Text

Rev 27 to Odcm
	ML20080F702
Person / Time
Site:	San Onofre
Issue date:	12/21/1994
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20080F694	List: ML20080F692; ML20080F696; ML20080F702;
References
	PROC-941221, NUDOCS 9501300162
	Download: ML20080F702 (189)
	v • d • e

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I RECB S c a; December 21, 1994 DEC21 g 0

SITE File COPY

SUBJECT:

Units 2/3 0FFSITE DOSE CALCULATION MANUAL Revision 27 Enclosed is Revision 27 to the Units 2/3 Offsite Dose Calculation Manual (0DCM).

Incorporated into this revision are 1) the inclusion of the new South Yard Facility (SYF), 2) changes made due to the 1993 Land Use Census, 3) the pump flow rates for the FFCPD HUT and Unit 3 TPS were changed to 1000 gpm and 100 gpm, respectively, 4) the batch liquid release setpoint determination to also allow the use of the tritium sample obtained prior to release of a radwaste tank, and 5) modified some monitor calibration constants based on recent isotopic calibrations. The pump flow rate changas were a result of recent design changes.

DCP A-7022.00SC is installing a new maintenance building, the South Yard Facility (SYF) in parking lot 1.

When finally completed, two potential airborne effluent release points will be created, one for the handling and working of radioactive material and another for the decontamination of equipment and components. The building is not scheduled to be fully operationc! until 1995.

Included in this revision are monitor information that will se pertinent when the equipment is installed and accepted by Station. Noted action statements, applicable when the radiation monitor is out of service, will be applicable if the building is used prior to full equipment implementation.

Indeed, if the SYF is to be used for handling or working radioactive material prior to final DCP turnover, a station procedure with the proper safety evaluation will be used to govern such interim usage to O

ensure that there is no adverse radiological impact to a member of the public.

Subsequent to the final DCP turnover, the next appropriate ODCM revision will incorporate all pertinent information regarding the SYF as effluent release points.

One change brought on oy the Land Use Census concerned the addition of a page of R, parameters for Outage Residents. These are plant workers who, during refueling outages, live on plant property. These workers are present only during outages, typically 3 months per unit every two years. They were present during the 1993 Land Use Census and so accordingly are presented in this document. The Outage Resident doses are not limiting as they are bounded by existing receptors.

In years when no outages occur, this page will not appear in either the Land Use Census or the ODCM.

One note was added to Table 4-3 regarding I hour particulate and iodine sampling time when only one channel is operable.

In the G.T. Gibson memorandum for file " Units 2/3 Clarification No.14", dated June 30, 1994, the position was stated:

normal monitor shutdown for filter changing does not result in the monitor being inoperable.

Shutdown beyond one hour should be carefully considered as bordering on " inoperable".

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9501300162 950113 PDR ADOCK 05000361 R

PDR

Even though this memorandum addressed radiation monitors R-7804 and R-7807 in their compliance to Technical Specification 3.4.5.1, the position was logically applied to other gaseous radiation monitors. The NRC concurred with the original memo regarding R-7804 and R-7807.

No safety evaluations were performed for updating radiation monitor calibration constants or implementing changes from the 1993 Land Use Census.

These changes reflect results from routine surveillances and as such do not constitute a modification in methodology for determining activity released from the site and subsequent dose to a member of the public.

Two radiation monitors had flow indicating switches installed in their sample flow lines, RE-7817 (BPS and FFCPD) and RE-7821 (TPS) in DCP 2&3 6191.00BJ.

These flow switches, FISL-7817 and FISL-7821 respectively, are required for monitor operability.

They alarm when the radmonitor's minimum required sample flow is not present.

By the action of the FISLs, they effectively become an integral part of the radiation monitor circuitry. When the FISL fails, the radmonitor is declared inoperable. When the FISL alarms on low flow, the radmonitor is declared inoperable.

Because of this method of capturing the essence of the requirement, calling out the individual flow switches in Tables 4-1 and 4-2 is not warranted. The flow instruments are being listed in individual maintenance procedures.

Because of problems e.~perienced with these new flow indicating switches, a new design of flow switch is planned for installation early next year. Testing of this new design is already occurring.

Per NRC Generic Letter 89-01, no safety review was required or performed for the correction of typographical errors.

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f The following is a complete list of the changes-Indicates typographical, sequential and page numbering, and format i

changes.

6 The South Yard Facility (SYF) is under construction. The schedule currently calls for completion in steps, with the final turnover occurring in the summer of 1995.

Interim use of the SYF, if necessary, will be controlled by a station procedure with the required safety evaluation. The next appropriate ODCM revision subsequent to the final DCP A-7022.00SC turnover will incorporate all pertinent information regarding the SYF.

The 1993 Land Use Census revealed increased occupancy factors in two locations, San Clemente Ranch Packing (Sector R, 2.6 miles) and "51

" Area" Beach (renamed from Enlisted Beach)(Sector Q, 1.4 miles) and a decreased occupancy factor for one location, Highway Patrol weigh station (Sector G, 2.0 miles). Correspondingly, the dose parameters for i

all affected age groups were affected in those three locations. The occupancy factors increased from 0.3425 to 0.3674 and from 0.2283 to 0.2568, respectively, and decreased from 0.2283 to 0.2146. This information was formally transmitted in the memorandum from E.M. Goldin to J.R. Clark, " Submittal of 1993 ODCMs Dose Parameters (R ) for San Onofre Nuclear Generating Station Unit I and Units 2/3", dated April 12, 1994.

ii' Revised page sequence numbering due to pages added in section 4.

iii' Revised page sequence numbering due to pages added in section 4.

iv' Revised page sequence numbering due to pages added in section 4.

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v' Revised page sequence numbering due to pages added in section 4.

1-10 Revised the definition of C. An option to use the tritium sample t

result obtained prior to each radwaste tank release is added in calculating the monitor setpoint.

1-15 Revised the FFCPD HUT waste flow rate to 1000 gpm per M0s 94050511, 94050513, 94050515, and 94050404. New stainless steel pumps were installed which produce higher flow rates.

1-21' Corrected alignment ca equation definitions.

l-23 Revised the Unit 3 Turbine Plant Sump pump flow rate to 100 gpm/ pump per DCP 3-6748.

1-26 Revised calibration constants.

b 2-2 Added South Yard Facility to continuous release pathways.

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6 2-4 Added note "j" regarding the South Yard Facility flow path.

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2-12' Deleted extra spaces between lines.

l 2-15' Properly aligned a paragraph.

2-18* Corrected typographical error.

I 2-25 Revised calibration constants.

2-28 Clarified definition for W, under equation 2-13.

i 2-30' Added missing parenthesis to equations 2-16 and 2-17.

t 2-32 Corrected a typographical error in equation 2-18. Also changed Health Physics Engineering to Corporate Health Physics and Environmental.

2-33 Clarified definition for We under equation 2-18.

Also corrected a typographical error in the same definition.

l 2-34 Clarified definition for W under equation 2-19.

e 2-40* Revised the pathway name from Enlisted Beach Trailers to 51 Area Beach Trailers.

I 2-40a*Cre.ated new page and new pathway in accordance. with the Land Use Census.

l This page reflects the periodic " outage resident" which reside:: on site t

during refueling outages.

2-41' Corrected typographical error in name of pathway.

2-44* Revised the pathway name from Enlisted Beach / Campground to 51 Area Beach / Campground.

2-45* 51 Area Beach Check-in occupancy fcctor increased ? rom 0.2283 to 0.2568 (Sector Q, 1.4 miles), thereby changing dose paraseters. Also, the name was changed from Enlisted Beach Check-in.

2-52* San Clemente Ranch Packing with residents occupancy factor increased from 0.3425 to 0.3674 (Sector R, 2.6 miles), thereby changing dose i

parameters.

2-77* Highway Patrol Weigh Station occupancy factor decreased from 0.2283 to 0.2146 (Sector G, 2.0 miles), thereby changing dose parameters.

2-81* Removed "3" from C, under equation 2-21.

l 4-7 Added footnote (4) to certain particulate and iodine samplers.

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4-8 Added this page to Table 4-3 to list the planned new SYF effluent flowpaths.

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4-9 Added clarification notes on I hour particulate and iodine sample time

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with only one channel operable. Also revised page sequence numbering V

due to pages added in section 4.

4-10' Revised page sequence numbering due to pages added in section 4.

4-11' Revised page sequence numbering due to pages added in section 4.

4-12' Revised page sequence numbering due to pages added in section 4.

6 4-13 Added this page to Table 4-4 to list the planned new SYF effluent flowpaths. Also revised page sequence numbering due to pages added in section 4.

b 4-14 Added note (5) regarding SYF building occupancy. Also revised page sequence numbering due to pages added in section 4.

4-15' Revised page sequence numbering due to pages added in section 4.

j 4-16' Revised page sequence numbering due to pages added in section 4.

4-17' Revised page sequence numbering due to pages added in section 4.

4-18' Revised page sequence number: 1g due to pages added in section 4.

5-1 Corrected name of required document in section 5.1.1.a.

O 5-11 Added a statement, to be consistent with existent procedures, regarding V

the reporting in the next Annual Radioactive Effluent Release Report of

^

new locations found by the yearly Land Use census which yields a calculated dose or dose commitment greater than those currently being l

calculated. Also corrected a typographical error.

5-16' Added "**" to item 41 Old Route 101-East to emphasize the footnote explaining that this TLD is located inside the Site boundary. The i

physical location was not changed.

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NECEIVG)Qy DEC21 y

'WflLE Copy OFFSITE DOSE CALCULATION NANUAL NUCLEAR ORGANIZATION i

UNITS 2 AND 3 O

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O s023-=cN Revision 27 12-21-94 er i

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t ODCM TABLE 0F CONTENTS EA9f.

LIST OF FIGURES............................ iv i

LIST OF TABLES...,........................ v vi INTRODUCTION............................. vii 1.0 LIQUID EFFLUENTS........................

1-1 thru l-30 1.1 Concentration.......................

1-1 1.1.1

. Specification...................

1-1 1.1.1.1, 1.1.1.2 Surveillances..............

1-1 1.2 Dose...-.-.......................

1-5 1.2.1 Speci ficati on...................

1-5 1.2.1.1 Surveillance...................

1-5 1.3 Liquid Waste Treatment..................

1-6 1.3.1 Specification...................

1-6 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances..........

1-6_

1.4 Liquid Effluent Monitor Setpoints.............

1-8 l

1.4.1 Batch Release Setpoint Determination 1-10 1.4.2 Continuous Release Setpoint Determination.....

1-16 1.5 Dose Calculations for Liquid Effluents..........

1-27 i

1.6 Representative Sampling..................

1-30 2.0 GASE0US EFFLUENTS.......................

2-1 thru l

2-82 2.1 Dos e Rate.........................

2-1 2.1.1 Specification....................

2-1 2.1.1.1, 2.1.1.2 Surveillances..............

2-1 2.2 Dose - Noble Gas.....................

2-5 2.2.1 Specification...................

2-5 2.2.1.1 Surveillance...................

2-5 2.3 Dose - Radiciodines, Radioactive Materials in Particulate Form and Tritium.....................

2-6 2.3.1 Specification...................

2-6

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2.3.1.1 Surveillance...................

2-6 S023-0DCM Revision 22 1

08-02-90

ODCM l

TABLE OF CONTENTS (Continued)

EASA C

2.4 Gaseous Radwaste Treatment 2-7 2.4.1 Speci fication....................

2-7 2.4.1.1 Surveillance...................

2-7 2.4.1.2, 2.4.1.3 Surveillances..............

2-8 2.5 Total Dose........................

2-9 2.5.1 Speci fication....................

2-9 2.5.1.1 Surveillance...................

2-9 2.6 Gaseous Effluent Monitor Setpoints 2-11 2.6.1 Pl ant Stack....................

2-11 2.6.2 Condenser Evacuation System............

2-15 2.6.3 Containment Purge.................

2-18 2.6.4 Waste Gas Header.................

2-21 2.7 Gaseous Effluent Dose Rate................'. 2-26 2.7.1 Nobl e Gases....................

2-26 2.7.2 Radiciodines and Particulates...........

2-27 2.8 Gaseous Effluent Dose Calculation.............

2-29 2.8.1 Nobl e Gases....................

2-29 O

2.8.1.1 Historical Meteorology.........

2-29 2.8.1.2 Concurrent Meteorology.........

2-30 2.8.2 Radiciodines and Particulates...........

2-32 2.8.2.1 Historical Meteorology.........

2-32 2.8.2.2 Concurrent Meteorology.........

2-33 2.9 Total Dose Calcul ations..................

2-80 2.9.1 Total Dose to Most Likely Member of the Public..

2-80 2.9.1.1 Annual Total Organ Dose.........

2-80 2.9.1.2 Annual Total Whole Body Dose......

2-81 t

2.9.1.3 Annual Total Thyroid Dose........

2-82 3.0 PROJECTED DOSES........................

3-1 thru 3-1 3.1 Liquid Dose Projection 3-1 r

3.2 Gaseous Dose Projection..................

3-1 4.0 EQUIPMENT...........................

4-1 thru 4-18 lb 4.1 Radioactive Liquid Effluent Monitoring Instrumentation..

4-1 4.1.1 Speci fication....................

4-1 O

4.1.1.1, 4.1.1.2 Surveillances..............

4-1 S023-0DCM Revision 25 ii 02-28-92

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TABLE OF CONTENTS (Continued)

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Pn9A 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation..

4-6 4.2.1 Specification....................

4-6 4.2.1.1 Surveillance...................

4-6 4.3 Operability of Radioactive Waste Equipment........

4-15 l6 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING.............

5-1 thru 5-25 5.1 Monitoring Program....................

5-1 5.1.1 Specification..................

5-1 5.1.1.1 Surveillance...................

5-2

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5.2 Land Use Census......................

5-11 5.2.1 Specification..................

5-11 i

5.2.1.1 Surveillance...................

5-11 5.3 Interlaboratory Comparison Program............

5-12 5.3.1 Specification..................

5-12 5.3.1.1 Surveill ance...................

5-12 5.4 Annual Radiological Environmental Operating Report....

5-13 O

i s s s P e toc tio#s s-14 6.0 ADMINISTRATIVE.........................

6-1 thru 6-16

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6.1 Definitions........................

6-1 6.2 Administrative Control s..................

6-7 6.3 Major Changes to Radioactive Waste Treatment Systems s

(Liquid and Gaseous) 6-9

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6.4 Bases...........................

6-10 r

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S023-0DCM Revision 25 iii 02-28-90

f ODCM

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LIST OF FIGURES O'

Fiaure Title-Paae i

1-2 Site Boundary for Liquid Effluents................

1-7 2-2 Site Boundary for Gaseous Effluents 2-10 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems..... 4-16 lR 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems 4-17 R-4-7 Solid Waste Handling....................... 4 18 R

I 5-1 Radiological Environmental Monitoring Sample Locations...... 5-23 j

5-2 Radiological Environmental Monitoring Sample Locations Orange County 5..........................

i 5-3 Radiological Environmental Monitoring Sample Locations

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San Diego County.........................

5-25 t

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O S023-0DCM iv Revision 26 12-20-93 4

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ODCN LIST OF TABLES Table Title Paoe 1-1 Radioactive Liquid Waste Sampling and Analysis Program..

1-2 l-3 Liquid Effluent Radiation Monitors l

Calibration Constants 1-26 1-4 Dose Commitment Factors A,

................ 1-28 i

2-1 Radioactive Gaseous Waste Sampling and Analysis Program.

2-2 i

2-3 Gaseous Effluent Radiation Monitor Calibration Constants..................

2-25 i

2-4 Dose Factors for Noble Gas and Daughters.........

2-35 2-5 Dose Parameters P 2-36 it 2-6 Controlling Location Factors...............

2-37 2-7 Dose Parameters R for Sector P 2-38 i

2-8 Dose Parameters R for Sector Q 2-40 i

h 2-9 Dose Parameters R, for Sector R 2-50 10 Dose Parameters R for Sector A 2-55 i

2-11 Dose Parameters R for Sector B 2-58 i

i 2-12 Dose Parameters R, for Sector C 2-61

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I 2-13 Dose Parameters R for Sector D 2-66 i

2-14 Dose Parameters R for Sector E 2-69

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2-15 Dose Parameters R for Sector F 2-72 i

2-16 Dose Parameters R, for Sector G 2-76 i

4-1 Radioactive Liquid Effluent Monitoring Instrumentation..

4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

................4-4

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4-3 Radioactive Gaseous Effluent Monitoring Instrumentation 4-7, 4-8 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements................

4-11 lR O

S023-0DCM Revision 25 i

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P LIST OF TABLES (Continued)

Table Title Paae 5-1 Radiological Environmental Monitoring Program......

5-3 5-2 Reporting Levels for Radioactivity Concentrations in

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Environmental Samples 5-7 i

5-3 Maximum Values for the Lower Limits of Detection (LLD)..

5-8 5-4 Radiological Environmental Monitoring Sample Locations..

5-15 f

5-5 PIC Radiological Environmental Monitoring Locations...

5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map.......

5-22 6-1 Operational Modes....................

6-5 l

6-2 Frequency Notation....................

6-6 i

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S023-0DCM i

Revision 25 l

vi 02-28-92

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (0DCM) is a supporting document of the O

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology an'd parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents.

In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarnVtrip setpoints. The environmental section contains a list of the sample locations for the i

radiological environmental monitoring program.

j The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculaticns to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current O

t methodology.

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O S023-0DCM Revision 21 vii 02-15-90

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l.0 LIQUID EFFLUENTS z

1.I' CONCENTRATION

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SPECIFICATION 1.1.1 The concentration of radioactive material released from the

' site (see Figure 1-2) 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.

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For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10" microcuries/ml total activity.

APPLICABILITY: At all times

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i ACTION:

a.

With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REOUIREMENTS

.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1.

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.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to i

assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.

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S023-0DCM 1-1 Revision 22 08-02-90 i

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TABLE 1-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (pC'/ml)'

A. Batch Waste P

P Principa) Gamma 5:t10-7 d

' Release Each Batch Each Batch Emitters 4

I-131 1x10-8 P

M Dissolved and 1x10-5 One Batch /M Entrained Gases 1 -

(Gamma emitters) j P

M H-3 1x10-5 i

h Each Batch Composite

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Gross Alpha 1x10-7 P

Q Sr-89, Sr-90 5x104 h

Each Batch Composite Fe-55 1x10-6 i

(

N_0_TE BATCH RELEASE POINTS:

Primary Plant Makeup Storage Tanks, Radwaste Primary i

0 Tanks, Radwaste. Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity) and holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown.

Principa 5x10-7 i

B. Continuous D

W Emitters) Gamma Releases',

Grab Sample Composite *

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4 I-131 1x10 M

M Dissolved and 1x10-5 I

Grab Sample Entrained Gases (Gamma emitters) l d

D M

H-3 1x10 Grab Sample Composite

Gross Alpha 1x10-7 D

Q Sr-89,'Sr-90 5x10-a Grab Sample Composite

Fe-55 1x10-'

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N_QIf CONTINUOUS RELEASE P0,1,NTS: Turbine Plant Sump *, Blowdown Processing Sump", S/G I

Blowdown Bypass Line, S/G Blowdown, Salt Water Discharge from CCW Heat Exchanger, Auxiliary Building Sitmp.

O S023-0DCM 1-2 Revision 25 02-28-92

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JBLE1-1 (Continued)

TABLE NOTATION O

a.

The LLD is the smallest concentration of radioactive material in a sample that V

will be detect;d rith 95% probability with 5% probability of falsely concluding that a blank ossemtion represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s" LLD =

i E. V. 2.22 x 10' Y. exp (-Mt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

se is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

5 2.22 x 10 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

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A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s3 used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an uriverified theoretically predicted variance.

Typical values of E, V, Y and At should be used in the calculation.

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

'For a more comf:.e discussion of the LLD, and other detection limits, see the l

following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (Jtne 22, 1972).

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S023-0DCM 1-3 Revision 26 12-20-93

TABLE 1-1 (Continued)

JB LE NOTATION (O

b.

A composite sample is one in which the quantity of liquid sampled is 0

proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c.

To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected con'inuously in proportion to the rate of flow of the effluent stream.

Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e.

A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

f.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7p21 is the turbine plant sump.

The first sump when transferring outlying sumps shall be treated as a batch release.

p Sampling of this flow is not required if at least once per 31 days blowdown bypass isola + ion valve (S21301MU618 for Steam Generator 2E088, S21301MU619 for Steam Generator 2E089, S31301MU618 for Steam Generator 3E088 and S31301MU619 for Steam Gener-tor 3E089) is verified locked shut.

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O S023-0DCM 1-4 Revision 26 12-20-93

1.0 LIQUID EFFLUENTS (C:ntinutd)

I 1.2 DQ1E C

SPEClEICATION 1.2.1 The dose or dose comitment.to an individual from radioactive materials in liquid effluents released, from each reactor unit, frori the site (see Figure 1-2) shall be limited:

j a.

During any calendar quarter to less than or equal to 1.5 mrem l

to the total body and to less than or equal to 5 mrem to any t

organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

j APPLICABILITY: At all times ACTION:

i a.

With calculated dose from the release of radioactive materials

+

in liquid effluents exceeding any of. the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases. and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

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SURVEILLANCE REOUIREMENTS

.1 Dose Calculation.

Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.

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O S023-0DCM 1-5 Revision 21 02-15-90 l

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1.0 LIQUID EFFLUENTS (Centinued) l.3 LIOUID WASTE TREATMENT l

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SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the l

radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the i

site (see Figure 1-2) when averaged over 31 days, wou 0.06 mrem to the total body or 0.2 mrem to any organ.ld exceed l

APPLICABILITY: At all times ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes r

the following information:

.. Explanation of why liquid radwaste was being. discharged l

without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability, l

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2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and i

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3. Summary description of actiencs) takee to prevent a recurrence.

l SURVEILLANCE RE0UIREMENTS i

l

.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1.

.2 During plant operation (Mode 1-4), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equi ment for at-least 15-minutes at least once per 92 days unless tie liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

.3 In plant shut-down (Mode 5, 6), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by l

operating the liquid radwaste treatment system equipment for at i

least 15-minutes prior to processing liquids unless the appropriate liquid radwaste system has been utilized to process radioactive i

liquid effluents during the previous 92 days.

.t Per reactor unit j

l O

S023-0DCM i

1-6 Revision 22 08-02-90

)

1

~

san morac uunzan GDtEAATWIE STATapet 180ETS t. 2 43

,.i o

00 p --

't r-2.

Tsa "Iden

+ -

s s f

~Yia

L M

~

t..we i

O~

)

f

/

I

/

s'r

\\,

%g

,/

SITE B0UNDARY FOR LIOUID EFFLUENTS FIGURE 1-2

REFERENCE:

TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 S023-0DCM 1-7 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation O

Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release i

point to the unrestricted area. To meet this specification and for the

)

purpose of implementation of Specification 1.1.1, thr alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

C,R

('}

s MPC,,,

t where:

O MPC,,,

effective effluent maximum concentration permissible limit (pci/ml) at the release point to the unrestricted area for the radionuclide mixture being released, 3

(1-2)

N

' y' '

E i =1

, MPC,,

9 O

S023-0DCM 1-8 Revision 21 02-15-90

1.0 LIQUID EFFLUENTS (Ccntinued) i 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued) h where:

fractional concentration'of the i radionuClide as obtained by h

th F,

sample analysis.

l r

N number of radionuclides identified in sample analysis.

t

=

th MPC, =

MPC of the i radionuclide (10CFR20, App B, Table II, Column 2).

i t

setpoint, representative of a radionuclide concentration for C,

the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, pCi/ml.

permissible waste effluent flow rate at the radiation monitor

(

R

=

location, in volume per unit time in the same units as for F.

l dilution water flow in volume per unit time. The dilution i

F water flow (F) is 185,000 gpm per cire pump (4 total) and 17,000 gpm per saltwater pump (2 total).

The design flowrate of each circulating water pump is 205,000 gpm. The value used in the determination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radicactive release concentration is not underestimated.

O r

l i

O S023-0DCM l-9 Revision 21 02-15-90

^

i 1.0 LIQUID EFFLUENTS (Continu:d) j 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued)

O

. administrative vaiues are used to reduce each setnoint to acceunt for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data (including, for example, any saltwater discharge of the component cooling water heat i

exchanger) and revised as necessary, f

1.4.1 Batch Release Setpoint Determination The waste flow (R) and monitor setpoint tc) are set to meet the condition of equation (1-1) for the effective MPC (MPC,,f) limit.

The method by which this is accomplished is as follows:

i STEP 1:

The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the O

measured ce#ce tratiens in the ta#x (or so P) -

determined by analysis.

(

}

C

= E, C + C, + C, + C +C.

1 r

where:

C

= total concentration in each batch tank, pCi/ml E C,,

= sum of the measured concentrations for each i

radionuclide,1, in the gamma spectrum, pCi/ml Cr,

= Fe-55 concentration as determined in the previous quarterly composite sample, pCi/ml C,

gross alpha concentration determined in the previous

=

monthly composite sample, pCi/ml C,

Sr-89 and Sr-90 concentrations as determined in the

=

previous quarterly composite sample, pCi/ml C

H-3 concentration as determined in the previous monthly

=

1 composite sample, or as measured in the sample taken R

prior to release, pCi/ml.

O S023-0DCM 1-10 Revision 27 12-21-94

' 1. 0 LIQUID. EFFLUENTS (Continued) 1.4.1 Batch Release Setpoint Determination (Continued)

STEP 2:

The effective MPC (MPC n) for each batch tank (or e

sump) is determined using:

(1-4) 3 MPC'" =

' C,,/C'

' C)C'

' C,/C'

' CJC'

' C ]C' 7

MPC,,,

MPC,,

MPC MPC,,

MPC 1,

re, MPC,,, MPC,, MPC, -

the limiting concentrations of the appropriate s

MPCre, MPC, radionuclide from 10CFR20, Appendix B, Table II, Column 2.

NOTE:

For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.

I STEP 3:

The radioactivity monitor setpoint C, pCi/ml, may now be O

specified based on the values of C, E,C,,, F, MPC,u and R i

to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

The monitor setpoint, cpm, is taken from the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor concentration limit C,, pCi/ml.

t h

i 2

4 S023-0DCM 1-11 Revision 21 02-15-90

3 1.0 LIQUID EFFLUENTS (C*ntinued) 1.4.1 Batch Release Setpoint Determination (Continued) f]

1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) l The value for C,, the concentration limit at the detector, is determined by using:

(-)

(RW)

(F)

(C,ff)

C*

C" (R +.. + R,)

+.. +

1 effl

effn, where:

number of tanks to be released.

n effective gamma isotopic concentration at the monitor for C,ff

=

the tank combination to be released (equal to E c, for iy single tank releases).

R (E,C,,) + R, (E,C,,) +... + R, (E,C,,),

l 3

R + R, +... + R, l

3 (E c,5),, etc.

= total gamma isotopic concentration of first (Es yi)3, c

i tank, second tank, etc. (pCi/ml).

R, R, etc. = typical effluent flow rate from first tank, 3

2 second tank, etc. Values of R for each tank are as follows:

Radwaste Primary Tanks R = 140 gpm/ pump (x no. of pumps to be run)

Radwaste Secondary Tanks R = 140 gpm/ pump (x no. of pumps to be run)

Primary Plant Makeup Tank R = 160 gpm/ pump (x no. of pumps to be run)

Condensate Monitor Tanks R = 100 gpm/ pump (x no. of pumps to be run) f l

()/

(*

S023-0DCM 1-12 Revision 26 12-20-93 i

i'

1.0 LIS'ID EFFLUENTS (Continu:d) 1.4.1.1 RADWASTE DISCHARGE LINE JITOR (2/3-7813)

(Cor,tinued)

/

L/ '

NOTE: Since the values of R are much smaller than F, the term (F + R) in equation (1-1)'may be replaced by F.

MPCeffi, MPC,ff2, etc.

values of MPC,ff from equation (1-4) for

=

first tank, second tank, etc.

values of C, total concentration, from equation C, C, etc.

=

3 2

(1-3) for the first tank, second tank, etc., in pCi/ml.

RW,13 and SGaa-2' SG bG bb 0 ' 0 ' I ' I are administrative 7

89-2' 88-38 89-3' 2

3 2

3 values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators as well as continuous discharges from the two Blowdown Processing Systems and the j

f two Turbine Plant Sumps. The fractions RW7s13 and SGas-28 SGa9-2 8 SGes-3 8 B, B, T, T will be assigned such that (RW7si3 + SGas-2 + SG89-2 SG, 3, 2

3 2

3

+ SGas-3 + SG -3 + b + B + T + 1 } $ 1.0.

I 89 2

3 2

3 t

i i

f i

o S023-0DCM i

1-13 Revision 21 02-15-90 l

-t 1.0 LIQUID EFFLUENTS (Ccntinued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813)

(Continued)

{

The 1.0 ~is an administrative value used to account for the potential-activity released simultaneously from other release points. This_

assures that the total concentration from all release points to the -

?

plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2 from l

t the Site.

1 E

NOTE:

If C, s C,ff, then no release is possible..To increase C.,

l increase dilution flow F (by running more circulating l

water pumps in the applicable discharge structure), and/or decrease the effluent flow rates R, R, etc., (by

{

2 2

throttling the combined flow as measured on 2/3FI-7643, 2FIC-4055, 2FIC-4056, 3FIC-4055 or 3FIC-4056 as O

99taarite) adrecic='tec.#s'#9the#

r a #8 l

equation (1-5).

l i

i i

i l

O i

S023-0DCM i

1-14 Revision 26 12-20-93 J

l

1.0 LIQUID EFFLUENTS -(Centinued) j 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALI2ER (FFCPD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-7817)

/)

V The value for C or C, the concentration limit at the Unit 2 or 2

3 Unit 3 detector, is determined by using:

t

(~

(B,) ( F) 3,C,,

2-(R)(C/MPC,,,)

(~}

l (B )(F)E,C,,

3 3-(R)(C/MPCerf) where:

C, I,C,,, MPC,,,

values of C, I,C,, and MPC,,, as defined in STEPS

=

1) and 2) for the Neutralization Sump /FFCPD Sumps.

R Typical release flow rates

=

500 gpm Neutralization Sump 500 gpm FFCPD High Conductivity Sump

)

600 gpm FFCPD Low Conductivity Sump 1000 gpm FFCPD Holdup Tank A

C2 instantaneous concentration at the detector i

=

(2RT-7817) in pCi/cc C3 instantaneous concentration at the detector

=

(3RT-7817) in pCi/cc B and B are administrative value's used to account for simultaneous 2

3 releases from both SONGS 2 and SONGS 3 neutralization sumps. The t

fractions B and Ba (each normally set to 0.05) will be assigned such

{

2 l

that (RWis33 + SGs2 + SGs-2 + SGes-3 + SGs-3 + B + B + T + T ) 1 1.0.

l 2

3 2

3 O

S023-0DCM l-15 Revision 27 12-21-94 1

.-m

--+w-m

j

+

'1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 NEUTRALIZATION $ UMP / FULL FLOW CONDENSATE POLISHER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-7817) h (Continued) j If C or. C s 2 0,,, then no release is possible. To increase NOTE:

2 3

5 C or. C, increase dilution flow F (by running more pumps),-

l 2

3 and/or decrease.the effluent flow rate R, (by throttling.the i

flow as measured on 2FI-3722 and 3FI-3772), and recalculate C 2 or C using the new F, R and equation (1-7) or (1-8).

l 3

l t

1.4.2 Continuous Release Setpoint Determination The waste flow (R) and monitor setpoint (C,) are set to meet the condition of equation (1-1) for the effective MPC (MPC,,,) limit. The' j

method by which this is accomplished is as follows:

f I

STEP 1:

The isotopic concentration for the continuous releases are O-obtained for each release stream (steam generator f

blowdown, steam ganerator blowdown bypass, blowdown neutralization sump and turbine plant sump) from the sum j

t' of the respective measured' concentrations as determined by analysis:

1

(

C = E,C,, + C, + C, + C, + Cre 1

1

.I l

i l

t i

O S023-0DCM l

1-16 Revision 26 i

12-20-93 i

i 1.0 LIQUID EFFLUENTS (C:ntinued)-

1.4.2 Continuous Release Setpoint Determination (Continued) l r

where:

C totcl concentration (pci/ml)

=

I,Cg total gamma' activity associated with'each radionuclide, 1, l

=

-in-the weekly composite analysis for the release stream, pC1/ml C,

total measured gross alpha concentration determined from

=

the previous monthly composite analysis for the release stream,pCi/ml Cr.

total Fe-55 concentration as determined in the previous

=

quarterly composite sample for the release stream, pCi/ml total measured H-3 concentration de'termined_ from the C,

=

previous monthly composite analysis for the release stream,pCi/ml I

C, total measured concentration of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis for the release stream, pCi/ml STEP 2:

The effective MPC (MPC,,,) for each release stream (steam

]

generator blowdown, blowdown neutralization sump, or

(

turbine plant sump) is determined using:

1

( - 0)

MPC,,, =

, C,/C, C)C

,C)C C ]C

, C)C 7

E

+

i MPC MPC MPC MPC MPC f,

s, Tc, t,

u w

=>

t i

O i

i S023-0DCM 1 - 17 Revision 22 08-02-90 t

1.0 LIQUIS EFFLUENTS (Continued) 1.4.2 Contir.uous Release Setpoint Determination (Continued)

(

STEP 3:

The setpoint, C (pci/ml), for each continuous release radioactivity monitor may now be specified based on the respective values of C, I C,,, F, MPC,,,, and R to provide -

i compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

The monitor setpoint, cpm, is taken from the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit C,

pCi/ml.

i l

l O

9 i

O S023-0DCM 1-18 Revision 21 02-15-90

+,

1.0 LIQUID EFFLUENTS (C:ntinued) 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITORS I

(2RT-7817. 3RT-7817) gs The value for C2 or C, the concentration limit at the Unit 2 or Unit 3

3 detector is determined by using:

(~

}

(B,) (F) E,C,,

2-(R) (C/MPC,,,)

(~

}

(B )(F)E,C,,

3 3~

(R)(C/MPC,,,)

where:

values of C, E,C,, and MPC,,, as defined in C, Z C,,,

MPC,,y i

STEPS 1 and 2 for the Steam Generator blowdown / BPS neutralization sump.

effluent flow rate at the radiation monitor as R

defined in STEP 2 (maximum of 500 gpm).

instantaneous concentration at the Unit 2 C

3 detector (2RT-7817) in pCi/cc

~

P instantaneous concentration at the Unit 3 C

3 detector (3RT-7817) in pCi/cc B and B are administrative values used to account for simultaneous 2

3 releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B and B will be assigned such that {RW 7313 + SG

-2 + SGas-2 +

88 2

3 Y 0 Y 0 + I + I ) $ 1.0 SG

.3 + SG89-3 2

3 2

3 33 i

i 1

S023-0DCM l-19 Revision 22 08-02-90

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITOR (2RT-7817. 3RT 7817)

(Continued)

NOTE:

If C or C s I,C,,, then no release is possible. To increase 2

3 C or C, increase dilution flow F (by running more circulating 2

3 water pumps), and/or decrease the effluent flow rate R, (by throttling the flow as measured on 2FI-3722 and 3FI-3772), and recalculate C or C3 using the new F, R and equation (1-11) or 2

(1-12).

O O

S023-0DCM 1-20 Revision 26 12-20-93

-1.0 LIQUID EFFLUDITS (Continued) i 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753. 2RT-6759. 3RT-6753. 3RT-6759)

The value for C,.2, C

.2, C,.3 or C

.3, the concentration limit at the 3

33 3

33 Unit 2 or Unit 3 detectors, is determined by using:

(1-3)

]

(SG,y)(F)I,C,,

58 4 (R)(C/MPC,,,)

II' )

(SG,q)(F)E,C,,

53 4 (R)(C/MPC,,,)

( -15)

(SG,.3) (F)I,C,,

5'-3 ~

(R)(C/MPC,,,)

(1-16) i (SG,.3) (F) E,C,,

{

ss (R)(C/MPC,,,)

O where:

C, I,C,,, MPC,,,

values of C, E,C,i and MPC,,, (as defined in

=

STEPS I and 2 above) for the steam generator i

blowdown bypass.

R maximum blowdown bypass effluent flowrate per i

=

steam generator, 200 gpm.

}

P instantaneous concentration at the Unit 2 i

C

.2

=

39 detector (2RT-6759) in pCi/ml j

i instantaneous concentration at the Unit 2 (4,

l C

.2

=

33 detector (2RT-6753) in pCi/ml F

instantaneous concentration at the Unit 3

[g-C,.3

=

3 detector (3RT-6759) in pCi/ml l

instantaneous concentration at the Unit 3 lE C

.3

=

33 detector (3RT-6753) in pCi/ml j

i i

O S023-0DCM 1-21 Revision 21 02-15-90 l

1.0 LIQUID EFFLUENTS (Ccntinued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753. 2RT-6759. 3RT-6753. 3RT-6759)

(Continued)

\\-

RW,13 and SG S G

-2' bb

-3' bb -38 0'0'I I are administrative 7

88-2' 89 88 89 2

3 25 3

values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators as well as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RW7823 and SGas.3, SGeg.z, SG 88-38 B, B, T, T will be assigned such that {RW SG

.3, 7333 + SG

.2 + SG g.,

eg 2

3 2

3 es e

+ SG88-3 + SG89-3 0 Y 0 + I + I ) s 1.0.

2 3

The 1.0 is an administrative value used to account for the potential activity released simultaneously from other release points. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2-from the site.

NOTE:

If C

.2, or C.3 s I,C,, (for the respective steam C

.2, C, 3, 39 3

33 33 generator), then no release is possible. To increase C s9-2 C s-2, Css 3 or C

.3, increase dilution flow F (by running more s

33 circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2FIC-4055, 2FIC-4056, 3FIC-4055, 3FIC-4056 or 2/3FI-7643, as appropriate) and recalculate C

.2, C

.2, C.3 or C.3 using the new values of 39 33 39 33 F, R and equation (1-13), (1-14), (1-15) or (1-16).

5023-0DCM 1-22 Revision 21 02-15-90 m-.

I 1.0 LIQUID EFFLUENTS (C ntinued)

L O

1.4.2.3 TURBINE-PLANT SUMP MONITORS (2RT-7821. 3RT-78211 The value for C, or C3 (the concentration limit at the Unit 2 or Unit 3 detector) is determined by using:

l

(~

}

(T,) ( F)I,C,,

i C, s (R)(C/MPC,,,)

( - 8)

(T )(F)E,C,i 3

Cs 3

(R)(C/MPC,,,)

where:

C, E c,,,

MPC,,,

values of C, I,C,, and MPC,,, (as defined in i

STEPS I and 2 above) for the turbine plant sump R

Typical waste stream release flow rates:

=

100 gpm/ pump (x no. sump pumps to be run) Unit 2 i

100 gpm/ pump (x no sump pumps to be run) Unit 3 lA, l

'Cr instantaneous concentration at the Unit 2 detector (2RT-7821),pC1/ml.

()

C3 instantaneous concentration at the Unit 3

=

detector (3RT-7821), pC1/ml.

i i

i b

O S023-0DCM l-23 Revision 27 12-21-94

1.0 LIQUID EFFLUENTS (C:ntinued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821. 3RT-7821) (Continued)

\\d T, and T are administrative values used to account for simultaneous 3

releases from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions Tz and T will be assigned such that (RW7313 + SG s-2 + SG89-2 +

3 a

SG s-3 + SG89-3 0+0+I+T}s1.0.

a 2

3 2

3 NOTE:

If C or C s 2 0,, (for the respective sump), then no release 2

3 5

is possible. To increase C or C, increase the dilution flow 2

3 F (by running more circulating water pumps) and recalculate C2 or C using the new value of F and equation (1-17) or (1-18).

3 Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 7821, in service and the normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:

v a.

The release permit shall account for the entire volume of water discharged from the Turbine Plant Sump.

b.

The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal and temporary paths.

c.

Procedures shall require the imediate termination of the discharge via the temporary path if the monitor on the normal path alarms.

OL)

S023-0DCM l-24 Revision 21 02-15-90

r I

t 1.0 LIQUID EFFLUENTS (Continusd) l O

a i

i

\\

t 1

I h

i

.i t

This page intentionally left blank.

l i

o i

l ll i

i i,

t t

i

!'l j

i O

S023-0DCM l-25 Revision 26 l

12-20-93 I

4 6

i

...-e

-,_..._-..,.-...--.____,m

.._..,,,,,,,u_.-..

..,.m.

Tablo 1-3 i

Liquid Effluent Radiation Monitor Calibration Constants (pCi/cc/ cpm)

MONITOR Co-60 Ba-133 Cs-137 l

2RT-6753 1.93E-8 1.94E-8 2RT-6759 2.18E-8 2.15E-8 E

'3RT-6753 1.63E-8 1.91E-8 2RT-6759 1.95E-8 1.93E-8 R

2/3RT-7813 2.15E-9 3.77E-9 5.48E-9 2RT-7817 2.36E-9 3.30E-9 4.86E-9 l

2RT-7821 2.32E-9 3.17E-9 4.71E-9 3RT-7817 2.34E-9 3.22E-9 4.95E-9 3RT-7821 2.33E-9 3.18E-9 4.73E-9 O

i I

l

'l

)

(a) This table provides typical (i 20%) calibration constants for the liquid

{

effluent radiation monitors.

O S023-0DCM 1-26 Revision 27 12-21-94

1.0 LIQUID EFFLUENTS (C:ntinued)

.. l. 5 Dose Calculation for Liquid Effluents

-s The liquid releases considered in the following dose calculations are described in Section 1.4.

The dose comitment to an individual from radioactive materials in liquid effluents released to unrestricted areas

~ are calculated for the purpose of implementing Specification 1.2.1 using the following expression.

(1-19)

D, = E, A,, I/At C Ff j y 3 where:

A, Site-related adult ingestion dose comitment factor to the total i

body or an organ, t, for each identified principal gama and beta r

emitter,1, from Table 1-4 in mrem /hr per pCi/ml.

Cy average concentration of radionuclide, 1, in the undiluted liquid effluent during time period, At, in pCi/ml.

j D,

dose comitment to the total body or an organ, t, from the liquid effluent for the time period, At, in mrem.

O y

F near field average dilution factor (actually mixing ratio) for C 3

y during the time period, At. This factor is the ratio of the 3

maximum undiluted liquid waste flow during time period, At, to j

the average flow from the site discharge structure to unrestricted receiving waters, or maximum liauid radioactive waste flow discharge structure exit flow 3

length of the jth time period over which C At y and F are averaged 3

for all liquid releases, in hours.

t b

I O

S023-0DCM l-27 Revision 26 12-20-93

TABLE 1-4 DOSE COMMITMENT FACTORS *, Aa 73 (mrem /hr per pCi/ml)

Radio-Total Nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.'1E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.b!E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+0 4.37E+2 Sr-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4

s Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4

('J Nb-95 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 Nb-95m 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 Nb-97 1.55E-2 3.91E-3 1.43E-3 4.56E-3 1.44E+1 Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-113 2.26E+5 Sn-117m 2.26E+5 Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 I-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 I-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 NOTE:

where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A

)

Methodology: USNRC NUREG-0133, Section 4.3.1

(_/

S023-0DCM 1-28 Revision 26 12-20-93

TABLE 1-4 DOSE C00mITMENT FACTORS *, An (mrem /hrperpCi/ml)

Radio-Total Nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+0 8.81E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+0 3.38E+3 La-140 1.57E+0 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96E+0 4.58E+0 2.74E-1 2.68E+0 2.20E+4 W -187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 NOTE:

where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, Table A-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 o

S023-0DCM 1-29 Revision 26 12-20-93

~1.0 LIQUID EFFLUENTS (Centinurd) e

()

1.6 Representative Sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG-0800, Section 11.5.

The methodology for mixing and sampling is described in S0123-III-5.II.23,

" Units 2/3 Liquid Effluent Release Permit" and S0123-III-5.2.23, " Units 2/3 Liquid Effluent Sample Collection".

O i

i i

O S023-0DCM l-30 Revision 21 02-15-90

2.0 GASE005 EFFLUENTS 2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following; a.

For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 arem/yr to the skin, and b.

For all radiciodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY: At all times ACTION:

a.

With dose rate (s) exceeding the above liniits, immediately decrease the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS

.1 The dose rate due ta noble gases in gaseous effluents shall be determitad to be within the above limits in accordance with Section 2.7.

O

.2 The dose rate due to radioiodines, tritium and radioactive materials 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 Section 2.7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

1 O

S023-0DCM 2-1 Revision 21 02-15-90

TABLE 2-1 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection i

Type Frequency Frequency Analysis (pCi/ml)'

l Batch P

P Principal Gamma Emitters' lx10'd Waste Gas Each Tank Each Tank Decay Tank Grab Sample i

i i

4 Incinerated Each Batch Each Batch Principal Gamma Emitters' 5x10 h

Oil Grab Sample Continuous Principal Gamma Emitters' lx10

Tritium lx10'6 d

W 1-131 lx10~22 Continuous' Charcoal Sampler Sample I-133 lx10'2 d

W Continuous' Particulate Principal Gamma Emitters 5 lx10-22 Sampler Sample (I-131 and Others)

M Continuous' Composite Gross Alpha lx10~2 Sampler Particulate g

Sample Q

Continuous' Composite Sr-89 and Sr-90 lx10~22 Sampler Particulate Sample Continuous' Noble Gas Noble Gases lx10~6 Monitor Monitor Gross Beta or Gamma

Sampling frequencies for noble gases and tritium are:

CONTINUOUS PATHWAYS: Containment Purge - 42" :

Each Purge

6 b

Containment Purge - 8" Monthly Grab b

Condenser Air Ejector Monthly Grab Plant Vent Stack Weekly Grab '

6 South Yard Facility Particulate and Iodine 4

J Sampling only GLJ S023-0DCM 2-2 Revision 27 12-21-94

IABLE 2-1 (Continued)

TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample a.

p that will be detected with 95% probability with 5% probability of falsely V

concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s6 LLD =

E. V = 2.22 x 106 Y

exp (-Mt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

is the standard deviation of the background counting rate or of the s 3 counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

6 2.22 x 10 is the number of transformai. ions per minute per microcurie, Y is the fractional radiochemical yield I.when applicable),

(]

1 is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s3 used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y and At should be used in the calculation.

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

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L.

A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J.

K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972).

S023-0DCM 2-3 Revision 26 12-20-93

TABLE 2-1 (Continued)

TABLE NOTATION I

b.

Analyses shall also be performed following shutdown, startup, or a THERMAL O

POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period. This regairement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

d.

Samples snall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

Sampling shall also be perfornad at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in I hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. This requirement does not apply if:

(1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased morc than a factor of 3.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

e.

Tritium grab samples shall be taken at least one per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f.

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 2.1, 2.2, 2.3.

g.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

h.

Incinerated oil may be discharged at points other than the plant vent stack.

Release shall be accounted for based on pre-release grab sample data.

i.

Samples for incinerated oil releases shall be collected from representative samples of filtered oil in liquid form.

j.

Radioactive airborne effluents only expected to be particulate and iodine.

6 S023-0DCM 2-4 Revision 27 12-21-94

9

(

2.0 GASE0US EFFLUENTS (Ccntinued) 2.2 DOSE - NOBLE GASES

]

SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 2-2) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year:

Less than or equal to 10 = rad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a.

With calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that O

subsequent releases will be in compliance with Specifica-tion 2.2.1.

SURVEILLANCE RE0VIREMENTS

.1 p_qte Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

i O

S023-0DCM 2-5 Revision 21 02-15-90

t 2.0 GASE0US EFFLUENTS (C:ntinued) 2.3 DOSE - RADIOI0 DINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radiciodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limited to the following:

I a.

During any calendar quarter:

Less than or equal to 7.5 mrem to any organ and, b.

During any calendar year: Less than or equal to 15 mrem to any i

organ, c.

Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result

[

of burning contaminated oil.

APPLICABILITY: At all times ACTION:

a.

With the calculated dose from the release of tritium, radioiodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report i

O required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Technical l

Specification 6.9.2 a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

SURVEILLANCE RE0VIREMENTS I

.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

i i

l O

S023-0DCM 2-6 Revision 21 02-15-90

2.0 SASE005 EFFLUENTS (Continued) 2.4 GASE0US RADWASTE TREATMENT SPECIFICATION 2.4.1 The GASE0US RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate i

portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior io their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2-2), when

~

averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 2-2) when averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY: At all times ACTION:

a.

With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information:

O

1. Explanation of why gaseous radwaste un being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

SURVEILLANCE RE0UIREMENTS

.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.

i

These doses are per reactor unit.

O S023-0DCM 2-7 Revision 22 08-02-90

2.0 GASE0US EFFLUENTS (C ntinued) i 2.4 GASEOUS RADWASTE TREATMENT (Continued)

SURVEILLANCE REOUIREMENTS (Continued) 2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive' gaseous effluents during the previous 92 days.

~

.3 In plant shut-down (Mode 5, 6), the applicable portions of the GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASE0US RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutes prior to processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.

A r

U S023-0DCM 2-8 Revision 22 08-02-90

2.0.SASE005 EFFLUENTS (Continued) i 2.5 TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose commitment to any member of the public, due to i

releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem c

to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.a,1.2.1.b, 2.2.1.a, 2.2.1.b, 2.3.1.a, or 2.3.1.b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 2.5.1.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 O

ce sec#tive e#ta Peried ta t 4 c'# des the reie se(s) cevered by this report.

If the estimated dose (s) exceeds the limits of Specification 2.5.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11(b).

Submittal of the report is considered a timely requert, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCM.

SURVEILLANCE RE0VIREMENTS

}

.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.

(v3 S023-0DCM 2-9 Revision 21 02-15-90 l

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NUCLEAR GENERATING STATION

cges Units 2 & 3 1

/

SITE BOUNDARY FOR GASEOUS EFFLUENTS j

Figure 2-2 1

____ L 2-10 S023-00CM 950/3D/6 Z-O /

M *

o, ;

2.0 GASE0US EFFLUENTS (Crntinu:d) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setnoints O

ad i#istr tive v 'ees re esed te redece ch setvei#t te ecee"t for t

the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data and revised l

as required. The sum total of all these administrative va' lues for the site shall be less than or equal to 1.0.

2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 l

2.6.1.1 2/3RT-7808 - Plant Vent Stack Monitor r

For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

Total Body

[

O The cencentretien at the detecter correspondine to a 500 mrem /yr total body dose rate at the exclusion area boundary is determined by:

(2-1) p i

C*

4 3

( 500 mrem /yr) (10 m /cc) where:

(0.38) 2120 C

=

the at Co,1 instantan (Flow rate, cfm) (X/Q, sec/m )

E, K,,

mrem /yr

' C, '

3 eous i

concentra pCi/m

, t,t 3

C tion at the detector, pCi/cc i

0.38 an administrative value used to account for potential activity from other gaseous release pathways O

l S023-0DCM 2-11 Revision 26 i

12-20-93

l 2.0' GASE0US EFFLUENTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 (Continued)

O total body dose conversion factor from K,

=

Table 2-4 for the 1*h g gas, mreny'yr per pCi/m,amma emitting noble th concentration of the i noble gas as C

i determined by sample analysis, pCi/cc total concentration of noble gases as C,1

=

1 determined by sample analysis, pCi/cc = I ci i

plant vent flow rate, cfm Flow Rate

=

82,000 cfm/ fan (x no. of fans to be run)

=

3 conversion constant, cfm per m /sec 2120 total body dose rate limit, as specified by 500 mrem /yr

=

Specification 2.1.1.a X/Q historical annual average dispersion factor,

=

sec/m 3

4.8E-6 sec/m

=

EkiB The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by:

(2-2) cfm 4 3 m /sec,

( 3000 mrem /yr) (10 m /cc)

(0.38) 2120 C

=

det (Flow rate, cfm)(X/Q, sec/m)

E, L, + 1.1M, **!##

3 i

3 C

pCi/m

,, 1,1 O

S023-0DCM 2-12 Revision 24 08-31-91

2.0 SASEOUS EFFLUENTS (C:ntinued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 (Continued)

!,,)

where:

skin Dose Conversion Factor from Table 2-4 for the L,

=

3 ith g]g 3 gg 7 gp air Dose Conversion Factor from Table 2-4 for the M,

=

t 3

i " noble gas, mrem /yr per pCi/m conversion factor to convert gamma air dose to 1.1

=

skin dose 3000 mrem /yr skin dose rate limit as specified by Specification

=

2.1.1.a Other values in equation (2-2) are defined in equation (2-1).

The smaller of the values of C,1 from equations (2-1) or (2-2) o is to be used in the determination of the maximum permissible monitor alarm setpoint (cpm), as follows:

()

The maximum permissible alarm setpoint (cpm) is determined using the calibration constant for 2/3RT-7808 given in Table 2-3.

The maximum permissible alarm setpoint is the value " cpm" corresponding to the concentration, Co,1 (the smaller value from equation (2-1) or (2-2)). The calibration constant used is based on Kr-85 or on Xe-133, whichever yieldt a lower detection efficiency (the largest value in term of pCi/cc/ cpm).

The alarm setpoint will be maintained at a value not greater than the maximum permissible alarm setpoint.

S023-0DCM 2-13 Revision 21 02-15-90

2.0 GASEOUS EFFLUENTS (C:ntinued)

C/

2.6.1.2 2RT-7865-1 and 3RT-7865-1 Wide Ranoe Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitors is determined by converting the concentration at the detector, C,1 (pCi/cc) to an equivalent release rate in pCi/sec, as o

follows:

(~

A, =

(C,,,, pCi/cc)(flowrate, cc/sec) where:

A, maximum permissible release rate, pCi/sec C,1 smaller of the values of Co,1 obtained from e

equations (2-1) or (2-2).

Flow Rate flow rate,'cc/sec

=

(3.87 x 10 cc/sec per fan) (number of fans)

=

O 2-r cter to ce=Reasete rar the se14t rie-between Unit 2 and Unit 3 plant vent stacks The release rate setpoint will not be set greater than the maximum release rate determined above, when this monitor is being used to meet the requirements of Specification 2.1.1.

g LJ S023-0DCM 2-14 Revision 26 12-20-93

2.0 GASE0US EFFLUENTS (C:ntinu:d)

(

2.6.2 CONDFNSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air Eiector Monitors '

For the purpose of implementation of Specification 2.1.1, the alarm setpoint level. for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

.l The concentration at the detector corresponding to a total body dose rate of. 500 mrem /yr at the exclusion area boundary is determined by using:

Total Body (2-4) s cfm (0.1)(0.5) 2120

( 500 mrem /yr) (10 m /cc) 4 3 C

=

det t

(Flow rate, cfm) (X/Q, sec/m')

E, K,,

mrenVyr C,

3 pCi/m,, tos,,

j The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:

3 10 (2-4a) 1

?

cfm m /sec,

( 3000 mrem /yr) (10 m'/cc) 4 (0.1)(0.5) 2120 C

=

det (Flow rate, cfm) (X/Q, sec/m') E, L, + 1.1M,, mrem /yr C,

3 pCi/m C,1 1

O S023-0DCM 2-15 Revision 26 12-20-93

i 2.0 GASEOUS EFFLUENTS l

t 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 i

g].

or 3RT-7870-1 (Continued) where:

0.1 is an administrative value used to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases from both SONGS 2 and SONGS 3 condenser air ejectors simultaneously.

Other parameters are specified in 2.6.1.1, and 2.6.2.2.

The smaller of the values Co., from equations (2-4) or (2-4a) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows:

l The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding t

Condenser Evacuation System Monitor given in Table 2-3.

The i

maximum permissible alarm setpoint is the cpm value O'

corresponding to the concentration, Co,1, [ smaller value from l

equation (2-4) or (2-4a)].

I The calibration constant used is based on Kr-85 or on Xe-133, t

whichever yields a lower detection efficiency (higher value l

in terms of pCi/cc/ cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.

4 O

S023-0DCM 2-16 Revision 21 02-15-90 l

L 2.0 GASE0US EFFLUENTS (C:ntinued)

I ()-

2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranae Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitor is determined by converting the concentration at the5 detector, Co,s (pC1/cc), to an equivalent release rate in pCi/sec.

(Co,1, pCi/cc) (flow rate, cc/sec)

(,

=

where:

maximum permissible release rate, pCi/sec

(,

=

smaller value of Co,1, as obtained from C,e

=

o equations (2-4) and (2-4a) flow rate of the condenser air ejector, cc/sec flow rate

=

4.719E5 cc/sec (conservatively assumed as

=

design flow rate)

O i

m h

l O

S023-0DCM 2-17 Revision 26 12-20-93 L

2.0 GASE0US EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 Ri Fo:- the purpose of implementation of Specification 2.1.1, the r'N tQ alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion boundary is determined by using:

Total Body (2-6)

CI" m /sec,

( 500 mrem /yr) (10 m /cc)

(0.38)(P,) 2120 4 3 Cdet2 =

(Flow rate, cfm) (X/Q, sec/m') E, K,,

mrem /yr C, '

3 C,1,,

pCi/m 1

(2-7) m /sec,

( 500 mrem /yr) (10 m /.cc)

(0.38)(P ) 2120 4 8 3

C

=

det3 (Flow rate, cfm) (X/Q, sec/m') E, K,, "#**!##

3 C,1, pCi/m 1

The concentration at the detector corresponding to a r

3000 mrem /yr skin dose rate at the exclusion area boundary is 1

determined by using:

Skin (2-6a) cfm m /sec,

( 3000 mrem /yr) (10 m /cc) 4 3 (0.38)(P,) 2120 C

det2

, C, (Flow rate, cfm) (X/Q, sec/m') E, L, + 1.lM,, a e yr 3

pCi/m C

, 1,1 (2-7a)

O S023-0DCM 2-18 Revision 22 08-02-90

t l

2.0 SASEOUS EFFLUDITS (C:ntinued)

.2.6.3 -

CDETA1191ElfLEURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued) l

)

where:

l Caett instantaneous concentration-of the Unit 2 5

detector,pCi/cc.

Co,13 instantaneous concentration of the Unit 3

=

detector,pCi/cc.

0.38 is an administrative value used to account for potential activity from other gaseous release pathways.

P, and P are administrative values used to account for 3

simultaneous purges of both SONGS 2 and SONGS 3.

The fractions P2 i

and P will be assigned such that Pr + P 51.0.

l 3

3 observed maximum flowrate in cfm from the unit i

Flow rate specific monitor 7828. Default values will be the i

h following conservative measured flows:

50,000 cfm full purge

=

3,000 cfm mini-purge-

=

(The above values replace the smaller design-flowrates.)

Other parameters are as specified in 2.6.1.1 above. The smaller of l

the values of maximum permissible Co,tz from equation (2-6) or l

(2-6a) and Co,13 from equations (2-7) or (2-7a) is to be used in determining the maximum permissible monitor alarm setpoints.

I O

S023-0DCM 2-19 Revision 22 08-02-90 j

2.0 GASE0US EFFLUENTS (Continued) i 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued)

)

-')

2.6.3.1 Maximum Permissible Alarm Settino (RT-7865)

The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (pCi/sec) is determined by converting the concentration at the detector, C,e (pCi/cc),to an equivalent release rate in pCi/sec.

o A.,= (Co,1, pCi/cc) (flow rate, cc/sec) where:

maximum permissible release rate, pCi/cc A,x smaller value of Ce,1, as obtained from equation C,1 o

(2-6, 2-6a) for Unit 2 or (2-7, 2-7a) for Unit 3.

i flow rate - flow rate, cc/sec 1.416E6 cc/sec for mini-purge.

2.360E7 cc/sec for main purge.

O

.2 Maximum Permissible Alarm Settina (RT-7828) 5 The maximum permissible alarm setting for RT-7828 is in pCi/cc and is the smaller of the values of Coeu (pci/cc) from equations (2-6) and (2-6a).

2 l

i

()

S023-0DCM 2-20 Revision 26 12-20-93 i

=2.0 GASE0US EFFLUENTS (C"_ntinued) i

~2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808-

[

t]

For the purpose of Specification 2.1.1, the alarm setpoint

/

level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Since the waste gas header discharges to the plant vent stack, either 3RT-7865 or 2/3RT-7808 may be used to monitor waste gas header releases.

9 The concentration at the detector corresponding to a total body 1

dose rate of 500 mrem /yr or a skin dose rate of 3000 mrem /yr at the exclusion area boundary is determined by using equations r

(2-1) or (2-2) with sample concentration (C ) and (C,1) being i

1 obtained from the waste gas decay tank to be released.

O The smaller of the values of maximum permissible concentration (Co,1) from equation (2-1) or (2-2) is to be used in f

determining the maximum pennissible monitor alarm setpoint.

1 2/3RT-7808 i

The maximum permissible alarm setting (cpm) is determined by using the calibration constant for plant vent stack monitor 7808 given in Table 2-3.

The maximum permissible setpoint is i

the cpm value corresponding to the concentration Co,1, (smaller I

value from equation (2-1) or (2-2)).

i i

i O

S023-0DCM 2-21 Revision 21 02-15-90

_~ -

i 2.0 GASE0US EFFLUENTS (C:ntinued) i 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 -(Continued)

~

3RT-7865 The maximum permissible alarm setting is expressed as a maximum a

release rate (pCi/sec) and is determined by converting-the concentration at the detector, C,1, to an equivalent release rate in pCi/sec by equation (2-8).

f A, =

(C,,,, W/cc) (Howrate, cc/sec) where:

A,1 the maximum permissible release rate, pCi/sec

=

the smaller value of C Co,s equation (2-1) or (2-2f.,, as obtained from

=

flowrate -

flowrate, cc/sec 7.74E7 cc/sec for 2 fan operation or

=

3.87E7 cc/sec for 1 fan operation

=

r correction for 3-7865 viewing only 1/2 the total 2

=

O ei #t ve#t st ck ri i

.1 A release from the waste gas header is not possible if:

(2-9)

C,),->c,,,

i

.s 7

where:

total concentration in waste gas holdup tank to be I,C,

=

released f

waste gas header effluent flow rate, cfm

=

plant vent stack flowrate in cfm (166,00C cfm for F

=

2 fan operation; 82,000 for I fan operation) e smaller of the values of C.1 from equation.(2-1)

C,1

=

or (2-2) with C, being obtained from the waste gas holdup tank to be released l

O S023-0DCM 2-22 Revision 24 08-31-91 i

c n -

1

-2.0 SASE0ti$ EFFLUEllTS.(C:ntinued)~

2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Continued)

O 2a42 (c "t'## d) 1 If a release is not possible, adjust' the waste gas header flow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Vent Stack Monitor

' setpoint in accordance with the following:

(2-10) f < (0.9)(C,,1)(F)

E C, s

where:

-t f-waste gas header effluent flow rate (cfm)

F=

plant vent stack flow rate (cfm) used in equation (2-1) or (2-2)

C., =

smaller of the value of Co,t from equation (2-1) or o

(2-2) i O

r,c, -

total gamma activity (pci/cc) of the waste gas holdup tank to be released, as determined from the pre-release i

sample analysis.

The 0.9 is an administrative value to account.for the potential i

activity from other releases in the same release pathway.

I i

i i

i O

5023-0DCM f

2 - 23 Revision 24 08-31-91 n.

.m,

O l

l THIS PAGE INTE'iTIONALLY LEFT BLANK O

r i

O S023-0DCM 2-24 Revision 26 12-20-93

{

Table 2-3(")

l Gaseous Effluent Radiation Monitor O

c i46r tioa coast at-(pCi/cc/ cpm)

MONITOR Kr-85 Xe-133 2/3RT-7808C 4.43E-8 4.81E-8 j

i e

2RT-7818A 4.27E-8 6.86E-8 2RT-7818B 7.31E-5 1.2E-4 lE 3RT-7818A 3.73E-8 5.12E-8 3RT-7818B 9.31E-5 1.2E-4 lA

[

O V

I r

i f

(a)This table provides typical ( 20%) calibration constants for the gaseous effluent radiation monitors.

O S023-0DCM 2-25 Revision 27 12-21-94

=

2.0 GASE0US EFFLUENTS (Ccntinued) 2.7 Gaseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions:

2.7.1 FOR N0BLE GASES:

(2-11)-

D, = E, K,(X7Q) Q, 7

(2-12)

(L + l lM ) (X70) Q D, " E t

s i

i I

where:

O total body dose rate in unrestricted areas due to Drs i

radioactive materials released in gaseous l

effluents, mrem /yr D,

skin dose rate in unrestricted areas due to

=

radioactive materials released in gaseous effluents, mrem /yr the total body dose factor due to gamma emissions K,

from Table 2-4 for each identified noble gas 3

radionuclide, i, in mrem /yr per pCi/m O

S023-0DCM 2-26 Revision 21 02-15-90

p 2.0 GASE0US EFFLUENTS (Ctntin=d) 2.7.1 FOR NOBLE GASES:

(Continued) skin dose factor due to the beta emissions from O'

L, i

Table 2-4 for each identified noble gas 3

radionuclide, i, in mrem /yr per pCi/m i

air dose factor due to gamma emissions from M

Table 2-4 for each identified noble gas 3

radionuclide, i, in mrad /yr per pCi/m (conversion constant of 1.1 mrent srad converts air

/

dose to skin dose.)

measured or calculated release rate of Qi radionuclide, i, for either continuous or batch gasecus effluents, in pCi/sec (X/Q)

Maximum annual average atmospheric dispersion factor.for any sector or distance at or beyond the unrestricted area boundary.

3 4.8E-6 sec/m.

^

2.7.2 FOR ALL RADI0I0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:

(2-13)

O V

D E

4(Pa g) Q, o

where:

O, organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem /yr O

S023-0DCM 2-27 Revision 22 08-02-90

2.0 GASE0US_EEFLUEMIS (C:ntinued) 2.7.2 FOR ALL RADI0I0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER

[].

THAN EIGHT DAYS:

(Continued)

Q, measured or calculated release rate of radionuclide,1,

=

for either continuous or batch gaseous effluents, pCi/sec P,,

dose parameter for radionuclide, i, for pathway, k,

=

from Table 2-5 for the inhalation pathway in mrem /yr 3

per pCi/m. The dose factors are based on the critical individual organ and the child age group.

9, Mghest calculated annual average dispersion (X/Q) or

=

deposition (IGQ) factor for estimating the dose to an g

individual at or beyond the unrestricted area Doundary for pathway k.

3 (X/Q), 4.8E-6 sec/m for the inhalation pathway. The location is the unrestricted area in the NW sector.

(D/Q), 4.3E-8 m-2 for the food and ground plane

=

pathways. The location is the unrestricted area in the l

E sector.

e O

S02 M 0CM 2-28 Revision 27 12-21-94

2.0 RASEGUS EFFLAIEN6 (Continued)

.t 2.8 Saseous Eff10 9t Dose calculation i

\\*

2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS l

The gaseous releases considered in the following dose calculations are described in Section 2.6.

The air dose in unrestricted areas due to noble gases released in gaseous f

effluents is calculated using the following expressions:

[

2.8.1.1 For historical meteoroloov:

I (2-14) l 4

D, = 3.17x10 E, M, (T/Q)Q, j

(2-15)

D, = 3.17x108 I, N, (T/Q)Q, i

i where:

D, =

total gamma air dose from gaseous effluents, mrad D, =

total beta air dose from gaseous effluents, mrad 3.17x10-8 inverse seconds per year

=

M, =

air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in arad/yrperpCi/m' Ni=

air dose due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad /yr per pCi/m' 4.8E-6sec/m'. The maximum annual average atmospheric (T/Q)

=

dispersion factor for any sector or distance at or beyond the unrestricted area boundary.

Qi =

amount of noble gas radionuclide, i, released in gaseous eff.luents, pC1.

O S023-0DCM 2-29 Revision 22 08-02-90

2.0 GASE0US EFFLUENTS (C:ntinued) 2.8.1.2 For meteoroloov concurrent with release:

j NOTE:

Consistent with the methodology provided in Regulatory Guide 1.109 end the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actu'il calculations.

(2-16)

D

= 1.14x10" E, M, E ( At3(X/Q)3,

)

g 3

i (2-17)

D,,

= 1.14x10" E, N, E ( Atj (X/Q)3,g )

R 3

where:

total gamma air dose from gaseous effluents

=

in sector 6, mrad D

total beta air dose from gaseous effluents in p

sector e, mrad 1.14x10" inverse hours / year i

=

O M,

air dose factor due to gamma emissions from i

=

Table 2-4 for each identified noble g'as i

radionuclide, i, in arad/yr per pCi/m N,

air dose factor due to beta emissions from

=

Table 2-4 for each identified noble gas 3

radionuclide, i, in mrad /yr per pCi/m i

t leng}h of the jth time period oVer which (X/Q)3, At

=

3 and Qi3 are averaged for gaseous releases in hours (X/Q)),

atmospheric dispersion factor for time period At

=

3 at exclusion boundary location in sector e determined by concurrent meteorology, sec/m' Q,3 average release rate of radionuclide, i, in

=

gaseous effluents during time period, At, pCi/sec i

3 1

O I

S023-0DCM 2-30 Revision 22 08-02-90

)

O i

l i

THIS PAGE INTENTIONALLY LEFT BLANK O

r k

b O

S023-00CM 2-31 Revision 26 12-20-93

.=

=. -.. -.-

'2.0 GASE0US EFFLUENS (Centinued)'

l 2.8.2 DOSE FROM TRITIUN. RADI0 IODINES AND RADI0 ACTIVE MATERIA'_S IN PARTICULATE FORM WITH HALF LIVES l

GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to an individual from tritium, radiciodines and f

radioactive materials in particulate form with half lives greater than eight days in gaseous effluents released to I

unrestricted areas is calculated using the following expressions:

2.8.2.1 For historical meteoroloav:

(2-18)

D, = 3.17x10 E, 3(R,,W,Q, R

4 where:

D, total projected dose from gaseous effluent; to an

=

individual, mrem 4

3.17x10 year /second Q,

amount of each radionuclide, i, (tritium,

=

j radioiodine, radioactive material in particulate form with half lives greater than eight days),

released in gaseous effluents, pCi EgR,W, sum of all pathways, k, for radionuclide, i, of-l i

the R W product, in ares /yr per pC1/sec. The i

E R,,Wg value for each radionuclide, i, is given in Table 2-6.

The value given is the maximum E R,,W, for all locations and is based on-the most restrictive age groups.

dose factor for each identified radionuclide, i, I

R,,

=

for pathway k, '(fpr the inhalation pathway in arem/yr per pCi/m and for the food and ground plane pathways in m'-ares /yr per pCi/sec), at the controlling location. The R g's for each i

controlling location for each age group are given in Tables 2-7 thru 2-16.

Data in these tables are derived using the NRC code, PARTS.

(See the

,l annual update of revised R, parameters based on i

changes in the Land Use Census provided by b

Corporate Health Physics and Environmental.)

t O.

1 S023-0DCM 2-32 Revision 27 12-21-94

I 2.0 GASEOUS EFFLUENTS '(Csntinued) 2.8.2.1 For historical meteoroloav:

(Continued)

~

r a di=a r iaa (r>5) r d aasitia"

. O w

n (D7Q)factorforestimatingthedosetoan individual at the controlling location for pathway k.

3 (X7Q)fortheinhalationpathwayinsec/m.

=

The (17Q) for each controlling-location is given in Tables 2-7 thru 2-16.

(D7Q)forthe_f.apdandgroundplanepathways

. i n a-,. The (D/Q) for each controlling location is given in Tables 2-7 thru 2-16.

lR.

(X74) for any H-3 pathway for each controlling.

location is given in Tables 2-7 through 2-16.

2.8.2.2 For meteoroloav concurrent with releases:

NOTE:

Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.

(2-19) lan Q

0, = 1.14 x lod EEE (At )(R )(W ) g 3

i 3

where:

total annual dose from gaseous effluents to an D.

=

individual in sector e, area.

7 length of the f" period over which W a and Qg At

=

3 3

are averaged for gaseous released, hours Qu =

average release rate of radionuclide, i, in gaseous effluents during time period At, pCi/sec j

3 i

l O

S023-0DCM 2-33 Revision 27 12-21-94 I

2.0 GASEOUS EFFLUENTS (C:sntinued) 2.8.2.2 For meteoroloav concurrent with releases:

(Continued) 73 Rue =

dose factor for each identified radionuclide 1, for pathway k for sector 6 (for the inhalation pathway in mrem /yr per p,'Ci/m and for the food and ground plane pathways in m mrem /yr per pCi/sec) at the controlling location. A listing of Rn for the controlling locations in each landward sector for each group is given in Tables 2-7 thru 2-16.

The e is determined by the concurrent meteorology.

W,-

dispersion (X/Q) or deposition (D/Q) factor for the R

3 time period At for each pathway k for calculating the 3

dose to an individual at the controlling location in sector e using concurrent meteorological conditions.

3 (X/Q) for the inhalation pathway, sec/m (D/Q) for the food and ground plane pathways, m-r

=

O o

S023-0DCM 2-34 Revision 27 32-21-94

TABLE 2-4 DOSE FACTORS FOR N0BLE GASES AND DAUGHTERS **

O Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K, Factor L, Factor M Factor N 3

3 Radio-(mrem /yr (mrem /yr (mrad /yr (mrad /yr 3

3 3

3 Nuclide per pC1/m )

per pCi/m )

Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr-85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3

~d Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3

- Source: USNRC Reg. Guide 1.109, Table B-1 O

S023-0DCM 2-35 Revision 21 02-15-90

TABLE 2-5 DOSE PARAMETER Pa*

t CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathwag Inhalation Pathway Radionuclide (mrem /yr per pCi/m )

Radionuclide (mrem /yr per pCi/m*)

H-3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1E+5 I -134 5.1E+4 Co-58 1.1E+6 I -135 7.9E+5 Co-60 7.1E+6 Cs-134 1.0E+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.0E+8 Cs-137 9.1E+5 Zr-95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6 i

Source: USNRC NUREG-0133, Section 5.2.1.1 O

S023-0DCM 2-36 Revision 23 02-28-91

TABLE 2-6 i

CONTROLLING LOCATION FACTORS O

ERW k ig e Radionuclide mrem /yr per pCi/sec Use:

H -3 9.62E-4 Q: San Onofre Mobil. Homes Cr-51 3.25E-2 Q: San Onofre Mobil. Homes Mn-54 6.52E+0 Q: San Onofre Mobil. Homes Co-57 1.66E+0 Q: San Onofre Mobil. Homes Co-58

-2.33E+0 Q: San Onofre Mobil. Homes Co-60 8.56E+1 Q: San Onofre Mobil. Homes Sr-89 4.34E+1 Q: SC Ranch (No. Res.)

Sr-90 1.82E+3 Q: SC Ranch (No. Res.)

Zr-95 2.90E+0 Q: San Onofre Mobil. Homes Nb-95 6.81E+0 E: Deer Consumer Ru-103 1.08E+1 E: Deer Consumer Te-129m 5.32E+0 E: Deer Consumer Cs-134 3.36E+1 Q: SC Ranch (No. Res.)

Cs-136 6.81E-1 Q: San Onofre Mobil. Homes Cs-137 3.67E+1 Q: San Onofre Mobil. Homes Ba-140 1.56E+0 Q: San Onofre Mobil. Homes Ce-141 5.74E-1 Q: SC Ranch'(No. Res.)

Ce-144 1.68E+1 Q: SC Ranch (No. Res.)_

I -131 1.19E+1 Q: San Onofre Mobil. Homes I -132 1.45E-1 Q: San Onofre ! Mobil. Homes O

I -133 2.82E+0 Q: San Onofre Mobil. Homes I -134 3.94E-2 Q: San Onofre Mobil. Homes I -135 5.94E-1 Q: San Onofre Mobil. Homes UN-ID 3.59E+0 Q: San Onofre Mobil. Homes i

i

)

t Footnote:

These values to be used in manual calculations are the maximum I R Wg for all locations based on the most restrictive age group.

g ig I

S023-0DCM 2-37 Revision 25 02-28-92

TABLE 2-7 DOSE PARAMETER R, FOR SECTOR P

(]

Page 1 of 2 Pathway - Surf Beach / Life Guard Distance = 0.4 miles X/Q = 1.8E-6 sec/m' D/Q = 8.2E-9 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.2E+1 5.1E+1 9.6E+1 Cr-51 1.8E+2 3.2E+4 8.4E+2 1.5E+5 1.1E+3 3.5E+5 Mn-54 1.6E+4 9.5E+6 8.0E+4 4.5E+7 1.1E+5 1.1E+8 Co-57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 2.8E+4 2.6E+7 Co-58 1.2E+4 2.6E+6 5.4E+4 1.2E+7 7.1E+4 2.9E+7 Co-60 7.3E+4 1.5E+8 3.5E+5 7.0E+8 4.5E+5 1.6E+9 Sr-89 2.2E+4 1.5E+2 9.7E+4 7.1E+2 1.1E+E 1.6E+3 Sr-90 1.1E+6 4.4E+6 7.5E+6 Zr-95 2.3E+4 1.7E+6 1.1E+5 8.2E+6 1.3E+5 1.9E+7 Nb-95 6.4E+3 9.4E+5 3.0E+4 4.5E+6 3.8E+4 1.0E+7 Ru-103 6.9E+3 7.5E+5 3.2E+4 3.6E+6 3.8E+4 8.3E+6 Te-129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5 8.8E+4

1. 5E+6 Cs-134 1.1E44 4.7E+7 4.5E+4 2.2E+8 6.5E+4 5.2E+8 Cs-136 1.8E+3 1.0E+6 7.8E+3 4.9E+6 1.1E+4 1.1E+7 Cs-137 9.4E+3 7.1E+7 3.4E+4 3.4E+8 4.7E+4 7.8E+8 f}

Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 9.7E+4 1.6E46 N-Ce-141 5.7E+3 9.4E+4 2.5E+4 4.5E+5 2.8E+4 1.0E+6 Ce-144 1.2E+5 4.8E+5 5.4E+5 2.3 E+6 5.9E+5 5.3E+6 I -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5 9.1E+5 1.3E+6 I -132 2.0E+3 8.5E+3 6.1E+3 4.1E+4 8.7E+3 9.4E+4 I -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 1.6E+5 1.9E+5 I -134 5.3E+2 3.1E+3 1.6E+3 1.5E+4 2.3E+3 3.4E+4 I -135 8.2E+3 1.7E+4 2.5E+4 8.2E+4 3.4E+4 1.9E+5 UN-ID 1.0E+4 5.1E+6 5.0E+4 2.4E+7 6.6E+4 5.7E+7 Inhalation Pathway, units = ]jmyr Food & Ground Pathway, units I* IImrem/vr)

C O

S023-0DCM 2-38 Revision 26 12-20-93

TABLE 2-7 DOSE PARAMETER R FOR SECTOR P i

Page 2 of 2 OQ Pathway - Former Nixon Estate (no garden)

Distance = 2.8 miles X/Q = 1.2E-7 sec/m' D/Q = 3.4E-10 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhal a-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1F+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60

4. 5 E+ 6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 l

Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 l

l Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.lE+7 O

Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 l

l l

l Inhalation Pathway, units = ]j"(Y" Food & Ground Pathway, units I* IImrem/vr)

C O

S023-0DCM 2-39 Revision 23 02-28-91

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 1 of 10 (m',)

Pathway - 51 Area Beach Trailers Distance = 1.1 miles S

X/Q = 9.3E-7 sec/m' D/Q = 4.6E-9 m'8 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.3E+2 Cr-51 7.2E+3 2.3E+6 Mn-54 7.0E+5 6.9E+8 Co-57 1.8E+5 1.7E+8 Co-58 4.6E+5 1.9E+8 Co-60 3.0E+6 1.1E+10 Sr-89 7.0E+5 1.lE+4 Sr-90 5.0E+7 Zr-95 8.8E+5 1.3E+8 Nb-95 2.5E+5 6.8E+7 Ru-103 2.5E+5 5.4E+7 Te-129m 5.8E+5 9.8E+6 Cs-134 4.2E+5 3.4E+9 Cs-136 ~0- 7.3E+4 7.5E+7 Cs-137 3.lE+5 5.lE+9 Ba-140 6.4E+5 1.0E+7 (v')

Ce-141 1.8E+5 6.8E+6 Ce-144 3.9E+6 3.5E+7 I -131 6.0E+6 8.6E+6 I -132 5.7E+4 6.2E+5 I -133 1.lE+6 1.2E+6 I -134 1.5E+4 2.2E+5 I -135 2.2E+5 1.3E+6 UN-ID 4.3E+5 3.7E+8 Inhalation Pathway, units = "C Food & Ground Pathway, units I"

"}

Ci/sec O

S023-0DCM 2-40 Revision 27 12-21-94

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page la of 10 Pathway = Outage Resident Distance = 0.7 miles X/Q - 1.8E-6 sec/m' D/Q = 9.9E-9 m' Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.lE+2 Cr-51 4.6E+3 1.5E+6 Mn-54 4.5E+5 4.5E+8 Co-57 1.2E+5 1.lE+8 Co-58 3.0E+5 1.2E+8 Co-60 1.9E+6 6.9E+9 Sr-89 4.5E+5 7.0E+3 Sr-90 3.2E+7 '

Zr-95 5.7E+5 8.lE+7 t

Nb-95 1.6E+5 4.4E+7 Ru-103 1.6E+5 3.5E+7 Te-129m 3.7E+5 6.3E+6 i

Cs-134 2.7E+5 2.2E+9 Cs-136 4.7E+4 4.8E+7 Q

Cs-137 2.0E+5 3.3E+9 Ba-140 4.lE+5 6.6E+6 O'

Ce-141 1.2E+5 4.4E+6 Ce-144 2.5E+6 2.2E+7 I -131 3.8E+6 5.5E+6 I -132 3.7E+4 4.0E+5 I -133

-n-6.9E+5 7.9E+5 I -134

-t 9.6E+3 1.4E+5 I -135

-L-1.4E+5 8.lE+5 UN-ID 2.8E+5 2.4E+8 Inhalation Pathway, units "C /

Food & Ground Pathway, units I"

Ci/sfc i

O S023-0DCM 2-40a Revision 27 12-21-94

TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 2 of 10 Pathway - San Onofre Mobile Homes Distance - 1.3 miles X/Q = 7.4E-7 sec/m' D/Q = 3.6E-9 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4

4. 7 E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6

2. 5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 F

Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 k]

Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units -

?"

Food & Ground Pathway, units I*

I Ci/sec O

S023-0DCM 2-41 Revision 23 02-28-91

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 3 of 10 OV Pathway - State Park Office Trailer Distance = 0.6 miles 3

X/Q = 2.2E-6 sec/m D/Q = 1.2E-8 m'2 1

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.8E+1 Cr-51 6.6E+2 2.1E+5 Mn-54 6.4E+4 6.3E+7 Co-57 1.7E+4 1.6E+7 Co-58 4.2E+4 1.7E+7 Co-60 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr-90 4.5E+6 Zr-95 8.lE+4 1.lE+7 Nb-95 2.3E+4 6.2E+6 Ru-103 2.3E+4 5.0E+6 Te-129m 5.3E+4 9.0E+5 Cs-134 3.9E+4 3.lE+8 Cs-136 6.7E+3 6.9E+6 Cs-137 2.8E+4 4.7E+8 Ba-140 5.8E+4 9.4E+5 O

Ce-141 1.7E+4 6.2E+5 Ce-144 3.6E+5 3.2E+6 I -131 5.4E+5 7.9E+5 I -132 5.2E+3 5.7E+4 I -133 9.8E+4 1.1E+5 1 -134 1.4E+3 2.1E+4 I -135 2.0E+4 1.2E+5 UN-ID 3.9E+4 3.4E+7 Inhalation Pathway, units = "C Food & Ground Pathway, units I*

C /sec O

t S023-0DCM 2-42 Revision 23 02-28-91

=

TABLE 2-8 i

DOSE PARAMETER R, FOR SECTOR Q Page 4 of 10 O

eathwar - Surf. Beach / Guard Shack oistence - 0.7 miies X/Q = 1.8E-06 sec/m' D/Q = 9.9E-09 m-8 i

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.2E+1 5.1E+1 2.2E+2 Cr-51 1.8E+2 3.2E+4 8.4E+2 1.5E+5 2.5E+3 8.0E+5 Mn-54 1.6E+4 9.5E+6 8.0E+4 4.5E+7 2.4E+5 2.4E+8 Co-57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 6.3E+4 5.9E+7 Co-58 1.2E+4 2.6E+6 5.4E+4 1.2E+7 1.6E+5 6.5E+7 Co-60 7.3E+4 1.5E+8 3.5E+5 7.0E+8 1.0E+6 3.7E+9 Sr-89 2.2E+4 1.5E+2 9.7E+4 7.1E+2 2.4E+5 3.7E+3 Sr-90 1.1E+6 4.4E+6 1.7E+7 Zr-95 2.3E+4 1.7E+6 1.1E+5 8.2E+6 3.0E+5 4.3E+7 Nb-95 6.4E+3 9.4E+5 3.0E+4 4.5E+6 8.6E+4 2.3E+7 Ru-103 6.9E+3 7.5E+5 3.2E+4 3.6E+6 8.6E+4 1.9E+7 Te-129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5

2. 0 E+5 3.4E+6 Cs-134 1.lE+4 4.7E+7 4.5E+4 2.2E+8 1.5E+5 1.2E+9 Cs-136 1.8E+3 1.0E+6 7.8E+3 4.9E+6 2.5E+4 2.6E+7 Cs-137 9.4E+3 7.1E+7 3.4E+4 3.4E+8 1.1E+5 1.8E+9 Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 2.2E+5 3.5E+6 fi Ce-141 5.7E+3 9.4E+4 2.5E+4 4.5E+5 6.2E+4 2.3E+6 Ce-144 1.2E+5 4.8E+5 5.4E+5 2.3E+6 1.3E+6 1.2E+7 I -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5

2. 0E+6 2.9E+6 I -132 2.0E+3 8.5E+3 6.lE+3 4.lE+4 2.0E+4 2.1E+5 I -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 3.7E+5 4.2E+5 I -134 5.3E+2 3.1E+3 1.6E+3 1.5E+4 5.lE+3 7.7E+4 I -135 8.2E+3 1.7E+4 2.5E+4 8.2E+4 7.7E+4 4.3E+5 UN-ID 1.0E+4 5.lE+6 5.0E+4 2.4E+7 1.5E+5 1.3E+8 F

Inhalation Pathway, units -

yr Food & Ground Pathway, units I*

Ci/sec i

O S023-0DCM 2-43 Revision 26 12-20-93 t

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 5 of 10 c

Pathway =51AreaBeachgCampground Distance = 1.1 miles lR X/Q = 9.3E-07 sec/m D/Q = 4.6E-09 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground 1

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+01 1.4E+02 1.6E+02 1.6E+02 Cr-51 1.6E+03 5.7E+05 2.1E+03 5.7E+05 2.6E+03 5.7E+05 1.8E+03 5.7E+05 Mn-54 1.2E+05 1.7E+08 1.9E+05 1.7E+08 2.4E+05 1.7E+08 1.7E+05 1.7E+08 Co-57 4.7E+04 4.2E+07 6.3E+04 4.2E+07 7.2E+04 4.2E+07 4.6E+04 4.2E+07 Co-58 9.6E+04 4.7E+07 1.4E+05 4.7E+07 1.7E+05 4.7E+07 1.1E405 4.7E+07 Co-60 5.6E+05 2.7E+09 8.7E+05 2.7E+09 1.1E+06 2.7E+09 7.4E+05 2.7E+09 Sr-89 2.5E+05 2.7E+03 2.7E+05 2.7E+03 3.0E+05 2.7E+03 1.7E+05 2.7E+03 Sr-90 5.0E+06 1.2E+07 1.3E+07 1.2E+07 Zr-95 2.2E+05 3.lE+07 2.8E+05 3.1E+07 3.3E+05 3.1E+07 2.2E+05 3.1E+07 Nb-95 5.9E+04 1.7E+07 7.6E+04 1.7E+07 9.3E+04 1.7E+07 6.2E+04 1.7E+07 Ru-103 6.8E+04 1.3E+07 8.2E+04 1.3E+07 9.7E+04 1.3E+07 6.2E+04 1.3E+07 Te-129m 2.lE+05 2.4E+06 2.2E+05 2.4 E+06 2.4E+05 2.4E+06 1.4E+05 2.4 E+06 Cs-134 8.7E+04 8.4E+08 1.3E+05 8.4E+08 1.4E+05 8.4E+08 1.0E+05 8.4E+08 Cs-136 1.7E+04 1.9E+07 2.1E+04 1.9E+07 2.4 E+04 1.9E+07 1.8E+04 1.9E+07 Cs-137 7.5E+04 1.3E+09 1.1E+05 1.3E+09 1.0E+05 1.3E+09 7.7E+04 1.3E+09 Ba-140 2.0E+05 2.5E+06 2.1E+05 2.5E+06 2.5E+05 2.5E+06 1.6E+05 2.5E+06 P)

Ce-141 6.4E+04 1.7E+06 6.7E+04 1.7E+06 7.6E+04 1.7E+06 4.5E+04 1.7E+06

\\/

Ce-144 1.2E+06 8.6E+06 1.5E+06 8.6E+06 1.6E+06 8.6E+06 9.6E+05 8.6E+06 I -131 1.8E+06 2.1E+06 2.0E+06 2.lE+06 1.8E+06 2.1E+06 1.5E+06 2.lE+06 I -132 2.1E+04 1.5E+05 2.4E+04 1.5E+05 1.9E+04 1.5E+05 1.4E+04 1.5E+05 I -133 4.4E+05 3.0E+05 4.7E+05 3.0E+05 3.6E+05 3.0E+05 2.7E+05 3.0E+05 I -134 5.5E+03 5.5E+04 6.3E+03 5.5E+04 4.9E+03 5.5E+04 3.7E+03 5.5E+04 I -135 8.6E404 3.1E+05 9.8E+04 3.lE+05 7.7E+04 3.1E+05 5.5E+04 3.lE+05 UN-10 8.0E+04 9.2E+07 1.2E+05 9.2E+07 1.5E+05 9.2E+07 1.1E+05 9.2E+07 Inhalation Pathway, units =

[#

Food & Ground Pathway, units I* IImrem/vr) pC O

S023-0DCM 4

2-44 Revision 27 12-21-94

TAtl2 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 6 of 10

,a i )

Pathway - 51 Area Beach Check-In Distance - 1.4 miles P-s',

X/Q - 6.8E-7 sec/m' D/Q - 3.2E-9 m

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.2E+2 Cr-51 3.7E+3 1.2E+6 Mn-54 3.6E+5 3.6E+8 00-57 9.5E+4 8.8E+7 Co-58 2.4E+5 9.8E+7 Co-60 1.5E+6 5.5E+9 Sr-89 3.6E+5 5.5E+3 Sr-90 2.5E+7 Zr-95 4.5E+5 6.5E+7 Hb-95 1.3E+5 3.5E+7 l

Ru-103 1.3E+5 2.8E+7 Te-129m 3.0E+5 5.lE+6 b

Cs-134 2.2E+5 1.8E+9 Cs-136 3.8E+4 3.9E+7 Cs-137 1.6E+5 2.6E+9 Ba-140 3.3E+5 5.3E+6

'T Ce-141 9.3E+4 3.5E+6 (V

Ce-144 2.0E+6 1.8E+7 I -131 3.lE+6 4.4E+6 I -132 2.9E+4 3.2E+5 1 -133 5.5E+5 6.3E+5 I -134 7.7E+3 1.2E+5 1 -135 1.2E+5 6.5E+5 UN-ID 2.2E+5 1.9E+8 Inhalation Pathway, units -

?"

i Food & Ground Pathway, units I*

Ci/sec o

S023-0DCM i

2-45 Revision 27 1

12-21-94

)

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 7 of 10 Pathway-Sheep (Meat)fShepherd Distance = 1.6 miles X/Q = 5.6E-7 sec/m D/Q = 2.6E-9 m-'

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pe hway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.lE+0 Cr-51 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.lE+3 2.lE+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 (dT Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4. 4 E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.lE+5 9.5E+4 4.8E+3 4.2E+6 i

Inhalation Pathway, units =

7" Food & Ground Pathway, units I*

""'*/yr) g$j ec O

S023-0DCM 2-46 Revision 26 12-20-93

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 8 of 10 Pathway - S. C. Res W Garden Distance = 4.1 miles X/Q = 1.2E-07 sec/m' D/Q = 4.1E-10 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 3.8E+3 1.3E+3

2.4E+3 1.3E+3 1.9E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 9.4E+6 2.lE+4 1.2E+7 1.4E+4 1.1E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.2E+9 1.4E+6 2.2E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 5.6E+8 5.9E+5 6.3E+8 3.7E+5 5.8E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.1E+8 1.3E+6 8.9E+8 9.3E+5 8.5E+8 I

Co-60 4.5E+6 2.2E+10 7.1E+6 2.3E+10 8.7E+6 2.4E+10 6.0E+6 2.4E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.1E+10 2.4E+6 1.2E+10 1.4E+6 7.2E+9 Sr-90 4.lE+7 1.0E+8 1.3E+12 1.1E+8 7.7E+11 9.9E+7 5.8E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.0E+9 2.7E+6 1.3E+9 1.8E+6 1.2E+9 Nb-95 4.8E+5 1.4E+8 6.lE+5 3.8E+8 7.5E+5 4.9E+8 5.0E+5 4.5E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 4.4E+8 7.8E+5 5.6E+8 5.0E+5 4.9E+8 i

Te-129m 1.7E+6 2.0E+7 1.8E+6 2.4E+9 2.0E+6 1.4E+9 1.2E+6 9.7E+8 Cs-134 7.0E+5 6.8E+9 1.0E+6 3.lE+10 1.lE+6 2.2E+10 8.5E+5 1.6E+10 Cs-136 1.3E+5 1.5E+8 1.7E+5 2.4E+t 1.9E+5

.2.lE+8 1.5E+5 1.9E+8 I

Cs-137 6.1E+5 1.0E+10 9.lE+5 3.4E+10 8.5E+5 2.3E+10 6.2E+5 1.8E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 1.3E+8 2.0E+6 8.8E+7 1.3E+6 7.4E+7

(^)

Ce-141 5.2E+5 1.4E+7 5.4E+5 3.4E+8 6.1E+5 4.2E+8 3.6E+5 3.3E+8 l

i v

Ce-144 9.8E+6 7.0E+7 1.2E+7 9.3E+9 1.3E+7 1.2E+10 7.8E+6 9.0E+9 I -131 1.5E+7 1.7E+7 1.6E+7 4.1E+9 1.5E+7 2.1E+9 1.2E+7 1.4E+9 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6

)

I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.3E+9 1.2E+6 2.4E+9 8.6E+5 1.8E+9 I

Inhalation Pathway, units =

yr Food & Ground Pathway, units I*

V l

Ci/sec O

S023-0DCM 2-47 Revision 23 02-28-91

TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i

Page 9 of 10 O

rathwar - San Cie ente aanch (ao aesidents)

Distance - 2.2 iles X/Q - 3.3E-7 sec/m D/Q - 1.4E-9 m

Infant Child Teen Adult i

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E+3 2.4E+3 1.9E+3 Cr-51 4.8E+6 7.4E+6 6.7E+6 i

Mn-54 6.lE+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E+8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co-60 2.0E+9 3.0E+9 2.7E+9 Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8E+11 l

Zr-95 7.8E+8 1.lE+9 9.1E+8-i Nb-95 2. 4 E+8 3.5E+8 3.1E+8 l

Ru-103 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 i

Cs-134 2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 i

Cs-137 2.3E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7 i

O Ce-141 3.3E+8 4.1E+8 3.2E+8 i

Ce-144 9.2E+9 1.2E+10 9.0E+9 I -131 4.1E+9 2.lE+9 1.4E+9 1 -132 6.0E-36 2.6E-36 1.7E-36 1 -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 1.7E-37 1 -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9 i

i i

f Inhalation Pathway, units -

yr Food & Ground Pathway, units I"

pCi/sec I

O l

5023-00CM L

2-48 Revision 23 02-28-91

TABLE 2-8 i

D0SE PARAMETER R, FOR SECTOR Q Page 10 of 10 lhh Pathway - San Clemente Ranch Adm. Offices Distance = 2.5 miles X/Q = 2.7E-7 sec/m' D/Q = 1.1E-9 m

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.3E+02 1.9E+03 Cr-51 4.9E+03 8.3E+06 Mn-54 4.8E+05 1.3E+09 Co-57 1.3E+05 3.6E+08 Co-58 3.2E+05 6.0E+08 Co-60 2.0E+06 1.0E+10 Sr-89 4.8E+05 7.2E+09 Sr-90 3.4E+07 5.8E+11 Zr-95 6.1E+05 9.9E+08 Nb-95 1.7E+05 3.6E+08 Ru-103 1.7E+05 4.2E+08 Te-129m 4.0E+05 9.6E+08 Cs-134 2.9E+05 1.2E+10 Cs-136 5.0E+04 8.7E+07 Cs-137 2.1E+05 1.1E+10 Ba-140 4.4E+05 6.0E+07 O

Ce-141 1.2E+05 3.2E+08 Ce-144 2.7E+06 9.0E+09 I -131 4.lE+06 1.4E+09 I -132 3.9E+04 4.2E+05 I -133 7.4E+05 8.4E+05 1 -134 1.0E+04 1.5E+05 I -135 1.5E+05 8.6E+05 UN-ID 3.0E+05 1.3E+09 Inhalation Pathway, units = ""{"(!"

Food & Ground Pathway, units I*

{

Ci/

i O

S023-0DCM 2-49 Revision 26 12-20-93

TABLE 2-9 DOSE PARAMETER R, FOR SECTOR R Page 1 of 5 O

e ta > = s # o#erre aebiie ae es oiste#ce - 1.2 iies 3

X/Q = 5.3E-7 sec/m D/Q = 3.2E-9 m-r Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.lE+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E46 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9

2. 0E+6 1.4 E+9 1.4E+6 l'.4E+9 Co-57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3 E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.lE+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.lE+7 1.0E+8 1.lE+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1 E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.lE+8 5.0E+5 1.lE+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1 E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.lE+5 1.0E+10 9.lE+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.lE+7 2.0E+6 2.lE+7 1.3E+6 2.1E+7 O-Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.lE+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3 E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 l

I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units "C

Food & Ground Pathway, units I*

Ci/sec O

S023-0DCM 2-50 Revision 23 02-28-91

TABLE 2-9 DOSE PARAMETER R, FOR SECTOR R Page 2 of 5

(,/

Pathway - San Clemente Ranch (No Residents)

Distance = 2.3 miles 3

X/Q = 2.0E-7 sec/m D/Q - 1.0E-9 m'2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E+3 2.4E+3 1.9E+3 Cr-51 4.8E+6 7.4E+6 6.7E+6 Hn-54 6.1E+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E+8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co-60 2.0E+9 3.0E+9 2.7E+9 Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8E+11 Zr-95 7.8E+8 1.1E+9 9.1E+8 Nb-95 2.4E+8 3.5E+8 3.1E+8 Ru-103 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 Cs-134 2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137 2.3 E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7

/)

Ce-141 3.3E+8 4.1E+8 3.2E+8

\\-

Ce-144 9.2E+9 1.2E+10 9.0E+9 I -131 4.1E+9 2.1E+9 1.4E+9 I -132 6.0E-36 2.6E-36 1.7E-36 I -133 4.0E-11 1.7E-11 1.1E-11 1 -134 6.1E-37 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9 Inhalation Pathway, units

""**(7" Food & Ground Pathway, units I*

Ci/ ec C/

S023-0DCH 2-51 Revision 23 02-28-91

TABLE 2-9 DOSE PARAMETER R, FOR SECTOR R Page 3 of 5 I_V)

Pathway - SC Ranch Packing with Residents Distance = 2.6 miles

'R l

X/Q = 1.7E-07 sec/m D/Q = 8.2E-10 m'*

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.6E+2 1.9E+3 Cr-51 5.3E+3 8.5E+6 Mn-54 5.1E+5 1.3E+9 Co-57 1.4E+5 3.7E+8 Co-58 3.4E+5 6.1E+8 Co-60 2.2E+6 1.1E+10 Sr-89 5.1E+5 7.2E+9 Sr-90 3.6E+7 5.8E+11 Zr-95 6.5E+5 1.0E+9 Nb-95 1.9E+5 3.6E+8 E

Ru-103 1.9E+5 4.2E+8 Te-129m 4. 3 E+'o 9.6E+8 Cs-134 3.1E+5 1.2E+10 Cs-136 5.4E+4 9.1E+7 Cs-137 2.3E+5 1.2E+10 Ba-140 4.7E+5 6.1E+7 (m'-) Ce-141 1.3E+5 3.2E+8 Ce-144 2.9E+6 9.0E+9 I -131 4.4E+6 1.4E+9 I -132 4.2E+4 4.6E+5 I -133 7.9E+5 9.0E+5 I -134 1.IE+4 1.7E+5 I -135 1.6E+5 9.3E+5 l

UN-ID 3.2E+5 1.3E+9 l

Inhalation Pathway, units -

7" Food & Ground Pathway, units I"

rem /vr)

Ci O

S023-0DCM 2-52 Revision 27 12-21-94

TABLE 2-9 DOSE PARANETER R FOR SECTOR R i

Page 4 of 5 O

Pathway = Sheep Meat / Shepherd Distance = 0.9 miles X/Q = 8.3E-7 sec/m D/Q = 5.2E-9 m'*

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 1 -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units =

7" Food & Ground Pathway, units 5 I ""'m/vri

$js O

S023-0DCM 2-53 Revision 26 12-20-93

TABLE 2-9 DOSE PARAMETER R FOR SECTOR R Page 5 of 5 O

V Pathway =DeerConsumep/ Hunter Distance - 2.2 miles X/Q = 1.8E-7 sec/m D/Q = 8.8E-10 m-Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 O

Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units - ]j"(Y" Food & Ground Pathway, units I" IImrem/vr) pC O

S023-0DCM 2-54 Revision 26 12-20-93

TABLE 2-10 DOSE PARAhETER R FOR SECTOR A i

Page 1 of 3 Pathway = Camp San Mateo Distance = 3.6 miles i

3 X/Q = 7.1E-8 sec/m D/Q = 4.lE-10 m-r Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway f

il -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 7r-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.lE+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.lE+7 O

Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2f+7 1.7E+7 i

I -132 1.lE+5

1. 2 E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 i

I -135 4.5E+5 2.5E+6 UN-ID -0 8.6E+5

7. 5 E+8 l

I Inhalation Pathway, units =

ff?"

Food & Ground Pathway, units = I" IImrem/vr)

C O

S023-0DCM 2-55 Revision 23 02-28-91

l IABLE 2-10 DOSE PARAMETER R, FOR SECTOR A l

Page 2 of 3

()

Pathway = Sheep (Meat){ Shepherd Distance = 0.2 miles X/Q = 6.7E-6 sec/a D/Q = 5.2E-8 ni 8

Infant Child Teen Adult Inhala-Food &

Inhala-food &

Inhala-Food &

I Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway I

r 11 -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.lE+3 2.0E+3 1.9E+6 l

Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6F+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+3 4.3E+3 7.0E+3 1.2E+5 O

Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 so-3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 1 -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 i

r i

Inhalation Pathway, units = "C Food & Ground Pathway, units I*

C / ec

(::)

S023-0DCM 2-56 Revision 26 12-20-93

TABLE 2-10 DOSE PARAMETER R FOR SECTOR A i

Page 3 of 3 Pathway-DeerConsumep/ Hunter Distance = 2.2 miles X/Q = 1.9E-7 sec/m D/Q = 1.4E-9 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

l Radio-tion Ground tion Ground tion Ground tion Ground i

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway t

H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 l

Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 i

Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 j

Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 i

Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 i

Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6

/O Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 U

Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 i

I -135 1.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = "C Food & Ground Pathway, units I"

f Ci/sec O

i S023-0DCM

[

2-57 Revision 26 t

12-20-93 i

r

~m

TABLE 2-11 DOSE PARAMETER R, FOR SECTOR B Page 1 of 3 Pathway-Sheep (Meat)gShepherd Distance = 0.2 miles i

X/Q = 6.lE-6 sec/m '

D/Q = 5.3E-8 m-Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway.

Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.lE+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 i

Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 l

Cs-136 5.1E+3 4.3E+3 8.lE+2 8.3E+5 l

Cs-137 1.3 E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+3 4.3E+3 7.0E+3 1.2E+5 i

D Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 d

Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I

1 -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 I

Inhalation Pathway, units =

j(yr m

Food & Ground Pathway, units = I" C /sec O

S023-0DCM 2-58 Revision 26 i

12-20-93

TABLE 2-11 DOSE PARAMETER R, FOR SECTOR B Page 2 of 3

\\

Pathway - Deer Consumer / Hunter Distance - 1.1 miles X/Q = 3.4E-7 sec/m' D/Q = 2.4E-9 m'2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E44 4.7E+7 Co-60 3.6E+7 7.2E+7

1. 6 E+ 5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4. 5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 q

Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 L)

Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5

5. 9E+ 8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units -

yr Food & Ground Pathway, units I"

C sec O

S023-0DCM 2-59 Revision 26 12-20-93

I TABLE 2-11 DOSE PARAMETER R FOR SECTOR B Page 3 of 3

()

Pathway = Sanitary Landfill Distance = 2.1 miles 3

X/Q = 1.4E-7 sec/m D/Q = 1.2E-9 m-r Infant Child Teen Adult Inhala-food &

Inhala-Food &

Inhala ' Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.lE+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 -C-1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 O

Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E46 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 Inhalation Pathway, units = ""'*(!"

Food & Ground Pathway, units I*

"I g$j3, O

S023-0DCM 2-60 Revision 23 02-28-91

1 TABLE 2-12 DOSE PARAMETER R FOR SECTOR C i

Page 1 of 5 O

eathwar - Ca > sae Onofre Distance - 2.e iies 3

X/Q = 9.22-8 sec/m D/Q - 8.4E-10 m'8 Infant Child Teen Adult 1

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 C0-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 i

Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.lE+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.lE+7 O

Ce-141 3.6E+5 1.4E+7 Co-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.lE+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units -

C/

Food & Ground Pathway, units I"

Ci/sec O

S023-0DCM 2-61 Revision 23 02-28-91 i

7-TABLE 2_12 DOSE PARAMETER R, FOR SECTOR C

'Page 2 of 5 Pathway =CampSanOnofreFr.Stn Distance = 2.3 miles X/Q = 1.1E-7 sec/m D/Q = 1.1E-9 m-2 Infant Child Teen Adult i

Inhala-Food &

Inhal a-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.2E+2 Cr-51 5.9E+3 1.9E+6 Mn-54 5.8E+5 5.7E+8 Co-57 1.5E+5 1.4E+8 Co-58 3.8E+5 1.6E+8 Co-60 2.5E+6 8.8E+9 Sr-89 5.8E+5 8.9E+3 Sr-90 4.1E+7 Zr-95 7.3E+5 1.0E+8 Nb-95 2.1E+5 5.6E+7 Ru-103 2.1E+5 4.5E+7 i

Te-129m 4.8E+5 8.1E+6 Cs-134 3.5E+5 2.8E+9 Cs-136 6.0E+4 6.2E+7 Cs-337 2.6E+5 4.2E+9 t

Ba-1'O 5.2E+5 8.4E+6 O

Ce-141 1.5E+5 5.6E+6 Ce-144 3.2E+6 2.9E+7 I -131 4.9E+6 7.1E+6 I -132 4.7E+4 5.1E+5 1

I -133 8.8E+5 1.0E+6 I -134 1.2E+4 1.8E+5 1 -135 1.8E+5 1.0E+6 I

UN-ID 3.6E+5 3.1E+8 Inhalation Pathway, units =

?"

Food & Ground Pathway, units I*

Ci/sec i

O S023-0DCM I

2-62 Revision 23 02-28-91 i

TABLE 2-12 DOSE PARAMETER R, FOR SECTOR C ci Page 3 of 5 4V Pathway - Sewage Facility Distance - 2.2 miles X/Q - 1.3E-7 sec/m' D/Q - 1.2E-9 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5

4. 5 E+6 Cs-134 1.9E+5 1.6E+9 Cs-336 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140 2.oE+5 4.7E+6 O

Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 Inhalation Pathway, units = "C /

r Food & Ground Pathway, units I* IImrem/vr)

C O

S023-0DCM 2-63 Revision 23 02-28-91

TABLE 2-12 DOSE PARAMETER R FOR SECTOR C l

i Page 4 of 5 V

Pathway-Sheep (Meat)fshepherd Distance = 0.2 miles X/Q = 6.5E-6 sec/m D/Q = 6.1E-8 m'8 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 ?.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 i

Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-5.1E+3 4.3E+3 7.0E+3 1.2E+5 O

ce 140 242

-o-

-o-2 st+3

-o-2 4t+3 2 ot+3 7 9t+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 1 -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 1 -132 6.3E+2 6.8E+3 1 -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 1 -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units -

yr Food & Ground Pathway, units I"

" rem /vr)

Ci O

S023-0DCM 2-64 Revision 26 12-20-93

TABLE 2-12 DOSE PARAMETER R FOR SECTOR C i

Page 5 of 5 l

Pathway-DeerConsumep/ Hunter Distance = 1.0 miles X/Q = 3.4E-7 sec/m D/Q = 5.1E-9 m-2

{

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 C0-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 i

Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 0- 5.0E+6 4.2E+6 3.5E+4 7.4E+6

]

Ce-141 1.5E+6 2.4E+6 9.9E+3

.2E+6 L

Ce-144 -0

. 1.8E+7 2.9E+7 2.lE+5 4 9E+7 l

I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 8.2E+2 1.2E+4 1 -135 1.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 I

i Inhalation Pathway, units -

7" Food & Ground Pathway, units = I" Ci/sec 0

S023-0DCM 2-65 Revision 26 12-20-93

TABLE 2-13 l

DOSE PARAMETER R, FOR SECTOR D Page 1 of 3 Pathway - Camp San Onofre Distance = 2.8 miles 3

X/Q = 6.6E-8 sec/m D/Q = 6.4E-10 m.2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

i Radio-tion' Ground tion Ground tion Ground tion Ground

{

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 l Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1* +7 O

Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.lE+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units =

jhr m

Food & Ground Pathway, units I*

Ci/sec O

S023-0DCM 2-66 Revision 23 02-28-91

TABLE 2-13 DOSE PARAMETER R, FOR SECTOR D Page 2 of 3 Pathway-Sheep (Meat)gShepherd Distance = 0.2 miles X/Q = 6.3E-6 sec/m D/Q = 6.6E-8 m'2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 i

Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 O

ce-142

-o-

-o-2 se+3

-o-2 4E+3 2 oc+3 7 $c+4 1

Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 1 -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 i

I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 l

1 -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 i

I i

Inhalation Pathway, units = "C Food & Ground Pathway, units =

~

C /sec O

S023-0DCM 2-67 Fevision 26 12-20-93

TABLE 2-13 DOSE PARAMETER R FOR SECTOR D i

Page 3 of 3 Pathway - Deer Consumer / Hunter

' Distance - 1.0 miles X/Q - 3.3E-7 sec/m D/Q - 3.3E-9 m-'

4 i

Infant Child Teen Adult Inhala-Food &

Inhal t-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i

H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 l

Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4 E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 i

Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 O

Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 1 -135 1.lE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units =

myr j

Food & Ground Pathway, units I*

Ci/sec O

S023-0DCM i

2-68 Revision 26 12-20-93

TABLE 2-14 i

DOSE PARAMETER R FOR SECTOR E i

Page 1 of 3 Pathway - Camp Horno Distance - 4.0 miles 3

X/Q = 6.6E-8 sec/m D/Q = 6.4E-10 m-2 j

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 [

Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 l

Sr-89 1.4E+6 2.2E+4 i

Sr-90 9.9E+7 i Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.lE+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 i

Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.lE+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.lE+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 l

1 -135 4.5E+5 2.5E+6 l

UN-ID 8.6E+5 7.5E+8 r

i i

Inhalation Pathway, units =

[I Food & Ground Pathway, units I"

Ci/sec i

0 5023-0DCM l

2-69 Revision 23 02-28-91 I

TABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 2 of 3

~

Pathway-Sheep (Meat)gShepherd Distance - 0.3 miles X/Q - 4.5E-6 sec/m D/Q - 5.9E-8 m-2 Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.lE+0 Cr-51 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.lE+6 Co-60 ?.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 5.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4t+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+3 4.3E+3 7.0E+3 1.2E+5

,C Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3 E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.lE+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units =

j(Y" Food & Ground Pathway, units b* }tmrem/vr)

C O

S023-0DCM 2-70 Revision 26 12-20-93

TABLE 2-14 DOSE PARAMETER R FOR SECTOR E i

Page 3 of 3 7.s k,)

Pathway - Deer Consumer / Hunter Distance = 1.2 miles 3

X/Q = 3.7E-7 sec/m D/Q = 8.3E-9 m'*

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 7-ss

( )

Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 1 -133 1.6E+1 8.60^0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 1 -135 1.IE-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 i

Inhalation Pathway, units mr m yr p

food & Ground Pathway, units I*

Ci/ ec G

.Y S023-0DCM 2-71 Revision 26 12-20-93 l

f TABLE 2-15 DOSE PARAMETER R, FOR SECTOR F Page 1 of 4 Pathway - San Onofre State Park / Guard Shack Distance - 0.8 miles 3

X/Q - 8.6E-7 sec/m D/Q = 7.5E-9 m-'

l Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground i

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i

H -3 2.2E+2 '

Cr-51. 2.5E+3 8.0E+5 l

Mn-54 2.4E+5 2.4E+8 Co-57 6.3E+4 5.9E+7 Co-58 1.6E+5 6.5E+7 Co-60 1.0E+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 i

Sr-90 1.7E+7 !

Zr-95 3.0E+5 4.3E+7 i

Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m 2.0E+5 3.4E+6 Cs-134 1.5E+5 1.2E+9 Cs-136 2.5E+4 2.6E+7 Cs-137 1.1E+5 1.8E+9 Ba-140 2.2E+5 3.5E+6 O

Ce-141 6.2E+4 2.3E+6 Ce-144 1.3E+6 1.2E+7 I -131 2.0E+6 2.9E+6 I -132 2.0E+4 2.1E+5 l

1 -133 3.7E+5 4.2E+5 t

I -134 5.1E+3 7.7E+4 I -135 7.7E+4 4.3 E+5 UN-ID 1.5E+5 1.3E+8 t

i i

i L

r Inhalation Pathway, units =

Food & Ground Pathway, units I*

I pCi/sec O

S023-0DCM 2-72 Revision 25 02-28-92

TABLE 2-15 DOSE PARAMETER R, FOR SECTOR F Page 2 of 4 AV Pathway - Border Patrol Checkpt.

Distance = 1.8 miles X/Q = 2.4E-7 sec/m' D/Q = 1.8E-9 m' Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.6E+2 !

Cr-51 4.lE+3 1.3E+6 Hn-54 4.0E+5 3.9E+8 Co-57 1.1E+5 9.8E+7 Co-58 2.6E+5 1.1E+8 Co-60 1.7E+6 6.lE+9 Sr-89 4.0E+5 6.2E+3 Sr-90 2.8E+7 Zr-95 5.0E+5 7.2E+7 Nb-95 1.4E+5 3.9E+7 j

Ru-103 1.4E+5 3.1E+7 Te-129m 3.3E+5 5.6E+6 Cs-134 2.4E+5 1.9E+9 Cs-136 4.2E+4 4.3E+7 Cs-137 1.8E+5 2.9E+9 Ba-140 3.6E+5 5.9E+6 O

Ce-141 1.0E+5 3.9E+6 Ce-144 2.2E+6 2.0E+7 1 -131 3.4E+6 4.9E+6 I -132 3.3 E+4 3.5E+5 I -133 6.1 E+5 7.0E+5 1 -134 8.5E+3 1.3E+5 I -135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 l

Inhalation Pathway, units = "C /

Food & Ground Pathway, units - (m )(mrem /vr) pCi/sec O

S023-0DCM 2-73 Revision 23 02-28-91

TABLE 2-15 DOSE PARAMETER R FOR SECTOR F i

Page 3 of 4 (O

Pathway-Sheep (Meat){ Shepherd Distance - 0.5 miles j

X/Q = 1.9E-6 sec/m D/Q = 1.7E-8 ng:

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhal a-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr,89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.0E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.dE+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5

()

Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4

\\--

Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units "C

Food & Ground Pathway, units I*

C/e O

S023-0DCM 2-74 Revision 26 12-20-93

TABLE 2-15 t

DOSE PARAMETER R, FOR SECTOR F Page 4 of 4 Pathway =DeerConsumep/ Hunter Dista:.ce = 1.4 miles X/Q = 3.0E-7 sec/m D/Q = 2.3E-9 m-2 Infant Child Teen Adult i

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway j

t H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 i

Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 j

Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+S 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 i

Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 O-Ce-141 1.5E+6 2.4 E+ 6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4

)

I -134 8.2E+2 1.2E+4 i

I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 4

Inhalation Pathway, units = % 7" Food & Ground Pathway, units = I*

C s >c O

S023-0DCM l

2-75 Revision 26 12-20-93

TABLE 2-16 DOSE PARAMETER R FOR SECTOR G i

Page 1 of 4 (j

Pathway - San Onofre State Beach Campground Distance = 0.8 miles

~

X/Q = 7.7E-7 sec/m D/Q = 3.9E-9 m.2 3

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+1 1.4E+2 1.6E+2 2.9E+2 Cr-51 1.6E+3 5.7E45 2.lE+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.lE+6 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.lE+5 8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.lE+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 3.2E+5 4.9E+3 Sr-90 5.0E+6 1.2E+7 1.3E+7 2.3E+7 Zr-95

2. 2 E+ 5 3.lE+7 2.8E+5 3.lE+7 3.3E+5 3.lE+7 4.0E+5 5.7E+7 Nb-95 5.9E+4 1.y+7 7

7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.lE+7 Ru-103 6.8E+4 1.3E+

8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 Te-129m 2.lE+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 Cs-134 8.7E+4 8.4 E+8 1.3E+5 8.4E+8 1.4E+5

8. 4 E+ 8 1.9E+5 1.6E+9 Cs-136 1.7E+4 1.9E+7 2.lE+4 1.9E+7 2.4E+4 1.9E+7 3.3E+4 3.4E+7 Cs-137

7. 5E+ 4 1.3E+9 1.lE+5 1.3E+9 1.0E+5 1.3E+9 1.4E+5 2.3E+9 Ba-140 2.0E+5 2.5E+6 2.lE+5 2.5E+6

2. 5E+ 5 2.5E+6 2.9E+5 4.7E+6 O

Ce-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7E+6 8.3E+4 3.1E+6 V

Ce-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 1.8E+6 1.6E+7 I -131 1.8E+6 2.lE+6 2.0E46 2.lE+6 1.8E+6 2.1 E+ 6 2.7E+6 3.9E+6 I -132 2.lE+4 1.5E45 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 I -133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 4.9E+5 5.6E+5 I -134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 6.8E+3 1.0E+5 I -135 8.6E+4 3.lE+5 9.8E+4 3.lE+5 7.7E+4 3.1E+5 1.0E+5 5.8E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 Inhalation Pathway, units = "C /

Food & Ground Pathway, units l*

Ci/ ec O

S023-0DCM 2-76 Revision 25 02-28-92

l TABLE 2-16 D0SE PARAMETER R, FOR SECTOR G Page 2 of 4 Pathway - Hwy Patrol Weigh Station Distance = 2.0 miles X/Q = 2.0E-7 sec/m' D/Q = 8.5E-10 m-r Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala ! ood &

Inhal a-Food &

F Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - 0 -- 2.7E+2 Cr-51 3.lE+3 1.0E+6 Mn-54 3.0E+5 3.0E+8 Co-57 7.9E+4 7.4E+7 Co-58 2.0E+5 8.1E+7 Co-60 1.3E+6 4.6E+9 Sr-89 3.0E+5 4.6E+3 Sr-90 2.1E+7 ;

Zr-95 3.8E+5 5.4E+7 Nb-95 1.lE+5 2.9E+7 g

Ru-103 1.]E+5 2.3E+7 Te-129m 2.5E+5 4.2E+6 Cs-134 1.8E+5 1.5E+9 i

Cs-136 3.1E+4 3.2E+7 Cs-137 1.3E+5 2.2E+9 Ba-140 2.7E+5 4.4E+6 O

Ce-141 7.8E+4 2.9E+6 V

Ce-144 1.7E+6 1.5E+7 1 -131 2.6E+6 3.7E+6 1 -132 2.5E+4 2.7E+5 I -133 4.6E+5 5.3E+5 I -134 6.4E+3 9.7E+4 I -135 9.6E+4 5.4 E+5 UN-ID 1.9E+5 1.6E+8 Inhalation Pathway, units =

?"

Food & Ground Pathway, units = I" Ci/sje O

S023-0DCM 2-77 Revision 27 L

12-21-94

TABLE 2-16 D0SE PARAMETER R, FOR SECTOR G Page 3 of 4 O

e18wv-sheep <aet><saePaero Dist :e - 2.7 iies I

X/Q - 1.2E-7 sec/m D/Q - 4.8E-10 m

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

P.adio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.lE+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.lE+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 k

Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+ 5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.lE+5 9.5E+4 4.8E+3 4.2E+6 InhalationPathway, units =]j"(7" Food & Ground Pathway, units I*

g$fsec O

S023-0DCM 2-78 Revision 26 12-20-93

TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G

)

Page 4 of 4 Pathway =DeerConsumep/ Hunter Distance = 3.3 miles X/Q = 8.8E-8 sec/m D/Q = 3.2E-10 m-2 j

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E45 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.lE+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 5

Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 O

Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = "Ch "

Food & Ground Pathway, units I*

Ci/sec O

S023-0DCM 2-79 Revision 26 12-20-93

2.9' TOTAL DOSE CALCULATIONS i

2.9.1 Total Dose to Most Likely Member of the Public

(

' The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet t

the dose limitations of 40 CFR 190 per twelve consecutive months.

The transportation of radioactive material is excluded from the dose calculations.

1 The Annual Total Dose is determined monthly for maximum organ (gas

& liquid), whole body (gas & liquid) and thyroid (gas & liquid) to 7

verify that the Site total (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.

.1 Annual Total Oroan Dose (Dro7 (0))

( - 0) 12 2/3 O (0G)+ D (0L)+ Dj (OG)

D,7 (0) = E E

i f

f 7

l=1 j =1 where:

NOTE: 0 (0G) = 0 for bone

- All to be summed over the most recent 12 months.

i (2-21) n Dp (0G) = K ECER W,

3 g a i =1 i = each isotope in specific organ category i

j = Units 1, 2 and 3 1 = months 1 - 12**

year-@

K = 3.1688 E-2 sec-Ci O

S023-0DCM 2-80 Revision 21 02-15-90

2,9 ' TOTAL DOSE CALCULATIONS (Continued) i 2.9.1 Total Dose to Most Likely Member of the Public (Continued) number of isotopes in the specified organ category n

=

C, total particulate gas curies released for the month S;

=

ER,uW, controlling location factors from ODCM Table 2-5,

=

k Unit I and Table 2-6, Units 2/3, for all pathways k.

D (OL) ji liquid organ dose for the specified organ in mrem for

=

the month.

[ Reference ODCM Units 2/3 (1-19), Unit I (1-13)]

h D (0G)* = gas organ dose form tritium in mrem for the month.

3i

[ Reference ODCM Unit 1 (2-14), ODCM Units 2/3 (2-18)]

.2 Annual Total Whole Body Dose Dm1W31 12 2/3

~

D (WBL)+ D[(0G) + 0.9 D ) (y) 4(DIRECT)

Dm(WB) = I E

33 3

l=1 j =1 where:

j= Units 1, 2 and 3 1=

months 1 - 12, to be summed over the most recent l

12 months i

,QV D (WBL) ji liquid whole body organ dose in mrem for the whole

=

month.

[ Reference ODCM Units 2/3 (1-19), ODCM Unit 1 (1-13)]

u3 Dyi(0G) gas organ dose from tritium in mrem for the month.

=

[ Refer ODCM Units 2/3 (2-18), ODCM Unit 1 (2-14)]

D (y) p gamma air dose in mrad for the month.

=

0.9 converts mrad to mrem.

[ Reference ODCM Units 2/3 (2-14), ODCM Unit 1 (2-10)]

(2-23) n 4

E D(bkgd),

D (Direct) = E max [D(beach),]

p=1

.0342 q=1 p = for all TLDs per quarter q = for Quarters 1-4 O

l l

S023-0DCM 2-81 Revision 26 12-20-93 t

2.9_ TOTAL DOSE CALCULATIONS (C ntinued) 2.9.1.2 Annual Total Whole Body Dose D7ar$fil (Continued) p.

D'

Direct Radiation l

The direct radiation levels are evaluated most recently using cadmium covered TLDs. The TLDs are placed at 47 locations around the site. The average dose measured by TLDs 5 to 50 miles from the site is used as background. These sites are subject to change.

The background is subtracted from the highest reading plant surrounding area TLD. This value is the direct dose but must be i

prorated by'the occupancy factor.

l Example: Beach time (west boundary, seawall) of 300 hrs /yr, east and north boundaries of 20 hrs /yr, or 8 hrs /yr for the south boundary and west fence of parking lot 1 (top of bluff).

]

O aerere#ce:

e a. ce184# ae or #a# rer riie. occ=9 #cv rectors t San Onofre Owner Controlled Area Boundaries," dated l

October 1, 1991.

.3 Annual Total Thyroid Dose D (T) 7e7

(~

}

12 2/3 j

D737(T) = E E

Dg (0G) + Df(0L) l=1 j =1 where:

i j=

Units 1, 2 and 3 1=

months 1 - 12, to be summed over the most recent 12 months thyroid organ dose from gaseous iodine for the month Dp (0G)

=

in mrem.

(from 2-21) liquid thyroid organ dose for the month in mrem.

Dp (0L)

=

[ Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)]

S023-0DCM 2-82 Revision 26 12-20-93 i

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:

1.

Determine the monthly total body and organ doses resulting from releases during the previous twelve months.

I P

2.

Projected dose - Previous 12 months' dose divided by 12 j

for the total body and each organ.

3.2 Gaseous Dose Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:

O l

1.

Determine the monthly gamma, beta and organ dose resulting j

from releases during the previous twelve months.

I 2.

Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.

1 0

S023-0DCM 3-1 Revision 22 08-02-90

4.0 EQUIPMENT 4.1 RADI0 ACTIVE LIOUID EF MJENT MONITORING INSTRUMENTATION f)

SPECIFICATION v

4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 1.4.

APPLICABILITY: At all times ACTIOh-a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint les:,

conservative than required by the above specification, immediately suspend the release of radioactive liquid efflurr's monitored by the affected channel or declare the chanui, operable.

I b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain p

inoperable for greater than 30 days, explain in the next Q

Annual Radioactive Effluent Release Report why the ine w ability was not corrected in a timely manner.

c.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.

SURVEILLANCE RE0VIREMENTS

.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.

.2 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

O S023-0DCM 4-1 Revision 26 12-20-93

LE 4-1 BaDI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM l

CHANNELS INSTRUMENT

OPERABLE ACTION 1

1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM l

TERMINATION OF RELEASE I

a.

Liquid Radwaste Effluent Line - 2/3 RT-7813 1

28 b.

Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 1

29 c.

Turbine Plant Sumps, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line-2(3)RT-7821 1

30 d.

Steam Generator (E088) Blowdown Effluent Line - 2(3)RT6759 1

29 e.

Steam Generator (E089) Blowdown Effluent Line - 2(3)RT6753 1

29 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

31 b.

Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line 1

31 c.

Steam Generator (E088) Blowdown Bypass Effluent Line 1

31 d.

Steat.; Generator (E089) Blowdown Bypass Effluent Line 1

31 S023-00CM 4-2 Revision 25 02-28-92

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

w e+.

m

)

TABLE 4-1 (Continued)

TABLE NOTATION Monitor Recorders are not required for the Operability of the monitor, O

providing the inoperable recorder does not cause the monitor to become U

inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance

{

requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable, j

ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may l

continue provided that prior to initiating a release:

1 a.

At least two independent samples are analyzed in accordance with Specification 1.1.1 and i

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving-t Otherwise, suspend release of radioactive effluents via this pathway.

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 a limit of detection of at least l

10-7 microcuries/ gram:

l a.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131-t b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 i

microcuries/ gram DOSE EQUIVALENT I-131; or c.

Lock closed valve HV-3773 and divert flow to T-064 for processing as liquid radwaste.

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 that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a limit i

of detection of at least 10-7 microcuries/mi or lock closed valve S2(3)2419MUO77 or S2(3)2419MUO78 and divert flow to the radwaste i

sump for processing as liquid radwaste.

ACTION 31 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this i

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 curves may be used i

to estimate flow.

j O

S023-0DCM 4-3 Revision 22 08-02-90

ABLE 4-2 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL-CHANNEL SOURCE CHANNELS FUNCTIONAL ~-

INSTRUMENT **

CHECK CHECK CALIBRATION TEST 1.

GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluents Line -

2/3 RT-7813 D

P R(2)

Q(1) b.

Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 D M

R(2)

Q(1) c.

Tu bine Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line - 2(3)RT-7821 D

M R(2)

Q(1) d.

Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 D

M R(2)

Q(1) e.

Steam Generator (E089) Blowdown Bypass Line - 2(3)RT6753 D

M R(2)

Q(1)

I 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(3)

N.A R

Q b.

Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line D(3)

N.A R

Q l

c.

Steam Generator (E088) Blowdown Bypass Effluent Line D(3)

N.A R

Q d.

Steam Generator (E089) Blowdown Bypass Effluent Line D(3)

N.A R

Q l

S023-0DCM 4-4 Revision 22 08-02-90

TABLE 4-2 (Continued)

TABLE NOTATION Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, i

alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(I) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure and Control Room alarm annunciation if any of the following conditions exist:*

I.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

t 3.

Instrument indicates a downscale failure.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.

These standards i

shall permit calibrating the system over its intended range of energy and l

measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

[

O (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

i

If the instrument controls are not in the operate mode, procedures shall require I

that the channel be declared inopec* ole.

i

[

O S023-0DCM 4-5 Revision 22 08-02-90 i

4.0 EQUIPMENT 4.2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

' SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined in accordance with ODCM.

APPLICABILITY: At all times ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-3.

Exert best efforts to 1

return the instrument to OPERABLE status within 30 days i

and, additionally, if the inoperable instrument (s) remain l

inoperable for greater than 30 days, explain in the next i

O Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

With less than the minimum number of radioactive gaseous i

effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken l

or the necessary surveillances not performed _at the specified frequency prescribed in Table 4-4~, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective i

actions to be taken to preclude recurrence of the event.

SB VElllANCE RE0VIREMENTS

.1 Each radioactive gaseous effluent monitoring instrumentation I

channel shall be demonstrated OPERABLE by performance of the l

CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.

i O

S023-0DCM 4-6 Revision 26 12-20-93

-m.

W

(

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION MINIMVM CHANNELS INSTRUMENT ***

OPERABLE APPLICABILITY ACTION 1.

WASTE GAS HOLDUP SYSTEM a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

1 35 2/3 RT-7808, or 3 RT-7865-1 b.

Process Flow Rate Monitoring Device 1

36 2.

CONDENSER EVACUATION SYSTEM a.

Noble Gas Activity Monitor - 2(3)RT-7818 or 2(3)RT-7870-1 1

37 b.

Iodine Sampler 1(4) 40 g

c.

Particulate Sampler 1(4) 40 d.

Associated Sample Flow Measuring Device 1

36 e.

Process Flow Rate Monitoring Device 1(1) 36 3.

PLANT VENT STACK a.

Noble Gas Activity Monitor - 2/3 RT-7808, or 2RT-7865-1 1(3) 37 and 3RT-7865-1 b.

Iodine Sampler 1(3)(4) 40 g

c.

Particulate Sampler 1(3)(4) 40 d.

Associated Sample Flow Measuring Device 1(3) 36 e.

Process Flow Rate Monitoring Device 2(2) 36 4.

CONTAINMENT PURGE SYSTEM a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1

38 b.

Iodine Sampler 1

40 c.

Particulate Sampler 1

40 d.

Process Flow Rate Monitoring Device 1

36 e.

Associated Sample Flow Measuring Device 1

36 S023-0DCM 4-7 Revision 27 12-21-94

r~

(s G

TABLE 4-3 (Continuedl RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT ***

OPERABLE APPLICABILITY ACTION 5.

SOUTH YARD FACILITY (SYF) WORV, AREA l

a.

Particulate Activity Monitor (RU-7904) 1 40 b.

Iodine Sampler 1

40 c.

Particulate Sampler 1

40 d.

Associated Sample Flow Measuring Device 1

36 e.

Process Flow Rate Monitoring Device 1

36 6.

SYF DECONTAMINATION AREA a.

Particulate Activity Monitor (RU-7905)

I 40 b.

Iodine Sampler 1

40 c.

Particulate Sampler 1

40 d.

Associated Sample Flow Measuring Device 1

36 e.

Process Flow Rate Monitoring Device 1

36 S023-0DCM 4-8 Revision 27 12-21-94

t' TABLE 4-3 (Continued)

TABLE NOTATION

At all times.

MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become j

inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) 2(3)RT-7818 is not equipped to monitor process flow.

If another means of continuously monitoring process flow is not avaihble, then comply with ACTION 36.

(2) 2/3RT-7808 is not equipped to monitor process flow.

If 2RT-7865 and 3RT-7865 are not available to continuously monitor plant vent stack flow, then comply with ACTION 36.

(3)

Due to unequal mixing in the Plant Vent Stack, both 2RT-7865 and 3RT-7865 are required to be operable when 2/3RT-7808 is inoperable.

i (4) hth only one channel operable, channel may be sampled so long as the time tiat the channel is shut down is one hour or less. Ref: Memorandum for R

File, " Units 2/3 - Clarification No.14", by G. T. Gibson, dated Os June 30, 1983.

ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

At least two independent samples of the tank's contents a.

are analyzed, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the ACTION 36 -

Minimum Channels OPE.RABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .. System design characteristics may be used to estimate flow.

S023-0DCM Revision 27 4-9 12-21-94

TABLE 4-3 (Continued)

TABLE NOTATION O

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 grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 40 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.

4 t

O S023-0DCM 4 - 10 Revision 26 12-20-93

)

ABLE 4-4 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE:

INSTRUMENT ***

CHECK CHECK CALIBRATION TEST IS REQUIRED 1.

WASTE GAS HOLDUP SYSTEM a.

Noble ' t Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2/3 RT-7808, 3RT-7865-1 P

P R(3) q(1) b.

Process Flow Rate Monitoring Device P

N.A R

Q 2.

CONDENSER EVACUATION SYSTEM a.

Noble Gas Activity Monitor -

2(3)RT-7818,2(3)RT-7870-1 D

M R(3)

Q(2) b.

Iodine Sampler W

N.A N.A N.A c.

Particulate Sampler W

N.A N.A N.A d.

Associated Sample Flow Measuring Device D

N.A R

Q e.

Process Flow Rate Monitoring Device (2(3)RT-7870-1)

D N.A R

Q 4

i S023-0DCM 4 -'11 Revision 26 12-20-93

... - =....... -

o TABLE,-4 o.

(Continued)-

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL

' MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT ***

CHECK CHECK CALIBRATION TEST IS REQUIRED 3.

PLANT VENT STACK a.

Noble Gas Activity Monitor -

D M

R(3)

Q(2) 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1 b.

Iodine Sampler W

N.A N.A N.A c.

Particulate Sampler W

N.A N.A N.A d.

Associated Sample Flow Measuring Device D

N.A R

Q e.

Process Flow Rate Monitoring Device D

N.A R

Q 4.

CONTAINMENT PURGE SYSTEM a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2(3)RT-7828,2(3)RT-7865-1 0

P(4)

R(3)

Q(1) b.

Iodine Sampler W-N.A N.A N.A c.

Particulate Sampler W

N.A' N.A N.A d.

Process Flow Rate Monitoring Device-D N.A R

Q 4

e.

Associated Sample Flow Measuring Device D

N.A R

Q 4

3 S023-0DCM t

4-12 Revision 22 08-02-90

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w.

w w.

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_s TABLET-4 (Continu;d)

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT ***

CHECK CHECK CALIBRATION TEST IS REOUIRED 5.

SOUTH YARD FACILITY (SYF) WORK AREA Particulate Activity Monitor (RU-7904) Exact instrumentation and requirements will be added subsequent to a.

final DCP A-7022.00SC turnover.

b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W

N.A.

d.

Process Flow Rate Monitoring Device D(5)

N.A.

R Q

[4 e.

Associated Sample Flow Measuring Device D(5)

N.A.

R Q

6.

SYF DECONTAMINATION AREA Particulate Activity Monitor (RU-7905) Exact instrumentation and requirements will be added subsequent to a.

final DCP A-7022.00SC turnover.

b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W

N.A.

d.

Process Flow Rate Monitoring Device D(5)

N.A.

R Q

e.

Associated Sample Flow Measuring Device D(5)

N.A.

R Q

NOTE:

For 5 and 6, surveillance requirements to take effect upon DCP A-7022.00SC turnover of these instruments.

S023-0DCM 4-13 Revision 27 12-21-94

TABLE 4-4 (Continued)

TABLE NOTATION

/7

At all times.

V Modes 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if, applicable), the loss of the i

recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure and control room alarm annunciation if any of the following conditions exist:#

I.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

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 exist:#

1.

Instrumen#t indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

O (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) Prior to each release and at least once per month.

(5) Daily checks only required during times of building occupation.

A!

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

O S023-0DCM 4-14 Revision 27 12-21-94

.~.

-i 4.3 OPERABILITY OF RADI0 ACTIVE WASTE EQUIPMENT i

The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown 1

in Figures 4-5 thru 4-7.

l i

i i

L t

O r

L i

f i

I t

O S023-0DCM 4-15 Revision 21 L

02-15-90 4

FIGURE 4-5 SONGS 2 & 3 RADIOACTIVE LIQUID WASTE TREATMENT SYSTEMS Storage Tank CCWSump h

I*

)

(Bate)

M nser I

n

)

Aux Buthng Turbme Sump Plant Sump "1

RT 7821 n

(Congnuous)

(Contnous) l 4

o Neutrakzaton BPS Sump g n:

RT 7817 (Batch / Cont) l I

I HCS LCS HUT (Batch)

(Batch)

(Batch) o n

l FFCPD O

l i

S/G E089 RT6753 S/G E088 RT 6759 D

CCW HX Saltwater (Congnuous)

Radwaste Pnmary Taiks Radwaste Secondary Tanks Primary Maletp Tanks 2/3 RT 7813 Condersate Monitor Tanks intilke f

(Batch)

Ouifall o

Pacific Ocean Radiation Monitor O

NOTE: Monitor pathways are unit specific unless SO23-ODCM indicated to be common to Units 2 and 3.

Revision 26 4-16 12-20-93

O O

.O:

Atmosphere Atmosphere Atmosphere Atmosphere

-e 2RT-7870-1

-e 2RT-7865-1 3RT-7870-1 e-2RT-7865-1(1) e-3RT-7865-1 e-

-* 3RT-7865-1(1)

-e 2RT-7818 3RT-7818 *--

2RT-7828 *-

-e 2/3RT-7808

-e 3RT-7828 Unit 2 Plant _,,

Unit 3 Containment Vent Containment Purge Purge Unit 2 Building Unit 3 Building Ventilation Exhausts Ventilatien Exha:'sts i

Unit 2 Condenser Gas Decay

' Unit 3 Condenser.

Evacuation System Tanks (6)

Evacuation System I

a Radioactivity Monitor.

(1) RT-7865 can be aligned to either containment purge or the plant vent stack FIGURE 4-6 SONGS 2 & 3 RADIOACTIVE GASEOUS WASTE TREATMENT SYSTEMS '

So23-oDCM 4-17 Revision 24 08-31-91

O O

O Resin Resin slutced from Transferred Loaded into "I"d Spent Resin Spent Resin SRT to disposal to MPHF shipping cask for

_p from II Accumulated in SRT container and for interim transport to to SRT dewatered staging burial site Filter evaluated Filter Filter stored for incinerability.

If not incinerable, Particluate removed in If incinerable.

packaged in

_p Process Filters from in line accumulation shipped

. _p drum liner position area on stte for off-site for disposal incineration Bags sealed Resulting disposable g

g9 Waste Shipped to waste packaged and Low Level Dry cargo container

+

processor for shipped from Active Waste for shipment to located around plant volume reduction processor to burial site waste processor Clothing packaged Clothing bags in boxes and co ec ed r s p Prottetive Clothing

_W returned to site yy_ j 7

plant monitoring facility Legend SONGS 2/3 Solid Weste Handling 5023-0DCM SRT: Spent Resin Tank Figure 4-7 Revision 26 MPHF: Multi Purpose Hand 11ng Fact 11ty 12 20 93 IX:

Ion Exchanger 4,gg

--.. ~

I 5.0 tADI0 LOGICAL ENVIRGISIENTAL NONITORING i

5.1. Nonitorina Proaram SPECIFICATION 5.1.1' The radiological environmental monitoring program shall be conducted as specified in Table 5-1.

The requirements are i

applicable at all times.

i APPLICABILITY: At all times ACTION:

Should the radiological environmental monitorina program i

a.

not be conducted as specified in Table 5-1, in Iieu.of any other report required by Technical Specification (he) Annua s

i 6.9.1,-prepare and submit to the Commission,.in t g.

Radiological Environmental Operating Report.(see i

Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

Should the level of radioactivity'in an environmental sampling medium exceed the reporting. levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification (s) 6.9.1,.

prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant.

to Technical Specification (s) 6.9.1.13.

When more than l

one of the radionuclides in Table 5-2 are detected in the i

sampling medium, this report shall be submitted if:

O eneeira4en m

+

encentra4 n m

....u. 0 limit level (1) limit level (2) c.

When radionuclides other than those in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted-if the potential annual dose to an individual is equal to or greater than the calendar.

year limits of Specification (s) 1.2.1, 2.2.1 or 2.3.1, as appropriate. This report is not required if the measured level of_ radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological.

Environmental Operating Report (see Section 5.4).

)

d.

With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the commission within 30 days, pursuant to l

Technical Specifications 6.9.2, a Special Report which.

l identifies the cause of the unavailability of samples and i

identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 5-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

S023-0DCM I

5-1 Revision 27 12-21-94 e

_, _ _ _ _ _ i._

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, _ _ ~

s, m

-.r,~

-~7

--.._y-r.-

5.0 RADIOLOGICAL ENVIR0001 ENTAL N0NITORING (Continued)

SURVEILLANCE REQUIREMENTS i

i

'.D

.1 The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Tables 5-4 and 5-5 and Figure 5-1 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

i e

i

~!

5 O

t t

i i

?

i O

S023-0DCM 5-2 Revision 22 08-02-90

{'

fl (v~')

%,/.BLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Samole and Samole Locations

Collection FrecuenCY' TYDe and FrecuencY of Ana1Yses 1.

AIRBORNE Samples from at least Continuous operation Radiciodine cartridge. Analyze Radiciodine 5 locations of sampler at least once per 7 days for I-131.

and 3 samples from offsite with sample collection Particulate sampler. Analyze for Particulates locations (in different as required by dust gross beta radioactivity 2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sectors) of the highest loading, but at least following filter change.

Perform calculated annual average once per 7 days.d gamma isotopic" analysis on each ground level D/Q.

sample when gross beta activity is

> 10 times the yearly mean of control 1 sample from the vicinity samples.

Perform gamma isotopic of a community having the analysis on composite (by location) the highest calculated sample at least once per 92 days.

annual average ground-level D/Q.

I sample from a control loca-tion 15-30 km (10-20 miles) distant and in the least pre-valent wind direction *

2. DIRECT At least 30 locations includ-At least once per Gamma dose. At least once per 92 days.

RADIATION

ing an inner ring of stations 92 days, in the general area of the site boundary and an outer ring approximately in the 4 to 5 mile range from the site with a station in each sector of each ring. The balance of the stations is in special interest areas such as popula-tion centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

S023-00CM 5-3 Revision 21 02-15-90

o TABLE 9-1 O

(Continued)

RADIOLOGICAL ENVIR0 MENTAL NOMITORING PROGRA8 Exposure Pathway Number of Samples Sampling and and/or Sample and Samole locations

Collection Freauency*

Tvoe and Freauency of Analyses 3.

WATERBORNE a.

Ocean 4 locations At least once per Gamma isotopic analysis of each month and composited' monthly sample. Tritium analysis t

quarterly of composite sample at least once per 92 days.

b.

Drinking 2 locations Monthly at each Gamma isotopic and tritium location.

analyses of each sample.

i c.

Sediment 4 locations At least once per Gamma isotopic analysis of each from 184 days.

sample.

Shoreline l

d.

Ocean 5 locations At least once per Gamma isotopic analysis of each Bottom 184 days.

sample.

i Sediments t

S023-DDCN 5-4 Revision 22 08-02-90

.n c

-n-

.ee,,-n--

ee,.

se. -.,, - - - - -

-,. -, - ~,. - -, >. -

.nw---

-n

,.n.,

,--.-ns-,-

-e

~ ~.,- - -.. -.. -, - ~,, -, - -.

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Samnle and Samole Locations

Collection Freouency*

Type and Frecuency of Analyses 4.

INGESTION a.

Nonmigratory 3 locations One sample in season, Gamma isotopic analysis on Marine or at least once per edible portions.

Animals 184 days if not seasonal. One sample of each of the follow-ing species:

1. Fish-2 adult species such as perch or sheephead.

2. Crustaceae-such as crab or lobster.

3. Mollusks-such as limpets, seahares or clams.

b.

Local Crops 2 locations Representative Gamma isotopic analysis on edible vegetables, normally portions semiannually and I-131 1 leafy and 1 fleshy analysis for leafy crops, collected at harvest time. At least 2 vegetables collected semiannually from each location.

S023-0DCM h

TABLE 5-1 (Continued)

TABLE NOTATION a.

Sample locations are indicated on Figure 5-1.

b.

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

c.

The purpose of this sample is to obtain background information.

If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.

d.

Canisters for the collection of radiciodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.

e.

Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. 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 purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters.

Film badges should not be used for reasuring direct radiation.

f.

Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

S023-0DCM

TABLE 5-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gases Marine Animals Local Crops 3

Analysis (pCi/1)

(pCi/m )

(pCi/Kg, wet)

H-3 2 x 10"*)

Mn-54 1 x 10' 3 x 10' 2

4 Fe-59 4 x 10 1 x 10 3

Co-58 1 x 10 3 x 10*

2 Co-60 3 x 10 1 x 10' 2

Zn-65 3 x 10 2 x 10' 2

Zr Nb-95 4 x 10 2

I-131 2

0.9 1 x 10 3

3 Cs-134 30 10 1 x 10 1 x 10 3

Cs-137 50 20 2 x 10 2 x 10 Ba La-140 2 x 10

(*)

For drinking water samples.

This is 40 CFR Part 141 value.

l S023-0DCM h

h-7 5

ision 21 5-90

TABLE 5-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)***

Airborne Particulate Water or Gases Marine Animals local Crops Sediment Analysis (pCi/1)

(pCi/m )

(pCi/Kg, wet)

(pCi/Kg, dry) gross beta 4

1 x 10

H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 l

7 x 10

60 b

Cs-134 15 5 x 10-2 130 60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140 60 La-140 15 S023-0DCM llh lllh 15-90

TABLE 5-3 (Continued)

TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample h

that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD =

5 E

V. 2.22 x 10 Y. exp (-AAt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

s is the standard deviation of the background counting rate or of 3the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 x 10 is the number of transformations per minute per h

6 microcurie, Y is the fractional radiochemical yield (when applicable),

1 is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ).

The value of s used in the calculation of the LLD for a detection system e

shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).

Typical values of E,V,Y and At shall be used in the calculations.

O S023-0DCM 5-9 Revision 22 08-02-90

i TABLE 5-3 (Continued)

TABLE NOTATION It should be recognized that the LLO is defined as an 1 oriori (before the fact) limit representing the capability of the measurement system and not as 1 costeriori (after the fact) limit for a particular measurement.*

b.

LLD for drinking water.

Other peaks which are measurable and identifiable, together with the c.

radionuclides in Table 5-3, shall be identified and reported.

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300. (revised annually).

(2) Currie, L. A.,

" Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J.

K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

O i

O S023-0DCM 5-10 Revision 21 02-15-90

5.0 RADIOLOGICAL ENVARONMENTAL MONITORING (C:ntinued) 5.2 LAND USE_CENSJE SPECIFICATION g

5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

For elevated relsases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.

APPLICABILITY: At all times ACTION:

With a land use census identifying a location (s) which a.

yields a calculated dose or dose comitment greater thin the values currently being calculated in Specification 2.3.1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location (s).

Identify the new locations in the next Annual Radioactive lg Effluent Release Report, b.

With a land use census identifying a location (s) which yields a calculated dose or dose comitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 5.1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comissicn within 30 days, pursuant to Technical Specification 6.9.2, a Special Re> ort which identifies the new location. The new location s1all be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose 19.

comitment via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

SURVEILLANCE RE0VIREMENTS

.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

S023-0DCM 5-11 Revision 27 12-21-94

5.0 RADIOLOGICAL ENVIRONNENTAL NONITORING (C:ntinued) 5.3 INTERLABORATORY COMPARISON PROGRAM hl SPECIFICATION 5.3.I Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times ACTION:

With analyses not being performed as required above, report a.

the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE0VIREMENTS

.]

A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.I of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).

O O

S023-0DCM 5-12 Revision 22 08-02-90

5.0 RADIOLOGICAL ENVIR0feiENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

5.4.1 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and 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 Section 5.2.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.

In the event that some 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; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.

A single suomittal may be made for a multiple unit station, combining those sections that are common to all units at the station.

O S023-0DCM 543 Revision 21 02-15-90

5.0 RADIOLOGICAL EMIR 0 MENTAL MONITORIM (Continued) 5.5 SAMPLE LOCATIONS

' /

The Radiological Environmental Monitoring Sample Locations are

\\ ')

identified in Figure 5-1.

These sample locations are described in Tables 5-4 and 5-5 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, i

Figure 5-1.

1 i

0 t

i i

\\

(}

1 S023-0DCM 5-14 Revision 21 02-15-90 I

Page 1 of 6 TABLE 5-4 RADIOLOGICAL ENVIR00 MENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION ***

(miles)

DIRECTION

l Direct Radiation 1

City of San Clemente (Former SDG&E Offices) 5.6 NL 2

Camp San Mateo (MCB, Camp Pendleton) 3.5 N

3 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 4

Camp Horno (MCB, Camp Pendleton) 4.5 E

5 DELETED 6

Old Route 101 (East-Southeast) 3.0 ESE 7

DELETED 8

Noncommissioned Officers' Beach Club 1.5 NW

^

9 DELETED 10 Bluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.3**

NW 12 South Edge of Switchyard 0.2**

E 13 Southeast Site boundary (Bluff) 0.4**

SE 14 Huntington Beach Generating Station 37.0 NW 15 Southeast Sits Boundary (Office Building) 0.2**

SE 16 East Southeast Site Boundary 0.4**

ESE 17 Transit Dose 18 Transit Dose 19 San Clemente Highlands 5.0 NNW 20 DELETED 21 DELETED 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 San Clemente General Hospital 8.2 NW 24 DELETED Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all i

sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber S023-0DCM 5-15 Revision 26 12-20-93

Page 2 cf 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS l

DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION ***

(miles)

DIRECTION

Direct Radiation (Continued) 25 DELETED 26 DELETED 27 DELETED 28 DELETED t

29 DELETED 30 DELETED 31 Aurora Park-Mission Viejo 18.7 NNW i

32 DELETED 33 Camp Talega (MCB, Camp Pendleton) 5.7 N

34 San Onofre School (MCB, Carrn Pendleton) 1.9 NW

~

35 Range 312 (MCB, Camp Pendleton) 4.7 NNE 36 Range 208C (MCB, Camp Pendleton) 4.2 NE 37 DELETED 38 San Onofre State Beach Park 3.3 SE 39 DELETED 40 SCE Training Center - Mesa (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.4**

E A

42 DELETED 43 DELETED t

44 Fallbrook Fire Station 18.0 E

45 DELETED 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE 48 DELETED l

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all f

sectors) and not required by Technical Specification.

- - MCB - Marine Corps Base PIC - Pressurized Ion Chamber I

j O

S023-0DCM 5-16 Revision 26 12-20-93 j

Page 3 cf 6 TABLE 5-4

(

RADIOLOGICAL ENVIR0 MENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION ***

(miles)

DIRECTION

Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station (CONTROL) 15.5 SE i

51 DELETED 52 DELETED t

53 San Diego County Operations Center 45.0 SE 54 Escondido Fire Station 32.0 ESE 55 San Onofre State Beach (Unit 1, West Southwest) 0.2**

WSW 56 San Onofre State Beach (Unit 1, Southwest) 0.1**

SW 57 San Onofre State Beach (Unit 2) 0.1**

SSW t

58 San Onofre State Beach (Unit 3) 0.1**

S 59 SONGS Meteorological Tower 0.3**

WNW f

l 60 Transit Control Storage Area 61 Mesa - East Boundary (Adjacent to PIC #4) 0.7 N

O 62 acB - c P ee#d'ete" (^a; ce#t te eic #s) oe "at 63 MCB - Camp Pendleton (Adjacent to PIC #6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.5 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8) 0.7 E

66 San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE

]

67 Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE

)

I Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber OV S023-0DCM 5-17 Revision 26 12-20-93

1 Page 4 of 6 TABLE 5-4 l

RADIOLOGICAL ENVIRONMENTAL NONITORING SANPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles 1 DIRECTION

Airborne 1

City of San Clemente (City Hall) 5.5 NW 2

Camp San Onofre (Camp Pendleton) 1.8 NE 3

Huntington Beach Generating Station (CONTROL) 37.0 NW 5

Units 2 and 3 Switchyard 0.13**

NNE 6

DELETED 7

AWS Roof 0.18**

NW 9

State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa E0F 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E

Soil Samples i

O c P s>" o#erre 2s "E

2 Old Route 101 - East Southeast 3.0 ESE 3

Basilone Road /I-5 Freeway Offramp 2.0 NW 4

Huntington Beach Generating Station (CONTROL) 37.0 IN 5

Former Visitor's Center 0.2**

NNW Ocean Water A

Station Discharge Outfall - Unit 1 0.5 SSW B

Outfall - Unit 2 0.7 SW j

C Outfall - Unit 3 0.7 SW D

Newport Beach (CONTROL) 30.0 NW l

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.

O S023-0DCM 5-18 Revision 26 12-20-93

Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIR00 MENTAL MONITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

DIRECTION

Drinking Water 1

Tri-Cities Municipal Water District Reservoir 8.7 FW 2

San Clemente Golf Course Well 3.5 NNW j

3 Huntington Beach (CONTROL) 37.0 NW Shoreline Sediment (Beach Sand)

I 1

San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2

San Onofre Surfing Beach 0.9 NW 3

San Onofre State Beach (3.1 miles Southeast) 3.1 SE 4

Newport Beach (North End) (CONTROL) 30.0 NW Local Crops 1

San Mateo Canyon (San Clemente Ranch) 2.6 NW 2

Southeast of Oceanside (CONTROL) 22.0 SE O

l l

l Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

O S023-0DCM 5-19 Revision 26 12-20-93

Page 6 of 6 TABLE 5-4

)

RADIOLOGICAL ENVIRONMENTAL N0NITORING SAMPLE LOCATIONS DISTANCE

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

DIRECTION

Non-Migratory Marine Animals A

Unit 1 Outfall 0.9 WSW i

B Units 2 and 3 Outfall 1.7 SSW C

Laguna Beach (CONTROL) 18.2 NW Kelp A

San Onofre Kelp Bed 1.5 S

B San Mateo Kelp Bed 3.8 WNW l

C Barn Kelp Bed 6.3 SSE D

Laguna Beach (CONTROL) 15.6 NW Ocean Bottom Sediments A

Unit 1 Outfall (0.5 mile West) 0.6 W

8 Unit 1 Outfall (0.6 mile West) 0.8 SSW L

Unit 2 Outfall 1.6 SW O

o ue413 0etfen u

SSW E

Laguna Beach (CONTROL) 18.2 NW r

I Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

O S023-0DCM 5-20 Revision 26 12-20-93

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONNENTAL NONITORING LOCATIONS y

Theta DISTANCE

PRESSURIZED ION CHAMBERS (Deareesl*

Meters miles DIRECTION / SECTOR

S1 San Onofre Beach 298*

1070 0.7 WNW P

S2 SONGS Former Evap. Pnd 313' 890 0.6 NW Q

S3 Japanese Mesa 340' 1150 0.7 NNW R

S4 MCB - Camp Pendleton 3*

1120 0.7 N

A 55 MCB - Camp Pendleton 19' 1050 0.6 NNE B

t S6 MCB - Camp Pendleton 46' 940 0.6 NE C

S7 MCB - Camp Pendleton 70*

870 0.5 ENE D

S8 MCB - Camp Pendleton 98*

1120 0.7 E

E S9 San Onofre State Beach 121' 940 0.6 ESE F

I

Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

i O

S023-0DCM 5-21 Revision 21 02-15 90 l

TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONNENTAL NONITORING SAMPLE LOCATION MAP A\\~ /

DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.5' Limit Line Limit Sector

Direction 348.75 0 & 360 11.25 A

N 11.25 22.5 33.75 B

NNE 33.75 45.0 56.25 C

NE 56.25 67.5 78.75 D

ENE 78.75 90.0 101.25 E

E i

101.25 112.0 123.75 F

ESE 123.75 135.0 146.25 G

SE 146.25 157.0 168.75 H

SSE 168.75 180.0 191.25 J

S 191.25 202.5 213.75 K

SSW 213.75 225.0 236.25 L

SW 236.25 247.5 258.75 M

WSW 258.75 270.0 281.15 N

W 281.25 292.5 303.75 P

WNW 303.75 315.0 326.25 Q

NW 326.25 337.5 348.75 R

NNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.

O S023-0DCM 5-22 Revision 21 02-15-90

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T L-S023-0DCM Sa;ple Location - San Diego Count y Revision 26 950 17-20-93

"^

6.0 ADMINISTRATIVE 6.1 DEFINITIONS j

O The defined terms of this section appear in capitalized type and are applicable through these Specifications.

ACTION 6.1.1 ACTION shall be that part of a specification which l

prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any serie:, of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 6.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog channels - the injection of a simulated signal into channel as close to the senscr as practicable to verify OPERABILITY, including alarm and/or trip functions.

b.

Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.

c.

Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY.

O 5023-0DCM 6-1 Revision 21 02-15-90 d

6.0 ADMINISTRATIVE (C:ntinued)

DOSE E0VIVALENT I-131 I

6.1.5 DOSE EQUIVALENT I-131 shall be that concentration of I-131 O

(microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844,

" Calculation of Distance Factors for Power and Test Reactor Sites."

FRE0VENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.

GASE0US RADWASTE TREATMENT SYSTEM 6.1.7 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.

INVESTIGATIVE REPORT b) 6.1.8 The group responsible for the missed ACTION or surveillance shall perform an evaluation which covers the root cause(s),

corrective action, and recommendations to preclude recurrence of the event.

Copies of the resulting report shall be provided to Effluent Engineering and the Unit Superintendent with the original sent to CDM-SONGS for retention.

MEMBERS OF THE PUBLIC 6.1.9 MEMBER (S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

O S023-0DCM 6-2 Revision 23 02-28-91

6.0 ADMINISTRATIVE (Centinutd) l OPERABLE - OPERABILITY l

6.1.10 A system, subsystem, train, component or device shall be l

OPERABLE or have OPERABILITY when it'is capable of performing its specified function (s), and when all necessary l

attendant instrumenhtion, controls, electrical power, cooling or seal wab, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are l

also capable of performing their related support i

function (s).

l PURGE - PURGING l

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

SITE BOUNDARY 6.1.12 The SITE B0UNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION l

O 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly i

distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

SOURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assessment of l

channel response when the channel sensor is exposed to a.

radioactive source.

THERMAL POWEB 6.1.15 THERMAL POWEP, shall be the total reactor core heat transfer I

rate to the reactor coolant.

i O

S023-0DCM 6-3 Revision 23 02-28-91 l-m

-a e

6.0 ADMINISTRATIVE (Cntinued) i VENTILATION EXHAUST TREATMENT SYSTEM

']

6.1.16 A VENTILATION EXHAUST TREATMENT SYSTEM is any s'ystem L

designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 6.1.17 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process.

5 (v

S023-0DCM 6-4 Revision 25 02-28-92

TABLE 6-1 OPERATIONAL MODES REACTIVITY

% OF RATED AVERAGE COOLANT OPERATION MODE

- CONDITION. K THERMAL POWER

TEMPERATURE m

-1.

POWER OPERATION 2 0.99

> 5%

2 350*F

2. STARTUP 2 0.99 s 5%

2 350*F

3. HOT STANDBY

< 0.99 0

2 350*F j

4. HOT SHUTDOWN

< 0.99 0

350*F> T.,,>200*F

5. COLD SHUTDOWN

< 0.99 0

1 200*F f

6. REFUELING **

$ 0.95 0

s 140*F 4

l

Excluding decay heat.

- Fuel in the reactor vessel with the vessel head closure bolts less than fully O

tensioned or with the head removed.

'5 i

I l

O 5023-0DCM i

6-5 Revision 21 02-15-90 m.

m.->

w

-+

w

TABLE 6-2

~

i FRE00ENCY NOTATION O,-

NOTATION FREOUENCY S

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

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

W At least once per 7 days f

M At least once per 31 days i

Q At least once per 92 days SA At least once per 184 days I

R At least once per 18 months

l i

S/U Prior to each reactor startup i

i P

Completed prior to each release l

N.A.

Not applicable Refueling Not to exceed 24 months Interval l

O i

i

A month is defined as a 31-day period.

l-i i

i i

a i

O S023-0DCM l

6-6 Revision 22 i

08-02-90 i

=.

6.0 ADMINISTRATIVE (Crntinu:d) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.2.1 Routine radioactive effluent release reports covering the o)eration of the unit during the previous calendar year slall be submitted before May I of each year.

6.2.2 The radioactive effluent release reports-shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, " Revision 1, June 1974, with data summarized on a quarterly basis following i

the format of Appendix B thereof.

The radioactive effluent release report 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 of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint freque~ncy distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an t

assessment of the radiation doses due to the radioactive i

liquid and gaseous effluents released from the unit or r

station during the previous calendar year. This same report p

shall also include an assessment of the radiation doses from i

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radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE B0UNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) ditions concurrent shall be included in these reports. The meteorological con with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses, The assessment of radiation doses shall be performed in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM).

A single submittal may be made for a multiple unit station. The submittel should combine those sections that are common to all units at the Station; however, for units with separate redweste systems, the submittal shall specify the releases of radioactive material from each unit.

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O S023-0DCM 6-7 Revision 26 L

12-20-93

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6.0 ADMINISTRATIVE (Continu:d) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 '(Continued)

The radioactive effluent release report 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 12 consecutive months to show conformance)with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear 1

Power Operation. Acceptable methods for calculating the 1

dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume, l

b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g., spent resin, compacted dry waste,evaporatorbottoms),

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and 7

f.

Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent' release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

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5023-0DCM 6-8 Revision 26 12-20-93

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6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGFS TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, & Gaseous)

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Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):

1.

Shall be reported to the Commission in the Monthly Operating Report (see NOTE) for the period in which the evaluation was performed pursuant to Technical Specification 6.5.2.

The discussion of each

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change shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto; e.

An evaluation of the change which shows the expected maximum O

exposures t individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f.

A comparison of the predicted releases _ of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and i

h.

Documentation of the fact that the change was reviewed and fotnd acceptable pursuant to Technical Specification 6.5.2.

2.

Shall become effective upon review and acceptance pursuant to Technical Specification E.5.2.

NOTE:

Upon approval of PCN 364, major changes to the radioactive waste treatment system will no longer be included in the Monthly Operating Report, but will be included in the Annual Radioactive Effluent Release Report.

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S023-0DCM 6-9 Revision 26 12-20-93

-6.0 ADMINISTRATIVE (C:ntinued) 6.4 BASES O

LIOUID EFFLUENTS V

CONCENTRATION (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site 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 outside the site will result in exposures within (1) the Section-II.A design objectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the populatien.

Tha concentration limit for dissolved or entrained noUse gases is based upon the assumption that Xe-135 is tne controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

p_0SX (1.2) 0 6.4.2 This specification is provided to implement the require-1 ments of Section 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 C

and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations 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 an individual through appropriate pathways is unlikely to be substantially underestimated. The ec uations specified in the ODCM for calculating the doses cue 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 I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from l

the shared system are proportioned among the units sharing that system.

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S023-0DCM 6-10 Revision 21 02-15-90

6.0 ADMINISTRATIVE (C:ntinu:d) 6.4 BASES (Continued)

LIOUID WASTE TREATMENT (1.3)

V 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effiuents 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 objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitab's fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid ef fluents.

GASEOUS EFFLVENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from

&ll units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of p

10 CFR Part 20, Appendix B, Table II, Column 1.

These V

limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B,. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For individuals who may :t times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the.

corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.

This specification applies to the release of gaseous effluents from all reactors at the site.

For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

O S023-0DCM 6-11 Revision 21 02-15-90

6.0 ADMINISTRATIVE (C:ntinu:d) 6.4 BASES (Continued)

DOSE - NOBLE GASES (2.2) 6.4.5 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 1.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as l

low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations 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 I.109, " Calculation of Annual Dosa 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 and Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water O

coo'ed ae cters." aevisie# i. a#'s 1977-ror 4#84 vie #e's who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BPJNDARY. For MEMBERS OF THE PUBLIC who traverse the SliE BOUNDARY via highway I-5, the residency time shall be considered negligible and hence the dose "0".

The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.

DOSE - RADIOI0 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 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 Conditior.s for Operation are the guides set forth in Section II.C 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 radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the O

S023-0DCM 6-12 Revision 22 08-02-90

6.0 ADMINISTRATIVE (Centinued) 6.4 BASES (Continued)

[s) 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 an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of 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. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of thesa 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.

GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABILITY of the GASE0US RADWASTE TREATHENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This 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 II.D 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.

5023-0DCM 6-13 Revision 21 02-15-90

6.0 ADMINISTRATIVE (Centinued) 6.4 SASil (Continued)

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10TAL DOSE (2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated t

doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of actior which should result in the limitation of dose to a member of the public for 12 consecutive months is within the 40 CFR 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose ccntributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.

If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a m iance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in

]/

violation of 40 CFR 190 have not already been corrected. An i

individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

l RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radicactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures 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.

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S023-0DCM l

6-14 Revision 21 02-15-90

)

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6.0 ADMINISTRATIVE (C:ntinued) 6.4 BASES (Continued) 2 l]

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2)

(

6.4.10 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 1

setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

MONITORING PROGRAM (5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by

[]

verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. 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 detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as 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, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

O S023-0DCM 6-15 Revision 22 08-02-90

6.0 ADMINISTRATIVE (Continued)'

6.4-BASES (Continued)

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LAND USE CENSUS (5.2) i

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6.4.12 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used.

This census i

satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.

INTERLABORATORY COMPARIS0N PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental shiaple matrices are l

performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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S023-0DCM 6-16 Revision 22 08-02-90

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ML20080F702

Text

SUBJECT:

REFERENCE:

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