ML20155J706
| ML20155J706 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1987 |
| From: | Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| GCA-88-110, NUDOCS 8806210007 | |
| Download: ML20155J706 (188) | |
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830, Sacramento CA 95852-1830,(916) 452 3211 I
AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA GCA 88-110 FEB 2 91983 U. S. Nuclear Regulatory Commission Attn: J. B. Hartin, Regional Administrator Region V 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 m
Docket No. 50-312 ,, .,p Rancho Seco Nuclear Generating Station G in ?!
License No. DPR-54 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT to
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Dear Mr. Martin:
Y The Sacramento Municipal Utility District hereby transmits two copies of the Semiannual Radioactive Effluent Release Report for the period of July 1 through December 31, 1987, in compliance with Technical Specification 6.9.2.3, Semiannual Radioactive Effluent Release Report.
Please contact me if you have any questions. Members of your staff with questions requiring additional information or clarification may contact Mr. Paul Lavely at (916) 452-5211, extension 4824.
Sincerely, ll $ 7xvwo G. Carl Andoghini Chief Executive Officer, Nuclear Attachments cc: G. Kalman, NRC, Rockville (w/atch)
A. D'Angelo, NRC, Rancho Seco (
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F. J. Miraglia, NRR, Rockville ( "
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8806210007 871231 PDR R
ADOCK 05000312 DCD Ik
[ lf'h RANCHO SECO NUCLEAR GENERATING STATION D 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION l
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l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- JULY - DECEMBER 1987 l RANCHO SECO NUCLEAR GENERATING STATION i
O V 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. 1 l
I began commercial operation on April 17, 1975. The single unit on the Rancho I 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 Munic w i Utility District to
! meet the reporting requirerents of Technical Specification 6.9.2.3.
l 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, Sacramento County Health Officer, and District offices as a public document.
This document reports the types and quantities of radioactive materials discharged in liquid and gaseous effluents, and solid radwaste shipments.
Estimates of the radiological impact to man associated with the gaseous and liquid effluent discharges are presentd. The report period is July 1, 1987 through December 31, 1987.
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) l O' Gaseous Effluents: (2) Liquid Effluents: (3) Solid Haste shipments: (4)
Radiological Impact on Man; (5) Meteorological data; and (6) Supplemental i
Information. Each section contains, where appropriate, narrative or l descriptive material to clarify the tables.
In accordance with Technical Specifications, the District maintains an Offsite Oose Calculation Manual. It contains the detailed methods and I
procedures to perform che radiological impact calculations supporting this l report.
1 Technical Specification 6.9.2.3 requires this report to include changes to l l the Offsite Dose Calculation Manual (ODCM) and the solid radwaste Process j Control Program (PCP), assessments of radiation doses associated with radioactive effluents to unrestricted areas, reports of abnormal releases, I and instances where radioactive effluent mcnitoring instrumentation is l inoperable for periods greater +.han 30 days. There were three abnormal liquid releases during this report period.
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION EXECUTIVE SUM M A revision to the Offsite Dose Calculation Manual was implemented on December 9, 1987. The interim change to the Offsite Dose Calculation Manual was made to correct technical errors and provide for equipment changes at Rancho Seco Nuclear Power Station, The 00CM changes are described in Appendix E.
The Process Control Manual (PCP) was completely reformatted and approved by the Plant Review Committee on December 1, 1987. Details of the changes to the PCP are in Section IX of this report. Appendix G is a copy of the new PCP.
The Appendix I numerical guidelines for gaseous effluents are:
(1) 10 mrad gamma air dose per calendar year /5 mrad per calendar quarter (2) 20 mrad beta air dose per calendar year /20 mrad per calendar quarter (3) 15 mrem to any organ per calendar year /7-1/2 mrem per calendar quarter The Appendix I numerical guidelines for liquid effluents are:
(1) 3 mrem total body per calendar year /1-1/2 m,7m per calendar quarter (2; 10 mrem total body per calendar year /5 mrem per calendar quarter O The redioective effiuent dischar9ed from Rencho Seco durin918 third and fourth quarters of 1987 equates to a calculated dose of: .
Third Ouarter Fourth Ouarter Gaseous Effluent
' organ (mrem) 4.45 E-03 5.31 E-03 gamma air (mrad) 1.68 E-08 0.0 beta air (mrad) 1.90 E-06 0.0 i
Liquid Effluent total body (mrem) 2.81 E-02 1.07 E-01 organ (mrem) 8.09 E-02 4.12 E-01 I
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 O/
s . RANCHO SECO NUCLEAR GENERATING STATION Part 190 of Title 40, Code of Federal Regulations, (40 CFR 190) requires that dose to any member of the public from Rancho Seco Nuclear Operations be less than 25 mrem to the total body or 75 mrem to the thyroid. If the dose to a maximum hypothetical' individual is twice the annual limits of Appendix I, 10 CFR 50, then dose calculations must be performed to determine compliance :
with limits of 40 CFR 190. ,
All of the above values are below the numerical guidelines of 10 CFR 50, Appendix I, and no 40 CFR 190 evaluation was performed.
Conclusion:
The radioactive effluents discharged from P.ancho Seco from July 1, 1987, through December 31, 1987, resulted in dosages that were as low as reasonably achievable.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION O TABLE OF CONTENTS en I. SUPPLEMENTAL INFORkATION 1 Table I-A Regulatory Limits 2 Table I-C Measurements and Approximation of Total Radioactivity 3 Table I-D Batch Releases 4 Table I-E Abnormal Releases 5 II. GASEOUS EFFLUENTS 9 Table II-A Gaseous Release Summary 11 Table II-B Ground Level Releases 12 Table II-C Lower Limits of Detection 13 Table II-D Radiation Dose Estimates 14 III. LIQllID EFFLUENTS 18 Table I2I-A Liquid Release Summary 19 Table III-B Liquid Effluents 20 Table III-C Lower Limits of Detection 21 Table III-D Radiation Dose Estimates 22 IV. SOLID HASTE 24 V. ESTIMATION OF ERROR 25 VI. RADIOLOGICAL IMPACT ON MAN 32 VII. MITEOROLOGICAL DATA 36 VIII.0FFSITE DOSE CALCULATION MANUAL (00CM) CHANGES 65 IX. PROCESS CONTROL PP.0 GRAM (PCP) CHANGES 68 X. RADIOACTIVE EFFLUENT HONITORING INSTRUMENTATION INOPERABILITY GREATER THAN 30 DAYS 69 XI. CHANGES IN LAND USE LOCATIONS 69
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i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION O TABLE OF CONTENTS (Continued) l l
l APPENDIX r
A. Radiological Impact on Man 1987 Quarter 3 Gaseous Effluent Pathway B. Rad *ological impact On Man ,
1987 Quarter 4 Gaseous Effluent Pathway l l
C. Radiological Impact on Man 1987 Quarter 3 Liquid Effluent Pathway 1
- 0. Radiological Impact On Man 1987 Quarter 4 Liquid Effluent Pathway E. Interim Revision of AP.310, Offsite Dose Calculation Manual F. RP.309 II-4 !
G. AP.309 II-4 ;
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.I SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION SUPPLEMENTAL INFORMATION i
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l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 1 RANCHO SEC0 NUCLEAR GENERATING STATION I. SUPPLEMENTAL INFORMATION Supplemental information as outlined in Regulatory Guide 1.21 is l presented in this section of the report.
A. GASEOUS EFFLUENTS All releases of gaseous effluents occurred at the ground level. l They are summarized in Table II-A, "Gaseous Effluents - Summation of All Releases," and Table II-8, "Gaseous Efficents - Ground Level '
Releases." Elevated releases were not evaluated because the gaseous effluent stack height is less than twice the height of its adjacent structure.
There were 6 Haste Gas Decay Tank releases and 25 Reactor Building batch releases during the period July 1 through December 31,
. 1987. There were no abnormal gaseous releases of radioactive material in this report period.
B. LIQUID EFFLUENTS There were 17 batch releases of radioactive liquid from the Regenerant Holdup Tanks (RHUT). The water was ultimately released p by 34 Retention Basin discharges. Liquid releases are summarized d in Table III-A and the isotopic contents are detailed in Table III-0. There were three abnormal releases of radioactive liquid in this report period.
C. SOLID HASTE There were 6 shipments of solid radioactive wastes to the Hanford Burial Site between July and December 31, 1987. These consisted of Low Specific Activity (LSA) boxes and 55 gallon drums.
D. MAXIMUM PERMISSIBLE CONCENTRATIONS The maximum permissible concentrations (HPC) used to calculate the percent of Technical Specification Limits in Tables II-A and III-A were obtained from 10 CFR 20, Appendix B, Table II. The most I conservative HPC valves were selected for use in the calculations.
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! SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION i l
O TABLE I-A i !
] SUPPLEMENTAL INFORMATION - REGULATORY LIMITS i ,
j A. Noble Gases in gaseous effluent ;
i Dose Rate - Site Boundary 500 mrem / year to whole body (limits based upon 10 CFR 20, 3000 mrem / year to skin
! Appendix B, Table II, Column 1) i 1 ~
) Air Dose - Site Boundary 5 mrad / quarter - Gamma i (design objectives of 10 CFR 50, 10 mrad / quarter - Beta
- Appendix I) 10 mrad / year - Gamma !
20 mrad / year - Beta B. Iodine 131, Tritium and Particulates in gaseous effluent with Half Lives greater than 8 days Dose Rate - Site boundary 1500 mrem / year to any organ !
(limits based upon 10 CR 20, Appendix B Table II, Column 1) l i
Dost to a member of the public 7.5 mrom/ quarter to any organ (design objectives of 10 CFR 50 15 mrem / year to any organ O Appendix I)
C. Liquid Effluents Effluents must not exceed the 10 CFR 20, Appendix 8. Table II, Column 2 concentration limits in the unrestricted area.
Dissolved and entrained noble gases less than 2.0E-04pCi/ml (total activity).
Dose to a member of the public 1.5 mrom/ quarter tu the total (design objectives of 10 CFR 50 body Appendix I) 5 mrem /quarr ' m any organ 3 mres/ year to it.. total body 10 mres/ year to any organ i
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 '
RANCHO SECO NUCLEAR GENERATING STATION TABLE I-C l SUPPLEMENTAL INFORMATION - MEASUREMENT METH00S FOR TOTAL RADI0 ACTIVITY >
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A. Fission and Activation Gases 4
Gamma Spectrometry (HPGe')
Liquid Scintillation (for H-3)
B. Iodines Gamma Spectrome* O U /Ce)
Beta Proportione nr-89, Sr-90)
Alpha Proportional (gross alpha)
C. Particulates
. Gamma Spectromritry (HPGe)
Beta Proportional (Sr-89, Sr-90) 1 Alpha Proportional (gross alpha)
D. Liquid Effluents Gamma Spectrometry (HPGe) j Liquid Scintillation (H-3)
Beta Proportional (Sr-89, Sr-90, gross beta) j Alpha Proportional (gross alpha) 1 i
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 l RANCHO SECO NUCLEAR GENERATING STATION
- o. TABLE I-D ,
SUPPLEMENTAL INFORMATION - BATCH RELEASES 1 3rd 4th Quarter Ouarter A. Gaseous
- 1. Number of batch releases 17 14 l 2. Total time period for batch releases (hours) 1919.1 1584.3 !
- 3. Maximum time period for a batch release (hours) 168 167.8
- 4. Average time period for a batch release (hours) 112.9 113.2
- 5. Minimum time period for a batch release (hours) 10.7 12.5 B. Liqu'd l
- 1. Number of batch releases 6 11
- 2. Total time period for batch releases (hours) 35.3 31.7
- 3. Maximum time period for a batch release (hours) 15.3 5.7
- 4. Average time period for a batch release (hours) 5.9 2.7
- 5. Minimum time period for a tacit release (hours) 2.4 1.6
! 6. Average stream flow durins, pwiod of
- release of effluent into a flowing stream (gpm) (I) 0 0 (1) There is negligible flow on an annual average basis in Clay Creek, upstream from the plant liquid effluent discharge point. However Rancho Seco now discharges a minimum of 5000 gpm into Clay Creek on a continuous basis into which the radioactive material in liquid effluent is discharged, i
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I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -- i JULY - DECEMBER 1987 !
RANCHO SEC0 NUCLEAR GENERATING STATION i
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TABLE I-E j i
SUPPLEMENTAL INFORMATION - ABNORMAL RELEASES j t
3rd 4th !
UNITS OUARTER OUARTER l A. Gaseous !
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- 1. Number of releases None None l
- 2. Total activity released offsite Ci NA NA l l
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- 1. Number of releases 2 1 l t
- 2. Total activity released offsite Ci 6.41E-6 1.89E-9 l O ;
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION I. SUPPLEMENTAL INFORMATIDf(
ABNORMAL RELEASES Abnormal releases are defined as an unplanned or uncontrolled release of radioactive material from the site boundary.
A. GASEOUS There were no abnormal Gaseous releases during the report period.
B. LIOUID
- 1. On Tuesday, September 1, 1987 valve FHS-020 leaked approximately 2,490 gallons of water to a storm drain which ;
led offsite. The water that is normally in this drain does '
not contain radioactive material. The measured concentration of the water was 5.31 E-7 pC1/ml of Cesium 137 and 1.08 E-7 pCi/ml of Cesium 134. The total amount of radioactive material released offsite was 6.03 E-6 Curies.
Calculations were performed in accordance with the ODCH using the above information. The results indicated a calculated whole body dose to a maximum hypothetical adult individual of 3.32 E-3 mrem and an organ dose of 4.74 E-3 mrem.
O 2. On August 28, 1987 approximately 2000 gallons of liquid leaked from the steam line atmospheric dump valves (ADVs) to a drain below the valves. The drain led directly offsite. The water that is normally in this drain does not contain radioactive material. The measured concentration of the water that was released was 5.14 E-8 pCi/ml Cesium 137. The total amount of radioactive material released was 3.89 E-7 Curies.
l Calculations were performed in accordance with the ODCH using the above information. The results indicated a calculated whole body dose to a maximum hypothetical adult individual of 1.94 E-4 mrem and an organ dose of 2.91 E-4 mrem.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION I. SUPPLEMENTAL INFORMATION ABNORMAL RELEASES (Continued)
- 3. On November 15, 1987 approximately 5 gallons of water overflowed from the "B" Steam generator level indicator to a storm drain on the 40 foot level of the Auxiliary Building. The storm drain led directly offsite. The water that is normally in this drain does not contain radioactive material. The measured concentration of the water that was released was 1.00 E-7 pCi/ml of Cesium 137.
The total amount of radioactive material released was 1.89 E-9 Curies.
Calculations were performed in accordance with the OOCH using the above information. The results indicated a calculated whole %dy dose to a maximum hypothetical adult individual of 9.46 E-7 mrem and an organ dose of 1.42 E-6 mrem.
- 4. Actions to Frevent Recurrence of Abnormal Releases The Short Term Effluent Control Task Force was established in late November, 1987, by the CEO-Nuclear. The purpose of this task force was to identify and implement immediate, short and long term actions that would minimize the potential for an unmonitored j release of either PCBs (Polychlorinated biphenyls) or radioactive '
O effluent. High risk drains have been identified. Immediate corrective actions implemented thus far include, but are not l
limited to, floor drain plugging, diversion dikes, and various '
administrative controls to reduce the risk for leaks or spills.
Both short term and long term corrective actions have been proposed as appropriate. Engineering evaluations, cost-benefit analysis, capital appropriations, work requests, etc., are being accomplished on a case-by-case basis to implement the recommendations. A complementary effort is also underway to systematically eliminate identified sources of leaks or spills that have significant i potential for causing an unmonitored release. All recommendations !
are being coordinated with the Radiological Effluent Control l Program and Hazardous Materials Task Force to ensure that the short term solutions will meet the long term goals of these two programs.
UNHONITORED RELEASES During this report period, there were two instances in which an unmonitored release of gaseous material were made from discharge vents that are used for radioactive gaseous materials. Analysis ;
showed that no radioactive material was released off site.
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION I. SUPPLEMENTAL INFORMATION (Continued)
- 1. On September 23, 1987 Engineers and Technicians started to perform testing of the Auxiliary Building Grade Level Vent System. Because of a design error, the fan motor for the Vent System started. This resulted in an unmonitored release of gaseous material from Rancho Seco Site.
Subsequent analysis of air samples from the areas serviced by the ~
Auxiliary Building Grade Level Vent System and other analysis showed that no radioactive material was released during this event. The design fault was corrected. Procedures involving the use of the system were also improved to prevent a recurrence of an unmonitored release from Auxiliary Building Grade Level Vent System. This event is detailed in Licensee Event Report 87-043.
- 2. On November 16, 1987, the first seven minutes of a 6,930 minute purge of the reactor building was not monitored. The remainder of the discharge was monitored in accordance with Rancho Seco Procedures. Analysis of pre-release samples, purge samples and post-release samples showed that no radioactive material was released. This event occurred due to a personnel error. The appropriate procedures were modified in order correct the problem. This event is detailed in Licensee Event Report 87-047.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 ,
p RANCHO SEC0 NUCLEAR GENERATING STATION II. GASEOUS EFFLUENTS Table II-A, "Gaseous Effluents-Gaseous Release Summary," provides a !
detailed listing of gaseous effluents released by quarter in four l categories:
. Fission and Activation Gases
. Particulates with half-lives greater than eight days
. Tritium Listed for each of the four categories are: )
. Total Curies Released
. Average Release Rate
. Percent of Technical Specification Limit
. Estimated Total Error j In addition, the particulate category lists the gross alpha 1 radioactivity released for each quarter.
The methodology used to calculate the percent of applicable limit is ;
presented at the end of this section. )
The methodology used to calculate the estimated total error in Table II-A l is presented in Section V of this report. ,
A table for "Gaseous Effluents - Elevated Release," is not applicable, since Rancho Seco Nuclear Generating Station Unit No. I does not conduct elevated releases.
Table II-8, "Gaseous Effluents - Ground Level Releases," provides a ,
systematic listing by radionuclide for the the quantity of radioactive 1 material released in gaseous effluents in four categories:
. Fission Gases
. Iodines
. Particulates
. Tritium The total radioactivity for er radionuclide is listed for each quarterly period by:
. Continuous Release Mode
. Batch Release Mode Containment purges and waste gas decay tank releases are considered to 1 be "batch" releases. Auxiliary Building stack releases are considered i to be "continuous" releases.
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- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION D
d II. GASEOUS EFFLUENTS Table II-C, "Gaseous Effluents - Lower Limits of Detection," provides a listing of typical radionuclide lower limit of detection activity concentrations.
Table II-D, "Gaseous Effluents - Radiation Dose Estimates at the Site and Exclusion Area Boundaries," provides a quarterly summary of calculated doses at the site boundary and exclusion area boundary for this report period.
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TABLE II-A GASEOUS EFFLUENTS - SUttiATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error, %
A. Fission & Activation Gases
- 1. Total Release Ci 8.29 E-04 0.0 E 8.00 E+00
- 2. Average Release Rate for period pCi/see 1.20 E-04 NA E
- 3. Percent of Technical Specification Limit % 1.15 E-05 NA E B. Iodines
- 1. Total Iodine - 131 Cl 0.0 E 0.0 E 7.00 E+00
- 2. Average Release Rate for period pCi/sec NA E NA E
- 3. Percent of Technical Specification Limit % NA E NA E O C. Particulates
- 1. Particulates With Half Lives > 8 days Ci 1.54 E-06 0.0 E 8.00 E+00
- 2. Average Release Rate for Period pCi/sec 1.98 E-13 NA E
- 3. Percent of Technical Specification Limit % 6.36 E-02 NA E 4 Gross Alpha Radioactivity Ci 4.87 E-07 9.01 E-02
- 0. Tritium
- 1. Total Tritium Ci 2.29 E-00 3.72 E+00 7.00 E+00
- 2. Average Release Rate for period pCi/sec 2.94. E-01 4.78 E-01
- 3. Percent of Technical Specification Limit % 6.36 E-02 7.08 E-02 l
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987
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\- ' TABLE II-B GASEQUS EFFLUENTS - GROUND-LEVEL RELEASES Continuous Mode Batch Mode 3RD 4TH 3RD 4TH Nuclides Released Unit Guarter Ouarter Ouarter Quarter
- 1. Fission Gases Argon-41 Ci 0.0 E 0.0 E 0.0 E 0.0 E Krypton-85 Ci 0.0 E 0.0 E 8.29 E-04 0.0 E Krypton-85m Ci 0.0 E 0.0 E 0.0 E 0.0 E Krypton-87 Ci 0.0 E 0.0 E 0.0 E 0.0 E Krypton-88 Ci 0.0 E 0.0 E 0.0 E 0.0 E Xenon-131m Ci 0.0 E 0.0 E 0.0 E 0.0 E Xenon-133 Ci 0.0 F 0.0 E 0.0 E 0.0 E Xenon-133m Ci 0.0 E 0.0 E 0.0 E 0.0 E Xenon-135 Ci 0.0 E 0.0 E 0.0 E 0.0 E Xenon-135m Ci 0.0 E 0.0 E 0.0 E 0.0 E Xenon-138 Ci 0. 0 E 0.0 E 0.0 E 0.0 E unidentified Ci 0.0 E 0.0 E 0.0 E 0.0 E Total for Period Ci 0.0 E 0.0 E 8.29 E-04 0.0 E O
2.0 Iodines Iodine-131 Ci 0.0 E 0.0 E 0.0 E 0.0 E Iodine-133 Ci 0.0 E 0.0 E 0.0 E 0.0 E Iodine-135 C1 0.0 E 0.0 E 0.0 E 0.0 E Total for Period Ci 0.0 E 0.0 E 0.0 E 0.0 E 3.0 Particulates Strontium-89 Ci 1.54 E-06 0.0 E 0.0 E 0.0 E Strontium-90 Ci 0.0 E 0.0 E 0.0 E 0.0 E Cesium-134 Ci 0.0 E 0.0 E 0.0 E 0.0 E Cesium-137 Ci 0.0 E 0.0 E 0.0 E 0.0 E Barium-Lanthanum-140 Ci 0.0 E 0.0 E 0.0 E 0.0 E Unidentified Ci C.0 E 0.0 E 0.0 E 0.0 E i
4.0 Tritium
/T Tritium Ci 1.68 E+00 2.81 E+00 6.08 E-01 9.11 E-01 V
l i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l g JULY - DECEMBER 1987 l ,,) RANCHO SEC0 NUCLEAR GENERATING STATION TABLE II-C GASEOUS EFFLUENTS - LOWER LIMITS OF DETECTION CONTINUOUS AND BATCH H0DE*
RADIONUCLIDES Tvoical LLD (uC1/cc)
- 1. Fission Gases Argon-41 9.60 E-08 Krypton-85 1.43 E-05 Krypton-85m 5.20 E-08 Krypton-87 1.30 E-07 Krypton-88 1.62 E-07 Xenon-131m 2.07 E-06 Xenon-133 1.22 E-07 Xenon-133m 3.94 E-07 Xenon-135 4.56 E-08 Xenon-135m 1.28 E-07 Xenon-138 2.13 E-07
- 2. Iodines Iodine-131 1.74 E-13
(] Iodine-133 Iodine-135
, 3.29 E-13 2.72 E-11
- 3. Particulates Barium-140 6.50 E-13 Colbalt-58 6.14 E-13 Colbalt-60 1.06 E-12 Cerium-141 1.74 E-13 Cerium-144 1.91 E-12 Cesium-134 2.24 E-13 Cesium-137 2.99 E-13 Iron-59 2.74 E-13 Lanthanum-140 5.10 E-13 Maganese-54 3.91 E-13 Molybdenum-99 4.03 E-12 Niobium-95 2.30 E-13 ;
Strontium-89 5.00 E-15 l Strontium-90 2.00 E-15 Technetium-99m 2.92 E-13 Zirconium-95 4.39 E-13 4 Tritium (H-3) 6.22 E-10 .
- Gas decay tank "Batch Mode" releases are through a "continuous mode" release P'*"'
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION l
\ TABLE II-D l l
GASEOUS EFFLUENTS - RADIATION DOSE ESTIMATES AT THE SITE AND EXCLUSION AREA BOUNDARIES SITE BOUNDARY EXCLUSION AREA MAXIMUM SECTOR MAXIMUM SECTOR A. Maximum Offsite 3RD 4TH 3RD 4TH-Ground-Level UNITS OUARTER OUARTER 00ARTER OUARTER Location (a)- (b) (c) (d)
- 1. a. Gamma Air mrad 1.00 E-8 0.0 1.68 E-8 0.0
- b. % Tech Spec Limit % 2.00 E-7 NA 3.36 E-7 NA
- 2. a. Beta Air mrad 1.13 E-6 0.0 1.90 E-6 0.0
- b. % Tech Spec Limit % 1.13 E-5 NA 1.90 E-5 NA i
- 3. a. Total Body mrem 6.59 E-9 0.0 1.10 E-08 0.0 l
- b. % Tech Spec Limit % NA NA NA NA l
- 4. a. Skin mrem 7.87 E-07 0.0 1.32 E-06 0.0 l
- b. % Tach Spec Limit % 2.62 E-08 0.0 4.40 E-08 NA MAXIMUM RECEPTOR 3RD 4TH QUARTER QUARTER (e) (f)
B. Tritium, Iodine, Particulate Unrestricted Areas All Pathways:
(a) (b)
- 1. a. Organ Dose mrem 4.45 5-3 5.31 E-03
- b. % Tech Spec Limit % 6.36 E-02 7.08 E-2 C. Direct Radiation (c) (d) l
- 1. a. Dose
- mrem 0.0 0.0
- b. % Tech Spec Limit % NA NA NOTE: ine ai>ove calculations were performed in accordance with the 00CM.
- Based on TLD Results (a) ENE 225 meters (b) SSH 200 meters (c) N/A (d) N/A (e) ENE 1140 meters, Garden, Teenager Organ (f) SH 1220 meters Nearest House, Child Organ
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION II. GASEOUS EFFLUENTS Percent of Technical Soecification Limits Calculation Methodology The percent of Technical Specification Limit tabulated in Table II-A was determined by calculation of the following parameters:
Dose Factor x Average
% Technical Specification Limit - Release Rate x X/0 X100 Dose Limit The Average Release Rate - Total Curies released in each category oer auarter Seconds per quarter X- The average quarterly atmospheric dispersion factor for the Q appropriate quarter and sector (sec/m3).
Quarter 1v Averace X/0 (sec/m31 1987 Quarter 3 Table A-II 1987 Quarter 4 Table B-II The percent of Technical Specification Limits tabulated in Table II-D is q the percent of the applicable dose rate limits of Table I-A.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 g RANCHO SECO NUCLEAR GENERATING STATION ,
TABLE A-II 1987 QUARTER 4 AVERAGE X/Q AND D/Q l
X/Q (SECONDS / METER **3)
D/Q l
LOCATION DISTANCE NO 2.26 DAY 8.00 DAY (1/ METER **2) l (meters) DECAY DECAY DECAY ;
UNDEPLETED UNDEPLETED DEPLETED 1 TRITIUM NOBLE IODINE & IODINE &
GAS PART PART l i
Exclusion area N 640 1.185E-05 1.183E-05 1.096E-05 5.709E-08 Exclusion area NNE 640 1.208E-05 1.206E-05 1.118E-05 3.866E-08 Exclusion area NE 640 1.272E-05 1.270E-05 1.176E-05 5.412E-08 Exclusion area ENE 640 1.357E-05 1.355E-05 1.256E-05 8.147E-08 Exclusion area E 640 1.088E-05 1.086E-05 1.006E-05 5.828E-08 Exclusion area ESE 640 9.375E-06 9.362E-06 8.672E 06 5.174E-08 Exclusion area SE 640 1.281E-05 1.279E-05 1.185E-05 8.742E-08 Exclusion area SSE 640 1.475E-05 1.473E-05 1.364E-05 7.077E-08 Exclusion area S 640 1.094E-05 1.092E-05 1.011E-05 3.509E-08 Exclusion area SSH 640 1.679E-05 1.676E-05 1.553E-05 3.984E-08 Exclusion area SH 640 2.700E-05 2.695E-05 2.497E-05 5.709E-08 Exclusion area HSH 640 1.926E-05 1.922E-05 1.781E-05 4.044E-08 Exclusion area H 640 1.982E-05 1.979E-05 1.833E-05 6.244E-08 Exclusion area HNH 640 2.132E-05 2.130E-05 1.972E-05 1.130E-07 Exclusion area NH 640 2.335E-05 2.333E-05 2.160E-05 1.820E-07 Exclusion area NNH 640 2.018E-05 2.015E-05 1.867E-05 1.005E-07
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION
TABLE B-II l 1987 QUARTER 3 AVERAGE X/Q AND D/Q l X/Q (SECONDS / HETER **3)
D/Q LOCATION DISTANCE NO 2.26 DAY 8.00 DAY (1/ METER **2)
(meters) DECAY DECAY DECAY UNDEPLETED UNDEPLETED DEPLETED TRITIUM NOBLE IODINE & IODINE &
GAS PART PART Exclusion area N 640 1.033E-05 1.031E-05 9.552E-06 5.474E-08 Exclusion area NNE 640 1.120E-05 1.119E-05 1.036E-05 6.909E-08 Exclusion area NE 640 1.826E-05 1.825E-05 1.690E-05 1.265E-07 Exclusion area ENE 640 3.269E-05 3.266E-05 3.024E-05 3.199E-07 Exclusion area E 640 3.829E-05 3.825E-05 3.542E-05 2.944E-07 Exclusion area ESE 640 1.966E-05 1.963E-05 1.818E-05 7.494E-08 Exclusion area SE 640 1.764E-05 1.762E-05 1.632E-05 5.899E-08 Exclusion area SSE 640 1.044E-05 1.042E-05 9.659E-06 2.339E-08 Exclusion area S 640 6.564E-06 6.552E-06 6.071E-06 1.594E-08 i Exclusion area SSH 640 3.826E-06 3.820E-06 3.539E-06 9.567E-09 Exclusion area SH 640 2.425E-06 2.421E-06 2.243E-06 5.846E-09 Exclusion area HSH 640 2.085E-06 2.082E-06 1.929E-06 4.783E-09 Exclusion area H 640 3.958E-06 3.952E-06 3.661E-06 8.504E-09 Exclusion area WNH 640 4.791E-06 4.784E-06 4.432E-06 1.169E-08 Exclusion area NW 640 4.785E-06 4.779E-06 4.426E-06 1.754E-08 t
Exclusion area NNH 640 7.252E-06 7.244E-06 6.709E-06 3.401E-08
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION l III. LIOUID EFFLUENTS Table III-A "Liquid Effluents - Liquid Release Summary," provides a detailed listing of liquid effluents released by quarter in three l categories:
. Fission and Activation Products
. Tritium
. Dissolved and Entrained Gases Listed for each of three categories are:
. Total Curies Released
. Average Diluted Concentration !
. Percent of Technical Specification Limit i
. Estimated Total Error In addition, Table III-A lists: ;
1
- Gross alpha radioactivity released I
. Volume of waste released prior to dilution I
. Volume of dilution water used during period 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 III-A is presented in Section V of this report. l Table III-B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactive material released in liquid effluents.
The total radioactivity of each radionuclide released in liquid effluent is listed for each quarterly period by batch mode released only. No radioactive liquid effluent releases are made on a continuous basis from Rancho Seco.
Table III-C, "Liquid Effluents - Lower Limits of Detection," provides a listing of typical lower limit of detection concentrations as defined in Section 5.0 of the Offsite Dose Calculation Manual.
Table III-D, "Liquid Effluents" - Radiation Dose Estimates to the Maximum Hypothetical Individual" provides a quarterly summary of calculated doses beyond the site boundary.
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SEMIANNUAL RADIOACTIVE FFFLUENT RELEASE REPORT-JULY - DECEMBER 1987
'% RANCHO SECO NUCLEAR GENERATING STATION TABLE III-A LIQUID EFFLUENTS - SUPfiATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error, %
A. Fission and activation products
- 1. Total Release (not including tritium, Ci 8.32 E-05 3.55 E-04 2.51 E+01 gases, alpha
- 2. Average diluted concentration -
pCi/ml 2.65 E-11 1.07 E-10 during period
- 3. Percent of Technical Specification Limit % 6.18 E-05 4.79 E-04 B. T ri tium i
- 1. Total Release Ci 7.40 E-06 0.0 E 1.92 E+01 1 l
- 2. Average dil'uted concentration pCl/ml 2.36 E-12 0.0 E during period l
- 3. Percent of Technical Specification Limit % 7.85 E-08 0.0 E l
C. Dissolved and Entrained Gases l
- 1. Total Release Ci 0.0 E 0.0 E 8.0 E+00
- 2. Average Olluted concentration pC1/ml 0.0 E 0.0 E during period
- 4. Percent of Applicable Limit % 0.0 E 0.0 E D. Gross Alpha Radioactivity J l
- 1. Total Release Cl 0.0 E 0.0 E NA E I
I E. Volums of waste released Liters 2.61 E 06 5.18 E-06 5.0 E+00 (prior to dilution) l F. Volume of dilution water used during period Liters 3.14 E 09 3.32 E 09 1.3 E+00 g . . . _ -
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~1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i JULY - DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION f3 TABLE III-B LIQUID EFFLUENTS BATCH HODE 3RD 4TH Nuclides Released Unit Ouarter 0 garter Strontium-89 Ci 0. _E 0. E Strontium-90 Ci 0. E 0. E Cesium-134 Ci 3.72 E-07 2.97 E-05 1 Cesium-137 Ci 6.90 E-06 2.58 E-04 i Iodine-131 Ci 0. E 0. E Cobalt-58 Ci 0. E 0. E Cobalt-60 Ci 6.43 E-06 6.68 E-05 1 Iron-59 Ci 0. E 0. E l Zinc-65 Ci 0. E 0. E Manaanese-54 Ci 0. E 0. E Chromium-51 Ci 0. E 0. E Zirconium-Niobium-95 Ci 0. E 0. E Molybdenum-99 Ci 0. E 0. E Technetium-9m Ci 0. E 0. E Barium-Lanthanum-140 Ci 0. 0.
( Cerium-141 Ci 0.
E E 0.
E E l Silver-110m Ci 0. E 0. E Iodine-133 Ci 0. E 0. E Cesium-136 Ci 0. E 0. E Tritium Ci 7.40 E-06 0. E Xenon-133 Ci 0. E 0. E Xenon-135 Ci 0. E 0. E 1
EQIE: No continuous releases of liquid radioactive effluent are made from i Rancho Seco Nuclear Generating Station. I l
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION
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\ TABLE III-C LIOUID EFFLUENTS - TYPICAL LOHER LIMITS IF DETECTION RADIONUCLIDES BATCH HODE (uCi/ml)
- 1. PARTICULATES Sodium-24 2.88 E-08 Chromium-51 2.27 E-07 ,
Manganese-4 2.60 E-08 !
Iron-59 6.85 E-08 :
Cobalt-57 1.67 E-08 I Cobalt-58 3.09 E-08 )
Cobalt-60 4.06 E-08 I Zinc-65 7.59 E-08 !
Strontium-89 5.00 E-08 ,
Strontium-90 5.00 E-08 i Niobium-95 2.91 E.08 1 Zirconium-95 5.62 E.08 Zirconium-97 3.29 E.08 ;
Molybdenum-99 1.60 E.08 Technetium-99m 3.29 E-08 Ruthenium-103 1.72 E-08 7 Silver-110m 3.64 E-08 Antimony-124 2.79 E-08 Antimony-125 6.41 E-08 Iodine-131 2.70 E.08 i Iodine-133 2.46 E-08 !
Cesium-134 2.80 E-08 '
Cesium-136 3.10 E-08 Cesium-137 3.90 E.08 ;
Barium-140 9.70 E-08 l Lanthanum-140 4.96 E-08 l Cerium-141 2.50 E-08 Cerium-144 1.45 E-07
- 2. DISSOLVED AND ENTRAINED GASES Krypton-85 8.16 E-06 Krypton-85m 4.92 E-08 Krypton-8 1.40 E-07 Xenon-131m 1.83 E-06 Xenon-133 1.27 E-07 Xenon-133m 3.39 E-07 ,
Xenon-135 3.65 E-08 I
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY'- DECEMBER 1987 MNCHO SECO NUCLEAR GENERATING STATION 3
C'A s l TABLE III-D LIOUID EFFLUENTS - RADIATION DOSE ESTIMATES TO THE '
MAXIMUM HYPOTHETICAL INDIVIDUAL 3RD 2ND UNITS OUARTER OVARTFB
- 1. a. Whole body dose mrem 2.81E-02(a) 1.07E-01(a)
- b. Percent Tech Spec Limit % 1.87E+00 7.13E+00
- 2. a. Organ dose mrem 5.13E-02(b) 4.12E-01(b)
- b. Percent Tech Spec Limit % 1.03E+00 8.24E+00 (a) Adult (b) Child - liver ;
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 l RANCHO SECO NUCLEAR GENERATING STATION l III. LIOUID EFFLUENTS Percent of Technical Soecification Limit Calculation Methodoloav l The percent of Technical Specification Limit tabulated in Table III-A was determined by calculation of the following parameters:
The percent of Technical Specification Limits tabulated in Table III-A is:
n I Ci _ X 100%
i-1 RPC) ,
Where: Cj - The average diluted concentration l n - Totai number of radionuclides identified. l MPCj - MPC of the ith radionuclide (10 CFR 20, Appendix B, Table II, Column 2) {
l Total curies released in each ;
category per quarter converted The average diluted concentration - to uCi l Total volume released (Part F in Os Table III-A) converted to ml.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
~~s JULY - DECEMBER 1987 g ,) RANCHO SECO NUCLEAR GENERATING STATION IV. SOLID HASTE ANG IRRADIATED FUEL SHIPMENT A. SOLID HASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of Haste Unit 6-month Est Total Period Error. %
- a. Spent resins, filter sludges, m8 0. . E evaoorator bottoms. etc. Ci 0. E . E
- b. Dry compressible waste, m8 1.17 E 02 3.00 E 01 contaminated eauioment. etc. C1 2.19 E 00 3.00 E 01
- c. Irradiated components, control m8 0. E . E rods. etc. 1Ci 0. E . E
- d. Other m8 0. E . E Ci 0. E . E
- 2. Estimate of major nuclide composition (by type of waste)
- a. NA %
- b. cobalt-58 % 3.00 E-01 silver-110m % 6.70 E-01 manaanese-54 % 7.70 E-01 O' cobalt-60
% 6.40 E-01 cesium-134 % 4.09 E 00 iron-55 % 1.50 E 01 cesium-137 % 1.33 E 01 nickel-63 % 1.13 E 01 tritium % 4.83 E 01
- c. NA
- d. NA
- 3. Solid Haste Disposition Number of Shioments Mode of Transoortation Destination 6 Truck (Sole Use Vehicle) Hanford Disposal Site, Richland, Washington
- 4. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shioments Mode of Transoortation Destination None N/A N/A EQIE: Dry compressible waste, contaminated equipment, etc. shipped in LSA containers. )
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 O RANCHO SEC0 NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR The estimate of error is based on combination of the following error estimates:
A. Airborne
- 1. Counting Error
- 2. Calibration' error of exhaust fans
- 3. Sample train flow rate meter error
- 4. 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 (HGDT) pressure gauge and flow rate me,te r.
B. Liquid
- 1. Counting error
- 2. Regenerant Hd d Up Tank (RHUT) release volume error
- 3. Retention basin dilution flow error
- 4. Retention basin outlet flow error 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
- 3. Particulate filter loss
- 4. Loss due to handling for iodine
- 5. Composit'e aliquots for liquids Error estimates for isokinetic sampling and airborne particulate plateout in monitor sample lines were not included bec&use no plant data exist on the subject. However, this does not necessarily mean that the errors are negligible.
The methods for establishing error estimates included communication with District 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 calibration set points data.
In determining the overall error in a release, error at one standard deviation and a bias were calculated. The error consists of random or indeterminate errors. Bias is influenced primarily by deterministic error which introduce a constant error into the data, y -- . - - . - _ . _ . _ _ . _ . . _ _ _ _ _
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT T JULY - DECEMBER 1987 d
RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR
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The error analysis was applied to the following release pathways. I
- 1. Auxiliary Building Vent (see note) 1
- a. Fission and activation gases l
- b. Iodines I
- c. Particulates
- d. Tritium
- 2. Haste Gas Decay Tank (HGDT)
- a. Fission and activation gases i
- b. Tritium
- 3. Reactor Building Vent f Fission and activation a.
- b. Iodines
- c. Particulates
- d. Tritium
- 4. Liquid Releases ;
I]
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 iodines and particulates that are released through the reactor building vent includes exhaust fan calibration error, not containment volume error. This is because iodines and particulates are vented on a continuous basis by the exhaust fan via a pre-filter, HEPA and charcoal filter. Also, error analysis for fission and activation. gases and tritium that are released through the reactor building vent includes containment volume error, not exhaust fan calibration error. l This is because fission and activation gases and tritium are released as a j function of containment volume. .
ILqta: Includes releases from the condenser air ejector, gland seal exhaust, and iodines and particulates from the HGDT. 1 The Auxilary Building Grade Level Vent was not included as a release pathway due to its inoperability.
The error for both airborne and liquid releases was determined at one standard deviation from the mean.
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i J SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 O' RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERRQR A. ERROR ANAi.YSIS FOR AIRBORNE RELEASES
- 1. AUXILIABY BUILDING STACK .
- a. Fission and Activation Gases Error * (o2 + 7,72 )
z 3.3% calibration error of exhaust fans z 6.9% process monitor flow serpoint error margin (3.32 + 6.92). 7,7 o counting error - (gross counts) x 100
- b. Iodine Ery_QI z (2 + 3.82)
= 3.3% calibration error of exhaust fans 1.9% process monitor flow rate setpoint error margin C (3.32 + _1,92 ) x 100 o counting error - (gross counts) x 100
- c. Particulate Error = (2 + 3.82)
Error is same as Iodine (auxiliary stack)
Bias: -5% handling loss
- d. Tritium Error' z (2 + 2 )
2 z 2% sample flow rate meter reading error j o counting error - (gross counts)% x 100 Bias: z5% collection efficiency *
- Available literature indicates that the collection loss is approximately 5%
for fritted bubblers of the type used by Rancho Seco. Rancho Seco uses a collection efficiency of 90%. Therefore, the actual bias is +5%.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT A JULY - DECEMBER 1987 V RANCHO SEC0 NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR
- 2. HASTE GAS DECAY TANK
- a. Fission and Activation Gases Error z (o2 + 2.82 )
z 2% calibration and reading error of HGDT pressure gauge 2 2% calibration and reading error of HGDT flow rate meter (22+2) 2 - 2.8 o counting error - (gross. counts) % x 100
- b. Tritium Error 2 (o2 + 2.82 )
e 2% reading error of sample flow rate meter z 2% reading and calibration error of HGDT flow rate meter (2 2 + 2 2)% x 100 O sias: +5x coiiectica efficiency error (see auxiiiary building vent tritium analysis)
- 3. REACTOR BUILDING VENT
- a. Fission and Activation Gases Error z (o2 + 2.82 )
z 5% containment volume error z 4.2% process monitor flow rate setpoint error margin (52 + 4.22 ) + 6.5 o counting error - (gross counts) x 100 Bias: -5% incomplete purge A Purge is a batch removal of Reactor Building air by the Reactor Building purge exhaust fan which discharges to the Reacter Building Stack.
The -5% bias was chcsen as a reasonable value for representing an estimate of incomplete purgs.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT A JULY - DECEMBER 1987 U RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR -
- b. Iodine Error 2 (o 2 + 3.62 )
3.3% calibration error of exhaust fans z 1.4% process monitor rate setpoint error margin (3.32 + 1,42 ) - 3.6 e counting error - (gross counts)% x 100 Bias: -5% not collected by charcoal
- c. PJrticulates Error 2 (o 2 + 3.62 )
Error is same as for Iodines (Reactor Building)
Bias: -5% handling loss
- d. Tritium Error z (o 2 + 5.4 )
2 O z 5% coatalameat voiu,e error 2 2% flow rate meter error (52+2) 2 - 5.4 o counting error - (gross counts)%x 100 Bias: 5% collection efficiency (see auxiliary building l vent tritium analysis) )
-5% incomplete purge i
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION HQII: The 12/23 to 12/26 Particulate sample from the Reactor Building Vent for Strontium 90 and Strontium 89 was misplaced after the sample was analyzed for gamma emitting activity. A detailed report of this occurrence is documented in Occurrence Description Report 87-1053.
The technician who discovered the misplaced sample found two samples in the envelope for the Auxiliary Building Vent sample.
The vent air samples are identical filter papers which are not visibly different. Because no gamma emitting radioactivity was detectr e on the samples, it was not possible to distinguish the Reactor Building Vent sample from the Auxiliary Building Vent sample. The Reactor Building Vent sample that was lost represents 1/24 of the sampling time for the period of July to December 1987.
Any Strontium - 89 that has been detected in other Reactor Building Vent samples during this time period have all had the same value.
Therefore, the lost data most likely represents only about 4% of the total activity released. Thus, this incident has had no affect on the estimation of error in connection with the calculation of radioactive gaseous releases from Rancho Seco Nuclear Generating Station.
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 O- RANCHO SECO NUCLEAR GENERATING STATION V. ESTIMATION OF ERROR B. ERROR ANALYSIS FOR LIOUID RELEASES
- 1. Liauid Effluent Release Error (o2 3,42 )1/2
- a. RHUT z 5% RHUT Volume o counting error - (gross counts) x 100
- b. Retention Basin z 1% inlet dilution volume error .
1% outlet flow error
- s. Dilution Flow z 1.3% discharge canal ficw rate error O Totei error
<s . 32.32 . i.3 )
a 2 3.4 O
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 O RANCHO SEC0 NUCLEAR GENERATING STATION VI. RADIOLOGICAL IMPACT ON MAN 1 1
This section contains tables which describe the radiological impact to both actual and hypothetical individuals. Tables include:
VI-A Compliance with 10 CFR 50, Appendix I VI-B Percent of 10 CFR 50 Appendix I for Table VI-A ,
l VI-C Dose Assessment for Unrestricted Area 3 Within the Site l Boundary l l
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j SEHIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i O JULY - DECEMBER 1987 i !
V RANCHO SECO NUCLEAR GENERATING STATION l TABLE VI-A j COMPLIANCE WITH 10 CFR 50 APPENDIX I Dose (Millirem) f 3RD 4TH -f SOURCE OUARTER OUARTER l I
A. Gaseous Effluents
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- 2. Noble Gases [
?
- a. gamma (mrad) 1.68E-08 0.0 !
t
- b. beta '(mrad) 1.90E-06 0.0 f B. Liquid Effis.ents t
- 1. wt. ole bod 9 1.95E-02 1.07E-01 l 0 ?. orhin 4'"
! 5.13E-02 4.12E-01 l
0.0 0.0 C. 7'01rict Radiation
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i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l JULY - DECEMBER 1987 i O RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-8 PERCENT OF 10 CFR 50 APPENDIX I FOR TABLE VI-A PERCENT (%) ;
3RD 4TH SOURCE OUARTER 00ARTER A. Gaseous Effluents l
- 2. Noble Gases
- a. gamma 3.36E-7 N/A
- b. beta 1.90E-5 N/A B. Liquid Effluents
- 1. whole body 1.30E+00 7.13E+00 0 2. organ 1.03E+00 8.24E+00 C. Direct Radiation N/A N/A
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 i RANCHO SECO NUCLEAR GENERATING STATION TABLE VI-C 1 DOSE ASSESSHENT FOR UNRESTRICTED AREAS ,
HITHIN THE SITE BOUNDARY l l
(HILLIREH) 3RD 4TH .
LOCATION OUARTER OUARTE8 A. Design City (1) 3.68E-03 2.46E-03 (East 250 meters)
B. Harehouse (2) 4.45E-03 2.97E-03 (East 225 meters)
C. Park Kiosk (3) 1.76E-03 9.76E-04 (East North East 525 meters)
D. Visitor Center (4) 3.33E-03 1.80E-03 (East North East 225 meters)
O The above doses represent the Total Body mrem dose and includes contributions from the plume, ground, and inhalation. The dose recorded is the highest between adult, teenager, child, or infant.
(1) 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week (2) 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week (3) 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> per week (4) 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> per week I
O .
)
t
i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION II. METEOROLOGICAL DATA The joint frequency distributions for this report period are presented on pages 39 thru 66. This data shows the stability class wind direction and number of hours of occurrence for the indicated conditions. This data was determined in accordance with USNRC Regulatory Guide 1.111, "Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
Heteorological information f.'om the sites meteorological tower was used to complete the data for the joint frequency distributions. The meteorological tower is setup and run in accordance with USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs." During the third quarter of 1987, the meteorological data acquisitions system recovered 96.9% of the data. During the fourth quarter 1987, 90.4% of the data was recovered.
- as -
O
l
.. l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987
(~5 s_) RANCHO SEC0 NUCLEAR GENERATING STATION )
l CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 l STABILITY CLASS: A ELEVATION: GROUND LEVEL RELEASE !
l WIND SPEED (MPH) AT 10 METER LEVEL WIND -
DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL i i
N 0 0 0 0 0 0 0 NNE O 1 0 0 0 0 1 l
NE O O O O O O 0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O 1 0 0 0 0 1 SSE O O O O O O O S 0 2 3 0 0 0 5 SSW 0 4 5 2 0 0 11 SW 0 6 17 14 0 0 37 WSW 0 22 88 17 0 0 127 l W 0 21 54 1 0 0 76 WNW 0 3 3 1 0 0 7 NW 0 2 2 0 0 0 4 N:lW 0 0 0 0 0 0 0 T 0'T C. 0 62 172 35 0 0 269 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 66 8
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT A JULY-DECEMBER 1987 V RANCHO SEC0 NUCLEAR GENERATING STATION CONTINU0US RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: B ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 1 0 0 0 0 1 NNE O O O O O O O NE O 0 0 0 0 0 0 ENE O O O O O O O E O O O O O O O ESE O 0 0 0 0 0 0 SE O 1 0 0 0 0 1 SSE O O O O O O O S 0 2 1 0 0 0 3 SSW 0 4 4 2 0 0 10 SW 0 2 9 1 0 0 12 WSW 0 20 21 4 0 0 45 W 0 6 16 1 0 0 23 WNW 0 1 2 0 0 0 3 1
NW 1 1 2 0 0 0 4
)
NNW 0 0 0 0 0 0 0 TOTAL 1 38 55 8 0 0 102 i VARIALLE WINDS (hours): O PERIODS OF CALMS (hours): 0
)
HOURS OF MISSING DATA: 66
t t
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 :
O* RANCHO SECO NUCLEAR GENERATING STATION l CONTINU0US RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: C ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 0 0 0 0 0 0 4 NNE O O O O O 0 0 NE O 0 0 0 0 0 0 ENE O O O O O O O E O O O O O O 0-ESE' 0 0 0 0 0 0 0 SE O O O O O O O SSE O 1 0 0 0 0 1 S 0 1 1 0 0 0 2 SSW 0 0 3 1 0 0 4 SW 1 4 12 0 0 0 17 WSW 0 13 32 1 0 0 46 I W 0 18 16 1 0 0 35 WNW 1 3 0 0 0 0 4 i
NW 0 0 1 0 0 0 1
- NNW 0 0 0 0 0 0 0 TOTAL 2 40 65 3 0 0 110 VARIABLE WINDS (hours)
- 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 66
l l
l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i T JULY-DECEMBER 1987 l
{V RANCHO SEC0 NUCLEAR GENERATING STATION j CONTINUOUS RELEASE METEOROLOGY f HOURS AT EACH WIND SPEED AND DIRECTION -
PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: D 1 ELEVATION: GROUND LEVEL RELEASE ,
WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 1 3 0 0 0 0 4 '
NNE O O O O 0 0 0 NE 1 0 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E 2 0 0 0 0 0 2 ESE O O O O O O O SE 1 5 0 0 0 0 6 SSE 2 7 1 0 0 0 10 S 1 14 5 ? 0 O 23 SSW 1 15 12 1 0 0 29 SW 4 39 33 3 0 0 79 j WSW 3 98 72 12 0 0 185 l W 2 81 36 2 0 0 121 WNW 3 17 6 0 0 0 26 NW 1 7 5 0 0 0 13 NNW 1 1 0 0 0 0 2 TOTAL 24 287 170 21 0 0 502 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 66 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION
. CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: E ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 5 4 0 0 0 0 9 NNE 5 1 0 0 0 0 6 NE 7 5 0 0 0 0 12 ENE 4 0 0 , 0 0 4 E 4 1 0 0 0 0 5 ESE 11 9 0 'O O O 20 SE 12 29 4 1 0 0 46 SSE 13 29 12 5 0 0 59 S 28 35 5 1 0 0 69 SSW 25 42 7 0 0 0 74 SW 31 55 27 1 0 0 114 WSW 26 68 55 4 0 0 153 W 26 40 7 0 0 0 73 WNW 22 23 0 0 0 0 45
. NW 9 9 0 0 0 0 18 NNW 11 6 0 0 0 0 17 TOTAL 239 356 117 12 0 0 724
- VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 66 i
r ------e ,,--,.,-,.,-r----.,.,,,-,-g,,_,.e-- n.mw_m_w7-, -, .-m,v--e-, p gm y , g,m w ,,w e
SEMIANNUAL FADI0 ACTIVE EFFLUENT RELEASE REPORT
(~)
\/
JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY l HOURS AT EACH WIND SPEED AND DIRECTION j PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: F !
ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 10 3 0 0 0 0 13 NNE 16 7 0 0 0 0 23 NE 14 5 0 0 0 0 19 ENE 10 2 0 0 0 0 12 E 4 4 0 0 0 0 8 ESE 6 5 0 0 0 0 11 SE 1 12 1 0 0 0 14 SSE 5 16 1 0 0 0 22 S 7 17 0 0 0 0 24 SSW 2 15 4 0 0 0 21 SW 7 24 4 0 0 0 35 WSW 11 20 11 0 0 0 42 W 9 7 0 0 0 0 16 WNW 7 3 0 0 0 0 10 NW 7 9 0 0 0 0 16 NNW 6 4 0 0 0 0 10 TOTAL 122 153 21 0 0 0 296 VARI.\BLE WINDS (hours): O PERIOOS OF CALMS (hours): 0 HOUR: OF MISSING DATA: 66 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O
V JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION CONTINU0US RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: G .
ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 6 3 1 0 0 0 10 NNE 5 9 0 0 0 0 14 NE 5 10 0 0 0 0 15 ENE 6 4 0 0 0 0 10 E 2 4 1 0 0 0 7 ESE 2 11 7 1 0 0 21 SE 6 3 0 0 0 0 9 SSE 1 4 1 0 0 0 6 S 2 4 0 0 0 0 6 SSW 1 2 0 0 0 0 3 SW 3 7 0 0 0 0 10 WSW 2 4 1 0 0 0 7 W 5 1 0 0 0 0 6 WNW 3 1 0 0 0 0 4 NW 2 6 0 0 0 0 8 NNW 2 1 0 0 0 0 3 TOTAL 53 74 11 1 0 0 139 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 ,
HOURS OF MISSING DATA: 66 l i
---.-,_,-7--,ym--_ y
_.,,7,,,,_.__,,._,y,,-.,,y, ,. , , , , ,,, py,.,-,,,-,,.3 ,---_w ,yy_ , . -,,w-,,.
- . e--m , - ,-- -- ,,w,,%,, , . , . - , -
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENE",ATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: A ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 0 0 0 0 0 0 NNE O O O O 0 0 0 NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O G 0 0 0 SE O O O O O O 0 SSE O O O O O O O S 0 2 3 0 0 0 5 SSW 0 1 1 0 0 0 2 SW 0 6 7 9 0 0 22 WSW 0 17 69 15 0 0 101 W 0 20 43 1 0 0 64 WNW 0 3 3 1 0 0 7 NW 0 2 2 0 0 0 4 NNW 0 0 0 0 0 0 0 TOTAL 0 51 128 26 0 0 205 VARIABLE WINDS (hours): O PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 59
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 19J7 QUARTER 3 STABILITY CLASS: 3 ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 1 0 0 0 0 1 ,
1 NNE O O O O O O O !
NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O 0 SE O 1 0 0 0 0 1 SSE O O O O O O O S 0 1 1 0 0 0 2 SSW 0 2 4 2 0 0 8 SW 0 1 7 1 0 0 9 WSW 0 17 18 3 0 0 38 l
W 0 6 15 1 0 0 22 '
WNW 0 0 2 0 0 0 2 l NW 0 1 2 0 0 0 3 ,
NNW 0 0 0 0 0 0 0 TOTAL 0 30 49 7 0 0 86 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 59 i
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
( JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 l STABILITY CLASS: C i ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-13 19-24 24 + TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O 0 SSE I O 1 0 0 0 0 1 S 0 1 1 0 0 0 2 SSW 0 0 1 1 0 0 2 SW 1 4 11 0 0 0 16 )
WSW 0 11 28 1 0 0 40 W 0 17 16 1 0 0 34 WNW 0 3 0 0 0 0 3 NW 0 0 1 0 0 0 1 NNW 0 0 0 0 0 0 0 TOTAL 1 37 58 3 0 0 99 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 59 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION l
BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION !
PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: D .
ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 1 3 0 0 0 0 4 NNE O O O 0 0 0 0 NE 1 0 0 0 0 0 1 ENE O O O O O O O E 2 0 0 0 0 0 2 ESE O 0 0 0 0 0 0 SE 1 3 0 0 0 0 4 ;
SSE 1 6 1 0 0 0 8 l S 1 9 5 3 0 0 18 {
SSW 1 10 10 1 0 0 22 SW 2 34 23 2 0 0 61 WSW 3 82 61 9 0 0 155 W 2 78 34 2 0 0 116 WNW 2 17 6 0 0 0 25 NW 1 7 5 0 0 0 13 NNW 1 1 0 0 0 0 2 TOTAL 19 250 145 17 0 0 431 VARIABLE WINDS (hours): 0 PERIODS OF CAlitS(hours): 0 l HOURS OF MISSING DATA: 59 i
I
. . . - - . - - =
l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION i
l BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION :
PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: E ELEVATION: GROUND LEVEL RELEASE ;
WIND SPEED (MPH) AT 10 METER LEVEL <
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 4 4 0 0 0 0 8 NNE 3 1 0 0 0 0 4 I NE 7 '3 0 0 0 0 12 ENE 4 0 0 0 0 0 4 E 4 1 0 0 0 0 5 ESE 10 7 0 0 0 0 17 SE 11 28 2 1 0 0 42 SSE 9 26 12 5 0 0 52 S 23 31 5 1 0 0 60 SSW 20 38 6 0 0 0 64 SW 29 47 25 1 0 0 102 )
WSW 24 54 52 4 0 0 134 W 24 34 7 0 0 0 65 1
WNW 20 23 0 0 0 0 43 i NW 8 7 0 0 0 0 15 NNW 11 6 0 0 0 0 17 l
TOTAL 211 312 109 12 0 0 644 t
VARIABLE WINDS (hours): 0 i PERIODS OF CALMS (hours): 0 l HOURS OF MISSING DATA: 59 l l
I u
l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
. JULY-DECEMBER 1987 j RANCHO SECO NUCLEAR GENERATING STATION a
j BATCH RELEASE METEOROLOGY 4
HOURS AT EACH WIND SPEED AND DIRECTION i t
4 PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: F 1 ELEVATION: GROUND LEVEL RELEASE
- 4 WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL
! N 9 2 0 0 0 0 11 NNE 15 7 0 0 0 0 22 i NE 13 4 0 0 0 0 17
(
ENE 8 2 0 0 0 0 10 .
i E 3 3 0 3 0 0 6 ESE 6 4 0 0 0 0 10 ,
SE 1 12 0 0 0 0 13 SSE 3 15 1 0 0 0 19 S 6 13 0 0 0 0 '19 l' SSW 3 11 3 0 0 0 17 I
SW 5 19 4 0 0 0 28 WSW 7 12 10 0 0 0 29 i
W 9 7 0 0 0 0 16 WNW 6 3 0 0 0 0 9 4
NW 6 , 0 0 0 0 14 1 NNW 5 4 0 0 0 0 9
.l - :
TOTAL 105 126 18 0 0 0 249 i VARIABLE WINDS (hours): 0
- PERIODS OF CALMS (hours): 0 i i HOURS OF MISSING DATA: 59 l i
i
'l
,, . - - - , - . , - , n ,,., , , , - , - , , - -,-,, -, .- , - . . , , , - . - - - , , , , _ - , -,.,-,_..,-----,w--w-,,,,e.-:,---~er.,e- ~ --n,,.--,v-
-.l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATIO!!
BATCH RELEASE HETEOROLOGY !
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 3 STABILITY CLASS: G ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL ,
N 3 3 1 0 0 0 7 NNE 6 9 0 0 0 0 15 NE 6 10 0 0 0 0 16 ENE 6 4 0 0 0 0 10 E 1 4 1 0 0 0 6 ESE 2 9 5 0 0 0 16 SE 6 2 0 0 0 0 8 SSE 1 1 0 0 0 0 2 S 0 2 0 0 0 0 2 SSW l 1 0 0 0 0 2 SW 3 6 0 0 0 0 9 WSW 2 2 1 0 0 0 5 l
W 5 1 0 0 0 0 6 WNW 3 1 0 0 0 0 4 NW 2 7 0 0 0 0 9 NNW 1 1 0 0 0 0 2 TOTAL 48 63 8 0 0 0 119 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 59 l i
l
--- . _ - - . . - . . . ~
i i
I SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION CONTINU0US RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 4 ,
STABILITY CLASS: A ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13 18 19-24 24 +., TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O 0 0 ENE O O O O O O O E O O O O O O O ESE O O O 0 0 0 0 SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 1 1 1 1 0 4 WSW 0 2 1 12 0 0 15 W 0 3 2 4 0 0 9 l WNW 0 1 3 4 0 0 8 l
NW 0 0 2 2 0 0 4 l I
NNW 0 0 0 1 0 0 1 TOTAL 0 7 9 24 0 0 41 VARIABLE WINDS (hours): 0 '
PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 308 SEMIANNUAL RADI0 ACTIVE EFFLVZNT RELEASE REPORT f_s) JULY-DECEMBER 1987 V' RANCHO SEC0 NVCLEAR GENERATING STATION CONTINV0VS RELEASE METEOROLOGY H0VRS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QVARTER 4 STABILITY CLASS: B ELEVATION: GR0VND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 O 0 0 'O O 0 NNE O O O O O O 0 NE O O O O 0 0 0 ENE O O O O O 0 0 E 0 0 0 0 0 0 0 ESE O O O O 0 O O l t SE O O 1 0 0 0 1 SSE O 1 4 0 0 0 5 S 0 0 0 1 0 0 1 SSW 0 0 1 2 0 0 3 SW 0 2 1 2 0 0 5 WSW 0 3 3 5 0 0 11 W 0 4 2 9 0 0 15 WNW 0 0 0 4 0 0 4 NW 0 0 0 2 1 0 3 NNW 0 0 0 0 0 0 0 TOTAL 0 10 12 25 0 0 48 VARIABLE WINDS (hours): O PERIODS OF CALMS (hours): 0 l HOURS OF MISSING DATA: 308 l l\ l
l l
..l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION l
\
CONTINUOUS RELEASE METEOROLOGY l HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 1987 QUARTER 4 :
STABILITY CLASS: C !
ELEVATION: GROUND LEVEL RELEASE !
WIND SPEED (MPH) AT 10 METER LEVEL WIND [
DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL :
N 0 0 0 0 0 0 0 NNE O 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 f
ENE 0 0 0 0 0 0 0 -
E 0 0 0 0 0 0 0 ,
ESE 0 0 0 0 0 0 0 !
SE 0 0 1 0 0 0 1 SSE O 1 2 3 0 0 6 i
S 0 0 2 2 0 0 4 i SSW 0 0 0 1 0 0 1 !
SW 0 1 0 1 0 0 2 WSW 0 3 4 7 0 0 14 W 0 4 2 4 0 0 10 WNW 0 2 1 7 0 0 10 NW 0 0 1 5 0 0 6 NNW 0 0 0 0 0 0 0 TOTAL 0 11 13 30 0 0 54 VARIABLE VIND3(hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 308 I
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT >
O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STA"ION :
CONTINU0US RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 4 STABILITY CLASS: D ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL l
N 2 3 2 0 0 0 7 !
NNE 2 0 0 0 0 0 2 NE 1 0 2 0 0 -0 3 ENE 1 2 0 1 0 0 4 E 1 2 1 0 0 0 4 ESE 2 9 11 1 0 0 23 I O se 2 12 2s 22 3 o e4 SSE 10 15 29 16 3 0 73 S 4 26 5 2 1 0 38 SSW 8 8 10 3 0 0 27 SW 3 13 8 4 1 0 29 WSW 7 25 10 3 1 0 46 l W 6 23 3 4 0 0 '36 WNW 2 9 8 5 0 0 24 NW 6 9 9 9 10 11 54 NNW 4 6 5 4 9 0 28 TOTAL 59 162 128 74 28 11 462 VARIABLE WINDS (hours): O PERIODS OF CALMS (hours): 0 l HOURS OF MISSING DATA: 308 l
l l
l 1
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i JULY-DECEMBER 1987 i RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 4 STABILITY CLASS: E ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 MITER LEVEL WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL l N 6 8 9 0 0 2 25 NNE 4 5 1 0 0 0 10 NE 6 3 8 0 0 0 17 ENE O 2 3 2 0 0 7 E 4 4 3 4 0 0 20 ESE 7 11 22 21 4 3 68 SE 7 21 50 67 12 17 174 SSE 6 11 16 15 1 2 51 S 7 13 8 2 0 0 32 SSW 3 8 2 1 1 0 15 SW 5 11 11 2 0 0 29 WSW 5 9 5 7 2 0 28 W 5 6 1 3 0 0 15 WNW 3 6 5 2 0 0 16 l 1
NW 3 10 12 10 8 0 43 l NNW 4 7 17 4 4 1 37 l TOTAL 75 137 178 140 32 25 587 {
VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 308 .
I
l t
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT '
JULY-DECEMBER 1987 ks RANCHO SECO NUCLEAR GENERATING STATION t
CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987 QUARTER 4 STABILITY CLASS: F ELEVATION: GROUND LEVEL RELEASE l WIND SPEED (MPH) AT 10 METER LEVEL DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL
< N 7 3 3 0 1 0 14 NNE 2 8 7 0 0 0 17 NE 10 7 0 1 0 0 10 ENE 5 12 1 0 0 0 18 E 6 19 10 2 0 0 37 ESE 4 25 40 3 0 0 72 SE 1 19 24 5 0 0 49 SSE 6 8 8 1 0 0 23 S 5 4 6 0 0 0 15 SSW 9 3 0 0 0 0 12 SW 5 3 4 0 0 0 12 WSW 4 7 3 2 0 0 16 W 4 2 1 1 0 0 8 WNW 5 8 7 1 0 0 21 4 NW 4 8 11 5 1 0 29 NNW 5 11 6 9 5 1 37 j TOTAL 82 147 131 30 7 1 398 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 308 l 1 i
1 SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT !
JULY-DECEMBER 1987 l RANCHO SECO NUCLEAR GENERATING STATION l
CONTINU0US RELEASE METEOROLOGY I
. HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 1987 QUARTER 4 !
STABILITY CLASS: G l
, ELEVATION: GROUND LEVEL RELEASE ;
WIND SPEED (MPH)_AT 10 METER LEVEL '
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL 2
N 3 4 5 1 0 0 13 l NNE 11 16 8 3 0 0 38 NE 18 27 9 4 0 0 58 ENE 15 18 6 0 0 0 39 E 8 11 23 2 0 0 44 ESE 1 8 16 2 0 0 27
)
8 3 11 1 0 0 17 2 1 0 0 0 11 l S 0 2 3 1 0 0 6 SSW 5 2 0 0 0 0 7 SW 5 3 2 0 0 0 10 WSW 2 4 1 0 0 0 7
)
W 3 1 1 0 0 0 5 i WNW 2 0 1 1 0 0 4 j
NW 1 4 2 1 0 0 8 j NNW 4 6 4 2 0 0 16
! TOTAL 88 111 93 18 0 0 310 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 i HOURS OF MISSING DATA: 308 3
. - , - - - -, . - - . . , - l
p SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l Q JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION ;
I PERIOD OF RECORD: 1987 QUARTER 4 i STABILITY CLASS: A ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 0 0 1 0 0 0 NNE O O 0 0 0 0 0 NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 l
1 SSW 0 0 0 0 0 0 0 4
SW 0 1 1 1 1 0 4 j WSW 0 2 1 12 0 0 15 I
W 0 3 2 4 0 0 9 WNW 0 1 3 4 0 0 8 l
NW 0 0 2 2 0 0 4 NNW 0 0 0 1 0 0 1
, TOTAL 0 7 9 24 1 0 41 1
i VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 265 i
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY )
HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD: 1987 QUARTER 4 STABILITY CLASS: B i ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL ,
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE 0 0 0 0 0 0 0 ,
E 0 0 0 0 0 0 0 ,
ESE O O O O O O O SE O O O O O O O !
SSE O 1 2 0 0 0 3 S 0 0 0 1 0 0 1 SSW 0 0 1 2 0 0 3 SW 0 2 1 2 0 0 5 ;
WSW 0 3 3 5 0 0 11 l
W 0 4 2 9 0 0 IS )
WNW 0 0 0 4 0 0 4 NW 0 0 0 2 1 0 3 i i
NNW 0 0 0 0 0 0 0
^
TOTAL 0 10 9 25 1 0 45 <
VARIABLE WINDS (hours): 0 .
PERIODS OF CALMS (hours): 0 l
HOURS OF MISSING DATA: 265 l
i i
. - _ _ __ = . - . _. - . -. -
4 i
.. l L
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1
JULY-DECEMBER 1987 '
- RANCHO SECO NUCLEAR GENERATING STATION i i BATCH RELEASE METEOROLOGY l HOURS AT EACH WIND SPEED AND DIRECTION j PERIOD OF RECORD: 1987 QUARTER 4 l STABILITY CLASS: C L
ELEVATION: GROUND LEVEL RELEASE .
WIND SPEED (MPH) AT 10 METER LEVEL
, WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL l
N 0 0 0 0 0 0 0 NNE O O O O O O 0 NE O O O O O O O !
ENE O O O O O O O ,
E O 0 0 0 0 0 0 ESE O 0 0 0 0 0 0 ,
]
) SSW 0 0 0 1 0 0 1 ;
J l j SW 0 0 0 1 0 3 1 WSW 0 3 4 7 0 0 14 W 0 4 2 4 0 0 10 WNW 0 2 0 6 0 0 8 NW 0 0 0 2 0 0 2 i,'
NNW 0 0 0 0 0 0 0 TOTAL 0 9 8 26 0 ~0 43
, VARIABLE WINDS (hours): 0 j PERIODS OF CALMS (hours): 0 t
HOURS OF HISSING DATA: 265
- 1 i
__m ___ _ __ _ __ _ _
') '
- k , s
? 13 4
' [ ,
( o t l' l // '
i 3
'/ ,k j '
'S ,
r SEMIANNUAL RACTSACTIVE EFFLUENT RELEASE REPORT
! )S h i bylY-DECEMBER 1987 y !'
'IA1CHO SECd NUCLEAR GENERATING STATION $
) )
' .l Y. . > , l
\ \ BATCH RELEASE METEOROLOGY J
4t 3 3 HOURS AT EACH WIND > SPEED AND DIRECTION / l'
(/. i ? t - I
< DIRIOD 0F RECORD: 1987 QUARTERi4' )[ >
y 3TABILITY CLASS: 0 ,
< f ELEVATION: /
- 3'j .q GROUND /.EVELREl. EASE
/ ,/ , WINDSPEED(MPH)AT10 MET,i[ LEVEL '
i i
i e .
]j,',/))tWlNDi DIRECT 7,0N i
1-3 4-7[ 1 8-12 13-16\ Y
' 19-24 24 +
/
g0TAL ;
~,
. j 4 . N t
' ' 2 3 s 2 0 0 0, 7 i
, ,( ; l '
I R NNE .. ,.
' 2, 0, / 0 0 0 01 2 .
/ , , 'i ( '
I ,
3' ,h % a 'O 1 0 0 0' I' s2 !
4 .
( <( l' s< gs Ed.E i 'f i), O I i 0 0 \ 43 j
-l
- 0) ,
E s 1 1 0 a c 0 0 s
& i
' .) ,
i ESE i ,' 1 3 71 1 i
, 0 0 <
12* - :
SE 1 4 17 11 2 0 35
, , o SSE +
,1 4 11 22 ' / 7 l -
y
) ,- 0 46 !
S '2 7 4 2 I 1. 0 16
) % .I i SSW 3 ,
2 10 3 3
'O '
O 18 t
't SW 0 9 8 4 '
1 0 22 I
's.i I e' i
,) l /\,33 j WSW
) ,
2 17 10 3 0 t
l f W ( 5 18 2 4 , b 0 29
'/ ; 1 WNW /, ; 1 8 4 5 ,0 0 18 , i
~
l -
I iW ') 3 8 5 1 5 l 8 28
., NNW 2 4 Y 2 7 , 0 18
}/
~
TOTAL T 30 98 06 44
~
.171 '
, 8 .291
\ t 9 .
"ARIABLE 31kCS(hours): ./0
)
9ER1'0DS OF CA _MS(hours): e(0 .!
j;HQURS OF MI5' SING CATA: 265; .t 4;
,il l ,
i 61 , i L<
rl
( 1 . , ,
~ ,l ;
D r \
1 , f' .\l 5,
, , e,1 ) *I ,, '
-( / t
\ f ,3 ! i\
J1 j' /jf t
'f a
-.m
.' ..,_m.__._.. ) ~ _ _ __ _ _ . -
f SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 Os RANCHO SEC0 NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD 0F RECORD: 1987 QUARTER 4 STABILITY CLASS: E ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL ;
N 2 4 6 0 0 0 12 l NNE 3 0 1 0 0 0 4 NE 3 1 8 0 0 0 12 ENE 0 1 3 2 0 0 6 E O 3 8 2 0 0 13 ESE 5 5 11 9 0 1 31 SE 6 12 22 34 8 12 94 SSE 3 8 11 9 0 2 33 S 6 9 5 1 0 0 21 SSW 3 4 2 1 1 0 11 SW 3 9 11 2 0 0 25 WSW 4 2 5 7 2 0 20 W 4 4 1 3 0 0 12 WNW 2 4 4 2 0 0 12 NW 0 5 8 5 6 0 24 NNW 2 6 10 3 1 0 22 TOTAL 46 77 116 80 18 15 352 VARIABLE WINDS (hours): O PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 265
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 b RANCHO SEC0 NUCLEAR GENERATING STATION l
BATCH RELEASE METEOROLOGY l HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD: 1987 QUARTER 4 STABILITY CLASS: F 1
ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND 4-7 8-12 13-18 19-24 24 +
DIRECTION 1-3 TOTAL N 5 1 2 0 0 0 8 NNE 2 3 5 0 0 0 10 ,
NE 5 3 0 1 0 0 9 ENE 4 5 1 0 0 0 10 E 1 11 8 2 0 0 22 ESE 1 9 27 3 0 0 40 SE 1 11 15 5 0 0 32 SSE 3 6 6 1 0 0 16 S 2 3 6 0 0 0 11 SSW 3 1 0 0 0 0 4 1
SW 4 0 4 0 0 0 8 WSW 3 7 3 2 0 0 15 W 3 1 1 1 0 0 6 l WNW 4 4 6 1 0 0 15 NW 1 6 8 4 1 0 20 NNW 3 8 4 2 0 0 17 TOTAL 45 79 98 22 1 0 243 VARIABLE WINDS (hours): O PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 265
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l JULY-DECEMBER 1987 l RANCHO SEC0 NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1987- QUARTER 4 STABILITY CLASS: G ELEVATION: GROUND LEVEL RELEASE WIND 3 PEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 24 + TOTAL N 2 2 5 1 0 0 10 NNE 7 14 8 3 0 0 32 NE 10 12 9 4 0 0 35 ENE 5 9 5 0 0 0 19 E 4 6 10 2 0 0 22 ESE 1 5 13 2 0 0 21 SE 1 1 5 1 0 0 8 SSE 8 2 1 0 0 0 11 S 0 2 3 1 0 0 6 SSW 2 1 0 0 0 0 3 SW 3 1 2 0 0 0 6 WSW 2 2 1 0 0 0 5 W 2 0 1 0 0 0 3 WNW 2 0 1 1 0 0 4 NW 1 3 1 1 0 0 6 NNW 1 2 4 2 0 0 9 TOTAL 51 62 18 0 0 0 200 VARIABLE WINDS (hours): 0 PERIODS OF CALMS (hours): 0 HOURS OF MISSING DATA: 265
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 7 JULY-DECEMBER 1987 (V RANCHO SEC0 NUCLEAR GENERATING STATION VIII. 0FFSITE DOSE CALCULATION MANUAL (00CM) CHANGES A. INTERIM CHANGE TO THE ODCM On December 9, 1987 an interim revision to the ODCM was ,
approved. The changes made are summarized on Table VIII-A. l Appendix E is a copy of the interim revision. I B. DETERMINATION OF EFFECT OF CHANGES l
There are two changes to the Interim Revision of the ODCM which ;
may affect the results of offsite dose calculations and monitor I setpoints. The bioaccumulation factor for fish was changed {
from 1400 to 2000. The annual uptake of fish for the I hypothetical adult age group was reduced from 35 to 21 j kilograms per year. In order to test the effect of these j changes, two test runs were made using the LADTAP computer j program. The LADTAP computer program uses the models and I methods as prescribed in the Offsite Dose Calculation Manual.
Both runs involved a hypothetical release of 1 Curie of Cs-137.
The test runs showed that the new factors resulted in a ;
computed dose for the total body of the maximum hypothetical adult which is 9.98 % lower than the dose computed with the old O
V factors. This reduction in computed dose is not a reduction in the accuracy or reliability of offsite dose calculations for I liquid effluents. The increase in the bioaccumulation factor i was made because studies by Lawrence Livermore National '
Laboratory (LLNL) indicated that a factor of 1400 was too low.
The LLNL studies show that the bioaccumulation factors for fish in Clay Creek are similar to those used in USNRC Regulatory Guide 1.109. The LLNL study, UCID-20295, among other things determined the bioaccumulation factor of Bluegill and Bass at several different locations. The geometric mean of the bioaccumulation factor for these field samples was 1990. The .
recommended value in USNRC Regulatory Guide 1.109 *s 2000. !'
Thus, use of the factor 2000 increases the accuracy of the calculation.
f i
)
i
.1 1
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT -
l JULY-DECEMBER 1987
['dm'l RANCHO SECO NUCLEAR GENERATING STATION B. DETERMINATION OF EFFECT OF CHANGES - Continued The original estimate of the fish consumption factor of 35 kilograms per- year was based on the total mass of the fish caught. Since only a portion of the fish is consumed, a lower weight is more realistic. The NRC regulatory guide value of 21 ,
kilograms - per year is chosen because this more accurately l reflects the actual mass of fish consumed by the maximum hypothetical user.
The monitor setpoint equations were changed so that the output l of the equation would be in microCuries per cubic centimeter.
This was done because the new monitors readout in microcuries per cubic centimeter. This change does not result in a change to the monitor setpoint other than to change units from counts per minute to microcuries per cubic centimeter.
O .
i l
, - . . - , - ~ . - - - , , . - - , = ~ -< -. . . - - , - - , - -
- - - ~ ~ - + ~ , - - , - -
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987
- RANCHO SEC0 NUCLEAR GENERATING STATION TABLE VIII-A
SUMMARY
OF INTERIM REVISION OF THE OFFSITE DOSE CALCULATION MANUAL PAGE NUMBER
SUMMARY
OF CHANGE 17 Correct misspelling of the word "uptake".
18 Correct misspelling of the word "dose".
19 Change the equilibrium bioaccumulation factor for Cesium in freshwater fish from 1400 to 2000.
20 Change the Usage Factor for the adult consumption of freshwater fish from an annual value of 35 kg/yr to 21 kg/yr.
52 Change the words "count rate", "ncpm" to "reading" and "uCi/ml" respectively. Delete equation 3.2-6 and the cefinition of "Ei".
() 56 Change the words "count rate", "ncpm" to "reading" and "uCi/ml" respectively. Change equation 3.2-10 to read:
C.R. -
(1.25]ECi)/F i
57 Delete the definition of "Ei". Change the term "cpm" to "uCi/ml".
58 Delete Table 3.2-2 and it's notes.
SEMIANNUAL P.ADICAFTIVE EFFLUENT RELEASE REPORT Il
(/
JULY-DECEMBER 1987 R/.NCHO SECO NUCLEAR GENERATING STATION IX. PROCESS CONTROL PROGRAM (PCP) CHANGES On December 1, 1987 the Plant Review Committee approved a rewrite of the Process Control Program Manual. The PCP manual was written to conform to the format called for by Rancho Seco Administrative Procedure, RSAP-0502. The new PCP also prevents solidification of resin from the Spent Resin Tank on the Solidification Pad until enclosure of -the Solidification Pad is completed. Referances to other Rancho Seco procedures were also changed to ensure that the correct procedure numbers are referenced.
These changes do not provide a departure from the solidification processes used in the previous PCP (AP.309.II 4). This is because no solidification processes were changed by the rewrite of the procedure. Therefore, this change to the PCP does not reduce the overall confermance of the solidified waste with existing criteria for solid wastes. A copy of the previous PCP, AP.309.II-4, is enclosed in Appendix H for comparison with the new PCP (RP.309.II-4). The new PCP is enclosed in Appendix G.
O
~ SEMIANNVAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION X. RADI0 ACTIVE EFFLUENT MONITORING INSTRUMENTATION- i I
IN0PERABILITY GREATER THAN 30 DAYS During the period of this report, both gaseous effluent monitors and the liquid effluent monitor we.e out of service.
The liquid effluent monitor was out of service due to ongoing modifications and testing of the Regenerative Holdup Tanks and associated piping. The liquid effluent monitor (R-15020) is expected to be returned to service in early 1988.
The old gaseous effluent monitors (R-15001 and R-15002) were replaced by new monitors. The new gaseous effluent monitors (R-15044 and R-15045) have been going through testing and ,
acceptance work throughout the last half of 1987. Because of (
other scheduled work, the new monitors will be placed in service in early 1988.
XI. CHANGE IN LAND USE CENSUS LOCATIONS The 1987 Land Use Census identified one location where there existed a potential for the calculated dose to be greater than 20 % higher than the previous years location. The 1986 Land Use Census iaentified the nearest house in the West sector as O- being at 3,414 meters from the center of the Reactor Building.
The 1987 Land Use Census determined that the nearest residence was 2,380 meters from the center of the Reactor Building. This change in distance would result in a 158 % increase in calculated dose from gaseous effluents over the 1986 location.
l U
l SEMI ANNUAL RADI0 ACTIVE EFFLUENT . RELEASE : REPORT A\AF- . JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION f
5
- APPENDIX A 3
e O
u a
l
_ _ . _ . . _ , - - _ - _ _ _ . . , _ . . . _ . . - _ . _ _ , _ _ . . _ _ _ _ . . _ . _ . _ _ _ _. _ _ _ 4
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT b,-
JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IllPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY 1
i General Ptblic lbse Sumery (man-nyn) l l
l PATINAY T. M GI.TRKT WE UVER KIlWY THYmID LLIC %IN l
.........p.........p .........p .........p .........p .........+..........+..........+..........+
PlLtE l 6.7%-09 l 6.7%-09 l 6.7%-09 l 6.7W-09 l 6.7%-09 l 6.7%-09 l 2.24E-09 l 1.13E-06 l
........ p.........p.........p.........p.........p.........+..........p.........p.........+
IIHAl. l 1.5%-03 l 1.5T-03 l 0.0 l 1.5%-03 l 1.5%.03 l 1.5%-03 l 1.5%4 l 1.5%-03 l
.........p.........p.........p .........p.........p.........+..........p.........p.........+
VETT l 2.65E-03 l 2.6%-03 l 0.0 l 2.65E4 l 2.6%-03 l 2.6%-03 l 2.G-03 l 2.6%-03 l
.........p.........p.........p.........p .........p.........+..........+..........p.........+
) CW MilX l 9.1%-04 l 9.1E-04 l 0.0 l 9.1%a l 9.1%-04 l 9.1%-04 l 9.1%-04 l 9.1E-04 l
.........p.........p.........p.........p.........p.........p.........p.........p.........+ l sr l 5.wa 15.ww I 0.0 l 5.99e a 1 5. w w 1 5. w a l 5. u .04 l 5. w a l l
.........p.........p.........p.........p.........p.........+..........p.........+..........+
- TOTAL
- l 5.6%-03 l 5.6%-03 l 6.7%-09 l 5.6%-03 l 5.6%-03 l 5.6%-03 l 5.6E-03 l 5.6%-03 l
.........p.........p.........p .........p.........p.........+..........p.........p.........+
l l
Averaoe Ittiividsal (nun)
PATINAY T. M GI-TRKT WE UVER XILMY 1HYmID LLEC %IN .
.........p.........e.........p.........p.........e..... ...p.........p.........p.........,
- TOTAL
- l 2.84E.12 l 2.84E.12 l 3.39E.15 l 2.84E.12 l 2.84E.12 l 2.84E.12 l 2.84E.12 l 2.84E.12 l
.........+.......... p ......... p ......... p .........p .........p .........p.........p .........+
APPENDIX A 0s PAGE 1
1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT !
JULY. DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION I
APPENDIX A l
RADIOLOGICAL IMPACT ON MAN l 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Site Area Boundary 1 4
l
............+...........y ..........p ..........p .........y .........+ l Beta Cama Total Distance Air Dose Air Dose Body Skin Sector (Meters) (?RAO) (MDI) (MDI) (MDI)
............ p ..........+...........+........... e .........+..........+
N l 658 l 7.54E-07 l6.65E-09 l 4.3E-09 l 5.M-07 l l
............p ..........p ..........+...........+..........+..........+
M l 670 l7.93E-07 l .7,0%-09 l 4.5%-09 l 5.51E-07 l
............p ..........p ..........+...........+..........+..........+
tE l 192 l 1.13E-06 l 1.0%-09 l6.5%-09l7.8E-07l l
...........-p ..........p ..........+...........+..........+..........+
M l 1185 l 7.31E-07 l 6.45E-09 l 4.M-09 l 5.07E-07 l p ............p..........p..........p..........p.........e.........#
\ E l 3605 l 3.4E-06 l 3.02E-10 l 1.9%.10 l 2.3E-B l
............p ..........p ..........p ..........+..........+..........+
E% l 1697 l 1.7%-07 l 1.5%-09 l 9.8E.10 l 1.1%-07 l
............p ......... p ..........p ..........p
.........+..........+ ,
% l 1152 l 2.1E-07 l 1.91E-09 l 1.2SE-09 l 1.5%-07 l \
............p..........p..........p..........p.........p.........+
ST l 1170 l1.8%-07 l 1.6E-09 l 1.09E-09 l 1.3%-07 l
........... p ..........p..........p..........+..........p.........+ l S l 1759 l 7.9%-06 l7.05E.10 l 4.6E.10 l 5.54E-% l
............p..........p..........y..........p.........p.........+
SW l 1103 l 4.6T-07 l 4.13E-09 l 2.71E-09 l 3.2SE-07 l l
............p ..........p ..........+...........+..........+..........+
% l 1146 l 5.1%-07 l4.57E-09 l 2.9%-09 l 3.5%-07 l
............p..........p..........p..........p.........p.........+
W% l 987 l 4.02E-07 l 3.55E-09 l 2.33E-09 l 2.79E-07 l
............p..........y..........y..........p.........p.........+
W l 969 l 2.3E-07 l 2.04E-09 l 1.34E-09 l 1.61E-07 l
............p ..........+...........p ..........p.........p .........+
MW l 967 l5.0E-07 l 4.4E-09 l 2.93E-09 l 3.5E-07 l
............p..........p..........p..........p.........p.........+
IN l 795 l 7.4%-07 l 6.53E-09 l 4.2%-09 l 5.14E-07 l
............p..........p..........p ..........p .........+..........+
MH l 670 l 6.9]E-07 l 6.1%-09 l 4.0%-09 l 4.8%.07 l
............p..........p..........p ..........p.........p.........+
( APPENDIX A Page 2
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT h
JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION 1
1 l
l 1
l APPENDIX A l 1
i RADIOLOGICAL IMPACT ON MAN I 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY l
Exclusion Area Boundary
............p..........p..........+.........--+..........+.........-+
Beta Gamn Total Ofstance Air & se Air &se Body Skin Sector (Meters) (MMO) (MOI) (M) (M)
............p..........p ..........p ..........+..........+..........+ 1 N l 640 l 7.8T-07 l 6.93E-09 l 4.54E-09 l 5.45E-07 l j
............p......... p ...........L...........f..........+=.====.==.+
ME l 640 l 8.4%-07 l 7.048-09 l 4.9T-W l 5.89E-07 l
............p ..........p ..........p ..........+..........+..........+
W l 640 l 1.5%.06 l 1.4T-B l 9.14E.09 l 1.1T-06 l
............p..........e..........+...........p.........+..........+
DE l 640 l 1.9T-06 l 1.6BC-B l 1.1T-m l 5.07E-07 l
~
............p..........p..........p..........p........ p.........+
E l 640 l 1.07E-06 l 9.4%-09 l 6.2T-G l 7.442-07 l
............p..........p ..........p ..........+..........p.........+
E% l 640 l 9.93E-07 l 8.7%-09 l 5.74E-09 l 6.89E-07 l
............p..........p..........p..........p.........p.........+
% l 640 l5.63E-07 l 4.9T-09 l 3.2SE-09 l 3.91E-07 l
............p ..........p ..........p ..........+..........p
.........+
SSE l 640 l 4.64E-07 l 4.09E-09 l 2.6BE-09 l 3.2T-07 l
............p..........p..........p..........p .........p ........+
S l 640 l 5.31E-07 l 4.69E-09 l 3.07E-09 l 3.69E-07 l
............p..........p ..........>...........y .........p .........+
SW l 640 l 1.19E-06 l 1.05E-B l 6.87E-09 l 8.2SE-07 l
............p..........p..........p..........p.........p.........+
% l 640 l 1.37E-07 l 1.21E-B l 7.94E-09 l 9.54E-07 l
............p..........p..........p..........p.........p.........+
W% l 640 l 8.54E-07 l 7.55E-09 l 4.94E-09 l 5.93E-07 l
............p..........p..........p..........p.........p.........+
W l 640 l 4.6]E-07 l 4.0%-09 l 2.6T-09 l 3.2T-07 l p......... p..........p..........p.........p.........+
MN l 640 l 1.04E-06 l 9.14E-09 l 5.99E-09 l 7.19E-07 l
............p..........p..........+ ..........p .........p.........+
W l 640 l 1.04E-06 l 9.21E-09 l 6.04E-09 l 7.2SE-07 l
............p ..........+...........+...........p .........p.........+
MN l 640 l 7.42E-07 l 6.55E-09 l 4.29E-09 l 5.1%-07 l
............p..........+...........y..........p .........p.........+
C APPENDIX A l PAGE 3 !
1 i
1
l p SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT I JULY-DECEMBER 1987 Q' RANCHO SEC0 NUCLEAR GENERATING STATION l
l APPENDIX A I l
RADIOLOGICAL IMPACT ON MAN l 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Neamst House (msn)
North East 1430 Meters PATH W T.800Y GI-TRKT WE LIVER KIUEY 7HYFOID LUG SKIN l PLLW 2.2 % -09 2.28E-09 2.28E-09 2.28E-09 2.2%-09 2.28E-09 6.07E-09 2.74E-07 GW1D 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
_ItHAL A0VLT 5.1]E-04 5.11E-04 0.0 5.11E-04 5.1]E-04 5.11E-04 5.11E-04 5.1]E-M TEBI 5.14E-04 5.14E-04 0.0 5.14E-04 5.14E-04 5.14E-04 5.14E-04 5.14E-04 WILD 4.54E-04 4.54E-04 0.0 4.54E-04 4.54E-04 4.54E-04 4.54E-04 4.54E-04 IIFNIT 2.61E-01 2.6]E-04 0.0 2.61E-04 2.61E-04 2.61E-04 2.61E 4 2.61E-04 TOTAL
" ~ ' ' ~ ' "'~' "'~*' "'"'~*' " "'~"' " " ' ' '
C] TEBI WILD 5.'14E-04 5.'14E-04 0.'0 4.54E-04 4.54E-04 0.0 5.14E-04 4.54E-04 5.14E-04 4.54E-04 5.14E-04 4.54E-04 5.'14E-04 5.'14E-04 4.54E-04 4.54E-04 IffAVT 2.6]E-04 2.6]E-04 0.0 2.6]E-04 2.6]F-04 2.6]E-04 2.6]E 4 2.6]E-04 Heamst House (msn)
East North East 1140 Meters PATH W T.BWY GI-TRCT WE LIVER VIDfY THYFOID ll!G SKIN PLLW 4.4 % -09 4.4%-09 4.4 % -09 4.4 % -09 4.48E-09 4.4%-09 1.19E-W 5.3%-07 G9XfD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Ith4L AWLT 1.28E-03 1.2%-W 0.0 1.2%-W 1.2%-W 1.28E-03 1.28E-W 1.28E-W TEEN 1.29E-W 1.29E-W 0.0 1.29E-m 1.29E-W 1.29E-W 1.29E-03 1.29E-m WILD 1.14E-03 1.14E-03 0.0 1.14E-m 1.14E-03 1.14E-03 1.14E-W 1.14E-03 IffMT 6.57E-04 6.57E-04 0.0 6.57E-04 6.57E-04 6.57E-04 6.57E-04 6.57E-04 TOTAL AWLT 1.2%-03 1.28E-03 0.0 1.2%-W 1.2%-W 1.28E-03 1.28E-m 1.2%-03 TEEN 1.29E-03 1.29E-03 0.0 1.29E-m 1.29E-m 1.29E-03 1.29E-03 1.29E-03 Wild 1.14E-W 1.14E-03 0.0 1.14E-03 1.14E-03 1.14E-03 1.14E-03 1.14E-03 ItFMIT 6.57E-04 6.57E-04 0.0 6.57E-04 6.57E-04 6.57E-04 6.57E-04 6.57E-04 O APPENDIX A O Page 4
(q) SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASEOUS EFFLUENT PATHWAY Neamst House (m)
South East 2560 Meters PATH W T.800Y GI-TRKT WE LIVER KIU 2 THYPOID WG %IN PLUE 2.12E-10 2.12E-10 2.12E-10 2.12E-10 2.12E-10 2.12E-10 5.65E-10 2.55E-%
GROLID 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IfMAL DIT 9.75E-05 9.75E-% 0.0 9.75E-W 9.75E-% 9.75E-% 9.7%-% 9.75E-05 TEM 9.8]E-% 9.8]E-% 0.0 9.8]E-W 9.8]E-M 9.8]E-% 9.8]E-% 9.8]E-B
_QlILD 8.67E-% 8.67E-% 0.0 8.67E-M 8.67E-% 8.67E-M 8.67E-% 8.67E-%
IIFMT 4.99E-% 4.99E-% 0.0 4.99E-M 4.99E-% 4.99E-% 4.99E-% 4.99E-B D TOTAL 0 DLT 9T75E-%
9.8]E-05 9.75E-%
9.8]E-06 0.0 0.0 9.75E-% 9.7%-% 9.75E-% 9.75E-% 9.75E-% l TEDI 9.8]E-% 9.8]E-% 9.81E-05 9.8]E-% 9.8]E-06
%ILD 8.67E-M 8.67E-% 0.0 8.67E-% 8.67E-B 8.67E-05 8.67E-% 8.67E-06 1 ItFMT 4.99E-05 4.99E-06 0.0 4.99E-% 4.99E-% 4.99E-M 4.99E-M 4.99E-M Neamst House (m)
South South East 7800 Meters PATlHAY T.&DY GI-TRKT WE LIVER KIU 2 THYlCID WG . %IN PLlW 2.2]E-11 2.2]E-11 2.2]E-11 2.2]E-11 2.21E-11 2.2]E-11 5.89E-11 f.6%-09 GR0llD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 G0 IIHAL MLT 7.69E-06 7.69E-06 0.0 7.69E-06 7.69E-06 7.69E-% 7.69E-06 7.69E-06 TEDI 7.74E-06 7.74E-06 0.0 7.74E-06 7.74E-06 7.74E-06 7.74E-06 7.74E 06
%ILD 6.85E-06 6.86E-06 0.0 6.85E-06 6.85E-06 6.8SE-06 6.8SE-06 6.8SE-06 i IIFMT 3.94E-06 3.94E-06 0.0 3.94E-06 3.94E-06 3.94E-06 3.94E-06 3.94E-06 TOTAL M LT 7.69E-05 7.69E-06 0.0 7.69E-06 7.69E-06 7.69E-06 7.69E-06 7.69E-06 ,
TEM 7.74E-06 7.74E-06 0.0 7.74E-06 7.74E-06 7.74E-06 7.74E-06 7.74E-06 l OIILD 6.86E-06 6.8SE-06 0.0 6.8SE-06 6.85E-06 6.85E-06 6.85E-06 6.85E-06 1 ItFMT 3.94E-06 3.94E-05 0.0 3.94E-06 3.94E-06 3.94E-06 3.94E-06 3.94E-05 O' APPENDIX A Page 5 l
l l
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i
V n! JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Neamst House (mrem)
South 6490 Meters
_EATMY T.800Y GI-TRKT BOT LIVER KIltEY THYROID WG SKIN PWE 3.5%-11 3.5T-11 3.5%-11 3.5%-11 3 SG-11 3.5 % -11 9.3]E-11 4.2T-09 GTUD 0.0 0.0 0. 0 0.0 0. 0 0.0 0.0 0.0 IfMAL M LT 7,9E-06 7.9E-06 0.0 7.9E-06 7.9E-% 7.9E-06 7.9E-M 7.9E-06 TEDV 7.9E-06 7.97E-06 0.0 7.97E-06 727E-M 7.97E-06 7.9E-06 7.97E-06 WILD 7.05E-06 7.0SE-06 0.0 7.0SE-06 7.0SE-06 7.%E-06 7.%E-% 7.0SE-%
q '
IffM 4.0SE-06 4.05F-06 0.0 4.0SE-06 4.0SE-06 4.0SE-06 4.0SE-06 4.0SE-M TOTAL MLT 7.92E-M 7.9E-06 0.0 7.92E-06 7.92r-05 7.92E-06 7.9E-06 7.92E-06 TEEN 7.9E-06 7.9E-06 0.0 7.97E-06 7.97E-06 7.97E-06 7.97E-% 7.97E-06 WILD 7.0SE-06 7.0SE-% 0.0 7.0SE-% 7.0SE-06 7.0SE-M 7.0SE-06 7.05E-06 ItFM 4.0SE-06 4.0SE-% 0.0 4.0SE-% 4.0SE-06 4.0SE-% 4.ME-06 4.0SE-06 Heamst House (nrtm)
South South West 2900 Meters PAT M Y T.BWf GI-TRKT BOE LIVER KI M Y THYROID WG SKIN PWE 3.5E-10 3.5E-10 3.5E-10 3.5E-10 3.5 E-10 I 3.52E-10 9.36E-10 4.23E-06
_[Ml!D 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IfRAL MLT 4.15E-% 4.15E-% 0.0 4.15E-% 4.15E-% 4.15E-% 4.15E-M 4.15E-05 , ,
TEEN 4.1E-% 4.17E-05 0.0 4.17E-% 4.17E-05 4.17E-05 4.17E-05 4.17E-%
MILD 3.69E-% 3.69E-W 0.0 3. W-% 3.69E-05 3.69E-05 3.69E-M 3.69E-05 ItFM 2.1E-05 2.12E-05 0.0 2.1E-% 2.12E-05 2.1E-05 2.1E-% 2.1E-%
TOTAL M LT 4.15E-05 4.15E-% 0.0 4.15E-% 4.15E-M 4.15E-M 4.15E-05 4.15E-W__._
TEEN 4.1E-05 4.1E-05 0.0 4.17E-% 4.1E-% 4.17E-% 4.1E-% 4.1E-%
MILD 3.69E-05 3.69E-B 0.0 3.69E-M 3.69E-% 3.69E-M 3.69E-% 3.69E-05 ItFM 2.1E-% 2.1E-05 0.0 2.1E-M 2.1E-05 2.1E-% 2.1E-05 2.1E-%
APPENDIX A
\ Page 6
l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 l h*) RANCHO SEC0 NUCLEAR GENERATING STATION l
APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Neamst House (mun)
South West 1220 Meters PATlHM T.800Y GI-TRACT BM LMR KilMY THYmID M SKIN PlLW 2.72E-09 2.72E-09 2.72E.fj9 2.72E-09 2.72E-09 2.72E-09 7.22E-09 3.26E-07 G91tD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IIRAL M LT 2. M -04 2. M -04 0.0 2. M -04 2. M -04 2. M -04 2. M -04 2.82E-04
__1[DI 2.83E-04 2. M -04 0.0 2. M -04 2.83E-04 2. M -04 2.8F-04 2.83E-04 MILD 2.5]E-04 2.5]E-04 0.0 2.5]E-04 2.5]E-04 2.5]E-04 2.5]E-04 2.5]E-04 ItFM 1.44E-04 1.44E-04 0.0 1.44E-04 1.44E-04 1.44E-04 1.44E-04 1.44E-04 TOTAL 2.82E-04 2. M -04 0.0 O 2. M -M AQULT 2.82E-04 2.82E-04 2.82E-04 2.82E-04 TEM 2.83E-04 2.83E-04 0.0 2.83E-04 2.83E-04 2.83E-04 2.83E-04 2.83E-04 MILD 2.5]E-04 2.5]E-04 0.0 2.5]E-04 2.5]E-04 2.5]E-04 2.5]E-04 2.5]E-04 ItFM 1.44E-04 1.44E-04 0.0 1.44E-04 1.44E-04 1.44E-04 1.44E-04 1.44E-04 Neamst House (myn)
West South West 1830 Meters PATIRM T.RDY GI-TPKT BM LMR KilMY 7M'mID LLIC SKIN PilW 6.29E-10 6.29E-10 6.29E-10 6.29E-10 6.29E-10 6.29E-10 1.6E-09 7.55E-%
Guro 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IIHAL AWLT 7.0SE-% 7.05E-% 0.0 7.05E-% 7.05E-% 7.05E-% 7.%E-% 7.%E-M TEEN 7.09E-% 7.09E-05 0.0 7.09E-05 7.09E-% 7.09E-% 7.09E-% 7.09E-%
Mild 6.27E-% 6.2E-% 0.0 6.2E-05 6.2E-% 6.2E-% 6.27E-% 6.2E-%
ItFM 3.61E-B 3.6]E-% 0.0 3.6]E-% 3.6]E-05 3.61E-% 3.6]E-B 3.61E-%
TOTAL MLT 7.%E-M 7.05E-% 0.0 7.05E-05 7.05E-% 7.0SE-% 7.05E-% 7.05E-%
TEEN 7.09E-% 7.09E-% 0.0 7.09E-% 7.09E-% 7.09E-05 7.09E-% 7.09E-%
._ Mild 6.2E-05 6.2E-05 0.0 6.2E-05 6.27E-% 6.2E-M 6.2E-% 6.2E-M IffM 3.6]E-05 3.6]E-% 0.0 3.61E-05 3.6]E-% 3.6]E-% 3.61E-05 3.6]E-%
APPENDIX A GT Page 7
cm -
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i.'
) JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Neamst House (mrem)
West 3230 Meters l PATWAY 7.m0Y GI TRACT WE LIVER KIUIEY THYROID litC SKIN
, PLWE 1.1X-10 1.1T-10 1. ]T-10 1.1T-10 1.1T-10 1.1T-10 2.9]E-10 1.32E-09 1
GFDLtD O.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ifRAL
@lT 1.9%-% 1.9%-05 0.0 1.9%-05 1,96E-05 1.9%-05 1.9%-05 1.9E-05 TEEN 1.97E-05 1.97E-05 0.0 1.97E-05 1.97E-05 1.97E-05 1.97E-05 1.97E-05 W!iD 1.74E-05 1.74E-05 0.0 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 l If M IT 1.00E-05 1.0T-W 0.0 1. M -05 1.00E-05 1.0'E-05 1.00E-05 1.0T-05
\
TOTAL
@ lT 1,9%-% 1,9E-05 0,0 1,9%-% 1,9%-% 1,96E-% 1,9%-% 1,9%-W 1
(') TEEN 1.97E-% 1.97E-05 0.0 1.97E-05 1.97E-05 1.97E-05 1.97E-B 1.97E-%
%. ) Wild II M IT 1.74E-W 1.74E-05 0.0 1.74E-05 1.74E-05 1.74E-% 1.74E-05 1.74E-05 1.00E-B 1.00E-05 0.0 1.0'E-05 1.0%-% 1. M -05 1.00E-05 1.0T-05 Hearest House (nrm) 1 West North West 4390 Meters I PATWAY T. BD' GT-TRKT WE LIVER KIUIEY THYF01D UIC SKIN PLUE 1.3%-10 1.3%-10 1.3E-10 1.3%-10 1.3T-10 1.3%-10 3.67E-10 1.6 % -09 G91tD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 11HAL
@ LT 1.83E-05 1.83E-05 0.0 1.83E-05 1.83E-05 1.83E-05 1.83E-05 1.83E-05 TEEN 1.84E-05 1.84E-05 0.0 1.84E-05 104E-05 1.84E-05 1.81E-05 1.84E-05 i
Wild 1.63E-05 1.63E-05 0.0 1.63E-05 1.63E-05 1.63E-05 1.63E-05 1.63E-05 I!FAW 9.3E-05 9.3T M O.0 9.3 %-05 9.3 ? 05 9.3T-06 9.3E-W 9.3?-06 TOTAL MLT 1.83E-05 1.83E-05 0.0 1.83E-05 1.83E-% 1.83E-05 1.83E-05 1.83E-05 TEEN 1.84E-05 1.84E-W 0.0 1.84E-05 1.84E-W 1.84E-05 1.84E-05 1.81E-05 i WILD 1.63E-05 1.63EDS 0.0 1.63E-W 1.63E-05 1.63E-05 1.63E-05 1.63E-05 IfMIT 9.3E-05 9.3T-% 0.0 9.3 %-06 9.3M-05 9.3T-06 9.3&-06 9.3M-05 l
( '. APPENDIX A 1/ Page 8
l l
> l l
.. l m SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
) JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN l 1987 QUARTER 3 GASEOUS EFFLUENT PATHWAY l Neamst House. (nrw)
North West 5330 Meters l
PMM T.Eluf GI-TRKT WE LIVER XIUEY TMID M %IN PLlW 9.6BE-11 9.6BE-11 9.68E-11 9.6T-11 9.6T-11 9.6BE-11 2.57E-10 1.1T-%
GUID 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IfHAL AallT 1.3T-% 1.3T-05 0.0 1.3T-M 1.3T-% 1.3T-% 1.3T-% 1.3T-%
TEEN 1.3]E-05 1.3]E-% 0.0 1.31E-% 1.3]E-% 1.31E-% 1.3]E-% 1.3]E-W ,
Wild 1.1T-05 1.1T-% 0.0 1.1T-% 1.1T-% 1.1T-% 1.1T-% 1.1T-05 l ItFMT 6.67E-06 6.67E-06 0.0 6.67E-06 6.6E-06 6.67E-06 6.6E-05 6.67E-06 TOTAL AllLT 1.3T-% 1.3T-M 0.0 1.3T-% 1.3T-% 1.3T-% 1.3T-W 1.3T-06 Q
Q TEM Wild 1.3]E-%
1.1T-%
1.3]E-05 1.1T-B 0.0 0.0 1.3]E-%
1.1T-%
1.3]E-%
1.1T-05 1.3]E-%
1.1T-05 1.3]E-M 1.1T-%
1.3]E-%
1.1T-05 ItFMT 6.67E-06 6.67E-06 0.0 6.6E-06 6.67E-06 6.67E-06 6.6E-C6 6.67E-M Neamst House (nrm)
North North West 7250 Meters PMM T.BWf GI-TRKT WE L1VER KIDtY TMID M %IN PLLW 3.9T-11 3.9T-11 3.9T-11 3.9T-11 3.9T-11 3.96E-11 1.05E-10 4.7T-09 GutD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ItHAL AllLT 7.7E-06 7.7E-06 0.0 7.77E-06 7.77E-06 7.7E-06 7.77E-06 7.77E-06 l TEM 7. M -06 7.M-06 0.0 7.M-06 7. M -06 7.M-% 7 M -06 7. M - % !
Wild 6.9E-06 6.9E-M 0.0 6.9E-06 6.9E-06 6.9E-06 6.9E-06 6.92E-06 ItFMT 3.98E-06 3.9BE-06 0.0 3.9BE-06 3.98E-06 3.9BE-06 3.98F-06 3.9BE-%
TOTAL NULT 7.77E-M 7.7E-06 0.0 7.77E-06 7.7E-06 7.7E-06 7.77E-06 7.7E-06 TEM 7.M-06 7.M-06 0.0 l
- 7. M - M 7.82E-06 7. M - M 7. M -06 7. M -06 WILD 6.9E-06 6.9E-06 0.0 6.9E-06 6.92E-M 6.9E-M 6.92E-06 6.9E-06 ItFMT 3.9BE-M 3.9BE-% 0.0 3.98E-06 3.9T-06 3,9BE-06 3.W-06 3.98E-06 i g
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT f' JULY-DECEMBER 1987 x .
RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASEOUS EFFLUENT PATHWAY Milk Ctw (m)
East North East 1140 Meters PATWM T. M GI.TRKT M UVER KIM THYROID WG MN ;
.........p.........p .........p.........p.........p .........y.........+..........p.........+ \
Ml!LT 7.83E-04 7. W -04 0.0 7. W -04 7.83E-04 7. W -04 7. W -04 7. W -04 TEEN 1.02E-03 1.02E-W 0.0 1.02E-W 1.02E-W 1.02E-W 1.02E-W 1.02E-03 Wild 1.6]E.03 1.6]E-03 0.0 1.6]E-03 1.6]E-03 1.6]E-03 1.61E-03 1.6]E-03 IfFM 2.44E-W 2.44Ed3 0.0 2.44E-03 2.44E-m 2.44E-03 2.44E-03 2.44E-03
.........e.........e.........p.........e.........+..........+..........+.........-+..........i Milk C<w (m) -
South West 3190 Meters PATWAY T. M GI-TRKT M UVER KI M THYh01D WG MN
.........p.........p .........p.........p.........p.........p.........+..........p.........+
N!)LT 2.1]E-05 2.1]E-M 0.0 2.11E-% 2.11E-05 2.1]E-05 2.11E-05 2.1]E-05 ;
TEEN 2.75E-% 2.75E-% 0.0 2.75E-05 2.75E-M 2.75E-% 2.75E-05 2.75E-%
Wild 4.35E-B 4.35E-% 0.0 4.35E-% 4.35E-% 4.35E.% 4.35E-05 4.35E-W IffMT 6.6T-M 6.6%-% 0.0 6.6T-% 6.6T-% 6.6T-05 6.6T-05 6.6T-03
.........p.........p.........p.........p.........p.........p.........p........ p.........+
Milk CM (m)
West South West 3620 Meters l PATWAY T. M GI-TRKT M UVER KIDD' THYFOID WG MN
.........p.........p.........e.........e.........p.........e.........e.........p.........+
M1]LT 1.09E-% 1.09E-% 0.0 1.09E-05 1.09E-M 1.09E-% 1.09E-B 1.09E-05 ;
TEEN 1.42E-% 1.42E-05 0.0 1.42E-% 1.42E-% 1.42E-% 1.42E-% 1.42E-M Mild 2.24E-% 2.24E-05 0.0 2.24E-M 2.24E-% 2.24E-05 2.24E-05 2.24E-05 IffMIT 3.4T-% 3.4T-M 0.0 3.4T-% 3.4T-05 3.4T-% 3.4T-09 3.4T-05
.........p ......... p .........+.......... p .........+..........+.......... p .........+..........+
APPENDIX A l PAGE 10 J
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 O.. RANCHO SEC0 NUCl. EAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Milk Ccw (nrun)
West 7740 Meters PATINAY T.800Y GI-TRKT WE LMR KIDtY TWIDID WG M4
.........p .........p .........p.... ....+ .........p .........p .........+..........p .........+
AQULT 2.4T-M 2.4E-M 0.0 2.4E-% 2.4 % -06 2. M -06 2.4E-06 2.4E-06 TEEN 3.2T-06 3.2T-06 0.0 3.2T-06 3.2T-06 3.2T-06 3.2T-M 3.2T-06 OlllD 5.0E-06 5.0T-06 0.0 5.0T-% 5.0 %-06 5.0T-% 5.%E-06 5.0%-06 IWM 7.6T-06 7.6T-06 0.0 7.6T-06 7.68E-06 7.6T-06 7.6T-06 7.6T-06
.........+..........p.........p.. ......e.........p .........p.........p.........p.........+
0 O APPENDIX A PAGE 11
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987
(-]-
RANCHO SCC 0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Meat Animi (mnan)
Nodh 440 Meters PATlWAY T. M GI-TRCT M LIVm KilMY THYmIO M %IN
.........p.........p.........p.........p.........p.........e.........p.........p.........+
MT 5.0BE-04 5.OBE-04 0.0 5.mE-04 5.0BE-04 5.0BE-04 5.0BE-04 5.mE-04 TEEN 3. W -04 3 W -04 0.0 3. W -04 3. W -04 3. W -04 3.03E-04 3. W -04 OliLD 3.66E-04 3.66E-04 0.0 3.66E-04 3.66E-04 3.66E-04 3.66E-04 3.66E-04-__
.........y .........p.........y.........p.........p.........y .........p.........p .........+
Meat Anim1 (nrun)
N East Nod h East 430 Meters PATlWAY T. M GI-TRKT M LIVB KIDEY THYmID M %IN
.........+..........p.........p.........p.........p.........p.........p.........p.........+
MT 5.71E-04 5.71E-04 0.0 5.71E-04 5.71E-04 5.71E-04 5.7]E-04 5.7]E-04 TEEN 3.41E-04 3.41E-04 0.0 3.4]E-04 3.41E-04 3.41E-04 3.41E-04 3.4]E-04 OIILD 4.1E-01 4.1E-04 0.0 4.1E.04 4.1E-04 4.1E-04 4.1E-04 4.1E-04
.........p.........p.........p.........e.........p.........p.........p.........p.........+
Meat kin 1 (nrvn)
North East 430 Meters PA11 HAY T. M GI-TRCT M LIVB KILMY THYmID M %IN
.........+..........p ......... p .........p .........p .........p .........p .........p .........+
MT 9.77E-04 9.77E-04 0.0 9.77E-04 9.77E-04 9.77E-04 9.77E-04 9.77E-04 TEEN 5. W -04 5. W -04 0.0 5. W -04 5. W -04 5. W -04 5. W -04 5. W -04 OlllD 7.04E-04 7.04E-04 0.0 7.04E-04 7.04E-04 7.04E-Od 7.04E-04 7.04E-04
.........+..........p .........p .........e .........p .........p .........e .........p .........+
APPENDIX A PAGE 12
_. SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 f'd 1 RANCHO SEC0 NUCLEAR GENERATING STATION 1
APPENDIX A 1
i RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Meat kimi (mun]
East North East 450 Meters l
PADNAY T.800Y GI-TRACT M LIVER KIM THYh010 WG MN 1
.........p .........p .........p .........p.........+..........p .........p.........p.........+
MT 1.42E-m 1.42E-03 0.0 1.42E-m 1.42E-W 1.42E-W 1.42E-03 1.42E-03 l TEEN 8.46E-04 8.46E-04 0.0 8.4E-04 8.46E-04 8.4E-04 8.4E-04 8.4E-04 WILD 1.02E-W 1.02E-03 0.0 1.02E-m 1.02E-W 1.02E-W 1. M -03 1.02E-W ,
.........+..........p ......... p .........e .........p ......... p .........p .........p .........+ j l
Meat kimi (myn) .
East 470 Meters PATINAY T.BWf GI-TRACT WE LIVER KIDEY THYmID WG MN
.........p .........p.........p .........p.........p.........+..........p .........p .........+
MT 1.31E-m 1.31E-W 0.0 1.31E-m ' 1.3]E-m 1.31E-W 1.3]E-m 1.31E-03 TEEN 7.83E-04 7.83E-04 0.0 7.83E-04 7.83E-04 7.83E-04 7.83E-04 7.83E-04 Wild 9.4E-04 9.4E-04 0.0 9.4E-04 9.4E-04 9.4E-04 9 M E-04 9.4E-04
.........p.........e.........e.........p.........e.........e.........p.........p.........+
Meat kimal (myn)
East South East 670 Meters PATINAY T.B00Y GI-TRACT M LIVER KIDtY THYmID WG MN
.........p.........p.........p.........p.........p.........e.........p.........p.........+
MT 4.33E-04 4.33E-04 0.0 4.33E-04 4.33E-04 4.33E-04 4.33E-04 4.33E-04 TEEN 2.5%-04 2.5%-04 0.0 2.5%-04 2.5T-04 2.58E-04 2.5T-04 2.5%-04 Wild 3.1E-04 3.12E-04 0.0 3.1E-04 3.1E-04 3.12E-04 3.1E-04 3.12E-04
.........p.........p.........p.........p........ p.........p.........p.........p.........+
] APPENDIX A PAGE 13
c SEIIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
(-) JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION l
l APPENDIX A l RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY 1
&at kin! (nm) 1 South East 240 Meters j l
i PATWM T. M GI-TRKT WE UVER KILMY TMID WG MN
.........p .........p .........p .........+..........p ........ p .........p .........+..........+
MT 2.0BE-03 2.0BE-03 0.0 2.0BE-03 2.0BE-W 2.0BE-03 2.03E-03 2.06E-03 ;
TEEN 1.24E-03 1.24E-03 0.0 1.24E-03 1.24E-03 1.24E-W 1.24E-W 1.24E-03 1 OIILD 1.5T-03 1.5T-W 0.0 1.5T-03 1.5T-W 1.5T-03 1.5T-03 1.5T-03
.........+..........p .........p .........p ......... p .........p .........p .........p .........+
t hat kim1 (nm)
O South South East 200 k ters
\
PATWM T.BD' GI-TRXT WE UVER KilMY THYlDIO WG MN
.........e.........p.........p.........p.........e.........p.........p.........p.........+
MT 1.8SE-03 1.8SE-03 0.0 1.8SE-03 1.8SE-03 1.8SE-03 1. W -03 1.8SE-W TEEN 1.1T-03 1.1T-03 0.0 1.1T-03 1.1T-03 1.1T-03 1.1T-03 1.1T-03 OIILD 1.33E-03 1.33E-03 0.0 1.33E-03 1.33E-m 1.33E-03 1.33E-03 1.33E-W
.........p.........p.........+..........p.........e.........p.........p .........p.........+
Meat kim1 (nn)
South 200 Meters PATWN T. M GI-TRKT WE UVER KILMY T M ID WG MN
.........p.........p.........p.........p.........e.........p.........p.........p.........+
MT 1.4]E-W 1.4]E-03 0.0 1.4]E-03 1.41E-03 1.4]E-03 1.4]E-03 1.4]E-03 TEEN 8.4E-04 8.42E-04 0.0 8.4E-04 8.42E-04 8.4E-04 8.4E-04 8.4E-04 OIILD 1.02E-W 1.02E-W 0.0 1.02E-W 1.02E-03 1.02E-W 1.0E 03 1.02E-03
.........p.........p.........p.........p.........p.........p.........p.........p.........+
3 APPENDIX A PAGE 14
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l'}
C JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASEOUS EFFLUENT PATHWAY Meat k imal (mnin)
South South West 200 Meters PATWAY T. M GI-TMCT WE LMR KID D' THYROID WG MN
.........p.........p.........p.........p.........p.........p.........p........-p.........+
MllLT 1.69E-03 1.69E-03 0.0 1.69E-W 1.69E-03 1.69E-03 1.69E-03 1.69E-03 TEDI 1.0]E-03 1.01E-W 0.0 1.01E-W 1.01E-03 1.01E-03 1.0]E-W 1.01E-03 OIILD 1.22E-03 1.22E-W 0.0 1.22E-03 1.22E-03 1.22E-W 1.22E-03 1.22E-03
.........p.........e .........p.........y .........p.........p.........e.........e.........+
Meat Animal (men)
South West 290 Meters PATWAY T. M GI-TMCT M LMR KIO D' THYmID WG MN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
MllLT 8.55E-04 8.5 % -04 0.0 8.55E-04 8.55E-04 8.55E-04 8.55E-04 8.55E-04 TEEN S.1T-04 S.1T-04 0.0 5.1T-04 S.1T-04 S.1T-04 S.1T-04 S.1T-04 OfflD 6.1T-04 6.]T-04 0.0 6.1T-04 6.1T-04 6.1T-04 6.1T-04 6.1T-0$
.........p .........e .........+..........e .........e .........p .........e .........+..........+
Meat k imal Lmm) l l
West South West 400 Meters PATWAY T.m0Y GI-TRACT M LMR KID D' THYmID WG MN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
MllLT 3.2SE-04 3.25E-04 0.0 3.2SE-04 3.25E-04 3.2SE-04 3.25E-04 3.25E-01 TEEN 1.94E-04 1.94E-04 0.0 1.94E-04 1.94E-04 1.94E-04 1.94E-04 1.94E-01 OULD 2.34E-04 2.34E-01 0.0 2.34E-04 2.34E-04 2.34E-04 2.34E-04 2.34E-01
.........p .........p .........p .........p .........p.........+..........p .........p .........+
/ APPENDIX A PAGE 15
i
) SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION i
l APPENDIX A l l
RADIOLOGICAL IMPACT ON MAN l 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY !
l l
HeatAnimal (nren) l West 510 Meters l 1
1 PATWAY T.BWf GI-TRACT WE UVER KI M Mml0 WG MN l
.........e.........e.........p.........p.........p.........p.........e.........p.........+
l MT 1.86E-04 1. M -04 0.0 1. M -04 1.85E-04 1.86E-04 1.86E-04 1.86E-04 j TEM 1.11E-04 1.11E-04 0.0 1.11E-04 1.11E-04 1.1]E-M 1.1]E-04 1.11E-04 Wild 1.34E-04 1.34E-04 0.0 1.34E-04 1.34E-04 1.34E-04 1.34E-04 1.34E-04
.........p.........+..........p.........y.........p.........+..........p.........p.........+
Meat Animal (pren)
West North West 440 Meters PATWAY T.BWY GI-TRKT BWE LIVER K! M THYml0 WG MN
.........p .........e .........p .........p .........y ..-......p .........p .........+..........+ j MT 4.05E-04 4.05E-04 0.0 4.05E-04 4.05E-04 4.05E-04 4.05E-04 4.05E-04 \
TEM 2.4]E-04 2.4]E-04 0.0 2.4]E-04 2.4]E-04 2.4]E-04 2.4]E-04 2.41E-01 WILD 2.92E-04 2.92E-04 0.0 2.9E-04 2.92E-04 2.9E-04 2.92E-04 2.92E-04 }
.........p .........p .........p .........p .........p .........p .........p.........+..........+
l Meat kimal (nrun). '
North West 500 Meters PATWAY T.BWf GI-TRKT WE UVER KIM THYmID WG MN
.........e.........p.........p.........p.........p.........p.........e.........p.........+
MT 3.2]E-04 3.2]E-04 0.0 3.2]E-04 3.2]E-04 12]E-04 72]E-04 3.2]E-04 TEEN 1.92E-04 1.9E-04 0.0 1.92E-01 1.92E-04 1.9E-04 1.92E-04 1.9E-04 Wild 2.32E-01 2.32E-04 0.0 2.3E-04 2.3E-04 2.3E-04 2.3E-04 2.32E-04
.........p.........p.........p.........p.........p.........p.........p.........p.........+
APPENDIX A V) t PAGE 16
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O Jul.'l-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION l
I lI i
APPEN0!X A ,
- c. i k i 3 ( ,
RADIOLOGICAL IMPACT Oh MAN ,
1 1 1987 QUARTER 3 GASEOUS EFFLULNT PATHWAY l f
') l l
l t, 8 MeatAnimel (nrw) . [
> (
North North West 440 Meters ,
- \
I PATlHAY T.B00Y GI-TRACT WE LMR KILMY IHfDID ' ILRC MN ,i'
.........p .........p .........p .........p .........p .........p . .......p .........+...... ...+,
ARILT 4.0E-04 4.0E-04 0.0 4.0E-04 4.0E-04 4.0.'E-M 4.0E-04/(4.07f-M__,
TEEN 2.43E-04 2.43E-04 0.0 2.43E-04 2.43E-04 2.4:E QA43EM l 2.43E-04 /
OliLD 2.93E-04 2.9X-t}4 0.0 2.93E-04 2.93E-01_.243E-04 2.2X-0% j.93E-04 \
.........p.........p.........e. .......p..... ...p.........e.........e..a. ....+..........+
l >
O Mi1kGoat LnamJ West 3230 Meters
(
\
l y ,i . l PAHWAY T.RD' GI-TR&~T WE LMR KIutY 1HMID 'lLRG MN
.........e.........p.........p . ..... .p.........p.........p........ p.........'+..........+ ,
AallT 2.43E % 2.43E-% 0.0 2.4X-M 2.43E-% 2.43E-M& ?.43E-% l 2.43E-% 'l 3.1E-% l TEEN 3.1E-% Q.0 3.1E-M 3.17E-% 3.1E-% ^ 3.1E-%' \ 3.17E-%
OilLD 5.01E-% 5.01E-% 0.Q 5.01E-% 5.01E-M S.01E-% 5.01E-% 5;01E-%
._!WMT 7.6T-% l 7.6%-% 0.0 7.6T-M 7kT-% i 7.6%-% 7.6E' -% 7.6%-tB__ \
.........p.........p. . .....p. .
.....p.........p....,....p.........p.. .. . + ..........+ l t J .i
/ I l
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t
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O APPENDIX A > l
'V PAGE 17 l l
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r es SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
/ 1 JULY.0ECEMBER 1987 O
RANCHO SEC0 NUCLEAR GENERATING STATION f , ;
e .
4 APPENDIX A
[
1
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A RACIOL0i.lCAL IMPACT ON MA'N i i 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY s
A Neamst Garden (nrun) 1 i
North East 4WO Meters v' PMM T. M , GI.TRKT M LMR Kli1Ef M 7WICID 9'IN
...... ..p .........+........; p.........p .........+..........p .........y ........+..........+
N11LT 6.69E-M 6f)E _05.\ O a 0_1 S.69C-% 6.69E-05 6.69E-% 6.69E-M 6.69E45 1Em 7.6T-05 7.6E DS 0. 0 7.6E-% 7.6T-m 7.6E-05 /.6T-05 7.66E-05 i Oilla 1.19E-04 1.19E-04 { 0.0 1.19&O4 1.19E-04 1.19E-M 1.19E-Od 1.1SE-04
.........+.-.......p........v.........p.........+..........+..........+..........+-..-......+
1
/ Neamst GarzfgG (nrun)
( \
8 East Nort' East 1140 Meters PMAY T..mf GE.TRKT M LTVER KIDD' THYiDID M MN
.........;...........p ....... .p .........p.........e .........+..........p
.........+..........+
111U . i 2.3E-W 2.3E.{L 0.0 2.33 4 2.3E W 2.32E-m 2.3E-W ' 2 3E-W TED { 2.65E-W 2.65E-W 0.0 2.65E-W 2.65E.W 2.65&W 28{:W 2.65E-W Olll[t_.J.4.JLE-W \ 4.11E-W 0.0 4.11E-W _
4.11E-03 4.11&W 4.11E-d3 4.11&W
...... . u.........y.........e.. ......e.........u ........e.........p.........p.........+
4 l
Wamst Garden (nrun)
, i
) . South East 2560 MeteqL t
I PMM T. M GI-TRACT M UVER KIOD' THYlDID M MN
.........p... .....p.........p.........p.........p.........p.........p.........p.........+
MILT 1.7T-04 1.7 % -04 0.0 ^ 1.7 T 04 1.7T-04 1.7T-04 1.7T-04 1.7%-M y TEN 2&lE04 2.01 & O4 0.0 2 01 & O4 2.0]E-04 2.01E-04 2.01E-04 2.01E-04 011LD 3.12E-04 3.1E-04 0.0 3.15-04 3.1E-04 3.1E-04 1 3.1E-04 3.1E-04
.........p.........p..........p.........p.........p.........p.........p .........p.........+
(~' s APPENDIX A j Page 18
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SEMIANNUAL RADI0 ACTIVE EFFLUENT ELE SE RFPORT i O'
V V < JULY-DECENSER 1987%
'/ RANCHO SEC0 NUCLEAR GENERATING STATION i
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- 'l' s aAP75tblX A [c'!/
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( 1 RADIOL 16I"Al., IMPACT dM MAN'
/ .) ' '
- y. j 1987 QUARTER;5'GASiOV.c EFFLUENT' PATHWAY, .
. /
y ; s
't /,
.,a samt h, nrw '
b,
\
, [sth C490 Meters
/
I
.f. : &
M UG ] jKILMY p.L...... j 1 M ID
'AllWM T.Bab' GI-TRKT LLtB SKIN f ......... p ......... p ......... p .........+.. ...)L. 4 L. ......p .........+..........+
l ; i AllLT 1.43E-% 1.43E-% 0.0 1.43E-%3 MY-% '1. G 4 1.43E-M 1.43E-%
TEBI 1.64E-M 1.64E % 0. 0 ._ ;.LD.4E.-9L. d.64E-M 1.64E-% 1.64E % 1.64E-B MILD 2.54E-% ?M-% 0.0 2.!igff 2.54EQ. ?.54E-M 2 k k '6 2.54E-%
.........p.........p.........p.........p........J.y.1-..,....,..,._...'...p.........y........+ .
0 ? .
l ;,,
\
Nearvst Garden (ntd \t i
. .\ '
SouthSouthWest5330MeL'a. r, ! , ,
,4 ,
(;-
r i i e PATlWM T. M ' GI-TRCT M LMR KilNEY THYmID M MN '/
.........p..........e.........p.........e.........e..........+.........p.........e.........+
AllLP ' JJ)6% 2.3% % LO 2.3T-M ' 2.3T-% 2.3T-% 2.3T-M 2.3%-%
TEEN ?,2T-% 2.73E-M QA 2.73E-% 2.73E-% 2.73E-M 2.73E-% 2.73E-% ;
MILD 4.2E % 4.22E-M 0.0 ii4.22E-B 4.22E-% 4.22E-% 4.22E-% 4.22E-lf \
.........p .........e ......... p .........p ......... p ......... p .........e ......... e ........ y.
Hearvst Garden Lor.3e) !
)
South West.1,1.% Meters \
\
g,s <
3
?/TlWAY T.800Y GT'RACT M LMR s'MY TMID M i MN ,
- r..........p.........p.......'.p..........p.........p..........p.......g.........4.........4 AallT 6.2T-% 5.W-% 0.0 6.2T-B 6.ER.% 6.2GiQl_f, REM 6.2%-%
\
GI 7. IE-% iaBE% 0.0 7.1%-% 7.1%-% 7.1g.-ty 7.IT-m 7.16E.% _
\
MILD 1.11E-04 1.11E-04
.....,.~ .p.........p.......
Q& 8 1.11E-04. _1.11E 4 1.11F OL.Ulk29.a L11E.-04 1,
.,..........p.. ..,...p...... ..p.........p.; ... ..p.........+
i \
I .
I s APPENDIX A ,
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..j SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT g]-
RANCHO T-JilLY-DECEMBER 1987 lVCLEAR GENERATING STATION i
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APPENDIX A l RADIOLOGICAL IMPACT ON MAN l 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY l Nearest Garden (mnen)
West South West 2380 Neters 1
PMN T. M GI-TRKT M UVER KIMY THYll0ID WG MN :
.........p.........p.......,.p.........p.........e.........p.........p.........e.........+
MULT 7.3%-% 7.3%-M 0.0 7.3%-% 7.3%-M 7.3%-% 7.3%-W 7.3%-%
TE% 8.43E-% 8. G-B 0.0 8. G-% 8.G-M 8.43&% 8.43E-% 8.43E-M
%ILD 1.31E-04 1.3]E-04 0. 0 1.31E-04 1.31E-04 1.31E-04 ,1.31E-04 1.31E-04
.........e.........e.........e.........e.........+ .........e.........p.........e.........+
t Nearest Garden (mnen) r West 3230 Meters PMM T. M GI-TRXT M UVER KIMY TH M ID WG MN
.........p .........p.........p .........p .........p .........p .........p .........+..........+
MULT 3.54E-% 3.54E-M 0.0 3.54&M 3.54E-% 3.54E-% 3.54E-M 3.54E-%
TEM 4.BE-% 4.0SE-B 0.0 4.0SE-% 4.%E-M 4.%E-M 4 %E-% 4.%E-%
%ILD 6.2E-% 6.2E-% 0.0 6.2E-% 6.2E-% 6.2N-% 6.2E-M 6.2E-% i j
.........p.........+..........p.........p.........+..........p.........+..........p.........+
l
< APPENDIX A Page 20 l
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASEOUS EFFLUENT PATHWAY Nearest Garthn Lw)
West North West 4390 Meters PATIMM T.BWf GI-TRKT M UVER KMY TH M ID M MN
.........e.........p.........p.........e.........p.........p.........p.........p.........+
MT 3.31E-% 3.31E-M 0.0 3.31E-% 3.3]E-% 3.3]E-% 3.31E-% 3.3]E-M TEM 3.79E-% 3.79E-M 0.0 3.79E-% 3.79E-% 3.79E-05 3.79E-% 3.79E-%
%Il.D 5.8W-% 5.8T-% 0.0 5.8W-% 5.ME-% 5.85E-M 5.M-% 5.95E-%
.........+..........p.........+..........p.........+..........p .........p .........p .........+
9 Nearest GarTien (mun)
North West 6750 Meters PAllHM T.BWf GI-TRKT M LMR KI0tY TH R ID M MN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
MT 1.5%-% 1.55E-M 0.0 1.5%-% 1.5%-% 1.55E-% I 1.55E-% l 1.55E-%
TEM 1.77E-% 1.77E-% 0.0 1.77E-M 1.77E-% 1.77E-% J7E-% 1.77E-%
%II.D 2.75E-% 2.7%-% 0.0 2.75E-% 2.75E-% 2.75E-% l 2.75E-% 2.75E-% l
.........#..........p.........p.........p.........p .........#..........p.........p.........#
APPENDIX A O'- Page 21
p SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT e 4 JULY-DECEMBER 1987 V RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Vfsitor Center East 225 Meters PATH W T.B00Y GI-TRACT M UVER KILMY THMID M SKIN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
PM l 6.79E-09 l 6.M-09 l 6.M4 l 6.M4 l 6.79E-09 l 6.79E-09 l 1.8%-m l 8.15E-07 l .
.........p.........p.........+..........p.........p.........p.........p.........+..........+
GRUD l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l 0.0 l 0.0 l 0.0 l
.........p.........p.........p.........p.........+..........p.........p.........+..........+
1MIAL MT 3.31E-03 3.31E 4 0.0 3.31E-03 3.31E 4 3.31E-03 3.3]E-03 3.31E-W
.........p.........p.........p.........p.........p.........p.........p .........p.........+
O TEEN l 3.33E-03 l 3.33E-03 l 0.0 l 3.33E4 l 3.33E-03 l 3.33E-03 l 3.33E-03 l 3.33E-03 l Q. ........ + .........p.........p.........p.........p.........p.........p.........p.........+
OlILD l 2.95E-03 l 2.95E-W l 0.0 l 2.95E-03 l 2.95E-03 l 2.95E-03 l 2.95E-03 l 2.95E-03 l
.........p.........+..........p.........p.........p.........p.........p.........+..........+
IWM l 1.69E-03 l 1.W-03 l 0.0 l 1.69E-03 l 1.69E-03 l 1.69E 03 l 1.69E4 l 1.69E-03 l
.........p.........+..........p.........p.........p.........p.........+..........+..........+
TOTAL MT 3.31E-03 3.31E-03 0.0 3.31E-03 3.31E 4 3.31E-03 3.31E-03 3.31E 4
.........p.........p.........p.........p.........p..........p.........p .........p.........+
TEEN l 3.33E-03 l 3.33E-03 \ 0.0 l 3.33E-03 l 3.33E-03 l 3.33E-03 l 3.33E-03 l 3.33E4 l
.........p .........+..........p .........p .........p .........p .........p .........p.........+
OlilD l 2.95E-03 l 2.95E-03 l 0.0 l 2.95E4 l 2.96E-03 l 2.95E-03 l 2.95E4 l 2.95E-03 l
.........p .........p .........p .........p .........p .........p .........p .........p........ 4 IWM l 1.69E-03 l 1.69E-03 l 0.0 l 1.69E4 l 1.69E-03 l 1.69EM l 1.69E4 l 1.69E-03 l
.........p .........p.........p.........e .........e.........y.........y .........+..........+
O APPENDIX A O Page 22
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O
V JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX A RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Park Kiosk East 525 Meters PA7WAY T.B00Y GI-TRACT BM LIVD1 KILMY 1HYml0 WC SKIN
.........p .........p .........p .........p .........+..........p .........+..........+..........+
PI M l 3.54E-09 l 3.54E-09 l 3.54E4 l 3.54E-09 l 3.54E-09 l 3.54E-09 l 9.42E-09 l 4.2SE-07 l
.........p.........p.........p.........p.........e.........p.........p.........e.........+
GWJD l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l 0.0 l 0.0 l 0.0 l
.........p.........p........ p.........p.........p.........p.........p.........p.........+
IlWl.
MT 1.7E-03 1.7E-03 0.0 1.75E-03 1.7E-03 1.75E 4 1.75E-03 1.7E-03 l
.........p.........p.........p.........p.........+ .........p.........p.........p.........+
l
~) ..
TEIN l 1.7E-03 l 1.7E-03 l 0.0 l 1.7E-03 l 1.7E-03 l 1.7E-03 l 1.7E-03 l 1.7E-03 l
......p.........p.........p.........p.........p.........p.........p.........p.........+
\
QillD l 1.5E-03 l 1.5E-03 l 0.0 l 1.5E-03 l 1.5E-03 l 1.5E-03 l 1.5E4 l 1.5E-03 l !
.........p.........p.........p.........p.........p.........p.........p.........p.........+ \
ItFM l 8.95E-04 l 8.95E-04 l 0.0 l 8.95E-04 l 8.95E4 l 8.95E-04 l 8.9EM l 8.95E-04 l l
.........p.........p.........p.........p.........p.........p.........p.........p.........+
TOTAL.
MT 1.75E-03 1.iSE-03 0.0 1.75E-03 1.7E-03 1.75E-03 1.75E 4 1.7E-03
.........p.........p.........p.........p.........p .........p.........p.........p.........+
TEIN l 1.7E-03 l 1.7E-03 l 0.0
. . . . . . . . .#. . . . . . . . . .p . . . . . . . l. 1.7E-03
.p . . . . .l .1.7E4
. . .p .l .1.7E-03
. . . . . . p .........p
. . . . . . . ..........+
.p . . . . . . . . .pll l
OlllD l 1.5E-03 l 1.5E-03 l 0.0 l 1.5E-03 l 1.5E-03 l 1.5E4 l 1.5E-03 l 1.5E-03 l l
.........e.........p.........p.........p.........p.........p.........p.........p.........+
IlfM l 8.95E-04 l 8.95E-04 l 0.0 l 8.95E-04 l 8.95E-04 l 8.95E-04 l 8.95E-04 l 8.95E-04 l
.........p.........p.........p.........p.........+..........+..........p.........p .........+
l l
l l
I l
l O
V APPENDIX A Page 23 .
1 i
J
1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
(~ JULY-DECEMBER 1987 U RANCHO SEC0 NUCLEAR GENERATING STATION i
APPENDIX A l
RADIOLOGICAL IMPACT ON MAN :
1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Wamhouse East North East 225 Meters PADNAY T.KDY GI-TRKT BM LIVDt KIDEY THYmID M SGN l
.........p.........p.........p.........e.........p.........p.... ....p.........e .........+ l PM l 1.5%-% l 1.5%-M l 1.5T-B l 1.5%-% l 1MB l 1.5%-M l 4.1%-M l 1.89E-06 l !
.........p .........+..........p .........p..........p ......... p .........p ......... p ........ 4 GW1D l 0.0 l0.0 lJ.0 l 0.0 l0.0 l 0.0 l 0.0 l0.0 l
.........e.........p.........p.........p.........p.........p.........p........-p.........+ j IIML KllLT 4.4E-03 4.4E-03 0.0 4.4E.03 4.4E.03 4.4E-03 4.4 5 03 4.4E.03
.........e.........p.........p.........e .........p.........p.........p.........p.........+
TiEN l 4.45E4 l 4.45E-03 l 0.0 l 4.45E-03 l 4.45E4 l 4.4%-03 l 4.4%-03 l 4.4%-03 l
.........p .........p .........p .........p .........p .........+..........p .........p .........+
qj OIIW l 3.93E-03 l 3.93E-03 l 0.0 l 3.93E-W l 3.9%-03 l 3.93E4 l 3.93E-W l 3.93E-03 l p.........p.........p.........p.........p.........p.........p.........p.........+
l IWM l 2.2T-03 l 2.2T-W l 0.0 l 2.2T-W l 2.2T-W l 2.2T-03 l 2.2T-03 l 2.2T-03 l
.........p.........p.........y.........p.........y.........p.........p.........p.........+
TOTAL AllLT 4.4E-03 4.4E-W 0.0 4.4E-03 4.43-03 4.4E4 4.4 E 03 4.4E-03
.........e.........p.........p.........p.........p.........p.........p........ p.........+
TM l 4.45E 03 l 4.45E-W l 0.0 l 4.45E-03 l 4.45E-03 l 4.45E-W l 4.45E-03 l 4.45E-03 l
.........p.........p .........p.........p.........p.........p.........p.........p.........+
OlIW l 3.93E-03 l 3.93E-03 l 0.0 l 3.93E-03 l 3.93E-03 l 3.93E-03 l 3.93E-03 l 3.93E4 l
.........e.........p.........p.........p.........p.........e.........p.........p.........+
IWM l 2.2G-03 l 2.2T4 l 0.0 l 2.2T4 l 2.2T-03 l 2.2T-03 l 2.2T-03 l 2.2T-03 l
.........p.........p.........e.........p...,.....p.........p.........p.........p.........+
1 i
1 l
~
i 1
O. APPENDIX A i V Page 24 1
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l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 O- RANCHO SEC0 NUCLEAR GENERATING STATION :
)
i APPENDIX B O
l l
1 i
O
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY General Ptb1ic Sumarv (man.nn)
PATWAY T. M GI.TRKT M LIVER KIM M MID M SKIN
.........p.........p.........,.........+..........+..........+..........+..........e.........+
PM l 0.0 l 0.0 l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l0.0 l
.........+..........e.........e.........+..........e.........e.........e.........e.........+
ImAt l 4.sw.m l 4.sx4 l 0.0 l 4.sw.m l 4.sw-W l 4.sw.W l 4.sx-W l 4.sx-W l
.........y......... .........
.........#.......... .........#.........y.........y..........
VETT l 5.0x4 l S.0T4 l 0.0 l 5.054 l 5.0T-W l S.0%-W l 5.0%-W l 5.0x W l OM MilX l 1.74E-03 l 1.74E-03 l 0.0 l 1.74E4 l 1.74E-03 l 1.7AE4 l 1.74E-W l 1.74E-03 l
......... ......... ....... y.........#..........y.........#.......... .........y.........# ,
n xAT l 1.14E4 l 1.14E4 l 0.0 l 1.14E4 l 1.14E4 l 1.14E-W l 1.14E-W l 1.14E4 l y ......... ......... .........#.......... .........y.........#..........#......... ..........
- TOTAL
- l 1.M-M l 1.M-N l 0.0 l 1.M4 l 1.M-M l 1.M-M l 1.M.M l 1.M-M l
.........e.........+..........+..........+..........+..........+..........e.........e........., l l
Averaae Individial (wen) 1
- 1 PATWAY T. M GI.TRKT M LIVER KIM THYMID M SKIN \
l
.........#..........# ......... .........y......... ......... ......... ..........
- TOTAL
- l 6.01E-M l 6.01E4 l 0.0 l 6.01E4 l 6.01E4 l 6.01E-06 l 6.01E4 l 6.01E4 l
.........#.......... ......... ......... .........y......... ......... ..........
i l
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APPENDIX B Page 1 I
4
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+-+-+--+-+-+-+-+-+-+-4-+-+- -+-+-+ +
I
- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUC!. EAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 GASE0US EFFLUENT PATHWAY Nearest House LnonL ,
North East 1430 Meters !
PATWM T.twY GI-TRWT M LMR KIDEY THYh010 M SKIN ,
.........p ........ p .........+..........p.........p .........p .........p .........p .........+ i PllW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GutD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IfM
@ LT 4.61E-04 4.64E-04 0.0 4.64E-04 4.64E-04 4.64E-04 4.64E-04 4.64E-04 TEEN 4.6E-04 4.6E-04 0.0 4.6E-04 4.6E-04 4.6E-04 4.67E-04 4.67E-04 WILD .4.13E-04 4.13E-04 0.0 4.13E-04 4.13E-04 4.13E-04 4.13E-04 4.13E-04 IWMT l 2.37E-04 2.37E-01 0.0 2.3E-04 2.3E-04 2.3E-04 2.37E-04 2.37E-04 TOTAL MLT 4.64E-04 4.64E-04 0.0 4.64E-04 4.64E-04 4.64E-04 4.64E-04 4.64E-04
~) TFEN 4.67E-04 4.67E-04 0.0 4.67E-04 4.67E-04 4.67E-04 4.6E-04 4.67E-04 WILD 4.13E-04 4.13E-04 0.0 4.13E-04 4.13E-04 4.13E-04 4.13E-04 4.13E-04
._IWNIT 2.3E-04 2.3E-04 0.0 2.3E-04 2.3E-04 2.3E-04 2.3E-04 2.37E-04
.........p.........p .........p .........p .........p .........p .........+..........p .........+
Nearest House (mun)
East North East 1140 MTERS PATWM T.BWY GI-TRKT M LMR KIUEY THYml0 M SKIN :
.........p.........p.........p.........p.........p.........p.........p.........p.........+ l PLlW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GUID 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I/M MLT 8.3E-04 8.3E-04 0.0 8.3E-04 8.37E-04 8.3E-04 8.37E-04 8.37E-04 i TEEN 8.4E-04 8.4E-04 0.0 8.43-04 8.4E-04 8.42E-04 8.4E-04 8.42E-04 Wild 7.45E-04 7.45E-06 0.0 7.4T-04 7.45E-04 7.45E-04 7.45E-04 7.45E-04 1 IWMT 4.2T-04 4.2T-04 0.0 4.2T-04 4.2T-04 4.2T-04 4.2T-04 4.2T-04 TOTAL MLT 8.3E-04 8.3E-04 0.0 8.3E-04 8.3E-04 8.3E-04 8.3E-04 8.37E-04 TEEN 8.4E-04 8.42E-04 0.0 8.4E-04 8.4E-04 8.42E-04 8.4E-04 8.42E-04 Wild 7.45E-04 7.45E-04 0.0 7.45E-04 7.45E-04 7.45E-04 7.45E-04 7.45E-04 IWMT 4.2T-04 4.2T-04 0.0 4.2T-04 4.2T-04 4.2T-04 4.2T-04 4.2T-04
..........p .........e .........+..........+..........e .........e .........p .........e .........+
4
' APPENDIX B Page 4
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 O.s RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Nearest House ( m )
South East 2560 Meters PATWM T. M GI-TRKT M LIVER KIM MMID M SKIN
......... y.........p .........p.........p .........p .........p .........e .........+..........+
PLlW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GMC 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I/M MLT 1.2SE-04 1.2SE-04 0.0 1.2SE-04 1.2SE-04 1.2SE-04 1.2SE-04 1.2SE-04 TEEN 1.2T-04 1.2T-04 0.0 1.2T-04 1.2T-04 1.2T-04 1.2T-04 1.2T-04 WILD 1.11E-04 1.))E-04 0.0 1.11E-04 1.11E-04 1.11E-04 1.11E-04 1.1]E-04 IWMT 6. 4T-% 6. 4T-% 0.0 6.4T-% 6.4T-% 6. 4T-% 6.4T-05 6.4T-05 TOTAL MLT 1.2SE-04 1.2SE-04 0.0 1.2SE-04 1.2SE-04 1.2SE-04 1.2SE-04 1.2SE-04 ,
\ TEEN 1.2T-04 1.2T 04 0.0 1.2T-04 1.2T-04 1.2T-04 1.2T-04 1.2T-01 WILD 1.11E-04 1.11E-04 0.0 1.11E-04 1.11E-04 1.11E-04 1.11E-04 1.11E-01 IWMT 6.4T-OS 6. 4T-B 0.0 6.4T-% 6. 4T-% 6.4T-% f 6.4T-B 6.4T-M
.......e.........p.........p.........e.........p.........e.........p.........e.........+
Nearest House (m)
South South East 7800 Meters PATWM T. M GI-TRKT M LIVDt KIM THMID M SKIN ;
.........p.........p.........+..........p.........p.........+..........p .........p.........+ l PLLW \ 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 '
GMD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I/M M LT 1.7T-05 1.7T-% 0.0 1.7T-% 1.7T-% 1.7T-05 1.7T-% 1.1T-05 TEEN 1.7]E-% 1.71E-% 0.0 1.71E-% 1.7]E-% 1.7]E-OS 1.71E-B 1.'1E-05 WILD 1.51E-OS 1.5]E-% 0.0 1.51E-% 1.51E-m 1.51E-% 1.5]E-05 1.11E-05 IWMT 8.7T-06 8.7T-% 0.0 8.7T-06 8.7T-06 8.7T-06 8.7T-06 8.!T-06 TOTAL l l MLT 1.7T-% 1.7T-% 0.0 1.7T-% 1.7T-OS 1.7T-OS 1.7T-M 1. ,'T-%
TEEN 1.71E-% 1.71E-% 0.0 1.71E-% 1.71E-% 1.71E-M 1.71E-% 1.)1E-05 WILD 1.51E-% 1.5]E-% 0.0 1.51E-% 1.51E-06 1.51E-% 1.5]E-B 1.51E-M IWMT 8.7T-06 8.7T-06 0.0 8.7T-06 8.7T-% 8.7T-06 8.7T-06 8.7T-06
.........p.........p.........p.........p.........p.........p.........p.........p.........+ l 1
7 (d
l APPENDIX B Page 5 l l
1
i l
l 1
- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT ID V
JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN i 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Neamst House (w)
South 6490 Meters PATINAY T. M GI-TRKT M UVER Kim THYlDID M SKIN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
-P!LW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Gu!D 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IthAL
@ LT 1.82E-% 1.M-% 0.0 1.M-% 1.82E-% 1.82E-% 1.82E-B 1. M -05 TEM 1.84E-% 1.84E-% 0.0 1.84E-% 1.84E-% 1.84E-05 1.84E-M 1.84E-05 WILD 1.62E-% 1.62E-05 0.0 1.62E-% 1.62E-% 1.62E-% 1.62E-% 1.62E-%
ItFM 9.33E-06 9.33E-05 0.0 9.33E-06 9.33E 06 9.33E-06 9.33E-06 9.33E-06 TOTAL ;
p) MLT 1.8?E-% 1.82E-M '
- 0. 0 1.82E-% 1.8?E-% 1.82E-05 1.82E-05 1. M -05
( 3 mild 1.84E-OS 1.62E 4 1.84E-OS 1.62E-05 0.0 0.0 1.84E-%
1.6E-05 1.84E-%
1.62E-W 1.84E-%
1.62E-05 1.84E-05 1.62E-05 1.84E-OS 1.62E-05 IffMIT 9.33E-06 9.33E-06 0.0 9.33E-06 9.33E-06 9.33E-06 9.33E-06 9.33E-06
.........p.........+..........+..........p.........p.........p.........p.........p.........+
Neamst House ( m )
South South 2900 Meters, PATINAY T.8D' GI-TRKT M WER KMY THYlDID M SKIN
.........p .........p .........e .........p .........p .........p .........e .........+..........+
PLlK 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9Q90 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IthAL M LT 1.23E-04 1.23E-04 0.0 1.23E-04 1.23E-04 1.23E-04 ' 1.23E-04 1.23E-04 TEM 1.24E-04 1.24E-04 0.0 1.24E-04 1.24E-04 1.24E-04 1.24E-04 1.24E-04 mild 1.1T-04 1.1T-04 0.0 1.1T-04 1.1T-04 1.1T-04 1.1T-04 1.1T-04 IWM 6. T-OS 6.3T-% 0.0 6.3T4 6.3T-% 6.3T-OS 6.3T-05 6.3T-%
TOTAL M LT 1.23E-04 1.23E-04 0.0 1.23E-04 1.23E-04 1.23E-04 1.23E-04 1.23E-04 TEM 1.24E-04 1.24E-04 0.0 1.24E-04 1.24E-04 1.24E-04 1.24E-04 1.24E-04 WILD 1.1%-04 1.1T-04 0.0 1.1T-04 1.1T-04 1.1T-04 1.1T-04 1.1T-04 ;
IWM 6.3T-05 6.3T-% 0.0 6.3T-% 6.3T-% 6.3T-B 6.3T-05 6.3T-W \
.........+..........p .........p .........p .........p .........p ......... p .........p .........+
0 APPENDIX B Page 6 1
i l
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
/G JULY-DECEMBER 1987
\d RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Nearest House (m)
South West 1220 Meters PATWAr T. M GI-TRCT M UVER KIM THYM 1D M SKIN
........ 4..........e.........p.........p........ p.........p.........e .........y.........+
PI M 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GUID 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I/M M LT 1.27E-B 1.2E-03 0.0 1.27E-03 1.27E-W 1.2E-03 1.27E-03 1.27E-03 TEM 1.2T-03 1.28E-03 0.0 1.2T-W 1.2T-m 1.2T-W 1.28E-03 1.2T-03 MILD 1.13E-m 1.13E-03 0.0 i.13E-03 3.13E-W 1.13E-03 1.13E-03 1.13E-03 IWM 6.51E-04 6.51E-04 0.0 6.51E-04 6.51E-04 6.5]E-04 6.51E-04 6.5]E-04 TOTAL MLT 1.27E-W 1.2E4 0.0 1.2N-B
,p TEEN 1.2T-W 1.2T-03 0.0 1.2T.03 1.27E-03 1.2T-W 1.27E-03 1.2T-W 1.27E-03 1.2T-03 1.27E-03 1.2T-03 WILD 1.13E-03 1.13E-03 0.0 1.?3E-D 1.13E-03 1.13E-W 1.13E-W 1.13E-03 I/F M 6.51E-04 6.S]E-04 0.0 6.51E-M 6.5]E-04 6.51E-04 6.51E-04 6.51E-04
.........p.........p.........p.........p.........p.........p........ + .........+.........+
Nearest Houg ( m )
hstSouthWett230 Meters PATWAY T. M GI-TRKT M UVER KIM THM O M SKIN
.........p.........p.........p.........p........ , .........p.........p.........p.........+
PI M GUID 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0
&0.0 0.0 0.0 0.0 0.0 0.0 0.0 l
1/M l MLT 3.23E-04 3.23E-04 0.0 3.23E-04 3.23E-04 3.23E-04 3.23E-04 TEM 3.23E-04_ _,
\
3.2SE-04 3.2SE-04 0.0 3.2SE-04 3.2SE-04 3.2SE-04 3.2SE-04 3.2SE-04 ;
Wild 2.8T-04 2.8T-04 0.0 2. W -04 2.8T-04 2.8T-04 2.8T-04 2. M -04 !
IWM 1.65E-04 1.65E-04 0.0 1.65E-04 1.65E-04 1.65E-04 1.65E-04 1.65E-04 l TOTAL
, MLT 3.23E-04 3.23E-04 0.0 3.23E-04 3.23E-04 3.23E-04 3.23E-04 3.23E-04 l TEEN 3.2SE-04 3.2SE-04 0.0 3.2SE-04 3.2SE-04 3.2SE-04 3.2SE-04 3.2SE-04 mild 2.8T-04 2.8T-04 0.0 2. M -04 2. M -04 2.8T-04 2.8SE-04 2. M -04 l I/FM 1.65E-04 1.65E-04 0.0 1.65E-04 1,65E-04 1.65E-04 1.65E-04 1.6EE-04
.........p.........p.........p.........p.........p.........p.........p.........e.........+
0 APPENDIX B Page 7 1 1
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 V RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Nearest House Lccel West 3230 Meters PATWN T. M GI.TRKT M UVER KI M Y 7HYmID M MN
.........p.........p.........p.........p.........p .........p.........p..........e.........+
PM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GQtt!D 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IMAL KblT 1.11E-04 1.11 & O4 0.0 1.11E-04 1.11E-04 1.11 & O4 1.11E-04 1.11E-04 TEM 1.1E-04 1.12E-04 0.0 1.1E-04 1.1E-04 1.1E-04 1.1E-04 1.12E.04 WILD 9.9T-% 9.00&% <>. 0 9.9T-% 9.9T-% 9.90&% 9.9T-% 9.9T-05 ItFMT 5.69E-% S.69E-W 0.0 S.69&% 5.69&B S.69&% S 69E-% S.69E-05 TOTAL KULT 1.11E-04 1.11E-04 0.0 1.11E-04 1.11&O4 1.11 & O4 1.1]E-04 1.11 & O4 O TEM WILD 1.1E-04 9.9T-%
1.12E-04 9.9T-%
0.0 0.0
! W -04
- 9. 9T-B 1.12E-04 9.9T-%
1.12E-04 9.9T-%
1.12-06 9.9T4 1.12 & O4 9.9T-%
ItFMT S.69E-% S.69E-% 0.0 S.69E-% S.69E-% 5.69E-B S.69&% S.69E-OS
.........e.........e.........e.........p.........p.........p.........e.........e.........+
Nearest House (nrvn)
West Nod h West 4390 Neters PATW N T. M GI-TRA"T M UVER KI M Y THYM 10 M MN
.........e.........p.........e.........e.........e .........e.........p.........p.........+
PM 00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GR0llD 0.0 0.0 ' O.0 0.0 0.0 0.0 0.0 0.0 IWAL l MULT 7.1T-% 7.1T-% 0.0 7.1T-% 7.1T-% 7.1T-% 7.1T-% 7.1T-W TEM 7.2T-% 7.2T-% 0.0 7.2T-% 7.2T-% 7.2T-% 7.2T-05 7.2T-%
%ILD 6.37&% 6.37E-% 0.0 6.37E-% 6.37E-% 6.3M-% 6.37&% 6.37E-%
IWMT 3.66E-% 3.6T-% 0.0 3.66E-% 3.66C-% 3.66&% 3.6T-% 3.6T-OS TOTAL MULT 7.1T-% 7.1T-% 0.0 7.1T-% 7.1T-05 7.1T-% 7.1T-% 7.1T-%
TEM 7.2T-% 7.2T-% 0.0 7.2T-% 7.2T4 7.?E-% 7.2T-% 7.2T-% i Wild 6.37&% 6.37&OS 0.0 6.37&% 6.37E-% 6.37E-% 6.37E-% 6.37E-%
IWMT 3.6T-% 3.66E-% 0.0 3.66E-% 3.6T-% 3.6T-% 3.66&% 3.6T-%
...........p.........p.........p.........p.........p.........p.........p.........p.........+
q Q
APPENDIX B Page 8
p SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Q JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Neartst House (m)
North West 5330 Meters PATWM T. M GI-TRKT M LIVER KIMY TMID M SKIN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
Plln 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GURD 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 IfMAL MLT S.4]E-M S.41E-M 0.0 S.41E-% S.4]E-M S.41E-% 5.41E-05 S.4]E-M TEM S.45E-05 S.45E-M 0.0 S.45E-W S.4SE-W S.45E-% 5.45E-% S.45E-%
WILD 4. M -M 4. M -M 0.0 4.82E-% 4. M -% 4.82E-% 4.82E-05 4.M-%
IWM 2.77E-% 2.77E-% 0.0 2.77E-M 2.77E-% 2.77E-M 2.77E-W 2.77E-B TOTAL M LT S.4]E-B 5.4]E-% 0.0 S.4]E-% S.41E-B S.4]E-% S.4]E-% S.41E-05 l
)< TEM Wild S.45E-%
4.82E-%
5.45E-B 0.0 0.0 S.45E-% S.45E-% 5.45E-M S.45E-05 S.45E-%
4.82E-05 4.82E-05 4.M-% 4.8?E-% 4.82E-05 4. M -05 IWM 2.77E-% 2.7E-% 0.0 2.77E-B 2.77E-% 2.77E-05 2.77E-M 2.77E-% l
.........p.........p.........p.........p.........p.........p.........p.........p.........+
Nearest House (m)
North North West 7250 Meters PATWM T. M GI-TRKT M LIVER KIMY TMID M SKIN j
.........+.........p.........p.........p.........p.........p.........p.........p.........+
PlLPE 0.0 l 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1 Guto 0.0 ' O.0 0.0 0.0 0.0 0.0 0.0 0.0 \
IthAL l MLT 2.6T-% 2.6T-% 0.0 2.6T-% 2.6T-% 2.6T-B 2.6T-% 2.6T-05 TEEN 2.7T-% 2.7T-05 0.0 2.7T-05 2.7T-OS 2.7T-05 2.7T-% 2.7T-%
\
i Wild 2.3T-OS 2.3T-M 0.0 2.3T-% 2.3T-% 2.3T-% 2.3T-% 2.3T-%
IWM i.3E-% 1.3E-% 0.0 1.3E-% 1.3E-% 1.3E-OS 1.37E-W 1.3E-%
TOTAL MLT 2.6T-05 2.6T-% 0.0 2.6T-05 2.6T-05 2.6T-% 2.6T-05 2.6T-%
TEM 2.7T-05 2.7T DS 0.0 2.7T-% 2.7T-% 2.7T.% 2.7T-% 2.7T-05 WILD 2.3T-05 2.3T-05 0.0 2.3T-05 2.3T-05 2.3T-% 2.3T-05 2.3T-05 IWM 1.3E-% 1.3E-05 0.0 1.3E-% 1.3E-% 1.3E-% 1.3E-OS 1.3E-05
.........e.........e.........p.........p.........y.........p.........e .........e.........+
f}
L APPENDIX B Page 9
p SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t i JULY-DECEMBER 1987
'w/ RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Milk Ccw (or m )
East North East 1140 Meters PATWM T. M Gl TRACT M M KIM 7MID LLIG MN
.........p .........e.........e.........p.........p.........p.........e........ p.........+
MT 5.1T-04 5.1T-04 0.0 S.1T-04 5.1T.04 S.1T-04 S.1T-04 S.1T-04 TEEN 6.64E-04 6.6tE-04 0.0 6.64E-04 6.64E-04 6.64E-04 6.64E-04 6.64E-01 WILD 1.0SE-W 1.%E-W 0.0 1.05E-03 1.%E-W 1.BE-W 1.%E-03 1.05E-03 IWM 1.59E-03 1.59E-03 0.0 1.59E-W 1.59E-W 1.59E-W 1.59E-W 1.59E-03
.........e .........e .........e .........+..........+.........-e .........+..........+.........-+
Milk Ccw (nrun)
South West 3190 Meters PA1W M T. M GI-TMCT M LIVER KIM T M ID M MN
.........p .........p.........p.........p. .......p.........p.........p.........p.........+
MT 9.44E-% 9.44E-M 0.0 9.44E-W 9.44E-M l 9.44E-% 9.44E-M 9.44E-05 TEW 1.23E-04 1.23E-04 0.0 1.23E-04 1.23E-04 > 1.23E-04 1.23E-04 1.23E-04 WILD 1.94E-04 1.94E-04 0.0 1.94E-04 1.94E-04 1.94E-04 1.94E-04 1.94E-04 IWM 2.95E-04 2.95E-04 0.0 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04
.........e.........e.........p.........e .........+..........p .........p.........p.........+
Milk Ccw (nrun)
West South West 3620 Meters PATW M T. M GI-TRACT M LIVER KIM TMID M MN
.........e.........e.........e.........p.........e.........e.........p.........e.........+
MT 5.11E-% 5.11E-% 0.0 5.11E-% S.11E-M 5.11E-% 5.11E-05 5.1]E-%
TEM 6.65E-05 6.65E-% 0.0 6.65E-% 6.65E-% 6.65E-% 6.65E-05 6,65E 4 WILO 1.05E-04 1.05E-04 0.0 1.TE-04 1.05E-04 1.05E-04 1.%E-04 1.05E-04 IWM 1.59E-04 1.59E-04 0.0 1.59E-04 1.59E-04 1.59E-04 1.5T-04 1.59E-04
.........p.........e.........p.........p.........p.........p.........p.........p.........+
D APPENDIX B Page 10
\
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY MHk Cm (nrm)
West 7740 Nettal.,
PATWAY T.8D' GI-TRKT LUE LMR KilMY TH M ID l.lhG SKIN
.........p .........p........ + .........e .........p .........p .........p .........+..........+
MT 1.41E-M l 1.41E-% 0.0 1.41E-M 1.41E-M 1.41E-% 1.41E-% 1.4]E-M TEM 1.84E-% 1.84E-M 0.0 1.84E-% 1.84E-% 1.84E-% 1.84E-% 1.84E-%
Wild 2.91E-% 2.91E-B 0.0 2.9]E-W 2.91E-% 2.91E-% 2.91E-% 2.91E-%
. IWM 4.41E-% 4.41E-M 0.0 4.41E-% 4.41E-% 4.4]E-% 4.41E-% 4.4]E-%
.........p.........p.........p.........p.........p.........p.........p.........p.........+
O !
l l
l l
I O' APPENDIX B Page 11
p SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Q JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY kat kin 1 (msn) k d h 440 k ters PATWAY T. M GI.TRKT WE LMR KIM THYml0 M MN 1
.........p .........e .........p .........p .........p .........+..........p .........+..........+
AWLT 8.2T-04 8.20E-04 0.0 8.2T-04 8.2T-04 8.2T-04 8.2T-M 8.20604 TEEN 4.89E-04 4.89E-04 0.0 4.89E-04 4. M -04 4.89E-04 4.89E-04 4.89E-04 Wild 5.9]E-04 S.91E-04 0.0 S 91E-04 S.91E-04 S.9]E-04 S 91E-04 S.91E-04
.........p.........p.........p.........e.........p.........p.........p.........e.........+
hat kimi (mnun) ;
O O kdh krth East 430 kters PATWAY T. M GI.TRKT DE LIVER KIM 1HYml0 M SKIN
.........y.........p.........p.........p.........p.........p.........p.........p.........+
AWLT 8.4E-04 8.4E-04 0.0 8.4E-04 8.4W-04 8.4E-04 8.4%.04 8.4E-04 '
TEEN 5.0T.04 S.06E-04 0.0 S.06E-04 5,06.E.04 S 0T-04 S.06E-04 S.0T.04 l Wild 6.11E-04 6.11E-04 0.0 6.11E-04 6.11E-04 6.11E-04 6.11E-04 6.11E-04 l
.........p.........p.........p.........p.........p.........p.........p.........p.........+
kat kful (mun) k dh East 430 k ters PATWAY T.B00Y GI.TRKT DE LIVER KIM THYml0 M MN
.........p.........e.........p.........p.........p.........p.........p.........e.........+
MllLT 9.ST-04 9.ST-04 0.0 9.ST-04 9.ST-04 9.ST-04 9.ST-04 9.ST-04 TEEN 5.7]E-04 S.7]E-04 0.0 S 7]E-04 S.71E-04 5.71E-04 S.7]E-04 S.71E-N WILD 6.9T-Of 6.9T-04 0.0 6.9T-04 6.9T-04 6.9T-04 6.9T-04 6.9T-04
..........p.........p.........p.........p.........p.........p.........p.........p.........+
O O APPENDIX B Page 12
(]j s,
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY
&at kin! (m)
East North East 450 kters PATWAY T. M GI. TRACT M M KIM THYmlO M MN
.........p.........e .........p.........p .........e .........p .........+..........e .........+
MT 9.61E-04 9.61E-04 0.0 9.61E-04 9.61E-04 9.61E-04 9.6]E-04 9.6]E-04 TEEN 5.73E-04 S.73E-04 0.0 S.73E-04 5.73E-04 S.73E-04 5.73E-04 S.73E-04 WILD 6.9E-04 6.9E-04 0.0 6.93-04 6.92E-04 6.92E-04 6.9E-04 6.92E-04
.........p .........p .........p.........p .........p .........+..........+..........+..........+
kat kin 1 (m)
East 470 K2ters PATWAY T. M GI.TRKT M LIVm KIM 7HYmlO M MN '
.... ....p.........+,.........p.........p.........p.........p........-p.........p.........+
C MT 7.24E-04 7.24E-Oe 0.0 7.24E.04 7.24E-04 7.24E-04 7.24E-M 7.2E-04 TEM 4.32E-04 4.32E-04 0. 0 4.3E-04 4.33-04 4.3E-04 4.32E-04 4.3E-04 Wild 5.22E-04 S.2E-04 C0 S.2E-04 S.22E-04 S.22E-04 S.2E-04 S.22E-04
.........p .........+..........p.........p.........+..........p .........p.........p .........+
k at k imal ( m )
East South East 670 k ters i l
PATWAY T.m0f GI.TRKT M LIVm KIM THYmlD M MN
.........p.........p.........p.........p.........y.........e.........p.........p.........+
MT 3.S3F-04 3.S3E-04 0.0 3.S3E-04 3.SX-04 3.53E-04 3.53E-04 3.S3E-04 TEM 2.1T-04 2.1T-04 0.0 2.1T-04 2.1T-04 2.1T-04 2.1T-04 2.1T-04 Wild 2.54E.04 2.54E-04 0.0 2.54E-04 2.54E-04 2.54E-04 2.54E-04 2.54E-04
.........p.........p.........p.........p.........p.........p.........p.........p.........+
l 1
l APPENDIX B Page 13 l l
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT hd JULY. DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION l
i APPENDIX B l 1
RADIOLOGICAL IMPACT ON MAN .
l 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY Meat kimi (nrm)
South East 240 Meters l pal % (Y T.M GI. TRACT M LIVER KIUD' TMID M MN \
.....-...p .........e .........p .........p .........p .........+..........p .........p .........+
.. M T 2.5W-W 2.5E4 0.0 2.5N-03 2.5W-03 2.57E-03 2.5W4 2.5W-W TEW 1.53E 4 1.53E 4 0.0 1.53E 4 1.53E-03 1.53E-03 1.53E-03 1.53E-03 Wild 1.8SE-m 1.85E-03 0.0 1.85E-03 1.85E-W 1. W 4 1.8SE 4 1.8SE-03
.........e .........p .........e .........p . .......+..........+..........+.....-....+.........-+
l 1
Meat kion1 (nrm) i South South East 200 Meters PATWAY T. M GI.TRKT M LinR KilMY TMID M SKIN
.........p........ p.........p.........p.........p.........p.........p.........e.........+ ;
MT 4.1N-03 4.1W-W 0.0 4.1N4 4.1N-W 4.1N4 4.17E-03 4.1N-m '
TEM 2. W -03 . 2. M -W 0.0 2. M -03 2. M -03 2. M -03 2.49E-03 2.49E-W WILD 3.0T-03 l 3.0T-03 0.0 3.0T-03 3.0T-03 3,0T-03 3.0T-03 3.0T-03
.........p.........p.........p.........p.........p.........p.........p.........p.........+
Neat kimal form)
South 200 Meters PA1WAY T. M GI. TRACT M LIVER KilMY TMID M MN
.........p.........p.........p.........p.........p.........p.........p.........e.........+
MT 3.24E-03 3.24E-03 0.0 3.24E.03 3.24E 4 3.24E-03 3.24E-03 3.24E-03 TEM 1.93E-m 1.93E-03 0.0 1.93E-W 1.93E-W }.93E-m 1.93E-03 1.93E-03 WILD 2.34E-W 2.34E-03 0.0 2.34E-a1 2.34E-03 2.34E-03 2.34E-03 2.34E-03
.........+..........p.........p.........p.........p.........p.........p.........p.........+
/ APPENDIX B l \ Page 14 i
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Os JULY. DECEMBER 1987 l RANCHO SEC0 NUCLEAR GENERATING STATION l l
APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY l
h at Anim i (mun) i South South West 200 k ters l
PAllHAY T. M GI-TMCT M LIVER KIM TMID M MN
.........p.........p.........p.........p.........p.........p.........p.........p.........+
MLT 5.31E-03 5.31E-03 0.0 5.31E-03 5.31E-03 5.3]E 4 5.31E-03 5.3]E-03 i TEEN 3.17E-03 3.1E-W 0.0 3.17E-03 3.1E-03 3.17E-03 3.1E-03 3.17E-D \
Wild 3.W-W 3.83E 4 0.0 3. W -03 3.W-W 3. W -03 3.83E-W 3. W 4 \
........ p........ + .........p.........p.........p.........p.........+..........p.........+ i l
kat kin 1 (mrL South West 290 kters
~
PATINAY T. M GI.TMCT M LIVER KT M TMID M MN
..................p.........p.........p.........#..........p.........p.........p.........+ l MLT 4.18-W 4.1 8 -03 0.0 4.1E4 4.1 8-03 \ 4.12E-G3 4.12E-m 4.13-03 l TEEN 2.45E-m 2.45E-W 0.0 2.45E-W 2.45E-W 2.45E-03 2.45E 4 2.45E-03 WILD 2.9E4 2.9E4 0.0 2.9E-03 2.97E-W 2.97E-W 2.9E-03 2.97E-03
.........p .........p .........p .........+..........p .........p .........+..........p .........+
kat kim1 (mun)
West South West 400 kters PAllWAY T. M GI-TRACT M LIVER KIM TMID WG MN
.........p.........p.........p.........p.........p.........p.........p.........p.......4 MLT 1.61E-03 1.61E-03 0.0 1.61E-03 1.61E 4 1.6]E-W 1.61E-03 1.61E-03 TEEN 9.59E-04 9.59E-04 0.0 9.59E-04 9.5 % -04 9.59E-04 9.5%-04 9.59E-04 l Wild 1.1T-03 1.1T-03 0.0 1.1T-G3 1.1T-03 1.1T-03 1.1T-W 1.1T-03 t l
.........p.........p.........p.-.......p.........p.........p.........p.........p.........+
l O APPENDIX B Page 15
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i O SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987
'd RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Neat Animi (m)
West 510 Neters PATIMM T. M GI.TRKT M LIVER KIM THYml0 M MN l
.........e ,........p.........p.........p.........p........ p.........p.........e.........+ 1 MT 1.0E-03 1.0E-03 0.0 ,
1.07E-03 1.07E-03 1.0W4 1.0E-03 1.0E-03 \
TEEN 6.3E-04 6.37E-04 0.0 6.3n-04 6.3W-04 6.37E-04 6.3E-04 6.37E-04 l OlllD 7.69E-04 7.69E-04 0.0 7.69 & O4 7.69E-04 7.69 & O4 7.69604 7.69604 i
.........p.........y.........p.........p.........y.........p.........p... .,...p.........+ l Neat Anim i (m) ;
West North West 440 Neters s
PATWAY T.800Y GI.TRCT M LIVER KIUEY 1HYml0 M MN
.........p.........p.........p.........e.........p.........p.........e.........e...,.....+ l MT 1.51 & O3 1.51E-03 0.0 E 1.51E-03 1.51E-03 1.5]E-03 1.51E m 1.51E M TEEN 9.00E-04 9.0T-04 0.0 E 9.00E-04 9.0T-04 9.0T-04 9.0T-04 9.0T-04 :
OlllD 1.09E-03 1.09E-03 0.0 E 1.09E-03 1.09E-03 1.09E 4 1.09E-03 1.09E-03 \
.........p.........p...... ..p.........p.........p.........p.........p.........p.........+
Meat k im i (m) l North West 500 Neters l l
PATINAY T. M GI.TRKT M LIVER KIDEY THYmID M MN
.........p.........e.........p.........p.........p.........p.........p.........e.........+ {
MT 1.3T-03 1.3T-03 0.0 1.3T-03 1.3T-03 1.3T-03 1.3T-03 1.3T-03 TEEN 7.?3E-04 7.73E-04 0.0 7.73E-04 7.73E-04 7.73E-04 7.73E-04 7.73E-04 l
, OlILD 9.34E-04 9.34E-04 0.0 9.34E-04 9.34E-04 9.34E-04 9.34 & O4 9.34E-04
.........p.........+..........p.........p.........p.........p.........p.........p .........+
APPENDIX B s Page 16
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O' JULY. DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY Meat Anim i (mun)
Mrth North West 440 Meters PADRM T. M GI. TRACT M LIVER KIM TH M ID M MN
.........p .........p .........p .........+..........p
.........+..........+..........+..........+
._ julT 1.486W 1. W-W 0.0 1.4T-W 1. W -03 1.4E.03 1.4T-03 1.4T-03 TEM 8.84E-04 8.84E-04 0. 0 8.84E-04 8.84E-Of 8.84E.0e 8.84E-04 8.84E-04 Wild 1.07E-W 1.07E-m 0.0 1.0E.03 1.07E.m 1.07E.B 1.07&W 1.07E-03
.........p .........+..........p .........p.........p .........+..........+..........+..........+
MilkGoat (mun)
West 3230 Meters PADNM T. M GI. TRACT M LIVER KIM TH M ID M MN
.........p.........+..........+..........p.........p.........p.........+..........+..........+
KULT 1.3T-04 1. M .04 0.0 1. H -04 1. M .04 1. H .04 1. H -04 1. M .04 TEDV 1.8T-04 1.8T-04 0.0 1.8T-04 1.8T.04 1.80604 1.8T-Od 1.80E-04 WILD 2.8SE-04 2.8SE-04 0.0 2.8SE-04 2.85E.04 2.8SE-04 2.8SE-04 2.8SE-04 IffMT 4.32E-04 4.32E-04 0.0 4.32E-04 4.32E.00 4.32604 4.32E.04 4.32E-04
.........+..........p .........p .........+..........p .........p .........p .........p .........+
0 APPENDIX B Page 17
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN -
1987 QUARTER 4 GASE0US EFFLUENT PATHWAY Nearest G4deo (mrn)
North East 48 0 Neters PATW M T.M GT-TRKT M WER KlatY TMID M MN
.........p.........p.........p.........p.........p.........+..........p.........+.........+
MT 6.37E-% 6.37E-05 0.0 6.3N-05 6.37E-% 6.37E-05 6.3N-05 6.3W-%
TEW 7. M -% 7. M -% 0.0 7. M -% 7. M -% 7. M -M 7. M -05 7. M -05 WILD 1.13 & O4 1.13E-04 0.0 1.13E-04 1.13E-04 1.13E-04 1.13E-04 1.13E-04 ,
.........+..........p .........p .........p .........p .........p ........ w .........p .........+ !
Nearest Garden (nrten)
East North East 1140 Meters PATWM T. M GI-TRCT M WER KMY T M 10 M MN
.........y .........p.........+..........p.........p.........y.........y .........p.........+
MT 1.51E-W 1.51E-W 0.0 1.51&O3 1.SiE 4 1.51E-03 1.51E-m 1.S1E 4 TEM 1.73E-03 1.73E-W 0.0 1.73E 4 1.73E-m 1.73E-W 1.73E 4 1.73E-W mild 2.6T-03 2.6T-W 0.0 2.6T-m 2.6T-03 2.6T-03 2.6T-W 2.6T-03 l
.........p.........p.........p.........p.........p.........p.........p.........p.........+
Nearest Garden fg m )
South East 2560 Neters PATWM T.M GI-TRCT M WER KlutY TMID M MN
.........y .........e.........p.........p.........e.........e .........y.........p.........+
MT 2. M -04 2. M -04 0. 0 2.M-04 2. M -04 C. M -04 2.2T-04 2. M -04 TEM 2.5T-04 2.5T-04 0.0 2.5T-04 2.5T-04 2.5T-04 2.5T-04 2.5T-04 Wild 4.0T-04 4.0T-04 0.0 4.0T-04 4.0T-04 4.0T-04 4.0T-04 4.0T-04
.........p.........p.........p.........p.........p.........p.........p.........p.........+
APPENDIX B C Page 18
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1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT J j (oj JULY-DECEMBER 1987 ..
f RANCHO SECO NUCLEAR GENERATING S7A710N /, )
APPENDIX B RADI0't0GICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY Neartst Gartien immL South 64 X k ters PATWM T.BXW ,.GI-TRXT M LIRR KilMY TH M ID M MN
.........p.........p..... ...p.........p..........p.........p.........p.........e... .....+
NULT 3.29E-% 1 3.29F-% 0.0 ' 3.M-M 3.M-CS 3. M -% 3.29E M 3.29E 4 TEM 3.77E-% 3.77E-M 0.0 3.17E-05 3.77E.% - 3.77E-M 3.77E-M 3.77E 4 WILD 5.84E-M S.84E-% 0.0 ,,,
5.84E-% 5.84E-% S.8T-% 5.84E-M S.84E-%
.........p.........+..........p ... .... m ..........e ..........+..........p .........e .........+
V Neartst Garden f.micL..
i f
s South South West $330 Meters I
PATWM T. M GI.TRKT M LMR KIDD' TMID M MN \
.........p.........+..........p .........p .........p .........+.. .......p.........+..........+
MULT 7.21E-M 7.21E-M 0.0 7.21E-@ .L2LEM 7.2]E-% 7.21E-M 7.21E M TEM 8.2SE-% 8.2SE-% 0.0 8.25E-% 8.2SE 4 8.2SE-% 8.2SE-% 8.2SE-QL ,
Wild 1. M -04 1.2%-04 0.0 1. M -04 1. M -04 1. M -04 1. M -04 1.2&-04 I
.........p .........+..... ....p.........+..........p .........p .........y.........p .........+
r, 3
~i Nearvst Gartien (mn)
South West 3190 kters
(
s PATWM T.8Dt GI-TRKT M LMR KilMY TWMD M MN ,
.........p .........p .........p . .......p.........p .........p .. . 1...e. .......p .... ... 4 MULT 2. M -04 2.8K-QL_QA .._ 2.8T-N 2.8T-N 2. M -04 2.8T-04 2. M -04 TEM 3.2T-04 3.2T-04_, , 0. 0 3.2T -04 3.2T-04 3.2T-04 3.2T 04 3.2T-04 WILD 4.96E-04 4.9 T 04 i 0.0 4.9T-04 4.9T-04 4.9T-04 4.9.iV-04 ) 4.9T-04
.........p.........p.........p.........e.........y.........p.........p.........y.........+
l 1
i APPENDIX B Page 19 l q .
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/ SEMIANN'UAL RADI0 ACTIVE EFFLUENT RCLEASE REPORT O
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APPENDIX B
. RADIOLOGICAL IMPACT ON MAN
- i 3 1937 QUARTER 4 GASEOUS EFFLUENT PATHWAY Nearvst Garden (nrm)
Mt South West 2380 Metga.
PATWAY T. M GI.TPKT M LIVER KILMY THYlDID M %1N
.........p .........p .........p .........p ... .....+..........+..........+..........+..........+
\'
\
__ MT TEEN 3.4T-01 3.9T-04 3.4T-Of 3.9T-Cl 0.0 0.0 3.4T N 3.9TM 3.4T-04 3.9T-04 3.4T-04 3.9T-04 3./M-04 3M-04 3.4T-N 3.?T-04 .
, .__ OlllD 6.04E.04 6M-04 0.0 6.00E.N 6.04E-04 6.04E-04 6M-04 6.N&.QL
.. ....-.p.. .. .. ,.........p.........p.........p .........+.........., .........+..........+
n fl '
1 : .
nmst Gankn tum)
/
,l hst 1230 Meters
\ PATWAY )'.M GI.TMCT M LIVER KilMY THYR 010 M %IN l .........p...... ..p.........p.. ......p.........p.........p.........p.........p.........+
MT 2.01EN.2&lE-04 0.0 2.01E.04 2.01 & O4 2.01E-04 2.01E-04 2.01E.04
!E!N. 2.3T-04 2.3T4 0.0 2.3T-04 . 2.3T4 2.3T-OL_f 3T4 2.3T-04_
. (tfill!
1&E-04 3.5EM 0.0 3.5E4 I 3.5E-04 3.56E 4 3.5E.{4 3.5E4
.........p... .....p.........p.........p... .....p.........p.........p.........p.........+
i ; ,
I t
3> APPENDIX B Page 20
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q SEMIANNUAL RAD [I0 ACTIVE EFFLUENT RELEASE REPOR TULY-DECEMBER 1987 '
GANCHO SEC0 NUCLEAR GrqERATdyy STATION l" l
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1 APPENDIX B ,
.e 3
RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY 1 i
i l !
h Neamst Gaden (mn)
West Nodh West 4390 Meters PA%k', $ T.W G1 TRKT BO\E ' LMR KIllD' THYROID WB MN
......../.e.....Y.u. tp.........e.... 7...)..........p.........p.........p.........p.........+
. 1. M -04 1. M -04 1. M -04 1.M-04').M-Of _ ,
1.4T-04 0.0 a .L.4T-04 1dT-04 1.4%-04 1.4T-04 hM-04 '
__ M ' ) J, M -04
. :_(HIID ,Z,& %_.2.29E 04 0.0 2. M -04 2.2sE-04 2. M -04 2. M -04 2.29E-04
, .. .... 4 ......g.. p ..' . ... p .......:. p ... .....+..........p......,,..p.........p........+
a l , i /\ < ,
T) ,
(D / ,
%)/ Neamst Gaden Layp.)_
r . ; i
\
s'3) ; ) Nodh Wgst 6750 Meters P^p H Q T. m 0Y GI-TRKT BOE LMR K2 THYROID LLNi MN
. . . j . . . . . p . . . . . . . . .p . . . . . . . . .p . . . . . . . . .p . . ..p.........+..........p.........+
. . . . . . .p . . .. . .f.Y MT_ .. .f.3E-M 6.3E-B 0.0 l 6.3E-% 1.6.3E<li 6.3N-% 6.3E-% 6.3E-%
[L K. 7.24E-% 7.24E-% 0.0 4 7.2K-% 1.24E W 7.24E-% 7.24E-M 7.24E-W QMD 1.12E-04 1.12E-0$ 0.0 l1.1E-04 1.12 -04 s 1.12E-04 1.1E-04 1.12E-04
.....y..+..........+..........y.........p.........p ........p.........y.........p.........+
i r* , .s f ( lt
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\ APPENDIX B V Page 21 i
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0U m>M=o mm 0 zcnrm> -
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- > o>r g ;o" oz z,2 a oroc _
mGmzw ; 2 =<-
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- 57a "hQ a DMi h nqD s ED 8. _
- t : : :: .t :: . i .t :. : . : .t :iit : : : : .t : . :i .t :!::t :i . : .+ -
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i: :t :::: .t :: . i .t : . : . : .t :! it ::: : .r : . :i .t : i: :t : i . : .+ -
l oo 9C 9o 9 9o oo 9 -9 -
- i::t :::: .t :l . i .t :. :. : .t :!it :: :: .t : . :i .t :i::t :i . : .+
"l gs "k6 'M6 9o &$6 "h.8 &M6 ". R g " . M.8
- i ::t : : :: .t :: . i .t : . : . :i:! !t :::: .t : . :i f :i::t :i . : .+
g "%6 MSM6 9o - ".$6 Mg6 M$6 ".%g ".$.8 -
3v
(
- i: :t :::: .t :: . i + :,: . : .t :!!t ::: : .t : . : i .t aG "g 6 'mM6 9o & $ 6 M $.8 M $ 6 ". R g ".%.8 -
i::t :i . : .+ -
- ! ::t :: :: .t : : . i .t :. :. : .t :i!t :::: .t : . :i.t : !:
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P"92 9"Mt 9o PNs P"Mk P~Ms 9Mg P52- _
- i:' f : ::: .t :: . i .t : . : . : .t :Iit ::l:.t : . li .t :i:- f :i . : .+
MR _
gs " k.8 b86 9o &M6 ". N 6 "k6 ". $ g " . $.8 -
- i:
lt :::: .t ::.i .t : .: . : .t :!lt :::: .t :. :! .t : i::t :i. : .+ -
g ".k.8 MS86 9o & $ 6 M $.8 ". $ 6 ".R g " $.8 - -
- i:
lt : : : : .t :: . i .t : . : . : .t :!!i::::.t : . :! .t i::t :i . : .+ _
as " % 6 MmM6 9o &$s M$.8 &$& ".Rg ".$.8-
- !:- + :: :
- .t : : . i .t : . : . : .t : i it : : : : .t : . : i .t : !:
- t :i . : .+
=44 9MP2 s"Mt 9o - 9N* P"Mk 9~Ns 95g P52-
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o0 Ob 2o*
m SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l JULY. DECEMBER 1987 l
RANCHO SEC0 NUCLEAR GENERATING STATION j i
APPENDIX B l I
RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASEOUS EFFLUENT PATHWAY ,
i l
Park Kiosk E'ast 52S Meters 1 PATINAY T. M GI-TRKT WE LIVER KilMY T M OID lifG SKIH ;
1
.........p.........p.........p........-p.........p .........p.........p.........p.........+
PM l 0.0 l 0.0 l0.0 l 0.0 l0.0 l 0.0 l 0.0 l0.0 l
.........y.........p .........p .........y .........p .........+...... ...p .........p .........+
GROLID l 0.0 l 0.0 l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l0.0 l
.........e.........p.........p.........p.........p.........p.........p.........e.........+
IMAL AQULT 9.7%-04 9.7%-04 0.0 9.7%-04 9.7%-04 9.7%-04 9.7%-04 9.7 % -04 f~\ .........+..........y .........y .........p .........p .........p .........p ......... p .........+
U TEEN l 9.7%-04 l 9.7%-04 l 0.0 l 9.7%-04 l 9.7%-04 l 9.7%-04 l 9.7%-04 l 9.7%-04 l
.........p.........p ...._.....p.........p.........p .........p.........p.........p.........+
WILD l 8.W-04 l 8.W-04 l 0.0 l 8.W-04 l 8.W-04 l 8.W-04 l 8.W-04 l 8.W-04 l
.........p.........p.........p.........+..........p.........p .........p.........p.........+
IWM l 4.9%-04 l 4.9%-04 l 0.0 l 4.9%-04 l 4.9%-04 l 4.9%-04 l 4.9%-04 l 4.9%-01 l
.........y.........p.........p.........y.........y.........p.........p.........p.........+
TOTAL MlllT 9.7%-04 9.7%-04 0.0 9.7%-04 9.7%-04 9.7%-04 9.7%-04 9.7%-04
.........p.........p.........p.........p.........p.........p.........p.........p.........+
TEEN l 9.7E-04 l 9.7%-04 l 0.0 l 9.7E-04 l 9.7%-04 l 9.7%-04 l 9.7%-04 l 9.7E-04 l
.........p .........p .........p .........p .........p .........+..........p .........p .........+
Wild l 8.W-04 l 8.W-04 l 0.0 l 8.W-04 l 8.W-04 l 8.W-04 l 8.W-04 l 8.W-04 l \
.........+..........y ......... p .........+.......... p .........p ......... p ......... p .........+
IWM l 4.9%-04 l 4.9%-04 l 0.0 l 4.9%-04 l 4.9%-04 l 4.9%-M l 4.9%-01 l 4.9%-04 l
.........y.........y...... ..y.........p.........p .........p.........p.........p.........+
O i APPENDIX B (d Page 23 l
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l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l m
JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION ;
l APPENDIX B RADIOLOGICAL IMPACT ON MAA' i 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY i Warthouse i East North East 225 Meters PATINAY T.B00Y GI-TRKT WE LMR KWD' THYmID WG SKIH l
.........p.........p.........p.........p.........p.........p.........p.........p.........+ l PME l0.0 l 0.0 l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l 0.0 l l
.........p.........p.........p.........p.........p.........p.........p.........p.........+
GUID l0.0 l0.0 l0.0 i90 l0.0 l0.0 l 0.0 l 0.0
.........p.........p.........p.........p.........p.........p.........p.........p.........;
l IIHAL MT 2.95E-03 2.95E-03 0.0 2.95E-03 2.95E-03 2.95E-03 2.95E-03 2.95E-03
.........p.........p.........p.........p.........p.........p.........p.........p.........+
TEN l 2.9E-03 l 2.9E-W l 0.0 0,' l 2.9E-W l 2.9E-03 l 2.9E-03 l 2.95-03 l 2.9E-03 l
.........+..........p.........p.........p .........p.........p.........p.........p.........+
OIIW l 2.63E-03 l 2.W-W l 0.0 l 2.QE-W l 2.W-03 l 2.W-03 l 2.W-03 l 2.W-03 l
.........p....,....p.........p.........p.........p.........p.........p.........p.........+
IwmT l 1.51E-W l 1.5]E-m l 0.0 l 1.51E-m l 1.51E4 l 1.5]E-W l 1.51E W l 1.51E4 l l
........ 4 .........p.........p.........p.........p.........p.........p.........p.........+
TOTAL MT 2.95E-03 2.96E-03 0.0 2.95E-m 2.95E-W 2.95E-03 2.96E-m 2.95E-W
.........p.........p.........+..........p.........p.........p.........p.........+..........]
TEN l 2.9E-03 l 2.9E-03 l 0.0 l 2.9E-03 l 2.9E-03 l 2.92-03 l 2.9E-03 l 2.9E-03 l
.........p.........p........ p.........p.........p.........p.........p.........p.........+
OIIW l 2.W-03 l 2.W-03 l 0.0 l 2.W-03 l 2.63E-03 l 2.W-03 l 2.W-W l 2.63E-03 l
.........p.........p.........p.........p .........p.........p.........p.........p.........+
IWMT l 1.5]E-03 l 1.5]E-03 l 0.0 l 1.51E-W l 1.5]E-m l 1.51E-03 l 1.51E-m l 1.5]E-03 l
.........p .........p .........p .........p .........p .. ......p .........+..........+..........+
APPENDIX B Page 24
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT O JULY-DECEMBER 1987 V RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX B RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 GASE0US EFFLUENT PATHWAY Desian City East North East 250 Meters PATINAY T. M GI-TRACT M LIVER KWD' THYmID WG SKIN
.........p.........p.........p.........p.........p.........+..........p.........+..........+
PLLW l 0.0 l 0.0 l 0.0 l 0.0 l 0.0 l0.0 l 0.0 l 0.0 l
.........p.........+..........p.........p.........p.........p.........p.........p.........+
GMD l 0.0 l 0.0 l0.0 l 0.0 l0.0 l 0.0 l 0.0 l 0.0 l
.........p.........p.........p.........e.........p.........e .........p.........p.........+
ItRAL AllLT 2.44E-03 2.44E-03 0.0 2.44E-03 2.44E-03 2.44E 4 2.44E-03 2.44E-03
(
e)
.........p .........p .........p .........+..........p .........+..........p .........p .........+
TEN l 2.4E-03 l 2.4E-03 l 0.0 l 2.4E-03 l 2.4E-03 l 2.4E-03 l 2.4E-01 l 2.4E-03 l
.........p.........p .........+......... e .........p .........e .........y.........p.........+
OlILD l 2.1E-03 l 2.1E-01 l 0.0 l 2.1E-03 l 2.1E-03 l 2.1E-W l 2.1E-03 l 2.1E-03 l
.........p.........p.........p.........e.........p.........p.........p.........e.........+
11FM l 1.M-03 l 1.M-03 l 0.0 l 1.M-03 l 1.M4 l 1.M-03 l 1.M-03 l 1.M-03 l
.........p.........p.........e.........e .........p.........p.........p.........p.........+
TOTAL MT 2.44E-03 2.44E-01 0.0 2.44E-03 2.44E-03 2.44E-03 2.44E-m 2.44E-03
.........+..........p.........p.. ......p.........y .........p.........y.........p.........+
TEEN l 2.4E-03 l 2.4E-03 l 0.0 l 2.4E-03 l 2.4E-W l 2.4E-03 l 2.4E-03 l 2.4E-03 l
.........p .........p .........e .........e .........e .........p.........+..........p
.........+
OlHD l 2.1E-03 l 2.1E-03 l 0.0 l 2.1E-03 l 2.1E-03 l 2.1E-03 l 2.1E-03 l 2.1E-03 l \
.........+..........p.........p.........p.........p.........p.........p.........p.........+
IlfM l 1.M-01 l 1.M-03 l 0.0 l 1.M-03 l 1.M-03 l 1.M-03 l 1.M-03 l 1.M-03 l
.........p.........p.........p.........p.........p.........+..........p.........p.........+
t l
l I
l i
3 APPENDIX B
{%/ Page 25 4 i
l
L i :
SEMI AllNUAL RADI0 ACTIVE EFFLUENT.-RELEASE REPORT'
- JULY-DECEMBER 1987-4%
W RANCH 0 SEC0 NUCLEAR GENERATING-STATION ~
l 9
APPENDIX C:
f
[ '
I 4
i
' I 4
i 1
1 4
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" " * " " * " " * ' " ' * * ~ m-w meerse w _ _ _ _ ._ _ _ me n e, wy_ , ,yg e y
O V SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 :
RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX C l
RADIOLOGICAL IMPACT ON MAN !
1987 QUARTER 3 LIQUID EFFLUENT PATHWAY !
l Madna Mtilt (MEMI i 1
..............p .........p.........p .........+.............p...........p ..........p .........p .........+
PATWAY SKIN WE LIVER TOTAL BD' TIM 010 KIUEY LUG GI.LLI FISH 0.0 2.17E-02 2.9BE-W 1.95E-W 1.9T-09 1.01E.02 3.3E-W 6.12E-04 IWERTEBR4TE 0.0 4.43E-M 6.1T-% 4.04E-M 5.6T-11 2.0T-B 6.85E-06 5.31E-06 WIfKitG 0.0 0.0 0.0 0.0 0.0 0.0 G.0 0.0 l 9 m ELIfE 2.0SE-03 1.7%-03 1.7T-W 1.7T-03 1.7E-03 1.7E-m 1.7E-W 1.76E-03 WimitG 0.0 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 :
VETTATIW 0.0 5.12E-03 7.01E-W 4.64E-m 3.1T-B 2.3%-03 7.92E-04 3.64E-01 l MilX 0.0 2.11E-03 ?.9T-W 1.9T-W 8.62E-09 9.84E-04 3.27E-04 6.4T-05 '
WAT 0.0 2.59E-04 3.58E-04 2.38E-04 6.73E-09 1.2]E-04 4.0]E-% 4.47E-%
TOTAL 2.0SE-03 3.1T-W 4.11E-N 2.8]E-M 1.7E-03 1.52E-02 6.29E-03 2.49E-03
..............p.........p.........p.........p............e...........p..........e.........p.........+ 1 V
Madan Teenaaer (MEM)
..............p.........p.........p.........p............p...........p ..........p.........p.........+
PATWAY SKIN WE LIVER TOTAL BD' 7HYlDID KIUEY LUG GI.LLI FISH 0.0 1.83E-M 2.44E-m 8.53E-W 1.19E-09 8.3%-03 3.23E-W 3.67E-04 IWtHitbR4TE 0.0 6.22E-% 8.33E-B 2.9T-% 5.6%.11 2.82E-% 1.1T-% 4.95E-06 WIIKitG 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9 0 ELI W 2.%E-04 1.7T-04 1.7%-04 1.7E-04 1.7%-04 1.7T-04 1.7T-04 1.7T-01 SWImitG 0.0 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 7.99E-07 VE6ETATIW 0.0 8.72E.m 1.17E-W 4.1T-03 3.88E-06 3.9T-03 1.54E-m 4.17E-01 MllX 0.0 3.83E-03 5.11E-W 1.79E-03 1.12E-B 1.74E-m 6.7 % -01 8.2T-05 WAT 0.0 2.15E-04 2.89E-04 1.04E-04 4.WE-09 9.77E-% 3.8T-M 2.44E-05 TOTAL 2.05E-04 3.13E-m 4.1E-m 1.55E-m 1.77E-04 1.43E-M 5.67E-03 1.07E-03
..............p.........p.........p.........p............p...........p..........p.........e.........+
APPENDIX C Page 1
SENIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (9
w/
JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX C RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 LIQUID EFFLUENT PATHWAY 1
Matinn Child (FREM)
..............+..........+..........p .........p ............+...........-p ........--e .........+.........-+
PATINAY SKIN WE UVER TOTAL BD' THYROID KHMY LLIC GI-LLI \
FISH 0.0 5.34E-M 5.13E-Q 7.6E-M 2.2E-09 1.67E-02 6.01E-03 3.37E-04 1 IINtHiten4TE 0.0 1.82E-04 1.75E-04 2.74E-M 1.0T-10 5.6E-% 2.04E-% 4.1]E-05 !
WIIKIIC 0. 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 i im ShCWUtE 2.87E-05 2.4E-% 2.4E M 2.4E-% 2. 4T-M 2.4E-B 2.4E-% 2.4E-W
(*) SWitHIfG Vt6tIATIM 0.0
- 0. 0 7.99E-07 2.1E-M 7.99E-07 2.02E-W 7.99E-07 3.07E-03 7.99E-07 6.14E-M 7.99E-07 6.57E-03 7.99E-07 2.3E-03 7.99E-07 2.93E-04 MilX 0.0 9.23E-03 8.86E-03 1.3]E-03 1.7E-M 2.89E-03 1.04E-03 6. ]E-05 FEAT 0.0 3.9T-04 3.82E-04 6.1E-% 4.85E-09 1.24E-04 4. 4E-% 1.27E-05 TOTAL 2.87E-04 8.42E-W 8.09E-W 1.2]E-W 2.55E-M 2.64E-M 9.5E-03 7.34E-01
..............e.........+..........e.........e ............p ...........p ..........p .........p ......... ,
1 4
l l
I l
O APPENDIX C Page 2
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX C RADIOLOGICAL IMPACT ON MAN 1 1987 QUARTER 3 LIQUID EFFLUENT PATHWAY Averaae kMt D.lB)
..............e.........e.........e.........e...........-+...........+...........+..........+.........-+
PATINAY SKIN WE LIVER TOTAL KD' TH @ l0 KilMY litG GI-LLI _
FI91 0.0 4. 2E-% S.87E-% 3.8SE-% 3.87E.12 1.99E-M 6.62E-06 1.2]E-%
IfWERTEMATE 0. 0 4.43E-07 6.1T-07 4.04E-07 5.6%.13 2.0T-07 6.85E-M S.3]E-%
WIIKIIG 0.0 1.64E-06 2.2SE-M 1.4T-M 2.3T-10 7. W -07 2.54E-07 1.2T-07 SCRELitE 1.7T-07 1.4T-07 1.4E-07 1.4E-07 1.46E-07 1.4E-07 1.4T-07 1.4E-07
%IMIW 0.0 6.63E.10 6. W .10 6. W .10 6. W .10 6. W -10 6.63E.10 6. W .10 834 TIM 0.0 3.3E.10 3.3E.10 3.3E.10 3.3 3 10 3.3E.10 3.3E.10 3.32E.10 VukiATIM 0.0 1.33E-% 1.82E-% 1.2T-03 8.23E.11 6.2T-06 2.0SE-06 9.3&-07 MIlX ' O.0 S.34E-06 7.3E-06 4.81E-% 2.1T-11 2.4%-M 8.27E-07 1.62E-07 WAT 0.0 1.6T-06 2.2]E-% 1.47E-06 4.1T.11 7.4E-07 2.4T-07 2.7E-07
(~)\
q TOTAL 1.7T-07 9.84E-% 8.73E-% 5.88E-% 1.47E-07 3.0SE-% 1.02E-M 2.88E-%
..............e.........e.........e.........e............e ...........e..........e.........e.........+
cO APPENDIX C V Page 3
i l
O SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT td JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX C RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 LIQUID EFFLUENT PATHWAY Averaoe Teenaaer (M9f) l l
..............p .........e.........p .........e ............+...........-p ..........+..........p .........+
PATWAY SKIN 8W LTVER TOTAL M TWFOID KID \EY LLIG GI-LL'__
FISH 0.0 4.53E-% 6.0SE-W 2.11E-M 2.94E.12 2.06E-% 7.99E-06 9.0T-b? .
~'h IWD1iEWATE 0.0 4.6E-07 6.2SE-07 2.22E-07 4.24E-13 2.1E-07 8.23E-B 3.7]E-B (Q BitKIfC Sh09ELIIE 0.0 9.64E-07
- 1. M-%
8.25E-07 2.1T-06 7.62E-07 1.63E.10 7.34E-07 2.8SE-07 7.98E-B 8.2SE-07 8.25E-07 8.25E-07 8.25E-07 8.25E-07 8.2SE-07 WIMfitC 0.0 3.75E-09 3.75E-09 3.75E-09 3.75E-09 3.75E-09 3.75E-09 3.75E-09 80ATIfB 0.0 1.8T-09 1.8T-09 1.88E-09 1.8BE-09 1.8T-09 1.88E-09 1.8W-09 VEGETATIB 0.0 4.19E-% 5.63E-06 1.9E-% 1.8E-10 1.9T-% 7.41E-M 2.01E-06 MilX 0.0 2.12E M 2.82E-% 9.8T-07 6.2W-12 9.62E-07 3.73E-07 4.53E-B WAT 0.0 2.1T-07 2.9]E-07 1.04E-07 4.04E-12 9.81E-B 3.8]E-06 2.45E-B TOTAL 9.64E-07 9.2SE-% 7.29E-% 4.3E-% 8.3]E-07 4.23E-% 1.7T-B 3.94E-06
..............p.........+..........p.........p............p...........p..........p.........+..........+
[')
'v APPENDIX C Page 4
c SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 i RANCHO SEC0 NUCLEAR GENERATING STATION I
APPENDIX C ;
RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 LIQUID EFFLUENT PATHWAY ;
t i
i Averaae Child (WEM) '
.............. p .........p .........p .........p ............p...........p ........-.y .........+..........+
PA11NAY SKIN WE UVER TOTAL B1h' TIMOID KHMY WG GI-lU ;
FIS1 0.0 5.5%-% 5.37E-% 7.9 %-06 2.3 % .12 1.75E-% 6.29E-% 3.53E-07 :'
IINtHittMTE 0.0 5.99E-07 5.77E-07 9.0SE-B 3.57E.13 1.87E-07 6.74E-W 1.3E-B
") WIfKItG 9EM UfE 0.0 1.95E-07 4.75-06 1.67E-07 4.54E-%
1.67E-07 6.9E-07 1.67E-07 3.13E.10 1.67E-07 1.4%-06 1.67E-07 5.32E-07 1.67E-07 6.79E-B 1.67E-07 \
%IWfItG 0.0 7.59E.10 7.59E.10 7.59E.10 7.59E.10 7.59E.10 7.59E.10 7.59E.10 -
BMTIfG 0.0 3.79E.10 3.79E.10 3.79E.10 3.79E-10 3.79E.10 3.79E.10 3.79E.10 V8tIATIW 0.0 1.45E-% 1.39E.% 2.13E-06 4.23E.11 4.55E-06 1.64E-06 2.01E-07 MllX 0.0 8.61E46 8.23E-06 1.22E-% 1.65E.11 2.69E-06 9.67E-07 5.72E-m WAT 0.0 6.49E-07 6.25E-07 1.01E-07 7.94E.12 2.mE-07 7.31E-B 2.07E-m ,
TOTAL 1.95E-07 8.5]E-05 8.17E % 1.24E-B 1.69E-07 2.6%-% 9.74E-06 8 &E-07
..............p.........p.........p.........p............p...........p..........p.........p .........; ,
i
( APPENDIX C
\ Page 5 1
l
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 d RANCHO SEC0 NUCLEAR GENERATING STATION l
APPENDIX C i RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 3 LIQUID EFFLUENT PATHWAY ;
f I
General Pooulation Lbses (MAV REM)
..............e.........e ........e.........e............p...........e..........e .........e.........+
PATWM l SKIN l WE l LIG l TOTAL BD' l 7WROID l KILMY l WG lGI-LLI l
..............e.........e.........e.........e............e ...........e..........e .........e........-+
p y
. FISH ItNtxttmATE 0.0 0.0 9.2M-m 9.6T-M 1.1T-W 6.3E-m 6.69E-%
7.14E-10 3.99E-03 4.1T-%
1.3W-% 2.0T-04 1.24E-04 1.04E.10 1.W-% 9.03E-05 WitK1tG 0.0 4.5T-04 5.5E-04 2.63E-04 4.95E-% 1.85E-04 6'.39E.05 2.2]E-%
90EUtE 5.45E-05 0.0 0.0 4.67E-% 4.67E-% 0.0 0.0 0.0 SWIM 11tG 0.0 0.0 0.0 2.1E-07 2.1E-07 0.0 0.0 0.0 BMTitG 0.0 0.0 0.0 1.0T-07 1.0T-97 0. 0 0.0 0.0 VEWTATIW 0.0 6.54E-03 7.71E-03 3.3T-W 2.9E-% 2.57E-W 9.01E-04 2.73E-M MilX 0.0 3.34E-W 3.WE-m 1.4E-W 9.2T-09 1.2%-03 4.5]E-04 5.5T-05 WAT 0.0 5.13E-04 6.49E-04 3.4T-04 1.11E-% 2.17E-04 7.4E-% 6.6T-%
TOTAL 5.45E-05 2.WE-W 2.47E-W 1.1T-W 4.7]E-% 8.2T-W 2.87E-03 6.34E-M APPENDIX C Page 6
l l
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l O JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX D O
l O
1
l t , SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT V JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX 0 ,
t RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY Muim Mult (M)
..............p .........e .........p .........p ........... p...........+...........p .........e.........+
PATWAY %IN WE UVER TOTAL M THYF010 KIUEY M GI-I,U FIS4 0.0 7.15E-02 1.04E-01 7.02E-02 0.0 3.5T-Q 1.1T-02 2.2T-03 IfNtXitbRATE 0.0 1.7T-04 2.49E-04 1.72E-04 0.0 8.33E-M 2.77E-% 4.55E-%
WIfKilm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SMUtE 9.8?E-W 8.39E-03 8.39E-03 8.39E-W 8.39E-03 8.39E-03 8.39E-03 8.39E-03 j WIMIfC 0.0 4.94E-06 4.94E-06 4.94E-% 4.94E-06 4.94E-06 4.94E-05 4.94E-06 VETTATIW 0.0 1.9T-M 2.84E-M 1.93E-02 0.0 9.53E-W 3.17E-03 2.79E-03 \
MllX 0.0 8.09E-03 1.1E-W 7.9]E-03 0.0 3.95E-03 1.3]E-03 3.02E-04 i TEAT 0.0 9.9]E-04 1.45E-03 1.01E-03 0.0 4.83E-04 1.6]E-04 3.99E-04 i TOTAL 9.8?E-03 1.09E-01 1.54E-01 1.07E-01 8.4T-03 5.74E-02 2.47E-02 1.4]E-02
..............p.........p.........p.........p............p...........p..........p.........p.........+
Maim Teenaaer (M) l
..............p.........p .........p .........p ............p ...........p..........+..........p
.........+
PATWAY %IN WE UVER TOTAL M THYROID KIUEY M GI.lU FIS4 0.0 1.0T-01 1.4]E-01 5.14E-W 0.0 E 4.7T-Q 1.86E-W 2.17E-03 Ilh'tHitbRATE 0.0 2.3T-04 3.39E-04 1.29E-04 0.0 E 1.13E-04 4.4T-06 4.1T-06 mitKIIC 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1 SMUfE 9.82E-04 8.39E-04 8.39E-04 8.39E-04 8.39E-04 8.39E-04 8.39E-04 8.39E-M
%ImitG 0.0 4.94E-06 4.94E-06 4.94E-M 4.94E-06 4.94E-06 4.94E-06 4.94E-06 VETTATIW 0.0 3.32E-W 4.6BE-W 1.73E-W 0.0 E 1.57E-Q 6.1T-03 3.13E-W MilX 0.0 1.4T-W 2.0T-M 7.47E-W 0.0 E 6.94E-m 2.69E-03 2.7T-M FEAT 0.0 8.2T-04 1.17E-03 4.53E-04 0.0 E 3.89E-04 1.5]E-04 2.1T-M TOTAL 9.82E-04 1.5T-01 2.))E-01 7.7T-M 8.44E-04 7.1T-02 2.83E-Gi 6.6T-03
..............p.........p.........p.........e............p...........p..........p.........p.........+ l
/9 APPENDIX D V Page 1
-m SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1 JULY-DECEMBER 1987 RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX D RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY Mainn Child (MOH
..............p.........e.........p.........e............p...........p..........p.........p.........+
PRTWAY SKIN WE UVER TOTAL BWY THYmID KHMY LitC GI-lU FISH 0.0 2.91E-01 2.94E-01 4.5T-W 0.0 9.5E-W 3.42E-M 1.96E-03 IWERTEBRATE 0.0 6.94E-04 7.0SE-04 1.25E-04 0.0 2.27E-04 8.15E-06 3.4T-0C WIIKIfC 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
% SmRELIFE 1.37E-04 1.17E-04 1.1E-04 1.17E-04 1.17E-04 1.17E-04 1.17E-04 1.17E-01
\ SWimitC 0.0 4.94E-06 4.94E-06 4.94E-06 4.94E-06 4.94E-06 4.94E-06 4.94E-06 VETTATIW 0.0 7.97E-M 8.04E-W 1.33E-W 0.0 2.6T-W 9.34E-03 2.13E-03 Milk 0.0 3.51E-02 3.53E-W 5.5T-03 0.0 1.14E-W 4.1]E-03 2.7T-01 WAT 0.0 1.51E-03 1.53E-03 2.8BE-04 0.0 4.9]E-04 1.7%-04 1.1T-01 TOTAL 1.37E-04 4.0BE-01 4.1E-01 1.93E-M 1.22E-04 1.33E-01 4.8T-02 4.63E-03
..............p.........+..........p.........p............p...........p..........p.........p.........+
l l
i l
APPENDIX D O' Page 2
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT ,
JULY-DECEMBER 1987 O~. RANCHO SEC0 NUCLEAR GENERATING STATION l
l l
APPENDIX D RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY Averaoe Adult (WH
..............+..........+..........p.........p............+............+...........+..........p........-+
PATWAY SKIN M LMR TOTAL M TH % ID KilMY IUG GI-LLI FISH 0.0 2.35E-05 3.4]E-B 2.3]E-M 0.0 1.15E-% 3.82E-06 7.2]E-07 IWERTEBR4TE 0.0 1.7T-07 2.49E-07 1.72E-07 0.0 8.33E-B 2.77E-B 4.54E-B BIFKI!G 0.0 6.3T-07 9.1T-07 6.27E-07 0.0 3.0T-07 1.TE-07 9.2T-B 90ELIfE 8.15E-B 6.9T-B 6.9T-B 6.9T-B 6.9T-B 6.ST-B 6.9T-B 6.9T-06 S'IMIfG 0.0 4.1T-10 4.1T-10 4.1T.10 4.1T.10 4.]T.10 4.1T-10 4.1T.10 WATitG 0.0 2.0SE.10 2 % E-10 2.%E.10 2.05E.10 2.0SE.10 2.%E-10 2.05E.10 VETTATIM 0.0 S.15E-06 7.ST-06 S.1T-% 0.0 2.52E-06 8.37E-07 7.31E-07 MilX 0.0 3.89E-% 5.63E-% 3.8T-% 0.0 1.9T-% 6.3T-06 1.45E-%
rs WAT 0.0 4.77E-% 6.97E-% 4.8T-06 0.0 2.32E-06 7.74E-07 1.92E-06 O TOTAL 8.15E-B 6.84E-% 1.0T-Of 7.15E-B 7.CT-06
..............p.........p.........p.........y............p.......... +
3.79E-05 1.19E-B S.03E-05
..........p........ 4..........p l
l l
l APPENDIX D Page 3 l i
1
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (m)
V JULY-DECEMBER 1987' RANCHO SEC0 NUCLEAR GENERATING STATION APPENDIX D RADIOLOGICAL IMPACT ON MAN 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY 1
l l
Averaoe Teenaaer (M90 l
..............p.........p.........+..........p............p...........+...........+..........+.........-+
PATWAY SKIH WE LIVER TOTAL WOf THYW)l0 KilMY WC GT-LLI FISH 0.0 2. 4T-% 3.5T-% 1.27E-W 0.0 1.1T-05 4.57E-06 5.3T-07 f IlWtHitbHATE 0.0 1.79E-07 2.54E-07 9.65E-M 0.0 8.5]E-M 3.3T-M 3.13E-M l
\ MIfKIfG 0.0 6.2T-07 8.7T-07 3.2T-07 0.0 2.95E-07 1.14E-07 6.04E-M j SHOWLifE 4.61E-07 3.94E-07 3.94E-07 3.94E-07 3.94E-07 3.94E-07 3.94E-07 3.94E-07 SVIMIIS 0.0 2.32E-09 2.3E-09 2.32E-09 2.32E-09 2.32E-09 2.32E-09 2.32E-09 KMTitG 0.0 1.1T-09 1,1T-09 1.1T-09 1.1T-09 1.1T-09 1.1T-09 1.1T-09 VETTATIM 0.0 1.6T-04 2.2SE-04 8.32E-% 0.0 2.93E-% 2.93E-% 1.5]E-05 MilX 0.0 7.02E-% 9.91E-% 3.59E-M 0.0 3.34E-% 1.29E.M 1.83E-06 WAT 0.0 3.94E-06 5.63E-06 2.1T-M 0.0 1.87E-M 7.2T-07 1.04E-06 TOTAL 4.61E-07 2.6T-04 4.39E-04 1.35E-04 3.97E-07 7.7]E-% 4.80E-% 1.9T-%
..............p .........+..........p .........p ......... ..e ...........p..........p ........ p .........+
0 APPENDIX D Page 4
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
\ JULY-DECEMBER 1987 i RANCHO SEC0 NUCLEAR GENERATING STATION I
APPENDIX D l
RADIOLOGICAL IMPACT ON MAN i 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY )
I l
1 Averaoe Child (M) i
..............p.........p.........p.........p............+............+...........+..........+..........+ j PATWAY . SKIN BOE UVER TOTAL KO' 7WICID KIIM Y WG GI-LU ,
FISH 0.0 3.%E-% 3.%E-% 4.79E-06 0.0 1.75E-% 6.29606 3.53E-07 QG IWERTEBRATE WItKItG 0.0 0.0 2.29E-07 1.8T-06 2.33E-07 1.M-%
4.11E-B 3.03E-07 0.0 0.0
- 7. 4T-B 5.89E-07 2.69E-B 2.12E-07 1.12E-B 4.98E-B 90 ELITE 9.32E-B 7.97E-m 7.97E-B 7.97E-B 7.9E-B 7.97E-B 7.97&B 7.97&B
%ItHItG 0.0 4.7T-10 4.7T-10 4.7T-10 4.79-10 4.7T-10 4.7%.10 4.7T-10 BOATitC 0.0 2.35E-10 2.35E-10 2.35E-10 2.35E-10 2.35E-10 2.35E-10 2.35E-10 VETTATIM 0.0 5.63&O6 5.6%-06 9.33E-07 0.0 1.83E-06 6.59E-07 1.49607 MilX 0.0 3.3T-06 3.4T-06 5.29E-07 0.0 1.1T-06 3.96& O7 2.67E-B WAT 0.0 2.59E-07 2.64E-07 4.95E-B 0.0 8.47E-B 3.04E-m 1.9%-B TOTAL 9.32&B 4.19&% 4.23&% 6.73E-% 8.04E-B 2.13E-% 7.69&O6 6.89607
..............+..........+..........p .........p ............p ...........p ..........p .........p.........+
APPENDIX D Page 5
i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT .
(s/s JULY. DECEMBER 1987 i RANCHO SEC0 NUCLEAR GENERATING STATION i APPENDIX D ,
l RADIOLOGICAL IMPACT ON MAN i 1987 QUARTER 4 LIQUID EFFLUENT PATHWAY l
l 1
l t
General Pow 1ation Doses (MAV REM) l
..............e.........e.........p.........e............e...........p..........+..........+..........+
PATWAY l SKIN l BK l UVER l TOTAL. BD' l THMID l KILMY l LUG l GI-LU l
..............p.........p.........p.........p............p...........p..........p.........p .........+ l O FISH 0.0 5.QT-m 6.8T-m 3.8]E-m 0.0 2.3T-m 7.8T-04 1.24E-04 >
G IWERTEBR4TE 0.0 3.7]E-m 5.NE-% 2.8T-% 0.0 1.67E-% 5.74E-06 7.7T-06 i MItKIfC 0.0 1.75E-04 2.24E-04 1.11E-04 0.0 7.43E-05 2.57E-% 1.69E-% i Sh0RELIfE 2.6]E-05 0.0 0.0 2.23E-M 2.23E-% 0.0 0.0 0.0 l
%Itt1"G 0.0 0.0 0.0 1.31E-07 1.31E-07 0.0 0.0 0.0 l
.LCATitG 0.0 0.0 0.0 6.57E-B 6.57E-B 0.0 0.0 0.0 t VEuETATIW 0.0 2.54E-03 3.15E W 1.41E-m 0.0 1.04E-m 3.65E-04 2.1T-M l MilX 0.0 1.21-W 1.59E-m 6.2E-04 0.0 5.25E-04 1.8SE-M 2.64E-05 \
PE4T 0.0 2.*M-04 2.77E-04 1.57E-04 0.0 9.15E-05 3.14E-% 6.27E-05 l TOTAL 2.6]E-05 9.35E-W 1.22E.m 6.17E-W 2.32E-% 4.05E-W 1.4T-03 4.4T-04 i
..............+..........p .........p .........e ............e ...........e ..........p .........p .........+ ,
I l
l APPENDIX D Page 6 j
- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE-REPORT O JULY-DECEMBER 1987 RANCHO SECO NUCLEAR GENERATING STATION APPENDIX E O
O
_ 1
e UOMUD SACRAMENTO MUNIC: pal. UT1UTY DISTRICT _ A. O. Box 15830. Sacramento CA 35852 1830.1916) 45213211 AN ELECTRIC SYSTEM SE?viNG 9E *EAA7 OF CALIFORNI A R'ANCHQ SECO NUCLEAR GENER ATING,STATlON NO.1
.P R O C ED U R E I N TER I M C H A N G E f0TI C E.
PROCEDURE INTERIM C)iAM6E MO. O[
- 1. Procedure Muster A P. ?I o Rev. -3 l
titte 0.cc a ta D e s e. oJ aa lats u M ' wI (COCM)
Effective Date /A 9 87' Esoiration Date _" " '
l Change Descrictica -'
Qan eher11.4 n t ha sen t .'6en s 3.'1/anao IO n-== f 2 i. relsen we s2 l 5 2 ta s m n2 4.=t
^
.*f.% : u . 6 NA.s k ll a.1.% fa n2w ss,lf 4 an oW a' b Un e. Re. .
. L. n.eu n in: v in t e n er utn u s1 =r, e ns o w v /ss t %
l Ts4le 2 . J = l =9w o's f/s d a r - *' ,'n M u a to 's n . r_ L s . - a +m Js/n ta saan toe. -94.'s:am
- a da fa n. tu at.% a 1* .a n 2,k _s a fu >%.T
./ 4 fa , u, i a J. M Reasoa for Changa r) Te }*wwls wa set era su AlrLh.see da d.%.Yo%s Nhne'bkils enulnneed Jm.-PL- N a3 mow a> n a ~ ~ , .s ., , .. 2 vwt a. .MA u1st'.~ A/.,~. a J A9rild .t*C w .'fn t)2A/ /d # o. /, /44
.g V -
Originator
~'
Signature l.kW WA - d OL.rM /
f /L 7D Title Cate ..
- 2. REVIEhER Revissed hv $$/N 0 /3hk2 I Signature Title 'Date
- 3. FfMAL AP99CVAL (Signature, Date)
Cognirant Departsent Manager 4 proved .
i2 //
/3 7 Quality Assuruce.. Ub nsA -
RS A $ O TO ? r )bJ Y $% 8 $* $
- Y*
/ ( r !
PRC Chairsas .), MW2
[) /) O Recoseend Aaproval J Yes No Receasend RSRC Revies: J Yes [ no e 1 8 / Forward for RSRC Review; 1 fes _,
No Directer 16uclear Operations and Maintena' ace
- 4. AEVIEWED: (Signature, Dats) v I
Ranagesent Saf ety Review Coesittee bg/ Mw /4 #fdC, #f#C #d 232,b 7 /M7
/ / I '
ADM-023 REV 5
,,c..
c .
3+ LIQUID EFFLUENTS (Continued) 2.3 (Continued)
Description of Variables Subscript Description a age group Average man or population infants 0-1 year i children 1-11 years l teenager 11-17 years 1 adult 17 and older Maximum man infants newborn children 4 years teenager 14 years adult 17 years p pathway i radionuclide l j organ (total bod /, bone, liver, thyroid, kidney, lung,91-111) variaole Description Value
' equilibrium bioaccu'mulation factor, Appendix A Big ,
expressed as the ratio of the concentration in biota to the radionuclide concentration in water (note 1)
Picv.dl # Biv M
concentration facto'r for u,,,ct: Appendix A from soil by edible parts of crops Oaipj dose factor used to calculate the Appendix A radiation dose from an intake of a radionuclide, or from exposure to a given concentration of a radionuclide in sediment or water F flow rate of the total liquid input variable
- effluent leaving the site (ft 3/sec)
O Rev. 3 AP.310-17 Picy-o
() 't $?
1 34 LIQUIO EFFLUENTS (Continued) 2.3 (Continued)
Description of Variables (Continued)
Va riable Oescription value fg fraction of the year crops are 1.0 irrigated FjA stable element transfer coefficient Appendix A that relates the daily intake rate i by an animal to the concentration I in an edible portion of animal product FFEED fraction of feed or forage not Table 2.3-4 irrigated with effluent water FWATER fraction of wat'er not obtained Table 2.3-4 i from effluent water I irrigation rate for irrigated foods Table 2.3-4 Mp mixing ratio (reciprocal of the Table 2.3-2 .
dilution factor) at the point of I exposure, or at the point of
( withdrawl of drinking or irrigation water, or at the point of harvest of aquatic food P effective surface density for soil 240 Kg/m2
' Qy consumption rate of coni:aminated Tab.le 2.3-5 A
water by an animal QF consumption rate of contaminated Table 2.3-5 feed or forage by an animal Qi release quantity of nuclide 'i' input variable (C1/yr) r fraction of deposited activity 0.25 retained on crops PICM-C L g Rapj total to organ 'j' to calculated individuals-in age group *a' from all radionuclides 'i' in pathway 'p' tb time period of long term buildup for 15 years
- activity in sediment or soil O Rev. 3 AP.310-18
.. ~
. PICu.On v39d
' ' ' ' # I --
34 l.IQUIO EFFl.UENTS (Continued) 2.3 (Continued)
Description of Variables (Continued)*
Variable Description Value t3 time period that crops are exposed Table 2.3-4 to contamination during the growing
' season holdup time that represents the Table 2.3-3 th time interval between harvest and consumption tp average time t,> tween analysis of Table 2.3-3 liquid effluent in regenerate holdup tank to release of effluent offsite, and time required fer nuclides to reach the point of exposure radioactive half-life of nuclide 'i' Appendix A Tj Uap usage factor that specifies the Table 2.3-1 exposure time or consumption rate W shoreline width factor 0.2 v agricultural productivity (yteld) Table 2.3-4 Yy AiE ef f ective removal rate constant for radionuclide 'i' from crops
, ' Appendix,A AEi " \i+% 11
% 0.0021 hr-l Aj radioactive decay constant Appendix A 1100 units conversion factor l l
(01/yr)/(f t /sec) 3 to pCi/L 110,000 units conversion factor multiplied by 100 to account for the proportionality constant used in the sediment model
+
note 1 the equilibrium bicaccumulation factor PZeg. oj e for cesium in freshwater fish is sit-s;;;df k ych: ..: f..M00 (Ref:.: :: 7.1")
- e ' R,G..L.109 value 44,2000 of Rev. 3 AP.310-19
- PEcu-o s y s q. n
r' I ' "'l '
34 LIQUIO EFFLUENTS (Continued) .-
TABLE 2.3-1
/\
RANCHO SECO SITE LIQUID EFFLUENT PATHWAY Usage Parameters U ap
._ - . - Maximum Exposed Individual Pathway Units Infant Child Teenager Adult af
?ECM*OI N reshwater F Fish Kg/yr 0 21 21 %
Freshwater Invertebrate Kg/yr 0 1 1 1 Orinking Water t/yr 0 0 0 0 Shoreline Deposits hr/yr 0 14 100 1000 Swiming br/yr 0 100 100 100 Boating br/yr 0 0 0 0 Irrigated Foods Fruits, Vegetables Grain Kg/yr 0 520 630 520 Leafy Vegetables Kg/yr 0 0 0 0 Milk t/yr 0 330 400 310 Meat, Poultry Kg/yr 0 41 65 110 Average Exposed Individual General Public O Freshwater Fish Kg/yr 0 2.2 5.2 6.9 Freshwater Invertebrate Kg/yr 0 0.33 0.75 1.0 Orinking Water t/yr 0 260 260 370 Shorelir:e Deposits hr/yr 0 9.5 47 8.3 Swiming e br/yr 0 9.5 ! 47 8.3 Boating hr/yr 0 9.5 47 8.3 Irrigated Foods Fruits, Vegetables, Grain Kg/yr 0 200 240 190 Leafy Vegetables Kg/yr 0 10 20 30 Milk t/yr 0 170 200 110 )
- Meat Poultry Kg/yr 0 37 59 95 j l
I 1
O Rev. 3
. ..n AP.310-20 '
V' 3 (7 -fi PIc A> - ol
N
..l GASEOUS EFFLUENTS (Continued) .
a r
( 3* 3.2.1.5 Detennine Cg (the maximum acceptable radioactivity concentration [
l of noble gas radionuclide 'i' in the gaseous ef fluent ( uC1/cc)) l for each individual noble gas radionuclide in the gaseous ef fluent: i 3* C =
(2.12E-303 )/F 3 (3.2-5) r where F =
The maximum effluent flow rate at the point of release (cfm) l
=
57,000 cfm (auxiliary building vent) ;
=
19,500 cfm (radwaste service area unit)
=
74,000 cfm (reactor building vent) '
2.12E-3 = Unit conversion factor to convert pC1/sec/cfm to pCi/cc !
C tC A/- Ol + vea din V
3* 3.2.1.6 Determine C.R. (the calculated monitor '^""* g *^ attributed to the noble gas radionuclide (n:::)): I (acynQ 2* C.R. # = T g QEj #
.(3.2-6,
= Tn f C; where E g
75[ detectier Officiency of the ~'ritca for ^^ble
~;!! adicauclide '4' (c?=/ ;Ci /cc) 'r0=_ TS5!: {
3* . -:.
PleM.cl 4---
3+ T g
=
Fraction of the total gaseous radioactivity that may be released from the site via each release point to ensure that the permissible radiation exposure limit at the site boundary is not exceeded due to simultaneous releases from several pathways.
20 percent (Auxiliary Building Vent)
- =
80 percent (Reactor Building Vent) .
O -
Rev. 3 AP.310-52 X3C/ if Plen-on
7 , Y o . {o ,
3 i
GASEOUS EFFLUENTS (Continued)
(%
O 3* 3.2.2.1.c (Continued)
~
(cfm) must be maintained at or below this calculated f value ar,the discharge can not be made from the vent. '
I 3
7 3.2.2.2 Oeterminethemonitorhighalarmsetpointsabovebact$oundfor effluent monitor *,.
l rc A PIcap-ci 4 a. Determine C.R. (the calculated monitor =at beteabovebackgroJnd I attributed to the noble gas radionuclides (n:;:)).
Y0 1 3* C.R. =
(1.25f ! C{ )/T - -
$ (3.2-10) l
& (1.2Tf (; p-where f O The maximum acceptable gaseous discharge flowrate
=
(cfm) determined in Section 3.1.2.1 F =
The ruximum design vent flowrate at the point of l
' i b release (cfm) l
= 57,000 cfm (auxiliary building vent).
= 74.000 cfm (reactor buidir,g vent) i 1.25 $ Correction f actor to increase the monitor alacr.
setpoint to prevent sDurious alarms caused by l
deviations in the mixture of radionuclides that i af hcc monitor response (the calculated f'- --de ; i has been decreased by this 1.25 factor) i i
O 4 dev. 3 ,,
A P. 310- 66 L( i p r w'-l oSh
( 3 \ ,
l !
r
' ]
l l
l GASE0US EFFLUENTS (Continued) 3+- 3.2.2.2.a (Continued) i Cg = RAJ1oactivi'/ concentration of noble gas e i radionuclide 'i' in the gaseous effluent (uci/cc)
I fr m the analysis of the gaseous effluent to be
)
released f
y.
(
I pgg. o 4 I q - cetectie ef *icie cy er-the - ite- '- aeb!e st-3* F44444wer',4 d e ' i ' ( c p ' ;C i 'c c * = T e b ' " 3 ? -?-
( (
pch/
h b. The monitor high clarm setpoint above backgrourd (490) should be I l
set at the C.R. plus monitor background value. l l
O
/
\
/ l t i a
, 4 l
/
(
\
Rev. 3 AP.310-57 i.
X 2 4 5' T s,
,2Id.d) ~ Ol i _. _ _
1 4
t
.y/
(
GASEOUS EFFLUENTS (Continued) ,
I C A/- O I ----> 1 79 unwrTno nrTrerno rrrrcerwetEs(a) 3*
I *I
~
I Muciide -
FFFiciancy (E')(c?">' UCi'cci(b) -
r a,- _. . n OE0 , ,
rr acm 1 !5ES- ',
7 r oc - 1.00E8
< -?? :.15CO -
/ \ rr mn -. 1.0lCO
' rr no 2.20C0 rr on i ??Es -
y=_1,1- 4.;4t?
_ r. 144m ,
g.A7E?
- v. ., _ i, s, ,, , o,ne,
- r=-135- -
3.!SE7 ,
r inc - ' ' . 2 5 E S =. -
-Xe-137 2.20C0 v3_33g i enra ,
', < nea, __
~
, ASEe '
i e
\ n .
0 t
p $ f f w a 1
'!(f n
., . s gvf
...,.x__
vu ww v.- n-m,u a r>n m a t w tu,scea v - - - - --
cma- r m uent sa mpier, l
u c e ! o ' ' - 2 . -u4-t B :: Mtt'!'ti0n t:t:0!Of O4+ W 3 203) e g f
\ m v
\'
t >J.
,' k, (b) A p p l i c a ble-te 44J X 44.j a ry -bu44 d ingm ent NJ fM40W44f r-444C t o r ;
V 1
'.' -eu!1 din 0 at m spher._ u 4 m .-ca e m - w at A t
\
r_- u q t8e a ma n a-EeI".C'bda*M M $ TI IOI. f ,* \ >
) >
\
?.LG M-O I x ,
i 1
1
- - /
5 ,
i r
,f S ,
/
v Rev. 3
( AP.310-59 i f *)
Pku -ot, O
.l e.
I 1
4
- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT -
'-' -)
.4- JULY-DECEMBER 1987
-W-
- RANCH 0 SECO NUCLEAR GENERATING STATION APPENDIX F-. ,
i h
l T
i i
t e l
i 4
4 l
J
! I I
i i
e t
4
'i o2 i
(
1'
n 7 RADRASTE CONTROL MANUAL NUMBER: RP.309.II.4
()
ts ,-
SOLIDIFICATION OF NATER OR SECONDARY RESIN USING CEMENT WITH FNSI RADHASTE SOLIDIFICATION SYSTEM REVISION: 0 PAGE 1 0F 16 LEAD DEPARTHENT: r EFFECTIVE DATE RADIATION PROTECTION f\ . 12-21-87
' 1 t \
f' y KH .
- L S h $. -- ----- ] - --------
C PWR PROD /DATE HGR. RAD PROT /DATE RA PROT SUPR/DATE QUALITY REVIEW REQUIRED X YES NO PRC REVIEH REQUIRED X YES NO V [ lDl-F7 PRC CHAIRPERSON /DATE REVISION
SUMMARY
- New Procedure.
- 1) Supercedes AP.309.II-4,
- 2) Formatted in accordance with RSAP-0502, RPAP-1002, 1003. -
- 3) Prevents solidification of resin from Spent Resin Tank on the Solidification Pad until enclosure of the present solidification pad is completed O (RSL 006, ID Number 3389).
l l
HP3749P D-0540P O 9
, . . . - , . - . - - - - - - - - - - ---r - -
,O 3- i
..) . .
O RADHASTE CONTROL MANUAL SOLIDIFICATION OF HATER OR SECONDARY RESIN USING CEMENT WITH PNSI RADNASTE SOLIDIFICATION SYSTEM NUMBER: RP.309.II.4 REVISION: O PAGE 2 0F 16 1.0 PURPOSE The purpose of this procedure is to'be the Process Control Program Manual as de.'ined in TS 6.15, providing a description of the appropriate methods and precautions for solidification of resins or liquid using cement with the (PNSI) Radwaste Solidification System, and the calculations necessary to determine activity of the final waste product. Calculations are normally performed by an RP Technician and reviewed by Radwaste Supervision. Solidification of resin from the Spent Resin Tank-is not allowed until the need to provide an enclosed area at the Solidification Pad is evaluated (RSL 006, ID Number 3389).
2.0 REFERENCES
2.1 US Ecology NRC License "Byproduct, Source, and Special Nuclear l Material" and NRC License (Hanford Site) 2.2 10 CFR 20.311, "Transfer for Disposal and Manifests" l 2.3 10 CFR 61, Licensing Requirements for Land Disposal of !
O Radioactive Maste-2.4 49 CFR 170-179, Department of Transportation Regulations 2.5 Technical Specifications, Appendix A. Sections 3.21, 4.25, 6.15, 6.17 2.6 Pacific Nuclear Systems, :nc. Solidification Procedures-Operation and Maintenance Manual, Radwaste Solidification System, OH-44 2.7 A.17, Miscellaneous Liquid Radwaste System 2.8 A.22, New and Spent Resin System 2.9 AP.306 III-F3, Chemistry Manual, Sampling and Analysis l Requirements (to be reissued as CHM-1350) 2.10 RP.309.I.8, Shipments of Radioactive Haste for Disposal at the Richland, Hashington Low Level Haste Disposal Facility.
. 2.11 RP.309.I.2, Determination of DOT Subtype and Packaging Requirements for Radioactive Materials O
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NUMBER: RP.309 II.4 O RADHASTE CONTROL MANUAL -
SOLIDIFICATION OF NATER OR SECONDARY RESIN USING REVISION: O CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 3 0F 16 2.12 RP.309.I.3, Classification of Radioactive Haste 2.13 RP.309.I.7, Haste Steam Identification and Sampling 2,14 RP.309.II.1, Resin Dewatering ;
2.13 TP-05, Rev. O, Operation Procedure for the Radwaste Solidification System.
2.16 TP-06, Rev. O, Envirostone Cement Encapsulation of Solid
, Radioactive Haterial.
2.17 RP.305, Radiation Control Manual 3.0 DEFINITIONS 3.1 MIQi - A tank of waste where the chemistry and radiochemistry will remain constant (ie. no additions are made to the tank).
3.2 SOLIDIFICATION - The process by which loose waste (i.e., water or resin) made into a solid mass to meet transportation and disposal requirements.
3.3 PCP TEST - A chemical analysis in accordance with the Process Control Program procedure (PCP) to ensure the chemical process of solidification is complete so the waste will meet all regulatory requirements.
1 3.4' ECE - Process Control Program for solidification of Resin or '
Hater as defined by TS 6.15 using cement with PNSI Radwaste Solidification System. The PCP procedure consists of:
RP.309.II.4, Sections 1-7; and Enclosure 8.2, Sections 1-3 ;
and 6-14. ,
4.0 PREREQUISITES 4.1 A Radiation Work Permit is required for solidification and all associated work, including set up of equipment.
4.2 A portable eye wash station is to be set up at the solidification -
area.
4.3 A job planning meeting, if necessary, must be held prior to solidification or transfer of waste to the liner.
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, - - , . , - , . - _ - - . - - - , ~ , - - , - . - - - . - .
-O RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 O SOLIDIFICATION OF MATER OR SECONDARY RESIN USING CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM REVISION: 0-PAGE 4 0F 16 4.4 Changes to the PCP procedure (as defined above) must meet the specific requirements of TS 3.21, 4.25, 6.15, and 6.17. Document.
the completion of these requirements using Enclosure 8.1.
4.5 The Radwaste Solidification System is to be installwd and set up in accordance with Enclosure 8.2.
5.0 PRECAUTIONS 5.1 A new PCP test must be performed for every ten (10) liners of waste solidified from a batch, every seven (7) days of waste processing from the same batch (whichever is least), or when chemistry is outside the parameters of prior PCP tests.
5.1.1 If any test specimen fails to verify solidification; suspend the solidification of the batch under test until such time as additional test specimens can be obtained, alternative ,
solidification parameters can be determined in accordance with the PCP, and a subsequent test verifies solidification. Solidi fication of the batch may then be resumed using the alternative solidification parameters determined by the PCP.
O 5.1.2 If the initial test specimen from a batch of waste fails to verify solidification, collect and test representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate solidification.
The PCP shall be modified as required, as provided in Specification 6.15, to assure solidification of subsequent batches of waste.
5.1.3 To ensure these requirements are met, a date and numbering system in conjunction with the Liner Index Log shall be~used.
5.1.4 This system will consist of the date of the latest PCP test and the number of liners solidified under the most current PCP test adjacent to the liner's container ID number.
5.2 Protective coverings will be placed over nearby manways and storm drains to prevent contamination in case of an accidental spill during the solidification or waste transfer process.
i
, 5.3 Ensure adequate and appropriate protective clothing and safety '
equipment is available at the solidification area. Familiarize yourself with the location of the nearest eye wash and safety shower, and how to use them.
i 5.4 Do not preload chemicals into the liners except within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> befor's solidification.
O O RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 V SOLIDIFICATION OF NATER OR SECONDARY RESIN USING REVISION: 0 CEMENT HITH PNSI RADNASTE SOLIDIFICATION SYSTEM PAGE 5 0F 16 5.5 Liners must be vented within the last 10 days prior to shipment.
5.6 A file shall be maintained containing copies of the information sheets, radiation surveys, enclosures, records, and forms prepared for each radioactive waste liner.
5.7 For Haste containers that have the potential to radiolytically generate combustible gases (contains water and/or organic materials), a determination must be made which addresses the factors affecting gas generation, as to whether the criteria stated below are met.
5.7.1 Over a period of twice the expected shipment time:
5.7,1.1 No more than 57. by volume of hydrogen gas is generated, OE 5.7.1.2 Inert to ensure oxygen limited to 57. by volume.
5.7.2 The above is not required if the waste is low specific activity (LSA) material MQ shipped within 10 days of preparation (sealing)
O or venting. .
6.0 PROCEDURE 6.1 Obtain a representative sample of the waste. Ensure that the waste I was recirculated (liquid) for at least four (4) hours prior to I sampling (Ref 2.9). I 6.2 Determine an acceptable solidification process in accordance with Enclosure 8.2.
6.2.1 Tritium, gross beta, gamma emitters, boron concentration, and pH must be quantified before liquid solidification.
6.2.2 The sum of the individual gamma emitters compared to the gross beta ;
should be within a factor of five or the tank shall be resampled.
6.2.3 If upon resample, the comparison still exceeds a factor of five, an I investigation of the source and composition of beta emitters is l necessary.
6.2.4 Gamma emitters must be determined before resin solidification.
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RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 SOLIDIFICATION OF HATER OR SECONDARY RESIN USING REVISION: 0 O- CEMENT N'TH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 6 0F 16 HQIE: Experience has shown for liquids with a gamma activity sum greater than 0.2 pCi/mi could yield dose rates greater than 10 mrem /hr at 2 meters from the vehicle.
6.3 Perform a leak test on the waste transfer line from RHS-204 for j concentrates to the solidift::ation unit fill head. l 6.3.1 Close or verify closed valves NS-1, HS-2, HS-3, HS-4, DH-1, DH-2, l D4 3, 04 4, SW1 and SH-2. l 1
6.3.2 Open HS-4, HS-2, HS-1, DH-2, 04 3, DH-4 and SH-1.
6.3.3 Open DMH-053 to supply tritiated DI water to the solidification system.
3 6.3.4 Hhen piping is full as evidenced by water flow into the liner, close HS-4. Open and close HS-4 as necessary to vent any air in the piping. '
6.3.5 Check all fittings, connections and valves for signs of leakage.
If any leakage is observed, close DHH-053 and open HS-4. Repair leak (s) and repeat leak test starting.with Section 6.3.2.
6.3.6 If no leakage is observed after ten minutes, close SH-1 and open HS-4 to depressurize the lines.
6.3.7 Close HS-1, HS-2, DW1 DH-2, 04 3 and DH-4.
6.4 Coordinate with Operations personnel and transfer waste into a solidification liner in accordance with Enclosure 8.2 and one of the following procedures:
6.4.1 Liquid waste is transferred to the solidification unit in accordance with A.17 Miscellaneous Liquid Radwaste System.
6.4.2 Spent secondary system resin has been loaded into a solidification liner in accordance with Reference 2.14.
6.5 The volume of waste being solidified in each liner must be determined by use of a CCTV monitor and/or a waste level indicator.
6.6 The number of gallons and activity of flush waste used in the waste must be determined. The volume of flush water is to be minimized.
6.7 Solidify the waste in accordance with Enclosure 8.2.
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RADHASTE CONTROL MANUAL SOLIDIFICATION OF NATER OR SECONDARY RESIN USING NUMBER: RP.309.II.4 REVISION: O CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM 'P\GE 7 0F 16 6.8 Determine the concentration of the waste to be shipped in each liner using Record 7.1. Add the activities of the individual gamma emitters and tritium for both the waste and flush water (if contaminated) to achieve the total activity. Aversge this activity over the volume of the final waste product..
6.9 Verify the waste has solidified properly. Wait at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after mixing the cement and waste, to inspect the waste. A visual inspection must show no free standing water and a uniform product.
The waste must also resist penetration with a dowel or other hard ob;tect. Enter results on Record 7.2 6.10 Store Records in the Radiation Protection Office or the Rancho Seco Records Management System.
7.0 RECORDS j The following individual / packaged documents and related correspondence completed as a result of this procedure are records. They shall be transmitted to Records Management in accordance with RSAP-0601.
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- Haste Solidification Norksheet
- Sample / Haste Solidification Verification
- Tech Spec 6.15 & 6.17 Requirement Checklist 7.1 Waste Solidification Worksheet 7.2 Sample / Haste Solidification Verification 8.0 ENCLOSNRES 8.1 Tech Spec 6.15 & 6.17 Requirement Checklist (RAD-047).
EQII: 8.2 is considered proprietary by Pacific Nuclear Systems and is not being distributed, except to the Radwaste Supervisor.
8.2 OH-44, Rev. O, "Operation and Maintenance Manual,' Radwaste Solidification System," Nuclear Packaging, Inc.
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V RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 SOLIDIFICATION OF MATER OR SECONDARY RESIN USING REVISION: O CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEN PAGE 8 0F 16 IC HASTE SOLIDIFICATION HORKSHEET A.502 j ace 1 of 7 Liner No
- of liners since Type of waste last PCP test Concentration of Haste X Volume of Haste - Activity of Haste Nuclide pC1/cc X cc's - pCi
- 1. X -
- 2. X -
! 3. X -
- 4. x -
Concentratiorr of Flush Hater X Volume of Flush Hater - Activity of Flush Water Nuclide pC1/cc X cc's - pCi N 1. X -
- 2. X -
- 3. X -
- 4. _
X -
Activity of Haste + Activity of Flush Water - Total Activity Nuclide pCi + pCl - pCi
- 1. + -
- 2. -
+ -
- 3. + -
- 4. + -
Volume of Final Haste Product (Waste & Flush Hater & Cement) = cc's Volume of Total Activity per Nuclide + Final Haste Product -
Final Concentration Nuclide pCi + cc's - pC1/cc
- 1. + .
- 2. + -
- 3. + -
- 4. + - '
Prepared By RP Tech Date Reviewed By Date (Sup RP Tech-Radwaste; Sup RP Tech-Decon; Radwaste Sup)
RECORD 7.1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ mm n m a
(3
(] RADHASTE CONTROL MANUAL NUMBER: M 309.II.4 V REVISION: O SOLIDIFICATION OF HATER OR SECONDARY RESIN USING CEMENT HITH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 9 0F 16 RIC SAMPLE / HASTE SOLIDIFICATION VERIFICATION 2A.502 Pace 2 of 7 OH-44, Rev. O Dated October 9, 1985 SAMPLE VERIFICATION HORKSHEET Operator: Date: No.
Utility /
Location:
Haste Type:
Haste Sample From/By:
Haste Temperature: F Haste pH: Sample Rad Level mr/hr (Gj Physical Characteristics (Viscosity, color, sedimentation, clarity, etc.)
Sample Proportions:
Haste Sample ml Environstone/ Cement gr.
pH Adjustment (and what, if any) ml Retarder (If any) gm Accelerator (If any) gm Blend the waste thoroughly (with pH adjustment additives, retarder, or conditioners, if required) and record the time when finished:
Blend the required volume of Environstone into the waste and record the time when finished: .
Record the time when the mixture viscosity increase to the point where the mixer is secured: (1).
Record the time when the mixture is firm to the touch: (2).
l RECORD 7.2 l PAGE 2 0F 7
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1 RADHASTE CONTROL MANUAL RP 309.II.4 SOLIDIFICATION OF HATER OR SEODNDARY RESIN USING CEMENT HITH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 10 0F 16 RIC 2A.502 Paae 3 of 7 OH-44, Rev. O Dated October 9, 1985 Solidific: tion Horksheet HEIGHT OF RETARDER to be added to the Liner: (Add only when needed to extend the waste set up time, as necessary to ensure that all of the Envirostone can be safely added to the liner prior to the set up time.
gms of Retarder / gms of Envirostone in Sample x lbs of Envirostone to be Added to the Liner lbs of RETARDER to be Added to the Liner pH ADJUSTHENT: The pH of the waste solution may be adjusted by adding NaOH O to increase the pH to between-3.0 and 6.0 for waste streams with a pH below 3.0 or by adding Sulfuric or Boric Acid to lower the pH to 5.0 to 7.0 for i
waste streams with a pH above 9.0. Haste streams with a pH between 3.0 and 9.0 normally require no adjustment.
gms of Accelerator / Conditioner in the Sample / gms of Envirostone in the Sample.
x lbs of Envirostone to be Added to the Liner :
lbs of ACCELERATOR / CONDITIONERS Added to the Liner i
Verified by i PNSI Operator Date RP Tech-Radwaste Date l
l O l RECORD 7.2 PAGE 3 0F 7
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t RADNASTE CONTROL MANUAL NUMBER: RP.309.II.4
\ REVISION: O SOLIDIFICATION OF HATER OR SECONDARY RESIN USING CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEN PAGE 11 0F 16 IC A.502 aae 4 of 7 OH-44, Rev. O Dated October 9, 1985 ,
SOLIDIFICATION HORKSHEET Operator: Date: No.
Utility / Location:
Haste Type:
Satisfactory Sample Verification No: Date:
Haste Solidification Efficiency: % (a)
() Liner Size: ' Inches High x Inches Diameter Liner Usable Haste Volume (with 2" sa'ety margin): CF (b)
Liner Volume Per Inch of Height: CF/ Inch (c)
HASTE VOLUME to be Added to liner: CF (a x b)
HEIGHT OF HASTE In Liner: In (a'x b/c) 1 (Haste Full / Level Bubble Tube to be Set at this Height)
HEIGHT OF ENVIROSTONE to be added to the Liner: (Use the Values Determined from the Sample Verification Worksheet.)
gms of Envirostone in Sample / ml of Haste in Sample x 62.38 - lbs of Envirostone/CF of Haste x CF of Haste to be Added to the Liner lbs of ENVIROSTONE to be Added to the Liner
( !
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RECORD 7.2 l PAGE 4 0F 7
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RADHASTE CONTROL MANUAL NUMBER:
REVISION:
RP.309.II.4 0
SOLIDIFICATION OF WATER OR SECONDARY RESIN USING CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM - PAGE 12 0F 16 RIC 2A.502 Pace 5 of 7 OH-44, Rev. O Dated October 9, 1985 Sample Verification Worksheet Sample Results:
Mix time (1): minutes Setup time (2): minutes Final Solidified Volume: minutes Solidification EFF: % (Haste Vol/ Solidified Vol x 100%)
( Free Hater, If any: -
Relative set (soft, firm, very hard):
Sample proportions and solidification results acceptable for calculation of large scale solidification ratios: yes no.
Verified By PNSI Operator Date RP Tech-Radwaste Date l
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RECORD 7.2 PAGE 5 0F 7 j
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p RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 V REVISION: O SOLIDIFICATION OF NATER OR M CONDARY RESIN USING CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 13 0F 16 IC
! PNSI Solidification Operations Log Sheet A.502 ace 6 of 7 OH 44, Rev. O Dated October 9,198S Operator: Date: No.
Utility / Location:
Haste Type:
Haste From:
Solidification Worksheet No:
Haste Volume Added: DF: Time Completed:
Time Hixer Started: Hydraulic press:
Retarder Added: - lbs. Time Added:
Haste Conottioner Added: Type: lbs: Time:
Haste Conditioner Added: Type: Its: Time:
pH ADJUSTHENT Added: lbs. Time Started: Complete:
Envirostone Added: lbs: Time Started: Complete:
Hixer Hydraulic pressure PSI Time Time Hixer R cured:
Haste Set up Time:
Time Fillhead Removed: Time Liner Capped:
p)
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Comments and Observations:
1 PNSI Operator Date RECORD 7.2
- PAGE 6 0F 7
(~' RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 ,
\ REVISION: O SOLIDIFICATION OF HATER OR SECONDARY RESIN USING CEMENT WITH PNSI RADHASTE SOLIDIFICATION SYSTEM PAGE 14 0F 16 RIC 2A.502 Paae 7 of 7 OH-44, Rev. O Dated October 9, 1985 Liner No.
(Circle One)
No free standing water YES/NO Haste shows uniform product YES/NO Haste resists penetration YES/NO '
Solidification Media is acceptable YES/NO
'g If any answer is NO, do not ship the liner. Notify the Radwaste Supervisor who will initiate corrective action.
i l
l Comments Verification Performed by Date PNSI Operator l
Date i RP Tech-Radwaste Hasta liner meets requirements for structural stability: YES / NO O Supv. RP Tech-Radwaste. Supv. RP-Tech-Decon, Date l
Radwaste Supervisor i RECORD 7.2 m s,
' O 9J RADNASTE CONTROL MANUAL NUMBER: RP.309.II.4 O'. SOLIDIFICATION OF NATER OR SECONDARY RESIN USING CEMENT HITH PNSI RADNASTE SOLIDIFICATION SYSTEN REVISION: 0 PAGE 15 De 16
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IC Tech Spec 6.15 AND 6.17 REQUIREMENT CHECKLIST .502 ama 1 of I Revtsion This change to the Process Control Progran procedure becomes effective upon approval by the Plant Review Comunittee, unless otherwise acted upon by the Nuclear Regulatory Coeunittee through written notification.
Items 1, 2, and 3 are the only signatures on this checklist required when subaltting this change to the PRC. After completing an itse, forward to the person perfonsing the next required signature.
- 1. This change is sufficiently detailed in information to totally support !
the rationale for the change without additional information being required.
Radweste Supenisor Date
- 2. I have determined that this ch'.nge s not reduce the overall conformance of the solidificat pr> duct to the existing criteria for Solid Maste. ,
A Radwaste Supervisor Date O 3. If the change cosolete the r System, per TS 6 hange to the Radwaste Treatment Systes, nts of TS 6.17, Major change to the Radvaste
.3: Yes/No. If Yes: TS 6.17 Requirements Coscleted by:
s l
R40 waste Supervisor Date
- 4. Docusentation is cosolete showing the review and acceptance of the change by the Plant Review Cosaittee. 1 PRC Chairperson Date
- 5. A copy of this change is prepared for submittal to the Nuclear Regulatory Cosnission by inclusion in the Seel-Annual Radioactive Effluent Release Report for the period this change is made.
i HP Services & Environmental Programs Sust. Cate Return to the Radwaste Supervisor M.S. - 244 RAD-047 Rev. O PAGE 1 OF 1 ENO O
ENCLOSURE 8.1 PAGE 1 0F 1
n RADHASTE CONTROL MANUAL NUMBER: RP.309.II.4 SOLIDIFICATION OF HATER OR SECONDARY RESIN USING REVISION: 0 Gi CEMENT WITH PNSI RADNASTE SOLIDIFICATION SYSTEM PAGE 16 0F 16 OH-44 REV. 0 OPERATION AND MAINTENANCE MANUAL RADWASTE SOLIDIFICATION SYSTEM NUCLEAR PACKAGING, INC.
OH-44 is considered proprietary by Pacific Nuclear Systems and is not being distributed, except to the Radwaste Supervisor.
O -
. O ENCLOSURE 8.2 PAGE 1 0F 1
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i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1987 O RANCHO SEC0 NUCLEAR GENERATING STATION l
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l APPENDIX G l l
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^ l SACRAMENTO MUNICIPAL UTILITY 't kPO 15 sacram nto CA 958521830.1916) 452 321 t -
(% RANCHO I SECO NUCLEAR GENERATING STATION Ng.1 C PROCEDURE CHANGE APPROVAL FORM '
Procedure Number AP.309 II-4 ggy 0 SOLIDIFICATION OF RESIN OR WATER USING CEMENT Willi Title PNSI RADWASTE SOLIDIFICATION SYSTEN Originator D. Gardiner/R. Bowser/A. Wolter Date 11-2-87 Approved s
bi/v a.: i uom.=
Date f Review by the Plant Review Committee Required: Yes C No %
Requested Change Delete entire procedure with the issue of RP.309.II.4
\
v Reason for Change uPerseded h U.M.H.4 Reviewed O
- w. a e, en :.- ee : e-e- Date l)' ! ~ h7 Recommend Review By Recommend Aporoval Management Safety Review Committee Yes I No C
- Yes C No 2 N - -
Date i2[z[g/
DIRECTOR RUCLEAR OF0i4TITSTulhTEun:E Forward to Management Safety Review Committee: Yes C NoZ _
Reviewed Date
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ADM-0006 REV O O _ _ _ _ _ _ _ _ _
EFFECTIVE DATE 06-03-87 ..
Original WP3749P 0-0218P AP.309 11-4 SOLIDIFICATION OF RESIN OR WATER USING CEMENT WITH PNSI RA0 WASTE SOLIDIFICATION SYSTEM 1.0 PURPOSE The purpose of this procedure is to be the Process Control Program Manual as defined in TS 6.15, providing a description of the appropriate methods and precautions for solidification of rc: ins or liquid using cement with the (PNSI) Radwaste Solidification System, and the calculations necessary to determine activity of the final waste product. Calculations are normally performed by an RP Technician and reviewed by Radwaste Supervision.
2.0 REFERENCES
2.1 US Ecology NRC License "Byproduct, Source, and Special Nuclear Material" and NRC License (Hanford Site) 2.2 10 CFR 20.311. "Transfer for disposal and manifests" 2.3 10 CFR 61, Licensing Reouirements for Land Disposal of Radioactive Waste 2.4 49 CFR 170-179 Department of Transportation Regulations 2.5 Technical Specifications, Appendix A, Sections 3.21, 4.25, 6.15, 6.17 2.6 Pacific Nuclear Systems, Inc. Solidification Procedures-Operation and Maintenance Manual, Radwaste Solidification System, OM-44 2.7 A.17, Miscellaneous Liquid Radwaste System
, 2.8 A.22,.New and Spent Resin System 2.9 AP.306 III-F3, Chemistry Manual, Sampling and Analysis Requirements 2.10 AP.309 I-1, Determination of the Requirements for a Shipment of
< Radioactive Material Offsite 2.11 AP.309 I-2, Determination of 00T Subtype and Packaging Requirements for Radioactive Materials .
O AP. 309 11-4-1
REFERENCES (Continued)
() 2.12 AP.309 I-3, Classification of Radioactive Waste 2.13 AP.309 I-7, Waste Steam Identification and Sampling 2.14 AP.309 11-1, Resin Dewatering 2.15 TP-05, Rev. O, Operation Procedure for the Radwaste Solidification System.
2.16 TP-06, Rev. O Envirostone Cement Encapsulation of Solid Radioactive Material.
2.17 AP.305, Radiation Control Manual 3.0 DEFINITIONS
3.1 BATCH
A tank of waste where the chemistry and radiochemistry will remain constant (ie. no additions are made to the tank).
3.2 SOLIDIFICATION
The process by which loose waste (i.e., water or resin) is made into a solid mass to meet transportation and disposal requirements.
3.3 PCP TEST: A chemical analysis in accordance with the Process Control
( Program procedure (PCP) to ensure the chemical process of
( solidification is complete so the waste will meet all regulatory requirements.
3.4 PCP: Process Control Program for solidification of Resin or Water as defined by TS 6.15 using cement with PNSI Radwaste Solidification System. The PCP procedure consists of:
AP.309 11-4, Sections 1-7, and Enclosure 8.1, Sections 1-3 and 6-14. .
l 4.0 PREREQUISITES 4.1 A Radiation Work Permit is required for solidification and all associated work, including set up of equipment. l 4.2 A portable eye wash station is to be set up at the solidification area.
4.3 A job planning meeting, if necessary, must be held prior to solidification or transfer of waste to the liner.
4.4 Changes to the PCP procedure (as defined above) must meet the specific l requirements of TS 3.21, 4.25, 6.15, and 6.17. Document the completion !
of these requirements using Record 7.3. 1 4.5 The Radwaste Solidification System is to be installed and set up in I
( accordance with Enclosure 8.1.
AP.309 II-4-2 i
--_..s
5.0 PRECA, , ,tr)
O 5.1 A new . m 9rformed for every ten (10) liners of waste V solidi- cm s u n, every seven (7) days of waste processing from the sa e ,
.nhichever is least), or when chemistry is outside the paramet m u prior PCP tests.
5.1 .1 If any test specimen fails to verify solidification; suspend the j solidification of the batch under test until such time as !
additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the !
PCP, and a subsequent test verifies solidification. Solidification )
of the batch may then be resumed using the alternative i solidification parameters determined by the PCP.
5.1 .2 If the initial test specimen from a batch of waste fails to verify solidification, collect and test representative test specimens from :
each consecutive batch of the same type of wet waste until at least l 3 consecutive initial test specimens demonstrate solidification. l The PCP shall be modified as required, as provided in Specification 1 6.15, to assure solidification of subsequent batches of waste. l 5.1 .3 To ensure these requirements are met,'a date and numbering system l in conjunction with the Liner Index Log shall be used. l l
5.1 .4 This system will consist of the date of the latest PCP test and the !
number of liners solidified under the most current PCP test J adjacent to the liner's container ID number. l 5.2 Protective coverings will be placed over nearby manways and storm drains to prevent contamination in case of an accidental spill during the solidification or waste transfer process.
5.3 Ensure adequate and appropriate protective clothing and safety equipment is available at the solidification area. Know the location of the nearest eye wash and safety shower, and how to use them.
5.4 Do not preload chemicals into the liners except within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> before solidification.
5.5 Liners must be vented within the last 10 days prior to shipment.
5.6 A file shall be maintained containing copies of the information sheets, radiation surveys, enclosures, records, and forms prepared for each radioactive waste liner.
5.7 For Waste containers that have the potential to radiolytically generate combustible gases (contains water and/or organic materials), a determination must be made which addresses the factors affecting gas generation, as to whether the criteria stated below ars met.
5.7 .1 Over a period of twice the expected shipment time:
C AP.309 11-4-3 i
n
l PRECAUTIONS (Continued) 5.7 .l.1 No more than 5% by volume of hydrogen gas is generated, a ,
5.7 .l.2 Inert to ensure oxygen limited to 5% by volume.
5.7 .2 The above is not required if the waste is low specific activity (LSA) material A,jl0 shipped within 10 days of preparation (sealing) l or venting.
6.0 PROCEDURE 6.1 Obtain a representative sample of the waste. Ensure that the waste was recircu'.ated (liquid) or mixed (resin) for at least four (4) hours prior to sampling. Refer to A.22, New and Spent Resin System, Section 5.31 for sampling the spent Resin Tank. .
6.2 Determine an acceptable solidification process in accordance with I Enclosure 8.1.
1 6.2 .1 Tritium, gross beta, gama emitters, boron concentration, and pH j must be quantified before liquid solidification.
6.2 .2 The sum of the individual gama emitters compared to the gross beta should be within a factor of five or the tank shall be resampled.
6.2 .3 If upon resample, the comparison still exceeds a factor of five, an investigation of the source and composition of beta emitters is necessary.
6.2 .4 Gama emitters must be determined before resin solidification.
NOTE: Experience has shown for liquids with a gama activity sum greater than 0.2 pCi/mi could yield dose rates greater than 10 mrem /hr at 2 meters f rom vehicle. l l
j 6.3 Perform a leak test on the waste transfer line from RWS-204 for l concentrates or from RWS-271 for resin, to the solidification unit fill head.
6.3 .1 Close or verify closed valves WS-1, WS-2, WS-3, WS-4, OW-1, DW-2, DW-3, DW-4, SW-1 and SW-2.
6.3 .2 Open WS-4, WS-2, WS-1, DW-2, DW-3, DW-4 and SW-1.
6.3 .3 Open DMW-053 to supply tritiated DI water to the solidification system.
- AP.309 11-4-4
PROCEDURE (Continued)
O V
6.3 .4 When piping is full as evidenced by water flow into the liner, close WS-4. Open and close WS-4 as necessary to vent any air in j
the piping.
6.3 .5 Check all fittings, connections and valves for signs of leakage, i If any leakage is observed, close OMW-053 and open WS-4. Repair l leak (s) and repeat leak test starting with Section 6.3.2.
6.3 .6 If no leakage is observed af ter ten minutes, close SW-1 and open WS-4 to depressurize the lines.
l 6.3 .7 Close WS-1, WS-2, OW-1, DW-2, DW-3 and OW-4. l l
6.4 Coordinate with operations personnel and transfer waste into a '
solidification liner in accordance with Enclosure 8.1 and one of the following procedures: I 6.4 .1 Liquid waste is transfered to the solidification unit in accordance with A.17, Miscellaneous Liquid Radwaste System.
6.4 .2 Spent primary resin is transfered to the solidification unit in accordance with A.22, New and Spent Resin System.
6.4 .3 Spent secondary system resin has been loaded into a solidification ,
liner in accordance with Reference 2.14. 1 l 6.5 The volume of waste being solidified in each liner must be determined by use of a CCTV monitor and/or a waste level indicator.
6.6 The number of gallons and activity of flush waste used in the waste !
must be determined. The volume of flush water is to be minimized.
6.7 Solidify the waste in accordance with Enclosure 8.1.
6.8 Determine the concentration of the waste to be shipped in each liner using Record 7.1. Add the activities of the individual gamma emitters and tritium for both the waste and flush water (if contaminated) to !
achieve the total activity. Average this activity over the volume of I the f.inal waste product.
6.9 Verify the waste has solidified properly. Wait at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after l mixing the cement and waste, to inspect the waste. A visual inspection 1 must show no f ree standing water and a uniform product. The waste must l also resist penetration with a dowel or other hard object. Enter results on Record 7.2 !
6.10 Store Records in the Radiation Protection Of fice or the Rancho Seco Records Management System.
i AP.309 11-4-5 l l
l
7.0 RECORDS 7.1 Waste Solidification Worksheet 7.2 Sample / Waste Solidification Verification 7.3 TS 6.15 & 6.17 Requirement checklist.
8.0 ENCLOSURES NOTE: 8.1 is considered proprietary by Pacific Nuclear Systems and is not being distributed, except to the Radwaste Supervisor, 8.1 CM-44, Rev. 0, "Operation and Maintenance Manual, Radwaste !
Solidification System," Nuclear Packaging, Inc.
h O
O AP.309 II-4-6 i
l l
- i
, 'i RECORD 7.1 ,
WASTE SOLIDIFICATION WORKSHEET ;
I ;
i # oi liners since Liner No Type of waste ,_ last 8CP tett ____ _
.)
Concentration of Waste X Volume of Wasto = . Activity of Waste ;
Nuclide uCi/cc X cc's = 'uti l
- 1. X =
- 2. X =
- 3. X = !
- 4. X =
i Coreentration of Flush Water X Volume of Flush Water = Activity of Flush Water Nuclide pCi/cc '
X cc's = --
uCi L. ,
3.
I X
=
- 4. X
'='
. , i l
Activity of Waste + Activity of Flush Water =
O Nuclide uCi + 901 =
Total Activity uCi
- 1. .
c=
- 2. '
e =
- 3. + = -
- 4. + = 4 .
Volume of Final Waste Product (Waste & Flush Water & Cement) = cc's Volume of Total Acti.vity per Nuclide + Final Waste Product = Final Concentration Nuclide uCi + cc's = uCi/cc 1 = '
.. +
- 2. . + =
- 3. + =
- 4. + =
Prepared By _. _, RP Tech Date Reviewed By _
Date .
Supv. RP Trtch-Radwaste,\.iupv. RP Tech Oecon, Rad-Waste Supervisor O AP.309 11-4 1
- L
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W-\$
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ti RECORD L2
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1 l V d i OM-4A, Rev. 0 SAMPLE / WASTE SOL 101FICAT10N VERIFICATION Octob d 'v, 1985 1
l SAMPLE VERIFICATION WORKSHEET
.perator: Date: No. '
Utility / >
Location: -
Waste Type: _
Waste Sample From/By:
Waste Temperature: F Waste PH: Sample Rad Level _Mr/hr l Physical Characteristics (Viscosity, color, sedimer, cation; clarity, eti.) ,_
l
' fs l b
Sample Proportions: ,
, \
l Waste Sample
' ml 10 Environstone/ Cement
/ gm pH Adjustment (and what, if any)' _,_ . _ ,,, ml' !
Retarder (It any) gm Accelerator (If any) < '
__ 9m Blend the waste thoroughly (with pH adjustment additives, retarder, of <
conditioners, if required) and record the time when finished: 1 Blend the required volune of Environstone into the waste and record the time when finished: .
Record the time when the mixture viscosity increase to the point where the mixer is secured: , (1).
Record the time when the mixture is firm to the touch: ,
, (2).
AP.309 !!-4-8 e
4
, 8 9 _.
. + \
r l OH-44, Rev. 0 October 9, 1985 l
, c J
. Solidification Worksheet I ' '
s
- - i WEIGHT OF RETAR0ES tnfbe added to the Liner: (Add only when needed to extend'
'/ - - the waste set up timi as necessary to ensure that all of the Envirostone can I
\ ,e, ,
(besafelyadded,t'pt'he-line/priortothesetuptime.
,,5t ] i
,q
/ gms of Retarder / gms off Envirostone in Sample o .
x lbs of Envirostone to be Added to the Liner i = lbs of RETARDER to be Added to the Liner pH ADJUSTMENT: The pH of the waste solution may be adjusted by. adding NaOH to increase the pH to between 3.0 ans 6.0 for waste streams with a pH below f3.0 or by adding Sulfuric or. Boric Acid to lower the pH to- 5.0 to 7.0 for ~
, waste streams with a DH above 9.0. 4/ aste streams with a pH between 3.0 and 9.0 normally require no adjustment. ~ i !
i j'
gms of Accelerator /Coaditioner in the Sample / gms of
<Envirostone in the Sample. ,
t s. ;
x lb3 of Envirostone to be Added to the Liner ,
.lbs of ACCELERATOR / CONDITIONERS Added to the Liner G )
Q Verified by P.N.';.I. Operator Date I
l 1 l RP Tech-Radwaste 'T< Date
) c'
- /
j e
{ i e
i ;,
l .
's s
V '
AP.309 11-4-9
. .\. >
t
= ,. - _ _ - . . . = . .. ,J ! . - . . - ---, . - . -..
x
.1 OH-44, Rev. 0 October 9,1985 e
SOLIOIFICATION WORKSHEET P
l Operator: Date: No. ;
Utility / Location:
Waste Type:
Satisf actory Sample Verification No: Date:
Waste Solidification Efficiency: % (a)
Liner Size: Inches High x Inches Diameter Liner Usable Waste Volume (with 2" safety margin): CF (b)
Liner Volume Per Inch of Height: CF/ Inch (c)
WASTE VOLUME to be Added to liner: CF (a x b)
HEIGHT OF WASTE In Liner: In (a x b/c)
(Waste Full / Level Bubble Tube to be Set at this Height)
WEIGHT OF ENVIROSTONE to be added to the Liner: (Use the Values Determined
(~j'\
\ from the Sample Verification Worksheet.)
gms of Envirostone in Sample / ml of Waste in Samp13 x 62.38 = lbs of Envirostone/CF of Waste x CF of Waste to be Added to the Liner
= lbs of ENVIROSTONE to be Added to the Liner C
O' AP. 309 11-4-10 1
OM-44, Rev.'0 ..
October 9, 1985 Sample Verification Worksheet
' Sample Results:
Mix time (1): minutes Setup time (2): minutes Final Solidified Volume: minutes Solidification.EFF:
% (Waste'Vol/ Solidified Vol x 100%)
Free Water, If any:
Relative set (soft, firm, very hard):
Sample large scale proportions and solidification solidification ratios: results acceptable for calculation of -
yes no.
Verified By PNSI Operator Date
() RP Tech-Radwaste Date ,
1 I
( AP.309 II-4-11 i
, _ _ . _ , . , . , . - , , , , - < - , , - - - - ~ ' ' ~ * ~ ' " ' -
" ' ' ~ ~ ~ ~ ' ~ ~
n #
OM-44, Rev. 0 October 9, 1985 PNSI Solidification Operations Logsheet Operator: Date: No.
-Utility / Location:
Waste Type:
Waste From:
Solidification Worksheet No:
Waste Volume Added: OF: Time Completed:
Time Mixer Started: Hydraulic press:
Retarder Added: lbs. Time Added:
Waste Conditioner Added: Type: lbs: Time:
Waste Conditioner Added: Type: lbs: Time:
pH ADJUSTMENT Added: lbs. Time Started: Complete:
Envirostone Added: lbs: Time Started: Complete:
Mixer Hydraulic pressure PSI Time Time Mixer Secured:
Waste Set up Time: i l
Time Fillhead Removed: Time Liner Capped:
Comments and Observations:
P.N.S.I. Operator Date AP. 309 11 12
Liner No.
(Circle One)-
No free standing water YES/NO Waste shows uniform product YES/NO Waste resists penetration YES/NO Solidification Media is acceptable YES/NO If any answer is NO, do not ship the liner. Notify the Radwaste Supervisor who will initiate corrective action.
Consnents O
Verification Performed by Date P.N.S. I . Operator Date RP Tech-Radwaste Waste liner meets requirements for structural stability: YES / NO Date Supv. RP Tech-Radwaste, Supv. RP-Tech-Decon, Radwaste Supervisor O AP.309 II-4-13 O
ENCLOSURE 8.1 OM-44 REV. 0 ,
OPERATION AND MAINTENANCE MANUAL ~
RA0 WASTE SOLIDIFICATION SYSTEM NUCLEAR PACKAGING, INC.
OH-44 is considered proprietary by Pacific Nuclear Systems and is not being distributed, except to the Radwaste Supervisor.
r 1
O i
1 1
ENCLOSURE 8.1 PAGE 1 0F 1 l O AP. 309 11-4-15 END
-l l
I
..__._.a.____. -._-___._..._______.________...__.._-._._,_.._.._,.__,_,._.._._..,...; -
RECORD 7.3 l
TS 6.15 AND 6.17 REQUIREMENT CHECKLIST --
O Revision V
This change to the Process Control Program procedure becomes ef fective upon approval by the Plant Review Conunittee, unless otherwise acted upon by the Nuclear Regulatory Conynittee through written notification.
Items 1, 2, and 3 are the only signatures on this checklist required when submitting this change to the PRC. Af ter completing an item, forward to the person performing the next required signature.
- 1. This change is sufficiently detailed in information to totally support the rationale for the change without additional information being required.
Radwaste Supervisor Date
- 2. I have determined that this change does not reduce the overall conformance of the solidification waste product to the existing criteria for Solid Waste.
Radwaste Supervisor Date
- 3. If the change is a major change to the Radwaste Treatment System, complete the requirements of TS 6.17, Major change to the Radwaste System, per TS 6.17.3: Yes/No. If Yes: TS 6.17 Requirements Completed by:
Radwaste Supervisor Date
- 4. Documentation is complete showing the review and acceptance of the change by the Plant Review Committee.
PRC Chairman Date
- 5. A copy of this change is prepared for submittal to the Nuclear i Regulatory Conynission by inclusion in the semi annual Radioactive l Effluent Release Report for the period this change is made.
HP & Environmental Support Supt. Date Return to the Radwaste Supervisor M.S. - 244 AP.309 11 14 O ,
I
- )
l i
ENCLOSURE 8.1 O OM-44, REV. 0 OPERATION AND MAINTENANCE MANUAL RADWASTE SOLIDIFICATION SYSTEM NUCLEAR PACKAGING, INC.
OH-44 is considered proprietary by Pacific Nuclear Systems and is not being distributed, except to the Radwaste Supervisor.
l O
l 1
O AP. 309 11-4-15 ENCLOSURE 8.1- PAGE 1 0F 1 END l
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