ML20058Q380

Rev 22 to ODCM

ML20058Q380
Person / Time
Site:	San Onofre
Issue date:	08/02/1990
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13309A922	List: ML13309A921 ML20058Q357 ML20058Q366 ML20058Q380
References
PROC-900802, NUDOCS 9008220054
Download: ML20058Q380 (196)

Text

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(I 0FFSITE DOSE CALCULATION NANUAL-NUCLEAR GENERATION SITE-UNITS 2 AND'3 4

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j ODCM TABLE OF CONTENTS P.A5 Lit 1

' LIST OF FIGURES.......................................................

iv l

LIST.0F TABLES......................................................... v-vi INTRODUCTION.......................................................... vii l

1.0 LIQUID EFFLUENTS..................................................-

1-1 1.1 Concentration................................................

1-1 1.1.1 Specification........................................

1

• 1.1.1.1, 1.1.1.2 Surveill ance s...............................

1 - 1 1.2 Dose 1.2.1 Speci fi c a t i on.......................................

1 - 5

1. 2.1.1 S u rve i l l an ce........................................

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 Effl uent Moni tor Setpoi nts...........................

1.

Batch Release Setpoint Determination................. 1-10 1.4.

1.4.2 Continuous Release Setpoint Determination...........

1-16 1.5 Dose Calculations for Liquid Effl uents....................... 27 1.6 Representative Sampling......................................

1-30 2.0 GASEOUS EFFLUENTS................................................

2-1.

2.1 Dose Rate...................................................

2-1 2.1.1. Specification.......................................... 2-1 2.1.1.1, 2.1.1.2-Surveillances...............................

2-1 2.2 D o s e - N o bl e G a s............. '...............................

2 - 5 L

2.2.1 Specification...............,........................

2-5.

2.2.1.1 Surveillance........................................

2-5:

1 2.3 Dose - Radiciodines, Radioactive Materials in Particulate

. Form and Tritium.............................................

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

2 -

2. 3.1.1 S u rve i l l anc e..... l...................................

2 - 6 Revision 22 i

08-02-90 APPROVED AUG 0 2 1990 l

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00CM l

g TABLEOFCONTENTS(Continued)-

EA9.1 2.4 -Gaseous Radwaste Treatment...................................

2-7

{

2. 4.1 Spe c i fi c at i on..........................................

2 - 7

2. 4.1.1 S u rve i l l ance......................................... 2 - 7 2.4.1.2, 2.4.1.3 Surve i11 ance s............................... 2 -8 2.5 T o t a l Do s e..................................................

2 - 9

2. 5.1 Speci fi c at i on.........................................

2 '

2. 5.1.1 S urve i l l ance.......................................... 2 2.6 Gaseous Effl uent Monitor Setpoints.......................... 11 y

2.6.I' Pl an t Stac k.......................................

2 - 11 2.6.2 Condenser Evacuation Systec.

2 2.6.3. Containment Purge'............s...................... 2-18 2.6.4 Waste Gas Header,...................................

2-21 2.7 Gaseous Effl uent Dose Rate.................................=.. 2-26 2.7.1 No bl e G a s e s......................................... 2 - 2 6 -

L 2.7.2 Radioiodines and Particulates.'.............._........ 2-27 j

i 2.8 Gaseous Effl uent Dose Calcul ation..........................

2 l' a

l-2.8.1 No bl e G a s e s........................................

2 - 2 9 2.8.1.1 Hi storicaliMeteorol ogy..................... 2-29 2.8.1.2-Concurrent Meteorology.....................;2-30 l

2.8.2

.Radiciodines and Particulates:........................L2-31 2.8.2.1 Hi storical Meteorology...................

2-31 2.8.2.2 Concurrent Meteorology................'.... 2-33

~

2.9 Total Dose ' Cal cul ati ons.....................................

2-79 2.9.1 Total Dose to Most Likely Member of the' Public...... ' 2-79 l-

-2.9.1.1 Annual Total Organ Dose.................

2-79 7

2.9.1.2

' Annual Total Whol e - Body Dose '..........._..

2-80 2.9.1.3 Annual-Total Thyroid' Dose................

2-81 e

3.0 PROJECTED DOSES-1 q

3.1 Liquid Dose Projection..................................... 3-1 3.2 Gaseous Dose Projection.....-...............................

3-1 j

i 4.0 EQUIPMENT...........................................................

4-1 4.1 Radioactive Liquid Effluent Monitoring Instrumentation......

4-13 i

4.1.1 Spe ci fi c a ti on......................................... 4 - 1 4-4.1.1.1, 4.1.1.2 Surveillances..............................

4-1 e

Revision 22

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11 08-02 APPROVED AUG 0 2 1990-t i

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TABLE OF CONTENT 5 (Continued)

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EAEA j

i 4.21 Radioactive Gaseous Effluent Monitoring Instrumentation.....

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

4-6 4. 2.1.1 S u rve 111 ance........................................

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

4-13 1

i 5.0 Radiol ogical Envi ronmental Moni toring..........................s.. 5-1

)

i 5.1 Monitoring' Program...............................,..........

5-1

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5.1.1 Specification...................................

5-1

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5.1.1.1 Surveillance....................................

52 i

5.2 L and U s e C e n s u s............................................. :. 5 1 1 l

5.2.1 Specification...................................

5 11 5.2.1.1 Surveillance....................................

5 11 5.3 Interl aboratory Compari son Program..........................

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

5 12 5.3.1.1 Surveillance....................................

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

5-13 5.5 S ampl e tocat i on s............................................

5 - 14 6.0 Administrative....................................................

6-l' 6.1 De f i n i t i o n s..................................................

6 - 1 1

6.2 Admi n i st rat i ve Con trol s.................................. ~~. 6 6 L

i 6.3 Major Changes to Radioactive Waste Treatment Systems l

(Liquid and Gaseous)........................................

6-8 6.4 Bases.......................................................

6-9 l

I i

i APPROVED AUG 0 21990 Revision 22 iii 08 02-90 1

I t

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1 00CM i

i LIST OF FIGURES Ligure Title Page.

12 Site Boundary for Liquid Effluents...............................

1-7 l

2-2 Site Boundary for Gaseous Ef fl uents..............................

2-10 j

i 4-5 SONGS 2 and 3 Radioactive L1'uid Waste Treatment Systems.........

4-14 46 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems........

4 15 l

4-7 Solid Waste Handling.............................................

4-16 5-1 Radiolog cal' Environmental Monitoring Sample Locations...........

5 23 5 25 A

I l-f 3

APPROVED AUG 0 21990 Revision 22 iv 02 02-90 r

a a

s-n

i ODCN LIST OF TABLES Table Title Paae i

i 11 Radioactive Liquid Waste Sampling and Analysis Program.....

1-2 l-3 Liquid Effluent Radiation Monitors Cal i brati on Constants.....................................

1 26 l4 Dose Commitment fac. tors A9..............................

1-28 l

2-1 Radioactive Gaseous Waste Sampling and Arialysis Program....

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

2-25 2 Dose Factors for Noble Gas and Daughters..................

2-35 l

i 2-5 Dose Parameters Pg.........................'...............

2-36 j

4 2-6 Controlling Location Factors..............................

2-37 2-7 Dose Parameters R for Sector P............................

2-38 4

28 Dose Parameters R for Sector Q............................

2-40 j

1 2-9 Dose Parameters R for Sector R............................

2-48 g

i 2-10 Dose' Parameters R for Sector A............................

2-53 i

g 2-11 Dose Parameters R for Sector B............................

2-56 g

2-12 Dose Parameters R for Sector C............................

2-59 g

2-13 Dose Parameters R for Sector D............................

2-64 g

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

2-67 g

2-15 Dose Parameters R for Sector F............................

2-70 g

2-16 Dose Parameters R for Sector G............................

2-5 g

4-1 Radioactive Liquid Effluent Monitoring Instrumentation....

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

4-4 t

4-3 Radioactive Gaseous Effluent Monitoring Instrumentation....

4-7 a-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveill ance Requi rement s..................................

4 -10 APPROVED AUG 0 21990 v

Revision 21 i

02-15-90

ODCM.

LIST OF TABLES (Continued))

Igble Titiv Pace 51 Radiological Environmental Monitoring Program..............

5 3 52 Reporting Leve'

%r Radioactivity Concentrations in Environmentr' Semp 5 7 53 Maximum Vale

• f-the Lower Limits of Detection (LLD).....

5-8 54 Radiological L'.<ironmental Monitoring Sample Locations.....

5-15 55 PIC Radiological Environmental Monitoring Locations........

5 21 56 SectorandDirectionDesi!nationforRadiological Environmental Monitoring ample Location Map..............

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

6 4 62 Frequency Notation.........................................

6-5 i

APPROVED /\\UG 0 21990 vi Revision 21 02-15-90 i

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of le PADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCh enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents.

In order to meet release limitations it additionally calculates the liquid and gaseous effluent monitnring instrumentation alarWtrip setpoints. The environmental section contains a list of the sample locations for the radiological environmental monitoring program.

The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications.

Changes in the calculational methodscor parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology.

l APPROVED AUG 0 2 1990 4

l l

i 1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECIFICATION 1.1.1 The concentration of radi.oactive. material released from the-site (see Figure 1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appindix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble concentration shall be limited to 2 x 10* gases, the microcuries/mi l

total activity.

APPLICABILITY: At all times ACTION:

)

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

I SURVEILLANCE REQUIREMENTS

^

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

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

)

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

4 9

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i APPROVED AUG 0 21990 I

l-1 Revision 22 i

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) a Tvoe Frecuency Frecuency Analvsls fuci/mli A. Batch W ste P

P Release Each Batch Each Batch Principa} Gamma 5x10 '

Emitters I-131 1x10

• P M

Dissolved and 1x10-'

One Batch /M Entrained Gases (Gamma emitters)

P M

H-3 1x10-'

Each Batch Compositeh Gross Alpha 1x10-'

P Q

Sr-89, Sr-90 5x10**

Each Batch Compositeb Fe-55 lx10-'

NQIE BATCH RELEASE PATHWAYS:

Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, p'l Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity).

B. Continuous

• D W

Principa; Gamma 5x10,

Releases,

Grab Sample Compositec Emitters e

1-131 1x10 '

M M

Dissolved and 1x10-'

Grab Sample Entrained Gases (Gamma emitters)

H3 lx10-'

D M

l Grab Sample Compositec ross Alpha 1x10 '

D Q

Grab Sample Compositec Sr-89, Sr-90 5x10

• Fe-55 lx10**

N_01.E CONTINUOUS RELEASE PATHWgg: Turbine Plant Sump, Blowdown Processing Sump,**

S/GBlowdownBypassLine

, S/G Blowdown, Salt Water Discharge from CCW Heat l

Exchanger.

Al'I'llO V E D HUG 0 2 1990 1-2 Revision 22 08 02-90

TABLE 1-1 (Continued)

TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

s For a particular measurement system (which may include radiochemica1' separation):

4.66 s LLD.

b E. Y. 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),

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

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

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

2.22 x 106 is the number of transformations per minute per m'icrocurie, Y is the fractional radiochemical yield (when' applicable),

A is the radioactive decay constant for the particular radionuclide, and j

At is the elapsed time between midpoint of sample collection and' time of j

counting (for plant effluents, not environmental samples).

The value of sb used in the calculation of the LLD for a particular measurement I

system shall be based on the actual observed variance of the background. counting.

rate or of the counting r3te of the blank samples (as appropriate) rather than on-l an unverified theoretically predicted variance.

In calculating the LLD for a radionuclide determined by gamma ray spectrometry, i

the background should include the typical contributions of other radionuclides i

normally present in the samples.

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

1 It should be recognized that the LLD is defined as an' A oriori (before the fact)-

L limit representing the capability of the measurement system and,not as n' I

oosteriori (after the fact) limit for a particular measurement.

i

1. or a more complete discussion of the LLD, and other detection limits, see the F

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),

i (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford. company Report ARH-2537 (June 22,-1972).

1 A P P R O V E,D AUG 0 2 1990 1

3 Revision 21 02 15 i I

TABLE 1-1 (Continued)

TABLE NOTATION b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of

-l the,11gulds released, c.

To be representative of the' quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously 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, i-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 j

thoroughly mixed, by a method described in the DDCM, to assure representative sampling.

e.

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

The principal gamma emitters for which the LLO specification applies

{

exclusively are the following radionuclides: Mn-54, Fe 59, Co 58, Co In-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 1

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

Administrative controls shall provide for composite sampling of the continuous releases per note b vice note c unti1' January 1, 1983.

Continuous proportional. sampling shall be in accordance with note c from January 1,1983 and all times subsequent as required by Table 1-1.

The first sump volume of BPS ion exchanger regeneration process sha'.1 be A :

treated as a batch release.

Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU618 for Steam Generator 2E088, S2130lMU619 i

for Steam Generator 2E089, S3130lMU618 for Steam Generator 3E088 and

)

S31301MV619 for Steam Generator 3E089) is verified locked shut.

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A PPitOVED AUG 0 2 1990 l-4 Revision 22 08-02-90

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i l'. 0 LIQUID EFFLUENTS (Continued) 1.2 0Q11 SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:-

a.

During any' calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less _than or equal to 3 mrom to the total body and to less than or equal' to 10 arem to any organ.

APPLICABILITY: At all times ACTION:

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.

SURVEILLANCE REQUIREMENTS 1

.1 Dose Calculation.

Cumulative dose contributions from liquid effluents shall be determined in accordance with Section l'.5 at least once per 31 days.

l u

i APPROVED AUG 0 21990 l'- 5 Revision 21 02-15-90j l'

H 1.0 LIQUID EFFLUENTS (Continued) 1.3 LIOUID WASTE TREATMENT SPECIFICATION 1.3.1 The -liquid radwaste treatment system shall-be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes' 3rior to their i

discharge when the projected doses due to tie liquid effluent from the site-(see Figure 1-2) when averaged over 31 days, would gxceed 0.06 mrem to the total body or,0.2 mrem to. any organ.

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 S1 other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant-tc Technical Specification 6.9.2 a Special Report which 1

inclues the following information:-

1.

Expleation of why liquid radwaste was being discharged withoui: treatment, identification of the inoperable:

R equipmer.t or subsystems and-the reason for inoperability, 2.

Action (s) taken to restore the inoperable' equipment to i

OPERABLE status, and

~

L 3.

Summary description of action (s) taken to.preventia recurrence.

l E

SURVEILLANCE RE0VIREMENTS Doses due to liquid

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

l

.2 During plant operation (Mode 1-4), the appropriate portions of the liquiu radwaste treatment system shall be demonstrated OPERABLE by Q'

operating the liquid radwaste treatment system equi) ment for at least 15-minutes at least once per 92 days.unless tie liquid i

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 treate nt system shall.be demonstrated OPERABLE by k

operating the liquid ruiwaste treatment system equipment for at least 15-minutes prior 'to processing-liquids unless the appropriate liquid radwaste system has been utilized to process radioactive.

j liquid effluents during the previous 92 days.

.1 "Per reactor unit 1-6 Revision 22 l

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REFERENCE:

TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 APPROVED AUG 0 9 1990 1-7 Rev. 21 02-15 90

~ _... _ _ _ _ _ _ - - _ _ - - - - - -

Lle0 LIQUID EFFLUDITS (Continued)

[

1.4. Liquid Effluent Monitor Methods of Setpoint Calculation j

Liquid Radwaste Effluent Line Monitors provide alarm and automatic l

termination' of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification j

and for the purpose of implementation of specification 1.1.1, f

the alarWtrip setpoints for liquid effluent monitors and floi' measurement devices are set to assure that the following equation e

is satisfied:

9 i

5 MPC'If (l'l)

F+R i

where:

MPC,ff = the effective effluent maximum concentration permissible limit (pCi/ml) at the release point t

to the unrestricted area for the radionuclide mixture.

i l

being released, 1~

l F.

N j

(1-2) g(

)

i=1 MPCj t

APPROVED AUG 0 21990 1-8 Revision 21 15-90'

1.0 LIQUID EFFLUENTS (Continued)

.l.4 Liquid Effluent Monitor Methods of setpoint Calculation (Continued) where:

F

= fractional concentration of the ith radionuclide as j

obtained by sample analysis.

N

= number of radionuclides identified in sample analysis.

MPC

= MPC of the ith radionuclide (10CFR20, App B, g

Table'II, Column 2).

C,

= the setpoint, in pCi/m1, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release.

-R

- the permissible' waste effluent flow rate.at the radiation monitor location, in volume per unit time in the same units as for F.

F

= the dilution water flow-in volume per unit' time.

The l

dilutionwaterflow(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 radioactive release-concentration is not underestimated.

APPROVED AUG 0 2 1990 1-9 Revision 21 02-15 90

1.0 LIJID EFFLUENTS -(Continued)-

1.4 Liquid Effluent Monitor Methods of Setpoint Calculation.(Continued)

Administrative values are used~to reduce each setpoint to account 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 -

k exchanger) and rev.._

necessary.

4 l. 4.1-Batch Release Setpoint Determination

.i The waste flow (R) and monitor setpoint (c) are set to meet the condition of equation (1-1) for the effective MPC (MPC,ff) limit. The method by which this is accomplished is as follows:

STEP 1:

The isotopic concentration for each batch j

tank (or sump) to be released is obtained from i

the sum of the measured cc,ncentrations-in the j

tank (or sump) as deteretned by analysis.

l C

= I C,4 + C, + Cs+Ct + C,-

(1-3) l p

where:

C

= the total concentration'in each batch tank.

(pCi/ml)

ECi

= the sum of the measured concentrations for each 1

1 7

1 radionuclide, i, in the~ gamma spectrum.

(pCi/ml) il C,

= the Fe-55 concentration as determined in the previous p

quarterly composite sample.

(pCi/ml)

APPROVED AUG 0 21990 1-10 Revision 22 l-08 02-90 L.

l-

1.0 LIQUID EFFLUDITS (Continued) 1.4.1 Batch Release Setpoint Determination (Continued)

C,

= the' gross alpha concentration ' determined in the

-previous monthly composite sample.

(pCi/ml)

C,

= the Sr-89 and Sr 90 concentrations as determined in the previous quarterly composite sample.

(pCi/ml)

C

= the H 3 concentration as determined.in the previous t

monthly composite sample.

(pCi/ml)

STEP 2:

The effective MPC (MPC,ff) for each batch tank (or sump) is determined using:

1 (14)

'fI

( h )), (C (MPC )

( g g) + (C,fq)

( g )

3j,q)

I (MPC,4 i

(MPC )

(MPC;)

(MPC,)

t p

s MPC 4, MPC, MPC, - the limiting concentrations of the 3

t MPC,, MPC, appropriate radionuclide from 10CFR20..

p 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, e

f '

STEP 3:

The radioactivity monitor setpoint C,.(pci/ml),

may now be specified based on the values of.

CI j, F. MPC,ff and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, j

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).

APPROVED AUG 0 21990 i

1-11 Revision 21-02-15-90

1.0 LI310 EFFLUDITS (Continued) j 1.4.1 latch Release Setpoint Determination (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) 1 The value for C,,

the concentration limit at the detector, is determined by using:'

(RW)

F)

(C_

)

(1-5)

C, i RC It C R,C i3 p2 n

MPC,ff3+' MPC

++

MPC eff2 sffn where:

n

= number of tanks to be released.

C,ff

= effective gamina isotopic concentration at the monitor for the tank combination to be released (equal to I C,4 for single tank releases).

R3(,g)3 + R2(hi)2+...+Rlfyi)n n

(16)

R3+R2 +... + Rn (I C,g)3, (I C,g)2, etc. = the total gar.aa isotopic concentration f

of first tank; second tank, etc. (pCi/ml).

]

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

2 second tank,,'etc.

Values of R for each j

tank are as follows:

l j

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

Radwaste-Secondary Tanks R.= 140 gp W pump (x no. of pumps to be run)

Primary Plant Makeup Tank R = 160 gpWpump (x no. of pumps to be:run)

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

MiE# AUG 0 21990 l

Revision 21 02-15-90

100' LICDID EFFLUDITS (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813)

(Continued) i j

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

MPCeffl, MPCeff2, etc. = values of MPC,77 from equation (14) for first tank, second tank, etc.

C, C, etc. = values of C, the total concentration, from,

g 2

equation (1-3) for the first tank,-second tank,etc.inpCi/ml.-

RW and SG88 2' 3089-2' 3088 3' N89 3'.Est 0,T,T are 3

2 3

7813 administrative 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 i

fractions RW and SG'8-2' 3089 2' 3088-3, SG89 3, B '

1,T'T3 7813 8

2 2-will be assigned such that RW7813 + 8088-2 + 3089 2 + S088-3

+ SG89-3 + B2+B3+T2 + T 3 1.0.

3 i

l APPROVED AUG 0 21990 1-13 Revision 21 02-15 90

)

T 1.0

' LIQUID EFFLUDITS (Continued)

' l.4.1. I' RADWASTE DISCHARGE LINE MONITOR (2/3-7813)

(Continued)

The 1.0 is an administrative value used to account for the potential activity released simultaneous 1y'from other release points. This assures that the total concentration from all release points to the plant discharge will not result in a rilease of concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2 from the site.

NOTE:

If C, s C,ff, then no release is possible. To increase C,,- increase dilution flow F (by running more circulating water pumps in the applicable dis-charge structure), and/or decrease the effluent flow-rates R, R, etc. -(by throttling the combined flow 3

2 as measured on 2/3F1-7643, 2FIC-4055, 2FIC 4056, 3FIC 4055 or 3FIC-4056 as appropriate) and recalculate C,using the new F. R and equation (1-5).

If there is no release associated with this monitor, the monitor setpoint should be established as close to background.

as practical to prevent spurious alarms and yet assure an alarm-should an inadvertent release occur.

APPROVED AUG A 91990 1-14 Revision 21-02-15-90

.-~

l 160 LIQUID EFFLUENTS (Continued) l-1.4.1.2 NEUTRAIEZATION SUM NFULI F.0W CONDENSATE POL: SHER DEMINERALIZER (FFCPD)

SUMP 1:SCHARGE LINI MDN T0il (batch) (2RT-781P. 3RT-7817)

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

3 l

Unit 2 or Unit 3 detector, is determined by using:

I (8)(F)tc

+

2 Tj II'7)

C 5 i

2 l

(R)(C/MPC,ff) l (B)(F)E 3

7j (1-8).

1 C3s l

(R)(C/MPC,ff) whers:

C EC(j,MPC,7f the values of C, EC,9 and MPC,ff

=

as defined in STEPS 1) and 2) for the Neutralization Sump /FFCPD Sumps.

Neutralization Sump R = 500 gpm.

L FFCPD High conductivity Sump R = 500 gpm 8

FFCPD Low Conductivity Sump R = 600 gpm 1

the instantaneous concentration at the C

=

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

=

3

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

3 simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B and B3 (each normally 2

t set to' 0.05) will be assigned such that RW7813 + S088-2

+ SG89-2 + S0 S089-3 + O2+03+T2+T3 s 1.0.

88-3 + P P R O V E D-AUG 0 2 '99 A

1-15 Rec sion 22 08-02-90 6

,.n

,,.a

,-m

,-~+,e

,--a

-~

100 LICDIO EFFLUDITS (Centicued) 1.4.1.2 EU"RAL: ZA"I0d SUMP /Fui F _0ii COM)ENSATF POL::SHE t D EMINERALIZER (FFCPD)

SUMPD3CMRG E LINE N00To t (batc il (2R"-781P. 3 ti-1817)

(Continued)

NOTE:

If C or C3s C.,j, then no release is possible.

2 To increase C or C, increase dilution f. low F (by 2

3 running more 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 C using the new 2

3 F, R and equation (1-7) or-(1-8)..

.If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release' occur.

j

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,7f) l limit. The method by which this is accomplished is as follows:

i STEP 1:

The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown-R neutralization sump and turbine plant sump) from the i

sum of the respective measured concentrations as determined by analysis:

C=

j+C +Ct+Cs+C, (1-9) q p

APPROVED AUG 0 91990 j

1-16 Revision 22 08-02-90~

m

1.0 LIQUID EFFLUENT $ (Continued)

'l.4.2 Continuous Release Setpoint Determination (Continued) where:

i total concentration (pCi/al)

C

=

the~ total gamma activity (pCi/ml) associated with g

each radionuclide,1, in the weekly composite analysis for the release stream.-

the total measured gross alpha concentration (pCi/ml)

C,

=

determined from the previous monthly composite analysis for the release stream.

1 C,

the total Fe-55 conce.ntration.(uci/mi) as determihed

=

p in the previous quarterly composin sample for-the

{

release stream.

thetotarmeasuredH-3 concentration (pci/ml) determined l

C

=

t from the previously monthly composite analysis for the

[

release stream.

the total measured concentration (pC1/ml) of Sr-89 C

=

s and Sr-90 as determined from the previous quarterly composite analysis for the release stream.

STEP 2:

The effective MPC (MPC,ff) for each release stream (steam generator blowdown, blowdown neutralization sump, or turbine plant sump) is determined using:

l (1-10) 1 MPC'II C

=

xgj_q)

( g )

(R,PC,)-(MPC,,)

((MPC )

C j_q)

(g) g)

j (RPC )

E i

g (MPC,)

(

(

p t

1-17 Revision 22 A PPR O V ED hlMo n 1999

. 100 LICID EFTLUDITS (Continued)-

1.4.2 Tontinuous Release Setpoint Determination (Continued)

.i t

ll STEP 3:

The setpoint, C, (pci/ml), for each continuous release radioactivity monitor may now be specified based on the respective values of C, IC,g, F, MPC,ff, and R to provide compliance with the limits of 10CFR20, i

Appendix B, Table II, Column 2.

The' monitor setpoint (cpm) is taken from the. applicable calibration constants i

given in Table 1-3 to correspond to the calculated l

monitor limit C, (pCi/ml).

t 6

i t

r t

i 1

'l t

t i

P t

APPROVED AUG 0'2 1990.-

e 1-18 Revision 21 02-15 90

'e-

. ~ ~.,-

,...,w,

-..e

.,4-._-

.-.w.

.4-+

1.0 LIQU10 EFFLUDITS (Continued) 1.4.2.1 NEll"RALIZATD")N SUNP DISCHARGE LINE MONITORS (2 t"-7817. 3lti-7817)

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

3 Unit 2 or' Unit 3 detector is determined by using:

(B)(F)IC (1-11) 2 g

C i I

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

(B)(F)EC7g (112) 3 C 1 1

3 (R)(C/MPC,ff) where:

C, 20,4, MPC,ff = the values of C, I C 4 and MPC,ff as defined in STEPS I and 2 for the g

4

~

Steam Generator blowdown / BPS neutra-l 11 ration sump.

1 R

, The effluent flow rate at the radiation monitor as defined in STEP 2 (maximumof500gpm).

C2=

the instantaneous concentration at the Unit 2 detector (2RT-7817)'in uti/cc C3= the instantaneous concentration at the Unit 3 detector (3RT-7817)inpCi/cc B and B are administrative values used to account for 2

3 simultaneous' releases from both SONGS 2 and SONGS 3 neutralization sumps.

The fractions B and B will be 2

3 assigned such that RW7813

• 8088-2 + 3089-2 + 3088-3 + S089-3

+B2+83+T2+T3 s 1.0 APPROVED DilG 0 9. 1990 1-19 Revision 22 08-02-90 7

-l

.l.0 LIQUl0 EFFLUENTS.'(Continued) 1.4.2.1 NEUTRALI7ATION SUMP DISCHARGE LINE MONITOR (2RT-7817. 3RT-7817)

(Continued) or C.5 I C,g; then no release is possible..

NOTE:

If C2 3

l To increase C or C, increase dilution flow F (by 2

3 i

running more circulating water pumps), and/or decrease the effluent flow rate R, (by throttling the flow as measured on 2FI-3722 and 3FI-3772), and recalculate using1the new F, R and equation (1-11) or C ?or C3 2

(1-12).

If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur.

l l

f i

APPROVED AUG 0 21990 1-20' Revision 21 02-15 90 m.,

,.-,-,,y

1.0-LICDIS EFFLUDif$

(Continued) 1.4.2.2 STEAM GENERATOR BLO W BYPASS DISCHARGE LINE MONITORS 12RT-6753. 2RT-6759. 3RT-6753. 3RT-6759)

The value for C59-2, C53-2, C59-3 or C53-3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:

(SG88 2)(F)E C j C59-2 i i

II'II)

(R)(C/MPC,ff)

C53-2 5 II

)

(R)(C/MPC,ff)

(SG88 3)(F)I C 4 C59-3 I I

II' $)

(R)(C/MPC,ff)

(SG89-3)(F)rCvi C

- (1-16) 53,3 5 g

(R)(C/MPC,ff) where:

C, I C,j, MPC,ff = values of C, I C,9 'and MPC,ff (as defined in STEPS I and 2 above) for the steam generator blowdown bypass.

R = the maximum blowdown bypass effluent flowrate per_ steam generator, 200 gpm.

C59 2 the instantaneous concentration at the Unit 2 detector (2RT-6759)inpCi/mi-C53-2 the instantaneous concentration at:the Unit 2 detector

=

(2RT-6753) in pCi/ml C$9,3 the instantaneous concentration at the Unit 3 detector

=

(3RT-6759) in pCi/ml C53-3 =

the instantaneous concentration-at the Unit 3 detector-(3RT-6753)inpCi/ml

- APPR0QD AUG 0.21990-Revision 21 1

02-15-90

7-l.0 LIQUID EFFLUDITS (Continued) 1.4.2.2 JTTAM GENERATOR B10WDOWN BYPASS DMSCHARGE LINE MONITOR 1 (21T-6753. 2RT 67 59. 3RT-6753. 3R'i-6759)

(Continued)

RW and SG88-2' 3089-2' 0088-3' 3089-3' 0 ' 0, T, T3 are 7g33 2

3 2

administrative 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 RW and SG88-2' 3089 2' S088 3' 00893 ' 0, 8, T, T3 7813 2

3 2

will be assigned such that RW7813 + 3088-2 + 8089-2 + 3088 3

+ SG 02+03+T2+T3 89-3 1.1.0.

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 C59-2, C53 2, C59-3, or C53-3sfC,g(forthe respective steam generator), then no release is possible.

To increase C59-2, C53 2, C59-3 or C33,3, increase dilution flow F (by running more 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 C59-2, C53-2, C59 3.or C53-3 using the new values of F, R and equation (1-13), (1-14), (1-15) or (1-16).

I APPROVED AUG 0 21990 1-22 Revision 21 1

02-15-90.

1.0 LIGIDEFFLUENTS (Continued) 1.4.2.2 5"EAM GENERATOR BLOWDOWN BYPASS D SCHARGE LINE MONITORS (HRT-6753. 2RT-6759. 3RT-6753. 3R" 6759)

(Continued) l If there is no release associated with this monitor, the mc'11 tor setpoint should be established as close to background as practical to prevent ~ spurious alarms.and yet assure an s

alarm should an inadvertent release occur.

j l

1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821. 3RT-7821)

~

i The value for C or C3 (the concentration limit at the 2

Unit 2 or Unit 3 detector) is determined by using:

(1-17)

.'(T)(F)IC 2'

i '4 i

Cg$

(R)(C/MPC,ff) 1 (1-18)

(T)(F)rc7j 3

.C 1

1 3

(R)(C/MPC,7f).

where:

C, j, MPC,ff = values of C, and MPCgf (as defined in STEPS 1 and 2 above) for the turbine plant sump I

1 R = 50 gpm/ pump-(x no, sump pumps-to be run)

C

- the instantaneous concentration at the Unit 2 2

' detector (2RT-7821) in Ci/ml.

C3 = the-instantaneous concentration at the Unit 3.

',etector(3RT-7821)inpCi/ml.

/

A PPROV ED - AUG 02.1990

'l-23 Revision 21 02-15-90 a

.-......l.

7 y-;&

' : 1.0 :

LMUID EFFLUDfr$;. (Continued)

[

'1.4.2.3 TURBINE PL/diLEltlP 'riONITORS' (2RT-7821. 3RT-7821) (Continued) -

T and'T are administrative values.used to account for 2

3 simultaneous-releases'from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions T2 and T will be. assigned'such 3

that RW d 3888 2 + 3089-2 + 3088 3 + SG89-3_B2+B3+T~

7813 2

+ T.3 1 1.0.

I NOTE:- 'If C or C s I C.,gl(for the respective sump),-then 2

3 i

no release is possible.

To increase' C or C,; increase-2 3

the dilution _ flow F (by running more circidating water!

l pumps)andrecalculate;C or C using the new value.

2 3

.ofFandequation(1-17)'or(1-18).

al 1

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 deaining the condensef td the outfall via this pathway. The fo1L..ng conditions.shall be met:

3 h

a.

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

i b..

The' alarm setpoint for the monitor. sball be adjusted' to take l

into account the entire discharge flow through both the normal 1

and temporary. paths.

I c.

Procedures shall require the immediate termination of the I

discharge via the temporary path if <the monitor on the normal path alarms.

APPROVED AUG'0 2.n0 1-24 Revision 21 02-15-90

- y J

4

1.0 LIQUID EFFLUENTS :(Cintinued).

1. 4 '. 2. 3 < --TURBINE PLANT SUMP MONITORS'(2RT-7821. 3RT-7821) _(Continued)

IfIhereisnoreleaseassociatedwiththismonitor,~the-monitor. setpoint should be established 'as-close to background -

as_ practical to prevent spurious alarms _and yet assure anl alarm should an. inadvertent release occur.-.

-i l

J i

i i

4

' l

'l

.i i

i 1

APP 110VED AUG 0 q jggy-1-25 Revision 22 08-02-90' I

-1

Table 1-3'-

l.iquid' Effluenf P?diation Monitor, Calibration constants, (uci/cc/ cpm)

I

t MONITOR Co 60'

'Ba-133 Cs-137-i

kRT-6753

.1.80E-8

'1.91E l i

2RT-6759 2.14E-8 l '. 99 E -'

h 3RT-6753 1.79E-8

-1.91E-8

.{

3RT-6759-1.94E-8 1.94E-8 h

2/3RT-7813 2.10E-9 3.54E-9 5.17E-9 2RT-7817 2.12E 13.64E-9 5.25E-9

.2RT-7821 2.10E-9~

3.58E-9

' 5.21E-9'

.i i

3Ri 1817-2.13E-9 3.63E-9',

5.26E ;

3RT-7821 2.11E-9 3.60E 5.19E-9,

)

i, f

l i

[

y j:

l:

t I

(a) This table providos typical (120%) calibra. tion constants' for the' liquid effluent radiation monitors.

\\

s i

APPROVED AUG 0 21990 1-26 Revision-22 1

08-07-90

I L

1.0J LIQUID EFFLUENTS- (Continued)L

{

1.5 Dose calculation for Liquid Effluents, The dose commitmen't to an individuals from radioactive ma'terials in.

1 liquid effluents released to unrestricted areas are1 calculated for.

~

,q

'the' purpose of implementing Specification:1,2.1 '.: sing the following; 1

expression.-

D, I(A,

(4tj 43;F)]-

(1-19)L f

C j

j 4

where:-

the-site related-ad01t ingestion dose commitment; A

h factor to the total body or an organ, r, for. each -

~

identified principal. gamma and beta emitter, i.,- from /

7 Table 1-4 in mreW hr per pCi/ml.

C) the_averageconcentration'of'radionuclide,i,(inthe:

9 l

undiluted liduid effluent during time period,--

a q

At in(pCi/ml).-

j

~

the dose commitment to the total. body or an organ, r, _

D;.

a from the-liquid effluent. for the time period,

~

at,-in mrem j

q F

3 the'near field average dilution factor-for C,3 during:the time period, at). - This factor is the ratio of the~ maximum undiluted liquid waste' flow during time: period, at), to the average flow from the site discharge structure to unrestricted.

t 1

receiving, waters, i

or maximum liauid radioactive waste flow 1

discharge structure exit flow.

1 1

atj the length of the jth time period-over which

$3 nd F3 are averaged for all liquid releases; q

C a

in hours.

l

. A P P ROV E D p.UG 0 9, 1990 1-27 Revision 21 1

02-19-90' L

1 l

t

w.

TABLE'l-4 D05E COMMITMENT FACTOR $*, AI'-

-(mres/hr parfpC1/ml),

Radio-

-Total Nuclide Body.

Bone.

Liver Thyroid Kidney.

Lung _

GI-LLI.

.t H3 2~80E.

2.80E 2.80E-1 2.80E-l' 2.80E,2.80E-1.

Na 4.57E-l'

-4.57E 4.57E-1 4.57E-1 4.57E-1 4.57E-1:

4.57E-1 1R <

Cr-51 5.60E0i 3.30E0 1.20E0-7.04E0 1.40E3.

Mn-54 1.35E3 7.08E3!

2.11E3:

2.17E4' Mn-56 3.15El 1.78E2 2.26E2 5.67E3 Fe 8.24E3

-5.12E4' 3.53E4 1.9'< E4

2.03E4 Fe-59 7.27E4--

8.07E4 1.90E5 5.30E4 6.23ES-Co_57 2.36E2 1.42E2 3.60E3 Co-58 1.35E3-6.04E2 l~.22 E4 Co-60 3.83E3 1.74E3 3.26E4 o

Cu-64 1.01E2

.2.14E2.

.5.40E2-

'l.83E4 Zn-65J 2.32E5 1.61ES

.5.13E5' 3.43E5 3.23E5 Br-84'

9. 39f. -2.14E2 7.37E-7:

0-88'-

9. 49 E-1.-

1.79E0 0.00E0 Sr-89

'l.43E2 4.99E3-

~8.00E2 l

Sr-90 3.01E4-1.23E5 13.55E3 Sr-91 3.71E0 9.18El 4.37E2 l6 i Sr 1.50E0~

3.48El 6.90E2 Y-90 1.62E-1 6.06E0 6.42E4 Y-91m-2.22E-3 5.72E-2 1.68E i Y-92 l '. 55E-2 5.32E-1

9.32E3-Zr-95 3.47E0 1.60El 5.12E0 8.03E0

'1.62E4' Zr-97 8.14E 8.80E-1 1.80E-1 2.70E

• 5.51E4 p~!

Nb-95 5.51E-1 1.84E0 1.02E0 1.01D 6.22E3 Nb-95m 5.51E-1 1.84E0 1.02E0

' l. 0'.E0 -

6.22E3-1 Nb-97 1.43E-3 1.55E-2 3.91E-3

'4.56E-3 L1.44El Mo-99 2.44El 1.28E2-2.90E2-2.97E2 Tc-99m 4.66E-1 1.30E-2 3'.66E-2 5.56E-1 1.79E-2 2.17El Ru-103 4.61El 1.07E2 4;08E2L 1.25E4 lS a:

Ru-106 2.01E2 1.59E3' 3.07E3

=1.03E5 Ag-llom 8.61E2 1.57E3 1.45E3.

2.85E3 5.91E5 Sn-113 2.20E5-a Sb-124 1.10E2-2.77E2 5.23E0 6.70E-1 7~.85E3 1

Sb-125 4.42El 2.20E2 2.37E0 2.00E-1 2.30E4 1.94E3 Te-129m 1.48E2

.9.33E2 3.48E2 3.20E2 3.89E3 4.67E3 g

Te-132 1.24E2 2.04E2 1.32E2 1~.46E2 1.27E3 6.25E3 1 -131 1.79E2-2.18E2 3.12E2-1.02E5 5.36E2 8.24El I -132.

9.96E0 1.06El 2.84El 9.96E2 4.54El 5.35E0 I -133 3.95El 7.46El 1.30E2 1.91E4 2.26E2 1.17E2 I -134 5.40E0 5.56E0 1.51El 2.52E2-2.40El 1.32E-2 I -135

'2.24El 2.32El 6.08El' 4.01E3 9.75El 6.87El

• Source: USNRC NUREG-0133, Section 4.3.1 APPROTED MJG 0 21990 1-28 Revision 22 08-02-90

E TABLE 1-4

~

D0SE COMMITMENT-FACTOR $*, A I'

(mrem /hr.per pC1/ml) l s

4 Radio--

-Total Nuclide Body Bone

. Liver

. Thyroid Kidney Lung GI-LLI Cs-134-1.33E4 6.84E3 1.63E4 5.27E3-1.75E3-2.85E2 C s-136 --

2.04E3'

- 7.16E2 2.83E3 1.57E3 2.16E2 3.21E2 1

Cs-137

-7.85E3 8.77E3 l'.20E4 4.07E3 1.35E3 2.32E2 Cs-138' 5.94E0 -

6.07E0 1.20El 8.81E0

. 8.70E-1 5.11E

• Ba-139 2.30E-1 7.85E0:

5.59E 5.~ 23 E. 3.17E-3'

,1. 39El-Ba-140 1.08E2 1.65E3

.2.07E01 7.00E-1 1.18E0

-3.39E3 La-140; 2.10E-1 1.58E0-8.00E-1

.5.84E4-Ce-141.

'2.60E-1 3.43E0 2.32E0 1.08E0:

18.86E3 Ce-143 4.94E-2

. 6,00E-1:

4.46E2 2.00E-1 51.67E4 (R

Ce-144-9.59E0 1.99E2 7.47El.

4.43E1

-6.04E4 Nd-147

2.74E-1 3.96E0' 4.58E0

-2.68E0 L2.20E4-W -187.

2.68E0-9.16E0 7.66E0-2.51E3' Np-239 1.92E-3 3.53E-2 3.47E-3' l'.08E-2 7.13E2 i

• Source: 'USNRC NUREG-0133, Section 4.3.1 i

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N;

}

i 4

-i 1

p APPROVED AUG 0 21990 t

1-29 Revision 22 I

08-02;90-i.

!?

j

+

110.

LIQUID EFFLUENTSJ (Continued)=

-1,6 ; Representative Sampling Priorfto sampling of aibatch. release, each batch shall be thoroughly mixed to' assure. represent'ative sampling.

The methodology. for mixing and sampling is described in

~S0123 !!I-5.11.

" Units 2/3 Liquid Effluent Release Permit" and S0123-111-5.2.23,, " Units 2/3 Liquid, Effluent Sample Collection",

1 3

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APPI[OV ED AUG 0 2.1990 3081c. man 1-30 Revision 21 02-15 i

7 2~ 0 i l4ASE005> EFFLUENTS 2.1-DOSE RATE SPECIFICATION

-2.1.1' The. dose:. rate in unrestricted areas due to rsdioactive materials released in gaseous effluents ~ from-the site (see Figure 2-2)E shall. be limited to the following:-

g a.-

For noble gase's:'_ Less than or equal-to 500 mrem /yr l

to the' total body and less than or equal _ to 3000 mres/yr to the skin, and

~I b.-

For all radiciodines, tritium and for--all radioactive materials:in particulate form with half.

i lives greater than 8 days:: Less.than or equal to i

1500 mres/yr to any organ.

1 APPLICABILITY: At all: times ACTION:-

With dose rate (s) exceeding the above limits, immediately decrease

-the release rata to:within the above limit (s).

j SURVEILLANCE REQUIREMENTS, b

1

.1 The dose rate due to noble. gases in gaseous effluents.shall be l

determined-to be within the'above limits?in accordance with.

i Section 2.7.-

q

.2 The dose rate due to radiciodines,: tritium and radioactive

.i 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-J with the sampling and analysis ~ program'specified Lin Table 2-1.

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i APPROVED AUG 0 21990 1

1 2 Revision 21 1

02-15-90

1II M

TABLE 2-l'

'RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis-Activity of. Detection i

3 Type-Frequency Frequency Analysis (pC1/ml)a Batch P

P Waste Gas.

Each Tank Each Tank' Principal Gama Emitters 9 lx10 *-

Decay Tank.

Grab Sample-q Incinerated' Each Batchi

-Each Batchi Principal Gama Emitters 9 5x10-'

Oilh Grab Sample:

1 Continuous Principal Gama Emitters 9:

1x10-4 q

Tritium 1x10 *-

q Wd I-131

-1x10-**

Continuousf Charcoal-Sampler Sample -

I-133 lx10-**

d yd Continuousf Particulate Principal Gama Emitters 9 lx10-

Sampler Sample-(1-131 and Others)

M h

Continuousf Composite Gross Alpha 1x10-**'

Sampler Particulate-Sample Q

Continuousf Composite

Sr-89 and Sr-90 1x10-**'

R Sampler Particulate Sample Continuousf Noble Gas Noble Gases 1x10 *-

Monitor Monitor Gross Beta-or Gama

• Sampling frequencies for noble gases and tritium are.

CONTINU0US PATHWAYS:

Containment Purge'-J42" :

Each Purge,c b

Containment Purge - 8" Monthly Grabb Condenser Air Ejector Monthly Graa -

b Plant Vent Stack Weekly Grab)te

\\

APPROVED AUG 0 2 1990 I

2-2 Revision 22 08 02-90

TABLE 2-1 -(Continued)-

JABLE NOTATION a.

The LLD is the smallest concentration of radioactive material inc a sample-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):

4.66 s LLD =

b E e: V e 2.22 x 10" Y e exp

(-Aat)-

i

.where:

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

i sbjis the standard deviation of the~ background counting rate.or of the:

counting rate of a blank sample as appropriate (as counts per minute),

R 1

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

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

2.22 x 106 is the number of transformations:per minute per microcurie, l

Y is'the fractional radiochemical yield (when applicable),-

1 A is the radioactive. decay constant for the-particular radionuclide,- and at is the elapsed time tietween midpoint'of sample collection and time of '

'I counting- (for plant effluents, not environmental" samples).

The value of-sb used:in the calculation of:the LLD forf 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.--

In calculating the LLD for. a radionuclide determined by gamma ray spectrometry,.

-the background should include;the typical contributions of other radionuclides.

normally present in the! samples.

Typical values of E, V,'Y and at should be used !

in the-calculation.

l It should be recognized that. the LLD is defined as an a orior'i (before the fact) limit representing the capability of t'he measurement. system and not as a-i costeriori (after the' fact) limit for a particular measurement.*

t

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

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

1 (2) _ Currie, L.? A., " Limits for Qualitative Detection and Quantitative l Determination -

~

Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Technique.4" Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

2-3 Revision'21 02-15-90 j

APPROVED AUG 0 21990

TABLE 2 (Continued)

TABLE NOTATION b.

Analyses shall also be performed following shutdown, startup, or alTHERMAL -

POWER change exceeding 15 percent'of the RATED THERMAL' POWER within'a 1-hour period. >This-requirement does not apply-if:!(1) analysis shows that: the DOSE A.

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..

i c.

Tritium grab ' samples.shall be.takeri at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal _ is flooded.

d.

- Samples'shall be changed at-least once per 7 days and analyses.shall be

~

completed within-48 hourst after. changing (or = after removal from sampler).

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.for.at_least 7.

t l.

~ days following each; shutdown,:startup, or a THERMAL POWER change exceeding,15-percent of RATED THERMAL POWER-in -1 hour and-analyses shall; be completed-within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected.for 24_ hours are i

analyzed,- the corresponding lLLDs may be increased by a factor of,10.

The, gr latter 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:

d has not increased more. than a factor of.3.

j 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..

-i f.

The ratio of the sample flow rate'to the sampled stream flow. rate shall. be known for the time period covered by each-doseior 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,i Fe-59,-C0-58, 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 toibe detected and reported.

Other 3

peaks which are measurable and= identifiable, together with the above nuclides, i

l 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.

e i.

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

i 1

A PPR O V E D AUG '() E 1990 2-4 Revision 22 08-02-90

2.0 SASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GMiji 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 mred fcr 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 subsequent releases will be in compliance with Specifica-tion 2.2.1.

SURVEILLANCE RE0VIREMENTS

.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.

APPROVED AUG 0 2 1990 2-5 Revision 21 02-15-90 1

y V2.0.;,14ASE00$' EFFLUENTS"(C5ntinued)l

i 2.3 DOSE ~- RADIDIODINES.'RADIDACTIVE' MATERIALS IN PARTICULATE FORM AND IRITIUM SPECIFICATION J

2.3.1 The dose to an individual from: tritium, radiciodines and l

radioactive materials in ' particulate form with half-lives greater than 8 days in gaseous effluents released, from'each -.

'~

. reactor unit, from _the site _ (see Figurei2-2): shall be: limited-to the following:

g 4

. Less than or_ equal-to 7.5 mrem

_ During any. calendar ; quarter:l a.-

_to any organ:and,

-b.

During any calendar year:

Less than or equal:to'15. mrem to j

any: organ.

c.

Less than 0.1% of the limits of 2.3.1L:(a) sand (b)!as a re ult:

1 of burning. contaminated oil.

2 y

' APPLICABILITY:. At all times' l'

ACTION:

.a.

- With the: calculated dose from the release o'f iritium, 1

radioiodines, and radioactive materials in' particulate form,.

L

-with half livest greater than 8 days,L in gaseous effluents 1

exceeding.'anyzof the above limits, in;11eu' of any other 1

h.

re > ort required byfTechnical< Specification 6.9.1, prepart and L

su)mit to the Commission withinl30 days pursuant to: Technical L

'_ Specification 6.9.2 a Special. Report which Lidentifies?the cause(s) for exceeding ~the limit;and defines the corrective' actions taken to reduce releases and.the proposed actions:to a

be taken to: assure that subsequent releases w;11 be in z

compliance with Specification 2.3.1.

SURVEILLANCE REQUIREMENTS

.1

' Dose Calculation's Cumul'ative dose contributions for the current L

calendar quarter:and current' calendar year shall be determined in accordance with!Section 2.8 at least once:per 31 days.

i l

t APPROVED AUG 0 21990

.l i.

L 2-6--

Revision.21'

[

02-15-90 l

L i

l m

n n

?!

-2c0 SASE005 EFFLUENTS (Continued)1 2.4; GASEOUS RADWASTE TREATMENT.

4 SPECIFICATION 2.4.1

.The GASEOUS'RADWASTE TREATMENT SYSTEM'and the VENTILATION EXHAUST. TREATMENT SYSTEM shal'1 be operable.

The appropriate portions of the GASEOUS RADWASid TREATMENT SYSTEM shall be used to reduce radioactive.

materials in gaseous. waste prior to their discharge when the projected _ gaseous effluent air doses due to i

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 eradefor beta radiation.

Theiappropriate-portions of the VENTILATION EXHAUSTz TREATMENT SYSTEM shall-be used:to reduce radicactive 3i materialsLin gaseous waste prior toitheir ' discharge.

when the projected doses due-to gaseous effluent 1 1

1 releases from;the. site (see Figure 2-2) when averaged.

over 31Ldays would' exceed 0.3. mrem to any organ.*

j

[

APPLICABILITYi At all -times ACTION:'

a.-

With gaseous waste being discharged'without treatment

]

and.in excess of the above limits, in lieu of anylother 1

report required by Technica1tSpecification.6.9.1,;

j prepare and submit?to;the Commission within 30 days, pursuant-to Technical S>ecification 6.9.2, a Special-Report which; includes 1tle followingTinformatio_n:

- l'. -

Explanation. of why_ gaseous-radwast'e wasfbeing 1

l

-discharged without treatmenthidentification 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-r recurrence, l

L SURVEILLANCE REQUIREMENTS

.1 Doses'due tofgaseous releases from the site shall be: projected l

at'least once per 31 days, in accordance with~Section 3.2..

i g

q r

APPROVED AUG () M990' "These-doses are per reactor unit.-

2-7 Revision'22 08-02-90

.r s

8

- ~.- -

7-_-.

~

'SASE005 EFFLUENTS (Continued)>

2.0; 2.4 GASEOUS RADWASTE TREATMENT (Continued)-

j SURVEILLANCE REQUIREMENTS (Continued):

DurinkSEOUS'RADWASTETREATMENT.SYSTEMandVENTILATIONEX

.2 the G i"

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 appropriatei

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 GA0E00S RADWASTE-TREATMENT-SYSTEM;and-VENTILATION EXHAUSTr R ': !

TREATMENT. SYSTEM shall be demonstrated.0PERABLE.by operating:

t

'the GASEOUS RADWASTE TREATMENT SYSTEM equipment and=,1 eas

=t VENTILATION' EXHAUST ~ TREATMENT SYSTEM l equipment for at

-l 3

15-minutes' prior to processing. gases!unless2the~ appropriate gaseous radwaste system has been utilized;to process p

radioactive gaseous effluents during the previous 92 days, n

I L

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L APPROVED AUG 0 E 1990 l

'I

'2-8 Revision 22 L

08-02-90 i

.. ~..--.,.,

.u.

J,

-2.0 SASE005 EFFLUENTS f(Continue'))

d 2.5= TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose commitment to' any member of the r

public, due to releases of radioactivity and radiation,-

from uranium-fuel cycle sources-shall be limited to 4

-less'than or equal' to 25 mrem to the total body or any i

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 f"om the' release of-radioactive materials in liquid or gaseous effluents.

1 exceeding twice the limits af Specifications:1.2.1.a.

o

.1.2.1.b,J2.2.1.a. 2.2.1.b; T..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,-

l Nuclear Reactor Regulation,: U.S.= Nuclear Regulatory '

.t Commission, Washington, D.C; 20555, within 30 days,-

which defines =the corrective action to be taken to 1

reduce subsequent releases-to prevent _ recurrence of-1 exceeding the limits of Specification' 2.5.1; This

.Special Report shall-include'an analysis which-

-estimates the radiation exposure-(dose) toca member of.

the public:from uranium fuel cycle' sources including -

1 all effluent pathways and direct radiation)(for a'12

-i

- consecutive month period thatlincludes the release (s) covered by this report.

If the estimated dose (s).

j excceds the limits of Specification 2.5.1, and if the

- j release condition resulting in violation of 40 CFR 190 t'

has not already been corrected,.the Special Report.

I 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' request, and~a; variance is granted until' staff actioncon the:-

request'is complete. The' variance-only: relates.to.the limits of340'CFR 190, and does: not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as-addressed:elsewheretin this.ODCM.

SURVEILLANCE RE0VIREMENTS a

' Dose Calculatiani l Cumulative? ose contributions from liquid-

.,1 d

i and: gaseous effluentsishall be determined -in'accordance with surveillance 1.2.1.1, 2.2.-l.1,'and 2.3.1.1'.

i k

A PPROV ED Ai]G () S 1990 2-9

' Revision 21 i

02-15-90

[

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.et sustfre eBS -

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a sumemme aus.ensse we-'atavese -

e-se-o -= --

B esmause ouctases 8

at emase conse=ese swecesavise

==- a ~~ = = a* = a :

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a set F e

ses s-p

,s&.....

g

. g.,,, -.. ~,

.t....,

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.,uf g

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/_

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l-

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S -'

& l'm

_ ^fl,

=

p s,

r

^ %( __,...____., -

(.e 4

+...-

• g t f_

?~ 4~ D'igp{

rp

- s....

-== -*g

=

e

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SITE BOUNDARY FOR GASEOUS EFFLUENTS-FIGURE 2

REFERENCE:

TECHNICAL SPECIFICATIONS, FIGURE-5.1-3 2-10 Revision 21

~02-15-90'

.i,.,-

aN

___.__________Lg---"-d.-

-- --+-

a.s_e

-4

,.e--

---'s

+4

--.r.w1

" -' mpy

• .e'r=---

.--*wc-

.'s.

m

---

w_--_m.

mw

~ 2 0;,

SASE005 EFFLUENTS (Continued).

l 7

-\\

2.61 Methods of calculation' for Saseous Effluent Monitor Satooints

. Administrative values' are used to reduce each setpoint to-account -

i for the potential activity in other release's.. These' administrative

. values shall be periodically reviewed based on actual release data' l

and revised as required.-

^

t 2.6.1 PLANT' VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865 ~

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

l Forl the. purpose of implementation of Specification. 2.1.1,.

a the alarm setpoint levelifor noble gas monitors is. based i

on the-gaseous effluent: flow rate and the meteorological l

dispersion-factor.

Ig.tal - Body

-The:concent' ration at the detector correspond'ing to a.

l 500 mrein/yr tota 11 body dose' rate at.the exclusion area.

~

3 boundary is. determined by:=

J i.

(0.38)(2120 sec) ( 500 mrem /yr)'(10 i m*/cc)-

(2-1)

Ri I

C det = (Flow rate, cfm)-(X/Q, sec/m")(I (K, stag /y.p)- (:._Qj -)).

j i

pC1/m C

)

tot; where:

C

- the instantaneous concentration at the:detec' tor, det pCi/cc an administrative value used to account for 0.38

=

q potential activity from other gaseous release-l pathways:

a n

i APPROVED AUG 0 9, 1990 2-11 Revision 22 08-02-90 4

2. 0_

GASE0US EFFLUENTS -(Continued)-

2 '. 6.1 PLANT VENT' STACK - 2/3RT-7808, 2RT-7865-1,-3RT-7865-1.

.(Continued)

K.

- _the total' body dose conversion factor for the ith g

gamma emitting noble _ gas, mrem /yr per pCi/ms, from Table _2-4 C

- concentration of the ith noble gas, as determined

]

g by, sample-analysis, pC1/cc1 lC

= total concentration 'of noble-gases,: asidetermined tot-by sample analysis, (pCi/cc) = IC1g 1

4 a

Flow Rate; the plant Event' flow rate, cfm

=

-(83,000 cfm/ fan (x no. of fans to be.run)?

l

+ 17,500 cfm (laundry facility) 2120

--conversionconstant,'cfmperm*/sec i

l 1

.,500 mrem /yr total body dose-rate limit,. as specified. by J

Specification 2.I'.1.a X/Q-historical annual average dispersion factor, g

=

-seC/ms'

' 4.8E-6_

.sec/m3

=

Skin The concentration:at:the' detector corresponding to.a-i

-l 3000 mrem /yr skin' dose rate at?the exclusion area boundary is determined.by:

i (0.38)(2120,.Qc 1 (3000 mnm/yr)/(10 ' m*/cc)

(2-2)

R Cdet

.(Flow : rate, cfm) (X/Q, sec/m')[r(Ly + 1.1M, mrem /vr)(._g,j

)]

4 i

pCi/m*

Ctott og

. APPROVED AUG 0 2 1990' 2-12 Revision.22

{

08-02-90 1

+; L

_c.

- L_

T2001 GASE0USEFFLUENTS'(Continued).

2.6;1-PLANT--VENT STACK --2/3RT-7808 2RT-7865-1, 3RT-7865-li-(Continued)

'where:

skin. Dose Conversion Factor for the ith noble L

=

gas, mrem /yr per pCi/ms, from Table 2-4

)

!M

=. air Dose Conversion Factor for the ith noble 4

gas, mrem /yr per pCi/ms, from-Table 2-4(

-1 M

lil

= conversion factar to convert gamma ~ air dose to o

skin dose-3000Jmrem/yr

=: ' skin. dose rate ;1imit,; as specified by Specification 2.1.1;at Other values in equation'(2-2) are defined in equatio'n (2-1).

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

j The maximum permissible alarm setpoint (cpm) is ' determined usitig 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, Cdet (the smaller i

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

The calibration constant i

i used:is based on Kr-85'orson Xe-133,'whichever yields a 1ower detection efficiency:(the largest value-in terms of pCi/cc/ cpm).

-The alarm setpoint will be maintained at _ a value' notLgreater t

than the maximum permissible ' alarm setpoint.

APPROVED AUG 0 21990 2-13

. Revision 21 y

02-15-90 4

,n a-q

+ v 2.0' GASE0US EFFLUENTS -(Continued):

-i

> 2. 6. l'.

PLANTVENTSTACK+2/3RT-7808,-2RT17865-1,3RT-7865-1. (Continued)L

.j If.there is no release associated with this monitor, the monitor:

- setpoint should be established as close as-practical to.

background to prevent spurious alarms and yet assure ~an alarm.

,i should -inadvertent release' occur.

2.6'.l.2 2RT-7865-1 and 3RT-7865-1' Wide Ranae' Gas Monitors-l-'

The maximum release l rate. (pC1/sec) for: Wide Range Gas-Monitorsiis. determined.by converting the concentration at

-the detector, Cdet'..(pci/cc) to an equivalent release-

~

fd'

-rate'in Ci/sec,'as follows:

ul 4

A 1Cdet. uCi/cc)(flowrate. cc/sec)

(2-3)j max where:

the-maximum permissible release rate,1 Ci/sec A

=

max the smaller of the values o'f C obtained C

det det from equations 1(2-1) Lor (2-2).

r-Flow Rate flow rate, cc/sec

=

- (3.917 x 10E cc/sec~per. fan)!(number of fans to be run)' + 8.^259 x?10' cc/sec-(laundry facility),

2-a factor? to compensatesfor-the split flow l

t between-Unit.2 and Unit.3 plant vent" stacks-The release rate setpoint.wil1 not be set greater than the j

maximum release rate determined above,'when this monitor i

is being used to: meet the requirements of Specification'2.1.1.

APPROVED AUG 0 21990 q

2 Revision 21 02-15-90

r L

. 200', GASE0US EFFLUENTS (Continued) 2;6.lf PLANT VENT STAG _ - 2/3itT-7808, 2RT-7865-1~, 3RT-7865-1 (Continued)

~

L

.If there is no release associated with this monitor,,the L.

monitor setpoint-should be' established as closeas practical to i

J L

' background to-prevent. spurious alarms and-yetl assure; an alarm -

should:an inadvertent release occur.'-

2.6.2

- CONDENSER-EVACUATION' SYSTEM l 2RT-7818.- 2RT-7870-1,l3RT-7818 or '

J 3RT-7.870 2.6.2.1'L2RT-7818 and 3RT-7818 Condenser Air Eiector Monitors For the purpose of implementation of Specification 2.'1.1, the.

alarm setpointilevel for noble gas monitors is based on the gas-

~

I

. eous 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 exclus'ioi area boundary is determined by using:

Total Body ci (0.1)(0.5)(2120 Nsec)(500 mrem /yr)-(10"m*/cc)-

C (2-4) det = (Flow rate, cfm) (X/Q, sec/m8)[I (K, mrem /vr) ( _Lj_-)]

1 4

g i

pCi/m*

Ctot The concentration at the detector corresponding to.a-3000 mrem /yr skin dose rato at the exclusion area boundary; is determined by using:

Shin l

(0,1)(0.5)(2120

[sec)(3000 mrem /yr)(10"m*/cc) det --(Flow rate, cfm) (X/Q,-sec/ms)[I(L +-1.lMj, mrem /vr)( _Gj_)]T(2-4 C

i j

i pC1/m" C

j tot-5 i

APPROVED AUG 02-1990 2-15.

. Revision 21 02-15.

)

I s

a

I

'2.0 GASE0USEFFLUENTS-(Continued) 2.6.2:

CONDENSER-EVACUATION SYSTEM - 2RT-7818, 2RT-7870 1, 3RT-7818-or 3RT-7870-1 (Continued)-

where:

0.~1'is an administrative value'used to account'forc potentialract',vity 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,:above.

i The smaller of.the values C fromequations(2-4).orL det (2-4a) is to' be used in determining;the maximum permissible-i

- monitor alarm setpoint- (cpm), :as follows:.

i l

l The maximum: permissible' alarm setting (cpm)'is 1

I determined by-using the calibration constant for.

j.

the corresponding condenser Evacuation System Monitor given. in Table-2-3.

The maximum permissible alarm-setpoint is the cpm value corresponding-to the i

r L

3 concentration,= Cdet, [ smaller value from equation-L (2-4)or,.:(2-4a)].

1

]

g The calibration: constant used is based on Kr-85 or on-i i

Xe-133,' whichever yields a lower detection efficiency 1

i (higher value in' terms of pCi/cc/ cpm). Thef i

alarm setpoint will not be set greater than thei maximum permissible alarm. setting'determin'ed' above; ci 1

e APPROVED AUG 0 2'1990

'2-16 Revision 21

.02-15-90 f

Y 2.0.-

GASE0US EFFLUENTS (Continued)

~2.6.2 CONDENSER EVACUATION SYSTEM =- 2RT-7818, 2RT-7870-1,-3RT-7818 or 3RT-7870-1 (Continued)

If there is no release associated with-this: monitor, the monitor setpoint should be established as close as i

l practicEl to bP.ckground to. prevent' spurious alarms yet.'

l assure an alarm should an inadvertent release occur.

1 2.6;2.2 2RT-7870-liand 3RT-7870-1 Wide Ranoe Gas' Monitors j

1 The maximum release rate (pC /sec) for Wide Range Gas Monitor

'l is determined by converting the. concentration at the detector,7 Cdet;(pC_1/cc), _ to an-equivalent release rate in pCi/sec -

-]

j A

= (Cdet, pCi/cc) -(flow rate, cc/sec) max l

where:-

-l A

- the maximum permissible release ' rate, pCi/sec7 max Cdet = the smaller value.of Cdet, as_obtained from i

equations.(2-4) and (2-4a):

.j flow rate-

= flow rate 'of the! condenser air ejector, cc/sec

=.4.719ES cc/sec-(conservatively assumed as design j

flow rate)

If there is no release associated with this monitor,"the l

monitor setpoint. shoulf be. establishedfas lclose as practical-

'to background to prevent spurious alarms-yet assure an alarm should an inadvertent release occur.

l

~. !

APPROV ED. AUG 0 2'1990-2-17' Revision 21 02-15-90

f.

,%\\'

. 200 GASE0US EFFLUENTS (Continued)

+

2.6.3 CONTAINMENT PURGE'-12RT-7823,'3RT-7828, 2RT-78'65, 3RT-7865' o,

For' the purpose of implementation of Specification-2.1.1;;

l the: alarm'setpoint level for noble gas monitors is. based on the gaseous effluent. flow rate and the meteorological dispersion'

{

factor.

i t

The concentrationiat ~ the. detector corresponding to a-total-

~

body, dose rate of-500 mrem /yr'at-the exclusion boundary is:.

determined by using:n Tota 1> Body t

r.

f (0.38)(P)(2120,9[,c (500 mrem /yr)110YmVcc)

(2 6): bi L

j C

det2 -(Flow-rate, cfm): (X/Q, sec/m')[I-(K, mrem /vr) ( lj_ -)).

4 f

1 pC1/m"-

C tot f

(0.38)(P)(2120,$j[,c)(500 mrem /yr)(10

'm*/cc)

(2-7) A-C det3 -(Flow rate, cfm)7(X/Q,.sec/m")[I_'(K, mrem /vr).( lj_ )]

'j 1

pCi/m" C tot' I

4 l

The concentration at:the detector corresponding-to a1 3000 mrem /yr skin dose' rate at the exclusion area

- i y

\\

l

-boundary is determined by using:~

1 l

Shin I

T f

(0.38)(P2)(2120 f [,c ') (3000 mrem /yr) (10f m*/cc)

(2-6'a) ki

^

C g j det2 =(Flow rate, cfm) (X/Q, sec/ms)[I(L + 1;1M,; mrem /vr)( Gj_ )]

j j

.i pC1/m" -

C 1

tot l f

(0.38)(P3)(2120,$ ec ) (3000 mreMyr) (10 m*/cc)

' (2-7a)l C et3 -(Flow rate, cfm)-(X/Q, sec/m")[I(L

/

d j + 1.lM,. mrem /vr)(-lj_;)].

j i

pCi/m" C

tot

.{

4 p'

APPROVED AUG 0 2 1990 2-18 Revision 22 08-02-90 e

I a---

,.--n-.

.+-~,-wr

-e

y 2.0 GASE005 EFFLUENTS'(Continued)j

2. 6.3,

CONTAINMENT PURGE 1 2RT-782803RT-7828,,2RT-7865,-3RT-7865-

-(Continued)-

where:

Chet2=Theinstant'neous. concentration:oftheUnit2 detector -

a

'l in pCi/cc.-

Cdet3;= The; instantaneous concentration ofithe Unit 3-detector

j

<in-pCi/cc.

l 0.38 is an' administrative 1 values used to; account for potential

(

activity.from other gaseous release pathways'.

P Land Pa are administrative values'used to acc(ent for simultaneous purges'of both. SONGS 2 and SONGS 3.; The' l

fractions'P24and Ps.will'be assigned such that-P + P s 1.0.

J

' Flow rate the observed maximum flowrate in.'cfm from the

=

unit specificimonitor 7828. Default values will' 1

-be the following conservative measured flows:

y 50,000 cfm full purge

=

3,000 cfm mini-purge.

-1

=

'(The above values replace:the smaller design -

flowrates.)

a Other parameters are as 'specified.in 2.6.1.1 above, f

i The smaller of the values of maximum permissible' C from det2

- equation (2-6) or (2-6a) and C from equations (2-7)l det3

+

or (227a) is to'be used in determining the maximum permissible 7

monitor alarm setpoints.

l APPROVED 'AUG 0 2 1990 1

2 ReviAion22~

08-02-90' 1.-

~

e

'j_

2.0L GASE0US EFFLUENTS L(Continued)_

2.6.3-CONTAINMENT PURGE --2RT-7828,' 3RT-7828,. 2RT-7865, 3RT-7865 (Continued);

' 2.6.3.1' Maximum Permissible Alarm Settino (RT-7865)

.I The' maximum permissible' alarm setting for the Wide Range Gas 1

Monitor expressed as a maximum release rate ( Ci/sec) is;

~

determined by converting.the concentrat1on at the detector, Cdet:(pCi/cc),to an equivalent release rate.in Ci/sec.

-A,,x ---(Cdet, pCi/ccT (f1_ow rate, cc/sec)-

where:

A

'= the maximum permissible release rate /(pci/cc)-

max.

C

- the smaller value of Cdet,.as obtained from det.

eg'uationl(2-6,-26a)forUnit'2for(2-7,.2-7a)

J for Unit 3.

flow rate- = ~ flow-. rate, cc/sec

= 1.416E6 cc/sec for' mini'-purge:

{

2.360E7 cc/sec for main-purge.-

l

=

a I

.2 Maximum Permissible Alarm Settina (RT-7828)'

.j The maximum permissible alarm setting'for RT-7828 is:in pCi/cc and is,the-smaller of the values of'C-det2 (pci/cc)'

from equations -(2-6) and _ (2-6a)..

If there is no release associated with this monitor, the.

monitor setpoint shouldt be established _as close as: practi. cal to background to prevent 1 spurious alarms yet assure an alarm j

.should an inadvertent' release occur.

APPROVED AUG 0 2 1990.

2-20 Revision 22-08-02-90 l

l

+

l '1 h

s. L.

m

'12iO; < GASE005 EFFLUENTS 1 (Continued)(

j

._ 7

2.6.4

. WASTE GAS HEADER: '3RT-7865, 2/3RT-7808f m

L

.1 For the purpose' of Specification:2.1.1,.the' alarm setpoint level-for. noble gas' monitors is base' on the _ gaseous effluent '

d flowirate and.the meteorological dispersion factor.. :Since the:

.d

' waste gas header discharges to -the' ~ lant vent stack,- either -

p 3RT-7865 Lor.2/3RT-7808 may be used to monitor..wLsteLgastheaders l

i

- releases.

1 m The concentration atithe detector corresponding =toLa total l body-i dose rate ofj 500 mrem /yr or a skin. dose rate of 3000 mrem /yr at' J

- theexclusionareaboundaryisdeterminedbyusingequations(2-1) orc (2H2) with sample ! concentration'(Cj) and (C d) being obtained1 t

fromthewastegasdecaytAnk-tobereleased, i

+~

The~ smaller of, the values of. maximum permi,ssible concentration 1

(Cdet) from equation'(2-1) or (2-2) is to be.used'in:

determining the maximum permissible monitor alarm setpoint..

.j

- i 2/3RT-7808 The maximum' permissible alarm setting (cpm) is determined; by using the calibration. constant for plant vent stack a

t monitor 7808 given in Table 2-3.

The maximum permiisible d

.aetpoint is the cpm value corresponding to-the-concentra-1 E'

tion Cdet, (smaller value from equation (2-1):or' (2-2))..

1 l

i i

i(

APPROVED AUG 021990 I

2-21 Revision 21-02-15-90

'k t,.

-2.0 GA$a005.EFFLUDlIS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Contiitued) 3RT-7865 t

The maximum permissible alarm setting is expressed as a maximum release rate (pCi/sec) and is determined by converting the concentration at the detector, Cdet, to an equivalent release rate in pC1/see by equation (2 8).

max ? $ et uti/cci (flowrate. cc/sec)

(28)

A d

2 where:

A

= the maximum permissible release rate, pCi/sec det

'C

= the smaller value of Cdit, as obtained from det equation (2-1) or (2-2).

flowrate = flowrate, cc/sec

= 7.83E7 cc/sec for 2. fan operation or

= 3.92E7 cc/sec for 1 fan operation 2

= correction for 3 7865_ viewing only'l/2 the total Plant Vent Stack Flow.

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

i.

(fC)(

.)>Cdet (2-9) g t

L l:

4 e

APPROVED AUG 0 21990 2-22 Revision 21 02-15-90

2.0-SASE00$ EFFLUENTS (Continued)'

2.6.4

-WASTE GAS HEALIB - 3RT-7865, 2/3RT 7808 (Continued) 2.6.4.1 (Continued) where:

l rC4== total concentration in waste gas holdup tank 1

i to be released

-f=

waste gas header effluent flow rate, cfm F = - plant vent stack f1wrate in efm (166,000 cfm i

for 2 fan operation; 85,000-for 1 fan operation)-

t

+ 17,500 cfm (laundry facility) l det_= smaller of the values of C fromequation(2-1)-

C det or (2-2) with C being obtained from the waste gas holdup tank to_be released-l i

If a rekue is not possible, adjust the' waste gas'neader flow

~

by determining the maximun, permissible waste gas header effluent flow rate' corresponding to the. Vent Stack Monitor setpoint in accordance with the following:

7 4 (0.9)(Cdet)(F)-

2-10)

IC 4

i where:

L f= waste gas header effluent flow rate (cfm)

F=

plant vent stack f1'ow rate (cfm) used-in l

l equation (211) or (2-2) i

. APPROVED AUG 0 2 1990 2-23 Revision ?.1 02-15-90 i

y, w'

y-g-

,ae-,

v.y.q-+

,-vyrq, w

260 RASE 005 EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER 3RT-7865, 2/3RT-7808 (Continued) 2.6.4.1 (Continued) det = the smaller of the value of C f"0" C

det equation (2-1)or(2-2) 4=

total gamma activity (pC1/cc) of the waste rC l

i gas holdup tank to be released, as determined

.from the pre-release sample-analysis.

The 0.9 is an administrative value to account for the potential activity from other releases in the same release pathway.

i i

1 i

I f

i 1

1 APPROVED AUG 0 21990 E,14 Revision 21 I

02-15-90 3;

4 4

~~--a

Table 2-3(*)

Gaseous Effluent Radiation Monitor Calibration Constants (gCi/cc/ cpm) t MONITOR Kr-85 Xe-133

~

2/3RT-78080..

3.90E-8; 4.62E 2RT-7818A 4.27E-8 6.63E-8 l

2RT-78188 7.31E 2.07E-5 3RT-7818A-3.73E S 5.09E-8 3RT-7818B 9.31E-5 2.T1E-5 9

9 8

h t

?

. (a)This table provides. typical (120%) calibration constants for the gaseous effluent radiation monitors.

l APPROVED AUG 0 21990 2-25 Revision 21 02-15-90

2c0 GASE0US EFFLUENTS (Continued) 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 NOBLE GASES:

TB ".*t _ i I57UI0 (2-11),

D K

1_

i g + 1.1M ) M Qg (2-12)

D,

=I (L

g where:

i b

total body dose rate in unrestricte' areas due TB d

=

to radioactive materials released in gaseous effluents, in mrem /yr D

skin dose rate in unrestricted areas due to

=

s radioactive materials released in gaseous-effluents, in mrem /yr i

K

- the total body dose factor due to gamma g

emissions for each _ identified noble gas radionuclide,- 1, in mrem /yr per pCi/m' from Table 2-4.

I e

A PPROVED HUG () 21990 2-2 Revision 21-02-15-90 e

)

l 2.0:

SASE00$ EFFLUENTS (Cor.tviued) k 2.7.1 FOR NOBLE GASES:

(Continued)

Lj skin dose factor due to the beta emissions for

=

each identified noble gas radionuclide, i, in arem/yr per pCi/m' from Table 2-4 i

M g the air dose factor due to'garna emisalons for

=

each identified noble gas radionuclide,' i, in mrad /yr per pCi/m' from Table 2-4.

(conversion constant of 1.1 mres/ mrad converts air dose to skin dose.)

Q $

the measured or calculated release rate of radionuclide, g

=

i, for either continuous or batch gaseous effluents, in pCi/sec (X/Q) 4.8E-6 sec/m'. The maximum annual;

=

averageatriosphericdispersionfactorfor any sector or distance at or beyond.the unrestricted area boundary.

I 2.7.2 FOR ALL RADIO 10 DINES. TRITIUM AND FOR'ALL-RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER j

THAN EIGHT DAYS:

z [I (Pik k) i]

(2-13)

=

o where:

Do.

organ dose rate in unrestricted areas due to

=

/

i radioactive materials released in gaseous

. effluents, in mrem /yr i

A PPR O VED A060 P,1990 2-27 Revision 22 08-02-90 A

200 RASE 005 EFFLUENTS -(Contihued) l 2.7.2 FOR ALL RAD 1010 DINES. TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER T_HAN EIGHT DAYS:

(Continued) 4 the measured or calculated release rate of radionuclide, g

Q i, for either continuous or batch gaseous effluents, inpC1/sec ik the dose parameter.for radionuclide, i,.for P

pathway,. k, from Table 2 5 for the inhalation pathway in mrem /yr per' Ci/ms. The dose.

factors are based on the critical' individual organ and the child age group.

9k the highest calculated annual average

=

dispersion parameter for estimating'the I

dose to an individuali at or beyond the i

unrestricted area boundary for pathway k.

= 4.8E-6 sec/m* for the inhalation pathway.

The location is the unrestricted area in the NW sector.

I 4.3E-8 m for the food and ground plane

=

pathways.

The location is the unrestricted area in the E sector, APPIt0VED AUG 0 21990 2-28 Revision 22 08-02-90

2.0 RASE 00$ EFFLUENTS (Continued) 2.8 Gaseous Effluent Dose CrIculation 2.8.1 DOSE FROM N0fitE GASES IN GASEOUS EFFLUENTS 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 effluents is calculated using the following expressions:

2.8.1.1 For historical meteoroloav:

'3.17x10EMtIX/0T.Q)

(2-14)

~

D

=

i i

7 i

3.17x10INtIX7DTQ)

-(2-15)

D

=

i i

p e

I I

where:

D, the total gamma air dose fron, gaseous

=

effluents, in mrad g

l O

the total beta air dose from gaseous

=

p effluents, in mrad 3.17x10

(inverse seconds per year)

=

the air dose factor due to gamma. emissions for M

g each identified noble gas radionuclide, i, in.

+

mrad /yr per pCi/m' from Table 2-4 the t.ir dose due to beta emissions for each N

=

g identified noble gas radionuclide, i,. in mrad /yr per Ci/m' from Table 2-4 MP AUG 0 21990 Revision 22 08-02-90

+

,e s-

-w-

,-y,,

~

2.0.

GA$EDU$ EFFLUENTS (Continued) 2.8.1.1 For historical meteoroloov:

(Continued)

Tr/0T

= 4.8E-6 sec/m'.

The maximum annual average atmospheric dispersion factor for any sector or.

distance at or beyond the unrestricted area i

boundary.

t Qq

= the amount of noble gas radion0clide, i, released in gaseous effluents in uC1.

2.8.1.2 For meteoroloov concurrent with release:

4 NOTE.

Consistent with the methodology provided in Regulatory

?

Guide 1.109 and the following equations, RRRGS (Radioactive Release bi Report Generating System) software is used to perform the actual calculations.

M[I(at)(X/Q)3,hjj')].

(2-16)

D,,

= 1.14x10' j

i N[E(ot)(X/Q)),hjj)]

(2-17)

D,

= 1.14x10 j

j 5

where:

D,,

= the total gamma air dose from gaseous

'j effluents in sector 8, in mrad J

O,

= the total beta air dose from gaseous l

g effluents in sector e, in mrad M

= the air dose factor due to gamma. emissions g

for each identified noble gas radionuclide, i, in mrad /yr per pCi/m' from Table 2-4.

APPRoyyg pyg 9 g )ggg 2-30 Revision 22 08-02-90 ll I

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

.l 200 RASE 005 EFFLUENTS (Continued) 2.8.1.2 For meteoroloav concurrent with release:

(Continued) the air dose factor due to beta emissions N

=

4 for each identified noble gas radionuclide, 1, in mrad /yr per pC1/m' fr'om Table 2-4.

j the length of the jth time period over-At

=

j which(X/Q)),andQjjareaverag,edfor gaseous releases in hours (X/Q)),

the atmospherir, dispersion' factor for l

t time period 4t). at 'xclusion boundary location i

in sector e astermined by concurrent meteorology,insec/m' Qjj

=.the' average release rate of radionuclide, j

1, in gaseous effluent's during time period, 1

at, in pCi/sec j

l ~

2.8.2 DOSE FROM TRITIUM. RADIOI0 DINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS s

The dose to an individual from tritium, radiciodines and radioactive materials in. particulate form with half lives greater than eight days in. gaseous effluents released to unrestricted areas-is calculated using,the following expressions:

2.8.2.1 For historical meteoroloav:

D =,3.17x10'*z ((ERik k) O ]

(2-18)

W i

o i

k APPROVED AUG 0 21990 2-31 Revision 21 02-15-90

.{

l.

7.

2.0 GASE0US EFFLUENTS (Continued) 2.8.2.1 For historical meteoroloav:. (Continued)-

where:

l the total projected ' dose from gaseous I

D,

=

effluents to an individual, in mrem.

j the amount of each radionuclide, 1, Qq

=

(tritium,radioiodine, radioactive' material in particulate form with half livesgreaterthaneightdays), released-in gaseous effluents in pCi i

ik k = the sum of all. pathways k for radionuclide,.

N ER k

i, of the R, W product in mrem /yr per j

pCi/sec.

The I R N value for each ik k radionuclide,1,. is given in Table 2-6.

ik k or all N f a

The given is the maximum x R k

locations and is based on the most~

restrictive age groups.-

the dose factor for. each. identified R

ik radionuclide, i, for ' pathway k (for the-inhalation nathway in ' mrem /yr per pCi/m' and for the food and ground plane pathways in m' - mrem /yr per pCi/sec) at the controlling location.

The Rik s for each controlling location for each age group are:

given in Tables 2-7 thru 2-16.-

APPROVED AUG 0.21990 2-32 Revision 21 02-15-90

-e-,->

we>m?,-

,,ns,

-w.

.,..,.4 umws

,m.

,.y-,.

12.0-GA510HS_EFFLUENIS (Continued) 2.8.2.1 For historical meteoroloov:

(Continued)

Wk the annual average' dispersion parameter for

=

estimating the dose to an individual at the controlling location for pathway k.

TY/QT for the inhalation pathway in,sec/ms.

=

-The TT/QT for each controlling location is given in Tab 1(1 2-7 thru 2-16.

]F/({J for the food.and ground plane pathways

=

in m".

TheTEI/lTJforeachcontrolling location are given in Tables 2-7 thru 2-16.

2.8.2.2 For meteoroloav concurrent with releases:

NOTE:

Consistent with the methodology provided in Regulatory I

Guide 1.109 and the following equations,. RRRGS (Radioactive. Release A1 Report Generating System) software is used to perform the actual-calculations.

1mn D,

= 1.14 x 10" I E [(at ) (Rike) (Njke) (Oij)] (2-19).

3 where:

0,-

- the total: annual dose from gaseous effluents to an individual in sector e in mrem.

At3 = the length of the jth period over which Wjke and-Q43 are averaged for gaseous released in hours j

Q

= the average release rate of radionuclide, i, in

]

$3 gaseous effluents dtring time period at3 n pCi/see i

APPROVED AUG 0 21990 2-33 Revision 22 08-22-90

[

.J

-2.0 GASE0US EFFLUENTS (Continued)

' 2.8.2.2. For meteoroloav concurrent with releases:

(Continued)

Riks = the dose factor for each identified radionuclide i, for pathway k for sector a (for the inhalation pathway in mrem /yr per pCi/m' and for the food

.and ground plane pathways in m' mrem /yr per Ci/sec) at:the controlling location.

A. listing of Rik for the controlling locations in each landward-sector for each group is given in Tables 2-7 thru 2-16. The e is deterained by the. concurrent meteorology.

jke = the dispersion parameter for the time perihd atj W

for each pathway k for calculating the dose to an individual at the controlling location'in sector e using concurrent meteorological conditions.

\\

- (X/Q) for the inhalation pathway in sec/m'

- (D/Q) for the food and ' ground plane pathways in m

• i I

=i APPRoyyo py(, g g 3990 2-34 Revision 21 02-15-90, 4

TABLE 2-4 D0SE FACTORS FOR NCBLE GASES AND DAUGHTERS **

Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose 1

Factor K Factor L Factor M Factor N i

i i

i Radio-(mrem /yr (mrem /yr (mrad /yr (mrad /yr Nuclide perpCi/m')

perpC1/m) pernCi/m')

perpCi/m')

8 Kr-85m 1.17E3*

1.46E3 1.23E3 1.97E3 Kr-85 1.61El 1.34E3 1.72El 1.95E3 Kr-87 5.92E3 9.73E3 6.17E3 1.03E4 Kr-88 1.47E4 2.37E3 1.52E4 2.93E3 Xe-131m 9.15El 4.76E2 1.56E2 1.11E3 Xe-133m 2.51E2 9.94E2 3.27E2 1.48E3 Xe-133 2.94E2 3.06E2 3.53E2 1.05E3 Xe-135m 3.12E3 7.11E2 3.36E3 7.39E2 Xe-135 1.81E3 1.86E3 1.92E3 2.46E3 Xe-138 8.83E3 4.13E3 9.21E3 4.75E3 i

Ar-41 8.84E,3 2.69E3 9.30E3 3.28E3 i

i l

8

• l.17E3 - 1.17 x 10

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

APPROVED AUG 021990 2-35 Revision 21 02-15-90 j

TABLE 2-5 DOSE PARAMETER P

• ik CHILD AGE GROUP CRITICAL ORGAN InhalationPathway InhalationPathway Radionuclido (mrem /yr per pCi/m )

Radionuclide (mrem /yr per pCi/m )

H

.3 1.1E3 I -131 1.6E7 Cr-51 1.7E4 I -132 1.9E5 Mn-54 1.6E6 I

133 3.8E6 Co-57 5.1E5 I -134 5.1E4 Co-58 1.1E6 I -135 7.9ES Co-60 7.1E6 Cs-134 1.0E6 Sr-89 2.2E6 Cs-136 1.7E5 Sr-90 1.0E8 Cs-137 9.1ES Zr-95 2.2E6 Ba-140 1.7E6 Nb-95 6.1ES Co-141 5.4E5 Te-129m 1.8E6 Ce-144 1.2E7 i

l l

• Source: USNRC NUREG-0133, Section 5.2.1.1 l

i 1

)

APPROVED qijG 0 21990 2-06 Revision 21 02-15-90 4

TABLE 2 6 CONTROLLING LOCATION FACTORS IR N ik k k

Radionuclide mrem /yr per gCi/sec H -3 9.62E-4

.Cr 1.58E-2 Mn-54.

4.02E0 Co 57 9.95E 1 Co 58-1.16E0 Co 60 6.14E1 Sr-89 4.34El Sr-90 1.82E3 Zr-95 1.66E0 Nb-95 6.81E0 Te-129m

.4.90E0 Cs-134 3.36El Cs-136 5,73E 1 Cs-137 3.08E1 Ba-140 2.28E,

Ce-141 5.74E-1 Ce-144 1.68E1 I -131 1.97E1.

I -133 2.82E0 I -135 5.92E-1 UN-ID 3.50E0 t

i

'l

(

Footnote:

These values to be used in manual calcul'ations are the-maximum IR N for_ all locations based on the 'most restrictive age group.

ik k k

1 APPROVED AUG 0 21990 1

2-37 Revision 21 j

02-15-90

i i

IARLE 2-7 DOSE PARAMETER Rt FOR SECTOR P Page 1 of 2 Path.ty = Surf Beach Distance = 0.4 miles X/Q = 1.8E-6 sec/m' D/Q.= 8.2E-9 m**

Infant Child Teen Adult i

Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

l Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0-0-

1.2E1 5.1El 8.7El Cr-51 1.1El 2.2E4 1.2E2 1.1E5 2.3E2 3.2E5 1

Mn-54 4.5E2 6.6E6 2.7E3-J.2E7 5.3E3 9.5E7 J

Co-57 0-1.4E2 1.6E6 1.3E3 7.9E6 2.2E3 2.3E7 Co 58 0- 3.6E2 1.8E6 3.8E3 8.7E6 7.3E3 2.6E7 Co-60 1.0E3 1.0E8 1.0E4 4.9E8 2.0E4 1.5E9 Sr-89 0-6.2E3 1.0E2 1.8E4 4.9E2 2.1E4 1.5E3

'Sr-90 1.1E6

- 4.4E6 6.8E6 >

Zr-95 0-6.3E2 1.2E6 6.0E3 5.8E6 1.0E4 1.7E7 Nb-95 3.8E2 6.6ES 3.9E3 3.1E6 7.1E3 9.4E6 Te-129m 5.2E2 9.4E4 2.1E3 4.5E5 2.5E3 1.3E6 Cs-134 1.1E4 3.3E7 4.5E4 1.6E8 5.8E4 4.7E8 Cs-136 0- 1.8E3 7.2ES-7.8E3 3.4E6

,1.0E4 1.0E7 Cs-137 8.6E3 4.9E7 3.4E4 2.4E8 4.3E4 7.1E8 Ba-140 7.7E2 9.9E4 9.2E3 4.7E5 1.5E4 1.4E6 Ce-141 5.9E2 6.6E4 5.1E3 3.1E5 8.2E3 9.4E5 Ce-144 4.0E3 3.3E5

'3.5E4 1.6E6 5.6E4 4.8E6 I -131

-0 ' 1.7E5 8.3E4 5.9E5 3.9E5 8.2E5 1.2E6 I -133 4.0E4 1.2E4 1.2E5 5.6E4 1.5E5 1.7E5 I -135 8.2E3

'1.2E4 2.5E4 5.8E4 3.1E4 1.7E5 UN ID 1.2E3 3.6E6 5.4E3 1.7E7 7.1E3 5.1E7 l

t l

Inhalation Pathway, units =

5" "I

Food & Ground Pathway, units I"

j 1

APPn0VED /1UG 0 21990 2-38 Revision 21 02-15-90 t-

TABLE 2-7 DOSE PARAMETER Rj FOR SECTOR P Page 2 of 2 Pathway = Former Nixon Estate (no garden)

Distance = 2.8 miles '

X/Q = 1.2E-7 sec/m*

D/0 - 3.4E-10 m' Infant Child

- Teen Adult Inhala-Food &

Inhala-Food &

Inhala.

Food &

Inhala-Food &

t Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E2 1.1E3 1.3E3 1.3E3 Cr-51 3.6E2 3.7E6 1.1E3' 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6 Mn-54 2.5E4-1.1E9 4.3E4 1.lE9 6.7E4 1.1E9

.7.7E4 1.lE9 Co-57 4.9E3 2.7E8 1.3E4 2.7E8 3.1E4 2.7E8 3.1E4 2.7EB Co-58 1.lE4 3.0E8 3.4C4 3.0E8 9.5E4 3.0E8 1.1E5 3.0E8 Co-60 3.2E4 1.7E10 9.6E4 147E10 2.6E5 1.7E10 2.8E5 1.7E10 Sr-89 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 1.7E4 3.0E5 1 7E4 Sr-90 4.lE7 1.0E8 1 lE8 9.9E7 Zr-95 2.2E4 2.0E8 6.1E4 2.0E8 1.5ES 2.0E8 1.5E5 2.0E8 Nb-95 1.3E4 1.1E8 3.7E4 1.lE8 9.7E4 1.lE8 1.0E5 1.lE8 Te-129m 3.2E4 1.6E7 5.0E4 1.6E7 5.2E4 1.6E7 3.7E4 1.6E7 Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.lE6 5.5E9 8.5E5 5.5E9 Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 1.9E5 1.2E8 1.5E5 1.2E8 Cs-137 6.lES 8.2E9 8.3Eb 8.2E9 8.5E5 8.2E9 6.2E5 8.2E9 Ba-140 5.6E4 1.6E7 7.4E4 1.6E7 2.3E5 1.6E7 2.2E5 1.6E7 Ce-141 2.2E4 1.lE7 5.7E4 1.1E7 1.3E5 1.lE7 1.2E5 1.1E7 Ce-144 1.5ES 5.6E7 3.9E5 5.6E7 8.6E5 5.6E7 8.2E5 5.6E7 I -131 1.5E7 1.4E7 1.6E7 1.4E7 1.5E7 1.4E7 1.2E7

'l.4E7 I -133-3.6E6 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6 2.2E6 2.0E6 I -135 7.0E5 2.0E6 7.9E5

'2.0E6 6.2E5 2.0E6 4.5E5 2.0E6 i

UN-ID 6.3E4 6.0E8 1.1ES 6.0E8 1.3E5 6.0E8 1.0E5 6.0E8 I

InhalationPathway, units =*"{*(5" Food & Ground Pathway, units I*

f*f"'*(Y"I APPROVED AUG 0 21990 2-39 Revision 21 02-15-90 b

TABLE 2-8 1

l DOSE PARAMETER Rj FOR SECTOR Q Pathway-SanOnofreMgbilHomes Distance = 1.3 miles' X/Q = 7.4E-7 sec/m D/Q = 3.6E-9 m' 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 l

H -3 6.5E2 0-1.1E3 1.3E3 1.3E3 Cr-51 3.6E2 3.7E6

'1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6 Mn 54 2.5E4 1.lE9 4.3E4 1.1E9 6.7E4 1.1E9 7.7E4 1.1E9 Co-57 4.9E3 2.7E8 1.3E4 2.7E8 3.1E4 2.7E8 3.lE4 2.7E8 Co 58 1.1E4 3.0E8 3.4E4 3.0E8 9.5E4 3.0E8 1.1ES 3.0E8 Co 60 3.2E4 1.7E10 9.6E4 1.7E10 2.6ES 1.7E10 2.8E5 1.7E10 Sr-89 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 Ic7E4 3.0E5 1.7E4 Sr-90 4.1E7 1.0E8 1.1E8 9.9E7 Zr-95 2.2E4 2.0E8 6.1E4 2.0E8 1.5E5 2.0E8 1.5ES 2.0E8 Nb-95 1.3E4 1.1E8 3.7E4 1.1E8 9.7E4 1.1E8 1.0E5 1.1E8 Te-129m 3.2E4 1.6E7 5.0E4 1.' 6 E7 5.2E4 1.6E7 3.7E4 1.6E7 Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.1E6 5.5E9 8.5ES 5.5E9 1.5E5 1.2E8 Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 1.9E5 1.2E8

-6.2E5 8.2E9 Cs-137 6.1ES 8.2E9 8.3E5 8.2E9 8.5ES 8.2E9 i

Ba-140 5.6E4 1.6E7 7.4E4 1.6E7 2.3E5 1.6E7 2.2E5 1.6L7 Ce-141 2.2E4 1.1E7 5.7E4 1.1E7 1.3E5 1.1E7 1.2E5 1.1E7 Ce 144 1.5E5 5.6E7 3.9E5 5.6E7.

8.6E5 5.6E7 8.2E5 5.6E7 I -131

1. 5E7' 1.4E7 1.6E7 1.4E7 1.5E7 1.4E7 1.2E7 1.4E7 I -133 3.6E6 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6 2.2E6 2.0E6 I

135 7.0E5 2.0E6 7.9ES 2.0E6 6.2E5 2.0E6 4.5ES 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5 6.0E8 1.0E5 6.0E8 I

Inhalation Pathway, units =

Food & Ground Pathway, units I*

"I 7

APPROVED AUG 0 2 590 2-40 Revision 21 02-15-90

=t

t TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 2 of 8 Pathway = State Park 0[fice Trailer Distance = 0.6 miles X/Q = 2.2E-6 sec/m D/Q = 1.2E 8 m**

1 Infant Child Teen Adult l

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 i

H -3 0- - 0- 5.8E1 '

Cr-51 -0 0-1.5E2 2.1E5 Mn-54 - 0-3.5E3 6.3E7 Co 57 -0.

1.4E3 1.6E7 Co-58 0-4.9E3 1.7E7 Co-60 0- 1.3E4 9.8E8 Sr 89 0-0- '1.4E4 9.9E2 Sr-90 4.5E6 '

Zr-95 6.9E3 1.1E7 Nb-95 0-4.8E3 6.2E6 Te-129m 0- 0- 1.7E3 9.0E5 Cs-134 0- 0- 0-

.3.9E4 3.1E8 Cs 136 6.7E3 6.9E6 i

Cs-137 0- 0- 2.8E4 4.7E8 Ba-140 0- 0- 1.0E4 9.4E5 Ce-141 5.5E3 6.2E5 Ce-144 3.7E4 3.2E6 I -131

-0

• 0- 5.4E5 7.9E5 I -133 0- 9.8E4 1.1ES I -135 2.0E4 1.2E5 UN-ID 4.7E3 3.4E7 l

L Inhalation Pathway, units = ]f(!"

5 r

Food & Ground Pathway, units =

j APPROVED AUG 0 21990 i

2-41 Revision 21 02-15-90

1 TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 3 of 8 Pathway = Surf. Beach Guard Shack Distance = 0.7 miles X/Q = 1.8E-06 sec/m*

D/Q = 9.9E-09 m**

]

Infant Child Teen Adult Inhala-Food &

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 0- 7.2El Cr-51 1.9E2 2.7E5 Mn 54 4.4E3 7.9E7 Co-57 1.8E3 2.0E7 Co-58 6.lE3 2.2E7 Co 60 1.6E4 1.2E9 Sr-89 1.7E4 1.2E3 Sr-90 5.7E6 Zr 95 0- 8.6E3 1.4E7 Nb 95 5.9E3 7.8E6 Te 129m 2.lE3 1.lE6 Cs-134 0-4.8E4 3.9E8 Cs-136 8.4E3 8.6E6 Cs-137 3.5E4 5.9E8 Ba-140 0- 1.2E4 1.2E6 Ce-141 6.9E3 7.8E5 l

Ce-144 4.7E4 4.0E6 4

I -131

-0* 0-6.8E5 9.8E5 I -133 1.2E5 1.4E5 I -135 -0 2.6E4 1.4E5 j

UN ID 0-5.9E3 4.3E7 i

l l

l 1

Inhalation Pathway, units =

"I Food & Ground Pathway, units I"

7 l

APPROVED AtlG 0 21000 2-42 Revision 21 02-15-90 L.

TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 4 of 8 Pathway =EnlistedBeaghCheck-In Distance = 1.4 miles X/Q = 6.8E-7 sec/m D/Q = 3.2E-9 m**

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 -0.

2.9E2 '

Cr-51 0- 7.6E2 1.1E6 Mn-54 o-n-1.8E4 3.2E8 I 7.2E3 7.8E7 Co-57 Co-58 -t - 2.4E4 8.7E7 Co-60 -C-6.5E4 4.9E9 Sr-89 6.9E4 4.9E3 Sr-90 0- 2.3E7 Zr-95 -0 ~

3.4E4 5.7E7 Nb-95 2.4E4 3.1E7 Te-129m 0- 0- 8.3E3 4.5E6 Cs-134 1.9E5 1.6E9 Cs-136 -0*

3.3E4 3.4E7 Cs-137 1.4E5 2.3E9 Ba-140 0- 5.0E4 4.7E6 Ce-141- 0-2.7E4 3.1E6 Ce-144 1.9E5 1.6E7 I -131 0* 2.7E6 3.9E6 I -133 4.9ES 5.6ES I -135 1.0E5 5.8E5 UN ID 2.4E4 1.7E8 l

[

Inhalation Pathway, units =

Food & Ground Pathway, units I*

"I j

APPROVED AUG 0 21990 2-43 Revision 21 t

02-15-90

l TABLE 2-8 f

DOSE PARAMETER Rj FOR SECTOR Q Page 5 of 8 j

Pathway - Sheep (Meat)'

Distance = 1.6 miles X/Q = 5.6E-7 sec/m D/Q = 2.6E 9 m

j 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 t

H -3 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 0- 5.lEl 1.0E2 1.8E1 2.6E4 Mn 54 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E3 8.1E3 1.7E2 1.9E6 Co-58 9.7E3 0-2.0E4 5.9E2 2.1E6 Co 60 3.7E4 7.3E4 1.6E3 1.2E8

• Sr-89 5.0E4 2.6E4 1.7E3 3.lEt Sr-90 0- 1.0E6 8.1ES 5.5ES 1.3E6 Zr-95 0- 0-6.3E4 1.3E5 8.3E2 1.6E6 Nb 95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.SE5 2.0E2 6.5E5 Cs-134 0- 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 0- -0' 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.lE3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4

t. 5E3 4.3E5 I -131

-0 ' 6.6E5 4.4E5 6.6E4 7.0E5 1 -133 1.6E-2 0-8.7E-3 1.2E4 1.3E4 I -135 1.lE-18 6.4E-19.

2.5E3 1.4E4 VN-ID 0-1.lES 9.5E4 5.7E2 4.2E6 l

l l

[

l l

Inhalation Pathway, units = ]j"(Y" Food & Ground Pathway, units I*

"I 7

APPROVED AUG 0 21990 2-44 Revision 21 02-15 90

TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 6 of 8 Pathway - S. C. Res W Garden Distanca = 4.1 miles X/Q = 1.2E-07 sec/m*

D/Q = 4.lE-10 m-'

t 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 4.0E3 0-2.6E3" 1.3E3 2.3E3 Cr 51 6.lE6 1.0E7 3.3E3 1.5E7 Mn-54 0-6.5E8 9.2E8 7.7E4 2.0E9 Co-57 2.4E8 3.2E8 3.1E4 5.6E8 C0-58 3.7E8 5.9E8 1.1E5 9.1E8 Co 60 0-2.1E9 3.2E9 2.8E5 2.0E10 Sr 89 3.5E10 1.5E10 3.0E5 9.8E9 Sr-90 1.4E12 8.3 Ell 9.9E7 6.7E11 Zr-95 0-8.8E8 1.2E9 1.5E5 1.4E9 Nb-95 2.9E8 4.5E8 1.0E5 5.8E8 Te-129m 2.9E9 1.8E9 3.7E4 1.2E9 Cs-134 2.6E10' 0-1.6E10 8.5E5 1.6E10 Cs 136 2.2E8 1.7E8

.1.5E5 2.9E8 Cs-137 2.4E10 1.4E10 6.2E5 1.7E10 Ba-140 2.8E8 2.lE8 2.2E5 2.8E8 Ce-141.0- 4.0E8-5.3E8 1.2E5 5.1E8 Ce-144.l.0E10 1.3E10 8.2E5 1.lE10 I -131

-0' 4.8E10 3.lE10=

1.2E7 3.8E10 I -133 8.1E8 4.6E8 2.2E6 5.3E8 I -135 9.8E6 5.7E6 4.5E5 8.6E6 UN-ID 2.7E9 1.9E9 1.0E5 1.9E9 L

Inhalation Pathway, units = ]j"(!"

Food A. Ground Pathway, units = l*

V"I 7

APPROVED AUG 0 21990 2-45 Revision 21 02-15-90 r

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

y

TABLE 2-8 OOSE PARAMETER Rj FOR SECTOR Q Page 7 of 8 Pathway - San Clemente Ranch (No Residents)

Distance = 2.2 miles X/Q = 3.3E-7 sec/m' D/Q = 1.4E-9 m**

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

Radio-tio0 Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E3 2.4E3 1.9E3 Cr 51 4.8E6 7.4E6 6.7E6-Mn-54 6.1E8 0-8.3E8 8.0E8 Co-57 2.2E8 2.9E8 2.4E8 Co-58 3.3E8 5.1E8 4.7E8 Co-60 2.0E9 3.0E9 2.7E9 Sr-89 0- 3.lE10 1.2E10 7.2E9 Sr-90 0- 1.3E12 7.7E11 5.8 Ell i

Zr-95 7.8E8 1.lE9 9.1E8 Nb 95 0-0-

2.4E8 3.5E8 3.1E8 To 129m 2.3E9 1.4E9 7.9E8 Cs-134 2.4E10 1.5E10 9.2E9 Cs 136 9.0E7 5.7E7

, 3.6E7 Cs 137 0- 2.2E10 1.3E10 7.8E9 Ba-140 0-1.1E8 6.8E7 0-5.3E7 Ce-141 3.3E8 4.1E8 3.2E8 Ce-144 0- 9.2E9 1.2E10 9.0E9 I -131

-0

' 4.lE9 2.1E9 1.4E9 I -133 4.0E-11 1.7E-11 1.lE-11 I -135 0- 6.9E-35 3.0E-35 1.9E-35 UN-ID 2.5E9 1.7E9 1.lE9 1

l t

Inhalation Pathway, units =

Food & Ground Pathway, units I"

j{c

" #V"I j

APPROVED AUG 0 21990 1

2-46 Revision 21 02-15-90 l

TABLE 2-8 DOSE PARAMETER Ri FOR SECTOR Q Page 8 of 8 Pathway - San Clemente Ranch Adm. Offices Distance - 2.5 miles X/Q=2.7E-7sec/(m*)

D/Q = 1.1E-9 m**

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 0- 2.9E2 1.9E3 Cr-51 0-7.6E2 7.8E6 Mn-54 0- 1.8E4 1.1E9 Co-57 7.2E3 3.2E8 Co-58 0- 2.4E4 5.6E8 Co-60 6.5E4 7.6E9 Sr 89 6.9E4 7.2E9.

Sr-90 0- 2.3E7 5.8E11 Zr-95 3.4E4 9.7E8 Nb-95 0- 2.4E4 3.4E8 Te-129m 8.3E3 7.9E8 Cs-134 1.9E5 1.1E10 Cs-136 3.3E4 7.0E7 Cs-137' 1.4E5 1.0E10 Ba-140 0- 5.0E4 5.8E7 Ce-141 0- 2.7E4 3.2E8 Ce-144 1.9E5 9.0E9 I -131

-0 ' 2.7E6 1.4E9 I -133 4.9E5 5.6E5 I -135 0- 1.0E5 5.8E5 ud-ID 2.4E4 1.2E9 l

Inhalation Pathway, units =

• (!"

Food & Ground Pathway, units I"

V"I APPROVED AUG 0 21990 2-47 Revision 21 02-15-90

TABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R Page 1 of 5 Pathway-SanOnofreMgbileHomes Distance = 1.2 miles X/Q = 5.3E-7 sec/m D/Q = 3.2E-9 m**

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 H3 6.5E2 1.1E3 1.3E3 1.3E3 Cr-51 3.6E2 3.7E6 1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6 Mn-54 2.5E4 1.lE9 4.3E4 1.1E9 6.7E4 1.1E9 7.7E4.

1.1E9 Co-57 4.9E3 2.7E8 1.3E4 2.7E8 3.1E4 2.7E8-3.1E4 2.7E8 Co 58 1.1E4 3.0E8 3.4E4 3.0E8 9.5E4 3.0E8 1.1ES 3.0E8 Co-60 3.2E4 1.7E10 9.6E4 1.7E10 2.6E5 1.7E10 2.8E5 1.7E10 Sr-89 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 1.7E4 3.0E5 1.7E4 Sr-90 4.1E7 1.0E8 1.iE8 9.9E7 Zr-95 2.2E4 2.0E8 6.154 2.0E8 1.5E5 2.0E8 1.5E5 2.0E8 Nb-95 1.3E4 1.1E8 3.7E4 1.1E8 9.7E4 1.1E8 1.0E5 1.1E8 Te-129m 3.2E4 1.6E7 5.0E4 -

1.6E7 5.2E4 1.6E7 3.7E4 1.6E7 Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.1E6 5.5E9 8.5E5 5.5E9 Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 1.9E5 1.2E8

.1.5E5 1.2E8 Cs-137 6.1E5 8.2E9 8.3E5 8.2E9 8.5E5 8.2E9 6.2E5 8.2E9 Ba-140 5.6E4 1.6E7 7.4E4 1.6E7 2.3E5 1.6E7 2.2E5 1.6E7 i

Ce-141 2.2E4 1.1E7 5.7E4 1.lE7 1.3E5 1.1E7 1.2E5 1.1E7 Ce-144 1.5E5 5.6E7 3.9ES 5.6E7 8.6C5-5.6E7 8.2E5 5.6E7-I -131 1.5ET 1.4E7 1.6E7 1.4E7 1.5E7 1.4E7 1.2E7 1.iE7 I -133 3.6E6 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6 2.2E6-2.0E6 I -135 7.0E5 2.0E6 7.9ES 2.0E6 6.2E5 2.0E6 4.5E5 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5-6.0E8 1.0E5-6.0E8 i

Inhalation Pathway, units =

Food & Ground Pathway, units = I*

APPROVED AUG 0 21990 2-48 Revision 21 02-15-90

TABLE 2-9 DOSE PARAMETER Ri FOR SECTOR R Page 2 of 5 Pathway San Clemente, Ranch (No Residents)

Distance - 2.3 miles X/Q = 2.0E-7 sec/m D/Q = 1.0E 9 m**

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala i' Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E3 2.4E3-1.9E3 Cr-51 4.8E6 7.4E6 6.7E6 Mn-54 6.lE8 8.3E8 8.0E8 Co-57 0- 2.2E8 2.9E8 2.4E8 Co-58 0- 3.3E8 5.1E8 0-4.7E8 Co-60 2.0E9 3.0E9 2.7E9 Sr-89 3.lE!0 1.2E10 7.2E9 Sr-90 1.3E12 7.7E11 5.8E11 Zr 95 7.8E8 1.lE9 9.1E8 Nb 95 0- 2.4E8 0-3.5E8 3.lE8 Te 129m 2.3E9 0-1.4E9 0-7.9E8 Cs-134 0-0- 2.4E10 1.5E10 9.2E9 Cs-136 9.0E7 5.7E7

. 3.6E7 Cs-137 0-0-

2.2E10 1.3E10 7.8E9 Ba-140 1.1E8 6.8E7 5.3E7 Ce-141 3.3E8 4.1E8 3.2E8 Ce-144 9.2E9 1.2E10 9.0E9 I -131

-0

• 0- 4.1E9 2.lE9 1.4E9 I -133 4.0E-11 1.7E-Il 1.1E-11 I -135 6.9E-35 3.0E-35 1.9E-35 UN-ID 0- 2.5E9 1.7E9 1.1E9 I

Inhalation Pathway, units = ]j(yr m

Food & Ground Pathway, units = I" "I

j APPROVED AUG 0 21990 2-49 Revision 21 02-15-90 F-r

TABLE 2-9 DOSE PARAMETER Ri'FOR SECTOR R s

Page 3 of 5 Pathway = SC Ranch Packing Distance = 2.6 miles X/Q = 1.7E-07 sec/m*

D/Q - 8.2E-10 m

• Infar.t Child Teen Adult j

Inhala-Food &- Inhala-Food-&

Inhala '

Food &

Inhala '

Food &

Radio-tion Ground tion Ground tion Ground tion Ground 1

Nuclide Pathway Pathway Pathway Pathway Pathway Paihway Pathway Pathway 1

-i H -3

-0. 3.8E3 2.4E3 1.2E3 1.9E3-Cr-51 4.8E5 7.4E6 3.0E3 1.0E7 Mn-54 6.1E8 8.3E8 7.1E4 1.9E9l Co-57

. 2.2E8 2.9E8 2.9E4 5.2E8 Co 58-3.3E8 5.1E8

-!.8E4 7.8E8 Co-60 -0.

0-2.0E9 3.0E9

' 6ES~

2.0E10 Sr-89 - 3.1E10 1.2EIO i ' 865 7.2E9 Sr 90 1.3E12 7.7E11 1.1E7 5.8E11 Zr-95 7.8E8 1.1 E9 '

i.4E5 1.1E9

-3.5E0 i.5E4 4.2E8 Nb-95 2.4E8

-O'-

Te-129m 2.3E9 1.4E9 1.4E4 8.0E8 Cs-134 2.4E10 1.5E10 7.8E5 1.5E10 Cs-136 9.0E7 5.7E7 1.3E5 1.6E8 Cs 137 2.2E10 1.3E10 5.7E5.

1.6E10 Ba 140 1.1E8 - 6.8E7 2.0E5 7.0E7 Ce-141 3.3E8 4.1E8' 1.1E5 3.3E8 Ce-144 9.2E9 1.2E10 7.5E5-9.0E9 I'-131

-0

• - 4.1E9 2.1E9 1.1E7 1.4E9 I -133 4.0E-11

.0 -

1.7E-11 2.0E6 2.0E6 L

I -135 6.9E-35 3.0E-35

-4.1ES 2.0E6 UN-ID 2.5E9 1.7E9 9.5E4 1.7E9 1

I Inhalation Pathway, units = ""'*(!"

Food & Ground Pathway, units I*

f*j"'*(V"I APPROVED AUG 0 21990 1

2-50 Revision 21 02-15 or l

1 TABLE 2-9 L

DOSE PARAMETER Rj.FOR SECTOR R Page 4 of 5

)

Pathway - Sheep Meat Distance = 0.9 miles 1

X/Q = 8.3E-7-sec/m*

D/Q = 5.2E-9 m-'

1 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 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 - 5.1El 1.0E2 1.8El-2.6E4 Mn-54 7.GE2 1.4E3 4.3E2 7.6E6 Co-57 - -0-'

4.7E3 8.1E3 1.7E2 1.9E6 Co-58 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 l_ 3.7E4 7.3E4 1.6E3' 1.2E8 Sr-89 ;.5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1E5 5.5ES 1.3E6 Zr-95 :9-6.3E4 1.1E5 8.3E2 1.6E6 lb-95 J 2.4E5

- 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5ES 2.0E2 6.5E5 Cs-134 1.4E5-1.2E5-4.7E3-3.8E7 Cs-136. 5.1E3-4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 l3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 -1.5E3 2.4E3 6.6E2

.7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 1 -131

'0- 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E1 I.-135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-10 1.1E5 9.5E4 5.7E2 4.2E6 l

p l

Inhalation Pathway, units = ]f(!"

Food 2. Grc.nd Pathway, units = (m')(mrem /vr) pCi/sec 2 % M G 0 2 N00 Revision 21 i

02-15-90

TABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R t

Pathway - Deer Consumer Distance = 2.2 miles X/Q - 1.8E-7 sec/m*

D/Q - 8.8E-10 m-'

Infant Child Teen Adult l

Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

l Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway.

Pathway Pathway Pathway Pathway' Pathway Pathway Pathway l

H -3 2.8E1 2.3E1 3.5El 3.9El I

Cr-51

- -0--

5.0E4 1.0E5 9.1El 3.2E5 i

Mn-54 7.7E5 1.4E6-2.1E3 4.1E7 Co-57 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 -0-- 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 - 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3-3.]E7 Sr-90 1.0E9 8.0E8 2.7E6 1.269 i

Zr-95

. 6.2E7 1.1E8 4.1 E3 -

2. 0E8,

Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6-4.2E6 4.0E3 9.5E6 Cs-137 1.2L8 9.3E7 1.7E4 4.0E8 Ba-140 -0-- 5.0E6 4.2E6-6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131

-0 ' 6.5ES 4.3E8 3.3E5 5.9E8 I

I -133

- 1.6El 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8F

1.4E8 4

i e

t Inhalation Pathway, units = "['j"(!"

Food &GroundPathway, units =I*'}f*/s

1. 'm/vr)

APPROVED AUG 0 21990 3102c. man 2-52 Revision 21 02-15-90

TABLE 2-10 DOSE PARAMETER R FOR SECTOR A Page 1 of-3 Pathway - Camp San Mateo Distance = 3.6 miles X/Q'= 7.1E-8 sec/m*

D/Q = 4.1E-10 m

-Infant Chi,1d Teen Adult Inhala-Food &-

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 f

H -3 0- 1.3E3 Cr-51 0- -0--

l 3.3E3-3.7E6 Mn-54

!)- -0--

7.7E4-2.7E8:

1.1E9 Co-57 - 3.1E4 Co-58 1.1E5 3.0E8 Co -0-- 2.8E5 1.7E10 i

Sr-89 3.0E5 1.7E4 Sr-90 9.9E7 ;

Zr-95 1.5E5 2.0E8 Nb-95

. 1.0E5 1.1E8 Te-129m 3.7E4 1.6E7 Cs-134 8.5E5 5.5E9 Cs-136,1.5E5 1.2E8 Cs-137 6.2E5-8.2E9 Ba-140 - 2.2E5 1.6E7 Ce-141 1.2E5 1.1E7 Ce-144 8.2E5 5.6E7 I -131

-0

' I '. 2 E7 -

1.4E7 I -133 2.2E6 2.0E6 I -135 4.5E5 2.0E6 l

UN-ID ' 0-1.0:5 6.0E8 I

L i

Ij'-

1 r

I

[.

j.

Inhalation Pathway, units -

Y" l

l -

Food & Ground Pathway, units = I"2 /]c 1

I j

APPROVED AUG 0 21990 2-53 Revision 21 02-15-90 t

l

.N

TABLE 2-10 DOSE PARAMETER R FOR SECTOR A-g Page 2 of 3 Pathway = Sheep (Meat)*

Distance - 0.2 miles X/Q = 6.7E-6 sec/m D/Q - 5.2E-8 m

Infant Child Teen Adult j

Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhal a--

Food &

- Radio-tion Grcund tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway' Pathway Pathway Pathway s,

H -3 1.5E0 -

1.2E0 7.0E0 2.1E0 Cr-51 5.1El

-0 1.0E2 1.8E1 2.6E4 i

Mn-54 7.8E2 ^1.4E3-4.3E2 7.6E6 Co-57.

0- 4.7E3 8.1E3 1.7E2 1.9E6 Co-58

-0. 9.7E3 -

2.0E4 5.9E2 2.1E6 Co-60 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1E5 5.5E5 1.3Ef Ir-95 -0--

6.3E4 1.1E5 8.3E2 1.6EG 1

Nb-95 2.4E5

-0.

4.5E5 E.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E?

6.5E5 Cs-134 1.4E5 1.2E5 4.7E3

-3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 -0-.

1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 0- 1.8E4-3.0E4-4.5E3-4.3E5 I -131'

-0

• 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2.

8.7E-3 1.2E4 1.3E4 1 -135 1.1E-18 6.4E-19 2.5E3:

1.4E4 UN-ID 1.1E5 9.5E4 5.7E2 4.2E6 4

1 Inhalation Pathway, units = *[*j"($"

y Food & Ground Pathway, units I* [*f'sc" A PPR O V E D AUG 0 ?,1990 2-54 Revision 21 02-15-90

'i l

TABLE 2-10 l-DOSE PARAMETER R -FOR SECTOR A Page 3 of 3 Pathway - Deer Consumer Distance = 2.2 miles X/Q = 1.9E-7 sec/m*

D/Q = 1.4E-9 m-'

Infant Child Teen Adult l

Inhala-Food &

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 H--3 2'. 8E1 2.3E1

' 71

'3.9El Cr-51 5.0E4-1;0E5 ~

3.2E5 Mn-54 - O '- 7.7ES 1.4E6 4.1E7 Co-57 4.6E6 8.0E6 2.3E7 Co-58 9.6E6 1.9E7 2.., u3 4.7J Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 4'.9E7 2.6E7-8.3E3 3.1E7 Sr-90: 1.0E9 8.0E8 2.7E6 1.2E9 Zr-95 6.2E7 1.1E8-4.1E3 2.0E8 -

Nb-95 2.3E8. 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4-3.4E8 Cs-136 5.1E6 4.2E6-4.0E3 9.5E6 Cs-137 1.2E8 9.3E7' 1.7E4 4.0E8 Ba-140 5.0E6 - 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6: 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4

-4.9E7 I -131

-0

' 6.5E8 4.3E8

~3.3E5 5.9E8 i

I -133 1.6El 8.6E0 5.924 6.7E4 I -135 1.1E-15 -6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 1

Inhalation Pathway,; units =

Food & Ground Pathway, units I"

"'*#vr) c APPROVED [6UG 0 21990 2-Revision 21 02-15.

TABLE 2-11 DOSE PARAMETER R FOR SECTOR B g

Page 1 of 3 Pathway --Sheep (Meat)*

Distance = 0.2 miles X/Q = 6.1E-6 sec/m D/Q = 5.3E-8 m

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala.

Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground ti Ground n thway Pathway Pathway.

Pathway Pathway Pathway Pathway Pathway Nuclidt.

a H.-3 1.5EO. 1.2E0 7.0E0 12.1E0 t

Cr-51 5.1El

-0.

1.0E2-1.8E1 2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 0- 4.7E3 8.1E3 1.7E2 1.9E6 Co-57 Co-58 9.7E3 2.0E4

'5.9E2 2.1E6 Co-60

. 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 -0--

5.0E4 -2.6E4 1.7E3 3.1E4

+

Sr-90. -0-- 1.0E6 8.1E5 5.5E5

-1.3E6 Zr-95 6.3E4 1.1E5 8.3E2 1.6E6 Nb-95

-C-2.4E5 4.5ES 5.7E2

'1.6E6 Te-129m 6.0E5-4.5E5 2.0E!

6.5E5 Cs-134 -0, 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3

.8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 -0.

5.1E3 4.3E3 1.2E3 1.2E5' Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5-I -131

-0

• 6.6ES 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4

.1.3E4' I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1E5 -.

9.5E4 5.7E2-4.2E6.

L l

l l

Inhalation Pathway, units -

5" Food & Ground Pathway, units I*

jc i APPROVED AUG 0 21990 2-56 Revision 21 02-15-90

TABLE 2-11 DOSE PARAMETER R FOR SECTOR B y

Page 2 of 3 Pathway - Deer Consumer-Distance = 1.1 miles X/Q = 3.4E-7 sec/m*

D/Q - 2.4E-9 m

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

Radio-tion Grcund tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway-Pathway Pathway' Pathway H -3 2.8E1 2.3E1 3.5El 3.9El Cr-51 5.0E4 1.0E5 9.1El 3.2E5 Mn-54 7.7E5 1.4E6 2.1E3 4.1E7 Co-57 '4.6E6 8.0E6 ~

8.6E2 2.3E7 Co-58 9.6E6_ 1.9E7 2.9E3 4.7E7 Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr 89 -0-- 4.9E7

. 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6' 1.2E9 Zr-95 6.2E7 1.1E8 4.1E3 2.0E8 Nb-95 2.3E8 4.5E8 2.8E3

- 8.2E8 Te-129m 5.9E8 4.5E8 1.0E3-5.3E8 Cs-134 1.4E8 1.2E8 2.3E4-3.4E8 l

Cs-136 5.1E6 4.2E6

,4.0E3 9.5E6

(

Cs-137 1.2E8 9.3E7 1.7E4.

4.0E8 l

Ba-140 -0--

5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6

' 0-2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 i

I -131

-0 ' ' 6.5E8 -4.3E8 3.3E5 5.9E8 I -133 1.6El 8.6E0'

. 5. 9 E4 -

6.7E4 I -135 1.1E-15.6.3E-16 1.2E4 6.9E4 i

UN-ID 1.1E8 9.4E7

.2.8E3 1.4E8

~. n.-- -

Inhalation Pathway, units a }jj"(!"

Food & Ground Pathway, units - 5 FI e

APPROVED AUG 0 21990 2-57 Revision 21 02-15-90

TABLE 2-11 DOSE PARAMETER R FOR SECTOR 8 I

Page 3 of 3 Pathway - Sanitary Landfill Distance = 2.1-miles-X/Q =_1.4E-7 sec/m*

D/Q - 1.2E-9 m '

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 - 2.9E2

• Cr-51

-0

, 7.6E2 1.1E6 Mn-54. -0--

1.8E4 3.2E8 Co-57 7.2E3 7.8E7 Co-58 2.4E4 8.7E7o Co-60 6.5E4 4.9E9 St-89 6.9E4 4.9E3 Sr-90 2.3E7 Zr-95 3.4E4 5.7E7 Nb-95 2.4E4 3.1E7 Te-129m 8.3E3 4.5E6 Cs-134' 1.9ES 1.6E9 Cs-136 3.3E4 3.4E7 Cs-137 '1.4E5 2.3E9-Ba-140- 5.0E4.

'4.7E6 Ce-141 - 2.7E4 3.1E6 Ce-144 1.9E5 1.6E7 l

I -131

-0 ' 2.7E6-3.9E6 I -133 4.9E5 5.6E5 I -135 1.0E4 5.8E5 UN-ID 2.4E4 1.7E8 I

Inhalation Pathway, units -

?"

Food & Ground Pathway, units I"

V"I APPR9ygg AlJg n 91990 Rem a 02-15-90

_IA_RLE 2-12 DOSE PARAMETER R FOR SECTOR C j

Page 1 of 5 Pathway - Camp San Onofre Distance - 2.6 miles X/Q = 9.2E-8 sec/m*

D/Q = 8.4E-10 m '

Infant Child Teen Adult Innala-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 H3 -0-- 1.3E3 '

Cr-51 3.3E3 3.7E6 Mn-54 7.7E4 1.1E9 Co-57 3.1E4 2.7E8

'Co-58 ' 0-1.1E5 3.0E8 Co-60 2.8E5 1.7E10 s

Sr-89 3.0E5 1.7E4 Gr-90 9.9E7 Zr-95 1.5E5 2.0E8 Nb-95 0- 1.0E5 1.1E8 4

Te-129m 3.7E4 1.6E7 Cs-134 -0-- 8.5E5 5.5E9 Cs-136 - 0.- 10-

,1.5E5 1.2E8 Cs-137 6.2E5-8.2E9 Ba-140 2.2E5 1.6E7 Ce-141 -0-- 1.2E5 1.1E7 Ce-144 0 -

8.2E5 5.6E7 I -131

-0 ' -0-- 1.2E7 1.4E7 I -133 2.~2E6 2.0E6 I -135 -0--.4.5E5 2.0E6 UN-ID - 1.0E5 6.0E8 Inhalation Pathway, units = *C /

Food & Ground Pathway, units I*

j[c

" ^"

APPROVED AUG 0 21990 2-59 Revision 21 02-15-90

k L

TABLE 2-12 DOSE PARAMETER R FOR SECTOR C Pathway - Camp San Onofre Fr. Stn Distance = 2.3 miles X/Q = 1.1E-7 sec/m' D/Q = 1.1E-9 m '

Infant Child Teen Adult l

Inhala-Food &

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 -0-- 5.2E2 Cr-51 1.4E3

-1.9E6 Mn-54 3.2E4 5.7E8-Co-57 1.3E4 1.4E8 Co-58 4.4E4 1.6E8 Co-60 1.2E5 8.8E9 Sr-89 -04 1.2E5-8.9E3

^

Sr-90, -0-'

4.lE7 Zr-95 6.2E4 1.0E8:

Nb-95 4.3E4 5.6E7 Te-129m -0-- 2-1.5E4 8.1E6 I

Cs-134 -0 '

3.5E5 2.8E9 Cs-136 6.0E4 6.2E7 Cs-137 -0--

2.6ES-4.2E9 Ba-140 9.0E4

'8.4E6-Ce-141 4.9E4 5.6E6.

Ce-144 3.4E5 2.9E7 1 -131

-0* 4.9E6 7.1E6 I -133 -0--

8.8E5

~1.0E6 I -135 1.8E5 1.0E6 UN-10 4.2E4 3.1E8

~

l l

Inhalation Pathway, units = "C" Food & Ground Pathway, units = I' V"I APPROVED AUG 0 21990 2-60 Revision 21 02-15-90

. ~

TABLE 2-12 i

l DOSE PARAMETER R FOR SECTOR C j

Page 3 of 5 l

l

' Pathway - Sewage Facility Distance - 2.2 miles X/Q = 1.2E-7 sec/m*

D/Q = 1.2E-9.m

• Infant Child Teen Adult

.1 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 2.9E2 Cr-51 7.6E2 1.1E6 Mn 1.8E4 3.2E8 Co-57 -0-- 7.2E3 7.8E7

.Co-58 2.4E4 8.7E7 j

Co-60 6.5E4 4.9E9 Sr-89 6.9E4 4.9E3 Sr-90 2.3E7- '

Zr-95 3.4E4.

5.7E7 Nb-95 2.4E4-3.1E7 Te-129m 8.3E3 4.5EG

~' -

Cs-134< -0--

1.9E5 1.6E9 Cs-136

-;-,3.3E4 3.4E7 Cs-137 1.4E5 2.3E9 Ba-140 5.0E4 4.7E6 i

Ce-141. -0--

'2.7E4 3.1E6 l

Ce-144 1.9ES 1.6E7 I -131

-0

• 2.7E6 3.9E6 l,

I -133 4.9E5 5.6E5 I -135 1.0E5 5.8E5 i

UN-ID 2.4E4:

1.7E8 Inhalation Pathway, units =

Food & Ground Pathway, units I"

"I 7

APPROVED AUG 0 21990 2-61 Revision 21 02-15-90

TABLE 2-12 DOSE PARAMETER R FOR SECTOR C Page 4 of 5 Pathway = Sheep (Meat)*

Distance = 0.2 miles X/Q = 6.5E-6 sec/m

-D/Q - 5.3E-8 m '

?

Infant Child'

. Teen Adult

\\

1 Inhala-Food &

Inhala-Food &

Inhala -

Food &

Inhala-Food &

l Radio--

tion Ground tion Ground tion Ground tion.

Ground i

Nuclide Pathway Pathway Pathway Pathway Pathway Pathw v Pathway Pathway H -3 1. 5 E0 - 1.2E0 7.0E0 2.1E0-i Cr-51 -0.

5.1E1 1. 0 E2 -

1.8E1 2.6E4 Mn-54 7.8E2 1.4E3' 4.3E2 7.6E6 Co-57 4.7E3 8.1E3 1.7E2 1.9E6 Co-58 -0-' 9.7E3 2.0E4 5.9E2 2.1E6 i

Co-60 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 L 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1E5 5.5E5 1.3E6; Zr-95 6.3E4 1.1ES 8.3E2-1.6E6~

Nb-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6~.0E5 4.5E5 -

2.0E2 6.5ES.

Cs-134 1.4E5 1.2E5-4.7E3-3.8E7 Cs-136 5.1E3 -4.3E3 8.1E2 8.3E5-Cs-137 '1.3E5 9.5E4

'3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3-1.2E5 Ce-141 1.5E3 2.4E3 6.6E2.

7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131

-0 ' 6.6E5 4.4E5 6.6E4 7.0E5 l

I -133 1.6E-2:.8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID - 1.1E5 -

9.5E4 5.7E2-4.2E6 1

l Inhalation Pathway, units = *[*j"(!"

Food & Ground. Pathway, units =I*,If*f

"**#V"I i

,1 AlPPROVED AUG 021990 2-62 Revision 21 15-90

-)

TABLE 2-12 DOSE PARAMETER R.FOR' SECTOR C Page 5 of 5

'i Pathway = Deer Consumer Distance = 1.0 miles-X/Q = 3.4E-7 sec/m*

D/Q = 5.1E-9 m

Infant Child-Teen Adult 1

Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway

_ Pathway

'l H -3 2.8E1 0-2.3E1 3.5El 3.9El l

Cr-51 5.0E4 1.0E5 9.1El 3.2E5 1

Mn-54 7.7ES 1.4E6 2.1E3 4.1E7 Co-57 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr'-89 4.9E7 2.6E7 8.3E3 3.1E7 St-90 1.0E9 8.0E8 2.7E6 1.2E9 2r-95 6.2E7 '1.1E8 4.1E3 2.0E8 Nb-95 2.3E8 4. 5 E8.

2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6

-0 '

.4.2E6

.4.0E3 9.5ES Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 -0-- 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6

-3.3E3 4.2E6 Ce-144 1.8E7 2;9E7 2.2E4 4.9E7 I -131

-0

' 6.5E8 4.3E8 3.3E5 5.9E8 I -133 1.6El 8.6E0 5.9E4 6.7E4 1 -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3' 1.4E8 Inhalation Pathway, units =

Food & Ground Pathway, units I"

/c APPROVED AUG 0 21990 2-63 Revision 21 02-15-90

1. q t

TABLE 2-It

!o v

DOSE PARAMETER R.FOR SICTOR D j

Page 1 of 3 Pathway = Camp San Onofre Dist'ance 2.8 riles.

X/Q = 6.6E-8 sec/m*

D/Q,6.4E-10 m '

Infant Child-Teen' Adult-Inhala-Food &

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

H -3 -0-- -0--

1.3E3

. ' 0- 3.3E3' 3.7E6.

Cr-51 '

Mn-54 7.7E4-

'l.1E9 Co -0-' -0--

3.1E4 2.7E8-Co-58 1.1E5 3.0E8 l

Co-60 -2.8E5 l'.7E10 i

Sr-89 - 3.0E5 1.7E4 Sr-90 9.9E7 !

Zr-95. ' 0- 1.'E E 5 2.0E8 Nb-95 -1.0E5 1.1E8 Te-129m - - 3. 7E4 -

1.6E7 Cs-134 8.5ES 5.5E9 Cs-136,1.5E5 1.2E8 Cs-137 -0--

6.2E5

'8.2E9 Ba-140 2.2E5 1.0E7 Ce-141 -0-- 1.2E5 1.1E7 Ce-144 -0-~ 8.2E5 5.6E7 I -131 1 -0 '

' 1.2E7 1.4E7 I -133 2.2E6 2.0E6 I -135 4.5E5 2.0E6 UN-ID 1.0E5-6.0E8 l

l l

r L

Inhalation Pathway, units =

Food & Ground Pathway, units I*

/c t

t 1

APPROVED AUG g g 3999 2-64 Revision'21 02-15-90

Tall.E 2-13 l

DOSE PARAMETER R FOR SECTOR D Page.2 of 3 I

Pathway = Sheep-(Meat)*

Distance - 0.2 miles l

X/Q=6.}E-6sec/m D/Q = 6.6E-8 m

• l Infant Child Teen Adult l

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 i

H -3 1.5E0 1.2E0

-7.0E0 2.1E0 Cr-51 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E. 8.1E3 1.7E2 1.9E6 Co-58 - 9.7b 2.0E4 5.9E2 2.1E6 i

Co-60 ' 0- 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89

-0 -0-'

5.0E4 2.6E4 1.7E3 3.1 E4' i

Sr-90 1.0E6 8.1E5 5.5E5 1.3E6 Zr-95 6.3E4 1.1E5 8.3E2 1.6E6 Nb-95 2.4E5 4.5E5 5.7E2.

1.6E6 l

Te-129m 6.0E5 4.5E5 '

2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 i

Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3-6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3-4.3E5 I -131

-0 ' 6.6ES 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4.

1.3E4 I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1E5 9.5E4 5.7E2 4'2E6 Inhalation Pathway, units =

f Food & Ground Pathway, units I*

"**'yr) c APPROVED AUG 0 21990 2-65 Revision 21 02-15-90 1

t l-TABLE 2-13' DOSE PARAMETER R _FOR SECTOR D Page 3 of 3 Pathway - Deer Consumer Distance = 1.0 miles X/Q = 3.3E-7 sec/m*

D/Q = 3.3E-9 m

• Infant Child Teen Adult Inhala I-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

Radio -

tion Ground tion Ground tion Ground-tion Ground Nuclide Pathway Pathway Pathm.t Pathway Pathway Pathway Pathway Pathway H3 2.8E1 2.3E1

'3.5El 3.9El Cr-51 5.0E4 1.0E5 9.1El 3.2E5 Mn-54 7.7E5 1.4E6-2.1E3

-4.1E7 Co 57-4.6E6 8.0E6 8.6E2 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 3.6E7 7.2E7 7.8E3

'7.2E8 Sr-89~ 4.9E7 -2.6E7 8.3E3 3.1 E7 -

Sr-90t 1.0E9 8.0E8 2.7E6 1.2E9 Zr-95 6.2E7 1.1E8 4.1E3 2.0E8 Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 1

Cs-137 1.2E8 9.3E7

1. 7 E4'-

4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131

-0 ' 6.5E8' 4.3E8 3.3E5

=5.9E8 1

I -133 1.6El 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 i

UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 i

i i

Inhalation Pathway, units -

h" Food '. Ground Pathway, units = I*

"I l

j APPROVED AUG 0 21990 2-66 Revision 21 02-15-90 4

TABLE 2-14

/

DOSE PARAMETER R FOR SECTOR E g

Page 1 of.3-i Pathway - Camp Horno Distance - 4.0 miles j

X/Q = 6.6E-8 sec/m*

D/Q = 6.4E-10 m '

Infant-Child Teen-Adult l

Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l

l H -3 1.3E3 Cr-51 3.3E3 3.7E6 Mn-54 7.7E4 1.1E9' i

Co-57 3.1E4 2'.7E8 Co-58 1.1ES 3.0E8 Co-60 2.8E5 1.7E10 Sr-89 3.0E5 1.7E4 Sr-90 9.9E7 -

Zr-95 1.5E5 2.0E8 Nb-95 -0-- 1.0E5 1.1E8 -

Te-129m -0. 3.7E4 1.6E7 Cs-134 8.5E5 5.5E9 i

Cs-136 1.5ES 1.2E8 i

Cs-137 6.2E5 8.2E9 Ba-140. 2.2E5 1.6E7 Ce-141 '1.2E5 1.1E7 Ce-144 -0.

8.2E5 5.6E7-I -131

-0 ' 1.2E7 1.4E7 I -133 2.2E6 2.0E6 I -135 4.5E5 2.0E6 UN-ID 1.0E5 6.0E8 i

a i

l l

Inhalation Pathway, units =

l Food & Ground Pathway, units I*

I "I

APPRoygg 799gg)ggg 2-67 Revision 21 02-15-90 i

TABLE 2-14 DOSE PARAMETER R FOR SECTOR E-7_

Page 2 of 3

]

Pathway = Sheep (Meat)'

Distance = 0.3 miles X/Q = 4.5E-6 sec/m D/Q = 5.9E-8 m

• Infant Child Teen-Adult

-l 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 1

H.-3 1.5E3 -

1.2E0 7 0E0 2.1E0 Cr-51 -0--

5.1El-1.0E2 1.8El-2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E3 8.1E4 1.7E2' 1.9E6 Cc 9.7E3 2.0E4 5.9E2 2.1E6 1

Co-60 -0--

3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4. 2.6E4 1.7E3 3.'1E4

-Sr-90 - '1.0E6-8.1E5 5.5E5 1.3E6 Zr-95 -6.3E4 1.1E5-8.3E2 1.6E6 Nb-95 2.4E5

- 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3

,8,1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3

- 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3

-4.3E5 i

I -131

-0

• 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 0-6.4E-19 2.5E3 1.4E4 l

UN-ID 1.1E5 0-9.5E4 5.7E2 4.2E6 Inhalation Pathway, units = ]j"h" Food & Ground Pathway, units = I*

• • 1. vr) c APPROVED AUG 0 21990 2-68 Revision 21 02-15-90 w_

r i

' TABLE 2-14 DOSE PARAMETER R FOR SECTOR E.

g Page 3 of 3 Pathway -' Deer Consumer Distance = 1.2 miles X/Q = 3.7E-7 sec/m*

D/Q = 8.3E-9 m

• Infant

. Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala--

Food &

Inhala-Food &'

Radio-tion-Ground tion.

Ground tion

' Ground tion Ground Nuclide1 Pathway.

Pathway Pathway Pathway Pathway.

Pathway Pathway Pathway 3

H -3 2.8El-2.3El' 3.5El 3.9El Cr-51 5.0E4 1.0E5 9.1El 3.2E5 f

Mn-54 7.7E5 -1.4E6.

2.1E3 4.lE7 Co-57 4.6E6-8.0E6 8.6E2 2.3E7 Co-58 -9.6E6 1.9E7 2.9E3 4.7E7 Co-60 -0--

3.6E7 -

7.2E7 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.lE7 Sr-90 1.0E9 8.0E8 2.7E6-l'. 2 E9 -

Zr-95 6.2E7~ 1.1E8 4.1E3' 2.0E8 '

Nb-95 2.3E8. 4.5E8

'2.8E3 8.2E8 i

Te-129m 5.9E8 4.5E8 1.0E3

-5.3E8 Cs-134 -0-.

1.4E8 1.2E8 2.3E4 3.4E8 3

Cs-136 5.1E6 4.2E6 4.-0E3 9.5E6-Cs-137

. 1.2E8-9.3E7.

1.7E4 4.0E8

'Ba-140 -0; -

5.0E6 4.2E6-6.0E3 7.4E6 i

Ce-141 1.5E6

- 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7'

-0.

2.9E7^

' 2 '. 2E4 :

4.9E7 I -131

-0 ' 6.5E8-4.3E8

~3.3E5 5.9E8 I -133 1.6El-8.6E0-5.9E4 6.7E4 l

I -135 -0-- 1.lE-15 6.3E-16 1.2E4 6.9E4 L

UN-ID 1.lE8 9.4E71 2.8E3

-1.4E8 i

l-Inhalation Pathway, units - (({*(("

l

. Food.& Ground Pathway, units I*

f*j"'"#yr) c APPROVED AUG 0 21990 2-69 Revision 21 02-15-90 t

-m

TABLE 2-15 DOSE PARAMETER R FOR SECTOR F g

Page 1 of 5 i,

Pathway - San Onofre State Park ^ i.rd Shack Distance = 0.8 miles X/Q~= 8.1E-7 sec/m' D/Q = 7.1E-9 m

• 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 3

H -3 - 7.2E1,

Cr-51. 1.9E2 2.7E5

'Mn-54 - 4.4E3 7.9E7 Co-57 1.8E3 2.0E7 Co-58 -0 '

-0 : 6.1E3 2.2E7 Co-60 -0-- 1.6E4 1.2E9 i

Sr-89 1.7E4 1.2E3 Sr-90 0- 5.7E6 i Zr-95 8.6E3 1.4E7 Nb-95 - 5.9E3

.7.8E6 Te-129m 2.1E3 '

1.1E6 Cs-134 4.8E4 3.9E8 Cs-136 8.4E3 8.6E6 Cs-137 -0-- 3.5E4 5.9E8 Ba-140 0- 1.2E4 1.2E6 Ce-141 6.9E3 7.8E5 Ce-144 4.7E4 4.0E6 I -131

-0

• 0- 6.8E5-9.8E5 I -133 -0-- 1.2E5 1.4E5-I -135 2.6E4 1.4E5 UN-ID 5.9E3 4.3E7 i

Inhalation Pathway, units =

1. ["

Food & Ground Pathway, units I*3 II""*"#V"I pCi/sec APPROVED AUG 0 21990 2-70 Revision 21 02-15-90 f

B BLE 2-15 DOSE PARAMETER R FOR SECTOR F Page 2 of 5 Pathway - Beach Concession Distance - 0.9 miles D/Q - 6.0E-9 m-2 i

X/Q = 6.9E-7 sec/m s Infant Child Teen Adult Inhala-Food &

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 -0-- 1.2E2 Cr-51 3.1E2 14.4E5 Mn-54 7.2E3-1.3E9 Co-57 2.9E3 3.2E7 Co-58 1.0E4 3.6E7 Co-60 2.7E4 2.0E9 Sr-89 2.8E4 2.0E3 Sr-90 -0

' 9.3E6: -;

Zr-95 1.4E4 2.4E7 Nb-95 9.7E3 1.3E7' Te-129m 3.4E3 1.8E6 Cs-134 7.9E4 6.4E8' Cs-136,1.4E4-1.4E7 Cs-137 5.8E4 9.6E8 Ba-140 2.0E4 1,9E6 Ce-141 -0--

1.1E4 1.3E6 Ce-144 -0. 7.6E4 6.5E6-I -131

-0

• 1.1E6 1.6E6 i

I -133 2.0E5 2.3E5 l

I -135 - -0-- 4.2E4 2.4E5 UN-ID 9.7E3 7.0E7:

l 1

i l'

I l

Inhalation Pathway, units =

["

t Food & Ground Pathway, units I*,

"I j

APPROVED AUG 0 21990 2-71 Revision 21.

02-15-90

TABLE 2-15 DOSE PARAMETER R FOR SECTOR F Page 3 of 5 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 &

Inhala -

Food &

Inhala-

_ Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway j

H -3 - - - 3.6E2-Cr-51 9.5E2 1.3E6 Mn-54 2.2E4 3.9E8 Co-57 9.0E3 9.8E7 Co-58. 3.0E4 1.1E8 Co-60 8.1E4 6.1E9 Sr-89. 8.7E4 6.2E3 Sr-90 2.8E7 Zr-95 -0-- 4.3E4 7.2E7 Nb-95 3.0E4 3.9E7 Te-129m 1.0E4 5.6E6-Cs-134 2.4E5 1.9E9 Cs-136 -0--

4.2E4 4.3E7 Cs-137 -0-- -

-Os 1.8E5 2.9E9 Ba-140 6.2E4 5.9E6 Ce-141

- 3.4E4 3.9E6 Ce-144 2.3E5 2.0E7 I -131

-0 ' -0-- 3.4E6 4.9E6 I -133-6.1E5 7.0E5 l

1 -135 1.3E5 2.2E5 UN-ID 2.9E4 2.1E8 l

l l

\\

Inhalation Pathway, units = yh" Food & Ground Pathway, units I*

"'*#yr) c l

l E

APPROVED AUG 0 21990 2-72 Revision 21 02-15-90

i TABLE 2-15 D05E PARAMETER R FOR SECTOR F Page 4 of 5 Pathway - Sheep (Meay '

Distance = 0.5 miles X/Q = 1.9E-6 sec/m D/Q = 1.7E-8 m '

Infant Child Teen Adult Inhala-Food &

Inhala-Food &

Inhala-Food &

Inhal' -

Food &

a Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 -0. 1.5E0 1.2EO.

7.0E0 L2.1E0 Cr-51 5.1El '1.0E2 1.8E1 2.6E4 Mn-54 7.8E2. 1.4E3 4.3E2-7.6E6, 4

Co 4.7E3 8.1E3 1.7E2 1.9E6-Co-58 9.7E3-2.0E4 5.9E2 2.1E6 Co-60 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 - 0,-

5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1E5

.5.5E5 1.3E6 Zr-95. 6'3E4-1.1E5 8.3E2 1.6E6 Nb-95 2.4E5 4.5E5 5.7E2 1.6E6

'0-4.5ES 2.0E2 6~5E5 Te-129m~ 6.0E5 Cs-134 1.4E5 1.2E5' 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7-Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3' 4.3E5 I -131 6.6E5

- 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 i

I -135 1.1E-18 6.4E-19 2.5E3

.1.4E4 UN-ID 1.1E5 9.5E4 5.7E2

.4.2E6 a.

Inhalation Pathway, units =

h" Food & Ground Pathway, units' I"

"I j

APPROVED AUG 0 21990 2-73 Revision 21 02-15-90

TABLE 2-15 DOSE PARAMETER R FOR SECTOR F g

Page 5 of 5 Pathway - Deer Consumer Distance = 1.4 miles

-X/Q = 3.0E-7 sec/m' D/Q = 2.3E-9 m '

Infant Child Teen Adult-Inhala-Food &

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 H -3 2.8E1 2.3El 3.5El' 3.9El Cr-51 -0--

-0 5.0E4 1.0E5' 9.1El 3.2E5 Mn-54 7.7E5 1.4E6

2. l E3' 4.1E7 Co-57 4.6E6 8.0E6 8.6E2, 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60

-0. 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3

-3.1E7 Sr 1.0E9 8.0E8 2.7E6 1.2E9 Zr-95 6.2E7 1.lE8 4.1E3 2.0E8 Nb-95 2.3E8 A 5E8 2.8E3 8.2E8-Te-129m 5.9E8 s.5E8 1.0E3 5.3E8

)

Cs-134 -1.4E8 1.2E8 2.3E4 3.4E8 l

Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 i

Cs-137 1.2E8 9.3E7 1.7E4-4.0E8-Ba-140 5. 0E6 -- 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131 '0- 6.5E8

--0--

.4.3E8 3.3E5 5.9E8 I -133 1.6El 8.6E0

-5;9E4 6.7E4-I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 Inhalation Pathway, units = yh" Food & Ground Pathway,' units I"

"*"#yr) c APPROVED AUG 0 21990 2-74 Revision 21 02-15-90

TABLE 2-16 DOSE PARAMETER R FOR SECTOR 6 g

Page 1 of 4 Pathway - San Onofre State Beach Campground Distance = 0.8 miles X/Q = 7.7E-7 sec/m' D/Q = 3.9E-9 m

• 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

-8.0El 1.4E2; 1.6E'2 -1.6E2 Cc 4.4El 5.7E5 1.3E2 5.7E5-3.7E2 5.7E5 4.1E2 5.7E5-Mn-54 3.1E3 1.7E8 5.3E3 1.7E8 8.2E3' 1.7E8 9.5E3 1.7E8 Co-57 6.0E2 4.2E7 1.6E3 4.2E7 3.9E3 4.2E7 3.9E3, 4.2E7 Co 58 1.4E3 4.7E7

~4.2E3 4.7E7 1.2E4' 4.7E7 1.3E4 4.7E7 Co-60 3.9E3 2.7E9 1.2E4 2.7E9-3.2E4 2.7E9 3.5E4 2.7E9-Sr-89 4.9E4 2.7E3 7.4E4 2.7E3 5.4E4 2.7E3 3.7E4 2.7E3 Sr-90 5.0E6 1.2E7 1.3E7. 1.2E7 <

Zr-95 2.7E3 3.1E7 7;5E3

.3.lE7 1.8E4

.3.lE7 1.9E4 3.1E7 Nb 1.6E3 1.7E7 4.6E3

.l.7E7 1.2E4

'l.7E7 1.3E4 1.7E7 Te-129m 3.9E3 2.4E6 6.2E3 2.4E6 6.4E3 2.4E6 4.5E3 2.4E6 Cs-134 8.7E4 8.4E8 1.3E5 8.4E8 1.4E5 8.4E8 1.0E5 8.4E8 Cs-136 1.7E4 1.9E7 2.1E4-1.9E7 2.4E4 1.9E7 1.8E4 1.9E7 Cs-137 7.5E4 1.3E9 1.0E5 1.3E9 1.0E5-1.3E9 7.7E4,

-1.3E9 Ba-140 6.9E3 2.5E6 9.1E3 2.5E6 2.8E4 2.5E6 2.7E4 2.5E6 Ce-141 2.7E3 1.7E6 7.0E3 1.7E6 1.6E4 1.7E6-

' I'. 5 E4 1.7E6 Ce-144 1.8E4 8.6E6 4.8E4 8.6E6 1 lES 8.6E6 1.0E5 8.6E6 I -131 1.8E6 2.lE6 2.0E6 2.1E6 1.8E6 2.lE6 1.5E6 2.1E6 I -133 4.4E5 3.0E5 4.7ES 3.0E5 3.6E5 3.0E5 2.7ES 3.0E5 I -135~

8.6E4 3.lE5 9.8E4 3 lE5 7.7E4 3.1ES '

5.5E4 3.1ES UN-ID 7.7E3 9.2E7 1.4E4 9.2E7 1.6E4 9.2E7 1.3E4 9.2E7 I

L Inhalation Pathway, units y

Food & Ground Pathway, units I"

""#vr) j c l

APPROVED AUG 0 21990 2-75 Revision 21 02-15-90

.. ~.

TABLE 2-16 DOSE PARAMETER R FOR SECTOR G g

Page 2 of 4 i

Pathway - Hwy Patrol Weigh Station Distance = 2.0 miles 4 -

X/Q = 2.0E-7 sec/m' D/Q = 8.5E-10 m

• 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 -0-- 2.9E2 Cr-51 7.6E2 1.1E6 Mn-54 1.8E4 3.2E8 Co-57 7.2E3 7.8E7 Co-58 -0. 2.4E4 8.7E7 Co-60 6.5E4 4.9E9 Sr-89 -0-- 6.9E4 4.9E3 Sr-90 2.3E7 Zr-95 3.4E4 5.7E7 Nb-95 2.?E4 3.1E7

.)

Te-129m -0. 8.3E3-4.5E6 Cs-134 - 1.9ES 1.6E9 Cs-136 3.3E4 3.4E7

-Cs-137 1.4E5 2.3E9 Ba-140' 5.0E4 4.7E6 Ce-141 2.7E4 3.lE6 i

Ce-144 1.9E5 1.6E7 I -131 2.7E6

'3.9E6-I -133 -0-- 4.9ES 5.6E5 I -135

-0 '. 41.0E5 5.8E5 UN-ID 2.4E4-1.7E8 l

Inhalation Pathway, units = }'

Food & Ground Pathway, units I"

"}

e APPROVED AUG 0 21990 2-76 Revision 21 02-15-90 l

u

. =_

TABLE 2-16 DOSE PARAMETER R FOR' SECTOR Q Pathway - Sheep (Meat)'

Distance = 2.7 miles l

X/Q = 1.2E-7 sec/m 0/Q = 4.8E-10 m

• L Infant Child Teen Adult Inhaia-Food &

Inhala-Food.&' Ir cla-Food &

Inhala-Food &

Radio-tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway-Pathway Pathway

_ Pathway Pathway

-Pathway H -3 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51, 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E3 8.1E3 1.7E2 1.9E6-Co-58 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 3.7E4 7.3E4 1.6E3-1.2E8-Sr-89 5.0E4 2.6E4

~1.7E3-3.1E4 Sr-90 1.0E6' 8.1E5 5.5E5 1.3E6 Zr-95 6.3E4 1.1E5 8.3E2.

1.6E6 Nb-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6 '. 5 E S '

Cc-134 -0--

1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 - 1.3E5 9.5E4 3.4E3 5.7E7-Ba 140 - -5.1E3-4.3E3 1.2E3-

1.2E5 Ce-141 '

1.5E3 2.4E3 6.6E2 7.9E4

.I Ce-144 -;

1.8E4 3.0E4-

-4.5E3 4.3E5

-l

! -131 6.6E5-4-

4.4E5-6.6E4:

7.0E5 I -133.l.6E-2 8.7E-3

~ 2.5E3 1.4E4 1.2E4

- 1.3E4 -

-l I -135 1.1E-18 -

6.4E-19 UN-ID 1.1ES 9.5E4 5.7E2-

-4.2E6 l.

InhalationPathway, units ={h" V"I Food &-Ground Pathway, units =

7 l

APPROVED AUG 0 21990 2-77 Revision 21 02-15-90 1j

i j

TABLE 2-16 D0SE PARANETER R FOR SECTOR G g

Page 4 of 4

,4 l

Pathway-DeerConsumep Distance = 3.3 miles X/Q = 8.8E-b sec/m D/Q = 3.2J-10 m '

Infant Child Teen Adult Inaala-Food &

Inhala-Food &

Inhala-Food &

Inhala-Fooo 1 Radio-tion Ground tion Ground tion Ground tion _

Grornd l

Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway 1

'N -3 2.8El 2.3E1 3.5El 3.9El Cr-51 0-5.0E4 1.0E5 9.lEl 3.2E5 Mn 54 7.7E5 1.4E6 2.1E3 4.1E7 Cc,457 4.6E6 8.0E6 8.6E2 2.3E7 Co-Sb 0- 9.6E6 1.9E7 2.9E3 4.7E7 Co 60 3.6E7 7.2E7 7.8E3 7.2E8 Sr 89 4.9E7 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6 1.2E9 Zr-95 0- 6.2E7 1.1E8 4.lE3 2.0E8 N495 2.3E8 4.5E8 2.8E3' 8.2E8 Te-;29m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Ct 136 5 lE6 4.2E6 4.0E3 9.5E6

-Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce 141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 -

2.9E7~

2.2E4 4.9E7 I -131 6.5E8 4.3E8 3.3E5 5.9E8 I -133 0-0- 1.6El 8.6E0 5.9E4 6.7E4 j

I -135 1.lE-15 6.3E-16 1.2E4 6.9E4 UM-ID 1.1E8 9.4E7 2.8E3 1.4E8

+

i l.

t l

Inhalation Pathway, units =

f Food & Ground Pathway, units I"

/c 1

APPROVED AUG 0 21990 2-78 Revir. ion 21 62-15-90

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 L

member of the public, due t0 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 the dose limitations =of 40 CFR 190 per twelve consecutive months.

The transportation of radioactive material is excluded-l from the dose calculations.

I The Annual Total ' ese is determined monthly for maximum J

D organ (gas & liquid), whole body (gas & liquid) and thyroid (gas & liquid) to verify _ that the Site total-4 (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem and 75 mrem respectively.

.1, Annudi Tot'al qrgan 5se (Do (organ))

12 2/

H8

~

s,D !crgan) = z I

D (OG) + D (OL) + Dj1 (OG)

(2 20)

TOT 1-1 j=1 11 j1 i

j = Units 1, 2 and 3

-1 = months 1 - 12**

j

• NOTE: DH8(OG),=$forbone i

j1 1

• • All-to be summed over the most recent 12 months.

l where:-

i n

(2-21)-

l D (OG) = K zC)Riki k;

i - each isotope in W

4 4

j1 i=1 specific organ category l

V'*"

K = 3.1688E-2 c

APPROVED AUG 0 21990 1

2-79 Revision 21 j

02-15-90 J

1 -

2.9 T01AL DOSE CALCULATIONS (Continued) 2.9.1 Total Dose to Most Likely Member of the Public (Centinued)

= number of isotopes in the specified organ category n

C)

= total particulate gas curies released for the month g

R W

- controlling location factors from ik k ODCM Tables 2-6, Units 1 and 2/3 j1(0L)

= liquid' organ dase for the specified organ in mrom for the 0

month.

(1eference ODCM Units 2/3 (1-19), Unit 1 (1-13)]

D"*

as organ dose form tritium in aram for the month.

ji (OG) =

Note: H. bone contribution = 04

.' 2 Armai Total Whole Body Dose - D E

TOT 12 2/3 Hs D. (WB) - E E

j1(WBL) + Dj1 (OG) + 0.9 D-(7)+D(Direct);

(2-22)

D TOT 1-1 j=1 j1 j =' Units 1, 2 and 3 1 = months 1 - 12*

• To be summed over the most recent 12 months.

where:

ji(WBL) = liquid whole body organ dose in arem for the whole month.

D (Reference ODCM Units 2/3 (1-19), Snit-1 ODCM (1-11)]

N D '(OG) = gas organ dose from tritium in _ mrem for the month.-

ji (from (2-21))-

~

f' D(y)

'= gamma air dose in mrad for the month.-

J ji 0.9 converts arad to mrem.

(Reference ODCM Unitt. 2/3 (2-14), Unit 1 ODCM (2-10)]

(

4 n

D (Direct) - E max (D(beach)$ 1-E D(bkgd)$

.0342 (2-23) j=1 i=1 n

i - for all TLDs-per quarter

j = for Quarters 1-4 APPROVED AUG 0 21990 2-80 Revision 21 02-15-90'

[

.2.9 TOTAL' DOSE CALCULATIONS (Continued)

E 2.9.1.2 Annual Total Whole Body Dose - D illAl (Continued)

TOT i

• Direct Radiation l

The airect radiation levels are evaluated most recently t

using cadmium covered TLDs.

The TLDs are pla:ed at 59 I

locations around the site.

The average dose from TL0s-i 5 to 50 miles from the site is used as. background. = These -

i sites are subbet to change.

I The backgrou:,d is subtracted from the' highest reading plant surrounding area TLD.

This value is the direct

-(

dose but must be prorated by the occupancy' factor j

Example:

beach time of 191Lb.imr.1, or a hours for landward occupancy.

j ye yr

.3 Annual Total Thyroid Do se.DTOT(THYROID) g 12.2/3 D (THYROID) = I I

(D (OG) + D (0L)

(2-24)

TOT.

1=1 j=1

.j1 j1 l

l j-- Units.1, ? and 3 1 = months 1 - 12*

• fo be summed over the most recent 12 months.

f I

where:

i i

_D (OG) = thyroid organ dose from gaseous-iodine for the month ji in mrem.

(from2-21) 9 D (OL) = liquid thyroid organ dose for the month.in mrem.

j j1 (Reference ODCM linits 2/3 (1-19), Unit:1 ODCM'(1-13)]

s 3

APPROVED AUG 0 21990 2-81 Revision-21 i

02-15-90

1 300 PROJECTED DOSES 3.1 Liquid Dose Projection l

The methodology used for projecting a liquid dose over 31 days j

for Specification 1.3.1 is as follows:

i 1.

Determine the aonthly total body and organ doses resulting i

l from. relet ses during the previous twelvt months.

i i

2.

Projected dose = Previous 12 months' dose divided by 12 for l

the total tody and each organ.

(

'l 3.2 Gaseous Dose Projection

~

r The metho61ogy used for' projecting a gaseous dose over 31 days for Specification 2.4.1'is as folles:

i 1.

Determine the monthly gamma beta and organ dose resulting from releases.during the previous-twelve months, t

2.

Projected dose = Previous 12 months' dose divided by 12 for i

the gamma, beta and organ doses.

l

,.5 i

.t.

i i

L i

'I i

APPROVED' AUG 09.1990 3 Revision 22 L

08-02-90 I

f

i 4.0 EQUIPMENT i

i 4.1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENIA110N l

f SPECIFICATION 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall= be OPERABLE with their alar # trip setpoints i

set to ensure that the limits of Specification 1.1.1 are not l

exceeded. The alar # trip setpoints of these channels shall be determined in accordance with Section 1.4.

APPLICABILITY: At all times ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than' required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive. liquid e'ffluent 4

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 inoperabic instrument (s) remain inoperable for greater than 30 days, explain in l the next Semiannual-Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

l SURVEILLANCE REQUIREMENTS

.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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilution to l

meet the site radioactive effluent concentration limits of Specification i

1.1.1 shall be determined to be operating and providing' dilution to the discharge structure.-

a s

APPROVED AUG 0 21990 i

4-1 Revision 21 02-15-90 4

.... ~..

Y l-TABLE 4-1 l

L RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRINENTATION MINI M CHANNELS l

INSTRUMENT

• OPERABt.Z ACTION 1

1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM TERMINATION OF RELEASE l

r i,

a.-

Liquid Radwaste Effluent Line - 2/3 RT-7813 1

28 i

b.

Steam Generator Blowdown (Neutralization Sump),

k l

full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 -

l' 29 l

3 c.

Turbine Plant Sumps Effluent Line - 2(3)RT-7821 1

30 i

t>

e d

.d.

Steam Generator (E088) Blowdown Fffluent ~

-:e Line - 2(3)RT6759 1

29 O

!~

e.

Steam Generator (E089) Blowdown Effluent g

Line.- 2(3)RT6753' 1

29 2>

2.

FLOW RATE MEASUREMENT DEVICES c-o l

4 a.

Liquid Radwaste Effluent Line 1

31 l

e w

i b.

-Steam Generator Blowdown (Neutralization Sump),

lA

.m i

18 Full Flow Condens.ite Polisher Effluent Line 1

31 i

i o

c.

' Steam Generator (E088) Blowdown Bypass Effluent Line 1

31 j

d.

Steam Generator (E089) Blowdown Bypass Effluent Line 1

31 l

4 h

^

4-2 Revision 22 08-02-90 4

1

,,_.m

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

TABLE 4 (Continued)

TABLE NOTATION i

)

• 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 opon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

ACTICN 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 1.1.1 and b.

At least two technically qualified members of the Facility i

Staff independently verify the release rate calculation and discharge line valving; i

Otherwise, suspend release of radioactive effluents via this t

pathway.

AG loN 29 - With the. number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may conti:ue provided grab samples are analyzed for gross radioactivity (bda or gamma) at a limit of detection of at least 10*' microcuries/ gram:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131; b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 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 recuirement, effluent releases via this pathway may continue providec that, at least once per 12 hou s, grab d;

samples are collected and analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of collection time for gross rapioactivity (beta or gamma) at a limit of detection of at least 10- microcuries/mi or lock closed valve S22U19-MV077 or S22Vl9 MUO78 and divert flow to the radwaste 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 pathway may continue provided the flow rate is estimated at least.

once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump curves may be used to estimate flow.

4-3 Revision 22 08-02-90 APPIl0VED AUG 0 21990-1

TABLE 4-2 RADI0 ACTIVE LIOUID EFFLUENT MONITORIIIG INSTRUMENTATION SURVEILUUICE REOUIREMENTS c[wgIEL -

CHANNEL' SOURCE CHAINIELS FUNCTIONAL INSTRUMENT **

CHECK _

CHECK CALIBRAT!_05 TEST 1.

GROSS BETA OR GAPMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMIIIAT10ll 0F RELEASE a.

-Liquid Radwaste Effluents Line -

j 2/3 RT-7813 D

P R(2)

Q(1) l b.

Steam Generator Blowdown (Neutralization Sump),

Full Flow Condensate Polisher Effluent i.Me - 2(3)RT-7817 D M

R(7.J Q(1) l Al W

Turbine Plant Sump Effluent Line g

o c.

i 2(3)RT-7821 D

M R(2)

Q(1) i to i

D d.

Steam Generator (E088) Blowdown Bypass i

22 Effluent Line - 2(3)RT-6759 D

M R(2)

Q(1) c-

[

e.

Steam Generator (E089) Blowdown Bypass Line - 2(3)RT6753 D

M R(2)

Q(1) y 2.

FLOW RATE MEASUREMENT DEVICES i

o a.

Liquid Radwaste Effluent Line D(3)

N.A-R Q

b.

Steam Generator Blowdown (Neutralization Sump),

' N.A R

Q l

Full Flow Condensate Polisher Effluent Line D(3) 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

)

4-4 Reirision 22 08-02-90 t

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wa9

<- w we

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+,,. w %.

wN-~eu---,

e-

.==w ew

,m m.

. - umwesc-

TABLE 4-2 (Continued)-

IABLE 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, A

alarm capability (if appitable), proper res onse based upon surveillance requirements) and isolation function (if app icabl ), the less of the 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 k

any of the following conditions exist:*

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards ceri,1fied by the National Bureau of Standards or 4

using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made, l

l t

s

• If-the instrument controls are not in the operate mode, procedures sna11 require that the channel be declared inoperable.

APPROVED AUG 0 21990 4 Revision 22 08-02-90

- - - _ ~

400 EQUIPMENT

+

4.2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTkUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent' monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their i

alarnVtrip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded. The alarnVtrip setpoints of these channels shall be determined in accordance with ODCM-APPLICABILITY: ~ At' a11' times ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alaravtrip setpoint less conservative than required by the above specification, immediately' sus and the release of radioactive gaseous effluents monitored by the affected' channel e

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 return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in-the next Semiannual Radioactive Effluent Release Report why the inoperability was not ' corrected in a timely manner.

-l SURVEILLANCE REOUIREMENTS 1

.1 Each-radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performece of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies'shown in Table.4-4.

1 Y

APPROVED AUG 0 21990 1

4-6 Revision 21 02-15-90

-rwwe+-

w gr

,, ~...

.-o..-.. -.,,s%,m,-.,.A

+-,,,-e,w+,e.wm-.

c

-h-w--w

. -,-*e

t i

TABLE 4-3 PADI0 ACTIVE GASECdS EFFLUENT MONITORING INSTRUENTATION

.i MINIMUM CHAISIELS INSTRUMENT ***

OPERABLE-APPLICABILITY 80J13 1.

WASTE GAS HOLDUP SYSTEM l

i a.-

. Noble Gas Activity Monitor -

Providing Alarm and Automatic j

Termination of Release -

1.

35 2/3 RT-7808, 2 RT-7865-1 or l

3 RT-7865-1 b.

Process Flow Rate Monitoring Device

.1 36 i

2.

CONDENSER EVACUATION SYSTEM

p m

a.

Noble Gas Activity Monitor - 2(3)RT-7818 or 2(3)RT-7870-1 1

37-

't!

b.

Iodine Sampier l'

40 c.

Particulate Sampler 1

40 W

d.

Associated Sample Flow Measuring Device 1

36 36 m

e.

Process Flow Rate Monitoring Device 1(1)

C

. PLANT VENT STACK j

3.

3 C

i o

a.

.. Noble Gas Activity Monitor - 2/3 RT - 7808, 2RT-7865-1 1

37-o or 3RT-7865-1 co b.

Iodine Sampler 1

40 m

c.

-Particulate Sampler 1

40 g

d.

Associated Sample Flow Measuring Device--

I' 36 i

e.

Process Flow Rate Monitoring Device 1(2)

~

36 4.

CONTAINMENT PURGE SYSTEM a.

Noble Gas Activity Monitor -' Providing Alam 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 h

d.

Process Flow Rate Monitoring Device

'1.

36 e.

Associated Sample Flow Mea 9 ring Device I

36 4-7 Revision 22 08-02-90

-l I

,._s 1

TABLE 4-3 (Continued)

)

TABLE NOTATION At all times.

1 MODES 1-4 with any main steam isolation velve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operabili+.y of the monitor, providing the inoperable recorder does not cause the 7,onitor to become inoperable (i.e., feedback signal). As long as the monitor has 4

indication, alarm capability (if applicable), proper response (based upon i

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 I.ot available, then comply with ACTION 36.

(2) 2/3 RT-7838 is not equi ped to monitor rocess flow.

If 2RT-7865 or-

'b 3RT-7865 is not availab e to continuous y monitor plant vent stack flow, then comply with ACTION 36.

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:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the' F'acility Staff independently verify the release rate' calculations and discharge valve lineup; Otherwise, suspend releases.of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the-flow rate is estimated at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. System design characteristics may be used to estimate flow.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels 0PERABLE requirement, effluent releases via'this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 39 - Remaining'in Technical Specifications.

' APPROVED AUG 0 9, 1990 4-8 Revision 22 i'

08-02-90

TABLE 4-3 (Continued)

TABLE NOTATION 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.

i i

t I

ihPPROVED Allt; o 9 7999

~

4-9 Revision 22 '

'08-02-90

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLMCE REOUIREENTS.

i' CHAMEL MODE FOR WICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT ***

CHECK CHECK CALIBRATION TEST IS REGUIRED i

1.

WASTE GAS HOLDUP SYSTEM a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2/3 RT-7808, 2RT-7865-1, t

3RT-7865-1 P-P R(3)

Q(1) i b.

Process Flow Rate Monitoring Device P

N.A' R

Q 4

2.

CONDENSER EVACUATION SYSTEM i

a.

Noble Gas Activity Monitor -

i b.

Iodine Sampler W

M R(3)

Q(2) 2(3)RT-7818,2(3)RT-7870-1 D.

N.A N.A N.A

-l c.

Particulate Sampler W

N.A N.A N.A f

d.

Associated S-

.le Flow l

..g l

m Measuring Device

.D N.A R

Q c

to e.

Process Flow Rate Monitoring o

Device (2(3)RT-7870-1)

D N.A R

Q-m i

ts n

C O

r o

r w

i i

i wc) j j

2

~

.4-10 Revision 22 I

08-02-90

.~..

~

~..

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

_M TABLE 4-4 (Continued)

RADIGACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATi 7 SURVEILLANCE REQUIREE NTE l

CHAINIEL MODE FOR W ICH CHANNEL SOURCE CHAINsEL FUNCTIONAL SU3VERLANCE INSTRUMENT ***

CHECK CHECK

.CALI N TION TEST IS RE0JIRED t

3.

PLANT VENT STACK l

a.

Noble Gas Activity Monitor -

D M-R(3)

Q(2) 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1 b.

Iodine iagler W

al A N.A N.A c.

Particulate Sampler W

>l. A N.4 N.A-d.

Associated Sample Flow l

t Measuring Device D

N.A R

Q e.

Process Flow Rate. Monitoring l

Device D

N.A R

Q 4.

CONTAllMENT PUPGE SYSTEM a.

Noble Gas Activity Monitor -

1 Providing Alarm and Automatic 4

Termination of Release -

t i

2(3)RT-7828,2(3)RT-27865-1 D

P(4)"

R(3)

Q(1)

{

y b.

Iodine Sampler.

W N.A-N.A N.A.

i c.

Particulate Sampler.

W-N.A N.A N.A cf d.

Process Flow Rate Monitoring l

c Device D

N.A R

Q e.

Associated Sample Flow j

[

3 i

c-Measuring Device D

N.A R

Q M

i O

4-11 Revision 22 08-02-90 i

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

IABLE 4-4 (Continued)

TABLE NOTATION At all times.

Modes 1-4 with any main steam isolation valve and/or any main steam 1

isolating h*W valve not fully closed.

Monitor Reco. a s 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-A) indication, alarm capability (if-applicable), proper response (based upon surveillance requirements) and isciette,a function (if applicable), the loss of the recorder does not rr,nder the monitor inoperable.

(1)

The CHANNEL DNCTIONAL> TEST shall also demonstrate verification of effluent path isolation closure ano control room alarm annunciation if Ri any of the following conditions exist:#

1.

Instrument indicates measured levels above the alarW trip setpoint.

2.

Circuit failure.

3.

Instrument-indicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room l

alarm annunciation occurs if any of the following conditions exist:#

J 1.

Instrument indicates measured levels above the alarm setpoint.

l 2.'

Circuit failure.

3.

Instrument indicates a downscale failure, j

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of l

the reference standards certified by the National Bureau of Standards or using' standards that have been obtained from suppliers that participate

'in measurement assuran.e activities with NBS.

These standards shall i

permit calibrating the system over its intended range of energy and t

measurement range.

For subsequent CHANNEL CALIBRATION, sources that have i

been related to the iaitial calibration shall be used, j

l (4)

Prior to each roles.se and at least once per month.

1. 1f the instrument controls ate not set in the operate mode, procedures shall call for ieclaring the channe; inoperable, i

APPROVED AUG 091990 4-12 Revision 22 08-02-90

f 4.3 OPERA 81LITY OF RADI0 ACTIVE WASTE E511PMENT i

The flow diagrams defining the treatment paths and the components of the j

radioactive liquid, gaseous and solid waste management systems are shown in Figures 4-5 thru 4 7.

j t

?

[

i I

i i

t 6

h

.t APPROVED AUG 0 21990 i

4-13 Revision 21 02-15 90

Full Flow S/G S/G Turbine Hain Condensate E088 E089 Plant Condenser Polisher Sump A

y RT-7021 (continuous)

Conductivity Sump

=

y.RT-6753,SteamCen.BlowdownBypass(continuous) tow Conductivity Sump y RT-6759, Steam Cen.-Blowdown Ilypass (continuous)

Ms Ms as Illowdown-O Processing System Saltwater from (continuous - sampled)

~

. llcutral ization Component Cooling y

. Sump llcat Exchanger c)

CD co g

y RT-7817 (batch or continuous)

E$

Itadwaste Primary Tanks y 2/3RT-7813 Liquid Itadwaste Effluent Line (batch}

ltadwaste Secorulary Tanks Primary Plant flakeup Tanks Condensate Itonitor Tanks PACIflC GCEAN y Intake e Radioactivity linnitor outra11 NOTE: Monitored pathways are unit specific unless indicated to be common to Units 2 and 3.

FIGURE 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems Revision 22 4-16 08-22-90

}

Atmosphere Atmosphere Atmosphere Atmosphere Unit 3 Vent-*

~

--Unit 2 Vent

~

)

-4 2RT-7870-1 3RT-7865-1 S-3RT-7870-1 4-2RT-7865-1(1) 9-

-4 2.".,!-7965 - 1

-4 3RT-7865-1(1)

.I t

-6 2RT-7818

-4 3RT-7818 1

c e

-4 2/3RT-7808

-4 2RT-7828 3RT-7828 e-

1. g Plant +

g 4

2xs Unit 2 Vent Unit 3 O

Containment Containment y

Purge Purge l

~!

c:s I

I

~

E Unit 2 Building Unit 3 Building 25 Ventilation Exhausts y

, Ventilation Exhausts o

i w

w Unit 2 Condenser Gas Decay Unit 3 Condenser w

Evacuation System Tanks (6)-

Evacuation System f

~

4 Radioactivity Mo?-!k27 l

i k

Figure 4-6 Release pathways and monitors of radluactive' gaseous effluents for SONGS Units 2 and 3.

~

4 o

(1)

RT-7865 can be aligned to either containment purge or the plant vent stac'

~

r i

FIGURE 4-6 SONGS 2 & 3 RADI0 ACTIVE GASEOUS WASTE TREATMENT SYSTDtS 4-15 Revision 22

[

08-02-90

f i

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aga=

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APPROVED AUG 0. 2 1990'

---

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l 5.0 MDIOL0t! CAL' ENVIR0001DITAL NONITORID l

l i

I i-5.1 Monitorina Procram SPECIFICAUQH l

5.1.1 The radiological environmental monitoring pcogram shall be i

conducted as specified in Table 5-1.

The,aquirements are applicable at all times, j

L APPLICABILITY: At all times ACTION:

a.

Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification (s) 6.9.1, prepare and submit to the Commission, in the Annual' l

Radiological Operating Report (see 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 otherreportrequiredbyTechnicalSpecification(s)6'9.1, prepare and submit to the Commission, within 30 days from I

. o\\ l l

the end of the affected calendar quarter a Report pursuant to Technical. Specification (s) 6.9.1.13.

When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report sha113e submitted if:

concentration'fli '

' concentration (21

+.. 2 1.0

+

limit level (1) limit'evel(2) a 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)is not required if the measured 1.2.1, 2.2.1 or 2.3.1, as appropriate. This report level of radioactivity was not the result of plant.

effluents; however, in such an event, the condition shall l

be reported and described in the Annual Radiological l

Environmentil Operating Report (see Section 5.4).

d.

With fruh 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 Technical Specifications 6.9.2, a~ Special Report which identifies the cause of the unavailability of st.1ples and 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 obtair;ed are added to the environmental monitoring program as replacement. locations.

5-1 Revision 22

)

08-02-90 A PPR OV E D AllC 0 p Jgg()

500 RADIOLMICAL EWIR000EffAL NOMITMIM (Continued)

SURVEILLANCE REQUIREMENTS

.1 The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in F.. t 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.

9 4

1 APPROVED. AUG 0 21990 l

5-2 Revision 22 08 02-90 I

F TABLE 5-1 RADIOLOGICAL ENVIROI5 ENTAL NOHITORING PROGRM 1

Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Collection Frs_;;;va Tyne and Frs_;;;v of Analyses 1.

AIRBORNE Samples from at least Continuous operation Radiciodine cartridge. Analyze of sampler at.least once per 7 days for I-131.

Radioiodine 5 locations with sample collection Particulate sampler. Analyze for r

and 3 samples from offsite Particulates locations (in different

, required by dust

. gross beta radioactivity 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> onceper7 days.jeast following filtgr change.

Perform loading, but at t

sectors) of the highest gamma isotopic analysis on each calculated annual average 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) i the highest calculated sample at least once per 92 days.

i annual average ground-level D/Q.

j i

l 1 sample from a control loca-tion 15-30 km (10-20 miles) distant and in the least pre-valent wind directionC

2. DIRErT At least 30 locations includ-At least once per Gamma dose. At.least once per 92 days.

l j

i R/if 'TIONG ing an inner ring of stations 92 days.

t in t:ia general area of the

~

site boundary and at outer 3

ring approximately in the 4 i

y

.e to 5 mile range from the site l

su with a station in each sector 3

o of each ring. The balance of

.i the stations are in special

~

s y

interest areas such as popula-tion centers, nearby residences, c%

schools, and in 2 or 3 areas to i

cn serve as control stations.

=>

N)

I ' '5 I

a 5-3 Revision 21 j

02-15-90 i

i

-.... ~

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

l TABLE 5-1 (Continued) l RADIOLOGICAL EllFIRel5EllTAL IIDIIITORIIIG PROERE Exposure Pathway Ilumber of Samples Sampling and-ud/or Sample and Sample Locationsa Collection Fre-;;;. ;va Tvoe and Freauency of Analyses i.

3.

WATERBORNE l

a.

Ocean 4 locations At least once per.

Gamma isotopic analysis of each f

monthly sample. Tritium analysis l

month and composited zaarterly of composite sgle at least once per 92 days. '

i b.

Drinking 2 locations flonthly at.each Gamma isotopic and tritium location.

analyses of each sample.

c.

Sediment 4 locations At least once per Gamma isotopic analysis cf each g

f from 184 days.

sample.

Shoreline 1-i d.

Ocean 5 locations At least once per Gamma isotopic analysis of each R-1 Botton 184 days.

sample.

Sediments i

i m

i N

l us o

4 en j

~D i

2>

C 4

]

O o

eo G

I I

o

^

1 5-4 Revision 22 08-02-90 1

i 4

TABLE 5-1 ~(Continued)

RADIOLOGICAL EMIRWWENAL WIIITORIM PMGM Exposure Pathway Number of Samples Sampling and i

and/or Sample and Sample Locationsa Collection Fr; u ;va Troe and Fre====ry of Analyses t

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 si;;p.;ad..

2. Crustaceae-such as crab or lobster.

3. Mollusks-such as l

1impets, seahares or class.

b.

Local Crops-

.2 locations Representative Gamma isotopic analysis on edible vegetables, normally portions semiannually and I-131 I leafy and 1 fleshy analysis for leafy crops.

col.lected at harvest m

time. At least 2 I

N vegetables collected m

M semiannually'fra 0

l each location.

4 L

t-s i

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(

3

.c-C O

I 4

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m i-ca

(

5-5 Revision 21 02-15-90 i

-.... - -. -.. ~

... - -. - -. - -........ ~ -

TABLE 5-1 (Continued) i TABLE IISTATIGIl

!N l

a.

Sample 1ocations are indicated on Figure 5-1.

b.

Gamuna isotopic analysis means the identification and quantification of gamma-emitting radionuclides that say be attributable to the effluents from the facility.

~

i c.

The purpose of this sample is to obtain background information.

If it is not. practical to establish control i

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 l

l checked before operation in the field or several should be mounted in series'to prevent loss of iodine.

l e.

Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) j systems used for environmental monitoring. One or more instruments, such as a pressurized 100 chamber, for J

measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

l For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more i-phosphors'in a packet may be considered as two or more dosimeters.. Film badges should not be used for measuring direct radiation.

~

f.

Composite samples should be collected with equipment (or equivalent) which.is capable of collecting an aliquot at L

time intervals which are very short (e.g., hourly). relative to the compositing period (e.g., mosthly).

J i

j eb' t

'15

• U M

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=

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4

~

5-6 Revision 22 l

08-02-90 i

o

,,..m J

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TABLE 5-2 RtPORTIES LEVELS FOR RADI0 ACTIVITY CWEEIERATIWS IN ENVIRMENTAL SMFLES

!!eporting Levels Airborne Particulate j

Water or Gases Marine Animals.

~ Local Crops Analysis (pCi/l)

(pCi/s*)

~

(pCi/Kg, wet)

(pC1/Kg, wet)

H-3 2 x 10*(a)

Mn-54 1 x 10 3 x 10*

I 8

I Fe-59 4 x 10*

1 x 10*'

[

Co-58 1 x 10*

3 x 10' Co-60 3 x 10*

1 x 10' Zn-65 3 x 10*

2 x 10' l

2 Zr-Nb-95 4 x 10 p

I x 10*

j.

I-131 2

0.9 f

Cs-134 30 10 1 x 10*

1 x 10"

3 i

o Cs-137 50 20.

2 x 10*

2 x 10*

i y

Ba-La-140 2 x 10' 3>

Ccn (a) For drinking water samples. This is 40 CFR Part 141 value.

o to

2 8

5-7 Revision 21.

02-15-90 1..s.

4 r..,-y.-

.,, ~,, ~.

,#-n,.,

,,m

,.w.

. %,,.[_

,,,,,,..,w

my

~__

~-

• LJABLE 5-3

_MAXIIRIM VALUES FOR THE LOWER LIMITS 0~ DETECTION (LLD) a,e

~-

Airborne-Particulate

~ :V Water

c. Gases MarinL Animals:

Local Crops Sediment Analysis-(pti/1)'

!(pC1/a*):

.(pC1/Kg'wot)

(pC1/Kg, wet)~

(pCi/kg,. dry)

~

gross beta

'4-1:x 10-*

~H-3 2600 Mn-54 15 130 s

Fe-59 30 260 Co-58, 60 el5.

130 Zn-65 30

.260 Zr-95:

30 Nb-95'.

15 m

I-131 1 b~.

-7 x;10

• 60 m

W Cs-134 IS

- 5 x 10 *'

139 60 150 O

I

Cs-137 18'

- 6 x 10 *l 150-

- 80

-180r

's Ba-140 60 :

3c=

m La-140 15 to G3

.- co 5-3' Revision 21-02-15-90

.--c m-m-

e.

2.e

..__,,,v,,

._u,w.

u

,,_.w_.wy,

_ j a,_,,,

_,_r y

l.r

~

TABLE 5-3' (Continued)

TABLE NOTATION a2 The LLOxis the smallest concentration of radioactive material-in' a sample that.'will be detected with 95% probability with.5% ' probability of_falcely concluding that a-birk _ observation represents a "real" signal.

For a particular measurementLsystem (which may include radiochenical separation):

4;66 s LLD --

b E e V e-2.22-x 10'. Y-

. exp- (-A4t) where:-

LLD_ is the "a. priori" lower limit of detection as defined above l

(as: microcurie pergunit-mass-or volume),

l sb is the standsrd deviation of the background cour,2ing rate' or.of the counting rate of'a blank l sample as appropriate (as counts per.

minute),-

E'is_the counti g efficiency l(as counts'per transformation),

l V is~ the. sample size (in units"of mass or volume),

2'22 x'10' is the number of transformations per minuteLper

' microcurie,

Y is the fractional radiochemical; yield!(when applicable),:

A is th9 radioactiveLdecay constantifor the narticular-radior.uclide, and environmental ~ sampir% not' plant effluents ). =

~

'(!

at is the elapsod time between midpoint'of sample collection or and of the collectior period.and time of counting (for j

~

i The value of sb used in the bicul. tion of the LLD,for. a detectionLsystem lR 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 calculatingithe LLD for 'a:radienuclide determined by gusna-ray Spectrometry,:the background i

shall include the +voical' contributions of other" radionuclides normally l

nresent in=the samples (e.g.,' potassium-40 in milk samples). Typi. cal -values i

of E,V,Y and:At'shall be used in ths' calculations.

1 APPROVED AUG o.91990 5-9 Revision 22 08-02e90

e

L --%

W- ' ' " '

~

' T T J O ~ ~~ ~^ K :s J ' L l ,

1 -

TABLE 5-3 (Continued 1-TABLE NOTATION 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 2

- A nosteriori- (after_'the fact) limit for aparticular measurement.*

b.

.LLD for drinking water.-

c.

Other. peaks which are measurable and. identifiable, together with the s

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, HA9L-300 - (revi sed ' annually).

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

'Hartwell, J; K.,." Detection Limits for Radioisotopic Counting a

'(3)hniques," Atlantic Richfield:Hanford Contpany Report ARH-2537 (June ~ 22, Tec 1972).-

a t

t

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u l'

5 t

j l'

li:

APPROVED AUG 0 21990 k'

5-10 Revision 21 02-15-90 i

5.0 Rf4DIOLOGICALENVIR0letENTAL. MONITORING-(Continued) q Si2 LAND USE CENSUS I

SPECIFICATION 5.2.1-

- A land-use census shall be conducted and. shall identify i.he-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.

L For elevated' releases as defined in Regulatory Guide 1.111,.

Revision 1,7 July 1977,- the land use census shall also m

identify: the locations. of all milk-animals and alligardens -

of greater than 500 square 4 feet producing fresh' leafy-vegetables'in-each'of the 16 meteorological sectors within

' a distance of!three miles.=

1

APPLICABILITY:

At all; times-ACT)0N:-

4 a.

With a land use census identifying a: location (s) which-yields a calculated dose or dose commitment greater-than

.i the va' sues currently being calculated in-Technical.

Specification 2.3.1,11n lieu of any other report required by Technical. Specification 6.9.1,- prepare and submit: to :

the~ Commission within 30 days pursuant <tol Technical-h, a Specification 6'.9.2,. a Special Report which identifies the -

t new. location (s).--

With a la'd use census identifying a;1ocation(s) which b.

n

yields;a calculated' dose-or dose commitment via the same' exposure. pathway: 20, percent-greater than;at a location from-l which samples 'are currently:being obtain'ed in accordance l

with Section 5.1,-in lieu of any other. report required by;'

Technical Specification 6.9.1,- prepare and submit to the 1

Commission within 30 days, pursuant:to Technical 4

. Specification 6.9.2, a Special Report which identifies the new location. 'The new location shalllbe.added to:the:

. radiological environmental monitoring program within.30'-

days. The sampling location, excluding the control station i

location, =having the lowest calculated does or dose commitment via the same, exposure pathway may be deleted from this monitoring program.after October 311of,the: year in'which;this land use census was: conducted.

SURVEILLANCE REQUIREMENTS t

.1 The land use census shall be conducted at.least once per-12 months between the dates of June 1 and October-lciising that information which will provide the best results, such as by a -

1 door.to-door survey, aerial survey, or by consulting local agriculture ~ authorities.

1

• Broad leaf vegetation sampling may be performed at the site boundary in the l

direction sector with the highest 0/Q in lieu of the garden census.

5-11 Revision 22 08-02-99

' APPROVED AUG n j ;ggg i

m 1

, 5.0:. RADIOLOGICAL'ENVIRONNENTALMONITORING'(Continued)'

'5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed 'on radioactive materials i

supplied as part of an Interlaboratory Comparison Program

-l J_

twhich has-been approved by the Commission.

APPLICABILITY:--At all times i

J ACTION:

La.

With analysesinot being; performed as required above,.

report'the corrsctive actions'taken'to' prevent a-t

' recurrence to t%e Commission in: the Annual Radiological-j.

Envi ronme::t..1_ Operati ng. Report.

j l

SURVEILLANCE REQUfREM':NTS -

.1 '

A summary;of the rasults obtained as part of the abov-red

'Interlaboratory (,aparison Program, and in accordance h sction=

5.4.1= of this docueent shall be included in the Annual Radiological lEnviror. mental Operating Report (set ection 5.4)..

~

1 E

i 4

55 L

l~

t*

l ~.

3 APPROVED AUG 0 21990 5-12

'RevisionL22 i

l 08-02-90 t

l o

3 5.0 RADIOLOGI' CAL =ENVIR000tENTAL NONITORING '(Conti$ued):

I 1

5.4: ANNUAL ~ RADIOLOGICAL' ENVIRONMENTAL OPERATING REPORT *

.l 4

5. 4'.1 ^

The-annual radiological environmental operating reports-shall include: summaries;. interpretations, and an analysis j

'of trends. of the results of the radiological environmental' surveillance activities for the' report; period, including a

. comparison with preoperational studies, operational, 2 controls (as appropriate), and previous environmental;

'l

< surveillance reports and:an assessment of the observed -

I.

L

' impacts of the plant _ operation lon the environment.: The reports shall also. include the-results of land use censuses L

required by-Section:5.2.

If harmful effects or evidence of irreversible damageTare detected,by the monitoring, the" report shall; provide an analysis of: the problem and a.

1 planned course of action to alleviate the problem.

I

The' annual radiological ~environmentalioperating reports-

-shall; include summarized-and> tabulated results in the format of Regulatory Guide 4.8, December-1975 of all-i-

radiological environmental' samples-taken during the report period. ' I6 the event: that:some results.are not available-

- for inclusion withithe report, the-report shall be-i submitted noting-and explaining the reasons for the. missing.

O results. - The m.issing datat shall-be submitted as soon: as-1

[

possible in a: supplementary report.

The reports shall also11nclude the following: < a - sunnary L

-description of the radiological' environmental monitoring 1

program; a map of a11' sampling locations keyed to a: table' giving_ distances;andidirections from the mid-point ofc i

reactor Units 2land 3;J and the resultsLuf -licensee participation -in the Interlaboratory Comparison' Program,'.

required by Section 5.3..

l-i y:

l'

[

A single submittal may be made for a multiple:unitL. station,[ combining those-

[

sections that are common to all units at the1 station.

4 s

('

i y

q c

Lr

[

s G

7 1

l APPROVED A(JG 0 21990-i 5-13 Revision'21 0

02-15-90~

0 7

. m

_,..J.,____.

.n.

...~

5.0'-RADIOLOGICAL ENVIR0000 ENTAL N0 NIT 0 RING (Continued)~

j g.

-5.5;SAMPLELOCATlgg

?The Radiological-Eny'ironmentalLMonitoring Sample Locations are-identified in Figure.5-1~. These sample: locations are described in

-[

o

- 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 L building complex.. Table 5-6 givesithe sector and direction' designation for the Radiological Environmental' Monitoring j

L 7 Sample Location on Pap,. Figure 5-1..

4..

1

'?

i J

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1 l-i a

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1{

$PPRoyggpyggpggg 5-14--

Revision 21

~

02-15-90 o

e.

Page 1'of 6 i

. TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING' SAMPLE LOCATIONS DISTANCE

• TYPE OF SAMPLE-AND SAMPLING LOCATION ***

(miles)

DIRECTION

• Direct Radiation 1-City _of San Clemente (SDG&E Offices)-

.5.6

NW.

2s Camp San Mateo (MCB,. Camp'Pendleton) 3,5 N

3 Camp San Onofre-(MCB, Camp Pendleton) 2.6-NE-4 C, amp Horno.(MCB, Camp Pendleton)

~ 4. 5 '

E L5' Camp Las:Pulgas (MCB, Camp Pendleton) 8.5 E-6 Old Route 101 (East-Southeast)-

'3.0-ESE' 7

Old Route 101 (East-Northeast) 0.5 ENE.

8 Noncommissioned Officers Beach Club 1.5' NW 9.

Basilone' Road /I-5 Freeway Offramp 2.0:

NW 10 Bluff (Adjacent'to PIC #1)'

O.7 WNW-11 Former-Visitor's 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

' sNW 15 Southeast Site Boundary (Office. Building).

0.2**-

SEL 16 East Southeast Site Boundary 0.4**

ESE 17 Transit Dose.

18 Transit Dose 19' San Clemente Highlands 5.0 -

NNW l

20 San Clemente Pier 5.3-NW 21 Concordia Elementary School - San Clemente 3.5 NW 22 Former Coast Guard Station - San Mateo Point 2.7 WNW 23' San Clemente General-Hospital 8.2 kW-24

-San Clemente High School 6.0 NW q

Distance (miles) and Direction (sector) are. measured relative to Units 2 a'd 3 midpoint.

Direction is-determitied 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.

,,p MCB - Marine Corps Base

-PIC - Pressur.ized Ion Chamber l

E0VED Alm a g 1990 5-15 Revision 22 i

08-02-90 u.

I E

Page 2 of 6 TABLE 5-4 1

1 RADIOLOGICAL-ENVIRONMENTAL MONITORING SAMPLE LOCATIONS.

DISTANCE *

' TYPE OF SAMPLE AND SAMPLING LOCATION ***

-(miles)

DIRECTION

• Direct Radiation (Continued) 25' Convalescent Home - San Clemente -

8.0 NW 26-Dana. Hills High School 11.0:

NW.

27 U.'S, Post 0fficeL-Dana Point 10.6 NW 28.Doheny Fire Station'- Capistrano Beach 9.5 NW 29-San Juan Capistrano Fire Station 10.8

.NW-30 Laguna Beach Fire Station 17.5 NW 31 Aurora Park-Mission Viejo 18.7 NNW 32 Santa'Ana Police Department.

32.0 NW

~

33 Camp Talega -(MCB, Camp Pendleton) 5.7 N

34 San'0nofre School (MCB, Camp Pendleton)-

1.9-

'NW 35' Range 312 (MCB, Camp Pendleton)'

4.7 NNE-36-Range'208C(MCB,CampPendleton) 4.2 NE' 37 Laguna Niguel Fire Station 14.2-

.NW-38 -San Onofre State Beach Park-3.3!

SE' 39 Basilone Road Trailer Park'(MCB, Camp Pendleton):

-1.4' NNW 40 SCE Training Center - Mesa (Adjacent to PIC #3)

0. 7. 5

NNW t ~

41 Old Route 101 - East 0.4 E

42 Horno Canyon (MCB, Camp Pendleton) 4.7-E 43 Edison Range (MCB,' Camp Pendleton) 10.6

'SE 44 Falibrook Fire-Station 18.0 E

45 interstate 5 Weigh Station-2.0 ESE 46-San Onofre State' Beach Park 1.0 SE

-47 Camp Ln ores (MCB, Camp Pendleton) 8.6 SE 48 Mainside (MCB, Camp.Pendleton).

15.0 ESE L

~

Distance- (miles) and Direction.(sector)' are _meesured relative' to Units 2 and l

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

! APPRoyy8 sng 0 21990 5-1 Revision 21 02-15-90

.m m.

, ~, _ _. -.

Page-3 of 6; TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL. 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 15.54 SE 51 Carlsbad Fire Station.

18.6 SE l

52 Vista Fire Station

-21.0 ESE:

53 ' San Diego-County Operations Center 45.0 SE 54 Escondido Fire Station.

32.0 ESE 55 San Onofre State B(ach (Unit l', West: Southwest) 0.2**

WSW 56-San Onofre State Bea:h (Unit 1, Southwest)

• 0.1**

SW-3 57 San Onofre State Beact (Unit 2) 0.1**

SSW 58' San'Onofre State Beach '. Unit 3) 0.1**

S

'59

' SONGS Meteorological Tower 0.3**

.WNW 60 Transit Control Storag; Area:

61 Mesa'- East Boundary (Adjacent to PIC #4)-

0.7 N

62 MCB - Camp Pendleton (Adjacent:to PIC #5) 0.6' NNE

~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

-l 66 San Onofre State Beach (Adjacent to PIC s9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to.PIC #2) 0.6 NW 68 Range 210C (MCB, Camp'Pendleton) 4' 3 ENE 99 Transit Dose Distance (miles) and Direction (sector).are measured relative to Units 2 ar.d 3 midpoint. Direction is determined from degrees true r. orth.

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 i

APPROVED-AUG 0 21990 5-17.

Revision 21 02-15-90

~_ ___ _ _ _ _ _ -

2 Page 4:of;6-TABLE 5-4

-RADIOLOGICAL ENVIRONNENTAL MONITORING'SANPLE LOCATIONS p

p

. DISTANCE

• l-TYPE OF SAMPLE AND SAMPLING LOCATION (milesF DIRECTION *-

d i

Airborne 3

'l City of San Clemente (City. Hall)

'5.5

- NW J

2-Camp San Onofre~(Camp Pendleton)'

l.8 NE 3

Huntington Beach Generating Station-

'37.0

.NW=

l 5

Units.2 and'3 Switchyard 0.13**-

NNEL

.6 SONGS Meteorologicalz Tower 0.3**

WNW-9~

. State Beach' Park 0.6 ESE:

l 10 Bluff 0.7' WNW 11 Mesa EOF.

.0.7 NNW 12 Former SONGS Evaporation Pond-0.6 NW 13.

Marine Corps Base (Camp.Pendleton East) 0.7 E~

. Soil Sampies 1

Camp San Onofre 2.5

.NE 2

Old Route 101 - East. Southeast 3.0-ESE 3

-Basilone Road /I-5' Freeway Offramp 2.0 NW:

4 Huntington Beach Generating Station 37.0 NW, 3

5 Former Visitor's Center 0.2**

NNW' Ocean Water l

L A

Station Discharge Outfall - Unit 1 0.5 SSW i

B Outtall - Unit 2 0.7 SW C

Outfall - Unit 3 0.7 SW.

D Newport Beach 30.0 NW i

i Distance'(miles) and Direction (sector).are measured relative to Units 2 and 3 midpoint.

Direction,is determined from degreer true north.

Distances are within the Units 2 and 3-Site boundary (0.4 mile in all sectors) and not required by Technical Specification.

APPROVED AUG n 9 IqSO 5-18 Revision 21 02-15-90

Page 5.of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS-i DISTANCE *

-i l

TYPE OF SAMPLE AND SAMPLING LOCATION failes)

DIRECTION

• Drinking Wat6r 1

Tri-Cities. Municipal Water _ District Reservoir-B. 7-NW 2

San Clemente Golf Course Well-3.5 NNW 3-Huntington Beach-37.0:

NW' Shoreline. Sediment (BeachSand).

1' San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2

San Onofre Surfing' Beach 0.9-11W -

3 San Onofre State Beach (3.1 miles Southeast) 3.1 SE-4 Newport Beach (North End) 30.0 NW i

Local Crops 1

San Mateo Canyon (San 'lemente Ranch)-

2.6 NW C

2-Southeast of Oceanside 22.0 SE 3

San Clemente Resident with Garden

'4.1

.NW l

1 f

l s

v.

U Distance (miles) and Direction (sector) are measured relative to Units 2 and 1

3 midpoint. Direction is determined from degrees true north.

APPROVEn pug 99;999 5-19 Revision 22 L

08-02-90' L

Page 6 of;6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE *'

TYPE OF SAMPLE-AP9 SAMPLING LOCATION (miles)

DIRECTION

• Non-Migratory Marine Animals A.

- Unit 1 Outfall 0.6 -

WSW B

Units 2 and 3 Outfall-0.7 SSW C

Newport Beach 30.0 NW-Kelp A

San OnofreLKelp Bed 1.5 S'

l' B-San Mateo Kelp Bed-3.5 WNW C

Barn Kelp %f ~

6.6 SSE D

Newport Beach 30.0 NW s

t Ocean Botton Sediments A

Unit 1 Outfall (0.5 mile I!est) 0.5 W

B Unit 1 Outfall (0.6 mile West).

0.6 W

C Unit 2 Outfall 0.8 SSW D

Unit '3 Outfall 0.9 S

E Newport Beach 30.0 NW-y

• ' Distance (miles) and Direction (sector) are m o sured relative to Units 2 and L

3 midpoint. Direction is determined from degrees true north.

H D AUG n p ;g99 5-20 Revision 21 02-15-90 L

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta t cT w r*

PRESSURIZED ION CHAMBERS (Dearees)*.

Mete-jiles DIRECTION / SECTOR

• S1 San Onofre Beach 298' 107c 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 S5.MCB - Camp Pendleton 19' 1050 0.6 NNE-B

$6 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

s Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

t 1

APPROVED AUG n 91990 5-21 Revision 21 02-15-90 1

TABLE 5-6 S

SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIR0MIENTAL N0NITORING SANPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE

' Sector:

-Center Sector 22.5' Limit Line Limit SE, tar' Direction:

348.75 0.& 360 11 ~. 25 A

N-11.25-22.51 33.75L B-NNE

?

~2 33.75-45.0 56.25:

C NE-56.251 67.5 78J5 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 l

168.75 180.0-191.25

-J-S 191.25' 202.5.

213.75 K

SSW-

'i l

.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 L

Distance (miles) and Direction (sector) are measured relative to i

i' Units l2 and 3 midpoint. Direction is determined from degrees true North.

l i

3103c. man APPROVED AUG 0 21990 5-22 Revision 21 02-15-90

. _j

Figuro F1 December 5,1989 g

.b D

nevision o L

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~6.0LADMINISTRAI1YI l

3

'6.1 DEFINITIONS LThe defined! terms of this section appear _ in capitalized type and are applicable through these. Specifications..

ACTION 6. 1. 11 ACTION shall be that part of a specification which

! prescribes remedial measures required under designated 1

conditions.' -

CHANNEL CALIBRATION 1

6.1. 2 '

A CHANNEL CALIBRATION shall' be the adjustment', as -

Lnecessaryl of the channet output such that.it respowls with Lthe necessary. range and. accuracy:to known values of.the'

- parameter which the channel monitors.

The CHANNEL.

. CALIBRATION. shall' encompass' the entire channel,! including -

1

'the sensor land ' alarm and/or trip functions, and shalls include the CHANNEL FUNCTIONAL TEST.

The' CHANNEL" CALIBRATION may. be' performed. by anyl series: of. sequential, "

i

- overlapping or total-channel stepsesuch that the entire -

channel is calibrated..

t CHANNEL CHECK

.l 6.1.3-A CHANNEL CHECK shallibe the qualitative ~ assessment of

. channel. behavior during operation.by observation?.This-j

. 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.-

s CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL' FUNCTIONAL' TEST: shall be:;

h 4

a.

Analog channels - the injection:of. a, simulated signal:

i into channel as close to the sensor as practicable tot verify OPERABILITY, including: alarmiand/or trip' functions.

b.

Bistable channels' - the injection:of a simulated:

1 signal into theLsensor to verify OPERABli.ITY, including' alarm and/or trip, functions.

o c.

. Digital computer' channels - the' exercising'of the-digital computer hardware using diagnostictprograms tand the injection of. simulated: process data into the channel to verify OPERABILITY.

s t

i APPROVED MlC 0 9. 1990 i

6-1 Revision 21:

02-15-90 i

u.

. 1.

16,0 ADMINISTRATIVE L(Continued)l DOSE EQUIVALENT'I-131 6.1.5)

DOSE EQUIVALENT-I-131 shall be that concentration of I-1315 (microcuries/ gram).which' alone would produce the same:

L thyroid dose.as the quantity andl isotopic mixture of I-131, a

p I-132,1-133,1-134, and I-135' actually present.

The-thyroid dose cony,ersion factors used for this calculation-shall be.those: listed in Table III of TID-14844,

c

" Calculation'of Distance Factors for Power and Test _ Reactor '

Sites."

r FREQUENCY NOTATION 6.1.6 TheFREQUENCYNOTATIONspecifiedfortheperformanceof5 n

= Surveillance Requirements shal_1 correspond ~ to the intervals i

l defined-in Table 6.2..

h L

SASf85 BMWASILIBEIMENT SYSTEM.

6.1. 7.

A GASEOUS RADWASTE TREATMENT SYSTEM is any. system designed' and< installed to r6 duce 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 radioactivityeprior. to release to the<

i-environment.

MEMBERS OF THE PUBLIC-L 6.1.8 MEMBER (S) 0F;THE PUBLIC:shall include all' individuals-who-by virtuef of their occupational status 'have no formal l

association;with the plant., This ~ category shall include F

nonempioyees -of-the 1iconsee-who am permitted' to: use l

portions of the siteifor recreational,_ occupational, or purposes not associated with plant functions. -This k.

i category shall not include non-employees such as vending-machine servicemen or postmen who, as part:of their formal l,

L job function, occasionally enter an' areaLthat,is l

controlled by the licensee for' purposes of protection of.

L individuals from exposure to radiation:and radioactive -

L material s..

a OPERABLE - OPERABILITY I

6.1.9 A system, subsystem, train, component or device shall be

~

H OPERABLE or have OPERABILITY when:it,is capable of j

performing its. specified-function (s),- and when all necessary attendant' instrumentation, controls, electrical power, cooling 'or seal water, lubrication or.other -

r auxiliary equipment that are required for the system, 1

4 i-subsystem, train,: component ~or device to-perform its..

1 function (s) are also capable of, performing their;related

[

support function (s).

l t

APPROVED AUG 0 2 1990 L

l 6-2

' Revision 22 08-02-90 i

1

.-m

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6T0D ADMINISTRATIVE (Continued);

PURGE' " PURGING-6.1.101 PURGE or PURGING is the controlled ~ process of-discharging air or: gas from a confinement-to" maintain temperature,^

l pressure,: humidity, concentration or other operating-condition,=in such a manner that replacement air or gas-is required.to purify the confinement.

SITE BOUNDARY 6.1.11 The SITE BOUNDARY shall be that 11ne beyond which the land. (

is not owned,11 eased, or: otherwise controlled by the '

licensee.

00LIDIFICATION 6.1.12-SOLIDIf1 CATION shall be.the conversion of radioactive' wastes from 1iquid' systems to a homogeneous (uniformly-distributed), monolithic, immobilized solid with definite ~

volume and shape,. bounded by a stable' surface of' distinct.

outline on all sides (free-standing).-

SOURCE CHECK

'6.1.13-

- A SOURCE CHECK shall be the ~ qualitative assessment of channel response when the: channel sensor:is exposed to a radioactive: source.

THERMAL POWER 6.1.14; THERMAL" POWER shall-be the total reactor. core heat transfer rate to'the reactor coolant.:

r.

VENTING

~

6.1.15 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 *!ENTING process ~.'

APPROVED 'AUG 0 21990 6-3 Revision 22 08-02-90

TABLE 6 OPERATIONAL MODES j

REACTIVITY

% OF RATED AVERAGE COOLANT.

i OPERATION MODE CONDITION. K,ff THERMAL POWER * -

TEMPERATURE-

1. POWER OPERATION 2 0'.99

> 5%

2 350*F

2. STARTUP 1 0.99 s 5%

2 350'F

3. HOT STANDBY

< 0.99 0

1 350'F

4. HOT SHUTDOWN

< 0.99 0

350*F> T,yg>200'F

5. COLD SHUTDOWN'

< 0.99 0

s 200'F

6. REFUELING **

s 0.95 0

1 140*F r

1 j

• Excluding decay-heat.

• • Fuel in the reactor vessel.with the vessel head closure bolts less than fully-l tensioned or with the head removed.

9 4.

l h

-;q APPROVED AllG 0 9 1990 6-4 Revhion 21 02-15-90

.c...

i TABLE;6-2 s.

l l -

i FREQUENCY NOTATION NOTATION FREQUENCY L

-S At'least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> L

'D-At least'once per 24' hours j

W At le.;t once'per 7_ days M'

At:least once per.31 days Q

' At least' once per 92: days -

SA

-At least-once per.'184 days' RT

'At least once per 18 months *-

llS S/U Prior to each reactor startup.

P Completed prior to each release -

N.A.

Not applicable.

Refueling.

Not to exceed l24 months Ii Interval-

• A month is defined as a 31-day period, b

i l

l APPROVED AUG 0 9.-1990 l

6-5 Revision-22

' 02 i L

e r

16.0 ADMINISTRATIVE (Continued) l 6.2-ADHijfjSTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

• 6.2.1 Routine radioactive effluent release reports covering the

. operation of the unit-during the previous 6 months-of t

operation shall-be submitted within 60 days after January 1 and July 1 of each year. The period of the firsttreport shall begin with-the date of initid criticality.

6.2.2 The radioactive' effluent release reports shall include a summary of the quantitics of radioactive. liquid.and gaseous effluents-and: solid waste released from the unit.as.

outlined-in Regulatory Gitide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Paterials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, " Revision:1,. June-1974, with data s:mnarized on.a quarterly basis following.

the formattof Appendtx:B thereof..

I The radioactive:eff16ent releas' report'to be. submitted 60 e

days after January I each year shallz include an annual.

summary of hourly acteorological, data collected over the previous year.,This annual summary may be either.in.the form of anihour-by-hour listing of wind speed, wind direction, and atmospheric. stability,c and precipitation-(if measured) on magnetic ~ tape,-or in'the form-of join +

frequency distributions of wind speed, wind direct un, and~

S

~

j.

. atmospheric. stability. This same report shall include an l

assessment of the radiation doses due.to the radioactive liquid and gaseous-' effluents released from the: unit or station during the previous calendar year. This.same report shall alsot include' an assessment of the-radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY-(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) shall be included in these reports.L The meteorologica1' conditions concurrent with the time of release of.

radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall h used for determining'the gaseous-pathway doses.

The an.essment of radiation doses shall be. performed in accordance with the OFFSITE DOSE CALCULATION-MANUAL (0DCM).

APPh0VED AUG 0 t1990 4 6 Revision-22 08-02-90

.t

+

2 m,.

.+

~.,. _ _ _ _ _ _ _ _

e-.

6.0: ADMINISTRAT1Yi (Continued) 1 1

L 6.2 ADMINISTRATIVECONTROLS-(Continued)-

j

~ The radioactive effluent release report to be submitted 60 days after January l'of each: year.shall also include-'an assessment of radiatiot, doses to the likely most exposed

'1 L

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 Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. I'.

3 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 l

b.

Total.arie cuantity (specify whether determined by met erement or estimate),

c.

Principal radionuclides (specify whether, determined by measurement or estimate),

d.-

Type of waste (e.g., spent. resin,, compacted dry.

waste, evaporetor bottoms),

e.

Type of container (e.g., LSA,: Type A, Type.B,

'3 Large-Quantity),-and.

k f.

Solidification Agent.(e.g., cement,. urea formaldehyde),

i

~

The radioactive effluent; re1 ease reports shall include-unplanned releases from the site to unrestricted areas-of I

radioactive materials in ' gaseous and liquid effluents on a

+

quarterly basis.

The. radioactive effluent release reports shalliinclude any changes to the PROCESS CONTROL' PROGRAM'(PCP)'made'during the reporting period.-

1 i

• A single submittal may be made for a. multiple unit station. The submittal.

should combine those sections that:are common to all-units at'the Station; however, for units with. separate radwaste systems', the submittal shall specify the rele'ases of radioactive material from each unit.

APPROVED AllG 0 9 1990 6-7 Revision 22 08-02-90 l

'I 6;0 ADMINISTRATIVE (Continued).'

6.3 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liqu'id,'&

-Gaseous)-

Licensee: initiated major changes ~to'the radioactive waste systems (liquid & gaseous):

.l..

Shall be reported to the Commission in the Monthly Operating l

Report.for the >eriod in which the evaluation was performed k?l pursuant to Tecinical Specification 6.5.2.

The discussion of each change shall contain:-

A summary of the evaluation-that led to the determisation a.-

.that the change could be made in accordance with 10 CFR 50.59; 3

b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or-l supplemental. information; i

c.

A detailed description of the equipment, components and l

processes involved and the interfaces with other plant t

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 L

the license. application and amendments.thereto; e.

An evaluation of the change which showstthe expected maximum exposurestto individual in the unrestri:ted area and to the general population that differ from those l

.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 a'ctual release for the period prior to when-the changes are to be made; l

g.

An estimtte of.the exposure-to plant operating personnel as a result of the change; and h.

Documentation of the. fact:that the change was reviewed and o.

found acceptable pursuant to Technical. Specification-6.5.2.

9 2.

Shall become effective ~ upon review and acceptance pursuant to:

o

' Technical. Specification 6.5.2.

N, APPROVED AllG 0 9, 1990 6-8 Revision 22 08-02,

a

l

~ 6.0 ADMINISTRATIVE (Continued)

)

Lp 6.4 ESE

- J LIQUID EFFLUENTS l

CONCENTRATION'(1.1)

~ J 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 -

j bodies of water outside thet site will result in-exposures i

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 population..- The concentration limit for-dissolved'or entrained noble gases is' based upon thes assumption that Xe-135:is the controlling radioisotope and l

2 its MPC in air (submersion) was converted to. an' equivalent' i

j concentration in water using.the methods described in 4

International Commission on Radiological Protection (ICRP)

Publication 2.

QD.S.E (1,2)'

6.4.2 This specification is. provided. to implement.the ' require-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 1. 'The-a ACTION statements provide the required operating flexi-bility 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:calcu-lations in the 00CM implement the requirements lin Secticn III.A of Appendix I that conformance with the guides of Appendix. I be 'shown. by calculationar procedures. based ~on models and data, such that the-actual exposure of an

. individual:through-appropriate pathways is unlikely to be substantially underestimated. :The equations specified.in the 00CM for calculating the doses:due to the actual release rates of radioactive materials 11n 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-l Evaluating Compliance with 10 CFR Part 50, Appendix.I,"

Revision;1,= 0ctober 1977-and Regulatory Guide 1.113,

" Estimating Aquatic Dispersion of Effluents' from Accidental and Routine Reactor Releases for'the Purpose of i

l Implementing Appendix' I," April 1977.~

.j This specification-appl.ies to the release of liquid effluents from each reactor at'thersite.

For' units with L

shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units

[

sharing that system.

APPROVED AUG 0 21990 9.

Revision 21

)

02-15-90 d

e-

~

....,-w,e

,.m..,

v...

,,._s

~_

.6,01 ADMINISTRATIVE (Continued).

6.4' BASES (Continued)

LIOUID WASTF TREATMENT (1.3)'

1 6.4.3 The OPERABILITY of the liquidiradwaste 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 l

that the releases of radioactive materials in liquid-effluents will: be kept "as low as is reasonably achievable." This specificationiimplements the requirements;of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 ard the design'

. i objective given in Section II.D of Appendix'I'to 10 CFR-

'Part 50. The=specified limits governing the use of_

l appropriate portions of the liquid radwaste treatment i

system were specified:as a suitable' fraction.of the dose design objectives set forth in Section II.A of Appendix I,-

10 CFR Part' 50, for liquid effluents..

i GASE0US EFFLUENT'S I

DOSERATE(2.1) l 6.4.4 This specification is provided to' ensure.that the dose at.

any time at the site boundary from gaseous effluents from a

all units on the' site will, be within the annual dose'-1imits of 10 CFR Part 20'for unrestricted areas. The annual: dose-s

' limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, ' Column 1.

These-limits provide reasonable assurance.that radioa'ctive. -

material discharged in. gaseous' effluents lwill: not_ result in

. t 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, TableIII: of/10 CFR Part; 20 (10 CFR Part 20.106.(b)).

For individuals who may at' times be within the-site boundary, the occupancy of the individual will. be sufficient 1', low to compensate for: any-increase = in the atmospheric diffusion' factor above that for the site.

bouncary. The specified release rate limits restrict,-at'

-all times, the corresponding gammaiand: beta dose-rates-l aboveibackground to an~ individual at or beyond the: site boundary to less than or equal to 500, mrem / year to the' i

total' body or to less'than or equal to'3000 mrem / year to the skin. These relea'se rate limits also restrict, at all-l times, the corresponding thyroid dose rate above background to a child via the inhalation pathway-to less 4than or equal to 1500 mrem / year.

L l

This specification applies to the release of gaseous' effluents-from all reactors' at the site.

For uni:s-with-shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the unitsi sharing that system.

APPROVED AUG 0 21990 6-10:

Revision 211 02-15-90 L

l

,.....mw

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

,s.,

6 0. ADMINISTRATIVE (Continued)'

0 6.4~ B&1El (Continued)'

l DOSE -' NOBLE GASES (2.2) 6.4.5 This specification is'provided'to implement the requirements of Sections II.B,-III.A and M.A of Appendix,I, 10 CFR Part 50. The Limiting Condition for li Operation implements the guides set forth in Section II.B-of Appendix I.

The ACTION-statements provide the required-

- i 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-E effluents will' be-keptL"as 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 anLindividual through. appropriate-l 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 1.109,.

" Calculation.of Annual Doses to' Man from Routine Releases _

j of Reactor Effluents for-the Purpose of Evaluating Compliance with 10!CFR Part 50,-Appendix 1," Revision 1, October 1977 and Regulatory Guide l'.111, " Methods for.

-Estimating Atmospheric Transport.and Dispersion of Gaseous a

Effluents in Routine Releases:from Light-Water Cooled Reactors," Revision 1,' July 1977.

For individu:,ls'who may at' times be within-the= site boundary cthe occupancy.of the individual will be<sufficiently low to compensate for any- _

A' 1

increase in the atmospheric diffusion factor-above that fe" the SITE BOUNDARY.

For MEMBERS OF THE PUBLIC who traverse

• the SITE. BOUNDARY via highway I-5,.the residency time shall i

be considered negligible and hence the dose "0". ~ The ODCM L

equations provided forJdetermining the air doses at:the l

l

= SITE' BOUNDARY:are ' based upon the' historical. average-

~;

atmospheric conditions.

DOSE - RADI0 IODINES.' RADIOACTIVE MATERIALS'IN PARTICULATE FORM AND l

TRITIUM (2.3) 6.4.6

- This specification is prov'ided to' implement the requirements of' Sections.II.C, III.A and.IV.A of.

Appendix I,c10'CFR'Part 50. The Limiting Conditions for' Operation'are the guides set.forth in Section II.C of Appendix 1. :The ACTION = statements: provide the required operating flexibility. and at the same time implementrthe guides set forth in Section IV.A;of. Appendix I to; assure that'the releases of radioactive' materials in gaseous -

i effluents will be'.kept "as low as is' reasonably achi evabl e'. " The ODCM calculational methods specified'in the Surveillance Requirements implement the requirements j

in Section III'.A of Appendix. I that confor' nance with the guides of Appendix I;be shown by calculational procedures i

N1(D AUG 0 21990 Revision 22

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'6.0; ADMINISTRATIVE (Continued)?

6,4 MSE1 (Continued) based on models' and. data, such thatithe actual exposure of-an individual through appropriate pathways is unlikely to 1

be substantially underestimated; -The ODCM calculational-methods for calculating the doses due to the actual ~ release-t 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, j

. October 1977 and Regulatory Guide 1.111, " Methods for LEstimating Atmaspheric. 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 actus.' doses based upon the historical average atmospheric e Titions. The release, rate specifications for radiciobes, radioactive-materials in particulate form and tritium are dependent on:the:..

l existing radionuclide pathways:to man, in the unrestricted i

r l

area'. The pathways which were examined in the development of these calculations were: 1) individual-inhalationof-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-t meat by man, and 4) deposition on:the ground with.:

subsequent exposure of man.

GASEOUS RADWASTE TREATMENT (2.4)

L 6.4.7 The OPERABILITY of the:GASE0US RADWASTE TREATMENT 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

'y 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 Atto-10 CFR Part 50, and the 1

design objectives given in Section.II.D of Appendix 1.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' 1

in Sections II.B-and'II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

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RWD AUG 0 21990 6-12 Revision 21 02-15-90:

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.6.0 ADMINISTRATIVE (Continued) 6.4 ~ BASES (Continued)

TOTAL DOSE (2.5)

~6.4.8-This-specificationtis provided to meet the dose limitations of 40 CFR 190. The specification requires =the H

preparation and' submittal-of a.Special-Report whenever.the 1

calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.

For sites 1

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. 404 CFR 190 if the: individual reactors remain-within the reporting requirement. level. The Special Report will describe-a course of action which should result'in the j

limitation of dose to a member of the public for 12:

l consecutive months to 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 i

uranium fuel cycle sources is negligible, with the exception that dose contributions from other: nuclear fuel cycle facilities at the same site orfwithin a radius.of-l 1

5 miles must be considered. -If the dose to:any member of-the public is estimated to exceed the requirements'of L 40 CFR 190, the.Special;Re) ort.with a' requestifor a i

variance in accordance witt the. provisions of-l 40 CFR 190.11, is considered to bela timely request and 3

fulfills the requirements of ~40 CFR 190 until NRC staff action is completed provided the releaseiconditions resulting-in violation of 40 CFR 190 have not already been corrected. An 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.

n 1

RADI0ACTIVELIOUIDEFFLUENTINSTRUMENTATION(4.1) 6.4.9 The radioactive liquid effluent' instrumentation is provided.

a to monitor and control, as applicable, the; releases-of ~

radioactive materials in liquid effluents dui ng actual or '

i potential releases of liquid effluents. - The: aistm/ trip

_setpoints for these' instruments shall' be calculated in 3

accordance with the procedures in the ODCM to ensure that-the alarm / trip will occur' prior to exceeding-the lir.Jtsf of 10.CFR Part 20.

The'0PERABILITY 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.

L.

i ED AUG I)l 1990' 6-13 Revision 21 02-15h90 t

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6.01 ADMINISTRATIVE (Continued) 6.4 BAES (Continued)--

RADI0ACTIVEGASEOUSEFFLUENTINSTRUMENTATION(4.2)]

6.4~.10 The radioactive gaseous effluent instrumentation is-1 provided to monitor and control, as' applicable, the q

releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.-

The: alarm / trip setpoints for these ' instruments shall be calculated in accordance with the procedures in the ODCM to

.nsure-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 cf Appendix-A to 10 CFR Part 50.

MONITORING PROGRAM (5.1)-

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 o

those radionuclides, which lead to'the highest potential.

radiation exposures of-' individuals resulting from.the

' station operation.

This monitoring program thereby=

supplements:the radiologicalL ' effluent monitoring nrogram by l

verifying.that the measurable concentrations of radioactive-3 materials and levels of radiation are not higher than expected ontthe basis of the effluent measurements.and.

modeling of the environmental exposure pathways. ' The

1 initially specified monitoring program will be effective' for at least the first three years of commercial operation.

'b Following this period,: program changes may-be initiated based on operational experience.

The detection capabilities required by: Table 5 are-state-of-the-art for routine environmental measurements 'in i

industrial laboratories.::It should be recognized that the LLD is defined as an A oriori=(before the fact). limit H

representing the capability of a measurement. system and not as a nosteriori- (after the fact) limit'for a particular

')

.mmsurement.. Analyses shall;be performed in such 'a. manner that.the stated LL0s will be. achieved under routine u

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 1

factors will 'be identified and described in the ' Annual.

Radiological Environmental Operating; Report.

tAPPROVED AUG 0 8 @

6-14 Revision 22 08-02-90~

p 6.0L ADMINISTRATIVE (Continued);

6.4 R&1ll (Continued)

LAND USE CENSUS (5.2) 6.4.12 This specification'is provided_to ensure that changes in j

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 satisfies ~the requirements of-Section IV.B.3 of-Appendix I to 10 CFR Part 50.. Restri.cting the census to-gardens-of greater than 500 square feet:provides assurance i

that significant exposure-pathways via leafy vegetables -

1 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 i

1.109 for consumption by a child. To determine this--

minimum garden size,;the following assumptions were used, S - li

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 COMPARISON PROGRAM-(5.3)-

6.4.13

'The requirement for participation'in an Interl'aboratory Comparison Program is provided to ensure that independent:

checks on the precision.and accuracy of the measurements of-radioactive material in environmental: sample matrices are performed as part of the quality assurance program for l

environmental-monitoring in order to demonstrate that the i

results are reasonably valid.

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i APPROVED Alle o a 1q99 6-15' Revision 22 08-02-90 a

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L ATTACHMENT B t

Responses to Comments on Revisionil9 of the l

l' SONGS Units 2 and 310DCM

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L The following provides responses to-the points raised in the Conclusions I

section of EG&G's " Technical Evaluation Report _for the Evaluation of ODCM (Updated Through Revision 19)."

Resoonse to Comments Under the Headina of "The followina discreoancies should be addressed:"

[

Comment 1:

"Section 1.1.1 and 1.1.2, respectively, should require thit the analyses required by Technical Specifications 4.11.1.1.1 and 4.11.1.1.3 be used to determine the setpoints for the liquid -

effluent monitors."

Response

The comment was addressed with the implementation of Comment 21.

SCE has always used the results of the radioactivity analyses surveillances to determine the.setpoints for the liquid effluent monitors in Section 1.4.

Section 1.4 has always stated explicitly its purpose to comply with ODCM Specification 1.1.1.

ODCM Surveillance Requirement (SR) 1.1.1.2 was revised to clearly state this requirement with the implementation of Comment 21..

Note:

ODCM, Revision 19, Section 1.1.1, " Batch Release Setpoint Determination," is now Section 1.4.1 in Revision 22.

ODCM,-

l Revision 19, Section 1.1.2. " Continuous Release Setpoint l

Determination," is now Section.1.4.2 in-Revision 22. -The Radioactive Effluent Technical Specifications (RETS) were relocated from the Technical Specifications (TS) to the ODCM with License Amendment Nos. 83 and 73 for SONGS Units 2 and 3,t respectively. TS SR 4.11.1.1.1 is now ODCM SR 1.1.1.1, and TS SR 4.11.1.1.5 was relocated to.0DCM SR 1.1.1.3.

However, ODCM SR 1.1.1.3 was deleted in Revision 22 in order to implement-the recommendations in Comment 21 of EG&G's Technical Evaluation l-Report (TER). ODCM SR 1.1.1.3 was no-longer needed with -the revised wording of ODCM SR 1.1.1.2.

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l Comment 2:

"Section 1.2 should identify the liquid' releases considered in' the dose calculations, the individuals exposed, the exposure pathways:

considered,-and the consumption and occupation factors used."

Response

SCE agrees'with the comment.

However,-the. revisions wil1<be made in the February 1991 ODCM update. A complete description of these items requires SCE to document the algorithms-of the NRC's PARTS computer code from NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978.

SCE uses the PARTS code to obtain parameters for the liquid dose calculations, and its. documentation requires

?

additional time.to complete. The code's documentation will-identify the required items. ODCM Section 1.5 will reference the -

code's documentation.

Note:-

ODCM, Revision 19, Section 1,2, " Dose Calcul'ation-for Liquid Effluents," is now Section 1.5 in' Revision 22.

j q

Comment 3:

" Table 1.2 should apparently be corrected.as shown below (See Section 3.7):

Nuclide T. Body Rang Liver Kidney GI-LLI Na-24 4.57E-01 Zr-97 1.80E-01 Sr-91 3.71E+00 9.18E+01 Ru-103 1.25E+04 Te-132 2.04E+02 4

Ce-143 4.46+02 "

Response

The corrections were incorporated, i-Note:

00CM, Revision 19, Table 1-2, " Dose Commitment Factors, Aqn" is

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now Table 1-4 in Revision 22.

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i Comment 4:- " Sections 2.1 and 2.2, respectively, for the setpoints of gaseous

' effluent monitors and gaseous effluent dose rate should account for releases from Unit 1."

Response

The comment was incorporated.

The Units 2'and 3 administrative factors for the monitor setpoints were changed in Revision 22 to account for Unit 1 gaseous releases from its single release point.

The gaseous effluent release from Unit 1 is only a small percentage of the s'um of the gaseous effluent releases from the site. The administrative factors for Units 2 and 3 were lowered by the percentage that Unit 1 is expected to contribute to the total release. The reduction.in the monitor setpoints.

i automatically limits the gaseous dose rates.

Note:

ODCM, Revision 19, Section 2.1, " Methods of Calculation for Gaseous Effluent Monitor Setpoints," is now Section-2.6 in Revision 22. OCCM, Revision 19, Section 2.2, " Gaseous Effluent Dose Rate," is now Section 2.7 in Revision 22.-

Comment 5:

" Table 2-1 should include calibration constants for all gaseous effluent monitors or identify the mixture or means of determining the mixture of radionuclides assumed for the calibration."

Pesponce:-

SCE disagrees with this comment. The calibration constants needed for calculations in the ODCM are contained in Table 2-1.

The table does not contain calibration constants for monitors 2RT-7865, 3RT-7865, 2RT-7870, and 3RT-7870 since the release units for these monitors are pci/sec and not pCi/cc.

In addition, a single radionuclide (Xe13) is assumed for the radionuclide calibration mixture. The. Semiannual Reports, - from 1985 through 1989 verify that more than 85% of all inert gaseous releases are Xe*3, and3RT-7870,the'Xe[33 or monitors 2RT-7865, 3RT-7865,'2RT-7870,.

calibration constant is used internally to derive the pC1/sec instrument' readings used for evaluating effluent release's.

Note:

ODCM, Re.ision:19, Table 2-1, " Gaseous Effluent Radiation Monitor Calibration Constants," is now Table 2-3 in Revision 22.

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Comment 6:- " Sections 2.2.1 and 2.2.2. should be expanded tofinclude descriptians of the methods used to determine release rates used -

in the c' tulation of-dose rates due to gaseous' effluents."

I

Response

SCE expan.ded the~ definition of the release. rates in Sections 2.7.1 l.

and 2.7.2.

However, the detailed. methods for determining either L

the measured or calculated release rates are documented in site chemistry procedures. The detailed step-by-step descriptions are best retained in-the procedures >and not in the ODCM.

-Note:

ODCM, Revision 19, Section 2.2.1, "For Noble Gases:," is now Section 2.7.1 in. Revision 22.

ODCM, Revision 19, Section 2.2.2, "For all Radiciodines, Tritium and for all Radioactive Materials-in Particulate Form with Half-Lives Greater Than Eight Days:," is now Section 2.7.2 in Revision 22.

Comment 7:

"Section 2.3 should identify the releases considered in the calculation of doses due to gaseous: effluent; and the methods used to determine the total releases or release rates."

Response

The comment was incorporated.

Section 2.8 was revised'to reference Section 2.6.'

Section 2.6 identifies the different-gaseous effluent releases considered in the dose calculations.

Note:-

ODCM, Revision 19, Section 2.3, " Gaseous Effluent Dose l

Calculation," is now Section 2.8 in Revision 22.

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Comment 8:

"Section 2.2.2 (sic) should include all parameters necessary for j

the calculation of the dose parameters, R, in. Tables 2-5 through i

2-14.

The equations used to calculate the values of Rr should also be identified, either by giving the equations or'by reference."

Response

SCE agrees'with the comment.

However, the revisions will be made in the February 1991 ODCM update.. The values of the parameters Ri are calculated using the PARTS computer code.

Section 2.8.2 will be revised to reference the code's documentation.

Note:

ODCM, Revision 19, Section 2.3.2, " Dose from Tritium, Radioiodines and Radioactive Materials in Particulate Form With Half Lives Greater Than 8 Days in Gaseous Effluents," is now Section 2.8.2 in Revision 22. ODCM, Revision 19, Tables 2-5 through 2-14, " Dose Parameter R for Sector...," are now Tables 2-7 through 2-16 in i

i Revision 22.

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Comment 9:

"The exclusion.of doses to the lung in Tables 2-5 though 214 should be justified."

Response:-

SCE agrees with the comment.

However, the revisions will be made in the February 1991 ODCM update.

SCE uses the NRC's PARTS-computer code from NUREG-0133 to calculate the dose parameters tabulated in Tables 2-7 through 2-16.

EG&G has identified a deficiency in the com) uter code.

The code assigns only one critical organ to eaci radionuclide regardless of the method of body cntry, i.e., inhalation or ingestion. The NRC supplied database for PARTS uses the ingestion _ pathway for critical. organ determination. Thus, the dose to the lungs is excluded. SCE will revise the PARTS code to correct this deficiency. The revision requires computer code changes as well as new Dose Conversion Factors for the inhalation pathway. These factors will be' obtained from Regulatory Guide 1.109. No significant changes to the offsite dose calculations are expected to result.

Note:

ODCM, Revision 19, Tables 2-5 through 2-14, " Dose Parameter R for Sector _...," are now Tables.2-7 through 2-16 in Revision 22 t Comment 10: " Sections 3.1 and 3.2 should include provisions for considering i

anticipated unur,ual releases when making dose projections."

i

Response

SCE does not agree with the comment. The dose projection requirements of ODCM SR 1.3.1.1 and 2.4.1.1 serve to indicate when the radwaste treatment systems should-be used to reduce effluent activity. However, the radwaste treatment systems = are always-used, as a matter of practice, to reduce effluent radioactivity prior to release. Dose projection increases due to anticipated unusual releases would not require any further action than what is already a station practice.

Thus, adding anticipated: unusual i

releases would not enhance the ODCM and was not included in the Revision 22 update.

Note:

TS SR 4.11.1.3.1 is now ODCM SR 1.3.1.1.

TS SR.4,ll.2.4.1 is now 4

ODCM SR 2.4.1.1.

Comment 11: "A map of environmental monitoring locations should be added to Section 5.0."

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Response

The comment was resolved.

Figure 5-1, Revision 0, " Radiological Environmental Monitoring Sample Locations," dated December 5,

'1989, was added to ODCM, Revision 21.

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Resoonses to Coments Under the Headina of "The followina discrepancies. which accarently arise from tvooaraphical errors or editorial omissions. should be corrected:"

I Comment 12: "In Table 1-2, the signs of the exponents of the liver factors for Zr-97 and Ce-143 should be changed, and the GI-LLI factor for Hu-103 should apparently be 1.25E+04 instead of 2.25E+04."

i

Response

The typographical errors were corrected.

Note:

ODCM, Revision 19, Table 1-2, " Dose Comitment Factors, An," _is now Table 1-4 in Revision 22.

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Comment 13: "Page 2-13 of Revision 19 should be corrected so Eq. (2-9) and the definitions of terms in Eq. (2-8) are not deleted, and the top of l

page 2-14 not duplicated."

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Response

The comment was not incorporated. The cause appears to have been a reproduction error limited to the reviewer's copy of the ODCM, Revision 19. The enclosed copy of the ODCM, Revision 22, has'been checked for completeness and is free of any such errors.

i Comment 14: " Sections 2.1.3 and 2.1.4 should be edited so setpoints of all gaseous effluent monitors are specifically addressed in the headings, subheadings, and tests."

Response

The comment was incorporated.

The consistency of Sections 2.6.3 and 2.6.4 between headings,-subheadings, and text were reviewed-and corrected where necessary.

Note:

ODCM, Revision 19, Section 2.1.3, " Containment Purge - 2RT-7828,-

l 3RT-7828, 2RT-7865, 3RT-7865," is now Section 2.6.3 in i

Revision 22. ODCM, Revision 19, Section 2.1.4, " Waste Gas Header 7865, 2/3RT-7808," is now Section 2.6.4 in Revision'22, i

Comment 15: "In Sections 2.3.1.1 and 2.3.2.1, the term " projected" should be removed, since it implies doses in the future instead of doses or dose commitments due to releases already made."

Response

The comment was incorporated. The term " projected" was deleted from Sections 2.8.1.1 and 2.8.2.1.

Note:

00CM, Revision 19, Section 2.3.1.1, "For historical meteorology:,"

is now Section 2.8.1.1 in Revision 22. ODCM, Revision 19, Section 2.3.2.1, '"For historical meteorology:," is now Section 2.8.2.1 in Revision 22.

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h Coment 16: "One of the " Unit 2" designations associated with Primary System Degassing"andTankCoverGasesin-Figure 4-1shouldbechangedto

" Unit 3.

Response

The coment-was resolved.

Figures 4-5 and 4-6 were revised in Revision 21, and they correctly-reflect' unit designations, t

Note:

00CM, Revision 19, Figure 4-1, " SONGS 2 and 3 Radioactive Liquid l

Waste Treatment Systems," is now Figure 4-5 in Revision 22. ODCM, Revision 19, Figure 4-2,." SONGS 2 & 3 Radioactive. Gaseous Waste Treatment Systemn # is now Figure 4-6_in Revision 22.

I Comment 17: " Figures 4.1 and 4.2 should indicate all release pathways and monitors of liquid and gaseous effluents consistent with the.

release pathways and monitors identified in Sections 1.1 and 2.1."

Response

The comment was incorporated.

Figures 4-5 and 4-6 were revised and are consistent with Sections 1.4 and 2.6.

Note:

ODCM, Revision 19, Figure 4-1, " SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems," is now Figure 4-5 in Revision 22. ODCM, Revision-19, Figure 4-2, " SONGS 2 & 3 Radioactive Gaseous Waste i

Treatment Systems," is now figure 4-6 in Revision 22. ODCM,-

Revision 19, Section 1.1, " Liquid Effluent Monitor Setpoints," is now Section 1.4 in Revision 22.

ODCM, Revision 19, Section.2.1, L

" Gaseous Effluent Monitor Setpoints," is now-Section 2.6 in Revision 22.

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Responses to Coments Under the Headina of " Additionally. the licensee may j

want to consider the followina chances:"

j Coment 18: "In Section 1.2, the Licensee may-wish to use the average l

dilutions flow for the reporting period in the calculations of i

doses due to liquid effluents, a method allowed.by the NRC Staff."

l Rosponse:

SCE agrees with the coment and is evaluating the' implementation i

of this recommendation. The present method ' calculates the liquid effluent dose on a permit-by-permit basis sumed over a quarter.

The NRC's method, in general, would arrive at the same dose.

However, SCE's method may on occasion overestimate the dose.

Any ODCM revisions resulting from SCE's evaluation will be 1

incorporated into the February 1991 update.

-Note:

ODCM, Revision 19, Section 1.2, " Dose Calculations for Liquid

~ Effluents,' is now Section 1.5 in Revision 22.

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1 Comment 19: "The Licensee may wish to modify the~ requirements in Section'2.2'.2 to match:the recomendations in the bases statement for Technical

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Specification 3.11.2.1.b for. SONGS Units 2 and 3 and in l,'

NUREG 0472:L i.e. that the~ organ' dose rate limit may be applied to 1

the thyroid of'a child via the inhalation pathway."

Response

SCE-agrees with the comment and is evaluating its implementation.

Currently, the dose is calculated for all' organs and age groups,.

and the maximum chosen.. This-is an acceptable, yet a more conservative, method.. Any_00CM revisions resulting from SCE's

[

evaluation will be incorporated into the February 1991 update.

Note:

ODCM, Revision 19,' Section' 2.2.2, "Radiciodines and Particulates,"

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is.now Section 2.7.2;in Revision 22. TS 3.11.2.1, " Dose Rate," is

-now ODCM Specification 2.1 in Revision 22, and its Bases is in Section 6.4.4.

E Coment 20: "The Licensee may wish to modify Section 2.3.2 to calculate the highest calculated dose to a single organ at the critical location.

for comparison with the technical. specification organ dose limit."-

Response

This comment will not be implemented.

SCE uses the sum of the highest organ doses for individual radionuclides to calculate' the maximum organ doses. This is an acceptable, yet a more conservative, methodology.

The method does' overestimate the liquid doses.

However, this is acceptable to SCE and.will not be j

changed.

Note:

ODCM, Revision 19. Section 2.3.2', "Radioiodines and Particulates,_"

is now Section 2.8.2 in Revision 22.

Comment 21: "The Licensee may wish to amend Technical.-Specifications.

4.11.1.1.1, 4.11.1.1.2, and 4.11.1.1'.3 to more nearly agree with i

-Specifications 4'11.1.1.1_and 4.11~.1.1.2 of Revision 3, Draft'7"

[ sic] or_NUREG-0472."

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Response

The comment was incorporated. ODCM SR 1.11.l'.1 and-1.1.1.2 were l

revised;to agree with Draft 7 of NUREG-0472, Revision 3,." Standard i

Radiological Effluent-Technical Specifications for Pressurized Water Reactors,-" September 1982, as recommended..

Note:

TS SR 4.11.1.1.1 is now ODCM SR 1.1.1.1, and TS'SR 4.11.1.1.2 ist-now ODCM SR 1.1.1.2.

TS SR 4.11'.'1.1.3 was relocated to 00CM SR !=.1.1.3..However, ODCM SR 1.1.1.3 was deleted.in-Revision 22

- r in order to implement the recommendations in Comment 21 of EG&G's.

Technical Evaluation Report.-

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' ATTACHMENT D

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Responses to-Comnents on Revision 19 of the-I SONGS Units 2'and-3 ODCM.

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provides res onses to the points raised in the Conclusions Thefollowink&G's" Technic 1EvaluationReportfortheEvaluationofODCM section of E (UpdatedThroughRevision19)

Response to Consnents Under the Headina of "The followina discrepancies should se addressed:"

Comment 1:

"Section 1.1.1 and 1.1.2, respectively, should require trat the analyses required by Technical Specifications 4.11-1.1.l and 4.11.1.1.3 be used to determine the setpoints for the liquid effluent monitors."

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Response

-The comment was' addressed with the implementation of Comment 21.

l SCE has always used the results of the radioactivity analyses surveillances to determine the setpoints for the liquid effluent monitors in Section 1.4.

Section 1.4 has always stated explicitly its purpose to comply with ODCM Specification 1.1.1.

ODCM-Surveillance Requirement (SR) 1.1.1.2 was revised to clearly state this requirement with the implementation of Comment 21.

t Note:.

ODCM, Revision 19, Section 1.1.1, " Batch Release Setpoint Determination," is now Section 1.4.1 in Revision 22. ODCM, Revision 19, Section 1.1.2, " Continuous Release Setpoint Determination," is now Section 1.4.2 in Revision 22. The Radioactive Effluent Technical Specifications (RETS) were relocated from the Technical Specifications (TS) to:the ODCM with License Amendment Nos. 83 and 73 for. SONGS U lts 2 and 3, respectively. TS SR 4.11.1.1.1 is now ODCM SR 1.1.1.1, and TS SR 4.11.1.1.3 was relocated to ODCM SR 1.1.1.3.

However, ODCM SR 1.1.1.3 was deleted in Revision 22 in order to implement the recommendations in Consnent 21 of EG&G's Technical Evaluation Report (TER). ODCM SR 1.1.1.3 was no longer needed with the revised wording of ODCM SR 1.1.1.2.

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4-Comment 2:

"Section 1.2 should identify' the liquid releases considered in the dose calculations, the individuals exposed..the exposure' pathways-considered, and the consumption and occupation factors used."

Response:.

SCE agrees with the comment.

However,. the revisions will be made-in the February 1991 ODCM update.- A complete-description of these items requires SCE to document'the algorithms of the NRC's PARTS

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computer code from NUREG-0133,1 " Preparation of. Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978. SCE uses the PARTS code to obtain parameters for t

the liquid. dose calculations, and its; documentation requires additional time to complete.

The code's documentation will identify the required items. ODCM Section 1.5 will reference the i

code's documentation.

i Note:-

ODCM, Revision 19, Section 1.2, " Dose Calculation for' Liquid Effluents," is now Section 1.5 in-Revision 22.

comment 3:

" Table 1.2 should apparently be corrected as shown below (See

)

Section3.7):

Nuclide T. Body Bone Liver Kidney GI-LLI ha-24

'4.57E-01 Zr-97 1.80E-01 Sr-91 3.71E+00 9.18E+01 Ru-103 1.25E+04 Te-132 2.04E+02 Ce-143 4.46+02 "

Response

The corrections were incorporated.

L Note:

00CM, Revision 19. T;ble 1-2, " Dose Commitment Factors, A," is n -

now Table 1-4 in Revision 22.

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Comment 4:

" Sections 2.1 and 2.2, respectively, for the setpoints of gaseous

-effluent monitors and gaseous effluent dose rate.should account i

for releases-from Unit 1.

- Response:

- The comment was incorportted.

The Units 2 and 3 administrative.

factors for the monitor setpoints were changed in Revision 22 to account for Unit 1 gaseous releases from its single release point.-

The gaseous effluent release from Unit 1 is only a small

-1 percentage of the sum of the gaseous effluent' releases from the H

site. The administrative factors for Units 2 and'3 were lowered -

by the percentage that Unit 1 is expected to contribute to the total release. The reduction in the monitor setpoints automatically limits the gaseous dose rates.

Note:-

ODCM, Revision 19. Section 2.1.1 " Methods of Calculation for b

Gaseous Effluent Monitor Setpoints," is now Section 2.6 in Revision 22. ODCM, Revision 19, Section 2.2, " Gaseous Effluent l

Dose Rate," is now Section 2.7 in Revision 22.

l Comment 5:

" Table 2-1 should include calibration constants for all gaseous-effluent monitors or identify the mixture or means of determining the mixture of radionuclides assumed for the calibration."

Response

SCE disagrees with this comment.

The calibration constants needed for calculations in.the ODCM ere contained,in-Table 2-1.

The-table does not contain calibration constants for monitors t

-2RT-7865, 3RT-7865, 2RT-7870, and 3R1-7870-since the release units for these monitors are pCi/sec and not pCi/cc.-

1 In addition,'a' single radionuclide-(Xe233)?is assumed for the l

radionuclide calibration mixture.

The Semiannual: Reports, from i

1985 through 1989, verify that more than 85% of all' inert gaseous i

33 releases are Xe and3RT-7870,theXe[33or monitors 2RT-7865. 3RT-7865, 2RT-7870, calibration constent"is used internally to derive the pCi/sec instrument readings used for evaluating effluent releases.

Note:

ODCM, Revision 19, Table ~2-1, " Gaseous' Effluent Radiation Monitor Calibration Constants,".is now Table-2-3 in' Revision 22.

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Comment-6:

Sections 2.2.1 and 2.2.2 should be expanded to include descriptions'of the methods used to determine release rates used in the calculation of dose ratee due to gaseous effluents."

Response

SCE expanded the definition of W elease rates'in Sections 2.7.1-and 2.7.2.

However, the detaileo <thods for determining either the measured or calculated release rates' are documented in site' chemistry procedures. The detailed step-by-step descriptions are-best retained in the procedures and not in the.0DCH.

Note:

ODCM, Revision 19, Section 2.2.1, "For Noble Gases:," is now Section 2.7.1 in Revision'22. ODCM, Revision 19, Section 2.2.2, "For all Radiciodines, Tritium and for all Radioactive Materials in Particulate Form with Half Lives Greater Than'Eight Days:," is now Section 2.7.2 in Revision 22.

f Comment 7:

"Section 2.3 should identify the releases considered in the-f calculation of doses due-to gaseous effluents and the methods used to detennine the total release or release rates."

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Response

The comment was incorporated. Section 2.8 was revised to reference Section 2.6.

Section 2.6 identifies.the different gaseous effluent releases considered in the dose calculations.

Note:

ODCM, Revision 19, Section 2.3, " Gaseous Effluent Dose Calculation," is now Section'2.8 in Revision 22.

Coimnent 8:

"Section 2.2.2-[ sic] should include all parameters necessary for f

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the calculation of the dose parameters, R, in Tables 2-5 through i

2-14.

The equations used to calculate the values of R should ~

i also be identified, either by giving the equations,or by reference."

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Response

SCE agrees with the comment. However, the' revisions will be made-in the February'1991 ODCM upaate, The values of the parameters Re are calculated using the PARTS computer. code. Section 2.8.2 will be revised to reference the code's documentation..

i Note:

ODCM, Revision 19, Section 2.3.2,iculate Form With Half Lives

" Dose From Tr:t'Jm, Radioiodines and Radioactive Materials in Part Greater Than 8 Days in Gaseous Effluents," is now Section 2.8.2 in-i Revision 22. 00CM,. Revision 19, Tables 2-5 through 2-14, " Dose Parameter R for Sector... " are now Tables 2-7-through 2-16 in i

Revision 22.

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. Commerit 9:. "The exclusion of doses to the lung in Tables 2-5 though 2-14 should be justified."

Response

SCE agrees'with the comment. However, the revisions will be'made in the February 1991 00CM update. SCE uses the NRC's PARTS computer code from NUREG-0133 to calculate the dose parameters tabulated in Tables 2-7 through 2-16.

EG&G has identified a deficiency in the com) uter code. The code assigns only one-critical organ to eac1 radionuclide regardless of the method of body entry, i.e., inhalation or ingestion.

The NRC supplied database for PARTS uses the ingestion pathway.for critical organ determination. Thus, the dose to the lungs is excluded. SCE will revise the PARTS code to correct this deficiency.

The revision requires computer code changes as well as new Dose Conversion Factors-for the inhalation pathway. These factors will be obtained from Regulatory Guide 1.109. No significant changes ~.to-

'the offsite dose calculations are expected to result.

Note:

ODCM, Revision 19, Tables 2-5 through 2-14. " Dose Parameter R for Sector...." are now Tables 2-7 through 2-16 in Revision 22. t Comment 10: " Sections 3.1 and 3.2 should include provisions _ for considering anticipated unusual releases when making dose projections."

Response

SCE does not agree with the comment. The dose projection requirement

• of ODCM SR.1.3.1.1 and 2.4.1.1 serve to indicate when the radwaste treatment systems should be used to reduce effluent activity. However, the radwaste treatment systems are always used, as a matter of practice, to reduce-effluent radioactivity prior to release. Dose projection increases due to anticipated-unusual releases would not require any further action than.what is already a ' station practice. Thus, adding anticipated unusual releases;would not enhance.the ODCM and was not' included-in the Revision _22 update.

Note:

TS SR 4.11.1.3.1 is now ODCM SR 1.3.1.1.

TS SR 4.11.2.4.1'is now ODCH SR 2.4.1.1.

Comment 11: "A map of environmental monitoring locations should be added to Section 5.0."

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Response

The comment was resolved.

Figure 5-1, Revision 0.. " Radiological Environmental Monitoring Sample Locations," dated December 5, 1989, was added to ODCM, Revision 21 t

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Responses to Comments Under the Headina of "The followina discrepancies. which aooarentiv arise from tvooarachical errors or editorial omissions. should be corrected:"

Comunt 12: "In Table 1-2, the signs of the exponents of the liver factors for Zr-97 and Ce-143 should be changed, and the GI-LLI factor for Ru-103 should apparently be 1.25E+04 instead of 2.25E+04."

Response

The typographical errors were corrected.

Note:

ODCM, Revision 19. Table 1-2, " Dose Comitment Factors, A,p" is now Table 1-4 in Revision 22.

Comment 13: "Page 2-13 of Revision 19 should be corrected so Eq. (2-9) and.the definitions of terms in Eq. (2-8) are not deleted, and the top of page 2-14 not duplicated."

Response

The coment was not incr porated.

The cause appears to have been a

a reproduction error limited to the reviewer's copy of the ODCM, Revision 19. The enclosed copy of the ODCM, Revision 22 has been checked for completeness and is free of any such errors.

Comment 14: " Sections 2.1.3 and .1.4 should be edited so setpoints of all

-seous effluent monitors are specifically addressed in the wadings, subheadings, and tests."

Response

The coment was incorporated.

The consistency of Sections 2.6.3' and 2.6.4 between headings, subheadings, and text were reviewed and corrected where necessary.

Note:

ODCM, Revision 19,.Section 2.1.3, " Containment Purge - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865," is now Section 2.6.3.in,.

Revision 22. ODCM, Revision 19, Section 2.1.4, " Waste Gas Header l 7865, 2/3RT-7808," is now Section 2.6.4 in Revision 22.

Comment 15: "In Sections 2.3.1.1 and 2.3.2.1, the term " projected" should be removed,. since it implies doses in the future instead of doses or dose commitments due to-releases already made."

Response

The coment was' incorporated. The term " projected" was deleted from Sections 2.8.1.1 and 2.8.2.1, Note:

ODCM, Revision 19, Section 2.3.1.1, "For historical meteorology:,"

is now Section 2.8.1.1 in Revision 22. ODCM, Revision 19, Section 2.3.2.1, "For historical meteorology:.." is now Section 2.8.2.1 ir, Revision 22.

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P Comment 16: "One of the " Unit 2" designations associated with Primary.ystem Degassing"and Tank Cover Gases in Figure 4-1 should be changed to

" Unit 3.

Response

The coment was resolved.

Fi Revision 21,andtheycorrectgures4-5and4-6wererevisedin

,y reflect unit designations.

Note:

ODCM, Revision 19, Figure 4-1, " SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems," is now Figure 4-5 in Revision 22. ODCM, Revision 19, Figure 4-2, " SONGS 2 & 3 Radioactive Gaseous Waste Treatment Systems," is now Figure 4-6 in Revision 22.

Coment 17: " Figures 4.1 and 4.2 should indicate all release pathways and monitors of liquid and gaseous effluents consistent with the release pathways and monitors identified in Sections 1.1 and 2.1."

Response

The comment was incorporated.

Figures 4-5 and 4-6 were revised and are consistent with Sections 1.4 and 2.6.

Note:

ODCM, Revision 19, Figure 4-1, " SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems," is now Figure 4-5 in Revision 22.

ODCM, Revision 19, Figure 4-2, SONGS 2 & 3 Radioactive Gaseous Waste Treatment Systems," is now Figure 4-6 in Revision 22.

ODCM, Revision 19, Section 1.1, " Liquid Effluent Monitor Setpoints," is now Section 1.4 in Revision 22. ODCN, Revision 19, Section 2.1,

" Gaseous Effluent Monitor Setpoints," is now Section 2.6 in Revision 22.

Resoonses to Comments Under the Headina of " Additionally. the Licensee may want to consider the followina chanaes:"

Comment 18: "In Section 1.2, the Licensee may wish to use the average dilutions flow for the reporting period in the calculations of dcses due to lic,uid effluents, a method allowed by the NRC Staff."

Response

SCE agmes with the coment and is evaluating the implementation of this recomendation. The present method calculates the liquid effluent dose on a permit-by-permit basis sumed over a quarter.

The NRC's method, in general, would arrive at the same dose.

However, SCE's method may on occasion overestimate the dose.

Any ODCM revisions resulting from SCE's evaluation will be incorporated into the February 1991 update.

Note:

ODCM, Revision 19, Section 1.2, " Dose Calculations for Liquid Effluents," is now Section 1.5 in Revision 22.

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-Comment 19: "The Licensee may wish to modify lthe requirements-in.Section 2.2.2-

to match the recommendations in the bases statement for. Technical y

p Specification 3.11.2.1.b for SONGS Units 2 and 3 and in

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NUREG-0472:.i.e. that the organ dose rate-limit may be applied to.

1 the thyroid of a child via the inhalation pathway."

Response

SCE agrees with the' comment and'is evaluating its implementation.

Currently, the dose is cabulated for all organs and age groups and the maximum chosen. This is an acceptable yet a more conservative, method. Any ODCM revisions resulting from SCE's evaluation will be incorporated into the February 1991 update.

Note:

ODCM, Revision-19 Section 2i2.2, "Radiciodines and Particulates,"

is now Section 2.7.2 in~ Revision 22. TS 3.11.2.1, " Dose Rate," is 1

now ODCM Specification 2.1 in Revision 22, and its Bases is in-Section 6.4 4.

i Comment 20: "The Licensee may wish to modify-Section 2.3.2 to calculate'the highest calculated dose to a single organ at the critical location for comparison with the technical specification organ dose limit."

Response

This comment was not incor orated.- SCE uses the sum of_the l

highest organ doses for individual radionuclides to calculate the maximum. organ doses. -This is an acceptable, yet a more conservr.h ve, methodology. The method does overestimate the-doses.

q Note:

ODCM, Revision 19 Section 2.3.2, " Dose. From'. Tritium,~ Radioiodines -

and Radioactive Materials in Particulate Form With Half Lives Greater Than 8 Days in Gaseous Effluents," is now Section 2.8.2 in Revision 22.

q Comment 21: "The Licensee may wish to-amend Technical Specifications' 4.11.1.1.1, 4.11.1.1.2,_and 4.11.1.1.3 to more nearly agree with-i Specifications 4.11.1.1.1 and 4.11.1.'1.2 of Revision 3' Draft 7"~

[ sic] of NUREG-0472.."

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Response

The comment was. incorporated. 00CM SR l'1.1.1 and 1.1.1.2 were revised to agree with Draft 7 of.NUREG-0472,: Revision 3. " Standard J

Radiological Effluent Technical. Specifications for Pressurized ~

l Water Reactors," September 1982,=as recommended..

1 Note:

TS SR 4.11.1.1.1 is now ODCM SR 1.1.1.1, and TS SR'4.11.1.1.2 is 1

now ODCM SR 1.1.1.2.

TS SR 4.11.1.1.3 was relocated to 0DCM SR 1.1.1.3.

However, ODCM SR 1.1.1.3 was deleted;in Revision' 22 l

in. order to implement the recommendations in. Comment 21'.of EG&G's i

Technical Evaluation Report.

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