ML20203H713

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Annual Radioactive Effluent Release Rept
ML20203H713
Person / Time
Site: Rancho Seco
Issue date: 12/31/1997
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20203H704 List:
References
NUDOCS 9803030307
Download: ML20203H713 (19)
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l RANCHO SECO Nuclear Generating Station l

LICENSE NUMBER DPR-54 i

ANNUAL RADIOACTIVE l

EFFLUENT RELEASE REPORT 1

JANUARY - DECEMBER 1997 k

I 9803030307 900225 DR ADOCK 0500 2

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RSNGS ANNUAL RADIOACTIVE EFFLt>ENT RELEASE REPORT JANUARY-DECEMBER 1997 t

TABLE OF CONTENTS INTRODUCTlON..............

................................................................................................................1:

I, S U P P LE M E N TAL I N F O R M ATlO N.................................................................................................. 2 A. ' Regulatory Limits & Guidelines for Effluent Releases.................................................................. 2 B. f 4aximu.n Ef fluent Concentrations............................................................................................ 3 C : Measurement Methods for Total Radioactivity............................................................................... 3 D. _ B atch R ele ases (via monitored pathways).................................................................................... 4 E.. U n pl a n n ed R e l e a s e s..........................................................................................................

F. Radioactive Effluent Monitoring instrumentation Inoperable for Greater Than 30 Days..................S II. E S Tl M A T I O N O F E R R O R......................................................................................................

111. GASEOUS FLUENTS.............................................................................................................7 Tableill A

. aseous Effluents Summation of All Releases.......................................................... 8

. Table Ill.B Gaseous Ef fluents - G round Level Releases.............................................................. 9 Table lit C Gaseous Effluents Typical Lower Limits of Detection..............................................10 Table Ill.D Radiological Impact on Man Due to Gaseous Effluents..............

11 IV. LI Q U l 0 E F F L U E N T S.....................................,,.....,.......................................,................ 12 Table IV A Liquid Effluents Summation of All Releases...........................................................13

. Table IV B Liq u id E f flu e nt s........................................................................................... 1 4 Table IV C Liquid Effluerits Typical Lower Limits of Detection..................................................15 Table IV D Liquid Effluents Radiological Impact on Man Due to Liquid Effluents.........................16 J

V.SOLIDWASTE...........................................................................................................................17

-ATTACHMENTS-

1. Radiological Environmental Monitoring Program Manual, Revision 9
2. Off Site Dose Calculation Manual, Revision 9
3.. Radiological Environmental Monitoring Program Manual. Revision 10

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. RSNGS ANNUAt. RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1997 -

INTRODUCTION Rancho Seco Nuclear Generating Station (RSNGS) Unit No.1 is located in Sacramento County, Calitomia approximately 25 miles southeast of Sacramento and 26 miles nodh-northeast of Stockton.

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

This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquid efflueni reieases made from Rancno Seco during the period January 1 through December 31,1997.

Also presented in this report is the projected radiological Impact from these releases and a summary of solid radwaste ship....its.

4 This report has been prepared by the Sacramento Municipal Utility District to meet the requirements of Rancho Seco Technical Spacification D6.9.3 and Offsite Dose Calculation Manual (ODCM) Step 6.15. It is presented it' accordance with the format of USNRC Regulatory Guide 1.21 The radiation doses reported in this ARERR are calculated for a hypotheticalindividual who receives the maximum possible exposure at or beyond the applicable Site Boundary.

Releases of radioactivity in gaseous and liquid effluents 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 evaluation is not required because radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix 1.

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RSNOS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY. DECEMBER 1997 L SUPPLEMENTAL INFORMATION A. " REGULATORY LIMITS & GUIDELINES 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 3000 mrem / year to the skin

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

5 mrad per calendar quarter for gamma iadiation 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 foi Gaseous Effluents for Tritium and i

radioactive material in particulate for with half lives greater than 8 days (ODCM Technical Requirement 6.14.6):

1500 mrem / year to any organ 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 guidellres of 10 CFR 50, Appendix l):

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

Liquid Effluents

a. The concentration of radioactive materialin liquid effluents released beyond the Site Boundary for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 2, Column ?.

This applies to all radionuclides except dissolved or entrained noble gases (ODCM Ochnical Requirement 6.14.2),

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

1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter to any organ 3 mrem per calendar year to the total body 10 mrem per calenJar year to any orgar

=

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L RSNGS AN IUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1997

8. MAXIMUM EFFLUENT CONCENTRATIONS
1. Gaseous Effluents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (alr) are not directly used 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 2, Column 1. ODCM Technical Requirement dose rate limits (mrem /yr) for gaseous effluents are provided to ensure that the e

dose rate from gaseous effluents at any time at the Site Boundary for Gaseous Effluents will

. be within the annual dose limits of 10 CFR 20 for unrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release rates.

2. Llquid Effluents The concentrallen values listed in 10 CFR 20, Appendix B, Table 2 Column 2 are used in 4

calculations to determine permissible liquid discharge flow rates. The most conservative Maximum Effluent Concentration (MEC) value for each radionuclide detected in the liquid effluent sample (excluding dissolved or entrained noble gases) is uud in the calculations.

C. MEASUREMENT METHODS FOR TOTAL RADIOACTIVITY

1. Fission and Activation Gases Gamma Spectrnscopy (HPGe)

Liquid Scintillation (H 3) 2.

Particulates Gamma Spectroscopy (HPGe)

Beta Proportional (Sr 90, gross beta)

Alpha Proportional (gross alpha) 3.

Liquid Effluents Gamma Spectroscopy (HPGe) m Liquid Scintillation (H 3)

Beta Proportional (Sr 90, gross beta)

Alpha Proportional (gross alpha).

NOTE:

. HPGe refers to Hyper Pure Germar. lum 3..

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RSNGS' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.

JANUARY DECEMBER 1997 D. BATCH RELEASES (via monitored pathways).

l 1.

Liquid (RHUT Releases)

Quarter 1 Quarter 2 Quarter 3 Quarter 4

a. Number of batch releases 3

1

-1 1

b. Total time period for batch releases (hours)-

-13 5

5 3

c.

Maximum time period for a batch release (hours) 8 5

5 3

d.

Average time period for a batch release (hours) 4 5

5 3

e. Minimum time period for a batch release (hours) 1 5

5 3

2.'. Liquid (Retention Basin Discharges)

a. Number of batch releases 1

0 0

2

b. Total time period for A a releases (hours) 12 0

0 23 c.

Maximum time period for a batch release (hours)-

12 0

0 12 d.

Avelage time period for a batch release (hours) 12 0

0 11

e. Minlmum time period for a batch release (hours) 12 0

0 11 f.

Average stream flow during periods of release of effluent into a flowing 15.4 15.5 15.6 16.0 stream (cfs) 4 4

4

- NOTE: - The Regenerant Holdup Tanks (RHUTs) are released to the Retention Basins. The Retention Basins are discharged offsite. All 10 CFR 50, Appendix i dose calcu;ations are based on the RHUT releases.. All 10 CFR 20 calculations are based on the Retention Basin discharges.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-JANUARY DECEMBER 1997_

i E. UNPLANNED RELEASES l

This section describes unplanned releases of radioactivity in liquid and gaseous effluent.

j Gascous None i

Uquid

.None-F. - RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION INOPERABLE FOR GREATER THAN 30 DAYS -

The Auxillary Building RadWaste Vent Radiation Monitor, R 15546A, was out of service between April 29,1997 and September 8,1997 because of sample flow and instrumentation problems. Radiological Effluent was not re' eased from the Auxillary Building RadWaste Vent during the year 1997, intermittent communication between the Interim On Site Storage Building Radiation Monitor, R 15106, and Radiation Monitor Computer, H 4DRM caused by defective hardware resulted in R 15106 being out of service from April 29,1997 through July 24,1997 and September 3, 1997 to December 10,1997. Four releases totaling approximately 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> occurred, using compensa,ary monitoring measures, during the outages.

The Reactor Building Radiation Monitor, R-15044, was inoperable from December 19,1996 through February 5,1997 because the power supply was removed and placed into Radiation Monitor R 15045, Auxiliary Building Stack. The power supply in monitor R 15045 had failed and an exchange was made bes use Reactor Building Purges are normally performed once per quarter. The Reactor Building was not purged while the monitor was out of service.

Radiation Monitor R 15044 was also inoperable for more than 30 days between March 24, 1997 and June 16,1997 due to a detector failure. Two purges occurred, using compensatory monitoring measures, during this outage One purge lasted only 9 minutes while the other release continued for about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.

JANUARY. DECEMBER 1997 lL ESTIMATION OF ERROR The methods for establishing error estimates included review of applicable station procedures, inspection of sampling equipment, engineering estimates, statistical applications, review of calibration setpoMt data, and communication with plant personnel. The various sources of error (s) in reported values of gaseous l effluents, liquid effluents, end solid waste are assumed to be independent, and thus the total error is calculated according to the formula:

1 Total Error =

gi2 + O2 + G3

+U i where: c, = relative error associated with component i i

i Sources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficiency, counting, and calibration.

- Sources of error for liquid eff,wnts include RHUT volume, dilution water flow rate, grab sampling, counting, and calibration.

s Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose rate meter reading, Wastetrak dose to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1997 111. GASEOUS EFFLUENTS Table lil-A, Gaseous Effluents. Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of fission and activation gases, particulates with half-lives groater than 8 days, and tritium. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows:

{(F )( Avg Rel Rate)(X / Q)(Dose Factor))

~

(Dose Rate Limit) where:

The fraction of the total number of Curies of nuclide i out of the total curies in that Fi

=

category for that quarter (unitless).

NOTE: F. always equals 1.0 for H-3 because it is the only nuclide in the category.

(Total Curies per category per quaner)

Avg Rel Rate = -

(# seconds in the quarter)

X/Q = A default dispersion factor determined to be conservative when compared to the use of actual data (sec/m3).

The values derived for each nuclide i from NRC Regulatory Guide 1.109 (KI, Dose Factor =

Ll+1.1Mi, or Ralj).

(Units in (mrem /yr)/(pCl/m3))

Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed in Section i of this report (mrem /yr).

NOTE: Particulates with half lives less thar. 8 days are not included in this calculation.

The meH odology used to calculate the Estimated Total Error (%) in Table lil-A is presented in Section ll 1

of this report.

Table ill-B, Gaseous Effluents Ground Level Releases, provides a complete quarterly summary of the amount of radioactivity (Cl) released per radionuclide in each quarter. Data from continuous and batch releases are provi6ad for fission gases, particulates, and tritium. Data reported for batch releases results only from unplanned releases.

Table lil C, Gaseous Effluents - Typical Lower Limits of Detection, provides a listing of the typicallower limit of detection (LLD) concentrations in pCl/cc for various radionuclides.

Tabh Ill-D, Radiological Impact on Men Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 1997 Annual REMP Report). The maximum calculated organ dose, gamma air dose, and beta air dose are listed for each quarter along with an annual total. The dose due to direct radiation based on Thermoluminescent Dosimeter (TLD) results is also listed. Presented in this table for each category is a comparison versus ODCM Technical Requirement dose limits with 'he exception of direct radiation measurements.

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R RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1997 TABLE IN-A i

GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES Est. Total.

[

. Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Enor.%

l A. l Fission & Activation Gases (i.e. Noble Gases)

'1.

Total Ra! caw Ci 0.00 E+00 0.00 E+00 0.C3 E+00 0.00 E+00 N/A.

' 2.

Average Re! ease Rate for period pCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 3; Percent of Tech Reg limit N/A N/A N/A N/A

8. Particulates
4. Particulates with half-lives >8 days Ci 0.00 E+00 0.00 E+00 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 0.00 E+00 0.00 E+00 3.

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

[

4 Gross Alpha radioactivity' Ci 0.00 E-00 1.56 E-07 5.86 E-08 1.17 E-08

_l C. Tritium l

1.

Total Release Ci 2.95E-01 6.27E-01 4.32E-01 2.58E-01 2.5 E+01 r

2.

Average Release Rate for period pCi/ rec 3.79E-02 7.97E-02 5.43E-02 325E-02 3.

Percent of Tech Req limit 321E-04 6.75E-04 4.60E 2.75E-04 i

Note 1: Gross alpha activity hhs been determined to be naturally occuning and not the result of tte fuel cycle.

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RSNGS' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 4 DECEMBER 1997.

TABLE lil-B GASEOUS EFFLUENTS. GROUND LEVEL RELEAH),

Continuous Mode i

Nuclides Released Unit

..Quader1 Quader 2 Quarter 3 Quarter 4 1._- Fission Gases (i.e., Noble Gases) -

None

'2. Particulates None

3. Tritium

(-

H3 Cl 2.95 E 01 6.27 E-01 4.32 E 01 2.58 E 01 1

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NOTE: Batch releases of gaseous effluent are no longer planned to be made from Rancho Seco Nuclear

. Generating Station.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY. DECEMBER 1997 TABLE Ill-C GASEOUS EFFLUENTS TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES LLD (uCi/ce) 1.

Tritium (H 3) 2.27 E 10 2.

Fission & Activation Gases:

Krypton-85 3.47 E-06 3.

Particulates:

Manganese 54 2.08 E 12 Cobalt 58 2.29 E 12 Iron-59 5.89 E 12 Cobalt 60 3.11 E 12 Strontium-89 2.00 E 15 Strontium-90 5.00 E 15 Cesium 134 1.52 E 12 Cesium 137 1.88 E 12 Barium 140 3.06 E 12 Cerium 141 1.15 E 12 Cerium 144 3.69 E 12 10

E RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1997 TABLE lil-Q RADIOLOGICAL IMPACT ON MAN DUF TO GASEOUS EFFLUENT RELE&$f&

- CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:

1997 M0]l Quader 1 Quarter 2 Quarter 3 Quarter 4

. Annual A. Tritium, Particulate

1. Maximum Organ Dose mrem 9.57 E 03 2.03 E 02 1.40 E 02 8.36 E-03 5.22E 02 (a)

(a)

(a)

(a)

(a)-

Percent Tech Req limit 1.28 E 01 2.71 E 01 1.87 E 01 1,11 E 01 3.48E 01 B. Noble Gas

1. Gamma Air Dose mrad 0.00 E+00 0.00 E+00 0.00 E400 0.00 E+00 0.00 E+00 Percent Tech Req limit N/A N/A N/A N/A N/A 2.

Beta Air Dose mrad 0.00 E+00 0.30 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Percent Tech Req limit N/A N/A N/A N/A N/A C. Direct Radiation 1,- Dose (TLD results) mrem 0.00 E+00* 0.00 E+00* 0.00 E+00* 0.00 E+00* 0.00 E+00*

2.

Percent of Tech Req limit N/A N/A N/A N/A N/A (a) Child - All Except Bone NOTE: The quarterly doses hsted above were calculated using dose factors from GASPAR and default meteorological data for each quader. Annual doses are the sum oi quarterly doses.

  • Averages of all doses at TLD Indicator Stations are less than the averages for all control stations for this Period. None of the Indicator stations indicate significant radiation attributable to Plant operations, 2

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1997 1

IV. LlQUID EFFLUENTS

- Table IV A, Liquid Effluents Summation of All Releases, provides a detailed summary of liquid effluent releases per quarter, This table summarizes releases of fission and activation products, tritium, dissolved and entralned gases, and gross alpha radioactivity, Also listed is the volume of waste released orlor to dilution and the volume of dilution water used during each quarter, t

The followin0 methodology is used to calculate the Average Diluted Coricentration and the Percent of ODCM Technical Requirement Limit in Table IV A:

% Tech Req Limit = f 4

I i.MEC,

i The total number of radionuclides identified

- where:

n

=

The average diluted concentration of radionuclide 1 C.

=

(Total Release per Category per Quarter in Ci)

_(Total Release Volume (part F in Table IV A) in ml)

MEC=

The MEC of the 4th radionuclide, from 10 CFR 20, Appendix B. Table 2, Column 2 i

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

- Table IV B, Liquid Elfluents, provides a complete quarterly summary of the amount of radioactivity (Cl) released per radionuclide in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tritium and gross alpha are net included in this table (they are listed in Table IV A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data is.

provided only for tatch releases.

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

Table IV D, Radiological Impact on Man Due To Liquid Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Liquid Effluents (actual doses will be assessed in the 1997 Annual REMP Report). The maximum calculated total body dose and organ dose are listed for each quarter along with an arinual total. A comparison versus ODCM Technical Requirement dose limits is also presented.

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P RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1997 '

r TABLE IV-A LIQUID EFF-LUENTS -SUMMATION OF ALL RELEASES Est Total' Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error. %

{

A.-. Fission & Activation Products 1.

Total Release (not including tritium, gases, alpha)

Ci 4.46 E-05 7.78 E-06 1.53 E-05 1.30 E-05 2.3 E+01

2. Averago diluted concentration during period pCi/mi 1.31 E-11 2.25 E-12 4.36 E-12 3.61 E-12 3.

Percent of Tech Req limit 1.31 E-03 225 E-04 3.90 E-04 3.61 E-04 B. Tritium 1.

Total Release Ci 1.25 E-03 ' O.00 E+00 0.00 E+00 6.90 E-03 2.3 E+01 1

2.

Average diluted concentration during r,eriod pCi/mi 3.68 E-10 0.00 E 00. 0.00 E+00 1.91 E-09 3.

Percent of Tech Req limit 3.68E-05 twA N/A 1 11 E-04 C. Dissolved and Entrained Gass (i.e., Noble Gases) t 1.

Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A

' 2.

Average diluted concentration during period pCi/mi 0.00 E+00 0.00 E+00. 0.00 E+00 0.00 E+00 D. Gross Alpha radioactivity 1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.3 E+01 E. Volume of Waste Released

[

Retention Basins (prior to dilution)

Liters 1.17 E+06 0.00 E+00 0.00 E+09.' 2.44 E+06 5.0 E+00

= RHUTs (prior to dilution)

Liters 6.85E+05 2.17 E+05 5.34 E+05 5.79 E+05 5.0 E+00 F. Volume of dilution water used during period Liters 3.40 E+09 3.46 E+09 3.52 E+09 3.60 E+09 2.0 E+01 -

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1997 -

TABLE IV-B LIQUID EFFLUENTS Nuclides Released Batch Mode

--1.

Fission and activation products (e:tcludina tritium. asses aloha)

Mall Quarter 1 - Quarter ?

Quarter 3 Quarter 4 Co 01 0.00E+00 0.00 E+00 2.43 E 06 0.00 E+00 Sr90 Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Cs-134 Cl 8.62 E 07 0.00 E+00 0.00 E+00 0.00 E+00 4

Cs-137 Cl 4.37 E 05 7,78 E-06 1,29 E 05 1,40 E 05 Total for period (above)

Cl 4.46 E-05 7.78 E 06 1.53 E 05 1.30 E 05

2. Dissolved and entrained oagji None t

NOTE: No continuce eleases of liquid radioactive effluent are made from Rancho Seco Nuclear Generating Station.

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' RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMGER1997

. TABLE IV-C LIQUID EFFLUENTS - TYFlCAL LOWER LIMITS OF DETECTION RADIONUCLIDEN BATCH MODE: LLD (uCl/mb 1.

Tritium (H 3) 2.60 E 06 2.

Particulates:

Manganese 54 2.11 E 09 Iron 59' 3.71 E 09 Cobalt 57 2.12 E 09 Coba!t 58 1.93 E 09 Cobalt-60 1.98 E 09 Zinc-65 4.34 E 09 Strontium 5.00 E 10 Ruthenium 106 1.79 E 08 Silver 110m 1.94 E 09 Antimony 125 5.78 E-09 Ceslum 134 1.93 E 09 Cesid.n 136 2.23 E 09 Ceslum 137 =

2.30 E 09 Berium-140 -

7.75 E 09 Cenum 141 3.60 E 09 Cerium-144 1.59 E 08 3.

Dissolved and Entralned Gases; Krypton 85 -

4.87 E 07 1

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L RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY. DECEMBER 1997 TABLE IV-D BAplOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCUMllip RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENLt 1997 Mall Quarter 1 Quarter 2 Quatier 3 Quarter 4 Annual A. Maximum Total Body Dose mrem 1.51 E 02 2.58 E 03 4.28 E 03 4.23 E-03 2.82 E 02 (a)

(a)

(a)

(a)

(a)

Percent Tech Req limit 1.01 E+00 1.72 E 01 2.85 E 01 2.82 E-01 8.73 E 01 B. Maximum Organ Dose mrem 3.16 E 02 5.51 E 03 9.07 E 03 8.91 E 03 5.51 E 02 (b)

(b)

(b)

(b)

(b)

Percent Tech Req limit 6.32 E 01 1.10 E 01 1.81 E 01 1.78 E 01 5.51 E 01 i

i i

i (a)

Adult

_b)

Child - Bone -

(

Note: The quarterly doses listed above were calculated usir,g dose factors from LADTAP and the average dilution flow (cfs) for each respective quarter. Aiinual doses are the sum of quarterly doses.

16 c.

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I RSNGS ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT JANUARY o DECEMBER 1997 V. SOLID WA8TE A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated fuel)

No shipments of radioactive waste were made to a disposal site during the reporting period.

8. lyr.ADIATED FUEL SHIPMENTS (Disposition)

Number of Shloments None 4

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