ML20214M148

Addendum to Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985

ML20214M148
Person / Time
Site:	Rancho Seco
Issue date:	12/31/1985
From:	Bradley E, Gardner R, Oesterling R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
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ML20214M119	List: ML20214M115 ML20214M133 ML20214M139 ML20214M148
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NUDOCS 8609100556
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JANUARY-JUNE 1986 RANCHO SECO NUCLEAR GENERATING STATION ADDENDUM 8 Addendum to Semlannual Radioactive Effluent Release Report, July-December 1985 I

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E 86091005S6 860828 PDR ADOCK 05000312 I R PDR O - . - - - - .

SEMIANNUAL RADI0ACT1VE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION EXECUTIVE

SUMMARY

The Rancho Seco Nuclear Generating Station Unit No.1 is located approximately 26 miles north-northeast from Stockton and 25 miles southeast from Sacramento in Sacramento County, California. Rancho Seco Unit No. I began commercial operation on April 17, 1975. The single unit on the Rancho Seco site is a pressurized water reactor supplied by Babcock & Wilcox. The rated capacity is 2,772 megawatts thermal and 963 gross megawatts electrical.

This report has been prepared by the Sacramento Municipal Utility District to meet the reporting requirements of Technical Specification 6.9.2.3, Operating License No. DPR-54. It is transmitted to the U. S. Nuclear Regulatory Commission Region V Office of Inspection and Enforcement. Copies are provided to the California Energy Commission, California Department of Public Health, California State University at Sacramento, Central Valley Regional Water Quality Control Board, local libraries, and District offices as a public document.

This document reports the quantities of radioactive materials released as liquid, gaseous effluents and solid radwaste shipments. Estimates of the radiological impact to man associated with the gaseous and liquid effluent I releases are presented. The report period is July 1, 1985 through December 31 1985.

The format of this report follows U. S. NRC Regulatory Guide 1.21 as required by Technical Specification 6.9.2.3. There are six major sections: (1)

Gaseous Effluents; (2) Liquid Effluents; (3) Solid and Radw3ste shipments; (4)

Radiological Impact on Man; (5) Meteorological data; and (6) Supplemental Information. Each section contains, where appropriate, narrative or descriptive material to clarify the tables. Several items included in Regulatory Guide 1.21 have been retained in this report, although they are outmoded by the " dose-based" Technical Specifications.

Additional information required by Technical Specification 6.9.2.3 is also presented. This includes changes to the Offsite Oose Calculation Manual and the solid radwaste Process Control Program, assessments of radiation doses associated with radioactive effluents to unrestricted areas, and reports of abnormal releases.

In accordance with Technical Specifications, the Olstrict maintains an Offsite Oose Calculation Manual. It contains the detailed methods and procedures to perform the calculations supporting this report.

The radiological liquid effluent control program that began in October 1984 has continued during this report pericd. Third and fourth quarter gaseous effluent releases are within the Technical Specification limits. The third quarter estimate of the liquid effluent releases exceeded the Technical Specification limits. The fourth quarter estimate of the 11guld effluent releases were within the Technical Specification limits.

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SEM1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION I. SUPPLEMENTAL INFORMATION - EFFLUENT AND WASTE DISPOSAL REPORT A. SUPPLEMENTAL INFORMATION Supplemental information as outlined in Regulatory Guide 1.21 is presented in this section of the report.

B. GASE0US EFFLUENTS Gaseous effluents are assumed to be ground level release and are summarized in Table II-A," Gaseous Effluents - Summation of All Releases," and Table II-8, " Gaseous Effluents - Ground Level Releases." Elevated releases are not evaluated at Rancho Seco because the gaseous effluent stack height is less than the height of its adjacent structure.

There were 5 Haste Gas Decay Tank releases and 7 Reactor Building >

purges during the period July I through December 31, 1985. There was one abnormal release of radioactive gases in this report period.

C. LIQUID EFFLUENTS There were 113 batch releases from Regenerant Holdup Tanks (RHUT) with the material ultimately released by 48 Retention Basin discharges.

Liquid releases are summarized in Table III-A and the isotopic contents are detailed in Table III-B. There were two abnormal liquid releases in this report period.

The estimate of the quantity of radioactivity in liquid effluent was determined in the following manner. Samples are routinely collected from each of the RHUT discharges and composited for analysis on a monthly basis. These monthly composites are then sent to the Olstrict's environmental monitoring contractor for strontium and alpha analysis. The Olstrict requested that these samples also be analysed I for gamma emitting radionuclides to better estimate the 1985 liquid effluent release. For those months that did not have adequate volume for gamma spectral analysis or were contaminated, a weighted average LLO (Lower Limits of Detection) value for the monthly RHUT discharges was calculated. The weighting was based ucon the RHUT discharge volumes. The weighted average LLD would then be an upper bound estimate of the monthly radloactive liquid effluent. Beginning in November 1985, the RHUT samples were separated into radiological and nonradiological samples and ccmposited separately on a monthly basis.

If the RHUT sample analysis resulted in observable tritium or gross beta, the sample was added to the radiological composite and its discharge volume added to the radiological liquid effluent volume. If no tritium, gross beta, or gamma emitting nuclides were observed, the sample was added to the nonradiological composite and its volume added I

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SEM1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION to the nonradiological liquid effluent volume. If the monthly composite sample analysis results in a higher estimate of radioactive liquid effluent than the individual RHUT sample analysis performed onsite, the higher values are recorded and reported.

The quantitles of radioactive liquid effluent in Table III-A and Table III-B are the results from the monthly composite of the RHUT discharges analyzed by the District's environmental monitoring contractor and weighted average LLO. The Olstrict's environmental 3 monitoring contractor's LLDs are much lower than the values reported 3 in Table III-C which are typical of the District's on site LLO capabilities.

D. SOLIO WASTE There were 57 shipments of radioactive wastes to the Hanford Burial Site between July I and December 31, 1985. These consisted of 200 ft3 containers of solidified 11guld waste, primary and low activity secondary resins, and cartridge type filters incorporated into concrete under an approved Process Control Program and shipped in approved LSA containers. In addition, dry compressible waste and contaminated equipment was shipped in approved LSA containers.

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE I-E EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION Abnormal Releases

a. Liquid

1. Number of releases 3

2. Total activity released offsite none

b. Gaseous

1. Number of releases 1

2. Total activity released offiste 3.27 E+01 Ci I

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SEMIANNUAL RADl0ACT!VE EFFLUENT RELEASE REPORT JULV-0ECEMBER 1985 RANCHO SEC0 NUCLEAR GENERATING STATION ABNORMAL RELEASE REPORTS A. GASEOUS

1. On December 26, 1985, at 0413 hours0.00478 days <br />0.115 hours <br />6.828704e-4 weeks <br />1.571465e-4 months <br />, the reactor tripped on high reactor coolant system (RCS) pressure initiated by a loss of electrical power to the unit's integrated control system (ICS).

Prior to the trip the unit was operating in a steady-state condition at 76 percent power. The reason for the power loss was a malfunctioning power supply volta? mnitor modula in the ICS. This module is designed to trip the ICS DC power supplies when they have low output voltage, however, it tripped the power supplies when voltage was normal.

The ICS provides the proper coordination of the reactor, steam generator feedwater control, and turbine under various operating conditions. The control modules used to accomplish this function utilize a -10 to +10 VDC signal range. Upon the loss of ICS power, all ICS demands went to midscale, which corresponds to zero volts.

This caused the main feedwater (MFH) valves to close to their mid-position, while the auxillary feedwater (AFH) control valves, atmospheric dump valves (ADVs), and the turbine bypass valves (TBPVs) opened to their mid-position.

The closing of the MFH valves reduced flow through the steam generators, thereby increasing RCS pressure and temperature, and producing the high RCS pressure trip. At approximately the same time AFH Pump P-318 was automatically started on low feedpump discharge pressure.

Because the ADVs and TBPVs were partially opened (as a result of ICS power failure), and the AFH flow initiated, the unit underwent a rapid RCS cooldown exceeding the Technical Specification Section 3.1.2 limits. During the cooldown period the RCS temperature dropped from approximately 582*F to 386* In 24 minutes. As a result of the rapid cooldown, RCS pressure decreased below 1600 psig and the safety features actuation system (SFAS) was initiated, including the Control Room / Technical Support Center Essential HVAC trains.

During the event, equipment operators were dispatched to manually close the ADVs, TBPVs, and AFH valves. The operators experienced difficulty in determining that the "A" AFH valve was closed and g applied a valve wrench, As a result, tha valve operator failed and I the valve reopened. An attempt to shut the manual isolation valve downstream of the "A" AFH valve failed. At approximately the same time (0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br />), Operations personnel determined that the ICS power supply breakers were tripped and restored power by reclosing the breakers. Technicians had previously checked the power supplies at approximately 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />, but had not observed the tripped breakers.

The "A" AFW valve was then closed from the Control Rocm.

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I SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> an " unusual event" was declared and the proper state and county agencies were notified. The NRC Outy Officer was notified I at 0442 hours0.00512 days <br />0.123 hours <br />7.308201e-4 weeks <br />1.68181e-4 months <br />. The " unusual event" was terminated at 0841 hours0.00973 days <br />0.234 hours <br />0.00139 weeks <br />3.200005e-4 months <br />.

During the subsequent plant recovery, make-up pump P-236 suffered extensive damage when operation without adequate suction flow resulted in the fallute of the pump seals. Approximately 400 gallons of water from the make-up tank spilled onto the pump room floor prior to the flow being valved off. Minor airborne activity was released to the atmosphere through the filtered Auxiliary Building ventilation system.

The quantity of radioactive material released totalled 32.7 curles of noble gases. The maximum doses to a nypothetical individual at the exclusion area boundary were 0.06 mrem to the total body and 0.2 mrem to the skin.

The significant actions already taken, planned and proposed to address this event cannot reasonably be included in this report but are available for review at the District office and the NRC Public Document Room. The 01 strict is continuing the development of the recovery plan for this event and will continue to provide the NRC's I Region V personnel with information and actions planned and/or taken to prevent a recurrence of this or similar events.

8. LIQUID

1. While aligning valving and equipment to fill "A" steam generator on I July 9, 1985, secondary water was unintentionally allowed to drain from a hose co1nected to the system to the storm drains. Analysis of the secondary system water indicated concentrations of C5-134 at 3.64 nCi per liter and Cs-137 at 7.74 nC1 per liter. A volume estimated at 450 liters was released.

The occurance resulted from a communication problem between shifts, and a failure of the operator to ensure that hoses, used on previous shifts, were still properly connected.

Elther the hanging of abnormal tags or the following of the valve lineup in the operations procedure would have avolded this occurrence. The procedures, if followed, appear adequate to avoid a re-occurrence without further corrective action. This error was I discussed with the coerator concerned to reemphasize the importance of checking lineups before proceeding.

The spill was contained onsite, and it was verlfled by the Senior Control Room Operator that no water was lost offsite. Due to the fact that no contamination remained after the spilled water evaporated, no consequences resulted from this incident.

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SEM8 ANNUAL RADICACTZVE EFFLUENT RELEASE REPORT JULV-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION

2. On July 30, 1985, during a refueling outage, clear plastic sleeving was found directing leakage from the High Pressure turbine throttle g valve, TV-3, to a storm drain on the +40 foot level of the turbine E building. The leakage was redirected to a monitored drain. A permanent drain has been installed discharging the leakage to a monitored drain at grade level in the turbine building.

The release of potentially radioactive liquid to a storm drain was a violation of procedures. The secondary system was known to be contaminated because of steam generator tube leaks. Leakage from the secondary system is potentially radioactive and should have been posted. The area around the leak has since been posted as a controlled area.

No consequences were expected from this event.

3. Approximately 30 gallons of tritiated water were released to the ground on December 28, 1985 as a result of draining the PASS backup water cooling tank. The concentration of tritium was 17 microcuries per liter for a total release of 1930 microcurles with none leaving the site. No radiological concequences are expected due to diffusion and evaporation.

Personnel were advised to check the radiological status of sources of water before using to flush systems.

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l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPCRT JULY-DECEMSER 1935 RANCHO SECO NUCLEAR GENERATING STATICN 1 Table II-C, " Gaseous Effluents - Lower Limit of Detection, provides a listing of radionuclide lower limit of detection concentrations.

Table II-0, " Gaseous Effluents - Radiation Oose Estimates at Site and Exclusion Area Boundaries," provides a quarterly summary of doses at the site boundary and exclusion area boundary for this report period, I

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SEMIANNUAL RA010ACT8VE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STA110N TABLE II-A GASECUS EFFLUENTS - SUMMATICN OF ALL RELEASES 3RD 4TH EST. TOTAL UNIT QUARTER QUARTER ERROR %

A. Fission and Activation Gases

1. Total release C1 2.66 E-02 8.25 E+02 1300 E+00

2. Average release rate for period pC1/sec 3.35 E-03 1.04 E+02

3. Percent of Tech. Spec.

limit  % 1.39 E-05 6.34 E-01 B. Iodines

1. Total lodine-131 Cl 1.04 E-04 2.05 E-03 1700 E+00

2. Average release rate for period pC1/see 1.31 E-05 2.57 E-04

3. Percent of Tech. Spec.

limit 7. 1.52 E-04 4.27 E-03 C. Particulates

1. Particulates with half-lives greater than 8 days Cl 6.39 E-05 8.21 E-04 1800 E+00

2. Average release rate for period pC1/sec 8.04 E-06 1.03 E-04

3. Percent of Tech. Spec. E limit  % 3.01 E-05 3.62 E-04 W

4. Gross alpha radio-activity Cl 2.22 E-07 6.53 E-07 3300 E+01

0. Tritium

1. Total release Cl 6.61 E+00 4.97 E+00 3700 E+00

2. Average release rate for period pC1/sec 3.32 E-01 6.25 E-01

3. Percent of Tech. Spec.

Ilmit 7. 5.21 E-03 5.60 E-03 l

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SEM! ANNUA.L RA010ACTZVE EFFLUENT RELEASE REPCRT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE II-B GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUCUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCL10ES RELEASED UN_I T QUARTER OUARTER QUARTER QUARTER

1. Fission Gases Krypton-85 C1 1.99 E-01 Krypton-85m Cl 4.76 E-01 6.15 E-05 Krypton-88 Cl 2.89 E-04 I

Xenon-133 Cl 2.56 E+02 2.66 E-02 5.48 E+02 Xenon-135 Cl 9.71 E+00 5.34 E-01 Xenon-135m Cl 3.73 E-04 Ary,n-41 Cl

• 2.17 E-02 Xenon-133m Cl 9.58 E-01 3.32 E+00 5.99 E+00 Xenon-131m Cl _

TOTAL FOR PERIOD Cl 2.67 E+02 2.66 E-02 5.58 E+02

2. Iodines Iodine-131 Cl 1.86 E-04 1.04 E-04 1.86 E-03 lodine-133 Cl 4.63 E-04 TOTAL FOR PERIOD Cl 1.86 E-04 1.04.E-04 2.32 E-03

3. Particulates Cesium-134 C1 1.89 E-04 I Ceslum-137 Cobalt-60 Cl C1 4.67 E-05 8.31 E-05 4.94 E-06 5.49 E-04 1.23 E-05

• TOTAL FOR PERICO C1 4.67 E-05 8.31 E-05 1,72 E-05 7.38 E-04

4. Tritium Cl 5.48 E+00 4.76 E+00 1.13 E+00 2.05 E-01 I 5. TOTAL VOLUME RELEASED cc 1.59 E-15 1.59 E-15 5.75 E+13 4.11 E+11

• Less than the Lower Limits of Detection, see Table II-C I

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SEMIANNUAL RAD 10AC QVE EFFLUENT RELEASE REPORT 3ULY-0ECEM5ER 1985 RANCHO SECO NUCLEAP GENERATING STATION TABLE II-C GASECUS EFFlufidS - LOWER LIMIT OF OETECTION CONTINUOUS AND BATCH MODE

• RADIONUCLIDES LLD (uC1/cc)

1. Fission Gases Argon-41 1.80 E-07 Krypton-85 1.65 E-05 Krypton-85m 7.53 E-08 Krypton-87 2.05 E-07 Krypton-88 2.25 E-07 Xenon-131m 2.61 E-06 l Xenon-133 n 5.01 E-07 5 Xenon-135m 1.12 E-06 Xenon-138 1.81 E-06 Xenon-133 1.52 E-07

2. Iodines Iodine-131 8.28 E-14 Iodine-133 2.91 E-12 Iodine-135 1.79 E-13

3. Particulates Barium-140 2.53 E-12 Cerium-141 6.82 E-13 Ceslum-134 7.54 E-13 Lanthanum-140 1.45 E-12 Nioblum-95 7.10 E-13 Strontium-89 5.00 E-15 Strontium-90 2.00 E-15 Telttum 6.22 E-10 Zleconlum-95 1.22 E-12

• Gas decay tank " Batch Mode" releases are through a " continuous mode" release path. ,

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f SEM! ANNUAL RA010ACTlV2 EFFLUENT RELEASE REPCRT JULY-0ECEMBER 1985 RANCHO SECO NU~ LEAR GENERATING STATION TABLE II-0 GASEOUS EFFLUENTS __- RADIATION 00SE ESTIMATES AT THE SITE AND EXCLUSION AREA BOUNDARIES SITE BOUNDARY EXCLUSION AREA MAXIMUM SECTOR. MAXIMUM SECTOR I Maximum Offsite A. 3RD 4TH 3RD 4TH Ground-level UNIT CUARTER QUARTER QUARTER CUARTER Location (a) (b) (c) (d)

1. a. Gamma Air Oose mead 5.32 E-06 3.61 E-01 6.75 E-06 3.88 E-01

b.  % Tech. Spec.  % 1.06 E-04 7.22 E+00 1.35 E-04 7.76 E+00 I 2. a.

b.

Beta Air Oose

% Tech. Spec.

mrad 1.58 E-05 1.00 E+00 1.58 E-04 1.00 E+01 2.01 E-05 1.13 E+00 2.01 E-04 1.13 E+01

3. a, Total Body mrem 3.35 E-03 2.58 E-01 1.23 E-02 2.76 E-01

b.  % Tech. Spec.  % N/A N/A N/A N/A

4. a. Skin mrem 3.95 E-03 6.55 E-01 1.45 E-02 7.04 E-01

b.  % Tech. Spec.  % 5.27 E-02 8.73 E+00 1.93 E-01 9.39 E+00

8. Tritium, Iodine, MAXIMUM RECEPTCR Particulate 3RD 4TH Unrestricted Areas UNIT CUARTER QUARTER All Pathways (e) (f)

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b.

Organ

% Tech. Spec.

mrem 3.66 E-02 2.41 E-01 4.88 E-01 3.21 E+00 C. Olrect Radiation

1. a. Oose mrem

• 4.76 E-01 6.74 E-01

b.  % Tech. Spec.  % N/A N/A NOTE: The above calculations were performed in accordance with the 00CM.

(a) North-northeast sector 670 meters.

(b) North-northwest sector 670 meters.

(c) East sector 640 meters (d) North-northwest sector 640 meters.

(e) Teenager thyrold.

I (f) Chlid thyrold.

4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> / week cccupancy time assumed I

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1 SEMIANNUAL RADICACHVE EFFLUENT RELEASL REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION II. GASEOUS EFFLUENTS Percent of Technical Specification Limits - Calculation Methodology The percent of Technical Specification Limit tabulated in Table II-A was determined by calculation of the following parameters:

Average Release x f x 100 g

% Technical Specification Limit = Rate Q 3 MPCeff The Average Release Rate . Total Curles released in each category per quarter Seconds per quarter 3 = The real time quarterly atmospheric dispersion for the appropriate Q quarter (sec/mJ). (Arithmetic average of the 16 sector values at the exclusion area boundary)

X/0 (sec/m3)

Iodine &

Tritium Noble Gas Particulate 1985 Quarter 3 1.252 E-05 1.249 E-05 1.158 E-05 1985 Quarter 4 1.792 E-05 1.789 E-05 1.657 E-05 The The MPCeff 15 defined as:

n g}

I l.1 MPC) l Where Fi- Fractional abundance of the ith radionuclide obtained by dividing the activity in curies for each radIonuclide Ct .

by the sum of all activities, C .t n- Total number of radioauclides identified MPCi- MPC of the Ith radionuclide (10 CFR 20, Appendix 0, Table

!!, Column 1)

The percent of Technical Specification Limit tabulated in Table II-0 is the percent of the appllCable dose limits of Table I-A.

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SEMIANNUAL RA080ACTlVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATICN III. LIQUID EFFLUENTS Table III-A " Liquid Effluents - Summation of All Releases," provides a detailed listing of liquid effluents released quarterly in three categories:

Fission and Activation Products Tritium 01ssolved and Entrained Gases Listed for each of three categories are:

Total Curles Released Average Olluted Concentration Percent of Technical Specification Limit Estimated Total Error.

In addition, Table III-A lists:

Gross alpha radioactivity released.

Volume of waste released prior to dilution.

Volume of dilution water added before release.

The methodology used to calculate the percent of Technical Specification Limit is presented at the end of this section.

The methodology used to calculate the estimated total error in Table

!!!-A is presented in Section V of this report.

I Table III-8, "Liculd Effluents," provides the sy<,tematic listing by radionuclide for the quantity of radioactivtty rtleased.

The total radioactivity of each radionuclide released in liquid effluent is listed for each quarterly period by batch mode release only. No k,nown radioactive liquid effluent releases are made on a continuous basis frcm Rancho Seco.

Table III-C, " Liquid Effluents - Lower Limit of Cetection," provides a listing of lower limit of detection concentrations as defined in Section 5.0 of the Offsite Oose Calculation Manual (page 197).

Table !!!-0, " Liquid Effluents" - Radiation Cose Estimates to the Mastmum Hypothetical Individual" provides a Qulrterly summary of the estimated I doses which would have been received by the " Hypothetical Individual" at the liquid $lte boundary location for this report period. Additional maximum doses to the " Hypothetical Individual" for altborne, direct, and noble gases cln be found in Section VI under "10 CFR 50 Append 14 I Requirements."

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SEMIANNUAL RADICACT8VE EFFLUENT RELEASE REPCRT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE III-A LIQUID EFFLUENTS - SUPMATION CF ALL RELEASES 3RD 4TH EST. TOTAL UNIT QUARTER OUARTER ERROR %

A. Fission and Activation Products

1. Total release (not including tritium, gases, alpha) C1 2.79 E-03 3.28 E-4 1700 E+00

2. Average diluted concentration during period pC1/mi 1.38 E-09 1.24 E-10

3. Percent of Tech. Spec. Ilmit  % 1.04 E-02 6.20 E-04

8. Tritium

1. Total release Cl 1.88 E+01 2.96 E+00 1800 E+00

2. Average diluted concentration during period pC1/ml S.35 E-06 1.12 E-06

3. Percent of Tech. Spec. Ilmit  % 3.12 E-01 3.73 E-02 C. Olssolved and entrained gases

1. Total release Cl *

• N/A

2. Average diluted concentration during period *

• pC1/ml

3. Percent of Tech. Spec, limit *

• t

0. Gross alpha radioactivity

1. Total release Cl 1600 E+00 E. Volume __ of was t_e released (prior to dilution) liters 1.78 E+07 9.19 E+06 1520 E+00 F. Volume of d_Ilution water used during period liters 2.02 E+09 2.65 E+09 1130 E+00

• Less than the Lower Limits of Detection, see Table !!I-C 11 I

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE III-8 LIQUID EFFLUENTS BATCH MCOE 3RD 4TH NUCLIOES RELEASM UNIT QUARTER OVARTER Cestum-134 C1 1.16 E-03 Ceslum-137 C1 1.63 E-03 3.28 E-04 Tritium Cl 1.88 E+01 2.96 E+00 TOTAL FOR PERIOD Cl 1.88 E+01 2.96 E+00 I

• Less than the Lower Limits of Detectioq of the Olstrict's environmental monitoring contractor I

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SEMIANNUAL RA080 ACTIVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABL E III-C LIQUID EFFLUENTS - LCHER LIMITS OF DETECTION RADIONUCLIOES BATCH MCOE (uCl/ml)

1. PARTICULATES Antimony-124 <4.44 E-08 Barium-140 <1.27 E-07 Cerium-141 <5.20 E-08 Cerium-144 <2.72 E-07 Ceslum-134 <4.82 E-08 Ceslum-136 <3.91 E-08 Ceslum-137 <5.92 E-08 l Chranium-51 <2.96 E-07 m Cobalt-57 <3.22 E-08 Cobalt-58 <4.23 E-08 Cobalt-60 <6.29 E-08 Iodine-131 <3.38 E-08 Iodine-133 <1.49 E-08 Iron-59 <7.92 E-08 Lanthanum-140 <4.33 E-08 Manganese-54 <3.82 E-08 Molybdenum-99 <2.28 E-09 Niobium-95 <4.50 E-08 Ruthenium-103 <3.92 E-08 Sodlum-24 <l.22 E-08 Strontium 89-90 <5.00 E-08 Technetium-99m <2.28 E-09 Zinc-65 <4.64 E-08

2. DISSOLVE 0 AND ENTRAINED CASES Krypton-85 <9.82 E-06 Krypton-85m <6.73 E-08 Krypton-88 <2.06 E-07 Xenon-131m <l.20 E-06 Xenon-133 <9.30 E-08 Xenon-133m <2.04 E-07 Xenon-135 <5.72 E-09 I

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE III-0 LIQUID EFFLUENTS - RADIATION 00SE ESTIMATES TO THE MAXIMUM HYPOTHETICAL INDIVIOUAL 3RD 4TH UNIT QUARTER QUARTER

1. a. Whole body dose (adult) mrem 2.37 E+00 1.79 E-01

b. Percent Tech. Spec. Limit  % 1,58 E+02 1.19 E+01

2. a. Organ dose (child liver) mrem 5.80 E+00 4.94 E-01

b. Percent Tech. Spec. Limit  % 1.16 E+02 9.88 E+00 I

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SEMIANNUAL RAD 10ACTlVE EFFLUENT RELEASE REPORT JULV-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION III. LIQUIO EFFLUENTS Percent of Technical Saecification Calculation Methodology The percent of Technical Specification Limit, tabulated in Table III-A was determined by calculation of the following parameters:

7. Technical Specification Limit = Average diluted x 100 concentration MPCeff Total curies released in each category per quart 2r converted The average diluted concentration - to pct Total volume released (Part F in Table III-A) converted to ml.

The The MPCerr is defined as:

n Ft I

11 MPC)

Where Fi- Fractional abundance of the Ith radionuclide obtained by dividing the activity in curies for each radienuclide C1 ,

by the sum of all activities, C t- '

n. Total number of radlonuclides identifled MPCi- MPC of the 1th radionuclide (10 CFR 20, Appendix B, Table II, Column 1)

The percent of Technical Specification Limit tabulated in Table III-0 is the percent of the appilcable dose limits of Table I-A.

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SEMfANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION IV. SOLID WASTE TABLE IV-A WASTE DISPOSAL

SUMMARY

Solid waste shipped offsite for burial or disposal (not irradlated fuel)

I 6 MONTH ESTIMATED

1. TYPE OF WASTE UNITS PERICO TOTAL ERROR 1

a. Spent resins, filter sludges, m3 4.10 E+02 evaporator bottoms, etc.(l) Cl 8.28 E+02 3.0 E+01

b. Dry Compressible waste, con- m3 3.34 E+02 taminated equipment, etc.(2) C1 4.71 E+02 3.0 E+01

c. Irradiated components, m3 *

• control rods, etc. Cl I d. Other .

• m3 Cl

• Not applicable I (I) Material solidified in concrete when required and shipped in LSA containers.

(2) Material shipped in LSA containers.

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SEMEANNUAL RA080ACT1VE EFFLUENT RELEASE REPORT JULV-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION

2. Estimate of major radionuclide composition (by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

Radionuclide Percent Cs-137 4.28 E+01 Fe-55 1.80 E+01 Ni-63 1.16 E+01 g Cs-134 1.34 E+01 3 Co-60 7.34 E+00 H-3 6.02 E+00 Co-58 5.90 E-01 Ag-110m 2.50 E-01 Cr-51 3.00 E-02 TOTAL 7.

ACCOUNTED 1.00 E+02

2. Estimate of radionuclide composition (by type of waste)

a. Dry compressible waste, contaminated equipment, etc.

Radionuclide Percent Co-58 3.58 E+01 Fe-55 2.07 E+01 Ag-110m 1.37 E+01 N1-63 1.30 E+01 Co-60 8.06 E+00 Cr-51 6.69 E+00 H-3 1.45 E+00 Cs-137 5.40 E-01 Cs-134 4.00 E-02 Mn-54 3.00 E-02 TOTAL 7.

ACCOUNTED 1.00 E+02

2. Estimate of radionuclide composition (by type of waste)

c. Irradiated components, control rods, etc.

Radionuclide Percent

• Not applicable I

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION

2. Estimate of radionuclide composition (by type of waste)

d. Other Radionuclide Percent

• Not applicable 1 3. Solid Waste Disposition During the period of July through December 1985, fifty-seven (57) shipments of radioactive waste were made by " sole use" vehicles to the Richland, Washington Hanford disposal site.

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SEMEANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE IV-B RAD WASTE SHIPMENT VOLUMES BY TYPE All volumes recorded in Cubic Feet (f t3)

GENERATE 0:

SEC. PRIMARY EVAP. FILTER ENCAP TOTAL 3

MONTH RESIN RESIN SOXES BARRELS BOTTOMS July 0.0 0.0 0.0 405.0 0.0 0.0 405.0 August 0.0 0.0 103.0 600.0 200.0 0.0 903.0 September 200.0 178.0 1,701.0 540.0 600.0 0.0 3,219.0 October 200.0 534.0 1,078.0 547.5 1,000.0 0.0 3,359.5 November 200.0 178.0 230.0 165.0 3,800.0 126.0 4,699.0 December 1,200.0 0.0 515.0 255.0 4,200.0 378.0 6,548.0 TOTAL 1,800.0 1,890.0 3,627.0 2,512.5 9,800.0 504.0 19,133.5 All volumes recorded in Cubic Feet (ft3 )

SHIPPEO:

SEC. PRIMARY EVAP. FILTER MONTH RESIN RESIN BOXES BARRELS BOTTOMS ENCAP TOTAL July 0.0 0.0 0.0 1,110.0 0.0 0.0 1,110.0 August 2,400.0 0.0 0.0 0.0 0.0 0.0 2,400.0 September 200.0 178.0 0.0 1,380.0 600.0 0.0 2,358.0 October 0.0 534.0 1,957.0 2,070.0 0.0 0.0 4,561.0 November 400.0 178.0 1,246.0 1,451.1 2,800.0 126.0 6,201.1 December 1,200.0 0.0 1,689.0 390.0 6,000.0 378.0 9,657.0 TOTAL 4,200.0 890.0 4,892.0 6,401.1 9,400.0 504.0 26,287.1 Inventory Change: -7,153.6 ft3 I

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r SEM1 ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT l

JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERRCR I The estimate of error is based on combination of the following error estimates:

A. Airborne

1. counting error

2. calibration error of exhaust fans I 3.

4.

sample train flow rate meter error process monitor flow rate setpoint error

5. charcoal cartridge efficiency 6 tritium bubbler collection efficiency

7. loss due to handling (for particulates)

8. Haste Gas Decay Tank (WGOT) pressure gauge and flow rate meter errors B. Liquid

1. counting error

2. Regenerant Hold Up Tank (RHUT) release volume error

3. retention basin dilution error

4. retention basin outlet flow error

5. flow rate error of discharge canal The following error estimates were considered, found to be negligible, and therefore were not considered in the error analysis:

1. Marinelli flask volume

2. sample mixing I 3.

4.

5.

particulate filter loss loss due to handling for lodine composite allquots for liquids Error estimates for anisokinetic sampling and airborne particulate plateout in monitor sample lines were not included because no plant data exist on the subject. However, this does not necessarily mean the errors are negilgible.

The methods for establishing error estimates included communication with Olstrict health physics / chemistry personnel, review of applicable station procedures, inspection of sampling equipment, review of previous District error analysis data, engineering estimates, statistical applications, literature reviews, and use of calibration set points data.

In determining the overall error in a release, error at one standard deviation I and a bias were calculated. The error consists of random or indeterminate errors. Blas is influenced primarily by determinate errors which introduce a constant error into the data.

The error analysis was applied to the following release pathways.

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SEMIANNUAL RAD 10ACTlVE EFFLUENT RELEASE REPORT JULV-DECEMSER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERRCR I

1. Auxiliary Building Vent (see note)

a. fission and activation gases

b. iodines

c. particulates

d. tritium

2. Haste Gas Decay Tank (HGDT)

a. fission and activation gases

b. tritium

3. Reactor Building Vent

a. fission and activation gases

b. iodines

c. particulates

d. tritium

4. Liquid Releases Includes the total error analysis for the RHUT to retention basin to discharge canal flow path.

It should be noted that the error analysis for lodines and particulates that are released through the reactor building vent includes exhaust fan calibration error, not containment volume error. This is because todines and particulates are vented on a continuous basis by the exhaust fan via a pre-filter, HEPA filter and charcoal cartridge. Also, error analysis for l

fission and activation gases and tritium that are released through the reactor l building vent includes containment volume error, not exhaust fan calibration

! error. This is because fission and activation gases and tritium are released is a function of containment volume.

I Note: includes releases from the condenser air ejector, gland seal exhaust, and iodines and particulates from the HGDT.

The Radwaste Service Area Vent was not included as a release pathway due to its inoperability.

i The error for both airborne and 11guld releases was determined at one standard deviation from the mean.

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR I A. ERROR ANALYSIS FOR AIRSORNE RELEASES

1. AUXILIARY BUILDING STACK

a. Fission and Activation Gases Error 2 (o2 . 7,72 )l/2 1 3.3% calibration error of exhaust fans 2 6.9% process monitor flow rate setpoint error margin (3.3 2 + 6.92 >1/2 . 7,7 o counting error - (gross counts)-1/2 x 100

b. Iodine Error 2 (o2 + 3.82)1/2 2 3.3% calibration error of exhaust fans i 1.9% process monitor flow rate setpoint error margin (3.3 2 , 1,92)1/2 - 3.8 o counting error - (gross counts)-1/2 x 100 Blas: -5% not collected by charcoal cartridge

c. Particulates Error 2 (o2 + 3.82 )l/2 Error is same as Iodine (auxiliary stack)

Blas: -5% handling loss

d. Tritium Error 2 (o2 + 22)1/2 2 2% sample flow rate meter reading error o counting error - (gross counts)-1/2 x 100 Blas: +5% collection efficiency

• I *Available literature indicates the collection loss is approximately 5% for fritted bubblers of the type used at Rancho Seco. Rancho Seco uses a collection efficiency of 90%. Therefore, the actual bias is +5"..

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SEMEANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR I

2. WASTE GAS DECAY TANK

a. Fission and Activation Gases Error 3 (o2 + 2.82 )l/2 1 2% calibration and reading error of WGDT pressure gauge 1 2% calibration and reading error of WGDT flow rate meter (2 2 + 22 )l/2 - 2.8 o counting error - (gross counts)-1/2 x 100

b. Tritium Error 1 (o2 + 2.82 )l/2 1 2% reading error of sample flow rate meter 1 2% reading and calibration error of WGDT flow rate meter (2 2 + 22 )l/2 - 2.8 o counting error - (gross counts)-1/2 x 100 Bias: +5% collection efficiency error (see auxiliary building vent tritium analysis)

3. REACTOR BUILDING VENT

a. Fission and Activation Gases Error 2 (o2 +.6.52 )l/2 2 5% containment volume error 1 4.2% process monitor flow rate setpoint error margin (5 2 , 4.2 2>1/2 - 6.5 o counting error - (gross counts)-1/2 x 100 Bias: -5% incomplete purge A Purge is a batch removal of Reactor Building air by the a Reactor Building purge exhaust fan which discharges to the 5 vent. The -5% bias was chosen as a reasonable value for representing an estimate of inccmplete purge.

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATICN OF ERROR E Iodines Error

b. 1 (o2 + 3.62 )l/2 1 3.3% calibration error of exhaust fans i 1.4% process monitor flow rate setpoint error margin (3.3 2 . 1,4 2)l/2 = 3.6 o counting error - (gross counts)-1/2 x 100 Bias: -5% not collected by charcoal

c. Particulates Error 3 (o2 + 3.62 )l/2 Error is same as for Iodines (Reactor Building)

Bias: -5% handling loss

d. Tritium Error 1 (o2 + 5.42)1/2 2 5% containment volume error 1 2% flow rate meter error (5 2 + 22 )l/2 - 5.4 o counting error - (gross counts)-1/2 x 100 Blas: +5% collection efficiency (see auxiliary building vent tritium analysis)

-5% incomplete purge

8. ERROR ANALYSIS FOR LIQUID RELEASES

1. Liquid Effluent Release Error 2 (o2 + 5.42 )l/2

a. RHUT 2 5% RHUT Volume o counting error = (gross counts)-1/2 x 100 I

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i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR

b. Retention Basin I

t 1% inlet dilution volume error 3 1% outlet f. low error l

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c. Oilution Flow t 1.3% discharge canal flow rate error Total Error (52.12,1 2 + 1.32 )l/2 - 5.4 I

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-A COMPLIANCE WITH 10 CFR 50 APPENDIX I Quarterly Maximum Dose to an Individual Dose (millirems)

SOURCE 3RD QUARTER 4TH QUARTER A. Liquid Effluents

1. whole body (adult) 1) 2.37 E+00 2) 1.79 E-01

2. organ (child liver) 3) 5.80 E+00 4) 4.94 E-01 I

B. Gaseous Effluents

1. tritium, lodines, 5) 3.66 E-02 6) 2.41 E-01 and particulates I 2. Noble Gases

a. gamma (mrad) 7) 6.75 E-06 8) 3.88 E-01

b. beta (mrad) 9) 2.01 E-05 10) 1.13 E+00 l C. Direct Radiation 11) 4.76 E-01 12) 6.74 E-01 Note Items 1 through 10 were calculated inaccordance with the ODCM. Items 11 7

and 12 are based on data in Table VI-C of this report. An occupancy time of four hours per week is assumed.

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-B -

COMPLIANCE WITH 10 CFR 50 APPENDIX I REQUIREMENTS Percent of Technical Specification Limits for Table VI-A Percent (7.)

SOURCE 3RD QUARTER 4TH QUARTER A. Liquid Effluents

1. whole body 1.58 E+02 1.19 E+01

2. organ 1.16 E+02 9.88 E+00 B. Gaseous Effluents

1. tritium, lodines, 4.88 E-01 3.21 E+00 and particulates

2. Noble Gases'

a. gamma . 1.35 E-04 7.7s E+00 4

b. beta 2.01 E-04 1.13 E+01

> C. Direct Radiatio 3 N/A N/A I

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SEMIANNUAL RADICACTZVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-C THERM 0 LUMINESCENT DOSIMETER RESULTS THIRD QUARTER FOURTH QUARTER LOCA- TOTAL EXPOSURE TOTAL EXPOSURE TION DISTANCE DIREC- EXPOSURE RATE EXPOSURE RATE NO. (miles) TION LOCA' TION DESCRIPTION (mrem) (uR/hr) (mrem) (uR/hr) 1 -

N Perimeter Fence 18.3 8.3 21.9 8.9 2 -

E Perimeter Fence 12.3 5.6 17.0 6.9 3 -

W Perimeter Fence 38.2 17.3 46.6 19.0 I 4 5

SW SE Perimeter Fence Perimeter Fence 25.5 14.0 11.6 6.4 24.4 17.2 10.0 7.0 6 Visitors Center 11.8 5.3 13.8 5.9 7 route 104 Entrance 13.6 6.2 11 4.6 8 6 NW 12.9 5.8 11.9 5.0 9 22 NE SMUD Headquarters 13.5 6.1 11.5 4.8 10 17 SW Lodi 16.8 7.6 16.3 6.7 11 0.25 S 11.9 5.4 12.9 5.4 12 11 E Ione 13.0 5.9 11.2 4.6 West Milk Station 10.6 4.8 13.4 5.4 I 13 10 W 14 11 SW Galt 14.1 6.4 16.0 6.4 15 11 SW Camanche Reservoir 12.2 5.6 15.0 6.2 16 0.5 W Clay 13.0 5.9 12.8 5.4 17 9 SW Southwest Milk Station 14.9 6.8 17.9 7.5 18 8 NE 10.3 4.6 15.8 6.3 19 1 SE 11.6 5.3 12.6 5.3 20 1.5 WSW 11.2 5.1 10.6 4.5 21 1.7 SW 14.8 6.7 11.6 4.9 22 1.8 S 12.6 5.7 13.5 5.4 23 1.8 SSW 19.2 8.7 11.2 4.7 24 1.8 SSE 10.5 4.8 14.0 5.7 25 3.8 SW 14.5 6.6 12.2 5.1 26 3.9 SSW 13.2 6.0 13.2 5.6 27 3.6 S 10.8 4.9 10.6 4.5 I

SEM1 ANNUAL RAD 10 ACTIVE EFFLUENT R2 LEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-C (contd.)

THERM 0 LUMINESCENT DOSIMETER RESULTS THIR0 QUARTER FOURTH QUARTER LOCA- TOTAL EXPOSURE TOTAL EXPOSURE TION DISTANCE DIREC- EXPOSURE RATE EXPOSURE RATE NO. (miles) TION LOCATION DESCRIPTION (mrem) (uR/hr) (mrem) (uR/hr) 28 3.7 SSE 12.2 5.5 missing 29 4.2 S 10.2 4.6 11.0 4.6 30 7.4 WSW Herald Fire Station 13.3 6.0 18.3 7.6 31 3.7 W 14.8 6.7 missing 32 4.8 WNW 12.9 5.8 12.0 5.0 33 3.8 WSW 12.8 5.8 missing 34 3.8 NW 12.4 5.6 11.9 4.9 35 1.9 W 14.1 8.7 14.4 6.2 36 1.6 WNW 13.5 6.1 11.6 5.0 37 1.9 NW 15.2 6.9 15.7 6.4 38 1.6 NNW 13.5 6.1 17.4 7.2 39 1.5 NNE 13.0 5.9 15.5 6.3 40 1.5 N 12.9 5.8 13.8 5.6 g 41 2.0 NE 18.5 8.4 25.6 10.3 5 42 4.4 SE 13.4 6.1 12.6 5.3 43 1.6 SE 10.0 4.5 9.4 4.0 44 1.4 E 9.6 4.4 12.1 5.1 45 1.4 ESE 10.8 4.9 11.2 4.7 46 1.3 ENE 16.3 7.4 15.9 6.7 47 3 NE 13.6 6.1 15.4 6.3 48 3.5 ENE 14.6 6.6 15.9 6.5 49 3.1 E 12.7 5.7 15.1 6.2 50 3.5 ESE 14.9 6.8 17.5 7.2 51 11 E Preston Sch, of Industry 11.6 5.3 11.1 4.6 52 19 E Jackson Civic Center 27.1 12.3 21.2 8.8 53 11 SE Camanche Reservoir 19.3 8.7 17.3 7.1 54 10 S Clements 16.4 7.4 19.4 8.0 I

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-C (contd.)

THERM 0 LUMINESCENT COSIMETER RESULTS THIRD QUARTER FOURTH QUARTER LOCA- TOTAL EXPOSURE TOTAL EXPOSURE TION DISTANCE DIREC- EXPOSURE RATE EXPOSURE RATE NO. (miles) TION LOCATION DESCRIPTION (mrem) (uR/hr) (mrem) (uR/hr) 55 8 'lNW Dillard School missing 14.4 5.8 56 4.6 NNW 12.8 5.8 13.9 5.7 57 7.6 N 12.1 5.5 11.8 4.9 58 6.6 NNE missing 12.8 5.3 59 11.3 NNW Sloughbouse Post Office 12.8 5.8 14.6 6.0 60 10.6 N Rancho Murieta 12.6 5.7 13.2 5.4 61 13 WNW Elk Grove Cemetery 12.0 5.4 12.5 5.3 62 11 SW Galt 13.0 5.9 missing 63 1 E 11.7 5.3 16.6 7.0 I

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SEMIANNUAL RADI0ACTlVE EFFLUEdi RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-E RADIOLOGICAL IMPACT - GAS PATHWAY THIRO QUARTER NEAREST HOUSE S 6492 METERS (MREM)

I PATHWAY T.80Dv GI-TRACT 80NE L!vER x!DNEY THvROIO LUNG SAIN PLUME 2.2tE-08 2.21E-08 2.21E-08 2.21E-08 2.21E-08 2.2tE-C8 2.32E-08 6.23E-08 GROUNO 6.94E-0o 6.94E-C6 6.94E-06 6.94E-06 6.94E-06 6.94E-06 6.94E-06 8.16E-06 INHAL ADULT 2.73E-05 2.73E-05 f.68E-08 2.73E-05 2.73E-05 3.17E-05 2.82E-05 2.73E-05 TEEN 2.75E-05 2.75E-05 2.35E-08 2.75E-05 2.75E-05 3.29E-05 2.87E-05 2.74E-05 CHILO 2.43E-05 2.43E-05 3.19E-08 2.43E-05 2.43E-05 3.03E-05 2.53E-05 2.43E-05 I TOTAL INFANT 1.40E-05 1.40E-05 2.26E-08 f.40E-05 1.40E-05 1.95E-05 1.46E-05 1.40E-05 ADULT TEEN 3.43E-05 3.43E-05 6.98E-06 3.43E-05 3.43E-05 3.87E-05 3.52E-05 3.55E-05

.HILO 3.45E-05 3.45E-05 6.99E-06 3.45E-05 3.45E-05 3.99E-05 3.57E-05 3.56E-05 3.13E-05 3.13E-05 6.99E-06 3.13E-05 3.13E-05 3.73E-05 3.23E-05 3.25E-05 INFANT 2.10E-05 2.10E-C5 6.98E-06 2.10E-05 2.1CE-05 2.65E-05 2.16E-05 2.22E-05 NEAREST HOUSE SSW 3718 METERS (MREM)

PATHwAv T.800v GI-TRACT BONE LIVER dIONEY THvROIO LONG SKIN I PLUME GR0uNO 4.54E-08 4.54E-08 4.54E-08 4.54F-08 4.54E-08 4.54E-08-4.77E-08 1.28E-07 INHAL t.81E-05 1.81E-05 f.8tE-05 f.8tE-05 1.81E-05 1.81E-05 1.81E-05 2.13E-05 ADULT 6.63E-05 6.63E-05 3.59E-08 6.63E-05 6.63E-05 7.56E-05 6.85E-05 6.62E-05 TEEN 6.67E-05 6.67E-05 5.03E-08 6.67E-05 6.67E-05 7.81E-05 7.COE-05 6.66E-05 CHILO 5.90E-05 5.90E-05 6.82E-08 5.90E-05 5.90E-05 7.17E-05 6.16E-05 5.89E-05 INFANT 3.39E-05 3.39E-05 4.82E-08 3.39E-05 3.39E-05 4.55E-05 3.58E-05 3.39E-05 I TOTAL ADULT TEEN CHILO 8.44E-05 8.44E-05 1.82E-05 9.44E-05 8.44E-05 9.37E-05 8.66E-05 8.76E-05 8.48E-05 8.48E-05 1.82E-05 8.48E-05 8.48E-05 9.62E-05 8.8TE-05 8.80E-05 7.7tE-05 7.71E-05 1.82E-05 7.7tE-05 7.71E-05 8.98E-05 1.97E-05 8.03E-05 INFANT 5.20E-05 5.20E-05 1.82E-05 5.20E-05 5.20E-05 6.37E-05 5.37E-05 5.53E-05 I

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SEM1 ANNUAL RADICACTEVE EFFLUENT RELEASE REPCRT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-E RADIOLOGICAL IMPACT - GAS PATHWAY THIRD QUARTER NEAREST HOUSE SW 1219 METERS (MREM)

PATHaAv T.800v GI-TRACT 80NE L!vER n10NEY THvR010 LUNG SKIN PLUME 6.78E-07 6.78E-07 6.78E-07 6.78E-07 6.78E-07 6.78E-07 7.12E-07 1.91E-06 GROUNO 3.64E-04 3.64E-04 3.64E-04 3.64E-04 3.64E-04 3.64E-04 3.64E-04 4.28E-04

[NHAL AOutT 1.01E-03 1.01E-03 5.68E-07 1.01E-03 1.01E-03 1.16E-03 t.05E-03 1.01E-03 TEEN 1.02E-03 1.02E-03 7.97E-07 1.02E-03 1.02E-03 1.19E-03 1.07E-03 1.02E-03 CHILO 8.99E-04 8.99E-04 1.08E-06 9.0CE-04 9.00E-04 1.10E-03 9.44E-04 8.99E-04

[NFANT 5.17E-04 5.17E-04 7.61E-07 5.18E-04 5.17E-04 6.97E-04 5.45E-04 5.17E-04 TOTAL AcutT 1.38E-03 1.38E-03 3.65E-04 1.38E-03 1.38E-03 1.53E-03 1.41E-03 1.38E-03 TEEN 1.39E-03 1.39E-03 3.65E-04 1.39E-03 1.39E-03 1.55E-03 1.43E-03 1.39E-03 CHELO t.26E-03 1.26E-03 3.66E-04 1.27E-03 1.27E-03 1.46E-03 1.31E-03 1.27E-03 INFANT 8.82E-04 8.82E-04 3.65E-04 8.83E-04 8.83E-04 1.06E-03 9.10E-04 8.83E-04 11 NEAREST HOUSE wSW 2103 METERS (MREM)

PATM*Av r.500v GI-TRACT 80NE LIVER KIONEY THvROIO LUNG SAIN PLUME 1 04E-07 1.04E-07 1. 04E -07 1.04E-07 1.04E-07 1.04E-07 1.09E-07 2.93E-07 GRouNO 5 48E-05 5.48E-05 5.485-05 5.48E-05 5.48E-05 5.48E.05 5.48E-05 6.45E-05 5 INHAL ADULT 1.88E-04 t.89E-04 8.f0E-08 1.88E-04 1.88E-04 2.10E-04 1.95E-04 f.88E-04 TEEN 1.89E-04 1.90E-04 1.19E-07 1.90E-04 1.90E-04 2.16E-04 1.99E-04 1.89E-04 CHILO t.68E-04 1.68E-04 ' .62E-07 1.68E-04 1.68E-04 1.97E-04 1.75E-04 1.67E-04 INFANT 9.64E-05 9.63E-05 i .14E-0 7 9.64E-05 9.64E-05 1.24E-04 1.01E-04 9.63E-05 TOTAL AOutT 2.43E-04 J.44E-04 5.50E-05 2.43E-04 2.43E-04 2.65E-04 2.50E-04 2.43E-04 TEEN 2.44E-04 2.4SC-04 5.50E-05 2.45E-04 2.45E-04 2.7tE-04 2.54E-04 2.44E-04 CHILO 2.23E-04 2.23E-04 5.51E-05 2.23E-04 2.23E-04 2.52E-04 2.30E-04 2.22E-04 INFANT 1.5tE-04 1.51E-04 5.50E-05 1.5tE-04 f.StE-04 1.79E-04 1.56E-04 1.51E-04 11 II ll

SEMTANNUAL RA010ACTEVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-E RADIOLOGICAL IMPACT - GAS PATHWAY THIRD QUARTER NEAREST MOUSE w 3414 METERS (MREM)

PATMwAv T.800v GI-TRACT BONE LIVER KIONEY TMvR0!O LUNG SAIN PLUME 3.15E-08 3.15E-08 3.'5E-08 3.15E-08 3.15E-08 3.15E-08 3.3tE-08 8.88E-08 GRouho 1.10E-05 1.10E-05 1.10E-05 1.10E-05 t. TOE-05 1.10E-05 1.10E-OS 1.30E-05 INMAL A0uti 4.02E-05 4.03E-05 2.50E-08 4.02E-C5 4.02E-05 4.67E-05 4.16E-05 4.02E-C5 TEEN 4.05E-05 4.05E-05 3.5tE-08 4.05E-05 4.05E-05 4.84E-05 4.25E-05 4.04E-05 I CMILO 3.58E-05 3.58E-05 4.76E-08 3.58E-05 3.58E-05 4.46E-05 3.74E-05 3.58E-05 INFANT 2.06E-05 2.06E-05 3.36E-00 2.066-05 2.06E-05 2.87E-05 2.16E-05 2.06E-05 TOTAL ADULT 5.12E-05 5.13E-05 1.ItE-05 5.12E-05 5.12E-05 5.77E-05 5.26E-05 5.33E-05 TEEN 5.15E-05 5.15E-05 1.11E-05 5.15E-05 5.15E-05 5.94E-05 5.35E-05 5.35E-05 CMILO 4.686-05 4.68E-05 1.1tE-05 4.68E-05 4.68E-05 5.56E-05 4.84E-05 4.89E-05 INFANT 3.16E-05 3.16E-05 1.11E-05 3.16E-05 3.16E-05 3.97E-05 3.26E-05 3.37E-05 I

NEAREST NOUSE wNw 4389 METERS (MREM)

PA?MwAv T.800v GI-TRACT 8CNE LIVER K!DNEY TMvR010 LuhG SAIN PLUME 1.58E-08 1.58E-08 1.58E-08 1.58E-08 1.58E-08 1.58E-06 1.66E-08 4.45E-08 GROUND 1.20E-05 1.20E-05 1.20E-05 1.20E-05 1.20E-05 1.20E-05 1.20E-05 1.4tE-05

!NMAL ADULT 3.84E-05 3.85E-05 1.23E-08 3.84E-05 3.84E-05 4.16E-05 3.97E-05 3.84E-05 TEEN 3.87E-05 3.87E-05 1.73E-08 3.87E-05 3.87E-05 4.26E-05 4.05E-05 3.86E-05 CHILO 3.42E-05 3.42E-05 2.34E-08 3.42E-05 3.42E-05 3.86E-05 3.57E-05 3.42E-05

!NSANT 1.97E-05 1.97E-05 1.66E-08 1.97E-05 1.97E-05 2.37E-05 2.06E-05 1.96E-05 I TCTAL A0 ULT TEEN CMILO 5.04E-05 5.05E-05 1.20E-05 5.04E-05 5.04E-05 5.36E-05 5.17E-05 5.2SE-05 5.07E-05 5.07E-05 1.20E-05 5.07E-05 5.07E-05 5.46E-05 5.25E-05 5.27E-05 4.62E-05 4.62E-05 1.20E-05 4.62E-05 4.62E-05 5.06E-05 4.77E-05 4.83E-05

!NFANT 3.17E-05 3.17E-05 1.20E-05 3.17E-05 3.17E-05 3.57E-05 3.2EE-05 3.37E-05 E

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SEMIANNUAL RAD 10ACT1VE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-E RADIOLOGICAL IMPACT - GAS PATHWAY THIRD QUARTER NEAREST HOUSE Nw 5334 METERS (MREM)

PATMwAv T.BOOV GI-TRACT BONE LIVER A[0NEY THvR0!D LUNG SAIN PLUME 1.42E-08 1.42E-08 1.42E-08 1.42E-08 1.42E-08 1.42E-08 1.43E-08 4.0tE-08 GRouNO 1.27E-05 1.27E-05 1.27E-05 1.27E-C5 1.275-05 1.27E-05 1.27E-05 1.50E-05 INMAL Acuti 4.47E-05 4.48E-05 1.09E-08 4.47E-05 4.47E-05 4.76E-05 4.62E-05 4.47E-05 TEEN 4.50E-05 4.51E-05 1.54E-08 4.50E-05 4.50E-05 4.85E-05 4.71E-05 4.50E-05 CHILO 3.98E-05 3.98E-05 2.08E-08 3.98E-05 3.98E-05 4.37E-05 4.15E-C5 3.98E-05

[NFANT 2.29E-05 2.29E-05 1.47E-08 2.29E-05 2.295-05 2.65E-05 2.40E-05 2.29E-05 TOTAL AOULT 5.74E-05 5.75E-05 1.27E-05 5.74E-05 5.74E-05 6.03E-C5 5.89E-05 5.97E-05 TEEN 5.77E-05 5.78E-05 1.27E-05 5.77E-05 5.77E-05 6.t25-C5 5.98E-05 6.00E-05 CHILO 5.2SE-05 5.25E-05 1.27E-05 5.25E-05 5.25E-05 5.64E-05 5.42E-05 5.48E-05 INFANT 3.56E-05 3.56E-05 f.27E-05 3.56E-05 3.56E-05 3.92E-05 3.67E-05 3.79E-05 11 NEAREST house NNd 7254 METERS (MAEM)

PATHaAv T.800v GI-TRACT BONE L!vER K!ONEY THvA0!O LUNG Sd!N PLUME 2.83E-08 2.83E-08 2.83E-08 2.83E-08 2.83E-08 2.83E-08 2.97E-08 7.98E-08 GA0uNO 1.44E-05 1.44E-05 1.44E-05 1.44E-05 1.44E-05 1.44E-05 1.44E-05 1.70E-05

[NHAL AOULT 4.64E-05 4.65E-05 2.12E-08 4.64E-05 4.64E-05 5.20E-05 4.79E-05 4.64E-35 TEEN 4.67E-05 4.68E-05 2.98E-08 4.67E-05 4.67E-05 5.36E-C5 4.89E-05 4.67E-05 CHILO 4.13E-05 4.13E-05 4.04E-08 4.13E-05 4.13E-05 4.90E-05 4.30E-05 4.t3E-05 IN5 ANT 2.38E-05 2.38E-05 2.86E-08 2.38E-05 2.38E-05 3.C8E-05 2.43E-05 2.37E-05 TOfAL ADutT 6.08E-05 6.C9E-05 1.44E-05 6.08E-05 6.08E-05 6.64E-05 6.23E-05 6.35E-05 W TEEN 6.11E-05 6.12E-05 1.44E-05 6.11E-05 6.1tE-05 6.80E-05 6.33E-05 6.38E-05 LMILO 5.57E-05 5.57E-05 1.44E-05 5.57E-05 5.57E-05 6.34E-05 5.74E-03 5.84E-05 INFANT 3.62E-05 3.82E-05 1.44E-05 3.82E-05 3.82E-OS 4.525-05 3.93E-05 4.08E-05 11 ll h.... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 )

RANCHO SECO NUCLEAR GENERATING STATION  !

TABLE VI-G RADIOLCGICAL IMPACT _ LIQUID PATHWAY THIRD QUARTER M.AXIMUM ADCL! (MREM)

PATHWAY SK !1 3CNE LIVER  !.300Y TRYROID K!DNEY  :.*JNG GI-L*

7:5H 0.0 1.24E+00 2.14E+00 1.58E+00 7.73E-03 7.16E-01 2.43E-0; 4.72E-02

NVIR 0.0 2.52E-03 4.58E-03 3.42E-03 2.22E-04 1.67E-03 ?.02E-04 3.03E-04 WATER 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SECRE 7.26E-02 7.94:'-02 7.34E-02 7.94E-02 7.34E-02 7.94E-02 7.94E-02 7.34E-02 SW:M 0.0 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 VEG 0.0 2.83E-01 6.10E-01 4.SOE-01 1.26E-01 2.87E-01 1.79E-01 1.35E-01 I MILK MEAT TOTAL 0.0 0.0 1.18E-01 2.36E-01 1.82E-01 3.42E-02 1.0LE-01 5.65E-02 3.79E-02 1.44E-02 5.13E-02 4.47E-02 2.67E-02 3.4)E-02 2.34I-02 2.72E-32 3.26E-02 1.74E+00 3.12E*00 2 . 3 7 T., + 0 0 2.74E-01 1.22E+00 5.88E-01 3.27E-01 I

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SEtiIANNUAL 4ADICACTKVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANC'0 SEC0 NUCLEAR GENERATING STATION TABLE VI-G RADIOLCGICAL IMPACT - LICUID PATHWAY THIRD QUARTER

, MAXIMCM TEENACER (MREM)

PATH

• DAY SKIN BCNE LIVER T.3CDY THYRCIO K!:NEY LONG G -LL:

T:SH 0.0 1.03E+00 1.73E+00 7.03E-0. 4.*i5-03 5.742-31 2.24E-01 2.78E-02 INVERT 0.0 3.43E-03 6.10E-03 2.60E-03 2.24I-04 2.'6E-03 9.71E-04 3.03E-04 WATER 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SECRE 9.26E-03 7.94E-03 7.34E-03 7.94E-03 7.34E-03 7.94E-03 7.34E-33 7.94E-03 SW:M 0.0 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 7EG 0.0 4.75E-01 9.46E-01 4.72E-01 1.54E-01 4.15E-01 2.55E-01 1.65E-01 M :.K 0.0 2.10E-01 3.36E-01 1.86E-01 4.46E-02 L.6LE-01 8.33E-02 4.93E-02 g 0.0 1.18E-02 3.56E-02 2.38E-02 1.59E-02 2.24E-02 1.34E-02 1.62E-02 MEA,T E

TOTAL 9.26E-03 1.74E+00 3.12E*00 1.40E+00 2.27E-01 1.13E*00 5.96E-01 2.67E-01 I

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI__G_

I RADIOLOGICAL IMPACT _ LIQUID PATHWAY THIRD QUARTER max:x::x cs::.D <xaZx)

PATHWAY SKIN SONI :IVER T.30DY THYRO!D r. DNEY .CNG G -LL:

T:53 0.0 2.95E+00 3.5;I+00 6.30E-01 9.03E-03 1.12E+00 4.10E-31 2.)SE-32

'.' VERT 0.0 1.00E-02 1.23E-02 2.54E-03 4.30E-04 4.23E-03 1.77E-03 5.00E-34 WATEa 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SHORE 1. 3 0 E-0 3 1.11E-0 3 1.11E-0 3 1.11E-0 3 1.11E-0 3 1. i' E-0 3 1.11E-0 3 1.11I-3 3 SW:M 0.0 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 6.23E-05 VEG 0.0 1.13E*00 1.57E*00 4.77E-01 2.44E-01 6.67E-01 3.96E-01 2.51E-01 x:LK 0.0 5.00E-01 6.59E-01 1.74E-01 7.04E-02 2.58E-01 1.38E-01 7.39E-02 MEAT 0.0 2.14E-02 4.44E-02 2.37E-02 1.92E-02 2.73E-02 2.21E-02 1.74E-02 TOTA:. 1.30E-03 4.61E+00 5.80E+00 1.31E+00 3.44E-01 2.03E+00 9.63E-01 3.75E-01 I

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SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEM6ER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-G RADIOLOGICAL IMPACT - LIQUID PATHWAY THIRO QUARTER AVERAGE A0tLT (MREM)

PATHWAY SX:N 3CNE  :.IVER  !.300Y THYRO:0 K 0NEY L"NG C :-L:,:

F:SH 0.0 2.43E-03 4.22E-03 3.'1E-03 1.53E-05 1.41E-03 4.73E-04 9.23I-05

."v'ERT 0.0 2.52E-05 4.58E-05 3.42E-05 2.2:E-06 1.67E-05 7.02E-06 3.03E-0 ORINX 0.0 3.33E-05 1.08E-03 1.03E-03 9.14E-04 9.675-04 3.32I-04 3.'7Z-04 SECRE 7.68E-06 6.57E-06 6.53E-06 6.57E-36 6.59E-06 6.5)E-06 6.595-06 6.57E-06 SWIM 0.0 5.17E-08 5.17E-08 5.17E-08 5.17E-08 5.17I-08 5.17E-08 5.'75-38 80ATING 0.0 2.58E-08 2.58E-08 2.5SE-08 2.58E-08 2.58E-08 2.58E-08 2.58E-08 VEGE 0.0 1.02E-03 2.19E-03 1.73E-03 4.59E-04 1.03E-03 6.50E-04 4.10E-04 L VEGE 0.0 1.74E-04 3.715-04 2.32E-04 7.43E-05 1.735-04 1.37E-04 8.00E-05 MILX 0.0 4.19E-04 8.42E-04 6.48E-04 1.22E-04 3.60E-04 2.01E-04 1.35E-04 MEA

• 0.0 '.25E-04 4.46E-04 3.88E-04 2.32E-04 3.03E-04 2.55E-04 2.36E-04 TOTAL 7.68E-06 4.30E-03 7.20E-03 7.24E-03 1.32E-03 4.27E-03 2.63E-03 1.96E-03 I

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SEMZANNUAL RADICACTlVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-G RADIOLOGICAL IMPACT - LIQUID PATHWAY THIRD QUARTER AVERACE TEINAGER (MREM)

PATHWAT SKIN 3CNE LIVER  !.300Y THYROID K 0NEY LONG GI-LL:

I I': S H INVERT 0.0 0.0 2.54E-03 4.29E-03 1.74E-03 1.17E-05 1.42E-03 5.55E-04 6.39E-05 2.62E-05 4.58E-05 1.95E-05 1.68E-06 1.62E-05 7. 9E-06 2.27E-0 ORINK 0.0 9.07E-05 8.01E-04 7.10E-04 6.48E-04 5.99E-04 i.68E-04 6.50E-04 SECRI 4.35E-05 3.73E-05 3.73E-05 3.73E-05 3.73E-05 3.73E-05 3.73E-05 3 73E-05 SWIM 0.0 2.93E-07 2.93E-07 2.93!-07 2.93E-07 2.93E-07 2.93E-07 2.93E-07 3CA? NG 0.0 1.46E-07 1.46E-07 1.46E-07 L.46E-07 L.46E-07 1.46E-07 1.46E-07 VE0E 0.0 1.79E-03 3.54E-03 1.77E-03 3.85E-04 1.56E-03 9.59E-04 6.26E-04 L VIGE 0.0 1.60E-04 3.17E-04 1.57E-04 4.97E-05 ;.38E-04 8.39E-05 5.34E-05 I MILX MEAT TOTAL 0.0 0.0 1.05E-03 1.99E-03 9.32E-04 2.24E-04 8.04E-04 4.48E-04 2.47E-04 1.07E-04 3.25E-04 2.17E-04 1.46E-34 2.05E-04 1.68E-04 1.48E-04 4.35E-05 5.80E-03 1.13E-03 5.59E-03 1.70E-03 4.88E-03>2.93E-03 1.83E-03 I

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SEMIANNUAL RADICACTlVE EFFLUENT RELEASE REPORT JULY-0ECEMSER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-G RADIOLOGICAL IMPACT - LIQUID PATHWAY THIR0 QUARTER AvEaAcE cx::.o ( .v.a E.m PAnwAt 5x:n scNE :vra  :.acov ara 0:3 n0NEY  :.::xG G :-c.:. :

r:SH 0.0 3.09E-03 3.68E-03 6.53E-04 9.46E-06 1.18E-03 4.2)E-04 3.09E-05

.~/IRT 0.0 3.31E-05 4.07E-05 8.38E-06 1.42E-06 1.39E-05 5.92E-06 1.65E-0 ORINK 0.0 2.61E-04 1.55E-03 1.30E-03 1.24E-03 *..J4E-33 1.28E-03 1.24E-03 SHORE 8.79E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 ?.54E-06 7.54I-0E 7.54E-06 SW:.M 0.0 5.91E-08 5.91E-08 5.91E-08 5.91E-08 5.91E-08 5.91E-08 5.91E-08 30A;;NG 3.0 2.96E-08 2.96E-08 2.96E-08 2.96E-08 2.96Z-08 2.96E-08 2.96E-08 VEGE O1 4.30E-03 5.95E-03 1.81E-03 9.32E-04 2.53E-03 1.51E-03 9.63E-04

. VIOE 0.0 2.31E-04 3.18E-04 9.58E-05 4.77E-05 1.35E-04 7.90E-05 4.94E-05 v.::.X 0.0 2.58E-03 3.40E-03 8.99E-04 3.63E-04 1.33E-03 7.12E-04 3.82E-04

. MEA? 0.0 1.94E-04 4.02E-04 2.15E-04 1.75E-04 2.48E-34 2.01E-04 1.76*-04 TOTA:. 8.79E-06 1.07E-02 1.53E-02 4.99E-03 2.77E-03 6.78E-03 4.22E-03 2.85E-03 I

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SEM8 ANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-G RADIOLCGICAL IMPACT - LICUID PATHWAY THIRD CUARTER GENEna:. r:a:.:c xAN-aEx PATHWAT SX:N 3CNE  :. 7ER T.2CDY !RYROID K!ONEY LONG G *.' I I T:SH 0.0 5.01E-OL 8.J6E-01 4.9tI-Ji 2.71E-03 2.57E-01 9.33E-02 1.54I-02 5.22E-03 8.*5E-03 5.45E-03 3.34E-04 3.15E-03 1.JtE-03 5.26E-04 INVIR 0.0 OR NX 0.0 2.45E-32 2.252-01 2.08E-01 1.88E-01 2.00E-01 1.92E-n i.98E-01 SECRI 2.35E-03 0.0 2.02E-03 2.02E-03 0.0 0.0 0.0 0.0 SWIM 0.0 0.0 1.58E-05 1.58E-05 0.0 0.0 0.0 0.0 20A;;NG 0.0 0.0 7.9;E-06 7.91E-06 0.0 0.0 0.0 0.0 VEGE 0.0 3.37E-n 6.00E-OL 3.47E-01 L.iiI-OL 2.71E-01 1.67E-01 1.17E-01

. VEGE 0.0 3.64E-32 7.09E-02 4.81E-02 1.33E-02 3.23E-02 1.38E-02 1.42E-02 I MIt.K MEAT TOTA:.

0.0 0.0 1.75E-01 2.34E-01 1.44E-01 3.52E-02 1.16E-01 6.37E-02 3.82E-02 2.73E-02 8.46E-02 6.74E-02 4.22E-02 5.62E-02 4.70E-02 4.29E-02 2.35E-03 1.11E*00 2.08E+00 1.3;E*00 3.93E-01 9.46E-01 5.84E-01 4.16E-01 I

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEM8ER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLOGICAL _ IMPACT - LIQUID PATHWAY FOURTH CUARTER xAx:xcx Acet.: < xaE.m PA*EWAY SKIN 3CNE f.!VER T . 303 *( !EHO D K:DNE't ;,USG C:- ,:,I 7:SE 3.0 1.22E-31 1.68E-01 1.10E-01 9.31I-04 5.75E-02 1.97E-02 4.16E-03 INVERT 0.0 2.49E-04 3.67E-04 2.49E-04 2.66I-05 1.42E-04 6.50E-05 3.32E-05 WATER 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SECRI 7.65E-03 8.27E-03 8.27E-03 8.27E-03 8.27E-03 8.27E-03 S.27E-03 8.27E-03 SWIM 0.0 3.12E-06 3.12E-06 3.12E-06 3.12E-06 3.12E-06 3.125-06 3.12E-06 VEG 0.0 2.88E-02 5.44E-02 4.09E-02 1.5LE-02 2.84E-02 1.95E-02 1.58E-02 xII,K 0.0 1.19E-02 2.03E-02 1.47E-02 4.0?E-03 9.61E-03 5.93E-0J 4.415-03 xEAT 0.0 1.46E-03 5.19E-03 4.50E-03 3.20E-03 3.87E-03 3.42E-03 3.23E-03 70'"A:. 9.65E-03 L.73E-01 2.57E-01 L.79E-01 2.10E-01 1.08E-01 5.69E-02 3.59E-02 I

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't SEHlANNUAL RADICACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLOGICAL IMPACT - LIQUID PATHWAY FOURTH QUARTER MAXIMCM TEENAGER (MREM)

PATHWAY SKIN 3CNE LIVER T.30 Y THYRC:D K:DNET LONG G:-LL:

TISE 0.0 1.03E-OL 1.375-31 4.82E-02 5.64E-04 4.71E-02 1.36E-02 2.515-03 INVIRT 0.0 3.50E-04 4.92E-04 1.89E-04 2.68E-35 1.85E-34 8.83E-05 3.35E-05 WATER 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 '

SHCRE 9.65E-04 8.27E-04 8.27E-04 8.27E-04 8.27E-34 8.27E-04 8.27E-04 8.27E-04 SWIM 0.0 3.12E-06 3.12E-06 3.12E-06 3.12E-06 3.;2E-06 3.12E-06 3.12E-06 VIG 0.0 4.90E-02 8.35E-02 4.llE-02 1.84E-02 4.0AE-02 2.71E-02 1.94E-02 MILK 0.0 2.15E-02 3.40E-02 1.53E-02 5.33E-03 1.!1E-02 9.12E-03 5.74E-03 I MIAT TOTAL 0.0 1.21E-03 3.52E-03 2.47E-03 1.91E-03 2.45E-03 2.12I-03 1.93E-03 9.65E-04 1.76E-01 2.59E-01 L.06E-01 2.71E-02 1.06E-01 5.78E-02 3.04E-02 I

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SEMXANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPCRT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLOGICAL IMPACT - LIQUID PATHWAY FOURTH QUARTER xAx:.xcx ca::.0 (xREx)

PATH

• DAY SKIN BONE *:vER T.3CDY THYRO:0 X 0NEY :ONG G * *. :

. :SH 0.0 3. 00E-01 2. 88E-01 4. 3 5E-0 2 '. 0 8 E-0 3 9. 47E-0 2 3. 48 E-0 2 2. 88 E-0 3 IN'/ERT 0.0 1.02E-03 1.03E-03 1.35E-04 5.14E-05 3.70E-04 1.66E-04 5.75E-05 WATER 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SHORE 1.35E-04 1.16E-04 1.16E-04 1.16E-04 1.16E-04 1.16E-04 1.16E-04 1.16E-04 S*4:x 0.0 3.12E-06 3.125-06 3.12E-06 3.12E-06 3.12E-06 3.12E-06 3.12E-06

'/EG 0.0 1.18E-01 1.425-01 4.5aE-02 2.91E-02 6.60E-02 4.24E-02 2.9aE-02 x::.K 0.0 5.19E-02 5.81E-02 1.5aE-02 8.42E-03 2.46E-02 1.42E-02 a.74E-03 MEAT 0.0 2.23E-03 4.44E-03 2.62E-03 2.30E-03 3.J0E-03 2.55E-03 2.32E-03 TOTA:, 1.35E-04 4.73E-01 4.94E-01 1.08E-01 4.llE-02 1.89E-01 9.42E-02 4.39E-02 I

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SEMIANNUAL RADICACTTVE EFFLUENT RELEASE REPORT JULY-0ECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLCGICAL IMPACT - LIQUIO PATHWAY FOURTH QUARTER 6

AVERAGE AOULT (MREM)

PATHWWE SKIN 3CNE LIVER T.3CDY THYROID K:DNEY LUNG G:

• L:

F Sa 0.0 2.40E-05 3.31E-05 2.17E-05 ;.83E-07 1.13E-05 3.89E-05 8.20E-07 INVERT 0.0 2.49E-07 3.67E-07 2.49E-07 2.66E-08 1.42E-0* 6.50E-08 3.32E-3 ORINK 0.0 9.21E-C7 1.22E-05 1.18E-05 1.09E-05 1.14E-05 1. lie-35 1. ICE-05 SHCRE 8.0lI-08 6.87E-08 6.87E-08 6.87E-08 6.87E-08 6.87E-c8 6.87E-08 6.87E-08 SWIM 0.0 2.59E-10 2.59E-10 2.59E-10 2.59E-10 2.59E-10 2.59E-10 2.59E-10 BCATING 0.0 1.30E-10 1.30E-10 1.30E-10 1.30E-10 1.30E-10 1.30E-10 1.30E-10 VEGE 0.0 1.08E-05 2.03E-05 1.52E-05 5.60E-06 1.06E-05 7.29E-06 5.89E-06 L VEGE 0.0 2.07E-06 3.87E-06 2.89E-06 1.05E-06 2.00E-06 1.36E-06 1.10E-06 MILK 0.0 4.37E-06 7.50E-06 5.43E-06 1.51E-06 3.54E-06 2.19E-06 1.62E-06 MEAT 0.0 1.34E-06 4.76E-06 4.13E-06 2.93E-06 3.55E-06 3.13E-06 2.96E-06 TOTAL 8.01E-08 4.39E-05 8.21E-0? 6.14E-05 2.23E-05 4.26E-05 2.91E-05 2.35E-05 E

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H l RADIOLOGICAL IMPACT - LIQUID PATHWAY FOURTH QUARTER l

AVERAGE TEENAGER (MREM)

PATH ~dAT SK:N 3CNE  :. IVER  !.300Y THYROID KIDNEY L *.*,NG G:-1LI FISH 0.0 2.55E-05 3.40E-05 1.'9E-05

. '. 40E-07 1.17E-05 4.625-05 6.21E-07 lNVERT 0.0 2.62E-07 3.69E-07 1.42E-07 2.015-08 1.39E-07 6.63E-08 2.51E-0 DRINK 0.0 9.09E-07 8.97E-06 9.18E-06 7.76E-06 S.17E-06 7.92E-05 7.775-06 SHORE 4.54E-07 3.89E-07 3.89E-07 3.89E-07 3.89E-07 3.89E-07 3.89E-07 3.89E-07 SWIM 0.0 1.47E-09 1.47E-09 1.47E-09 1.47E-09 1.47E-09 1.47E-09 1.47E-09 SCA NG 0.0 7.34E-10 7.34E-10 7.34E-10 7.34E-10 7.34E-10 7.34E-10 7.34E-10 7EGE 0.0 1.91E-05 3.25E-05 1.60E-05 7.17E-06 1.58E-05 1.05E-05 7.49E-06 VEGE 0.0 1.94E-06 3.28E-06 1.60E-06 7.03E-07 1.58E-06 1.04E-06 7.40E-07 MILK 0.0 1.12E-05 1.76E-05 7.95E-06 2.77E-06 7.81E-06 4.75E-06 2.98E-06 MIAT 0.0 1.16E-06 3.39E-06 2.38E-06 1.84E-06 2.37E-06 2.04E-06 1.86E-06 TOTAL 4.54E-07 6.04E-05 1.00E-04 4.85E-05 2.08E-05 4.80E-05 3.13E-05 2.19E-05 I

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLOGICAL IMPACT - LICUID PATHNAY FCURTH QUARTER AVERAGE CH:'.D (MREM)

PATHWAT SKIN 3CNE :7ER  ?.300Y TH7Ro 3 K:: NET *. L*NG GI-L:,;

E*3H 0.0 3.14E-05 3.02E-05 4.56E-06 1.'3E-07 9.92E-06 3.64E-06 3.02E-07 --

• NVIRT 0.0 3.375-07 3.39E-07 6.46Z-08 1.70E-08 L.22Z-07 5.48E-08 1.90E-0 ORIN.; 0.0 2. 6 5 E-0 6 1. 7 4Z-0 5 1. 5 2E-0 5 1. 4 9 E-0 5 1. 5 7 E-0 5 1. 5 2 5-0 5 1. 4 9 E-0 5 SECRF 9.17E-08 7.86E-08 7.86E-08 7.365-08 7.86E-08 7.86E-08 7.86E-08 7.86E-08 SWIM 0.0 2.97E-10 2.975-10 2.97E-10 2.97E-10 2.97Z-10 2.97E-10 2.97E-10 BCATING 0.0 1.48E-10 1.48E-10 1.48E-10 1.48E-10 1.485-10 1.48E-10 1.48E *0 7:05 0.0 4.63E-05 5.58E-05 1.80E-05 1.14E-05 2.59E-05 1.66E-05 1.'7E-05 I L VIGE M : *.K MEAT 0.0 0.0 0.0 2.82E-06 2.77E-05 2.14E-06 3.38E-06 3.10E-05 4.24E-06 1.07E-06 8.43E-06 2.51E-06 6.73E-07 4.49E-06 2.21E-06 1.55E-06 1.312-05 2.88E-06 9.91E-07 7.62E-06 2.45E-06 6.90E-07 4.66E-06 2.22E-06 To*AL 9.17E-08 1.13E-04 1.42E-04 4.99E-05 3.39E-35 6.92Z-05 4.66E-05 3.46E-05 E

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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1985 RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-H RADIOLOG! CAL IMPACT - LIQUID PATHWAY FOURTH CUARTER GENE.u:. ;cs::c .uS-AIM PArawAr sx:S sone  ::vEa  :.acor ruvaO:o x::sEY  :.::No c: .:.:

E:SW 0.0 4.79E-03 6.39E-03 3.43E-03 3.25Z-05 2.18Z-03 7.68E-04 1.3SE-04 INVER 0.0 5.20E-05 7.08E-05 3.79E-05 4.72E-06 2.70E-05 1.24E-05 5.81E-06 ORINx 3.0 2.45E-04 2.54E-03 2.39E-03 2.25Z-33 2.35E-03 2.28E-03 2.25E-03 SHORE 2.45E-05 0.0 2.10E-05 2.10E-05 0.0 0.0 0.0 0.0 SW:M 0.0 0.0 7.94E-08 7.94E-08 0.0 0.0 0.0 0.0 s0A :NG 0.0 0.0 3.97E-08 3.97E-08 0.0 0.0 0.0 0.0 VIGE 0.0 3.60E-03 5.58E-03 3.15E-03 1.36Z-03 2.77E-03 1.85E-03 1.425-03

• ., 7 IGE 0.0 4.36E-04 7.40E-04 4.83E-04 1.87E-]4 3.74E-04 2.51I-04 1.96Z-04 l M :'.x 0.0 1.86E-03 2.56E-03 1.24E-03 4.35E-04 1.14E-03 6.85E-04 4.62E-04 g MEA? 0.0 2.91E-04 8.39E-04 7.2SE-04 5.34E-04 6.57E-04 5.76Z-04 5.39E-04 TOTA:. 2.45Z-05 1.15E-02 1.88E-02 1.15E-02 4.80E-03 9.50E-03 6.42E-03 3.01E-03

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