ML20056G671

Semiannual Radioactive Effluent Release Rept Jan-June 1993

ML20056G671
Person / Time
Site:	Rancho Seco
Issue date:	06/30/1993
From:	Shetler J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
DAGM-NUC-93-172, NUDOCS 9309070037
Download: ML20056G671 (24)

Text

.

O

$SMUD SACRAMENTO MUNICIPAL UTIUTY DISTRICT C 62G1 S Street. P.O. Box 15830. Sacramento CA 95852-1830.(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA DAGM/NUC 93-172 August 30, 1993 U. S. Nuclear Regulatory Commission Attn: B. Faulkenberry, Regional Administrator Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 l

Docket No. 50-312 Rancho Seco Nuclear Station Licens-No. DPR-54 JANUARY-JUNE 1943 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPOPT

Dear Mr. Fe alkenberry:

In accordance with 10 CFR 50.36a(a)(2) and Rancho Seco Permanently Defueled Technical Specification D6.9.3, the District submits the enclosed Rancho Seco Semiannual Radioactive Effluent Release Report for the period January I through June 30.1993.

Members of your staff requiring additional information or cla.Jication may contact E;nar Ronningen at (916) 452-3211. extension 4467.

Sincerely,

/

h\\

b g James R. Sheller Deputy Assistant General Manager Nuclear Attachment ec:

Document Control Desk, NRC, Washington D.C. 20555 M. Cillis, NRC, Walnut Creek S. Brown. NRC, Rockville I

y[/

[f nonaF

% 09070037 930630 y'

h(

PCR ADOCK 05000312 y R

PDR Q

RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald CA 95638 9799;(209) 333 2935

I l

l l

l

%.S :/[!.}~

~

2 l

T:

i M'"5 y._r /.

0 l

RANCHO SECO i

l Nuciear Generating Station iE LICENSE NUMBER DPR-54

E il

?

SEMIA2/ NUAL RADIOACTIVE "I

4 EFFLUENT RELEASE REPORT

.l 5

i l

JANUARY - JUNE 1993

,I I

e

w w w w+yuw,

~m-n A

.L

' ^

l ~l.'..

Y i

m 'f, mT... yl *

e

.t 4',

.! d l

' ' *f l z%*

4 i_

t y

7 "g

~

g V,_._,,,)yn x.

m

~

m. g.a

>v; O

QI '

'E' W

G'**

~'

o' L

> h.Shl

• ^

%v.

e m.

r

,f

^-

7i i

?

a

,]*.=,

q}

?

?e

0;

, y' S' y, :;

si :s s

g '

. q Y

.s 4

x

,-3

..)

%'.l.

c-l.t, n-, :=-)

y

', .,w' ; I (.-,

.; 6

s zn

. g.

m-y v<n... -

~

n s

+

~

w m,,a, y a

s-y 2,

q p,

• ?:

'j

. 4.*

=.

.pg

.. ~,.,.

c g y, n

a p

^

.]

w 3

y j

n*-

)[

p gz,e.. "y-y

+

g y

c, 5

q

~

y, wy cr; hn

E ', '",, <-

n:n

+. -

J R A N C H QiS E C O,1

^'

n M

w' a

M 1;~-

Nuclear Generating; Station:

d.

)L LICENSE NUMBER'DPR25 41

%9 3

1 u

T

.)

lMlI

'i SEMIXS:SUALRADIOACTIVE N,

'g: m 3

l(i.

EFFLUE:ST RELEASES: REPORT:

~

/!

,p

,I

(

m.

l

?

-. g ;_

m:

a.

t 9-.,

g 2

p '

rr

^

{d

/' p

~

sa r

p.

p i

Sm'E

' JANUARY: JUNE 1993 1

15

+',

s i

4 s

I e

r

" U.)a

!l,k j dk 94-e i

1

' h4 /I, i*

L '

g Wr

' ' :ic

,7' 8e 11 X

(

i,,

1 1

l.%.!.

[

,9 r ,

.n c

~

-s m.e r

??

M. 7

- i

' S' M ;

i

>y sM 2

4 s

QpQ K

.g l:.

gKc;

$$ f U..

, 'i j _hM

$@ b':' g['I s k.V:; 1 U9

'"*['s i.,,,

. j],9. J.

N{

"'..Q.

o

+

s

,N M$4, L i.[__,

(G.

2[

p

. d[t v

e v4 s

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT c.ANUARY - JUNE 1993 I

TABLE OF CONTEPUS 5

PAGE 1.

SUPPLEMETRAL INFORMATION 2

A.

Regulatory Umits & Guidelines for Effluent Releases 2

I B.

Maximum Permissible Concentrations 3

C.

Measurement Methods for Total Radioactivity 3

D.

Batch Releases (via monitored pathways) 4 I

E.

Unplanned Releases 5

F.

Radioactive Effluent Monitoring instrumentation inoperable for Greater than 30 Days 5

11.

ESTIMATION OF ERROR 6

Ill.

GASEOUS EFFLUEPRS 7

Table ill-A Gaseous Effluents - Summation of All Releases 8

Table lil-B Gaseous Efflucnts - Ground Level Releases 9

Table lil-C Gaseous Effluents - Typical Lower Umits of Detection 10 I

Table lil-D Radiological Impact on Man Due to Gaseous Effluent Releases 11 IV.

UQUID EFFLUENTS 12 Table IV-A Liquid Effluents - Summation of All Releases 13 Table IV-B Liquid Effluents 14 I

Table IV-C Uquid Effluents - Typical Lower Limits of Detection 15 Table IV-D Radiological Impact on Man Due to Uquid Effluent Releases 16 V.

SOUD WASTE 17 I

ADDENDA l

Corrections To The July To December 1991 SRERR I

I I

i I

L.

j

I i

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY. JUNE 1993 i

I INTRODUCTION Rancho Seco Nuclear Generating Station (RSNGS) Unit No.1 is located in Sacramento County, Cahfornia approximately 25 m;les southeast of Sacramento and 26 miles north-northeast of Stockton. Rancho Seco Unit No.1 began commercial operation on April 17,1975. The single unit on the Rancho Seco site is a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity is 963 gross megawatts electrical. Because of a public vote on June 6,1989, the g

District shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8,1989.

This Semiannual Radioactive Effluent Release Report (SRERR) provides a summary of gaseous I

and liquid effluent releases made from Rancho Seco during the period January 1 through June 30,1993. Also presented in this report is the p.ojected radiological impact from these releases and a summary of solid radwaste shipments.

This report has been prepared by the Sacramento Municipal Utility Distrid to meet the requirerr ents of Rancho Seco Permanently Defueled Technical Specification D6.9.3. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. The radiation doses I

reported in this SPERR are calculated for a hypothetical individual who receives the maximum possible exposure at or beyond the Site Boundary.

j i

Releases of radioactivity in gaseous and liquid effluenis during this report period did not exceed the limits of 10 CFR 20 or the numerical guidelines of 10 CFR 50, Appendix 1. A 40 CFR 190 dose l

evaluation is not required because radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix l.

I I

I I

I I

E RSNGS SEM! ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

L SUPPLEMENTAL INFORMATION A.

REGULATORY UMfTS & GUIDEUNES FOR EFFLUENT RELEASES 1.

Gaseous Effluents

a. Noble Gas dose rate limit at or beyond the Site Boundary for Gaseous Effluents (Offsite Dose Calculation Manual (ODCM) Technical Requirement 6.14.6):

500 mrem / year to the total body "I

3000 mrem / year to the skin I

b. Noble Gas air dose limit at or beyond the Site Boundary for Gaseous Effluents (ODCM Technical Requirement 6.14.7, numerical guidelines of 10 CFR 50, Appendix I):

5 mrad per calendar quarter for gamma radiation 10 mrad per calendar quarter for beta radiation 10 mrad per calendar year for gamma radiation 20 mrad per calendar year for beta radiation

c. Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.14.6):

1500 mrem / year to any organ I

d. Dose commitment to a member of the public at or beyond the Site Boundary for Gaseous Effluents from tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.14.8, numerical guidelines of 10 CFR 50, Appendix I)-

7.5 nirem per calendar quarter to any organ 15 mrem per calendar year to any organ 2.

Uguid Effluents

a. The concentration of radioactive material in liquid effluents released beyond the Site Boundary for Uquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 11, Column 2. This applies to all radionuclides except dissolved or entrained noble gases (ODCM Technical Requirement 6.14.2).

b. The total concentration of uissolved or entrained noble gases shall not exceed 2.0E-04 pCi/ml (ODCM Technical Requirement 6.14.2).

c. Dose commitment to a member of the public at or beyond the Site Boundary for Liquid Effluents from radioactive materials in liquid offluents shall be limited to (ODCM Technical Requirement 6.14.3, numerical guidelines of 10 CFR 50, Appendix f):

1.5 mrem per calendar quarter to the totrl body 5 mrem per calendar quarter to any organ I

3 mrem per calendar year to the total body 10 mrem per calendar year to any organ 2

i RSNGS SEM! ANNUAL RADIOACTIVE EFFlRNT RELEASE REPORT JANUARY - JUNE 199J I

B.

MAXIMUM PERMISSIBLE CONCENTRATIONS 1.

Gasoous Effluorus The concentrations listed in 10 CFR 20. Appendix B, Table ll, Column 1 are not directly '; sed in calculations for determining permissible gaseous effluent release rates. The annual dose limits of 10 CFR 20 for unrestricted areas are the doses

(

associated with the concentrations of 10 CFR 20, Appendix B, Table 11, Column 1.

Technical Specification dose rate limits (mrom/yr) for gaseous effluents are provider 1 J

I to ensure that the dose rate from gaseous effluents at any time at the Site Boundary J

for G iseous Effluents will be within the annual dose limits of 10 CFR 20 for i

unrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release rates.

2.

Liquid Effluents The concentration values listed in 10 CFR 20, Appendix B. Table II, Column 2 are l

used in calculations to determine permissible liquid discharge flow rates. The most l

conservative MPC VdJe for eaCh radionuClide detected in the liquid effluent sample (excluding dissolved or entrained noble gases) is used in the calculations.

For dissolved or entrained noble gases, the total allowable concentration in the liquid at the point of offsite discharge is limited to 2.0E-04 pCi/ml.

C.

MEASUREMENT MET 140DS FOR TOTAL RADIOACTMTY 1.

Fission and Activation Gases l

Gamma Spectroscopy (HPGe)

Liquid Scintillation (H-3) 2.

Particulares Gamma Spectroscopy (HPGe) i Beta Proportional (Se 40, gross beta) l Alpha Proportfonal (gross alpha) i 3.

Uguid Effluents l

l Gamma Spectroscopy (HPGe)

Liquid Scintillation (H-3)

Beta Proportional (Sr-90, gross beta)

Alpha Proportional (gross alpha) l NOTE:

HPGe refers to Hyper-Pure Germanium y

3

I I

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

D.

BATCH RELEASES (via monitored pathways) 1.

Uguid (RHUT Releases)

Quaner 1 Ouarter 2

a. Number of batch releases 3

1

b. Total time period for batch releases (hot.3 16 5

c. Maximum time period for a batch release (hours) 7 5

d. Average tirne period for a batch release (50urs) 5 5

e. Minimum time period for a batch release (hours) 3 5

l 2.

Uquid (Retentson Basin Discharges)

a. Number of batch releases 6

2

b. Total time period for batch releases (hours) 38 17

c. Maximum time period for a batch release (hours) 9 9

d. Average time period for a batch release (hours) 6 8

e. Minimum time period for a batch release (hours) 4 8

8 days Ci 0.00 E +00 0.00 E+00 2.5 E+01

2. Average Release Rate for period pCi/sec 0.00 E+00 0.00 E+00 I

3. Percent of Tech Req limit N/A N/A

4. Gross Alpha radioactivity' Ci 3.05 E-08 1.04 E-07 C. Tritium

1. Total Release Ci 2.80 E+00 2.11 E+00 2.5 E+01 I

2. Average Release Rate for period pCi/sec 3.60 E-01 2.68 E-01

3. Percent of Tech Req limit 3.05 E-03 2.27 E-03 1

I I

lI l

lI I

.g 5

Note 1: Gross alpha activity has been determined to be naturally occurring and not the result of the fuel cycle.

8

I RSNGS SEM1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

TABLE Ille GASEOUS EFFLUENTS - GROUND LEVEL RELEASE _S CONTINUOUS MODE BATCH MODE Nuclides Released Ung Quarter 1 Ouarter 2 Ouarter 1 Ouader 2 1.

Fission Gases (i.e., Noble Gases)

None 2.

Particulates None 3.

Tntium H.3 Ci 2.80 E + 00 2.11 E + 00 0.00 E+ 00 0.00 E+00 I

I NOTE: Batch releases of gaseous effluent are no longer planned to be made trom Rancho Seco Nuclear Generating Station.

I I

I I

I I

I I

e

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 TABLE 1l84 GASEOUS EFFLUENTS - TYPICAL LOWER UMITS OF DETECTION CONTINUOUS AND BATCH RADIONUCUDES LLD (uCi/cc) 1.

Tritium (H-3) 2.27 E-10 2.

Fission & Activation Gases:

Krypton-85 3.47 E-06 I

3.

Particulates:

Manganese-54 2.08 E-12 Cobalt 58 2.29 E-12 I.

Iron-59 5.89 E-12 Cobalt 60 3.11 E-12 Strontium-89 2.00 E-15 I

Strontium-90 5.00 E-15 Cesium-134 1.52 E-12 Cesium-137 1.88 E-12 I

Barium-140 3.06 E-12 Cerium-141 1.15 E-12 Cerium-144 3.69 E-12 I

I I

I I

I I

I

. I I

10

>h RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 1

I TABLE Ill-D RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES 1

CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:

I UNIT Ouarter 1 Ouarter 2 A. Tritium, Particulate

1. Maximum Organ dose mrem 9.08 E-02 6.84 E-02 I

(a)

(a)

Percent Tech Req Limit 1.21 E+ 00 9.12 E-01 I

B.

Noble Gas

1. Gamma air dose mrad 0.00 E+00 0.00 E+00 Percent Tech Req Lima N/A N/A

2. Beta air dose mrad 0.00 E+00 0.00 E + 00 Percent Tech Req Limit N/A N/A C. Direct Radiation

1. Dose (TLD results) mrem 0.00 E + 00*

0.00 E + 00*

Percent Tech Req Limit N/A N/A I

(a) Child - All Except Bone NOTE: The quarterly doses listed above were calculated using dose factors from GASPAR and default meteorological data for each quarter.

Averages of all doses at TLD Indicator Stations are less than the averagos for all control stations for this Period. None of the Indicator stations indicate significant radiation attributable I

to Plant operations.

I I

I 11

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

D/ UOUID EFFLUEtRS Table IV-A, Liquid Effluents - Summation of All Releases, provides a detaileo summary of liquid I

effluent releases per quarter. This table summtrizes rel eases of fission and activation products, tritium, dissolved and entrained gases, and gross alpha radioactivity. Also listed is the volume of waste released prior to dilution and the volume of dilution water used during each quarter.

The following methodology is used to calculate the Average Diluted Concentration and the Percent of Offsite Dose Calculation Manual (ODCM) Technical Requirement Limit in Table IV-A:

% Avg Diluted Concentration = totet curies neteesed in tech catenorv ner overter in uti total Voltsne Retcased (Part F in Table Iv-A) converted to ml I

C i

% ODCM Technical Requirement Limit -

11 MPC, The total number of radionuclides identified where:

n

=

The average diluted concentration I

C,

=

The MPC of the ith radionuclide, from 10 CFR 20, Appendix B, Table ll, J

MPC,

=

Column 2 The methodology used to calculate the estimated total error in Table IV-A is presented in Section 11 of this report.

I Table IV-B, Liquid Eftluents, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tntium and gross alpha are not included in this table (they are listed in Table IV-A). Since no continuous releases of liquid radioactive effluent are I

made from RSNGS, data is provided only for batch releases.

Table IV-C, Liquid Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in pct /mi for various radionuclides.

Table IV-D, Radiological impact on Man Due To Liquid Effluent Releases, provides a summary of calculated radiatiori doses delivered to a maximum exposed hypothetical individual at the Site I

Boundary for Liquid Effluents (actua; doses wi!I be assessed in the 1993 Annual REMP Report).

The naximum calculated total body dose and organ dose for quarter 1 and quarter 2 are listed. A comparison versus ODCM Technical Requirement cose limits is also presented.

'I I

I 12

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 TABLE IV-A UOUID EFFLUENTS - SUMMATION OF AU. RELEASES I

Est. Total Unit Ouarter 1 Ouarter 2 Error %

A.

Fission & Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 1.27 E-04 4.95 E-05 2.3 E+01

2. Average diluted concentration I

during period gCl/mi 2.80 E-11 1.13 E-11

3. Percent of applicable limit 1.48 E-04 5.92 E-05 B. Tritium

1. Total Release Ci 2.97 E-02 5.06 E-03 2.3 E+01

2. Average diluted concentration during period pCi/mi 6.52 E-09 1.15 E-09

3. Percent of applicable limit 2.17 E-04 3.84 E-05 C. Dissolved and Entrained Gases (i.e., Nobb Gases)

1. Total Release Ci 0.00 E+00 0.00 E + 00 2.3 E+01

2. Average diluted concentration during period pCi/mi 0 00 E+00 0.00 E+00 I

3. Percent of applicable limit N/A N/A D.

Gross Alpha radioactivity

1. Total Release Ci 0.00 E+ 00 0.00 E+00 N/A E. Volume of waste released Retention Basins (prior to dilution)

Litors 5.68 E+06 2.26 E + 06 5.0 E+00 RHUTs (pnor to dilution)

Liters 1.06 E+06 3.07 E+05 5.0 E+00 F.

Volume of dilution water uc.ed during period Liters 4.55 E+09 4.39 E+09 1.0 E+01 I

h 13

i 1

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993

}

TABLE IVB 1

1.JOUID EFFLUENTS

I

{

Nuclides Released Batch Mode Fission and activation products (excludirLq tritium aases, alpha)

Unjt Quarter 1 Ouarter 2 Cobalt.60 Ci 2.50 E-Os 8.as e-07 lE3 Cesium-134 Ci 6,89 E-06 2.33 E-06 Cesium-137 Ci 1.18 E-04 4.63 E-05 Total for period (above)

Ci 1.27 E-04 4.95 E-05 2 ""

Dissolved and entrained cases None 1

NOTE:

No continuous releases of liquid radioactive effluent are made from Rancho Seco Nuclear Generating Station.

A

'I I

I I

I I

14

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 TABLE NC UQUID EFFLUENTS - TYPICAL LOWER UMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (uCi/m0 1.

Tritium (H-3) 2.60 E-06 2.

Particulates & lodines:

Manganese-54 2.11 E-09 I

fron-59 3.71 E-09 Cobatt 57 2.12 E-09 Cobatt-58 1.93 E-09 Cobalt 60 1.98 E-09 Zinc-65 4.34 E-09 Strontium-89 1.00 E-09 I

Strontium-90 5.00 E-10 Rutnenium-106 1.79 E-08 Silver-110m 1.94 E-09 I

Antimony-125 5.78 E-09 Cesium-134 1.93 E-09 Cesium-136 2.23 E-09 I

Cesium-137 2.30 E-09 Ba.ium-140 7.75 E-09 Cerium-141 3.60 E-09 Cerium-144 1.59 E-08 3.

Dissolved and Entrained Gases:

Krypton-85 4.87 E-07 I

I I

I I

g-

,5

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 TABLE IV-D l

RADIOLOGICAL IMPACT ON MAN DUE TO UQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:

UNIT Ouarter 1 Ouarter 2 A.

1. Maximum Total Body dose mrem 3.27 E-02 1.31 E-02 (a)

(a) g

2. Percent Tech Req Limit 2.18 E + 00 8.73 E-01 B

1. Maximum Organ dose mrem 6.58 E-02 2.67 E-02 (b)

(b)

I

2. Percent Tech Req Limit 1.32 E + 00 5.43 E-01 (a) Adult (b) Child - Bone NOTE: The quarterly doses listed above were calculated using dose factors from LADTAP and the average dilution flow (cfs) for each respective quarter.

I I

I I

!I l

16

I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

E SOUD WASTE A.

SOUD WASTE SHIPPED OFFSITE FOR BURIAL OR DISICSAL (Not imxkated fueQ No shipments of radioactive waste were made to a disposal site during the reporting period.

i B.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments None I

I I

I I

I I

I I

I 4T

aa 2-L I

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 I

I I

I ADDENDUM CORRECTIONS TO THE JULY TO DECEMBER 1991 SRERR I

l I

I i

g

!lI I

I I

I

.s 4 mmms&am.a M

aA,k L

gamW_s s

Js, e

a,,

sy,,

asg_ w a

,_ noma

-g,y

,,yumx_u

_g,_ _,

g i

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

JULY - DECEMBER 1991 l

i a

i l

I I

I g

I I

I

RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1991 I

TABLE V-D RADIOLOGICAL IMPACT ON MAN DUE TO UOUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:

1991 UNIT Ouarter 3 Quarter 4 Annual A.

1. Maximum Total Body dose mrem 9.73 E-03 6.36 E-03 4.59 E-02 (a)

(a)

(a) l

2. Percent Tech Spec Limit 6.49 E-01 4.24 E-01 1.53 E + 00 I

l B.

1. Maximum Organ dose mrem 1.88 E-02 1.24 E-02 8.69 E-02 (b)

(c)

(b)

2. Percent Tech Spec Limit 3.76 E-01 2.48 E-01 8.69 E-01 I

i l

l I

(a) Adult (b) Child - Uver (b) Child - Liver, Bone NOTE: The quartery doses listed above were calculated using dose factors from LADTAP and the average dilution flow (cts) for each respective quarter. Annual doses are the sum of quarterly doses.

17

I RSNGS SEM! ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1991 I

E SOUD WASTE A.

SOUD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradunod fuel) 6-Month Est. Total

1. Type of Waste Unit Period Error, %

3 a.

Spent resins, filter sludges, m 5.31 E + 00 evaporator bottoms, etc.

Ci 1.20 E + 00 2.5 E+01 3

b.

Dry compressible waste, m

1.91 E+01 contaminated equip, etc.

Ci 4.15 E + 00 2.5 E + 01 3

c.

Irradiated components, m

control rods, etc.

Ci None N/A 3

d.

Other: Radium Sources m

2.12 E-01 (See Note 1)

Ci 1.05 E-04 3.6 E+01

2. Eetimate of major nuclide composition (by type of waste) a.

Cs-137 5.39 E+01 H-3 1.98 E+01 I

Cs-134 7.90 E+ 00 Fe-55 7.88 E + 00 Ni-63 6.58 E+ 00 Co 60 2.70 E + 00 Sb-125 5.07 E-01 St-90 3.48 E-01 Ag-110m 1.44 E-01 Te-125m 1.02 E-01 I

b, Ni-63 3.59 E+01 Fe 55 2.04 E + 01 Co-60 1.81 E + 01 I.

H3 1.05 E+01 Cs-137 7.13 E+00 Ce-144 1.57 E+ 00 C-14 1.36 E+00 Cs-134 1.04 E+ 00 l

Ag-110m 1.00 E + 00 I

Mn-54 9.24 E-01 1

Sb-125 9.18 E-01 l

Ru 106 6.80 E-01 f

Te 125m 2.16 E-01 c.

N/A d.

Ra-226 1.00 E+02 18