c) These radiological emuent controls are described below.
- 2. Radiological Effluent Controls a) The cumulative gamma air dose, due to noble gases in gaseous emuents released to UNRESTRICTED AREAS, shall be less than 10 mrads in any calendar quarter, and shall be less than 20 mrads in any calendar year (per Specification 3.11.2.2) b) The routine surveillances which are performed to verify compliance with ;
these radiological effluent controls are described below.
- 3. Surveillance Requirement (s) a) The cumulative gamma air doses, for the current calendar month, the calendar quarter, and the current calendar year, due to noble gases in i gaseous effluents, shall be determined at least once every 60 days (
Specification 4.11.2.2). b) The plant group (s) responsible for performing the required surveillance (s) are identified below.
- 4. Responsible Plant Organizations ;
i a) The Chemistry Section is responsible for calculating the cumulative l gamma air doses for the current calendar quarter and the current I calendar year. _ b) The CCNPP Chemistry Section calculates the cumulative gamma air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions
3 , Offsete Dose Calculation Mcnual Page 167 of 298 ! RCvision 2, Change 0 l a) The cumulative gamma air doses due to noble gases in gaseous l emuents shall be determined at least once per 60 days ( Specification 4.11.2.2). j, b) - The cumulative gamma air coses due to noble gases in gaseous emuents shall be calculated for each release of a WGDT (CP-604). The cumulative gamma air doses due to noble gases in gaseous I c) . effluents shall be calculated for each vent of a containment building (CP- : 604). d) The cumulative gamma air doses due to noble gases in gaseous , effluents shall be calculated for each PURGE of a containment building l (CP404). j e) The cumulative gamma air doses due to nop gases in gaseous ' effluents shall be calculated at least weekly for CONTINUOUS discharges from plant vent stacks (CP-612). l f) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each discharge of combustion products 1 resulting from the buming of contaminated oil. g) The cumulative gamma air doses due to noble gases in gaseous ; effluents shall be calculated for each ABNORMAL AND/OR .
! UNANTICIPATED RADIOACTIVE GAS RELEASE' (CP412).
6 h) Whenever the correct initiating conditions are present, the cumulative ! 3 gamma air doses shall be calculated as described below. -
- 6. Calculation Methodology ;
a) The cumulative gamma air dose at the SITE BOUNDARY (e.g., for the . r current calendar month, current calendar quarter, current calendar year, : or previous g2 days) due to noble gases in gaseous effluents shall be calculated using the following equation"- l CUMULATIVE GAMMA, g, AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t .l D, = h D,, Eq.17G Where,
" The frequency is controlled by the implementing procedure, CP 612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).
" The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in CP-612 or CP-604.
" The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Specification 3.3.3.9).
._ . _ . . - . . - _ . . _ _ _ _ _ _ _ _ . _ _ - - - - _ _ _ _ _ _ . _ . _ _ . . _ _ _ _ . . _ _ ~ _ ,
Offsite Dose Calculation Manud Page 168 of 298 Revision 2, Change 0
.Dg: = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas ,
radionuclides contained in all gaseous radweste discharged from the site during the ; time interval, t
~ D,, = the cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in gaseous radweste release, r, discharged from the site ;
during the time interval ofinterest i t , Calculate the values of Derfor each gaseous release as described below. - b) At CCNPP, two methods exist for calculating Der (i.e., the gamma air i dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site dunng a 4 specified time interval). i (1) The rigorous method shall be used IF a computer system and the ! appropriate software are available. ! (2) The simplified method may be used IF a computer system and the : appropriate software are NOT available. ; (3) These methods, as well as additional supporting information, are presented in the following sections. c) rigorous method (1) Solution of the following equation may prove too rigorous for ; routine use unless a computer system and appropriate software .i are available. (2) If a computer system and the appropriate software are available, ! the gamma air dose due to noble gases in gaseous effluents , released to UNRESTRICTED AREAS shall be calculated in : accordance with equation 18G. l l GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION) , i D,, = ( 3.17E-0 ) ( x/Q ) h [ ( M )i ( Q'y ) ) Eq.18Go2 Where, 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of 4 seconds in a year. x/Q = the highest calculated annual average relative concentration for any area at or ' beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases'3, and as such, the highest ! historical annual average dispersion factor, (x/Q), is used in the dose calculations. -j i s2 Equation 18G has been derived from NUREG-0133,5.3.1..
Offsite Dose Calculation Minuil Paga 169 of 298 Revision 2, Change 0 The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on-shore concentrations occur in the southvast i' sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). M, = the air dose factor due to gamma emissions for each identified noble gas radionuclide, I (mradlyr per microcurie / cubic meter) The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10. Q'i, = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries). At CCNPP, all releases are considered long term releases. Calculate the values of Q i , for each release in accordance with equation 19G. TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r , Q'i, = ( A,) i ( F,) ( t,) i ( c' ). Eq.19G i A,, = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter) 1 F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be : used to calculate the average activity for nuclide 1. Whenever possible, the actual discharge flow rate determined from actual release conditions (e.g., initial pressure, volume, and temperature of a WGDT along with ' final pressure and temperature) shall be used in equation 19G. f Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). t, = the duration of the gaseous radwaste release (seconds) , c' = a conversion constant,1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter. " NUREG-0133, 3.3 ; i 4
Offsite Does Calculation Manual Page 170 of 298 Revision 2, Change o l
'(3) In the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous emuents released to UNRESTRICTED '
AREAS. t (4) . The simplified method is presented below, d) simplified method 7 (1) If a computer system and appropriate software are NOT available to perform the rigorous gamma air dose calculation described in the previous section, the gamma air dose, due to noble gas radionuclides, in any single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 20G. GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) D,, = [ ( 3.17E-8 ) ( x/Q ) ( M , ) / Kg ] h Qi, . Eq.20G" 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of f seconds in a year. [ x/Q = the highest calculated annual average relative concentration for any area at or ! beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases'8, and as such, the highest i historical annual average dispersion factor, (x/Q), is used in the dose calculations. The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for i purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). . The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). j M., = the empirically derived; site specific, average gamma air dose factor for each identified noble gas radionuclide, I (mradlyr per microcurie / cubic meter) A site-specific, average, gamma air dose factor has been calculated from historical data. j The calculation of this site-specific, average, gamma air dose factor is presented on ; Attachment 11 (use section 3.4.5 of the old ODCM.) 1
" Equation 20G has been derived from NUREG-0133,5.3.1. " NUREG-0133,3.3
Offsite Dose Cr.iculation Minual Page 171 cf 298 ; Rev:eion 2, Ch;nge 0 K, = a constant, actually a safety factor, which is the ratio of the CCNPP gamma air dose limit to the gamma air dose limit of Specification 3.11.2.2, (unitiess)
'- The safety factor chosen shall be less than or equal to 1.00. This ensures the gamma air dose is always less than or equal to the gamma air dose limit of ,
i Specification 3.11.2.2. A safety factor of 1.00 will yield an gamma air dose which corresponds to the i gamma air dose limit of Specification 3.11.2.2. A safety factor of 0.500 will yield an gamma air dose which corresponds to one-half the gamma air dose limit of Specification 3.11.2.2. , it is recommended that a safety factor of 1.0 be used for calculating the gamma air dose, however, other values-not to exceed 1.00-may be used as directed by the l General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control ; over the use of simplified equations for generating radioactive gaseous release , permits. This administrative control is designed to minimize the possibility of - ; violating Specification 3.11.2.2 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20], make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as : is reasonably achievable." j This safety factor has been included in equation 20G to account for any potential nonconservatism associated with applying the empirically derived gamma air dose factor, M,y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a j gamma air dose factor greater than M., are present in a gaseous release. l Qi, = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries) j At CCNPP, all releases are considered long term releases. Calculate the values of Q, for each release in accordance with equation 19G. I L TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = ( A,) ( F,) ( t, ) ( c' ) Eq.19G A, = the specific activity of noble gas radionuclide, i, in release, r, discharged during the i time interval of interest (microcuries/ cubic centimeter). ! 1 F, = the discharge flow rate for release, r, discharged during the time interval of interest ! (cubic meters per second). l
i Offsite Dose Calculation Manual Page 172 of 298 - Revision 2, Change 0 l If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i. l Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). t, = the duration of the gaseous radwaste release (seconds). c' = a conversion constant,1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter. e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for quarterly and yearly gamma air doses for gaseous effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.
b) Refer to Specification 3.11.2.2 for ACTIONS to be taken in the event the calculated cumulative gamma air doses exceed 10 mrads per calendar quarter or 20 mrads per calendar year.
- l. Cumulative Beta Air Doses Due To Noble Gases in Gaseous Effluents
- 1. Introduction a) Appendix l to 10 CFR 50 specifies cumulative beta air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls a) The cumulative beta air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 20 mrads in any calendar quarter, and shall be less than 40 mrads in any calendar year (per Specification 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
- 3. Surveillance Requirement (s) i 1
Offsite Dose Calculation Manual Page 173 of 298 Revtion 2, Change 0 a) The cumulative beta air doses,ior the current calendar quarter and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days ( Specification 4.11.2.2). , b) The plant group (s) responsible for performing the required surveillance (s) l are identified below.
- 4. Responsible Plant Organizations a) The Chemistry Section is responsible for calculating the cumulative beta air doses for the current calendar quarter and the current calendar year.
I b) The CCNPP Chemistry Section calculates the cumulative beta air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.
- 5. Initiating Conditions a) The cumulative beta air doses due to noble gases in gaseous effluents shall be determined at least once per 60 days ( Specification 4.11.2.2).
b) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each release of a WGDT (CP-604). c) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each vent of a containment building (CP-604). d) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each PURGE of a containment building (CP-604). e) The cumulative beta air doses due to noble gases in gaseous effluents are calculated at least weekly'8 for CONTINUOUS discharges from plarit ) vent stacks (CP-612). l f) The cumulative beta air doses due to noble gases in gaseous effluents I are calculated for each discharge of combustion products resulting from the burning of contaminated oil, g) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE'7 (CP-612). h) Whenever the correct initiating conditions are present, the cumulative beta air doses shall be calculated as described below. Calculation Methodology i 6.
' " The frequency is controlled by the implementing procedere, CP-612, and is based on plant ;
l conditions. Under no conditions shall the frequency be less than once per month (Technical J Specification 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2). '
The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in CP-612 or CP-604.
s
Offsite Dose Cricuttion Manu 1 Pag 3174 of 298 -- Revision 2, Ch nge 0 a) The cumulative beta air doses (e.g., for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated in accordance with equation 21G. CUMULATIVE BETA AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dat
= 0 Ds,eq. 21G ,
Where, Dat
= the cumulative beta air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contair.ed in all gaseous radwaste discharged from the site during the time interval, t Da, = the beta air dose (mrad) due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of Dg, for each gaseous release as described below.
b) At CCNPP, two methods exist for calculating Dar (the beta air dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site). (1) The rigorous method shall be used IF a computer system and the appropriate software are available. (2) The simplified method may be used IF a computer system and the - appropriate software are NOT available. (3) These methods, as well as additional supporting information, are presented in the following sections. c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available. (2) If a computer system and the appropriate software are available, the cumulative beta air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated i in accordance with equation 22G. BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)
Offsite Dose C:lculation M:nual Page 175 of 298 R; vision 2, Ching) 0 Da, = ( 3.17E-8 ) ( x/Q ) h [ ( Ni ) ( Qi, ) ] Eq. 22G" , f Where, Da, = the beta air dose due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of seconds in a year. x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases", and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. i The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR,2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). N, = the air dose factor due to beta emissions for each identified noble gas radionuclide, i 4 (mradlyr per microcurie / cubic meter) The beta air dose factors have been obtained from Regulatory Guide 1.109, l Appendix B Table B-1. j l The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10 (Attachment 1 of old ODCM). Oi, = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries). At CCNPP, all releases are considered long term releases. l Calculate the values of Q,, for each release in accordance with equation 19G. l TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLlDE iIN GASEOUS RELEASE r Qi, = ( A,, ) ( F, ) ( it , ) ( c' ) Eq.19G A,, = the specific activity of noble gas radionuclide, i, in release, r, discharged during the l time interval of interest (microcuries/ cubic centimeter).
" Equation 22G has been derived from NUREG-0133,5.3.1.
" NUREG-0133, 3.3 1
E_ _ ______ _ _______ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Offsito Dose Calculation Manual Page 178 of 298 - Revision 2, Change 0 F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second). If the discharge flow rate is unknown (e.g., the gassous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i. Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). tg = the duration of the gaseous radwaste release (seconds). - c' = a conversion constant,1E6 cubic centimeters per cubic meter. (3) in the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS (4) The simplified method is presented below. d) Simplified method (1) If a computer system and the appropriate software are NOT available to perform the rigorous beta air dose calculation described in the previous section, the beta air dose resulting from a single release of waste gases discharged to UNRESTRICTED AREAS may be calculated in accordance with equation 23G. - BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION) Da, = [ ( 3.17E-8 ) ( x/Q ) ( N , ) / K.,] h O'u Eq.23G'" 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of seconds in a year. x/Q = . the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) All releases are considered "long-term" releases *, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations. ; The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR, 2.3.6.3). ]
- Equation 23G has been derived from NUREG-0133,5.3.1.
- NUREG-0133, 3.3 i
l i
Offsite Dose Cilculation MInu;I Page 177 cf 298 R;vhion 2, Chrnge 0 The maximum annual average on-shore concentrations occur in the southeast sector at a distance cf 1300 meters for purposes of routine, long-term concentrations (e.g., routine noble gas releases) (UFSAR,2.3.6.3). N,, = the empirically derived, site specific, average beta air dose factor for each identified noble gas radionuclide, I (mrad /yr per microcurie / cubic meter) A site-specific, average, beta air dose factor has been calculated from historical data. The calculation of this site-specific, average, beta air dose factor is presented on Attachment 11. K., = a constant, actually a safety factor, which is the ratio of the CCNPP beta air dose j limit to the beta air dose limit of Specification 3.11.2.2, (unitiess) { The safety factor chosen shall be less than or equal to 1.00. This ensures the beta air dose is always less than or equal to the beta air dose limit of Specification 3.11.2.2. A safety factor of 1.00 will yield an organ dose which corresponds to the beta air dose limit of Specification 3.11.2.2. l A safety factor of 0.500 will yield an beta air dose which corresponds to one-half the beta air dose limit of Specification 3.11.2.2. It is recommended that a safety factor of 1.0 be used for calculating the beta air dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. , The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Specification 3.11.2.2 when simplifying assumptions are used. l The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... in addition to complying with the limits set forth in this part [10 CFR 20), make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." This safety factor has been included in equation 23G to account for any potential nonconservatism associated with applying the empirically derived beta air dose factor, N,y, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a beta air dose factor greater than N,y are present in a gaseous release. Qi = the total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries) At CCNPP, all releases are considered long term releases. Calculate the values of Q, for each release in accordance with equation 19G. L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Offsite Dose Calculation Manual Page 178 of 298 - Revision 2, Change 0 TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE iIN GASEOUS RELEASE r Q'i, = ( A,, ) ( F, ) ( it , ) ( c' ) Eq.19G A,, = the specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter) F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) , if the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i. Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). t,i = the duration of the gaseous radwaste release (seconds). c' = a conversion constant,1E6 cubic centimeters per cubic meter. e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-213) shall contain/and or reference administrative and/or Technical Specification limits for quarterly and yearly beta air doses for gaseous effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.
b) Refer to Specification 3.11.2.2 for ACTIONS to be taken in the event the calculated cumulative beta air doses exceed 20 mrads per calendar quarter or 40 mrads per calendar year. J. Cumulative Organ Doses Due To lodines And Particulates in Gaseous Effluents
- 1. Introduction a) Appendix l to 10 CFR 50 specifies cumulative organ dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix 1. c) These radiological effluent controls are described below.
- 2. Radiological Effluent Controls
~ .
~ .. - -
Offsete Deze Calculation Manual . Page 179 of 298
- Revision 2, Change 0 a) The cumulative organ dose due to iodines and particulates in gaseous emuents released to UNRESTRICTED AREAS shall be less than 15 mrems per calendar quarter, and shall be less than 30 mrems per calendar year (per Specification 3.11.2.3).
b) The cumulative organ dose due to lodines and particulates in gaseous, contaminated oil combustion products released to UNRESTRICTED AREAS shall be less than 0.015 mrems per quarter, and shall be less than 0.030 mrems per year (per Specification 3.11.2.3). :
?
c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.
- 3. Surveillance Requirements a) The cumulative organ doses (due to iodines and particulates in gaseous -
waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 60 days in accordance with the ODCM (per Specification 4.11.2.3). l b) The plant group (s) responsible for performing the required surveillances are identified below.-
- 4. Responsible Plant Organizations ,
a) The Chemistry Section is responsible for implementing the surveillances required by Specification 4.11.2.3. i i b) The CCNPP Chemistry Section calculates the cumulative organ doses j . whenever the appropriate initiating conditions are present 4 c) These initiating conditions are contained in the following section. l l
- 5. Initiating Conditions ,
a) The cumulative organ dose-for each organ-shall be determined at least i once per 60 days ( Specification 4.11.2.2). j
. I b) The cumulativa organ dose-for each organ-due to iodines and l particulates in gaseous effluents shall be calculated at least weekly" for -l CONTINUOUS discharges from plant vent stacks (CP-612).
c) The cumulative organ dose-for each organ--due to iodines and l particulates in gaseous effluents shall be calculated for each discharge of combustion products resulting from the buming of contaminated oil. 1 d) The cumulative organ dose-for each organ-due to iodines and j particulates in gaseous emuents shall be calculated for each ABNORMAL AND/OR UNAN1lCIPATED RADIOACTIVE GAS RELEASE (CP-612).
- The frequency is controlled by the implementing procedure, CP-612, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Specification !
4.11.2.1.1 or 4.11.2.1.2, Table 4.112). l
' ~
~ I l:
; Offsite Dose Calculation Manual Page 180 of 298 -
Revision 2, Change O L e) Whenever the correct initiating conditions are present, the annual cumulative organ doses shall be calculated as described below. ;
- 6. Calculation Methodology L a) The cumulative organ doses (for the calendar month, calendar quarter, l
previous 92 days, and calendar year) due to iodines and particulates in l' gaseous waste discharged to UNRESTRICTED AREAS shall be calculated in accordance with equation 24G. CUMULATIVE DOSE TO ORGAN, o, FROM ALL GASEOUS RELEASES, r, DISCHARGED : DURING TIME INTERVAL, t D, = h D , Eq. 24G Where, Det = the cumulative dose (mrad) to organ, o, at the SITE BOUNDARY, due to iodine and particulate radionuclides contained in gaseous waste discharged from the site during _ ! the time interval, t D, = the cose (mrad) to organ, o, at the SITE BOUNDARY due to iodine and particulate o radionuclides in gaseous release, r, discharged from the site during the time interval of interest Calculate the values of Do, for each gaseous release as described below. b) At CCNPP, two methods exist for calculating D (the organ doses due to lodines and particulates resulting from any sing 7e release of radioactive 1 gases to an UNRESTRICTED AREA). (1) The rigorous method shall be used IF a computer system and the ! appropriate software are available. -l (2) The simplified method may be used IF a computer system and the appropriate software are NOT available. (3) These methods, as well as additional supporting information, are i presented in the following sections. c) Rigorous method . (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and the appropriate software are available. ; (2) If a computer system and the appropriate software are available, the organ doses due to iodines and particulates contained in any ; single release of radioactive gases to UNRESTRICTED AREAS shall be calculated in accordance with equation 25G. t b 7 1 d e ---
Offsite Dose C:lculation Minuti Pags 181 of 298 R:vtion 2, Ching2 0 DOSE TO ORGAN, o, DUE TO IODINES AND PARTICULATES IN GAS RELEASE, r (RIGOROUS EQUATION) D,o
= ( 3.17E-8 ) ( W, ) h ( R,,, ) ( O'i, ) Eq. 25G' 8
- Where, D,o
= the dose (mrem) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the site during the time interval of interest 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of seconds in a year.
W, = the dispersion parameter for estimating the dose to an individual at the controlling , location for long term releases, and may assume one of two values as described below W, is x/Q for the inhalation pathway (2.2E-6 sec/ cubic meter) W,is D/O for the food and ground plane pathways (meters-2) D/O = the dispersion parameter at the controlling location for long term releases (meters-2) The value for D/Q has been determined to be 8.63E-10 m-2,1N The grass-cow-milk pathway is the controlling pathway.' 8 The controlling sector is the south-southwest sector.' 8 The controlling location is at a distance of 4800 meters.'07 R,,o = the dose factor for each identified iodine or particut te radionuclide, i, exposure pathway, p, receptor age group, a, and organ, o (m mrem / year per microcuries/second or mrem / year per microcuries/ cubic meter) dose factors have been derived for the following pathways
- 1) inhalation - see Attachment 12
- 2) ground plane - see Attachment 12
- 3) grass-cow-milk-see Attachment 12
- 4) grass-cow-meat - see Attachment 12
- Equation 25G has been derived from NUREG-0133,5.3.1.
- See CP-607, Revision 2 section 3.4.3. !
- See the " Land Use Survey",1990.
- It should be noted that the controlling sector mentioned in the UFSAR, section 2.3.6.4, is inaccurate because the UFSAR has not been updated to include the results of the 1990 " Land Use Survey."
- See the " Land Use Survey",1990.
._ _ _ _ _ _ _ . . . ._ _ _. . 4 _ .
s Offsde Dose Calculation Manual Page 182 of 298 - Revision 2, Change 0 ,
.i
- 5) vegetation - see Attachment 12 The inhalation pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.1. .
The ground plane dose factors were obtained using the formula from NUREG-0133, -l 5.3.1.2. , The grass-cow-milk pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.3. l The grass-cow-meat pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.4. ' f The vegetation pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.5. Q', =' the total (time averaged) activity of iodine or particulate radionuclice, i, in gaseous , release, r, discharged during the specified time interval (microcurie.s) { At CCNPP, all releases are considered long term releases. Calculate the values of Qirfor each release in accordance with equation 19G. l TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r ! Q'r = ( A,) ( F,) ( t,) ( c') Eq.19G l A,, = the specific activity of iodine and particulate radionuclide, i, in release, r, discharged ! during the time inteival of interest (microcuries/ cubic centimeter) - ! F, = the discharge flow rate for release,' r, discharged during the time interval of interest ; (cubic meters per second) 7 If the discharge flow rate is unknown (e.g., the gaseous radweste has not been l released), the " Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be i used to calculate the average activity for nuclide 1. l Additional guidance for calculating discharge flow rates may be contained in .; approved chemistry section procedures (e.g., CP-801 and CP-604). ! t, = the duration of the gaseous radweste release (seconds) ; c' = a conversion constant,1E6 cubic centimeters per cubic meter 3 (3) In the event a computer system and the appropriate software are unavailable, a simplified equation may be used to calculate the organ doses due to individual gaseous releases. ;
}
Offsde Dose Calculation ManurJ Page 183 of 298 Revision 2, Change 0 , (4) The simplified method is presented below. , d) simplified method (1) If a computer system and appropriate software are NOT available to perform the rigorous organ dose calculations described in the ' previous section, the organ doses due to iodines and particulates . in a single release of radioactive gases discharged to an UNRESTRICTED AREA may be calculated in accordance with ! equation 26G. DOSE TO ORGAN, o, FROM IODINES AND PARTICULATES IN GAS RELEASE, r (SIMPLIFIED EQUATION) D.,,, = [ ( 3.17E-8 ) ( W, ) ( Ry3, ) / Kg ] h ( Q'i, ) Eq. 26G* D.,,, = the maximum dose to any organ, o, due to iodines and particulates contained in any single release, r, of radioactive gases to an UNRESTRICTED AREA 3.17E-8 = The conversion constant,3.17E-8, represents the inverse of the number of seconds in a year. D/Q = the dispersion parameter at the controlling location for long term releases (meters.2) The value for D/Q has been determined to be 8.63E-10 m-2,* e The grass-cow-milk pathway is the controlling pathway."' The controlling sector is the south-southwest sector "' The controlling location is at a distance of 4800 meters." l Ry33 = the infant, thyroid, dose factor for 1-131 via the grass-cow-milk pathway (m2 mrem / year per microcuries/second) This value is 1.05E12 and it is listed on Attachment 12. Kg = a constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Specification 3.11.2.3, (unitiess) The safety factor chosen shall be less than or equal to 1.00. This ensures the organ , dose is always less than or equal to the organ dose limit of Specification 3.11.2.3.
'" i Equation 26G has been derived from NUREG-0133,5.3.1.
- See CP-607, Revision 2 section 3.4.3.
"' See the " Land Use Survey",1990. "' It should be noted that the controlling sector mentioned in the UFSAR, secton 2.3.6.4, is inaccurate because the UFSAR has not been updated to include the results of the 1990 " Land Use Survey." "* See the Land Use Survey",1990.
l Offsite Dose Calculation Manual Page 184 of 298 l Revision 2, Change O A safety factor of 1.00 will yield an organ dose which corresponds to the organ dose limit of Specification 3.11.2.3. A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose limit of Specification 3.11.2.3. It is recommended that a safety factor of 1.0 be used for calculating the organ dose, however, other values-not to exceed 1.00-may be used as directed by the General Supervisor Chemistry. The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative controlis designed to minimize the possibility of violating Specification 3.11.2.3 when simplifying assumptions are used. The use of a safety factor is consistent with 10 CFR 20.1(c) which states that the licensees should, "... In addition to complying with the limits set forth in this part [10 CFR 20], make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable." This safety factor has been included in equation 2GG to account for any potential nonconservatism associated with applying the infant, thyroid, grass-cow-milk dose factor, Ry33, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a pathway dose factor greater ihan Ry3, are present in a gaseous release. O'y = the total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r (microcuries) At CCNPP, all releases are considered long term releases. This value shall be calculated in accordance with equation 19G. TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE iIN GASEOUS RELEASE r Q', = ( A, ) ( F,) ( t, ) ( c' ) Eq.19G A, = the specific activity of iodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/ cubic centimeter) F, = the discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second) If the discharge flow rate is unknown (e.g., the gaseous radwaste has not been released), the Maximum Discharge Flow Rate" listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide 1. l
Offsite Dose C:lculation Minu 1 Paga 185 of 298 Revision 2. Change 0 Additional guidance for calculating discharge flow rates may be contained in approved chemistry section procedures (e.g., CP-601 and CP-604). t, = the duration of the gaseous radwaste release (seconds) c' = a conversion constant,1E6 cubic centimeters per cubic meter e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-213) shull contain/and or reference administrative and/or Technical Specification limits for cumulative organ dose for gaseous effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.
b) Refer to Specification 3.11.2.3 for ACTIONS to be taken in the event the calculated cumulative gamma air doses exceed any of the radiological effluent controls listed above. K. Limits For The Gaseous Waste Processing System
- 1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the gaseous waste processing system for the purpose of controlling effluents to the environment.
b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a. c; These radiological effluent controls are described below.
- 2. Radiological effluent controls a) The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXiMUST TREATMENT SYSTEM shall be used to reduce radioactive rr,cterials in gaseous waste prior to their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 1.20 mrads gamma radiation in a 92 day period (per Specification 3.11.2.4).
b) The GASEOUS RADWASTE TREATMENT JYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air dose, to isreas at and beyond the SITE BOUNDARY, exceeds 2.4 mrads beta radiation in a 92 day period (per ; Specification 3.11.2.4). ! 1 l
Offsite Dose Calculation Manual Page 186 of 298 Revision 2, Change O c) The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce the quantity of radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY exceeds 1.80 mrem to any organ in a 92 day period (per Specification 3.11.2.4). d) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.
- 3. Surveillance Requirement (s) a) The cumulative gamma air dose, for the previous 92 days, due to noble gases in gaseous effluents, shall be determined at least once every 60 days ( Specification 4.11.2.2).
b) The plant group (s) responsible for performing the required surveillance (s) are identified below.
- 4. Responsible Plant Organizations a) The Chemistry Section is responsible for calculating the cumulative gamma air doses for the current calendar month, the previous 92 days, the current calendar quarter, and the current calendar year.
b) The cumulative gamma air dc,.,s for the p;avious 92 days is calculated whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.
- 5. Initiating conditions a) For a listing of initiating conditions associated with calculating gamma air doses, see " Initiating Conditions"in the section of the ODCM titled,
" Cumulative Gamma Air Doses Due To Noble Gases in Gaseous Effluents."
b) For a listing of initiating conditions associated with calculcting beta air drees, see " Initiating Conditions"in the section of the ODCM titled, "C a 7lative Beta Air Doses Due To Noble Gases in Gaseous Effluents." c) For a listing of initiating conditions associated with calculating cumulative organ doses, see " initiating Conditions"in the section of the ODCM titled,
" Cumulative Organ Doses Due To lodines And Particulates in Gaseous Effluents."
- 6. Calculation methodology a) Calculate the previous 92-day cumulative gamma air dose as described in the section " Cumulative Gamma Air Doses Due To Noble Gases in Gaseous Effluents."
b) Calculate the previous 92-day cumulative beta air dose as described in the section " Cumulative Beta Air Doses Due To Noble Gases in Gaseous Effluents."
Offsite Dose Calculation Manual Page 187 of 298 - Revision 2 Change O c) Calculate the previoua 92-day cumulative organ dose as described in the section " Cumulative Organ Doses Due To lodines And Particulates In Gaseous Effluents;."
- 7. Corrective ACTIONS a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification limits for 92-day cumulative gamma, beta, or organ doses for gaseous effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded, b) Refer to Specification 3.11.2.4 for ACTIONS to be taken in the event the calculated 92-day cumulative gamma air, beta air, or organ doses exceed any of the radiological effluent controls listed above. ,
i L. Limits On Total Annual Dose - Gases, Liquids, and Uranium Fuel Cycle Sources j
- 1. Introduction a) 40 CFR 190 specifies annual dose limits for radionuclides released to the I environment.
o) Radiological effluent controls have been established to implement the requirements of 40 CFR 190. l 1 c) These radiological effluent controls are described below.
- 2. Radiological effluent controls a) The total body dose from exposure to the combination of liquid releases, '
gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Specification 3.11.4). \ l b) The organ dose (for the maximum exposed organ, not including the thyroid) from exposure to the combination of liquid releases, gas l releases, and uranium fuel cyt,le sources shall be less than 25 mrem for ) the current calendar year (per Specification 3.11.4). c) The thyroid dose from exposure to the combination ofliquid releases, gas releases, and uranium fuel cycle sources shall be less than 75 mrem for the current calendar year (per Specification 3.11.4). d) The routine surveillances which are perforn;ed to verify compliance with these radiological effluent controls are descrined below. j 3. Surveillance Requirements a) The cumulative gamma air doses, for current calendar month, the current calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 60 days ( Specification 4.11.2.2).
l l l Offsite Dose Calculation M:ne:1 Page 188 of 298 ) Revision 2, Change 0 l b) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar i month, the current calendar quarter, and the current calendar year, shall l be determined at least once every 60 days in accordance with the ODCM (per Specification 4.11.2.3). c) Cumulative total body dose to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the calendar quarter, and the current calendar year-shall be calculated at least once per 60 days (per Specification 4.11.1.2). d) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS-for the current calendar month, the current calendar quarter, and the current calendar year-shall be calculated at leest once per 60 days (per Specification 4.11.1.2). e) The direct radiation dose to members of the public exposed to uranium fuel cycle sources (i.e., recctor units and outside storage tanks) shall be determined IF THE APPROPR! ATE INITIATING CONDITIONS ARE , PRESENT. 4
- 4. Responsible Plant Organization (s) a) The Chemistry Sec+ ion is responsible for implementing the effluent surveillances requireo by Specification 4.11.4.1.
b) The Chemistry Programs Unit, BG&E CCNPPD, is responsible for
- ensuring implementation of the direct radiation surveillances required by Specification 4.11.4.2.
c) it should be noted that no survcillances need be pecformed unless the appropriate initiating conditions are present. d) These initiating conditions are contained in the following section.
- 5. Initiating conditions a) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated doses from liquid effluents exceed any of the following (per Specification 4.11.4.2):
(1) Six (6) mrem per nyarter to the total body (2) Twelve (12) mrom per calendar year to the total body (3) Twenty (20) mrem per quarter to any organ (4) Forty (40) mrem per calendar year to any organ b) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated air doses from noble gasses in gaseous effluents exceed any of the following (per Specification 4.11.4.2): I 1
Offsite Dose Calculation Manu;l Page 189 of 298 - Revision 2 Change 0 (1) Twenty (20) mrad gamma per quarter (2) Forty (40) mrad gamma per calendar year (3) Forty (40) mrad beta per quarter (4) Eighty (80) mrad beta per calendar year c) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated organ doses from iodines and particulates in gaseous effluents exceed any of the following (per Specification 4.11.4.2): (1) Thirty (30) mrem per quarter to any organ (2) Sixty (60) mrem per calendar year to any organ d) Whenever the correct initiating conditions are present, the total doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be caiculated as shown below.
- 6. Calculation methodology a) The total body dose and the organ doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated in accordance with equation 1T and 2T respectively.
TOTAL, TOTAL BODY DOSE FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Dean
= Drot + Dg+ D ,nu Eq.1T TOTAL ORGAN DOSES FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Do.n = Drot + Dot+ D ,ng e
Eq.2T Desu
= the dose (mrem) to total body resulting from the combination of all gas releases, all liquid releases, and all uranium fuel cycle sources.
Dnea
= the dose (mrem) to organ, o, resulting from the combination of all gas releases, all ;
liquid releases, and all uranium fuel cycle sources. Separate values shall be calculated for each of the organs listed below:
- 1. bone
- 2. liver
A Offsite Dose Calculation Manual Page 190 of 298 Revision 2, Change 0 .!
- 3. thyroid
- 4. kidney
- 5. lung 6, Gl tract -
Da = the cumulative dose (mrem) to organ, o, for all liquid releases discharged in a given l time interval i Calculate this value as specified by equation 8L. D, = the site-boundary cumulative gamms air dose (mrad) due to noble gas radionuclides ! contained in all gaseous radweste discharged from the site during the time interval, t Calculate this value as specified by equation 17G, except substitute K, for M (see Attachment 10). , Da = the site-boundary cumulative organ dose (mrem) resulting from the release of iodine ) and particulate radionuclides in gaseous releases from the site i Calculate this value as specified by equation 24G. ; Dung = the calendar-year cumulative dose (mrem) to the maximum exposed MEMBER OF THE PUBLIC due to direct radiation from the reactor units and outside storage tanks This value shall be based on the results of direct radiation measurements from TLDs or continuous dose rate instruments placed near the SITE BOUNDARY (e.g., from ' radiological environmental monitoring sites DR1-DR9 described on Attachment 13 . and shown on Attachment 18). The Environmental Programs Section, BG&E Corporate Affairs Group, and the f Radiation Safety Section are responsible for determining this value. b) Compare the calculated values to the radiological effluent controls (listed j in this section), and if any of the radiological effluent controls have been r exceeded, perform the appropriate corrective ACTIONS listed below. ! l
- 7. Corrective ACTIONS l
a) Chemistry Section surveillance procedures (e.g., CP-212) shall contain/and or reference administrative and/or Technical Specification limits for total dose for liquid releases, gaseous releases, and uranium fuel cycle sources and shal! specify corrective ACTIONS to be initiated i when these limits are exceeded. ! b) Refer to Specification 3.11.4 for ACTIONS to be taken in the event the ! total dose exceeds any of the radiological effluent controls listed above. l i I i
- _ - - . . - . _ _ _ _ . _______ _m
OFsib Dose Criculation Minu::1 Page 191 of 298 - Revtion 2, Ch*nge O c) If any of the radiological effluent controls have been exceeded, refer to 40 CFR 302, Appendix B, and verify the quantities of radioactive materials released are less than the values specified. [375B] M. Special Exceptions and Assumptions Fo Calculation of Doses and Dose Rates
- 1. Camp Conoy a) Location (1) Camp Conoy is located within the site boundary.
(2) Camp Conoy is located in the SE sector. (3) Camp Conoy is approximately 3000 feet from the plant. b) Occupancy (1) Camp Conoy is frequently visited by MEMBERS OF THE PUBLIC. (2) Maximum occupancy for MEMBERS OF THE PUBLIC at Camp Conoy is restricted to approximately 3380 hours per year. c) Meteorology (1) The highest historical annual average x/Q for Camp Conoy is 2.40E-6 seconds per cubic meter.' d) Dose calculation assumptions (1) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at Camp Conoy will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the site boundary."' (2) No special considerations are required for addressing potential exposure at Camp Conoy.
- 2. Visitors Center a) Location (1) The Visitors Center is located within the site boundary.
(2) The Visitors Center is located in the WNW sector. (3) The Visitors Center is approximately 1000 feet from the plant. b) Occupancy I l See CP-607, Revision 2 page 24. See CP-607. Revision 2 page 24.
,p . _ _ . _..
7 s i r Offsite Dose Calculation Manual Page 192 of 298 Revision 2 Change 0 l (1) The Visitors Center is frequently visited by MEMBERS OF THE l PUBLIC. i (2) Maximum occupancy for MEMBERS OF THE PUBLIC at The , . Visitors Center is restricted to daylight hours. ; 4 c) Meteorology . (1) The highest historical annual average x/Q for the Visitors Center - is 6.68E-6 seconds per cubic meter."5 (2) The wind frequency for the WNW sector, based on 1983 meteorological data, is four percent (4%)."' d) Dose calculation assumptions (1) "Using a conservative basis of 10% wind frequency, and individual visiting the center for 330 hours / year during the periods of worst case meteorological conditions would be mrpt highly exposed.""7 (2) The dose calculated for the controlling site baundary is more ! conservative by a factor of 7.us (3) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at The Visitors Center will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the site boundary. (4) No special considerations are required for addressing potential . exposure at The Visitors Center. 2 l See CP-607 Revision 2 page 24. See CP-607, Revision 2 page 24. l See CP-607. Revision 2 page 24. ! See CP-607, Revision 2 page 24. i
1 Offsite Dose Calculation Minual Page 193 of 298 Revbon 2, Ch;nge O VII. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program;119 l l
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.
b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1, Section IV.B.2. c) These radiological environmental controls are described below.
- 2. Controls on the Radiological Environmental Monitoring Program (REMP) l a) The REMP shall consist of environmental sample locations, analy::is parameters, analysis frequencies, detection limits, and ACTION levels p!!
of which conform to the requirements of Specification 3.12.1. (See i Attachment 13,14,15,16, and 17). I b) The REMP shall maintain a map showing sample locations near the site boundary in accordance with Specification 3.12.1. (See Attachment 18). c) The REMP shall maintain a map showing sample locations within a 8 km. { radius of the plant in accordance with Specificatian 6.9.1.7. (See i Attachment 19).
- 3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations DR1-DR23 listed on Attachment 13.
(2) In the event any of the monitoring stations, DR1-DR23, described on Attachment 13 become unavailable, establish new monitoring stations (with new dosimetry) as described below: 1 (a) In lieu of any location DR1-DR9 described on Attachment 13, establish a new monitoring station in the same meteorological sector in the general area of the SITE BOUNDARY.
- This portion of the environmental monitoring program is designed to monitor the environment surrounding the CCNPP. A separate environmental monitoring program designed to monitor the environment surrounding the Independent Spent Fuel Storage installation is described elsewhere j in the ODCM.
l . l
i Offste Dose Calculation Minu:1 Page 194 of 298 ' ; Revision 2, Change 0 j (b) in lieu of any location DR10-DR18 described on , Attachment 13, establish a new monitoring station in the ! same meteorological sector in the G-8 km range from the l site. ! (c) In lieu of any location DR19-DR23 described on I Attachment 13, establish a new monitoring station in either ; a special interest area (e.g.,' population center, nearby : residence, school) or a control station whicnever is : applicable. ; (3) In the event any dosimetry at an existing monitoring location DR1- t
)
DR23 becomes unavailable, place new dosimetry at the monitoring station. . (4)- Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14. , I (5) The sampling locations (s), excluding the control station location, i having the lowest calculated dose or dose comn.itment(s), via the , same exposure pathway, may be deleted from the , RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ! after October 31 of the year in which the land use census was conducted in accordance with Specification 3.12.2.b. -l b) Surveillances for airbome activity (1) Radioiodine and particulate samples shall be collected from - locations A1-A5 listed on Attachment 13.- (2) In the event any of the monitoring stations, A1-AS, described on . Attachment 13 become unavailable, establish new monitoring : station (s) (fitted with new radioiodine and particulate samplers) as ! described below: (a) In lieu of any location A1-A3 described on Attachment 13, , establish a new monitoring station in the general area of ; the SITE BOUNDARY, such that the three monitoring i stations are located in the meteorological sectors with the l three highest calculated annual average ground level D/Q. ) l (b) In lieu location A4 described on Attachment 13, establish a j new monitoring station near a community having the , highest calculated annual average ground level D/Q. (c) In lieu of location A5 described on Attachment 13 establish a new " control" location 15 to 30 kilometers from the plant in the least prevalent wind direction. (3) In the event any radioiodine cartridge or particulate filter becomes unavailable from an existing monitoring location A1-A5 described on Attachment 13, place new radioiodine cartridge or particulate filter in the air sampler at the monitoring station. I i
Offsite Dose Calculation ManuCI Page 195 of 298 Revision 2. Change 0 , (4) Analyze the samples at the frequencies and for the parameters identified on Attachment 15. , (5). The sampling locations (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPAM , after October 31 of the year in which the land use census was conducted in accordance with Specification 3.12.2.b. Surveillances of waterborne activity I c) (1) Water and sediment samples shall be collected from the locations Wa1, Wa2, and Wb1 listed on Attachment 13. l (2) in the event any of the samples at Wa1, Wa2, or Wbi are unavailable, collect substitute samples as described below: ; (a) In lieu of a liquid sample at Wa1, collect a substitute ,' sample of surface water from the intake area. (b) In lieu of a liquid sample at Wa2, collect a substitute sample of surface water from the discharge area. (c) In lieu of sample at Wb1, collect a substitute sample of {' sediment from a downstream shoreline with existing or potential recreational value. (3) Analyze the samp'es at the frequencies and for the parameters identified on Attachment 16. , The sampling locations (s), excluding the control station location,' ; (4) ' having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from the j RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted in accordanen with Specification 3.12.2.b. 1 i d) Surveillances for ingestible activity l (1) Fish / invertebrate, milk, and food product samples shall be ! collected from the locations lai thru la6 and Ib1 thru Ib9 listed on Attachment 13. ! (2) In the event any of the samples at la1 thru la6 or Ib1 thru 169 are ! unavailable, collect substitute samples as described below: (a) In lieu of samples at la1 thru la3, collect substitute three commercially and/or recreationally important species (two fish species and one invertebrate species) from the vicinity l of the plant discharge area. _ (b) in lieu of samples at la4 thru la6, collect three ; commercially and/or recreationally important species (two l r I
Offsite Dose Calculation Manual Page 196 of 298 Revision 2, Change O fish species and one invertebrate species) from an area not influenced by plant discharges. (c) In lieu of samples at Ib1 thru Ib6, collect three kinds of broad leaf vegetation grown near the SITE BOUNDARY at two different locations of highn everage ground level 120 D/Q , (d) In lieu of samples at Ib7 thru lb9, collect one sample each of the similar broad leaf vegetation grown 15-30 km distant ' in the least prevalent wind direction. f3) Analyze the samples at the frequencies and for the parameters identified on Attachment 17. (4) The sampling locations (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from the Radiological Environmental Monitoring Program after October 31 of the year in which the land use census was conducted in accordance with Specification 3.12.2.b.
- 4. Responsible Company Organizations a) The Chemistry Programs Unit, Chemistry Section, BG&E CCNPPD i:
responsible for ensuring performance of the surveillances listed above.
- 5. Initiating conditions a) Collect samples in accordance with the frequencies specified on Attachments 14,15,16, and 17.
b) Analyze samples in accordance with the frequencies specified on Attachments 15,16, and 17. c) Calculate the potential annual doses in accordance with the methodology outlined below if any of the following conditions are true: (1) any of the above surveillance results reveallevels of environmental activity greater than the ACTION Levels specified i on Attachments 15,16,17 (per Specification Table 3.12-2)
]
~(2) any radionuclides other than those in Attachments 15,16, and 17 are detected, and the radionuclides are the result of plant effluents.
d) The REMP Manager is responsible for notifying the General Supervisor-Chemistry, CCNPP, if any of the following conditions are true
- With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, perform corrective actions specified by Technical Specification S.12.1.c. l l
Offsete Dose Calculation M:nurl Page 197 of 298 Revtion 2 Ch:ngs 0 (1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 15,1617 (per Speedication Table 3.12-2) (2) any radionuclides other than those in Attachments 15,16, and 17 are detected, and the radionuclides are the result of plant effluents, and the potential annual doses due to the radionuclides are greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.
- 6. Calculation methodology a) If the correct initiating conditions, as described above, are present, calculate potential annual doses for the pathway of interest in accordance j with the methodologies contained in ODCM, or J b) if methodologies other than those listed in the ODCM are used to l calculate potential annual doses, such methodologies shall be documented in the AREOR in accordance with Specification 3.12.1.b.
- 7. Corrective ACTIONS a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR (per Specification 4.12.1, Table 3.12-1, notation "a").
b) If the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is not being conductod in accordance with Attachments 13,14,15,16, or 17 document deviations in the AREOR (per Specification 3.12.1.a). c) With fresh leafy vegetable samples unavailable from one or more of the ) sample locations listed on Attachment 13, establish a new monitoring l I location and document applicable information in the AREOR (per Spn;fication 3.12.1.c). d) When the analysis result for any parameter exceeds the ACTION Level i ,l listed on Attachments 15,16, or 17, submit a Special Report to the NRC l (per Specification 3.12.1.b). l e) When radionuclides other than those listed on Attachments 15,16, and ! 17 are detected; and if those radionuclides are the result of plant l effluents; and if the potential annual doses due to the radionuclides are greater than the calendar year limits c, Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3; submit a Special Report in accordance with Specification
- 3.12.1.b.
I B. Land Use Census
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.3 requires licensees to identify changes in the use of UNRESTRICTED AREAS in order to permit modifications in monitoring programs.
u s er i nqurtm1-
1 a Offsite Dose Calculation ManuCI Page 198 of 298 l Revision 2, Change 0 - ; 1
- b) Radiological environmental controls have been established to implement '
the requirements of 10 CFR 50, Appendix 1, Section IV.B.3. c) These radiological environmental controls are described below. I
- 2. Controls on the Land Use Census a) Identify the location of the nearest milk animal, within a distance of 8 km 4 of the plant site, in each of the g meteorological sectors (per !
Specification 3.12.2). E b) Identify the location of the nearest residence, within a distance of 8 km of - the plant site, in each of the g meteorolog! cal sectors (per Specification - 3.12.2). c) Identify the location of the nearest garden, within a distance of 8 km of ; the plant site, in each of the g meteorological sectors; or if the garden census was not conducted, obtain samples of three different kinds of broad leaf vegetation from the SITE BOUNDARY in two different j meteorological sectors which have the highest predicted SITE ! BOUNDARY D/Q (per Specification 3.12.2). l
- 3. Surveillance Requirement (s) !
Perform a land use census that will provide the best results. Example ; a) methods may include, but are not limited to, the following:
.l (1) door-to-door surveys j (2) serial views ;
(3) consult local agricultural authorities , b) Document the results of the land use census in the Annual Radiological t Environmental Operating Report in accordance with Specification 6.g.1.7. :
- 4. Responsible Company Organizations a) The Chemistry Programs Unit, BG&E CCNPPD, is responsible for ensuring the performance of the surveillances listed above.
- 5. Initiating conditions l a) Conduct the land use census during the growing season, and conduct the l land use census at least once per 12 months.
- 6. Calculation methodology a) Calculate doses for the pathways of interest in accordance with the
, methodologies contained in Regulatory Guide 1.10g, or b) if methodologies other than those listed in Regulatory Guide 1.10g are used to calculate doses, such methodologies should be documented in the Annual Radiological Environmental Operating Report.
Offsite Dose Calculation M:nu*l Pag)199 of 298 Revision 2, Change 0
- 7. Corrective ACTIONS a) The results of the land use census shah be used to determine the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM's samr>le locations identified on Attachmem 13.
b) If the land use census has identified a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, perform the following activities. (1) Document the new location (s) in the next Annual Radiological Environmental Operating Report in accordance with Specification 6.9.1.7, and (2) revise the figures and tables in the ODCM to reflect the new location (s). c) If the land use census has ident;iled a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) which is 20% greater than the equivalent location identified on Attachment 13, perform the following activities. (1) Add the new location (s) to the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM within 30 days, (2) document the new location (s) in the next Annual Radiological Environmental Operating Report in accordance with Specification 6.9.1.7, and (3) revise the figures and tables in the ODCM to reflect the new location (s). C. Interlaboratory Comparison Program
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.
b) Radiological environmental controls have been established to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. c) These radiological environmental controls are described below.
- 2. Controls on the Interlaboratory Comparison Program 1
I a) Analyze IN I'ERLABORATORY COMPARISON PROGRAM samples supplied by either the Commission or a Commission approved laboratory b
Offsite Dose CCiculation Manud Page 200 of 298 Revision 2, Change O for all parameters listed on Attachments 15,16, and/or 17, as applicable 121 (per Specification 3.12.3).
- 3. Surveillance Requirement (s) a) A summary of the results obtained as part of the interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.
b) This section of the ODCM shall describe the Interlaboratory Comparison Program.
- 4. Responsible Company Organizations a) The Chemistry Programs Unit, Chemistry Section, BG&E CCNPPD, is responsible for performing the surveillances listed above.
- 5. Initiating conditions a) Analyze INTERLABORATORY COMPARISON PROGRAM samples whenever they are supplied by either the Commission or a Commission approved laboratory.
- 6. Calculation methodology a) Analysis methods and calculational methodologies used to satisfy the above surveillances shall be documented in approved procedures.
- 7. Corrective ACTIONS a) If analyses are not performed as required, document ACTIONS taken to prevent reoccurrence in the Annual Radiological Environmental Operating Report (AREOR) pursuant to Specification 6.9.1.7.
D. Annual Radiological Environmental Operating
- 1. Introduction a) 10 CFR 50, Appendix 1, Section IV.B.2 requires licensees to provide data on measurable levels of radiation and radioactive materials in the environment.
b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix 1, Section IV.B.2. c) These radiological environmental controls are described below.
- 2. Controls on the Annual Radiological Environmental Operating Report (AREOR)
- The EPA may supply the INTERLABORATORY COMPARISON PROGRAM samples. Since no Commission approved laboratory supphes TLDs as part of a comparison program, no TLDs are analyzed as part of the INTERLABORATORY COMPARISON PROGRAM.
l l
- . .. _ .. . =- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
q OffsNe Dose C;iculation Manu 1 - Page 201 of 298 Revrion 2, Chinge 0 a) The AREOR shallinclude a summary description of the radiological environmental monitoring program (REMP). b) The AREOR shallinclude a summary description of the Independent Spent Fuel Storage installation Monitoring Program (ISFSIMP). c) The AREOR shall include a table similar to Attachment 13 which states p' the distance and direction from the central point between the two . containment buildings to each of the REMP sample points. d) The AREOR shall include a table similar to Attachment 20 which states the distance and direction from the central point of the ISFSI to each of the ISFSIMP sample points. e) The AREOR shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance J activities for the report period. f) The AREOR shall include a comparison between the annual REMP results and the Radiological Environmental Operating Report i preoperational studies. g) The AREOR shall include a comparison between the annual ISFSIMP results and Radiological Environmental Operating Report pre-fuel-load studies. h) The AREOR shall include a comparison with operational controls as appropriate. j i i) The AREOR shall include a comparison with the previous environmental surveillance reports. j) The AREOR shallinclude an assessment of the observed impacts of plant operation on the environment, k) The AREOR shall include an assessment of the observed impacts of ISFSI operation on the environment. l} The AREOR shall include the results of the land use censuses required by Specification 3.12.2. m) The AREOR shallinclude the results of analysis of all radiological environmenta, camples taken during the period pursuant to the locations { specified on Attachments 13 and 20. I n) The AREOR shallinclude the results of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20. , o) The AREOR shall include summarized and tabulated results-in the format of the table in the Radiological Asse,ssment Branch Technical Position, Revision 1, November 1979--of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20.
__ _ _ __ _ _._, _._ .. _ _ ~ . _ _ . _ _ _ . Offsite Dose Cilculation Minull Page 202 of 298
, Revision 2, Change 0 p)- The AREOR shallinclude summarized and tabulated results-in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979-of all environmental radiation measurements taken during the period pursuant to the locations specifed on Attachments 13 and 20. .j q) The AREOR shall include an explanation for missing results, if some .
individual results (as described in the above paragraph) are not available i forinclusion with the report. 1
. r) The AREOR shall include any data which was missing from previous .,
reports. : 122 s)' The AREOR shall include at least two legible maps covering all REMP ! sampling locations keyed to a table giving distances and directions from - the central point between the two containment buildings. t) The AREOR shallinclude at least one legible map covering all ISFSIMP i sampling locations keyed to a table giving distances and directions from ! the central point of the ISFSI. u) The AREOR shallinclude results of the licensee participation in the INTERLABORATORY COMPARISON PROGRAM required by Specification 3.12.3.
.v) The AREOR shallinclude a discussion of all deviations from the sampling .i schedules listed on Attachments 14,15,16, and 17, and specify the ;
reason (s) for the deviations, and the plan for preventing recurrence. , w) The AREOR shall include a discussion of all analyses in which the LLD listed on Attachments 15,16, and 17 (and required by Specification j Table 4.12-1) was not achievable. x) The AREOR shallinclude the identification of the cause of unavailability : of samples (if any), and describe the locations used for replacement samples. y) The AREOR shall include any permanent changes in the sample locations in the monitoring program, z) The AREOR shall include revised figure (s) (e.g., like Attachments 18 and l 19) and tables (e.g., like Attachment 13) for the ODCM which reflect any i new REMP sample location (s). ; sa) The AREOR shall include revised figure (s) (e.g., like Attachments 21 and
- 22) and table (s) (e.g., like Attachment 20) for the ODCM which reflect any new ISFSIMP sample location (s). j bb) The AREOR shall receive an independent review for technical content prior to submittal to the NRC.
l
- One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant )
stations.
Offsite Dose Calculation M:nual Page 203 of 298 Revrion 2 Change O cc) The AREOR shallidentify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result. I dd) material provided in the AREOR shall be consistent with the objectives ) outlined in the ODCM and 10 CFR 50, Appendix I, Section IV.3.2, IV.3.3 l and IV.C
- 3. Surveillance Requirement (s) a) Write the Annual Radiological Environmental Operating Report covering the previous calendar year's operation of the reactor units.
- 4. Responsible Company Organizations l
The Chemistry Programs Unit, BG&E CCNPPD, is responsible for ! a) 123 ensuring the performance of the surveillances listed above , (
- 5. Initiating conditions {
i Submit the Routine AREOR (covering operation of the reactor units for j a) the previous calendar year) by May 1 of each year. l l
- 6. Calculation methodology l I
a) Calculational methodologies used to satisfy the above surveillances l should be documented in approved procedures, or should be included in the AREOR.
- 7. Corrective ACTIONS a) If analyses are not performed as required, document ACTIONS taken to prevent reoccurrence in the AREOR pursuant to Specification 6.9.1.7.
l E, independern Spent Fuel Storage Installation Monitoring Program l l 1. Introduction a) The Technical Specifications for the Independent Spent Fuel Storage Installation12' (ISFSI), licensed under 10 CFR 72, require that monitoring for the ISFSI be added to the existing environmental monitoring program for CCNPP. b) BG&E has committed to additional monitoring for the ISFSI.125 l
- A separate company may M contracted to complete the Routine AREOR.
- The Technical Specifications For Calvert Cliffs Independent Spent Fuel Storage Installation is ,
Appendix"A' to Materials License SNM-2505. l l
- See the le'ter titled
- Response to NRC's Comments to Environmental issues Regarding BG&E's I License Application for Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI)" from Mr. R. E. Denton (BG&E) to Director, Office of Nuclear Material Safety and Safeguards (NRC),
, dated November 1,1990. , l 1 l I
9 Offsite Dose CCiculation Manual Page 204 of 298 Revision 2, Change O c) Radiological environmental controls have been established to implement the requirements and commitments described above. d) These radiological environmental controls are described below. i
- 2. Controls on the ISFSI Monitoring Program i
a) Environmental monitoring sites, as described in Attachment 20, shall be i established to monitor the air, vptation, and soil as well as direct , radiation in the ISFSI environs. - b) Analysis parameters, analysis frequencies, detection limits, and ACTION levels shall conform to the applicable requirements of Specifications 3.12.1. (See attachment 14,15,16, and 17) c) Map (s) shall be maintained and shall show the locations of the environmental monitoring sites with respect to plant facilities. (See attachment 21 and 22). .
- 3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations SFDR1-SFDR16, DR7, and DR30 listed in Attachment 20. ;
(2) in the event any dosimetry at an existing monitoring location : SFDR1-SFDR16, DR7, or DR30 becomes unavailable, place new ; dosimetry at the monitoring station. (3) Analyze the dosimeters at the frequencies and for the parameters + identified on Attachment 14. b) Surveillances for airborne particulate activity (1) Air particulate samples shall be collected from locations A1 and SFA1-SFA4 listed on Attachment 20. (2) In the event any particulate filter becomes unavailable from an existing monitoring location A1 or SFA1-SFA4 described on Attachment 20, place a new particulate filter in the air sampler at the monitoring station. (3) Analyze the samples at the frequencies and for the parameters identified under " Particulate Filters" on Attachment 15. c) Surveillances for deposition on vegetation Environmental monitoring sites and rnonitoring parameters specifically excluded from the ISFSIMP include airbome radioiodines, radioiodines in food products, surface water, and fish and invertebrates. Additionally, soil sampHs shall be collected in lieu of shoreline sediment. The sampling frequency for vegetation and soil shall be quarterly.
Offsite Dose Calculation M:nu:1 Page 205 of 298 i Revbion 2, Change 0 1 (1) The vegetation samples SFb1-SFb5 shall be collected from the locations listed on Attachment 20. (2) in the event any of the sampling sites SFbi-SFb5 described on l Attachment 20 become unavailable, establish new sampling sites as described below: (a) in lieu of sample SFb1, collect vegetation grown in the NW sector of the ISFSI. (b) In lieu of sample SFb2, collect vegetation grown in the general vicinity of the CCNPP Visitor's. Center. (c) In lieu of sample SFb3, collect vegetation grown in the North North West sector of the ISFSI. (d) In lieu of sample SFb4, collect vegetation grown in the South sector of the ISFSt. (e) In lieu of sample SFb5, collect vegetation grown in the Southeast sector of the ISFSI. (3) Analyze the samples quarterly for the non-lodine parameters identified under " Food Products" on Attachment 17. d) Surveillances for soil activity (1) The soil samples SFS1-SFS5 shall be collected from the locations listed on Attachment 20. (2) In the event any of the sampling sites SFS1-SFS5 described on Attachment 20 become unavailable, establish new sampling sites as described below: (a) in lieu of sample SFS1, collect soilin the NW sector of the l ISFSt. (b) In lieu of sample SFS2, collect soil in the general vicinity of the CCNPP Visitor's Center. (c) In lieu of sample SFS3, collect soil in the North North West sector of the ISFSI. (d) In lieu of sample SFS4, collect soil in the South sector of the ISFSI.
)
(e) in lieu of sample SFS5, collect soilin the Southeast sector of the ISFSt. (3) Analyze the samples quarterly for the parameters identified under
" Shoreline Sediment Sample" on Attachment 16.
- 4. Responsible Company Organizations
. _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ A
Offslie Dose Calculation Manu 1 'Page 206 of 298 Revision 2. Change 0 ; a) The Chemistry Section, BG&E CCNPPD, is responsible for ensuring the e performance of the surveillances listed above.
- 5. Initiating conditions ,
a) Collect samples in accordance with the frequencies specified on ! Attachments 14,15,16, and 17. Soil and vegetation samples shall be collected quarterly.- , b) Analyze samples in accordance with the frequencies specified on Attachments 14,15,16, and 17. Soil and vegetation samples shall be analyzed quarterly. c) Calculate the potential annual doses in accordance with the methodology > outlined elsewhere in this section if any of the following conditions are true: (1) any of the above surveillance results reveallevels of environmental activity greater than the ACTION Levels specified on Attachments 14,15,16, and 17, as appropriate. (per Specification Table 3.12-2), or (2) any radionuclides other than those listed on Attachments 14,15, l 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than the limits listed in Specification 3.12.1.b.' ; I d) The Chemistry Programs Unit, BG&E CCNPPD, is responsible for ' notifying the General Supervisor--Chemistry, CCNPP, if any of the following conditions are true: (1) any of the above surveillance results reveallevels of environmental activity greater than the ACTION Levels specified - on Attachments 14,15,16, and 17, as appropriate (per , Specification Table 3.12-2), or (2) any radionuclides other than those in Attachments 14,15,16, and 17 are detected, and the radionuclides are the result of plant ' effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than i the limits listed in Specification 3.12.1.b.
- 6. Calculation methodology a) If any (of the above) surveillance results reveallevels of environmental activity greater than the ACTION Levels specified on Attachments 14,15, 16, or 17 (per Specification Table 3.12-2), calculate potential annual doses for the pathway of interest, in accordance with the methodologies contained in Regulatory Guide 1.109.
b) If methodologies other than those listed in Regulatory Guide 1.109 are used to calculate potential annual doses, such methodologies shall be I
' Offsite Dose Calculation Manual
- Page 207 of 298 Revision 2, Change O documented in accordance with Specification 3.12.1.b. l
- 7. Corrective ACTIONS a) If a sample is unobtainable due to sampling equipment malfunction, then
!. attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR. } I b) If the ISFSIMP is not being conducted in accordance with the
" Surveillance Requirements" listed elsewhere in this section, document deviations in the AREOR.
c) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15,16, or 17, as eppropriate, submit a Special l l Report to the NRC (per Specification 3.12.1.b). j d) When radionuclides other than those listed on Attachments 15,16, and 17 are detected, and when tnose radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, submit a Special Report if required by and in accordance with Specification 3.12.1.b. I l i I l l 1 l
)
I
Offsite Dose Calculation M:nu;l Page 208 of 298 Revision 2, Change O Vill. RADIOACTIVE EFFLUENT RELEASE REPORT 1 A. Introduction
- 1. Specification 6.6.2 requires submittal of a written report to the NRC every 12 months.
- 2. The report is described below.
B. Responsibilities
- 1. The General Supervisor Chemistry is responsible for the timely and accurate completion of the report.
C. Report Contents
- 1. The Radioactive Effluent Release Report covering the operation of the unit shall be submitted every 12 months in accordance with 10 CFR 50.36a.
- 2. The Radioactive Effluent Release Report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and in conformance to 10CFR50.36a and 10CFR50, Appendix 1, section IV.B.1. Principle Gamma Emitters from Batch Waste Releases and Turbine Building Sump shall be analyzed and included in this report pursuant to Table Notation c of Specification Table 4.11-1, " Radioactive i Liquid Waste Sampling and Analysis Program." In addition, Principal Gamma Emitters from the Waste Gas Storage Tank, Containment Purge and Vent, and the Main Vent shall be analyzed and included in this report pursuant to Table ;
Notation b of Technical Specifications Table 4.11-2," Radioactive Gaseous ! Waste Sampling and Analysis Program." Additionalinformation which may be l required in the report is contained in Specifications 3.3.3.9.b,3.3.3.10.b and ! Technical Specification 6.5.1.127
- 3. The Radioactive Effluent Release Report shallinclude an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint freguency distributions of wind speed, wind i direction, and atmospheric stability 12 . This same report shallinclude an I I
assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
- In lieu of ..., Sr" and Sr" analysis... after submittal of the Radioactive Effluent Release Report.
- In lieu of submission with the Radioactive Effluent Release Report, this summary of required meteorological data may be retained on site in a file that shall be provided to the NRC upon request.
1 1 I I
Offsite Dose Calculation Manual Page 209 of 298 Revtion 2 Change 0
- 4. The radioactive Effluent Release Report shall also include an assessment of radiation ooses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nesty uranium fuel cycle sources, including doses l from primary effluent pathways and direct radiation, for the previous calendar year to show conformance w4h 40 CFR Part 190, Environmental Radiation l Protection Standards for Nuclear Power Operation. Acceptable methods for '
I calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiolooical Effluent Technical Specifications for Nuclear Power Plants.U
- 5. The Radioactive Effluent Release Report shall include the following information for each class of solid waste (as defiwd by 10 CFR Part 61) shipped offsite during the report period:
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement or estimate),
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
- e. Solidification ageai ^ absorbent (e.g., cement).
- 6. The Radioactive Effluer.;,.elease Report shallinclude a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
- 7. The Radioactive Effluent Release Report shallinclude any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and a listing of new locations for dose calculations identified by the annual land use census pursuant to Specification 3.12.2.
- 8. The Radioactive Effluent Release Report shallinclude any changes made during the reporting poriod to the PROCESS CONTROL PROGRAM (PCP)129. The report shall contain:
- a. A description of the equipment, components and processes involved.
- b. Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the POSRC.
D. Report Submittal
- 1. The report will be submitted every 12 months in accordance with 10 CFR 50.36a and 50.4.
- Licensee initiated changes to the PCP shall become effective upon review by the POSRC and approval of the Plant General Manager.
Offsete Dose Calculation Manual Page 210 of 298 Revision 2. Change 0 IX. ADMINISTRATION OF THE ODCM A. Introduction
- 1. Procedures covering the ODCM and the implementation of the ODCM shall be implemented..
- 2. Administrative controls have been established to implement controls on the ODCM.
- 3. These administrative controls are described below.
B. Controls On The ODCM
- 1. The format, organization, content, and administration of the ODCM are controlled by CH-1-103.
- 2. Methodologies identified in the ODCM are implemented by various BG&E organizations in accordance with approved procedures. (See the
" RESPONSIBILITIES" section of CH-1-103 for a list of those Sections of BG&E responsible for approving and maintaining procedures which implement the requirements of the ODCM.)
- 3. The main vent stack flow rates shall be verified in accordance with the surveillances described in the following section.
- 4. Licensee initiated changes to the ODCM:
a) Shall be documented and records of reviews performed shall be retained. This documentation shall contain (1) Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s); (2) A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and 10 CFR Part 50, Appendir I, and not adversely impact the accuracy or reliability of effiuent dose, or setpoint calculations; b) Shall become effective upon review by the onsite review function and approval of the plant manager; and c) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented. C. Surveillance Requirements
7 Offsite Dose Calcu stion Manual . Page 211 of 298 Revision 2. Change 0
- 1. Complete audits and PERIODIC REVIEWS of the ODCM in accordance with CH-1-103. ]
- 2. Determine main vent stack flow rates for both units as described below.
a) The main vent stack flow rate shall be determined, in accordance with approved procedures, at least once per 6 months (125%). , i b) The Test and Equipment Unit shall be responsible for performing this test. c) The results of the main vent flow rate test shall be evaluated to ensure the m&in vent flow rates used in the ODCM are an accurate reflection of ' the true main vent flow rates. , d) IF the main vent stack flow rate for either unit, as determined in accordance with approved Test and Equipment procedure (s), changes i 10% from the values referenced in Attachment 7 of the ODCM, a i technical evaluation shall be initiated to determine if the ODCM should be revised. ; D. Responsible Company Organizations
- 1. CH-1-103 identifies the responsibilities of various personnel and company ;
organizations which administer and implement the ODCM. This section of the ODCM identifies company organizations which are assigned responsibility for implementing the surveillances described above.
- 2. The Test Equipment Unit is responsible for ensuring the main vent stack flow rate test procedure (e.g., TE-001 or equivalent) is completed in accordance with the surveillances listed above. .
- 3. The Test Equipment Unit is responsible for forwarding main vent stack flow rate test results to the General Supervisor- Chemistry.
- 4. The RETS Program Manager, CCNPPD Chemistry Section, is responsible for ,
evaluating main vent flow rate test results (e.g., TE-001 or equivalent results) and for performing the technical evaluation described in the above surveillances. E. Initiating Conditions 1
- 1. Main vent stack flow rates shall be determined at least once per 6 months (i f 25%), or more often if required by Specifications.
- 2. Complete PERIODIC REVIEWS of the ODCM as specified in CH-1-103.
F. Calculation Methodolog'es
- 1. Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures.
- 2. Documents which serve as a basis for calculation methodologies used in the
- ODCM should be maintained in an accessible location.
' Offsite Dose Calculation Manual Page 212 of 298 ' RevElon 2, Change 0 (1) Supporting documents may be incorporated into the ODCM (e.g., as !
Attachments).
]
(2) Supporting documents may be maintained in a " procedure history file". (3) Supporting documents may be identified in the " references" section of the ! ODCM. ! a G. Corrective ACTIONS
- 1. IF main vent stack flow rates, as determined in accordance with appropriate Test >
Equipmant procedure (s), change i 10% from the values referenced in , Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine ; if the ODCM should be revised. , H. Bases
- 1. [BS27), NRC Inspection Report INSR 91-30/30 ,
I t a f i i l I I
1
. Offsite Dose Calculation Manual. Page 213 of 298 R vhion 2, Change 0 ,
/
- l. Executive Summary Of Changes Rev. Chg. Description No. No. . .
j 0 0 . Initial issue of ODCM under control of CCl 413 0 1 Added the words " Revision 0, Change 1" to title page. Added commitment / bases , tracking number [B527] to margins of pages 10,11,12, and 60. Added a " Bases" ) socbon to page 160. Added " Executive Summary of Changes" secbon to page 160. : Modified " List Of Effective Pages." Changed " Fossil Energy Devision" to " Corporate { Affairs Group."
)
1 0 This revision adds the Radiological Environmental Monitoring Program for the ISFSI to the ODCM. Other minor changes were made , All changes are listed below. Page numbers refer to Revision 1, Change 0. l (1) Changed Revision numbers on all pages (pp.1-247). (2) Changed title from RETS t f Coordinator to RETS Program Manager (pp.1,70,75,82,87,163). (3) included Radiation Safety Section in the Applicability / Scope (p. 4) and assigned them responsibility to assist in measurement of direct radiation (p.145). (4) Corrected !' typographical errors (pp. 9, 27, 33, 45, 49, 53, 63, 74,124,136,138,143,151,152, 168,181,225,236). (5) Updated references to reflect new revision numbers for safety evaluations, and added another safety evaluation (pp.10,11,55). (6) Clarified i requirements for minimum number of circulating water pumps for liquid releases (pp.18, l' 29,39). (7) included reference to Technical Specification 3.3.3.10 (pp.18,29,39). (8) Removed subjective reference to " insignificant" related to monitor background count j rates (pp. 20,31,41). (9) Deleted referenas to specific section numbers within the , ODCM (pp. 21,25,31,35,41,65,71,78,85,96). (10) Provided additional guidance . ! regarding when fixed setpoints should be changed pp. 21,31,41,71,85, and 96). (11) ! Changed reference from release permit,01-17C, or Ol 17D to Alarm Manual (pp. 73,86, , 97), and deleted inappropriate reference to Alarm Manual (pp. 32,33,42,43). (12) l Stipulated that the adjustment of monitor setpoints is not required if the monitor is either j inoperable or not the primary monitor (pp. 23,33,43,76,88). (13) Modified definitions j of parameters to " actual" instead of " minimum" flow rates (pp. 46, 47, 48, 52, 54, 55, ! 56). (14) Deleted unnecessary paragraphs (pp.46,47,48,52,53,54,56). (15) 1 Specified that the flow rate of undiluted redweste and the flow rate of service water may l be 0 gpm when calculating dilution water flow rate (pp. 47,48,53,54,56). (16) Moved - i paragraphs (pp. from p. 63 to pp. 61 and 62). (17) Deleted incorrect sensitivity , requirement for plant radiation monitors (pp. 66,78,89). (18) Changed name of f setpoints (pp. 67-73). (19) Deleted reference to 2 MPC limit (p. 67). (20) Updated i ODCM to correspond to recent change to CCNPP Alarm Manual (p. 71). (21) Editorial : changes (pp. 72,150,236,233). (22) Removed provision for not changing the adjustable setpoint for routine gaseous releases (p. 73).(23) Modified formula for fixed setpoint to include value of background (pp. 92,95). (24) Deleted inappropnote reference to adjusting setpoint for 0-RI-2191 when discharging containment vents and l purges (p. 98). (25) Specified units for dose rate (pp.101). (26) Specified calculation ' constant for calculating instantaneous release rate (pp.102,103,104,105,110,112, 117,118,120) (27) Specified units for dose (pp.136). (28) Specified value of x/Q , and D/Q (pp.136). (29) included environmental monitoring program for ISFSI (pp.148, 155-161,233,238-241,243). (30) Revised Attachment 5 (guidance for ceiculating "radionuclide mixture") to include use of computer data base (p.172). (31) Added i system interconnections between liquid and solid waste processing systems to diagram of liquid waste processing system, Attachment 4 (p.171). (32) Added containment vent release path to diagram of gaseous waste system, Attachment 9 (p.178). (33) l Changed list of effective pages (pp. 244-247). , i
r Offsite Dose Calculaton Manual Page 214 of 298 ) Revision 2, Change 0 Rev. Chg. Description - No. No. 2 0 Extensive revision to incorporate Technical Spec #,c tion removed by license i amendment. Part 1 and Part 2 incorporate parts of previous version of ODCM and l Technical Sper#eGeii to be removed in the license amendment. Part 3/4 are the ! Technical Specifications moved and modified to fit in the ODCM. Part 5 is the remaining - contents of the previous verson of the ODCM with modificatens to references to the removed portons of the Technical Specificatons and the new structured Technical - i Specifications. l l L i l 1
)
i l l
Offsite Dose Calculation Manual Page 215 of 298 Revision 2, Change 0 l i l i l ) l 1 1 4 f l I l 1 i l i l
)
I? , Offsite Dose Calculation Manual Page 216 of 298 , Revision 2, Change O ATTACHMENT 1 Final Grading And Drainage Plan A reference diagram which depicts the grading for and the drainage from the Calvert Cliffs Nuclear Power Plant can be found in the following reference: Final Grading And Drainage Plan Calvert Cliffs Nuclear Power Plant Units I and 2, BGE Document ID Number: 61517SH0001 BGE Document ID Number: 61514SH0002 The above referenced grading and drainage plan is intended for reference only. This drawing may not reflect the changes and rnodifications sinca March 1975. I I l l l 1 l
Offsite Dose Calculation Manual Page 217 of 298 Revision 1. Change O ATTACHMENT 2 (Page 1 of 3) OUTFALL 001 - SOURCES OF LIQUID RADIOACTIVE WASTE Waste Radiation Type of Max. Discharge Maximum Volume Notes . Stream Momtor release Flow Rate gal / min hters/ min gal liters Rx. Coolant Wst Mon. Tk. 0-RE-2201 Batch 120 454 9000016 3.407E5 16 Rx. Coolant Wst Rec. Tk. 0-RE-2201 Batch 120 454 9000016 3.407E516 Misc. Wst Mon. Tk. 0-RE-2201 Batch 120 454 40001 s 1514016 Misc. Wst Rec. Tk. 0-RE-2201 Batch 120 454 400016 1514016 Aux. Boiler Steam Drum All releases are via Auxiliary Blowdown Tank Aux. Blowdown Tk. UnmonitoredContinuous 20015 757 N/A N/A Waste Neut Tk.11 Unmonitored Batch 10001 37901 45988 1.74E5 Waste Neut Tk.12 Unmonitored Batch 10001 37901 47749 1.80E5 Stm. Gen. Blowdown Tk. 1/2-RE-401417 Batch 14 2252 8522 23503 88953 Component Cooling Waterd UnmonitoredContinuous variable 5 variable 5 440906 1.669ES Condenser Hotwells Unmonitored Batch 13 45007 170007 1.05ES 3.97E5 Salt Water System UnmonitoredContinuous 15500 58670 N/A N/A ' Condensate Storage Tanks Unmonitored Batch variable 9 variable 9 3.5E510 1.3E610 Demin. Water Storage Tank 11 Unmonitored Batch variable 9 variable 9 3.5E510 1.3E610 Precoat Sump 12 UnmonitoredContinuous 50 94.6 10305 39004 L
Offsite Dose Calculation Manual Page 218 of 298 Revision 1, Change O ATTACHMENT 2 (Page 2 of 3) OUTFALL 001 - SOURCES OF LIQUID RADIOACTIVE WASTE
- 1. This flow rate is only an approximation. The motive force is gravity
- 2. This is the maximum flow rate. The actual flow rate will be considerably less.
- 3. This is the maximum volume of the tank, however, since this is a continuous release, the volume discharged would be calculated from the discharge flow rate and duration of the telease.
- 4. There is no direct path by which radioactive liquid from the CCW System could enter outfall 001. Liquid from the CCW System may leak into either the Salt Water System (which drains to outfall 001) or the Liquid Waste Processing System (via Aux. Bldg. Drains).
- 5. Radioactive liquid is not normally released from the CCW system. Flow rate to outfa!I 001 may occur via Salt Water System. For this pathway, the flow rate will vary (e g.., depending on size of leak). See Safety Analysis No. 2, FCR 82-1053, Supplement 1.
- 6. System volume is 5894 cubic feet. Conversion constant is 0.13368 cubic feet per gallon.
- 7. The flow rate shown here is the flow rate for one condensate pump. Verify the number on condensate pumps in service, and modify this fkm rate accordingly.
- 8. Radioactive liquid is not nonnally released from the CST, The CST would drain to outfall 001 only if catastrophic tank failure occurred.
Small leaks would be collected by storm drains which would be released to outfall 002.
- 9. Flow rate should be calculated on a case-by-case basis.
- 10. Volume obtained from " Plant Data Book" BG&E CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1 Job 6750.
- 11. Radioactive liquid is not normally released from the demineralized water storage tank (DWST). The DWST would drain to outfall 001 only if l catastrophic tank failure occurred. Small leaks would be collected by the storm drains which would be released to outfall 002.
- 12. If the precoat sump contents were contaminated, releases would probably be directed to outfall 001, however depending on the valve line-ups, the sump may be discharged to outfall 002.
- 13. May be a continuous release if contaminated sealing steam is operated during the release.
ATTACHMENT 2 (Page 3 of 3) OUTFALL 001 - SOURCES OF LIQUID RADIOACTIVE WASTE
- 14. Although steam generator releases are normally BATCH RELEASES, discharges may at times be continuous. Verify type of release to be conducted prior to discharge.
- 15. This is the maximum rated discharge for two pumps in operation. If less than two pumps wi!I be operable for the release, a flow setpoint should be specified for the release.
- 16. The volume specified is the design basis volume from Table 11-1 of the UFSAR.
- 17. The steam generator blowdown effluent radiation monitor,1/2-RE-4095, may be equivalent to the 1/2-RE-4014 (see section V.D.2).
Offsde Dose Calcula6cn Manual Page 219 of 296 1 l *tevisson 1, Change 0 , f ATTACHMENT 3 (Page 1 of 2) OUTFALLS 002, 003. 004 - POTENTIAL SOURCES OF LIQUID RADIOACTIVE WASTE N Waste Radiation Type of Max. Discharge Maximum Volume Outfall Stream Monitor ' Release Flow Rate gai/mn htersinn gal liters r Turtune Bldg. Sump No.11 UnmondoredContmuous 470 889 1950 7381 002 Turbine Bldg. Sump No.12 UnmonitoredContmuous 470 889 2415 9141 002 ! Turtune Bldg. Sump No. 21 UnmondoredContinuous 470 889 2490 9425 002 Turtwne Bldg. Sump No. 22 UnmondoredCordmuous 470 889 2182 8259 002 , Precoat Sump UnmondoredContmuous 50 94.6 10305 39004 002 Diesel OilInterceptor Sump UnmondoredContmuous 100 378.5 5790 21920 004 Yard OilInterceptor UnmonitoredContmuous vanable3 vanable3 N/A N/A 002 Refuelmg Water Tank UnmondoredBatch/ Cont 7 vanable3 vanable3 4.2E5 1.6E6 any' Condensate Storage Tank UnmondoredBatch/ Cont 7 vanable3 vanable3 3.5E5s 1.3E6e 0022A Service Water System 1/2-RE-1595Contmuous variable 3 variable 3 31418 1.189E5 002. Demm WaterStorageTank UnmondoredBatch/Corit 7 vanable3 vanable3 3.5E5s 1.3E6e 0022 _ , Plant Hestmg System UnmondoredContmuous variable 3 vanable3 N/A N/A 002a i ATTACHMENT 3 (Page 2 of 2) ; OUTFALLS 002, 003, 004 - POTENTIAL SOURCES OF LIQUlO RADIOACTIVE WASTE
~
The maximum discharge flow rate is dependent on the influent flow rate (e.g., turtwne building sump discharges). ! 1.
- 2. The contents of these tanks are not normally discharged to the envwonment, however in the event of a small leak or catastrophic tank l f
failure, the tank contents could be released to the designated outfall(s),
- 3. Maximum discharge flow rate shall be determmed on a case-by-case basis. !
- 4. It is also possible for the CST to be discharged via the condenser hotwells
- 5. Flow rate should be calcu.ated on a case-by-case basis. !
i
- 6. Volume oblamed from " Plant Data Book". BG&E CCNPP Units 1 and 2, Bechtel Power Corporabon, Volume 1 Job 6750.-
- 7. Releases via this pathway would be considered a BATCH RELEASE if a 64 tank failure occurred in the event of a small leek, the release may be considered a contmuous release The release mode should be determmabon on a case-by-case basis. ,
- 8. The plant heebng system is a closed system and is not normally released to the envronment in the event of a leak, the effluent may be released to the envwonment via the turbme buildmg sumps (outfall 002). In some cases, depending on the locahon of the leak, the effluent would be collected in the auxthery building sump and W=arW released through the liquid radioechve waste processmg system. The !
effluent pathway should be determined on a case-by-case basis.
. _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ __ _ __u_..._... ._ _ _ _ _ _ _ . _.- . _ . . . _ . _ - . _ . _
Offsde Dose Calculaten Manual - Page 220 of 296 Revision 1, Change 0
- 9. The contents of Lese tanks are not normaNy discharged to the environment, however in t.w event of a smaR leak or catastrophc tank -
failure, the ts* contents could be released to outfaN 002,003, or 004.. l
Offsde Dose Calculabon Manual Page 221_*W 296 Revisson 1, Change O ATTACHMENT 4 BLOCK DIAGRAM OF LIQUID RADIOACTIVE WASTE SYSTEMS er.ecter corsies we-N "'***""'""'E'"*1 Jff t 12999 1 &#tt 2 J%# 2 l#49 . # 2 Aasir Elst3 M ,p sm <> a.. . ev u.es c ac,.w T , ac.r*i s l _. scve.co., s-n.,o
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Offsite Dose C:lculation Minual Page 222 of 298 l Revision 2 Change O ATTACHMENT 5 DOMINANT AND LESS DOMINANT RADIONUCLIDES IN TYPICAL RADWASTE DISCHARGES The term f,- a FRACTION which represents the relative activity contribution of nuclide i to the average total effluent activity -is used in several equations in the ODCM (e g., equations 2G, SG,3L, and 4L). This attachment provides guidance for calculating the values of f.i
- 1. Select the ca endar quarters which contain at least one " typical" liquid (or gas) release (see definition of TYPICAL RADWASTE RELEASE).
- 2. For each of the calendar quarters selected above, obtain a listing of the nuclides, nuclide activities, and release (end) dates.
- a. This data may be obtained from the Semi-Annual Radioactive Effluent Release Report (s) for the time periods ofinterest, or
- b. this data may be obtained from a computer-based effluent management system (if available).
- c. The values of nuclide activities and release end times may be close approximations of the true values. ,
- 3. Sum the quarterly activities (curies) for each individual radionuclide.
Aj7 = hA in Eq. IR
- 4. Sum the quarterly activities for all radionuclides, i.
A7 = h A ri Eq.2R S. Calculate the FRACTION of the total activity attributable to each radionuclide (i.e., the relative activity of nuclide 1). fi = A;7/A T Eq. 3R
- 6. Characterize each radionuclide as either dominant" or "less dominant" as shown below:
- The radionuclide is defined as a DOMINANT RADIONUCLIDE if the following inequality is true.
fi >_ 0.010 Eq. 4R
- The radionuclide is defined as a LESS DOMINANT RADIONUCLIDE if the following inequality is true.
fi < 0.010 Eq.5R
Offsite Dose Calculation Minu'I Paga 223 of 298 RevWon 2 Change 0 , ATTACHMENT 6 ' i LIQUID EFFLUENT DOSE FACTORS (mrem /hr per uCi/ml) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ' H-3 0.000E+00 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 I BE-7 2.700E+01 1.100E+01 6.500E+01 1.300E+00 1.600E+01 3.100E+00 2.700E+02 i C-14 1.450E+04 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 NA-24 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 , P-32 4.690E+06 2.910E+05 1.810E+05 0.000E+00 0.000E+00 0.000E+00 5.270E+05 CR-51 0.000E+00 0.000E+00 5.580E+00 3.340E+00 1.230E+00 7.400E+00 1.400E+03 , MN-54 0.000E+00 7.060E+03 1.350E+03 0.000E+00 2.100E+03 0.000E+00 2.160E+04 l MN-56 0.000E+00 1.780E+02 3.150E+01 0.000E+00 2.260E+02 0.000E+00 5.670E+03 FE-55 5.110E+04 3.530E+04 8.230E+03 0.000E+00 0.000E+00 1.970E+04 2.030E+04 FE-59 8.060E+04 1.900E+05 7.270E+04 0.000E+00 0.000E+00 5.300E+04 6.320E+05 L CO-57 0.000E+00 1.420E+02 2.360E+02 0.000E+00 0.000E+00 0.000E+00 3.590E+03 l CO-58 0.000E+00 6.030E+02 1.350E+03 0.000E+00 0.000E+00 0.000E+00 1.220E404 CO-60 0.000E+00 1.730E+03 3.820E+03 0.000E+00 0.000E+00 0.000E+00 3.250E+04 NI-63 4.960E+04 3.440E+03 1.670E+03 0.000E+00 0.000E+00 0.000E+00 7.180E+02 I NI-65 2.020E+02 2.620E+01 1.200E+01 0.000E+00 0.000E+00 0.000E+00 6.650E+02 CU-64 0.000E+00 2.140E+02 1.010E+02 0.000E+00 5.400E+02 0.000E+00 1.830E+04 ZN-65 1.610E+05 5.130E+05 2.320E+05 0.000E+00 3.430E+05 0.000E+00 3.230E+05 ZN-69 3.430E+02 6.560E+02 4.560E+01 0.000E+00 4.260E+02 0.000E+00 9.850E+01 BR-82 0.000E+00 0.000E+00 4.070E+00 0.000E+00 0.000E+00 0.000E+00 4.670E+00 BR-83 0.000E+00 0.000E+00 7.250E-02 0.000E+00 0.000E+00 0.000E+00 1.040E-01 BR-84 0.000E+00 0.000E+00 9.390E-02 0.000E+00 0.000E+00 0.000E+00 7.370E-07 BR-85 0.000E+00 0.000E+00 3.860E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 6.240E+02 2.910E+02 0.000E+00 0.000E+00 0.000E+00 1.230E+02 RB-88 0.000E+00 1.790E+00 9.490E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RE-89 0.000E+00 1.190E+00 8.340E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.990E+03 0.000E+00 1.430E+02 0.000E+00 0.000E+00 0.000E+00 8.000E+02 SR-90 1.230E+05 0.000E+00 3.010E+04 0.000E+00 0.000E+00 0.000E+00 3.550E+03 SR-91 9.180E+01 0.000E+00 3.710E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+02 SR-92 3.480E+01 0.000E+00 1.510E+00 0.000E+00 0.000E+00 0.000E+00 6.900E+02 Y-90 6.060E+00 0.000E+00 1.630E-01 0.000E+00 0.000E+00 0.000E+00 6.420E+04 Y-91M 5.730E-02 0.000E+00 2.220E-03 0.000E+00 0.000E+00 0.000E+00 1.600E-01 Y-91 8.880E+01 0.000E+00 2.370E+00 0.000E+00 0.000E+00 0.000E+00 4.890E+04 Y-92 5.320E-01 0.000E+00 1.560E-02 0.000E+00 0.000E+00 0.000E+00 9.320E+03
Offsite Dose Cilculation Minurl P:ge 224 of 298 Revtion 2 Ching) 0 ATTACHMENT 6 LIQUID EFFLUENT DOSE FACTORS (mrem /hr per UCi/ml) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract Y-93 1.690E+00 0.000E+00 4.660E-02 0.000E400 0.000E+00 0.000E+00 5.350E+04 ZR-95 1.590E+01 5.110E+00 3.460E+00 0.000F+00 8.020E+00 0.000E+00 1.620E+04 ZR-97 8.810E-01 1.780E-01 8.130E-02 0.000E+00 2.680E-01 0.000E+00 5.510E+04 NB-95 4.470E+02 2.490E+02 1.340E+02 0.000E+00 2.460E+02 0.000E+00 1.510E+06 NB-97 3.750E+00 9.490E-01 3.460E-01 0.000E+00 1.110E+00 0.000E+00 3.500E+03 MO-99 0.000E+00 1.280E+02 2.430E+01 0.000E+00 2.890E+02 0.000E+00 2.960E+02 TC-99M 1.300E-02 3.660E-02 4.660E-01 0.000E+00 5.560E-01 1.790E-02 2.170E+01 , TC-101 1.330E-02 1.920E-02 1.880E-01 0.000E+00 3.460E-01 9.810E-03 0.000E+00 RU-103 1.070E+02 0.000E+00 4.600E+01 0.000E+00 4.070E+02 0.000E+00 1.250E+04 RU-105 8.890E+00 0.000E+00 3.510E+00 0.000E+00 1.150E+02 0.000E+00 5.440E+03 RU-106 1.590E+03 0.000E+00 2.010E+02 0.000E+00 3.060E+03 0.000E+00 1.030E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , CD-109 2.100E+05 4.000E+06 1.600E+06 1.500E+05 2.200E+07 1.800E+05 2.500E+06 AG-110M 1.560E+03 1.450E+03 8.600E+02 0.000E+00 2.850E+03 0.000E+00 5.910E+05 ; SN-113 6.700E+03 1.200E+03 2.100E+04 6.200E+02 1.600E+03 7.300E+02 2.200E+05 SB-122 5.300E+01 5.520E+01 6.690E+02 8.780E+00 2.610E+01 1.140E+01 6.580E+03 SB-124 2.770E+02 5.230E+00 1.100E+02 6.710E-01 0.000E+00 2.150E+02 7.860E+03 SB-125 1.770E+02 1.980E+00 4.210E+01 1.800E-01 0.000E+00 1.360E+02 1.950E+03 TE-125M 2.170E+02 7.860E+01 2.910E+01 6.520E+01 8.820E+02 0.000E+00 8.660E+02 TE-127M 5.480E+02 1.960E+02 6.680E+01 1.400E+02 2.230E+03 0.000E+00 1.840E+03 TE-127 8.900E+00 3.200E+00 1.930E+00 6.600E+00 3.630E+01 0.000E+00 7.030E+02 TE-129M 9.310E+02 3.470E+02 1.470E+02 3.200E+02 3.890E+03 0.000E+00 4.690E+03 TE-129 2.540E+00 9.550E-01 6.190E-01 1.950E+00 1.070E+01 0.000E+00 1.920E+00 TE-131M 1.400E+02 6.850E+01 5.710E+01 1.080E+02 6.940E+02 0.000E+00 6.800E+03 TE-131 1.590E+00 6.660E-01 5.030E-01 1.310E+00 6.990E+00 0.000E+00 2.260E-01 TE-132 2.040E+02 1.320E+02 1.240E+02 1.460E+02 1.270E+03 0.000E+00 6.240E+03 I-130 3.960E+01 1.170E+02 4.610E+01 9.910E+03 1.820E+02 0.000E+00 1.010E+02 I-131 2.180E+02 3.120E+02 1.790E+02 1.020E+05 5.350E+02 0.000E+00 8.230E+01 I-132 1.060E+01 2.850E+01 9.960E+00 9.960E+02 4.540E+01 0.000E+00 5.350E+00 I-133 7.450E+01 1.300E+02 3.950E+01 1.900E+04 2.260E+02 0.000E+00 1.160E+02 I-134 5.560E+00 1.510E+01 5.400E+00 2.620E+02 2.400E+01 0.000E+00 1.320E-02 I-135 2.320E+01 6.080E+01 2.240E+01 4.010E+03 9.750E+01 0.000E+00 6.870Er01
Offsite Dose C:lculation M: null Pag)225 of 298 Revisbn 2 Change 0 ATTACHMENT 6 LIQUID EFFLUENT DOSE FACTORS i (mrem /hr per uCl/ml) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract CS-134 6.840E+03 1.630E+04 1.330E+04 0.000E+00 5.270E+03 1.750E+03 2.850E+02 CS-136 7.160E+02 2.830E+03 2.040E+03 0.000E+00 1.570E+03 2.160E+02 3.210E+02 CS-137 8.770E+03 1.200E+04 7.850E+03 0.000E+00 4.070E+03 1.350E+03 2.320E+02 CS-138 6.070E+00 1.200E+01 5.940E+00 0.000E+00 8.810E+00 8.700E-01 5.120E-05 BA-139 7.850E+00 5.590E-03 2.300E-01 0.000E+00 5.230E-03 3.170E-03 1.390E+01 , BA-140 1.640E+03 2.060E+00 1.080E+02 0.000E+00 7.020E-01 1.180E+00 3.380E+03 BA-141 3.810E+00 2.880E-03 1.290E-01 0.000E+00 2.680E-03 1.630E-03 1.800E-09 BA-142 1.720E+00 1.770E-03 1.080E-01 0.000E+00 1.500E-03 1.000E-03 0.000E+00 LA-140 1.570E+00 7.940E-01 2.100E-01 0.000E+00 0.000E+00 0.000E+00 5.830E+04 CE-139 1.000E+02 4.800E+01 3.700E+02 6.200E-01 3.400E+01 4.800E+00 3.200E+03 LA-142 8.060E-02 3.670E-02 9.130E-03 0.000E+00 0.000E+00 0.000E+00 2.680E+02 CE-141 3.430E+00 2.320E+00 2.630E-01 0.000E+00 1.080E+00 0.000E+00 8.860E+03 CE-143 6.040E-01 4.460E+02 4.940E-02 0.000E+00 1.970E-01 0.000E+00 1.670E+04 CE-144 1.790E+02 7.470E+01 9.590E+00 0.000E+00 4.430E+01 0.000E+00 6.040E+04 PR-143 5.790E+00 2.320E+00 2.870E-01 0.000E+00 1.340E+00 0.000E+00 2.540E+04 PR-144 1.900E-02 7.870E-03 9.640E-04 0.000E+00 4.440E-03 0.000E+00 2.730E-09 ND-147 3.960E+00 4.580E+00 2.740E-01 0.000E+00 2.680E+00 0.000E+00 2.200E+04 W-187 9.160E+00 7.660E+00 2.680E+00 0.000E+00 0.000E+00 0.000E+00 2.510E+03 1 NP-239 3.530E-02 3.470E-03 1.910E-03 0.000E+00 1.080E-02 0.000E+00 7.110E+02 HG-203 1.400E+05 0.000E+00 1.600E+05 0.000E+00 1.600E+06 1.000E+05 3.200E+05 1
Offsite Dose Calculation Manual Page 226 of 298 Revision 2 Cha.y 0 ATTACHMENT 7 (page 1 of 2) GENERAL INFORMATION RELATED TO GASEOUS REl. EASES VIA THE MAIN VENTS Waste Stream" Radiation Type of Nominal Discharge Maximum Discharge Notes Monitor release Flow Rate Flow Rate m3/sec SCFM m3/sec SCFM Waste Gas System (WGDT) 0-RE-2191 Batch N/A N/A 2.36E-2 50 Cntmt. Vent (via H2 Purge) ts 1/2-RE-5415 : Batch' N/A N/A 2.36E-2 50 Cntmt. Purge (5% Modified) 1/2-RE-54153Continuous N/A N/A 1.928 4085 Cntmt. Purge (10% Modified) 1/2-RE-54153Continuous N/A N/A 7.996 16940 Cntmt. Purge (100% Modified) 1/2-RE-54153Continuous N/A N/A 17.70 37500 '" Iniviinativa for waste streams not listed in this table should be evaluated on a case-by-case basis. '" Since the WGDT is released to the plant vent stack,1/2-RE-5415 and 1/2-RE-5416 may also be used to monitor releases from a WGDT. "2 The WRGM,1/2-RE-5416, may also monitor main vent releases. '" A containment vent is considered a " batch" release (even though inleakage of radioactrve gases into the containment atmosphere may occur during the time the vent is in progress).
Offsite Dose Calculebon Manual Page 227 of 298 Revision 2 Change O ATTACHMENT 7 (page 2 of 2) GENERAL INFORMATION RELATED TO GASEOUS RELEASES VIA THE MAIN VENTS Waste Stream"" Radiation Type of Nominal Discharge Maximum Discharge Notes - Monitor release Flow Rate Flow Rate m3/sec SCFM m3/ sec SCFM Unit 1 Main Vent Release 1-RE-5415'" Continuous 59.4
- 1258586 65.34'87 1384447 8
(55.5*) (117548 ) (61.0 * ) (129303') i Unit 2 Main Vent Release 2-RE-5415" Continuous 47.16 997496 51.787 1097247 Iniviiii.i;uii for waste streams not listed in this table should be evaluated on a case-by-case basis. The WRGM,1-RE-5416, may also monitor main vent releases. This is the mean main vent stack flow rate as determined by approved Engineenng Test Procedure (i.e., ETP-87-16). This is the maximum vent stack flow rate as determined by approved Engineenng Test Procedure (i.e., ETP-87-16).
'" This is the mean main vent stack flow rate as determmed by approved test procedure (i.e. TE-001) for penod 8/90 through 4/95. '" This is the maximum vent stack flow rate as determmed by approved test procedure (i.e. TE-001) for the period 8/90 through 4/95.
The WRGM,2-RE-5416, may also monitor main vent releases.
. --_y. _ ,,wo. e.~2-, 3-.c e. m ,
Offsite Dose Calculebon Manual Page 228 of 296 Revisen 2 Change O ATTACHMENT 8 GENERAL INFORMATION RELATED TO GASEOUS RELEASES VIA PATHWAYS OTHER THAN THE MAIN VENTS Waste Stream"' Radiation Type of Nominal Discharge Notes Monitor Release Flow Rate Aun Boiler Deaerator UnmonitoredSee Footnote
- See Footnote
- Stm. Gen. Atm. Stm. Dumps UnmonitoredSee Footnote 2 See Footnote 3 Plant Nitrogen System UnmonitoredSee Footnote 2 See Footnote 3 Turbine Bidg. Vent. Exh. UnmonitoredSee Footnote 2 See Footnote 3 Emergency Air Lock UnmonitoredSee Footnote 2 See Footnote 3 Plant Compressed Air UnmonitoredSee Footnote 2 See Footnote 3 Main Steam Line Penetrations UnmonitoredSee Footnote 2 See Footncie3
"' ink,in-#vvi for waste streams not listed in this table should be evaluated on a case-by-case basis.
"2 Since radcactrve gaseous waste is not normally vented via this pathway, the detemwnation of release type (i.e., continuous or batch) will be evaluated on a case-by-case basis.
"' Since radooctwe gaseous waste is not normally vented via his pathway, the detemunation of discharge flow rate will be evaluated on a case-by-case basis.
~ _ . _ ~ - - .- . - . - - - . . - . - . - - - . - - . . - - , , . . . - - . - - - . . - . . - - . - - . . - . . . _ _ .
Offsde Dose Calcuis#on Manual Page 229 of 296 Revisson 2 Change O ATTACHMENT 9 BLOCK DIAGRAM OF GASEOUS RADIOACTIVE WASTE SYSTEMS 3 : a li, j Unit I Contetnment spent a33 jJ uet 2 Cont atnment two a mu.= Fuel Pool g {h ue, 2 % fwY. Unit i Ewheust a)3j )h g DD, Unit 2 8 - Aux Fm 2 5 w 8 - Aux tm, g sw [ Building Equieraent Jfg g fp ,y s +.-- [ f Dullding Equicwnent i vont west, ces g g Vent y e Unit 1 . / hg ,5_ Unit 2 5 8 condenser t 18 ici , i g condenser Icw ar I
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Offsio Dose CIlculation Minuti Page 230 of 298 R: vision 2 Change 0 , ATTACHMENT 10 NOBLE GAS DOSE FACTORS GAMMA 800Y DOSE t BETA SKIN DOSE GAMMA AIR DOSE BETA AIR DOSE kJCLIDE Kj Mj I' Nj i l Lf (mrem /yr)/(scl/m 33 l (arem/yr)/(stf/m 3) (ared/yr)/ fact /m 3) (ared/yr)/(gel /m 33 Ar-41 i 8.84E+03 2.69E+03 i 9.30E+03 i 3.28E+03 Kr 85 i 1.61E+01 1.34E+03 4 1.72E+01 i 1.95E+03 Kr-85m i 1.17E+03 i 1.46E+03 6 1.23E+03 i 1.97E +03 Kr-87 5.92E+03 i 9.73E+03 i 6.17E+03 f 1.03E+04 Kr 88 < 1.4 7E + 04 2.37E+03 < 1.52E+G4 ~ l 2.93E+03 Me-131m i 9.15E+01 4.76E+02 i 1.56E+02 i 1.11E+03 xe-133 i 2.94E+02 i 3.06E+02 3.53E+02 1 1.05E+03 Ne-133m i 2.51E+02 i 9.94E+02 i 3. 27E +02 i 1.48E+03 , Ne-135 1.81E+0h , 1.86E+03 i 1.92E+03 ! 2.46E+03 , Xe 135m 3.12E+03 ' 7.11E+02 i 3.36E+03 i 7.39E+02 xe-138 8.83E+03 4.13E+03 9.21E+03 4. 75E +03 i 9 I 6 i I
l Offsite Dose Calculation Minu 1 Page231of 298 I Revision 2 Change 0 ATTACHMENT 11 EMPIRICAL DERIVATION OF SITE-SPECIFIC DOSE FACTORS Page 1 of 5 , The total body dose, the skin dose, and the air doses-resulting from gamma and beta emitting radionuclides in discharges of gaseous radwaste-are normally calculated using nuclide specific dose ' factors. However, these same doses may be estimated using empirically derived, site specific, dose factors as shown below. TOTAL-BODY, GAMMA-DOSE FACTOR A site-specific, total-body, gar,ima-dose factor has been derived from historical data in accordance with the following equation. K,y, = h(K )(f i )i Eq.IF K,,, = the empirically derived, site-specific, total-body, gamma-dose factor due to all noble gases released during a specified time period l Values of K,,, have been calculated using gaseous radwaste discharge data collected over I several years. The results of the calculations appear in the Table on page 5 of this attachment. 1 Ki = the total body dose factor due to gamma emissions for each identified noble gas ; radionuclide, i (mrem /yr per microcurie / cubic meter) l i The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The total-body dose factors for various noble gas radionuclides are tabulated in Attachment 10. f = a FRACTION which represents the relative activity contribution of noble gas radionuclide i , to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) l This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5. I
Offsit) Dose C:lculation Minull Page232of 298 Revision 2 Change O ATTACHMENT 11 EMPIRICAL DERIVATION OF SITE 4PECIFIC DOSE FACTORS Page 2 of 5 SKIN, BETA-DOSE FACTOR A site-specific, skin, beta-dose factor has been derived from historical data in accordance with the following equation. L,y, = h(L )(f i )i Eq.2F L,,, = the empirically derived, site-specific, skin, beta-dose factor due to all noble gases released , during a specified time period Values of L,yg have been calculated using gaseous radwaste discharge data collected over several years. The results of the calculations appear in the Table on page 5 of this attachment. Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i ; (mrem /yr per microcurie / cubic meter) The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10. fi = a FRACTION which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5. l l l i
Offsite Dose C:lculation M:nual Pag:233of 298 Revision 2 Change O ATTACHMENT 11 EMPIRICAL DERIVATION OF SITE 4PECIFIC DOSE FACTORS Page 3 of 5 GAMMA-AIR-DOSE FACTOR , A site-specific, gamma-air-dose factor has been derived from historical data in accordance with the following equation. M avs = ( Mi )( fi ) Eq.3F M,y, = the empirically derived, site-specific, gamma-air-dose factor due to all noble gases released during a specified time period Values of M,y several years. , have been calculated using gaseous radwaste discharge data The results of the calculations appear in the Table on page 5 of this attachment. Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad /yr per microcurie / cubic meter) The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10. fi = a FRACTION which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5.
Offsit) Dose CIlculation MInuit . Page234of 298 Revision 2 Change O ATTACHMENT 11 EMPIRICAL DERIVATION OF SITE-SPECIFIC DOSE FACTORS Page 4 of 5 BETA-AIR-DOSE FACTOR A site-specific, beta-air-dose factor has been derived from historical data in accordance with the following equation. N,y, = h(N i)(f)i Eq.4F i. I N,y, = the empirically derived, site-specific, beta-air-dose factor due to all noble gases released during a specified time period Values of N,,, have been calculated using gaseous radwaste discharge data collected over several years. The results of the calculations appear in the Table on page 5 of this attachment. i Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mradlyr per microcurie / cubic meter) i The beta air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1. The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10 : (Attachment 1 of old ODCM). i fi = a FRACTION which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitiess) This value has been calculated for all gaseous radwaste discharges for the years 1986,1987, and 1988 in accordance with equation 3R on Attachment 5. l l l
._ ~
I Offsite Dose Calculation Manu:1 Page235of 298 Revision 2 Change 0 l ATTACHMENT 11 l l EMPIRICAL DERIVATION OF SITE SPECIFIC DOSE FACTORS l Page 5 of 5 l SITE-SPECIFIC, AVERAGE DOSE FACTORS Year Kayg 1.,yg M avo N,yg 1986 330 790390 1100 , 1987 340 810400 1100 1988 390 960450 1200 Average 350 850410 1100 Maximum % difference 11 % 13% 10% 9% As can be seen from the above table, the percent difference between the yearly dose factors and the 3-year average dose factors range from 9% to 13%. This variability is minor considering other areas of. uncertainty inherent in the environmental dose calculation models. It should be noted that the emperical!y-derived, site-specific, average dose factors listed in the above table shall only rarely be used. In those rare instances where emperically-derived, site-specific, average dose factors are used, the results shall be carefully evaluated by qualified members of the facility staff to ensure the estimated doses are only a small FRACTION of the Specification limits. Additionally, the doses shall be recalculated using the RIGOROUS METHODS prior to submitting the Annual Radioactive Effluent Release Report. l l I
Offsite Dose Calc 6.ation Manud Page 236 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS i ADUG (m2
- mrem /yr per uCi/sec) i l
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract j H-3 0.000E+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 ; C-14 3.330E+05 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 i NA-24 1,840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 P-32 4.650E+09 2.890E+0B 1.800E+08 0.000E+00 0.000E+00 0.000E+00 5.230E+08 CR-51 0.000E+00 0.000E+00 7.070E+03 4.220E+03 1.560a+03 9.380E+03 1.780E+06 MN-54 0.000E+00 9.150E+06 1.750E+06 0.000E+00 2.720E+06 0.000E+00 2.800E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 2.930E+08 2.020E+0B 4.720E+07 0.000E+00 0.000E+00 1 130E+08 1.160E+0B FE-59 2.670E+08 6.270E+08 2.400E+08 0.000E+00 0.000E+00 1.750E+08 2.090E+09 CO-57 0.000E+00 5.640E+06 9.370E+06 0.000E+00 0.000E+00 0.000E+00 1.430E+0B CO-58 0. 000E+00 1. 830E+07 4.100E+07 0.000E+00 0. 000E4 00 0. 000E+00 3.700E+08 CO-60 0.000E+00 7.520E+07 1.660E+08 0.000E+00 0.000E+00 0.000E+00 1.410E+09 NI-63 1.890E+10 1.310E+09 6.330E+08 0.000E+00 0.000E+00 0.000E+00 2.730EdOB NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 2.950E-07 1.390E-07 0.000E+00 7.450E-07 0.000E+00 2.520E-05 ZN-65 3.560E+08 1.130E+09 5.120E+08 0.000E+00 7.570E+08 0.000E+00 7.130E+08 : ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 : RB-86 0.000E+00 4.870E+0B 2.270E+08 0.000E+00 0.000E+00 0.000E+00 9.600E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; SR-89 3.010E+08 0.000E+00 8.650E+06 0.000E+00 0.000E+00 0.000E+00 4.840E+07 SR-90 1.240E+10 0.000E+00 3.050E+09 0.000E+00 0.000E+00 0.000E+00 3.590E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.070E+02 0.000E+00 2.860E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+06 I Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.130E+06 0.000E+00 3.030E+04 0.000E+00 0.000E+00 0.000E+00 6.240E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ' Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.080E-07 ZR-95 1.880E+06 6.040E+05 4.090E+05 0.000E+00 f 480E+05 0.000E+00 1.910E+09 i ZR-97 1.830E-05 3.690E-06 1.690E-06 0.000E+00 5.580E-06 0.000E+00 1.140E+00 NB-95 2.290E+06 1.280E+06 6.860E+05 0.000E+00 1.260E+06 0.000E+00 7.750E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 1.090E+05 2.070E+04 0.000E+00 2.460E+05 0.000E+00 2.520E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 } TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 i RU-103 1.060E+08 0.000E+00 4.550E+07 0.000E+00 4.030E+08 0.000E+00 1.230E+10 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 2.800E+09 0.000E+00 3.540E+08 0.000E+00 5.400E+09 0.000E+00 1.810E+11 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OODE+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
)
i h
Offsite D0se Calculation Minu:1 Page 237 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 6.690E+06 6.190E+06 3.670E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 SB-122 5.580E+03 5.820E+03 7.050E+04 9.250E+02 2.750E+03 1.200E+03 6.930E+05 SB-124 1.980E+09 3.740E+07 7.850E+0B 4.800E+06 0.000E+00 1.540E+09 5.620E+10 SB-125 1.910E+09 2.130E+07 4.540E+08 1.940E+06 0.000E+00 1.470E+09 2.100E+10 TE-125M 3.590E+0B 1.300E+0B 4.810E+07 1.080E+08 1.460E+09 0.000E+00 1.430E+09 TE-127M 1.120E+09 3.990E+0B 1.360E+08 2.850E+08 4.530E+09 0.000E+00 3.740E+09 TE-127 0.000E+30 0.000E+00 0.000E+00 0.000E+00 1.090E-09 0.000E+00 2.100E-08 TE-129M 1.140E+09 4.270E+08 1.810E+08 3.930E+08 4.770E+09 0.000E+00 5.760E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.510E+02 2.210E+02 1.840E+02 3.500E+02 2.240E+03 0.000E+00 2.190E+04 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.400E+06 9.070E+05 8.510E+05 1.000E+06 8.730E+06 0.000E+00 4.290E+07 I-130 2.350E-06 6.940E-06 2.740E-06 5.880E-04 1.000E-05 0.000E+00 5.980E-06 I-131 1.080E+07 1.540E+07 8.830E+06 5.050E+09 2.640E+07 0.000E+00 4.070E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 4.300E-01 7.470E-01 2.280E-01 1.100E+02 1.300E+00 0.000E+00 6.720E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 6.570E+08 1.560E+09 1.200E+09 0.000E+00 5.060E+0B 1.680E+08 2.740E+07 CS-136 1.180E+07 4.670E+07 3.360E+07 0.000E+00 2.600E+07 3.560E+06 5.300E+06 CS-137 8.720E+08 1.190E+09 7.810E+08 0.000E+00 4.050E+08 1.350E+08 2.310E+07 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.880E+07 3.610E+04 1.890E+06 0.000E+00 1.230E+04 2.070E+04 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , LA-140 3.600E-02 1.810E-02 4.790E-03 0.000E+00 0.000E+00 0.000E+00 1.330E+03 I LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.400E+04 9.480E+03 1.080E+03 0.000E+00 4.400E+03 0.000E+00 3.620E+07 CE-143 2.090E-02 1.550E+01 1.710E-03 0.000E+00 6.800E-03 0.000E+00 5.780E+02 l l CE-144 1.460E+06 6.090E+05 7.830E+04 0.000E+00 3.610E+05 0.000E+00 4.930E+08 PR-143 2.130E+04 8.540E+03 1.060E+03 0.000E+00 4.930E+03 0.000E+00 9.330E+07 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.080E+03 8.180E+03 4.900E+02 0.000E+00 4.780E+03 0.000E+00 3.930E+07 W-187 2.160E-02 1.810E-02 6.320E-03 0.000E+00 0.000E+00 0.000E+00 5.920E+00 NP-239 2.560E-01 2.510E-02 1.390E-02 0.000E+00 7.840E-02 0.000E+00 5.150E+03 i i
o Offsite Dose Cdculation M:nuil Page 238 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS TEEN (m2
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Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 C-14 2.810E+05 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 NA-24 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 P-32 3.930E+09 2.440E+08 1.520E+08 C.000E+00 0.000E+00 0.000E+00 3.300E+08 CR-51 0.000E+00 0.000E+00 5.650E+03 3.140E+03 1.240E+03 8.070E+03 9.500E+05 MN-54 0.000E+00 6.980E+06 1.380E+06 0.000E+00 2.080E+06 0.000E+00 1.430E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 2.380E+08 1.690E+0B 3.930E+07 0.000E+00 0.000E+00 1.070E+08 7.300E+07 FE-59 2.130E+0B 4.980E+08 1.920E+08 0.000E+00 0.000E+00 1.570E+00 1.180E+09 CO-57 0.000E+00 4.530E+06 7.590E+06 0.000E+00 0.000E+00 0.000E+00 8.450E+07 CO-58 0.000E+00 1.410E+07 3.250E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+08 CO-60 0.000E+00 5.830E+07 1.310E+08 0.000E+00 0.000E+00 0.000E+00 7.600E+08 NI-63 1.520E+10 1.070E+09 5.150E+08 0.000E+00 0.000E+00 0.000E+00 1.710E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 2.410E-07 1.130E-07 0.000E+00 6.100E-07 0.000E+00 1.870E-05 ZN-65 2.500E+08 8.690E+0B 4.050E+0B 0.000E+00 5.560E+08 0.000E+00 3.680E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.060E+08 1.910E+08 0.000E+00 0.000E+00 0.000E+00 6.010E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , SR-89 2.540E+08 0.000E+00 7.290E+06 0.000E+00 0.000E+00 0.000E+00 3.030E+07 SR-90 8.050E+09 0.000E+00 1.990E+09 0.000E+00 0.000E+00 0.000E+00 2.260E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 8.980E+01 0.000E+00 2.420E+00 0.000E+00 0.000E+00 0.000E+00 7.400E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 9.560E+05 0.000E+00 2.560E+04 0.000E+00 0.000E+00 0.000E+00 3.920E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.6SLC-07 ZR-95 1.510E+06 4.760E+05 3.270E+05 0.000E+00 6.990E+05 0.000E+00 1.100E+09 ZR-97 1.530E-05 3 020E-06 1.390E-06 0.000E+00 4.580E-06 0.000E+00 8.180E-01 NB-95 1.790E+06 9.940E+05 5.470E+05 0.000E+00 9.640E+05 0.000E+00 4.250E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 8.980E+04 1.710E+04 0.000E+00 2.060E+05 0.000E+00 1.610E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 6.600E+07 0.000E+00 3.680E+07 0.000E+00 3.030E+0? 0.000E+00 7.180E+09 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 2.360E+09 0.000E+00 2.970E+08 0.000E+00 4.550E+09 0.000E+00 1.130E+11 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
1 l < Offsita Dose Cilculation Manut! Pzge 239 of 298 l Revision 2 Change 0 l l ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS I TEEN (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract i
................. ..._______........................___________............... j AG-110M 5.060E+C6 4.790E+06 2.910E+06 0.000E+00 9.140E+06 0.000E+00 1.350E+09 SB-122 3.300E+03 3.440E+03 4.170E+04 5.460E+02 1.620E+03 7.080E+02 4.100E+05 SB-124 1.620E+09 2.980E+07 6.310E+0B 3.670E+06 0.000E+00 1.410E+09 3.260E+10 SB-125 1.5F0E+09 1.710E+07 3.660E+0B 1.490E+06 0.000E+00 1.370E+09 1.220E+10 l i TE-125M 3.030E+08 1.090E+08 4.050E+07 8.470E+07 0.000E+00 0.000E+00 8.940E+08 [
l TE-127M 9.410E+08 3.340E+08 1.120E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.750E-08 TE-129M 9.580E+0B 3.560E+08 1.520E+08 3.090E+0B 4.010E+09 0.000E+00 3.600E+09 ' TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.760E+02 1.800E+02 1.500E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.150E+06 7.260E+05 6.840E+05 7.660E+05 6.970E+06 0.000E+00 2.300E+07 l I-130 1.890E-06 5.480E-06 2.190E-06 4.470E-04 8.440E-06 0.000E+00 4.210E-06 l I-131 8.950E+06 1.250E+07 6.730E+06 3.660E+09 2.160E+07 0.000E+00 2.480E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 3.590E-01 6.100E-01 1.860E-01 8.510E+01 1.070E+00 0.000E+00 4.610E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 5.230E+0B 1.230E+09 5.710E+08 0.000E+00 3.910E+08 1.490E+08 1.530E+07 CS-136 9.220E+06 3.630E+07 2.440E+07 0.000E+00 1.970E+07 3.110E+06 2.920E+06 CS-137 7.240E+0B 9.630E+0B 3.360E+0B 0.000E+00 3.280E+0B 1.270E+08 1.370E+07 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.380E+07 2.910E+04 1.530E+06 0.000E+00 9.880E+03 1.960E+04 3.670E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 2.960E-02 1.450E-02 3.870E-03 0.000E+00 0.000E+00 0.000E+00 8.350E+02 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.180E+04 7.860E+03 9.030E+02 0.000E+00 3.700E+03 0.000E+00 2.250E+07 CE-143 1.760E-02 1.280E+01 1.430E-03 0.000E+00 5.740E-03 0.000E+00 3.850E+02 CE-144 1.230E+06 5.080E+05 6.600E+04 0.000E+00 3.040E+05 0.000E+00 3.090E+08 j PR-143 1.790E+04 7.150E+03 8.920E+02 0.000E+00 4.160E+03 0.000E+00 5.900E+07 ] PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 j ND-147 6.240E+03 6.790E+03 4.060E+02 0.000E+00 3.980E+03 0.000E+00 2.450E+07 l W-187 1.810E-02 1.480E-02 5.170E-03 0.000E+00 0.000E+00 0.000E+00 3.990E+00 NP-239 2.230E-01 2.110E-02 1.170E-02 0.000E+00 6.610E-02 0.000E+00 3.390E+03 i
~ - - , . . , - -_ , - - - - - -
Offsit9 Dose CCiculation Manual Page 240 of 298 Revision 2 Change 0 ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec) ,
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 C-14 5.290E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 NA-24 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 P-32 7.410E+09 3.470E+08 2.860E+0B 0.000E+00 0.000E+00 0.000E+00 2.050E+08 , CR-51 0.000E+00 0.000E+00 8.810E+03 4.890E+03 1.340E+03 8.930E+03 4.670E+05 MN-54 0.000E+00 7.990E+06 2.130E+06 0.000E+00 2.240E+06 0.000E+00 6.700E+06 , MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 4.570E+08 2.420E+08 7.510E+07 0.000E+00 0.000E+00 1.370E+08 4.490E+07 FE-59 3.780E+08 6.120E+08 3.0SOE+08 0.000E+00 0.000E+00 1.770E+08 6.370E+08 CO-57 0.000E+00 5.920E+06 1.200E+07 0.000E+00 0.000E+00 0.000E+00 4.850E+07 CO-58 0.000E+00 1.650E+07 5.040E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+07 CO-60 0.000E+00 6.930E+07 2.040E+0B 0.000E+00 0.000E+00 0.000E+00 3.840E+08 NI-63 2.910E+10 1.560E+09 9.910E+08 0.000E+00 0.000E+00 0.000E+00 1.050E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; CU-64 0.000E+00 3.240E-07 1.960E-07 0.000E+00 7.820E-07 0.000E+00 1.520E-05 ZN-65 3.750E+08 1.000E+09 6.220E+08 0.000E+00 6.300E+08 0.000E+00 1.760E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.760E+08 3.540E+08 0.000E+00 0.000E+00 0.000E+00 3.710E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , SR-89 4.820E+08 0.000E+00 1.380E+07 0.000E+00 0.000E+00 0.000E+00 1.860E+07 , SR-90 1.040E+10 0.000E+00 2.640E+09 0.000E+00 0.000E+00 0.000E+00 1.400E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.010E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.700E+02 0.000E+00 2.550E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.810E+06 0.000E+00 4.830E+04 0.000E+00 0.000E+00 0.000E+00 2.410E+08 Y-92 0.000E+00 0.000E+00 C 100E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.550E-07 ZR-95 2.680E+C6 5.890E+05 5.240E+05 0.000E+00 8.430E+05 0.000E+00 6.140E+0B ZR-97 2.840E-05 4.100E-06 2.420E-06 0.000E+00 5.890E-06 0.000E+00 6.210E-01 NB-95 3.090E+06 1.200E+06 8.610E+05 0.000E+00 1.130E+06 0.000E+00 2.230E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 1.250E+05 3.090E+04 0.000E+00 2.670E+05 0.000E+00 1.030E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU 103 1.560E+08 0.000E+00 5.980E+07 0.000E+00 3.920E+08 0.000E+00 4.020E+09 [ RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 4.440E+09 0.000E+00 5.540E+0B 0.000E+00 5.990E+09 0.000E+00 6.900E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
P Offsite Dose Calculation Minull Paga 241 of 298 R: vision 2 Changs O ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS ' CHILD (m2
- mrem /yr per uCi/sec) ,
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract : AG-110M 8.400E+06 5.670E+06 4.530E+06 0.000E+00 1.060E+07 0.000E+00 6.750E+08 SB-122 2.080E+03 2.170E+03 2.630E+04 3.450E+02 1.020E+03 4.460E+02 2.580E+05 SB-124 2.930E+09 3.80GE+07 1.030E+09 6.460E+06 0.000E+00 1.620E+09 1.830E+10 SB-125 2.850E+09 2.190E+07 5.960E+08 2.640E+06 0.000E+00 1.590E+09 6.800E+09 TE-125M 5.690E+08 1.540R+08 7.590E+07 1.600E+08 0.000E+00 0.000E+00 5.490E+08 ! TE-127M 1.770E+09 4.780E+08 2.110E+08 4.240E+08 5.060E+09 0.000E+00 1.440E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 1.660E-08 TE-129M 1.810E+09 5.040E+0B 2.800E+08 5.820E+08 5.300E+09 0.000E+00 2.200E+09 , TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i TE-131M 7.000E+02 2.420E+02 2.580E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.090E+06 9.270E+05 1.120E+06 1.350E+06 8.600E+06 0.000E+00 9.330E+06 I-130 3.390E-06 6.850E-06 3.530E-06 7.540E-04 1.020E-05 0.000E+00 3.200E I-131 1.660E+07 1.670E+07 9.490E+06 5.520E+09 2.740E+07 0.000E+00 1.490E+06 l I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; I-133 6.680E-01 8.260E-01 3.120E-01 1.530E+02 1.380E+00 0.000E+00 3.330E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 9.220E+08 1.510E+09 3.190E+08 0.000E+00 4.690E+08 1.680E+0B 8.150E+06 CS-136 1.590E+07 4.370E+07 2.830E+07 0.000E+00 2.330E+07 3.470E+06 1.540E+06 t CS-137 1.330E+09 1.280E+09 1.880E+08 0.000E+00 4.160E+08 1.500E+08 7.990E+06 i CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.390E+07 3.850E+04 2.560E+06 0.000E+00 1.250E+04 2.290E+04 2.220E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.410E-02 1.890E-02 6.380E-03 0.000E+00 0.000E+00 0.000E+00 5.270E+02 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 2.220E+04 1.110E+04 1.640E+03 0.000E+00 4.840E+03 0.000E+00 1.380E+07 CE-143 3.300E-02 1.790E+01 2.590E-03 0.000E+00 7.510E-03 0.000E+00 2.620E+02 CE-144 2.320E+06 7.260E+05 1.240E+05 0.000E+00 4.020E+05 0.000E+00 1.890E+08 PR-143 3.390E+04 1.020E+04 1.680E+03 0.000E+00 5.510E+03 0.000E+00 3.660E+07 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.170E+04 9.480E+03 7.340E+02 0.000E+00 5.200E+03 0.000E+00 1.500E+07 W-187 3.360E-02 1.990E-02 8.920E-03 0.000E+00 0.000E+00 0.000E+00 2.790E+00 NP-239 4.200E-01 3.020E-02 2.120E-02 0.000E+00 8.730E-02 0.000E+00 2.230E+03
--. . . ~ . . _ - - _ - . . ,,
t Offsite Dose Cilculation Manu11 Page 242 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-COW-MEAT DOSE FACTORS INFANT - (m2
- mrem /yr per uci/sec)
Nuclide Bot.a Liver Tbody Thyroid Kidney Lung Gitract k l i 5 e t f i e l i 3 I r
, ~. - .. . . - . . - -
l Offsite Dose Calculation MonuCI Pag 9243 of 298 Revision 2 Change 0 ; ATTACHMENT 12 ! GRASS-COW-MEAT DOSE FACTORS : INFANT . (m2
- mrem /yr per uCi/sec) '
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract . i i
.i i
4 i i t k i I l l 4 i l i s -,e, - - - - - - -_ - - - _ - - - . - - - - - - . - m
Offsite D0se Calculition Minual Page 244 of 298 Revisbn 2 Change 0 : ATTACHMENT 12 , VEGETATION DOSE FACTORS ADULT (m2
- mrem /yr per uci/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 , C-14 8.970E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 f NA-24 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 l P-32 1.400E+09 8.730E+07 5.420E+07 0.000E+00 0.000E+00 0.000E+00 1.580E+08 : CR-51 0.000E+00 0.000E+00 4.660E+04 2.790E+04 1.030E+04 6.190E+04 1.170E+07 MN-54 0.000E+00 3.110E+08 5.940E+07 0.000E+00 9.270E+07 0.000E+00 9.540E+08 MN-56 0.000E+00 1.610E+01 2.850E+00 0.000E+00 2.040E+01 0.000E+00 5.130E+02 FE-55 2.090E+08 1.450E+0B 3.370E+07 0.000E+00 0.000E+00 8.060E+07 8.290E+07 FE-59 1.270E+08 2.990E+08 1.140E+08 0.000E+00 0.000E+00 8.350E+07 9.960E+08 CO-57 0.000E+00 1.170E+07 1.950E+07 0.000E+00 0.000E+00 0.000E+00 2.970E+08 CO-58 0.000E+00 3.090E+07 6.920E+07 0.000E+00 0.000E+00 0.000E+00 6.260E+08 CO-60 0.000E+00 1.670E+0B 3.690E+08 0.000E+00 0.000E+00 0.000E+00 3.140E+09 NI-63 1.040E+10 7.210E+08 3.490E+08 0.000E+00 0.000E+00 0.000E+00 1.500E+08 NI-65 6.150E+01 7.990E+00 3.650E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 CU-64 0.000E+00 9.270E+03 4.350E+03 0.000E+00 2.340E+04 0.000E+00 7.900E+05 ZN-65 3.170E+0B 1.010E+09 4.560E+08 0.000E+00 6.750E+08 0.000E+00 6.360E+08 ZN-69 8.750E-06 1.670E-05 1.160E-06 0.000E+00 1.090E-05 0.000E+00 2.51CE-06 BR-82 0.000E+00 0.000E+00 1.510E+06 0.000E+00 0.000E+00 0.000E+00 1.730E+06 i BR-83 0.000E+00 0.000E+00 3.210E+00 0.000E+00 0.000E+00 0.000E+00 4.630E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.190E+08 1.020E+08 0.000E+00 0.000E+00 0.000E+00 4.320E+07 ! RB-88 0.000E+00 0.000E+00 0.000E+C0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 9.960E+09 0.000E+00 2.860E+08 0.000E+00 0.000E+00 0.000E+00 1.600E+09 SR-90 6.050E+11 0.000E+00 1.480E+11 0.000E+00 0.000E+00 0.000E+00 1.750E+10 ' SR-91 3.200E+05 0.000E+00 1.290E+04 0.000E+00 0.000E+00 0.000E+00 1.520E+06 SR-92 4.270E+02 0.000E+00 1.850E+01 0.000E+00 0.000E+00 0.000E+00 8.460E+03 Y-90 1.330E+04 0.000E+00 3.560E+02 0.000E+00 0.000E+00 0.000E+00 1.410E+08 Y-91M 5.830E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.710E-08 Y-91 5.130E+06 0.000E+00 1.370E+05 0.000E+00 0.000E+00 0.000E+00 2.820E+09 Y-92 9.010E-01 0.000E+00 2.630E-02 0.000E+00 0.000E+00 0.000E+00 1.580E+04 Y-93 1.740E+02 0.000E+00 4.800E+00 0.000E+00 0.000E+00 0.000E+00 5.520E+06 ZR-95 1.190E+06 3.810E+05 2.580E+05 0.000E+00 5.970E+05 0.000E+00 1.210E+09 l ZR-97 3.330E+02 6.730E+01 3.080E+01 0.000E+00 1.020E+02 0.000E+00 2.080E+07 NB-95 1.420E+05 7.910E+04 4.250E+04 0.000E+00 7.810E+04 0.000E+00 4.800E+08 : NB-97 2.900E-06 7.340E-07 2.680E-07 0.000E+00 8.560E-07 0.000E+00 2.710E-03 [ MO-99 0.000E+00 6.250E+06 1.190E+06 0.000E+00 1.410E+07 0.000E+00 1.450E+07 TC-99M 3.060E+00 8.660E+00 1.100E+02 0.000E+00 1.320E+02 4.240E+00 5.120E+03 l TC-101 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , RU-103 4.800E+06 0.000E+00 2.070E+06 0.000E+00 1.830E+07 0.000E+00 5.610E+0B RU-105 5.390E+01 0.000E+00 2.130E+01 0.000E+00 6.960E+02 0.000E+00 3.300E+04 RU-106 1.930E+08 0.000E+00 2.440E407 0.000E+00 3.720E+0B 0.000E+00 1.250E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ' RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I
Offsit3 Dose C:lculation Minuti Page 245 of 298 l Revision 2 Change 0 ATTACHMENT 12 y VEGETATION DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 1.060E+07 9.760E+06 5.800E+06 0.000E+00 1.920E+07 0.000E+00 3.980E+09 SB-122 7.500E+05 7.820E+05 9.470E+06 1.240E+05 3.690E+05 1.610E+05 9.320E+07 SB-124 1.040E+08 1.960E+06 4.110E+07 2.520E+05 0.000E+00 8.080E+07 2.950E+09 , SB-125 1.360E+08 1.520E+06 3.250E+07 1.390E+05 0.000E+00 1.050E+08 1.500E+09 TE-125M 9.660E+07 3.500E+07 1.290E+07 2.900E+07 3.930E+08 0.000E+00 3.860E+08 TE-127M 3.490E+08 1.250E+08 4.260E+07 8.920E+07 1.420E+09 0.000E+00 1.170E+09 TE-127 5.760E+03 2.070E+03 1.250E+03 4.270E+03 2.350E+04 0.000E+00 4.540E+05 TE-129M 2.550E+08 9.500E+07 4.030E+07 8.750E+07 1.060E+09 0.000E+00 1.280E+09 TE-129 6.650E-04 2.500E-04 1.620E-04 5.100E-04 2.790E-03 0.000E+00 5.020E-04 TE-131M 9.120E+05 4.460E+05 3.720E+05 7.060E+05 4.520E+06 0.000E+00 4.430E+07 i TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i TE-132 4.290E+06 2.770E+06 2.600E+06 3.060E+06 2.670E+07 0.000E+00 1.310E+08 i I-130 3.960E+05 1.170E+06 4.610E+05 9.900E+07 1.820E+06 0.000E+00 1.010E+06 I-131 8.090E+07 1.160E+08 6.630E+07 3.790E+10 1.980E+08 0.000E+00 3.050E+07 2 I-132 5.740E+01 1.540E+02 5.380E+01 5.380E+03 2.450E+02 0.000E+00 2.890E+01 I-133 2.120E+06 3.690E+06 1.120E+06 5.420E+08 6.440E+06 0.000E+00 3.310E+06 I-134 1.060E-04 2.880E-04 1.030E-04 5.000E-03 4.590E-04 0.000E+00 2.510E-07 I-135 4.080E+04 1.070E+05 3.940E+04 7.040E+06 1.710E+05 0.000E+00 1.210E+05 CS-134 4.660E+09 1.110E+10 9.070E+09 0.000E+00 3.590E+09 1.190E+09 1.940E+08 ! CS-136 4.200E+07 1.660E+08 1.190E+08 0.000E+00 9.240E+07 1.270E+07 1.890E+07 [ CS-137 6.360E+09 8.700E+09 5.700E+09 0.000E+00 2.950E+09 9.810E+08 1.680E+08 , CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 2.950E-02 2.100E-05 8.640E-04 0.000E+00 1.960E-05 1.190E-05 5.230E-02 BA-140 1.290E+08 1.620E+05 8.430E+06 0.000E+00 5.490E+04 9.250E+04 2 650E+08 I BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.970E+03 9.920E+02 2.620E+02 0.000E+00 0.000E+00 0.000E+00 7.280E+07 LA-142 1.400E-04 6.350E-05 1.580E-05 0.000E+00 0.000E+00 0.000E+00 4.640E-01 CE-141 1.960E+05 1.330E+05 1.510E+04 0.000E+00 6.170E+04 0.000E+00 5.080E+08 CE-143 1.000E+03 7.420E+05 8.210E+01 0.000E+00 3.260E+02 0.000E+00 2.770E+07 CE-144 3.290E+07 1.380E+07 1.770E+06 0.000E+00 8.160E+06 0.000E+00 1.110E+10 PR-143 6.340E+04 2.540E+04 3.140E+03 0.000E+00 1.470E+04 0.000E+00 2.780E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.340E+04 3.860E+04 2.310E+03 0.000E+00 2.250E+04 0.000E+00 1.850E+08 ; W-187 3.820E+04 3.190E+04 1.120E+04 0.000E+00 0.000E+00 0.000E+00 1.050E+07 NP-239 1.420E+03 1.400E+02 7.720E+01 0.000E+00 4.370E+02 0.000E+00 2.870E+07 I 5 f I e
l-l Offsite Dose Calculation Minu11 Page 246 of 298 f i j Revision 2 Change 0 ATTACHMENT 12 VEGETATION DOSE FACTORS TEEN (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract j p H-3 0.000E+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 J j C-14 1.450E+06 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 NA-24 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 P-32 1.610E+09 9.960E+07 6.230E+07 0.000E+00 0.000E+00 0.000E+00 1.350E+08 CR-51 0.000E400 0.000E+00 6.200E+04 3.440E+04 1.360E+04 8.850E+04 1.040E+07 ! MN 54 0.000E+00 4.520E+08 8.970E+07 0.000E+00 1.350E+08 0.000E+00 9.270E+08 MN-E6 0.000E+00 1.450E+01 2.580E+00 0.000E+00 1.830E+01 0.000E+00 9.540E+02 FE-55 3.250E+08 2.310E+08 5.380E+07 0.000E+00 0.000E+00 1.460E+08 9.980E+07 j FE-59 1.810E+08 4.220E+08 1.630E+08 0.000E+00 0.000E+00 1.330E+08 9.980E+08 {' CO-57 0.000E+00 1.790E+07 3.000E+07 0.000E+00 0.000E+00 0.000E+00 3.340E+08 CO-58 0.000E+00 4.380E+07 1.010E+08 0.000E+00 0.000E+00 0.000E+00 6.040E+08 CO-60 0.000E+00 2.490E+08 5.600E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 NI-63 1.610E+10 1.130E+09 5.450E+08 0.000E+00 0.000E+00 0.000E+00 1.810E+08 l NI-65 5.730E+01 7.320E+00 3.330E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 l CU-64 0.000E+00 8.400E+03 3.950E+03 0.000E+00 2.120E+04 0.000E+00 6.510E+05 ZN-65 4.240E+08 1.470E+09 6.860E+08 0.000E+00 9.410E+08 0.000E+00 6.230E+08 ZN-69 0.190E-06 1.560E-05 1.090E-06 0.000E+s 1.020E-05 0.000E+00 2.880E-05 BR-82 0.000E+00 0.000E+00 1.330E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.010E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00
- BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.730E+08 1.280E+08 0.000E+00 0.000E+00 0.000E+00 4.050E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.510E+10 0.000E+00 4.330E+08 0.000E+00 0.000E+00 0.000E+00 1.800E+09 SR-90 7.510E+11 0.000E+00 1.850E+11 0.000E+00 0.000E+00 0.000E+00 2.110E+10 SR-91 2.990E+05 0.000E+00 1.190E+04 0.000E+00 0.000E+00 0.000E+00 1.360E+06 SR-92 3.970E+02 0.000E+00 1.690E+01 0.000E+00 0.000E+00 0.000E+00 1.010E+04 Y-90 1.240E+04 0.000E+00 3.340E+02 0.000E+00 0.000E+00 0.000E+00 1.020E+08 j Y-91M 5.430E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E-07 l 7.870E+06 0.000E+00 2.110E+05 0.000E+00 0.000E+00 0.000E+00 3.230E+09 i
Y-91 Y-92 8.470E-01 0.0*0E+00 2.450E-02 0.000E+00 0.000E+00 0.000E+00 2.320E+04 , Y-93 1.630E+02 0.000E+00 4.470E+00 0.000E+00 0.000E+00 0.000E+00 4.980E+06 l ZR-95 1.740E+06 5.490E+05 3.780E+05 0.000E+00 8.070E+05 0.000E+00 1.270E+09 ZR-97 3.090E+02 6.110E+01 2.810E+01 0.000E+00 9.260E+01 0.000E+00 1.650E+07 NB-95 1.920E+05 1.060E+05 5.860E+04 0.000E+00 1.030E+05 0.000E+00 4.550E+08 ! NB-97 2.690E-06 6.670E-07 2.440E-07 0.000E+00 7.800E-07 0.000E+00 1.590E-02 MO-99 0.000E+00 5.740E+06 1.090E+06 0.000E+00 1.310E+07 0.000E+00 1.030E+07 TC-99M 2.700E+00 7.540E+00 9.770E+01 0.000E+00 1.120E+02 4.190E+00 4.950E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i RU-103 6.870E+06 0.000E+00 2.940E+06 0.000E+00 2.420E+07 0.000E+00 5.740E+08 RU-105 5.000E+01 0.000E+00 1.940E+01 0.000E+00 6.310E+02 0.000E+00 4.040E+04 RU-106 3.090E+08 0.000E+00 3.900E+07 0.000E+00 5.970E+08 0.000E+00 1.480E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
Offsite Dose C:lculation M:nuil P:gs 247 of 298 l Revisbn 2 Change 0 l ATTACHMENT 12 l l VEGETATION DOSE FACTORS TEEN . (m2
- mrem /yr per uCi/sec) b Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract l AG-110M 1.520E+07 1.440E+07 8.740E+06 0.000E+00 2.740E+07 0.000E+00 4.040E+09 SB-122 4.920E+05 5.130E+05 6.220E+06 8.150E+04 2.420E+05 1.060E+05 6.120E+07 SB-124 1.550E+08 2.850E+06 6.030E+07 3.510E+05 0.000E+00 1.350E+08 3.110E+09 SB-125 2.140E+08 2.340E+06 5.000E+07 2.040E+05 0.000E+00 1.880E+08 1.660E+09 TE-125M 1.480E+08 5.340E+07 1.980E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+08 TE-127M 5.510E+08 1.960E+08 6.560E+07 1.310E+0B 2.240E+09 0.000E+00 1.370E+09 TE-127 5.430E+03 1.920E+03 1.170E+03 3.740E+03 2.200E+04 0.000E+00 4.190E+05 ,
TE-129M 3.670E+08 1.360E+0B 5.810E+07 1.180E+0B 1.540E+09 0.000E+00 1.380E+09 TE-129 6.220E-04 2.320E-04 1.510E-04 4.450E-04 2.610E-03 0.000E+00 3.400E-03 TE-131M 8.440E+05 4.050E+05 3.380E+05 6.090E+05 4.220E+06 0.000E+00 3.250E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TF-132 3.900E+06 2.47CE+06 2.320E+06 2.600E+06 2.370E+07 0.000E+00 7.820E+07 I-130 3.540E+05 1.020E+06 4.090E+05 8.350E+07 1.580E+06 0.000E+00 7.870E+05 I-131 7.700E+07 1.080E+08 5.790E+07 3.140E+10 1.850E+08 0.000E+00 2.130E+07 j I-132 5.180E+01 1.360E+02 4.870E+01 4.570E+03 2.140E+02 0.000E+00 5.910E+01 I-133 1.970E+06 3.340E+06 1.020E+06 4.660E+08 5.860E+06 0.000E+00 2.530E+06 i I-134 9.590E-05 2.540E-04 9.130E-05 4.240E-03 4.010E-04 0.000E+00 3.350E-06 I-135 3.680E+04 9.480E+04 3.520E+04 6.100E+06 1.500E+05 0.000E+00 1.050E+05 i CS-134 7.090E+09 1.670E+10 7.740E+09 0.000E+00 5.300E+09 2.020E+09 2.080E+08 CS-136 4,290E+07 1.690E+08 1.130E+08 0.000E+00 9.190E+07 1.450E+07 1.360E+07 CS-137 1.010E+10 1.350E+10 4.690E+09 0.000E+00 4.590E+09 1.780E+09 1.920E+0B CS-138 0.000E+00 0.090E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 2.770E-02 1.950E-05 8.080E-04 0.000E+00 1.810E-05 1.340E-05 2.470E-01 , BA-140 1.380E+0B 1.690E+05 8.910E+06 0.000E+00 5.750E+04 1.140E+05 2.130E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ! BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.800E+03 8.840E+02 2.350E+02 0.000E+00 0.000E+00 0.000E+00 5.080E+07 LA-142 1.280E-04 5.690E-05 1.420E-05 0.000E+00 0.000E+00 0.000E+00 1.730E+00
- CE-141 2.820E+05 1.880E+05 2.160E+04 0.000E+00 8.860E+04 0.000E+00 5.380E+08 ;
CE-143 9.370E+02 6.820E+05 7.620E+01 0.000E+00 3.060E+02 0.000E+00 2.050E+07 CE-144 5.270E+07 2.180E+07 2.830E+06 0.000E+00 1.300E+07 0.000E+00 1.330E+10 PR-143 7.120E+04 2.840E+04 3.550E+03 0.000E+00 1.650E+04 0.000E+00 2.340E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.630E+04 3.940E+04 2.360E+03 0.000E+00 2.320E+04 0.000E+00 1.420E+08 ; W-187 3.550E+04 2.900E+04 1.020E+04 0.000E+00 0.000E+00 0.000E+00 7.840E+06 NP-239 1.380E+03 1.300E+02 7.240E+01 0.000E+00 4.090E+02 0.000E+00 2.100E+07 i l l l i
)
1
Offsite Dose C lculition Manu11 Paga 248 cf 298 Revison 2 Change 0 ATTACHMENT 12 VEGETATION DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ) .__..............__..__........__........... ___........__...___.............. l H-3 0.000E+00 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 ; C-14 3.500E+06 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 ] NA-24 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 P-32 3.370E+09 1.580E+08 1.300E+0B 0.000E+00 0.000E+00 0.000E+00 9.300E+07 i CR-51 0.000E+00 0.000E+00 1.180E+05 6.540E+04 1.790E+04 1.190E+05 6.250E+06 MN-54 0.000E+00 6.610E+08 1.760E+08 0.000E+00 1.850E+08 0.000E+00 5.550E+08 MN-56 0.000E+00 1.900E+01 4.280E+00 0.000E+00 2.290E+01 0.000E+00 2.750E+03 FE-55 8.000E+08 4.240E+08 1.310E+08 0.000E+00 0.000E+00 2.400E+08 7.860E+07 ' FE-59 4.010E+08 6.490E+08 3.230E+08 0.000E+00 0.000E+00 1.880E+08 6.760E408 CO-57 0.000E+00 2.990E+07 6.040E+07 0.000E+00 0.000E+00 0.000E+00 2.450E+08
- ::llll:::':':ll:ll':':ll:::::llll:ll::lllllll::lll":ll':llll:ll :
NI-63 3.950E+10 2.110E+09 1.340E+09 0.000E+00 0.000E+00 0.000E+00 1.420E+08 NI-65 1.050E+02 9.890E+00 5.770E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 CU-64 0.000E+00 1.110E+04 6.690E+03 0.000E+00 2.680E+04 0.000E+00 5.200E+05 ZN-65 8.120E+08 2.160E+09 1.350E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 ZN-69 1.510E-05 2.180E-05 2.020E-06 0.000E+00 1.320E-05 0.000E+00 1.380E-03 BR-82 0.000E+00 0.000E+00 2.040E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.550E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 f RB-86 0.000E+00 4.520E+08 2.780E+08 0.000E+00 0.000E+00 0.000E+00 2.910E+07 3 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; SR-89 3.590E+10 0.000E+00 1.030E+09 0.000E+00 0.000E+00 0.000E+00 1.390E+09 ! SR-90 1.240E+12 0.000E+00 3.150E+11 0.000E+00 0.000E+00 0.000E+00 1.670E+10 ; SR-91 5.500E+05 0.000E+00 2.080E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+06 SR-92 7.280E+02 0.000E+00 2.920E+01 0.000E+00 0.000E+00 0.000E+00 1.380E+04 Y-90 2.300E+04 0.000E+00 6.170E+02 0.000E+00 0.000E+00 0.000E+00 6.560E+07 Y-91M 9.940E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.950E-05 Y-91 1.870E+07 0.000E+00 5.010E+05 0.000E+00 0.000E+00 0.000E+00 2.490E+09 Y-92 1.560E+00 0.000E+00 4.460E-02 0.000E+00 0.000E+00 0.000E+00 4.510E+04 Y-93 3.010E+02 0.000E+00 8.250E+00 0.000E+00 0.000E+00 0.000E+00 4.480E+06 ZR-95 3.900E+06 8.580E+05 7.640E+05 0.000E+00 1.230E+06 0.000E+00 8.950E+08 , ZR-97 5.640E+02 8.150E+01 4.810E+01 0.000E+00 1.170E+02 0.000E+00 1.230E+07 NB-95 4.100E+05 1.590E+05 1.140E+05 0.000E+00 1.500E+05 0.000E+00 2.950E+08 NB-97 4.900E-06 8.850E-07 4.130E-07 0.000E+00 9.820E-07 0.000E+00 2.730E-01 MO-99 0.000E+00 7.830E+06 1.940E+06 0.000E+00 1.670E+07 0.000E+00 6.480E+06 TC-99M 4.650E+00 9.120E+00 1.510E+02 0.000E+00 1.330E+02 4.630E+00 5.190E+03 l I TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.550E+07 0.000E+00 5.940E+06 0.000E+00 3.890E+07 0.000E+00 3.990E+08 RU-105 9.170E+01 0.000E+00 3.330E+01 0.000E+00 8.060E+02 0.000E+00 5.980E+04 RU-106 7.450E+08 0.000E+00 9.300E+07 0.000E+00 1.010E+09 0.000E+00 1.160E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 t
- ~ e -e, n
l Offsite Dose Calcut: tion Minu:1 Prge 249 Of 298 l Revtion 2 Ch nge O ATTACHMENT 12 VEGETATION DOSE FACTORS CHILD i (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 3.220E+07 2.170E+0" 1.740E+07 0.000E+00 4.050E+07 0.000E+00 2.580E+09 SB-122 3.050E+05 3.180E+05 3.850E+06 5.050E+04 1.500E+05 6.540E+04 3.790E+07 SB-124 3.520E+08 4.570E+06 1.230E+08 7.780E+05 0.000E+00 1.960E+08 2.200E+09 SB-125 4.990E+08 3.850E+06 1.050E+08 4.620E+05 0.000E+00 2.780E+08 1.190E+09 TE-125M 3.510E+08 9.500E+07 4.670E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+08 TE-127M 1.320E+09 3.560E+08 1.570E+08 3.160E+08 3.770E+09 0.000E+00 1.070E+09 TE-127 1.000E+04 2.700E+03 2.150E+03 6.930E+03 2.850E+04 0.000E+00 3.910E+05 TE-129M 8.540E+08 2.390E+08 1.330E+08 2.750E+08 2.510E+09 0.000E+00 1.040E+09 TE-129 1.150E-03 3.220E-04 2.740E-04 8.220E-04 3.370E-03 0.000E+00 7.170E-02 TE-131M 1.540E+06 5.330E+05 5.680E+05 1.100E+06 5.160E+06 0.000E+00 2.160E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 6.980E+06 3.090E+06 3.730E+06 4.500E+06 2.870E+07 0.000E+00 3.110E+07 I-130 6.210E+05 1.260E+06 6.470E+05 1.380E+08 1.880E+06 0.000E+00 5.870E+05 I-131 1.430E+08 1.440E+08 8.180E+07 4.760E+10 2.360E+08 0.000E+00 1.280E+07 I-132 9.200E+01 1.690E+02 7.770E+01 7.840E+03 2.590E+02 0.000E+00 1.990E+02 I-133 3.590E+06 4.440E+06 1.680E+06 8.250E+08 7.400E+06 0.000E+00 1.790E+06 I-134 1.700E-04 3.160E-04 1.460E-04 7.280E-03 4.840E-04 0.000E+00 2.100E-04 I-135 6.540E+04 1.180E+05 5.570E+04 1.040E+07 1.810E+05 0.000E+00 8.980E+04 CS-134 1.600E+10 2.630E+10 5.540E+09 0.000E+00 8.140E+09 2.920E+09 1.420E+0B CS-136 8.060E+07 2.220E+08 1.430E+08 0.000E+00 1.180E+08 1.760E+07 7.790E+06 CS-137 2.390E+10 2.290E+10 3.380E+09 0.000E+00 7.460E+09 2.680E+09 1.430E+08 CS-130 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 5.110E-02 2.730E-05 1.480E-03 0.000E+00 2.380E-05 1.610E-05 2.950E+00 BA-140 2.770E+08 2.430E+05 1.620E+07 0.000E+00 7.900E+04 1.450E+05 1.400E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.230E+03 1.130E+03 3.810E+02 0.000E+00 0.000E+00 0.000E+00 3.150E+07 LA-142 2.320E-04 7.400E-05 2.320E-05 0.000E+00 0.000E+00 0.000E+00 1.470E+01 CE-141 6.350E+05 3.260E+05 4.840E+04 0.000E+00 1.430E+05 0.000E+00 4.070E+08 CE-143 1.730E+03 9.360E+05 1.360E+02 0.000E+00 3.930E+02 0.000E+00 1.370E+07 CE-144 1.270E+08 3.980E+07 6.780E+06 0.000E+00 2.210E+07 0.000E+00 1.040E+10 PR-143 1.480E+05 4.460E+04 7.370E+03 0.000E+00 2.410E+04 0.000E+00 1.600E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.160E+04 5.800E+04 4.490E+03 0.000E+00 3.180E+04 0.000E+00 9.180E+07 W-187 6.470E+04 3.830E+04 1.720E+04 0.000E+00 0.000E+00 0.000E+00 5.380E+06 NP-239 2.550E+03 1.830E+02 1.290E+02 0.000E+00 5.300E+02 0.000E+00 1.360E+07 l l l l
Offsite Dose Calculation Minu'.I Page 250 of 298 ! Revision 2 Change O ATTACHMENT 12 VEGETATION DOSE FACTORS INFANT , (m2
- mrem /yr per uci/sec) >
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract J e o i t 9
,.. - ._ . . -= - .. J Offsste Dose Cilculation M: null Page 251 of 298 : Revision 2 Change 0 , ATTACHMENT 12 ! VEGETATION DOSE FACTORS
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INFANT (m2* mrem /yr per uC1/sec) : Nuclide Bone- Liver Tbody Thyroid Kidney Lung Gitract ! 4 4 r i e i i. l h k
- . _ _ _ - . . _ , _ , - , . . - _ . ~- - . -
I
. Offsit) Dose C:1cuttion Mmual Page 252 of 298 Revision 2 Change 0 l ATTACHMENT 12 GROUND PLANE DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
'. :lide Bone Liver Tbody Thyroid Kidney Lung Gitract 1
)
I a e l l \ l l l l 1 1.- L_- _ -____-______-_-__ ______ - __-__ -____-_____________ ____________-__ _ _____________ __ _ _.. . __}
1 Offsite Dose' Calculation Minual Page 253 of 298 -
. RIv': ion 2 Chang) 0 -
i ATTACHMENT 12 GROUND PLANE DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
Nuclide' Bone Liver .Tbody Thyroid -Kidney Lung Gitract
.........__....................._____............__......................__... +
1 E t i f h T j f 4 L 4 I i I J 1
Offsite Dose C lculation Minuti Page 254 of 298 Revision 2 Change O ATTACHMENT 12 . I l GROUND PLANE DOSE FACTORS TEEN (m2
- mrem /yr per uti/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.0!OE+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0J0E+00 0.000E+00 0.000E+00 FE-59 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+0B 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.620E+08 3.820E+08 3.820E+08 , CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 , BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 o RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.220E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 ' Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 ,Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2.480E+08 2.480E+08 2.480E+08 2.480E+0B 2.480E+0B 2.480E+08 2.480E+08 ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 i TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 l TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ' AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06
r s
. Offsite Dose C:lculation Manu11 Page 255 of 298 l
Ravcion 2 Change O ATTACHMENT 12 GROUND PLANE DOSE FACTORS i TEEN (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract ; TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 TE-129M 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 TE-129 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.03CE+06 8.030E+06 8.030E+06 i TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 j I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1 ! I-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 I-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 l I-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 I-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 l CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+0B 1.490E+0B 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 j BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 l ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 l H-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 l l l l
Offsite Dose Calculation Minu:1 Page 256 of 298 Revision 2 Change 0 : ATTACHMENT 12 GROUND PLANE DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec) l l
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract i H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 . P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l FE-59 2.750E+08 2.750E+08 2.750E+b8 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+0B 3.820E+0B 3.820E+08 3.820E+08 ' CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 > BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 , RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 ; Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 ' Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1. OBOE +06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 ! Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 L ZR-95 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+0B 2.480E+0B 2.480E+08 ! ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+0B 1.360E+08 1.360E+08 1.360E+08 1.360E+08 MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 q I TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+0B 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1 4
Offsite Dose CDicuttion Manual Page 257 of 298
' Revision 2 Change 0 ;
i ATTACHMENT 12 ; GROUND PLANE DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody' Thyroid Kidney Lung Gitract TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 TE-129M 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 : TE-129 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 I-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 i I-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2 470E+06 ! I-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 I-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 : CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 [ CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 ! BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 l BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 i CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06
Offsite Dose Criculation M: null Page 258 of 298 Revision 2 Ch:nge 0 ATTACHMENT 12 GROUND PLANE DOSE FACTORS INFANT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 j CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 I MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 f MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 1 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.750E+0B 2.750E+0B 2.750E+08 2.750E+0B 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+0B 3.820E+0B 3.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 l , NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+0* 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 % C00E+00 0.000E+00 0.000E+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 . BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 ! I BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.170E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.0BOE+06 1.080E+06 1.080E+06 1.080E+06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2.480E+08 2.480E+08 2.480E+08 2.480E+0B 2.480E+08 2.480E+08 2.480E+08 ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+0B 1.090E+08 3.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 l SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06
Offsite Dose Cdculation Minual Page 259 of 298 l Revision 2 Change 0 i l ATTACHMENT 12 j i GROUND PLANE DOSE FACTORS i INFANT l (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 # TE-129M 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 TE-219 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 I-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 I-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 I-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 , I-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 , BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 l LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 f CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 , CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 I
I Offsite Dose C:lculation Minuit Pcge 260 of 298 Revision 2 Change O ATTACHMENT 12 INHALATION DOSE FACTORS ADULT (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 C-14 1.020E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 P-32 1.320E+06 7.710E+04 5.010E+04 0.000E+00 0.000E+00 0.000E+00 8.640E+04 CR-51 0.000E+00 0.000E+00 1.000E+02 5.950E+01 2.280E+01 1.440E+04 3.320E+03 MN-54 0.000E+00 3.960E+04 6.300E+03 0.000E+00 9.840E+03 1.400E+06 7.740E+04 MN-56 0.000E+00 1.240E+00 1.830E-01 0.000E+00 1.300E+00 9.440E+03 2.020E+04 FE-55 2.460E+04 1.700E+04 3.940E+03 0.000E+00 0.000E+00 7.210E+04 6.030E+03 FE-59 1.180E+04 2.780E+04 1.060E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 CO-57 0.000E+00 6.920E+02 6.710E+02 0.000E+00 0.000E+00 3.700E+05 3.140E+04 CO-58 0.000E+00 1.580E+03 2.070E+03 0.000E+00 0.000E+00 9.280E+05 1.060E+05 CO-60 0.000E+00 1.150E+04 1.480E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 NI-63 4.320E+05 3.140E+04 1.450E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 NI-65 1.540E+00 2.100E-01 9.120E-02 0.000E+00 0.000E+00 5.600E+03 1.230E+04 CU-64 0.000E+00 1.460E+00 6.150E-01 0.000E+00 4.620E+00 6.780E+03 4.900E+04 ZN-65 3.240E+04 1.030E+05 4.660E+04 0.000E+00 6.900E+04 8.640E+05 5.340E+04 ZN-69 3.380E-02 6.510E-02 4.520E-03 0.000E+00 4.220E-02 9.200E+02 1.630E+01 BR-82 0.000E+00 0.000E+00 1.350E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+04 BR-83 0.000E+00 0.000E+00 2.410E+02 0.000E+00 0.000E+00 0.000E+00 2.320E+02 , BR-84 0.000E+00 0.000E+00 3.130E+02 0.000E+00 0.000E+00 0.000E+00 1.640E-03 BR-85 0.000E+00 0.000E+00 1.280E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.350E+05 5.900E+04 0.000E+00 0.000E+00 0.000E+00 1.660E+04 RB-88 0.000E+00 3.870E+02 1.930E+02 0.000E+00 0.000E+00 0.000E+00 3.340E-09 RB-89 0.000E+00 2.560E+02 1.700E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.040E+05 0.000E+00 8.720E+03 0.000E+00 0.000E+00 1.400E+06 3.500E+05 SR-90 9.920E+07 0.000E+00 6.100E+06 0.000E+00 0.000E+00 9.600E+06 7.220E+05 SR-91 6.190E+01 0.000E+00 2.500E+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 SR-92 6.740E+00 0.000E+00 2.910E-01 0.000E+00 0.000E+00 1.650E+04 4.300E+04 Y-90 2.090E+03 0.000E+00 5.610E+01 0.000E+00 0.000E+00 1.700E+05 5.060E+05 Y-91M 2.610E-01 0.000E+00 1.020E-02 0.000E+00 0.000E+00 1.920E+03 1.330E+00 Y-91 4.620E+05 0.000E+00 1.240E+04 0.000E+00 0.000E+00 1.700E+06 3.850E+05 Y-92 1.030E+01 0.000E+00 3.020E-01 0.000E+00 0.000E+00 1.570E+04 7.350E+04 Y-93 9.440E+01 0.000E+00 2.610E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05 ZR-95 1.070E+05 3.440E+04 2.330E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 ZR-97 9.680E+01 1.960E+01 9.040E+00 0.000E+00 2.970E+01 7.870E+04 5.230E+05 NB-95 1.410E+04 7.820E+03 4.210E+03 0.000E+00 7.740E+03 5.050E+05 1.040E+05 NB-97 2.220E-01 5.620E-02 2.050E-02 0.000E+00 6.540E-02 2.400E+03 2.420E+02 MO-99 0.000E+00 1.210E+02 2.300E+01 0.000E+00 2.910E+02 9.120E+04 2.480E+05 TC-99M 1.030E-03 2.910E-03 3.700E-02 0.000E+00 4.420E-02 7.640E+02 4.160E+03 TC-101 4.180E-05 6.020E-05 5.900E-04 0.000E+00 1.080E-03 3.990E+02 0.000E+00 RU-103 1.530E+03 0.000E+00 6.580E+02 0.000E+00 5.830E+03 5.050E+05 1.100E+05 RU-105 7.900E-01 0.000E+00 3.110E-01 0.000E+00 1.020E+00 1.100E+04 4.820E+04 RU-106 6.910E+04 0.000E+00 8.720E+03 0.000E+00 1.340E+05 9.360E+06 9.120E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
Offsite Dose C:lculation Minuil Pzge 261 of 298 Revision 2 Change O ATTACHMENT 12 INHALATION DOSE FACTORS ADULT (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 1.080E+04 1.000E+04 5.940E+03 0.000E+00 1.970E+04 4.630E+06 3.020E+05 SB-122 3.100E+03 4.110E+03 4.110E+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 3.120E+04 5.890E+02 1.240E+04 7.550E+01 0.000E+00 2.480E+06 4.060E+05 SB-125 5.340E+04 5.950E+02 1.260E+04 5.400E+01 0.000E+00 1.740E+06 1.010E+05 TE-125M 3.420E+03 1.580E+03 4.670E+02 1.050E+03 1.240E+04 3.140E+05 7.060E+04 TE-127M 1.260E+04 5.770E+03 1.570E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 TE-127 1.400E+00 6.420E-01 3.100E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 TE-129M 9.760E+03 4.670E+03 1.580E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 TE-129 4.980E-02 2.390E-02 1.240E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 TE-131M 6.990E+01 4.360E+01 2.900E+01 5.500E+01 3.090E+02 1.460E+05 5.560E+05 TE-131 1.110E-02 5.950E-03 3.590E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 TE-132 2.600E+02 2.150E+02 1.620E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 I-130 4.500E+03 1.340E+04 5.280E+03 1.140E+06 2.090E+04 7.690E+03 0.000E+00 I-131 2.520E+04 3.580E+04 2.050E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 I-132 1.160E+03 3.260E+03 1.160E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 I-133 8.640E+03 1.480E+04 4.520E+03 2.150E+06 2.500E+04 0.000E+00 8.880E+03 I-134 6.440E+02 1.730E+03 6.150E+02 2.980E+04 2.750E+03 0.000E+00 1.010E+00 I-135 2.680E+03 6.980E+03 2.570E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 CS-134 3.730E+05 8.480E+05 7.280E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 CS-136 3.900E+04 1.460E+05 1.100E+05 0.000E+00 8.560E+54 1.200E+04 1.170E+04 CS-137 4.780E+05 6.210E+05 4.280E+05 0.000E+00 2.220E+05 7.520E+04 8.400E+03 CS-138 3.310E+02 6.210E+02 3.240E+02 0.000E+00 4.800E+02 4.860E+01 1.860E-03 BA-139 9.360E-01 6.660E-04 2.740E-02 0.000E+00 6.220E-04 3.760E+03 8.960E+02 BA-140 3.900E+04 4.900E+01 2.570E+03 0.000E+00 1.670E+01 1.270E+06 2.180E+05 BA-141 1.000E-01 7.530E-05 3.360E-03 0.000E+00 7.000E-05 1.940E+03 1.160E-07 BA-142 2.630E-02 2.700E-05 1.660E-03 0.000E+00 2.290E-05 1.190E+03 0.000E+00 LA-140 3.440E+02 1.740E+02 4.580E+01 0.000E+00 0.000E+00 1.360E+05 4.580E+05 LA-142 6.830E-01 3.100E-01 7.720E-02 0.000E+00 0.000E+00 6.330E+03 2.110E+03 CE-141 1.990E+04 1.350E+04 1.530E+03 0.000E+00 6.260E+03 3.620E+05 1.200E+05 CE-143 1.860E+02 1.380E+02 1.530E+01 0.000E+00 6.080E+01 7.980E+04 2.260E+05 CE-144 3.430E+06 1.430E+06 1.840E+05 0.000E+00 B.480E+05 7.780E+06 0.160E+05 PR-143 9.360E+03 3.750E+03 4.640E+02 0.000E+00 2.160E+03 2.810E+05 2.000E+05 PR-144 3.010E-02 1.250E-02 1.530E-03 0.000E+00 7.050E-03 1.020E+03 2.150E-08 ND-147 5.270E+03 6.100E+03 3.650E+02 0.000E+00 3.560E+03 2.210E+05 1.730E+05 W-187 8.480E+00 7.080E+00 2.480E+00 0.000E+00 0.000E+00 2.900E+04 1.550E+05 NP-239 2.300E+02 2.260E+01 1.240E+01 0.000E+00 7.000E+01 3.760E+04 1.190E+05
l Offsite Dose C11cuttion Minu11 Page 262 of 298 Ratision 2 Chinga 0 ATTACHMENT 12 INHALATION DOSE FACTORS TEEN (mrem /yr per uC1/m3 ) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 C-14 2.600E+04 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 P-32 1.890E+06 1.100E+05 7.160E+04 0.000E+00 0.000E+00 0.000E+00 9.280E+04 CR-51 0.000E+00 0.000E+00 1.350E+02 7.500E+01 3.070E+01 2.100E+04 3.000E+03 MN-54 0.000E+00 5.110E+04 8.400E+03 0.000E+00 1.270E+04 1.980E+06 6.680E+04 q MN-56 0.000E+00 1.700E+00 2.520E-01 0.000E+00 1.790E+00 1.520E+04 5.740E+04 l FE-55 3.340E+04 2.380E+04 5.540E+03 0.000E+00 0.000E+00 1.240E+05 6.390E+03 ) FE-59 1.590E+04 3.700E+04 1.430E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 ) CO-57 0.000E+00 6.920E+02 9.200E+02 0.000E+00 0.000E+00 5.860E+05 3.140E+04 l I CO-58 0.000E+00 2.070E+03 2.7BOE+03 0.000E+00 0.000E+00 1.340E+06 9.520E+04 CO-60 0.000E+00 1.510E+04 1.980E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 NI-63 5.800E+05 4.340E+04 1.980E+04 0.000E+00 0.000E+00 3.070E+05 1.420E+04 NI-65 2.180E+00 2.930E-01 1.270E-01 0.000E+00 0.000E+00 9.360E+03 3.670E+04 CU-64 0.000E+00 2.030E+00 8.480E-01 0.000E+00 6.410E+00 1.110E+04 6.140E+04 ZN-65 3.860E+04 1.340E+05 6.240E+04 0.000E+00 8.640E+04 1.240E+06 4.660E+04 ZN-69 4.830E-02 9.200E-02 6.460E-03 0.000E+00 6.020E-02 1.580E+03 2.850E+02 BR-82 0.000E+00 0.000E+00 1.820E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-83 0.000E+00 0.000E+00 3.440E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 BR-85 0.000E+00 0.000E+00 1.830E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l RB-86 0.000E+00 1.900E+05 8.400E+04 0.000E+00 0.000E+00 0.000E+00 1.770E+04 ) RB-88 0.000E+00 5.460E+02 2.720E+02 0.000E+00 0.000E+00 0.003E+00 2.920E-05 RB-89 0.000E+00 3.520E+02 2.330E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 SR-89 4.340E+05 0.000E+00 1.250E+04 0.000E+00 0.000E+00 2.420E+06 3.710E+05 SR-90 *
.080E+08 0.000E+00 6.680E+06 0.000E+00 0.000E+00 1.650E+07 7.650E+05 SR-91 8.800E+01 0.000E+00 3.510E+00 0.000E+00 0.000E+00 6.070E+04 2.590E+05 SR-92 9.520E+00 0.000E+00 4.060E-01 0.000E+00 0.000E+00 2.740E+04 1.190E+05 Y-90 2.980E+03 0.000E+00 8.000E+01 0.000E+00 0.000E+00 2.930E+05 5.590E+05 Y-91M 3.700E-01 0.000E+00 1.420E-02 0.000E+00 0.000E+00 3.200E+03 3.020E+01 Y-91 6.610E+05 0.000E+00 1.770E+04 0.000E+00 0.000E+00 2.940E+06 4.090E+05 Y-92 1.470E+01 0.000E+00 4.290E-01 0.000E,00 0.000E+00 2.680E+04 1.650E+05 Y-93 1.350E+02 0.000E+00 3.720E+00 0.000E600 0.000E+00 8.320E+04 5.790E+05 ZR-95 1.460E+05 4.580E+04 3.150E+04 0.000 Leu 0 6.740E+04 2.690E+06 1.490E+05 ZR-97 1.380E+02 2.720r+01 1.260E+01 0.000E400 4.120E+01 1.300E+05 6.300E+05 NB-95 1.860E+04 1.030E+04 5.660E+03 0.000E+00 1.000E+04 7.510E+05 9.680E+04 NB-97 3.140E-01 7.780E-02 2.840E-02 0.000E+00 9.120E-02 3.930E+03 2.170E+03 MO-99 0.000E+00 1.690E+02 3.220E+01 0.000E+00 4.110E+02 1.540E+05 2.690E+05 TC-99M 1.380E-03 3.860E-03 4.990E-02 0.000E+00 5.760E-02 1.150E+03 6.130E+03 TC-101 5.920E-05 8.400E-05 8.240E-04 0.000E+00 1.320E-03 6.670E+02 8.720E-07 RU-103 2.100E+03 0.000E+00 8.960E+02 0.000E+00 7.430E+03 7.830E+05 1.090E+05 RU-105 1.120E+00 0.000E+00 4.340E-01 0.000E+00 1.410E+00 1.820E+04 9.040E+04 RU-106 9.840E+04 0.000E+00 1.240E+04 0.000E+00 1.900E+C5 1.610E+07 9.600E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4
w- ~ . - .. .. . -- . . _ _ _ ~
n-l Offsite Dose Calculation M: null hge 263 Of 298 Revision 2 Change O ATTACHMENT 12 INHALATION DOSE FACTORS TEEN (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 1.380E+04 1.310E+04 7.990E+03 0.000E+00 2.500E+04 6.750E+06 2.730E+05 SB-122 3.100E+03 4.110E+03 4.110E+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 4.300E+04 7.940E+02 1.680E+04 9.760E+01 0.000E+00 3.850E+06 3.980E+05 SB-125 7.380E+04 8.000E+02 1.720E+04 7.040E+01 0.000E+00 2.740E+06 9.920E+04 TE-125M 4.880E+03 2.240E+03 6.670E+02 1.400E+03 0.000E+00 5.360E+05 7.500E+04 TE-127M 1.800E+04 8.160E+03 2.180E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 TE-127 2.010E+00 9.120E-01 4.420E-01 1.420E+00 7.280E+00 1.120E+04 8.080E+04 TE-129M 1.390E+04 6.580E+03 2.250E+03 4.580E+03 5.190E+04 1.980E+06 4.050E+05 TE-129 7.100E-02 3.380E-02 1.760E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 TE-131M 9.840E+01 6.010E+01 4.020E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 TE-131 1.580E-02 8,320E-03 5.040E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 TE-132 3.600E+02 2.900E+02 2.190E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 I-130 6.240E+03 1.790E+04 7.170E+03 1.490E+06 2.750E+04 0.000E+00 9.120E+03 I-131 3.540E+04 4.910E+04 2.640E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 I-132 1.590E+03 4.380E+03 1.580E+03 1.510E+05 6.920E+03 0.000E+00 1.270E+03 I-133 1.220E+04 2.050E+04 6.220E+03 2.920E+06 3.590E+04 0.000E+00 1.030E+04 I-134 8.880E+02 2.320E+03 8.400E+02 3.950E+04 3.660E+03 0.000E+00 2.040E+01 I-135 3.700E+03 9.440E+03 3.490E+03 6.210E+05 1.490E+04 0.000E+00 6.950E+03 CS-134 5.020E+05 1.130E+06 5.490E+05 0.000E+00 3.750E+05 1.460E+05 9.760E+03 CS-136 5.150E+04 1.940E+05 1.370E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 CS-137 6.700E+05 8.480E+05 3.110E+05 0.000E+00 3.040E+05 1.210E+05 8.480E+03 CS-138 4.660E+02 8.560E+02 4.460E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01 BA-139 1.340E+00 9.440E-04 3.900E-02 0.000E+00 8.880E-04 6.460E+03 6.450E+03 BA-140 5.470E+04 6.700E+01 3.520E+03 0.000E+00 2.280E+01 2.030E+06 2.290E+05 BA-141 1.420E-01 1.060E-04 4.740E-03 0.000E+00 9.840E-05 3.290E+03 7.460E-04 BA-142 3.700E-02 3.700E-05 2.270E-03 0.000E+00 3.140E-05 1.910E+03 0.000E+00 LA-140 4.790E+02 2.360E+02 6.260E+01 0.000E+00 0.000E+00 2.140E+05 4.870E+05 LA-142 9.600E-01 4.250E-01 1.060E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 CE-141 2.840E+04 1.900E+04 2.170E+03 0.000E+00 8.880E+03 6.140E+05 1.260E+05 CE-143 2.660E+02 1.940E+02 2.160E+01 0.000E+00 8.640E+01 1.300E+05 2.550E+05 CE-144 4.890E+06 2.020E+06 2.620E+05 0.000E+00 1.210E+06 1.340E+07 8.640E+05 PR-143 1.340E+04 5.310E+03 6.620E+02 0.000E+00 3.090E+03 4.830E+05 2.140E+05 PR-144 4.300E-02 1.760E-02 2.180E-03 0.000E+00 1.010E-02 1.750E+03 2.350E-04 ND-147 7.860E+03 8.560E+03 5.130E+02 0.000E+00 5.020E+03 3.720E+05 1.620E+05 W-187 1.200E+01 9.760E+00 3.430E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+05 NP-239 3.380E+02 3.190E+01 1.770E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05
Offsite Dose Criculation M: null Page 264 of 298 Revisbn 2 Change 0 ATTACHMENT 12 l INHALATION DOSE FACTORS CHILD (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.61CE+04 1.610E+04 1.610E+04 1.610E+04 P-32 2.600E+06 1.140E+05 9.880E+04 0.000E+00 0.000E+00 0.000E+00 4.220E+04 CR-51 0.000E+00 ).000E+00 1.540E+02 8.550E+01 2.430E+01 1.700E+04 1.080E+03 MN-54 0.0005+00 4.290E+04 9.510E+03 0.000E+00 1.000E+04 1.580E+06 2.290E+04 MN-56 0.000E+00 1.660E+00 3.120E-01 0.000E+00 1.670E+00 1.310E+04 1.230E+05 FE-55 4.740E+04 2.520E+04 7.770E+03 0.000E+00 0.000E+00 1.110E+05 2.870E+03 FE-59 2.070E+04 3.340E+04 1.670E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 CO-57 0.000E+00 9.030E+02 1.070E+03 0.000E+00 0.000E+00 5.070E+05 1.320E+04 CO-58 0.000E+00 1.770E+03 3.160E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 CO-60 0.000E+00 1.310E+04 2.260E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 NI-63 8.210E+05 4.630E+04 2.800E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 ' NI-65 2.990E+00 2.960E-01 1.640E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 CU-64 0.000E+00 1.990E+00 1.070E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 ! ZN-65 4.260E+04 1.130E+05 7.030E+04 0.000E+00 7.140E+04 9.950E+05 1.630E+04 ZN-69 6.700E-02 9.660E-02 8.920E-03 0.000E+00 5.850E-02 1.420E+03 9.510E+03 BR-82 0.000E+00 0.000E+00 2.090E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 4.740E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 5.480E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 2.530E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 I RB-86 0.000E+00 1.980E+05 1.140E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 RB-88 0.000E+00 5.620E+02 3.660E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01' RB-89 0.000E+00 3.450E+02 2.900E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 SR-89 5.990E+05 0.000E+00 1.720E+04 0.000E+00 0.000E+00 2.160E+06 1.670E+05 SR-90 1.010E+0B 0.000E+00 6.440E+06 0.000E+00 0.000E+00 1.480E+07 3.430E+05 SR-91 1.210E+02 0.000E+00 4.590E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 SR-92 1.310E+01 0.000E+00 5.250E-01 0.000E+00 0.000E+00 2.400E+04 2.420E+05 Y-90 4.110E+03 0.000E+00 1.110E+02 0.000E+00 0.000E+00 2.620E+05 2.680E+05 Y-91M 5.070E-01 0.000E+00 1.840E-02 0.000E+00 0.000E+00 2.310E+03 1.720E+03 Y-91 9.140E+05 0.000E+00 2.440E+04 0.000E+00 0.000E+00 2.630E+06 1.840E+05 Y-92 2.040E+01 0.000E+00 5.810E-01 0.000E+00 0.000E+00 2.390E+04 2.390E+05 Y-93 1.860E+02 0.000E+00 5.110E+00 0.000E+00 0.000E+00 7.440E+04 3.890E+05 ZR-95 1.900E+05 4.180E+04 3.700E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 ZR-97 1.880E+02 2.720E+01 1.600E+01 0.000E+00 3.890E+01 1.130E+05 3.510E+05 NB-95 2.350E+04 9.180E+03 6.550E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 NB-97 4.290E-01 7.700E-02 3.600E-02 0.000E+00 8.550E-02 3.420E+03 2.780E+04 ) 0.000E+00 1.720E+02 4.260E+01 0.000E+00 3.920E+02 1.350E+05 1.270E+05 MO-99 TC-99M 1.780E-03 3.480E-03 5.770E-02 0.000E+00 5.070E-02 9.510E+02 4.810E+03 l TC-101 8.100E-05 8.510E-05 1.080E-03 0.000E+00 1.450E-03 5.850E+02 1.630E+01 l RU-103 2.790E+03 0.000E+00 1.070E+03 0.000E+00 7.030E+03 6.620E+05 4.480E+04 RU-105 1.530E+00 0.000E+00 5.550E-01 0.000E+00 1.340E+00 1.590E+04 9.950E+04 RU-106 1.360E+05 0.000E+00 1.690E+04 0.000E+00 1.840E+05 1.430E+07 4.290E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1
l l Offsite Dose C:lculation Manuil P ga265 of 298 l Revision 2 Change 0 l ATTACHMENT 12 INHALATION DOSE FACTORS CHILD (mrem /yr per uci/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 1.690E+04 1.140E+04 9.140E+03 0.000E+00 2.120E+04 5.480E+06 1.000E+05 SB-122 1.440E+03 1.980E+03 1.900E+04 4.960E+02 7.180E+02 7.730E+34 9.360E+04 SB-124 5.740E+04 7.400E+02 2.000E+04 1.260E+02 0.000E+00 3.740E+06 1.640E+05 SB-125 9.840E+04 7.590E+02 2.070E+04 9.100E+01 0.000E+00 2.320E+06 4.030E+04 TE-125M 6.730E+03 2.330E+03 9.140E+02 1.920E+03 0.000E+00 4."70E+05 3.380E+04 - TE-127M 2.490E+04 8.550E+03 3.020E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 TE-127 2.770E+00 9.510E-01 6.110E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 TE-129M 1.920E+04 6.850E+03 3.040E+03 6.330E+C3 5.030E+04 1.760E+06 1.820E+05 TE-129 9.770E-02 3.500E-02 2.380E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 TE-131M 1.340E+02 5.920E+01 5.070E+01 9.770E+01 4.000E+02 2.060E+05 3.080E405 TE-131 2.170E-02 8.440E-03 6.590E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 TE-132 4.810E+02 2.720E+02 2.630E+02 3.170E+02 1.840E+03 3.770E+05 1.380E+05 I-130 B.180E+03 1.640E+04 8.440E+03 1.850E+06 2.450E+04 0.000E+00 5.110E+03 I-131 4.810E+04 4.810E+04 2.730E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 I-132 2.120E+03 4.070E+03 1.880E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 I I-133 1.660E+04 2.030E+04 7.700E+03 3.850E+06 3.380E+04 0.000E+00 5.480E+03 I-134 1.170E+03 2.160E+03 9.950E+02 5.070E+04 3.300E+03 0.000E+00 9.550E+02 I-135 4.920E+03 8.730E+03 4.140E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 CS-134 6.510E+05 1.010E+06 2.250E+05 0.000E+00 3.300E+05 1.210E+05 3.850E+03 CS-136 6.510E+04 1.710E+0! 1.160E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 , CS-137 9.070E+05 8.250E+05 1.280E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 CS-138 6.330E+02 8.400E+02 5.550E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 BA-139 1.840E+00 9.840E-04 5.370E-02 0.000E+00 8.620E-04 5.770E+03 5.770E+04 BA-140 7.400E+04 6.480E+01 4.330E+03 0.000E+00 2.110E+01 1.740E+06 1.020E+05 BA-141 1.960E-01 1.090E-04 6.360E-03 0.000E+00 9.470E-05 2.920E+03 2.750E+02 BA-142 5.000E-02 3.600E-05 2.790E-03 0.000E+00 2.910E-05 1.640E+03 2.740E+00 LA-140 6.440E+02 2.250E+02 7.550E+01 0.000E+00 0.000E+00 1.830E+05 2.260E+05 LA-142 1.300E+00 4.110E-01 1.290E-01 0.000E+00 0.000E+00 B.700E+03 7.590E+04 CE-141 3.920E+04 1.950E+04 2.900E+03 0.000E+00 B.550E+03 5.440E+05 5.660E+04 CE-143 3.660E+02 1.990E+02 2.870E+01 0.000E+00 8.360E+01 1.150E+05 1.270E+05 CE-144 6.770E+06 2.120E+06 3.610E+05 0.000E+00 1.170E+06 1.200E+07 3.890E+05 I PR-143 1.850E+04 5.550E+03 9.140E+02 0.000E+00 3.000E+03 4.330E+05 9.730E+04 l PR-144 5.960E-02 1.850E-02 3.000E-03 0.000E+0D 9.770E-03 1.570E+03 1.970E+02 : ND-147 1.080E+04 8.730E+03 6.810E+02 0.000E+00 4.810E+03 3.280E+05 8.210E+04 W-187 1.630E+01 9.660E+00 4.330E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 NP-239 4.700E+02 3.340E+01 2.350E+01 0.000E400 9.730E+01 5.810E+04 6.400E+04 I I l
Offsite D0se C:lculation M:nual Page 266 cf 298 Revision 2 Change O ATTACHMENT 12 i INHALATION DOSE FACTORS INFANT (mrem /yr per uCi/m3) Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 6.47CE+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 C-14 2.650E+04 5 'J10E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 P-32 2.030E+06 1.120E+05 7.740E+04 0.000E+00 0.000E+00 0.000E+00 1.610E+04 CR-51 0.000E+00 0.000E+00 B.950E+01 5.750E+01 1.320E+01 1.280E+04 3.570E+02 MN-54 0.000E+00 2.530E+04 4.980E+03 0.000E+00 4.980E+03 1.000E+06 7.060E+03 MN-56 0.000E+00 1.540E+00 2.210E-01 0.000E+00 1.100E+00 1.250E+04 7.170E+04 FE-55 1.970E+04 1.170E+04 3.330E+03 0.000E+00 0.000E+00 B.690E+04 1.090E+03 FE-59 1.360E+04 2.350E+04 9.480E+03 0.000E+00 0.000E+00 1.020E+06 2.480E+04 CO-57 0.000E+00 6.510E+02 6.410E+02 0.000E+00 0.000E+00 3.790E+05 4.860E+03 CO-58 0.000E+00 1.020E+03 1.820E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 CO-60 0.000E+00 8.020E+03 1.180E+04 0.000E+00 0.000E+00 4.510E+06 3,190E+04 NI-63 3.390E+05 2.040E+04 1.160E+04 0.000E+00 0.000E+00 2.090E+05 2.420E+03 NI-65 2.390E+00 2.840E-01 1.230E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 CU-64 0.000E+00 1.880E+00 7.740E-01 0.000E+00 3.980E+00 9.300E+03 1.500E+04 ZN-65 1.930E+04 6.260E+04 3.110E+04 0.000E+00 3.250E+04 6.470E+05 5.140E+04 ZN-69 5.3 90E-02 9.670E-02 7.180E-03 0. 000E+00 4. 020E-02 1.470E+03 1.320E+04 BR-82 0.000E+00 0.000E+00 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 4.000E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 2.040E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.900E+05 8.820E+04 0.000E+00 0.000E+00 0.000E+00 3.040E+03 RB-88 0.000E+00 5.570E+02 2.870E+02 0.000E+00 0.000E+00 0.000E+00 3.390E+02 RB-89 0.000E+00 3.210E+02 2.060E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 SR-89 3.980F+05 0.000E+00 1.140E+04 0.000E+00 0.000E+00 2.030E+06 6.400E+04 SR-90 4.090E+07 0.000E+00 2.590E+06 0.000E+00 0.000E+00 1.120E+07 1.310E+05 SR-91 9.560E+01 0.000E+00 3.460E+00 0.000E+00 0.000E+00 5.260E+04 7.340E+04 SR-92 1.050E+01 0.000E+00 3.910E-01 0.000E+00 0.000E+00 2.380E+04 1.400E+05 Y-90 3.290E+03 0.000E+00 8.820E+01 0.000E+00 0.000E+00 2.690E+05 1.040E+05 Y-91M 4.070E-01 0.000E+00 1.390E-02 0.000E+00 0.000E+00 2.790E+03 2.350E+03 Y-91 5.880E+05 0.000E+00 1.570E+04 0.000E+00 0.000E+00 2.450E+06 7.030E+04 Y-92 1.640E+01 0.000E+00 4.610E-01 0.000E+00 0.000E+00 2.450E+04 1.270E+05 Y-93 1.500E+02 0.000E+00 4.070E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+05 ZR-95 1.150E+05 2.790E+04 2.030E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 ZR-97 1.500E+02 2.560E+01 1.170E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 NB-95 1.570E+04 6.430E+03 3.780E+03 0.000E+00 4.720E+03 4.790E+05 1.270E+04 NB-97 3.420E-01 7.290E-02 2.630E-02 0.000E+00 5.700E-02 3.320E+03 2.690E+04 MO-99 0.000E+00 1.650E+02 3.230E+01 0.000E+00 2.650E+02 1.350E+05 4.870E+04 TC-99M 1.400E-03 2.880E-03 3.720E-02 0.000E+00 3.110E-02 8.110E+02 2.030E+03 i TC-101 6.510E-05 8.230E-05 8.120E-04 0.000E+00 9.790E-04 5.840E+02 8.440E+02 RU-103 2.020E+03 0.000E+00 6.790E+02 0.000E+00 4.240E+03 5.520E+05 1.610E+04 RU-105 1.220E400 0.000E+00 4.100E-01 0.000E+00 8.990E-01 1.570E+04 4.840E+04 RU-106 8.680E+04 0.000E+00 1.090E+04 0.000E+00 1.070E+05 1.160E+07 1.640E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1
)
Offsit) Dose Criculation Manull. P ge 267 of 298 Revision 2 Change O ATTACHMENT 12 INHALATION DOSE FACTORS INFANT (mrem /yr per uCi/m3) l Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 9.980E+03 7.220E+03 5.000E+03 0.000E+00 1.090E+04 3.670E+06 3.300E+04 i SB-122 5.430E+02 7.200E+02 7.200E+03 1.880E+02 2.720E+02 2.930E+04 3.540E+04 SB-124 3.790E+04 5.560E+02 1.200E+04 1.010E+02 0.000E+00 2.650E+06 5.910E+04 - SB-125 5.170E+04 4.770E+02 1.090E+04 6.230E+01 0.000E+00 1.640E+06 1.470E+04 TE-125M 4.760E+03 1.990E+03 6.580E+02 1.620E+03 0.000E+00 4.470E+05 1.290E+04 TE-127M 1.670E+04 6.900E+03 2.070E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 TE-127 2.230E+00 9.530E 01 4.890E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 TE-129M 1.410E+04 6.090E+03 2.230E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 TE-229 7.880E-02 3.470E-02 1.880E-02 6.750E-02 1.750E-01 3.000E+03 2.630E+04 '
, TE-131M 1.070E+02 5.500E+01 3.630E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 TE-131 1.740E-02 8.220E-03 5.000E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 TE-132 3.720E+02 2.370E+02 1.760E+02 2.790E+02 1.030E+03 3.400E+05 4.410E+04 I-130 6.360E+03 1.390E+04 5.570E+03 1.600E+06 1.530E+04 0.000E+00 1.990E+03 I-131 3.790E+04 4.440E+04 1.960E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 ,
I-132 1.690E+03 3.540E+03 1.260E+03 1.690E+05 3.950E+03 0.000E400 1.900E+03 [ I-133 1.320E+04 1.920E+04 5.600E+03 3.560E+06 2.240E+04 0.000E+00 2.160E+03 ! I-134 9.210E+02 1.880E+03 6.650E+02 4.450E+04 2.090E+03 0.000E+00 1.290E+03 , I-135 3.860E+03 7.600E+03 2.770E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 , CS-134 3.960E+05 7.030E+05 7.450E+04 0.000E+00 1.900E+05 7.970E+04 1.330E+03 l CS-136 4 830E+04 1.350E+05 5.290E+04 0.000E+00 5.640E+04 1.180E+04 1.430E+03 ' CS-137 5.490E+05 6.120E+05 4.550E+04 0.000E+00 1.720E+05 7.130E+04 1.330E+03 j CS-138 5.050E+02 7.810E+02 3.980E.02 0.000E+00 4.100E+02 6.540E+01 8.760E+02 BA-139 1.480E+00 9.840E-04 4.300E-02 0.000E+00 5.920E-04 5.950E+03 5.100E+04 BA-140 5.600E+04 5.600E+01 2.900E+03 0.000E+00 1.340E+01 1.600E+06 3.840E+04 BA-141 1.570E-01 1.080E-04 4.970E-03 0.000E+00 6.500E-05 2.970E+03 4.750E+03 BA-142 3.980E-02 3.300E-05 1.960E-03 0.000E+00 1.900E-05 1.550E+03 6.930E+02 LA-140 5.050E+02 2.000E+02 5.150E+01 0.000E+00 0.000E+00 1.680E+05 8.480E+04 LA-142 1.030E+00 3.770E-01 9.040E-02 0.000E+00 0.000E+00 8.220E+03 5.950E+04 CE-141 2.770E+04 1.670E+04 1.990E+03 0.000E+00 5.250E+03 5.170E+05 2.160E+04 CE-143 2.930E+02 1.930E+02 2.210E+01 0.000E+00 5.640E+01 1.160E+05 4.970E+04 CE-144 3.190E+06 1.210E+06 1.760E+05 0.000E+00 5.380E+05 9.840E+06 1.480E+05 PR-143 1.400E+04 5.240E+03 6.990E+02 0.000E+00 1.970E+03 4.330E+05 3.720E+04 PR-144 4.790E-02 1.850E-02 2.410E-03 0.000E+00 6.720E-03 1.610E+03 4.280E+03 ' ND-147 7.940E+03 8.130E+03 5.000E+02 0.000E+00 3.150E+03 3.220E+05 3.120E+04 W-187 1.300E+01 9.020E+00 3.120E+00 0.000E+00 0.000E+00 3.960E+04 3.560E+04 : NP-239 3.710E+02 3.320E+01 1.880E+01 0.000E+00 6.620E+01 5.950E+04 2.490E+04 l ep -- e - -
l 1 Offsite Dose C:lculation M: null Page 268 of 298 l Revision 2 Change 0 1 1 ATTACHMENT 12 P GRASS-COW-MILK DOSE FACTORS ADULT (m2
- mrem /yr per uC1/sec)
Nuclide- Bone Liver Tbody Thyroid Kidney Lung Gitract H3 0.000E+00 7.630E+02 7,630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 ! C-14 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 P-32 1.710E+10 1.060E+09 6.600E+08 0.000E+00 0.000E+00 0.000r+00 1.920E+09 CR-51 0.000E+00 0.000E+00 2.860E+04 1.710E+04 6.300E+03 3.800E404 7.200E+06 MN-54 0.000E+00 8.400E+06 1.600E+06 0.000E+00 2.500E+06 0.000E+00 2.570E+07 ; MN-56 0.000E+00 4.230E-03 7.510E-04 0.000E+00 5.380E-03 0.000E+00 1.350E-01 FE-55 2.510E+07 1.730E+07 4.040E+06 0.000E+00 0.000E+00 9.670E+06 9.950E+06 FE-59 2.980E+07 7.000E+07 2.680E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 CO-57 0.000E+00 1.280E+06 2.130E+05 0.000E+00 0.000E+00 0.000E+00 3.250E+07 CO-58 0.000E+00 4.720E+06 1.060E+07 0.000E+00 0.000E+00 0.000E+00 9.570E+07 CO-60 0.000E+00 1.640E+07 3.620E+07 0.000E+00 0.000E+00 0.000E+00 3.080E+08 NI-63 6.730E+09 4.660E+0B 2.260E+08 0.000E+00 0.000E+00 0.000E+00 9.730E+07 NI-65 3.700E-01 4.810E-02 2.190E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 CU-64 0.000E+00 2.410E+04 1.130E+04 0.000E+00 6.080E+04 0.000E+00 2.050E+06 ZN-65 1.370E+09 4.360E+09 1.970E+09 0.000E+00 2.920E+09 0.000E+00 2.750E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.590E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 5.110E+08 : i RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 , SR-89 1.450E+09 0.000E+00 4.160E+07 0.000E+00 0.000E+00 0.000E+00 2.330E+08 SR-90 4.680E+10 0.000E+00 1.150E+10 0.000E+00 0.000E+00 0.000E+00 1.350E+09 SR-91 3.130E+04 0.000E+00 1.270E+03 0.000E+00 0.000E+00 0.000E+00 1.490E+05 SR-92 4.890E-01 0.000E+00 2.110E-02 0.000E+00 0.000E+00 0.000E+00 9.680E+00 Y-90 7.070E+01 0.000E+00 1.900E+00 0.000E+00 0.000E+00 0.000E+00 7.500E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.600E+03 0.000E+00 2.300E+02 0.000E+00 0.000E+00 0.000E+00 4.730E+06 Y-92 5.420E-05 0.000E+00 1.580E-06 0.000E+00 0.000E+00 0.000E+00 9.490E-01 Y-93 2.330E-01 0.000E+00 6.430E-03 0.000E+00 0.000E+00 0.000E+00 7.390E+03 ZR-95 9.460E+02 3.030E+02 2.050E+02 0.000E+00 4.760E+02 0.000E+00 9.620E+05 ZR-97 4.260E-01 8.590E-02 3.930E-02 0.000E+00 1.300E-01 0.000E+00 2.660E+04 NB-95 8.250E+04 4.590E+04 2.470E+04 0.000E+00 4.540E+04 0.000E+00 2.790E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-09 MO-99 0.000E+00 2.520E+07 4.800E+06 0.000E+00 5.720E+07 0.000E+00 5.850E+07 TC- 99M 3.250E+00 9.190E+00 1.170E+02 0.000E+00 1.400E+02 4.500E+00 5.440E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.020E+03 0.000E+00 4.390E+02 0.000E+00 3.890E+03 0.000E+00 1.190E+05 RU-105 8.570E-04 0.000E+00 3.380E-04 0.000E+00 1.110E-02 0.000E+00 5.240E-01 RU-106 2.040E+04 0.000E+00 2.580E+03 0.000E+00 3.940E+04 0.000E+00 1.320E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
Offsits Dose Cdcuttion Minuit Paga 269 of 298 Revision 2 Change 0 ATTACHMENT 12 , GRASS-COW-MILK DOSE FACTORS ADULT . (m2
- mrem /yr per uC1/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract f AG-110M 5.830E+07 5.390E+07 3.200E+07 0.000E+00 1.060E+08 0.000E+00 2.200E+10 SB-122 6.010E+05 6.270E+05 7.590E+06 9.960E+04 2.960E+05 1.290E+05 7.470E+07 ' SB-124 8.580E+08 1.620E+07 3.400E+08 2.080E+06 0.000E+00 6.680E+08 2.440E+10 SB-125 6.810E+08 7.610E+06 1.620E+08 6.930E+05 0.000E+00 5.250E+08 7.500E+09 TE-125M 1.630E+07 5.900E+06 2.180E+06 4.900E+06 6.630E+07 0.000E+00 6.500E+07 ! TE-127M 4.580E+07 1.640E+07 5.580E+06 1.170E+07 1.060E+08 0.000E+00 1.540E+08 ' TE-127 6.720E+02 2.410E+02 1.450E+02 4.980E+02 2.740E+03 0.000E+00 5.300E+04 TE-129M 6.040E+07 2.250E+07 9.570E+06 2.080E+07 2.520E+08 0.000E+00 3.040E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.610E+05 1.770E+05 1.470E+05 2.800E+05 1.790E+06 0.000E+00 1.750E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 . TE-132 2.390E+06 1.550E+06 1.450E+06 1.710E+06 1.490E+07 0.000E+00 7.320E+07 I-130 4.260E+05 1.260E+06 4.960E+05 1.070E+08 1.960E+06 0.000E+00 1.080E+06 [ I-131 2.960E+08 4.240E+08 2.430E+08 1.390E+11 7.270E+08 0.000E+00 1.120E+08 I-132 1.640E-01 4.370E-01 1.530E-01 1.530E+01 6.970E-01 0.000E+00 8.220E-02 I-133 3.970E+06 6.900E+06 2.100E+06 1.010E+09 1.200E+07 0.000E+00 6.200E+06 I-134 C.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I I-135 1.390E+04 3.630E+04 1.340E+04 2.400E+06 5.830E+04 0.000E+00 4.100E+04 CS-134 5.650E+09 1.340E+10 1.100E+10 0.000E+00 4.350E+09 1.440E+09 2.L50E+0B CS-136 2.610E+08 1.030E+09 7.420E+08 0.000E+00 5.740E+0B 7.870E+07 1.170E+08
- CS-137 7.380E+09 1.010E+10 6.610E+09 0.000E+00 3.430E+09 1.140E+09 1.950E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 4.700E-08 0.000E+00 1.380E-09 0.000E+00 0.000E+00 0.000E+00 8.340E-08 ,
BA-140 2.690E+07 3.380E+04 1.760E+06 0.000E+00 1.150E+04 1.930E+04 5.540E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.490E+00 2.260E+00 5.970E-01 0.000E+00 0.000E+00 0.000E+00 1.660E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E-08 CE-141 4.840E+03 3.270E+03 3.710E+02 0.000E+00 1.520E+03 0.000E+00 1.250E+07 CE-143 4.190E+01 3.090E+04 3.420E+00 0.000E+00 1.360E+01 0.000E+00 1.160E+06 CE-144 3.580E+05 1.500E+05 1.920E+04 0.000E+00 8.870E+04 0.000E+00 1.210E+08 PR-143 1.590E+02 6.370E+01 7.880E+00 0.000E+00 3.680E+01 0.000E+00 6.960E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 9.420E+01 1.090E+02 6.520E+00 0.000E+00 6.370E+01 0.000E+00 5.230E+05 W-187 6.560E+03 5.480E+03 1.920E+03 0.000E+00 0.000E+00 0.000E+00 1.800E+06 NP-239 3.660E+00 3.600E-01 1.980E-01 0.000E+00 1.120E+00 0.000E+00 7.390E+04 I l 1
Offsite Dose Calculation Manual Page 270 cf 298 Revision 2 Change 0 ATTACHMENT 12 GRASS-COW-MILK DOSE FACTORS TEEN (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 ; C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 P-32 3.150E+10 1.950E+09 1.220E+09 0.000E+00 0.000E+00 0.000E+00 2.650E+09 CR-51 0.000E+00 0.000E+00 5.000E+04 2.780E+04 1.100E+04 7.130E+04 8.400E+06 MN-54 0.000E+00 1.400E+07 2.780E+06 0.000E+00 4.170E+06 0.000E+00 2.870E+07 MN-56 0.000E+00 7.510E-03 1.330E-03 0.000E+00 9.500E-03 0.000E+00 4.940E-01 FE-55 4.450E+07 3.160E+07 7.360E+06 0.000E+00 0.000E+00 2.000E+07 1.370E+07 FE-59 5.200E+07 1.210E+0B 4.680E+07 0.000E+00 0.000E+00 3.820E+07 2.870E+08 CO-57 0.000E+00 2.250E+06 3.760E+06 0.000E+00 0.000E+00 0.000E+00 4.190E+07 CO-58 0.000E+00 7.950E+06 1.830E+07 0.000E+00 0.000E+00 0.000E+00 1.100E+08 CO-60 0.000E+00 2.780E+07 6.260E+07 0.000E+00 0.000E+00 0.000E+00 3.620E+08 NI-63 1.180E+10 8.350E+08 4.010E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+08 NI-65 6.780E-01 8.660E-02 3.940E-02 0.000E+00 0.000E+00 0.000E+00 4.700E+00 CU-64 0.000E+00 4.290E+04 2.020E+04 0.000E400 1.090E+05 0.000E+00 3.330E+06 ZN-65 2.110E+09 7.310E+09 3.410E+09 0.000E+00 4.680E+09 0.000E+00 3.100E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.0008+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.730E+09 2.220E+09 0.000E+00 0.000E+00 0.000E+00 7.000E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.670E+09 0.000E+00 7.660E+07 0.000E+00 0.000E+00 0.000E+00 3.180E+08 SR-90 6.610E+10 0.000E+00 1.630E+10 0.000E+00 0.000E+00 0.000E+00 1.860E+09 SR-91 5.750E+04 0.000E+00 2.290E+03 0.000E+00 0.000E+00 0.000E+00 2.610E+05 SR-92 8.950E-01 0.000E+00 3.810E-02 0.000E+00 0.000E+00 0.000E+00 2.280E+01 Y-90 1.300E+02 0.000E+00 3.500E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+06 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.580E+04 0.000E+00 4.240E+02 0.000E+00 0.000E+00 0.000E+00 6.480E+06 Y-92 1.000E-04 0.000E+00 2.900E-06 0.000E+00 0.000E+00 0.000E+00 2.750E+00 Y-93 4.300E-01 0.000E+00 1.180E-02 0.000E+00 0.000E+00 0.000E+00 1.310E+04 ER-95 1.650E+03 5.220E+02 3.590E+02 0.000E+00 7.670E+02 0.000E+00 1.200E+06 ZR-97 7.750E-01 1.530E-01 7.060E-02 0.000E+00 2.320E-01 0.000E+00 4.150E+04 ' NB-95 1.410E+05 7.80C1+04 4.300E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.340E-0B MO-99 0.000E+00 4.560E+07 8.690E+06 0.000E+00 1.040E+08 0.000E+00 B.160E+07 TC-99M 5.640E+00 1.570E+01 2.040E+02 0.000E+00 2.340E+02 8.730E+00 1.030E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.810E+03 0.000E+00 7.750E+02 0.000E+00 6.400E+03 0.000E+00 1.520E+05 RU-105 1.570E-03 0.000E+00 6.080E-04 0.000E+00 1.970E-02 0.000E+00 1.260E+00 RU-106 3.750E+04 0.000E+00 4.730E+03 0.000E+00 7.230E+04 0.000E+00 1.800E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
L Offsite Dose Calculaton M:nu::1 Page 271 of 298 Revision 2 Change 0 - ATTACHMENT 12 GRASS-COW-MILK DOSE FACTORS TEEN (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 9.630E+07 9.110E+07 5.540E+07 0.000E+00 1.740E+08 0.000E+00 2.560E+10 i SB-122 7.760E+05 8.090E+05 9.800E+06 1.290E+05 3.820E+05 1.660E+05 9.640E+07 I SB-124 1.530E+09 2.820E+07 5.970E+08 3.470E+06 0.000E+00 1.340E+09 3.080E+10 SB-125 1.220E+09 1.330E+07 2.850E+08 1.160E+06 0.000E+00 1.070E+09 9.480E+09 TE-125M 3.000E+07 1.000E+07 4.020E+06 8.390E+06 0.000E+00 0.000E+00 8.860E+07 TE-127M 8.440E+07 2.990E+07 1.000E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 TE-127 1.240E+03 4.410E+02 2.680E+02 8.590E+02 5.040E+03 0.000E+00 9.610E+04 TE-129M 1.110E+08 4.100E+07 1.750E+07 3.570E+07 4.620E+08 0.000E+00 4.150E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E-09 0.000E+00 2.180E-09 TE-131M 6.570E+05 3.150E+05 2.630E+05 4.740E+05 3.290E+06 0.000E+00 2.530E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 4.280E+06 2.710E+06 2.550E+06 2.860E+06 2.600E+07 0.000E+00 8.580E+07 I-130 7.490E+05 2.170E+06 8.660E+05 1.770E+08 3.340E+06 0.000E+00 1.670E+06 I-131 5.380E+08 7.530E+08 4.040E+08 2.200E+11 1.300E+09 0.000E+00 1.490E+08 I-132 2.900E-01 7.590E-01 2.720E-01 2.560E+01 1.200E+00 0.000E+00 3.310E-01 I-133 7.240E+06 1 230E+07 3.750E+06 1.720E+09 2.150E+07 0.000E+00 9.300E+06 1 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 2.470E+04 6.350E+04 2.350E+04 4.080E+06 1.000E+05 0.000E+00 7.030E+04 CS-134 9.810E+09 2.310E+10 1.070E+10 0.000E+00 7.340E+09 2.800E+09 2.870E+08 CS-136 4.450E+0B 1.750E+09 1.180E+09 0.000E+00 9.530E+08 1.500E+08 1.410E+08 CS-137 1.340E+10 1.780E+10 6.200E+09 0.000E+00 6.060E+09 2.350E+09 2.530E+0B CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 8.690E-08 0.000E+00 2.530E-09 0.000E+00 0.000E+00 0.000E+00 7.750E-07 BA-140 4.850E+07 5.950E+04 3.130E+06 0.000E+00 2.020E+04 4.000E+04 7.490E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 8.060E+00 3.960E+00 1.050E+00 0.000E+00 0.000E+00 0.000E+00 2.270E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.230E-07 CE-141 8.870E+03 5.920E+03 6.810E+02 0.000E+00 2.790E+03 0.000E+00 1.690E+07 CE-143 7.690E+01 5.600E+04 6.250E+00 0.000E+00 2.510E+01 0.000E+00 1.680E+06 CE-144 6.580E+05 2.720E+05 3.540E+04 0.000E+00 1.630E+05 0.000E+00 1.660E+08 PR-143 2.920E+02 1.170E+02 1.450E+01 0.000E+00 6.770E+01 0.000E+00 9.610E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.810E+02 1.970E+02 1.180E+01 0.000E+00 1.160E+02 0.000E+00 7.110E+05 W-lbi 1.200E+04 9.780E+03 3.430E+03 0.000E+00 0.000E+00 0.000E+00 2.650E+06 NP-239 6.990E+00 6.590E-01 3.660E-01 0.000E+00 2.070E+00 0.000E+00 1.060E+05 1
Offsite Dose Cdculation M: null Pag 2 272 of 298 Revision 2 Change O ATLACtHAENT 12 ) i J GRASS-COW-MILK DOSE FACTORS CHILD l (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 P-32 7.770E+10 3.640E+09 3.000E+09 0.000E+00 0.000E+00 0.000E+00 2.150E+09 CR-51 0.000E+00 0.000E+00 1.020E+05 S.660E+04 1.550E+04 1.030E+05 5.410E+06 MN-54 0.000E+00 2.090E+07 5.580E+06 0.000E+00 5.870E+06 0.000E+00 1.760E+07 ' MN-56 0.000E+00 1.310E-02 2.950E-03 0.000E+00 1.580E-02 0.000E+00 1.900E+00 FE-55 1.120E+08 5.930E+07 1.840E+07 0.000E+00 0.000E+00 3.350E+07 1.100E+07 FE-59 1.200E+08 1.950E+08 9.710E+07 0.000E+00 0.000E+00 5.650E+07 2.030E+08 CO-57 0.000E+00 3.840E+06 7.770E+06 0.000E+00 0.000E+00 0.000E+00 3.140E+07 CO-58 0.000E+00 1.210E+07 3.720E+07 0.000E+00 0.000E+00 0.000E+00 7.080E+07 Co-60 0.000E+00 4.320E+07 1.270E+08 0.000E+00 0.000E+00 0.000E+00 2.390E+08 ; NI-63 2.960E+10 1.590E+09 1.010E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 1.660E+00 1.560E-01 9.110E-02 0.000E+00 0.000E+00 0.000E+00 1.910E+01 - CU-64 0.000E+00 7.550E+04 4.560E+04 0.000E+00 1.820E+05 0.000E+00 3.540E+06 ZN-65 4.130E+09 1.100E+10 6.850E+09 0.000E+00 6.940E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.140E-09 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
- BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 8.770E+09 5.390E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 6.620E+09 0.000E+00 1.890E+08 0.000E+00 0.000E+00 0.000E+00 2.560E+08 SR-90 1.120E+11 0.000E+00 2.830E+10 0.000E+00 0.000E+00 0.000E+00 1.510E+09 SR-91 1.410E+05 0.000E+00 5.330E+03 0.000E+00 0.000E+00 0.000E+00 3.120E+05 SR-92 2.190E+00 0.000E+00 8.760E-02 0.000E+00 0.000E+00 0.000E+00 4.140E+01 Y-90 3.220E+02 0.000E+00 8.610E+00 0.000E+00 0.000E+00 0.000E+00 9.150E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 3.910E+04 0.000E+00 1.040E+03 0.000E+00 0.000E+00 0.000E+00 5.210E+06 '
Y-92 2.460E-04 0.000E+00 7.030E-06 0.000E+00 0.000E+00 0.000E+00 7.100E+00 Y-93 1.060E+00 0.000E+00 2.900E-02 0.000E+00 0.000E+00 0.000E+00 1.570E+04 ZR-95 3.840E+03 8.450E+02 7.520E+02 0.000E+00 1.210E+03 0.000E+00 B.810E+05 ZR-97 1.890E+00 2.720E-01 1.610E-01 0.000E+00 3.910E-01 0.000E+00 4.130E+04 - NB-95 3.180E+05 1.240E+05 8.840E+04 0.000E+00 1.160E+05 0.000E+00 2.290E+08 ; NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E-06 MO-99 0.000E+00 8.290E+07 2.050E+07 0.000E+00 1.770E+08 0.000E+00 6.860E+07 l TC-99M 1.290E+01 2.540E+01 4.200E+02 0.000E+00 3.680E+02 1.290E+01 1.440E+04 i TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-203 4.290E+03 0.000E+00 1.650E+03 0.000E+00 1.080E+04 0.000E+00 1.110E+05 ; RU-105 3.820E-03 0.000E+00 1.390E-03 0.000E+00 3.360E-02 0.000E+00 2.490E+00 RU-106 9.240E+04 0.000E+00 1.150E+04 0.000E+00 1.250E+05 0.000E+00 1.440E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
Offsite Dose C:lculation Minu:1 Page 273 Of 298 Revision 2 Change 0 ATTACHMENT 12 GRASS-COW-MILK DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 2.090E+08 1.410E+08 1.130E+08 0.000E+00 2.630E+08 0.000E+00 1.680E+10 SB-122 4.140E+06 4.320E+06 5.230E+07 6.870E+05 2.040E+06 8.890E+05 5.150E+08 SB-124 3.620E+09 4.700E+07 1.270E+09 7.990E+06 0.000E+00 2.010E+09 2.260E+10 SB-125 2.900E+09 2.240E+07 6.080E+08 2.690E+06 0.000E+00 1.620E+09 6.930E+09 TE-125M 7.380E+07 2.000E+07 9.840E+06 2.070E+07 0.000E+00 0.000E+00 7.120E+07 TE-127M 2.000E+0B 5.600E+07 2.470E+07 4.970E+07 5.930E+0B 0.000E+00 1.680E+08 TE-127 3.060E+03 8.250E+02 6.560E+02 2.120E+03 8.710E+03 0.000E+00 1.200E+05 TE-129M 2.720E+08 7.610E+07 4.230E+07 8.780E+07 8.000E+0B 0.000E+00 3.320E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.870E-09 0.000E+00 6.120E-08 TE-131M 1.600E+06 5.530E+05 5.890E+05 1.140E+06 5.350E+06 0.000E+00 2.240E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.020E+07 4.520E+06 5.460E+06 6.580E+06 4.200E+07 0.000E+00 4.550E+07 I-130 1.750E+06 3 540E+06 1.820E+06 3.900E+08 5.290E+06 0.000E+00 1.660E+06 I-131 1.300E+09 1.310E+09 7.460E+08 4.340E+11 2.150E+09 0.000E+00 1.170E+08 I-132 6.860E-01 1.260E+00 5.800E-01 5.850E+01 1.930E+00 0.000E+00 1.480E+00 I-133 1.760E+07 2.180E+07 8.230E+06 4.040E+09 3.630E+07 0.000E+00 B 770E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 5.840E+04 1.050E+05 4.970E+04 9.300E+06 1.610E+05 0.000E+00 8.000E+04 CS-134 2.260E+10 3.710E+10 7.830E+09 0.000E+00 1.150E+10 4.130E+09 2.000E+08 CS-136 1.000E+09 2.760E+09 1.790E+09 0.000E+00 1.470E+09 2.190E+08 9.700E+07 CS-137 3.220E+10 3.090E+10 4.550E+09 0.000E+00 1.010E+10 3.620E+09 1.930E+0B CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 2.140E-07 0.000E+00 6.190E-09 0.000E+00 0.000E+00 0.000E+00 1.230E-05 , BA-140 1.170E+08 1.030E+05 6.840E+06 0.000E+00 3.340E+04 6.120E+04 5.940E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.930E+01 6.740E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.880E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.510E-06 CE-141 2.190E+04 1.090E+04 1.620E+03 0.000E,00 4.780E+03 0.000E+00 1.360E+07 CE-143 1.890E+02 1.020E+05 1.480E+01 0.000E+00 4.290E+01 0.000E+00 1.500E+06 CE-144 1.620E+06 5.090E+05 8.660E+04 0.000E+00 2.820E+05 0.000E+00 1.330E+0S PR-143 7.230E+02 2.170E+02 3.590E+01 0.000E+00 1.170E+02 0.000E+00 7.800E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 4.450E+02 3.600E+02 2.790E+01 0.000E+00 1.980E+02 0.000E+00 5.710E+05 W-187 2.910E+04 1.720E+04 7.730E+03 0.000E+00 0.000E+00 0.000E+00 2.420E+06 NP-239 1.720E+01 1.230E+00 B.680E-01 0.000E+00 3.570E+00 0.000E+00 9.140E+04
Offsite D0se Cciculation Manual Page 274 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-COW-MILK DOSE FACTORS INFANT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 C-14 3,230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 P-32 1.600E+11 9.420E+09 6.210E+09 0.000E+00 0.000E+00 0.000E+00 2.170E+09 CR-51 0.000E+00 0.000E+00 1.610E+05 1.050E+05 2.300E+04 2.050E+05 4.710E+06 MN-54 0.000E+00 3.890E+07 8.830E+06 0.000E+00 8.630E+06 0.000E+00 1.430E+07 MN-56 0.000E+00 3.210E-02 5.530E-03 0.000E+00 2.760E-02 0.000E+00 2.910E+00 < FE-55 1.350E+08 8.720E+07 2.330E+07 0.000E+00 0.000E+00 4.270E+07 1.110E+07 l FE-59 2.250E+08 3.930E+0B 1.550E+08 0.000E+00 0.000E+00 1.160E+08 1.880E+0B CO-57 0.000E+00 8.950E+06 1.460E+07 0.000E+00 0.000E+00 0.000E+00 3.050E+07 CO-58 0.000E+00 2.430E+07 6.060E+07 0.000E+00 0.000E+00 0.000E+00 6.050E+07 CO-f0 0.000E+00 8.010E+07 2.080E+0B 0.000E+00 0.000E+00 0.000E+00 2.100E+08 NI-63 3.490E+10 2.160E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 3.510E+00 3.970E-01 1.810E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 CU-64 0.000E+00 1.880E+05 8.690E+04 0.000E+00 3.170E+05 0.000E+00 3.850E+06 ZN-65 5.550E+09 1.900E+10 8.780E+09 0.000E+00 9.230E+09 0.000E+00 1.610E+10 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.360E-09 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 RB-86 0.000E+00 2.220E+10 1.100E+10 0.000E+00 0.000E+00 0.000E+00 5.690E+08 j f 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-88 ! RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I SR-89 1.260E+10 0.000E+00 3.610E+0B 0.000E+00 0.000E+00 0.000E+00 2.590E+08 SR-90 1.220E+11 0.000E+00 3.100E+10 0.000E+00 0.000E+00 0.000E+00 1.520E+09 SR-91 2.940E+05 0.000E+00 1.060E+04 0.000E+00 0.000E+00 0.000E+00 3.480E+05 SR-92 4.650E+00 0.000E+00 1.730E-01 0.000E+00 0.000E+00 0.000E+00 5.010E+01 Y-90 6.800E+02 0.000E+00 1.820E+01 0.000E+00 0.000E+00 0.000E+00 9.390E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 7.330E+04 0.000E+00 1.950E+03 0.000E+00 0.000E+00 0.000E+00 5.260E+06 Y-92 5.220E-04 0.000E+00 1.470E-05 0.000F+00 0.000E+00 0.000E+00 9.970E+00 Y-93 2.250E+00 0.000E+00 6.130E-02 0.000E+00 0.000E+00 0.000E+00 1.780E+04 ZR-95 6.830E+03 1.660E+03 1.180E+03 0.000E+00 1.790E+03 0.000E+00 8.280E+05 ZR-97 3.990E+00 6.850E-01 3.130E-01 0.000E+00 6.910E-01 0.000E+00 4.370E+04 NB-95 5.930E+05 2.440E+05 1.410E+05 0.000E+00 1.750E+05 0.000E+00 2.060E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.700E-06 MO-99 0.000E+00 2.120E+08 4.130E+07 0.000E+00 3.170E+08 0.000E+00 6.980E+07 TC-99M 2.690E+01 5.550E+01 7.150E+02 0.000E+00 5.970E+02 2.900E+01 1.610E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 8.690E+03 0.000E+00 2.910E+03 0.000E+00 1.810E+04 0.000E+00 1.060E+05 RU-105 8.060E-03 0.000E+00 2.710E-03 0.000E+00 5.920E-02 0.000E+00 3.210E+00 RJ-106 1.900E+05 0.000E+00 2.380E+04 0.000E+00 2.250E+05 0.000E+00 1.440E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
i Offsita Dose C:lcul tion M*nurl Page 275 of 298 Revision 2 Change 0 ATTACHMENT 12 - GRASS-COW-MILK DOSE FACTORS INFANT (m2
- mrem /yr per uCi/sec) i Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract .
i AG-110M 3.860E+08 2.820E+08 1.860E+08 0.000E+00 4.030E+0B 0.000E+00 1.460E+10 SB-122 6.400E+05 6.670E+05 8.080E+06 1.060E+05 3.150E+05 1.370E+05 7.950E+07 j SB-124 6.980E+09 1.030E+08 2.160E+09 1.850E+07 0.000E+00 4.370E+09 2.150E+10 SB-125 4.980E+09 4.820E+07 1.020E+09 6.240E+06 0.000E+00 3.130E+09 6.640E+09 ! TE-125M 1.510E+08 5.040E+07 2.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 i TE-127M 4.210E+08 1.400E+08 5.100E+07 1.220E+08 1.040E+09 0.000E+00 1.700E+08 i TE-127 6.500E+03 2.180E+03 1.400E+03 5.290E+03 1.590E+04 0.000E+00 1.360E+05 TE-129M 5.590E+0B 1.920E+08 8.620E+07 2.150E+0B 1.400E+09 0.000E+00 3.340E+08 TE-129 2.080E-09 0.000E+00 0.000E+00 1.750E-09 5.180E-09 0.000E+00 1.660E-07 TE-131M 3.300E+06 1.360E+06 1.120E+06 2.760E+06 9.350E+06 0.000E+00 2.290E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.100E+07 1.040E+07 9.720E+06 1.540E+07 6.510E+07 0.000E+00 3.850E+07 I-130 3.600E+06 7.920E+06 3.180E+06 8.880E+08 8.700E+06 0.000E+00 1.700E+06 I-131 2.720E+09 3.210E+09 1.410E+09 1.050E+12 3.750E+09 0.000E+00 1.150E+08 , I-132 1.420E+00 2.890E+00 1.030E+00 1.350E+02 3.220E+00 0.000E+00 2.340E+00 I-133 3.720E+07 5.410E+07 1.580E+07 9.840E+09 6.360E+07 0.000E+00 9.160E+06 I-134 0.000E+00 0.000E+00 0.000E+00 1.010E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.210E+05 2.410E+05 8.800E+04 2.160E+07 2.690E+05 0.000E+00 8.740E+04 CS-134 3.650E+10 6.800E+10 6.870E+09 0.000E+00 1.750E+10 7.180E+09 1.850E+0B CS-136 1.960E+09 5.770E+09 2.150E+09 0.000E+00 2.300E+09 4.700E+08 8.760E+07 CS-137 5.150E+10 6.020E+10 4.270E+09 0.000E+00 1.620E+10 6.550E+09 1.880E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 4.550E-07 0.000E+00 1.320E-08 0.000E+00 0.000E+00 0.000E+00 2.880E-05 i BA-140 2.410E+08 2.410E+05 1.240E+07 0.000E+00 5.730E+04 1.480E+05 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 I LA-140 4.030E+01 1.590E+01 4.090E+00 0.000E+00 0.000E+00 0.000E+00 1.870E+05 LA-142 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.210E-06 CE-141 4.330E+04 2.640E+04 3.110E+03 0.000E+00 8.150E+03 0.000E+00 1.370E+07 CE-143 4.000E+02 2.650E+05 3.020E+01 0.000E+00 7.720E+01 0.000E+00 1.550E+06 i CE-144 2.330E+06 9.520E+05 1.300E+05 0.000E+00 3.850E+05 0.000E+00 1.330E+08 PR-143 1.490E+03 5.590E+02 7.410E+01 0.000E+00 2.0BOE+02 0.000E+00 7.890E+05 I PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 8.820E+02 9.060E+02 5.550E+01 0.000E+00 3.490E+02 0.000E+00 5.740E+05 W-187 6.120E+04 4.260E+04 1.470E+04 0.000E+00 0.000E+00 0.000E+00 2.500E+06 NP-239 3.640E+01 3.250E+00 1.840E+00 0.000E+00 6.490E+00 0 000E+00 9.400E+04 l l 1 l l l
N 1 Offsite Dose Cdcul tion Minull Paga 276 Of 298 Revision 2 Change 0 ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 C-14 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 P-32 2.050E+10 1.270E+09 7.930E+0B 0.000E+00 0.000E+00 0.000E+00 2.310E+09 CR-51 0.000E+00 0.000E+00 3.430E+03 2.050E+03 7.560E+02 4.560E+03 8.640E+05 MN-54 0.000E+00 1.010E+06 1.920E+05 0.000E+00 3.000E+05 0.000E+00 3.090E+06 MN-56 0.000E+00 5.080E-04 9.010E-05 0.000E+00 6.450E-04 0.000E+00 1.620E-02 FE-55 3.260E+05 2.250E+05 5.260E+04 0.000E+00 0.000E+00 1.260E+05 1.290E+05 FE-59 3.870E+05 9.090E+05 3.490E+05 0.000E+00 0.000E+00 2.540E403 3.030E+06 CO-57 0.000E+00 1.540E+05 2.550E+05 0.000E+00 0.000E+00 0.000E+C0 3.900E+06 CO-58 0.000E+00 5.660E+05 1.270E+06 0.000E+00 0.000E+00 0.000E+00 1.150E+07 CO-60 0.000E+00 1.970E+06 4.340E+06 0.000E+00 0.000E+00 0.000E+00 3.700E+07 NI-63 8.070E+08 5.600E+07 2.710E+07 0.000E+00 0.000E+00 0.000E+00 1.170E+07 NI-65 4.440E-02 5.770E-03 2.630E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 CU-64 0.000E+00 2.690E+03 1.260E+03 0.000E+00 6.770E+03 0.000E+00 2.290E+05 ZN-65 1.650E+08 5.240E+08 2.370E+08 0.000E+00 3.500E+08 0.000E+00 3.300E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 3.900E+06 0.000E+00 0.000E+00 0.000E+00 4.470E+06 BR-83 0.000E+00 0.000E+00 1.240E-02 0.000E+00 0.000E+00 0.000E+00 1.790E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 3.110E+08 1.450E+08 0.000E+00 0.000E+00 0.000E+00 6.140E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.050E+09 0.000E+00 8.740E+07 0.000E+00 0.000E+00 0.000E+00 4.890E+08 SR-90 9.830E+10 0.000E+00 2.410E+10 0.000E+00 0.000E+00 0.000E+00 2.840E+09 SR-91 6.580E+04 0.000E+00 2.660E+03 0.000E+00 0.000E+00 0.000E+00 3.130E+05 SR-92 1.030E+00 0.000E+00 4.440E-02 0.000E+00 0.000E+00 0.000E+00 2.030E+01 Y-90 8.480E+00 0.000E+00 2.280E-01 0.000E+00 0.000E+00 0.000E+00 8.990E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0005+00 0.000E+00 0.000E+00 Y-91 1.030E+03 0.000E+00 2.760E+01 0.000E+00 0.000E+00 0.000E+00 5.680E+05 Y-92 6.510E-06 0.000E+00 1.900E-07 0.000E+00 0.000E+00 0.000E+00 1.140E-01 Y-93 2.800E-02 0.000E+00 7.720E-04 0.000E+00 0.000E+00 0.000E+00 8.870E+02 ZR-95 1.140E+02 3.640E+01 2.470E+01 0.000E+00 5.710E+01 0.000E+00 1.150E+05 ZR-97 5.110E-02 1.030E-02 4.710E-03 0.000E+00 1.560E-02 0.000E+00 3.190E+03 NB-95 9.900E+03 5.510E+03 2.960E+03 0.000E+00 5.440E+03 0.000E+00 3.340E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 3.030E+06 5.760E+05 0.000E+00 6.860E+06 0.000E+00 7.020E+06 , TC-99M 3.900E-01 1.100E+00 1.400E+01 0.000E+00 1.670E+01 5.400E-01 6.520E+02 ) TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.220E+02 0.000E+00 5.270E+01 0.000E+00 4.670E+02 0.000E+00 1.430E+04 RU-105 1.030E-04 0.000E+00 4.060E-05 0.000E+00 1.330E-03 0.000E+00 6.290E-02 RU-106 2.450E+03 0.000E+00 3.100E+02 0.000E+00 4.730E+03 0.000E+00 1.580E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
Y Offsite Dose Cilculation Minuil Paga 277 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS ADULT (m2
- mrem /yr per uCi/sec)
Nuclide Bone- Liver Tbody Thyroid Kidney Lung Gitract AG-110M 6.990E+06 6.470E+06 3.840E+06 0.000E+00 1.270E+07 0.000E+00 2.640E+09 SB-122 7.210E+04 7.520E+04 9.110E+05 1.200E+04 3.550E+04 1.550E+04 8.960E+06 SB-124 3.090E+06 5.840E+04 1.220E+06 7.490E+03 0.000E+00 2.410E+06 8.770E+07 SB-125 2.450E+06 2.740E+04 5.840E+05 2.490E+03 0.000E+00 1.890E+06 2.700E+07 TE-125M 1.950E+06 7.080E+05 2.620E+05 5.880E+05 7.950E+06 0.000E+00 7.810E+06 TE-127M S.490E+06 1.960E+06 6.690E+05 1.400E+06 2.230E+07 0.000E+00 1.840E+07 TE-127 8.060E+01 2.890E+01 1.740E+01 5.970E+01 3.280E+02 0.000E+00 6.360E+03 TE-129M 7.250E+06 2.710E+06 1.150E+06 2.490E+06 3.030E+07 0.000E+00 3.650E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.330E+04 2.120E+04 1.770E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.870E+05 1.860E+05 1.740E+05 2.050E+05 1.790E+06 0.000E+00 8.790E+06 I-130 5.110E+05 1.510E+06 5.950E+05 1.280E+08 2.350E+06 0.000E+00 1.300E+06 I-131 3.560E+08 5.090E+08 2.920E+08 1.670E+11 8.720E+08 0.000E+00 1.340E+08 I-132 1.960E-01 5.250E-01 1.840E-01 1.840E+01 8.360E-01 0.000E+00 9.860E-02 I-133 4.760E+06 8.280E+06 2.520E+06 1.220E+09 1.440E+07 0.000E+00 7.440E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 1.670E+04 4.360E+04 1.610E+04 2.880E+06 6.990E+04 0.000E+00 4.920E+04 CS-134 1.700E+10 4.030E+10 3.300E+10 0.000E+00 1.310E+10 4.330E+09 7.060E+08 CS-136 7.840E+08 3.090E+09 2.230E+09 0.000E+00 1.720E+09 2.360E+08 3.520E+08 CS-137 2.210E+10 3.030E+10 1.980E+10 0.000E+00 1.030E+10 3.420E+09 5.860E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 5.640E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-08 i BA-140 3.230E+06 4.050E+03 2.110E+05 0.000E+00 1.380E+03 2.320E+03 6.650E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.380E-01 2.710E-01 1.990E+04 0.000E+00 0.000E+00 0.000E+00 1.990E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.640E-09 CE-141 5.810E+02 3.930E+02 4.450E+01 0.000E+00 1.820E+02 0.000E+00 1.500E+06 CE-143 5.020E+00 3.710E+03 4.110E-01 0.000E+00 1.630E+00 0.000E+00 1.390E+05 CE-144 4.290E+04 1.790E+04 2.300E+03 0.000E+00 1.060E+04 0.000E+00 1.450E+07 PR-143 1.910E+01 7.650E+00 9.450E-01 0.000E+00 4.410E+00 0.000E+00 8.350E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.130E+01 1.310E+01 7.820E-01 0.000E+00 7.640E+00 0.000E+00 6.270E+04 W-187 7.870E+02 6.580Et02 2.300E+02 0.000E+00 0.000E+00 0.000E+00 2.160E+05 NP-239 4.390E-01 4.320E-02 2.380E-02 0.000E+00 1.350E-01 0.000E+00 8.860E+03
F 'v : Offsite Dose Cilculation M: null Pag 3 278 of 298 Revision 2 Change 0
/VFIACHMENT 12 <
GRASS-GOAT-MILK DOSE FACTORS TEEN (m2
- mrem /yr per uci/sec) ,
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 P-32 3.780E+10 2.340E+09 1.470E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 CR-51 0.000E+00 0.000E+00 6.000E+03 3.330E+03 1.310E+03 8.560E+03 1.010E+06 MN-54 0.000E+00 1.680E+06 3.330E+05 0.000E+00 5.010E+05 0.000E+00 3.440E+06 ' MN-56 0.000E+00 9.010E-04 1.600E-04 0.000E+00 1.140E-03 0.000E+00 5.930E-02 FE-55 5.790E+05 4.100E+05 9.570E+04 0.000E+00 0.000E+00 2.600E+05 1.780E+05 FE-59 6.750E+05 1.580E+06 6.090E+05 0.000E+00 0.000E+00 4.970E+05 3.730E+06 CO-57 0.000E+00 2.690E+05 4.520E+05 0.000E+00 0.000E+00 0.000E+00 5.030E+06 CO-58 0.000E+00 9.540E+05 2.200E+06 0.000E+00 0.000E+00 0.000E+00 1.310E+07 CO-60 0.000E+00 3.340E+06 7.510E+06 0.000E+00 0.000E+00 0.000E+00 4.350E+07 NI-63 1.420E+09 1.000E+08 4.810E+07 0.000E+00 0.000E+00 0.000E+00 1.590E+07 ]
~
NI-65 0.130E-02 1.040E-02 4.730E-03 0.000E+00 0.000E+00 0.000E+00 5.640E-01 CU-64 0.000E+00 4.790E+03 2.250E+03 0.000E+00 1.210E+04 0.000E+00 3.710E+05 ZN-65 2.530E+08 8.780E+08 4.090E+08 0.000E+00 5.620E+08 0.000E+00 3.720E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 6.670E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 2.290E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E+08 2.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 5.620E+09 0.000E+00 1.160E+08 0.000E+00 0.000E+00 0.000E+00 6.690E+08 SR-90 1.390E+11 0.000E+00 3.430E+11 0.000E+00 0.000E+00 0.000E+00 3.900E+09 SR-91 1.210E+05 0.000E+00 4.810E+03 0.000E+00 0.000E+00 0.000E+00 5.480E+05 ; SR-92 1.880E+00 0.000E+00 8.010E-02 0.000E+00 0.000E+00 0.000E+00 4.790E+01 Y-90 1.560E+01 0.000E+00 4.200E-01 0.000E+00 0.000E+00 0.000E+00 1.290E+05 i Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i Y-91 1.900E+03 0.000E+00 5.090E+01 0.000E400 0.000E+00 0.000E+00 7.780E+05 Y-92 1.200E-05 0.000E+00 3.480E-07 0.000E+00 0.000E+00 0.000E+00 3.300E-01 l Y-93 5.160E-02 0.000E+00 1.410E-03 0.000E+00 0.000E+00 0.000E+00 1.580E+03 l ZR-95 1.990E+02 6.260E+01 4.310E+01 0.000E+00 9.200E+01 0.000E+00 1.450E+05 ZR-97 9.300E-02 1.840E-02 8.480E-03 0.000E+00 2.790E-02 0.000E+00 4.980E+03 , l NB-95 1.690E+04 9.370E+03 5.160E+03 0.000E+00 9.080E+03 0.000E+00 4.010E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.610E-09 MO-99 0.000E+00 5.470E+06 1.040E+06 0.000E+00 1.250E+07 0.000E+00 9.800E+06 TC-99M 6.770E-01 1.890E+00 2.450E+01 0.000E+00 2.810E+01 1.050E+00 1.240E+33 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ; RU-103 2.180E+02 0.000E+00 9.310E+01 0.000E+00 7.670E+02 0.000E+00 1.820E+04 RU-105 1.880E-04 0.000E+00 7.290E-05 0.000E+00 2.370E-03 0.000E+00 1.520E-01 RU-106 4.500E+03 0.000E+00 5.670E+02 0.000E+00 8.680E+03 0.000E+00 2.160E+05 RH-103M O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
v Offsita Dose Cliculation Manu11 Paga 279 of 298 R; vision 2 Chrnge 0 ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS i TEEN l (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 1.160E+07 1 090E+07 6.650E+06 0.000E+00 2.090E+07 0.000E+00 3.070E+09 SB-122 9.310E+04 9.710E+04 1.180E+06 1.540E+04 4.580E+04 2.000E+04 1.160E+07 SB-124 5.510E+06 1.020E+05 2.150E+06 1.250E+04 0.000E+00 4.810E+06 1.110E+08 ; SB-125 4.380E+06 4.790E+04 1.030E+06 4.190E+03 0.000E+00 3.850E+06 3.410E+07 TE-125M 3.600E+06 1.300E+06 4.820E+05 1.010E+06 0.000E+00 0.000E+00 1.060E+07 TE-127M 1.010E+07 3.590E+06 1.200E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 TE-127 1.490E+02 5.290E+01 3.210E+01 1.030E+02 6.050E+02 0.000E+00 1.150E+04 TE-129M 1.330E+07 4.920E+06 2.100E+06 4.280E+06 5.550E+07 0.000E+00 4.980E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.890E+04 3.780E+04 3.150E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 5.130E+05 3.250E+05 3.060E+05 3.430E+05 3.120E+06 0.000E+00 1.030E+07 I-130 8.990E+05 2.600E+06 1.040E+06 2.120E+08 4.010E+06 0.000E+00 2.000E+06 I-131 6.450E+08 9.030E+08 4.850E+08 2.640E+11 1.560E+09 0.000E+00 1.790E+08 I-132 3.480E-01 9.110E-01 3.270E-01 3.070E+01 1.430E+00 0.000E+00 3.970E-01 I-133 8.690E+06 1.470E+07 4.500E+06 2.060E+09 2.590E+07 0.000E+00 1.120E+07 f I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 2.960E+04 7.620E+04 2.820E+04 4.900E+06 1.200E+05 0.000E+00 8.440E+04 CS-134 2.940E+10 6.930E+10 3.210E+10 0.000E+00 2.200E+10 8.410E+09 8.620E+08 CS-136 1.330E+09 5.250E+09 3.530E+09 0.000E+00 2.860E+09 4.510E+08 4.230E+08 CS-137 4.020E+10 5.340E+10 1.860E+10 0.000E+00 1.820E+10 7.060E+09 7.600E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 1.040E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.310E-08 , BA-140 5.830E+06 7.140E+03 3.750E+05 0.000E+00 2.420E+03 4.800E+03 8.980E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 9.760E-01 4.750E-01 1.260E-01 0.000E+00 0.000E+00 0.000E+00 2.730E+04 LA-142 1.980E-12 8.780E-13 2.190E-13 0.000E+00 0.000E+00 0.000E+00 2.670E-08 CE-141 1.060E+03 7.110E+02 8.170E+01 0.000E+00 3.350E+02 0.000E+00 2.030E+06 CE-143 9.230E+00 6.720E+03 7.500E-01 0.000E+00 3.010E+00 0.000E+00 2.020E+05 CE-144 7.900E+04 3.270E+04 4.240E+03 0.000E+00 1.950E+04 0.000E+00 1.990E+07 PR-143 3.500E+01 1.400E+01 1.740E+00 0.000E+00 8.130E+00 0.000E+00 1.150E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 2.180E+01 2.370E+01 1.420E+00 0.000E+00 1.390E+01 0.000E+00 8.530E+04 W-187 1.440E+03 1.170E+03 4.110E+02 0.000E+00 0.000E+00 0.000E+00 3.180E+05 NP-239 8.390E-01 7.910E-02 4.390E-02 0.000E+00 2.480E-01 0.000E+00 1.270E+04
Page 280 of 298 Offsite Dose Cciculation M:nual Revtion 2 Change 0 ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS CHILD (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract I H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 l NA-24 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 P-32 9.330E+10 4.370E+09 3.600E+09 0.000E+00 0.000E+00 0.000E+00 2.580E+09 CR-51 0.000E+00 0.000E+00 1.220E+04 6.790E+03 1.860E+03 1.240E+04 6.490E+05 MN-54 0.000E+00 2.510E+06 6.690E+05 0.000E+00 7.050E+05 0.000E+00 2.110E+06 MN-56 0.000E+00 1.570E-03 3.550E-04 0.000E+00 1.900E-03 0.000E+00 2.280E-01 j i FE-55 1.450E+06 7.700E+05 2.390E+05 0.000E+00 0.000E+00 4.360E+05 1.430E+05 FE-59 1.570E+06 2.530E+06 1.260E+06 0.000E+00 0.000E+00 7.350E+05 2.640E+06 CO-57 0.000E+00 4.600E+05 9.320E+05 0.000E+00 0.000E+00 0.000E+00 3.770E+06 { CO-58 0.000E+00 1.460E+06 4.460E+06 0.000E+00 0.000E+00 0.000E+00 8.500E+06 CO-60 0.000E+00 5.180E+06 1.530E+07 0.000E+00 0.000E+00 0.000E+00 2.870E+07 NI-63 3.560E+09 1.900E+08 1.210E+0B 0.000E+00 0.000E+00 0.000E+00 1.200E+07 NI-65 1.990E-01 1.870E-02 1.090E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 { 0.000E+00 B.410E+03 5.080E+03 0.000E+00 2.030E+04 0.000E+00 3.950E+05 ) CU-64 ZN-65 4.960E+08 1.320E+09 8.220E+08 0.000E+00 0.330E+08 0.000E+00 2.320E+08 ) I ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 1.390E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.620E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ( BR-84 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+09 6.470E+08 0.000E+00 0.000E+00 0.000E+00 6.770E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.390E+10 0.000E+00 3.970E+0B 0.000E+00 0.000E+00 0.000E+00 5.380E+0B SR-90 2.350E+11 0.000E+00 5.950E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 2.970E+05 0.000E+00 1.120E+04 0.000E+00 0.000E+00 0.000E+00 6.550E+05 SR-92 4.590E+10 0.000E+00 1.840E-01 0.000E+00 0.000E+00 0.000E+00 8.690E+01 Y-90 3.860E+01 0.000E+00 1.030E+00 0.000E+00 0.000E+00 0.000E+00 1.100E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 4.690E+03 0.000E+00 1.250E+02 0.000E+00 0.000E+00 0.000E+00 6.250E+05 Y-92 2.950E-05 0.000E+00 8.440E-07 0.000E+00 0.000E+00 0.000E+00 8.520E-01 Y-93 1.270E-01 0.000E+00 3.480E-03 0.000E+00 0.000E+00 0.000E+00 1.890E+03 ZR-95 4.610E+02 1.010E+02 9.030E+01 0.000E+00 1.450E+02 0.000E+00 1.060E+05 ZR-97 2.260E-01 3.270E-02 1.930E-02 0.000E+00 4.690E-02 0.000E+00 4.950E+03 NB-95 3.810E+04 1.400E+04 1.060E+04 0.000E+00 1.390E+04 0.000E+00 2.750E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-07 MO-99 0.000E+00 9.950E+06 2.460E+06 0.000E+00 2.120E+07 0.000E+00 8.230E+06 TC-99M 1.550E+00 3.040E+00 5.040E+01 0.000E+00 4.420E+01 1.550E+00 1.730E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 5.150E+02 0.000E+00 1.980E+02 0.000E+00 1.300E+03 0.000E+00 1.330E+04 RU-105 4.590E-04 0.000E+00 1.660E-04 0.000E+00 4.030E-03 0.000E+00 2.990E-01 RU-106 1.110E+04 0.000E+00 1.380E+03 0.000E+00 1.500E+04 0.000E+00 1.720E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l - _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ._ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
i Offsite Dose Calculation Manus! Page 281 of 298 j Revision 2 Change 0 ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS CHILD (m2
- mrem /yr per uti/see)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 2.510E+07 1.690E+07 1.350E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.650E+04 9.540E+06 SB-124 1.300E+07 1.690E+05 4.570E+06 2.880E+04 0.000E+00 7.240E+06 8.150E+07 SB-125 1.040E+07 8.050E+04 2.190E+06 9.670E+03 0.000E+00 5.820E+06 2.490E+07 TE-125M 8.850E+06 2.400E+06 1.180E+06 2.480E+06 0.000E+00 0.000E+00 B.540E+06 TE-127M 2.500E+07 6.720E+06 2.960E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 TE-127 3.670E+02 9.910E+01 7.880E+01 2.540E+02 1.050E+03 0.000E+00 1.440E+04 TE-129M 3.270E+07 9.130E+06 5.080E+06 1.050E+07 9.600E+07 0.000E+00 3.990E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0.000E+00 7.340E-09 TE-131M 1.920E+05 6.640E+04 7.070E+04 1.370E+05 6.430E+05 0.000E+00 2.690E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.230E+06 5.420E+05 6.550E+05 7.900E+05 5.040E+06 0.000E+00 5.460E+06 I-130 2.100E+06 4.250E+06 2.190E+06 4.6BOE+0B 6.350E+06 0.000E+00 1.990E+06 I-131 1.570E+09 1.570E+09 8.950E+08 5.210E+11 2.580E+09 0.000E+00 1.400E+0B I-132 8.230E-01 1.510E+00 6.960E-01 7.020E+01 2.320E+00 0.000E+00 1.780E+00 I-133 2.110E+07 2.610E+07 9.880E+06 4.850E+09 4.350E+07 0.000E+00 1.050E+07 I I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 7.000E+04 1.260E+05 5.960E+04 1.120E+07 1.930E+05 0.000E+00 9.600E+04 CS-134 6.790E+10 1.110E+11 2.350E+10 0.000E+00 3.450E+10 1.240E+10 6.010E+08 CS-136 3.010E+09 8.280E+09 5.360E+09 0.000E+00 4.410E+09 6.580E+0B 2.910E+08 CS-137 9.670E+10 9.260E,10 1.370E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+0B l CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 2.560E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.4BOE-06 BA-140 1.410E+07 1.230E+04 8.210E+05 0.000E+00 4.010E+03 7.340E+03 7.120E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 2.310E+00 B.090E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.260E+04 l LA-142 4.770E-12 1.520E-12 4.770E-13 0.000E+00 0.000E+00 0.000E+00 3.020E-07 CE-141 2.620E+03 1.310E+03 1.940E+02 0.000E+00 5.730E+02 0.000E+00 1.630E+06 CE-143 2.270E+01 1.230E+04 1.780E+00 0.000E+00 5.150E+00 0.000E+00 1.800E+05 CE-144 1.950E+05 6.100E+04 1.040E+04 0.000E+00 3.380E+04 0.000E+00 1.590E+07 PR-143 8.670E+01 2.600E+01 4.300E+00 0.000E+00 1.410E+01 0.000E+00 9.350E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 5.340E+01 4.320E+01 3.350E+00 0.000E+00 2.370E+01 0.000E+00 6.850E+04 i W-187 3.490E+03 2.070E+03 9.270E+02 0.000E+00 0.000E+00 0.000E+00 2.900E+05 NP-239 2.060E+00 1.480E-01 1.040E-01 0.000E+00 4.280E-01 0.000E+00 1.100E+04 l l f
Y Offsite Dose Calculation M: null Page 282 of 298 Revisbn 2 Change 0 ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS INFANT (m2
- mrem /yr per uCi/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.000E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 C-14 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 [ P-32 1.920E+11 1.130E+10 7.450E+09 0.000E+00 0.000E+00 0.000E+00 2.600E+09
- CR-51 0.000E+00 0.000E+00 1.940E+04 1.260E+04 2.760E+03 2.460E+04 5.650E+05 MN-54 0.000E+00 4.670E+06 1.060E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 MN-56 0.000E+00 3.850E-03 6.630E-04 0.000E+00 3.310E-03 0.000E+00 3.490E-01 FE-55 1.760E+06 1.130E+06 3.030E+05 0.000E+00 0.000E+00 5.540E+05 1.440E+05 FE-59 2.920E+06 5.110E+06 2.010E+06 0.000E+00 0.000E+00 1.510E+06 2.440E+06 CO-57 0.000E+00 1.070E+06 1.750E+06 0.000E+00 0.000E+00 0.000E+00 3.660E+06 CO-58 0.000E+00 2.910E+06 7.270E+06 0.000E+00 0.000E+00 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 2.500E+07 0.000E+00 0.000E+00 0.000E+00 2.520E+07 NI-63 4.190E+09 2.590E+08 1.450E+08 0.000E+00 0.000E+00 0.000E+00 1.290E+07 NI-65 4.210E-01 4.770E-02 2.170E-02 0.000E+00 0.000E+00 0.000E+00 3.630E+00 (
CU-64 0.000E+00 2.090E+04 9.680E+03 0.000E+00 3.540E+04 0.000E+00 4.290E+05 ZN-65 6.660E+08 2.280E+09 1.050E+09 0.000E+00 1.110E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 2.330E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 1.190E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ' BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+0C 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.670E+09 1.320E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 l i RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.640E+10 0.000E+00 7.580E+08 0.000E+00 0.000E+00 0.000E+00 5.430E+08 ; SR-90 2.550E+11 0.000E+00 6.500E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 6.180E+05 0.000E+00 2.240E+04 0.000E+00 0.000E+00 0.000E+00 7.310E+05 SR-92 9.760E+00 0.000E+00 3.620E-01 0.000E+00 0.000E+00 0.000E+00 1.050E+02 Y-90 8.160E+01 0.000E+00 2.190E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.800E+03 0.000E+00 2.340E+02 0.000E+00 0.000E+00 0.000E+00 6.310E+05 Y-92 6.270E-05 0.000E+00 1.760E-06 0.000E+00 0.000E+00 0.000E+00 1.200E+10 Y-93 2.700E-01 0.000E+00 7.350E-03 0.000E+00 0.000E+00 0.000E+00 2.130E+03 ZR-95 8.190E+02 2.000E+02 1.420E+02 0.000E+00 2.150E+02 0.000E+00 9.940E+00 ZR-97 4.790E-01 8.220E-02 3.760E-02 0.000E+00 8.290E-02 0.000E+00 5.240E+03 NB-95 7.120E+04 2.930E+04 1.690E+04 0.000E+00 2.100E+04 0.000E+00 2.470E+07 NB-97 6.590E-12 1.410E-12 5.070E-13 0.000E+00 1.100E-12 0.000E+00 4.440E-07 MO-99 0.000E+00 2.540E+07 4.960E+06 0.000E+00 3.800E+07 0.000E+00 8.830E+06 TC-99M 3.230E+00 6.660E+00 B.570E+01 0.000E+00 7.160E+01 3.480E+00 1.930E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.040E+03 0.000E+00 3.490E+02 0.000E+00 2.170E+03 0.000E+00 1.270E+04 RU-105 9.670E-04 0.000E+00 3.260E-04 0.000E+00 7.110E-03 0.000E+00 3.850E-01 RU-106 2.280E+04 0.000E+00 2.850E+03 0.000E+00 2.700E+04 0.000E+00 1.730E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
v i Offsite Dose C0lculation Manual Pcge 283 of 298 Revision 2 Change O ATTACHMENT 12 GRASS-GOAT-MILK DOSE FACTORS INFANT (m2
- mrem /yr per uci/sec)
Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract AG-110M 4.630E+07 3.380E+07 2.240E+07 0.000E+00 4.340E+07 0.000E+00 1.750E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.650E+04 9.540E+06 SB-124 2.510E+07 3.700E+05 7.790E+06 6.670E+04 0.000E+00 1.570E+07 7.750E+07 SB-125 1.790E+07 1.740E+05 3.690E+06 2.250E+04 0.000E+00 1.130E+07 2.390E+07 TE-125M 1.810E+07 6.050E+06 2.450E+06 6.090E+06 0.000E+00 0.000E+00 8.620E+06 TE-127M 5.050E+07 1.680E+07 6.120E+06 1.460E+07 1.240E+08 0.000E+00 2.040E+07 TE-127 7.800E+02 2.610E+02 1.680E+02 6.350E+02 1.900E+03 0.000E+00 1.640E+04 TE-129M 6.710E+07 2.300E+07 1.030E+07 2.580E+07 1.680E+08 0.000E+00 4.010E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.000E-08 TE-131M 4.050E+05 1.630E+05 1.350E+05 3.310E+00 1.120E+06 0.000E+00 2.750E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.520E+06 1.250E+06 1.170E+06 1.840E+06 7.820E+06 0.000E+00 4.620E+06 I-130 4.320E+06 9.510E+06 3.820E+06 1.070E+09 1.040E+07 0.000E+00 2.040E+06 I-131 3.270E+09 3.850E+09 1.690E+09 1.270E+12 4.500E+09 0.000E+00 1.370E+08 I-132 1.710E+00 3.470E+00 1.230E+00 1.630E+02 3.870E+00 0.000E+00 2.810E+00 I-133 4.460E+07 6.490E+07 1.900E+07 1.180E+10 7.630E+07 0.000E+00 1.100E+07 I-134 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.460E+05 2.900E+05 1.060E+05 2.600E+07 3.230E+05 0.000E+00 1.050E,05 CS-134 1.090E+11 2.040E+11 2.060E+10 0.000E+00 5.250E+10 2.150E+10 5.540E+08 CS-136 5.880E+09 1.730E+10 6.460E+09 0.000E+00 6.900E+09 1.410E+09 2.630E+08 CS-137 1.540E+11 1.810E+11 1.280E+10 0.000E+00 4.850E+10 1.960E+10 5.650E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 5.450E-08 0.000E+00 1.580E-09 0.000E+00 0.000E+00 0.000E+00 3.450E-06 BA-140 2.890E+07 2.890E+04 1.490E+06 0.000E+00 6.870E+03 1.780E+04 7.110E+06 BA-141 0.000E+00 0.000E+00'O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.840E+00 1.910E+00 4.900E-01 0.000E+00 0.000E+00 0.000E+00 2.240E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 5.200E403 3.170E+03 3.730E+02 0.000E+00 9.780E+02 0.000E+00 1.640E+06 CE-143 4.800E+01 3.180E+04 3.630E+00 0.000E+00 9.270E+00 0.000E+00 1.860E+05 CE-144 2.790E+05 1.140E+05 1.560E+04 0.000E+00 4.620E+04 0.000E+00 1.600E+07 PR-143 1.790E+02 6.710E+01 8.890E+00 0.000E+00 2.490E+01 0.000E+00 9.470E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.060E+02 1.090E+02 6.660E+00 0.000E+00 4.190E+01 0.000E+00 6.890E+04 W-187 7.350E+03 5.110E+03 1.770E+03 0.000E+00 0.000E+00 0.000E+00 3.000E+05 NP-239 4.360E+00 3.900E-01 2.210E-01 0.000E+00 7.780E-01 0.000E+00 1.130E+04
7 Offsite Dose Calculation Manual Page 284 of 298 , ' Revision 2 Change 0 l* ATTACEMENT 13 ENVIRONMENTAL MONITORING SITES FOR REMP -! SAMPLE SITE SECTOR DISTANCE'" DESCRIPTION f km mi DR1 NW 0.6 0.4 Onsite, Along Cliffs [ DR2- WNW 2.7 1.7 ' Rt. 765, Auto Dump l DR3 W 2.3 1.4 Rt. 765, Giovannrs Tavem (Knotty Pine) i DR4 WSW 2.0 1.2 Rt. 765, Across from White Sand Drive ! DR5 SW 2.4 1.5 Rt. 765 at Johns Creek - DR6, A4 SSW 2.9 1.8 Rt. 765 at Lusby . DR7, A1, Ib4, Ib5, Ib6 S 0.7 0.5 On site before entrance to Camp Conoy l DR8, A2 SSE 2.5 1.5 Camp Conoy Road at Emergency Siren ! DR9, A3 SE 2.6 1.6 Bay Breeze Road DR10 NW 6.4 4.0 Calvert Beach Rd & Decatur St DR11 WNW 6.6 4.1 Dirt Road off Mackall Rd & Parran Rd , ' DR12 W 6.7 4.2 Bowen Rd & Mackall Rd
- DR13 WSW 6.1 3.8 Mackall Rd naar Wallville i
DR14 SW 6.4 4.0 Rodney Point DR15 SSW 6.2 3.9 Mill Bridge Rd & Tumor Rd i DR16 S 6.5 4.1 Across from Appeal School DR17 SSE 5.9 3.7 Cove Point Rd & Little Cove Point Rd ! 7.1 4.5 Cove Point ! DR18 SE DR19 NW 4.4 2.8 Long Beach DR20 NNW 0.4 0.3 Onsite near shore DR21, A5, Ib7, Ib8, Ib9 WNW 19.3 12.1 Emergency Offsite Facility off Rt. 231 DR22 S 12.5 7.8 Solomons Island } DR23 ENE 12.6 7.9 Taylors Island i Wai NNE 0.2 0.1 Intake Vicinity Wa2, la1, la2 N 0.3 0.2 Discharge Veinity ! Wb1 ESE 0.6 0.4 Camp Conoy Shoreline {' Ibi, Ib2, Ib3 SSE 2.6 1.6 Garden Plot off Bay Breeze Rd la4, la5 Area not influenced by Plant Disch. Pa0Jxent River it3 E 0.9 0.6 Camp Conoy . la6 NNW 10.7 6.7 Kenwood Beach l i t i 9
- Distance and direction from the central point of the two containment buildings. l l
t
- s Offsite Dose Calculation Manu:1 Page 285 of 298 Revrion 2 Ch:nge O ATTACHMENT 14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCES FOR DIRECT RADIATION PARAMETER i UNITS I FREQUENCY j LLD i ACTION LEVEL GAMMA DOSE (1) i mR l at least quarterly I (2) l N/A (1) Each sample point shall be monitored using two or more dosimeters OR one instrument for measuring and recording dose rate continuously. (2) LLD for TLDs used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. I l l 1
i 4
' Offsite Dose Calculation Manual Page 286 of 298 Revision 2 Change O ATTACHMENT 15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM )
SURVEILLANCES FOR AIRBORNE ACTIVITY RADIOIODINE CANNISTER ! PARAMETER I UNITS I FREQUENCY LLD l ACTION LEVEL (5) l l-131 I pCi/m 3 i at least weekly 0.07 l 0.9 PARTICULATE FILTER (O PARAMETER I UNITS i FREQUENCY I LLD I ACTION LEVEL (5) Gross Beta Activity i pCi/m 3 l at least weekly (2) i 0.01 ! N/A (3) l Cs-134 i pCi/m3 I at least quarterly (9 0.05 ! 10.0 l ( Cs-137 pCi/m 3 I atleast quarterly (4 0.06 l 20.0
)
(1) All samples consist of continuous sampler operation with sample collection weekly, or more frequently if required j by dust loading. (2) Analyze for gross beta activity 24 hours or more after sampling to allow for radon and inoron daughter decay. (3) Although there is not an ACTION Level for gross beta activity, if this parameter is greater than ten times the yearly mean of the control sample, perform gamma isotopic analysis on the individual sample. (4) Perform a gamma isotopic analysis of a quarterly compostte sample. A separate composite sample shall be prepared for each sample location, A1 thru A5. Each composite sample shall be a prepared from individual particulate filter samples collected during the applicable calendar quarter and from a single location. (G) If an ACTION Level is exceeded, check the initiating conditions listed in sections Vll.A.S.c and Vll.A.S.d, and perform the corrective ACTIONS specified in section Vll.A.7.d and/or Vll.A.7.e. 1 l l
l' i ! 1 L Offste Dose Cciculation Minual Paga 287 of 298 Revision 2 Chang 3 0 ATTACHMENT 16 ] RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l l l- SURVEILLANCES FOR WATERBORNE ACTIVITY ' SURFACE MATER SAMPLEM l PARAMETER I UNITS l FREQUENCY l LLD i ACTION LEVEL (2) H-3 l pCi/l I atleast quarterly i 2000(31 l 20,000(d) l Mn-54 I pCi/l I at least monthly ! 15 i 1000 Fe-59 I pCi/l I at least monthly 6 30 1 400 Co-58 I pCi/l I at least monthly i 15 l 1000 Co40 ! pCill I at least monthly 1 15 1 300 I Zn-65 i pCi/l I atleast monthly I 30 I 300 Zr-95 / Nb-95 I pCi/l I at least monthly 1 15 1 400 1-131 I pCi/l i at least monthly 1 1 1 2 Cs-134 i pCill I at least monthly i 15 ! 30 < Cs-137 I pCi/l i at least monthly i 18 I 50 I Ba-140 / La-140 i pCi/l ! at least monthly i 15 i 200 l l SHORELINE SEDIMENT SAMPLE PARAMETER ! UNITS I FREQUENCY ! LLD I ACTION LEVEL (2) Cs-134 I pCi/kg, dry I at least semiarnually 150 i N/A Cs-137 1 pCi/kg, dry I at east semiannually 180 i N/A (1) The water sample shall be a composite of individual samples collected over a 1 month period. (2) If an ACTION Leveiis exceeded, check the initiating conditions listed in sections Vll.A.5.c and Vll.A.S.d, and perform the corrective ACTIONS specified in section Vll.A.7.d and/or Vll.A.7.e. (3) If a drinking water pathway does not exist, a value of 3000 pCi/l may be used. (4) If a drinking water pathway does not exist, a value of 30,000 pCill may be used. l 1 l l l 1
Offsite Dose Calculation Manual Page 288 of 298 Revision 2 Change O ATTACHMENT 17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCES FOR INGESTIBLE ACTIVITY FISH AND INVERTEBRATESM PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) Mn-54 pCi/kg, wet (2) 130 30,000 Fe-59 pCi/kg, wet (2) 260 10,000 Co-58 pCi/kg, wet (2) 130 30,000 Co-60 pCL/kg, wet (2) 130 10,000 2n45 pCl/kg, wet (2) 260 20,000 Cs-134 pCi/kg, wet (2) 130 1000 Cs-137 pCi/kg, wet (2) 150 2000 NILK , PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) 1131 pCill, wet at least monthly (4) 1 3 Cs-134 pCi/l, wet at least monthly (4) 15 60 Cs-137 pCill, wet at least monthly (4) 18 70 Ba-140 / La-140 pCill, wet atleast monthly (4) 15 300 : FOOD PRODUCTS PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5) 1-131 pCi/kg, wet atleast monthly (3) 60 100 Cs-134 pCi/kg, wet atleast monthly (3) 60 1000 Cs-137 pCL/kg, wet atleast monthly (3) 80 2000 (1) Edible portions of the fish and invertebrates shall be used for analysis. (2) The fish and invertebrates shall be sampled at least once per year in season, or semiannually if they are not seasonal. (3) The food products shall be sampled during the growing season. (4) The milk samples need be collected and analyzed only if the milk is comrnercially available in quantities greater i than 310 liters per year (see NUGREG-0133,5.3.1.1). (G) If an ACTION Levelis exceeded, check the initiating conditions listed in sections VII AS.c and Vll.A.S.d, and perform the corrective ACTIONS specified in section VilA7.d and/or Vll.A.7.e. j l
i Offsite Dose Cr.lculation Minual Page 289 of 298 Revhion 2 Ch:;nge 0 l ATTACIDENT 18 l I MAP OF ENVIRO)OMNTAL MONITORING SITES FOR REMP (5 KM RADIUS)
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l Offsite Dose Calculation Manual Page 291 of 298 I Revision 2 Change O ATTACIDENT 20 ENVIROBOGNTAL MONITORING SITES FOR ISFSI j l STATION DESCRIPTION DISTANCE"' DIRECTION"5 q (Kilometers) (Sector) AIR RAnapirRs . A1"* On Site Before Entrance to Camp Conoy 0.3 '.sE SFA1 Meteorological Station 0.4 NW .' SFA2 CCNPP Vaitors Center 0.7 HNE ; SFA3 North Northwest ofISFSI 0.1 NNW SFA4 South ofISFSI 0.1 S TLD LOCATIONS SFDR1 Collocated with Plant TLD #159 0.1 SW SFDR2 Collocated with Plant TLD #160 0.1 NNW I SFDR3 Collocated with Plant TLD #161 . 0.1 NNE SFDR4 Collocated with Plant TLD #162 <0.1NE SFDRS Collocated with Plant TLD #163 <0.1 E SFDR6 Collocated with Plant TLD #164 0.1 ESE SFDR7 CCNPP Voltors Center 0.7 NNE SFDR8 North ofISFSI 0.1 N ! SFDR9 South ofISFSI 0.1 S ! SFDR10 North Northwest ofISFSI 0.1 NNW SFDR11 West Northwest ofISFSI 0.1 WNW SFDR12 West ofISFSI <0.1 W ; SFDR13 South Southwest ofISFSI <0.1 SSW J SFDR14 South Southeast ofISFSI 0.1 SSE l SFDR15 East Northeast ofISFSI <0.1 ENE i SFDR16 West Southwest ofISFSI <0.1WSW ! DR72 On Site Before Entrance to Camp Conoy 0.3 SE DR30 Meteorolog2 cal Station 0.4 NW VEGETATION SFb1 Meteorological Station 0.4 NW SFb2 CCNPP Vmitors Center 0.7 NNE SFb3 North Northwest ofISFSI 0.1 NNW SFb4 South ofISFSI 0.1 S SFb5 On Site Before Entrance to Camp Conoy 0.3 SE ! RDL . SFS1 Meteorological Station 0.4 NW l SFS2 CCNPP Voltors Center 0.7 NNE SFS3 North Northwest ofISFSI 0.1 NNW SFS4 South ofISFSI 0.1 S SFSS On Site Before Entrance to Camp Conoy 0.3 SE 1
- Distance and direction from the Central Point of the ISFSt.
" Common to both the REMP and the ISFSIMP.
Offsite Dose Colculation Manuel Page 292 of 298 Revision 2 Change 0 ATTACIDENT 21 MAP OF ENVIRONMENTAL MONITORING SITES FOR ISFSI i N / NNE NNW l
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Offsite Dose Calculation Manual Page 293 of 298 i Revision 2 Change 0 ATTACIDEENT 22 MAP OF ENVIRONMENTAL MONITORING SITES FOR ISFSI (ENLARGED) i MAP OF ENVIROMGMTAL MONITORING SITES FOR ISFSI (ENLARGED) l DR30 , m
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) e SFDR - SPENT FUEL DIRECT RADIATION SFA - SPENT FUEL AIR SAMPLER Plc - PRESSURIZED lDN CHAMSER Enlarged Map of Sampilng Sites independent Spent Fuel Storage Installation '
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Offsite Dose Calculation Manual Page 294 cf 298 Revision 2 Change O ATTACHMENT 23 EFFLUENT RADIATION MONITORS Description Radiation Radiation Element Indicator Liquid Waste Discharge Radiation Monitor 0-RE-2201 0-RI-2201 Steam Generator Blowdown Emuent Radiation Monitor 1-RE-4095 1-RI-4095 Steam Generator Blowdown Emuent Radiation Monitor 2-RE-4095 2-RI-4095 Steam Generator Blowdown Tank Radiation Monitor 1-RE-4014 1-RI-4014 Steam Generator Blowdown Tank Radiation Monitor 2-RE-4014 2-Rl4014 Wide Range Gas Monitor, Low Range 1-RE-5416 1-RIC-5415 Wide Range Gas Monitor, Low Range 2-RE-5416 2-RIC-5415 Westinghouse Plant Vent Stack Monitor 1-RE-5415 1-RI-5415 Westinghouse Plant Vent Stack Monitor 2-RE-5415 2-RI-5415 Gaseous Radwaste Treatment System Radiation Monitor 0-RE-2191 0-RI-2191 Accident Monitors Not Addressed By The ODCM Wide Range Gas Monitor, Mid Range 1-RE-5417 Wide Range Gas Monitor, High Range 1-RE-5418 Wide Range Gas Monitor, Mid Range 2-RE-5417 Wide Range Gas Monitor, High Range 2-RE-5418 l 1
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