ML20212H582
| ML20212H582 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/12/1987 |
| From: | Carfagno S, Cheu S CALSPAN CORP. |
| To: | NRC |
| Shared Package | |
| ML20211N624 | List: |
| References | |
| CON-NRC-03-81-130, CON-NRC-3-81-130 TAC-64735, TAC-64736, TER-C5506-657, NUDOCS 8701270242 | |
| Download: ML20212H582 (151) | |
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i ij TECHNICAL EVALUATION REPORT I
NRCDOCKETNO. 50-312 FRC PROJECT C6606 I
NRC LICENSE NO. DPR-54 FRC ASSIGNMENT 24 NRC CONTRACT NO. NRC 0341-130 FRCTASK 657 i
RADICIDGICAL EFFLUENT RELEASE AND I
RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTS FOR 1984 SACRAMENIO MUNICIPAL UTILITY DISTRICT j
RANCHO SECO NUCLEAR GENERATING STATION TER-C5506-657 g
i Preparedfor Nuclear Regulatory Commission FRC Group Leader:
S. Pandey Washington, D.C. 20555 NRC Lead Engineer:
- w. Meinke January 12, 1987 1
This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any a0ency thereof, or any of their employees, makes any warranty, expressed or impiled, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apps-ratus, product or process disclosed in this report, or represents that its use by such third party would not infrin0e privately owned rights.
Prepared by:
Reviewed by:
Approved by:
W N
$h Princip!~
DYpartment Dipctor alAuthor Date:
Date: b~U Date: 1"/Z #I7 i
A FRANKLIN RESEARCH CENTER A7 DMSION OF ARVIN/CALSPAN
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TER-C5506-657 CWTENTS II Section Title Page 1
INTRODUCTION 1
2 TECHNICAL SIRemRY 2
2.1 Plant-Specific Background.
2 2.2 Radioactive Effluent Releases.
3 2.3 Radiological Dose Impact 8
2.4 Radiological Environmental Monitoring Program.
9.
2.5 Review of Revisions to ODCM, PCP, and Radwaste Treatment Systems 17 2.6 Analysis of Release / Exposure Trends 18 2.7 Information Contained in Licensee's Reports 24
.i 3
CONCLUSIONS.
29 4
REFERENCES.
32 APPENDIX A PLANT AND SITE DESIGN FEATURES APPENDIX B
SUMMARY
DATA ON LICENSEE-REPORTED QUARTERLY EFFLUENT RELEASES AND DOSES APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND lI LICENSEE-REPORTED RESULTS APPENDIX D EVALUATION OF LICENSEE-REPORTED REVISIWS TO CDCM, PCP, AND I
RADWASTE TREATMENT SYSTEMS i
APPINDIX E TABLES OF LICENSEE'S REPORT COIGGTMENTS APPENDIX F CHECKLIST EVALUATION OF LICENSEE'S RETS REPORTS I
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FOREWORD This Technical Evaluation Report was prepared by Franklin Research Center
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under a contract with the U.S. Nuclear Regulatory Ceaunission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NRC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.
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TER-C5506-657 4-1 S
1.
INTRODUCTION This technical evaluation report presents the review and summary of i
radioactive offJuant reliaases and radiological environmentti monitoring,
reports for the calendat' year 1984 suhaitteri by the Licensee of Rancho Seco Nuclear Generating Station in accordance with plant Radiological Effluent 1
I, Technical Specifications (RETS). A summary of plant-specific trends in the effluent data reported for the years 1980 through 1984 has also been included.
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TECHNICAL SUtelARY
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J The review was conducted on the Licensee's 1984 Annual Radiological
- p Report [1].*
The review also includes the latest changes made by the Licensee
{i to the Offsite Dose Calculation Manual (ODCM), the Process Control Program "I
(PCP), and the radwaste treatment systems, which are documeniad in the Semiannual Radioactive Effluent Release Reports of 1985 [2, 3].
In some places throughout the report, a comparison is also made between the 1984 data b
and the data taken from the Licensee's 1983 Annual Radiological Report * [4].
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f 2.1 PLANT-SPECIFIC BACKGROUND
[- '
The Rancho Seco Nuclear Generating Station consists of one single unit.
The following information is pertinent to this RETS report review:
Type of Reactor PWR (Babcock & Wilcox)
{.
Licensed Thermal Power 2,772 MWt Maximum Dependable Capacity 873 MWe Net Commercial Operation April 17, 1975 l
RETS Implementation July 1984 I
Condenser Water Cooling Closed-Cycle
-System (Cooling Towers)
J Major Gaseous Discharge Containment Building Stack Point (145 ft El. above grade)
Total 1983 3,036 Gwh Electricity Output Total 1984 4,040 Gwh Electricity Output Average 1983 Unit Capacity 37.3%
Factor 4
l Average 1984 Unit Capacity 49.1%
Factor 2:
5,
- The Licensee's Annual Radiological Report is the only RETS report submitted I
for 1983 and 1984. The report consists of information that includes effluent release data and the results of the environmental monitoring program...
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Diagrams of the liquid and gaseous effluent release systems ar. recorded in j
the Licensie's Offsite Dose Calculation Manual (00CM) are given in Appendix A.
'In 1983, the Rancho Seco plant experienced a major outage from February
.is to August for refueling and TMI modifications. Another major shutdown was recorded for steam generator tube repair from September through November.
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l In 1984, the plant was shut down in January and February due to a hydrogen. ' explosion in exciter enclosure. Several more outages were experienced for steam generator tube repair from July to October.
2.2 RADIOACTIVE EFFLUENT RELEASES e
The reported effluent releases for the year 1984 were generally low for
' gaseous effluent. However, a high content of radio-cesium isotopes (Cs-134 and Cs-137) was reported. There were no abnormal liquid releases reported by i
the Rancho Seco Station during 1984, but they did report three abnormal gaseous releases that resulted in the release of 8.09 Ci (primarily noble gas I
and' iodine). A surunary of the effluent release, solid waste shipment, effluent dilution, and radiological dose impact data provided by the Licensee in the semiannual reports is presented in Table 2-1 and in the following g
paragraphs. More detailed quarterly data are compiled in the tables given in Appendix B.
( l 2.2.1 Liquid Effluent Releases Radioactive liquid effluents from *he 'fancho Seco plant are discharged with the two cooling towers' blowdwtD 'o P.a selville Creek via a discharge canal. The Licensee does not norme Ay we sarge significant quantitites of radioactive material in liquid effluents, since all liquids from the radwaste hl treatment system associated with the primary coolant are reused. However, since 19R, ;he plant has experienced several steam generator tube leaks, which resulted in contamination of the secondary coolant. The releases of j
radioactive material since 1981 resulted from release of regenerant solutions V
from the'(secondary side) polishing domineraliser.
The circulating water system operates in the closed-cycle mode, with makeup water being taken from the Folsom South Canal and blowdown released to Clay Creek. The only liquid discharge pathway of potentially contaminated water is via the regenerant holdup tank, which normally receives water only.
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TER-C5506-657 l
Table 2-1.
Susunary of Reported Effluent Releases / Exposures for 1984, Rancho Seco Nuclear Generating Station 1
(Data taken from Licensee's 1984 Semiannual Radioactive 1
Effluent Release Reports)
I.
ACTIVITY RELEASED Solid Wastes and Liquid Effluents Gaseous Effluents Irradiated Fuel Shipments A.
Fission and Activation A.
Particulates A.
Spent Resins, Filter Products Sludge, Evaporation Total : 0.000184 Ci Bottoms, etc.
Total : 0.636 Ci Cs-137 : 0.000080 (43.5%)
Cs-137: 0.301 (47.3%)
Unident: 0.000060 (32.6%)
Total: 37.9 C1 Cs-134: 0.153 (24.1%)
Co-60 : 0.000044 (23.9%)
I-131 : 0.123 (19.4%)
Others :
0.0 Co-60 : 0.019 ( 3.0%)
i Others: 0.040 ( 6.3%)
B.
Tritium B.
Tritium B.
Dry Compressible j
Waste, Contaminated Total: 297 Ci Total:
194 Ci Equipment, etc.
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Total:
8.1 Ci C.
Dissolved and Entrained C.
Noble Gases C.
Irradiated Components Noble Gases Control Rods, etc.
Total: 0.0389 Ci Total : 3,880 Ci None I'
Xe-133: 3,650 (94.1%)
Xe-135:
178 ( 4.6%)
Others:
52 (13%)
q D.
Gross Alpha D.
Iodines D.
Others Total: 0.0000268 Ci Total : 0.0321 Ci None I-131 : 0.0235 (73.2%)
I-133 : 0.00336 (10.5%)
I-135 : 0.00510 (15.9%)
Others: 0.00014 ( 0.4%)
E.
Batch Releases E.
Batch Releases E.
Disposal Site Number
- 211 Number: 39 Richland, WA:
Total Time: 2,812.5 min Total Time: 2,570.2 min 30 truck shipments F.
Abnormal Releases F.
Abnormal Releases None Number: 3 Total :
8.09 Ci
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.1 i1 Table 2-1 (Cont.)
Sununary of Reported Effluent Releases / Exposures for 1984, Rancho Seco Nuclear Generating Station (Data taken from Licensee's 1984 Semiannual Radioactive
- i Effluent Release Reports)
II.
EFFLUENT DILUTION
- i A.
Liquid Effluents Circulation Dilution Volume (GL)
Circulation Flow Rate Discharge Licensee NRC System (GL/yr)
Mode Report Estimate Closed-cycle 3.69 (1st quarter)
Batch 5.22 90 (Cooling Towers) 4.55 (2nd quarter) 8.61 (3rd quarter) 4.72 (4th quarter)
B.
Gaseous Effluents (NRC Parameters for Maximum Doses - Continuous Release)**
(sec/m3)
(mg)
X/Q D/
Location 3.6 x 10-5 1.6 x 10-7 Site Boundary: NNE 0.43 mile (Purge) 2.2 x 10-5 g,9 x 10-8 Site Boundary: NNE 0.43 mile (Continuous)
- f III. MAXIMUM INDIVIDUAL DOSES Liquid Effluents Gaseous Effluents Direct Radiation A.
Total Body Dose A. Noble Gas Air Dose TLD Dose (Mean) 186 arem (6,200%)***
Gansna:
0.780 mead (7.8%)***
Control Location:
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16.2 arem/qtr Beta :
1.94 mrad (9.7%)***
Indicator Location:
17.2 arem/qtr (Relatively high levels were reported at the Nest Perimeter Fence near the waste drum storage area, with a 4th quarter reading of 38.5 aces.)
B.
Organ Doses B. Organ Doses (iodines and particulates) 305 arem (3,050%)***
8.02 arem (0.53%)***
(Adult Liver)
(Infant Thyroid) iI
- 1 GL = 109 liters.
ii
- NRC staff evaluation for 10CFR50, Appendix I.
- Percent of Technical Specification reporting level.
A TER-C5506-657 1
from secondary side sources. In the event of a primary to secondary leak, this would be the pathway by which contaminated liquids would be released to the environment. There are no direct connections from the radioactive liquid radweste treatment systems to the environment. Excess liquids from these systems are solidified.
Several important aspects of the Licensee's 1984 liquid effluent releases are noted, as follows:
Releases were made only by batch mode during 1984.
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There were 0.636 Ci of fission and activation products and 297 Ci of o
tritium released.
o The most abundant radioisotopes among the fission and activation products were Cs-137 (47.3%), Cs-137 (24.1%), I-131 (19.4%), and Co-60 (3.0%).
g A total of 5.22 GL was reported as the dilution water volume during o
- 1984, i
i There were no abnormal liquid releases reported during 1984.
o The 1984 reported amount of release was much higher than that of 1983.
The Licensee-reported volume was much lower than the NRC-estimated dilution j
water. The estimated Cs-137 concentration in the dilution effluent stream, based on the reported volume of 5.22 GL* for the dilution volume, is very high,** 1.e., about 87 sci /GL.
2.2.2 Gaseous Effluent Releases There are three release points for radioactive gaseous discharges:
(1) the radweste building stack (not presently in operation and not shown in Figure A-3; see Licensee's Technical Specification Table 3.16-1), (2) the auxiliary building stack, and (3) the containment building stack. The turbine building ventilation exhaust is not considered a release point for radioactive material.
- GL = 1 x 109 liters.
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TER-C5506-657 l
1 For the two release points currently in operation, the reactor building u
effluents are released via the containment building stack. Radioactive gas from the compressor, radwaste area, fuel handling area, and radiochemical service area are released via the auxiliary building stack. Neither stack is
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considered an elevated release point. The plant gaseous discharge pathways l
are shown in Appendix A.
1 Several important aspects of the Licensee's 1984 gaseous releases are as follows:
o Releases were made both in the continuous mode and in the batch mode, and from two release points.
I Total gaseous releases included 3,880 Ci of noble gases, 0.0321 Ci of o
radioiodines, and 0.000184 Ci of particulates.
o A total of 194 Ci of tritium were released.
o The auxiliary building contributed 65% of the total gaseous activity discharged.
o The most abundant radioisotopes in each gaseous group were Xe-133 for noble gases (94.1%), I-131 for radioiodines (73.4%), and Cs-137 for particulates (43.5%).
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There were three abnormal gaseous releases reported during 1984 (8.09 Ci, mostly noble gases and iodines).
The release pattern is similar to that recorded for 1983, except that the amount of noble gas releases had increased by almost a factor of 5 in 1984.
The Licensee reported maximum (X/Q) values for the following receptor 3
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locations:
2.79.x 10 (sec/m ) as annual average from the continuous releases to the site boundary (NNW 670 meters) and 1.462 x 10" (sec/m )
for the nearest meat animal (SSE 198 meters). For purge releases, the (X/Q) values at the site boundary (NNW 670 meters) is 3.211 x 10 ' (sec/m ) and 3
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2.268 x 10 (sec/m ) for the nearest meat animal (SSE ~498 meters). The i
Licensee's (X/Q) values at the site boundary are somewhat more conservative than the NRC staff evaluation of 10CFR50 Appendix I (see Table 2-1).
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\\2.2.3 Solid Radioactive Waste Shipments Information.concerning the Licensee's shipments of solid radwaste to offsite locations is as follows: i
l TER-C5506-657,
A total of 257 m3 of solid radwestes containing 37.9 curies of o
. activity was shipped offsite; it consist 4d of spent resins, filters, sludges,-evaporator bottoms, etc.
o A total of 168 m3 of solid radwestes containing 8.1 curies of activity was shipped offsite; it consisted of dry compressible waste, contaminated equipment, etc.
o A total of 30 shipments were made by truck to the Richland, Washington burial site.
o Solidification agent was concrete, when used.
I No unusual release pattern is noted in the reported data.
1 2.3 RADIOLOGICAL DOSE IMPACT As seen in Table 2-1, the reported dose impact to the maximum individuals
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in the unrestricted area (Figure A-1) from liquid releases is high, especially from liquid effluent releases. The offsite doses resulting from liquid r
effluent releases are about 6,200% of the Technical Specification reporting level, and those from gaseous releases are 54% of the respective reporting limit. The high dose levels raise the concern about the Licensee's compliance I
with 40CFR190 limits. This is discussed in Section 2.3.3.
A summary of the dose to the maximum individuals beyond the site boundary or in the unrestricted areas for the liquid and gaseous effluent release is presented in the following paragraphs.
2.3.1 Liquid Effluent Dose The following are the Licensee's reported annual doses:
The whole body liquid dose is 186 mrom (6,200% of the technical o
specification reporting level of 3 meen).
o The critical organ was identified as child's liver, and the organ dose is 305 mrom (3,050% of the technical specification reporting 1evel of 10 mren).
More discussion on liquid doses are provided in Section 2.3.3.
2.3.2 Gaseous Effluent Dose The following gaseous effluent doses were reported by the Licensee:
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The annual air dose at the site boundary from gasuna emissions was o
0.780 mrad (7.8% of the technical specification reporting level of 10 j,-
mead).
1 The annual air dose at the site boundary from beta emissions was 1.94 o
mead (9.7% of the technical specification reporting level of 20 mrad).
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For radiciodines and particulates, the Licensee identified the infant o
ll thyroid as the critical organ, for which the annual dose is 8.02 arem ji (53% of the technical specification reporting level of 15 ares).
t 2.3.3 Total Dose The Licensee discussed the fact that the maximum total body and organ l.
(liver) doses calculated using the procedures specified in the CDCM were far above the 40CFR190 [6] (fuel cycle) limits of 25 area. The Licensee also noted that the criteria for exceeding the fuel cycle limits are real doses received by real individuals, and described additional studies undertaken to determine if these limits had in fact been exceeded. The Licensee stated that preliminary results of the additional studies indicated that the limits were not exceeded, and therefore that the reported calculated doses were very conservative. The Licensee, however, has not documented these results in the annual report. It is suggested that an independent study be conducted to l
verify the Licensee's compliance with 40CFR190 limits.
2.4 RADIOLOGICAL DNIRONMENTAL MONITORING PROGRAM The Licensee's reports present the data obtained from the analyses of a f
number of environmental samples collected during 1984 for the Licensee's Radiological Environmental Monitoring Program. The monitoring program jf reported is summarised in Table 2-2.
Detailed infomation is given in
- 1 Appendix C.
Most of the Licensee's analysis results are at or below the lower limits of detection (LLDs) specified in the Licensee's reports. Activities above the detection limits in these routinely collected liquid sample media were lI observed above the natural and atmospheric origin.
Particular emphasis in the program was placed on iodine-131 and air particulate monitoring, as well as on measurement of direct radiation outside l
the site boundary. Highlights of the results can be summarized as follows: -- --
t TER-C5506-657.
Table 2-2.
Outline of Environmental Monitoring Program. Rancho Seco Nuclear Generating Station Collection" Analysis
- Type Number of Analysis Sample Tune No. af Locatlan Freauency Freanancv Anah ti s Performed in 1484 Air Particulate B
a Weekly Weekly Gross Betab 403 Quarterly Ganna Spec.(compo-328 Alpha'y location) site b 32 Airborne I-131 8
a Weekly Weekly 1-131 403 Surface Water 8
a Monthly Monthly I-131 36 Gross Beta (Susp.)
36 (Dissolved) 36 M-3 36 b
Beta. H-3, 16 r
Will Water' 4
a Quarterly Quarterly and I-131 b
Drinking Water
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Quarterly Quarterly Beta. H-3, 12 and I-131 Runoff Water 1
a Fortnightly Fortnightly I-131 21 (Approx.)
(Approm.)
Gross Beta (Susp.)
21 (Dissolved) 21 Gamma Spec.
21 M-3 21 Food Products 4
a At harvest At harvest Gross Betab 8
(Human Vegetation) b 48 l
Food Products' 4
a Quarterly Quarterly Gross Beta (Animal Vegetation)
$r-90 48 l
Milk 4
a Weekly Weekly I-131 208 Monthly Sr-90' 48 Fish I
a Quarterly Quarterly Gross Betab 8
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Sr-90' I
Rabbit Flesh' I
a Quarterly Quarterly Betab 8
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a Quarterly Quarterly Sr-90 8
Ribbit Thyroid' I
a Quarterly Quarterly I-131 8
Al'gae' 1
a Monthly Monthly Betab $r-90 11 and Genna Spec.
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Hud and Silt 2
a Monthly Monthly Gross Beta 17 t
Gamma Spec.
17f TLD 62 1
Quarterly Quarterly Exposure Rate 243 j
a.
No control locations identified.
b.
Reported as gross beta and gross beta less K-40.
Required number of samples less number Licensee reported as " missed" c.
Required only if gross beta activity of a sample is greater than 10 times that of an " appropriate control sample.
d.
Not required by technical specifications.
e.
f.
Technical specifications require sampling "at least semiannually."
3 TER-C5506-657
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.p A total of 208 milk samples were analysed for iodine-131. In no case o
was iodine-131 detected. All measurements were below the iodine-131
'i LLD of 0.5 pCi/m3 Weekly airborne iodine samples from eight locations (403 samples) o contained an average I-131 concentration of 0.0031 pCi/m3 for the 16 (of 32) quarterly averages with non-sero concentrations (see discussion in Section 2.4.2).
Weekly airborne particulate samples from eight locations (403 o
samples) contained an average gross beta concentration of 0.0148 3
i pCi/m.
All surface, runoff, ground, and drinking water samples contained o
detectable gross beta activity. The highest concentration was 3.7 pCi/L (92% of the RETS maximum LLD) in a groundwater sample. The only other radioactivities detected in water samples were H-3 and I-131, each reported in one of 12 three-sample averages of surface water samples.
I Mud and silt samaples from the " waste water course at the SMUD o
property line" showed gross beta activities (maximum LLD = 4 pCi/g dry) from 1.6 to 78 pCi/g dry. Significant concentrations of activation and fission products were also detected in these samples, l
l including Cs-134, Cs-137, Co-58, Mn-54, and Co-60 in more than half of the samples.
Quarterly direct radiation measurements were reported from 62 o
indicator locations and 1 control location. The mean of exposures was 16.2 arem/qte at the control 3ocation and 17.2 ares /qtr at indicator locations (see discussion in Section 2.4.1).
Four of eight fish samples from the site reservoir contained gross I
o beta (less K-40) activity averaging 0.40 pCi/g dry (maximum LLD for gross beta = 0.1 pCi/g dry). Sr-90 was detected in one sample (0.1 pCi/g dry).
Algae samples at the site boundary effluent stream contained an o
average of 48 pCi/g dry of gross beta activity in 10 of 11 samples.
Gamma spectrometry of the algae samples detected Co-60, Mn-54, Cs-137, Cs-134, Co-60, and Co-58 in morce than half of the samples.
In animal-consumed vegetation, beta activity (less K-40) was detected lI o
i in 8 of 16 samples at an average concentration of 0.70 pCi/g dry (maximum gross beta LLD = 0.1 pCi/g dry for food products). Sr-90 was detected in 11 of 16 samples at an average concentration of 0.12 l
PCi/g dry, i
Human-consumed vegetation samples showed no detectable radioactivity o
except naturally occurring K-40.
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Rabbit samples showed beta (less K-40) activity of 4.4 pCi/g dry in one average of two flesh samples and Sr-90 activity averaging 0.88 pCi/g wet in two out of four averages of two femur samples. No I-131 activity was detected in eight rabbit thyroid samples.
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Some concerns about the potential deficiencies in the Licensee's~
environmental monitoring program are discussed in the following:
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Table 3.22-1 of the Licensee's existing Technical Specification Section 3.22 on the Radiological Envi m tal Monitoring Program does not contain provisions to perform gasma isotopic analyses for the following sampling pathways as specified by the model RETS (NUREG-0472): surface water, mud and silt, milk, fish, and food.
These gasma isotopic analyses have not been regularly performed by the Licensee's existing contractor, Controls for Environmental i
Pollution, Inc. (CEP). Rather, they were performed by the Lawrence Livermore National Laboratory in special tasks initiated by the i
Licensee in 1984 to investigate the concentration of radionuclides in freshwater fishes downstream of the Rancho Seco site.
o The Licensee's Table 3.22-2 of the existing Technical Specification, which specifies the reporting level for radioactivity concentration in environmental samples, does not contain reporting levels for individual isotopes specified by the model RETS (NUREG-0472). The same applies to the food products. This happens because the Licensee's Technical Specification requires only gross beta analyses instead of the gasuna isotopic analysis for these pathways. In the 1984 study, high cesium concentrations were reported by the Lawrence Livermore National Laboratory (UCID-20295). These levels of concentrations, in many cases, have exceeded the reporting levels specified by NUREG-0472.
2.4.1 Air Particulate Samples The Licensee's discussion of weekly airborne particulate and iodine samples states that the samples were " generally analysed within nine days of collection." The results of these analyses were reported as the quarterly average by location, so the results for individual samples were not available unless the report included a special discussion. The Licensee's discussion of airborne particulate samples states, "all stations are clearly recording the same phenomena."
The Licensee discussed one iodine sample showing plant effect. This was from the onsite sampler, and was associated with a reactor building purge.
Extrapolation from the quarterly average of 13 samples indicates that the level of I-131 in the sample was about 4 times the RETS maximum LLD and 1/3 the reporting level.
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1 2.4.2 Direct Radiation r
The Licensee identified the TLD location at the west site fence, where i j f
the annual average dose was 29.4 meen/qtr (1.7 times the average of all f
locations), as receiving direct radiation due to plant operation. This was the result of being near the storage yard for radioactive waste drums. Other I
locations gave values from 12.3 to 28.0 arem, and were reported as being i
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consistent with data from previous years. At these other locations, the highest annual average doses were recorded, in declining order, at 2 miles NE, 19 miles E, the SW site fence, 19 miles E, 11 miles SE, 10 miles SW, and 10 miles S.
The locations of these highest readings tend to support a conclusion i
that the location at the west site fence was the only one exhibiting plant 1
effect.
(Note: The Licensee reported TLD results in Table 3 of the annual report in units of arem/qtr and discussed the same numerical values in Section l
II.c.11 with units of arad/qtr, but no conversion of units was discussed.)
The NRC conducted a direct radiation monitoring program comparable to l
that performed by the Licensee (see Tables C-1 and C-4 of Appendix C).
The average exposure at the NRC's indicator locations was 3% lower than at the control locations. The NRC's indicator and control location exposure values in (mR/qtr) were, respectively, 13% lower and 5% higher than the doses reported by the Licensee (in mrem /qtr).
(Exposure values in mR are not expected to be numerically equal to dose values in arem, but a more accurate comparison is not possible without detailed knowledge of the gamma spectrum involved.)
The reported mean values are comparable to the NRC TLD measurements.*
2.4.3 Waterborne and Food Products Except for well-water samples, results of water sampling and analyses were reported only as the averages of several samples. Averages of three
- The NRC TLD measurements are under NUREG-0837, "3GIC TLD Direct Radiation Monitoring Network."
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1 TER-C5506-657 I
i Table 2-3.
Comparison of Gross Beta Activities in Airborne Particulates Since 1971, Rancho Seco Nuclear Generating Station g
(Taken from Licensee's Annual Radiologial Environmental Operating Report) n Indicator
Background
(sci /m31 (sci /m31 Preoperational 0.228 1971 Operational 1980 0.032 0.026 1981 0.036 0.032 i
1982 0.010 0.010 1983 0.012 0.012 1984 0.015 0.015 t
l Note: Preoperational data and data taken from the Licensee's 1985 Annual i
I Radiological Environmental Operating Report (Figures 1 and 2).
e 6 __
1 TER-C5506-657 samples were reported for drinking water and surface water, and the number of
'i runoff samples averaged for reporting purposes varied from four to seven.
Some individual samples were discussed in Section II.c of the Licensee's Annual Radiological Report.
The Licensee reported maximum gross beta activities of 3.7 and 4.1 pCi/L, respectively, in well water and drinking water samples, and stated that the results were comparable to previous measurements. The Licensee states, " gross beta values ranged from nondetectable to a anzimum 2.3 pCi/1 in surface water samples, and from nondetectable to 5.6 pC1/1 in runoff waters except for several samples inappropriately taken during periods of controlled releases were not included in the average gross beta levels reported for runoff water." These gross beta activities are also shown in Table C-3 of Appendix C in this report.
l The Licensee noted that two surface water samples contained reported quantities of radionuclides which could not be explained. A sample from the l
site reservoir on August 14 contained 543 pCi/L of tritium, and a sample from Comanche Reservoir (11 miles SW of the site) on July 17 contained a reported 1.9 pCi/L of I-131, only slightly below the reporting level of 2 pCi/L. Later l
samples from these locations had no measurable amounts of either I-131 or H-3.
Algae and mud and silt samples from the " waste water course" at the SMUD property line were the only environmental samples showing consistent plant effects. Gross beta (less K-40) levels in algae and other aquatic plants ranged up to 133 pCi/g (13 times the reporting level for fish), and Cs-137 levels ranged up to 281 pCi/g (other isotopes detected in algae included Co-60, Mn-54, Cs-134, CO-58, and I-131, each at less than 281 pCi/g). Mud and silt samples from the waste water course showed gross beta activities up to 78 pCi/g and Cs-137 activities up to 126 pCi/g. Other fission and activation products detected were Cs-134, Co-58, Mn-54, Co-60, Cr-51, Mb-95, Zr-95, and I
I-131, all at lower concentrations than Cs-137. No reporting levels existed i
for algae or mud and silt samples.
Eleven of 208 milk samples contained detectable I-131. The highest 1
concentration in a single sample was 1.2 pCi/L, which is below the reporting l
e I
TER-C5506-657 level of 3 pCi/L. Sr-90 was detected in 9 of the 208 samples, which was consistent with prior years' data and not considered to indicate a plant effect.
The low levels of gross beta (less K-40) activity detected in about half of the animal vegetation samples collected were similar to levels detected in the past. No radioactivity that could be related to the plant was detected in any human-edible vegetation.
Fish samples were taken from Rancho Seco Reservoir. The Licensee stated, "all fish samples contained low gross beta activity; the highest value was 0.8 I
pCi/g dry."
One sample had an insignificant, but measurable, Sr-90 value.
However, a separate study by the Lawrence Livermore National Laboratory (UCID-20295), initiated by the Licensee, showed high concentrations of Cs-134
}
I and Cs-137 in fish samples. The report concludes that the concentrations are related to the plant releases.
l 2.4.4 Land Use Census t
The annual land use census required by the Licensee's Technical Specifica-l tion 3.23 was conducted during 1984. Three locations were identified that I
would give higher calculated dose commitments from airborne particulates, 1-131, and tritium in specific sectors than the locations previously iden-tified. In compliance with Technical Specification 3.23a, the Licensee reported these locations as 6.7 lan (instead of 7.8 lan) SSE,1.5 km (instead of 3.8 lum) SSW, and 2.334 lan ESE (a new resident). The Licensee stated, "the SSW resident possible was previously categorised as the SW section resident at 1.2 lan. " The Licensee stated that none of these could result in different "nazimum individual" pathways. No reference was made to location of milk animals.
The Licensee stated, "a liquid exposure pathway not previously sampled was identified early in 1984, prior to [ implementation of] the Technical Speci-fication, after calculations of the theoretical exposure to man via liquid routes indicated that specific isotopes concentrating in fish would produce a significant pathway." Increased sampling of mud and silt and fish from downstream locations and vegetation from creek irrigated grazing land has been designated, apparently as the result of the identification of the new pathway.
j c
TER-C5506-657 j
1 3.4.5 Quality Assurance Program The Licensee stated, "in compliance with Technical Specification 3.26, verification was made that the laboratory performing analyses of radiological i
environmental monitoring program samples participates in a Commission approved Interlaboratory Comparison Program."
I Appendix F of the Licensee's Annual Radiological Report contains a copy of a certificate dated February 1, 1983 from "The American Association for Laboratory Accreditation" conferring accreditation on " Controls for Environ-mental Pollution, Inc." in the " Chemical Field of Testing." The reviewers are not familiar with either of the organisations mentioned in the certificate.
Appendix F of the Licensee's annual report also contains a letter (undated) from Irwin T. Dickstein, Director, Environmental Services Division,
~,i United States Environmental Protection Agency, Region VIII, 1860 Lincoln i
Street, Denver, Colorado granting " reciprocal certification to Controls for l'
Pollution, Inc., for the radiochemical analysis of drinking water from Region il VIII." The letter also states, "this reciprocal certification is subject to I
the regulation established by the State of New Mexico certification program.
The laboratory must continue to participate in the EPA cross check and l
performance programs. The data must be within the acceptable limits defined I
ili Appendix F of the report also contains tables of comparison of results from Controls for Environmental Pollution, Inc. (CEP) with EPA. The samples compared with EPA values included air filters, water, and milk. Approximately 70% of the sample results were within i 3s of the EPA known values. The quality of the results was not discussed.
The implication of these statements and data in the Licensee's Annual Radioactive Report is that CEP performs analyses of environmental samples for 1
i 6
the Licensee, but this is not specifically stated in the report.
I 2.5 REVIEW OF REVISIONS TO ODCM, PCP, AND RADNh5TE TREATMENT SYSTDES The Licensee has made several changes, in the Annual Radiological Report through December 31, 1985, to the ODCM submitted on November 25, 1983 [6] and approved by NRC (7).
l 1 -_._._-. -.. -, - - -
r k
TER-C5506-657 i
The Licensee has reported several changes to the radweste treatment systems in the Licensee's updated FSAR through January 1, 1986. The Licensee has also made changes in procedures to the Process Control Program (PCP) [8],
which has been approved by NRC [9]. Regardless, FRC was instructed by the NRC staff not to review these changes to the PCP since the Licensee is in the process of changing vendors which makes the present PCP obsolete.
Evaluation of the Licensee's CDCM and Jta changes have been completed and is given in Appendix D.
Review of the changes to the radweste treatment system is also given in Appendix D.
2.6 ANALYSIS OF RELEASE / EXPOSURE TREND 2.6.1 Trend of Effluent Releases Trends of releases of radioactive materials from Rancho Seco and calculated offsite doses for the 1980-1984 period are discussed below:
o Releases of fission and activation products in liquid effluents during 1984 were approximately two and a quarter greater than in e
1983.
I o
Releases of fission and activation gases (noble gases) in gaseous effluents increase steadily over the years.
o In 1983, the I-131 release was lower by 90% than in 1984.
o Releases of long-lives particulates in gaseous effluents were generally low but peaked in 1982.
o Release of tritium in gaseous effluents also did not show a particular trend.
Reported liquid doses have been high except for 1980, with a peak in o
1984.
No particular trend has been observed for air doses. For organ doses o
from iodine-131 and particulate, a peak was identified for 1984.
Releases of quantitities of radionuclides in liquid effluents which should have been reported as giving calculated whole body and organ doses in excess of 10CFR50 design objectives during 1961, 1982, and 1983 went unreported until early 1984 because of errors in input parameters to the. _.
1
~_.
p j
i l
s TER-C5506-657 computer code for calculating doses. As a result of the errors, the
\\
- j calculated doses reported were below the 10CFR50 values. Releases were always far below the concentration limits of 10CFR20, Appendix B, but the small
)
f dilution volume (5.22 GL/yr) used when discharging radioactive material into a normally dry stream resulted in high calculated doses when correct parameters
)
were used. The Licensee has contracted studies of the effect of radioactive affluents on the environment to the Lawrence Livermore National Laboratory.
l The Licensee stated that "the examination revealed a significant under-estimation of the liquid pathway dose to man as reported in previous ll Radioactive Effluent Release Reports." Doses due to both liquid and gaseous
!I effluents were calculated at 0.61 miles WSW of the " center of the site."
(The distance appears to have been actually measured from the reactor.)
- i l
Total radioactive material releases and selected calculated doses for 1980 through 1982 (from Appendix F to the Licensee's Annual Radiological Report for f
1984) are shown in Table 2-4 with corresponding data for 1980 through 1985 i
from the Licensee's periodic reports. These data are also plotted in Figure 2-1.
1 j
The apparent inconsistency.tn the ratio of liquid radioactive effluents to whole body and organ doses that occurs between 1982 and 1983 is explained I'
by the fact that releases in 1983 and 1984 contained a much higher fraction of fl cesium compared to cobalt radionuclides than the releases in 1981 and 1982.
(Both the bioaccumulation factor in fish and the ingestion dose factors are larger for the cesium radionuclides than for the cobalt radionuclides.) The l,
low calculated doses for 1980 and 1985 are consistent with the relatively low l
l releases of radioactive material in liquid effluents in 1980 and 1985 compared
[
to the 1981-1984 period.
The reasons for the relatively large reported site boundary gamma air l
dose shown in Figure 2-1.c for 1983 is not clear. The 1983 air dose is l
reported to have been calculated using " default meteorology," and is reported as being at the east site boundary. It is also stated to occur at the " site l
boundary distance of 640 meters." However, the actual distance from the
- reactor to the east site boundary is 3605 meters. For 1984, the site boundary H
dose is reported at 1036 meters NNW, although the ODCM gives the site boundary l
I i l
i l
i i
Table 2-4 Liquid and Gaseous Ef fluent Release, Solid Waste Shipment, and Exposure Data from 1980 to 1905, i
Reported for Rancho Seco Nuclear Generating Station I
RACIDACTIVITY RELEASE i
i Lieuid Ef fluents l
Total (Not Including Gaseous Ef fluents Salid Masta Shipments Tritium. Alpha, Gases)
Tritium Noble Gases Iodine-131 Particulates Tritium Vol Activity YtAr iCil (Cil iCil ICil ICil ICil 3
ICil 1,580 0.0105*
19E0 0.00377 f
[
1961 0.614 1.360 0.00469*
1.480 0.262*
19E2 0.217 1963 0.280 74.3 692 0.002 0.00023 175 272 225 r
I J
1964 0.636 297 3,880 0.0235 0.00018 194 425 46 I
1%5 0.000005 89.9 4,670 0.00641 0.00151 33.1 1,208 1,844 L
HMIMM IPWIVIDuAL DOSE Lieuld [ffluents Cassaus Effluents Whole Body Organ Air Dose Gamma Air Dose Beta Whole Body Skin Iodine-131/Particulates ItAI farami fareal ierad1 ierad1 (mramt ieram) ieraan 2.37 j
1980 2.99 0.0187 1.63 1981 63.2 86.8 1982*
17.5 24.1 0.762 1983 106 146 5.9 2.2 1.18 1.58 1.39 1984 186 305 0.780 1.94 0.463 1.27 8.02 1985 "
1.19 1.20 1.48 3.82 0.849 2.202 0.756 Reporting f
Level:
3 aren 10 mrom 10 mrad 20 mrad 5 arem 15 mrom 15 mrom vi t
- Data includes I-131 and particulates I
l
" See footnotes to Tables B-4 B-8, and 8-12.
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l E3 ACTIVITY DOSE i
1.to
- 6. coo %
g,,3 171 1.52 152 s.ooos 1-1 g>a y3.14 n, j
- e. coos I i o.n E
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,. coot e 3
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& o.ts 78 3
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5 o.n n
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19 o.19
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ino inn in i,'n 3,..
Year (a) Liquid Release /Whole Body Dose T/S Appendix I Reporting Level - 1984: 3 ares /yr E B8W 31o
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2.79 i
219
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- 2. son 2.40 2e8 E
r 3
-g, 2.ns 217 2,oon p g
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o.n soot l
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o.o neo feet (b) Liquid Release / Organ Dose T/S Appendix I Reporting Level - 1984: 10 mres/yr Figure 2-1.
Trends of Reported Effluent Releases and Estimated Doses to the f
" Maximum" Member of the Public, Rancho Seco Nuclear Power statinn, 1990 to 19R4 i
4 e
TER-C5506-657 t
(EIl ACTIUITY DOSE s.000 s.O 60%
S.400 S.4 50%
4.000
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4.0 5
2 4.200
~
4.2 a 1-mF 53.600 5
i 3.s 3
i i
3.000 g
3.0, - 30g g O
2 I
3 2.4l
.400
)~
2 1.000 1.0 2
1.200 1.2 h
600 0.5
=
0
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, 0.0 2
0%
1940 1981 1982 1903 1944 Year (c) Noble Gas Release /Whole Body Dose T/S Appendix I Reporting Level - 1984: 30 mead /yr (3 units) i 1
unu ACTIVITY 200%
i Em DOSE i
0.210 27.0 1
0.243 24.3
?
150% "
$ 0.216 21.6 U
t j
ng,g
{
0.109 0.162 16.3 1***{
I-0.135 g3,3 j
{ 0.100 10.0 ] 1 0.0e1 s.1 m2 1 0.054 s.4 :
0.027 3.7 E
E E
j 0.0 1980 1901 1992 1903 1994 Year (d) Todines and Particulates/ Organ Dose T/S Appendix I Reporting Level - 1984: 45 meem/yr (3 units)
Figure 2-1 (Cont.). Trends of Reported Effluent Releases and Estimated Doses to the " Maximum" Member of the Public, Rancho Seco Nuclear Power Station,1980 to 1984
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- m... _
__m...
m m
m mm._
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distance in that direction as 670 meters. The 1985 reports give maximum noble j
gas gamma air doses to an individual (by quarter), but do not specify distance or direction to the dose point.
(The Licensee also included calculated site boundary gamma air doses for each of 16 sectors for each quarter, but these l
values were not used to verify the maximum dose in Table 2-3 and Figure 2-1.c due to obvious errors in the data for the third quarter.)
I There appears to be an inconsistency in the values of the calculated organ doses plotted with I-131 and particulate releases in Figure 2-1.d.
(In i
this case, the maximum organ dose for 1983 from the Licensee's annual report j l is to the thyroid at 0.75 mi BIE, which is the same as the maximum organ dose to the thyroid of a child at 0.61 mi NSW reported in Appendix F of the 1984 annual report.) However, the high release in 1982 compared to the calculated
,i j i organ dose is apparently due to the fact that the releases during 1982 (but l
not 1983) were dominated by Co-58, for which Regulatory Guide 1.109 contains I
the entry "NO DATA" or much lower values of inhalation dose factors than for I-131.
(It is reasonable to assume that the Licensee used 0.0 for inhalation dose factors shown as "NO DATA.") The calculated maximum organ doses for 1980 4
through 1984 appear to be consistent with being primarily due to I-131. For 1985, the Licensee reports maximum doses due to tritium, iodines, and I
particulates in airborne effluents, but does not specify location, type of individual, or whether whole body or organ dose.
[The value of 0.756 mrem obtained by summing these maximum quarterly doses is smaller than the sum of calculated doses in an infant via the gas-milk cow pathway (0.92 arem) at the location for which the highest organ dose due to gaseous effluents was reported in the 1983. The value of 0.92 area was obtained by summing values taken from the Licensee's table containing al1~ dose calculations for the year.)
j 2.6.2 Trend of Environmental Measurements
' l Direct radiation levels for 1983 and 1985 and gross beta activities in airborne particulates for 1980 through 1985 measured in the Licensee's environmental monitoring program are listed in Table 2-5 and plotted in Figure 2-2.
i 4
No long-term trend was observed in the direct radiation measurements during the 1980-1985 period. Airborne gross beta activity levels in 1980 and l
- IL
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_ _ _ _ _ _ ~ _ _ -... _ - _ _,.... - - -
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I TER-C5506-657 l
Table 2-5.
Direct Radiation and Airborne Activity Measurement Data from 1980 to 1985, Rancho Seco Nuclear Generating Station DIRECT RADIATION W ure Level (aR/std month) i Year Control Indicator 1980*
1981*
I 1982 17.5 18.7 1983 16.0 17.7 1984 16.2 17.2 1985 13.9 15.9 9
AIRBORNE ACTIVITY Activity Level (oCi/m31 Year Contro1**
Indicator 1980 0.026 0.032 1981 0.032 0.036 1982 0.010 0.010 1983 0.012 0.012 1984 0.015 0.015 1985 0.020 0.020
- Data not available from the Licensee's annual reports.
- The Licensee did not identify a control locations. The control location value shown are for the samples at the TLD references locations.
0
>i TER-C5506-657
'l
- 1 1981 were nearly three times the 1982 level, due to fallout from the Chinese atmospheric tests (the last of which occurred in October 1980). The plot shown in Figure 2-2.8 of airborne gross beta activity reported during the 3
1982-1985 period shows a constant increase from 0.010 pCi/m to 0.020 pCi/m'. The Licensee did not discuss this apparent trend. In the l
environmental monitoring report for 1985, the Licensee included a comparison of plant measurements of airborne gross beta activity with measurements performed by the State of California at the same locations and noted higher j
readings by the State of California program. However, the graph provided of
}
the data shows the measurements were from different time periods and, i.
therefore, not comparable.
u f
2.7 INFORMATION CONTAINED IN LICENSEE'S REPORTS Information contained in the Licensee's reports was compared with the Licensee's report comunitments (see tables in Appendix E) for the Licensee's annual radiological report for 1984 [1]. The completeness of the reports submitted compared to the report commitments is discussed in the following
)
l paragraphs (see tables in Appendix F).
2.7.1 Annual Radiological Environmental Monitorina Report l
The Licensee described the radiological environmental monitoring program conducted during 1984 and reported results of the program. The report ll included results of the radiological environmental monitoring program, results fI of participation in an interlaboratory comparison program for environmental samples, and a description of changes required in the environmental monitoring program as the result of the land use census. The Licensee also noted that a liquid exposure pathway not previously sampled was identified early in 1984, prior to implementation of the current technical specifications, after calculations indicated possible significant esposure via the fish pathway. As a result of this identification, the sampling program was expanded to include l
a significant number of additional samples.
lI The Licensee reported radiation doses via the principal pathways of lI exposure resulting from plant emissions of radioactivity, including gamma and beta air doses in the unrestricted area..
TER-C5506-657 Eml CONTROL W
INDICATOR ao le 16 5
14 g
le j
e l*
=
um "3
, E g
O 1980 1941 1942 1983 1904 Te (a) Direct (Ambient) Gamma Exposure Note: The Licensee's 1983 annual report is not available from the NRC.
mm CONTROL INDICATOR 0 04G 0.036 1
E E
a 0.032 m
0.014 i
k 3 0.02.
I T
E E
k 0.020 j
0.016 i
a m
6 0.012 e.00s 0.004 E
0.0 j
1940 1901 1943 1903 1944 Test (b) Airborne Gross Beta Activity Note: The Licensee's 1983 annual report is not available from the NRC.
Figure 2-2.
Trends of Reported Effluent Measurement Levels, j
Rancho Seco Nuclear Power Station,1980 to 1984
! i
I;I TER-C5506-657 i J The Licensee reported 12 cases of air sampler filters not being removed 3j in the proper time frame (weekly changes). Ten of these cases were due to a single contractor; SMUD employees are now performing the weekly changes.
l,>
(This report of failure to properly collect air sample filters was reported in l
compliance with Technical Specification 3.22a, which requires a description of l*
reasons for not conducting the monitoring program as specified in Technical I
,I Specification Table 3.22-1.)
ll, The Licensee reported seven packets of TLDs vandalised or lost during high winds, and two packets left in the field beyond the normal retrieval date I
due to inaccessibility.
l,)
The following deficiencies were noted in the Licensee's reports:
In 1984, the Licensee should have reported an Annual Radiological
! '}
o Environmental Operating Report and two Semiannual Radioactive Effluent Release Reports per the Licensee's Technical Specification l
6.9.2: the Licensee instead only submitted one Annual Radiological 8
Report.
Except for the TLDs, the monitoring and sampling locations were o
incompletely identified. Most identifications were only by name or code number. The table and map identifying sampling locations and l,
giving distances and directions, required by Technical Specification 6.9.2.2.2, were not included.
l l
The reports did not include susmarised and tabulated results in a o
I consistent format (e.g., TLD results were reported quarterly for each l
location, results of weekly milk sampling were reported only in a I
I f l,
e v
TER-C5506-657 quarterly composite by location, analyses of mud and silt samples
~
were reported for each sample, etc.) The Licensee's Technical Specification 6.9.2.2.2 requires, "the reports shall include i
summarised and tabulated results in the format of Table 6.9-1, of all samples taken during the report period," but the technical j
specifications contain no Table 6.9-1.
i The frequency at which samples were analysed was not stated for most o
ies.
The comparisions with preoperational studies, operational controls, 4
o and previous reports, as required by Technical Specification I
6.9.2.2.2, were generally cursory or omitted.
2.7.2 Effluent and Waste Disposal Semiannual Reports FRC did not receive for review semiannual reports issued by the Rancho Seco plant for 1984. The Annual Radiological Report for 1984 included data required by the Licensee's RETS to be in the semiannual reports, and was i
reviewed as though it were the semiannual reports. The Licensee reported a radioactive effluent release summary for liquid and gaseous effluents and solid radioactive waste disposal according to the format of Regulatory Guide 1.21 [9] with some minor exceptions (noted below). The Licensee reported three abnormal or unplanned effluent gaseous releases from the plant during 1984.
The following deficiencies were noted in the Licensee's liquid effluent,
[
gaseous effluent, and solid waste reporting.
The volume of radioactive solid waste shipping containers was given o
in cubic feet rather than cubic meters. The solid waste was given in cubic meters.
I Solid waste data were not given in 6-oonth periods, but only in o
l annual totals.
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A Tr2-C5506-657 I
s 3.
CfMCLUSIONS I
s The Licensee reported radiosctive effluent releases, offsite doses, and results of radiological environmental monitoring all under a single report, the Annual Radiological Report for 1984. This is contrary to the Licensee's s
RETS reporting commitments (Section 6.9.2), which designate na Annual s
Radiological Rnvironmental Operating Report for reporting results of
'i environmental monitoring and two Semiannual Radioactive Rff3uent Release Reports for reporting eff1wnt releases and offsite duss.
The Licensee-reported liquid releases in 3.934 were relatidely higin in)
Cs-134 and Cs-137. A study (UCID-20295) by the Licensee's contractor, the 4
Lawrence Livermore National Laboratory, has concluded that th,e relatively high cesium concentrations in fish samples _ ore relsted to tSe plant releases. Ths-
?
reported whole body dose and organ dose toc t'ho maximum individual have been '
i
'6,200% and 3,050% as high as the respective Technical Specification report sg.
s levels. Although the Licensee indicated that reavchuatior of the doses by its contractorislikelytodemonstrateLicensee'scompliancewith40CFR190 limits, the study is not yet made availrble to the revi w or.
Further
- )
i independent study is needed to investigate ths Licensee's compliance with 40CFR190.
s f
Analyses of many hundreds cf indicator and control simplei from the Licensee's environmental rionitortng program showed signifacant increase of cesium (Cs-134 and Cs-137) cora ntrations in the liquid (aud and silt) pathways for 1984 over 1983.
'*his is consis+. cat with the relativsly high level of cesiusa recorded in the liquid effit mt releases. For airtoene pathways, the reported results showed no measurable radioactivity'in most samples outside of the site bourdary that, was attributable to the plant.
Although the Licensee h u geaerally demonstrated compliance with the plant Technical Specificatiorin, several potential definier.cles, hopaver, have been identified in the Licensea's existing Technical Specificatima throughout the review. These potential deficiencies are oatlined in the fcklowing:
The gansna isotopic analyses has not been specified in ths Lici: u ae's o
Radiological Environmental Monitoring Program (Table 3.22-1 ef the Licensee's Technical Specification 3.22) for saveral important j
environmental pathways:
surface water, milk, fish, and foo).
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TER-C5506-657.
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The inclusion of such analysis is generally required by the model i
RETS (NUREG-0472). As a result, concentrations of potential isotopes, such as cosiums, are not identified in the Licensee's regular annual report for many pathways. Although results of such analyses have been reported in special tasks performed by the Licensee's contractor, the Lawrence Livermore National Laboratory, i
such analyses are not reported in the Licensee's annual reports on n
samples regularly conducted by the Licensee's existing contractor, j
Controls for Environmental Pollution, Inc.
j.
o The Licensee's reporting levels for radioactivity concentrations in i
environmental samples (Table 3.22-2 of the Licensee's Technical I
Specification 3.22) are not provided for specific isotopes in pathways such as fish and food products; these levels are generally required by the model RETS (NUREG-0472). According to the study t.a, performed by the Lawrence Livermore National Laboratory, most of the cesium (Cs-134 and Cs-137) concentrations in fish samples taken in 3
1984 have far exceeded the reportinct levels specified by the model RETS.
- . A, /
{-
3 o
The Licensees's existing Technical Specification does not contain a provision to treat liquid effluents, as required by the model RETS 4
(NUREG-0472) Specification 3.11.1.3.
The Licensee has not comunitted to project the liquid doses to the unrestricted areas at least once F
per 31 days as specified by the model RETS (Specification 4.11.1.3).
i In view of the above, it is reconumended that a full evaluation of the Licensee's existing RETS comunitments be conducted to eliminate the potential i
e deficiencies and therefore streamline the control of the Licensee's radioac-tive effluent releases and operation of the environmental monitoring program.
During 1984,* the Licensee made several changes to the CDCM, the PCP**,
{
1) and radweste treatment systems. The Licensee's ODCM and its revisions have i
been found to contain numerous deficiencies which require further clarifi-cation or corrections in order to meet the current NRC criteria. The Licensee-poposed changes to the radweste treatment systems have been found to meet the L
I i
current NRC guidelines.
i i
- Review of the CDCM also includes the latest revisions submitted by the j
Licensee in the Semiannual Radioactive Effluent Release Reports of 1985.
- Per NRC staff instructions, the Licensee's PCP and its revisions are not 4
evaluated here due to plant-specific situations.
4 j b t
I TER-C5506-657 ll The operational measurement data in 1984 effluent report provide
.l substantive documentation showing increased radioactive levels over the past years. The results of the data analysis indicate possible adverse environ-q' mental conditions for 1984 that have resulted from the operation of the plant.
I i
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I.
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,I :;
TER-C5506-657 4.
REFERDICES I
1.
" Annual Radiological Report - January 1 through December 31, 1984,"
Rancho Seco Nuclear Generating Station NRC Docket No. 50-312 (Available in NRC-PDR) 2.
" Semiannual Radioactive Effluent Release Radiological Report - January 1 through June 30, 1985," Rancho Seco Nuclear Generating Station NRC Docket No. 50-312 (Available in NRC-PDR) g 3.
" Semiannual Radioactive Effluent Release Report - July 1 through December 31, 1985," Rancho Seco Nuclear Generating Station NRC Docket No. 50-312 (Available in NRC-PDR) 4.
" Annual Radiological Report - January 1 through December 31, 1983,"
!i Rancho Seco Nuclear Generating Station NRC Docket No. 50-312 (Available in NRC-PDR)
(
5.
C. Nillis (NRC)
Memo to C. Miller (NRC)
Subject:
Additional Credit for Dilution of Liquid Effluents from Cooper by the Missouri River November 28, 1984 1
6.
Title 40, Code of Federal Regulations, Part 190, " Environmental Radiation i
Protection Standards for Nuclear Power Operations" l
r 7.
Offsite Dose Calculation Manual for Rancho Seco Nuclear Generating
+
Station, NRC Docket No. 50-312, Submittal with letter dated October 11, 1984 8.
D. R. Miller (NRC/DSI)
Memo to G. C. Lains (NRC/DL)
Subject:
DSI Safety Evaluation and Environmental Consideration of Rancho Seco Nuclear Generating Station, Unit 1, Supporting A Licansa Amendment (RETS, MPA Item A-02), February 9, 1985 9.
Process Control Program for Rancho Seco Nuclear Generating Station, NRC Docket No. 50-312, Submittal dated May 1979 10.
" Measuring, Evaluating, and Reporting Radioactivity in Solid Nestes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Nater-Cooled Nuclear Power Plants" June 1974 USNRC, Regulatory Guide 1.21, Rev. 1
m 8
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4 8
APPENDIX A PLANT AND SITE DESIGN FEATURES i
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I FRANKUN RESEARCH CENTER l
ONISION OF ARVIN/CALSPAN 20th & RACE STREETS.PMILADELPHIA.PA 19103 I
TER-C5506-657 The site boundary and restricted areas for the Rancho Seco Nuclear
!t Generating Station are shown in Figure A-1, which is taken from the Licensee's existing REIS (Figure 3.18-1).
i i
The liquid and gaseous affluent treatment systems for the Rancho Seco Nuclear Generating Station are recorded in Figures A-2 and A-3, respectively.
These figures are taken from the NUREG/CR-2348, "In-Plant Source Term Measurements at Rancho Seco Station."
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A-1
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eget ternaart.***
j nesenseed Asse m
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a 8tECME AT9000
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Figure A-1.
Rancho Seco Unit 1: Area Map [Reproduc;pd from Figure 3.13-1 of the Plant's RE"rS in Appendix A to Operating License No. DPR-54 j
(Docket No. 50-312) as revised through amendment 78, dated l
Dacember 24, 1985]
4
~
Reactor ains and,
Th Steam generefors (
Reactor
-=. coolant drain
,wnps lank m
i t
f f
e r Spent Letdown Migen regenerant CooHng
,,3ge, g r
makeup tanks towers system i
C.I.
f OH absorber n
Flash filler 2
tank Makeup water l
~
l and chemicals l
Reactor coolant Domineralizer primary i
domineralizers 1
d, Misc wastes
'8"8 Misc waste Coolant waste Spent concentrate evapaatw j
receivertanks fuelpool hold tanks 4
f Distitiale f
l Misc waste Reactor coolant Ship off sHe condensale secondary pigger,
sIorage Iank DomineraHzed demineralizers reacforcoolant f
storage tank Concentrated Misc water g
Coolant waste I
boric acid Domineraffrer storage tank holdup lank holdup lank y
Condensate 4
hineralizers
(
Concentrate Reuse g
Bwic acid g
f Distillate evaporator INEL A ts esa U
Figure A-2.
Rancho Seco Unit 1 Liquid Radwaste System (Reproduced from Figure 1.1 of "In-Plant Source Term Measurements at Rancho Seco Station," NURIX;/CR-2348. Octohar l'181]
4
TER-C5506-657 E
I Containment bido stack Auxiliary bido stack Prom q
blowdown tank n A- >
-n I
r
< wastew e g
i l
m
=
.u, e
.as y
,,,m I"""
weste
-(
"C" >
l l
gas Weste gas 8
c compressor
,0 )
Tanks 1 = Prefitter g
g I
2 = HEPA filter I
la Charcoal l
I
@s Sample point l
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i 22.000 cf m f Plenum
,j g
9 Redwaste g
area
[
,jite r g
i Filter 8
8 h
I I 42.300 cfm Avuil ary i i 213 8
7-3 l
10,000 cfm I
9 I I Fuel handling a
a,.a i i
= = *"
l I 42,300 cfm I
filtIr f
i as 1l213 A
1 Building W
9890 cfm g g
{
Q Radiochemica!
-e 1 2 service area o
Filter Dilution l ;
air I
Containment
$6,700 cfm winter p
,,,, I f 16,670 cfm summer gg,,
Air.. Intake cleanup I
74.000 cfm @
h 'i: = lI 2
W. inter i > t -
C><3 system C><3 from T_
=
,..umm.,-
i d,,,,,,,m 4 Fliter
=
S agh I
g g
m.-
Figure A-3.
Rancho Seco Unit 1 Gaseous Radwaste System [ Reproduced from Figure 1.1 of "In-Plant Source Term Measurements at Rancho Seco Station," NUREG/CR-2348, October 1981]
j A-4 l t l
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APPENDIX B 1
SUMMARY
DATA ON LICENSEE-REPORTED QUARTERLY EITLUENT RELEASES AND DOSES
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FRANKUN RESEARCH CENTER DMSION OF ARVIN/CALSPAN 20th & RACE STREETS,PHnADELPHIA.PA 19103 1
I
l TER-C5506-657 The data sununarized here are taken from the Licensee's Semiannual g
j Radioactive Effluent Release Reports submitted for 1983, 1984, and the first 6 months of 1985.
I r
The Licensee's effluent release data for 1983 are susmarized in Tables B-1 and B-2 for liquid releases and gaseous releases, respectively. The tables show the quarterly data as well as the combined annual data on activity releases, release volume, length and frequency of batch releases, and abnormal releases. Table B-3 summarizes the shipment of solid radioactive waste for offsite burial.
In Table B-4, the quarterly doses reported by the Licensee for maximum individuals are shown for liquid as well as gaseous releases. The annual doses are summed from the quarterly doses as a conservative estimate, since critical organs in each different quarter may not be the same.
Similar data are shown in Tables B-5 to B-8 for 1984, and in Tables B-9 to B-12 for the first 6 months of 1985.
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B-1
e Table B-l.
1983 Liguld Ef fluent telease Beta ter manche Seco Insclear Generatlag Statlea Etanea f rom Licensee's 1983 Amasal medlelegical Reportl Total teleases en.n a and r aa-
-l anoch talemama ramel-
- tal --- -
' - - tame== a Annual Amamal Act6,6Ly M M 2nd Str 3rd Sir 4th Str* fatal 1st Str 2nd Sir 3rd Sir 4th Sir Intal M h iLil I-A. Badlamativity Anlamaan I. fission and Cl 5.5 M -82 9.4 M-84 4.9eE-02 1.75t-01 2.80E-04 2.get-01 Cs-137 1.1M-81 49.4 Activatlen Products ts-134 6.99t-42 24.9 I-131 3.67E-02 13.4 Co-SS 3.22t-02 II.5 raja t.5M a2 s_4 letal 2.7st-48 %.3
- 2. Dissolved and Cl tetralmed Isable i
j Genes 7.4M+04
- 1. Frillum Cl 6.49t+41 4.70E-41 8.94t+44 8.l?t+00 7.4Me41 y
- 4. Gross Alpha Cl 2.57E 2.57t-43 2.57E-43 5.
Rataana Valanes
- 1. Weste Elfluent GL 3.57t-42 6.16t-03 3.2M-82 5.1M-82 1.2H-81 1.26E-41 2.97t+40
- 2. 061stlea Water GL 5.87t-SI 6.67t-42 7.25t-89 7.72t-01 2.97+48 C.
tea 9th and Frequency
}
af amark malamana*
l S. leumber of teleases lle.
59 ISS 167 1.40te43 167 l
- 2. tength of Releases Iers. 4.24t*42 9.74Ee42 1.40E*43 I
D.
Ahmamal Antammen 1
- 1. laumher of Aeteases Ito.
t 0
1 5.00E-42
- 2. Activity Released Cl 5.00E-82 0.8 5.00E-92
- Reported samlanavally.
64 A,
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fable 0-2.
1981 Geseous Eff* seat selease Gate for seache 5ece k lear Generatlag Station (tahea f rea ticeasee's 1983 Annual Radiele9 cal Report) i Total teleases ea.seh and ramsI-
-I maesh gelmaama faatt:
- Reimanaa emainmat laataman Aaaval Aanval Actieety M lat Sir h 3rd Sir 4th Sir fel.at lat Sir 2nd Sir 3rd Sir 4th Sir hMh n 1
A. Radlaartletty Anlaamme
- 8. Isobte Gases Cl 3.34t+01 2.17t-01 2.6 M +02 9.57E-41 2.90E+-2 1.06t+02 0.00t+M 1.70t+02 1.19t+02 3.94E+02 6.92t+02 se-133 6.48t+02 92.6 no-135 2.4M+0i 3.5 as-ina t.ver+el 2.6 J
letal 6.07t+02 98.7
- 2. Iodines Cl 1.9W-03 0.00E+00 9.05t-05 0.00t+00 2.0X-03 6.5X-M 0.00E+00 7.77t-05 2.00t-04 2.04E-04 2.31t-93 I-1312.0W-01 00.0 1-133 2.7et-04 12.s letal 2.31t-01 IM.0 l
- 3. Particulates Cl 1.07E-04 0.0 2.29E-05 0.00t+ M 1.29t-04 3.79t-45 1.36E-05 2.99t-05 f.44t-05 9.56t-05 2.25t-04 Cs-827 1.00E-44 44.6 to-te 5.67t-05 25.2 Cs-tM 3.50t-05 15.6 ta-se u nt-es 14.7 istal 2.25E-04 IM.0
- 4. fritiva*
Cl 3.51t+49 1.65f+44 3.00E+01 9.30t+01 1.75t+02 1.75t+02 g
Ito 0.
Averste Rate af Relaamas*
I
- 1. Isoble Geses uCl/sec -
1.70E+49 2,76t-02 5.44t+01 1.51E*01 2.10E+0i 2.10E*01 1
2.llt-04 0.00E*M 2.22E-05 2.52t-05 6.45t-05 6.45t-05 j
- 1. Particulates uCl/sec 1.04t-05 I 72t-06 6.70E-06 1.0M-45 7.15t-06 7.15t-06
- 4. Tritium uCl/sec -
4.46t+00 2,10t+00 3.77t+00 1.10E*01 5.5M +00 5.5 M+00 C.
tea 9th and frequency of Batch Anlamama*
- 9. Ieusher of Releases IIe.
29 85 44 44
- 2. teatth of Releases pers.
2.05t +03 0.70t+02
- 3. 7W+01 3.7W+03 D.
ehearmal animanas I. Ie aber of Releases Ite.
0 0
0 0
0 u
- 2. Activity Released Cl 0.00 0M 0.00 0.M 0.M
- all releases.
tv1
" Reported seelanavally.
M 6
U, US C3 On Icn U1
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table B-3.
1993 Solid Weste and Irradiated Fuel Shipments for Reache Sete stoclear Generating $tatlea (taten f rom Licensee's 1993 Anamel tadlelegical Report) lat 6 lemnthe 2'ad 6sh ne
^
-1 teamt Weste lume Act6,6ty flajor fenclel Waste Volume Activity 9tejer fluclel toeste elume Activity n
atti tammesittaa is3a stin tamanantian
- i sten I.
free of Weste l
a.
Spent resins, illter 0
0 0
0 0
0 sIveges, evaporator bottoms, etc.
b.
Dry compressible 0
0 107 7.30 Co-50 54E 107 7.30 waste, contaminated Co-.07 39E egulpment. etc.
Bee-54 ISE 1
Cs-137 35 c.
Irradiated components, centrol reds, etc.
0 0
0 0
0 0
f d.
Other 0
0 85.2 Zie Co-545 05.2 210 C 50
-E m-54 IDE Cs-137 31 Shipplat lesde of fee. of Shipelag finde of Inc. of Shipplas gas, of heatimattaa fransmartattaa himmmata hostinating Iramanartatlan himments heattmatian hammmata 2.
Solid Weste Dispositten Richland, tan fruck (sele use) 33 Olchland, tan 13 3.
Type of Centalaer Itot discussed used for Shipment 4.
Sellelfled Agent seet discussed
- 4 N
A u,
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On ion (19 4
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=
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- a *e M esapeme W
puneeen u.--
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b Table S-4 1983 Summary of feesteme Individual Deses for Rancho Sece stucteer Generating Station (taaen free licensee's 1983 Annual Radielegical Deport)
Direct flanid iffl mat Airharme fffl mme Radiattaa IIeble Gas.
lesole fees.
ledines and Llantd. fatal Ende Llamid. Organ h
Reta particulate < ornam Tetal and, 1st Otr one (aree)*
tecellen sist. to): sir.
2nd Otr esse (erse) tecetten sist. (m): Str.
3rd Qtr tese (erent Locatio Dist. (m): Str.
txt c'n 4th Otr seee (ersel*
tocation sist. (m): Dir.
Annual een (are )
106 146 5.9 ered 2.2 ared 1.39 erad les plant effect e= cept (Adult-adhele (Adult.tiver)
(E.2.5 al)
(t.2.1 el)
(Thyreld 40 mrom at north fence Sedy) free moray eachtme. and (if5tf - 9.61 el)**
(w98-0.61 el)**
(flut-8.76 el) le eram at mest fence free weste storage area.
Annual tielt fores) 3 18 1e erad 2e erad 15 1 Annual 3533 1868 59 11 9
tielt letal Dese (area) the Licensee did not discuss the calculated deses ulth respect to dose comettaent iloits of 40Cftl98. which aepear to have eq Dese been e=ceeded. See fable 8-8 for the statement contained in the 1984 Annual #adielegical Report for Ranche Sece concerning M
(40CFRl90) 40CFR198 limits.
- D A
tJe ese
- the deses shown are these due to all gaseous effluents. The ticensee reported the total organ dose to the moslaus esposed ladividual due to gaseous o
effluents. but did not report the dose due te (.138. particulates, and tritive separately. The licensee stated. "Due to the relativet targe segnitude of cn the noble gas source teve la comparison to the ledine and particulate source teros, the total body and organ doses were deelnated by t plume pathay."
8
- Location and direction inferred f ree Appendia F of the 1984 Annual Radlelegical Repeet which specifies the fecetten at 975 m (0.61 ell wStf free the center of the site.
4 ee
e table 0-5.
1984 Liguld Elfluent telease Data for Sanche Sece E clear Generatin9 Station Itaten from Licensee's 1994 Annual Sadielegical Deportl Total teleases eamash ama rm.aI- -
-3 manch mal-----*
rm.el-Det-----
u--
n a _.
Anaval Annuei Attieity M lat Sir 2nd Sir 3rd Sir 4th Str fatal lat Sir 2nd Sir 3rd Sir 4th Sir h Amamat laSi m e 1Lil
.1.
A. Sadlaattivity balansas I. fission and C1 2.07E-41 2.32E-01 1.94E-01 3.07E-03 6.36E-01 6.36E-41 Cs.137 3. tit-SI 47.3 Activation Products Cs-134 1.5 M-01 24.9 I.131 1.21E-SI l9.4 Ca-40 1.0E-02 3.0 Total 5.97E-04 93.0
- 2. Olssolved and Cl 2.01E-03 2.77E-02 5.79E-03 2.6M-03 3.99E-02
- 3. Set-02 se-133 3.3eE-02 07.2 g
En.ralaed Isable Ea-tM a_eN.m 12.s e
Gases fetal 3.09E-02 100.0
- 1. tritium Cl 4.50Ee00 1.70E,00 9.70E*02 1.lM*02 2.97E*02 2.97Ee02
- 4. Gross Alpha Cl 0.00E*00 0.00E+00 2.60E-05 0.00E+00 2.60E-45 2.00E-05 8.
malaana 401ssist I. Ideste Effluent OL 5.17E-02 5.6 X-02 3.2 X-02 2.97E-02 3.70E-01 1.70E-01
- 2. Olletten tieter GL
- 3. Fit-05 1.00E+00 2.12E*00 1.1M*00 5.22Ee00 5.22E+00 i
C.
Length and frequency af Satch Onlaaman I. stumber of teleases see.
- 2. Length of teleases lors.
til 2il 2.01E+03 2.01E+03 l
0.
Abnarmal Salamaan i
I. Ilumber of teleases Ite.
i
- 2. Act6eity teleased Cl
=
=
- 4 A
u, (31 C3 m
1m US 4
e e
P-
.m
,e
=e se
s l
fable 3-6.
1984 Gaseous Ef fluent Release Geta for Ranche Sete leuclear Generating Station Itaken from Licensee's 1984 Annual Sadielegical apportl Total Seleases fame,h and ramel-
-l match teleason ramten-a-. an1*****
._D m inant asetages Annual Annual AcLiw4ty hit ist str 2nd Str 3rd Sir 4th Otr letal_
ist Sir 2nd Sir 3rd Sir 4th Sir total.
8maal featmas (Q1
.3 A. Radlaattivity Salaaman I. eseble Geses Cl 1.47t+02 5.tM+01 1.17t*03 0.39E*00 9.30t*03 1.01E+03 7.40E+02 f.69t+02 5.67t+02 2.50E*03 3.OSE+03 Ee-133 3.65E+03 94.5 1
Es-135 1.7K +A2 4.8 total 3.0M *01 98.7
- 2. todines Cl 9.2M-84 0.00E*00 9.9M-03 1.54E-07 2 6M-02 3.60E-04 5.96t-05 4.76t-03 6.1M-84 5.79E-03 3.21t-021 131 2.3M-02 73.4 t-933 3.36t-03 10.5 1-tm L aer-a1 n,3 total 3.2st-02 99.e
- 3. Particulates Cl 0.00t+00 3. Set-06 7.11t-05 3.39E-05 1.09t-04 9.36t-06 2.25t-05 4.llE-86 3.94t-05 7.5M-051.04E-04 Co-137 0.0M-05 43.6 thildt. 6.00E-05 32.6 Ea.4A 4.3K-05 23.A total 5.04E-04 190.0
- 4. tritl #
CI 3.1M +02 6.5M +01 7.16t+00 9.4 M+00 8.94t+02 1.94t*02 e
B.
Av, erg, ___s_t_e
- t. Isable Geses aC1/sec 1.4 M +02 1.0 M +02 f.69t+02 7.2 M*08 1.2M +02 9.2M +02
- 2. Iodine-131 aCl/sec 1.64E-04 7.50E-06 I.46t-93 1.34E-03 7.49t-04 7.48t-04
- 3. Particetates utt/sec -
I.19E-06 3.34E-06 9.57E-06 9.37t-06 5.OSE.06 5.05t-06
- 4. tritium aCl/sec 1.4?t*01 0.31t+00 9.01t-0 4 1.19E+0S 6.tM+00 6.1M*00 C.
Length and Frequency
_af match Ralemaan 39 39
- 1. esumber of Releases IIo.
2.57t+03 2.57t+03
- 2. Len9th of Releases Mrs.
D.
Shaarmal Ralaanen 3
3 I. seister of Releases lie.
0.09t+00 0.09t*00
- 2. Act4*lty Released Cl 64
- oata 9 en under hatch releases reported.
4 g
A U,
Ut Oas 9
at U1 J
i i
fable B-7, 1904 Solid teoste and Irreellated Fuel Slpments for Sancho $ece IInclear Generating Station (taten from Lleensee's 1984 Annual Radietegical soport) 131 6 enanthe 2nd 6 m==nha
-1 faa.m1 lume Activity seojer gesclel toeste gelisme Activity teoste Volume Activity plejer stoclel toastepI J1 fCil Camm11tlan J
I[il Cammaaltlan JB JL 1.
Type of teoste W3 Sd5 257 37.9
$ pent resles, illter Fe-55 ISE a.
siedges, evaporater N643 111 bottoms, etc.
Cs-137 95 Co-40 SE b3 d2E 140 0.1 b.
Dry compressible fe-55 24E waste, contaminated N643 19E egelpment, etc.
Cs-837 2E i
Cs-te ISE to 0
0 c.
Irradiated compements.
control reds. etc.
0 0
d.
Other Shipping stede of gee, of Shipping feede of No. of Shipplag sto. of Bestimatlam frammaartallas
$himmmats testimatlam frannaartattaa lhlammata testimattaa M
elchland, tan 30 alchland, ten Truck (Sete Use) 2.
Solid teoste Dispeellion Richland,184 Truck (Sele Use)
=
3.
Type of Centelner Liners, drums Net specified used for Shipment mood and metal bones 4.
Sellelflod Agnat Concrete (sic)
- 0nly annual dote provided.
- Annual anclel ceapositten, g
A.
u t#9 O
cFt I
(Ft Ut M
e 0
9
=
me =
- 3.,
w m
sup= - =m m
a==-
en mm so e==
amp
4 4
4 fable B-4, 1984 Sumnery of 81sulmen Individual Deses for Ranche Sece IInclear Generettag Stetten (taken from Licensee's 1994 Anneet Radlelegical Report)
Direct tim-Id Eff?-ame Alrharas Efff====8 Radiattas defines and Lienid. fatal Bade llamid. Organ unble Gas. Gamma umble Gas. Esta Particulates. Argan fatal Ande 1st Str Dese (erse) location Olst.(s); Sir.
2nd Otr Dese (areal Locatlen Dist.(e); Dir.
3rd 9tr Dese (eros) location Dist.(e); Sir.
td I
4th Str Gese (erse)
LD tecollen Dist.(ett Str.
annual Sese* (areal 856 305 0.700 erad 4.94 erad 5.02 (Adult)
(Child. Liver)
(Infant. Thyroid)*
(w5u-e.61 ell **
(w1W-0.61 ell **
(seef-4.64 el)
(W9W-4.61 ell (EE.4.75 el)
Anneel 3
le it ered 2e ered 15 tielt (ares) 5 Annual tielt 6200 3050 7.8 9.7 54 letal Dese (ares) Ise Licensee's Annual Radiological Report for 1994 contains the following statement concerning 80C79190 Ilette: "If Dese the calculated results enceed design objectives, entensive environmental stedles, pelbic censumptlen, and recreettenel (accreI98) habit leformatten is needed to determine if the trA eranium feel cycle dose llelt of 25 ores per year has been esceeded. Calcolettens for the ligold effisents escoeded the design objectives levels and estensive stedles and evaleettent were made and are still in progress to determine if the EPA Ilelt has been exceeded. Infereellen to date shows that no ladividual in the pubitc has esceeded this [PA Ilmit."
g
- 1he Licensee reported doses separately for Ingestion and for other pathways. A reelew of the reports ladicates that the total dose to ard g
inf ant's thyreld should probably be 9.1 mrom higher (i.e.
8.3 areal when the dose due to inhalatten is censidered.
O tP
- tecation and directies inf erred f rom Appendes F of the 1984 Annual Rad 6elegical apport which specifies the locatten at 974 m (9.b1 ell If9W 4A f ree the center of the site.
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TER-C5506-657 i
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se .4 t~ gi i 49 i j E E: II e e ee as .e js s ss as gj j-i is i,l i = 11 13
- 13 Is, l
n. _, d E 11 I8 11 3 22 31 5: a g! l.t l: 2 =x w :.; n,- x a ai
- a a
s 4 e J e ? B-10 I
m D l Table 0-10. 1995 Gaseems Ef fluent Selease Data for Sanche Sece Iowclear Generating Statten l Itaten from Licensee's 1995 anreal Sa46eleg6 cal teport) { Total teleases l sa.a,6 man e-a n -i j n.e,h am?----- r--a? - ame-mentammt inaamaan i manual Annemi attie6ty ggli lat Sir 2nd Sir 3rd Sir 4th Sir fatal. lat Str 2nd Sir 3rd Sir 4th Sir Iatal., amenal teatman if.11 _L A. Sadlamativity Salmanan I. Isobte Gases Cl 1.21t 43 3.05te40 2.tet-42 5.50t+42 l.77t+03 2.6Me03 l. tete-I O.00te00 2.67t+-42 2.91t.e3 4.67t 43 Se-133 4.40t 41 94.1 En-lE 2.22Ee02 4.7 1stal 4.62 41 98.8
- 2. leelnes Cl 6.0X -04 3.94t-04 1.04E-44 2.32t-03 3.4 N -43 3.67t 83 6.76t-43 0.00Ee00 1.06E-44 3.9N -83 7.35E-03 1-133 5.42teOS 39 I-In 5.40te00 40 total 1.30EeSt let
- 3. Particulates Cl 1.00E-44 3.66E-44 1.7N-45 7.30E-44 1.2M-83 0.69E-45 6.29E-05 4.67t-45 0.31t-85 2.00E-04 1.51t-43 Co-137 7.14t-44 47.3 Co-40 4.7N-44 31.3 I
Es-134 2.3M -84 1%.4 08
- s. net-as s.l total 1.50E-41 99.8 h
>.0
- 4. irttlem*
Cl 1.ON eel 1.1X ett 6.61E 40 4.97t*00 3.31t+01 3.31te41 8. Average Gate af Salaasen 4.09te421.99E 00 3.35t-431.04te42 1.40t.02 1.40teet I. Itable Geses uCl/sec
- 2. Iseine-838 aCl/ set -
4.04t-44 5.071-45 1.31t-45 23.57t-04 2.0M 44 2.0M-44 2.40E-05 5.45E-85 0.1M -46 1.04t-04 4.00E-45 4.00E-85 l 3. orticolates ate /sec I.30E*00 9.44EeGG O.3N-41 6.25E-01 9.05E.00 1.05Ee00
- 4. frlttua uCl/sec C.
Length and frequency
- af Satch Galamaan.
44
- 9. Itumber of Seleases Ite.
32 32 44 3.26te03
- 2. Length of Seleases lors.
2.44te43 0.24te42 3.26t 03 i D. Ahme m al Salenten* 1 1 I 0
- 1. Ituater of Seleases De.
0.00 3.27te41 3.27t.01 3.27t*01
- 2. Activity teleased Cl
.e. r,- laan ,,7 3 v1 (19 Om Im (19 .J 1 1
e fable 5-13. 1995 Selld toeste end Irredleted feel %lpments for Reache Seco nutteer Generating Stetten (teten from Licensee's 1905 Annuel Sadlelegical Report) ist a haL 2nd 6 en--aka -1 Tan =1 Weste eleme Activity Mejor Nuclel tieste eleme Actietty stojer fluttel Weste line Activity l fCil Cammaattian 1 (Cil Cammaaltlas i ICll I. Type of tieste e. Speat resias, fliter let 263 Cs 137 42.31 558 1100 Cs-137 42.3E 779 1363 sludges. eveperator fe-55 28.35 Fe-55 16.4E i bottoms etc. N 6-63 14.65 Ni-%3 12.25 t Cs-134 8.e5 C s- # ^> 12.11 Co-48 7.85E Co-44 7.495 Me-3 5.995 M-3 5.96E M b. Dry compressible 51.7 5.04 M-3 54.9E 306 476 Co-SS 35.45 4Je del 'h esaste, centesinated Fe-55 87.3E fe-55 29.5E A -Itte 13.65 pa egulpment, etc. Ni-43 13.21 9 Co-60 6.871 no-63 13.0E Ce-137 3.ME Co-ee 8.051 Cr-SI 6.625 ( I 9 0 0 0 i c. Irredleted campements. 0 8 control reds. etc. e e e e e I d. ether e e Elpplag sense of see, of Dipping sende of eso, of DIpples see. of amattmattam frammaartattaa Shipmmmin heattaattan framanartattaa jblagggga heathmatlan $hisnants 2. Selld Weste SIspeeltlee Alchlead. W4 "Sete Use* 29 Richtend. ten " Sele Use' 77 Richland, ten 97 Vehicle Vehicle 3. Type of Container LSA and Type 5 Used for Slpment 4. Selldlfled Agent Concrete (sic) A. U Ut O On Icn (19 4 e 9 0 'W m.
- W-W.use
.meerm p W
= esamme u. s i l 1995 (first 6 lesathst %emmary of steeless fadividual Booes for Ranche Sece asoclear Generating Stetten I fable 5-12. (taken from Licensee's 1985 Annual Radielegical Reportl Direct alrharme Eff1 ame Radiaties 1 tiened tff1
==a j Iodines and Limald _ fatal hade Llauld. Organ Ilmble Gas. Gemen Ilm61e Cae Beta 2 articulates. Orgna Istal Bady lit Otr Dese tarsal 2ad Otr Dese (areal i 3rd Qtr Dese (ersal eth Sir Gese (ersal t39 letal 3.1g eroe 1.29 eroe 1.48 ered* 3.82 erad' O.7% 4* i (Individual-orgen) (child-total tedy) (Child Liveel g w .ansai 3 m,em i e,em
- i. -w
- 2. e,w i5 timet teree)"
j I
- Annual tient 39.7 12
?1.9 19.1 5 j Direct radiatten due to the plant een apporontly negligible es if IImmerleet votest were not reported by the Licensee. i there are no erantee feel cycle f 8Cilities in the ylcinity of the plant, the total body er ergen dose to the seelese total Sese (areal i esposed ladividual use lees than the see of the numerleet walees of the ehele body, ergen. and alt detes given en thefir Dese ta0CFA190) of 40CfR190 125 ares total body. T5 area thyreld, and 25 mrom any other ergen). These tables Indicate deoes are
- ale dose selees were tehen free the Licensee's fable I f or Jonsory-June and Table VI-A for July.4ecember.The Licensee's fehle VI-E which glees third guerter air do
- guarterly seelsen doses to an ladividual."eteness errors Indicated by the fact that the alt deses reported are about two orders of magnitude lower than the total body and s l
"Value laten free the Licensee's fable 1 of the Januar Table VI A of the July-December r The Licensee else reports organdosesduetogaseeseeffluentsformiscellaneousf-Jenereportandocalles. pathways,andladividualsenagearterlyTrt. sis. n A 4 g O ct l l w' O 4 4 9
9 k O i l l e 9 b f e t t I
0 o I i APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND LIC MSEE-REPORTED REStHTS I l t l q l ~ } l i i PRANKUN RESEARCH CENTER DMSION OF ARVIN/ CAL 5 PAN I 20tts & RACE STREET 5.PMILADELPHIA,PA 19103 .i (,
I a TER-C5506-657 The conduct of the Licensee's radiological environmental monitoring program, as reported in the Licensee's Annual Radiological Report is summarized in this Appendix. ,f Rancho Seco Nuclear Generating Station consists of a single pressurized water reactor (PWR). The plant is located about 20 miles southeast of Sacramento, California. The main condenser cooling water system operates in a i closed-cycle mode (with cooling towers). Nater for the system is taken from l4 the South Folsom Canal and blowdown from the cooling towers is discharged to Clay Creek, which intersects Hadselville Creek 3.0 jun downstream from the plant: Hadselville Creek water drains to Laguna Creek at a point some 6.5 km l 1i from the plant outfall. Laguna Creek flows to the Constseenes River at a point near Twin Cities road between Interstate 5 and State Highway 99 (about 20 km f from the plant). The Consumenes River flows into the upper end of San Paolo Bay and thence out the Golden Gate. The radiological environmental monitoring program provides measurements of direct radiation and of radioactive materials in those exposure pathways and of those radionuclides which lead to the highest potential radiation exposures to individuals as a result of plant operation. The program thereby supplements the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation.are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. 1 The program is sununarized in Table 2-2 of the text of this report. I Figures C-1, C-2, and C-3 show the sampling locations of the environmental monitoring program. Program details and compilations of the results of the program for 1983 and 1984 are shown in Tables C-1, C-2, and C-3. The NRC monitored direct (ambient) radiation in the environs of Rancho Seco Station during 1984. Locations of the monitors (TLDs) used are shown in Table C-4 and also in Figure C-4. The monitoring programs conducted by the l Licensee and by the NRC were similar. Both programs used several monitors near the site boundary and other monitors distributed at distances up to about 20 miles. There were 62 indicator locations in the Licensee's program and 27 in the NRC's program. The Licensee classified one location 23 miles C-1
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Mp;7 .,. g.r g - -:. General Environmental Sample Locations for Rancho Seco Figure C-1. Station (Reproduced from Map 4.5A of the Licensee's " Environmental Monitoring Manual," (AP.307), Rev. 1, April 24, 1985) C-2 ,e-rw-,---n --r .m .,-,-,--,-.----,---w,.--.,-o =..,--,m.,n-------
,.6 a TER-C5506-657 l ,(. s o y a t Im k uh 0 S 'j l( e"~i v l E t 3 t! u j i b,j \\ 34 t V. J / \\ 3 1,,c' ha id 4, s 1 l y i ( 1 t 'i )5 9 ~q % g, u'f / '. ~ ^ ^.i f p-f#~s i, N +"**} hop ' /, r\\-~ --'I 4, h \\ <e f, jj ) a u.- h' t.. M g 7,3 e _n /,e ~ k{k T.p % i N c, ,s_ s r a 'T ' 'f 3 s, 3 i \\ \\4 .I s .s,.,\\._f, / ( \\68 j,, > o ( ( ,.i',,5 , l c ~..e }....... ti.1 c1,.,d n s y/ \\ ^]- J } 'Q I, ~ '...,. 7 - ' 2. ~ I i <.,. ...A l .VA / I N j.i % /h\\ q 'QJ. f. \\ rg o -J' Figure C-2. Environmental TLD W ations Within 5 Miles of Rancho Seco f Station [ Reproduced from Map 4.5B of the Licensee's (, gJ I " Environmental Monitoring Manual," (AP.307), Rev. 1, April 't 24, 1985) 5 MIL E II AltlVS V f r f C-3
m.. g . p A. g,o f g s. TER-C5506-657 " ' ~ j{ ~ j,\\ L'"j a'sa'iri % \\ ?S w ftA8eciso COAOoVA LAVAOSE n 1 - g P b.3 h j$ ...v.* a. . Loo ,u acaoaa inA I} } [g ',-[ 69 .rtone. [ PLVe80Utse e M s I \\ 67
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"'f' 0 g- .\\ es .C Nwm.M.V.d-\\ ,IFigureC-3. Envirormental TLD Locations from 5 to 20 Miles from Rancho m% Seco Station [ Reproduced fre Map 4.5C of the Licensee's " Environmental Monitoring Manual," (AP.307), hv.1, April
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Ju b, TER-C5506-657 's, .NRC TLD DOSES FOR RANCHO SECO ARER (mR oer 90 ciavs ) I t Is 13
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t - I'igure C-4. Environmental TLD Locations from 5 to 20 Miles from Rancho ~ Seco Station [ Reproduced from Map 4.5C of the Licensee's " Environmental Monitoring Manual," (AP.307), Rev. 1, April 24, 1985) f,' .I I l I:(d,
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4 TER-C5506-657 Table C-1. Description of Radiological Environmental Sam le Locations for the Rancho Seco Nuclear Generating Station a) (Taken from Table 10 of the Licensee's 1984 Semiannual Effluent Release Report) Environmental Description tocation Map Number __pample Type of Location Dist. (mi) Sector 2 Air Samples Miller Residence 7 NW 16 Air Samples SMUD Headquarters 23' NW 14 Air Samples Imdi 18 SSW 6 Air Samples Tchay Substation 1 SSW 10 Air Samples Ione 9 E ~ 17 Air Samples Carbondale 8 NE 8 Air Samples Fish Hatchery 11 SSE g 1 Air Samples Rancho Seco Onsite Onsite 1 Runoff Water Site Boundary 0.3 WSW 8 Surface Water Camanche Reservior 11 SW 4 Surface Water Folsom South Canal 3 W 1 Surface Water Site Reservoir 0.3 ESE j i g 1 Drinking Waterb Site Drinking Fountain Onsite Onsite 1 Well Waterb Rancho Seco Site Onsite Onsite 11 Well Waterb Clay Area 2.1 WSW 1 Well Waterb P.eservoir Well 1.25 E 6 Well Waterb Clay Cattle Feedlot 0.25 S l 1 Mud and Silt Site Reserroir 1.5 ESE 1 Mud and Silt site Boundary 0.3 WSW 3 Mud and Silt Madeiros Dairy 7 KW 9 Mud and Silt Angelo Dairy 10 SW 12 Mud and Silt Warmordam Dairy 9 W 1 Mud and Silt Marciel Ranch 1 E i 1 Fish Site Reservoir 1.5 ESE ~ 1 Fish Site Boundary 0.3 WSW i 4 Fish Hadseville Creek 3 W l near Folsom S Canal 1 11 Human Vegetation Clay Station Area 13 WSW 10 Human Vegetation Ione Area 10 E 7 Human Vegetation Clements Area 12 S 5 Human Vegetation Sloughouse Area 11 N b Warnerdam Dairy 9 SW 12 Pasturage b 3 Pasturage Madeiros Dairy 7 NW b Angelo Dairy 10 W 9 Pasturage 1 Pasturageb Marcial Dairy 1 E b 1 Pasturage Pasture irrigated by 0.5 W l Clay Creek C-6 l s _. - _ _ _ ~, - _. _,. _ _ _ _ -,
TER-C5506-657 Table C-1. (Cont.) I Environmental Description Location Map Number Sample Type of Location Dist. (mi) Sector 1 TLD N. Perimeter Fence N E f 2 TLD E. Perimeter Fence l 3 TLD W. Perimeter Fence W SW 4 TLD S.W. Perimeter Fence 5 TLD 5.E. Perimeter Fence SE 6 TLD Vistors Center 7 TLD Route 104 Entrance 6 NW 8 TLD l 9 TLD Sacramento 22 NE 8 10 TLD Lodi 17 SW 0.25 S 11 TLD 12 TLD Ione 11 E 13 TLD Milk Station 10 W 14 TLD Galt 11 SW 15 TLD Camanche Reservoir 11 SE 16 TLD Clay 0.5 W 17 TLD Milk Station 9 SW 8 NE 18 TLD l 19 TLD 1 SE 1.5 WSW 20 TLD 1.7 SW 21 TLD 1.8 S 22 TLD 1.8 SSW 23 TLD 1.8 SSE 24 TLD 3.8 SW 25 TLD 3.9 SSW 26 TLD 3.6 S 27 TLD 3.7 SSE 28 TLD 4.2 S 29 TLD 30 TLD Herald Fire Depart-7.4 WSW ment 3.7 W 31 TLD 4.8 WNW 3 32 TLD 3.8 WSW 33 TLD 3.8 NW 34 TLD 1.9 W 35 TLD 1.6 WNW 36 TLD 1.9 NW 37 TLD l] 38 TLD 1.6 NNW 1.5 NNE l 39 TLD 1.5 N 40 TLD 2.0 NE 41 TLD 4.4 SE 42 TLD 1.6 SE 43 TLD 1.4 E 44 TLD 1.4 ESE 45 TLD 1.3 DJE 46 TLD C-7 ~
TER-C5506-657 Table C-1. (Cont.) 8 Environmental Description Location Map Number Sample Type of Location Dist. (mi) Sector 47 TLDb 3 NE 48 TLDb 3.5 ENE 49 TLDb 3.1 E 50 TLDb 3.5 ESE 51 TLDb Ione, Preston School 11 E of Industry 52 TLDb Jackson Civic Center 19 E 53 TLDb Camanche Reservior 11 SE i 54 TLDb Clements 10 S 55 TLDb Across from Dillard 8 WNW School g 56 TLDb 4.6 NNW 57 TLDb 7.6 N 58 TLDb 6.6 NNE 59 TLDb Sloughouse P.O. 11.3 NNW l 60 TLDb Entrance to Rancho 8 Murietta 10.6 N 61 TLDb Elk Grove Cemetary 13 WNW 62 TLDb Galt 11 SW 63 TLDb 1 E a. Information taken from Licensee's AP.307-1, " Environmental Monitoring, l Description, Scheduling, and Record Keeping," April 24, 1985. More locations for drinking water, well water, mud and silt, fish, and pasturage sampling are described than are required by the technical specifications. The technical specifications require four milk sampling locations, but none are specified in AP.307-1. b. Not required by technical specifications. c. Direction is wrong in Licensee's table (should be NW). l I, C-8
.a 4 i fable C-2, testlegNptNTAL seStal0wl(At SWittigatus peggense tes campe SECS Et98!8ATINE STATION Fee TME Vtas 1983 I ladtrator Letellen olth Centrol I s --a lame Ntahmat " -1 Banaa tumelana leg. of se,dlem.er Pettasey .Ippe.and Iotel .Lemer tielt m.a*trgec.le t n,
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- v. Perleeter 24.5 (4/41 16.0 (4/4)
Locations Post-int Esposere 149 f 17.2 4169/169) Ist of Site 22.4 (4/4) See above Locetleas 2. Ale 00eut Portle 1stes Gross Sete 4989 0.002 8.189 test /491) Site t (leael 0.913 (4/4) lesae 4 Ai,ne nf 0.se$ <tte n.ae I stone Gemme Spec 32 i etts 4 t 1 (1 ledlae I-131 419 0.004 0.0016 (93/N) Site A tallier 6.0038 (2/4) 8 0.003-0.905 sesidencel 5.001-4.985 lesae 7 mi (NW) ] 3. tatifeggest Serface talver) Gross este M 9 0.5 9.48 15/12) Site Deservelr 3.9 ft/4) usae water (pCl/L3 (Sespeaded) 0.21-8.9 0.3 el (ESE) 9.8-1.5 Grose Sete 369 8.S 5.09 1 9/92) Site seserwele 4.01 (3/49 scene teissolved) 0.3-l.2 0.3 el (tSt) 8.8-1.2 08-3 369 250 ettt lesae I-118 369 0.5 ette Ianne evneff water Gross Sete M9 0.5 9.23 13/4) Site Besadery 9.23 (3/4) leone 4 (pCl/tl ISeepended) 9.8-2.9 5.3 el (tr$es) 3.3-2.8 Grose Sete M9 9.5 1.75 14/49 Site Boondary 1.75 (4/4) lesae (Distelved) 5.2-5.5 0.3 el (W5es) 0.2-5.5 i N-3 M9 250 677 (t/49 Site ge adery 6?? (1/4) lesae 677 4 77 8.3 el twSW) 677 - g scene N t-931 M9 9.5 ette A = w O I m I I ew l M e 1 4
0... ~~- fehle C-2. (Ceurf.) Indicator tocetten with Centre) 1 l a-mesana - Islahman - -1 saman e -metema tardlem er Pethuey fppe end fetet Lower (left IIe of gg,,,; gggg g, pg,,,b gp,g,gt pg,,,b gg,p,gt gg g,gg, bgg,,(,gt Sameted quelt of Itumeer of anaty-et Det tten Iteen Jeg_ ^t ama Perfarmed ,,,131ggtLisa L Ramme,,,,,, _ _ Ramme _ Ilmamurammetad 1. teette9M (Cent.l Ground fuetil Gross Sete 14 S.S 2.29 (14/96) $lte urtt F.08 (4/48 sesne Water (pCl/tl I.5-1.5 1 2.0-1.4 53 16 250 ette Isone IIone I t-139 16 0.5 <ttB Orlantag water h (pCl/t) Greas Bete Ik 9.5 2.92 (4/4) Site wells 2.82 84/4) tenne h taene E3 12 250 ette I-831 12h 9.5 ettt stone nh stud and $llt Grote Sete IF 0.95 0.36 (87/t73 Site eeundary 9.52 (31/t33 scene O fpCl/g. drpt 2.7-17.3 S.3 at twSW) 2.9-17.3 Samme Spot 17 i Cs-1M 9.083 1.50 (14/97) $lte Soundary 1.7 (13/131 stone Co-437 0.042 3.52 (IS/IP) Some 4.95 (11/t31 IIene I O.07-6.7 1.0-6.7 Co-95 0.027 1.99 (11/17) Same t.99 493/131 leone 8.1-5.9 0.8-5.9 b 54 0.956 S.Il (t3/tfl Site soundary I.18 (13/13) Inone 0.3-4.5 8.3 el (W5W) 0.34.5 Co-40 0.960 3.St (13/97) Some 3.81 (83/t3) leone 5.9-19.5 0.9-19.5 t-131 0.019 f.2 (t/lig Some 1.2 (t/13) leone 1.2. - 1.2. - N
- 0. 16 16./97) 8.17.(.5./ 9 3) g Same leone 4 95 9.934
.8-0.i 0. A EfB O (n 5 (M (P w e e l l
l L t fable C-2. (CONT.) n.,. tee.l Cen Indicator Lacellen erlth seydlem oc pathuey type eat foto) Leuer tielt telht ammmat samma es.. n,namme Iso. of amane(,g,gt gg,,,b g g,p, gt ggg g,gg, b gg bgg,,g,gt lemme Slttente feeen Semeled (Smit of laumber of Analy-of totettlen feeen amm9s _ Ihasarmesatad !qean-t1. ama earfamma _.113 Sam 9e aeeaanaaeni 8 3. unitettent (Cent.l fr-95 0.941 .12 11/IP) Same 0.12 (1/11) leone 9.12- - 9.12- - A1 ee Dete less 12 9.92 4.36 (12/12) Site Deendary 9.M (12/12) stone 9 E-49 9.9-19.3 9.3 el (W5W) 9.9-19.3 i Dete (It-49) 12 9.991 7.79 t12/82) Some 7.79 (12/12) eeone 1 0.9-i7.9 9.9-17.9 Sr-99 82 9.91 0.29 (t/lf) Same 49.29 (t#t2) leone 9.29- - 9.29- - l n s.ms. S,et it I i 1 [ Co-99 9.969 19.9 199/12) Same 19.5 (10/12) leone 3.2-59.7 3.2-$9.7 i the-54 0.056 11.7 89/12) Same 11.7 (9/12) Itone 2.3-33.4 2.3-3I.4 I Cs-137 9.942 12.9 til/12) Some 12.9 til/12) leone 2.7-$9.5 2.7-59.5 Co-134 0.983 2.68 09/12) Site Dosadery 7.61 (9/12) IIsme 1.5-25.7 9.3 ml (W5W) 1.5-25.7 Co-57 9.999 1.0 (2/t?) Same 1.9 (2/12) leone 9.I-3.5 9.1-3.5 4 95 9.934 4.2 13/12) Same 4.2 (3/12) stone 2.0-4.3 2.0-6.1 Co-SS 9.27 15.S 49/12) Same IS.S 19/12) leone 2.7-51.9 2.7-51.9 I-131 0.999 II.2 II/12) Same II.2 ft/12) stone g ii.2- - it.2- - g A us (Je Om 1m tJe 9
- e
w.. 1 i fatte C-2. (CONT.) i ? Inditeter tecellen with-- - u namma Centret j Mg telg est - -1 perdlem er Pethuey type and fotel teuer tielt Iss. of tgry,g,ge geone: Gestante seront gr g,ge ge,,,b g r,p, gt em sped. Someted ( > lt et sesseer of analy-of Getettlee 8oren n ana emeta - me lle* Jirectlant A A Ihanarmin8 1 i 4 IseECSIIGee i sollt EpCl/t) 1-131 2000 0.5 0.00 (6/I6) tenettel Solry 0.1 (t/4) leone 0.05-0.0 1.0 el (t) 9.9. - l Se-90 400 1.0 1.07 (88/96) Some I.52 (4/41 leone 0.4-3.2 0.5-3.2 I Fish EpCl/. dryl Dete fees 0 0.02 0.05 (t/0) Site seeeevele 0.5 (t/0) leone 0 u-se 0.5- - I.5 el iESt3 0.5- - Sete (E-409 0 0.001 0.29 40/09 Some 9.29 (0/0) Isene 3.4.14.0 3.4-14.0 $r-90 0 0.03 0.99 (2/0) Some 10.10 12/0) None g 0.5-0.9 0.I-0.9 h anlest Sete less 460 0.02 0.99 (10/169 Igorclel Solry I.24 (3/4) leone DJ vegetetten E-40 0.44-9.4 1.0 el (t) 3.97-l.4 (PCl/0. dry) l Bete (E-40) 400 0.001 10.5 (16/16) feedleree Balry 25.7 (t/III leone 7.0 16.y 7 el tesft 25.7 - l Sr-90 400 0.03 0.064 (7/96) Serges Delry 0.005(2/3)I leone 9.04-0.50 -(-) 0.07-0.it t I temmen vege-Sete fees 0 0.02 0 (9/03 Isene tetten R-40 l (ptt/0. dry) { Oote (R-40) 0 0.009 24.6 (0/0) Clemente area 30.5 (2/2) leone i 96-33 12 el iSI 20-33 1 totbit Fleek Bete lese SS 0.02 0 (0/4) leone IpCI/g. dry) E-40 Sete (R-de) et 0.001 4.30 (4/4) Sanche Sete Site 4.20 (4/4) leone 2.2-6.2 2.2-6.2 Setbit Feuer Sr-90 et 0.01 0.59 (1/4) Some 0.59 (1/49 leone i (pCS/g. wet) 0.4-0.06 0.4-0.06 g l A U1 O Os Ion W =J e e* 4 I
j Table C-2. (CONT.I a. teel Cen Inditeter Lacetten ulth el a tocatless Mlahmet ^ -1 Ile. of seedlem ee Pethey type and fetet temer tielt irgec.lc le,e,b gy,p,ge nu opts. d seeme: Olstence larant b(freg.gc sameted tunit et shamer of analy-er oetectlen sneen men parfa - =d j_ _ seirectlaal A_ mamp _ h amnatn jan-r-e n 4 IstEtlittu (COPT.) leone Bahtit Thyreld t-131 89 9.95 S (0/dl w 1 n 1 I N tas All Ltte given in the envleemmentet eenstering report were egual L49
- Lower Llett of Detectlen es defInod in the Licensee's techalcol spectftcettene.Ifled in the Licensee's techalcol speelficellens, where oppilgeblo ll.e.. for red I
- e.
l to or less then emeleum Ltts itDs are given la the techalce specificettentl. i sepen and range are based en detectable seesurements only. detectable -ts to tete) asser of analyses. b.
- free." e Retle of number of onelyses glelThe Licensee is committed to report any red settletty levels la en enetrommetal sempting medlem eeceeding the rep I
c. f d. fehle udten everaged over any guerter. Itene of these fewels were encoeded. Investigstlen showed the high Second guerter value from too locetten et the leerth Perleeter fence (58.4 area /gtrl le entladed from dote shoun here. i e. reading to be related to n-rey laspectles telag perfereed in that generet eres. l f. last defined. Therefore, mean tractlen, and range shown are for the guerterly everage eatees. Licensee reported only geerterly everage by locetten. g. h. Values thans are overages of amittple semples. .s a Om 1m 139 4 e
~~.- - ~ +.. ~ - - - ~* -~ - ~ Table C-3. turlegsstufat Ba010t0GICAt IsottettNG p00GBAft F00 SANDS SECO GENESAflIIG STAf tell F00 flE TEAS 1984 Indicator tocation eith Centrol l a m mataan w%t - -- s-antana enselee er Pathmey type and fetal teuer tielt Ite of bgg,,g,yc Sampled genet es shmeer of Analy. of Detectlen teeen b gg,,,gc gg,,,6 g g,p,y c set Optd. usme: Bestance steen g ..teessuremmat t. .aan Perlaceed J_ telreettant samen _ __ Sange _ Ilmaserammetn8 i 9. SistCf 848848 E010 tilest les/qtel Origleal reposere 76' e 16.2 (76/76) 93 W. Perleeter 29.4 84/4) 16.2 (4/4) totettens 13.6-30.5 feace: - ful 22.9-30.5 14.9-17.1 1 Post-iset reposere 167 e 17.7 4167/967)
- 49. IIt of $lte 24.2 (4/49 See above tocatleas 13.1-20.0 2.0 el tut) 80.I-20.0 2.
Ata00en Partical tes Gross Deta 403' O.002 0.0140 (N/NI Site F 0.0110 lenne 1 Ipti/m ) 0.000-0.020 0at(W) Alpha 32I e ett0 Iteme = = radla. I-131 4039' O.004 0.001: eiS/NI site n 0.0007 (3/49 Q tpCl/e ) 0.001-0.022 (Onsliel 0.001.022 Items l .. warte00sn Serface telveel tross Sete MI 0.5 0.30 (5/123 Commache Bes. 0.0 (1/43 liene j water spCt/11 45=speaded) 0.2-0.0 Il e4 (Sul G.0 tross Sete M ' O.S 0.01 (82/12) Site Geservelr 0.95 (4/4) leone j telssolved) 0.2-I.5 0.3ml(EMI 0.5-4.4 16-3 MI 250 101 (1/92) Site Geservelr ISI (1/4) Itene ISI P3elitMI tel I-133 M' O.S 0.6 (1/92) Camenche Ges. 0.6 11/128 samme Il et (5et) 0.6 Someff water Grose Beta 28' O.S l.15 (4/49 Site Bosadert t.lS (4/43 Itene tPC6/t i ESospendeel 0.0-I.9 0.0 1.9 } I 0.5 2.90 (4/43 Site Soundary l Grote. Beta 21 (Siss i.edt i..-3.2 2.50 44/4) Itsne i.4-3.2 j n-3 2i' 250 .ite m.ne g 3-1,, 21, G., .tto u. L/l Om i De L.Fl M e i
.-o 4 l Table C-3. (C018T. ) Indicator Location with Castrol n, anaam anseheat --- -1 n-, men a me, et perdlem er Potensey 7ppe and fetal tause Llett b gr,g,ge ge,,,bgy,p,ge un tytd. tgy,,(,gc Itemo: Distance tenenaamp(_ Sampled i m it of laumber of Analy-of Detectlen 9tren 8 aansa _ hammeta -1 ama earfm-na J_ amans _ aaaeneaeami 3. uniteesent (Coat.I I Ground twelll Gross Sete 16 0.5 9.74 (15/16) Cley Cattle Co. 2.65 14/4) Ilume I water (ptt/t) 0.5-3.7 S.25 mi (S) 8.8-3.7 1 stone 16-3 16 250 ettS stone t-131 16 0.5 etLD Deleting water s pCl/t) Gross Sete 129 9.5 2.02 84/41 Site Deleting 2.82 14/4) stone O.F.3.0 Fountalas S.7-3.9 Onstte n. -3 i29 25. .u. n Ieone M t-131 129 9.5 <ttB 84 8 and Sllt Gross Sete 17 0.95 15.5 117/17) Site Soundary 19.0 113/13) Iemme spClig, dry) 1.5-78 1.6-75 l Gamme Spot 17 Cs-1M 8.813 19.2 (11/17) Site Soundary 19.2 (11/139 IIene 1.5-53.2 0.3 el twsul I.5-53.2 J l Cs-137 0.042 30.9 412/173 Same 42.4 (11/131 samme 1 0.I 93.4 3.6-93.4 ) Co-54 0.027 4.50 (11/t7) Some 4.50 (11/139 lemme ten-54 S.9% 0.M tit /tfl Site Boundary 9.M til/131 IIene 0.1-3.8 0.3 el twsul 8.t-3.5 i i Co-44 0.960 5.M 191/173 Same 5.M (11/131 leone 1 e.e-Is.4 e.s-te.4 84 Some 4.38 (4/135 sanne 1.30.(.4/I73 l t-131 0.919 g 2 ..-i.2 6 5e . 22 (2/13, no ..n.it,ifi -95 ...u v ..N.4 ..N .4 us Om Im 1,19 4 4 e i a
TER-C5506-657 4 l .i, DE -i u. e-J 31 Iiii i i i i i i i 1 -1 6 2
- =
=
= = 0 c a g = c -e~s:.5 Bs c
- c. c g,1 z' 3: =g :.
.:4 s4 m z4,.:~ v _i.2. . ~~.7 a.f. v4 4. s: s~ .. -, a-e~ h I sj i1 8 31 af I
- f f
f_ -j ' a! ..-.=.=.:_- = .= .= .= l E
- n. e:n. =n.
- n +E E
- n +E E
E E z a e e m. 3 e. + 3 + e O 2. t t. 3 2 5j g = s< 2 3 3 2 E C 21
- l C-
" R ..O g 2 03 0' -O -0 -2 g 0 8 35
- 4 A ~4
- J *!J *:2 TI "as *:d "es '.1
- ~2 4
A I 1
- ss a
es v.: s.: se = s =s 3.: l 5I 0 E% 3 2 3 3 I I I E I I E i gp s e e e e e e e e e e s l L = = 5o1 ~ ~.j. KJ 9 3 i-2 2 = IT 4 I I E ~
- 4.,I II 2
b: gF a l=1 I 3J 1 p, a s .j N I i 9 6 e C-16 I 9
m... 4 Tatte C-3. (Ceuf.)
- n...rol Cent Indicator tecellen with i
n-meinn. 9 ee - q -- - ser4I m er Pethuey type one fotel Lowe tielt pas, of page,; gggg,,,, ge,,,b gg,g,gt pg,,,b gg,,ge Im Epte, d bgg,,g,gt g ) Sampled lifelt of Itumher es Amely-of estettlee DIsen __ etreetlant samme _ Emage _ hammeh q yma- "I san Parfarmed__ L L Ba_ m_ g l 4 ImEf5ften Mile Idl/t) I-838 20e' e.it 17/16) teneuerdam solry: e.t$ (2/4) tiene e.8-e.2 9 on (SW) 0.I-8.2 stortlet selry: 0.se (3/43 samme I el til 3.5-e.t St-90 de' t.e e.52 lett6) storslet selry e.70 83/43 IIsme e.2-1.2 i el til e.3-1.2 risk sete lese e 0.e2 s.se (4/el Site seservelr s.de (4/el scene spCt/s ery) s-de 0.1-8.e 1.5 el Itsu e.t-e.e O sets ts-det e
- e. Set 18.6 40/03 Same 30.6 10/81 stone e.9-83.7 0.9-13.7 Y'
Sr-9e 9 e.e3 e.t st/93 Site seeervetr e.1 ft/el ensne e.t-. s.5 et st50 e.t.. Anleel vege-este tese 4B' O.e2 e.Fe (0/163 Angelo solry 1.15 (2/4) Itene i tation R-de e.3 1.6 le el (SWI e.7-l.6 IPCl/g. ery) eets (R-4el 40'
- e. set 16.7 (16/163 senrelet seach 21.4 (16/96) eene 11.e-39.9 9 et til 12.6 39.7 Sr-90 de' s.03 0.12 (II/16)
Angelo solry 0.15 (3/4) leone It el (Sul e.1-e.2 temmen Wege-sete less e 0.e2 <tte IImme totien E-40 spCl/e.oryl 1 eete 18-481 s' O. Set 20.6 1e/03 Clay Area 39 12/21 IIene l' 96.-45 83 e6 tw5t#1 33-45 i n.e.ii eie.n
- t. ies.
s' O.e2 4.4 ti/4 e.n e Se<. Sii. 4.4 ti/4 e.no 4.4- - E-40 4.4-. xy eeta (R-del O' O est 6.0 (4/43 Same 6.0 (4/43 Isone g 4.9-e,t 4.9-e.I a. Om 0 i m I t/I w e
- e i
l l
' i': i
- i
=l APPENDIX D EVALUATION OF LICENSEE-REPORTED REVISIONS TO ODCM, PCP, AND RADWASTE TREATMENT SYSTEMS l. l I I ll F i FRANKUN RESEARCH CENTER DMSION OF ARVIN/CALSPAN 20th & RACE STREETS. PHILADELPHIA.PA 19103
a-TER-C5506-65i D.1. EVALUATION OF LIC MSEE-REPORT NS TO 00CM The Licensee has made seversi changes (R Radioactive Effluent Release Reports
- i ev. 3),
in the Semiannual that was submitted by the Licensee i through December 31, 1985, to the CDCM These changes (Rev. 3) have been in n October 1982 and approv CDCN and reviewed as a whole. The result of the evaluation a stand-alone document, and is given in th I e to be e following attachment to Appendix D.2 EVALUATION OF LICDISEE-REPORTED IONS TO PCP The Licensee has made several chan Radioactive Effluent Release Report
- ges (Rev.1), in the Semiannual that was submitted by the Licensee i through December s
31, 1985, to the PCP Subsequent to the issuance of the PCPn October 198 i for solidifying the liquid waste , the Licensee contracted a vendor operating under a new PCP that supersedes thConsequently, th operating processes are administrative 1y e 1979 version. The vendor's Licensee-submitted changes to the PCP controlled by procedures. The Despite these changes made by the Liare related to these [ by NRC to omit the review of these ch censee, the reviewer was instructed the process of changing vendors anges, since the Licensee is currently i The PCP is thus not reviewed in thi, wh I rewrite of the PCP. n s report. t D.3. EVALUATION OF CHANGES TO THE RADWA a EATNENT SYSTES The Licensee's RETS require major ch { solid redwaste treatment systems to be repanges to the liquid, ga Analysis Report (FSAR) updates. orted in the annual Final Safety \\ l ~
- The Licerisee reported the changes to th jl Radiological Report.
I
- The Licensee's ODCM was approved by NRC Di i ie CDC (DSI) on February 9,1985 j
v s on of Systems Integration \\ of Licensing (DL) is yet to be issued , but the final approval letter from the Divi i i s on \\ D-1
TER-C5506-657 The Licensee has made updates to the radwaste treatment systems through Amendment No. 4 as of July 1, 1986 in the Licensee's updated FSAR. The updates include an installation of a new dry waste compactor in the auxiliary building waste solidification room. The new compactor has a higher volume reduction capability, and the original compactor remains as a backup. These updates have been reviewed and are determined to meet the NRC guidelines. t 9 e t I f a l D-2
- 1 a
.s 3 i SUPPLDENT .l TO APPENDIX D jr EVALUATION OF LICENSEE-REPORTED REVISIONS TO THE ODCM Il
- l l
l
- t I
I i f l l l 3 FRANKUN RESEARCH CENTER DMSION OF AWIN/CALSPAN I 20th & EACE STREET 1, PHILADELPHIA.PA 19103 1
I d a TER-C5506-657 O 1 1. DrtRODUCTION I 1 1 1.1 PURPOSE OF REVIEW f The purpose of this document is to review and evaluate revisions or updates made to the Rancho Seco Plant Offsite Dose Calculation Manual (00CM) through December 31, 1985, as reported in the Licensee's Semiannual Radioactive Effluent Release Reports. These changes update the Licensee's (IOt from the one originally submitted in October 1982 [1] and subsequently approved by NRC by letter dated February 9, 1985 [2]. The ODCM is a supplementary document for implementing the Radiological Effluent Technical Specifications (RETS) in compliance with 10CFR50, Appendix I requirements [3]. d:l 1.2 SCOPE OF REVIEW As specified in NUREG-0472 [4] and NUREG-0473 [5), the ODCM is to be developed by the Licensee to document the methodology and approaches used to calculate offsite doses and maintain the operability of the effluent system. As a minimum, the ODCM should provide equations and methodology for the l following topics: alars and trip setpoint on affluent instrumentation o liquid effluent concentration in unrestricted areas o gaseous effluent dose rate at or beyond the site boundary o j liquid and gaseous effluent dose contributions o l liquid and gaseous effluent dose projections. l o In addition, the ODCM should contain flow diagrams, consistent with the systems being used at the station, defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management f' systems. A description and the location of samples in support of the environmental monitoring program are also needed in the (BCM. i 1.3 PLANT-SPECIFIC BACKGROUND On behalf of the Rancho Seco Nuclear Generating Station, the Sacramento i Municipal Utility Distric (SMUD) submitted changes to the existing ODCM in the lII:I D-4 II ~,..,
TER-C5506-657 Annual Radiological Report of 1984 [6] and in the Semiannual Radioactive Effluent Release Reports of 1985 [7, 8] since the submittal of the original l ODCM. The Licensee's RETS reports and the changes of the CDCM were transmitted to an independent review team at the Franklin Research Center for review. The review was subsequently conducted by FRC, and the results and conclusions of the CDCM evaluation are presented in Section 3 and 4 of this document. l l l e I I i i e f l i D-5 I
1 o TER-C5506-657 1 2. REVIEW CRITERIA I I Review criteria for the (IICM were provided by the NRC in three documents: NUREG-0472 [4], RETS for PWRs NUREG-0473 [5], RETS for ENRs NUREG-0133 [11), Preparation of RETS for Nuclear Power Plants. In the ODCM review, the following NRC guidelines are used: " General Contents of the Offsite Dose Calculation Manual," Revision 1 [9], and NUREG-0133 [10). Regulatory Guide 1.109 [11] also provides technical guidance' for the review. The ODCM format is left to the Licensee and may be simplified
- i by tables and grid printouts.
i l1 ti' l i i l t i f l 'I
- I ll D-6
i TER-C5506-657 3. EVALUATION I The Licensee has generally followed the methodology of NUREG-0133 [10] to determine the alarm and trip setpoint for the only liquid effluent monitor at A the regenerate hold-up tanks (RHUT), to ensure that the maximum permissible concentrations (NPC), as specified in 10CFR20, will not be exceeded by discharges from the NHUTs. Releases from RHUTs are normally made to a j retention basin prior to being released offsite. Since only one tank can be l released at a time, no provision is required to adjust the setpoint for simultaneous releases. Several discrepancies, however, are found in the Licensee's approach to the setpoint calculations; they are listed below: o Licensee's Equation (2.1-2) should be i Ct = (F + f) 1 II Si I i( MPCi, rather than: i s Ct = (F + f) I(SMPC) I 1 i f i 1 o The Licensee's minimum dilution flow rate (F = 800 gpm) seems small, e compared with the maximum acceptable flow rate (f = 300 gpe). The l Licensee should also state the nominal flow rates for the release. o Since the RHtJr monitor setpoints are based on a default radionuclide i mix, Section 2.1.1.1, a comparison should be made between prerelease isotopic analysis and the default six to ensure the setpoint is i conservative. This is particularly so as the 1984 releases were a disproportionally large amount. Equatign (2.1-7) does not appear to have considered the requirement o [ C __,J i 1 that 4 i i i MPCi, Equation (2.1-7) should be equivalent to Equation (2.1-4) except that the nuclides are measured and are not the default mix. I o In Equation (2.1-7), it is not clear why the high alarm setpoint is increased by the factor 1.25. A low or intermediate alarm may justify a setpoint increase to prevent spurious alarms, but the high alarm setpoint should not be increased. I D-7
); a TER-C5506-657 ,a o The detector efficiencies listed in Table 2.1-1 must be current l* values and specific for the RHUT monitor detector in use. The data 'I in Table 2.1-1 appear to be for a detector system that may or may not be in use. l i For gaseous setpoint calculations, the Licensee has also generally followed the methodology of MUREG-0133. To address the possibility of simultaneous releases, the Licensee has considered 20% release from the auxiliary building vent and 80% from the reactor building vent. Several discrepancies are however, found in the Licensee's approach: The Licensee has not specifically committed to using the highest o annual average (X/Q) values and thus the conservatism is not ensured. In Section 3.2.1.1, Table 3.2-1 should be referenced instead of Table o 3.1-1. ll The justification for the 1.25 correction factor in Equations o )j (3.2-8), (3.2-9), and (3.2-10) is not clear. Decreasing the flowrate in Equations (3.2-8) and (3.2-9) is acceptable to ensure the 10CFR20 limits are not exceeded. However, increasing the high alarm setpoint by 1.25 in Equation (3.2-10) is not acceptable as the monitor's ,j response is independent of flow.
- 3 o
The detector efficiencies listed in Table 3.2-2 must be currect values and specific to the detector system in use. It is not clear how a single set of values is applicable to several monitors as indicated in the footnotes to Table 3.2-2. il'i The Licensee demonstrated the method of calculating the radioactive !1 liquid concentration by describing in the CDCM the means of collecting and analyzing representative samples prior to and after releasing liquid effluents lj into the circulating water discharge. The method provides for added assurance 3 of compliance with 10CFR20 for liquid effluent releases, and thus satisfies the guidance specified by NUREG-0133, except for the following discrepancies: The Licensee has not explained how the total maximum permissible o concentration (TMPC) is obtained, and has not provided a unit for o Equation (2.1-2)* is incorrect. It should be written as MDF = (MPCF)(R) - R
- Should be Equation (2.2-2), as the Licensee has mistakenly numbered all the equations under Section 2.2.
D-8 ,o -. + - +.,.- - --..---- -,.-_,.,,,- - ,,,__m- __m_ _ _, _ _. - -. - - - -. -
TER-C5506-657 i i instead of i NDF = (NPCF)(R) o The justification for the 1.25 factor in Equation (2.1-1) is not i clear. Decreasing the flowrate will not change the monitor's response to the volume of liquid seen by the detector. An adjustment can be made by multiplying Equation (2.1-4) by 1/1.25 with the justification of decreasing the batch release rate to ensure against i exceeding the 10CFR20 concentration limits. t Methods are also included for showing that dose rates at or beyond the site boundary due to noble gases, iodine-131, tritium, and particulates with half-lives greater than 8 days are in compliance with 10CFR20. In this I calculation, the Licensee has considered effluent releases from the auxiliary building ventilation exhaust and radwaste area exhaust as continuous releases and those from the reactor building punge exhaust and waste gas decay tank exhaust as exhaust purges. The Licensee has considered the child's thyroid as 'the reference receptor. The Licensee has demonstrated that the described methods and relevant ,I parameters have generally followed the approaches provided by NUREG-0133 and Regulatory Guide 1.109 for liquid effluent dose rate calculations. Several discrepancies are found in the Licensee's dose rate calculations: o The Licensee has not committed to using the highest annual (X/Q) values to ensure conservatism. o The Licensee has not addressed the possibilities of simultaneous releases from various release points. o In Section 3.3.2, the definition for Pi$ contains a reference to Table 3.2-1, whereas the reference should be to Table 3.3-1. Evaluation of the essmulative dose is to ensure that the quarterly and annual dose design objectives specified in RETS are not exceeded. For liquid releases, the Licensee has identified the following viable pathways from inges' tion of freshwater fish, freshwater invertebrates, potable water, and irrigated foods. In addition, pathways from shoreline deposits, j swimming, and boating are also considered. In the calculation, the Licensee D-9
4 TER-C5506-657 has used near-field and far-field dilution factors specific to the plant; l other key parameters have generally followed the suggested values given in l Regulatory Guide 1.109. As in the case of dose rate calculation, the Licensee has used the maximally exposed individual as the referenced receptor. To correctly assess the cumulative dose, the Licensee intends to estimate the dose once per 31 days. However, several discrepancies, listed below, were found in the Licensee's approach: The expressions for Irrigated Foods in Section 2.3 contain the factor ll o 1100 and Mp. It is not clear that these factors belong in these expressions since these expressions are similar to Eguation (4) on ,, a page 1.109-3 of Reg. Guide 1.109. The expression for irrigated foods: Milk contains the term o (1-W ATER). However, NATER=1.0 for milk in Table 2.3-4, which zeros out the dose contribution to the milk pathway from cows drinking f contaminated water. Is this a true representation of actual conditions surrounding the plant? l The expression for tritium on page 16 of Section 2.3 is not an o expression for dose, but an expression for the tritium concentration. Additionally, it is not clear that the factors 1100 or Mp belong in this concentration expression as indicated by Eguations (A-14) or (A-16) in Reg. Guide 1.109. Note 1 in the description of variables on page 19 of the submittal t o I states the bioaccumulation factor for cesium in freshwater fish is a site-specific factor of 1400 instead of the 2000 pCi/kg per pCi/ liter .I recommended in Reg. Guide 1.109. lI Table 2.3-1 lists an infant's usage parameter of 0 liter / year for o milk instead of the 300 liter / year recommended in Reg. Guide 1.109. .[ I Table 2.3-1 lists freshwater fish usage factors of 21, 21, and 35 i o kg/ year instead of the 6.9,16, and 21 kg/ year values recoamended in Reg. Guide 1.109 for the child, teenager, and adult, respectively. 9 o Table 2.3-3 does not include a tp value of 24 hours for leafy vegetables for the maximum exposed individual as recommended in Table ,i E-15 of Reg. Guide 1.109. i Table 2.3-3 lists the release holdup and transit time as 72 hours o 'g instead of 24 hours as recommended for th in Table E-15 of Reg.
- l Guide 1.109.
Table 2.3-4 lists the non-irrigated water fraction as 1.0 for milk. o This means there are no milch cows on pastures irrigated with contaminated water. Is this a valid representation? 1 I 'l D-10
i TER-C5506-657 e o The expression on page 24 for the total calculated dose does not include the dose contribution from tritium. i The units in the definition of A j on page 26 should be o i i stem. ft3 instead of aren. sec l Ci Ec Ci f t?. ( o The data in Table 2.3-6 appear to be incorrect. l It is assumed the A13 values are calculated using the following expression: g$ = k' + (U )(BF ) N A g g g s [ where Uw = 0.0 3 k = 1120 g. ft _. y Ci liter sec f = 35 Ig from Table 2.3-1 in the ODCM l U yr i For the case of an adult's total body due to Na-24, this yields: A13 = 1120 "0.0 + (35) (100)]1.7x10-6=6.66meen.g3 Ci sec e i versus 0.131 in Table 2.3-6 of the 0008. l o The bioaccumulation factor for phosphorus on page 163 should be the updated values of 3 x 103 and 6 x 102 for freshwater fish and invertebrate. a o The bioaccumulation factor for tellurium on page 164 for freshwater intertebrate should be 6.1 E+03 instead of 1.0 E+05. o The bioaccumulation factor for cesium on page 164 is 1400 instead of the value of 2000 as recessended in Reg. Guide 1.109. o It is not clear why reA= dant tables are included on pages 177 through 190. i Evaluation of the cumulative dose from noble gas releases includes both beta and gamma and air doses at and beyond the site boundary. The critical organs under consideration are the total body and skin for gamma and beta radiation, respectively. i l D-11 9
6 TER-C5506-657 For iodine-131, tritium, and particulates with half-lives greater than 8 days, the Licensee has provided a method to demonstrate that cumulative doses calculated from the release meet both quarterly and annual design objectives. l There are, however, several discrepancies identified in the Licensee's approach: 2 o The definition of Riiak on page 70 should have units of m (arem/yr) per (uci/sec) for D/Q dependent pathways instead of (ares /yr) per (uci/sec). The inhalation and grevand exposure pathways should be included with o the listing on page 71 of Section 3.4.2. I The usage parameter for fruits, vegetables, and grain in Table 3.4-22 i o g i should have units of kg/yr instead of kg/hr. o The Sr-90 bone and total body values for the ingestion and inhalation pathways for all age groups in Appendix A are incorrect as compared to Reg. Guide 1.109. o The values on page 156 are interchanged for the skin and total body values for I-132. The same situation exists for I-135. 'I 1 The Licensee has not provided a method to project the monthly liquid dose as the Licensee's RETS does not contain such a provision for dose projection. The review recommends that the Licensee include the specification per the model RETS (NUREG-0472) Section 3.11.1.3 for the liquid radwaste treatment system and per Section 4.11.1.3 for the liquid dose projection. For gaseous dose projection, the Licensee intends to use the present month result for the projection of the following month. This method, however, is not backed by a more concrete, detailed approach for projection. The Licensee has also provided a method to da=anatrate compliance with the total dose (40CFR190) requirement, from the uranium fuel cycle sources, as specified by the Licensee's Technical Specification 4.29. However, the Licensee should provide a method for direct radiation dose to be included in the total dose. The Licensee has not provided flow diagrams defining the effluent paths and components of the radioactive liquid and gaseous waste treatment systems. The Licensee has provided a description in Enclosure 4.4 and also in the maps for the environmental sampling locations in the ODCM, which satisfies the Licensee's RETS comitment. The discrepanies found were as follows: D-12
6' TER-C5506-657 o Specific parameters of distance and the direction sector from the centerline of the reactor and additional information for the environmental monitoring program are not included in the CDCM, i although the CDCM states the information is contained in procedure AP.307, " Environmental Monitoring Manual." The procedure must be included with an ODCM submittal. Because the procedure was not submitted, the procedure was not reviewed. o The LLD description in Section 5.1 should be modified, to be I I consistent with the model RETS, to read "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above { system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'real' signal." In addition, the A ters should be defined for both the effluent and environmental samples as follows: Effluents At = the elapsed time between the midpoint of sample collection and time of counting. Environmental At = the elapsed time between sample collection, or end of the sample collection period, and time of counting. In sununary, the Licensee's 00CM and the revised changes used consist of numerous discrepancies that are inconsistent with the methodology and guidance in NUREG-0133, and therefore are not considered an acceptable reference until } I all issues are properly addressed. J t e i D-13
~. k i e' s TER-C5506-657 f properly addressed. These deficiencies have been discus, sed 16 the text and i
- l are listed in the following:
s 's Liquid Effluent Setpoir.ts lll Licensee's Equation (2.1-2) should be: o Ct = (F + f) 1 f I._Si l 1( hPCi rather than: Ct *-(F + f) I (S MPC ) i 1 f i i as stated in the 00CN. t i The Licordeee's minimum dilution flow rate (F = 800 gym) seems small, o compared with the maximum acceptable flows rate (f = 300 gym). The 1 Licensee should also provide nominal ficar rates for comparison, o Since the RHUT monitor setpointr'are based on a default radionuclide mix, Section 2.1.1.1, then a comparison should be made between the l prerelease isotopic analysis and the default six to ensure the setpoint is conservative. This'is particularly true in case of the 1984 releases when cesium isotopes nee releastd in dipproportionally large amount. o tion (2.1-7) Men not appear to consider the requirement that l 91 i1 q i MPCi Equation (2.1-7) should be e pivalent to Equation (2.1-4) except tha.c g l the nuclides are measured and are not the default mix.
- The Licensee submitted a revision to CDCM in the Annual Radiological Report l
for--1984. Il +- f D-14 l
l.i TER-C5506-657 i i o In Equation (2.1-7), it is not clear why the high alarm setpoint is - I increased by the factor 1.25. A low or intermediate alarm may I justify a setpoint increase to prevent spurious alarms, but the high alarm setpoint should not be increased. I o' The detector efficiencies listed in Table 2.1-1 must be current values and specific for the RHUT monitor detector in use. The data in Table 2.1-1 appear to be for a detector system that may or may not be in use. Gaseous Effluent Setooints I o The Licensee has not specifically committed to using the highest annual average (X/Q) values, and thus the conservatism is not ensured. o In Section 3.2.1.1, Table 3.2-1 should be referenced instead of Table 3.1-1. o The justification for the 1.25 correction factor in Equations (3.2-8), (3.2-9), and (3.2-10) is not clear. Decreasing the flowrate in Equations (3.2-8) and (3.2-9) is acceptable to ensure the 10CFR20 limits are not exceeded. However, increasing the high alarm setpoint by 1.25 in Equation (3.2-10) is not acceptable as the monitor's response is independent of flow. o The detector efficiencies listed in Table 3.2-2 must be current f values and specific to the detector system in use. It is not clear how a single set of values is applicable to several monitors as i indicated in the footnotes to Table 3.2-2. o The Licensee has not explained how the total maximum permissible i concentration (TMPC) is obtained or what are the units of TMPC. o Equation (2.1-2)* is incorrect. It should be written as MDF = (MPCF)(R) - R V instead of MDF = (MPCF)(R) n i The justification for the 1.25 factor in Equation (2.1-1) is not o clear. Decreasing the flowrate will not change the monitor's response to the volume of liquid seen by the detector. An adjustment can be made by multiplying Equation (2.1-4) by 1/1.25 with the justification of decreasing the batch release rate to ensure against exceeding the 10CFR20 concentration limits. Liquid Concentration and Gaseous Dose Rate (10CFR20) o The Licensee has not connitted to using the highest annual (X/Q) i value:: to ensure conservatism. i
- Should be Equation (2.2-2), as the Licensee has mistakenly numbered all the eqvations under Section 2.2.
D-15 e
r I
- ll 4
TER-C5506-657 The Licensee has not addressed the possibilities of simultaneous o releases from various release points. o In Section 3.3.2, the definition for P.; contains a reference to i Table 3.2-1, whereas the reference should be to Table 3.3-1. The orpressions for Irrigated Foods in Section 2.3 contain the factor o 1100 and Np. It is not clear that these factors belong in these expressions since these expressions are similar to Equation (4) on page 1.109-3 of Reg. Guide 1.109. i
- (
o The expression for Irrigated Foods: Milk contains the ters
- l (1-FMATER). However, FMATER=1.0 for milk from Table 2.3-4, which l'
seros out the dose contribution to the milk pathway from cows drinking contaminated water. The expression for tritium on page 16 of Section 2.3 is not an o expression for dose, but an expression for the tritium concentration. Additionally, it is not clear that the factors 1100 or Mp belong in this concentration expression as indicated by Equations (A-14) or (A-16) in Reg. Guide 1.109. Note 1 in the description of variables on page 19 of the submittal o states the bioaccumuletion factor for cesium in freshwater fish is a site-specific factor of 1400 lastead of the 2000 pCi/kg per pCi/ liter recommended in Reg. Guide 1.109. o Table 2.3-1 lists an infant's usage parameter of 0 liter / year for milk instead of the 300 liter / year recommended in Reg. Guide 1.109. o Table 2.3-1 lists freshwater fish usage factors of 21, 21, and 35 kg/ year instead of the 6.9,16, and 21 kg/ year values recommended in ] Reg. Guide 1.109 for the child, teenager, and adult, respectively. + l o Table 2.3-3 does not include a t value of 24 hours for leafy p vegetables for the maximum exposed individual as reccamended in Table l E-15 of Reg. Guide 1.109. 1 11 o Table 2.3-3 lists the release holdup and transit time as 72 hours ll instead of 24 hours as recommended for th in Table E-15 of Reg. Guidel 1.10?. f o The definition of Ri ag on page 70 should have units of m (ares /yr) per (uCi sec) for D/Q dependant pathways instead of 2 I' l (pres /yr) per (uci/sec.) ll The inhalation and ground exposure pathways should be included with !a o l the listing on page 71 of Section 3.4.2. The usage parameter for fruits, vegetables, and grain in Table 3.4-22 o should have units of kg/yr instead of kg/hr. il i D-16 l
1 TER-C5506-657 o The Sr-90 bone and total body values for the ingestion and inhalation pathways for all age groups in Appendi:: A are incorrect as compared l to Reg. Guide 1.109. g i o The values on page 156 are interchanged for the skin and total body values for I-132. The same situation exists for I-135. Liouid Radwaste Treatment The Licensee's RETS does not contain a provision to treat the liquid o effluent prior to discharge. The provision for monthly liquid dose projection is therefore lacking in the C008. o The Licensee has not provided a flow diagram defining the affluent paths and components of the radioactive liquid weste treatment system. Gaseous Radweste Treatment o The Licensee's method for projecting the monthly gaseous dose lacks clarity and a specific approach. The Licensee should provide a more specific method for projecting the monthly dose. o The Licensee has not provided a flow diagram defining the effluent paths and components of the radioactive gaseous waste treatment system. Environmental Monitoring Proaram o Specific parameters of distance and the direction sector from the centerline of the reactor and additional information for the environmental monitoring program are not included in the ODCM, although the CDCM states the information is contained in procedure AP.307, " Environmental Monitoring Manual." The procedure must be included with an ODCN submittal. Because the procedure was not submitted, the procedure was not reviewed. o The LLD description in Section 5.1 should be modified, to be n consistent with the model RETS, to read "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'real' signal." In addition, the A term should be I defined for both the effluent and environmental samples as follows: Effluents l At a the elapsed time between the midpoint of sample collection and time of counting. Environmental At a the elapsed time between sample collection, or end of the l saaple collection period, and time of counting. I D-17
i TER-C5506-657 I 5. REFERENCES c i 1. Offsite Dose Calculation Manual for Rancho Seco Generating Station i. Sacramento Nuncipal Utility District NRC Docket No. 50-312 October 1982 2. MRC Approval Letter by Division of Systems Integration
Subject:
NRC/DSI approval of Rancho Seco CDCM MRC Docket No. 50-312 February 9,1985 3. Title 20, Code of Federal Regulations, Part 50, Appendix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to l Neet the Criterion, 'As Iow As Is Reasonably Achievable,' for Radioactive j' Material in Light-Water-Cooled Nuclear Power Reactor Effluents" 'l 4. " Radiological Effluent Technical Specifications for Pressurised Water g Reactors," Rev. 3 Draft 7," intended for contractor guidance in reviewing REIS proposals for operating reactors l NRC, September 1982 l NUREG-0472 l 5. " Radiological Eifluent Technical Specifications for Boiling Water Reactors," Rev. 3 Draft 7," intended for contractor guidance in reviewing RETS proposals for operating reactors NRC, September 1982 NUREG-0473 6 " Annual Radiological Report - January 1 through June 30, 1984," Rancho Seco Generating Station, Sacramento Nuncipal Utility District I NRC Docket No. 50-312 ] 7. Semiannual Radioactive Effluent Release Report - January 1 through July l l 1, 1985," Rancho Seco Generating Station, Sacramento Nuncipal Utility District NRC Docket No. 50-312 i< 8 Semiannual Radioactive Effluent Release Report - July 1 through Decmeber l 31, 1985," Rancho Seco Generating Station, Sacramento Nuncipal Utility District l MRC Docket No. 50-312 l ll 9. " General Contents of the Offsite Dose Calculation Manual," Revision 1 'l Branch Technical Position, Radiological Assessment Rranch NRC, October 1978 NUREG-0133 1 I 10. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, A Guidance Manual for Users of Standard Technical Specifications" NRC, October 1979 NUREG-0133 D-18
t TER-C5506-657 11. " Calculation of Annual Doses to Man from Routine Release of Reactor ) Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I" NRC, October 1977 Regulatory Guide 1.109, Rev. 1 t D-19
I i i I i I APPENDIX E I TABLES FOR LICENSEE-REPORTED COBEITMDITS s l FOR RANCHO SECO NUCLEAR GENERATING STATION 1 License No. DPR-54 (As of 08/09/84 through Amendment No. 53) I 4 t l t I e I FRANKLIN RESEARCH CENTER l DIVISION OF ARVIN/CALSPAN q 20tti & RACE STREETS. PHILADELPHIA.PA 19105
~~ .. ~ l RANDO SECS IIg[ttAS EtNERAllIG 114fl0W UNtf 9. (9100fflWffS OF AIEIWht BASI $tGGitAt (10Fl0EISWlfAL OstthfflIE St90Rf' Table E 1. tart t n= ales -
- tam -
a forhalent taaetflentlema tre/ h reattl - a IIsla tes-- - et t1 Ism. Samttftr tamag[tmeatt " rw - a 4 Radiele9 tal taviremmental 9 A. fesellering Program 1. Iteatterlag Program 3.22 the redlelegical envireemental asaltoelag program the reports shall else inclede the fe11eula9: e shall be condected as specified in table 3.221 sammary description of the redlelogical eaweten. meatet asalterlag program, lacledlag hauptf ag arthods for each sample type, slee aml physical characteelstics of each semple type. 'templa preperstlen methods, onelytical mothefs. ered messerlag egelpmeat osed. 46.g.2.2.21 2. Sempilag tecellens table 3.22.1 Sampilag lecellens speelffed la feb'e 3.F2 8 d.26 The redletegIcel envirosmontal moniterlag the reports sha's else lectode the fellemlag: a samples shall be cellected from the locations est of all samollag locations tepd to e t.shle shown la the gotM. gevlag enstances sad directleas eram aae reacter (6.9.2.2.23 8. Sadlelegical toetreamental tesaltersag program Servel11ence Icet env rsamental mentteel temples the annual reflelegical emelessutental atlag e ) Stealterlag program d.26 The redlet shall be e lected persweat to Table 3. .I reports shell inclose summerleed and I ated ea f rom the locettens shown in the 800M and resells in the forest of f able 6.g-l** et all shall be smalysed persesit to the require-redlelegical eavleesmeatal samples tenen declag meats of Tables 3.221 eaJ d.26 9 the report peeled. In the event thet some reselts are not evellette for inc1esten with the report, the report shell to submitted noting and espletalag the reasons fee the elseseg results, i the elselag dote shall to emboltted es seen es possible la e supplementory report. 46.g.2.2.23. The enamel redlelegical emetremmentei reports shell leclodo sa w les, laterpretetm as, and e J stelletical evoleotten of the resultn of the ( radioingicol en.tre montei sur eitiene octletties fee the report perled. Gottedlag e l compeelsea with peseperettene) stedt.es, operettenet centrols les appropelotel, one prevlees saviremmental serveillance toports. and sa essessmeat of the absorved tapects of the plant operetten en the eaviresumat. If here-a ..e.t la. c.dl.,.,4c.,.a...o_ ate, .tle, r.p.rts c erla, _ op-et t. of the.al t..,a, ~ p_le.s c.,.a e - s,, es tted pee. to a May I of each year. (83
- there is ao such table la the Beache ptt$.
tJe tJt Oon I et 08/99/95 Page 1/3
fehle C.I. Amstle StCS selCttAR GtuttafisIE STATION tmtf 1. C0pOIff9EWil Og mammau gagggggggggt guygggigggggg gygagggggg gggggy gg,,g,g Part I en-time - - I an ^ - ' fachatral smertf traliams - tCS/bryalllamem 4 fitta Litannas Afft um. hc l f t e r t e
- r - a-S.
Gedlelegical tavironmental fel effects or owldouce of Irrowersible demoges stonitorsag Program see detected y the monitoring. the report shall Servelllence provide en enesysis of the problem and a planned course of actlen to alleelete the prettom. Itsaltering Progree it.g.2.2.29 ICont.) Other poets nelch are messeroeble and Ident184 able. together with the listed nuclides, shall be lesatified and reported. liebte d.421. Isole c and table d.261. Isote di C. tend Use Centes 3.23 A land use conses shall be conducted and shell The reports shell else lactade the felle.Ing: Identif y the locetten of the nearest allt enleet, the esselts of the land use conses the nearest residence. the neerest perden* of 16.9.2.23 greater then 500 square feet edec ong f resh bety vegetables in estar of e, t; .vteorological sectors within a s'istence of flee elles.
- Sroad leaf vegetallen sempting eey be perfomed at the site beender in the derectlen sector with the highest 9/$ la les of the garden census.
h d.2f the' land use centes shall be conducted annually by using methods that sitt provede the best results, such as deer.to.deor servey, eertal servey, or by consetting local agelcultore eetheeltles 9. Interleberstory Camportsen 3.26 the contracter perfereing the emetysis of redle. The reports shall else ing1sde the folleging: logical enviremmental program samples for reele. ective esterielt shall perticipate la Inter. The resells of Licensee partictpellen la the 1storatory Compeelsen Program approved by the Interleberstory Camperleen fregram. 16.g.2.2.29 Camelssten l l 9 N A tst est om Im tse Page 2/3 08/99/95 w e e ~
mumme amammam
= =
anICIO $tte liutttAR StWanitus 11Atleulleef t 1. Cepeelfstat$ OF asumat antietestCAL tutteentiftet getanfing arpeer (Cent.) table t-1. Part it - O tan - "a smalart ta r==dittama tenbeltal semelficattama -- Lta/ hrwelllmana 1Ii1a Lisegnet.K1h h eifIc Cammitaentn - r===a - A. nadieleylcel tovire -eatai femallering program 1. 14 mattering Program 3.22.s with the radiological envIresumental program met Propere and submit to the Comedesten. In the belag conducted as specified la table 3.22 8 Aaamel Radiological tavironmental Soport, a description of the reesens for not conductlag the program as required and the pleas for preventsag a recorrence 13.22.3) 9. Redlelegical tavleenmentel stealtecong program Servel11aare 1. seporting tevels 3.2Z.S with the level of radleettivity not the resett the conditlen shell be reported and described In of plant efiteents in en environmental sampling the Anneet Radlelegical Envireamental Report medlem esteeding the lletts of fehle 3.22-2 (3.22.b1 iAen averaged ever any calender guerter 2. temer tielt of fable d.26-1 Analyses shell be performed la such e menner la such cases. the contribellen factors will be Setection tit 9) IIsle a that the stated LL9e ul11 he achieved seder identitled and described in the Anneet Radiologi-roottae readillons. Octosionally bactgreemd cat tavireamratal Operellag Report. (fatte fluctuelleas, saaveldably small sample slaes, d.26-l. Note al t,3 presence of laterferrlag nuclides, or other I oncentrollable circeostances any reader these 4d8 LL9s enschievable. C. Intertaberstery Casperleen 3.26 The contractor perferedag the emetysts of redle-Report the corrective actless taken to prevent logical pavironmental program samples for reste-a recorrence to the Commelssten la the Anneet Program active esteelels shall participete la Inter-redselegical Enviresmontal toport (3.268 laboratory Camportson Program approved by the Commissten with analyses not being perfereed as regelred above... l 1 s, a Ut Om Im 08/99/95 u.4 s Page 1/3 9
febte t.2. asuCse Mtg leftttAR (dN[BallHG STATION Willt 8. C0peelfigut$ tr Stulemmaa negleACilVt (FFtWENT StttAM Street
- pars t. am. ales
- O lme "
a fashmical semelficattama -. EfR/ hrwelllamaa tIsla 1is.easee K81 ilm. %emeiI6e t===.tammea - ramma-a A. Gedleettlee Effloont Beteeses I. Effluent telease le m ry 10Cre50.36el23 }50.36etechalcatspecificellensoneffluents the redleettive effluent release reports shall tigold sros nuclear poser reatters. Include a summary of the geantitles of redle. Geseems tal la order to teep releases of redleective active ligmid and geseems efflacats released meterials to marestricted areas declag aermel f rom the emit as settlaed in Depletery Golde reacter operetleas. lectedlag espected operettenet 1.21. =nseserlag, tweleetlag, and topetlag etcorrentss. as low as It ressenably achieve 61o. Bodleettivity la 5elld seestes and seiesses each license eetherlanag aperation of a nuclear of Sedleective Meterials in tigold and poser reacter allt laclade techalcel specifice. Geseees Ef flecats f rom tipt. tester. Cooled tiens that. la aCJltlen to requirlag templiance metteer power plaats." with dele sammerleed eith appilcable prowlstens of W.196 of this en a guerterly bests feilenlag the chapter, regelre: f ormet of Appendle S thereof (6.g.2.3.5)
- 1. That operettag procedures developed to g50.3delti for the centret of off seats he estetlished and fellemed and that egelpment testelled la the endl.sective easte system, perseent to $54.386e) be malatalmed and esed.
- 2. The schmission of a report to the appropelate tg NBC Beglemel Offece sheen in Appendte 8 of I
part 29 of this chapter olthis slety feel days e af ter Janeery I and July I of each year spets-f ylag the geantity of each of the pelattpel redlonoclides released to enrestricted stees la ligold and in poseems ef fluente dorlag the preelses als del months of operetten, and such other leformellen as aey be regelred by the Commisslea to estlante asalmen potential anmoel redletten deses to the public resettlag from effluent releases. Coples of such report shall be sent to the Director of laspettles and taf orcement. U.S. Metteer Repletory Commelssten. tsesblagtea. 0.C. 29555
- Reuttae redloettlee elflueet release reports coverlag the operetten of the unit declag the prevlees 6 eenths of operetten shall be sehmitted olthla 60 days af ter Jensory I end July I of each year.
a. v Ut O cFt I cFt page 1/7 99/09/95 vi -J e e
- 7..
. ~ - mammen am RAIDS SECS IIItttAA GttiftettesG Stattese usett t, Cessettsmets et 9tselassesat enefeattivt tfrtutist etttaw steget (Cent.) Table f.t. Fars t. W las - Otma - ^* f ekstral semelficattama Ltethrwellia=*= r=w - ^a tItIa t4===== atIi seg, sneg11 M ongtstanta A. Sadloettive Effloont seleases It quantitles of redloettive meterials reteesed I. Effluent telease Semansey derlag the reportlp9 period ere sigalficaatty (Ce=t.) above destyi objectives, the report shall cover f this speelficaley. Da the bests of such reports sad say additlenet Inf ormellen the Commissten l may obtain from the 14ceasee er others, the Ceselssten may f rom time to time regstre the licensee to to e soth acteoas as the Commission n deces appropetate. the redleottive effloset releese esport shall 7. Ipaetaaned tffluent 10CftSt. m (2) See A.t ebeve laclude the felle= tag Inforuoteen for all on. P eaned releases to oncestricted stees of l teleases redleettive meterials la gasesos and ligold offluents:
- e. A description of the event and egelpment
- lavelved,
- b. Cowse(s) for the emptenned rolesee, t1
- c. Actleas laten to prevent eecorrence.
e t#5
- d. C es of the unplanned releeee.
Ligold Geseoue the restesettve effluent retoose reporte theit The selld reesette eyeten shall be used as laclede e asumery of the guantitles of reele. 9. Solid Sedleective 3.23 applicotte in accordence with a procese eteste control program to process met redleective active solid weste roleesed from the salt es westes to meet shipplag and berget regelre. est16med In Regeletery Golde 1.21. "Itseterlag, twelesting, one Reporting Westemetivity in seats. Selld teattes and seleases of Sadleettive festerlets in Ligold and Geseems Ef fleente from Light.4seter-Cooled Iteclear poner plante
- with data seminarleed en a guerterly bests felteslag the formet of Appendte 5 theeoef (6.9.2.3.ft the redleective effloont reteeee reporte shell C.
SadlelegIcel Dese 10CT990. m (2) See A.1 above lactade the release of geseems effluents during each guerter, as outlined in Segeletery Golde Assessment 3.25, with the data sommerlsed on a guerterly [ bests, fo11 swing the foruust of Appeedle S O thereof. A sammary of meteorelegical W conditlens dorlag the release of geseems effluents allt be retelmed on slie for tue m years. 8* 08/99/95 page 7/F e e no
l l l l l l 6 fable C-2. RAsID S SECS ORICitAR Gtlet04fil6 Siellest 18117 1, CggeelfMut$ gr geslaamaana ameleaClivt Ef/Llftlft attrast etpgei (Comt.) Part t. am-alan - - lam - a Tenhalent immelfinallame -- Ef t/Larwell1==<a 1111a L i s -- -- Af f t sea. semelfte r - s - e. - rw - e C. eedlelegisel Sese l Assessment (Cent.) The redleectlee effloset release reports shell laclade se essessment of the redletten doses from redleectlee effluents to ledt,$ duals due to their actieltles laside the site basadery during the report perled. All essemptions esed la meting these essessments (e.g.. specifle attletty. esposere llae. and lacetioni shell be lacladed in these reports. the redleective ef floset release reports shell laclede en essessment of redletles doses from the redleectlee ligold and geseous efflosets released from the unit declag each talender guerter, as settleed la Segulatory guide 1.23. The releases of efflesets shell be used for detersialag the pseees pathmer deses. the essessment of reeletten doses shall be perfereed la accordance eith the Of fsite Gese toiseletten pioneet (GBDel. (6.9.2.3.11 M im N A. a 159 Om 1m Pege 3/f 90/99/95 t/' w e e ~ ~ ~ ~ ~ - ~~
- ~
7
~.- mon - - s fable t-2. RAIEIG SECO IRfCit48 EtuttettuG Sf4ff81818817 9 CEBestf8tWfS OF StsstasenIAL ResteaCTIVE ffFlutWf AtttAM SEPEtt Itent.) Eart it. - " Imm -
- a tetant ta ra-alatamm techalcal Smetif f ratimma - Ltathrwells== =
rw-h efer r - 6ammata fitta Licensen Atti lla. A. Moniterlag Instrumentellen I. Ligold Effluents table 3.15-1 With the megenerent Moldg fenh Discherge Line tepe11e In the mest Seelenmuel tedloettive Moalter Insperable...tsert best ef f orts to return Ef floont Release Report by the laeperability the lastroseat to OPteettt states within 30 days mes not terrected la e timely eenmer. IIsble sad. of unsectessful.... 3.15-11 2. Geseems tiflesats Isone Inone leone D. aedleettivity tieterle) Inventory tigold se lde, tents 3.17.3 the geantity of redleMtive asterlet contalmed testribe the evoete 1eedley to thle tendition e la each of the f ollowing tents shall be llelted in the meet Seelannual Sedigettlee Ef fluent to less thea er egnet to 30 terles. eettedlag selease seport. 13.17.39 trillem and dissolved or entralmed noble gases:
- a. Regenerent Molder feats
- b. Detside fouperary feats 3.17.3 with the quantity of redloettive esterlet in say of the listed tents esteedlag the above Ilott. Ismediately suspend all seditleas of redle.
g,3 attive meterial to the taab and within 48 heers f redete the tent teatents to within the llett. 4 and... C. Radlelegical tavleemmental nonitoring program I. Sampitag Reletetten 3.22.c with ellt er eresh leefy vegetable temples propero and esbelt to the Comotesten within 3e enevellable from any of the semple Setettens days e Special Report d ich identitles the reestred by Table 3.22 5... The totettens from tasse of the enevellability of temples and dich temples sete emovellable any then be Identifies 1stettens for obtelming repletement deleted from table 3.22-1 provided the semples. 13.22.tl legetlens from d ich the repletament semples tuote: the Licensee hoe temeltted to e M-day sere obtelned are added to the savironmentel Sancial Ammart.) eeniterlag program as replMement letettens. If evellable. 2. tend Use Coates 3.22.s With a tend use tensee Identifylag a 1stettonist identify the nos 1stettene le the meet $sel-ohlth yleids a talteleted dote temeltmoet p etee annual medleMtive Ef fluent Selease Boyert. then the valers currently being specified se 13.23.el Specificellen d.22.3.... a. a U9 Om I Os pagP 4/7 N/99/95 e 4 f
l i lable t-2. RANCIS StCe ullCttaa GrufealluG $14tlest taill I. C0peellettell er srlelaamaans emeleactivt Eff tutul utttAM Rtfeef (Cont.) Part 11 -
- s=a -
t- ^ = La men t sa r w aiiana 1.nhainal teost ficatlana - trathregilta=,. titta ten - arts an. sa <tfac r - se - se
- r - a-C.
Badlelo9 cal tovironmental t Monitoreng Program (Cont.) 2. Land Opse Conses (Cent.) 3.23.h ifith a tend ese reases identifying a identify the new locaties?st le the Sealanneet locatients) which yleids a calculated Radioactive Effluent Seloose Soport and also dose er dose commitment Ivla the same esposere include in the report a revised flgereist and 1 pathmey) 295 greater than at a locatten f rom table for the WCf6 reflecting the new loca-uttch samples are corrently being obtaleed tients). 13.23.b3 in accordance with Specification 3.22. edd the new locatten to the redeelegcal environ. mentet monitoring program within 30 days. The sampling locatten, escluding the control sletten locetten having the lowest cal-colated dose or dose commetaset 191e the same esposere patinsey) may be deleted from this monitoring program after 19cteter 31) of the year in which this land use conses was conducted. D. 44censee-Initteted Changes to PCP/0BCit/Sadmaste l 1. PCP 6.15.2 Licensee-Inittsted changes to the PCP: this submittal shall centeln: t'j Shell to ochmitted to the Commission by e. $ efficiently detalled Infocustlen to tetelty I 08 lacleston In the Seelanneet Badlesettee Effluent suppset the retienele for the change without i Release Report for the period in which the benefit of adeltlenet er supplemental Inter-j changels) was made. setten: I b. A detevelastion that the change did met reduce lhe overall conformance of the se14dified weste predert to solsting criteria for selld westes; and c. Secumentetten of the fact that the thenge has been reelemed and feend acc V eble by the Plant Review Committee. 16.45.2) the redlesctlee effloont release reports shall Include any thenge to the PROCtl$ ChlBOL PegEmase IPCP) ande emelag the reporting perled as provided in specificatten 6.15 16.g.2.3.Il 2. 9300 6.16.2 Licensee-laltlated changes to the OBCll: this submittel shall contale Shell be submitted to the Commission in the a. Selfielently detailed Infeeeellen to totally Seelanneet medleective Effluent selease seppert the rattenele for the change witheet
- Report, benefit of additional or temental infeem tlen. Inferestion tied should h
c.nsist of a,eaagt of it.se ges of it.e OBCM to be changed with each page numbered W and provided with an approval and date bee. Q together with appropriate analyses or g evaleetlens jestifying the thengelsi; cyg Page 5/7 ge/g9/05 e ..e ee w s-N
m m ~ fehle t-2. RAIIDW SECS IWCttas 6tIItaattIIG STAlleN 180371. C91 gilt 9E181$ OF SE90tammeha gagggetilgg grFtg[ggg ggggggg gggggg gggag,g Part ll. Remarting Renaleer d a tenters ta r==ditImma fa.h=Ical smerificattama - trathrwalttanes i fikle Licempe gf15 leg sanelIle r=== teen t s
- re
{ D. Eltensee-Initleted Changes l to PCP/gatst/Wedneste (Cent.) 2. getM (Cent.) 6.95.2 b. A detevelnetten that the thenge will not redece the etteracy or cellshitity of dose te1 relations er setpoint determinellent; and t. Setumentatten of the feet that the thenge het been revleued and feend acceptable by i both the PeC and 86aC. 46.96.2) l The redlesctive efflusst reisese to shall lattede any a to the eff5tfC CALCULAlleII I WC88) ende during the i reporting perled, es provided la speelftcellen j 6.l.6 86.g.2.3.1) i 3. Seeweste System 6.17.2 ticensee-laltleted thonyes to the redle-The disconsten of eeth change shall conteln: active weste systems fligold, geseees and selld): n. A sammary of the evoleotten that led to the The Camelssion the11 he Infereed of all determinetten that the thenge could he made licensee-Initiated thenges to the redleective lin acceedence with lette5g.59); l M weste systeme by the inclesten of a settable discussion of each change la the Annual fSet 6. Sufficient detalled Informellen to totetty Update fee the period in which the changes support the reason for the thenge ulthout = l were ende, benefit of additlenal er supplemental Informellen: t. A detalled desciption of the egelpment, egelpment, tempenents and esses envolved and the laterfaces with et plant systems d. An evelsettee of the thongo ulti he sub-ettled uhtch shone the predicted lacrease of releases of reeleottive estorials in ligold and geteese efflesets and/or geen-tity of solid teste from these provleesty predicted in the licensee applltetten and amendments therete: e. An evaluellen of the ebenge edileti shows the espected lagreese la the meeleum esposeres to en ladividual la the unrestricted stee from those ewles iir - ep,{it.ti. sly estlested in the g and amend.pnis it.erete: f. A temporison of the predicted lacrease of L releeses of radlesttive esteriets la Ilgeld O and geseems effluents and in selld weste to the actual releases for the period the o changes were made; m I Page 6/7 88/99/95 e
e tehte E4. RAIOS MCS SWCitAR GEIIthAtlEIG stall 0N UNtf 1. CipselltWet$ W WestAfstftt SeDItaCIIVE EFFLutiff NLEAM REPORT (Cent.) I Part I1 - Ima - - a Ldalart ta readattama i tankiral tamelficattama - ifA/Larwel11amas -rw-a fitta llamasse Bill IIn. immelfer r - to - en 9. Licensee-Initleted Changes to PCP/WCIWeedmeste (Cont.) 3. Sedneste System (Cent.) 6.17.2 g. An estiaste of the esposere to plant operating persammel es a resett of the
- M ages and h.
Betementattee of the fact that the thenge was revlemed and found acceptable by the both the PSC and 185eC (6.II.2) t9 I 1 i ea O I l 6 w Oe 1e Page fit 08/99/05
- w e
e p.. .m W N **
~Y ammamE .k i.~'~,. ~_ ' h.. an-mae we ,eb,.. 3. .c. I. = => = = > i. c.--s. mc=====re l . - I,al - Iftrail _ m.,gere.lis It11e t4 - KIs sam. smeetfte r - se - e. . ce.. A. tigsld Effluent Seses 3.fF.2 with the calculated dose er dose cemettaent to Propero and submit to the Completten within 30 e member of the public from redloettive esterials days. e Special Soport. This report =498 in tigold effisents released beyond the site identif y the cessets) for esteeding the ilelts and defines the corrective actlens to be toten boundary emceeding to reduce the releases and the proposed
- e. 1.5 eron to the tetet body or 5 mrom to any corrective actions to be toten to essere orgen. dering any calender guerter er the sobsequent releases will be la compitsace with the llette (3.87.25
- b. 3 arem to the tetet body or 19 arem to any organ, during any calender peer se,,,
S. Ligold Reh este Treeteent leone leone System C. puble Gee Effluent 3.10.2 with the celesisted air dose from redlesctive Propero and schalt to the Camelssten within 30 noble geses released la geseees effluents days, a Special Report. This report will at and beyond the site beendary escoeding: Identify the castels) for esconding the Deses llettis) and defines the correctie, actlens to
- a. 5 mrod for poeme redletten er 19 mrod for be tenen to reduce the releases and the beta redletion during any calender guerter er proposed correctlee stilens to be toten to essere that outseguent releases will be in
- b. It ored for gamme refletten er 79 meed for compliance with the lletts. 43.09.2) beta redletten dering any calender year.
t'l i Special reports shall be sobaltted to the Director of the Regulatory Operettens Beglenal Office within the flee perled for each report. NW B A. v t#9 Om Im U9 4 Page I/3 gg/gg/gg e ee
l Table C-3. RAIIDS StCO IInfCttAR EfilthAf file STAtl8Bf 18 elf I. CEuestilteff 5 SF SPEClht 30-tav atpgetS (Cent.1 tub-tral somet ricatiana - trashreallla-. intia tiransas REIS son. sannetac r-a-
- re D.
Iodine.139. ledine-133 3.98.3 with the calcolated dose er dose commitment to a
- -epero and sd ait to the Ce W estem wishin 3e Trilles and Radlenec11 des seeker of the public free I-131. tentlen, days, a Specle) Report. this Report will in particulate fore Deses and radienec11 des in particulate fore with identify cause(s) for succeding the llelt half-lives greater than elght days. In gaseous and defines the correttlee actlens taken to be effluents released at and beyond the site to reduce the releases and the proposed correc.
beendary exceeding: llee octlens to be taken to essere that subsequent releeses will be la coepilence with.
- a. 7.5 meen to any orgen during any calender the lletts. 43.98.31 quarter er
- b. IS eron to any orgon during any calender year.
Irlth geteews meste being discherged withest treatment when the ejected geseems effluent air deses due to le gas reseases at and be-yond the site boundary Isoe flgere 3.98-91. esteed 0.2 ared for esses redletten and 0.4 erad for beta redletion. over 31 days. t. Geseems Badueste freeteent 3.It System propero and sabelt to the Commissten within 30 days, a Special espect edblch includes the i falleming lafeenetien: Y es
- 9. taplanetten of why geseems reh este mes N
being discharged withest treeteent. Identificetten of the egelpment er subsystema not operable and the ressen for enoperability.
- 2. Actlan(s) taken to eestere the lamperable egelpment te operable states.
- 3. Summary descriptlen of actlan(s) tatsa to present a recorrence. 63.999 f.
Ventitetten teheest 3.19 With gaseous weste being discharged withest propere and seemit to the Camelssion withen 30 freatment System treatment when the projected deses due to days, a Special esport uhich includes the gaseous ef fluent releases from the site to areas fellowing internellen: at er beyond site beendary escoed 0.3 area to any ergen over 31 days. I. toplanetten of thy gaseous reemeste mes being discherged withest treatment identification of the egelpment er subsystems not operable and the ressen for inoperability. g
- 2. Actlen(s) taken to restore the Insperable N
egelpment te operellenet states.
- 3. Summary description of actlan(si taken to L#'
prevent a recorrence. (3.191 'o#' Om page 2/3 88/99/95 e e e, e ps., we.
- N
amme easspe $tte emitttee 6tleteattiss Statique 158971. (tseslistWIS OF SPEClat 30-any strest$ ICent.) Table t-3. s h-anni s elflemalama tut" _ all--,= - r==ma - ^. sane t t t e tw - ^ a fitta ien- - etts an. with the calculated annual dose or dose commiteoat Propere and schalt to the Commission a Spetf el G. Total Dese to e mester of the put14c due to releases of reste Deport within 30 days, welch defines the I 3.25 Mlletty ead radiatten from eventum feel cycle correctlee ettlen to be Laten to reduce sub. l seerces includ6ng the release of redleective seguent releases to prevent recorrence of meterials la ligold er gaseses effluents esteeding the lletts of Specificetten 3.25 and lactudes the schedule for w hlevlag esteeding 25 area to the total body of ear ergen conformance with these lletts, this Special tescept the thyreld, where the 14eit shall be Report as defined la 80 CIA part 29.dO54ct, 75 areal shall laclede en analyste dich estimates the redletten esposere (desel to e esmeer of the puttle from erealem feel cute seeeces. 6actedlag all effluent petimmeys and direct redletten. for the calender year that IMlades the releasels) covered by this report. It shall else descelte lowess of redletten and concentrattens of refleMtive seterial involved and the cause of the esposere levels er concentrattens. If the estlested loose) esceeds the llette of $pecificetten 3.25. end if the release confitten reselling in vietetten of 40Citl90 has met already been corrected, the Special Report shell include a roguest fer verlance la accordance with the provistens of dOCTEl98. Setsittal of the report is considered a timely reguest, and a verlance is g greated untti staff M tlon en the roguest is g complete. 13.25) p.a with the level of redleectfesty la en environ. Propero and satelt to the Commissten within 30 ad le. Redsetegical tavironentel 3.22 mental sempting sedlem esceedlag the lletts of days after the level of redleactletty het been determined e Special esport iAlch incledes leent tering fatte 3.22-2 eeen everaged over say calender en evateotten of any release conditlems. the esteedlag of fable 3.22 2 fevels environeratal I nters or other espects eAlch guetter... may result from more then one redlenec15de cowsed the llette to to seceeded. This report in the sampilag medium (f! will deflad corrective Mllent to reduce Cancantraliam Ett e tamaantrattam 121 e.. 2 1.9 selssleas soch that potential annual esposeres pop. Level 421 sep.LevelIb will meet Specificelleas 3.17.2. 3.10.2. ead 3.18.3. 13.22) Dese calcolettens wl11 laclede sit asesored redlenectides of plant origin. This report is not regelred if the moesered Iewel of redle-M tivity met met the result of plant effluents. l 6 me Om ie i 98/99/95 w Page 3/3 t
i l l l l table E-d. RANCMS SECO IGftttAR EfEtellIIG SIATIGII istli 1. Cepeelff0Nf 5 Of tf Ds. 80s. and Aes' tm. htemt samalficattama -- LfA/ breal11mme= 1 fleta Liramaam M IS Mm. h tfte r -; -
- rw-4 Deportable Occurrences 6.9.4 the Licensee tweat toports of Specificettens (Licensee twent toports) 6.9.d.1 below. Incledlag corrective actleas ead seesures to prevent recorrence shall reported to the IIRC. Supplemental reports may be required to folly describe final resolotles of occurrence. In case of corrected er supplemental reports, a licensee event report shall be made to the erittnel report date. perseent to the requirements of 10CFR50.73.
l. Ihlrty-toy teritten Reports 6.9.d.1 the types of events ilsted beten shell be the the wellten report shall faclode, se a einleem. subject of written reports to the Director of a completed copy of a licensee event report fore. the teglenal Office within thirty days perseant to IOCF950.73 and the goldence of IRMG-of occurrence of the event. 1972 16.9.d.9) 6.9.d.b I. Any airborne redleectivity release that euceed 2 times the applicable cearentrations of the lletts speelf6ed la Appendle B. lable il of 10CfR20 la enrestricted areas, when averaged t'l over a time period of one hour. I [
- 2. Any 11 geld ef fisent release that esteeded 2 times the lletting comblaes 80selsene permissible Concentratten 189CI Isee Isote I of Appendte e to 10CfR20) et the point of entry late the receleing meter 14.e.. enrestricted eree) for all radio.
nuclides encept tritism and dissolved noble gases edwa averaged ever a llee period of one hour. I I t
- tte : Licensee tweet Reports, a0 m Boyertable Octorrences. A0 Abnormal Occurrences.
A sse un om 9m ete 00/09/05 4 e ... ~
!6* I I APPENDIX F CHECKLIST EVALUATION OF LICENSEE'S RETS REPORTS e e i e l i 1 ? 1 FRANKLIN RESEARCH CENTER DIVISON OF AaVIN/CALSPAN l 20tn & aAct STREET 5.PMILADELPHIA.PA 19103 .I I m_..
M M' .o...e .o CHECKLIST FOR ANNUAL RADIOLOGICAL EWIRONME*TAL OPERATING REPORT
- TA8tf F-1.
Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 12-31-84 Plant Name: h rt I - Routine i ;;rtina Resul a ;-ts Infa. :tlan in Lice =__ 's *- '!ttal e I Not Not Applicable / I Canaltit Drttal addtt11td _ffgLReauired__ Reportina Contents Radiological Environmental Monitoring Program A. (Susanary Description) Direct Radiation (NUREG-0472/0473, Table 3.12-1) 1 1. ft0 locations (#=[3) a. / Sampling method and collection frequency b. f[ Type and frequency of analysis c. 2. Airborne (NUREG-0472/0473, Table 3.12-1) Sample location for radiolodine and [
- a. particulates(#=[)
[ Sampling methods and collection f requency b. Type and frequency of analysis i c. p t 3. Waterborne (NUREG-0472/0473. Table 3.12-1) i w I Surface Water N N#$ N i ./ a. l V Sample locations for surf ace water (# = Q. ) i o l Samp1tng method and collection frequency o Type and frequency of analysis o I b. Ground Water b Sample locations for ground water (# = ) o o Sampling method k-h Type and frequency of analysis o o 1" I
- Licensee's specific title if different:
ww Annual Radiological Report i l l //-/T-ff vate:
TABLE F-l. CHECKLIST FOR ANNUAL RADIOLOGICAL E WIRONNENTAL OPERATING REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 12-31-84 Part I - Routine " : rtina Reeuli;;.;r.ts Inf s;= tion in Li censee's ' '
- ttal Not Not Applicable /
geportina Contents Complete Partial Addressed Not Reauired A. Radiological Environmental Nonitoring Program 3. Waterborne (NUREG-0472/0473, Table 3.12-1) (Cont.) c. Drinking Water o Sample locations for drinking water (# = f) o Sampilng method and collection frequency Type and frequency of analysis o Sediment from Shoreline (M>d M M N) d. Sample locations for shoreline water l# = d 1 o Sampilng method and collection frequency o Type and frequency of analysis o 4 Ingestion (NUREG-6472/0473, Table 3.12-1) a. Milk Sample locations for milk (# = h ) o o Sampilng method and collection frequency o Type and f requency of analysis b. Fish and Invertebrates o Sample locations for fish and v invertebrates (# = f ) A o Sampling method and collection frequency o Type and frequency of analysis a S Il-t r-g na :
TAOLE F-1. CHECKLIST FOR ANNUAL RADIOLOGICAL EWilRONENTAL OPERATING REPORT (Cont.) plant Name: Rancho Seco Nuclear Generating Station Report period: 01-01-84 to 12-3144 Part 1 - Routine i n rtina h ir x..ts Information in Licensee's hbmittal Not Not Appilcable/ R_tfortina Centents ComRlRiR partial Addressed Nat Reauired__ A. Radiological Environmental Monitoring program 4. Ingestion (NUREG-0472/0473, Table 3.12-1) (Cont.) Food products ( k M pod da:Maf Y
- )
p c. Sample locations for food products (# = p 1 o [ o Samp1tng method and collection frequency o Type and frequency of analysis 5. Table and Maps for Sample Locations (NUREG-0472/0473 Specification f>.9.1.11) i ((m) a. Table and map of sample locations near i the site, givi distance and directions from the center Ine of the re&ctor I W b. Table and map of other sample locations at g more distant stations, giving distances and direction from the centerline of the reactor B. Radiological Environmental Monitoring program Surveillance 1. Direct Radiation (NUREG-0472/0473, Specification 4.12.1) h I o Results of qsarterly TLD gasuna doses for all sample locatic.as (# seats =g ) o Trend results and interpretation for control and [ indicator locations o Comparison with preoperational studies h I b o Assessment of the observed impact of plant operation on the environment S .L Yl //.ff_jeg n.. i.. : t
TA8tE F-1. CNECKLIST TOR ANNUAL RADIOLOGICAL EWIRONNENTAL OPERATING REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 12-31-84 4 1 Part 1 - Rautine Resortina M lie. c.ts Informatlan in Licensee's **Ittal Not Not Applicable / Comolete Partial Addressed Not Reauired R_ggortina Contents Radiological Environmental Monitoring Program Survel11ance B. 2. Airborne (NUREG-3472/0473, Specification 4.12.1) Results of weekly iodine-131 analysis [ o (# anal =#foy O) Results of weekly gross beta radioactivity o analysis (# anal =//33) d 1[ ( ) Results of quarterly composite gamma isotopic o analysis (# anal =J2) Trend results and interpretation for control o and indication locations Comparison with preoperational studies o i/ 7 o Assessment of the observed impact on the v environment 1. Waterborne (NUREG-0472/0473 Specification 4.12.Il a. Surface Water M E' ' # - (Mab [{S) o Results of monthly gamme isotopic composite analysis (# anal = g g) g y u g gg g } o Results of quarterly tritium composite analysis (# anal = 8 2I o Trend results and interpretation for control [ 4 and indicator locations o Comparison with preoperational studies 4$ o Assessment of the observed impact on O the environment c'n 5 e p-i?-F4 n,:
CHECKLIST FOR ANNUAL RA010t0GICAL EfWIRONPCTAL OPERATING REPORT (Ccnt.) TA8tE F-1. I plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-41-84 to 12-31-84 Part I - RautIne Resortine Resule w..ts Infa atlan in tie m 9 s
- M ttal Not Not Applicable /
CRmolete Partial Addressed Not Reautred R_tportina Centents Radiological Environmental Monitoring Program Surveillance B. 3. Waterborne (NUREG-0472/0473, Specification 4.12.1) [ (h) g
- b. Ground Water Results of quarterly gamma isotopic o
analysis (# anal = g ) g Results of quarterly tritium composite o analysis (# anal = ) 3 Trend results and interpretation for control [ Mk o and indicator locations MA Comparison with preoperational studies o l g4 Assessment of the observed impact o on he environment ,,s j t* c. Drinking Water f [0) g4 Results of E f, lodine-13I o j composite analysis (# anal = JJ ) . /h) Results of monthly gross beta V o composite analysis (# anal = /2,) Results of monthly gamma isotopic o composite analysis (# anal = p ) o Results of tritium composite analysis (# anal =/g) Mk Trend results and interpretation o /Yd Comparison with preoperational studies o g[ g-g Assessment,0f the observed impact V 4 o on the environment U
- e
- Ik O
- CHE'CKLIST FOR ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Cont.)
TABLE F-1. Rancho Seco Nucicar Generating Station Report Period: 01-01-84 to 12-31-84 Plant Name: Part I - Rautine Errrrtina "rrrli_ _ rts Information in Licensee's
- A-Ittal Not Not Applicable /
Comolete Partial Addressed Nat Reemired Resortina Contents Radiological Environmental Monitoring Program Surveillance B. 3. Waterborne (NUREG-0472/0473, Specification 4.12.1) (Cont.) Sediment from Shoreline (Mkd M S3kl 6) d. l Results of soulannual gamma o j isotopicanalysis(# anal =2fl l V Trend results and interpretation o Comparison with preoperational studies o b) Assessment of observed impact on the f o environment 4. Ingestion (NUREG-0472/0473, Specification 4.12.1) h a. Milk Results of w.n"k -'"; iodine-131 o analysis (# anal = 2eg) Results of somimonthly/ monthly ganna o isotopic analysis (# anal = o ) Trend results and interpretation f or control [ o and indication locations Comparison with preoperational studies o d o Assessment of the observed impact ./ kJ on the environment __V 6 RL5 9 //-/K 74 ~ [ I
g gN wO@% w ~ b ~ / _ e. ld 4 n be ar d ct g iu g 8 l a pe 1 3 l pR a A g o N_ f t t 2 t ta 1 f) o m N t h y [ ) 4 . 8 d t s R [ e s C e oe , V 'e e n 1 ts o 0 ta s Nr n ( 1 0 n d I e d T c & R j h' iJ i O P d L r I l /t y/ E o n o R i a G e N p e. i t t I r T t i A r t a R o a P E p m r P e O R r I t fn e LA e T l N y E N C C.' s N a OR n I o 1 V i N t ) ) E a l h t t L S e n c o ) / AC g n C s = l I n i l 4 o s a ( i s o G 1 l r i 1 1 y r O t a t s L a l t W n n y O r 1 a n l v 2 n o - a e e c s s l I e i a C e a c s D n r 1 e s) n) bl A e u ( r i a y I o d r i p c,g R G S 4 o d f u s f u e t t n a L r m n S-Ni t t s n s c o n i A a a o ) y o-a i ar p= /. n s c U e r i l i l p t o o a H^ pi N l g t M l p a t a m a 1l tl N c o a a n i t 3a oa e= t a m A u P n. .t o e 1 n sn f r c = a n i b-N l e i d . e i d g a ia i t o R f r t e e e O o g l n ( p a v V n# e# a r t F c n e. y m( n p a f' rs r r i( e l a rs r r .1T i 8 d T S s he en r n on an I o a o S f en e e S t s t o A-l o go t to p s ni o b k' yn t i ni o b s a it e o w L h s r~- i it e e a r t ya n 5' K c n dc p 'e n
- r. '
l e l e e s a r t P dc p e C n o 7 hs hs no he t G-E a s M 4 a o no he t t al h tn N R l 0 ng ng r i al h im sr i fo ? on on e t n C l / t ~ n b t a 2 Mg; t o w or ( mi mi i f o t 7 e ' r sr h A. w w < . e n 4 t - o to w or i lt F N n m e f ua n tv s f ua n tv s f o f o i - a a e 0 r p lt m l n G v oe sc o nn t o sc o nn t or or E t t o E n l ei s ee c ei s ee c g g m u s s i m u s rd i se d t n r se d tg t g r R I sb rd l v N d ld di a sh o l di a sh o l n l n i U ti n i = t n et r u n p et r ui ui 8 a m s P sr sr g n ( n ue n e '. e d A l s s P rn o sn eu eu T P n s E a s ed e n l o h Ro T a C Ao d R Ta C Ao d Rd Rd t n en rn o sn o o o n e a i s o t n i s F o o o o F o o o o F o o i t c t i u e g e )' o C o g d l n c R a o I b ~ n i i d t a I r R 4 t o r P a t P_ R H ~ Ms w ~ Q 4 s j.' 3'. i .\\ !{ ,h~ i ^
m f^g ^~ ^ '~ ~ ^ 8);cy s .+ g l TABLE F-1. CdCKLIST FOR ANNUAL rad 50LOGtfAL ENVIRONME%TAL OPERATING REPORT (Cont.) _ c Plant Name: Rancho Seco Huclear't.ense.tir.g Station Report Period: 01-01-84 to 12-31-84 - ] i. j ~~ ~ I' Part I Rautine tomartina Enaufran nts Inforunation in Lirmaame's $rdamittal Not Not Applicable / u '(emplgit Partial Addressed Nat Reauired Reportino fantAD11 B. Radiological Environmental-Monitoring Program Surveillance 4. Ingestion (NUREG-8473, Specification 4.12.1) d. Food Products (Broad Leaf Vegetation) (Cont.) o Trend results and interpretation for control and indicator locations Comparison with preoperational studies o ,/ o Assessment of observed impact on the V environment C. Land Use Census (NUREG-8472/0473 Specification 4.12.2) o Results of the land use census for the past 7 12 months co D. Interlaboratory Comparison Program (NUREG-0472/0473, Specification 4.12.2) o Results of licensee participation in the Interlaboratory Comparison Program 6 5: Ra5 e
- f. rv 4 /
a ~
,7-;----------g TABLE F-1.
CHECRLIST FOR ANNUAL RA0f0 LOGICAL ENV!RONNE 3 AL OPERATING REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-01-64 Le 12-31-44 Part II - Resortina Reenirements Subject to Conditions Is the Subject Resorted in ibtJwhill*ll-If Yes. Not Applicable / Inf::=:llan in Licentee's ' ^ lital If1_ .Ng_ _Not.Reevire L .__ Complete Partial RtPgrtina Contents A. Radiological Environmental Monitoring Program 1. Any deviation from monitoring program of fable 3.12-1 of the Technical Specifica-tions? If there are deviations, discuss reasons acd plans for preventing recur-rences (NUREG-0472/0473 Specifica-tien 3.12.1) m~ 2. Is the potential annual dose to a NEletR 0F THE PUBLIC equal to or greater than the calendar year limits of Specifications 3.11.1.2. 3.11.2.2. and 3.11.2.3. If yes, O) then is it the result of plant ef fluent releases? If no, the candition should be reported and described (NUEEG-0472/ .,3 1 0473. Specification 3.12.1) 8. Radiological Environmental Monitoring Prograi Surveillance Were any LLDs required by Table 4.12-1 of the Technical Specifications unschievable? i II so, identify and describe the factors con-tributleg to not achieving the required LLD. (NUREG-0472/0473. Specification 4.12.1) C. Failure to perform analyses on radioactive materials in accordance with interlaboratory comparison program during the reporting period? If there was a tailure, state corrective actions taken to prevent a recurrence of the failure. (NUREG-0472/ b 0473. Specification 3.12.3) Eg s ln l U i l //-/[- [ b Date: i
"i"P CHI.CI(LIST FOR ANNUAL RADIOLOGICAL EINIMINNEXTAL OPERATING REPORT (Cont.) TA8tE I-l. plan
- Maes: Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 12-31-8d Eart III - Other Saecial KTS-Related R:: rtina Commitments of the Licensee
- ts the Subject Renarted in_the Lahmittal?
If Yes. Infer =:tian in Licentee's * ^ lital Not Applicable / Ygi_ _Ha_ Nat Reauired rammlete Partial Resortina Cantents
- The requirements are those of the licensee's N!TS-related reporting casaltments which are different from those of the model RET 5.
Footonotes:
- a. Extept for direct radiation pathway, the Licensee has not provided a table designating distances and directions for The Licensee he, not provided maps to describe such locations except for sediment sample as the sample locations.
locations. The measurements are instead estimated by h
- h. The Licensee did not report the annual total for the sample measurements.
o the reviewer from the information available from the report.
- c. Although the Licensee attirbuted the detection of Cs-137 to long term fallout of nuclear tests, the no concentration was measured in the Ist and 2nd quarters,
- d. The Licensee emplained that no gamma spectral analysis were performed since the reporting level is l
- c. offered by the Licensee has not satisfactorily emplain the cause.
A3 5:a5 //-/f-f4 nate: a N N
~
= =
==
ammm m CHECRLIST FOR SEMIANNUAL R4010ACityt EFFLtENT RELEASE REPORT
- TABLE F-2.
+ Rancho Seco Nuclear Generating Sta*lon Report Period: 01-01-84 to 6-30-8d Plant Name: 1 i Eart 1 - Routine t;; rtina I _-li.a xts Informatlan in Licensee's *
- Ittal Not Not Applicable /
Eggelete Partial Mdressed _Nat Resulred R3PO @ e_Eentents Supplemental Report Information A. Technical Specification Ilmits for radioactive 1. materials released in liquid and gaseous effluents IRegulatory Guide 1.21. Appendiu 8. Section A) Masimum permissible concentrations (MPCs) used in 2. determining allowable release rates or concentrations IRegulatory Guide 1.21. Appendiu 8. Section Al s Fission and activation gases: a. b. todines: Particulates, half-lives greater than 8 days: c. d. Liquid effluents: I
- n
/ Average energy (E) of the radionutilde misture in f h 3. 2 releases of fission and activation gases I N IRegulatory Guide 1.21. Appendim 8. Section A) Methods used to determine ef fluent total radioactivity, 4. the radionucilde composition, and overall errors in measurement (Regulatory Guide 1.21. Appendia 8. Section A) i a. Fission and activation gases: b. Iodines: c. Particulates: d. Liquid effluents: il 6 e, o 'ticensee's specific title if different: Annual Radiological Report E The Licensee reported the RETS-related information under only one report, the Annual radiological Report, for Note: 1984 9 //-/f-M n,e:
TA8tE F-2. Cl4ECKLIST FOR SEMI ANNUAL RADI0 ACTIVE EFFLUCT RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 91-01-84 to 6-30-84 Part I - Rautine Renarting Requir = ta Information in Licensee's *
- lttal Not Not Applicable /
Conslete Partial Addressed Not Reamired Reportina Contents A. Supplemental Report Information (Cont.) 5. Information relating to batch releases of radioactive materials in liquid and gaseous effluents (Regulatory j Guide 1.21. Appendia 8. Section A) I a. Liquid V
- 1. Number of batch releases:
- 2. Total time period for batch releases:
- 3. Maulmum time period for a batch release:
- 4. Average time period for batch releases:
- 5. Minimum time period for a batch release:
b
- 6. Average stream flow during period of release
/ V of effluent into a flowing stream: N b. Gaseous
- 1. Number of batch releases:
- 2. Total time period for batch releases:
- 3. Maximum time period for a batch release:
- 4. Average time period for a batch release:
- 5. Minimum time period for a batch release:
6. Abnormal Releases (Regulatory Guide 1.21. Appendia 8 Section A) a. Liquid E e
- 1. Number of releases:
- 2. Total activity released:
//-/[- [h (sat e: w e om, e e ww E__
-.~. ~ TABLE F-2. CHECKLIST FOR $EMIANNUAL RAOIOACTIVE EFFLUENT RELEASE REPORY (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: t'l-91-8d to 6-30 8d Part I - Rautine tomartine Reenirements Information in Licename's submittal Not Not Applicable / Reportine Centents Casalete partial Addressed !sni_geevi red A. Supplemental Report Infornation I 6. Abnormal Releases (Regulatory Guide 1.21 Appendiu 8, Section A) (Cont.) 3 ) b. Gaseous
- 1. Number of releases:
- 2. Total activity released:
I l 8. Radioactive Ef fluent Releases B-1. Liquid Ef fluent Release Susanary I l. Mixed Fission and Activation Products IRegulatory Guide 1.21. Appendin B. Section C) 7 a. Quarterly sums of total curies of radioactive 0 material detemined to be released in liquid effluents (not including tritium, dissolved and entrained gases, and alpha-emitting material). ] (Table 2A of Regulatory Guide 1.21) i b. Average concentrations (uCl/ml) of slued fission and activation products released to unrestricted / areas, averaged over the quarterly periods covered / l by the report + j c. Percent of appilcable limit of average concentra-tions released to unrestricted areas. Include the / limit used and the bases in the supplemental report f information d. Quarterly sums of total curies for each of the h radionuclides determined to be released in liquid to effluents, based on analyses performed. Data should be separated by type of release mode, g/ os /,, i.e. continuous or batch v S Date: //-//-fd 4
I TABLE F-2. CHECKLIST f0R SEMIANNUAL RADI0 ACTIVE EfFLtpENT RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 6-30-84 i Eart I - Rautine Reeertine i __li z ats Inf==.=tian in Licentam's *- ' *ttal Not Not Applicable / Complete Partial Mdressed Met Reemired Renartine Cantents f B. Radioactive Effluent Releases I i B-1. Liquid Ef fluent Release Summary j 2. Tritium (Regulatory Guide 1.21 Appendia B. Section C) (Cont.) Quarterly sums of total curies of tritium a. tietermined to be released in liquid ef fluents b. Average concentrations (uCl/ml) of tritium released in liquid effluents to unrestricted areas, averaged over the quarterly periods covered by the report c. Percent of appilcable Ilmit of average concentra-tions released to unrestricted areas, i.e., percent / at of 3 m 10-3 uCl/ml. Include the limit and the y h bases in the supplemental report information 3. Dissolved and Entrained Gases (Regulatory Guide 1.21 Appendia B. Section C) Quarterly sums of total curies of gaseous a. l radleactive material determined to be released l in liguld effluents b. Average concentrations I.uCl/el) of dissolved and entrained gaseous radioactive material released to unrestricted areas. averaged over the guarterly periods covered by the report c. Percent of technical specification limit of average concentrations released to unrestricted areas. Include the limit used and the bases in the supplemental report information h un o d. Quarterly sums of total curies for each of the 7 radionuclides determined to be released as on dissolved and entrained gases in liquid effluents l 4 l l 9 /J-M-1( ot:
TAOLE l'-2. CHECKLIST FOR SENIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Cont.) Plant Nase: Rancho Seco Nuclear Generating Station Report Period: 91-01-84 to 6-30-84 Part I - Rautine Remartina Reeuls;. att Information in Licename's Submittal Not Not Applicable / Resortine Centents Complete Partial Addressed _Nat Reenired B. Radioactive Effluent Releases B-1. Liguld Effluent Release Summary 4. Alpha Radioactivity (Regulatory Guide 1.25 Appendia 8. Section C) ,v/ Quarterly sums of total curies of gros! alpha-emitting material determined to be released in liquid effluents 5. Volumes (Regulatory Guide 1.21. Appendim 9. Section C) Quarterly sums, in liters, of total measured volume. a. prior to dilution, of liquid effluent released b. Quarterly sums of total determined volume. in / liters, of dilution water used during the period / l
- ,s of the report 5'
Estimates of the total error associated with i c. certain total values should be provided in each report. These error values should be the best / effort at an overall estimate of the errors g/ associated with the totals in the report I B-2. Gaseous Ef fluent Release Summary 1. Gases (Regulatory Golde 1.21. Appendia B. Section B) a. Quarterly. sues of total curies of fission and activation gases released b. Average release rates (uCl/sec) of fistion and d activation gases for the quarterly periods covered 5d by the report 6$ =, LM u 9 i J ),I-ff~~ f k f rat e: o
CMECKLIST FOR $[MIANNUAL RA010ACTivt EffLUEET RELEASE REPORT (Cont.) TABLE F-2. Rancho seco Nuclear Generating Station Report Period: 01-01-84 to 6-30-84 Plant Name: Part 1 - Rautine :: -tina R m irez nts Informatlan in Licensee's " Ittal Not Not Applicable / Comolete Partial Addressed _Nat Reauired R oortina Centents J B. Radioactive Effluent Releases I B-2. Gaseous Ef fluent Release Summary Gases (Regulatory Guide 1.21 Appendix 8. Section 81 1. Percent of technical specification limit forThis c. releases of fission and activation gases. should be calculated in accordance with technical specification limits Quarterly sums of total curies for each of the d. radionuclides determined to be released, based on analyses of fission and activation gases. The data should be cater 9erized by (I) elevated releases, batch and continuous modes, and (2) ground-level releases, batch and continuous modes. (Tables 18 and IC of Regulatory 7, Guide 1.21) e-as Iodines (Regulatory Guide 1.21 Appendix 8. Section 8) 2. Quarterly suas of total curies of iodine-131 a. released b. Average release rate (uCl/sec) of iodine-131 Percent of technical specification limit for c. __ y iodine-131. Quarterly sums of total curies of each of the d. isotopes, iodine-131, iodine-133, and iodine-135 +4 determined to be released. (Tables 18 and IC Q of Regulatory Guide 1.21) 63 2 4. 5 //-/[ _f/I Date: .~.-
~ ~ ~ ~ ^ ~ ~---~ ~-~-~ CHECKLIST FOR $[NIANNUAL RA0104CTIVE EFFLUENT RELEASE REPORT (Cont.) TABLE F-2. Rancho Seco Nuclear Generating Station. Report Period: 91-01-84 to 6-30-84 Plant Name: I Part I - Deutine Resortine h ireewnts Infr..m tlan in Llrennee's " !ttal Not Not Appilcable/ CamRltit Partial Addressed __Not Reemired R Portine Centents t r B. Radioactive Effluent Releases B-2. Gaseous Ef fluent Release Susanary Particulates (Replatory Guide 171, 3. } Appendia 8, Section 8) i Quarterly sums of total curies of radioactive a. j material in particulate form with half-lives greater than 8 days determined to be released / Average release rate (uCl/sec) of radioactive f b. material in particulate form with half-lives greater than 8 days Percent of technical specification Ilmit for c. radioactive material in particulate form with half-Ilves greater than 8 days 7 Quarterly suas of total curies for each of the w I' d. radionoclides in particulate form determined to be / released based on analyses performed. (Tables ,V 18 and it of Regulatory f;ulde 1.21) Quarterly suas of total curies of gross alpha e. radleacttwity determined to be released Tritium (Regulatory Guide 1.21, Apndia 8, Section B) 4. Quarterly sums of total curies of tritium a. determined to be released in gaseous effluents i b. Average release rate (uCl/sec) of tritium A5 2 .L$ i i //~N'- 8A I l w e:
l TA8tE F-2. (HECKLl5T FOR SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Cont.) plant Name: Rancho Seco Nuclear Generating Station Report Periodt 01-08-84 to 6-30-84 l l 1 Part I - Routine Renartina Reauir -..ts Information in Licensee's hbalttal Not Not Applicable / Comolete Partial Addressed _Not Reauired ECPortina Contents 8. Radioactive Effluent Releases B-2. Gaseous Effluent Release Summary 4. Tritium (Regulatory Guide 1.21 Appendia 8, Section B) Percent of appropriate technical specification or c. MPC limits for tritium Estimates of the total error associated with certain total values should be provided in each report. (Table 2A of Regulatory Guide 1.21.) These error values should be the best ef fort at an overall estimate of the errors associated with the totals in the report Is the Subject __ Reported in the submittal? If Yes, Ih Not Applicable / Information in Licensee's SubyJ1Lgl Reportino Contents
- Ygi,
,,Mg. Not Reauired Comolete Partial co H. Radioactive Effluent Releases H-4. Unplanned Effluent Releases Did any of the following unplanned releases occur during the report period? / 1. Liquid Raleases 2. Gaseous Releases if any unplanned releases occurred, the report shall include a list and description b et 'he release (s) 8 a 0 e e //-//' M o.u e:
e CHECKLIST FOR SENIANNUAL RADI0ACTIvt EFFLtKNT RELCASE REPORT (Cont.) TABLE F-2. Rancho Seco Nuclear Generating Station Report Period: 01-01-.84 to 6-36-.84 Plant Name: l Part I - Routine 2;;:-tine Resul.a;;ts l Information in Licensee's ^- M ital Not Not Applicable / Comolete Partial Addressed Not Resuired R_gportina fantents E. Solid Radioactive Waste The semiannual total quantity in cubic meters and 1. the semiannual total radioactivity in curies for the categories or types of waste. (Requiatory Guide 1.21 4/ Table 3) Spent resins, filter sludges, evaporator bottoms . A^t ) a. v Dry compressible waste contaminated equipment, etc.
- t )
b. [ ((A) Irradiated components control rods, etc. _p c. 3r d. Other (furnish description) An estimate of the major nuclide composition in the 2. waste categories, taegulatory Guide 1.21 7 Appendia 8. Section D) The disposition of solid waste shipments. (Identify e* 3. the number of shipments, the mode of transport, and the destination.) (Regulatory Guide 1.21 l Appendia 8. Section D) 4. The disposition of irradiated fuel shipments, f (Identify the number of shipments, its mode of i transportation, and the destination.) (Regulatory I Guide 1.21. Appendia 8. Section D) J provide the following information for each class of 5. solid waste (as defined by IOCFR Part 61) shipped offsite during the report period: h Container volume, in liters h a. b. Total curie quantity (specify whether determined e by measurement or estimate) E a. e l)-l$~ f b Date:
CHEfELIST FOR SEMIANNUAL RA010 ACTIVE EFFLUECT RELEA'5E REPORT (Cont.) TABLE F-2. Rancho Seco Nuclear Generating Station Report Period: 01-01-8d to 6-30-8d l l Plant Name: Part I Rautine Renartina teensi. a nts J Infe.= tian in Licaname's '-- H ilal 3 Not Applicable / Not Complete Partial Addressed _Nat Reenaired R_egertina Cantants C. Solid Radioactive Weste (Cont.) Provide the following information for each class of 5. solid waste (as defined by 10CTR Part 61) shipped offsite durirg the report period: Principal radionuclides (specify whether determined c. by measurement or estimate) d. Source of weste and processing employed (e.g., dewatered spent resin, compact dry waste. evaporator bottoms) ,[ Type of container (e.g.. L5A. Type A. Type 8 v e. Large Quantity) f. Solidification agent or absorbent (e.g., cement. urea formaldehyde) y (NUREG-Od72/Od73. 6.9.1.12) wo Estimates of the total error associated with certain 6. total values should be provided in each report. These error values should be the best ef fort at an overall estimate of the errors associated with the totals in the report (Table 3 of Regulatory Guide 1.21) Radiological Dese Assessment D. IRegulatory Guide 1.21. Appendix 8. Section El Total body and significant organ deses to individuals 1. in unrestricted areas from receiving-water-related esposure pathways Total body and skin deses to individuals esposed at b 2. the point of manimum offsite ground-level concentrations of radioactive materials in gaseous effluents E E //-/[- [ tiat e: ~ ~ ' ~
--mm en-mamm ammmme m CHECKLIST FOR SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT (Cent.) TABLE F-2. Rancho Sece Nuclear Generating Station Report perled: 91-41-8d to 6-30-84 Plant Name: part I Ramatine amanettaa Reansle-----it Infe-a- tlan in t l e ----'s
- ' -l ttaf Not Not Applicable /
Casalete Partial Addressed Nat Reauired Reportine fantents Radiological Dese Assessment D. (Regolatory Guide 1.21, Appendir 8, Section E) Organ deses to Individuals in unrestricted areas 3. from radioactive ledine and radioactive material in particulate form from all pathways of esposure Total body deses of individuals and populations in 4. unrestricted areas from direct radiation frons the faci 15ty / Total body deses to the population and average doses to individuals in the population from all / 5. receiving-water-related pathways 6. Total body deses to the population and average deses to individuals in the population f rom gaseous effluents to a di-tance of 50 miles from the site. If a significantly large populatten area is located M O just beyond 50 elles from the site, the dose to this w populatten group should be considered Total deses to the most esposed MEDGER OF THE PUBLIC 7. from reactor releases and other nearby uranium fuel cycle sources Meteorelegical Data
- 8.
(Regulatory Guide 1.23 and Tables 4A and 48 in Appendiu 8 of Regulatory Guide 1.21) iThe report should include the cumulative joint frequency distribution of wind speed, wind direction, and atmospheric stability for the guarterly periods. Similar data should be reported separately for the meteorological conditions during batch releases.) g
- In lieu of submitting data to the NRC, the Licensee may retain this summary of required meteorological data on site i
e I in a file that should be provided to the NRC upon request. l l //-/s-It; on :
TABLE F-2. CHEEKLIST FOR SEMIANNUAL RA010 ACTIVE EFFtUENT RELEQ5E REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 6-30-84 Part 11 - 5:::rtina -li__ ts Sub_ lect te Conditions i is the Subject Resorted in the inhalttal? If Yes, Not Applicable / Inf: = tian in Licensee's * ' ittal Reportina Cantents Igi. .Mg. _Not Reauired commlete Partial A. Monitoring Instrumentation Esplanation of why inoperability was not corrected in a timely manner for: 1. Liguld Effluent (NUREG-0472/0473, A Specification 3.3.3.10) 2. Gaseous Ef fluent (NUREG4472/0473, [ g Specification 3.3.3.11) B. Radioactivity inventory (NUREG-0472/0473, Specification 3.11.1.4) Description of event (s) leading to exceeding gk curie limit for liquid holdup tanks "s Radiological Environmental Monitoring Program s. 1. Sampling Relocation (NUREG-0472/0473, Specification 4.11.2) o Causes of unavailability of allk and [ g& fresh leafy vegetable samples o Revised figure (s) and table for the g 00CM reflecting t** new location (s) Nb o Identification of the new location (s) 2. Land Use Census (NUREG-0472/0473, Specification 3.12.2) o identification of the new location (s1 6 as a result of land use census vi us E [h) o Revised figure (s) and table for the 4 00CM reflecting the new location (s) us as a result of land use census w 9 e e /)-/[- N b in.s e e :
CHECKLIST FOR SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Cont.) I TABLE T-2. Rancho Seco Nuclear Generating Station Report Period: 01-01-84 to 6-30-84 plant Name: Part II
- rrtine Reautrementt Subject to Canditions Is the Subject If Yes.
_ Reported in the Submittal? Information in Licensee's Subelttal Not Applicable / Iti_ _Ng_ .Hg1_Rtquired__ _.__Comolete Partial Reportine Centents D. Licensee-Initleted Changes to the PCP/0DCM/Radwaste 1. PCP (NUREG-0172/0473. Specification 6.13) o Rationale for changes Compliance with eulsting PCP criteria o i Review ard acceptance by the plant [ l o Unit Review Group (URG) 2. 00CM (NUREG-0472/0473 Specification 6.14) i Rationale for changes [ f o Compliance with eulsting ODCM 7 o criteria w Review and acceptance by the e plant URG 3. Radweste Systems (NUREG-0472/9473, Specification 6.15) Detailed rationale for changes o Compilance with 10CFR50.59 o Review and acceptance by the [ o i plant tRG H N b
- No change made during period. (NA) ui
- fo be reported in
.(NR) per E I //-/f-RJ n tr: \\
TA8LC F-2. CMECKLIST FOR SEMIANNUAL RADIOACilvE EFFLUENT RELEASC REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 91-01-84 to 6-30-84 Part lif - Other Saecial RETS ~; elated Resortina Commitments of the Licensee
- Is the Subject Resorted in the submittal?
If Yes, NJt Applicable / Infe.m tlan in Licensee's ' ^ ittal i Reportina Cantents 181_ _f!R_ tiet Reauired Commlete Partial l
- The requirements are those of the Licensee's RETS-related reporting comunitments which are dif ferent f rom those of the model RETS.
Footnotes: Instead of reporting semiannual results of the solid radwaste shipment, the Licensee reported only the annual ? a. re alts. u* b. The Licensee indicated that the new locations identified, and the revised map will be incorporated into the 00CM for 1985 reports. As the Licensee is in the process of changing the vendor, the reviewer is instructed by the NRC staf f not to review c. the Licensee's current PCP and its revisions. e-a N A3 ? a.5 e //-/ E. N n... H o
~ a=== ,,s I TABLE F-3. CHECKLIST FOR SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT
- plant Name: Rancho Seco Nuclear Generating Station Report Perled: 97-41-84 to 12-31-84 l
l Part 1 - O wtine "-- riina Reemis u nts J Inf;;r=tlen in Lir---- 't " " Ittal Not Not Applicable / l Catnolete partial Addressed Nat Reeuired Resortine Centents A. Supplemental Report Information Technical Specification limits for radioactive I 1. materials released in liquid and gaseous ef fluents IRegulatory Guide 1.21. Appendia 8. Section A) Maulmum permissible concentrations (MPCs) used in 2. determining allowable release rates or concentrations i IRegulatory Guide 1.21. Appendia 8. Section Al a. Fission and activation gases: b. Iodines: Particulates, half-lives greater than 8 days: c. j d. Liquid effluents: s e U 3. Average energy (E) of the radionecilde sluture in releases of fission and activation gases (Regulatory Guide 1.21. Appendia 8. Section A) Methods used to determine effluent total radioactivity. d. l the radionocilde composition, and overall errors in measurement (Regulatory Guide 1.21. Appendia 8. Section Al a. Fission and activation gases: b. Iodines: /, ) c. particulates: j / d. Liquid ef fluents: b 4 m o
- Licensee's specific title if o!'f a-ent:
e Annual Radiological Report T,he Licensee reported the RETS-related information under only one report, the Annual radiologic w-a Note: m. 1 //-/ 8-N osc: i
TA8LE F-3. CHECKLIST FOR SENIANNUAL RADIDACTIVE EFFLUEIT RfLEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 07-0l-84 to 12-31-84 Part I - Rautine I:22-tina E m le m.tn Information in t.icensee's %hmittal Not Not Applicable / Casalete Partial Addrened Nat aeauired Renartina Cantents A. Supplemental Report Infarma(ion (Cont.) 5. Information relating to batch releases of radioactive materials in Ilguld and gaseous effluents (Regulatory Guide 1.21. Appendia B. Section A) a. Liquid
- 1. Number of batch releases:
- 2. Total time period for batch releases:
- 3. Naulmum time period for a batch release:
e/
- 4. Average time period for batch releases:
- 5. Minimum time period for a batch release:
4
- 6. Average stream flow during period of release
_f of effivent into a flowing stream: v m b. Gaseous
- 1. Number of batch releases:
s" V
- 2. Total time period for batch releases:
- 3. Naminum time period for a batch release:
- 4. Average time period for a batch release:
,L
- 5. Minimum time period for a batch release:
[ g n 6. Abnormal Releases (Regulatory Guide 1.21. Appendin B. (I) Section A) a. Liquid g e*
- 1. Number of releases:
//
- 2. Total activity released:
ll-/[ Ib p.s w .~.
~ . - ~ ~. -v CHECKLIST FOR SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT (C9nt.) TABLE F-3. Ranche Sete Nuclear Generating Station Report perled: 97-01-84 to 12-31 44 plant flame: Part 1 - Rautine - --thne Remirements Infe m tlan in tirr-m 's '- M ital Not Not Appilcable/ CARRlaia Partial Addressed Nat Resulred Reportine fantents Supplemental Report Information A. Abnormal Releases (Regulatory Guide I.21. Appendiu 8 6. Section A) (Cent.) b. Gaseous
- 1. Mus6er of releases:
- 2. Total activity released:
R. Radioactive Effluent Releases B-l. Liquid Ef fluent Release Summary Mixed Fission and Activation products I. (Regulatory Guide 1.21. Appendia 8. Section Cl Quarterly sums of total curies of radioactive
- 's 8
a. material determined to be released in liquid U effluents (not including tritium, dissolved and entrained gases, and alpha-emitting material). (fable 2A of Regulatory Guide 1.21) Average concentrations (vCl/m1) of mined fission b. and activation products released to unrestricted areas, averaged ever the guarterly periods covered by the report Percent of appilcable Ilmit of average concentra-c. tiens released to unrestricted areas. Include the limit used and the bases in the supplemental report information Quarterly sums of Letal curies for each of the h d. radionuclides determined to be released in liquid E e effluents, based en analyses performed. Data should be separated by type of release mode. i.e., continuous or batch w-t /Nt-14 na. : 4 '"~
IABLE F-3. , CHECKLIST FOR SEMIANNUAL RADI0 ACTIVE EFFLUE%f RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating $tation Report Period: 07-01-84 to 12-31-84 Part 1 Rautine h==rtine ":2_ l i x.- t t Infs.ation in Licename's 'Alttal Not Not Applicable / Camelete Partial Addressed Not Reeuired groortina Centents B. Radioactive Effluent Releases B-1. Liguld Ef fluent Release Susanary 2. Tritium (Regulatory Guide 1.21, Appendia 8, Sectlen C) (Cont.) Quarterly sums of total curies of tritium a. determined to be released in liquid effluents b. Average concentrations (uCl/ml) of tritium released in liquid effluents to unrestricted areas, averaged over the quarterly periods covered by the report percent of applicable limit of average concentra-c. tiensrelegsedtounrestrictedareas,i.e., percent 10- uCi/m1. Include the limit and the of 3 x 7 bases in the supplemental report information so 3. Dissolved and Entrained Gases (Regulatory Guide 1.21 Appendia 8, Section C) Quarterly sums of total curies of gaseous a. radioactive material determined to be released in liquid ef fluents b. Average concentrations (uCi/ml) of dissolved and entrained gaseous radioactive material released to unrestricted areas, averaged over the guarterly periods covered by the report percent of technical specification limit of c. average concentrations released to unrestricted t areas. Include the limit used and the bases in ,0 the supplemental report information un d. Quarterly sums of total curies for each'of the g s radionucildes determined to be released as dissolved and entrained gases in liquid effluents I e u //-/f-ES va ;
CHECKLIST FOR SEMI ANNUAL RADIDACTIVE EFFLLENT RELEASE REPORT (Cont.) TABLE F-3. Rancho Seco Nuclear Generating Station Report Period: 87-81-8d to 12-31-84 Plant Name: .l l Eart I - Rautine 5- :-tina Resulia..tt Infermation in tiraname's * '-lttal Not Not Applicable / Comolete Partial Addressed Nat Reautred _ RfPortina Centents R. Radioactive Effluent Releases 8-1. Liguld Ef fluent Release Summary Alpha Radioactivity (Regulatory Guide 1.21 4 Appendia 8, Section Cl Quarterly sums of total curies of gross alpha-emitting material determined to be released in liquid effluents Volumes (Regulatory Guide 1.21 Appendl= 8, Section C) I 5. Quarterly sues In 11ters, of total measured volume, prior to dilution, of liquid effluent released a. Guarterly sums of total determined volume, in b. liters, of dilution water used during the period M of the report I Estimates of the total error associated with e certain total values should be provided in each c. These error values should be the best report. effort at an overall estimate of the errors assotiated with the totals in the report p-2. Gaseous Effluent Release Summary Gases (Regulatory Guide 1.21. Appendl= 8, Section 8) 1. i Guarterly sees of total curies of fission and a. activation gases released l Average release rates (uCi/seci of fission and l activation gases for the quarterly periods covered h f b. by the report i R A S l 9 l I ,h/hfd rute:
TA8LE F-3. CttECKLIST FOR SEMIANNUAL RADIDACTIVE EFFLUECT RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Perled: 87-41-84 to 12-31-84 i i i Part T - Reastine " rr-tina L_ I r;;.;.;ts i Infe. a tlan in tirentas's * '-iltal Not Not Applicable / Canelate Partial Addressed hat Reassired R p rtina Centents i. B. Radioactive Effluent Releases 1 8-2. Gaseous Effluent Release Summary 1. Geses (Regulatory Guide 1.21, Appendia 8. Section 8) 4 c. Percent of technical specification limit for releases of fission and activation gases. This shovid be calculated in accordance with technical specification limits d. Quarterly sums of total curies for each of the radionuclides determined to be released, based on analyses of fission and activation gases. The data should be catergerized by (1) elevated ) releases, batch and continuous modes, and (2) 9round-level releases. batch and continuous l' modes..(Tables 18 and IC of Regulatory q j Guide 1.21) o 2. Iodines (Regulatory Guide 1.21. Appendia 8. Section el a. Quarterly sums of total curies of iodine-131 released b. Average release rate (uCi/sec) of iodine-131 c. Percent of technical specification limit for [ i iodine-131. V i I' d. Quarterly sums of total curies of each of the I isotopes, lodine-131. todine-133 and iodine-135 j determined to be released. (Tables 18 and IC of Regulatory Guide 1.21) A3 l 2a 4 5 l 1 i i H-/T-H o.a n e j l
~ O CHECKLIST FOR SEMIANNUAL RAO!0 ACTIVE EFFLUENT RELE'ASE REPORT (Cont.) TABLE F-3. Rancho Seco Nuclear Generating Station Report Period: ST-01-84 to 12-31-84 plant Name: l Part I - Rautine "----tine Resuli _ --it Information in tirre__ 's * * ! ital i e Not Not Applicable / Comotete Partial Addressed Not Reeuired R portina Centents f B. Radioactive Effluent Releases I B-2. Gaseous Ef fluent Release Summary I l 3. Particulates (Replatory Guide 1.21 Appendia 8. Section 8) Quarterly sums of total curies of radioactive a. material in particulate form with half-lives 9reater than 8 days determined to be released Average release rate (uCl/sec) of radioactive ,/ I b. material in particulate form with half-lives V greater than 8 days Percent of technical specification limit for i c. radioactive material in particulate form with half-lives greater than 8 days
- 'tb Quarterly sums of total curies for each of the d.
radionucildes in particulate form determined to be released based on analyses performed. (Tables 18 and it of Regulatory Guide 1.21) l Quarterly sums of total curies of gross alpha e. radioactivity determined to be released 4 Tritium (Regulatory Guide 1.21. Appendim 8. Section 8) Quarterly sums of total curf es of tritium a. determined to be released in gaseous effluents i b. Average release rate tuCi/sec) of tritium A i i Cn A 1 //-/ /-/( i- ) n.:
TA8tE F-3. CHtERLIST FOR SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Period: 07-01-84 te 12-31-84 Part I - Reistine M w rtine Ermira_ ;.it Information in Licensee's
- M ttal Not Not Applicable /
Resortina Cantents Canalete Partial Addressed Nat Reenaired B. Radioactive Ef fluent Releases B-2. Gaseous Effluent Release Summary I 4 T'ritium (Regulatory Guide 1.21. Appendia 8. Section B) c. Percent of appropriate technical specification or l MPC limits for tritium Estimates of the total errer associated with certain total values should be provided in each report. (Table 2A of Regulatory Guide 1.21.1 These error values should be the best effort at an overall estimate of the errors associated with the totals in the report is the Subject Resorted in the submittal? If Yes, j y Not Applicable / Informatian in Licensee's Labat tial I w l Ygi_ _!!a_ Not Reauired ra==lete Partial I N Resortina Cantents R. Radioactive Effluent Releases 1 H.l. Unplanned Ef fluent Releases 2 Did any of the following unplanned releases occur during the report period? 1. Liquid Releases 4 2. Gaseous Releases i If any unplanned releases occurred, the j report shall include a list and description 7 i of the release (s) n0 2 a$ i j //,if fL
m M h h h TA8tE F-3. CHECKLIST FOR SEMIANNUAL RADl0ACilvt EFFLUENT llELEASE REPORT (Cont.) e plant Name: Rancho Seco Nuclear Generating Station Report period: 87-41-84 to 12-31-8d Eart I - Rautine 5:::rtine fee i. _ nts Inferation in Lir_m_e's * ':ttal Not Not Applicable / Casalete partlal Mdressed Not Reeuired l ReporLine Centents i C. Solid Radioactive Waste I 1. The seelannual total quantity in cubic meters and the semiannual total radioactivity in curies for the categories or types of waste. (Regulatory Guide 1.21 (4) Table 3) Spent resins, filter sludges, evaporator bottoms a. b. Dry compressible waste, contaminated equipment, etc. c. Irradiated components, control rods, etc. d. Other (furnish description) 2. An estimate of the major nuclide composition in the waste categestes. (Regulatory Guide 1.21, 7 Appendia 8. Section D) 3. The disposition of solid waste shipments. (Identify the number of shipments, the made of transport, and the destination.) (Regulatory Guide 1.21 [ Appendia 8. Section D) 4. The dispositten of irradiated fuel shipments. / (Identify the number of shipments, its mode of transportation, and the destination.) (Regulatory y Guide 1.21. Appendia 8. Section D) 5. provide the fellowing information for each class of i solid waste (as defined by 10CFR part 61) shipped offsite during the report period: 5d a. Centainer volume, in liters h an 'I b. Total curie quantity (specify whether determined ta i j by measurement or estimate) o I S k //-/r-// ni: l
t i Ta8LE F-3. CHECKLIST FOR SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Cont.) Plant Name: Ranche Seco Isuclear Generating Station Report Period: 07-01-84 to 12-31-44 4 Part I - Rautine Renartina Reauir w c.ts Infer =:tian in Lirmaame's * " ttal l Not Not Applicable / Resortina Cantants Canalete Partial Addressed . pent Reauired C. Solid Radioactive Waste (Cont.) l 5. Provide the following information for each class of solid weste (as defined by 10CFR Part 61) shipped of fsite during the report period: c. Principal radiensclides (seecify whether determined by measurement er estimate) d. Source of waste and processing employed (e.g., I dewatered spent resin, compact dry waste. l evaporator bottoms) I e. Type of container (e.g., LSA Type A. Type 8, ,/ Large Quantity) Y i f. Solidification agent er absorbent (e.g., cement, 1 urea f.r.aueh,de) (NUREG-8472/9473, 6.9.1.12) j 6. Estimates of the total error associated with certain I total values should be provided in each report. These error values should be the best effort at an / 1 I everall estimate of the errors asseclated with the / l totals in the report (Table 3 of Regulatory Guide 1.21) l l D. Radiological Dese Assessment ) IRegulatory Guide 1.21 Appendin B, Section E) 1 I 1. Total body and significant organ deses to individuals in unrestricted areas from receiving-water-related empesure pathways l 2. Total body and skin deses to individuals exposed at b the point of monimum offsite ground-level concentrations of radleactive materials in gaseous effluents o I I. i i I l //-/[ ft[ p...
e CHECKLIST FOR SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT (Cont.) TABLE F-3. Plant Name: Rancho Sete Nuclear Genirating Station Report Period: 07-01-84 to 12-31-84, Part f - Reentine Reeartina t _f. x xts Information in Licename's Summittal Not Not Applicable /~ Complete Partial Addressed Not Reenaired R p rtine Cantents D. Radiological Dose Assessment IRegulatory Gs:Ide 1.21 Appendl= 3. Section E) Organ doses to individuals in c. restricted areas .,[ 3. from radioactive iodine and radioactive material in V particulate form from all pathways of esposure a Total body doses of individuals and populations in, ,[ 4 unrestricted areas from direct ndiation f rom the 3 V \\ e facility Total body doses to the population and average -l# i 5. doses to individuals in the population f rom all 4 i s c receiving-water-related pathways 6. Total body doses to the population and average s desirs to individuals in the population f rom gaseous etfluents to a distance of 50 miles from the site, i If a significantly large populathn area is _tocated /, y just beyond SS su es from the site, the M i to this a population group should be ceasierred Total' deses to the most exposed MEHt M OF THE PUBLIC t 7. from reactor releases and other nearby wranium fuel cycle sources } Meteorological Data
- B.
(Regulatory Gvide 1.23 and Tables 4A and 48 in Appendix 8 of e Regulatery Guide 1.21) (The report should include the cumulative joint frequency distribution of wind speed, wind direction. and atmospheric 1 N stability for the guarterly periods. Siellar data should he repoded separately for the metecrological conditions 7 s
- D
~ -h during batch releases.) w
- In lieu of submitting data ti the NRC, the Licensee may retain this summary of' required meteorological data on site in a file that should be provided to the NRC upon request.
,. f f l i ~ O hs //-/ T-M nate: ~i _ _ 7,. 4 9 f = 9,
L, Qx = e j-4- TAGLE F-3. CHECEM,fet MMIANNUAL EAOt0 ACTIVE EFFLUENT RELEASE rep 0RF(Cont.) I Plant Name: Rancho fece Nuclear Generating Station Report Paried: 07-01-84 to 12-31-84 k Part II "-- _-tina em !rmeents h biert ta Canditlans It the Sub act '/ Resorted {n the 11 - If Yps, 4 ~ ~ Met Applicas.te/ Informatian Ir. ti mum h ' Alttal ~ Renartina Caetanta h A A t Reauired g Commlete partial A. Monitoring Instrumentation ^ E=planation of why inoperability was not l corrected in a timely manner for: l 1. Liquid Ef fluent (InfREG-8472/0473. g4 Specific:, tion 3.3.3.10) i '~ [ g l Specification 3.3.3.11) 2. Geseems If fluent (NUREG-8472/0473, ] B. Radioactivity Inventory (IRREG-0472/0473, l Specificatica 3.11.1.4) i Description of event (s) leading to exceeding g( curie limit for liquid heldue tanks M j (. Radielegical Environmental Monitoring Program 1. Sampilng Relocation (NUREG-0472/0473 j 5pecification 4.11.2) o Causes of unavailability of milk and g[ fresh leafy vegetable samples o Revised figure (s) and table for the 00CM reflecting the new 13 cation (s) o Identification of the new location (s) Mk i i 2. Land Use Census (NUREG-0472/0473. Specification 3.12.2)
- 4 N
o Identification of the new location (s) 6 as a result of land use census e w l o Revised figure (s) and table for the h) E I 00CM reflecting the new location (s) a as a result of land use census m w e nate: /H f-f4 i
TA8tC F-3. CHECKLI$f FOR SEMIAIRIUAL RADISACflVC EFFLUDri SELEASF REPORT (Cont.) plant Name: Rancho Seca Nuclear Gener: ting St:tlen Report period 97-01-84 to 12-31-84 Part II - Resortlan Reentr-ats hblect to Canditlans IstheSubject ttal? If veg, _ Resorted in the Not Applicable / Informatlam in Licensges * '-lttal R_eportine Centents Yti_ _ lit Not Resulred___ Commlete _ Partial I D. Licensee-Initiated Changes to the PCP/0DCN/Radwaste I. PCP (IIUREG-0472/0473. Specificatrt,e o.13) e Rationale for changes M o Compilance with entsting PCP criteria o Review and acceptance by the plant Unit Review Group (URG) r 2. ODCM (NUREG-0472/0473, Specification 6.14) e Rationale for changes y criteria _ _ _ _g e Compliance with eulsting ODCM a w" o Review and acceptance by the plant URG 3. Radweste Systems (NUREG-0472/0473 Specification 6.15) e Detailed rationale for changes e Compilance with 10CrR50.59 ) e Review and acceptance by the / plant URG jL,_
- No change made during period. (NA) g "To be reported in
,o ve per .(NR) g ek 5 //-//,F6 nt:
TABLE F-3. CHEfRLIST FOR $ENIANNUAL RA910 ACTIVE EFFLUENT RELEASE REPORT (Cont.) Plant Name: Rancho Seco Nuclear Generating Station Report Perled: 07-41-84 to 12-31-84 Part III - Other Saecial MT1-Related Romertina femmitments of the Licensee
- Is the $vbject Remerted in the Subelttal?
If Yes. Not Applicable / Infe m ilan in Licensee's ' 'ittal R_gpartina Centents Ygi. _ha_ Not Reauired ..Commlete Partial
- The requirements are those of the Licensee's RETS-related reporting commeitments which are dif ferent from those of the model RETS.
Footnotes: a. Instead of reporting semiannual results of the solid radwaste shipment, the Licensee reported only the annwel y i results. W b. The Licensee indicated that the new locations identified, and the revised map will be incorporated into the 00CN for 1985 reports, As the Licensee is in the process of changing the vendor, the reviewer is instructed by the NRC staf f not to review t. the Licensee's current PCP and iti revisions. 6 A:: Ran l //-/E-SC oale: _..., _ _}}