Text

Proposed Tech Spec Changes to Environ Monitoring Program & Radiological Effluent Tech Specs (NUREG-0472) Re Administrative Controls,Plant Design & Sys Capabilities
	ML20106C123
Person / Time
Site:	Calvert Cliffs
Issue date:	10/11/1984
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20106C109	List: ML20106C108; ML20106C123;
References
	RTR-NUREG-0472, RTR-NUREG-472 NUDOCS 8410240012
	Download: ML20106C123 (181)
	v • d • e

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Attachment 1 D

, INDEX DEFINITIONS PAGE Gaseous Radwaste Treatment System ..................... 1-7 Member (s) of the Public . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 Offsite Dose Calculation Manual (ODCM) ................... 1-7 Process Control Program (PCP) ........................ 1-7 Purge-Purging . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 Site Boundary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 Solidification ................................. 1-8 Source Check . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Unrestricted Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 Ventilation Exhaust Treatment System . . . . . . . . . . . . . . . . . . . . . 1-8 Ven tin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 i

CALVERT CLIFFS UNIT 1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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, Attachment 1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING PAGE 3/4.12.1 MONITORING PROGRAM .................. 3/4 12-1 3/4.12.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . . 3/4 12-12 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ...... 3/4 12-13 CALVERT CLIFFS UNIT 1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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, Attachment 1 INDEX BASES

! 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING, Page 3/4.12.1 MONITORING PROGRAM ................. B 3/412-1 3/4.12.2 LAND USE CENSUS ................... B 3/412-2 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ...... B3/412-2 CALVERT CLIFFS UNIT 1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

. ATf/1CittiEN7 I 1.0 DEFINITIONS

.s DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER _

1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt. M CPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant

temperature specified in Table 1.1.

+ht part e[ A S esi$ICALIon t WM'h P '*' Crib *'

- 1.5 ACTION shall be th::: Odditi0n:1 r:Wir:: nt:-;pe i"Od :: 00f 0lla ry- '

t:::::: : :: : e pr',:!pi: ;;;;&f4e+t4:n =d -9411 be put-of-th:

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rerseditI neasures tefuired nder des @nn4.e4 condMions.

OPERABLE - OPERABILIT'Y 1.6 A system, subsystem, train, component or device shall be OPEPABLE 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 inst'rumentation, controls, normal and emergency ele *ctrical power sources, cooling or seal water, lubrication or other required auxi?iary couipment that are required for the systen, sub-system, train, component or device to perform its function (s) are also capable of performing their related support function (s).

CALVERT CLIFFS UNIT 1 11 Amendment No. /

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, 1.0 DEFINITIONS GASEOUS RADWASTE TREATMENT SYSTEM 1.29 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.

MEMBER (S) OF THE PUBLIC 1.30 MEMBER (S) OF THE PUBLIC shall include a!! 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 deliverles.

OFFSITE DOSE CALCUL ATION MANUAL (ODCM) 1.31 The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring program.

PROCESS CONTROL PROGR AM (PCP) 1.32 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be inade 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 compilance with 10 CFP. Part 20,10 CPR Part 71 and Federal and State and local regulations governing the disposal of the radioactive waste.

PURGE - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, hurnidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

CALVERT CLIFFS UNIT 1 1-7 Amendment No.

CALVERT CLIFPS UNir 2 Amendment No.

Attachment i

. 1.0 DEFINITIONS (Continued)

SITE BOUNDARY 1.34 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOLIDIFICATION 1.35 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping anJ burial ground requirements.

SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a scurce of increased radioactivity.

UNRESTRICTED AREA t 1.37 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 materlats, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.38 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA' filters for the purpose of removing lodines 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.

VENTING 1.39 VENTING la the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other eperating 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.

CALVERT CLIPPS UNIT 1 1-8 Amendment No.

l CALVERT CLIFF 5 UNIT 2 Amendment No.

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AttachmGnt i

. TABLE 1.2

' FREQUENCY NOTATION

_N_OTATION FREQUENCY S- At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W --- At least once per 7 days.

M- At least once per 31 days.

Q At least once per 92 days.

'SA At least once per 6 months.

R At least once per 18 months.

S/U Prior to each reactor rtartup.

P Completed prior to each release.

N.A. Not applicable.

CALVERT CLIFFS UNIT 1 1-10 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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- 5.0' DESIGN FEATURES _

5.1 SITE MAP DEFINING THE SITE BOUNDARY AND EFFLUENT RELEASE POINTS 3.1.1 . A map of the Calvert Cliffs Nuclear Power Plant site identifyir.g the major plant structures as well as defining the radioactive effluent release points, and the SITE BOUNDARY is shown in Figure 5.1 1.

- LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2.

5.2 CONTAINMENT CONFIGURATION

-5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:

a. Nominal inside diameter = 130 feet,

b. Nominal inside height = 1812/3 feet,

c. Minimum thickness of conctete walls = 3 3/4 feet.

-. d. Minimum thickness of concrete roof = 31/4 feet,

e. Minimum thickness of concrete floor pad = 10 feet,

f. Nominal thickness of steel liner = 1/4 inches.

g. Net free volume = 2 x 10' cubic feet.

l CALVERT CLIFFa UNIT 1 3-1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

3/4'12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1- - The radiological environmental monitoring program shall be conducted as

.A specified in Table 3.12-1.

APPLICABILITYd At all times.-

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 Operating Report required by Specification 6.9.1.7, 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, pursuant to Specification 6.9.2, a f Special Report that identifies the cause(s) for exceeding the limit (s) and N

defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to a MEMBER OF THE PUBLIC is less than the; calendar year limits 'of Specifications 3.11.1.2, 3.11.2.2, and v 3.11.2.3. 5When more than one of the radionuclides in Table 3.12-2 are detected in the sample this report shall be submitted If:

concentration (l) + concentration (2) +..>1.0

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reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the r result of plant efflueats, this report shall be submitted if the potentui 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 required if the measured 1evel of radioactivity was not the result of plant effluents; however,-in fu'ch an event, the condition shall be reported and y described in the Annual Radiological Environmental Operating Report.

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CALVERT CLIFFS UNIT 1 3/4 12-1 Amendment No.

- CALVERT CLIFFS UNIT 2 Amendment No.

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_ . Attachment 1 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ACTION - (Continued)

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 6.9.1.7, 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.

The methodology and parameters used ; to estimate the potential annual dose to a MEMBER OF .THE PUBLIC shall be indicated in this report.

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'CALVERT CLIFFS UNIT 1 3/4 12-2 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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TABLE 3.12 .,

g. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM yie Number of 3.3 Representative .

Exposure Pathway Samples and Sampling and . Type and Frequency and/or Sample Sample Locations a Collection Frequency of Analysis NP 1. DIRECT RADIATION b 23 routine monitoring stations At least Quarterly Gamma dose at least (DRI-DR23) either with two or quarterly.

more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

an inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY We- (DRI-DR9);

M an outer ring of stations, one in

& each meteorological sector in the 6- to 3-km range from the site (DR10-DR18);

the balance of the 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.

2. AIRBORNE Radioiodine and Samples from 5 locations (Al- Continuous sampler Radiciodine Cannister Particulates A5): operation with 1-131 analysis weekly.

sample collection 3 samples (Al-A3) from close weekly, or more to the 3 SITE BOUNDARY frequently if required g by dust loading.

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Attachrmnt 1

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' TABLE 3.12-1 '(Continued)-

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

' Number of -

9K ' Representative

? ? Exposure '<athway Samples and ' Sampling and Type and Frequency.

EE and/or Sample Sample Locations

Collection Frequency 'of Analysis

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"" locations, in different sectors . Particulate Sampler:

"" of the highest calculated annual Gross beta radioac-average ground-level D/Q. tivity analysis follow .

ing filter change;c 1 sample (A4) from the vicinity of a community having the highest Gammajsotopic analysis of compo-calculated annual average ground- site (by location) level D/Q. quarterly.

I sample (A5) from a control location, as for example 15-30 km l T

distant and in the least prevalent i wind direction.

-g k 3. WATERBORNE

a. Surface I sample at intake area (Wal) Composite sample 1 sample at discharge area Gammajsotopic over 1-month period" analysis monthly.

(Wa2) Composite for tritium analysis quarterly.

b. Sediment from I sample from downstream area Semlannually shoreline with existing or potential Gammajsotopic analysis semi-annu-recreational value (Wbl). ally.

4. INGESTION k a. Fish and Inverte-brates 3 samples of commercially and/or Sample in season, or Gammajsotopic recreationally important semiannually if they analysis on edible species (2 fish species and are not seasonal. portions, gg 1 invertebrate specie)in vicinity of plant discharge ff area. (Ial - Ia3). Attachment 1

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' TABLE 3.12-l'- (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 99 Number of

.. j j .

Representative ue Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations a Collection Frequeng of Analysis y g 3 samples of same species in areas not influenced by plant discharge (la4 - Ia6).

b. Food' Products Samples of 3 different kinds Monthly during grow- Gamma isotopicd and of broad leaf vegetation grown ing season I-131 analysis.

near the site boundary at 2 different locations of highest predicted annual average ground-level D/Q (Ibl-Ib6).

g 1 sample of each of the similar Monthly during grow- Gamma isotopicd and y

broad leaf vegetation grown 15- ing season I-131 analysis.

m- 30 km distant in the least preva-lent wind direction (Ib7-Ib9).

?ri EE Attachment I h5

.n TABLE 3.12-1 (Continued) .

oo gg TABLE NOTATION R'R a a The code in parenthesis, e.g. DR1, Al, 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 4 the central point between the two containment buildings and additional description where pertinent, is provided for each "M

sample location in Table 3.12-1, and in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of GG gg Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978", and to Radiological Assessment yG Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if mp specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next samplin6 Period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. 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 mcy be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples W

" 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 M location (s).

& b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. Due to the geographical limitations,9 sectors are monitored around the Calvert Cliffs Nuclear Power Plant.

c Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Il nn Attachment 1

-oo ' TABLE 3,12-1 (Crntinued)

TABLE NOTATION--

d Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be yy attributable to the effluents from the facility. "

h-HI e A composite sample is one in which the quantity (aliquot) of liquid sampled is 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 ru H 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.

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TABLE 3.12-2 ,

1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES'-

n aq REPORTING LEVELS

.kd B a- Water Fish & Invertebrates Milk Food Products 1

l Airborne or GasesParticulg)te Analysis (pCi/1) (pCi/m (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

NH H-3 20,000*

Mn-54 1,000 30,000 l Fe-59 400 10,000 Co-53 1,000 30,000 W

Co-60 300 10,000 M Zn-65 300 20,000

!:o 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

s k *For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l

- may be used.

Et N 55 Attachment 1 z__ - _ _ _ .

r TABLE 4.12-1 oo hh DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa,b RR LOWER LIMIT OF DETECTION (LLD)c hh Water Fish & Invertebrates Milk Food Products Sediment Analysis (pCi/1) Airborne or GasesParticulg)te (pCi/m (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 w

D Co-58,60 15 130 s

y Zn-65 30 260 Zr-Nb-95 15 I-131 Id 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 g( *If no drinking water pathway exists, a value of 3000 pCi/l may be used, nn ff Attachment 1

Attachmeat 1 TABLE 4.12-1 (Continued)

TABLE NOTATION 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 6.9.1.7.

, :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 represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

.LLD=

EV -

2.22

Y

exp (- A At)

Where:

LLD is the "A priori" lower limit of detection as defined above, as picocuries per unit mass or volume,

-sb is the standard. deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per 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 at for environmental samples 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.

CALVERTCLIFFS UNIT 1 3/4 12-10 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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o-Attachment 1 TABLE 4.12-1 (Continued)

TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(after the fact) limit for a particular measurement. 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 6.9.1.11.

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- LLD. for drinking water samples. If no drinking water pathway exists, the LI,D of gamma isotopic analysis may be used.

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~ CALVERT CLIFFS UNIT 1 3/412-11 Amendment No.

- CALVERT CLIFFS UNIT 2 Amendment No.

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.- Attachment 1 RADIOLOGICAL ENVIRONMENTAL MON'ITORING LAND USE CENSUS

' " LIMITING CONDITION FOR OPERATION l

3.12.2 , A land use census shall be conducted and shall identify within a distance of 8 km (5 - l miles) the nearest location residence and in theeach of the nearest 9 meteorological garden sectors

of greater than 50 m 500 of fttp(nearesj) producing milk broadanimal, !

. leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, '

13uly 1977, the land use census shall also identify within a distance of 5 km-(3 miles) the

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locations in each f the 9 meteorological sectors of all milk animals and all gardens of

. greater than 50 m2 producing broad leaf vegetation).

APPLICABILITY: 'At'all times.

ACTION L 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 6.9.1.7.

. b. .With a land use census identifying a location (s) that yields a calculated dose or dose i 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 i

the new location (s) to the radiological envionmental monitoring program within 30 days.

t The calculatedsampling . location dose or (s), excluding dose commitment ,-.via (s)he control the same station exposure location, pathway, having may be deletedthe lowes from this monitoring program af ter (October 31) of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.7, 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).

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c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS I -4.12.2 The land census shall be conducted during the growing season at least once per 12

- , ; months using that information that will provide the best results, such as by a door-to-door l- survey, aerial survey, or by consulting local agriculture authorities. The results of the land j- use census shall be included in the Annual Radiological Environmental Operating Report

' pursuant to Specification 6.9.1.7.

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Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the-site boundary in each of two different direction sectors with the highest t predicted D/Qs 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.

i CALVERT CLIFFS UNIT 1 3/4 12-12 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

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Attachment 1 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 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 Specification 6.9.1.7.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

CALVERT CLIFFS UNIT 1 3/4 12-13 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

i s

.- Attachm:nt 1

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 ' MONITORING' PROGRAM

'~

The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive material:,in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures fo MEMBERS OF THE. PUBLIC resulting from the plant operation. This

' monitoring progam implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The'. initially _ specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(after the fact) limit for a particular measurement.

. Detailed discussion of the LLD, and other detection limits, can be found in HASL

- Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," anal. Chem.

40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

CALVERT CLIFFS UNIT 1 B 3/412-1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No. ;

Attachment 1 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.

The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m 2provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broag leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m .

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

CALVERT CLIFFS UNIT I B 3/412-2 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

)

ATTACHMENT 2 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS.1 AND 2 APPENDIX B PARTI ENVIRONMENTAL TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 NOTE Section 3.0, Environmental Surveillance and

- Monitoring, has - been deleted. Any other portion of the Appendix B Part a l- Environmental Technical Specifications dealing with Environmental Monitoring is hereby superceded by Appendix A Technical

< ' Specification Section 3/4.12.

l When the Radiological Effluent Technical Specifications (RETS) are fully implemented, Appendix B, Part I will be deleted in its entirety.

ISSUED BY THE U. S. NUCLEAR REGULATORY COMMISSION l - Calvert Cliffs Unit 1 Amendment No.

Calvert Cliffs Unit 2 Amendment No.

l:

'3.0 ENVIRONMENTAL SURVEILLANCE AND MONITORING-- DELFTlb o

b '3. Non-Radiological Surveillance - Deleted O

3.1.1 tic - Cel.eted . .

3.1. 2 Biotic - ed -

3.1. 2. a Gener atic Ecolo '- 1 Surveys - Deleted 3.1 Impingement of Organisms - Delet. .

f See. Spee10colion. 3}H . IL m Appendix A o -

CALVERT CLIFFS - UtlIT 1 3.1-1 M endment No. ;3, 70 CALVERT CLIFFS - UttIT 2 , tendment .No . 3 3, 53

- - )

. . 3 Radiclcgical Environmental Monitcring

/9W/fQNEAT L

.2 ,

Ob. etive An en ironmental radiological monitorfng program is conducted to provide dat on D

measura e levels of radiation and radioactive materials in the Calvert C .ffs environs i order to verify that radioactive releases and related publ exposure:s from Calvert iffs Unit 2 are within allovable limits.

Specifications A. Enb ron= ental s les shall be collected and analyzed ace rding to Table 3.2-1. Sampling ations are' shown in Fig. 3.2-1.

- B. Analytical technique used shall be such that the tection capabilities listed in Table 3 2-2 are achieve C. During the season when co are on pasture, s ples of fresh milk vill be obtained monthly from cows a location in cated in Fig. 3.2-1 and analyzed for cheir radiciodine content, culat d as' iodine-131, within 8 days -

(one I-131 half-live) of sampling.

~~~

S Reportina Recuirement Reports for the radiological" envi amental a teillance program shall be made in accordance with Section 5.6.1. - Part B.

Basis -

Th- monitoring program u lizes 30 sampling location which were selected by con-sidering the projecte anticipated releases of radioef ents., site meteorology, population distrib ion and appropriate pathways having a ignificant potential for radiation e osure to biota and man.

Media which rst show changes in radicactivity are sampled mos frequently. Those which are ess affected by transient changes but are expected to s v long-term ace ' tion are sampled at longer intervals.

The pecifications and effluent monitoring requirements in Section 2.h ' dioactive fluents" insure that releases of radionuclides in liquid and Easeous effl ents J

3.2-1 .

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ENVIRONMENTAL RADI .3ICAL MONITORING CALVERT CLIFFS NUCLEAR POWER PLANT TYPE OF SAMPLE SAMPLE POINT SAMPLE SAMPLE POINT DESCRIPTION FREQUENCY ANALY818 R NARKS Fich 1 Commercial pound nets Quarterly Flesh Edible pecies vill be south of Cove Point (if availabic) Camma rpectrum som ed from the catch made

. Bone a Commercial Fisherman.

Br-89. -90 Shellfish 3 Kenwoo eache Qustterly Flcsh The location of crab samples may oycters (3. 5) le Rocky Poi Gamma spe um vary depending upon their availa-crs.bs (3. 3. PS) 4 5 Camp Conoy . bility. samples vill be collecta PJ' Plant' site - N th of during the blue crab season. A Station (8) and v t ."

reasonable effort vill be made to of Station (7) ,

obtain samples.

Bottom Sediments 5 Camp Conoy miannu y Br-90 6 Iong Beach camma spectrum 7 Plant outfall area 8 Plant intake area Bay Water 7 Plant outra11 area Monthly amma spectrum Sr-89. -90 on quarterly composite 8 Plant intake are titum Gr- -90

.recipitation IS On site cation Monthly ' Gross bet H3 H3 in iuarterly l composite samples Caneta spect Sr-89. -90 on quarterly composite 1 Gr-89. -90 All analyses sub.1ect to sufficier sample collection.

Ground Water 2 Chesapeake Country Q1ub' Quarterly Camma spectrum On'aite well

^

1 Tritium 1 ,long Beache 25 White Sands Clube

.. g n

e nble 3 2-l (5s./) .

TABLE 3 2-1 . hoet 2) (j -

ENVIRONMENTAL RADIOLOGICAL IONITORTNG CALVERT CLIFFS h11 CLEAR POWER PLANT.

TYPE OF LE SAMPLE POINT SAMPLE FREQUENCY ANALYSIS RD4 ARKS SAMPLE POI DESCRIPTION Air Iodine 17, 18 site locations Continuous I-131

20 Lu collection-23 Taylo Island

cartridge .

change weekly 11, 12 'On site locat no Semiannually Camma spec tus Soil 13 - Sr-90 .

a spectrum Predominant' food crops (corn and getation 11: On site location . At harvest ,

C small grains) will be sampled

15. 16 nearby farms ime r-89 -90 at harvest time. Corn stalks, if used as a fodder, will also be sampled. Pasture and forage are to be sampled at Sample Point 16 monthly when the cows are on pasture and analyzed for gamma spectrum. Sr-89 -90. ,

! 'k 16 Nearby farm Monthly -

I-131 Samples-will be collected when 30 local stor pasteur- Gamma spe rum milk is available from location in town of Sr-89 -90 16. Twice a yen c(at the be-ized mi Lusb r St. Leonard ginning of and midwey through the pasture season) surveys vill e made of the area to determine i ny cows are being pastured at 1 tions nearer than Sample Point 1 If cows are found, samples of -ilk vill be obtained for these lo tions and analyzed

,' ~

- as required for ample Point 16.

Rooted atic 29 Flag Ponds area Semiannually Camma spectrum Sampics will be coll ted when Pc l 8 (6Pring & Sr-09. -90 rooted aquatic plants a availah fall)

A W A C)/ M d W T 2.

6 - _

g

.~a .o . - .oum .s o

['d )'

ENVIRONMENTAL RADIO ICAL MONITORING '

~ "

CALVERT CLIFFS NUCLEAR POWER PLANT TYPE OF SAMPLE SAMPLE POINT SAMPLE

- SA!!PLE INT DESCRIPTION FREQUENCY ANALYSIS REMARKS l

Lr particulates 17, 18 On site locations Continuous Gross beta (after 19 otty Pine collection- a minimum of 20 by filter of 72-hour decay 21 Long each cht nge period). Gamma spectrum, Cr-8 22 Cove P t veckly 23 Taylors I and" ,

-90 on quart ly (

,. composite , of veekly amples.

'ntion 7 Plant outfall area . Monthly lent radiation metcra 17, 18, 2h On site locations dose rate L .:rmolumine- 19 Knotty Pine scent) 20 Lusby 21 Long Beach 22 Cove Point '

23 Taylors Island" 25 White Sands Club Sign .

26 St. Leonard 27 Solomons ,

28 Bertha g

>te: (1) Asterisks (* denote control stations *

, (2) An addit al TLD is located in Baltimore and may serve as an additional control. %

for a . ent radiation.

3 b

r .

3

\t g ffACNMSN V b

,\

2 e properly controlled and monitored. The data obtained as a result of t se

..O re, rement v111 er 1t an eva1=ation of tae verforr.ance et the sta=1. in terms O

of onuclides releass.d to the environment.

The e vi naental monitoring program requires sufficient sampling ocations, types of samples d sensitivity of analyses which, with preoperation and background data, vill pro de verification of the effectiveness of stat on radioeffluent control, andndic ion of r.easurable change in radiation d radioactivity levels in the en vire ent, and provide reasonable ass- ce that the design ob-jective releases / doses ecified in Section 2.3 are et exceeded.

e t

9 e +

m g

9 S

e 6

e

9 4

f I

O J

i 3.2-2 E

TABLE 3. 2-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSl$

Lower Lirnit of Detection (LLDie Alstioine Partaculate Fish Meat.

Water or G4 or Pouls.y Mdk Vegeneason Sod Analysas (p(.1/I) (DCi/n I (pCi/k g, wet) (pC4/G fpCs/kg, weg) IpCs/Lg. sja y)

- = _.

gross beta 5

x 10-2 .

3H 330 -

54.tn 8 15 430 '

59 Fe 30 260 S&60 Co 15 1 .

65 2n 30 260 -

S9 Ss 10 10 3 40 0 .

90 sr 2 1 x 10-3 8 O

2 150 05 10 Zr-Nb 33I i .4 7 x 10-2 0.4 ,

80 III 337 '

Cs 15 ,, 1 x 10-2 130 15 150 140 15 Ba-L -15 n

, \ k 8 The nom.siallower flanat os detection as defiwci in HASL 300 (Rev. 8/741, pp. D 08 01.07.03 et the 95% confidence level.The LLD tevels are decay corrected to the e of the sosee sampre n 3 peseod. The LLD for radionuctodes enelyzed by gamme ogwcasornstry wdl wary accordeng to the number of radionuclides encountered an envwonmental samp k y 3 Applies to drinking water only. . [9 u *,

Arrscurar3

, INDEX '

l.IMIT!NG CC"0!T!CNS FOR OPERAT*CN AMD SURVEI'_ LANCE RECU!aEMENTS SECTICN ? AGE 3/4.2 POWER OISTRI30 TION LIMITS 3/4.2.1 LINEAR HEAT RATE'........................................ 3/4 2-1 3/4.2.2 TOTAL PLANAR RADI AL PEAKING FACTOR . . . . . . . . . . . . . . . . . . . . . . 3/ 4 2-6 3/4.2.3 TOTAL INTEGRATED RADI AL PEAKING FACTOR . . . . . . . . . . . . . . . . . . 3/ 4. 2-9 f

' 3 / ; 2- 12 3/J.2.4 A ZIMUTHAL PCW ER T I LI . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4.2.5 O N S P A RAM E T ER S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/42-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTI'IE INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IN S TRUM E NT AT IO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 3 - 10

'3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ........ ........... 3/4 3-25 Incore Detettors ........................................ 3/4 3-29 S e i smi c In s t rume nt a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/1 3- 31 Meteorological Instrumentation . . . . . . . .'. . . . . . . . . . . . . . . . . . 3/4 3-34 Remote Shutdown Instrumentation ......................... 3/4 3-37 <

.Pos t- Accident Instrumentation ........................... 3/4 3-40 l e 3/4 3-43 mrcar_ qg,tgmi tica_Instrumen d<eisainob 'on^~diraikci gtj.grt-. _ - M '.dc. __-.......

'g

,3/2.4 REACTOR COULANT 5fSTEM .

l. 3 / 4 '. 4.1 C00L\NT LGGPS AND CCOLANT CIRCULATION . . . . . . . . . . . . . . . . . . . 3/4 4-1 -

p d

I, S t a r t u p a n d Po w e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/44-1 ;)

Ho t S t a n d b y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/22-?

] 3/11-Za lp a n u t dow n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

'I' 3/1.1.2 3 A F ET Y '/ A L / E 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 1-3 j

l'3/2.4.3 RELIEF 7AL'/E5 ........................................... 2/2 2-4 l

l l l CAL 1ERT CLI??5 - UNIT 1 IV amen; men; No. 3?, 33, 55

! CAL'/ERT CLIFF 5 - UNIT 2 Amendmen: No. 13, 36, 33 1

AfrMMrsr3 to Alc/ Oe loe lo w 5pe ci#ca.4 low fiHes ud Teckn,co.I pacje H of %e U.nlt n 2.

5peci fi coRo a s akere ind,'ca+ed an de< 3/y, 3,3

. a o s'. te<in g ra s +r une a+o.+ie r r <

r v Radios.c4ive. L.iqu;d E fflueni Pfeniloring .Tns4runen+alios T ns+runen +a+ ion. , , , , , , , ,s}q 3-31 P,adioachbe ' Gascoas Effluent M onikiny

< < > nj

r.. ,

Attachmtnt 3 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-1 Dose ............................ 3/4 11-5 Liquid Radwaste Treatment System ............. 3/411-6 3/4.11.2 GASEOUS EFFLUENTS Dose Rate ......................... 3/411-7 Dose-Noble Gases . . . . . . . . . . . . . . . . . . . . . . 3/4 11-11 Dose-lodine-131i and Radionuclides in Particulate Form ............. 3/4 11-12 Gaseous Radwaste Treatment . . . . . . . . . . . . . . . . 3/4 11-13 Explosive Gas Mixture . . . . . . . . . . . . . . . . . . . . 3/4 11-14 Gas Storage Tanks . . . . . . . . . . . . . . . . . . . . . . 3/4 11-15 3/4.11.3 SOLID RADIOACTIVE WASTE . . . . . . . . . . . . . . . . 3/4 11-16 3/4.11.4 TOTA L DOSE . . . . . . . . . . . . . . . . . . . . . . . . 3/411-17 CALVERT CLIFFS UNIT 1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

Attachm:nt 3 9

INDEX BASES SECTION PAGE

.i.

3/4.11 RADIOACTIVE EFFLUENTS 9 3/4.11.1 . LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . B 3/411-1 3/4.11.2 GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . B3/411-2 3/4.11.3 SOLID RADIOACTIVE WASTE ............... B3/411-5 3/4.11.4 TOTAL DOSE ....................... B3/411-5 l

1

- CALVERT CLIFFS UNIT 1 Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

Attachment 3 INSTRUMENTATION -

JRADIOACTIVE LIQUID t.: it,UENT MONITORING INSTRUMENTATION

4

LIMITING' CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in LTable 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensu e 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).

' APPLICABILITY: At all times.

ACTION:

, a. With a radioactive liquid effluent monitoring instrumentation channel e . alarm / trip setpoint less conservative than - required by the above specification, without delay suspend the release of radioacti.ve liquid M -

effluents monitored by the affected channel, or declare the channel y ;,

inoperable, or change the setpoint so it is acceptably conservative,

~'

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the lisstruments to OPERABLE status.within 30 days and, if unsuccessful, explain in the next Semiannual 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.

y9 SURVEILLANCE REQUIREMENTS j-

. 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be fjd!!iy demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, r .# 7 CHANNEL CALIBRATION and CHANNEL FUNCTIONAF TEST operations at the

. U V frequencies shown in Table 4.3-12.

gjf[ <&

n

. s.

py CALVERT CLIFFS UNIT 1 3/4 3-47 Amendment No.

. - CALVERT CLIFFS UNIT 2 Amendment No.

{l~ ..

Q ex

) .

h i,

s a TABLE 3.3-12 .

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

'9_9_

hh GG MINIMUM '

@@- - CHANNELS yg INSTRUMENT OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE -

a. Liquid Radwaste Effluent Line (1) 28 m,

b. Steam Generator Blowdown Effluent Line (1) 29

2. FLOW RATE MEASUREMENT DEVICES y a. Liquid Radwaste Effluent Line (1) 30

. b. Steam Generator Blowdown Effluent Line (1) 30 k

=a nn Attachment 3

. Attachment 3 TABLE 3.3-12 (Continued)

TABLE NOTATION 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 releases

a. - At least two independent samples are analyzed in accordance with

Specification 4.11.1.1.1, and

b. : Atileast two technically qualified members of the Facility Staff

. ' 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the E secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131.

b. At least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months when the specific activity of the secondary coolant is less than 'or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during' actual releases. Pump performance curves may be

- used to estimate flow.

.1 A:

4

.CA'LVERT CLIFFS UNIT it 3/4 3-49 . Amendment No.

CALVERT CLIFFS UNIT 2 ' Amendment No.

g TABLE 4.3-12 .

, RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

E. E h CHANNEL SOURCE CHANNEL FUNCTIONAL

yg INSTRUMENT CHECK CHECK CALIBRATION ' TEST

1. GROSS RADIOACTIVITY MONITORS PROVIDING l ALARM AND AUTOMATIC TERMINATION OF RELEASE i

a. . Liquid Radwaste Effluent Line D P R(2) SA(1)

b. Steam Generator Blowdown Effluent Line D P R(2) SA(1) .

Y

2. FLOW RATE MEASUREMENT DEVICES Y

g a. Liquid Radwaste Effluent Line D(3) N.A. R N.A.

b. Steam Generator Blowdown Effluent Line D(3) N.A. R N.A.

4 na

                 .& .9 Attachment :

F Attachment 3 [ . TABLE 4.3-12 (Continued) TABLE NOTATION i (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation I-of this pathway and/or control room alarm annunciation occur if the appropriate I following 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 CALIBRATION, 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.

        - CALVERT CLIFFS UNIT 1                                    3/4 3-51         Amendment No.

CALVERT CLIFFS UNIT 2 Amendment No.

p

               .-                                                                                                                                                                      Attachment 3 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
                   - LIMITING CONDITION FOR OPERATION 3.3.3.9                                    'The radioactive gaseous effluent morltoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels'shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
                  ' APPLICABILITY: As shown in Table 3.3-13 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 change the setpaint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring -instrumentation channels OPERABLE, take the ACTION i shown in Table 3.3-13. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannuai- 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 4.3.3.9- Each radioactive ' gaseous effluent monitoring instrumentation channel shall

                  - be demonstrated OPERABLE by' performance of the CHANNEL CHECK, SOURCE
                   ' CHECK, CHANNEL CALIBRATION"and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

5 CALVERT CLIFFS UNIT l- 3/4 3-52 Amendment No. L CALVERT CLIFFS UNIT 2 Amendment No. L' - . .

ga TABLE 3.3-13 , RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ' -j n ee a

     '9 '9 j j                                                                   MINIMUM CHANNELS uu                                INSTRUMENT                                      OPERABLE        APPLICABILITY                      ACTION

1. WASTE GAS HOLDUP SYSTEM .l

     "                                                                                                                                                          I

a. _ Noble Gas Activity monitor -

Providing Alarm and Automatic Termination of Release (1)

35

b. Effluent System Flow Rate Measuring Device (1)

36

2. MAIN VENT SYSTEM M= a. Noble Gas Activity Monitor (1)

37 w

h b. Iodine Sampler (1) 38 Particulate Sampler

38

c. (1) k

}}

EE Attachment 3

                                                                                                          ' \-

L__

SE Attachmtnt 3

                                                                                        -TABLE 3.3-13 (Continued) c                                                                                                   TABLE NOTATION
                 "*' At all times.

ACTION 35 - With the number of channels OPERABLE less than required by the

       .                                                                   Minimum . Cnannels 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 analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified cperators 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. L ' 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 activit" 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.

CALVERT CLIFFS UNIT 1 3/4 3-54 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

n TABLE 4.3-13 .- RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ff y y

u. u . INSTRUMENT CHANNEL' SOURCE CHANNEL CHANNEL MODES IN WHICH '

FUNCTIONAL SURVEILLANCE CHECK CHECK CALIBRATION TEST REQUIRED EG

 @@    1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release P P R(3) SA(1) - *

b. Effluent System Flow Rate Measuring Device D(4) N.A. R N.A. *

2. MAIN VENT SYSTEM Y

a. Noble Gas Activity Monitor D M R(3) SA(2) . *'

Y

    $     b. Iodine Sampler                         W          N.A. N.A.            N.A.             *

c. Particulate Sampler W N.A. N.A. N.A. *

}}

E3 Attachment 3

      ,                                                                                                       7
          --                                                                                     Attachm nt 3 TABLE 4.3-13 (Continued)

TABLE NOTATION

tat all times other than when' the line is valved out and locked.

               - (1)    The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation iof this pathway and/or control room alarm annunciation occurs if the appropriate fol:owing condition (s) exists:

11.- Instrument indicates measure levels above the alarm / trip setpoint.

2. 1 Circuit iallure.

3. Instrument indicates a downscale failure.

(2) 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 tte system Lwithin 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.

CALVERT CLIFFS UNIT 1 3/4 3-56 Amendment No.

             ' CALVERT CLIFFS UNIT 2                                                          Amendment No.

L

y Attachmsnt 3 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS

CONCENTRATION

LIMITING CONDITION FOR OPERATION 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 II, Column 2 for radionuclides other than dissolved or entrained.

noble gases.)

               ~ APPLICABILITY: At all times. -

Y - 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 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. 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. s e-CALVERT CLIFFS UNIT 1 3/4 11-1 Amendment No.

             . CALVERT CLIFFS UNIT 2                                                      Amendment No.

t-

Attachmtnt 3 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit

                                           - Minimum                                              of Detection
    -   Liqpdype        Release .           greq  en g amglin    greq   ency nalgsis            Type of Activity         (LLD)a Analysis            (uCi/ml)

A, P P Batch Wgste Releases . ' Each Batch Each Batch Principal Gamma 5x10-7 Emittersc I-131 lx10-6 Mo-99, Ce-144 2x10-6 P M H-3 1x10-5 Each Batch Composited Gross Alpha lx10-7 Each Batch Composite d Sr-89, Sr-90 5x10-8

       ~ B.           Turbine Building          M           M          Principal Gamma               5x10-7
                   ' Sump                                              Emittersc I-131                         lx10-6 Mo-99, Ce-144                 2x10-6 i

CALVERT CLIFFS UNIT 1 3/4 11-2 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. l=

i t AttachmGnt 3 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 yleid 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 = 4.66sb E* V

2.22 x 10 6 . y .

exp ( Aat) Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sh'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, Y is the sample size in units of mass or volume, 2.22 x'106is the number of disintegrations per minute per microcurie, cY is the fractional radiochemical yleid, when appilcable, Als 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 priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(after the fact) limit for a particular measurement. 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. CALVERT CLIFF 5 UNIT 1 3/411-3 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. e_______-_______--__-____ - --_-- _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ -

i: Attachment 3 (? TABLE 4.11-1 (Continued) TABLE NOTATION c The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-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 analyzcd and reported in the Semlannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8. d A composite sample is one in which the quantity of i!qold sampled is proportional to the quantity of liquid waste discharged in which the nethod of samp!!ng employed o results in a specimen that is representative of the liquich released. l CALVERT CLIFFS UNIT 1 3/4 11-4 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. I .__ . . _ - - , - . - .- _ . _ _ . _ _ , , _ - . _ -.- _ - _ -_ _. _ - _ -_- _ _ __

o. AttachmGnt 3'

_c 4 (

                        . RADIOACTIVE EFFLUENTS .

t DOSE ' LIMITING CONDITION FOR OPERATION , 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.L - During any calendar quarter to less than or equal to 3.0 mrems to the total body

                                                   ' and to less than or eque. 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 mat '.als in liquid                                                                 r

,, effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective , actions that have been taken to reduce the releases and the proposed corrective - actions to be taken to assure that subsequent celeases 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 i l' 1-l- CALVERT CLIFFS UNIT 1 3/4 11-5 Amendment No.

                       - CALVERT CLIFFS UNIT 2                                                                                                          Amendment No.

f' r b t

         --- .,    y  . - - . _ . . _ . , , , . , . , _ . , _ _ . . . , _ , .    .   ,,._._,,,,_....m,...y_y,..-              . . . . _7,,.      ,,,y.__,,,_             my.y---r-

y _ n 7 g. _ Attachm::nt 3 IRADIOACTIVE EFFLUENTS

                                                     ' LIQUID RADWASTE TREATMENT SYSTEM t z LIMITING CONDITION FOR OPERATION
  -: ~                                                                                                                                                   ,

1

3.11.l.3 The liquid' radwaste- 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, t APPLICABILITY: At all times.- ACTION: . a.. With radioactive liquid waste being discharged without treatment and in excess of the above .llmits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

1. - Explanation of why liquld radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and

                                                                          .the reason for the inoperability, l 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. CALVERT CLIFFS UNIT 1 3/411-6 Amendment No. j- CALVERT CLIFFS UNIT 2 Amendment No. I i

(

     ~2 Attachm:nt 3

[ .

           ' RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS I            DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 .       The dose rate due to radioactive materials released in gaseous effluents from-the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

a. - For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. For lodine-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 lodine-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 specified in Table 4.11-2. CALVERT CLIFFS UNIT 1 3/4 11-7 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYS5 PROGRAM E E Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)a h Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)

         %                                    P             P
         "   A. Waste Gas 3toragef '8    Each Tank     Each Tank   Principal Gamma Emittersb      1x10-4 Tank                    Grab Sample               (Gaseous Emissions Only) ll 88                                      P             P mH     B. Containment Purge       Each Batche  Each Batchc  Principal Gamma Emittersb      1x10-4 and Vent                Grab Sample               (Gaseous Emissions Only)

C. Main Vent M Mc Principal Gamma Emittersb lx10-4 Grab Samplec (Gaseous Emissions Only) Continuousd M H-3 lx10-6 Y x-p Continuousd W I-131 lx10-12

Charcoal Sample
Coatinuousd W Principal Gamma Emittersb lx10-II Particulate (I-131, Others)

Sample

Continuousd M Gross Alpha lx10-II Composite Particulate Sample 3D Continuousd Q Sr-89, Sr-90 lx10-II kk Composite SS Particulate gg Sample Continuousd Noble Gas Noble Gases 1x10-6 Monitor Gross Beta or Gamma Attachment 3

- J

m y y Attachment 3 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 yleid 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' V

2.22 x 10 6 . y .

exp (- Aat) Where LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting

                     - rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yleid,' 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 ' a t 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 posteriori(after the fact) limit for a particular measurement. CALVERT CLIFFS UNIT 1 3/4 11-9 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. t_--------________-

   ..                                                                                 Attachm:nt 3 TABLE 4.11-2 (Continued)

TABLE NOTATION b The principal gamma emitters for which the LLD specification applies exclusively are the following radlonuclides: 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, 2n-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 Seminannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8. c 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 EQUIVALENT 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 accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours af ter changing, or af ter removal from sampler. When sample collection time is less than seven days, the corresponding LLDs may be increased by a proportional factor. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary 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.

I Waste Gas Decay Tank samples shall be collected and analyzed for oxygen once per week on the in-service 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 times. 8 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 uC1/ml. CALVERT CLIFFS UNIT 1 3/4 11-10 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. E.-______-..__-_-. _- - . - - . - - - - - --

1 Attachm:nt 3 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

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, e

b. During any calendar years Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.

APPLICABILITY: At all times. ACTION: 7

a. With the calculated air dose from radioactive noble gases in gaseous ef fluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compilance with the above limits,

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 currect calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days. CALVERT CLIFFS UNIT 1 3/4 11-11 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

1

 ,                                                                                                   Att chmtnt 3
                  - RADIOACTIVE EFFLUENTS g                       DOSE -IODINE-131 AND RADIONUCLIDES IN PARTICULATE FORM i

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC ~ from lodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) 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 years Less than or equal to 30 mrems to any organ,

c. Less than 10% of the limits of 3.ll.2.3(a) and (b) as a result of burning contaminated oil.

APPLICABILITY: At all times. ACTION:

a. With the calculated dose from the release of lodine-131 and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding 2ny of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the 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 current calendar year for lodine-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. CALVEdT CLIFFS UNIT 1 3/4 11-12 Amendment No. , CALVERT CLIFFS UNIT 2 Amendment No. ;

c- , Attrchment 3 RADIOACTIVE EFFLUENTS

            - GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4         The GASEOUS RADWASTE TREATMENT SYSTEM 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 doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) 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 (see Figure 3.1-1) exceeds 1.8 mrem to any organ in a 92 day period.

APPLICABILITY: At all times.

            ~ ACTION:
                            - a. With gaseous wam being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, 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.

SURVEILLANCF, REQUIREMENTS 4.11.2.4.1 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. CALVERT CLIFFS UNIT 1 3/4 11-13 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

o

       = J.

Att chment 3 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen rich systems not designed to withstand a hydrogen explosion) LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited 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 thea 4% by volume immediately 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.

l b. The provisions of Specifications 3.0.3 and 3.0.4 are not app!! cable. SURVEILLANCE REQUIREMENTS 4.!!.2.5 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by the sampling program described in Table 4.11-2. l CALVERT CLIFFS UNIT 1 3/4 11-14 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

e e Attachment 3 RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 58,500 curles noble gases (considered as Xe-133). APPLICABILITY: At all times. ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately 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 4.11.2.6 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 uCl/ml. CALVERT CLIFFS UNIT 1 3/4 11-15 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

r

                                                                                                   ' Attachment 3 RADIOACTIVE EFFLUENTS SOLID RADIOACTIVE WASTE
 ,                 LIMITING CONDITION FOR OPERATION 3.11.3         The solid radwaste program shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.

APPLICABILITY: At all times. ACTION:

a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid -

radioactive wastes from the site.

b. The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 THE' PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator

                 . bottoms, boric acid solutions, and sodium sulfate solutions).

i CALVERT CLIFFS UNIT 1 3/4 11-16 Amendment No. l CALVERT CLIFFS UNIT 2 Amendment No.

Attachm:nt 3 RADIOACTIVE EFFLUENTS TOTAL DOSE LIMITING CONDITION FOR OPERATION 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 thyrold, which shall be limited to less than or equal to 75 mrems. APPLICABILITY: At all times. ACTION:

a. With the calculated do:ics from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.ll.l.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.ll.2.2.b, 3.ll.2.3.a, or 3.ll.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, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 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 sha!! also describe levels of radiation and concentrations of radioactive materlal 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 CPR Fart 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of 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.!!.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 unty under conditions set forth tn Specification 3.11.4.a. CALVERT CLIFFS UNIT 1 3/411-17 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. t s

Attachment 3 INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this Instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3.ll.2.1.a based on average annual X/Q. The OPERABILITY and use of this Instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. CALVERT CLIFFS UNIT I B 3/4 3-4 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

Attachment 3 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS _. 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population. i The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K.,

                           " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of tascactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ' dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of 1 MEMBER OF THE PUBLIC through appropriate pathways is enlikely to be substantiale, underestimated. The equations specified in the ODCM for calculating the - - doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977, Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". ' CALVERT CLIFFS UNIT 1 B 3/411-1 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. kN

                                                                                                                     ,. oy

Attachment 3

                                                      -RADIOACTIVE EFFLUENTS BASESb47-c 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM                                                      ;
                ~
                     ' The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be ktpt "as low - as . is reasonably achievable". This specification implements _ the               ;

requirements of.10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is'provided to ensure that the dose at ar. .me at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the, doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in th( exposure of'a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, exceeding the !!mits specified in Appendix B,

                     ' Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). For .02MBERS OF THE PUBLIC who may at. times be'within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric
                      ' diffusion factor above that for the SITE BOUNDARY.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300,

               -       Currie, L. A.,'" Limits for Qualitative Detection and Quantitative Determination -
                      - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K.,
                       " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

CALVERT CLIFFS UNIT 1 B 3/411-2 Amendment No.

     *              . CALVERT CLIFFS UNIT 2                                                              Amendment No.

L

i? -

                                         -,     -a..          -

                -                                                . . . -  . . .    .- .         ~_        -
          ,                                                                                          Attachmtnt 3 RADIOACTIVE EFFLUENTS BASES (Continued) ~

3/4.11.2.2 ' DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and

. IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set _ forth in Section II.B of Appendix I. The ACTION statements provide the require? operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materialin gaseous
. effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section llI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways ' unlikely to be substantially underestimated. The dose calculation methodology _ and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent' with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the t)urpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision
--1, . July 1977, and NUREG-0133 " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

4 The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical annual average atmospheric conditions. 1 CALVERT CLIFFS UNIT 1 B 3/411-3 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

    ._            _         _ _ _ __. _ _ ~. _ . _ - _ _ _ . . . _ . .                  _ _ _ _ _             _-_ _ . _ ,_

Attachment RADIOACTIVE EFFLUENTS BASES [ M ^ 3/4.11.2.3 DOSE -IODINE 131 AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth'in Section II.C of Appendix I. The ACTION statements provide the 2 required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous , . effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." " The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of ' Appendix I be shown by calculational procedures based.on models and data, such that the +- actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with' the methodology provided in Regulatory Guide 1.109,

                             " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October.

1977, 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, and NUREG-0133 , " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". These equations also provide for determining the actual doses based ~ upon the historical annual average atmospheric                                                                    !

conditions. - The release rate specifications for lodine-131, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing

                          - radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were:                                                          1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas                                                                   '

where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The requirement that the appropriate portions of these systems be used, when specified,

                         ' provides . reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design

                          ' Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ILD of Appendix I to 10 CFR Part 50. The specified limits governing the use of
                          ,  appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

c; CALVERT CLIFFS UNIT 1 B 3/411-4 Amendment No. CALVERT CLIFFS UNIT 2 Amer-iment No. 1 1

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Attachment 3 U ' RADIOACTIVE EFFLUENTS BASES h% % ed)' 3/4.11.2.5 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 Ult of oxygen.                                      Maintaining the concentration of oxygen below its flammability limit provides assurance that the releases of radioactive materials will be                                                                      l controlled in conformance with the requirements of General Design Criterion 60 of
                  . Appendix A to 10 CFR Part 50.
                 '3/4.11.2.6 GAS STOR AGE 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 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 10 CFR 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 J resulting ~ total body exposure ;to - a MEMBER OF THE PUBLIC at the nearest SITE
                 ~ BOUNDARY will not exceed accident guidelines.
                 ' 3/4.11.3 SOLID RADIOACTIVE WASTE .
                            ~

,' This ' specification implements the requirements of 10 CFR Part 50.36a and General design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters are , included in the PROCESS CONTROL PROGRAM. 3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have

                 -been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or. any organ, except the thyroid, which shall bc limited to less than or equal to 75 Lmrems. : The Special Report'will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part L190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible.

_ .CALVERT CLIFFS UNIT 1 B 3/411-5 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. y r w - , 4 y , . , , - - - , . , ~ - . . .,.-+,,-,e.m.--.-,,-.. -m- ,-4,-,-,-.r.,,-.y-,, , , - ---,-,-sv .--~,-.------,.-,.-w--e 4.cr,--, , ,~

                 ;                                                                                                                     Attachmtnt 3
         ~

RADIOACTIVE EFFLUENTS BASES

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of l

                         . 40 CFR Part 190, the Special Report with a request for a variance (provided the release                                   i conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in
                         . accordance with the provisions of 40' CFR .Part 190.11 and 10 CFR Part6 20.405c, is                                       '
                         . considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until
                        . NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in

carrying out any operation that is part of the nuclear fuel cycle.

c h

 '71I e

i E CALVERT CLIFFS UNIT 1. B 3/411-6 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

a 4 ' f, ifWACN!45M 3 ADMINISTRATIVE CONTROLS MEETING FREQUENCY " - -6,5.1.4 The POSRC shall meet ~at least once per calendar month and as convened by the POSRC Chairman'or his. designated alternate. QUORUM 6.5.1.5 A qu~orum of the POSRC shall consist of the Chairman or his designated alternate and four members including al ternates. RESPONSIBILITIES 6.5.1.6. The POSRC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety. .

b. Review of.all proposed tests and experiments that affect -

nuclear safety. .

c. _ Review of all proposed changes to Appendix "A" Techni_cil'

 ' ' .v                           . Specifications.                  :

d. Review of all proposed changes oi modifications to plant systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications ,

including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager - Nuclear Power Department and to the Chairman of the' Off Site Safety Review Committee.

f. Review of all REPORTABLE- EVENTS.

l

                             .g. Review of facility operations to detect potential safety hazards.
                             'h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Sa fety Review Commi ttee.
                             -1. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off Site Safety                ;

Review Committee.

j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Of f Site Safety Review

                                 . Cy mittee                   , - ,               ,-             .

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                                     .Tnsert Par ^fAf hS ' k *nd I Sf " ^ItA C here.

WV CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 25, 20. 9 , 94 cALVKAT ~ CLIFF 5T -(ANIT 1 Af endgent go, p( /g 7g

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       .T.N5 6 AT       TV1f    foLL0wtNL IN fort n AftbH AS PM A -

GRAPHS k. &n I. unDGA TECHulCA L SPEtt ricA71M L . C. I . & , PAG 6 6-7: W .

k. Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3 includind the preparation of reports covering evaluation, recornmendations and disposition of the corrective )

action to prevent recurrence and the forwarding of these reports to 4 the Plant Superintendent and the Off-Site Safety Review Com- ! mittee.

1. Review of changes to the PROCESS CONTilOL PilOGRAM and the OFFSITE DOSE CALCULATION MANUAL. q Y

d CCC M

7_ j' Aff7NCHMOT ] 4 ADrilNISTRATIVE COMTROLS L AUDITS 6.5.2.8.1 Audits of-facility activities shall be performed under the cognizance [ of the OSSRC. These audits shall. encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months,

b. The performance, training and qualification of the entire facility staff at -least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that af fect nuclear safety at least once per 6 months.

d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e. Deleted - 3

f. The Safeguards Contingency Plan and implementing procedurej_ at least 'G o'nce per.12 months in accordance wi_th 10 CFR 73.40(d). .

s.. .

g. Any other area of facility operation considered appropriate by the OSSRC or the Vice President-Supply,

h. .The Facility Fire Protection Program and implementing procedures .

at least once per 24 months,

i. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licens~ee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant a t l ea s t _o.n c a *r 16 p ths. u m me ZHECAT 'PANANltheft g, t, rn end n Men ATfMN6b JMf T s ^

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MGM 6.5.2.8. ..eview oFfacility activities snaR~fi pirTo"rmed ubMr the cognizance of 'the OSSRC. These reviews shall encompass: 2;

a. The Facility Emergency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR Part 50.54(t). d>

             ..         AUTHORITY                                                                      .,.    .

! 6.5.2.9 The OSSRC shall report to and advise the Vice President-Supply on _ l those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. ,- CALVERT Cl.IFFS - UNIT 1 6-11 Amendment No. 26,82 CAtMRT CufM - urn? 2. kendment tio. k th

f , A T AVC//M E W 3

e Z NS CK'T Tf46 f6 L G O M IrJ G P&CAG R APM K., D ., rn , n, unoER TECH NICA L SPECtflCATtM

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PACE ( -I(: f T 'q

k. The radiological environmental monitoring program and the results thereof at least once per 12 months.

1

1. The OFFSifE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

., m. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

n. The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.

        .t; e

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^ ... V )$W)90YMfM .3 ADMItilSTRATIVE C0t:TROLS

    '~                 6.7     SAFETY LIMIT VIOLATION.

6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STA!!DBY within one 1 hour.

                              .b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager - iluclear Power Department and the OSSRC shall be notified within 24 hours.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation. Report shall be submitted to the Commission, the OSSRC and the Manager - Uuclear Power Department withi;.14 days of the viola tion.

6.8 PROCEDURES .- ,

1*

   ;                    6.8.1      Written procedures shall be establishedT implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide l .33 Ravision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation. -

f. Fire Protection Program implementation.

g. The amount of overtime worked by plant staff members performing . $.

safety related functions must be limited in accordance with the 5

                  ~e RC Polic Statement on workin ho rs (Generic Letter No. 82-12).                     $

Z~NCCRT MMGMMS h Md A from AffM@ts sitccr Henf } ^ 6.8.2 Each procedurehe p^o t icy of 6.i3.1 Tbove' and changes thereto shall be reviewed by the POSRC and approved by the Plant Superin-tendent prior to implementati.on and reviewed periodically as set forth 'in " administrative procedures.

          /                           ,

CALVERT CLIFFS - UtilT 1 6-13 Amendment :;o.26, .4, 73,82 CAIMECf Cliffs - Unr1 2. Agendment No j{, jf, f t,5 e

1

s I l l. ZNSERT 77t[ s'o t L U NING IN fodr'llTieri A l'AAACAAAAS h.and i unc E A Tid 3 NIC A L SPL C o fic HTltrl !<. f. ) 55 N ~lb

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                                   /                                                                                                 s
                                  ' h.                PRocEs3 CONTRCL PROGRAM i plementatien.                                          )

N A. CFF51TE DCSE CALCULMION MANUA'_1::alementa:. ion. i

                                \                                                                                                           ,

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          ,                                                                                   Attachment 3 ADMINISTRATIVE CONTROLS 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 Commission, Washington, D.C. 20555, ATTN: Document Control Desk, with a copy to the Regional Administrator and to the NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL' ENVIRONMENTAL OPERATING REPORT *

            - 6.9.1.7 -       Routine Radiological Environmental Operating Reports covering the
            . operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretatlobs,' and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.' The reports shall also include the results of land use censuses required by Specification 3.12.2. The- Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation

measurements taken during the period pursuant to the locations specified in the Table and Figures in~the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch

            . Technical Position,' Revision 1, November 1979. In the event that some individual results
            . are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as
            - soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the central point between

            ' the two containment buildings; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD
             . required by Table 4.12-1 was not achievable.

CALVERT CLIFFS UNIT 1 6-16 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

Attachment 3 ( - ADMINISTRATIVE CONTROLS The Annual Radiological Environmental Operating Report will include the identification

            . of the cause of unavailability of samples (if any), and will describe the locations used for the replacement samples. The report will also include any permanent changes in the sample locations which could appear in the monitoring program. It willinclude a revised figure (s) and table for the ODCM reflecting the new location (s).

A single submittal may be made.

             ** One map shall cover stations near the site boundary; a second shall include the more distant stations.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 . Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6

           . January 1 and July 1 of each.,rponths of operation shall be submitted within 60 days after The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include 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 oignt frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the. unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). i

A single submittal may be made for Calvert Cliffs, since the radwaste systems are common to both units.

             **     In lieu of submission with the Semi-Annual Reports, Sr89, Sr90 analyses results may
                   . be submitted in a supplementary report within 120 days after January 1 and July 1 of each year.
             ***    In lieu of submission with the first half year Radioactive Efflaent 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.

           - CALVERT CLIFFS UNIT 1                                                                  6-17                                       Amendment No.

l CALVERT CLIFFS UNIT 2 Amendment No. l t L > a ._, _ . . . _ _ . _ _ _ _ _ _ _ . _ , _ _ _ . . __ ._, _ . _ . . . , _ _ _ _ _ _ _ _ _ , . , , . _ _ _ _ ,

r y Attachment 3 ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) The Radioactive Effluent Release Report to N submitted 60 days after January 1 of

            ' each year shall also include an assessment of radiation doses to the likely most exposed
            -MEMBER.OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar. year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

The Radioactive Effluent Release Reports shall include the following information for each class of solid wastei (as defined 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 agent or absorbent (e.g., cement).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in i gaseous and liquid effluents made during the reporting period. , The Radioactive Effluent Release Reports shall include any changes made during the 2' reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose

calculations identified by the annual land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix D,10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 within

the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference
specification

l l . CALVERT CLIFFS UNIT 1 6-18 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. l ( L-

           ,                                                                                             Attachm:nt 3 -                    ,
         ~
      ,.                                                                                                                                   l l

ADMINISTRATIVE CONTROLS

a. .ECCS Actuation, Specifications 3.5.2 and 3.5.3.

I b.- Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3. c. Inoperable Meteorological, Monitoring Instrumentation, Specification 3.3.3.4.

                    ' d.      Seismic event analysis, Specification 4.3.3.3.2.

e. - Core Barrel Movement, Specification 3.4.11.

f.~ - Fire Detection Instrumentation, Specification 3.3.3.7.

                    . g.      Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4 and 3.7.11.5..

h. ' Penetration Fire Barriers, Specification 3.7.12.

i. , . Steam Generator Tube Inspection Results, Specification 4.4.5.5.

J.' Specific Activity of Primary Coolant, Specification 3.4.8.

k. Containment Structural Integrity, Specification 4.6.1.6.

1. Radioactive Effluents - Calculated Dose and Total Dose, Specifications

- 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.I1.4.

m. Radioactive Effluents -

Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.2 and 3.11.2.4.

n. Radiological Environmental Monitoring Program, Specification 3.12.1.

r CALVERT CLIFFS UNIT 1 6-19 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No.

c l

             %                                                                                     *      'i a

ADMItlISTRATIVE C0t1TROLS v

d. Records of radiation exposure for all individuals entering radiation control areas.

e. Records of gaseous and. liquid radioactive material released to the environs,

f. Records of transient or operational cycles for those facility

                          ' components identified in Table 5.7.1.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of- Quality Assurance activities identified in the NRC approved QA Panual as lifetime records.

j. Records of' reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. _

k. Records of meetings of the.POSRC and the OSSRC. .,

      -               1. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.
         .            m. Records of the service lives .of all snubbers listed on Table 3.7-4 7 including the date at which the service life commences and associated   #[

install _ation 2nd maintenamce__ratcor_ds

                        &claf naa]up5_n. on arracus saar nue 6.11     RAllATION PROTECTION PROGRArt Procedures for p~ersonnel radiation protection shall be prepared consistent ~

with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA . 6.12.1 In lieu of the " control-device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:

a. A high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as -a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individua.ls .

         -                   permitted to enter such areas shall be provided with a radiati6'n monitoring device which continuously indicates the radiation
     -                       dose rate in the area.

CALVERT CLIFFS - UNIT 1 6-20 Amendment No. 8 4 CALVW CWfs - uno-r 2,- fyrsenbrut No. % a

  /             :                                               a.:

Ar7WCHMENT 3 3~MsE M 1hd rottouwc enit Acwa Arrea. 17tn "m: on Pa3e. G -2 0 :

                            . (t s, 4.to. 2)
                                                                                           <           v

n. Secord5 o f ana(yses ceguired by -}he. radio-legica i en oian nen+n I rno nifa cin<, progrs m.

As.t wonId permit evalualion o4 the accuracy of the snalysis a t s. Idee da le , Tht.c should include precedures effecAive s.t specified fines and d) A records showing that thest procedures we re followec/. b u- A l' 4 4

      . . . . .   - ., _.       ,       n   ,   . . - - _
                                                            ,,.,,-..-.,,..v.-...,,,..-n..,   , _ . . - - . - . - - , - ~ , , - , , - , , , , , , , - , , . , . . , . , . , - - . , . _ -

AttachmGnt 3

  ~I       ADMINISTRATIVE CONTROLS 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1   The PCP shall be approved by the Commission prior to implementation.
         - 6.16.2 , Licensee initiated changes to the PCP:

1. Shall~ be. submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

This submittal shall contain:

a. An evaluation supporting the premise that the change did not reduce

                               - the overall conformance of the solidified waste product to existing criteria for solid wastes; and

b. A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to the POSRC.

2. Shall become effective upon. review and approval by the responsible Nuclear Power Department unit and approval of Plant Superintendent.

         ~6.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1    The ODCM shall be approved by the Commission prior to implementation.

(6.17.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

a. ' Sufficient information to support the rationale for the change.

Inforrration submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a change number and/or change date together with appropriate analyses or evaluations justifying the. change (s); y

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the POSRC.

2. Shall become effective upon review by the POSRC and approval of the Plant Superintendent.

CALVERT CLIFFS UNIT 1 6-24 Amendment No. CALVERT_ CLIFFS UNIT 2 Amendment No.

e-Attachmtnt 3 9 ADMINISTRATIVE CONTROLS 6.18 MA3OR CHANGES TO RADIOACTIVE LIQUID, GASdOUS AND SOLID WASTE TREATMENT SYSTEMS , 6.18.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Semiannual 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 reviewed and found acceptable by the POSRC.

                                                                                               ..e .

CALVERT CLIFFS UNIT 1 6-25 Amendment No. CALVERT CLIFFS UNIT 2 Amendment No. F'

                     ? . ,e                                                           ., .,

v;, p 4;= -

                                                      ,.          ,    AWAO/MSNY S
      -                                             ,e CALVERT CLIFFS NUCLEAR PCWER PLANT                   -

UNIT NOS, 1 AND 2 - APPENDIX 3

                                            ? ART I ENVIR0hMENTAL TECHNICAL SPECIFICAi!0NS FACILITY OPERATING LICENSE NOS. OPR-53 AND OPR-69 l'  bWW gppgn sl g a PA AT 1 In iSs LN TI ACTY.

ISSUED BY THE U. S. 'iUCLEAP. REGULATORY CCMM135'^N Mene.en: No . 23, 70 Calver: Clif fs Unit 1 M endment No. 7, 53 Calvert Clif fs Unit 2-

r l l l l l i ATTACHMENT (4) OFFSITE DOSE CALCULATION MANUAL (ODCM) I CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE GAS AND ELECTRIC COMPANY i l l l l i l'

I I ODCM TABLE OF CONTENTS PAGE 1.0' SETPOINTS 1 2.0 RADIOACTIVE LIQUID EFFLUENTS 4 2.1 Processing Equipment and Flow Paths 4 2.2 Liquid Effluent Concentrations 4 2.3 Liquid Effluent Dose 5 3.0 RADIOACTIVE GASEOUS EFFLUENTS 13 3.1 Processing Equipment and Flow Paths 13 3.2 Gaseous Effluent Concentrations 13 3.3 Gaseous Effluent Dose Rate 14 3.4 Gaseous Effluent Dose 16 3.5 Camp Conoy/ Visitors Center Dose' Evaulation 24 4.0 40 CFR 190 COMPLIANCE 25 5.0 RADWASTE SYSTEM MODIFICATIONS 26 L 6.0 ENVIRONMENTAL MONITORING 27 (-

t. '

a )

l o ) l ODCM LIST OF ATTACHMENTS ' Attachment (1) Dose Factors for Noble Gases Attachmmt (2) Radioactive Effluent Monitoring Instrumentation Attachment (3) Radioactive Liquid Waste System Attachment (4) Liquid Effluedts Dose Conversion Factors

         ' Attachment (5) ' Liquid Effluents - Adult Dose (Fish and Shellfish Pathway)

Attachment (6) Radioactive Gaseous Waste System Attachment (7) Gaseous Effluents - Pathway Dose Parameters Attachment (8) Gaseous Effluents - Effective Dose Factors (Noble Gases) Attachment (9) Locations of Environment Sampling Sites Attachment (10) Map'of Environmental Sampling Sites (10 mile radius) Attachment (11) Map of Environraental Sampling Sites (2 mile radius) t- j

1 9 OFFSITE DOSE CALCULATION MANUAL 1.0 SETPOINTS 1.1 _ Liquid Effluents 1.1.1 In accordance with the requirements of Technical Specification 3.3.3.10, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the concentration of radioactive material released in liquid effluents does not exceed the limits of 10CFR20 Appendix B, Table II, Column 2. 1.1.2 The setpoint shall be established taking credit for operation of five of the twelve circulating water pumps in accordance with the liquid waste processing description in the Final Safety Analysis Report (FSAR). 1.1.3 Setpoint shall be determined as follows: SP = (A gx RMS Responsei) x Dilution Water Flow Rate + Bkgd Discharge Flow Rate Where: i SP = Setpoint (cpm) Ag= Specific Activity (uCi/ml) of radionuclide i as defined in the Final Safety Analysis Report (FSAR) for Liquid Waste. The radionuclide mixture shall include I-131 (95%), Cs-134 (0.5%), Cs-137 (1.5%), Co-58 (2.2%) and Co-60 (0.25%). The actual uCl/mi shall be determined using the appropriate MPCs as defined in 10CFR20 Appendix B, Table II, Column 2. RMS Response g = Monitor sensitivity (cpm /uCi/ml) for radionuclide 1 1

r ,

           .     . Dilution Water Flow Rate = Dilution from 5 circulators (IE+06 gpm)

Discharge Flow Rate = Maximum liquid effluent flow rate into circulating water (gpm).

a. Liquid Waste (120 gpm)

b. Steam Generator Blowdown (225 gpm per generator)

Bkgd = RMS background level (cpm) 1.2 Gaseous Effluents 1.2.1 In accordance with the requirements of Technical Specification 3.3.3.11, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the dose rate due to radioactive materlats released in gaseous effluents does not exceed 500 mrem /yr (total body) or 3000 mrem /yr (skin). 1.2.2 Setpoint shall be de'termined as follows: SP = [(A x RMS Response ) n

                                                                  +  Bkgd (K/q) x (F)

Where:

SP = Setpoint (cpm) Ag= Specific Activity (uCl/ml) of noble gas radio nuclide I as defined in the Final Safety Analysis Report (FSAR) for the radionuclide mixture of

 .                                               Xe 133 (95%), Xe 135 (4%) and Kr 88 (1%).

(Refer to Section 1.2.3) RMS Reponseg = monitor sensitivity (cpm /uCl/ml) for radionuclide 1 i X/Q = average annual meteorological dispersion based on 1983 meteorological data (2.2E-06 sec/m3 ) J

s

     ; - s-F = System flow rate for release point radiation 3

o monitor (m /sec) Bkgd = RMS background level (cpm) 1.2.3 ' The total body dose rate conversion factors (Attachment 1) shall be used to calculate the nuclide concentrations since they are more restrictive than the skin dose factors for the radionuclide mixture of interest, described in the FSAR. 1.2.4 The main vent setpoints shall be set to ensure that simultaneous releases from both U-l and U-2 Main Vents do not exceed established dose limits at the site boundary. 1.3 The radiation monitor response (cpm) for effluent releases shall be predicted using prerelease data as follows: cpm = (A; x RMS response g) + Bkgd x 1.5 Where: Ag= Specific Activity (uCl/ml) RMS Response; = (cpm /uCl/ml) for each isotope based on calibrated monitor response tables / graphs supplied by vendors or generated in plant. Bkgd = RMS background level (cpm) 1.5 = Detector tolerance as defined in FSAR (150% of anticipated count rate) 1.4 The liquid and gaseous waste radiation monitor descriptions including effluent controls and sample points are listed on Attachment (2). 1.5 The radiation monitors have remote visual / audible alarms and visual meter Indications at the local detector locations. In addition, remote detector alarms, meters and recorders are located in the Control Room. j

y .. . 7 2.0 RADIOACTIVE LIQUID EFFLUENTS 2.1 Processing Equipment and Flow Paths 2.1.1 The normal liquid waste processing equipment flow paths and monitoring systems are defined on Attachment (3). 2.1.2 Non routine lineups for the liquid waste processing system include tank recirculations, bypass options, extended filtration and ion exchange. These may be utilized as required by system chemical and operational activities. 2.2 Liquid Effluent Concentration 2.2.1 Routine batch liquid waste releases to the Chesapeake Bay include:

a. Miscellaneous Waste

b. Reactor Coolant Waste

c. Steam Generator Blowdown (Unit 1 and Unit 2) 2.2.2 Steam Generator Blowdown is normally discharged to the condensate system and recycled. Discrete volumes are occasionally discharged to the Chesapeake Bay in a batch form rather than a continuous type effluent.

2.2.3 Prior to discharge a grab sample of the waste stream (s) shall be

                         ,    collected and analyzed to verify compliance with 10CFR20 Appendix B, Table II, Column 2.
                                        \""'  A,    x Discharge Flow Rate            =
                                                                                     ~   3 L MPC g        Dilution Water Flow Rate Where A; = specific activity (uCl/ml) of isotope i from waste stream sample MPCg = 10CFR20 limit, Appendix B, Table !!, Column 2 (uCl/ml) 4 J

J .'. a. r.. (The soluble MPC shall be used if the s' radionuclide solubility state is unknown.): Discharge Flow Rate = ' flow rate (gpm) of waste stream into circulating , water. ,- Dilution Water Flow Rate = ~ dilution from 5 circulators (IE+06 gpm)' s 2.2.4 l Reactor Coolant and Miscellaneous Waste Tank Volumes shall be recirculated prior to sample collection to ensure a representative

sample for analysis.

2.2.5 A liquid' waste discharge permit shall be prepared for routine batch I radioactive liquid releases. The perm.it shall document the release conditions and approvals, sample analysis results and compliance with

                                                         ' the Radiological Effluent Technical Specifications.

2.2.6.- Credit for dilution of liquid waste shall be taken for (5) circulating s kwater pumps having a total capacity of 1.0E+06 gpm. 2.2.7 h lieu of using the prerelease sample for post release accounting and

                                                        ; monthly / quarterly analyses, a representative composite sample may e                                                          be collected during the release and used for dose commitment and reporting requirements.

N - 2.3 Liquid Effluent Dose

                                          ,  2.3.1         Technical Specification 3.11.1.2 limits thd dose or dose commitment i-    J

[ to members of the public from radioactive materials in liquid

                            - r ,Yf                      -effluents from the Calvert Cliffs Nuc lear Power Plant to:

y

                        ,                                             - during any calendar quarter; 5 3.0 mrem to total body . J 510.0 mrem to any organ!
                                         -1 Q.                                                                              $'                           p-s
                                                                                     -5.~

n j , J

i

          ; . _. r x,
                                         - during any calendar year; f 6.0 mrem to total body
                                        . 5 20.0 mr m to any organ.

Dose'due to liquid effluents may be calculated using the equations in Section 2.3.2 or 2.3.4. 2.3.2 Dose Commitment (Expanded Equation) To fulfill the surveillance requirements of Technical Specification 4.11.1.2, the fo!!owing calculation may be used for determining the dose or dose commitment due to the liquid radioactive effluents. Do = 1.67E-02 x V x[(A; x Cio) CW

                          ' Where:

Do = dose or dose commitment to organ o, including total body (mrem) 1.67E-02 = conversion factor (hr/ min) - V = volume of liquid effluent released (gal) CW = average circulating w?ter discharge rate during release period (gal / min) A; = Specific Activity (uCi/ml) of radionuclide 1, in undiluted liquid effluent representative of the volume (V) Cio = site-related ingestion dose conversion factor to the total body or any organ o for radionuclide 1 (mrem /hr per uCi/ml) 2.3.3 Dose Conversion Factors The site-related dose / dose conversion factors (Cio) are presented in 4 4

                  .1
        .-4
                                                          ' Attachment (4) and have been derived in accordance with guidance of NUREG-0133 by the equation:                  .

xBl)i x DF;, [ C;o = l.14E+05 ~x (Up x BF i) + (Ug L . Where: - C;o = . composite dose conversion factor for the total body or critical organ of an adult for radionuclide 1, for the fish and invertebrate ingestion pathways (mrem /hr per uCl/ml) 1.14E+05 = conversion factor (pCi/uCi x ml/kg x yr/hr) Up' = 21 kg/yr, adult fish consumption BF; = bioaccumulation factor for radionuclide i in fish (pC1/kg per pCl/1) from Regulatory Guide 1.109, Table A.1 Ug'= 5 kg/yr, adult invertebrate consumption BI; = bioaccumulation factor for radionuclide i in invertebrate (pCi/kg per pCi/1) from Regulatory Guide 1.109, Table A-1 DF;o = dose conversion factor for radionuclide i for adult in'the organ o (mrem /pCi) from Regulatory Guide 1.109, Table E-Il For conservatism, no additional dilution by the receiving water body (Chesapeake Bay) has been included in the determination of these site-related dose commitment factors. The radionuclides included in the periodic dose assessment per the requirements of Technical

                                                         .. Specification 3/4.11.1.2 are those as identified by gamma spectral
                                                         ; analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1, Table 4.11-1.

1

                                                ._ - _ _            _ _   _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                                    J

L'- Radionuclides requiring radiochemical analysis (e.g, Sr-89 and Sr-90) will be added to the dose analysis consistent v/ith the required minimum analysis frequency of Table 4.11-1. 2.3.4 Dose Commitment (Simplified Equation) In lieu of the individual radionuclide dose assessment as defined in Section 2.3.2, the following simplified dose calculational equation may be used for verifying compilance with the dose limits of

                   ' Technical Specification 3.11.1.2. Refer to Section 2.3.5 for the derivation and justification for this simplified method.

Total Body Dtb = 2.22E+02 x V x A; CW Maximum Organ Dmax = 1.70E+03 x V x A; CW Where: Dtb = conservatively evaluated total body dose (mrem) 2.22E+02 = conversion factor (hr/ min) and the conservative total body dose conversion factor (Cs-134 total body - 1.33E+04 mrem /hr per uCl/ml) i

V = volume of liquid effluent released (gal) l l CW = average circulating water discharge rate during release period (gal / min)

A; = average specific activity (uCi/ml) of radionuclide i in undiluted liquid effluent representative of the volume (V) [ a

4

                                                         'Dmax = conservatively evaluated maximum organ dose (mrem) 1.70E+03 = conversion factor (br/ min) c.nd the conservative maximum organ dose conversion factor (I-131),
                   ,                                              thyroid - 1.05E+05 mrem /hr per uCl/ml) 2.3.5 Dose Commitment (3ustification for Simplified Approach)

The radioactive liquid effluents for the years 1981,1982 and'1983 were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the radionuclide distribution of effluents from Calvert Cliffs, the controlling organ is either the thyroid or the GI-LLI. The calculated thyroid dose is almost exclusively dictated by the radiolodine releases; the GI-LLI dose is primarily a function of the'Mn-54, Co-58, Co-60 and Ag-110m releases. The radionuclides, Mn-54, Co-58, Co-60, Sr-90, Cs-134 and Cs-137 contribute essentially all of the calculated total body dose. The results of this evaluation are presented in Attachment (5). For purposes of simplifying the details of the dose calculation, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e, cumulative activity for all radionuclides) by this dose conversion factor provides for a conservative simplified dose calculation. j _ - _ _ - a

i; .

                 ~
       -.i For the evaluation of the maximum organ dose, it is conservative to use the I-131. thyroid dose conversion (1.02E+05 mrem /it per uCi/ml, thyroid). The radionuclide Ag-110m has a higher dose conversion factor (5.9E+05 mrem /hr per uCl/ml, GI-LLI). However, since Ag-110m releases are typically less than 5% of the total releases, it is conservative (while not being overly restrictive) to use the I-131 factor. By this approach, the maximum organ dose will be routinely
             - overestimated. For 1981, using this simplified conservative method would overestimate the maximum organ dose by a factor of 8; for 1982, the conservatism is a factor 3; and for 1983, a factor of 6.

For the total body calculation, the Cs-134 dose factor (1.33E+04 mrem /hr per uCi/ml, total body) is the highest among the identified dominant nuclides. There are several reactor-generated radionuclides with higher values (e.g,2n-65); however, in terms of an overall dose significance, the contribution of these nuclides will be minor, attributable to relative abundances in the effluent streams. For 1981, using this simplified conservative dose calculation would overestimate *

             - the total body dose by a factor of 7; for 1982, the conservatism is a factor of 4; and for 1983, a factor 5.

For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may be used: Total Body Al Dtb = 1.67E-02 CW x V x C Cs-134

Where:

Dtb = dose to the total body (mrem) A

s? 1.67E-02 = conversion factor (hr/ min) V = volume of liquid effluent released (gal) .

                                             'CW = average circulating water discharge rate during release period (gal / min)-

CCs-134 = 1.33E+04, total body ingestion dose conversion factor for Cs-134 (mrem /hr per uCl/ml) Ai = total specific activity of all radionuclides (uCi/ml) Substituting the value for the Cs-134 total body dose conversion factor, the equation simpilfies to: D tb = 2.22E+02 CW x V x [j A Ma:umum Organ - Dmax _ = 1.67E-02 x V x Cg ,g3g x A; X CW

                  . Where:

D max = maximum organ dose (mrem) CI-131 = 1.02E+05, thyroid ingestion dose conversion factor for I-131 (mrem /hr per uCl/ml) Substituting the value for C g,g3g, the equation simplifies to: D max = 1.70E+03 x V x {A; CW Only the maximum organ dose need be evaluated by this simplified method since it represents the more limiting (compared with the total body dose) for demonstrating compliance with Technical Specification 3.11.1.2. Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose retulting from normal

                                                                                           .,.__.-._ -. _ .-_ -- _                        _ - _ - ~ - - - . - ~

2

reactor releases is negligible and is essentially independent of

                     -radwaste system operation. The amount of tritium releases annually is about 1000 curies. At Calvert Cliffs,1000 C1/yr releases to the Chesapeake Bay produces a calculated whole body dose of 1.6E-03 mrem /yr via the fish and shellfish pathways. This amounts to 0.05%

of the design objective dose of 3 mrem /yr. Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation. I.'

3.0 RADIOACTIVE GASEOUS EFFLUENTS 3.1- Processing Equipment and Flow Paths The normal gaseous waste processing flow paths, equipment and monitoring systems are defined in Attachment (6). 3.2 Release Parameters 3.2.1 Routine gaseous waste releases to the environment include: Batch Releases: Containment Vents Containment Purges Waste Gas Decay Tanks Continuous Releases: Main Vent Headers 3.2.2 Prior to discharge of batches, a grab sample shall be collected and analyzed for gaseous gamma radionuclides. 3.2.3 Continuous release samples shall be collected and analyzed on a weekly basis in accordance with the Technical Specifications. 3.2.4 Radioactivity buildup and decay shall be accounted for in continuous main vent samples. 3.2.5 All lodines and particulate gamma emitters discharged from the plant shall be accounted for with the continuous main vent header samples since all gaseous effluents are discharged via this path. 3.2.6 A gaseous waste discharge permit shall be prepared for batch releases to document release conditions and approvals, sample analysis results and compliance with Technical Specifications. 3.2.7 Credit shall be taken for main vent dilution from the reactor unit through which a release is conducted. Unit 1 - Main Vent Flow - 63.7 m3/sec 3

                       !! nit 2 - Main Vent Flow - 57.5 m /sec
                                                                                                       )

x

     ~. ,                                                                                                 .
               - 3.3 -Gaseous Effluent Dose Rate 1

3.3.1 Site Boundary Dose Rate (Total Body, Skin) Technical Specification 3.11.2.la limits the dose rate at the sitel i boundary due to noble gas releases tof 500 mrem /yr, total body. and 5 3000 mrem /yr, skin. Radiation monitor alarm setpoints are established to assure that these release limits are not exceeded. In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the unrestricted area dose rate resulting from the release may be performed using the following , equations: Dtb = X/Q x (hg x Q;) D3 - = X/Q x ([L + 1.lM;) x Qi Where: Dtb = total body dose rate (mrem /yr) X/Q = atmospheric dispersion to the controlling site boundary 2.2E-06 (sec/m3) K g= total body dose conversion factor for noble gas radionuclide 1 (mrem /yr per uCl/m3 ) from Attachment (1) Q; = average release rate of radionuclide 1 over the release period under evaluation (uCi/sec) D =., skin dose rate (mrem /yr) s L g= beta skin dose conversion factor for noble gas radionuclide 1 (mrem /yr per uCl/m3 ) from i Attachment (1)

.J

7

?:*,
           -Y                    '

t M; = gamma air dose conversion factor for noble gas radionuclide 1 (mrad /yr per uC1/m3 ) from Attachment (1) 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) Actual meteorological conditions co.icurrent with the release period may be used for evaluating the gaseous effluent dose rate. 3.3.2 Site Boundary Dose Rate (Radiolodine and Particulates) For I-131 and particulates with half-lives greater than 8 days, Technical Specification 3.11.2.1.b lim!ts the dose rate to S 1500 mrem /yr to any organ. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g, nominally once per 7_ days). The following equation may be used for the dose

rate evaluation.

bo= X/Q x ([Rg x Qg) Where: b o= average organ dose rate over the samp!!ng time period (mrem /yr) X/Q = atmospheric dispersion to the controlling site boundary for the inhalation pathway (2.2E-06 3 sec/m ) Rg= dose parameter for radionuclide 1, (mrem /yr per uC1/m3 ) for the child inhalation pathway from Attachment (7) Qg = averaSe release rate over the appropriate sampling period and analysis frequency for L- ' _j

e-

      .mM6 m
                                                                                                                      ?

radionuclide 1 - I-131 or other radionuclide in i particulate form with half-life greater than eight days (uCl/sec) JBy substituting 1500 mrem /yr for Do solving for Q, an allowable release rate for I-131 can be determined. ' Based on the annual average meteorological dispersion (2.2E-06 sec/m3 ) and the most

limiting potential pathway, age group and organ (inhalation pathway, child thyroid - R g= 1.62E+07 mrem /yr per uCl/m3 ), the allowable

                !                      release rate for I-131 is 20 uCl/sec. An added convervatism factor of 0.5 has been included in this calculation to account for any potential
  .                                    dose contribution from other radioactive particulate material. For a 7 day period which is the nominal sampling and analysis frequency for k-                                     I-131, the cumulative allowable release is 12.5 Cl. Therefore, as long as the I-131 releases in any 7 day period do not exceed 12.5 Cl, no additions! analyses are needed to verify compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.

3.4 Gaseous Effluent Dose-

                               '3.4.1  Gaseous Dose - Noble Gases (Expanded Equation)

Technical Specification 4.11.2.2 requires a periodic assessment of

                                      - releases of noble gases to evaluate compliance with the quarterly dose limits of (510 mrad, gamma-air and520 mrad, beta-air) and the calendar year limits (520 mrad, gamma-air and540 mrad, beta-air).

The following equations may be used to calculate the gamma-air and beta-air doses: D = 3.17E-08 x X/Q x ([Mg x Qg) D = 3.17E-08 x X/Q x ([Ng x Qg) _ _ _ _ _ _ - _ - _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ a

p

Where

                                                          = air dose due to gamma emissions for noble gas radionuclides (n rad) 3.17E-08 = conversion factor (yr/sec)

X/Q = atmospheric dispersion to the controlling site boundary (2.2E-06 sec/m3) Mg= air dose factor due to gamma emissions from noble gas radionuclide 1 (mrad /yr per uC1/m3) from Attachment (1) Qg = cumulative release of noble gas radionuclide 1 over the period of interest (uCl) D = air dose due to beta emissions from noble gas radionuclides (mrad)

                                                     'N g= air dose factor due to beta emissions from noble gas radionuclide 1(mrad /yr per uC1/m3)

Attachment (1) 3.4.2 ' Gaseous Dose - Noble Gases (Simplified Equation) in lieu of the Individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2. (Refer to Section 3.4.5 for the derivation and justification for this simplified method.) D = 3.17E-08 x X/Q x M,gg x{Qg and D = 3.17E-08 x X/Q x N,gg x { Qg

           .f Where       >

M,gg = 3.9E+02, effective gamma-air dose factor (mrad /yr per uC1/m3) N,gg = 1.1E+03, effective beta-air dose factor (mrad /yr per uC1/m3) Actual meteorological conditions concurrent with the release period ( may be used for the evaluation of the gamma-air and beta-air doses. 3.4.3 Gaseous Dose - Radioiodine and Particulates (Expanded Equation) Per the requirements of Technical Specification 4.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit (515 mrem) and calendar year limit (530 mrem) to any organ. The following equation may be used to evaluate the maximum organ dose dup to releases of I-131 and particulates with half-lives greater than 8 days. . D,op = 3.17E-08 x W x ({Rg x Qg) Where

                                    -D,op = dose or dose commitment for age group a to
                                             - organ o, including the total body, via pathway p from I-131 and radionuclides in particulate form with half-life greater than eight days (mrem)

W = atmospheric dispersion parameter (X/Q or D/Q) to the controlling location (cesidence and vegetable garden at 2200 m, SSE) X/Q = atmospheric dispersion for Inhalation pathway via other pathways (4.9E-07 sec/m3) D/Q = atmospheric deposition for vegetable milk and meat pathways (3.2E-09 m-2)

                                                            . Rg = dose factor for radionuclide I, (mrem /yr per
                                                                  'uCi/m 3) or (m2 - mrem /yr per uCl/sec) from Attachment (7) for each age group a and the applicable pathway p.

Values for Rj were derived in accordance with + the methods described in NUREG-0133. Qi = cumulative release over the period of interest for radionuclide 1 - I-131 or radioactive materialin particulate form with half-life greater than 8 days (uCl).

           ,                    3.4.4    Gaseous Dose - Radiolodine and Particulates (Simplified Equation)
                              ,          In lieu of the individual radionuclide (I-131 and particulates) dose assessment as presented above, the following simplified dose calculational equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3.

Dmax = 3.17E-08 x W x R g,g3g x {Qg Where: Dmax = maximum organ dose (mrem) Rg,g3g = I-131 dose parameter for the thyroid for the identified controlling pathway

                                                                = 4.76E+10, child thyroid dose parameter with the vegetation pathway controlling (m2 - mrem /yr per uCl/sec)
                                                                = 1.05E+12, infant thyroid dose parameter with 2

the cow-milk pathway controlling (m - mrem /yr per uCl/sec)

(. The ground plane exposure and inhalation pathways need not be i! considered when the above simplified calculation is used because of E the overall negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides

                    . (e.g, Co-60 and Cs-137), the ground exposure pathway may represent
                    . a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the applicable vegetation or milk pathway.

The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Calvert Cliffs as identified by the annualland-use census (Technical Specification 3.12.2). Otherwise the dose will be evaluated based on the predetermined controlling pathways, i.e, residence and vegetable garden at 2200 m, SSE. 3.4.5 Technical Bases for Effective Dose Factors The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose to the environment (i.e,instead of having to perform individual radionuclide dose analyses only a single multiplication (K,gg, M,gg or N,gg) times the total quantity of radioactive material released would be needed). This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculation. The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:

1) K,gg = [(Kg ) x (f g)

Where: K,gg = the effective total body dose factor due to gamma emissions from all noble gases released K g= the total body dose factor due to gamma emissions frm each noble gas radionuclide I released f g= the fractional abundance of noble gas radionuclide I relative to the total noble gas activity

2) (L + 1.1 M) egg = [(Lg + 1.1 Mg ) x ig Where (L + 1.1 M),gg = the effective skin dose factor due to beta and gamma emissions from all noble gases released (L g+ 1.1 M g) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide I released

3) M,gg = {Mixfg

           . Where:

M,gg = the effective air dose factor due to gamma emissions from all noble gases released Mi = the air dose factor due to gamma emissions 1 from each noble gas radionuclide i released

4) . N,gg =[Ngxig Where:

N,gg = the effective air dose factor due to beta emissions from all noble gases released ! Ng= the air dose factor due to beta emissions from each noble gas radionuclide 1 l To determine the appropriate effective factors to be used and to i evaluate the degree of variability, the atmospheric radioactive ef fluents for the past 3 years have been evaluated. Attachment (8) presents the results of this evaluation. I l I As demonstrated by the data in Attachment (8), the effective dose transfer factors vary little from year to year. The maximum j l observed variability from the average value is less than 10%. This 1 variability is minor considering other areas of uncertainty and I conservatism Inherent in the environmental dose calculation models. , 1 For evaluating compliance with the dose !!mits of Technical l l Specification 3.11.2.2, the following simp!! fled equations may be used: I D = 3.17E-08 x X/Q x M egg x { Qg D = 3.17E-08 x X/Q x N,gg x { Qg i I

1 i

r; , y Where: D = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)

     ,                        D = air dose due to beta emissions for the cumulative release of all noble gases (mrad)

X/Q = atmospheric dispersion to the controlling site boundary (sec/m3) M,fg = 3.9E+02, effective gamma-air dose factor (mrad /yr per uC1/m3) N,ff = 1.lE+03, effective beta-air dose factor (mrad /yr per uC1/m3) Qg = cumulative release for all noble gas radionuclides (uCl) 3.17E-08 = conversion factor (yr/sec): Combining the constants, the dose calculation equations simplify to: D = 1.24E-05 x X/Q x [Qg, and' D = 3.49E-05 x X/Q x [Qi Only the beta-air dose need be evaluated by this simplified method since it represents the more limiting (compared with the gamma-air. dose) based on the limits of Technical Specification 3.11.2.2. The effective dose factors are used on a very limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunctions where a detailed dose assessment may be unavailable. Dose assessments using the detailed, radionuclide dependent calculation are performed

       ,                                                                                                                                                                      o*
                                                                                                                                                                                   ^

at least every six months for preparation of the Semi-Annual

Radioactive Effluent Reports. Comparisons can be performed at this time to assure that the use of the effective dose factors does not substantially underestimate _ actual doses. j

                          '3.5 Camp Conoy/ Visitors Center Dose Calculation 3.5.1   Camp Conoy and the Visitors Center are the only locations within the                                                                         ,

Calvert Cliffs Site Boundary that are frequently visited by members i of the public. Based on the data in Section 3.5.2 and 3.5.3 any actual exposure to individuals at these locations will be less than the calculated exposure for the site boundary and controlling of fsite , location Therefore, no special considerations are required for - addressing potential exposure at these onsite locations. 3.5.2 Camp Conoy is located in the south east (SE) sector approximately ' 3000 ft from the plant. Maximum occupancy for any individual at this

        '-                             recreational facility is approximately 900 hours per year. The average annual X/Q for the SE sector at 3000 ft is 2.40E-06 sec/m3 .                                                                        ,
                                     ' The dose calculation for the controlling site boundary is more conservative by a factor of 9.

3-3.5.3 The Visitors Center is located in the West North West (WNW) Sector at 1000 ft from the plant. The wind frequency for the WNW sector based on 1983 meteorological data is 4% Using a conservative basis of 10% wind frequency, an Individual visiting the center for 330

     .                                hours / year during the periods of worst case meteorological conditions                                                                      :

would be most highly exposed. The average annual X/Q for the WNW r 3 sector at 1000 ft is 8.68E-06 sec/m The dose calculation for the controlling site boundary is more conservative by a factor 7. Y .-- - __ - . - - - _ _ -__ _.. ___ - _ - _ _ - - - - - - - _ _ . _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _

5 4.0 40CFR190 COMPLIANCE In accordance with the requirements of Technical Specification 3.11.4, doses to any member of the public due to releases of radioactivity and direct radiation from reactor units and outside storage tanks shall be calculated when doses from liquid or gaseous effluents exceed twice the limits of Technical Specifications 3.11.1.2, 3.11.2.2 or 3.11.2.3. Total Dose (mrem) = D(L) + D(G) + D(R) Where D(L) = Dose (mrem) from liquid effluents based on the yearly isotopic distribution and determined by the equation in Section 2.3.2. D(G) = Dose (mrem) from gaseous effluents. The

     <                                                 maximum exposed individual is in the SSE Sector based on historical X/Q and wind frequencies at 1300 meters. Dose shall be calculated using the equation in Section 3.4.1 and 3.4.3 and substituting average annual X/Q for the year of interest.

D(R) = Dose (mrem) for the maximum exposed individual located in the Southwest (SW) Sector where the direct radiation from the reactor units and outside storage tanks would be most conservative. The dose at the site boundary shall be based on the onsite TLD readings in the general vicinity of the Refueling Water tanks.

-25

5.0 RADWASTE SYSTEM MODIFICATIONS 5.1 In accordance with Specification 6.15.1, major changes to the radioactive waste system shall be reported to the Commission in the Semlannual Radioactive Effluent Release Report for the period in which the modification to the waste system was completed. 5.2 A major radwaste system modification would include removal or permanent bypass of any of the'following equipment:

                             - Degasifiers
                             - Reactor Coolant Waste Tanks
                             - Letdown Filters
                             - Reactor Coolant Waste Ion Exchangers
                             - Miscellaneous Waste Inn Exchanger and Filter
                             - Miscellaneous Waste Tanks
                             - Waste Gas Decay Tanks
                             - Waste Gas Surge Tank f,                            - Spent Resin Metering Tank e

c 6.0 ENVIRONMENTAL MONITORING 6.1 The objectives of the Radiological Environmental Monitoring Program are: 6.1.1 To determine whether any statistically significant increase occurs in the concentration of radionuclides in the environment. 6.1.2 To 6tect any measurable buildup of long-lived radionuclides in the environment. 6.1.3 To monitor and evaluate ambient radiation levels. 6.1.4 To verify that radioactivity and ambient radiation levels attributable to th'e plant are within the limits specified in the Environmental Radiation Protection Standards as set forth in 40 CFR Part 190. 6.2 The radiological environmental monitoring stations are listed in Attachmenc (9). The location of these stations with respect to the Calvert Cliffs Nuclear Power Plant are shown on topographic maps in Attachments (10) and (11). Laboratories performing radiochemical analyses on samples obtained from the Radiological Environmental Monitoring Program shall participate in an Interlaboratory Comparison Program, such as the one offered by the Environmental Protection Agency. The choice of the type of samples analyzed should coincide with the type of samples routinely analyzed in the Radiological Environmental Menitoring Program (i.e., gamma isotopic analyses, tritium determinations, gross beta activity analyses, etc.). The g actual results shall be compared to the theoretical results reported by the Interlaboratory Comparison Program in order to assess the laboratory's accuracy and precision. If it becomes apparent that the laboratory's results seem biased or that the analysis lacks reproducibility, the detecting instrument shall be checked and the analytical procedure shall be investigated to determine if there are any inherent problems. If such problems manifest t themselves, corrective action shall be taken to rectify the situation.

ATTACHMENT (1) DOSE FACTORS FOR NOBLE GASES

Total Body Gamma Air - Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K- L M. N.

Radionuclide (mrem /yr per uCi/m3) (mrem /yr pe;r uCi/m3) (mrad /yr pe*r uCi/m3) (mrad /yr per uCi/m3) Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.%E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9J3E+03 6.17E+03 1.03E+04 Kr-88 1.47 E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29 E,03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 - 4J6E+02 1.56E+02 1.llE+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94 E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.llE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27 E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28 E+03

Derived from Reg. Guide 1.109 l

7.

=.

ATTACHMENT (2) RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION Auto Shutoff Valves Detector Type Sample Point and RMS Alarm Liquid Effluent Monitors

c. Liquid Waste Discharge Scintillation 0-SX-6487 0-CV-2201 *

(0-RE-2201) (in line) 0-SX-6488 0-CV-2202

RCW-328 Control Room Alarm MWS-509 b, Steam Generator Discharge Scintillation Steam Generator 1-CV-4015 *

(l(2)-RE-4095) (of f line) Sample Sink 2-CV-4015

Control Room Alarm Gaseous Efffuent Monitor

c. Waste Gas Discharge GM Tube 0-SX-2188 0-CV-2191 *

(0-RE-2191) (in line) 0-SX-2189 0-CV-2192

0-SX-2190 Control Room Alarm b, Main Vent Gaseous GM Tu!:e 1(2)-5414 I or Control Room Alarm

(!(2)-RE-5415) (off line) 1(2)-5414 3 or Main Vent Noble Gas Beta Detector 1(2)-5414 I or Control Room Alarm (1(2)-RE-5416) (of f line) 1(2)-5414 3 (l(2)-RE-5417) (l(2)-RE-5418) o Automatic isolation valve controlled by radiation monitor. L

                                                                                                                             = o.  :3 ATTACHMENT (3)

RADIOACTIVE IJQUID WASTE SYSTEMS CALVERT CLIFFS NUCLEAR POWER PLANT Reactor Coolant Taste Miscellaneous Waste U-l CVCS U-2 CVCS U-1 Steam U-2 Steam Aux Building Laundry & Letdown Letdown Generator Generator Drains (U-1 Laboratory Blowdown Blowdown & U-2) Drains U-1 CVCS U-2 CVCS Filters (2) Filters (2) 120 gpm 120 gpm 1r U-1 V 37 Degasifier 11 & 12 U-2 R C Waste b Degasii er, Miscellaneous Ion Exchangers

Waste Receiver Tank 4,000 gal 1I l-RE-4095 2-RE-4095 3r 11 & 12 R C Waste Miscellaneous Receiver Tanks R R Waste Ion 90,000 gal Exchanger I I Evaporators 20 gpm 4

l] d I k Automatic 1 P Isolation ~E k 1r Valves 13 & 14 R C Waste _ 11 R C Waste a r r r Miscellaneous Ion Exchanger Monitor Tank ( ( Waste Turbine Bldg 12 R C Waste Sump Monitor Tank

                                             ,                                                    m       Chesapeake
                                             --   Circulating Water                               "

Bay A O-RE-2201 -3 I Automatic Isolation k Valve

e N-44 V.

       "'4                                          >
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                                           .y
       ,                                          ATTACHMENT (5)

ADULT DOSE CONTRIBUTIONS FISH AND SHELLFISH PATHWAY

1981~ 1982 1983 T.B. Dose GI-LLI Dose T.B. Dose GI-LLI Dose T.B. Dose GI-LLI Dose Radionuclide Ci/yr Fraction Fraction Ci/yr Fraction Fraction Ci/yr Fraction Fraction Mn-54 0.38 0.10 0.26 0.043 < 0.01 < 0.01 0.015 0.03 0.02 Co-58 1.27 0.32 0.48 1.5 0.12 0.12 0.60 0.13 0.47 Co-60 0.21 0.15 0.22 0.19 0.04 0.04 0.08 0.05 0.17 Sr-90 0.027 0.15 < 0.01 0.062 0.11 < 0.01 0.007 < 0.01 < 0.01 Ag-110m 0.22 0.01 0.83 0.0077 < 0.01 0.29 Sb-125 0.076 < 0.01 < 0.01 0.27 < 0.01 < 0.01 0.33 < O.01 0.04 Cs-134 0.051 0.13 < 0.61 0.44 0.34 = 0.01 0.18 0.38 < 0.01 Cs-137 0.10 0.15 < 0.01 0.80 0.37 < 0.01 0.32 0.40 < 0.01

6

ATTACHMENT (6) RADIOACTIVE GASEOUS WASTE SYSTEM CALVERT CLIFFS NUCLEAR POWER PLANT D-3 Air 2 U-l U-l Aux Spent Frel Fool U-2 Aus Enhaust Fan Degastfiere U-2 Aus U- 2 Buildtig Containnent Buttdlog g p g Ven'flation Equip Vents Equip Vents 07 gas analyser Ventilation

                                                    }                                  Pressuriser Quench Tanks Reactor Coolant Drain Tenka value Contaol Tanks A

U-2 Steam U-2 Usete cas Cenerator Cnnelenner U-I Steam U-t (Cf Surge Tank Generator Conelenser BIowdown _Olt Gats _ off Cas (50 reta) Tank Vent Blowdown Tank Vent rH- U., ,e Ca. rH-l Condenser l / Stora r Tanke (3) l Condenser l A (150 reig each) LXj;J :: O < S , ICI ; O Crmtrotted controlled a

   !.reme                                                       -                                                    Areas k                                    I
                                                                                                      - - automatic Jk 'footation A                                                                                                Ivalve         A
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                                                                                                                             ~

ATTACHYENT 7 Pattway Dose Parameters Rg MemM M Mb ( AGE 1 ADULT-j PATHWAY 1 INHALATION NO ISOTOPE W. BODY THYROID BONE . LIVER KIDNEY LUNG GI-LLI SKIN -CRITICAL' ! ( 1 H-3 1.244Et03 1.244Ef03 0.000E-01 1.244Et03 1.264Et03 1.264Et03 1.264Et03 1.264Et03 W. BODY 2 C-14 3.408Et03 3.408Ef03 1.816Et04 3.408E+03 3.408Ef03 3.408Et03 3.408Et03 3.400Ef03 BONE I 3 Na-24 1.024Ef04 1.024Et04 1.024E+04 1.024Et04 1.024Et04 1.024Et04 1.024Et04 0.000E-01 W. BODY ( 4 P-32 5.00CEt04 0.000E-01 1.320Et04 7.712Et04 0.000E-01 0.000E-01 8.640Ef04 0.000E-01 BONE 5 SC-46 2.480Ef05 0.000E-01 4.408Et05 8.560Ef05 8.000Et05 0.000E-01 2.584Ef05 0.000E-01 LIVER 6 CR-51 1.000Et02 5.952Et01 0.000E-01 0.000E-01 2.280Ef01 1.440Ef04 3.320E103 0.000E-01 LUHG ( 7 MN-54 4.296Et03 0.000E-01 0.000E-01 3.960Et04 9.840Ef03 1.400Et06 7.736El04 0.000E-01 LUNG 8 HN-56 1.832E-01 0.000E-01 0.000E-01 1.240Ef00 1.304Et00 9.440Et03 2.021El04 0.000E-01 GI-LLI 9 F E-55 3.941Et03 0.000E-01 2.456Et04 1.696Et04 0.000E-01 7.200Et04 6.032Et03 0.000E-01 LUNG ( 10 tE-59 -1.056Ef04 0.000E-01 1.176E604 2.776Et04 0.000E-01 1.046EiO6 1.000Et05 0.000E-01 ILUNG 11 EO-58 2.072Et03 0.000E-01 0.000E-01 1.584Et03 0.000E-01 9.200Ef05 1.044Ef05 0.000E-01 LUNG 12 EO-60 1.480Ef04 0.000E-01 0.000E-01 1.152Et04 0.000E-01 5.960Et06 2.843El05 0.0000-01 LONG

13 N1-59 5.41 set 03 0.000E-01 3.24 set 04 1.160Et04 0.000E-01 6.568Et03 4.GCELt03 0.000E-01 LUNG 14 NI-63 1.440Ef04 0.000E-01 4.320Et05 3.144Et04 0.000E-01 1.784EtOS 1.334Ef04 0.000E-01 BDHE 15 NI-65 9.120E-02 0.000E-01 1.536Et00 2.096E-01 0.000E-01 5.600Et 03 1.232Lt04 0.000E-01 GI-LLI

! 16 CU-64 4.152E-01 0.000E-01 0.000E-01 1 464Ef 00 4.624Et00 6.784Ef 03 4.896Et04 0.000E-01 GI-LLI 17 ZN-65 4.654Et01 0.000E-01 3.240E t04 1.032Eto$ 6.896Ef 04 8.640Ef 05 5.344Et04 0.000E-01 LUNG 1 10 ZN-69 4.520E-03 0.000E-01 3.304E-02 6.512E-02 4.216E-02 9.200Ct02 1.632Et01 0.000E-01 LUNS I? BR-83 2.403E102 0.000E-01 0.000E-01 0.000E-91 0.000E-01 0.000E-01 2.320Et02 0.000E-01 W. BODY ! 20 ER-84 3.123Ct02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.C00E-01 1.640E-03 0.000E-01 W. DODY j 21 1:R-85 1.230Ef01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 22 Rb-86 5.896Ef04 0.000C-01 0.000E-01 1.352El05 0.000E-01 0.000E-01 1.664Ef04 0.000E-01 LIVER 23 RB-03 1.?28Ef02 0.000E-01 0.000E-01 3.872E402 0.000E-01 0.000E-01 3.344E-09 0.000E-01 LIVER 21 RD-89 1.6V'Eto2 0.000E-01 0.000E-01 2.540Et02 0.000E-01 0.000E-01 9.280E-12 0.000E-01 LIVER i 25 ER-89 0.720Et03 0.000r-01 3.040E105 0.000E-01 0.000E-01 1.400E406 3.496Et05 0.000E-01 LONG 26 LR-90 6.096Et06 0.000E-01 9.920Ef07 0.000E-01 0.000E-01 9.600Et06 7.216E105 0.000E-01 DOHE 27 $N-91 ?.5010100 0.000E-01 6.192EiO1 0.000E-01 0.000E-01 3.640E604 1 912Et05 0.000E-01 GI-LLI 23 SR-92 2.91?E-01 0.000E-01 6.744Ef00 0.000E-01 0.000E-01 1.618Ef04 4.301Ef04 0.000E-01 GI-LLI 29 Y-90 5.608E401 0.000E-01 2.080Ef03 0.000E-01 0.000E-01-1.696Ef05 5.056Et05 0.000E-01 GI-LLI 30 Y-91M 1.016E-02 0.000E-01 2.608E-01 0.000E-01 0.000E-01 1.920Et03 1.329Et00 0.000E-01 LUNG 31 Y-91 1.210Et01 0.000E-01 4.624Ef05 0.000E-01 0.000E-01 1 704Et06 3.848Et05 0.000E-01 LUNG 32 Y-92 3.016E-01 0.000E-01 1.032Et01 0.000E-01 0.000E -01 1.548Et 04 7.352Ef 04 0.000E-01 GI-LLI , 33 Y-93 2.60DEt00 0.000E-01 9.440Et01 0.000E-01 0.000E-01 4.840Ef04 4.216Ef05 0.000E-01 GI-LLI 31 ZR-95 2.328El01 0.000E-01 1.072Ef05 3.440Et04 5.416Lf04 1.768Et06 1.50iE405 0.000E-01 LUNG 35 ZR-97 9.040Ef00 0.000E-01 9.600Ef01 1.960Et01 2.968Et01 7.872Et04 5.232Et05 0.000E-01 GI-LLI i I I . I

Pzgm 2 cf 39 ATTACHMENT 7 Pathway Dose Parameters Rg (arem M per W ah ACE 1 ADULT PATHWAY 1 INitALATION NO ISOTOPE. W. BODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL t 36 HD-95 4.208Ef03 0.000E-01 1.408Ef04 7.816Et03 7.735E+03 5.048E+05 1.040E+05 4.208Et03 LONG 37 ftB-97 2.048E-02 0.000E-01 2.224E-01 5.624E-02 6.544E-02 2.400Et03 2.414E102 0.000E-01 LUNG 38 NO-99 2.296Et01 0.000E-01 0.000E-01 1.208Ef02 2.912E402 9.120E+04 2.490Et05 0.000E-01 GI-LLI

39 TC-9VM 3.7040-02 0.000E-01 1.032E-03 2.912E-03.4.416E-02 7.640E+02 4.160E103 0.000E-01 GI-LLI 40 TC-101 5.904E-04 0.000E-01 4.176E-05 6.016E-05 1.000E-03 3.992E+02 1.038E-11 0.000E-01 LUNG 41 RU-103 6.504Et02 0.000E-01 1.528E+03 0.000E-01 5.832Ef03 5.040E103 1.104E405 0.000E-01 LUNG t 42 RU-105 3.112E-01 0.000E-01 7.904E-01 0.000E-01 1.016E+00 1.096E+04 4.016Et04 0.000E-01 GI-LLI 43 RU-106 8.720E+03 0.000E-01 6.912E+04 0.000E-01 1.336E+05 9.360Et06 9.120E!05 0.000E-01 LUHG 14 AG-110N 5.944Et03 0.000E-01 1.080E+04 1.000Ef04 1.va8E404 4.632E406 3.02iEt05 0.000E-01 LUNG t 15 ED-115H 6.360E403 0.000E-01 0.000E-01 1.960E405 1.504Et05 1.408Ef06 3.010Lt05 0.000E-01 LUNG 45 SD-124 1.210E t04 7.352E t01 3.120E 604 5.030E t02 0.000E-01 2.4SOE4 04 4.064E 105 0.000E-01 LUHG 17 TE-125M 4.672Et02 1.043Et03 3.416Et03 1.504Et03 1.240E404 3.136E+05 7.064Et04 0.000E-01 LUHG i iS TE-127H 1.56SEf03 3.283E603 1.264E+04 5.763Et03 4.5/4Et04 9.600E605 1.494L105 0.000E-01 LtlNG 4? TE-127 3.096E-01 1.056E600 1.400Et00 6.424E-01 5.096Et00 6.512E103 5.7JoEt04 0.000E-01 GI-LLI 50 TE-129H 1.534EiO3 3.440Et03 9.760Et03 4.672El03 3.656Et04 1.160E404 3.032Et05 0.000E-01 LUNG s 51 TE-129 1.240E-02 3.896E-02 4.974E-02 2.392C-02 1.u72E-01 1.936E+03 1.56CC+02 0.000E-01 LUNG 52 TE-131M 2.904Et01 5.501Et01 6.992Et01 4.360Ef01 3.00 set 02 1.456E405 5.560E105 0.000E-01 GI-LLI 53 TE-131 3.592E-03 9.360E-03 1.112E-02 5.952E-03 4.36SE-02 1.392EiO3 1.340C601 0.000E-01 LUNG t Si TE-132 1.616Et02 1.uv6Et02 2.600E+02 2.152Et02 1.456E103 2.080EIO3 5.096Et05 0.000E-01 GI-L LI 55 I-130 5.280Et03 1.136C106 4.576E+03 1.314EtC4 2.OC8Ef04 0.000E-01 7.633Et03 0.000E-01 THYROID 56 I-131 2.018Et 04 1.192E+07 2.520C+04 3.576Et04 6.12eEf 04 0.000E-01 6.230C4 03 0.000E-01 TitVROID s 57 1-132 1.160Et03 1.144E t05 1.160Et03 3.256Et03 5.104Ef 03 0.000E-01 4.064C602 0.000E-01 TilYROID 58 I-133 4.520E103 2.152E104 8.640E403 1.4SOEt04 2.534Ef04 0.000E-01 8.b000f03 0.000E-01 1H(ROID 59 I-134 6.152Lt02 2.9CiEf04 6.440E+02 1.720E+03 2.752Et03 0.000E-01 1.00SE400 0.000E-01 THfROID .

60 I-135 2.568Et03 4.400E105 2.680Et03 6.984Et03 1.112Et04 0.000E-01 5.240Et03 0.000E-01 THYROID 41 CS-134 7.200El05 0.000E-01 3.720E+05 8.400Et05 2.872Ef05 Y.740E104 1.040Et04 0.000E-01 LIVER 62 ES-136 1.101E105 0.000E-01 3.904E t04 1.464E4 05 8.560Et04 1.200E+04 1.168Et04 0.000E-01 LIVER s 63 EG-137 4.280Et05 0.000E-01 4.784Et05 6.200E+05 2.224E105 7.520Et01 8.400El03 0.000E-01 LIVER 64 CS-133 3.210Et02 0.000E-01 3.312Et02 6.200Et02 4.800E+02 4.856E401 1.864E-03 0.000E-01 LIVER 65 CS-139 1.112C102 0.000E-01 2.048E402 2.904E102 2.440Et02 2.27?Ft01 0.000E-01 0.000E-01 LIVER L 64 CA-139 2.73?E-02 0.000E-01 9.360E-01 6.654E-04 6.224E-04 3.760C103 8.940E402 0.000E-01 1.UHG 67 BA-140 2.560Et03 0.000E-01 3.904Et04 4.904Ef01 1.672Ef01 1.272Ef 06 2.104Ef 05 0.000E-01 LUNG 68 DA-141 3.360E-03 0.000E-01 1.000E-01 7.520E-05 7.000E-05 1.936Et03 1.140E-07 0.000E-01 LUNG L. 49 CA-142 1.656E-03 0.000E-01 2.632E-02 2.704E-05 2.200E-05 1.192E403 t.568E-16 0.000E-01 LUHG 70 LA-140 4.584E601 6 000E-01 3.440Ef02 1.736Ef02 0.000E-01 1.360E405 4.584E105 0.000E-01 GI-LLI

                                                                                     ,                                               t s

g P ga 3 ef 39 .

                                           < m ww m,.m ATTACmENT 7 Pathway Dose Parameters Rg (mrem /yr per tC1/a3 )

AGE 3 ADULT PATHWAY 1 INHALATION NO ISOTOPE W. BODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 72 CE-141 7.720E-02 0.000E-01 6.832E-01 3.104E-01 0.000E-01 6.328Ef03 2.112E403 7.720E-02 LUNG 73 EE-143 1.528Et03 0.000E-01 1.992Ef04 1 352Ef04 6.264E403 3.616E+05 1.200Ef05 0.000E-01 LUNG 74.CE-144 1.528Ef01 0.000E-01 1.864Ef02 1.376E+02 6.000Ef01 7.976Ef04 2.264Ef05 0.000E-01 GI-LLI 75 PR-143 1.840E+05 0.000E-01 3.432E406 1.430Ef06 8.480E+05 7.776Ef06 8.160Ef05 0.000E-01 LUNG 76 PR-144 4.640Ef02 0.000E-01 9.360E+03 3.752E+03 2.160Ef03 2.808El05 2.000E+05 0.000E-01 LUNG 77 HD-147 1.528E-03 0.000E-01 3.008E-02 1.249E-02 7.048E-03 1.016EiO3 2.152E-OS 0.000E-01 LUNG 78 W-185 3.648E402 0.000E-01 5.272E+03 6.096E+03 3.540EiO3 2.208E+05 1.728E405 0.000E-01 LUNG 79 W-187 5.448Ef01 0.000E-01 1.560Ef03 5.176E+02 0.000E-01 4.456Et05 0.560Ef04 0.000E-01 LUNG 00 U-235 2.400E400.0.000E-01 8.480E+00 7.0BOEt00 0.000E-01 2.904EF04 1.552Ef05 0.000E-01 GI-LLI 81 U-230 4.056E+06 0.000E-01 8.000Et07 0.000E-01 1.872Ef07 3.920Ef08 3.872Et05 0.000E-01 LUNG D2 NP-239 4.536Et06 0.000E-01 7.664E+07 0.000E-01 1.744E+07 3.661E+0S 3.210Et05 0.000E-01 LUNG 1.240Ef01 0.000E-01 2.296E+02 2.256EiO1 7.000E+01 3.760E404 1.192E+05 0.000E-01 GI-LLI e ___.____--.------.J

Prga 4 of.39 . ATTACIDENT 7

                                                            . ..                   . ~ . -

Pathway Dose Parameters 3 Rg(mrem /yrper(C1/m) AGE'! TEEN PATHWAY I INHALATION. NO ISOTOPE W. BODY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 1 H-3 2 C-14 1.272Et03 1.272E+03 0.000E-01 1.272Et03 1.272Et03 1 272Ef03 1.272Ef03 1.272Et03 W. BODY 3 NA-24 4.872Et03 4.872Et03 2.600E104 4.872Ef03 4.872E403 4.872E403 4.872E403 4.872E403 BONE 4 P-32 1.376E404 1.376Ef04 1.376Et04 1.376Et04 1.376Ef04 1.376Et04 1.376Et04 0.000E-01 W. BODY 5 SC-44 7.160E104 0.000E-01 1.888Et04 1.096E+05 0.000E-01 0.000E-01 9.280Et04 0.000E-01 BONE 4 ER-G1 2.400Ct05 0.000E-01 4.408Et05 8.560Ef05 8.000Et05 0.000E-01 2.504E405 0.000E-01 LIVER 7 MH-54 1.352Et02 7.494El01 0.000E-01 0.000E-01 3.072Ef01 2.096E404 3.000E403 0.000E-01 LUNG O NN-56 0.400Et03 0.000E-01 0.000E-01 5.112Ef04 1.272E404 1 901Et06 6.600E104 0.000E-01 LUNG 9 FE-55 2.520E-01 0.000E-01 0.000E-01 1.696Et00 1.792El00 1.520El04 5.741E404 0.000E-01 GI-LLI 10 FE-59 5.541EiO3 0.000E-01 3.344EF04 2.384E104 0.000E-01 1 240EtOS 6.392Et03 0.000E-01 LUNG 11 CO-50 1.432Et04 0.000E-01 1.592Ef04 3.6?6EiO4 0.000E-01 1.520E606 1.784El05 0.000E-01 LUHG 12 CO-60 2.776E603 0.000E-01 0.000E-01 2.072E403 0.000E-01 1.344Et04 9.520Et04 0.000E-01 LUNG 1J HI-59 1.934Et04 0.000E-01 0.000E-01 1.512Et04 0.000E-01 8.720E106 2.592Ct05 0.000E-01 LUMG 11 HI-63 5.416Cf03 0.000E-01 3.240Et04 1.160Et04 0.000E-01 6.56 set 01 4.8SOEt03 0.000E-01 LUNG 15 HI-65 1.976Et04 0.000E-01 5.000Et05 4.344Et04 0.000E-01 3 072Et05 1.416Ef04 0.000E-01 BUNE 16 EU-64 1.272E-01 0.000E-01 2.184Et00 2.92BE-01 0.000E-01 9.360Et03 3.672Et04 0.000E-01 GI-LLI 17 ZH-65 0.400E-01 0.000E-01 0.000E-01 2.032Ef00 6.408Ef00 1 112E404 6.144E404 0.000C-01 GI-LLI 10 ZN-69 6.29vLt04 0.000E-01 3.856E t0 4 '1.336Et05 8.640Et04 1 240Et06 4.461Ef04 0.000E-01 LONG 19 11:-93 6.456E-03 0.000E-01 4.832E-02 9.200E-02 6.024E-02 1.584Et03 2.8tuEf02 0.000E-01 LUNG 20 bR-Di 3.440Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 21 BR-05 4.320Ef 02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E -01 0.000E-01 0.000E-01 W. LUDY 22 RD-06 1.032Et01 0.000L-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. CODY 23 RB-33 8.400Etoi 0.000E-01 0.000E-01 1.904Et05 0.030E-01 0 000E-01 1.740E104 0.000E-01 LIYLR 21 Rb-09 2.720E602 0.000E-01 0.000E-01 5.454Et02 0.000E-01 0.000E-01 2.920E-05 0.000E-01 LIVER 25 ER-09 2 32DE+02 0.000E-01 0.000E-01 3.520Et02 0.000E-01 0.000E-01 3.376E-07 0.000E-01 LIVER 2a LR-90 1.2iSE toi 0 000E-01 4.344Et05 0.000E-01 0.000E-01 2 416E104 3.712Et05 0.000E-01 LUNG 27 SR-91 4.600E t06 0.000E-01 1.080Ef08 0.000E-01 0.000E-01 1.610Ef07 7.64SE405 0.000E-01 BONE 28 SR-92 3.512C100 0.000E-01 R.000Et01 0.000E-01 0.Co0E-01 6.072Et04 2.592E405 0.000E-01 CI-LLI 29 Y-90 4.064E-01 0.000E-01 9.520Et00 0.000E-01 0.000E-01 2.744Ef01 1.192Et05 0.000E-01 GI-LLI 30 Y-91H 8.000E101 0.000E-01 2.904Et03 0.000E-01 0.000E-01 2.92 set 05 5.592E105 0.000E-01 GI-LLI 31 Y-91 1.416E-02 0.000E-01 3.704E-01 0.000E-01 0.000E-01 3.200Et03 3.014Ef01 0.000E-01 LUNG 32 Y- 92 1.76 bet 04 0.000E-01 6.600Et05 0.000E-01 0.000E-01 2.936Et04 4.000E405 0.000E-01 LUNG 33 Y-93 4.203E-01 0.000E-01 3.720Et00 0.000E-01 1.472El01 0.000E-01 0.000E-01 2.680Ef04 1.640Et05 0.000E-01 GI-LLI 31 ZR-95 1.352E102 0.000E-01 0.000E-01 0.320E404 5.792Et05 0.000E-01 GI-LLI 35 ZR-97 3.152Et04 0.000E-01 1.456E105 4.58 4Et04 6.736Et04 2.688Et06 1.488E605 0.000E-01 LUNG 1.256Et01 0 000E-01 1.376Et02 2.720Et01 4.120Et01 1 296Et05 6.304Et05 0.000E-01 GI-LLI J

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P;ga 6 cf 39 :. ATTACHIENT 7 Pathway Dose Parameters 3 Rg(mrem /yrperifi/m) AGE 1 TEEN PATHWAY l INHALATION tiO ISOTOPE W. LODY . THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 1.056E-01 0.000E-01 9.600E-01 4.24BE-01 0.000E-01 1.016E+04 1.200E+04 1.056E-01 GI-LLI 72 CE-141 2.160E+03 0.00CE-01 2.840E+04 1.896E404 8.030E+03 6.136E+05 1.264E605 0 000E-01 LUNG 73 EE-143 2.160Et01 0.000E-01 2.656E+02 1 936E+02 8.610E+01 1.304E+05 2.552E+05 0.000E-01 GI-LLI 74 CE-144 2.624E+05 0.000E-01 4.898E+06 2.024E406 1.208E+06 1.336E+07 8.640Et05 0.000E-01 LUNG 75 PR-143 6.624Elo2 0.000E-01 1.336E404 5.312Et03 3.000E+03 4.832E+05 2.136Et05 0.000E-01 LUNG 76 PR-144 2.176E-03 0.000E-01 4.296E-02 1.760E-02 1.000E-02 1.752E+03 2.352E-04 0.000E-01 LUNG 77 HD-147 5.120E+02 0.000E-01 7.864E+03 8.560Et03 5.024E403 3.720Ef05 1.024El05 0.000E-01 LutlG 79 W-185 5.440E401 0.000E-01 1.560E+03 5 174E+02 0.000E-01 4.456Et05 8.560Etoi 0.000E-01 LUNG 79 W-187 3.432E+00 0.000E-01 1.200E401 9.760Et00 0.000E-01 4.736E+04 1.76SE405 0.000E-01 GI-LLI 80 0-235 4.856Et06 0.000E-01 8.000E+07 0.000E-01 1.872Ef07 3.920E+08 3.872Et05 0.000E-01 LureG 81 U-238 4.536E406 0.000E-01 7.664E407 0.000E-01 1.744E607 3.644CiOB 8.240Lt05 0.000E-01 LUNG 82 NP-239 1.768Et01 0.000E-01 3.394Et02 3.192Ef01 1.000E+02 6.49eE+04 1.320Et05 0.000E-01 GI-LLI T e

                                                                                                                                         . . .b

t 1P gml7 of 39 .. . 3 ATTACHMENT 7

                                                                ' Pathway Dose Parameters R g (m M r per M D AGE 1 CHILD PATHWAY 1 INHALATIDN NO ISOTDPE          W. BODY . THYROID'   BONE.            LIVER    KIDNEY   LUNG   GI-LLI     SKIN    ERITICAL 1 H-3            1.125E+03 1.125E+03 0.000E-01 1.125E+03 1 125E+03 1.125E403 1.125E+03 1.125E+03 W. DODY 2 C-14           6.734Et03 6.734E+03 3.589E404 4.734E+03 6.734E+03 6.734E+03 6.734E403 6.734E+03 BONE 3 NA-24          1.609Et04 1.609Et04 1.609E+04:1.609Et04 1.609Et04 1.609E+0i 1.609E+04 0.000E-01 W. BODY 4 P-32           9.879E+04 0.000E-01 2.605Cf06 1.143E405 0.000E-01 0.000E-01 4.218E+04 0.000E-01 BOHE 5 SC-46          1.151E+05 0.000E-01 2.039C+05 3.959Ef05 3.700E+05 0.000E-01 1.195C405 0.000E-01 LIVER 6 CR-51          1.54 Et02 8.547E401 0.000E-01 0.000E-01 2.431Et01 1.698Et04 1.084EiO3 0.000E-01 LurfG 7 MN-54          9.509E+03 0.000E-01 0.000E-01 4.292E+04 1.003Ct09 1.576EF06 2.290E404 0.000E-01 LUNG D MH-56          3.119E- 01 0. 000E-01 0. 000E-01 1.658El00 1.672E100 1.313Et04 1.237E405 0.000E-01 GI-LLI 9 FE-55          7.770Et03 0.000E-01 4.736E+0i 2.516E t04 0.000E- 01 1.110E tOS 2.06/E103 0.000E-01 LUHG 10 FE-59          1.649Et04 0.000E-01 2.068E+04 3.345E+04 0.000E-01 1.269C+06 7.067EiO4 0.000E-01 LUNG
                .11 CO-58'         3.163Et03 0.000E-01 0.000E-01 1.772Et03 0.000E-01 1.106Et06 3.437EiO4 0.000E-01 LUHG 12 CO-60          2.264Et04 0.000E-01 0.000E-01 1.313E+04 0.000E-01 7.067EiO6 9.420EiO4 0.000E-01 LUNG 13 NI-59          2.505Et03 0.000E-01 1.502E+04 5.102Ef03 0.000E-01 3.038El01 2.261Et03 0.000E-01 LUNC.

14 NI-63 ' 2.797E+01 0.000E-01 8.214Et 05 4.625E+04 0.000E-01 2.749E t05 6.327E t03 0.000E-01 B0HE 15 NI-65 1.643E-01 0.000E-01 2.990E+00 2.956E-01 0.000E-01 0.177EiO3 8.3?9E404 0.000E-01 GI-LLI 16 CU-64 1.073EiOO 0.000E-01 0.000E-01-1.994Et00 6.031E+00 9.583E+03 3.670Et04 0.000E-01 GI-LLI 17 ZH-65 7.030Et04 0.000E-01 4.255E+04 1.132E405 7.141E+04 9.953Ef05 1.432Et04 0.000E-01 LUHG 18 ZH-69 8.917E-03 0.000E-01 6.697E-02 9.657_'-02 5.846E-02 1.421Ct03 1.017E104 0.000E-01 GI-LLI 1Y bR-03 4.736Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 20 BR-81 ~ 5.476Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000C-01 W. PODY 21 BR-C5 2.531Et01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 22 RD-D6 1.143EtOS 0.000E-01 0.000E-01 1.983EtOS 0.000E-01 0.000E-01 7.992Ef03 0.000E-01 LIVER 23 RB-88 3.462E 102 0.000E-01 0.000E-01 5.624Ef 02 0.400E-01 0.000E-01 1.724E601 0.000E-01. LIVER 24 RB-89 2.897Et02 0.000E-01 0.000E-01 3.452Et02 0.000E-01 0.000E-01 1.871Et00 0.000E-01 LIVER 25 SR-89 1.724Ll04 0.000E-01 5.994Ef05 0.000E-01 0.000E-01 2.157E+06 1.672Et05 0.000E-01 LUNG 26 GR-90 4.430El06 0.000E-01 1.010Ef08 0.000E-01 0.000E-01 1.476E107 3.434E105 0.000E-01 DONE 2/ SR-V1 4.50bCtOO 0.000E-01 1.214Et02 0.000E-01 0.000E-01 5.328E+04 1.739Ef05 0.000E-01 GI-LLI 28 SR-92 5.254E-01 0.000L-01 1.310Et01 0.000E-01 0.000E-01 2.401Et04 2.423E+05 0.000E-01 GI-LLI 29 Y-?O 1.106Et02 0.000E-01 4.107E403 0.000E-01 0.000E-01 2.616E+05 2.679E405 0.000E-01 .GI-LLI 30 Y-91M 1.843E-02 0.000E-01 5.069E-01 0.000E-01 0.000E-01 2.812Ef03 1.717E403 0.000E-01 LUHG 31 Y-91 2.43DEt01 0.000E-01 9.139Et05 0.000E-01 0.000E-01 2.627EiO6 1.839E+05 0.000E-01 LUNG 32 Y- 92 5.809E-01 0.000E-01 2.035Et01 0.000E-01 0.000E-01 2.390Et04 2.3?0EiO5 0.000E-01 GI-LLI 33 Y-93 5.106Et00 0.000E-01.1.865Et02 0.000E-01 0.000E-01.7.437E+04 3.885Ef05 0.000E-01 GI-LLI 34 ZR-95 3.700Et04 0.000E-01 1.8V8Ef05 4.181Ef04 5.957Et04 2.231E+06 6.105E+04 0.000E-01 LUNG 35 ZR-97 1.59BE+01 0.000E-01 1.876E+02 2.716E+01 3.885E+01 1.132E+05 3.511E+05 0.000E-01 GI-LLI 4

                                               .-                                                                                                           JPcgm 8 cf 39; y.3       7 r

N., ATTACIBiENT 7 Pathway Dose Parameters Rg . (mram/yr per tri/m3 ) AGE 1 CHILD PATHWAY l'INHALATIDN NO ISOTOPE W. BODY THYROID BONE LIVER KIDNEY LUNG GI-LLI. SAINI CRITICAL. 36 NB-95 -6.519Et03 0.000E-01 2.349Ef04 9.176Ef03 8.621Et03 4.142EiO5 3.700Et04 6.549Ef03 l LUNG ~ 37 HB-97 9.472E-03 0.000E-01 1.029E-01.2.601E-02 3.027E-02-1.110Et03 1.117Et02 0.000E-01 LUNG-38 HO-99 1.255Et01 0.000E-01 0.000E-01 1.724Et02 !.922Et02 1.354EtOS 1.245El05 0.000C-01 LUNG 39 TC-9?M '5.772E-02 0.000E-01 1.700E-03 3.432E-03 5.069E-02 9.509E102 4.810Et03 0.000E-01 GI-LLI 40 fC-101 1.077E-03 0.000E-01 8.103E-05 8.510E-05 1.450E-03 5.846E402 1.632E101 0.000E-01 LUNG < of-RU-103 1.073E603 0.000E-01-2.867E+03 0.000E-01 7.030E103 6.623Et05 9.47/0604 0.000E-01 LUHG 42 RU-105 5.550E-01 0.000E-01 1.528E+00 0.000E-01 1.343E+00 1.591Et oi 9.953E4 0 4 0.000E-01 GI-LI,I : 43 EU-106 1.691E101 0.000E-01 1.362E+05 0.000E-01 1.83?E+05 1.432Ef 07 4.2'/2E 4 05 0.000E-01 LUNG 44 AG-110M 9.13YL103 0.000E-01 1.687Ef04 1.140Et04 2.124E104 5.476E+06 1.003Et05 0.000E-01 LUNG 45.CD-115M 2.941Et03 0.000E-01 C.000E-01 9.102Et04.7.326E+04 6.512EiO5 1.776EFO's 0.000E-01 LUNG 46 SD-124 5.735Et03 3.493Et01 1.443Ef04 2.723Et02 0.000E-01 1.147E!O6 1.OU0Et05 0.000E-01 LUNG 17 TE-125M 9.139Et02 1.921E103 6.734E+03 2.327Et03 0.000E-01 1.773E105 3.37CEt01 0.000E-01 LUMG 43 TE-127M 3.02/E103 6.06CE103 2.486EiO4 ~ 8.517Et03 6.364E104 1.400Et06 7.111Et01 0.OOOC-01 LUMG 49 TE-127 6.105E-01 1.941E400 2.771Ef 00 9.509E-01' 7.067E400 1.003E t01 5.62 *Etoi O.000E-01 GI-l.LI 50 TE-129M 3.011E103 6.327Et03 1.920Et04 6.815EiO3 5.032E+04 1.761Et06 1.817E+05 0.00CE-01 LUNG 51 TE-129 2.333E-02 7.111L-02 9.768E-02 3.496E-02 2.56DE-01 2.934Ef03 2.519E401 0.000E-01 G1-LLI 52:TE-131M 5.069E101 9.768E101 1.343Et02 5.920Ef01 3.996Et02 2.057EtO5 3.07CEt05 0.000E-01 GI-LLI 53 TE-131 6.586E-03 1.69CE-02 2.172E-02 8.436E-03 5.883E-02 2.053E403 1.332El03 0.000E-01 ~ LUNG 54 TE-132 2.631Ef02 3.175E+02.4.81CE102 2.723Ef02 1.772Et03 3.771Ef05 1.374Et05 0.000E-03 LUNG 55 I-130 8.436Et03 1.816Ef06 8.177Et03 1.639E+04 2.146E104 0.000E-01 G.106EiO3 0.000E-01 lHYRulb 56 I-131 2.727Et04 1.624E607 4.810Et04 4.810Et04 7.801Ef04.0.000E-01 2.042El03 0.000E-01 THYR.0ID 57 I-132 1.876E+03 1.9352405 2.116Et03 4.070E+03 6.253E103 0.003C-01 3.000Et03 0.OO0E-01 TH)ROID 50 I-133 7.6?6Eic3 3.010Et06 1.65BE+04 2.031Et04 3.378EiO4 0.000E-01 5.476EiO3 0.000E-01 ilMNOID 59 I-131 9.953Et02 5.069L404 1.173Et03 2.161E+03 3.300Ef03 0.000E-01 9.516EiO2 0.000E-01 THYRUID 60 I-135 4.191L103 7.910Et05 4.921E403 8.732Ef03 1.339Et04 0.000E-01 4.440E103 0.000E-01 THYROID 61 ES-134 2.246Lt05 0.000E-01 4.512EiOS 1.014Ef06 3.304El05 1.210EiO5 3.040EiO3 0.000E-01 LIVER 62 CS-136 1.142E105 0.000E-01 6.512E+01 1.709Ef05 9.546E104 1.454E401 4.181L103 0.000E-01 LIVER ' 63 ES-137- 1.281Et05 0.000E-01 9.065El05 8.251Et05 2.823E105 1.040E+05 3.6190f03 0.000E-01 PONE 61 CS-138 5.550Et02 0.000E-01 6.327Et02 8.399Et02 4.216Ef02 6.300Et01 2.697Et02 0.000E-01 LIVER

65 ES-139 5.143Et01 0.000E-01 9.472E401 1.313E t02 1.128Ei O2 1.051E101 0.000E-01 0.000E- 01 LIYLR

! 66 BA-139 5.365E-02 0.000E-01 1.843Ef00 9.842E-04 8.621E-04 5.772Ef03 5.772Et04 0.000E-01 GI-LLI

,                                        67  BA-140      4.329Et03 0.000E-01 7.400Et04 6.475Et01 2.113Et01 1.743Et06 1.017Ef05 0.000E-01 Lul4G 68  BA-141      6.364E-03 0.000E-01 1.957E-01 1.091E-04 9.472E-05 2.919Et03 2.753E+02 0.000E-01 LUttG 1-                                        69  BA-142      2.790E-03 0.000E-01 4.995E-02 3.600E-05 2.912E-05 1.643E+03 2.742Et00 0.000E-01 LUNG 70  LA-140      7.548Et01 0.000E-01 6.438Ef02 2.250E+02 0.0002-01 1.828E405 2.257E+05 0.000E-01 GI-LLI t

I

.+

4 PIgr 9 of?39 .. ATTACIPENT 7 Pattway Dose Parameters

                 -                                                                        3 Rg(mrem /yrperuC1/m)

AGE 1 CHILD

    . PATit' JAY 1 INHALAT10N HO ISOTOPE        W. BODY     THYROID  BONE       LIVER      KIDNEY               ' LUNG   GI-LLI SKIN CRITICAL 71 LA-142       1.291E-01 0.000E-01 1.295E400 4.107E-01 0.000E-01 8.695E403 7.535Et04 1.291E GI-LLI 72 CE-141       2.897Ef03 0.000E-01 3.922Et04 1.954EiO4 8.547EiO3 5.439E405 5.641Ef04 0.000E-01 LUNG 73 CE-143       2.875E401 0.000E-01 3.659E+02 1.987Et02 8.342Et01 1.154Ef05 1.273EiOS 0.000E-01 GI-LLI 74 CE-144       3.615Et05 0.000E-01 6.771EiO6 2.116Et06 1.173E+06 1.195Eic7 3.005Ef05 0.000E-01 LUNG 75 PR-143       9.13'?E+02 0.000E-01 1.846Ef04 5.550Et03 3.001Et03 4.329Et05 9.731E404 0.000E-01 LUNG 76 F R-144      2.997E-03 0.000E-01 5.957E-02 1.844E-02 9.768E-03 1.565E103 1.94cEt02 0.000E-01 LUNG 77 ND-147       6.800Et02 0.000E-01 1.000Et04 8.732Ef03 4.810Et03 3.202Elos 0.21*E+04 0.000E-01 LUHG 78 W-185        2.520E101 0.000E-01 7.215Ef02 2.494Et02 0.000E-01 2.061E105 3.059EiO4 0.000E-01 LONG 79 W-187        4.329Et00 0.000E-01 1.632Ef01 9.657E+00 0.000E-01 4.107E101 9.102Ef04 0.000E-01 GI-LLI SO U-235        2.246Lf06 0.000E-01 3.700Ef07 0.000E-01 8.658E+06 1.813Ef03 1.791El05 0.000E-01 LUHG 81 U-2J8        2.0V8E t06 0.000E-01 3.545E t07 0.000E-01 8.06aEiO6 1.695E t 08 3.811EiO5 0.000E-01 LUNG 82 NP-239       2.34 vet 01 0.000E-01 4.662E402 3.345Ef01 9.731Et01 5.809Et04 6.101Et01 0.000E-01 GI-LLI 6

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ATTACHMENT 7 Pathway Dose Parameters 3 Rg (mram/yr per (C1/m ) AGE ! INFANT PATHWAY 3 INHALATION NO ISOTOPE W. BODY THYRDID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36 NB-95 3.780Ef03 0.000E-01 1.568E+04 6.42&Et03 4.718E403 4.788Ef05 1.267Ef0.4 3.780Et03. LUNG 37 NB-97 3.584E-03 0.000E-01 3.892E-02 9.842E-03 1.145E-02 4.200Ef02 4.229E401 0.000E-01 L'JNG 38 MO-99 3.234Et01 0.000E-01 0.000E-01 1.632Et02 2.646Et02 1.340Et05 4.872Et04 0.000E-01 LUNG 39 TC-99M 3.724E-02 0.000E-01 1.397E-03 2.884E-03 3.100E-02 8.106E402 2.030Et03 0.000E-01 GI-LLI 40 TC-101 8.120E-04 0.000E-01 6.510E-05 8.232E-05 9.786E-04 5.830Et02 8.442Et02 0.000E-01 GI-LLI 41 RU-103 6.790Ct02 0.000E-01 2.016Et03 0.000E-01 4.242Et03 5.516E+05 1.610E404 0.000E-01' LUNG 42 RU-105 4.102C-01 0.000E-01 1.224Et00 0.000E-01 8.988E-01 1.560Ef04 4.814Et04 0.000E-01 GI-LLI 43 RU-106 1.080Ct04 0.000E-01 8.680Et04 0.000E-01 1.065E+05 1.156E+07 1.63 set 05 0.000E-01 LUNG. 44 AG-110N 4.990Et03 0.000C-01 9.982Et03 7.224El03 1.092E404 3.668Ct06 3.304Et04 0.000E-01 LUNG 45 CD-115M 1.113Ct03 0.000E-01 0.000E-01 3.444Ef04 2.772Et04 2.444EiO5 6.720El04 0.000C-01 LUNG 46 SB-124 2.170Et03 1.322Et01 5.440Et03 1.030Et02 0.000E-01 4.340Et05 7.112Et04 0.000E-01 LUNG 47 TE-125M 4.580E402 1.624Et03 4.760Et03 1.900Et03 0.000E-01 4.466Et05 1.291E104 0.000E-01 LUNG 48 TE-127M 2.072Et03 4.072Et03 1.666Et04 6.902Et03 3.752EiO4 1.312Ct06 2.730Ef04 0.000E-01 LUNG 49 TE-127 4.886E-01-1.0400900 2.226E400 9.531E-01 4.858C100 1.035C404 2.436Et04 0.000E-01 GI"LLI 50 TE-129M 2.226E403 5.474Et03 1.414Et04 6.090Et03 3.178Et04 1.680EiO6 6.902Ef04 0.000E-01 LUNG 51 TE-129 1.876E-02 6.74uE-02 7.082C-02 3.472E-02 1.750E-01 2.996tt03 2.632E604 0.000E-01 GI-LLI 52 TE-131M 3.626E4 01 8.932Et01 1.067E t02 5.502Et01 2.646Ct02 1.980E4 05 1.191Et05 0.000E-01 LUNG 53 TE-131 4.990E-03 1.502E-02 1.736E-02 8.21EE-03 3.990E-02 2.05CEt03 8.210Et03 0.000C-01 GI-LLI 54 TE-132 1.764Et02 2.786E102 3.724E602 2.366Et02 1.035Et03 3.402E405 4.410Et04 0.000E-01 LUt'G 55 I-130 5.572EIO3 1.596E104 6.356E103 1.337E104 1.526E404 0.000C-01 1.98DE103 0.000E-01 THfROID 56 I-131 1.960E404 1.4SiEt07 3.794EiO4 4.438E104 5.180Ef04 0.000C-01 1.05HEt03 0.000E-01 lilYROID 57 I-132 1.259Ct03 1.694CIOS 1.694Ct03 3.542Et03 3.94SE403 0.000E-01 1.904Ef03 0.000E-01 THYROID 50 I-133 5.600Et03 3.b56Et06 1.324Et04 1.918E604 2.240Et04 0.000E-01 2.156Et03 0.000E-01 THYROID 59 I-134 4.650Ct02 4.452Et04 9.212Et02 1.876Et03 2.086Et03 0.000C-01 1.29?EiO3 0.000E-01 THYROID 60 I-135 2.7720 t03 6.950E105 3.864El03 7.602Et03 8.4>0E403 0.000E-01 1.831Et03 0.000E-01 THYRDIb 61 CS-134 7.44SCt04 0.000E-01 3.962Et05 7.02 set 05 1.901E105 7.966Et04 1.334Et03 0.000E-01 LIVER 62 CS-136 5.292Ct04 0.000E-01 4.830EiO4 1.345E105 5.612CiO4 1.176Et04 1.423C603 0.000E-01 LIVEN 63 CS-127 4.550C404 0.000E-01 5.480Et05 6.118Ef05 1.722Et05 7.126Et04 1.334E103 0.000E-01 LIVER 44 CS-113 3.976El02 0.000C-01 5.054E402 7.812Ef 02 4.102Et02 6.530C t01 0.764Et02 0.000E-01 GI-LLI 65 CS-1L9 1.946Et01 0.000E-01 3.504Et01 5.002El01 4.270Et01 3.976Et00 0.000E-01 0.000E-01 LIVEN 66 BA-139 4.298E-02 0.000E-01 1.484EiO3 9.842E-04 5.922E-04 5.950Ct03 5.096Et04 0.000E-01 GI-LLI 67 PA-140 2.890Ct03 0.000E-01 5.600E404 5.600E401 1.343E101 1.594Et06 3.836Et04 0.000E-01 LUHG 60 BA-141 4.970C-03 0.000E-01 1.56SE-01 1.078E-04 6.496E-05 2.960Ct03 4.746Et03 0.000E-01 G:-LLI 69 BA-142 1.960E-03 0.000E-01 3.976E-02 3.304E-05 1.904E-05 1.551Et03 6.930Et02 0.000E-01 LUNG 70 LA-140 5.152Et01 0.000E-01 5.054Ef 02 2.002Et02 0.000E-01 1.680E t05 8.484Et04 0.000E-01 LUNG

m Pzgi 12 of 39- ,.

                                                                                                                       .L
                                         , v~                ._

ATTACHMENT 7 Pathway Dose Parameters 3 Rt(mrem /yrper(Ci/m) AGE 1 INFANT PATHWAY ! INHALATION , NO ISOTOPE W. BODY THYROID BONE- LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 9.044E-02 0.000E-01 1 030Et00 3.764E-01 0.000E-01 8.218Ef03 5.950Et04 9.044E-02 OI-LLI 72 EE-141 1.98DEf03 0.000E-01 2.772E+04 1.666E+04 5.250E+03 5.166Ef05 2.156Et04 0.000E-01 LUNG 73 CE-143 2.212Et01 0.000E-01 2.926Ef02 1.932Ef02 5.642E+01 1.162Ef05 4.970E101 0.000E-01 LUNG 74 CE-144 1.764E+05 0.000E-01 3.192Ef06 1.211E+06 5.376Et05 9.842E406 1.404Ef05 0.000E-01 LUNG 75 PR-143 6.906Et02 0.000E-01 1.400Ef04 5.236E+03 1.974E+03 4.326Et05 3.724Et04 0.000E-01 LUNG 76 PR-144 2.403E-03 0.000E-01 4.780E-02 1.818E-02 4.720E-03 1.610Et03 4.2C4Et03 0.000E-01 GI-LLI 77 ND-147 4.990Et02 0.000E-01 7.938E+03 8.134Ef03 3.150E+03 3.220Et05 3.122E404 0.000E-01 LUHG i 70 W-185 9.531E+00 0.000E-01 2 730Ef02 9.058E401 0.000E-01 7.790Ef04 1.4?EEt04 0.000E-01 LUNG 7Y W-187 3.122E+00 0.000E-01 1.296E401 9.016Et00 0.000E-01 3.962E404 3.556Et04 0.000E-01 LUNG 80 U-235 8.4vuEt05 0.000E-01 1.400Et07 0.000E-01 3.276Ef06 6.860Et07 6.776Et04 0.000E-01 LUNG 01 U-238 7.93GEt05 0.000E-01 1.341E+07 0.000E-01 3.052E+06 6.412Et07 1.442Et05 0.000E-01 LUNG

1. 02 NP-239 1.076E+01 0.000E-01 3.710El02 3.310E+01 6.622Ef01 5.950Et04 2.4?2Ef01 0.000E-01 LUNG i

j 1 .I 1

4 1 J

                                                                                                      --Pcgn 13 of'39 .

v w e. ATTACHMENT 7 pattway Dose Parameters Rt N - m M per M d AGE 1 ADULT PATHWAY 1 VEGETATION NO ISOTOPE- W. BODY THYROID BONE LIVER KIDNEY LUNG GI-LLI- EKIN CRITICAL 1 H-3" 2.260E+03 2.260E+03 0.000E-01 2.260Et03 2.260E+03 2.260Ef03 2.260E403 2.260E+03 W. BODY 2 C-14, 1.793E+05 1.793Ef05 8.966E+05 1.793Ef05 1.793E+05 1.793Et05 1.793Ef05 1.793E405 BONE 3 NA-24 2.692E+05 2.692E+05 2.692E405 2.692Ef05 2.692E+05 2.692E+05 2.692Et05 0.000E-01 _W. BODY 4 P-32 5.433Ct07 0.000E-01 1.406E+09 8.740E407 0.000E-01 0.000E-01 1.580Ef08 0.000E-01 BONE 5 SC-46 1.414Et05 0.000E-01 2.505E+05 4.910Et05 4.547EtOS 0.000E-01 2.369Efo9 0.000E-01 GI-LLI 6 CR-51 4.656Et04 2.783Ef04 0.000E-01 0.000E-01 1.026E404 6.178E104 1.171E+07 0.000E-01 GI-LLI 7 MN-54 5.969CtO7 0.000E-01 0.000E-01 3.120E+08 9.309E+07 0.000E-01 9.503Et00 0.000E-01 GI-LLI 8 MM-56 2.730E+00 0.000E-01 0.000E-01 1.539Et01 1.954Ef01 0.000E-01 4.912E602 0.000E-01 GI-LLI 9 FE-55 3.376E+07 0.000E-01 2.096Ef08 1.448Ef08 0.000E-01 0.077Et07 0.306E607 0.000E-01 BONE 10 TE-59 1.135E408 0.000E-01 1.260E t0B 2 961Ef 00 0.000E-01 8.273E407 9.069E t08 0.000E-01 GI-LLI 11 E0-58 6.939Et07 0.000E-01 0.000E-01 3.096Et07 0.000E-01 0.000E-01 6.274E103 0.000E-01 GI-LLI 12 EO-60 3.686E+00 0.000E-01 0.000E-01 1.671Et08 0.000E-01 0.000E-01 3.139El09 0.000E-01 GI-LLI 13 NI-59 1.304f100 0.000E-01 7.830E+08 2.685E608 0.000E-01 0.000E-01 5.530E607 0.000E-01 DONE 14 NI-63 3.489Et00 0.000E-01 1.040Et10 7.211E+00 0.000E-01 0.000E-01 1.50LEt08 0.000E-01 BONC 15 NI-65 3.537Et00 0.000E-01 5.967E401 7.752Et00 0.000E-01 0.000C-01 1.944E102 0.000E-01 GI-LLI 16 EU-61 4.267Ct03 0.000E-01 0.000E-01 9.090E103 2.292E+04 0.000E-01 7.7 t1E105 0.000E-01 GI-LLI 17 ZH-65 4.556E108 0.000E-01 3.16BEf08 1.00CEt09 6.742Ef08 0.000E-01 6.3SvC400 0.000E-01 LIVER 18 ZN-69 1.040E-06 0.000E-01 7.819E-06 1.495E-05 9.716E-06 0.000E-01 2.2*IE-06 0.000E-01 LIVER 19 0R-83 3.0S7FtOO 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 4.414E600 0.000E-01 GI-LLI 20 BR-84 2.003E-11 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 1.57/E-16 0.000E-01 W. DODY 21 BR-05 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. PODY 22 kB-06 1.019E+0D 0.000E-01 0.000E-01 2.187Ef00 G.000E-01 0.000E-01 4.311E607 0.000E-01 LIVER 23 RB-83 9.802C-23 0.000E-01 0.000E-01 1.063E-22 0.000E-01 0.000E-01 0.000E-01 0.000E-01 LIVER 24 RB-89 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 25 SR-09 2.057E+0D 0.000E-01 9.954EiO9 0.000E-01 0.000E-01 0.000E-01 1.5?6E109 0.000E-01 DONE 26 SR-90 1. 401E t 11 0.000E-01 6.046E+11 0.000E-01 0.000E-01 0.000E-01 1.747E+10 0.000E-01 LONE 27 ER-91 1.215E t 0 4 0.000E -01 3.009EiOS 0.000E-01 0.000E-01 0.000E-01 1.433E106 0.000E-01 GI-!.LI 28 SR-92 1.704Et01 0.000E-01 4.125Et02 0.000E-01 0.000E-01 0.000C-01 8.172Et03 0.000E-01 GI-LLI 29 Y-90 3.564Et02 0.000E-01 1.330Ef04 0.000E-01 0.000E-01 0.000E-01 1.410EtOS 0.000E-01 GI-LLI 30 Y-91M 1.909E-10 0.000E-01 4.930E-09 0.000E-01 0.000E-01 0.000E-01 1.448E-00 0.000E-01 GI-LLI 31 Y-91 1.36CCt05 0.000E-01 5.116Et06 0.000E-01 0.000E-01 0.000E-01 2.816Ef09 0.000E-01 GI-LLI 32 Y-92 2.615E-02 0.000E-01 8.946E-01 0.000E-01 0.000E-01 0.000E-01 1.567Et04 0.000E-01 GI-LLI 33 Y-93 4.751E100 0.000E-01 1.721E+02 0.000E-01 0.000E-01 0.000E-01 5.457Ef06 0.000E-01 GI-LLI 34 ZR-95 2.596EiO5 0.000E-01 1.196E404 3.835E+05 6.019Ef05 0.000E-01 1.216Et09 0 000E-01 GI-LLI 35 ZR-97 3.094E101 0.000E-01 3.354E402 6.767E+01 1.022Et02 0.000E-01 2.096E+07 0.000E-01 GI-LLI

Units are (mres/yr per uCi/m 3)

J

Pzga 14 cf 39 ' : .

                                                                            .    .M ATTACHMENT 7 Pathuey Dose Parameters :
                                                        -Rg M E M F M O M AGE 1 ADULT PATHWAY 3 VEGETATION NO ISOTDPE       W. BODY    THYROID    BONE          LIVER     KIDNEY      LUNG. GI-LLI     SKIN'    CRITICAL 3a HD-95       '4.254Ct04 0.000E-01 1.423E405 7.914Et04 7.822Ef 04 0.000E-01 4.803E400 0.000E GI-LLI-37 HB       2.516E-07 0.000E-01 2.730E-06 6.889E-07 8.037E-07 0.000E-01 2.542E-03 0.000E-01 GI-LLI 33 MO-99        1.167C+06 0.000E-01 0.000E-01 4 136E406.1.390Et07 0.000E-01 1.422Et07 0.000E-01        GI-LLI 39 TC-99M-      1.113Ef02 0.000E-01 3.093Ef00 8.710Et00 1.327Ef02 4.283LiOO 5.172E403 0.000E-01 GI-LLI
      ~

40 TC-101 0.000E-01 0.000C-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 41 RU-103 2.074E406 0.000E-01 4.815EiO6 0.000E-01 1.837Ct07 0.000C-01 5.621Et03 0.000E-01 GI-LLI 42 Ru-105 2.10iEt01 0.000E-01 5.330Ct01 0.000E-01 6.8SOEiO2 0.000C-01 3.261Et01 0.000E-01 GI-LLI 43 RU-106 2.441Et07 0.000E-01 1.929Et08 0.000E-01 3.724E400 0.000E-01 1.240Et10 0.000E-01 GI-LLI 44 AG-110M 5.796Ct06 0.000C-01'1.055Ef07 9.753C404 1.919Et07 0.000E-01 3.992CiO9 0.000E-01 GI-LLI 45 CD-115M 1.643Ct06 0.000E-01 0.000E-01 5.1577907 4.092Et07 0.000E-01 2.169Et09 0.000E-01 GI-LLI 46 SD-124 4.115El07 2.517Et05 1.042E108 1.965E406 0.000E-01 8.031E607 2.vi7Et09 0.000E GI-LLI 4/ TC-125M 1.296Et07 2.909Et07. 9.672Et07 -3.504E107 3.934Et08 0.000C-01 3.062Et03 0.000E-01 KIDNEY 40 TE-127H' 4.255Et07 8.921E+07 3.492EiOS.1.248Et00 1.410E10? 0.000C-01 1.171E109 0.000E-01 KIDNEY 49 TE-127 1.230Et03 * . 211Et03 5.684Ct03 2.041Et03 2.315El04 0.000E-01 4.405El05 0.000E-01 GI-LLI 50 TE-129M 3.9b5C407 8.534E407 2.499C400 9.323E407 1.043Et09 0.000C-01 1.25CEtO9 0.000E-01 GI-LLI 51 TE-129 1.901E-04 5.9Y7E-04 7.813E-04 2.934E-04 3.204E-03 0.000E-01 5.097E-04 0.000E-01 KIDHEY 52 TE-131M- 3.705Et05 7.013Et05 9.092Et05 4.446Et05 4.501El06 0.000C-01 4.415Et07 0.000E-01 GI-LLI 53 TC-131 4.341E-16 1.131C-15 1.375E-15 5.744E-16 6.023E-15 0.000L-01 1.9470-16 0.000E-01 KIDHEY 54 TE-132 2.600Et06 3.05DEt06 4.202Et06 2.769E106 2.660Ct07 0.000E-01 1.310EtOS 0.000E-01 GI-LLI 55 I-130 4.591E405 v.061E107 3.941Et05 1.163Et06 1.816Et06 0.000L-01 1.002E606.0.000C-01 THYROID 56 I-131 6.422Et07 3.787Et10 8.079Ct07 1.155E40tl 1.901El00 0.000E-01 3.049L107 0.000E-01 THYRDID 57 1-132 4.?60Et01 4.963El03 5.308Ef01 1.420Et02 2.262Et02 0.000E-01 2.467EiO1 0.000E-01 THYROID 50 I-133 1.103E t06 5.318Et03 2.ODOE t 06 3.618El06 6.314Cl06 0.000E-01 3.252EtC6 0.000E-01 TilYROID 59 I-134 0.304E-05 4.024E-03 8.548E-05 2.322E-04 3.693E-04 0.000E-01 2.024E-07 0.000E-01 THYROID 60 I-135 3.491Ef 01 6.597E t04 3.820Et01 1.000Ef 05 1.601E t 05 0.000E-01 1.130Et05 0.000E-01 TilVROID 61 CS-134 9.076Ct09 0.000E-01 4.666Ef09 1.110Ct10 3.593EiO9 1.193Et09 1.943E400 0.000E-01 LIVER 62 CG-134 1.195Et03 0.000E-01 4.204Et07 1.660Cf 08 9.235E407 1.266E407 1.834Et07 0.000E-01 LIVER 63 CS-137 5.696E409 0.000E-01 6.353Et09 8.696Ef09 2.952E409.9.013Et03 1.633Ef08 0.000E-01 LIVER 64 CS-138 3.554E-11 0.000E-01 3.633E-11 7.174E-11 5.272C-11 5.206E-12 3.0612-16 0.000E-01 LIVER 45 CS-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000C-01 0.000E-01 W. BODY 66 DA-139 7.V250- 01 0.000E-01 2.707E-02 1.92CE-05 1.003E-05 1.094C-05 4.000E-02 0.000E-01 GI-LLI a7 BA-140 8.405Ef06 0.000E-01 1.203El08 1.611Et05-5.479EiO4 9.227Ef04 2.642Et08 0.000E-01 GI-LLI 68 BA-141 3.309E-23 0.000E-01 1.004E-21 7.589C-25 7.056E-25 0.000E-01 0.000E-01 0.000E-01 BONE 69 BA-142 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 70 LA-140 2.634Ct02 0.000E-01 1.97 bet 03 9.96BE402 0.000E-01 0.000E-01 7.318Et07 0.000C-01 GI-LLI

                                                                                                                               - _    _.---.____O

Pcg2: 15 4f 39- . m< ...mw .,- ATTACHMENT 7 Pathway Dose Parameters Rg 2(m -m%rp Wsd AGE 1 ADULT PATHWAY 1 VEGETATION NO ISOTDPE W. BODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 1.508E-05 0.000E-01 1.331E-04 6.051E-05 0.000E-01 0.000E-01 4.419E-01 0.000E-01 GI-LLI 72 CE-141 1.511Et04 0.000E-01.1.970Ef05 1.332Et05 6.188Ef04 0.000E-01 5.094Et08 0.000E-01 GI-LLI 73 CE-143 8.154Et01 0.000E-01 9.966Ef02 7.369Et05 3.244Et02 0.000E-01 2.751Et07 0.000E-01 GI-LLI 74 CE-144 1.765Et06 0.000E-01 3.288E407 1.375Et07 8.153Ef06 0.000E-01 1.112Et10 0.000E-01 GT-LLI 75 PR-143 3.101Et03 0.000E-01 6.256Ef04 2.509Et04 1.448E404 0.000E-01 2.710Et00 0.000E-01 GI-LLI 76 FR-144 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. T<0DY 77 ND-147 2.303Et03 0.000E-01 3.330Et04 3.849Et04 2.250Et04 0.000E-01 1.04 set 08 0.000E-01 GI-LLI 78 W-185 6.065Et05 0.000E-01 1.734C107 5.766Et06 0.000E-01 0.000E-01 6.663E t 011 0.000E-01 GI-LLI 79 W-187 1.112Et04 0.000E-01 3.806Ef04 3.101Et04 0.000E-01 0.000E-01 1.0 CE l07 0.000E-01 GI-LLI 80 U-235 3.895Et0? 0.000E-01 6.427Et10 0.000E-01 1.499Et10 0.000E-01 6.259EtO9 0.000E-01 Bot!E 01 U-238 3.646Et09 0.000E-01 6.147Et10 0.000E-01 1.402Et10 0.000E-01 1.33tEt10 0.000E-01 B0HE C2 NP-237 7.693E101 0.000E-01 1.419Et03 1.396Et02 4.351E402 0.000E-01 2.Os3Cio? 0.000E-01 GI-LLI 9 _ . _ _ - _-_-_____---.--_.___--._...A

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?- :m P;ga'17 ef 39 . ATTACHMENT 7 Pathway Dose Parameters Rt (m2 ; mren/yr per (C1/sec) AGE 1 TEEN PATHWAY 1 VEGETATION s NO ISOTOPE W. BODY TilYROID BONE LIVER AIDNEY LUNG GI-LLI SKIN CRITICAL 36 HD-95 5.865Et04 0.000E-01 1.921Ef05 1.065E+05 1.033E405 0.000E-01 4.55iEf08 0.000E-01 GI-LLI 37 t1B-97 1.651E-07 0.000E-01 1.791E-06 4.521E-07 5.274E-07 0.000E-01 1.663E-03 0.000E-01 GI-LLI 20 MD-99 1.074E+06 0.000E-01 0.000E-01 5.631Ef06'1.28?Et07 0.000E-01 1.009Et07 0.000E-01 KIDNEY 39 TC-99M 9.041E101 0.000E-01 2.728Et00 7.610Et00 1.134Ef02 4.224Ef00 4.996El03 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. PODY 41 RU-103 2.916Et06 0.000E-01 6.091EiO6 0.000E-01 2.42?Et07 0.000E-01 5.756Et00 0.000E-01 GI-LLI 42 RU-105 1 922Ct01 0.000E-01 4.952Et01 0.000E-01 6.247Et02 0.000E-01 3.990El04 0.000E-01 GI-LLI 43 RU-106 3.903Et07 0.000E-01 3.097Ct08 0.000E-01 5.Y73EtOS 0.000E-01 1.435El10 0.000E-01 GI-LLI 44 AG-110M 0.735Et06 0.000E-01 1.517Et07 1.436Et07 2.739E607 0.000E-01 4.031Ct09 0.000E-01 GI-LLI 45 ED-115N 1.726Et06 0.000E-01 0.000E-01 5.401E107 4.205Et07 0.000E-01 2.272Et09 0.000E-01 GI-LLI 46 SD-121 4.433E107 2.712Et05 1.122Et08 2.116Et06 0.000E-01 0.70sEic7 3.175EiO9 0.000E-01 GI-LLI 47 TE-125M 1.986Lt07 4.150Et07 1.486E108 5.352E407 0.000E-01 0.000E-01 4.303E100 0.000E-01 GI-LLI 40 TE-127M 6.559Et07 1.312E608 5.515Et08 1.956El08 2.236Et09 0.000E-01 1.371Et09 0.000E-01 KIDNEY 49 TE-127 1.153Et05 3.696Et03 5.350Et03 1.899Et03 2.170Et04 0.000E-01 4.137Et05 0.000E-01 GI-LLI 50 TE-129M 5.60?tt07 1.160Et00 3.594Ef00 1.331EiOS 1.504El09 0.000E-01 1.319Et0? 0.000E-01 KIbHEY 51 TE-129 1.780E-04 5.225E-04 7.315E-04 2.727E-Oi 3.070E-03 0.000E-01 4.001E-03 0.000E-01 GI-LLI 52 TE-131M 3.366Ef05 6.070Et05 8.416Et05'4.035Ef05 4.200Et06 0.000E-01 3.239Et07 0.000E-01 GI-LLI 53 TE-131 3.994E-16 9.818E-16 1.27DE-15 5.267E-16 5.588E-15 0.000E-01 1.019E-16 0.000E-01 KIDNEY 54 TE-132 2.319Et06 2.59AEt06 3.891Et06 2.464Et06 2.36.4Et07 0.000E-01 7.005Et07 0.000E-01 GI-LLI b5 1-130 4.074E405 0.320Et07 3.527E405 1.020E406 1 572Et06 0.000E-01 7.841Et05 0.000E-01 THYR 01D 56 1-131 5.783Et07 3.141Et10 7.689Et07 1.076E600 1.053Et08 0.000E-01 2.12 vet 07 0.000E-01 TiiV601D 57 I-132 4.496El01 4.221E103 4.709E+01 1.253Et02 1.97 jet 02 0.000E-01 5.457EiO1 0.000E-01 TitYRDID 58 I-133 9.998L405 4.576Et03 1.932El06 3.279EiO4 5.749Et06 0.C00E-01 2.400E404 0.000E-01 TilYROID 59 I-134 7.356E-05 3.413E-03 7.726E-05 2.048E-04 3.22DE-04 0.000E-01 2.699E-06 0.000E-01 TilVROID 60 I-135 3.291Et04 5.715Ef04 3.452E404.8.894C404 1.403E+05 0.000E-01 9.846E104 0.000E-01 THYRDID 61 CS-134 7.7500609 0.000E-01 7.097Et09 1.670Et10 5.300E409 2.027Et09 2.077E108 0.000E-01 LIVER 62 C5-136 1.133E100 0.000E-01 4.289E107 1.680El00 9.187E407 1.41GE407 1.350Et07 0.000E-01 LIVER 63 EG -137 ri.6?LEl09 0.000E-01 1.013El10 1.318Et10 4.506Et09 1.702Et09 1.910El00 0.000E-01 LIVER 61 CS-138 3.210E-11 0.000E-01 3.352E-11 6.136E-11 4.751E-11 5.52?C-12 2.920E-14 0.000E-01 LIVER 65 CS-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. B0bY 66 BA-139 7.417L-04 0.000E-01 2.545E-02 1.791E-05 1.688E-05 1.234E-05 2.271E-01 0.000E-01 GI-LLI 67 BA-140 8.882Et06 0.000E-01 1.370El08 1.689Et05 5.727E104 1.136EtO5 2.126Et03 0.000E-01 GI-LLI 68 BA-141 3.131E-23 0.000E-01 9.387E-22 7.009E-25 6.505E-25 4.7VSE-25 0.000E-01 0.000E-01 LONE 69 DA -142 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. EODY 70 1.A- 140 2.362Ef02 0.000E-01 1.807Ef03 8.878Ef02 0.000E-01 0.000E-01 5.090Et07 0.000E-01 GI-LLI

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i' ATTACHMENT 7 Pathway Done Parameters Rg M - mram/yr per tri/sec) AGE 1 TEEN PATHWAY 1. VEGETATION

z NO ISOTOPE W. BODY THYROID 'DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 1.351E-05 0.000E-01 1 221E-04 5.424E-05 0.000E-01 0.000E-01 1.651Et00 0.000E-01 G1-LLI 72 CE-141 2.1680101 0.000E-01 2.827Et05 1.888Ef05 8.886E404 0.000E-01 5.399E408 0.000E GI-LLI 73 CE-143 7.571Lt03 0.000E-01 9.315Et02 6.778EtOS 3.040Ef02 0.000E-01 2.037Et07 0.000E-01 GI-LLI 7a CE-144 2.833Et06 0.000E-01 5.271E+07 2.181Ef07 1.303E407 0.000E-01 1.325E110 0.000E-01 GI-LLI

       . 75 FR-143-    3.480t +03 0.000E-01 6.995Et04 2.793E404 1.623Et04 0.000E-01 2.301E408 0.000E GI-LLI 7c,PR-144     0.000E-01 0.000E-01 0.000E-11 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 77  HD-147    2.356E403 0.000E-01 3.617Et34 3.933E404 2.310Et04 0.000E-01 1.419E408 0.000E-01 GI-LLI 79  W-185     6.613Et05 0.000E-01 1.891E407 6.287E+06 0.000E-01 0.000E-01 7.265E108 0.000E-01 GI-LLI 79  W-18/     1.011Et04 0.000E-01 3.540Et04 2.885E+04 0.000E-01 0.000E-01 7.80elt06 0.000E-01 GI-LLI

_ 90 U-235 4.117E409 0.000E-01 7.289Et10 0.000E-01 1.700Et10 0.000E-01 7.09fEt09 0.000E-01 BONE 81 U-238 4.136E109 0.000E-01 6.971Et10 0.000E-01 1.591E110 0.000E-01 1.509Et10 0.000E-01 B0fC 02 HP-239 7.217Et01 0.000E-01 1.378E403 1.299Ef02 4.078EiO2 0.000E-01 2.090E107 0.000E-01 GI-LLI e s e

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pig 2-20 cf 39; . 1 . ATTACHMENT 7 j Pathway Done Parameters Rt (m2 _ ,,,,7y,p ,gggy,,g). AGE 8 CHILD PATHWAY 1 VEGETATION NO ISOTDPE W. BODY THYROID BONE LIVER KIDNEY LUNG' GI-LLI' SKIN CRITICAL, 34 MB-95 1.141Et05 0.000E-01' 4.101E405 1.597E+05 1.500Ef 05 0.000E-01 2.953Ef 08 0.000E-01 GI-LLk 37 NB-97 1.022C-07 0.000E-01 1.109E-06 2.799E-07 3.265E-07 0.000E-01 1.033E-03 0.000E-01 GI-LLI 39 MO-99 1.V03C+06 0.000E-01 0.000E-01 7.693Ef06 1.643Et07 0.000E-01 6.362E+06 0.000E-01' KIDf!EY 4 39 TC-99M 1.526Ef02 0.000E-01 4.695Et00 9.20CE+00 1.330E102 4.675Et00 5.240E403 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01. 0.000E-01 0.000E- 01 0.000E-01 0.000E-01 W. BODY 41 RU-103 5.959Et04 0.000E-01 1.550Et07 0.000E-01 3.902Ef07 0.000E-01 4.008E408 0.000E-01 GI-LLI 42 RU-105 3.290Et01 0.000E-01 9.070Et01 0.000E-01 7.973E+02 0.000E-01 5.920Ef04 0.000E-01 GI-LLI-43 RU-106 9.300C+07 0.000E-01 7.459Ef08 0.000E-01 1.007El09 0.000E-01 1.160Et10-0.000E-01 GI-LLI

44 AG-110M 1.734E+07 0.000E-01.3.216Ef07 2.172E407 4.046E+07 0.000E-01 2.50*EiO9 0.000E-01 GI-LLI 45 CD-115M 1.359Et06 0.000E-01 0.000E-01 4.251Et07 3.373Ef07 0.000E-01 1.7 DOE 109 0.000E-01 GI-LLI 44 SD-124 3.524Et07 2.156Et05 8.921E+07 1.603E+06 0.000E-01 6.921Et07 2.521Et09 0.000E-01 GI-LLI 4 47 TE-125M 4.683Et07 9.859E407 3.512Et09 9.520Et07 0.000E-01 0.000E-01 3.309EtOS 0.GOOE-01 B0HE j - 40 TE-127M 1.549Et03 3.161E+0S 1.322E109 3.559Ct00 3.74 vet 09 0.000E-01 1.070Ct09 0.000E-01 KIDHEY 2.120Et03'6.843EiO3 9.037Et03 2.664Et03 2.813E101 0.000E-01 3.062Ef05 0.000E-01 GI-LLI 49'TE-127 50 TE-129M 1.297Ct08 2.693Et08 8.354E+08 2.333E408 2.453Et09 0.000E-01 1.019Et09 0.000E-01 KIDHEY 51 TE-129 3.215E-04 9.661E-04 1.35LE-03 3.701E-04 3.963E-03 0.000E-01 8.131E-02 0.000E-01 GI-LLI 1

52 TE-131M 5.650Ct05 1.093Ef06 1.537E406 5.314Ef05 5.146Ef06 0.000E-01 2.154Ef07 0.000E-01 GI-LLI 53 TE-131 7.003E-16 1.800E-15 2.353E-15 7.174C-16 7.117E-15 0.000E-01 1.236E-14 0.000E-01 GI-LLI

              . 54 TE-132    3.727Et06 4.491Et06 6.972E406 3.086E+06 2.~0$5E407 0.000E-01 3.106Et07 0.000E-01 GI-LLI 55 1-130      6.443Et05 1.37CEtOS 6.199E+05 1.251Et06 1.849Et06 0.000E-01 5.850EiO5 0.000E-01 THYROID
                                                                  ~

54 I-131 8.175Et07 4.757E+10 1.430EiO8 1.439Et08 2.362E400 0.000E-01 1.281E107 0.000E-01 THYROID 57 I-132 7.101E+01 7.245E403 8.498Et01 1.562Et02 2.390Et02 0.000E-01 1.83CE102 0.000E-01 THYROID 58 I-133 1.649EiO6 8.094Et09 3.523E+06 4.356Et06 7.261Ef06 0.000E-01 1.756Ef06 0.000E-01 .1HYROID 59 I-134 1.173E-0 4 5.864E-03 1 373E-04 2.549E-04 3.898E-04 0.000E-01 1.490E-04 0.000E-01 THYRDID 60 I-135 5.220Et04 9.774Et04 6.130Ef04 1.103Et05 1.692EiO5 0.000E-01 8.407E104 0.000E-01 .1HYROID 61 CS-134 5.549E409 0.000E-01 1.603C+10 2.631Ef10 9.152Ef09 2.?25Et09 1.110EiO3 0.000E-01 LIVER i 62 CS-134 1.434Et08 0.000E-01 8.062E+07 2.216E403 1.130E108 1.760Et07 7.707Ef06 0.000E-01 LIVER l 63 CS-137 3.380Et09 0.000E-01 2.392Et10 2.290Et10 7.462Efo9 2.685Ef09 1.434Ef08 0.000E-01 BONE i 64 CS-138 5.375E-11 0.000E-01 6.097E-11 8.474E-11 5.963E-11 4.417E-12 3.904E-11 0.000E-01 LIVER

45 CS-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY l 66 BA-139 1.360E-03 0.000E-01 4.693E-02 2.505E-05 2.18DE-05 1.474E-05 2.709E400 0.000E-01 GI-LLI: 47 BA-140 1.611Ef07 0.000E-01 2.761Et08 2.419Et05 7.875Et04 1.442E+05 1.399Ef08 0.000E-01 BONE j 60 BA-141 5.638E-23 0.000E-01 1 732E-21 9.699E-25 8.392E-25 5.698E-24 9.872E-22 0.000E-01 EDNE

!               69  BA-142    0.000E-01 0.000E-01 0.000E-01.0.000E-01 0.000E-01 0.000E-01 0.000E-01 0'.000E-01 W. BODY l               70  LA-140    3.335Ef 02 0.000E-01 3.2 t&E403 1.134E403 0.000E-01 0.( 00E-01 3.162E+07 0.000E-01 GI-LLI i

v

Pcgi 21 cf 39 1 ATTACHMENT 7

                                                                      ~.            ,_   _ ___                    ,

Pattwey Dose Parameters 2 Rg (m -mram/yrper(Ci/sec) AGE 1 CHILD PATHWAY i VEGETATIDH-NO IEDTCPE W. PODY THYRDID BONE LIVER KIDNEY LUNG GI-LLI SKIN. CRITICAL , 71 LA-142 2.209E-05 0.000E-01 2.213E-04 7.054E-05 0.000E-01 0.000E-01 1.390Et01 0.000E-01 GI-LLI 72 CE-141 4.854Et04 0.000E-01 6.555Et05 3.26*E+05 1.433E+05 0.000E-01 4.07CEt08 0.000E-01 GI-LLI 73 CE-143 1.34/El02 0.000E-01 1.715Et03 9.300E+05 3.902E+02 0.000E-01 1.362Lt07 0.000E-01 DI-LLI 74 CE-144 4.780E+06 0.000E 01 1.270E408 3.982E+07 2.205E+07 0.000E-01 1.03 set 10 0.000E-01 GI-LLI 75 PR-143 7.216Et03 0.000E-01 1.454E+05 4.367E+04 2.365E+04 0.000E-01 1.569Et0D 0.OOGE-01 GI-LLI 76 Pf?!44 0 000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 2.632F-23 0.000E-01 GI-LLI 77 HD-147 4.1/ set 03 0.C 00E-01 7.140E+04 5.783E+04 3.173E t04 0.000E-01 9.161Lt07 0.000E-01 GI-LLI 73 W 195 5 279EtOS C.000E-01 1.509Et07 5.019Et06 0.000E-01 0.000E-01 5.80GitOS 0.000E-01 GI-LLI 79 u-tS7 1.711E604 0.00CE-01 6.439E404 3.813E404 0.000E-01 0.000L-01 5.359f.106 0.000E-01 GI-LLI 80 U-235 3.5/30409 0.000E-01 5.095Et10 0.000E-01 1.375Et10 0.000E-01 5.741E:09 0.000E-01 PONE 81 U-238 3.345Et09 0.000E-01 5.630Et10 0.000E-01 1.206Lt10 0.000E-01 1.220E010 0.000E-01 PONE 82 NP-239 1 231Et02 0.000E-01 2.544Ef03 1.827Et02 5.282E+02 0.000E-01 1.352E407 0.000E-01 GI-LLI 4

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Pattway Dose Parameters 2 Rg(m - erem/yr per tri/sec) AGE 1 ADULT PATHWAY : CDU MILK NO ISOTDPE W. BODY THYRDID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36 NB-95 2.46CE t04 0.000E-01 8.253Et04 4.591E+04 4.539Et04 0.000E -01 2.706E TOG 0.000E-01 GI-LLI 37 NB-97 5.419E-13 0.000E-01 5.880E-12 1.484E-12 1.731E-12 0.000E-01 5.475E-09 0.000E-01 GI-LLI 33 MO-99 4.705E606 0.000E-01 0.000E-01 2.473Et07 5.600Ef07 0.000E-01 5.732EIO7 0.000E-01 GI-LLI 19 TC-99M 1.216Et02 0.000E-01 3.378E+00 9.545Et00 1.450Ef02 4.677Ef00 5.64SE603 0.000E-01 GI-LLI ^ 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 C.000E-01 0.000E-01 0.000E-01 W. DODY 43 RU-103 4.39CEt02 0.000E-01 1.021Ef03 0.000E-01 3.896E403 0.000E-01 1.192Et05 0.000E-01 GI-LLI 42 ku-105 3.425E-04 0.000E-01 8.676E-04 0.000E-01 1.121E-02 0.000E-01 5.307E-01 0.000E-01 GI-LLI 43 RU-106 2.582Et03 0.000E-01 2.040E+04 0.000E-01 3.939Ef04 0.000E-01 1.321Et06 0.000E-01 GI-LLI 4 4 AG-110M 3.200ff07 0.000E-01 5.82SEf07 5.383E+07 1.05YEt08 0.000E-01 2.199Et10 0.000E-01 GI-LLI 45 CD-115M 3.931Lt04 0.0uoE-01 0.000E-01 1.246E+06 9.881E 605 0.000E-01 5.210t;t07 0.000E-01 GI-LLI 46 SB-124 1.021E t07 6.2430 t04 2.584Ef 07 4.873E+05 0.000E-01 2.005E t 07 7.310EtOS 0.000E-01 GI-LLI 17 TE-125M 2.103Ef06 4.YO2Et06 1.630Et07 5.905Et06 6.62?Et07 0.000E-01 6.507Et07 0.000E-03 KIDt!EY 46 TE-127M 5.5790f 06 1.170Et07 4.570E607 1.636EtO7 1.060E408 0.000F-01 1.535Lt08 0.000E-01 KIL1 REY 4? TE-127 1.442Et02 4.93/0402 6.663Et02 2.393El02 0.71*Et03 0.000E-01 5.250Et04 0.000E-01 GI-LLI 50 TE-129M 9.511Et04 2.064E407 6.009E107 2.242E+07 2.500L+03 0.000E-01 3.026Eto8 0.000E-01 GI-LLI 51 TE-129 8.203E -11 2.501E-10 3.367E-10 -1.245E- 10 1.415E-09 0.000E-01 2.541E-10 0.000E-01 K!bHEY 52 10-131M 1.470L405 2.795Et05 3.408Et05 1.764Et05 1.707Et06 0.000E-01 1.752Et07 0.000C-01 GI-LLI 53 TE-131 0.000E- 01 0.000E -01 0.000E-01 0.000E-01 1.913E-32 0.000E-01 0.000E-01 0.000E-01 KIDHEY 54 TE-132 1.452E?O4 1.709Et06 2.392Et06 1.547E+06 1.490Et07 0.000E-01 7.31 vet 07 0.000E-01 GI-LLI 55 I-130 4.930Et05 1.0/0Et03 4.273E405 1.262Et06 1.949Ef06 0.000E-01 1.00tEt06 0.000E-01 lilYh01D 56 I-131 2.428Ef08 1.309Ei11 2.9630908 4.237EtOB 7.064Et08 0.000E-01 1.118El03 0.000E-01 ill(RGID 57 I-132 1.405E-01 1 405Et01 1.501E-01 4.015E-01 6.397E-01 0.000E-01 7.543C-02 0.000E-01 THYROID 50 1-133 2.056Et06 9.910EtOS 3.877Et06 6.743Et06 1.377Ef07 0.000E-01 6.061Et06 0.000E-01 THYCOID 59 I-131 1.834L-12 8.805E-11 1.887E-12 5.120E-12 8.155E-12 0.000E-01 4.969E-15 0.000E-01 TilYRDID 40 1-135 1.222Et04 2.18*Lt06 1.265Et04 3.312Et04 5.311Ef04 0.000E-01 3.741Et04 0.000E-01 Tt!(ROID 61 CS-139 1.1000t10 0.,000E-01 5.652E109 1.345Ef10 4.353Efo9 1.445Efo9 2.351Et08 0.000E-01 LIVER 62 ES-136 7.4250000 0.oOOC-01 2.613Ef08 1.032Ef09 5.739Ef08 7.867Ef07 1.172Et08 0.000E-01 LIVER 63 CS-137 4.613Ll09 0.000E-01 7.331E409 1.009Et10 3.427Et0V 1.139Ef09 1.954EiO8 0.000E-01 LIVLR 44 CS-138 1.013E-23 0.000E-01 1.034E-23 2.045E-23 1.503E-23 1.484E-24 8.724E-29 0.000E-01 LIVER 45 CS-139 0.000L-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 46 BA-139 1.2?DE-09 0.000E-01 4.434E-08 3.159E-11 2.953E-11 1.792E-11 7.863E-08 0.000E-01 GI-LLI 67 PA-140 1.760Et04 0.000E-01 2.684Ef07 3.374E404 1.147Ef04 1.932Ef04 5.531Et07 0.000E-01 GI-LLI 68 BA-141 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 69 BA-142 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 70 LA-140 4.025E-01 0.000E-01 4.523Ef00 2.280Ef00 0.000E-01 0.000E-01 1.474Et05 0.000E-01 GI-LLI J
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i AGE ! ADULT PATHWAY 8 COW MILK-NO ISOT0FE W.' BODY- THYROID } BONE- KIDNEY LUNG .GI-LLI EKIN CRITICAL 1}IVER - 71 LA-142 1.030E-12 0.000E-01 9.161E-12;4.165E-12'O.000E-01 0.000E-C1 3.042E-08 0.000E-01 GI-LLI 72 CE-141 3.715E+02 0.000E-01 4.844Et03.3.276E403 1.521E403 0.000E-01 1.252E407 0.000E-01 GI-LLI -.
-73 CE-143 3.404Ef00 0.000E-01 4.162E+01 3.078E+04 1.355Ef01 0.000E-01 1.150E+06'O.000E-01 GI-LLI 'A' ~ , 74 CE-144 1.920EiO4 0.000E-0 3.577E605 1.495E+05 8.860Et04 0.000E-01 1'209E108 0.000E-01 GI-LLI $w-75 PR-143. 7.823EiOO 0.000E-01 1.578E402 6.331E+01 3.654E401 0.000E-01.d.914E405 0.000E-01 GI-LLI '
76 PR-144' O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 77 ND-147 6.50?ct00 0.000E-01 9.412E+01 1.088E+02 6.359E401 0.000E-01 5.2.'2E+05 G.000E-01 GI-LLI _ 78 W-105 4.539Et01 0.000E-01:1.298Et06.4 315E+05 0.000E-01 0.000E-01 4.987C107 0.000E-01 GI-LLI 79.W-187- ._.1.915E+03 0.000E-01 6.551E+03 5.476E+03 0.000E-01 0.000E-01 1.794Et06 0.000E-01 GI-LLI 80 U-235 ~1.878E+00 0.000E-01 3.099E+09 0.000E-01 7.226E+08 0.000E-01 3.010E108 0.000E-01 Bot 4E 01 U-238. .1.758E+00 0.000E-01 2.964E+09 0.000E-01 6.763Et08 0.000E-01 6.41%Et08 0.000E-01 B0 rte 82 MP-23V 1.979E-01 0.000E-01 3.452E+00 3.591E-01 1.120E+00 0.000E-01 7.3655101 0.000E GI-LLI
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. ~ . . . _ .
Pathwy Dose Parameters - Rg (8 - mrem /yr per'tfi/sec) AGE 1 TEEN FATHWAY I COW MILK ~
.W. DODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL NO ISOTOPE 71 LA-142- 1.0282-12 0.000E-01 1.653E-11 7.341E-12 0.000E-01 0.000E-01 2.235E-07 0.000E-01 GI-LLI-72 CE-141 6.811EiO2 0.000E-01 0.801E403 5.929E+03 2.791Lt03 0.000E-01 1 696El07 0.000E-01 GI-LLI
-73 CE-143 6.217Ct00 0.000E-01 7.649Et01 5.56LEt04 2.497Ef01 0.000E-01 1.673Ef06 0.000E-01 GI-LLI 79 CL-144 3.537C104 0.000E-01 6.582Et05 2.724E+05 1.627E+05 0.000E-01 1.655E400 0.000E-01 GI-LLI GI-LLI 1.443L401 0.000E-01 2.900E402 1.158E102 6.730Et01 0.000E-01 9.541EiO5 0.000E-01 W. BODY 7:. FR-143 76 ifi-141 -0.C00E-01 0.000E-01 0.Q00E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 GI-LLI 77 ND-147 1.100Ct01 0.000E-01 1.011E+02 1.969E+02 1.157Et02 0.000E-01 7.105El05 0.000E-01 70 4-105 5.057Lt04 0.000E-01 1.675Ef06 5.568E+05 0.000E-01 0.000E-01 6.431Ef0/ 0.000E-01 GI-LLI 79 U -107 3.4220t03 0.000E-01 1.198E+04 9.747E+03 0.000E-01 0.000E-01.2.643Et06 0.000E-01 GI-LLI U0 U-235 2.423Et03 0.000E-01 3.999El09 0.000E-01 9.324E+00 0.000E-01 3.091Et03 0.000E BOffE 01 U-220 2.26 vet 00 0.000E-01 3.024Efo9 0.000E-01-0.726t+0B 0.000E-01 8.277El00 0.000E-01 ' BONE C.! HP -239 3.6510-01 0.000E-01 6.949Et00 6.573E-01 2.063E+00 0.000E-01 1.007EICG 0.000E-01 GI-LLI 9
P gs 31 of:39q,.
, , . . . --w-l ATTACHMENT 7 Pathway Dose Parameters 2-Rg (m - mram/yr per tri/sec) i AGE J CHILD -
1 PATilWAY 1 COW NILK 2 W. BODY THYROID ' BONE : LIVER KIDHEY LUNG GI-LLI SKIN CRITICAL' NO ISOTOPE 1 H-3 g 1 570Et03 1.570Et03 0.000E-01 1.570E+03 1.570Et03'1.570Et03 1.570E+03 1.570Et03 W. BODY- ! 2 C-14 3 294E405 3.294Ef05 1.647Et06 3.294Et05 3.294Et05 3.294E405 3.294Et05 3.294E+05 BONE - l 3 NA-24 8.930Et06 8 932E+06 8.932E+06 8.932Et06 8.932E106 8.932E+06 8.932E406 0.000E W. BODY d 4 P-32 2.999Et09 0.000E-01 7.781E+10 3.641E+09 0.000E-01 0.000E-01 2 150E409 0.000E-01. BONE 4 5 SC-46 1.078Et02 0.000E-01 1.910Et02 3.744Et02 3.466Et02 0.000E-01'1 006E+06 0.000E-01 GI-LLI 9 6 CR-51 1 019EtC5 5.654E404 0.000E-01 0.000E-01 1 545E104 1.032E+05 5.402E404 0.000E-01 GI-LLI 7 MH-54 5.505Et06 0.000E-01 0.000E-01 2.097E+07 5.879Ct06 0.000E-01 1.76CE407 0.000E-01 LIVER 8 MH-56 2 832E-03 0.000E-01 0.000E-01 1 277E-02 1 544E-02 0.000E-01 1.850El00 0.000E-01 GI-LLI
9 FE-55 1 037Et07 0.000E-01 1.118E+08 5.930Ef07 0.000E-01 3.351E+07 1.098E607 0.000E-01 B0HC l 10 FE-59 9.686Et07 0.000E-01 1.202Et08 1.944Ef08 0.000E-01 5.637Et07 2.025El08 0.000E-01 GI-LLI 1
la f;0-58 3.719Et07 0.000E-01 0.000E-01-1.215E+07 0.000E-01 0.000E-01 7.000E+07 0.000E-01 GI-LLI 12 CO-60 1.273Et08 0.000E-01 0.000E-01 4.310Et07 0.000E-01 0.000E-01 2.391Et08 0.000E-01 JGI-LLI 13 HI-59 'O.985El07 0.000E-01 5.386E+08 1.847E408 0.000E-01 0.000E-01 3.003E407 0.000E-01 BONE
14 NI-63 1 000E109 0.000E-01 2.964Et10 1.507Et09 0.000E-01 0 000E-01 1 069Et08 0.000F-01 BONE 15 NI-65 9.107E-02 0.000E-01 1.657E400 1.560E-01 0.000E-01 0.000E-01 1.911E101 0.000E-01 GI-LL4 e 16 CU-64 4.465Et04 0.000E-01 0.000E-01-7 392Et04 1.786Et05 0.000E-01 3.470Et06 0.000E-01 GI-LLI 17 ZH-65 6.047Et09 0.000E-01 4.132EiO9 1.101Et10 6.937Et09 0.000E-01 1.933Et09 0.000E-01 LIVER 2.950E-12 0.000E-01 2.214E-11 3.200E-11 1.941E-11 0.000E-01 2.017E-09 0.000E-01 GI-Lt.1 18 ZH-69 1
19 BR-83 .4.617E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000L-01 0.000E-01 0.000E-01 W. BODY 20 DR-04 5.739E-23 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY 21 FR-85 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY $ 22 RB-S6 5.337Et09 0.000E-01 0.000F-01 8.760E609 0.000E-01 0.000E-01 5.635Et08 0.000E-01 1.IVER ^ 23 RB-88 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY I 24 RD-89 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01.0.000E-01 0.000E-01 0.000E-01 W. DODY I 25 SR-89 1.890E t08 0.000E-01 6.616Ef 09 0.000E-01 0.000E-01 0.000E-01 2.561Ef 08 0.000E-01 PONE 24 SR-90 2.833Et10 0.000E-01-1.117Et11 0.000E-01 0.000E-01 0.000E-01 1.505E609 0.000E-01 DONE 27 SR-91 4.885Et03 0.000E-01 1.294El05 0.000E-01 0.000E-01 0.000E-01 2.853El05 0.000E-01 GI-LLI 1 20 ER-92 8.64aE-02 0.000E-01 2.162Et00 0.000E-01 0.000E-01 0.000E-01 4.094Et01 0.000C-01 GI-LLI i 29 Y-90 8.637Et00'O.000E-01 3.227Et03 0.000E-01 0.000E-01 0.000E-01 9.107Et05 0.000E-01 GI-LLI i 30 Y-91H 1.015E-20 0.000E-01 2.871E-19 0.000E-01 0.000E-01 0.000E-01 5.420E-16 0.000E 01 GI-LLI 31 Y-91 1.044EiO3 0.000E-01 3.904E104 0.000E-01 0.000E-01 0.000E-01 5.200Ef06 0.000C-01 GI-LLI 32 Y-92 /.226E-06 0.000E-01 2.525E-04 0.000E-01'O.000E-01 0.000E-31 7.296E100 0.000C-01 GI-LLI j '33 Y-93 2.881E-02 0.000E-01.1.049Et00 0.000E-01 D.000E-01 0.000E-01 1.565Et04 0.000E-01 GI-LLI
! 34 ZR-95 7.533Et02 0.000E-01 3.852Et03 8.468Ef 02 1.212Et 03 0.000E-01 8.833Et05 0.000E-01 GI-LLI
35 ZR-97 1.633E-01 0.000E-01 1.915Ef00 2.767E-01 3.972E-01 0.000E-01 4.191E+04 0.000E-01 GI-LLI i
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DC MN MM N M' L E . 4673990120 I1 P M135605457799112 H CY O T 579900001 999911 11111111 12222223330123453333334444 1111 133333311 11111111 A O - - - - - - - - - - - - - - - - - - - 11 1 111 - SSSSSAAAAA 1W S BBDCCUUUGDBEEEEEEEE- - - - - ET H I NHMTTRRRACE1TTTTlTTIII1IICCCCCBBBBL GA O 678?01 - 2315670901231 5673901 234567890 AP N 33234444444444555555555546666666667
g - -- r - Pc; gal 33 cf '39. ;. ATTACHMENT 7
-~. - __ . _ . .
Pathway Dose Parameters 2 Rg (m - mren/yr per afi/sec) AGE 1 CHILD PATHWAY 1 COW MILK NO ISOTorE W. BODY TilYROID - BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 3.984C-12 0.000E-01 3.992E-11 1 272E-11 0.000E-01 0.000E-01 2.522E-06 0.000E-01 GI-LLI 72 CE-141 1.620Et03 0.000E-01 2.187Et04 1.091Ef04 4.701Et03 0.000E-01 1.361Et07 0.000E-01 GI- LLI 73 CE-143 1.474E+01 0.000E-01 1.877Ct02 1.010Et05 4.270Et01 0.000E-01 1.490Et06 0.000E-01 GI-LLI-74 CE-144 8.660E+04 0.000E-01 1.623Et06 5.087Et05 2.814E+05 0.000E-01 1.326E100 0.000E-01 GI-LLI 75 F R-143 3.561E+01 0.000E-01 7.177Et02 2.155Et02 1.167E+02 0.000E-01 7.744Et05 0.000E-01 GI-LLI 76 FR-144 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 77 ND-147 2.700E401 0.000E-01 4.444Ef02 3.600Et02 1.975Et02 0.000E-01 5.703E+05 0.000E-01 GI-LLI 78 W-155 4.832E+04 0.000E-01 1.382Et04 4.594Et05 0.000E-01 0.000E-01 5.300E+07 0.000E-01 GI-LLI 79 W-187 7.719Et03 0.000E-01 2.905Et04 1.720E+04 0.000E-01 0.000E-01 2.417E606 0.000E-01 GI-LLI 80 u-235 1.999Et08 0.000E-01 3.299Efo9 0.OOOE-01 7.693Et09 0.000L-01 3.213C608 0.000E-01 bOME 81 U-238 1.872Ef08 0.000E-01 3.155Et09 0.000E-01 7.199Et08 0.000E-01 6.829Ct09 0.000E-01 BONE 82 NP-239 C.657C-01 0.000L-01 1.71 set 01 1.2J2Et00 3.561Et00 0.000L-01 9.115E604 0.000E-01 GI-LLI 9 J
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ATTACHMENT 7-
~ Pathway Dose Parameters 'Rg k .- mram/yr per_LEl/sec) -
AGE : INFANT PATHWAY I COW MILK NO ISOTDPE W. BODY THYROID DONE RLIVER KIDNEY LUNG: GI-LLI SKIN CRITICAL'
'36 NB-95 1.412E t05 0.000E-01 5 932E+05 2.444Et05.1.751E+05 0.000E-01 2.062E 608 0.000E-01 GI-LLI 37 NB-97 ' 5.768E-13 P 900E-01 6.259E-12 1.580E-12 1.843E-12 0.000E-01 5.828E-09 0.000E-01 GI-LLI -
38 MD-99 4.049Ef07 0.000E-01'O.000E-01 2.077E+08 3.103E+08 0.000E-01 6.841E+07 0.000E-01 KIDNEY 30 TC-99N 7.424Et02 0.000E-01 2 795E+01 5.765E+01 6.202EiO2 3.013Ef01 1.471Et04 0.000E-01 GI-LLI 43 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01'O.000E-01 0.000E-01 0.000E-01 0.000E-01' W. BODY 41 RU-103 2.90BEf03 0.000E-01 8.694E403 0.000E-01 1.809Ef04 0.000E-01 1.057Et05 0.000E-01 GI-LLI 42 RU-105 2.747E-03 0.000E-01 8 156E-03 0.000E-01 5.997E-02 0.000E-01 3.215Et00 0.000E-01 GI-LLI
, 43 RU-106 2.377Et04-0.000E-01 1.903E+05 0.000E-01 2.251Et05.0.000E-01-1.415Et06 0.000E-01 OI-LLI 44 AG-110M 1.864Et08 . 000E-01 3.860Et08 2.817E108 4.030Et08 0.000E-01 1.143E+10 0.000E-01 GI-LLI 45 CD-115M 4.237E+04 0.000E-01 0.000E-01 1.326Et06 1.052Et06 0.000E-01 5.570C107 0.000E GI-LLI 46 SB-124- 1.006Et07 6.646Et04 2.751E+07 5.18 set 05 0.000E-01 2.134E407 7.782E+08 0.000E-01 GI-tLI 47 TE-125H 2.039Et07 5.0/6El07 1.508El0D 5.043Et07 0.000E-01 0.000E-01 7.186Et07 0.000E-01 B0HE 40 TE-127H 5.097EF07 1.217E608,4.211E608 1.397EtCD 1.037E+09 0.000E-01 1.699EtOS 0.000E-01 hIDHEY 19 TE-127 1.336El03 5.249C603 6 449Et03 2.160Et03 1 573Et04 0.000E-01 1.354Ef05 0.000E-01 GI-LL I .
50 TE-129H 8.567Et07 2.136Et08 5.563Et08 1.908Et08 1.391Ef09 0.000E-01 3.321E100 0.000E-C1 KIDHEY 51 TE-129 7.569E-10 2.717E-09 3.242E-09 1.110E-09 8.071E-09 0.000E-01 2.591E-07 0.000E-01 GI-LLI 52 TE-131M 1.121Ef06 2.753Et06 3.375Et06 1.359Et06 9.347Et06 0.000E-01 2.237EtO7 0.000E-01 GI-LLI 53 TE-131 1.166E-32 3.705E-32 4 153E-32 1.534E-32 1.062E-31~0.000E-01 1.678E-30 0.000E-01 GI-LLI Si TE-132 9.711Et06 1.534L407 2.102E+07 1.041Et07 6.508Et07 0.000E-01 3.850Ef07 0.000E-01 KIDHEY 55 I-130 3.193Ct06 8.915E608 3.614Et06 7.952E606 8.735Ef06 0.000E-01 1.705Et06 0.000E-01 lilYROID 56 I-131 1.410Et09 1.054E+12 2.722Efo9 3.207Et09 3.745Ef09 0.000E-01 1.145EiO8 0.000E-01 THYROID 57 I-132 9.416E-01 1.244E102 1.307E+00 2.653Ef00 2.940Ef00 0.000E-01 2.149El00 0.000E-01 THYliOID SS IL133 1.549Et07 9.619E609 3.633Et07 5.289E107 6 219Et07 0.000E-01 8.?LIC106 0.000E-01 THYROID 59 I-131 -1.200E-11 7.966E-10 1.647E-11 3.374E-11 3.772E-11 0.000E-01 3.400E-11 0.000L-01 TilVLOID 60 I-135- 8.02EEt04 1.973E607 1 106Et05 2.201Et05 2.453Ef05 0.000E-01 7.941Ef04 0.000E-01 THYROID 61 CG-134 6.Ca8Lio9 0.000E-01 3.647Et10 6.G01Et10 1.751Ef10 7.170EiO9 1.84 set 08 0.000E-01 LIVER 62 CS-136 2.153E109 0.000E-01 1.961El09 5.768Et09 2.29?El09 4.700Et08 8.759El07 0.000E-01 LIVER 63 CC-137 4.26?El09 0.000E-01 5.146El10 6.024Et10 1.617E110 6.546Efo9 1.083EIO8 0.000E-01 LIVER., 7 64 CS-138 7.569E-23 0.000E-01 9.607E-23 1.562E-22 7.789E-23 1.216E-23 2.197E-22 0.000E-01 GI-LLI 65 CS-139 0.000E-01 0.000L-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 66 FA-139 1.241E-08 0.000E-01 4 207E-07 2.812E-10 1.708E-10 1.723E-10 2.715E-05 0.000E-01 GI-LLI 67 BA-140 1.241E107 0.000E-01 2.400Ef08 2.408E+05 5.718Ef04 1.479EiO5 5.916E107 0.000E-01 BONE 68 BA-141 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.0000-01 0.000E-01 0.000E-01 0.000E-01 W. BODY
> 69 BA-142 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 70 LA-140 4.122Et00 0.OOOE-01 4 044Et01 1.602EiO1 0.000E-01 0.000E-01 1.882Et05 0.000E-01 GI-LLI
M
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~ P; gi 36 ;f 39 . . . ,
s. w b ATTACHMENT 7 Pattuey Dose Parametere 2 Rg (m - mrem /yr per tri/sec) AGE ! INFANT PATHWAY 1 COW MILK NO' ISOTOPE W. BODY TitVRDID BONE ' _ -LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 72 EE-141 7.367E-12 0.000E-01 8.380E-11 3.070E-11 0.000E-01 0.000E-01 5.226E-06 0.000E-01 GI-LLI 73 CE-143 3.112Et03 0.000E-01 4.335E+04 2.644E104 8.153Et03 0.000E-01 1.364Et07 0.000E-01 GI-LLI 74 EE-144 3.008E101 0.000E-01 3.974Et02 2.63/EiO5 7.680Ef 01 0.000E-01 1.539El06 0.000E-01 GI-LLI 75 FR-143 1.303E t 05 0.000E-01 2.325Ef 06 9.51CE4 05 3.046E105 0.000E-01 1.33tEtOS 0.000E-01 GI-LLI 76 OR-144 7.360Lt01 0.000E-01 1.485Ef03 5.552Et02 2.064Et02 0.000E-01 7.035Et05 0.000E-01 -GI-LLI 77 ND-117 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E -01 0.000L -01 0.000E-01 W. 1<0DY 70 W-185 5.543Et01 0.000E-01 8.809Ef02 9.010E102 3.480E102 0.00CE-01 5.731EtOS 0.000E-01 GI-LLI 79 W-187 4.832Et04 0.000E-01 1.302Et06 4.594Ef05 0.000E-01 0.000E-01 5.303Ct0/ 0.000E-01 -GI-LLI 80 U-235 1.469Et04 0.000E-01 6.114Et04 4.252Et04 0.000E-01 0.000E-01 2.49dEiO4 0.000E-01 'GI-LLI 4 31 U-239 1.999Et08 0.000E-01 3.299Et07 0.000E-01 7.693Et00 0.000E-01 3.213L t00 0.000E 01 B0llE 22 NP-239 1.872E t 00 0.000E- 01 3.155E t09 0.000E-01 7.199Et00 0.000E-01 6.820EiOc 0.000E-01 l'OdC 1.833Et00 0.000E-01 3.626Et01 3.244E100 6.468Ef 00 0.000E-01 9.37;Et04 0.000E -01 GI-LLI J e 1 4 t .h J
) . ' 9 3 f o 7 3 a Y Y Y g YY Y Y YY D D L D DD D a A DD D 0 O P C I OO O BBNbNNNN1tNNDBNNNBt 0 ! OO 1II O ! N0HNNNBNNNNNNNl II II1I I IIl IIIII l N T I
.K .IIII III KKNN . NAN . . hhN .NA .NAhN .hKKht;hNKA I
R C WWSWSSSEWSSSWWSSSWSSWCSSEWSSSSSSSSC 1171869618801 1558135174541653565506 0000000000010000000O0O0000000000000
- tt1 t - + 1 + - 44 4 - 1i - t t t t - 1 ttt t 44 t t EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEELEEE 0090172702020018202601 6070754396153 N
I K 00800126009300552005025500021601314 00306560024500485013007450563129594 G 00109511034200368072013120285111223 5655S6 1171869518801155O13516tS41653 0000000000O10000O00000OO000000000O0 t t - t ttt - t t t4 1 +1 tt t - tt t t - t i t - - tt i I L EEEEECEEEFCEEfEEECCEEEEEEEEEEEEECEE 0053200010 t720379005271 44930 L I
- 00902633023500751 0000161 9C206e060469070415 0 010 3 6 3 0 0 7 010 0 9 0 4 0. D. 0 0 9. *. 21017 4 0 0 8 8 5 9 G
00100419023200267042053120274111122 155S135164541653565506 171O6951S301 0000O0000001C000O0000000000000O0000 1
- - f - it 4 t l 6 t - - tt t - t f f tt f - tt t6 it4 4t EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 00801S1 005320001 0072037900527444938 G
N U 00902683023500751082068060469070415 001036300781 00904080092210174008859 L 00108419023200267042083120274111122 _ ss e
)
c 1171D695180011558135164S414S3565586 0000O00000C100000000000O00OOO000000 t t t t - i i it6 6 t6 t Y - - t - i t1 t - 6 i t - - t tl - 1 t - r/ ei E EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 000018400S320001 00720379005274 14938 00902633023500751082068060169070415 7 te(C N T r r a r D I 00103430070100904080092210174008059 11122 wN E r a p e K 001084190232002670420831202741 64541653S65536 M P ey r 117106951B80115581351 000000000001000000O0000000000O00000 4 ttt 4 4 tt t 1 H - - t - ttt+ - tt+ - - t4 t - i t - t ttt C A s/ em R EEEEEEEEEEEEEEEEEEEEEEEEEtEEEEEEEEE 0080184005320001007203??00S274 44938 T T
. Dymer E V
I 00902403023500751032018060169070415 00103630078100904080092210174008859 A - haw - L 00100419023200267042083120274111122 t2 am 117186951880115581 00000000000100000000000000000000000 35164541653565586 P( g -EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE
- t - t t+ t - t9 t - - ft t - t t - 4 14t - t ttt ttft+
R E 0080184005320001007203790052744i938 00902603023500751002068060469070415 N O 00103630078100904080092210174008059 B 00108419023200267042003120271111122 65356S5S6 D 117186951S0011553135141541 000000000O010000C00000000000O00O0OO - t 4 tf - t 1 i+ tt1 tI
- - t - t6 t 4 - I f t - - 1 f t - t t I
O R EEEEEEEEEFEEEEEEEEEEEEEEEEEEEEEEEEE 007203790052744 1933 Y 00001810053200C1009026330235007510S2068060149070415 0171000059 H 001036300.*010090408009221 . . T 00108419023200247040083120274111122 5655S6 E N Y 1171D69513801155S1351615416530000O000000CO00000000O0 0000C0C00001 - ! 4 t ! t t t t t l 1 t t D - - t - t 4t6 - ttt - - l 4 I - t 1 A L O B EEEEEEEEEEEEEELEEEEfEE0CEEEEEEEEEEE 00801840053200010072037?00527111930 69070415 F D . 009026330235007510020630601 001036300781009040000922101 74000859 N U O W 00108419023200267042033120274111122 R G E M 57 L1 L F O 614659809354593456C99012 99?9912399 42245555556566664G08CC0899901 4
- - - - - - - - - - - - - - - - - N-AY T -
1W A C S 31
- - A CRNiECO0I1CUift RRRP1DkicRR- - - - - RR f
HCNPSEMhFI CENNt EZ?LBBRhRSCESYYYYYZZ t H I 23* 5673901231 5 ET GA AF - O N 12345678901231567090112222222222333333 1 11 111 111 f
Pag 3.38 Mf 39' . ATTACHMENT 7 Pathway Dose Parameters 2 Rg (m - srrem/yr per tC1/sec) ACE 1 ALL F'ATHW.Y 1 GROUND PLANE HQ ISOTDPE W. 90DY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36 NS-95 1.346Et08 1.366Et08 1.366E+C8 1.364Et08 1.366Et08 1.366E+08 1.364Et08 1.607EiOS SKIN 37 NB-97 1.797Et05 1.797Et05 1.797Ef05 1.797E+05 1.797Et05 1.797Ef05 1.797C+05 2.109E+05- SHIN 33 M3-99 3.990Et06 3.990E+06 3.990E104 3.990E+04 3.990E+06 3.990Ef 06 3.990Et06 4.620Et06 SKIN 39 TC-99M 1.015E+05 1.ui5Et05 1.845E4 05 1.845E+05 1.845E+05 1.845E+05 1.845Et05 2.115Ef 05 SKIN
. 40 TC-101 2.034Et04 2.034Et04 2.034E+04 2.034Ef04 2.034E404 2.034Et04 2.034E604 2.260E+04 SAIN 41 RU-103 1.093E+08 1.093Ef 09 1.093E+08 1.093EiOB 1.093EtOB 1.093E408 1.093CiOB 1.275EiOS SKIN 42 RU-105 6.373E+05 6.373E605 6.373Et05 6.373Et05 6.373Ef05 4.373Ct05 6.373Et05 7.223E405 SAIN 43 RU-106 4.239Et0D 4.239C400 4.239Et0B 4.239Et08 4.239Et0D 4.239EiOB 4.23VE108 5.004Et0B SAIN 44 AG-110M 3.4600409 3.460E409 3.460EiO9 3.460Et09 3.460Et09 3.460Et09 3.4600409 4.037E609 SAIN 15 ED-115M 0.000E-01 0.000E-01 0.000E-01 0.000E-01.0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. LiODY 46 SS-124 5.994Et00 5.994EtOS 5.994E408.5.994Et08 5.994Et08 5.994C100 5.9910608 4.916E+08 CCIH 47 TE-125M 1.555Ct06 1.555Et06 1.555Et06 1.555Et06 1.555Et06 1.555E406 1.555Lt06 2.133Ct06 SKIN 43 TE-127M V.165Et04 9.165C404 9.165Et04 9.165Et04 9.165EiO4 9.165Ef04 9.1450004 1.003Ct05 SKIft 49 TE-127 2.?91Lt03 2.?viEt03 2.9910403 2.991Et03 2.?91Et03 2.991E403 2.991Ef03 3.290Ef03 SKIN 50 TE-129H 1.9670607 1.947C407 1.967Et07 1.967E+07 1.967Et07 1.967E607 1.947C407 2.300Ef07 SAIN 51 10-129 2.639Et01 2.639E+04 2.439Et01 2.639Et04 2.639Et04 2.43?Et01 2.639Et04 3.122E104 SNIN 52 1E-131M 8.023Et06 8.023Et06 8.023Et06 8.023Et06 0.023Et06 8.023Et06 0.023Et06 9.456E106 SAIN 53 TE-131 2.926Et04 2.926Et04 2.926Et04 2.926Ef04 2.926Et04 2 926Et04 2.926Et04 3.iSOC107 SKIN Si TE-132 4.220C106 4.220Et06 4.220Ef06 4.220Et04 4.220Ef06 4.220Et06 4.220Et06 4.945Et06 CA1H 55 I-130 5.529E606 5.539Et04 5.539E106 5.539Et06 5.53vE406 5.53?Cf06 5.539C604 6.726E406 EAIN 56 I-131 1.722Ef07 1.722Et07 1.722E+07 1 722C+07 1.722E607 1.722E+07 1.722Et07 2.091E+07 CNIll 57 I-132 1.23 set 04 1.230Et06 1.230Et06 1.238E606 1.23 set 04 1.23CEf06 1.23DEt06 1.457E406 SAIN 50 I 133 2.453Et04 2.153Et06 2.453E406 2.453E+06 2.453C406 2.453E406 2.453E606 2.983Ef06 SAIN 57 I-134 4.160E405 4.140C605 4.460E605 4.460Et05 4.4602105 4.460Cf05 4.460Et05 5.294Ef05 EKIN 60 I-135 2.520E606 2.520Et06 2.520Et06 2.520E+06 2.520Et06 2.520EiO6 2.520Et06 2.940Ef06 SKIN 61 ES-134 6.031Et09 6.834EiO9 6.831Et09 6.831E+09 6.C34Et09 6.831E+09 6.031Et09 7.972Et09 5NItf c2 CC-136 1.491Et00 1.491Et00 1.191E600 1.4Y1Et00 1.491E608 1.491Et03 1.491Et00 1.690E108 SKIN 63 ES-137' 1.030Ef10 1.030Et10 1.030C+10 1.030Et:0 1.030Ef10 1.030E110 1.030Et10 1.202Ef10 SKIN 61 CS-13S 3.597Ef 05 3.597E+05 3.597E+05 3.597E105 3.L97EtOS 3.597Et05 3.597E t05 4.111E+05 SAIN 65 CS-139 3.115Ef04 3.115EiO4 3.115Et04 3.115E+04 3.115Et01 3.115Et04 3.115E+04 3.561Ef04 SKIN 66 FA-139 1.059Et05 1.059E405 1.059E+05 1.05?C+05 1.059C105 1.05?E105 1.059EiO5 1.191E+05 SKIN 67 BA-140 2.0L1E+07 2 051Et07 2.051El07 2.051E+07 2.051Et07 2.051Et07 2.051Et07 2.343E+07 SKIN 63 hi-141 4.179E604 4.1/9Ef04 4.179E904 4.179Et04 4.179E404 4.179E+04 4.179E+04 4.762C+04 SKIN 69 I'A-142 4.436Et04 4.486E404 4.486E404 4.486E604 4.484Ef04 4.484E+04 4.484Et04 5.110E604 SAIN 70 LA-140 1.924Et07 1.924Et07 1.924Et07 1.924EF07 1.924E+07 1.924Et07 1.924Et07 2.181E+07 SKIN h .- - . . _ _ _ . _ . _ ~ _ _ .
B 7 Pigi39lcfI39i;,:,,
. .? -
Ah[NCHMENT7 < Pathway Dese Parameters R gN-uM#CM
~
AGE I ALL' '
PATHWAY I GROUND PLANE-
-NO ISOTOPE W. BODY THYROID- DONE LIVER KICNEY LUNG GI-LLI' SKIN CRITICAL 71 LA-142 7.359Et05 7.359Et05 7.359E40ii 7.359Et05 7.359E605 7.359Et05 7.359Et05 8.830Et05 . SKIN-72 CE-141 SKIN:
73 CE-143 1.365Et07 2.314Et06 2.314Etu6 1.365E4072.314Et06 1.345Et07 1.365Et07 2.314Et06 1.365Et07 2.314Et06 1.36*Et07 2.314Et04 1.365Et07 2.314E406 1.539Et07 ~ SKIN 2.630Et06 74 CE-144 6.934E607 6.934El07 4.934Et07 4.934E407 4.934Et07 6.934E107 6.934Eio7 8.017Et07 SKIN. 75 FR-143 0.000E-01 0.C00E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01.-W. It0DY 76 PR-144 1.833E4 03 1.833Et03 1.833Et03 1.833Et03 1.833Et03 1.833E 6 03 1.833E l03 2.100Et 03 - SKIN 77 ND-147 8.389Et06 8.309Et06 8.~u?Et06 8.389Et06 8.389Et06 8.389E 606 0.339Et06 1.007E407 SKIN
-78 u-185 0.000E-01 0.000E-01 0 000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 79 W-187 2.358Et06 2.358Et06 2.358Et06 2.35 bet 06 2.358Et06 2.358Ct06 2.359Et06 2.737Et06 SKIN 80 U-235 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 81 U-233 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01..W. PODY.
82 NP-239 1.703E406 1.703Et06 1.703Et06 1.703Et06 1.703Ft06 1.703Et06 1.703Et06 1.972Et06 SKIN 9 b
ATTACHMENT (8) . GASEOUS EFFLUENTS - EFFECTIVE DOSE FACTORS FOR NOBLE GASES Total Body Effective Skin Effective Gamma Air Effective Beta Air Effective Dose Factor Dose Factor Dose Factor Dose Factor K egg (L+1.1 M) M egg Negg Year (mrem /yr per uCi/m3) (mrem /yr per u,b7i/m3 ) (mrad /yr per uCi/m3) (mrad /yr per uCi/m3) 1981 3.6E+02 7.9E+02 4.2 E+02 1.l E+03 1982 3.lE+02 7.4E+02 3.7 E+02 1.lE+03 1983 3.lE+02 7.4E+02 3.7 E+02 1.lE+03 Average 3.3E+02 7.6E+02 3.9E+02 1.lE+03 s
e - ATTACHMENT (9) Page 1 of 2 LOCATIONS OF THE ENVIRONMENTAL SAMPLING SITES FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT SITE SAMPLE SECTOR DISTANCE
DESCRIPTION KM MI 1 DR1 NW 0.6 0.4 Onsite, along cliffs 2 DR2 WNW 2.7 1.7 Route 4, across from auto dump 3 DR3 W 2.3 1.4 Route 4, Giovanni's Tavern 4 DR4 WSW 2.1 1.3 Route 4, across from White Sands 5 DR5 SW 2.1 1.3 Route 4, at Johns Creek 6 DR6,A4 SSW 2.9 1.8 Route 4, at Lusby 7 DR7, A1, Ib4, S 0.8 0.5 Onsite, near guard house, off Ib5, Ib6 Camp Conoy Road 8 DR8,A2 SSE 2.4 1.5 Camp Conoy Road, at the emergency stren 9 DR9,A3 SE 2.5 1.6 Bay Breeze Road 10 DR10 NW 7.8 4.8 Route 765, St. Leonard 11 DR11 WNW 6.5 4.0 Dirt Road, off Mackall & Parran Roads 12 DR12 W 6.7 4.2 Bowen & Mackall Roads 13 DR13 WSW 6.1 3.8 Mackall Road, near Wallville 14 DR14 SW 6.5 4.0 Rodney Point 15 DR15 SSW 6.4 3.9 Mill Bridge & Turner Roads 16 DR16 S 6.7 4.2 Appeal School 17 DR17 SSE 6.1 3.8 Cove Point & Little Cove Point Roads -
18 DRl8 SE 7.2 4.5 Cove Point m
ATTACHMENT (9) Page 2 of 2 LOCATIONS OF THE ENVIRONMENTAL SAMPLING SITES FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT SITE SAMPLE SECTOR DISTANCE
DESCRIPTION KM MI 19 DR19 NW 4.5 2.8 Long Beach 20 DR20 NNW 0.6 0.4 Onsite, near shore 21 DR21, AS, Ib7, WNW 19.3 12.0 At the Emergency Offsite Ib8, Ib9 Facility, off Route 231 22 DR22 S 12.9 8.0 Solomons Island 23 DR23 ENE 12.7 7.9 Taylors Island 24 Wa l, Ial, NNE&NE 0.2 0.1 Intake area la2 25 Wa2 N 0.3 0.2 Discharge area 26 Wbl ESE 0.6 0.4 Shoreline at Camp Conoy 27 lbl, Ib2, Ib3 SSE 2.6 1.6 Garden plot off Bay Breeze Road 28 la4, la5 WNW N/A N/A Patuxent River 29 la3 E 0.9 0.6 Camp Coney 30 la6 NNW 10.7 6.6 Kenwood Beach

from the Central Point between the two containment buildings.
. . . . m . . - , - ,- ,. . .
= ATTACHMENT (10) L
M AP OF ENVIRONMENTAL SAMPLING SITES w
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ATTACHMENT (5) PROCESS CONTROL PROGRAM (PCP) CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE GAS AND ELECTRIC COMPANY
a PROCESS CONTROL PROGRAM 1.0 - WET WASTE 1.1 Dewatering Solids In High Integrity Containers (HIC) The exhausted ion exchange resin is transferred to a spent resin metering tank. The resin is transferred from the spent resin metering tank to a high integrity container and dewatered. After the dewatering process is complete, as per Radiation Safety Procedures, the HIC is transferred into a CASK and shipped to a burial site. 1.2 Solids such as bead resin, filter cartridges and powdered resin may be dewatered and shipped in HIC's per approved vendor procedures and the HIC certificate of compilance. 1.3 High integrity containers are approved by the individual burial sites as meeting 10 CFR 61 waste form stability requirements. 1.4 Free water determination as defined in 10CFR61 part 61.56 shall be verified by the successful completion and documentation of the vendors approved dewatering procedure. 2.0 SOLIDic TION Solidification of the wet waste shall be conducted by a mobile solidification system. The process equipment procedures, solidification agent, QC and PCP program shall meet all of the local, county, federal and state burial criteria. 2.1 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g, filter sludges, spent ruins, evaporator bottoms, and boric acid solutions). 2.1.1 If any test specimen falls to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until
such a time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM and a subsequent test verifies SOLIDIFICATION. The SOLIDIFICATION of the batch may then be resumed using alternate SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM. 2.1.2 If the initial test specimen from a batch of waste falls to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM (PCP) shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PCP shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.
- NOTE -
At present, radioactive waste is not solidified at Calvert Cliffs.
- 3.0 10 CFR 61 REQUIREMENTS 3.1 The waste classification and manifest reporting program was developed by the Calvert Cliffs Nuclear Power Plant to comply with the requirements of 10 CFR 20.311,10 CFR 6161.55 and 61.56. The 10 CFR 61 classification requirements will be met using scaling factor methodology as per provisions stated in 10 CFR 61.55.
3.2 The scaling factors will be updated by an ongoing analysis program of actual waste streams. The program willinitiate with annual samples of available
( ] g waste streams and may be modified to longer intervals if the data base
. warrants. ' 4.0 . VENDOR SERVICES FOR WASTE PROCESSING Contractor supplied services and/or systems may be used at Calvert Cliffs for the processing of radioactive waste. For the operation of such process . systems, it may be desirable to use process control measures and procedures ' developed by the contractor specifically for the system. Therefore, previously addressed process control measures for a particular waste stream . may be superseded by contractor supplied measures as appropriate. The following discussion addresses the administrative controls that are imposed to assure that contractor supplied services and/or systems for processing radioactive waste for disposal at a burial site are compatible with plant operations, procedures and regulatory requirements.
Prior to the use of any contractor for the processing of waste at Calvert Cliffs, management review of the contractor's process controls and operating procedures is performed for the purpose of assuring a safe operation in accordance with plant procedures'and applicable regulatory requirements. For the processing of waste that is intended to be shipped for disposal to a l licensed radioactive waste burial site, additional precautions are taken to assure a final waste product that meets the appropriate waste characteristic ( requirements for solidification or dewatering. In particular, the following i-j ltems are to be documented by the contractor (or Calvert Cliffs manuals or procedures) prior to utilization for solid waste processing at Calvert Cliffs. U ~ a general description of the solidification process, including type of 4 solidification agent, major process equipments and Interface with plant l
F l . 9 equipment, type of wastes that can be processed, and operating parameters; a Process Control Program (PCP) that provides for the verification of the generation of a suitable waste product, including items such as representative sampling, laboratory tests to establish waste-to-process medium ratios, and criteria for evaluating acceptability of lab test; specifically approved procedures for the operation of the process equipment that will assure operation within the bounds as determined by the Process Control Program (PCP); and, appropriate QC check point and acceptance criteria for evaluating the acceptability of the final waste product. l
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ML20106C123

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