ML20216G804
| ML20216G804 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1997 |
| From: | Redeker S SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| MPC&D-98-053, MPC&D-98-53, NUDOCS 9804200492 | |
| Download: ML20216G804 (76) | |
Text
g e
4AUsuun SACRAMENTO MUNICIPAL UTIUTY DISTRICT C 6201 S Street. P.o. Box 15830, Sacramento CA 95852 1830,1916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA MPC&D 98-053 March 26, 1998 U. S. Nuclear Regulatory Commission Attn: E. W. Merschoff, Regional Administrator Region IV Parkway Central Plaza Building 611 Ryan Plaza Building, Suite 400 Arlington, Texas 76011-4085 Docket No. 50-312 Rancho Seco Nuclear Station License No. DPR-54 1997 RANCIlO SECO ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
Dear Mr. Merschoff:
Enclosed is the Rancho Seco 1997 Annual Radiological Environmental Operating Report (AREOR). The enclosed repon contains the information required by Rancho Seco Permanently Defueled Technical Specification (PDTS) D6.9.2.3, " Annual l
Radiological Environmental Operating Report."
Members of your staff requiring additional information or clarification may contact
)
Mr. Steve Nicolls at (916) 452-3211, extension 4292.
Sin
/
A
]g2 C
/
th teve J. Redeker Manager i
Plant Closure & Decommissioning Enclosure cc w/atch:
Document Control Desk, NRC, Washington D.C. 20555 R. Dudley, NRC, Rockville 9804200492 971231 PDR ADOCK 05000312 R
PDR RANCHO SECO NUCLEAR GENERATING STATION D 14440 Twir, Cities Road, Herald, CA 95638-9799;(209) 333 2935
AXNEAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT cW ob s.,
m.e
.. _,. i y JANUARY -- DECEMBER 1997 Rancho Seco Nuclear Station Herald, California License Number DPR-54
1997 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT t
TABLE OF CONTENTS TABLE OF CONTENTS..
...................I Ll ST O F FI G U R ES.................................................................
..................................11 LIST OF TABLES.............................................................................................................ill
- 1. EXEC UTIVE S UM MARY...........................................................
.................................1
- 11. LAN D US E C EN S US..................................................................
......................................2 111. RADIOLOGICAL IMPACT EVALUATION...................................................................................... 2 PREDICTED POTENTIAL RADIOLOGICAL IMPACT...........................
............................2 FU EL CYCLE DOSE EVALUATION.................................................................................. 3 OBSERVED POTENTIAL RADIOLOGICAL. IMPACT................................................ 3 IV. PROGRAM ANALYSIS RESULTS
SUMMARY
.................................................................... 6 IV-A. ATMOSPHERIC MONITORING............
....................................................6 IV-B. DIRECT RADIATION MONITORING...........
............................................7 IV-C. TERRESTRIAL MONITORING................................
.........................7 IV-D. AQUATIC LIFE MONITORING.................................
....................8 I V-E. WATER M O N ITORI NG........................................................
.......9
)
- v. R E F ER E N C E S.......................................................................
........................................18 i
l VI.
APPENDICES................................................................................................................19 1996 LAN D US E CEN SUS RESULTS..................................................................... A-1 SAMPLE SITE DESCRIPTIONS AND MAPS........................................................ B-1 QUALITY CONTROL SAMPLE ANALYSIS RESULTS................
.........................C-1 SAMPLE COLLECTION AND ANALYSIS METHODS......................
........................D-1 ENVIRONMENTAL MONITORING PROGRAM DESIGN............................................... E-1 1997 SAMPLE ANALYSIS RAW DATA TABLES...............
.........................F-1 1 G 97 M I S S E D SAM PLE R EPORT....................................................................... G-1 1
Rancho Seco Nuclear Station i
1997 AREOR
I LIST OF FIGURES FIGURE TITLE PAGE FIGURE B 1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ON AND NEAR THE SITE B-3 FIGURE B-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN 1 MILE FROM THE REACTOR BUILDING B-4 FIGURE B-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE REACTOR BUILDING B-5 FIGURE B-4 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS S TO 25 MILES FROM THE REACTOR BUILDING B-6 Rancho Seco Nuclear Station il 1997 AREOR
4 LIST OF TABLES TABLE TITLE PAGE 1
1997 LIQUID EFFLUENT PATHWAY POTENTIAL DOSE COMPARISON 5
2 ENVIRONMENTAL RADIO 8.OGICAL MONITORING PROGRAM ANNUAL
SUMMARY
10 B-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS B-7 C-1 1997 INTERLABRATORY COMPARISON PROGRAM C-4 E-1 REPORTING LEVELS FOR RADIOACTIVIT( CONCENTRATIONS IN ENVIRONMENTAL SAMPLES E-10 E-2 MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES E-11 F-1 1997 WEEKLY AIR SAMPLE
SUMMARY
F-2 F-2 1997 TLD
SUMMARY
(DIRECT RADIATION)
F-4 F-3 1997 GARDEN VEGETABLES F-5 F-4 1997 SOIL AND SEDIMENT F-5 F-5 1997 FISH F-10 F-6 1997 ALGAE F-10 F-7 1997 WELL WATER F 11 F-8 1997 RUNOFF WATER F-12 F-9 1997 SURFACE WATER F-13 F-10 1997 DRINKING WATER F-15 F-11 1997 RAIN WATER F-16
)
i Rancho Seco Nuclear Station iii 1997 AREOR
1997 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l.
EXECUTIVE
SUMMARY
This report contains results from the Radiological Environmental Monitoring Program (REMP) for the Rancho Seco Nuclear Station (RSNS) compiled for the period January 1,1997 through December 31,1997. This program is conducted by the Radiation Protection / Chemistry Group at RSNS and is conducted in accordance with section D6.8.3.b of the RSNS Permanently Defueled Technical Specifications.
The results of the 1997 Radiological Environmental Monitoring Program showed that the operation of RSNS had no significant radiologicalimpact on the environment.
Currently, the Plant is (1) permanently shutdown, (2) in a Custodial SAFSTOR condition, and (3)'
undergoing partial dismantlement known as incremental Decommissioning. The Post Shutdown Decommissioning Activities Report (PSDAR) describes performing incremental Decommissioning during Custodial SAFSTOR, then placing the plant into a Hardened SAFSTOR mode with Deferred Dismantlement. The SMUD Board of Directors has approved an incremental Decommissioning Action Plan which will be evaluated on an ongoing basis to determine cost effectiveness. Fuel off-loading into dry storage is currently scheduled to begin in 1999 to an independent Spent Fuel Storage Installation (ISFSI). The ISFSI civil construction was completed in 1995, with concrete storage modules in place.
During the reporting period, the atmospheric, terrestrial and aquatic environs adjacent to RSNS were monitored. The sample measurements showed that the levels of radioactivity in the sampled media were consistent with previous evaluations and Station operations. All positively detected results were well below the reporting levels.
Doses resulting from ambient exposure to terrestrial and atmospheric direct radiation sources were measured through the placement and retrieval of thermoluminescent dosimeters (TLDs). Direct radiation measurements attributable to Station operations, based on control and indicator locations, were indistinguishable above background levels. Two TLD Icx:ations, placed in an area being monitored as part of the characterization program, are indicating doses higher than the indicator average. The doses do not exceed regulatory limits. The elevated readings are due to historical releases ofliquid effluents.
Isotopic identifications were consistent with known releases of radioactive material from the Station to the atmospheric and aquatic environments. As expected, fish samples obtained from the aquatic environment of the No Name, Clay, Hadselville, and Laguna Creeks contributed the majority of positive isotopic identifications. Cesium -137, Cobalt-60, and Cesiun>134 were the predominant nuclides identified in the aquatic environment. Nuclides of Station origin were not detected in the gaseous effluent exposure pathways.
Rancho Seco Nuclear Station 1
1997 AREOR
11.
l.AND USE CENSUS 6
The 1996 Land Use Census was conducted in accordance with the Rancho Seco Permanently Defueled Technical Specificaton (PDTS) sechon D 6.8.3.b.2 and Radiological Environmental Monitoring Program (REMP) manual section 4.G. The 1996 Land Use Census did not identify any changes in the use of the unrestricted areas that would require modif' ation to the REMP for c
evaluating doses to individuals from principal pathways of exposure. This evaluation and determination are in accordance with the regarsments of 10CFR50, Appendix 1, section IV.B.3.
The land use census is performed on a biennial schedule and will be performed during 1998 and completed in 1999.
Ill.
RADIOLOGICAL IMPACT EVALUATION PREDICTED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways The maximum predicted potential annual organ dose commitment due to gaseous releases of tritium and particulate isotopes was 0.052 mrem (as calculated using the Rancho Seco Offsite Dose Calculation Manual (ODCM)). This predicted potential organ dose commitment was 0.35% of the associated PDTS limit (10CFR50, Appendix l guideline).
Since no detected noble gas activity was released from RSNS during 1997, there is no predicted gamma or beta air dose calculation from the ODCM. Therefore, the predicted air doses were within the applicable PDTS limits (10CFR50, Appendix l guidelines).
Uauid Effluent Exposure Pathways During 1997, 3.61 E+06 liters of waste water were released into "No Name' Creek from the two onsite Retention Basins. This volume of waste waterwas dispersed into 1.40 E+10 liters of dilation water. The estimated error associated with determining these volumes were 5% and 20%,
respectively.
The Uquid source term resulted in a predicted potential annual adult total body dose commitment of 0.026 mrem and a predicted potential child bone dose commitment of 0.055 mrem (as calculated using the ODCM). These predicted potential dose commitments were 0.87% and 0.55%,
respectively, of the associated PDTS limits (10CFR50, Appendix l guidelines). The dose commitments reflect the age groups that could have received the highest annual dose commitrnent from the liquid source term. This information is summarized in Table 1.
Rancho Seco Nuclear Station 2
1997 AREOR
111.
RADIOLOGICALIMPACT EVALUATION (continued)
FUEL CYCLE DOSE EVALUATION PDTS section D6.9.2.3 [NRC74] requires each Annual Radiological Environmental Operating Report (AREOR) to include information related to REMP manual sechon 5.0; Fuel Cycie Dose. The Fuel Cycle Dose Specification limits the dose or dose comnutment to any g!pl member of the public to 25 mrom to the total body or any organ, except the thyroid which is limited to 75 mrem. This, specification implements requirements promulgated by the United States Environmental Protection Agency [CFRd].
Consistent with REMP manual sechon 5.0, no fuel cycle dose evaluation was required to be performed during 1997 since no REMP measurement exceeded the established reporting levels.
Addebonally, the Statien effluent dose predictions did not exceed twice the dose guidelines of 10CFR50, Appendix 1 (CFRc]. The station operated within the Appendix i guidelines envelope for radioactive effluents (a condition supported by Program measurements); therefore, determination of en aghtml dose commitnSent delivered to a real member of the public was not required.
OBSERVED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways The predicted potential gaseous effluent dose commitment calculation of 0.052 mrem [RS97] is based on tritium activity. No particulate or gaseous isotopes of Station origin were released during 1997. The observed dose commitment dose calculation, if completed, using the gross beta data (which is primarily due to naturally occuning radioisotopes ) would not provide an accurate correlation. Therefore, no dose comparison was completed. This was also confirmed during 1997 es none of the REMP gamma isotopic analysis results for the airborne pathway indicated the presence of nuclides of Station origin.
Direct Radiation Exposure Pathway l
Based on thermoluminescent dosimeter (TLD) control and indicator locations measurement results obtained during 1997, the Station proper did not contribute an observable component to the -
recorded direct gamma radiation field. This TLD data supports the Gaseous Effluent Exposure Pathway conclusions and supports the conclusion that the Plant has no direct radiation effect on j
the environment.
TLDs placed near the effluent stream were used to evaluate the dose from this area. As expected, i
the dose from this area is exhibthng the normal decay. Dose levels at these locations are only slightly higher than the mean of the control and indicator locahons reported.
Rancho Seco Nuclear Station 3
1997 AREOR l
I
l I
Ill.
RADIOLOGICALIMPACT EVALUATION (continued)
OBSERVED POTENTIAL RADIOLOGICAL IMPACT Liauid Effluent Exposure Pathways To evaluate more accurately the impact on the environment from the liquid effluent pathway, dose commitment calculations were performed and compared with the annual dose commitment predictions reported in the January - December 1997 Rancho Seco Annual Radioactive Effluent Release Report [RS97]. The observed results presented in Table 1 wore obtained using the average, positive activity concentrations identified in fish (Appendix F, Table F-5), default consumption quantities for fish (ODCM), and nuclide-specific dose factors [NRC77).
The observed potential dose commitments listed in Table 1 are subject to uncertainty, principally due to the assumption that the predicted radioactmty was due to 1997 Station operations only and was not affected by radioactivity introduced into the environment prior to 1997. A major portion of the activity identified by Program measurements in 1997 is attributable to historical releases documented in previous annual reports. Additionaly, the observed dose cogwi;1rnent calculations l
are based on conservative default consumption factors for fish and fresh garden vegetables.
The 1996 Land Use Census indicates the potential for an liquid / fish or liquid / irrigated vegetation pathway. This potentialis based on the possibility and not actual data supporting the use of the effluent streams for a source of fish orirrigation of vegetation. Conservative consumption factors for fish were used for the observed dose commitment based on this potential.
)
f Rancho Seco Nuclear Station 4
1907 AREOR i
e 111.
RADIOLOGICAL IMPACT EVALUATION (continued)
OBSERVED POTENTIAL RADIOLOGICAL IMPACT TABLE 1 1997 Liquid Effluent Pathway Potential Dose Comparison POTENTIAL DOSE COMMITMENT (based on the maximally exposed group)
PREDICTED DOSE OBSERVED DOSE PERCENT OF THE COMMITMENT (a)
COMMITMENT (b)(c) 10CFR50 APPENDIX l DOSE LIMIT (mrem)
(mrem) 0.026 0.187 6.2 %
(adult's total body)
(adult's total body)
Total Body 0.055 0.282 2.8 %
(child's bone)
(child's liver)
Organ Notes:
(a)
Estimated by the Offsite Dose Calculation Manual (ODCM)
(b)
Estimated using observed average positive values for fish samples,(Appendix F, Table F-5).
(c)
The observed dose commitments for organ doses reflect the age group that could have received the highest annual dose commitment from the liquid source term Rancho Seco Nuclear Station 5
1997 AREOR s
IV.
PROGRAM ANALYSIS RESULTS
SUMMARY
This section compiles all Program data with corresponding evaluations. Each of the following five subsections presents information about each of the principal environmental exposure pathways monitored by the Program:
= Atmospheric (Section IV-A) o Direct Radiation (Section IV-8) e Terrestrial (Section IV-C) e Aquatic Life (Section IV-D)
= Water (Section IV-E)
Each of these sections contains a data evaluation subsection which provides a summary of the data collected.
Table 2 is a comprehensive, all-media data summary presented in a format considered acceptable by the US Nuclear Regulatory Commission. Information contained in Table 2 was derived from data presented in Appendix F.
IV-A. ATMOSPHERIC MONITORING DATA EVALUATION
/
No radionucl: des attributable to the operation of Rancho Seco were observed in gamma spectmmetry analyses of the quarterly composites of the particulate filters. No table is presented for this data since all the data were reported as being below the associated minimum detectable activity for the nuclides of interest.
i The data indicates that there was no measurable contribution to the airbome radioactivity inventory which could reasonably be attributable to Station operations.
l The results of the gross beta analyses of the particulate samples are given in Appendix F, Table F-1.
Rancho Seco Nuclear Station 6
1997 AREOR l
l
[
1 4
IV-B. DIRECT RADIATION MONITORING DATA EVALUATION A comparison review of all TLD data for the indicator and control locations during 1997 showed that there was no observable direct radiation component due to Station operations (i.e.,
storage or utilization of licensed radioactive material within the restricted area.)
Two TLD locations are being used to characterize the dose in areas next to the effluent stream. The data from these locations indicates doses are within regulatory limits.
The summary data for 1997 direct radiation monitoring is presented in Table 2.
Comprehensive data tables are given in Appendix F, Table F-2.
IV-C. VERRESTRIAL MONITORING.
DATA EVALUATION Garden Vegetation - 6 routine garden vegetation samples were collected and analyzed for nuclides of Interest during 1997. No gamma emitting isotopes were found in any of the simples analyzed. A site boundary irrigated garden has been evaluated to be a conservative I
method for evaluating the liquid effluent pathway. This method meets the requirement of the
..tnd Use Census for monitoring gardens. This site boundary garden is used for the Land Use Census.
Soil (discharge canal)- 8 soil samples were collected and analyzed for nuclides of interest from the effluent discharge canal and downstream creeks dering 1997. Cs-137 (7 samples,77 to 1581 pCi/kg, 534 pCi/kg mean) and Co-60 (2 samples,53 to 81 pCi/kg,67 pCl/kg mean) was detected by the analyses. The remaining nuclide identi'ications were numerically below the required LLD-equivalent activity concentration. The prese me of the identified nuclides is Ettributed to historical Station operations and Cs-137 fallout sources. The decay trend for these locations is as anticipated. Soil sampling at these locations is not required by the REMP.
Soll (storm drain outfall)- 30 soil samples were collected from 15 storm drain outfall locahons during 1997. These outfalls are located along the perimeter of the Industrial Area Boundary (Restricted Area). Three (3) locations at the ISFSI were added in 1997 to obtain pre-operational data. Gamma spectrometry analysis of these samples revealed the presence of Cs-137 (12 samples,23 to 86 pCL/kg,48.8 pCl/kg mean). These results are within the range cf the activity levels previously detected in the vicinity of Rancho Seco and are within the enticipated decay trend.. Soil sampling at these locations is not required by the REMP.
i Rancho Seco Nuclear Station 7
1997 AREOR f
IV-C. TERRESTRIAL MONITORING (continued)
DATA EVALUATION Soil (depression area)- Samples were taken in 1997 as part of the decommissioning site characterization program. The site characterization surveys are being conducted to monitor areas in the vicinity of the discharge canal, within District property, to provide data on activity levels from historical, permitted releases. These sample points were added to provide programmatic control and correlation for the data collected. Fourteen (14) soil samples at 7 locations were collected in 1997 as part of this program. Gamma spectrometry analysis of these samples indicated the presence of Cs 137 (14 samples,123 to 19500 pCi/kg,4648 pCi/kg mean), Co-60 (7 samples,102 to 588 pCi/kg,284 pCi/kg mean), and Cs-134 (4 samples,65 to 163 pCi/kg,111 pCi/kg mean). The results for these samples are within the anticipated decay trend indicated by the initial site characterization samples. Soil sampling at these locations is not required by the REMP.
The summary data for 1997 terrestrial monitoring is presented in Table 2. Comprehensive data tables are given in the following Appendix F tables:
= F-3 (Garden Vegetables)
= F-4 (Soil and Sediment).
IV-D. AQUATIC LIFE MONITORING DATA EVALUATION Fish - 2 fish samples were collected during 1997 and analyzed for nuclides of interest by j
gamma spectrometry. Cs-137 (2 samples,120 to 130 pCi/kg,' 125 pCi/kg mean) was identified.
In the gamma spectrometry analysis.
The identification of Cesium nuclides in fish samples is attributed mainly to permitted historical liquid effluent discharges. Since Cesium nuclides were not identified in effluent discharge canal or creek water samples, it appears that the observed Cesium uptake in fish could ultimately be traced indirectly to sediment sources.
The summary data for 1997 aquatic life consumption exposum pathway is presented in Table
- 2. A comprehensive data table is given in Appendix F, Table F-5.
Sediment - 17 samples of sediment were collected from the discharge canal and the Clay /
Hadselvillel Laguna Creeks during 1997. Gamma spewvmetry analysis of these samples indicated the presence of Cs-137 (17 samples,19 to 329 pCi/kg,169 pCi/kg mean) and Co-60 (6 samples, 8 to 16 pCi/kg,13 pCi/kg mean).
The presence of nuclides of interest in sediments is attributed to historical permitted liquid effluent discharges with some contribution trom fallout sources.
Rancho Seco Nuclear Station 8
1997 AREOR t
IV E. WACR MONITORING DATA EVALUATION Algae - 5 samples of algae were coilected from the discharge canal and the Clay / Hadselville/
Laguna creeks during 1997. Cs-137 (5 samples,16 to 54 pCi/kg,32.4 pCi/kg mean) was detected by gamma spectrometry analysis.
The identification of nuclides of interest in the algae samples is attributed to permitted historical liquid effluent discharges. Additional contributions would be expected to have occurred from sediment activity and fallout sources.
j Well Water - 22 well water samples were collected at indicator and control locations around the site during 1997. Gamma spectrometry and tritium analysis of the samples indicated results less than LLD for all isotopes of interest. Gross beta activity levels were within j
regulatory limits Runoff Water-No nuclides of interest were identified by gamma spectrometry or tritium cnalysis of the 30 samples collected in 1997.
Surface Water-5 locations (3 indicator and 2 control) were included in the surface water monitoring Program. Composite samplers located at the Plant intake (Folsom South Canal) cnd effluent discharge provide monthly composite samples. During 1997,63 samples were collected and analyzed for nuclides of interest. No gamma-emitting nuclides or tritium were detected in any of the samples analyzed.
Drinking Water - Water supplied from the site well is distributed in a potable water supply j
system for Station personnel consumption and use. On a monthly frequency, a sample of this i
water was collected and analyzed for nuclides of interest. A sample from the Rancho Seco Reservo8r Well is co!!ected as a control location. No gamma emitting isotopes or tritium were found to be present in the 24 samples collected in 1997. Gross Beta analysis showed activity within regulatory limits.
Rain Water - On a seasonal basis, rain water is collected at the site meteorological tower. The sample is analyzed for gamma emitting isotopes and tritium. During 1997,11 samples were collected at this location. No isotopes of interest were detected in these samples. Rainwater samples are not required to be collected by the REMP.
The summary data for the water monitoring program is shown in Table 2. Comprehensive data t;bles are given in the following Appendix F Tables:
=> F-4 (Soil and Sediment)
= F-6 (Algae)
=> F-7 (Well Water)
=> F-8 (Runoff Water)
=> F-9 (Surface Water)
= F-10 (Drinking Water)
=> F-11 (Rain Water)
Rancho Seco Nuclear Station 9
1997 AREOR
f f
f TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
l t
s Rancho Seco Nuclear Station 10 1997 AREOR
ut e r n
- int s e R
n d. o a
p em 0
0 f
O o o oedmre
- nr r e s
ER ne 4
A iov 0
3
/
2 t it 1
/
7 ci s 4
3 9
ar o 0
2 FP 1
9
)ly 1
sn nO o
7 is 4
1 t
ae 0
1 cu o
ot e
T 0
2 La g
iV n
a v e R
b G-m 90 0
u v
o 0
1 r
Cc F
0 1
P
(
n 2
D D 6
D D D D D a
2 L
L L
L L
L L
e 0
L L
4 Y
M 0
L L
L L
L 1
R 7
A 9
ne M
9 iovi 25 3
t t M
1 ci
/
/
s 2
3 a
U r
r o 5
e FP S
4 b
L 5
m 5
7 o
4 A
R e
T 0
8 U
P c
e 0
2 g
N D
e n
N D
a 0
R m
2 A
o n
o 0
5 1
N y
e F
0 2
a r
M r
M t
A e
a R
k u
la )y n
2 D D 0
ul a
2 L
L c
n nn e
0 L
L 7
G o
a nO M
0 2
O D
J As Me R
o a c
u cl P
d VV i o S
E n
W e
r o
He Di G
n i
hi v t
o r
t s N
i e
i it 2
R a
P wo e
I t
nP c s t
E O
S g
io(
n e 7
4 al ism t
i 0
0 1
n a
t L
T c
I o
it r
c D
1 B
N c
L o
A O
e p
S e
O O
T M
o R
e E
N m
7 4
L h
a A
c N
0 0
IC n
A a
C G
R ii 0
1 ne 3
6 ov O
dl a
t R
/
/
1 1
c L
s 3
6 a
r o 0
1 O
y r
s )y FP 1
1 D
l e
nl t
I i
H ionO i
t A
c a
8 cs o
4 5
R a
y oe T
0 8
F i
L la g
t u
e 0
2 L
f ic oV n
l r
A o
a a
t a
ic e 0
9 9
R m
T e
F df o
v N
m R
0 0
E a
o In s r
1 f
l P l
o F
0 A(
M N
n N
o n
2 D D 0
D D D D D a
2 L
L L
L L
L L
O it e
0 L
t 5
L t
L L
L a
M 0
1 R
I c
V o
L n
N o
f i 1
1 1
c) 0 0
0 A
0 0
r ot E
et N
6 6
wieD 0
0 0
mteL oi L
LLD(
n o
s r
e it 9
a e
s 7
6 6
3 4
4 4
4 4
t b
y 0
lam fa 2
1 1
1 S
to u n
f TNoA r
ae f is
. ac47 ac 4
7 l
c 4
0 5
3 3
s a pmip33 D
mip 5
6 6
u osy st el oe m mte1 1 o
n L
mt n o 1
1 s s N
pa rB o aess T
ao yn G
TA o
c e
N
)
s e yD n y 'r O s
S r
te tat r
t iof q I
le o
ta r
yd m
lue m ct e/
T b) ly o
mae) iu e/
r l
t V eatr m Sn ag l
h iuwlps Aic eC icr r i et a
aC i d ae Ed eWiu c
tr u Da uR W (p a q (p Gr gC m n t
d h mi d
t n
a aaU P
Rqm a e n
eMPS(
P
(
N G V (p e n a
I sa R
!l l
Il
ne 9
ov 9
hi n 1
c s
)
a ly r o FP sn nO o
b s ae o
cu T
ol e
La l V g
n o
t c
a m
r R
o nCC o
rF F
ill
(
na Y
e R
M 7
A 9
M 9
ne ovt
/2 2
2 M
1 Si
/
/
ci 2
1 s
r a o 1
U r
e FP S
4 b
L 5
m A
R e
o 1
8 6
1 U
P c
T 8
5 8
e 1
N D
e g
N D
n a
A o
R n
5 6
r 1
N y
n o
8 8
1 a
r 4
M r
t e
F A
e a
M R
k u
la )y n
D D
D D D D c
n ul a
L 1
L 9
L L
L L
6 8
G o
a nn e
L 8
L 9
L L
L L
8 nO M
O D
J As R
t e s u P
d h a c
el t
e W
W W
ig V.
G n
o in S
r S
i H
Dno o
r N
e h J i
I t
t 2
R a
P w
t e
E O
S g
nf c s o
n e 5
5 3
2 L
I o
in n
al T
i 0
1 1
t t
a ism r
c B
N c
o o
D A
O e
p L
T S
e M
o R
O O
O L
h e
M N
L A
c m
6 5
3 s
0 C
n A
N 0
1 I
a C
G R
O d
av 0
ne l
ui 8
8 3
L a
cit
/
/
/
O y
r a s 2
7 2
r o 1
l e
s )y FP t
I i
H D
ic nO nd or A
a 1
a y
cs o
1 8
6 R
F i
oe t
l T
8 5
8 L
f il Lu e
1 A
o c
ra g
oV n
a t
T e
F ca a
e B v R
m N
m um o
5 7
2 3
7 3
f E
a o
ke F
r o
M N
n A(
E P N
o n
D D D D D D D 8 4
O it a
L 7
L L
3 L
L L
L e
L 6L L
5 L
L L
L 8
a R
c M
4 VI o
L n
N a
f ro e) 0 0
0 0
0 0 E
eteD c
9 6
5 5
5 5
5 5
1 4
w mteL 1
1 1
1 1
1 oi L
LLD(
no r
s e
e it lab e
f r 4
4 4
4 4
a omot 8
8 8
8 8
2 2
2 2
2 t
t e
S Tu n
N A rae f is e
4 7
l a?
m%
i 4 8 1
1 c
4 7
m 4
0 5
3 3
m 4
0 5
3 3
os u
y el m
5 6
6 1
1 W
pa o
n-s- o N
yn a
n o-n- s-s a
r M C Z C C TA Gt M C Z C C G;
oc la l
e a
r u
u S
e o
n n
yd v
mae)
RE n )g RE n )g o
uwps EN l
ak EN mnk h
ak l
n ai V TR; dhmR TRl e taaU AoloCaenmC Aol oamC c
i r i V
o t
r e n
MPS(
W B S D C S (p WBS S D s (p aR (I
i 1ll l!
,1
l ee ut R
s
- int sn ro ae 0
0 0
O 0 0
0 0
0 0
O f
ntup o
oe em o
- nr rdme E
RA n e eiv 7
tcR 9
e a o 9
)ly rFP sn 1
nioOs o
tae T
cu e
ol L a g
l V na m
o o R
o r
w tnt F
r oi s Co l
P
(
nae M
YR 7
v A
io i
2 2
2 5
5 9
t t
/
/
f
/
5 c
M 9
a is
/
2 2
2 5
r o
M 1
FnPe U
re S
4 b
o 8
3 0
9 m
T 8
6 50 6
L 5
2 5
1 9
1 3
A R
e ge 1
U P
c n
a N
D e
R 9
0 N
D m
83 5
2 4
1 n
o 2
6 4
1 2
A o
a F
r 7
2 N
y e
M r
M Il t
A e
a d )y 5
R k
u ul D
nn 3 D 4 6
D D D 5 c
n nO n
L L
4 L. 4 L
L 7
1 1
G o
a A
a L
4 L
1 L
L 2
1 3
'c s
e 1
O D
J t e M
s u el R
ha P
d igV ce n W
W W W
W He i i S
S S S
S o
r G
n ir iwo i
o v
ht Dt o
N e
t is I
it 2
R a
P nP E
O S
g io(
e t
e ta n
4 4
4 6
6 L
T n
c as t e 0
0 0 0
0 3
o t
i o
isl I
L i
1 B
N c
o DM r
A O
e p
T S
e 2
2 2
M o
R P
P P O
O e
L h
m M
M M M
M A
c a
4 4
4 6
6 N
0 0 0 0
0 C
n I
a C
G R
O d.
ne iovi 4
4 4
7 7
1 1
t t 1
1 L
l ci
/
/
/
1
/
s
/
O y
r r o 7
4 4
a a
6 7
1 1
s )y FP I
it e
nl D
l H
on i
tiO A
c a
0 a
y cs 8
3 0
R F
oe o
6 9
it T
8 6
5 2
L f
il Llu e
5 1
9 1
3 ra g
1 A
o c
tov n
a a
a T
e F
ic e R
v N
m di 2
5 3
t E
a o
inis om 0
8 2
8 9
f r
1 o
F 1
1 E P M
N n
A(
N o
n D 4 D 8
D D D 9 O
i 1
t a
L 8
L 4
L 3
L L
8 1
a e
L 2
L 6
L 1
L L
R c
M 4
1 1
I V
o 1i L
N n
o E
f i rot 0
0 0
0 0
0 c) 5 5
5 5
5 5
et eD wmteL 1
1 1
1 1
1 oi L
LLD(
n o
s i
t r
e e
s a
b y
4 4
4 4
4 7
7 7
7 7
t Wm la S
1 1
1 1
1 1
1 1
1 1
ou n
f r
TNoA a
e a
l s
4 7
c e
mWM 4
7 i @
fios 4
0 5
33 n
4 0 5
3 3
u y
m 5
6 6
1 1
m 5
6 6
1 1
el N
pa e
n o-n s-s GM M C Z C C o
a n
o-n s s yn G
C 7 CC TA 1
ce n
u i a S
la l
u
)l t
ro e
n Sn) o mae)
RE
's n )g RE yd ng s
ak EN
&ak h
uwlps EN e
di/
c ihmi TR;pamC n
t e
l TR t
t r i/
d taaU AOoer AOiumC n
l loMep a
e e
MPS(
W B S D A S (p WBS(
s(
R
e R
-n dr O
oee u s st 0
0 0
0 0
C 0 0 0 0 nnMee f it an E
ou sroemm R
s A
7 ne 9
ov 9
tiit 1
ci s
)
a fy r o sn FP mO t s ae o
cu T
ol e
La l
l V gn o e a
1 r
v R
i tni t
or ois F
CoP(
n D D D D D D D D D D a
L L
L L
L L
L L
L L
e L
L L
t L
L L
L L
L Y
M R
7 A
9
.e M
9
- 6. t 2
h 2
M 1
t
/
/
ms 2
2 r
io U
e FP S
4 b
L 5
m 0
4 A
R e
To 3
5 U
P c
e 1
N D
e gn N
D aR m
0 8
A o
n o
2 2
N y
a r
1 M
r e
F t
A e
a M
l R
k u
la )y n
D D D D D D D D 5
L L
L 1
c n
ul a
L L
L L
2 t
L U-t 4
nn e
t L
L L
G o
a nO M
1 O
D J
As R
seu t
el c
W W
P d
GV a
e in S
r o
G n
i He Dio o
r v
N e
hi 2
R a
P t t i
I t
iswo e
t iP c s E
O S
g
(
n e 6
7 4
al I
o in 2
t i 0
0 L
T iM 1
s t
r D
B N
c o
n_
A O
e p
S e
T M
O O
o R
e M
N L
h m
6 7
A c
a 0
0 C
n A.
N I
a C
G R
ne O
la cit 2
5 d
i
/
/
L iov 2
5 t
s O
y r
s )y a o r
I i
e nl FP t
on D
i H
l iO t
A c
acs O
4 a
y oe o
R F
it L l g
u T
5 e
L f
i oV n
i l
r a A
o c
ta e a
a c
R m
0 6
T e
F idt o
2 h
N m
1 f
Inis F
r 1
E a
o t P l
o A(
M N
n n
D D D D D D D D 4 5
N o
a L
L L
L 2
L L
L t
2 L
L L
L e
L L
L L
O i
M
< 3 t
1 a
R c
I o
V L
n f io N
rot 0
0 0 0
0 0
0 0
c) 3 3
6 3
3 5
5 5
E et eD 1
1 2
1 1
1 1
1 wmteL oi L
LLD(
no s
r e
it e
s a
s c,
- a f
2 2 2 2 2 5 5 5 5 5 tS to n
T'MA r
2 ae f is
.c 4 7 ac 4 7 lc os
- n. ip 4
0 5 3 3 mip 4 W 5 3 3 u
o 5
y ef
. o 5 6 6 1 1 mt 6 1 1 pa nt n s s N
yn oo n o-n- s s ao n
TA Gi M C Z C C Gi M C Z C C s
s oce N
la l
S a
O u
u r
I n) n)
c yd T
ng n
RE ng o
)
mae)
S ak l
t l
e o EN ak TRamCit h
iuwps E
i ei/)
l/bi c
t dhmin GshmCd o Aolg e
i r e taaU e
n N i e p (e p WBAs(Pw MPS(
a Fs(
(
I R
l
.~
i
,lll i)l lj n
do oee ru R
i s
nn st 0
0 0
0 0
0 0
0 0
0 0
O wnn f b sn cu ee E
o 8 r ir r R
iI A
n e 7
iov 4
t it
/
9 ca s 4
9
)
r o ty FP 1
sn i_O s
5 2
e o
4 u
-- la g
e T
t_ V n
lo e a
rtnh R
m R
o 5
o s r
1 Co F
P
(
n D
D D D D D D
DD D D D ae L
L L
L L
L 5
L L
L L
L L
Y L
L L
t L
t 3
L L
L L
L L
R M
7 A
9 M
9 n e ov M
1 it i 4
t
/
c s U
r a
4 r o e
FP S
4 b
L 5
m A
R e
o 6
U P
c T
5 e
7 N
D e
g A
o.
D n
N a
R m
7 N
y n
o a
r 4
M r
e F
t A
e a
M 1
R k
u la )y n
D D D D D D 2 D
D D D D f;
c n
ul a
L L
L L
L L
0 L
L L
L L
L G
o a
nn e
nO M
6 L
L t
L t
L t
t L
t L
L O
D J
As R
t e s u et t
P d
h a c
o igV e
E G
n i
He Di in S
r o
o r
IN v
e hi i
R t
t 2
R a
P iswo t
e E
O S
g nP c s io(
n e 3
5 o
in t
L T
al s i t
a tiM 0
1 I
r c
B N
c o
o D
A O
e p
L S
e T
M o
R O
L h
e E
m A
c 3
C n
A.
a N
0 I
a C
G R
O d.
n e ov l
it i 8
L t
1 a
c
/
O y
r a s 8
s )y ro 1
D i
e nl FP I
t on A
il H
hO c
a a
y oe o
6 cs R
F i
Lu T
5 t
e 7
L f
ic oV n
l l
g ra A
o t
a a
a T
e F
ic e n
w R
r d!
o 9
N m
t r
f Inis F
1 E
a o
R Po M
N n
l A(
n D
D D D D D 0 D
7)
D D D N
o a
i e
L L
L L
L L
9 L
L L
L L
L O
t L
L L
L t
L L
L L
L L
t a
M
< 3 R
c IV o
L n
N o
fi 0
0 r ot E
c) 0 5
5 0
0 0
0 5
5 0
5 8
et 4
wieD 0
1 1
3 1
1 0
1 1
3 1
1 mteL 1
2 oi L
LLD(
n s
o re e
it s
b y
2 2
2 2
2 2
2 0
0 0
0 0
0 a
lam la 2
2 2
2 2
2 2
3 3
3 3
3 3
t o u n
S t
f TNoA ra a
e f is
- c m
m ic 4
7 lc 4
7 s
m i
ip 5
6 6
u 40 5
3 3 s a 4
0 5
3 3
os p 56 y
u pa t
m o 6
u t
et 1
1 o e i
o o
1 1
n o n-it i
t n o n-t s s N
r yn T
G t
M C Z C C G B r
s s a os T
G Is M C Z C C TA o
ce e
S r
r tay o
yd RE RE y
o n ae)
ENWl
)
lk) r f
idhmd TR5 teL ENf r e h
r L
uwlps
/
ce e/i c
r l
T R n 'a iwC n
n A OeaC A Ou etaaU u
MPS(
W B W q (p W B R W B (p a
R ill lll
i Ilij1 dr R
s eeut O
. i t ae 0
0 0 0 O 0 0
0 0 0 0 0 0
n sn wem E
f ntu o o o,m.
R
- nr A
2 7
ne 9
1 iov
/
t it 2
9 ci s a
1 1
o r
t FP
)y sn no o
8 is 8
tae o
5 cu T
ol La l V o e 1
t v m
5 r
ni o
t r
4 oi s Co F
P
(
n D
D D D O D D
D D D D D a
L L
L L
L L
L L L L
L L
3 Y
e L
L L
L L
t t
L t
t L
L 5
m_
M R
7 A
9 ne 2
M 9
iovi 2
1 M
1 tcits
/
r a o 1
U r
e FP S
4 b
5 L
m 6
A R
e o
U P
c T
7 N
D e
N D
A o
n 6
r N
y n
e 1
M e
r t
e F
r A
e a
M k
u i
D D D D D D D
D D D D D R
c n
la )y re L
L L
L L
L L
L L
L L L 5
ul G
o a
nn e
t t
L t
L L
t L
t L
t t
5 O
D J
nO M
As R
- 4. l eu t
P d
.a c
E o
VV e
S G
n i
He Dn in r
o o
r N
v e
hit i
I t
t i 2
R a
P iswo e
t E
O S
g nP c s 1
6 n
io(
n e tab 0
1 L
T o
it a
t iM s
I r
c B
N c
o o
D A
O e
p L
S e
T M
o R
o e
G L
h A
c m
1 a
0 C
n A
N I
a C
G R
O d.
ne 2
ov 1
L a
tcit
/
l ii 2
O y
r a s 1
r o t
s )y l
e nl FP I
i H
on D
ic io A
a t
6 a
y cs o
R F
i Lu T
oe 7
t L
f i
ra l
l A
o c
oV t
a a e m
8 T
e F
c iv di o
1 N
m t
r f
ni F
s E
a o
o I
E P M
N n
A(
n D
D D D D D D
D D D D D N
o a
L L
L L
L L
L L
L L L L
5 i
e t
L L
t t
L L
L L L L L
5 O
ta M
R c
I o
V L
n fi 0
0 o
N r ot 0
5 5
0 5 8 0
5 5 0 0 0 4
c)
E et eD 0
1 1
3 1 1 0
1 1 3 1 1 i
wmteL 2
1 oi L
LLD(
no s
it r
e e
s 3
3 3 3 3 3 4
4 4 4 4 4 4
a h
6 6 6 6 6 6 2
2 2 2 2 2 2
t b
lam a
S to u n
f r
TNoA ae 4 7 s
l a 2 4 0 5 3 3 a
4 7 m
m --
f is m
m ic 4 0J 3 3 1 1 i
m M 4 6 s a c
os p
5 4 u
1 1 oe u
t y
u H
i.
m c r s s it a
- r o n s s-rB N
el n o 2
t t
pa yn T
G Is M C Z C C T
G :; M C Z C C G
r a o r
o TA ce S
r o
RE g f) o yd mae)
REe ly) n J L h
ENcrh L ENir TR k e E/
c uwlps aet /
hmi TRf t nt i i t
id ni r
a oC A Dia uC n
t n
Aoru MPS(
W B S W M (p W B D W u (p a
eaaU R
ll1l l
-n da R
r
~
oeeu s
O nnt st roan f it oupee E
- roemm 0
0 0
0 0
0 R
r A
7 n e iov 9
t it 9
ci
)
a s y
r o 1
ln FP mO e.
2 o
T
- e
?.
- a. V I
tn e
a mit R
m avi o
r s
Co F
P
(
n D
D D D D D a
L L
L L
L L
Y e
L L
t L
L L
M R
7 A
9 M
9 ov ne M
1 it i t
ci s a
U r
ro e
FP S
4 b
L 5
m A
R e
o U
P c
T e
N D
e gn N
D a
R A
o m
n N
y a
o M
r t
r e
F A
e a
M R
k u
lu y) n D
D D D D D a
c n
G o
a nn a
L L
L L
L L
nO e
t t
L L
L t
O D
J As M
R s
t eu el P
d h a c
t G
n o
igV e
He i n r
i I
t t it Dso o
r v
N e
hi i
2 R
a P
iwos e
t eP E
O S
g c
a hi 7
(
n I
o in L
T ta t
t c
iM 1
s B
N c
o L
D r
o A
O e
p S
e T
M o
R L
h e
A c
am C
n A
N I
a C
G R
O d
iovi ne L
l t
a cit O
s I
y r
ar o s )y D
it e
nl FP A
i H
on l
iO c
ta a
y cs R
F i
Lu e
oe o
t T
L f
i r l g
l a
A o
c tov n
a a
a e R
m T
e F
c iv N
m di o
f nlt r
a F
E a
o o
m I
E P M
N n
A(
N o
n D
D D D D D O
i a
L L
L L
L L
t e
L L
L L
t L
a M
RI c
V o
L n
N fb rot 5
5 0 o 0 E
c) et 0
1 1
3 t
1 wieD 0
mteL 0
o L
LUD(
1 n
o se i
r t
e s
a b
y t
lam la S
t u n
1 1
1 1
1 1
o f
TNoA 1
1 1
1 1
1 rae f is a
4 7
lc os m
m ?_4 5
3 3
et i
- m y
u pa t
m 5
u 6
1 1
r n o s N
yn i
a
_ n TA T
G ;+ M C Z C C oce S
ro yd mae)
RE le) o iuwlps EN rb L h
TRntea/l c
t dh min A Oiari C n
etaa a
a M P S (U W B R W V (p a
R t
I m
V.
REFERENCES CFRa Code of Federal Regulations,1996, " National Primary Drinking Water Regulations," Title 40, Part 141.
CFRb Code of Federal Regulations,1997," Standards for Protection Against Radiation," Title 10, Part 20.
CFRc Code of Federal Regulations,1997," Domestic Ucensing of Production and Utilization Facilities," Title 10, Part 50.
CFRd Code of Federal Regulations,1996,"Environrnental Radiation Protection Standards for Nuclear Power Operations," Title 40, Part 190.
NRC74 United States Nuclear Regulatory Commission,1974, " Permanently Defueled Technical Specifications for the Rancho Seco Nuclear Station,"
Appendix' A to Facility License No. DPR-54 (as amended).
NRC77 United States Nuclear Regulatory Coremission,1977, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1,"
Regulatory Guide 1.109, Revision 1.
NRC79a United States Nuclear Regulatory Commission,1979, "An Acceptable Radiological Environmental Monitoring Program," Branch Technical Position, Revision 1.
NRC79b United States Nuclear Regulatory Commission,1979, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) -
Effluent Streams and the Environment," Regulatory Guide 4.15, Revision 1.
NRC92 United States Nuclear Regulatory Commission, " Air Sampling in the Workplace", Regulatory Guide 8.25, June 1992 NUREG79 United States Nuclear Regulatory Commission,1979, " Radiological Effluent Technical Specifications for PWRs," NUREG-0472, Revision 2.
NUREG80a United States Nuclear Regulatory Commission,1980, " Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40CFR190)," NUREG-0543.
RS97 Rancho Seco Nuclear Station,1997, " Annual Radioactive Effluent Release Report, January -December 1997," Sacramento Municipal Utility District report.
l l
l Rancho Seco Nuclear Station 18 1997 AREOR l
we l
l l
I f
VI. APPENDICES i
i l
l Rancho Seco Nuclear Station 19 1997 AREOR
APPENDIX A 1996 LAND USE CENSUS RESULTS in compliance with the Rancho Seco Permanently Defueled Technical Specifications, section D6.8.3.b.2 and the REMP Manual, section 4.0," Land Use Census", a land use census was completed on March 19,1997. The method of conducting the primary survey was to use an s:erial survey that was conducted during June 1996. Evaluating the aerial photographs continues to provide an accurate method of determining locations and distances of the nearest residences. When the review of the survey photos indicated that an actual on-scene survey was needed to verify the use of identified structures, a visual observation was made. The cerial photos also provided a method to identify any changes in f's agricultural, comrr arcial, or industrial use of the land surrounding the site. The use of conservative dose factors for the purpose of projected dose calculations still requires that we evaluate the use of the area surrounding the site. The information that is presented is to verify this assumption and validate the process.
The land use census covered an area bounded by each of the sixteen meteorological sectors out to a two mile radius from the Reactor Building.
I The 1996 Land Use Census did not identify any changes in the use of the unrestricted areas that would require modifications in the Radiological Environmental Monitoring Program for evaluating dotes to individuals from principal pathways of exposure. This evaluation and determination are in accordance with the requirements of 10CFR50, Appendix 1, section IV.B.3.
The Land Use Census is completed on a biennial schedule. Aerial surveys will be conducted during 1998 and the Galt irrigation report covering 1997 and 1998 will be requested during the last quarter of 1998. This information will be used to complete the 1998 census currently due on February 9,1999.
l Rancho Seco Nuclear Station A-1 1997 AREOR l
A.
RESIDENT EXPOSURE PATHWAY
SUMMARY
Inhalation, Ground Plane and Water Consumption The 1996 census determined that seven of the 16 radial sectors have residences that are within the 2 mile (3219 meters) Land Use Census radius. The closest residence in each of the seven sectors is identified below:
Sector Distance Ranking (meters)
(Nearest to Farthest)
A
>3219 NA B
>3219 NA C
1267 3
D 1038 1
E
>3219 NA F
>3219 NA G
2315 6
H
>3219 NA J
>3219 flA K
2267 5
L 1133 2
M 1943 4
N 3181 7
P
>3219 NA Q
>3219 NA R
>3219 NA It is expected that all seven residences use well water for consumption and other domestic purposes.
Rancho Seco Nuclear Station A-2 1997 AREOR
B.
CEPOSITION EXPOSURE PATHWAY
SUMMARY
Beef Consumption Based on conservative dose calculation parameters in use, the following is a summary for the 1996 land use census of the potential deposition exposure pathways at the locations listed below-Sector Distance l Consumption Pathway Comment (meters)
A 433 Beef Unrestricted Area Boundary B
430 Beef Unrestricted Area Boundary C
430 Beef Unrestricted Area Boundary D
448 Beef Unrestricted Area Boundary E
472 Beef Unrestricted Area Boundary F
667 Beef Unrestricted Area Boundary G
235 Beef Unrestricted Area Boundary H
198 Beef Unrestricted Area Boundary J
195 Beef Unrestricted Area Boundary K
195 Beef Unrestricted Area Boundary L
286 Beef Unrestricted Area Boundary M
404 Beef Unrestricted Area Boundary N
509 Beef Unrestricted Area Boundary P
442 Beef Unrestricted Area Boundary Q
500 Beef Unrestricted Area Boundary R
448 Beef Unrestricted Area Boundary Because of the extremely small amount of radioactive gaseous effluent released from the site, D: position Exposure Pathway changes were considered inconsequential. The changes indicated in the beef consumption table do not necessitate modification of GDOM or REMP practices.
l R:ncho Seco Nuclear Station A-3 1997 AREOR 1
C.
IRRIGATED CROP EXPOSURE PATHWAY SUMMurtY Laguna Creek Based on information stated in the Galt irrigation District's 1996 Crop Report,2919.1 acre-feet of Laguna Creek water was diverted for inigation purposes during the 1996 crop production season (up to October 31,1996. A totalland area of 1081 acres was subject to inigation as follows:
Acro Feet Acreage Crop Water irrigated 223.96 50 Sudan 22.44 90 Clover 385.16 156 Sudan 202.54 20' aot specified 355.74 100 Sudan I
331.74 130 Pasture
(
273.90 50 Clover 376.72 135 Sudan 165.96 50 Clover i
263.83 120 Com, other 199.77 60 Com
'100.71 30 Other 16.65 90 Sudan Based on direct observation cattle consume water from the Clay, Hadselville,'and Laguna Creeks.
Rancho.Seco Nuclear Station A-4 1997 AREOR 1
D.
OTHER EXPOSURE PATHWAYS The 1996 Land Use Census confirmed previous knowledge that the Clay / Laguna Creeks are utilized by the general public for aquatic life consumption purposes. Past census evaluat ons have been unsuccessful in determining the usage / occupancy factors for their consumptbn.
Therefore, insufficient data existed to justify ODCM usage factor modification.
E.
REMP EVALUATION An objective of the 1996 Land Use Census was to compare census and current REMP Manual locations to ensure consistency exists between monitoring activities and actual land utilization.
The following discussion is a summary of the comparison evaluation for each of the four exposure pathways.
Resident Exposure Pathway The inhalation and ground plane exposure pathways, the principal components of the Resident Exposure Pathway, are monitored directly and indirectly by thermoluminesence dosimetry (TLD), air, and soll sampling and analysis. Well water was monitored at six locations.
Since the existing REMP was more conservative with respect to Resident Exposure Pathway monitoring, no changes were required.
Deposition Exposure Pathway The Deposition Exposure Pathway (Section B) is monitored directly within the Station Site Boundary through garden vegetation sampling and analysis. The potential for a deposition pathway has been evaluated by the ODCM and REMP programs and found to have little potential for the current plant status. Since the current REMP was representative and conservative with respect to Deposition Exposure Pathway monitoring, no changes were required.
Irriaated Croo Exposure Pathway The REMP was effective in monitoring the identified irrigated crop exposure pathways. This conclusion was based on the fact that the REMP included irrigated vegetation sampling.
REMP surface water surveillance activities monitor irrigation water radiological quality. Current ODCM calculations are conservative since dilution effects are not included when predicting potential dose delivered through downstream pathways.
Rancho Seco Nuclear Station A-5 1997 AREOR j
l
E.
REMP EVALUATION (continued)
Other Exposure Pathways Existing aquatic life, surface water and sediment sampling and analysis practices are effective in monitoring potential observable effects associated with recreational activities occuning at the Clay Creek, Hadselville Creek, Laguna Creek, Folsom South Canal and Rancho Seco Lake. With respect to availability and quantity of food sources, the other identified consumption activities were considered inconsequential for pathway monitoring purposes.
No REMP changes were required to monitor other exposure pathways.
F.
ODCM EVALUATION Based on 1996 Land Use Census findings, the following potential exposure pathways exist at the indicated locations:
GASEOUS EFFLUENT Exposure Pathway Location Comment inhalation 1128 m ENE Resident location having the highest dispersion parameter Ground Plane 1128 m ENE Resident location having the highest deposition parameter LIQUID EFFLUENT Exoosure Pathway Location Comment Freshwat'r Fish Clay Creek Recreation beyond the Site Boundary Swimming Clay Creek Recreation beyond the Site Boundary.
Shoreline Deposits Clay Creek Recreation beyond the Site Boundary Inigated vegetation Clay Creek Potential for residences beyond the site boundary irrigated forage Clay Creek Cattle grazing beyond the Site Boundary Drinking Water Clay Creek Cattle drinking water beyond the Site Boundary Rancho Seco Nuclear Station A-6 1997 AREOR
F.
ODCM EVALUATION (continued) l The GASEOUS EFFLUENT locations for inhalation and ground plane used by the ODCM are conservative since they are located at the Station Site Boundary.
I Specifying the Laguna Creek location also provides additional conservatism since the beneficial effects of downstream dilution are not considered when specifying effluent release r'strictions.
As required by the 1996 Land Use Census the above information for exposure pathways and j
locations was submitted for incorporation in the ODCM for use during 1997.
I 1
l Rancho Seco Nuclear Station A-7 1997 AREOR l
l
APPENDIX B SAMPLE SITE DESCRIPTIONS AND MAPS This appendix provides descriptive information about the sampling locations and maps of all the locations for the Radiological Environmental Monitoring Program sites.
Table B-1 provides information on sample type, identification codes, and map location references. The sample identification code is an alphanumeric string beginning with the prefix "R" (for Rancho Seco Nuclear Station) followed by two letters to identify the sample media:
AS Air SL Soil RW Runoff Water FS Fish SW Surface Water LV Garden Vegetable DW Drinking Water AG Algae WW Well Water TL Direct Gamma Radiation (TLD)
MS Mud and Silt RN Rainwater The numeric designations which follow the letter designations indicate the straight-line distance (in miles) from the center of the Reactor Building to the monitoring site.
The next letter designates the sector in which the monitoring location is located. The letters A through R are used for sector designators. The letters I and O are not used to prevent confusion with the numbers one and zero in the ID codes.
Sector Letter Degrees Azimuth Compass Point A
348.75 to 11.25 N
B 11.25 to 33.75 NNE C
33.75 to 56.25 NE D
56.25 to 78.75 ENE E
78.75 to 101.25 E
F 101.25 to 123.75 ESE G
123.75 to 146.25 SE H
146.25 to 168.75 SSE l
J 168.75 to 191.25 S
K 191.25 to 213.75 SSW L
213.75 to 236.25 SW M
236.25 to 258.75 WSW N
258.75 to 281.25 W
P 281.25 to 303.75 WNW Q
303.75 to 326.25 NW R
326.25 to 348.75 NNW 4
Rancho Seco Nuclear Station B-1 1997 AREOR
SAMPLE SITE DESCRIPTIONS AND MAPS (continued)
The final letter designation indicates if the location is part of the operational REMP program
("O") or post-operational REMP program ("P").
Table B-1 Lists each location referencing the sample type and the location ID code to the map site number on one of the four Radiological Environmental Monitoring Site Maps included in this Appendix.
Figure B-1 Site Location Man: Shows the locations of the sample locations on and/or near the Site (including Storm Drain locations).
Figum B-2 One Mile Radius man: Sampling locations within one mile of the Reactor Building centerline are shown on this map.
Figure B-3 Five Mile Radius man: Sampling locations between one and five miles from the Reactor Building centerline are shown on this map.
Figure B-4 25 Mile Radius man: Sampling locations between five to 25 miles from the Reactor Building centerline are shown on this map.
l I
1 l
i Rancho Seco Nuclear Station B-2 1997 AREOR 1
RO ER A
799 1
i n
gii I l
I;
.v_. 6 s(
0
)
t 1
e a
)
e i
t 3=
2 (s S
1 3
I I g l
s I I :
s e
Qt 1.1' i
a
-_,7s h
)
2 1(
t g
r ia W
a s'
e u
n L
so I
31 d
0 P
S1
_ 8#
ri W7/
i o
2 1(
n (3
a n
._L 1
s
.3 g,
)
w8* n )s 1.*(
oi p
p, r._, __
is t e J.
a h
ct on 1I
]
Le r ga o
np 3
- 5,
/
i n
l pi B
) me r_
_ s
)
/
r i
at
/
,2 (e aa
_0 2s
/
S
(
s+
s
/
r 8
l r
I ae 2
t b
,*2 (8 m
)
7 n
/
2 e
(
m u n
no n
)
r i
=
3e o
e 2 (s a_
g i
vt s
a nc 2*
7 Eo 5
2 f'
3-g l
g l
,,g an
',2..
a ci
' s ',
s
)
a 4
r i
U
- 2 (s 1
,s g
S oD lom i rdo atS R(
3
- s 5
1 5
-B n
e o
ru it g
a t
i L
F S
rae lcunoce S
o hcna R
i l
f u
m ww 43 l
eNE I
'f I
i
/
u.
j'
//
i I
(
W s.
E 1
e N'4 "" \\ j['9 tr-
- ,,\\
f l.
i.
E sw se
/
saw m
\\
S onann Figure B-3 Radiological Environmental Sampling Locations from 1 to 5 miles from the Reactor Building Rancho Seco Nuclear Station B-5 1997 AREOR i
\\
N
/
1W
~~
/
NW I
g
. Secremento ik 4.I www sa e Ek Grove f
t'
.58 Jt.[.
lone g
,,=,, _
Rancho Seco 37 e
ss - so u m m ggg g7 sw S
\\
l
---man y i
l Figure B-4 Radiological Environmental Sampling Locations 5 to 25 miles from the l
Reactor Building I
Rancho Seco Nuclear Station B-6 1997 AREOR I
1 I
I
\\
l l
l l
\\
N j
l NNW MNE l
/
1 59
/se6 www sea i
=
wNw
=
l 00 l
o o [_
1 k
2?
- ~
i 84 VV 3-i i
1 l
i WSW I ESE l
61 3
),
36 13 SW I
SE i
\\
s t
Figure B-2 Radiological Environmental Sampling Locations within 1 mile from the Reactor Building Rancho Seco Nuclear Station B-4 1997 AREOR
ro tc C E M F M
N F N M N G F E D L M M M O
M M N N N e
S R
se 1
7 3
8 6
7 3
7 3
8 1
8 3
8 8
7 2
5 8
3 6
7 8
7 O
8 O 0 0
1 0
0 1
3 0
1 0
1 0 0 0 3
2 1
0 0
0 O 1
3 E
M RA 7
99 la e 1
n n a
r s
e C e s
k k
h e
e la ru h
c e e n t
s u is r
r o
o D C C a lc S
C t
e o
n n
)
n g
E s
p ei r
o E
a m e lv e
i
'g r
le c i
r v
ta G e o lu W
s W
t t
)
e e
e e
a n s f
w o e i
t ln s w
n e S c
D o l
f e
it B
W y
o W ip e o
r y
e s o E d
S e
h c
o L
T p d ra r
e F e
in c o T
w T
e r
e m L
B t
(
h a m H o r
d r
t e H o e t
n e t
f 2
o n
u R a c L e a F o (
c d P
r d
e L
t s
s n u s
o.
A S-e o
r c
e l
n S o W R e e a i
u S d ls v
u S
o r
e l
u d W W j
D o r r
n o c
n n
P l
p a
i_
t B
e a F o e e a l
e t
s B
e e p
o 1
e e n
a m m y
h S
i i
o u
it n e t
S t
e c
t r
e a y
t C F e
y n
a a c
S r
e R a
W la a l
o e
e e e
o a S C n
it p
S
_ u W C o u
it y
e r
k S
h S
a h M a v A i
^
f f
o i
l n
8 S
a r
i e
c e
f c
l a
^
f c
n c
n e m o R n C S y
E W
E o
r c
s O ""
e a n o C
^
o e
S R
o o e a
la
^
e L
D o p c R
C c e o
p n
n n h
m m e e u p
c a
C lu u n o
a n
o C f
8 a
n n
J M
R O o o
(
O C C C
d C S a
I I
n S
se t
i S
7 g
y
-B n
c s e 1 i n
e is t
- r e
s Bo u
o o a la la l
t q
y y
y p
p y
y y
y y
e y
y y
y y
y y
l l
l l
t ly y
y u u u W.
ein n
e o e e e
t N m m N N N e e e e
e e
bo F
le l
M M ld l
l n n n r
d d
N t
C C l
t t
t t
t t
t t
r r
r r
r r
r r
l e
e n n n o e e e
o o t
t u u i M M A
n n n
n n r
r r
r r
ra r
r a a a a a a a aM o
W W W W i
M M ly y
w o o o
o o
u u u u u u M
M M Q Q Q Q Q Q m m m T
B h H i
Q Q l
t e o e a
c t
e n n S S S t
o o 8
n o
M M e
C mnor n
i o
v it a
a E
c.
0 5
6 7 8
3 9 0
0 1
2 3
o o 1
2 3 8
4 9
2 3
5 6 9 8
LN 3
1 3
1 1
1 1
4 la p
c a
ig M
o lo id s
a s
D D D N D
D N N D D D N D N D D D D D
D D D D D a
N N N O I
I C C I
N I
O I
O N N N N I
I N N N N N
N O O N C
I N
N R
I I
I I
N N
I I
I I
l C
C C
I I
I n
io t
a O
O O O O O O P O O 0 O O P t
O O O P C E M F M
N F N M N G F E D M M M O
O O O O O S
e D
M M N N N 1
o 1
7 3
8 6
7 3
7 3
8 1
8 3
8 8
7 1
5 8
3 6
7 8
7 r
d 1
D O
1 3
D 1
O 1
D O O 3 2
1 O
O O O t
3 a
C O O O S
S S S W
W W W W W W W W W W W W W N
S S S S S le D
A A A A R
S S S S S D D W W W W W W R
M M M M M c
I R R R R R
R R R R R R R R R R R R R R
R R R R R u
N o
C R
R R R R R R R e
e E
E E E E E E
E T T T T T S
p T
T T
T T
T T
T R R R R R R R
L L
L L
L y
A A A A A A A A E E E E E E E
I S S S SI o
T T T T
T T
T S
I I
I h
T W
W W W W W W W A A A A A A A
D D D D D C
e I
R R R R
I I
I F
E E E E E G G W W W W W W W
N N N N N n
lp A A A A F
C C C C C I
N L
L L
L L
L A A A A A a
N I
N m
O A A A A A K K L
L L
L L
L I
D D D D D R
F F
F F
F E
E E
E E E A
U U U U U a
N N N S
U R R R R R I
R U U U U U R
I W W W W W W R
M M M M M R
S S S S S D D
ro c
M M N F N
M M N N N H H J K L H M M M M N N N B N Q M M M N t
e S
R I
3 6
7 5
8 3
6 7
8 7
2 2
2 2 3 2
3 3
3 6
7 5
8 3
3 3
4 4
4 3
O se I
0 0
0 1
1 O 0 O 1
3 0
0 0
0 0
0 0
0 0
0 0
1 1
0 0
0 0 0 0
0 E
M RA 799 1
s k
la e
k k
e e
e n e
e r
a r
C C C C
r le le n
le l
h l
r i
v i
o i
l i
h le 0 2
1 o v l
v e
it e
D v le p
s 1
2 3
4 5 6
7 8
9 s
1 1
1 e a e e w
a r
c y
e s
r p
s d 1
d m
. o o o o o o o o y
y d
. o e e e n p
a o
p r
t a
- o. o r
r r
a m
e a o
e-m H N N N N N N N N N a m
e H N N N A A A i
o r
a L
W u d ls u R H d
r iM d
u S o d u S n F ia a ia ia in ia ia ia i
n u p
d n n n n n d o
n m n n n n n n f
o.
D o r
c n D o r
a r
r r
r r
r r
r r
o r P a
in i
ia io e is t
n a
a u S o n o h r
a a s s S
t r
r r
t B
e e a
y a
D D D D D D D D D B e
r y D D D s s s o
n n
t B
e t
a a t
S y
n ta la k m m m m m m m m m t
l l
e e e n o
n e a v r
r r
o i
e e a o i
e e r
r r
r r
r r
r r
i W
i C m m m p
p o I
m h C k
it W C e W
t a
r l
it u
it ip f
S S
r r
r e e o S e
o o o o o o o o o S f
c f
S f
t t
t t
t t
t t
t f
o o o c
E n o E
o C S S S S S S S S S o
t t
t D D D F f
r f
S S S S
C s
a e
li n
c le e
I o
e R s.
c n
L D
v 6-lu le l
e eu p
s f
fn d n
f a
n o a o
M oC C H C
dna Se t
iS 8-g y
B
)d n
cn 1
i e
r e
l l
la l
l l
ts la la l
l la la l
l l
Bu o
u l
l l
l l
la l
l l
l l
l l
him i
i m
i m
m i
im im i
i L
i i
h a
a a a
a a
a a a a
a a
a a a
a a
a a
a a a t
q u u u u
u u u u u u u u u u u u u u u u u u u u u u u u u n
i n n n n n n n n n i
e n n n
n n
n n n n n n n n n n n n n n r
n n n n n n n n n ei n
r n n n n n n
i n
i n
n 9
n n n n n n n n l t F
A A A A A A k A N A A h im m m m
m m m m m m m A
A A A A A A A A A A A A A A A A b n o
n s
H h
ao M
o i
TC i
m im im m m im m im m m im r
r r
r r
r l
t e e e e e
e o e e e e e e e e e e e e e e e e e e e o e e a u
(
a c
S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S n
le t
l o
e C
m ii nor n
iv o
n ita 9
6 7
8 9
9 9
0 E
c o.
5 6
7 8
9 0 1
2 3
4 1
1 1
1 2
2 2
2 2
5 6
2 3
5 6 7 9
3 5
6 9
8 2
2 2
2 2
2 5
loN la p
C a
M I
go lo i
d s
a s
D D D N D D D D D D D D D D D D D D D D D D D D D O D D D D R
l I
N N O N I
I N N N N N N N N N N N N N N N N N N N NI N N N a
N C
I I
C I
N N I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I n
o i
ta
\\
1 2
7 8
9 1
2 3
I t
O O O O O O O O O O O O O O O O O O O O O O O O O O P P P P S
M M N F N
M M N N N J
K L H M M M M N N N A N Q M M M N e
o 3
6 7
5 8
3 6
7 8
7 H H 2 2
3 2
r d
2 2
3 3
3 6
7 5
8 3
3 3
4 4
4 3
a S S S S S G G G G G O O L
L L
L O O O O O 1
1 O O O C
O O O 1
1 O O O 1
3 O O O O L
L L
L L
L L O O O O e
L L
L L
L L
L L
L S S S S S S S S d
S S S S S S S S S S D
F F
F F
F A A A A A S S R R R R R R R R R R R R R R R R R R u
I R R R R R R R R R R R R N
oCe S
e O
p h
y E E E E E e
S S S S
S G G G G G O
I l
L t
L L
L L
L L
L L
L L
L L
L l
t c
T H H H H H A A A A A I
O O O O O O O O O O O O O O O O O O O n
L L
i I
l I
I I
I I
I I
I I
I I
I I
i l
lp F
F F
F F
L L
L L
L S S S S S S S S S S S S S S S S S S S S a
I I
I I
I m
A A A A A R
aS
(
llll
,l l!
lll l
- fIfl(l1l1 1l'
ij lj!
l ro c
M M M M M
A t
N R C N L H F C K H M K C G M K M N M e
S s
R i
5 5 5 5 6
A 3 3 3 3 3 4 5 8 0 l
.1 2 8 7 5 9 4 7 8 O
e M
0 0 0 0 0
N 0 0 0 0 0 0 0 0 0 2 8 7 1 1 3 7 3 3
E 1
RA r
3 e
l 6
3 7
a ta c
1 s
9 o
8 8
9 w
l 4
8 o
1 1
n k
e 1
2 d
0 s
e h
8 8
R e
- # 3 ; 5 #
e t
1 e
d
-, 8 s
n 7 n
3 3
t e
- b m
r r
8
- 7 R
8 t
lo 8
8 S 5
i 1
- ; n e
C o
)
E o
n 1
C 8 g
3 0 8 d
d e
r
. h i
f f
o a
f P
t : d 4 2
m i
k N
- e. S i
R #
8 2
R R ip f
e
=
o y
o c
r
- )
- M o
r 8
e a
m n
k y a le ie C d c
. ;6 W
6 e E o la
. e S 1
(
N e
a o
S n
L la N t u
D
- e-i o
~
c 1
C o n R R 8 P
d t
p o
e R im n o 8 e
t
/
a 1
1 h
o r d e h h
3 e
o r
N n
l o N n 4 de f
4 d
. e. 4 A it l
O t.
o 6 e 6 1
1 t
s (
e 7 F
c c 3 g b e
n a
I p a A n
r d d 2 n 6 n
r L
r a
c N
e h
a w
a r
1 n u
-.. w d
lo
- J.
e 1
A o o a C f
t n o r
t R
e d
m 1
C O o B 7 n h
/
e e
o h
i o o a o e
se e d o
r a
r o a o N o t
t s
n u b B B 8 B e
d m
o e a 1
t C c e 0 e t n 8 la t
t e
t t
8 u
n o
c m g
r o S c
r o
o t
W e
n N 8 n Q t
a e e e e m
F o e r
e n n c h a e i
t o
e f
h e a S r
r S
I S S S S lm o c e e o
h e
/
e I
i p
I c
it it n
d y
n re n n c
g C a
y y
r r
e r
is e c
& S e
m t
i c
n p
t e e n n a
c F
S e F F
e t
k e e t
n p
f t
o t
e e m o o 8 S s
e F n a h R c
s S
e h
r F F
e c
m e
F s
e r
c T
c m d u m u
l r
o D
I S
n i
n e e o o r
t s e l
p E W i
S F
e h
t o
e e t
e o 4 e
e r
L I
G w
P t
e
'nn C e E y S F 0
H m m o t
ll 1
o m
R e a e a t
p y
n G
i i
m m S d t
W C r
v h
e s
l l
o e
e e i
o t s ip a r
a r
e r
o s c o o F T E e
P P e
t t
R r
a d
r i
E b
r l
M d
r e
a o n W
P P h
n a
ta J
H F a
u G
N E W r
n B
k N N W
P d
o t
y m
n c
S as e
a e
u C
S M
a i
r t
e in L
s S
T B
t iS 9
g y
c B
)d n
n 1
i e
e r
u l
la l
l ts la l
l Bu o
q u u u u u u u
u
- b "..
a a a a
a i
1 1
^a;b :a ;b ;6 ^ab ;e 1
1 1
1 i
1 1
1
- a L a
- 1
, ;i 1. ;1 t
e n n n n n n n
n n
- e
^
i ei n
F n n n n n n n
n r
^_ 6
^.
l t ao M
o u > >
A A
M b h h h b h h A h A h h h - h h'.- h bn o
n
- A A A M i
m m
A
^
e n m m m m m T C i
C C
t e e o e e e e
o l
c S S S S S S S
S
(
a e
l t
l n
o e
C mno n
r o
i it v
a n
c.
o o 1
2 A
1 2
7 0
3 4
5 8
7 4
7 8
0 0
1 2
3 4
E LN 5
5 5
5 5 5 5
N 3
3 1
2 3
3 3 3
5 1
3 3
3 4 4 4
4 4
l p
a a
c M
igo lo id ss D D D D D D D
N D D D D D D D D N D D D D D D D D D a
a R
C IN N N N IN IN IN O
N N N N N N N N OC I N N N N N N N N N
I I
I I I I I
I l
I I I C
I I
I I
I I
I I
no it K L M N a
2 3 e
P P A A A A O
X O 0 O O O 0 O O P O O O O O O O O O t
P P P P M
X.
R C N L H F C K H M K C G M K M N M S
d N N 0
o 3 3 M M M M 8
X 3 3 3 3 3 4 5 8 7 2 8 7 5 9 4 7 8 r
5 5 5 5 O
X O O O O O O O O 0 2 8 7 O 1 3 7 3 3 a
C O O 1
D L L O O O O V V L
L L L
L L
L L
L L
L L
L L
L L L
L e
S S L L L L L
L T T T T T T T T T T T T T T T T T T l
I C
R R S S S S R R R R R R R R R R R R R R R R R R R R u
R R R R N
o Ce e
S S
S p
E E
y NL NL o
T EB EB O
I L L L L L L I
I f
I DA DA D D D D D D D D D D D D D D D D D D h
e I
O O O O O RT RT L L L L L L L L L L L L L L L L L L C
lp S S S S S S AE A E T T T T T T T T T T T T T T T T T T n
m GG GG a
a E
E R
S V
V llII
ro R
tc N F D E P D M N N P N N P Q Q J P
e O
S ERA s
0 0
8 6
4 4
3 3
4 5
3 7
7 4
l 9
8 4
e i
1 1
1 8
0 0 0
0 0 0 0 0
0 0 0 0
7 0
9 M
1 i
9 1
6 3
4 9
8 8
9 3
2 y
1 4
0 6
9 ra 4 1
1 8
5 8
a
. 5 6
, d 9
n n #
t d
8 6
s u 5
d R R
8 7
io o 3
l
/
o n n 8 8
p b e
n iu d lo R n 6 i
r t
id o e o
t c 8 9
0 1
n e io
. B o
p i
d lo lt 8
8 9
9 o
i h
s t
r e
8 8
8 8
8 r
s o 5 C a e e 8 8
I, I,
- t. p o o a
C c G
s c
r u
f t
y n s 8
n o
i C e 8
. S S S r
L lo a ie e to w d n
r n
cn e
y C
- e n F F
F t
e s h n
f e
it o
C t
C a o T t
a e
a u
o
& n r h 6 io C m n d S S S e
y c
I I
I r
o c
s l
it r
n a
n ia i
t c
i e a t
t t
s n n
2 C F G o e e h lo A r
o s s e e
e S 6 c
o r.
T d
4 i
O.
C M w
lo r
1 r
o f
y O s s h R
t i
w w o t
o t
tp e e t
n i
W W t
h h
e p k
n o a r
e L
e r
a o h i
a le i
n t
t c
M L e c D G, d
_ P o o o 4 n A u
r r
n S N N 0 o L p
s e
S a
e e o it u
E 1
d A D
d c S m
L o S
o I
o a
M e e B
H S O t la e C R
S
/
a F
d o E. e ic it t
S 6 s S n
h r
s P r
a I
c a le e
a n
i M
E M
y s
R la e
9 C
t 0
0 iS 1
g B
)d n
1 i
- e r
yc Bu o
n t
e n
i ei n
u bn o
e l
l l
l ly y ly y
y y
y y
y y
y y
y l t q
y y
y y
t l
l l
l l
t r
r r
r r
r r
r r
r r
r r
l l
t l
r r
r r
r e e e
e e e
e e e e
e e
e e
e e
e ao M
F t
t t
t t
t t
t t
t t
t t
t t
t t
TC r
r r
r r
r r
r r
r r
r r
r r
r l
n a a a a a a a a a ra a a a a a a a o
u u u u u u u u u u u u u u u u u
(
a it t
Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q n
c e
e l
m lo C
no r
i n
v o
i n
ta E
c.
5 6 8
7 2
9 9
8 3
4 6
6 9 1
2 o o 9 5
a LN 4
4 5
4 1
2 2
4 5
5 5
5 5
6 6
l c
p i
a g
M o
lo i
s d
s D D D N D D D D D D D D D DD D D a
a N N N O N N N N N N N N N NN N N l
I I
I C
R C
I I
I I
I I
I I
I I
I I
I no O O O P O O O O O O P P P P P P P 1
d N F D 0 P D M N N P N N P Q Q J P
i E
t e
a 3
3 4
5 3 7
7 4
t o
9 8
4 0
8 6
4 4
0 8 O D O D D O O D D O O D S
C 1
1 1
1 L
L L
L L
L L
L L
L L
L L
L L
L L
T T T T
T T
T T
r D
T T
T T T T T T T
R R R R R R R R R R R R R R R R R a
I e
lCu l
f e
o py c
D D D D D D D D D D D D D D D D D S
e Te L
L L
L L
L L
L L
L L
L L
L L
L L
lp T
T T
T T T T T T T T T T T T T T o
m h
a c
S naR ll u
APPENDIX C QUALITY CONTROL SAMPLE ANALYSIS RESULTS QUALITY ASSURANCE AND CONTROL Implementation of the Radiological Environmental Monitoring Program (REMP) consists of a number of discrete stepsinduding:
=> Sample collection,
=> Packaging,
=> Shipment and receipt,
=> Measurements of radioactivity,
=> Data evaluation, and
=> Reporting.
These program elements are performed according to approved, written procedums to assure the validity of REMP results. This section discusses the intemal quality control measurements made by the analysis laboratory, Thermo NUtech, and the results of their participation in the Intertaboratory Comparison Program conducted by the United States Environmental Protection Agency (EPA).
The Interiaboratory Comparison Program and the analysis laboratories Quality Assurance Programs provide infonnation on the validity (accuracy and precision) of the REMP implementation steps listed above.
Because REMP measurement validity is important for evaluating protection of the health and safety of the public, RSNS has established an Environmental Quality Assurance Program (EQAP) for radiological environmental measurements. The Environmental QA Program implements the guidance provided in Regulatory Guide 4.15, (NRC79a).
INTERLABORATORY COMPARISON PROGRAM Thermo NUtech participates in the Interlaboratory Comparison Program (ICP). The ICP is a radiological analysis quality control program sponsored by EPA's Environmental Monitoring Systems Laboratory in Las Vegas. Participation in the ICP is a requirement of the Permanently Defueled Technical Specification (section D6.8.3.b.3). It provides for an independent check of the proficiency of the laboratory. It also providos information on the precision and accuracy of l
measurements of radioactive material in REMP samples by Thermo NUtech, and other laboratories.
The extent of lhermo NUtech participation in this program includes all of the environmental radioactivity determinations that are offered by the EPA and related to the analyses required by the REMP manual.
)
1 Rancho Seco Nuclear Station C-1 1997 AREOR
ir ABORATORY COMPARISON PROGRAM (con' ' ed) 1 The EPA Intercomparison Program consists of a variety of sample media spiked with known quantities of specific radioactive materials at levels normally found in environmental samples.
These levels are generally quite low. Most samples require long counting times to determine if any activity is present, and the tr sults may have large deviations from the mean. When the samples are distributed by the EPA, there is an implied precision requirement given in terms of the analysis requested to be performed. After all the labs provide the results of their analyses (three are required from each lab), the EPA publishes a statistical summary of all the results by all laboratories. This report includes the EPA acceptance controllimits, the mean of alllaboratories and the standard deviation of the results by all labs, among other statistics.
If the results of a detennination by Thermo NUtech in the ICP is outside the specified controllimits or do not pass the outliers test, Thermo NUtech must investigate and, if a problem is identified, take corrective action to prevent problem recurrence.
During 1997, Thermo Nutech analyzed 21 ICP samples related to the current REMP program. All sample results reported by ThermoNUted1 were within the control limits.
The Thermo Nutech measurement results are presented in Table C 1 along with the acceptable EPA values for each test.
l INTRALABORATORY QUAUTY ASSURANCE PROGRAM Thermo Nutech by contract also operate an intralaboratory Comparison Program (Quality Assurance Program) to maintain an acceptable quality level on a routine basis.
1 As part of their Quality Assurance Program, the laboratory performs background counts, an analysis of a spiked samples, and duplicate sample counts for every ten Rancho Seco REMP samples analyzed. These quality control procedures are performed for all analyses except gamma spectrometry, forwhich weeldy energy and efficiency checks are performed. The spiked and duplicate samples are prepared by personnel not directly involved with the analysis. Spiked samples, as weR as the radioactive sources used for the gamma spesvineter checks, are traceable to the National institute for Standards and Tedriciogy (NIST).
In all cases during 1997, the duplicate analyses and the tritium spikes were acceptable.
RANCHO SECO AUDIT AND SURVEILLANCE RESULTS The Rancho Seco Quality Program requires periodic audits of REMP activities, including Thermo NUtech. Contract laboratory perfonnance is evaluated by the Rancho Seco QA Department.
Rancho Seco Nuclear Station C-2 1997 AREOR I
CONCLUSIONS Re intralaboratory and Interlaboratory results provided by the EPA and Thermo-NUtech indicate that Thermo-NUtech performance was acceptable.
DIRECT RADIATION (TLD) COMPARISON PROGRAM The TLD vendor, ICN Dosimetry Services, participand in a monthly blind spike comparison testing program sponsored by the University of Michigan. As of the second quarter of 1997 they implemented a quarterly program. A review of ICN's results of the participation in this testing program indicates that ICN has satisfactorily completed all of the required tests for the types of environmental radiation monitored at RSNS.
This comparison program satisfies the requirement of the REMP manual section 6.0.
1 l
Rttncho Seco Nuclear Station C-3 1997 AREOR
~
99 s
8 1
4 9
t i
m 9
90 1
2 6
7 9
3 3
6 2
1 3
3 0
0 iL 0
56 5
2 3
3 3
3 3
0 3
5 8
3 2
2 7
8 3
0 5
2 3
3 4
l 1
0 1
o 6
1 2
1 1
4 9
- 6. 2 2
3 1
4 6
1 6
1 r
t 6
n 0
6 3
0 7
2 0
7 7
7 8
7 7
7 6
9 7
7 7
o 4
7 7
7 8
7 9
0 7
C 3
2 0
9 9
2 1
0 7
6 3
2 2
9 8
8 7
8 8
2 5
2 9
3 3
2 1
1 3
5 2
2 1
4 4
1 1
5 8
1 8
3 9
3 1
3 1
4 3
0 3
8 5
6 3
1 3
oht 4
5 5
8 6
1 5
5 5
2 2
5 1
2 3
5 Z"
mcl i
0 7
6 0
i 1
5 2
u 2 1
4 1
5 i
r e s i 6 1
0 1
0 i 2 0
i 01
- 1 et i
i
- 3 1
M h Ue i 7
1 1
i i i t A "A i
3 1
3 7
68 i i i i 3 5 7 7
3 b
T N R 3 3
3 3
3 3
2 0
3 3
6 82
. 0 3
3 0
0 8
6 6
6 3
1 3
3 3
3 0
0
. 2 1
05 3
4 Ra 1
71 2
3 2
1 1
2 5
1 1
12 3
4
- 9. 3 9
8 0
6 7
4 39 2
2 0
0 1
2 3
9 5
12 2
0 GL 1
4 7
1 7
2 Og Rni Pd t
0 3
0 5
l n
u No s
0 0
5 0
0 0
0 0
i 0
0 0
0 0
0 0
0 1
9 0
0 0
2 Op e
5 1
1 7
5 5
5 i i 5 5
5 5
5 5
5 5
8 5
5 5
Ss R
i i i
i
- i i t i 0 i i i
i i i i
- 00 i
e IRR)
A 0
1 0
4 4
0 0
0 0
0 0
0 1
0 0
0 9
0 0
0 0
11 P
7 A rh E
4 9
2 1
1 0
0 2
9 8
5 11 4
1 0
4 8
5 0
4 7
C 0
2 0
00 3
Poc 1
7 2
3 2
1 1
2 4
1 1
11 3
4 1
1 4
7 1
7 2
1-Mf e C
OtaU t
a a
a a a E
CaN t
t t
t t
L Do y
e e
e e e e B B
B B B B
Y a
4 7
A Rrym sp m
7 4
4 7
m 7
4 s
3 3
0 s 5 3
3 0
s 3
3 0
s s 5 3
3 0
sy s
u u
6 s
s 6 1
1 6
r 1
1 6
s 8 1
1 6
s i
1 1
T Oae A T o o o i
o t
o s s o r
r n
s-s o t
Tmh s s o r
n s s o r
ir r
ir AmT G T C C C G Z C C C G T C C C G G Z C C C
(
Ru BS e
7 7
7 7
7 At l
Lo pt 7
7 7
7 7
7 9
9 9
9 9
7 7
7 7
r e 9 7
9 9
9 9
7 7
7 7
9 7
/
/
/
/
/
9 9
9 9
Rp ma 1
1 1
1 1
/
/
/
/
/
9
/
/
/
/
9 9
9 9
/
9 2
2 2
2 3
7 7
7 7
1
/
5 5
5 5
/
/
/
/
8
/
Ee aD 3
7 1
1 1
1 6
6 6
6 1
8
/
/
/
/
/
/
/
/
/
/
/
/
/
/
/
1
/
/
/
/
/
0 0
0 0
0 1
1 1
1 TR S
1 3
4 4
4 4
6 6
6 6
7 8
1 1
1 1
1 1
1 1
1 Nl a I
c 7i B B B B B B B B t
9s 9i d
d d
d d
d d
d n n n n t
n n n n i
i i
i 1 a l
B B B r
B B B B r
i i
i i
B l
l l
l l
l l
tS re e
e a
n n n t
t t
a a
n n n n n
e y
t t
t t
i u
t i
W o o o W
o o o o p
W io i
i i
i t
t T
in a a a a n
a a a a n i
i u u u u u u u u l
la l
l a
a e
a a a a a r
r r
r l
l l
l r
r r
r n
t a
a a t
l t
p e
r v v v v e e e e e r
v v v v e e e e e o
t t
t t
t t
t t
m B
e E E E E a a a a B e
E E E E B a a a a i
t t
t a
W W W W
/
a e e e e W W W W a
l a
e e e e l
t a W W
c c c c a a
S S
h c c c c n n n n h n n n n n n n n n n n n h r
lp n a a a a i
i i
i p
n a a a a lp i
i i
i a
A m m m m a a a a lA m m m m A a a a a i
i e
m r
r r
r s m m m m m
m m m m s l
r r
r r
s c
u o o o o s m m m m u
s u o o o o m m m m s i
f f
f f
o i
f f
f f
o t
r r
r r
o r
it r
r r
r a a a a N
e e e e a a a a r
i e e e e r
r r
G T P P P P G G G G G T P P P P G G G G G o
ce S
o hcnaR 1l, j
ll I
APPENDIX D SAMPLE COLLECTION AND ANALYSIS METHODS For each of the sample media collected, the method of collection is documented in Rancho Seco Nuclear Station procedures. Detailed analysis methods are documented in procedures controlled by the contractlaboratory, Thermo Nutech. A brief description of these collection end analysis methods is included in this Appendix.
Sample Media Collection / Analysis Method AIR An air sampler continuously moves air through a filter paper designed to capture particulates by filter paper impaction. The air samplers are equipped with a flow totalizer which measures the volume of air that has passed through the filter paper.
l The filter paper is exchanged weekly. At least one day is allowed to elapse between sample collection and counting to reduce the I
interference of naturally occurring raden and thorium daughters on the sample analysis. The filter paper is assayed for gross beta radioactivity by placing the filter on a stainless steel planchet and counted with an intemal gas flow proportional counter.
The individual particulate filter papers are saved over a calendar quarter and the composite collection is assayed for gamma isotopic radioactivity by gamma spectroscopy.
I DIRECT RADIATION Thermoluminescent dosimeters (TLDs) are located within a ten (10) mile radius of the site. TLD's within a five (5) mile radius are considered j
indicator TLD's. Two (2) TLD's, each containing three CaSO4Dy phosphors, are placed at each monitoring location to assure adequate data recovery and to improve measurement statistics. The TLD field exposure cycle is approximately ninety (90) days. At the end of the field exposure cycle, the TLD's are exchanged and retumed to a contract laboratory for processing. The exposure reported by the laboratory is the average of six values, corrected for non-field exposure cycle contributions, i
Rancho Seco Nuclear Station D-1 1997 AREOR
l l
Sampic Media Collection / Analysis Method I
l SOIL &
SEDIMENT Samples of sediment and soil are collected from the top three inches of the sampled material. Sediment samples are obtained approximately two feet from the shoreline. Each sample is assayed directly for gamma isotopic radioactivity by gamma spectroccopy.
GARDEN PRODUCE Samples of vegetables are collected semi-annually from a garden which is maintained at the Station Site Boundary Controllocation samples are collected from a local commercial vendor. The vegetables are assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
FISH Fish are collected semi-annually from the Clay Creek system. The dissected (edible) portion of each sample is assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
ALGAE Samples of algae in the Clay Creek system are collected semi-annually I
I and assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
WATER One gallon grab samples of water from locations in the liquid effluent pathway and groundwater are collected as follows:
Surface water and drinking water are collected monthly
)
Runoff wateris collected biweekly Wellwateris collected quarterly.
At two locations, samples are obtained to provide a monthly composite sample. Al' samples are assayed for tritium by liquid scintillation counting and for gamma isotopic radioactivity by gamma spectroscopy.
Drinking and Well water samples are analyzed for Gross Beta activity.
RAIN WATER One gallon grab samples of rainwater, collected at the Meteorological Tower location, are collected on a seasonal basis. All samples are assayed for tritium by liquid scintillation and for gamma isotopic radioactivity by gamma spectroscopy.
l Rancho Seco Nuclear Station D-2 1997 AREOR
APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program (REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operation REMP is a continuation of a similar progran :nitiated prior to and during operation of the Station.
Samples of the surrounding envinnment are collected on a routine basis and analyzed to determine the amount of radiation and radioactive materials present in the exposure pathways.
During 1997 the program was directed and executed by the Radiation Protection / Chemistry Superintendent. Sample collection is performed by the Technical Staff and the Chem 1 Rad Decommissioning Technicians. Data review and Program maintenance are performed by the Radiological Health Supervisor. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.
The Program is designed consistent with Title 10, Code of Federal Reaulations. Part 50, Appendix l - Section IV, B.2, B.3 and C, and Appendix A, " General Design Criteria for Nuclear Power Plants," Criterion 64. The program also complies with Title 10, Code of Federal Reaulations. Part 20, " Standards for Protection Against Radiation," Section 1302. These i
federal requirements are cited in the Rancho Seco Permanently Defueled Technical i
Specifications and the REMP manual. REMP requirements are implemented through the
)
1 review, approval and routine use of several documents, namely the REMP Manual, Offsite Dose Calculation Manual, Surveillance Procedures and Health Physics implementing Procedures.
1 The programmatic elements of the REMP are based on regulatory requirements and cssociated guidelines. The objectives of the Program are to:
1.
Provide the technological basis and the instruction for monitoring the environs for radioactivity sources. The radioactive sources which contribute to detectable radioactivity in the local environs are comprised of:
o naturally occuning background, o releases during normal operations, o worid-wide weapons testing, and o majorglobalnuclearaccidents i
i Rancho Seco Nuclear Station E-1 1997 AREOR l
PROGRAM BASIS
' (Continued) 2.
Provide the means to verify the effectiveness of the Rancho Seco Nuclear Station Radiological Effluents Control Program.
3.
Meet the minimum detectable limits for radioisotopes in environmental samples.
4.
Provide quantitative measurements in the gaseous, liquid and direct radiation exposure pathways for radionuclides.
5.
Provide indications of the largest potential radiation exposure for individuals as a result of radionuclides in the principle exposure pathways.
The Program is developed and conducted using recognized standards and practices NRC79a, NRC79b, NUREG79, NUREG80a.
REMP CHANGES The Permanently Defueled Technical Specifications administrative requirements for the REMP program were not revised during 1997. The REMP manual (revision 10) was revised on August 19,1997 to:
- 1. Change the required number of montt'y composite water samples from one (1) to two (2) in Table 1, section 3.a. This change was implemented to add clarity to the sampling l.
l program.
I i
l EXPOSURF 'ATHWAYS The fundamental parameters which have been defined prior to monitoring the environs are:
1.
Identification of the effluent release pathways 2.
Identification of the human exposure pathways 3.
Identification of the land use parameters by the population within a two mile radius of the plant site.
Each of these three parameters is discussed below.
t Rancho Seco Nuclear Station E-2 1997 AREOR l
N EXPOSURE PATHWAYS Effluent Release Pathways There are three principal pathways which may result in human exposure to radiation and radioactive material originating from Station operation:
- 1. Gaseous effluents
- 2. Liquid effluents and
- 3. Direct radiation from these effluents and onsite sources.
Gaseous Effluents Gaseous ventilation and process effluents are released, through particulate filtration units to the environment from the Reactor Building, Auxiliary Building and Auxiliary Building Grade Level Vent stacks.
In the gaseous pathway, airbome radioactive materials can be inhaled or ingested by humans.
Animals can inhale or ingest radioactive material present in the atmosphere which are r;tained in animal food products (meat or milk). Radioactive materials which are carried by air currents can also be deposited on vegetation or water sources which are in tum directly consumed by humans or animals.
Liauid Effluents in the liquid exposure pathway, radioactive materials in surface waters can be ingester 5y.
humans directly or indirectly through the consumption of aquatic foods such as fish and shellfish. Humans can consume vegetation which is irrigated with Clay Creek water which may contain radioactive material. Another exposure pathway from liquid effluents results from the consumption of animal products such as meat and milk from animals which have fed upon irrigated vegetation or otherwise drank Clay Creek water.
Direct Radiation in the direct radiation pathway, potential radiation exposure may occur from radioactive material storage vessels which are contained within the site boundary such as the Borated Water Storage Tank. People can potentially be exposed to direct radiation from gaseous cffluents or from ground deposition of particulates deposited on the ground from gaseous or i
liquid effluents. When the fuel off-load is completed, the ISFSI will become part of the direct radiation pathway.
R ncho Seco Nuclear Station E-3 1997 AREOR l
l
i LAND USE CENSUS On an biennial basis, a land use census is conducted within a two mile radius to identify any changes in the human exposure pathways. The Land Use Census is used to determine the changes needed for REMP monitoring activities. The results of the land use census conducted during 1996 is presented in Appendix A of this Report. The next scheduled land use census will be conducted in 1998 and reported in the 1998 AREOR. From data obtained from the Land Use Census, exposure pathways are analyzed through a systematic process I
which identifies a semple medium or organism that is found to potentiaily contribute to an individual's radiation exposure. Usage and bloaccumulation factors (NRC77) are then specified which represent the magnitude of radioactive material transfer through the food chain to a receptor. The analysis of the affluent and exposure pathways enables monitoring sites to be identified as " indicator" (for sites at which the potential effects of Station effluents would be readily detected) or " control" (for those sites whlen are not expected to be influenced by i
Station operation). The analysis results of samples obtained at indicator and control sites are routinely compared to identify potential exposures above background levels.
MONITORING LOCATION SELECTION The REMP maintains the monitoring sites required by the REMP manual, Table 6. This program is supplemented with additional samples to compensate for changes in the radiological environment surrounding Rancho Seco. Some of the monitoring sites were also selected by the United States Nuclear Regulatory Commission'and the Califomia Department
)
of Health Services as part of their monitoring programs. Indicator sites are placed in areas which would be most sensitive to the effects of Station effluents such as downwind or downstream areas near the Station. If radioactive materialis detected above background at any of these indicator sites, observed potential exposure and dose to humans can be estimated to verify the effectiveness of the Offsite Dose Calculation Manualin predicting potential exposures or doses. It is important to note that the detection of radioactive material in indicator samples does not necessarily mean that it's presence can be attributed to Rancho Seco operations.- Moreover, especially with most liquid effluent pathway samples, the I
detection of radioactive material is difficult to interpret since it is unknown when the material was deposited. In many instances, the observed radioactive material could correctly be -
ascribed to historical (pre-1997) depositions.
Control locations provide data that should not be influenced by the operation of Rancho Seco.
These locations are selected based upon distance from the Station in the upwind or upstream I
direction of the effluent release pathways. Samples obtained from controllocations should, upon analysis, reveal information about the presence and distribution of naturally occurring and man-made radioactive materials. Data from these locations are used to aid in the discrimination between the effects of Rancho Seco releases and other natural phenomena or accidental releases (such as the 1986 Chemobyl accident) which may result in human exposure.
t Rancho Seco Nuclear Station E-4 1997 AREOR
l l
MONITORING LOCATION SELECTION l
(continued)
I G:seous effluent indicator monitoring sites are generally placed in areas which receive l
prevailing winds crossing the Rancho Seco site. Liquid radioactive effluents are discharged in b tches from two onsite Retention Basins into "No Name" Creek located southwest of the Station. Dilution water, obtained from the Folsom South Canal, is discharged into "No Name" l
Creek to give reasonable assurance of compliance with the 10CFR50, Appendix I dose guidelines. "No Name" Creek flows southerly into the Clay Creek. Without this dilution water flow, the Clay Creek would be in a dry state for most of the year.
i Beyond the Site Boundary at a point north of Highway 104, the Clay Creek empties into the Hrdselville Creek. Hadselville Creek then empties into the Laguna Creek at a point west of I
N:rth Clay Station Road near the Folsom South Canal. Finally, Laguna Creek flows into the Cosumnes River at a point located approximately 20 straight-line miles west of Rancho Seco.
l Since this stream system is the only routine release pathway for liquid radioactive and non-l r dioactive effluents from the Station, the liquid exposure pathway indicator sites are located l
cl:ng these creeks and nearby land.
The direct radiation pathway is monitored principally through a network of passive devices (thermoluminescent dosimeters - TLD's) at monitoring sites distributed in sectors centered on ths Station. The TLD's are located primarily at the site, residential, and recreational areas ground the Rancho Seco location. This design provides the capability to easily detect Station-induced direct radiation contributions to the observed terrestrial and cosmic direct radiation bIckground.
Some TLD's have been sited in speciallocations to record direct radiation resulting from l
known depositions of radioactive material and to provide pre-operational data for the interim Spent Fuel Storage Installation (ISFSI).
Appendix B contains a detailed description and illustration of the REMP sample and monitoring locations.
l l
i R ncho Seco Nuclear Station E-5 1997 AREOR l
SAMPLE MEDIA Samples are collected from predetermined monitoring sites at a specified frequency. The sample media chosen is a function of the type of monitoring desired and coincide with one of the following exposure pathways:
o Atmospheric o
Direct radiation o
Terrestrial o
Aquatic life o
Water Atmospheric monitoring is accomplished by filtering a volume of air using a mechanical air pump to collect particulates with a particulate filter paper. Four air sampler Iccations are used to collect weekly air samples. Two locations (Meteorological Tower and Rancho Seco Reservoir) are control locations and the remaining two locations are indicator locations on the plant site.
Direct radiation monitoring is achieved by placing TLD's at above-ground sites. TLD's respond to, and record the amount of, gamma radiation exposure. The source of this gamma radiaticr. exposure is varied and includes potential Station effluents and naturally-occurring i
terrestrial and cosmogonic radionuclides. The TLD's are also influenced by seasonal and global (fallout) radiation sources. Almost all the exposure recorded by a TLD could be traced to terrestrial radionuclides.
There are 34 sites which are monitored by thermoluminesence dosimetry within a 10-mile radius of the Station. The TLD's are placed at the Station industrial Area Boundary, near the property boundary, locations of interest such as nearby residences, and also at control locations located beyond five miles of the Station.
Terrestrial monitoring is accomplished by obtaining samples of sediment, soil, and garden vegetation to measure the quantity of radioactive material deposited from gaseous and liquid effluents. There are 5 mud and silt,27 soil, and 2 garden vegetation locations.
Aquatic monitoring includes the sampling of fish and algae. Algae is an excellent concentrator of radioactivity contained in water and is sampled to provide an earty indication of l
I increased liquid radioactive material concentration. There are 4 fish and 5 algae sample locations.
l l
l Rancho Seco Nuclear Station E-6 1997 AREOR l
I
SAMPLE MEDIA (continued)
Water monitoring includes samples of surface, runoff, drinking, and well sources from locations in the liquid effluent pathway and from art a wells. The 6 surface water sampling i
I locations monitor site supply water (Folsom South Canal), runoff water and water discharged from the Station. Drinking water is sampled from 6 groundwater wells and two drinking water taps. A new Drinking Water location was added to sample a residence located near the Clay Creek system. This location was added to reflect the change is agricultural use of the surrounding area. Rain water is also collected at one location on a seasonal basis.
SAMPLE ANALYSIS & DATA HANDLING The laboratory which provides radio-analytical services for the Program is Thermo Nutech located in Richmond, Califomia. Sample analysis results submitted by Thermo Nutech are reviewed for accuracy and completeness and then entered into a computerized data base for evaluation and trending.
Data comparisons are made between individual control and indicator sample sites to isolate potential Station influences on the measurement results.
The summarized results of the 1997 Radiological Environmental Monitoring Program are presented in Table 2.
Individual (raw data) results are presented in Appendix F, Tables F-1 through F-11.
REGULATORY REPORTING LEVELS Sample analysis data is promptly reviewed and evaluated by the Radiological Health Supervisor as the results are received. All sample analysis results are reviewed for correct sensitivity and anomalies.
The activity concentration values listed in Table E-1 are the environmental Fuel Cycle Dose quantities that, if exceeded, require a Special Report to be submitted to the USNRC. In cccordance with the REMP Manual (Section 5, Fuel Cycle Dose), the Special Report must include an evaluation of any release conditions, environmental factors or other aspects which j
caused the reporting limits to be exceeded.
Rancho Seco Nuclear Station E-7 1997 AREOR
REGULATORY REPORTING LEVELS (continued)
In addition to the Fuel Cycle Dose reporting requirements, a Special Report is required to be submitted to the USNRC when more than one of the radionudides in Table E-1 are detected in the sampling medium and the summed ratio of detected activity concentration to the respective Reporting Level concentration is greater than, or equal to, unity (1). When radionuclides other than those listed in Table E-1 are detected which are a result of Station effluents, a Special Report is required to be submitted if the potential annual dose commitment exceeds the 10 CFR 50, Appendix 1 guidelines.
No reports of the types described above were required to be submitted during 1997.
SENSITIVITY OF THE REMP MEASUREMENT PROCESS All Program measurements must be performed at a sensitivity which meets USNRC requirements. This sensitivity is determined "before the fact" (a priod) for each radionuclide of interest and sample analysis type. Typical controllable sensitivity parameters includa:
o Sample volume or mass o Sampling efficiency
= Time from sample collection to measurement
= Instrument detection efficier$cy for the nudides (energies) of interest o Background radiation levels o Chemicalrecoveryfactors By adjusting and controlling each of these parameters to maximize measurement process efficiency, a maximum sensitivity level (activity concentration) can be specified for each nudide of interest and analysis type while maintaining an economic measurement process. The maximum sensitivities in the REMP are specified by the USNRC in the REMP Manual approved for Rancho Seco. These sensitivities are referred to as "LLD's", an acronym for
" Lower Limit of Detection". LLD's are specified on an "a p#orf' basis and apply to routine measurement process capabilities when no other interfering radioactivity is present. 'Ihe word
" routine"is emphasized since occasional cimumstances, such as limited sample mass, elevated levels of background radiation and interfering nudides can contribute to sensitivity degradation.
Such occurrences are normally noted and reported during the conduct of REMP activities.
Rancho Seco Nudear Station E-8 1997 AREOR
SENSITIVITY OF THE REMP MEASUREMENT PROCESS (continued)
Meeting the LLD requirements is a quality control function shared by both REMP and the
. cnalytical laboratoar personnel. Once the laboratory establishes values for the controllable parameters for each analysis type, sample chain of custody controls ensure that these parameters are upheld. If all parameters are upheld, then compliance with the LLD requirements has been demonstrated. The specific LLD values for Program measurements tre included in Table E-2.
Since most of the samples analyzed result in the detection decision " activity not identified", a Minimum Detectable Activity (MDA) concentratiori value is calculated and reported. This value can be thought of as the LLD-at-the-time-of-counting since it is calculated using an equation which is similar to the one used to establish LLD parameters. The biggest difference is that actual (not "a priott') parameters are used, including interference from natural radioactive material in the sample. It is important to note that MDA's are reported only for those measurements where the " activity not identified" decision has already been made.
MDA values are used primarily to identify changes in the measurement process and to convey more information about the measurement itself. Without the use of the MDA concept, most Program measurements would be reported simply as "<LLD". With MDA used, Program measurements are reported as "< xxx " where "xxx" is the calculated MDA concentration.
l i
l Rancho Seco Nuclear Station E-9 1997 AREOR l
l
TABLE E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Airborne Fish Food (pCl/L)
Particulate or (pCilkg, wet)
Products Gases (pCi/m*)
(pCilkg, wet)
H-3 20000*
Mn-54 1000 30000 Co40 300 10000 Zn45 300 20000 Cs-134 30 10 1000 1000 Cs-137 50 20 2000 2000 b
Gross Beta 40 2*
Notes:
- For drinking water samples, this is a 40 CFR Part 141 value
- Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample (NRC79a). Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.
- Gross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.
Rancho Seco Nuclear Station E-10 1997 AREOR
'f
i 1
l l
TABLE E-2 l
MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES *
(NRC79A)
)
Airborne Fish Food Sediment Particulate (pCilkg, Products (pCilkg, dry)
Analysis Water or Gases wet)
(pCilkg, dry) l (d)
(pCi/L)
(pCilm')
Gross Beta 4
0.01 H-3 2000 (1000, D)
Mn-54 15 130 Co-60 15 130 150' Zn-65 30 260 Cs-134 -
15(10")
d 130 60 150 0.01 Cs-137 18 (10")
d 150 0.01 130 60 l
Notes:
(a)
An9 lysis requirements are those recommended in the BTP (NRC79AJ and RETS
[NUREG79].
(b)
LLD for water samples utilized for human consumption only (NUREG79].
-(c)'
Other peaks which are measurable and identifiable, together with the nuclides in Table E-2 shall be identified and reported.
(d)
Composite analysis LLD is Shown; individual sample LLD is 0.05 pCi/m*(Site specific value).
(e)
LLD for Mud and Silt Co-60 is not required by RETS [NUREG79). This value is consistent i
with the RETS required value for Cs-134 and CS-137.
i Rancho Seco Nuclear Station E-11 1997 AREOR l
1 i
Y APPENDIX F l
1997 SAMPLE ANALYSIS RAW DATA TABLES l
l l
l i
l I
I l
t 1.
i '
t l
\\
i I
l I
l-i l
r i
, RIncho Seco Nuclear Station F-1 1997 AREOR
)
TABLE F-1 1997 WEEKLY AIR SAMPLE
SUMMARY
Gross Beta Activity in Air Particulates i
(pCl/m')
C:llection RASO.1CO 2 sigma RASO.3MO 2 sigma RASO.7EO 2 sigma RAS 1.8FP 2 sigma Date 1/6/97 0.012 0.001 0.012 0.001 0.011 0.001 0.011 0.001 1/13/97 0.034 0.001 0.027 0.001 0.032 0.001 0.031 0.001 1/21/97 0.027 0.001 0.024 0.001 0.024 0.001 0.024 0.001 1/28/97 0.011 0.001 0.009 0.001 0.01 0.001 0.000 0.001 2/3/97 0.022 0.001 0.019 0.001 0.019 0.001 0.018 0.001 2/10/97 0.023 0.001 0.022 0.001 0.022 0.001 0.021 0.001 0.026 0.001 0.023 0.001 0.022 0.001 0.021 0.001 2/18/97
_ 0.018 0.001 0.017 0.001 0.016 0.001 0.016 0.001 2/25/97 5/3/97 0.019 0.001 0.017 0.001 0.015 0.001 0.015 0.001 3/10/97 0.021 0.001 0.019 0.001 0.015 0.001 0.02 0.001 3/18/97 0.024 0.001 0.021 0.001 0.025 0.001 0.021 0.001 3/25/97 0.031 0.002 0.027 0.001 0.03 0.001 0.029 0.002 3/31/97 0.018 0.001 0.018 0.002 0.018 0.001 0.017 0.002 4/7/97 0.015 0.001 0.014 0.001 0.014 0.001 0.014 0.001 4/15/97 0.016 0.001 0.014 0.001 0.014 0.001 0.015 0.001 4/22/97 0.015 0.001 0.013 0.001 0.014 0.001 0.013 0.001 4/29/97 0.015 0.001 0.013 0.001 0.014 0.001 0.013 0.001 5/5/97 0.026 0.002 0.031 0.002 0.026 0.001 0.024 0.001 5/12/97 0.019 0.001 0.021 0.001 0.019 0.001 0.019 0.001 5/20/97 0.02 0.002 0.019 0.002 0.02 0.002 0.019 0.002 5/27/97 0.02 0.004 0.017 0.001 0.019 0.002 0.017 0.001 6/2/97 0.014 0.001 0.014 0.001 0.015 0.001 0.014 0.001 6/9/97 0.015 0.001 0.013 0.001 0.014 0.001 0.014 0.001 6/17/97 0.013 0.001 0.012 0.001 0.013 0.001 0.013 0.001 6/24/97 0.015 0.001 0.016 0.001 0.016 0.001 0.014 0.001 6/30/97 No Data No Data 0.015 0.002 0.017 0.001 0.013 0.001 R:ncho Seco Nuclear Station F-2 1997 AREOR
TABLE F-1 1997 WEEKLY AIR SAMPLE
SUMMARY
(continued)
Gross Beta Activity in Air Particulates (pCi/m*)
C:llecti:n RASO.1CO 2 sigma RASO.3MO 2 sigma RASO.7EO 2 sigma RAS 1.8FP 2 sigma Date 7/7/97 0.018 0.002 0.016 0.001 0.018 0.002 0.016 0.001 7/14/97 0.016 0.002 0.015 0.001 0.014 0.001 0.018 0.003 7/21/97 0.017 0.002 0.018 0.002 0.018 0.001 0.017 0.001 7/29/97 0.02 0.002 0.02 0.002 0.021 0.001 0.019 0.001 8/5/97 0.017 0.001 0.017 0.001 0.018 0.001 0.017 0.001 8/11/97 0.022 0.001' O.021 0.002 0.025 0.002 0.022 0.001 8/18/97 0.018 0.001 0.019 0.001 0.021 0.001 0.017 0.001 8/26/97 0.015 0.001 0.014-0.001 0.015 0.001 0.014 0.001
~
9/2/97 0.015 0.001 0.015 0.001 0.016 0.001
- 0.38 0.001 9/8/97 0.025 0.002 0.022 0.002 0.026 0.002 0.024 0.002 9/16/97 0.024 0.001 0.021 0.001 9/23/97 0.021 0.001 0.02 0.001
~0.fi23 0.001 0.021 0.001 0.022 0.001 0.02 0.001 9/30/97 0.035 0.002 0.035 0.002 0.04 0.002 0.035-0.002 l
10/6/97 0.018 0.002 0.017 0.001 0.021 0.001 0.018 0.002 10/13/97 0.019 0.002 0.018 0.001 0.02 0.001 0.016 0.001 i
10/21/97 0.041 0.002 0.039 0.002 0.044 0.002 0.037 0.002 -
10/28/97 0.04 0.003 0.038 0.003 0.047 0.002 0.042 0.002 -
11/4/97 0.037 0.002 0.048 0.003 0.038 0.002 0.035 0.002 11/11/97 0.037 0.002 0.033 0.002 0.034 0.002 0.035 0.002 11/18/97 0.018 0.001 0.016 0.001 0.017 0.001 0.016 0.001 11/25/97 0.026 0.002 0.023 0.002 0.044 0.004 0.025 0.002 12/2/97 0.018 0.001 0.018 0.001 0.017 0.001 0.019 0.001 12/8/97 0.034 0.002 0.034 0.003 0.031 0.002 0.036 0.002 12/16/97 0.025 0.001 0.022 0.001 0.021 0.002 0.023 0.001 12/23/97 0.021 0.002 0.022 0.002 0.022 0.001 0.022 0.001 12/30/97 0.048 0.003 0.043 0.003 0.046 0.002 0.05 0.004
- Volum3 for sample 200 cubic feet due to mechanical problem with air sampler.
t Rrncho Seco Nuclear Station F-3 1997 AREOR
I Table F-2 1997 TLD Summary (Direct Radiation)
Quarterly (mrem)
Location ID Type 97-1 97-2 97-3 97-4 RTLO.3RO INDICATOR 13.4 15 15.3 15.8 RTLO.3CO INDICATOR 14.3 15.5 14.7 16.4 RTLO.3NO INDICATOR 14 15 15.4 17.1 RTLO.3LO INDICATOR 13.1 14.7 14.9 14 RTLO.3HO INDICATOR 13.3 14.3 14.1 15.3 RTLO.4FO INDICATOR 11.2 13.5 13.9 14.1 RTLO.5CO INDICATOR 12.3 14.8 15.5 17.7 RTLO.6KO INDICATOR 12.3 14.1 14.8 14 RTM0OHP CONTROL 12.7 14.4 15.3 16.6 RTL2.7MO INDICATOR 10.9 13.4 13.3 14.1 RTL8.2KO CONTROL 14.2 17.5 Missing 21.1 RTL7.8CO CONTROL 11.7 12.6 15.5 15.8 RTL1.8FO INDICATOR 11.2 13.8 12.9 18.4 RTL1.5MO INDICATOR 12.6 14.9 14.7 14.1 RTL3.9KO INDICATOR 11.4 14.4 14.2 14.1 RTL7.4MO CONTROL 12.7 15.3 14.1 14.8 RTL3.7NO INDICATOR 13 13.9 14.4 16
)
RTL3.8MO INDICATOR 13.9 14.1 14.9 17.5 RTL1.9NO INDICATOR 13.6 15.9 17.2 16.1 RTL1.7FO INDICATOR 12.4 13.6 15.2 13.9 RTL1.4DO INDICATOR 13.1 16.3 16.5 16.4 RTL10.0EP CONTROL 11 13.9 14.2 13.9 RTL8.0PO CONTROL 13.7 14.4 14.7 16.7 RTLO.8DO INDICATOR 11.4-14.6 14.4 15.7 RTLO.6MO INDICATOR 11.6 13.6 13.8 11.9 RTLO.4NO INDICATOR 25.2 27.1 27 28.5 RTLO.4NO1 INDICATOR 14.3 16.2 16.5 16.5 RTLO.3PO INDICATOR 13.1 14.1 16.4 15.4 RTLO.3NP INDICATOR 16 15 14.8 16.4 RTLO.4NP INDICATOR 13.8 14.7 16.2 15.6 RTLO.5NP INDICATOR 14.2 16.3 15.9 16.1 RTLO.3QP INDICATOR 13.9 14.4 14.7 15.7 RTLO.70P INDICATOR "L1 14.8 14.7 14.4 RTLO.7JO INDICATOR 13.4 15.3 14 15.6 RTLO.4PP INDICATOR 17.5 15.4 16.1 19 Rancho Seco Nuclear Station F-4 1997 AREOR
1 Table F-3 1997 Garden Vegetables (pCi/kg, wet)
Sample ID Collection Date Mn44 Co40 Zn45 Cs-134 Cs-137 -
RLVO.6MO 2/10/97
<51
<38 RLV18.0KO 2/10/97
<54
<41 RLVO.6MO 7/21/97
<4.0
<5.0
<11
<6.0
<5.0 RLV18.0KO 7/21/97
<10
<13
<24
<11
<10 RLVO.6MO 9/11/97
<S 0
<5.0
<12
<6.0
<4.0 RLV18.0KO 9/11/97
<4.G
<5.0
<12
<6.0
<8.0 TABLE F-4 1997 SEDIMENT Quarterly (pCi/kg)
Co40 Cs 137 Sample ID Collection date Mn44 Co40 2 sigma Zn45 Cs-134 Cs-137 2 sigma RMSO.3MO 2/10/97
<10
<11
<10
<12 86 12 RMSO.7NO 2/10/97
<7.9
<8.5
<18
<9.6 165 11 RMSO.6MO 2/10/97
<4.6 16 5.3
<12
<9.3 329 8.5 RMS1.8NO 2/10/97
<5.3
<6.3
<14
<10 328 8.7 RMS3.7NO 2/1007
<11
<12
<28
<15 76 14 RMSO.3MO 8/11/07
<8.0
<8.0
<21
<10 -
150 11 RMSO.7NO 8/11/57
<6.0
<6.0
<13
<7.0 81 8.0 RMSO.6MO 8/11/97
<4.0 14 4.0
<9.0
<5.0 240 6.0 RMSO.6MOQ 8/11/97
<7.0 14 7.0
<19
<9.0 210 10 RMS1.8NO 8/11/97
<8.0
<6.0
<17
<9.0 57 5.0 RMS3.7NO 8/11/97
<17
<17
<43
<19 34 16 RMSO.3MO 11/18/97
<12
<14
<33
<15 106 17 RMSO.7NO 11/18/97
<10
<10
<27
<13 91.0 10 RMSO.6MO 11/18/97
<5.0 14 5
<12
<7 304 8
RM 'O.6MOQ 11/18/97
<11 14 10
<27
<14 294 16 RMS1.8NO 11/18/97
<6 8
5
<15
<12 296 8
RMS3.7NO 11/18/97
<8
<9
<24
<13 19 7
Acncho Seco Nuclear Station
.F-5 1997 AREOR i
r.-
I l
l TABLE F-4 (continued) 1997 SOIL AND SEDIMENT Effluent Creek Semi-Annual l
(PCl/kg)
Sample ID Description Collection Mn-54 Co-60 Co40 Zn45 Cs-134 Cs-137 Cs-137 Date 2 sigma 2 sigma RSL1.8NO Hadselville/
3/3/97
<10
<9
<28
<8
<9 l
l Clay Creeks i
RSL1.5NO Silva 3/3/97
<14
<13
<29
<10 415 36 l
Property RSLO.7NO Water Sump 3/3/97
<12
<10
<26
<10 191 30 RSLO.6MO Site 3/3/97
<12 81 24
<29
<10 952 54 Boundary l
RSL1.8NO Hadselville/
9/8/97
<15
<14
<34
<12 77 l
Clay Creeks RSL1,5NO Silva 9/8/97
<14 53
<36
<12 1581 Property RSLO.7NO Water Sump 9/8/97
<11
<13
<29
<10 117 RSLO.6MO Site 9/8,97
<13
<18
<30
<12 405 Boundary Rancho Seco Nuclear Station F-6 1997 AREOR
TABLE F-4 4
(continued) 1997 SOIL AND SEDIMENT Storm Drains Semi-Annual (PCi/kg)
S mple ID -
Description Collection Mn-Co-Co-60 Zn.
Cs-Cs-Cs-137 t
Date 54 60 2 sigma 65 134 137 2 sigma RSLO.3NP1 ISFSI#1 3/3/97
<11
<9
<26
<8
<11 RSLO.3NP2 ISFSI#2 3/3/97
<9
<10
<27
<8
<9 RSLO.3NP3 '
ISFSl#3 3/3/97
<9
<8
<24
<7
<8 RSLO.2HO1 Storm Drain 3/3/97
<9
<7
<19
<7
<8
- 1 RSLO.2HO2 Storm Drain 3/3/97
<11
<11
<28
<8 38 21
- 2 RSLO.2JO Storm Drain 3/3/97
<12
<10
<26
<8
<11
- 3 RSLO.2KO Storm Drain 3/3/97
<9
<10
<24
<6 49 11
- 4 i
RSLO.3LO Storm Drain 3/3/97
<11
<8
<27
<8
<11
- 5 RSLO.2HO Storm Drain 3/3/97
<12
<1L
<37
<10
<12
- 6-RSLO.3MO7 Storm Drain 3/3/97
<10
<7
<21
<7
<9
- 7 RSLO.3MO8 Storm Drain 3/3/97
<11
<10
<28
<8 45 20
- 8 RSLO.3MO9 Storm Drain 3/3/97
<12
<8
<27
<9 36 21
- 9 RSLO.3AO Storm Drain 3/3/97
<9-
<10
<27
<7
<9
- 10 RSLO.3QO Storm Drain 3/3/97
<9
<7
<23
<7
<7
- 11 RSLO.3NO -
Storm Drain 3/3/97
<9
<10
<23
<8 34 20
- 12 e
. Ranchs Seco Nuclear Station F-7 1997 AREOR
TABLE F 4 (continued) 1997 SOIL AND SEDIMENT Storm Drains Semi-Annual (PCi/kg)
Simple ID Description Collection Date Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RSLO.3NP1 ISFSI #1 9/11/97
<10
<11
<32
<9
<47 RSLO.3NP2 ISFSI#2 9/11/97
<12
<11
<27
<9
<59 RSLO.3NP3 ISFSI #3 9/11/97
<10
<10
<26
<8
<45 RSLO.2HO1 Storm Drain #1 9/8/97
<14
<14
<31
<10
<72 RSLO.2HO2 Storm Drain #2 9/8/97
<12
<14
<30
<9 49 RSLO.2JO Stotm Drain #3 9/8/97
<13
<13
<25
<10
<59 RSLO.2KO Storm Drain #4 9/8/97
<13
<13
<28
<10 67 RSLO.3LO Storm Drain #5 9/8/97
- 412
<13
<28
<10 86 RSLO.2HO Storm Drain #6 9/8/97'
<12
<12
<30
<10 23 RSLO.3MO7 Storm Drain #7 9/8/97
<10
<11
<28
<7 29 RSLO.3MO8 Storm Drain #8 9/8/97
<10
<11
<22
<9 68 RSLO.3MO9 Storm Drain #9 9/8/97
<11
<11
<28
<9 61 RSLO.3AO Storm Drain #10 9/8/97
<8
<12
<25
<9
<92 RSLO.3QO Storm Drain #11 9/8/97
<10
<8
<20
<8
<17 RSLO.3NO Storm Drain #12 9/8/97
<9
<10
<22
<8
<41 t
l Rrncho Seco Nuclear Station F-8 1997 AREOR l
l
TABLE F-4 (continued) i 1997 SOIL AND SEDIMENT Characterization
{
Site Boundary / Depression Areas Semi-Annual (PCi/kg)
Sample ID Description Collection Mn-54 Co-60 Co-60 2 Zn-65 Cs-Cs-Cs-137 Date sigma 134 137 2 sigma RSLO.4MP1 Depression 3/3/97
<17 119 40
<37
<18 3337 106 RSLO.4MP2 Depression 3/3/97
<11 238 31
<25 65+-
7429 116 22 RSLO.4MP3 Depression 3/3/97
<9
<9
<21
<7 349 34 RSLO.5MPAK Site 3/3/97
<10
<9
<25
<7 163 27 i
Boundary RSLO.5MPAL Site 3/3/97
<12
<13
<25
<10 169 30 Boundary RSLO.5MPAM Site 3/3/97
<12 148 31
<29
<10 1252 59 Boundary RSLO.5MPAN Site 3/3/97
<12
<10
<28
<8 170 30 Boundary RSLO.4MP1 Depression 9/11/97
<17 459
<44 145 18230 RSLO.4MP2 Depression 9/11/97
<22 588
<55 163 19500
( RSLO.4MP3 Depression 9/11/97
<20 102
<37 69 8239 l RSLO.5MPAK Site 9/11/97
<15
<13
<33
<11 367 Boundary RSLO.5MPAL Site 9/11/97
<20
<17
<35
<14 345 Boundary RSLO.5MPAM Site 9/8/97
<17 333
<39
<19 5405 Boundary RSLO.5MPAN Site 9/8/97
<12
<12
<32
<8 123 l
Boundary 4
R:ncho Seco Nuclear Station F-9 1997 AREOR a
\\
TABLE F 5 1997 FISH Semi-Annual (pCi/kg, wet)
Sample ID Collection Date Mn 54 Co40 Zn45 Cs-134 Cs-137 RFSO.6MO(1) 5/1/97
<17
<19
<45
<23 120 19 RFSO.6MO(1) 12/3/97
<30
<44
<91
<38 130 37 l
TABLE F-6 1997 ALGAE Semi-annual (pCi/kg, wet)
Sample ID Collection Date Mn' 54 Co40 Zn45 Cs-134 Cs-137 RAGO.7NO 3/25/97
<14
<17
<30
<17 54+-16 RAG 3.7NO 3/25/97
<14
<13
<29
<15 30+-14 RAGO.7NO 9/11/97
<9.0
<10
<21
<11 28+-11 RAG 1.8NO 9/11/97
<11
<13
<23
<13 34+-12_
RAG 3.7NO 9/11/97
<5.0
<6.0
<10
<7.0 16+-5 Rincho Seco Nuclear Station F-10 1997 AREOR
{
o
TABLE F-7 1997 WELL WATER Quarterly (PCi/L)
SamploID Collection Gross Beta Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 Date RWWO.8DO 3/18/97 4.5
<211
<9.8
<11
<23
<12
<10 RWW2.1MO 3/18/97 2.4
<209
<16
<16
<36
<18
<16 RWWO.8LO 3/18/97 4.5
<213
<18
<18
<30
<19
<17 RWWO.3EO 3/18/97 6.7
<214
<3.3
<3.7
<7.0
<4.4
<3.3 I RWW3.7MO 3/*.8/97 3.7
<217
<5.8
<7.8
<13
<7.8
<6.0 l RWWO.8CG 6/17/97 4.1
<170
<11
<9.5
<22
<11
<9.2
(
l RWW2.1MO 6/17/97 2.4
<170
<3.6
<3.7
<7.3
<4.6
<3.3 l RWWO.8LO 6/17/97 3.9
<170
<9.1
<10
<19
<11
<9.7
)
l RWWO.3EO 6/17/97 4.7
<170
<8.7
<10
<21
<10
<8.9 l RWW3.7MO 6/17/97 3.8
<170
<9.1
<8.4
<19
<11
<8.8 RWW3.7MO 9/16/97 3.5
<190
<9.4
<11
<20
<11
<10 RWWO.3EO 9/16/97 5.1
<200
<9.4
<11
<23
<12
<10 RWW1.5MP 9/16/97 3.1
<200
<8.6
<9.0
<19
<11
<9.4 RWW2.1MO 9/16/97 1.9
<200
<9.3
<9.5
<19
<9.8
<9.1 RWWO.8LO 9/16/97 4.6
<190
<11
<13
<23
<13
<10 l RWWO.8DO 9/16/97 4.1
<200
<3.9
<4.0
<8.5
<5.2
<3.7 RWW3.7MO 12/16/97 4.19
<100
<9.3
<12
<20
<1
<19 RWWO.3E0 12/16/97 7.56
<200
<3.4
<3.8
<7.2
<4.4
<3.3 RWW1.5MP 12/16/97 2.89
<190
<3.3
<3.5
<7.7
<4.3
<3.0 RWW2.1MO 12/16/97 2.93
<190
<8.5
<8.8
<20
<10
<8.4 RWWO.8LO
?2/16/97 2.31
<200
<8.6
<12
<18
<9.6
<8.9 RWWO.8DO 12/16/97 1.49
<200
<9.1
<10
<23
<12
<9.9 i
R:ncho Seco Nuclear Station F-11 1997 AREOR
r-1 TABLE F-8 1997 RUNOFF WATER Biweekly l
(pCi/L)
Sample ID Collection Date Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RRWO.6MO 1/13/97
<191
<9
<11
<22
<11
<9.6 RRWO.6MO 1/28/97
<208
<10
<10
<22
<12
<9.3 RRWO.6MO 2/10/97
<240
<4.0
<4.1
<8.7
<4.8
<3.6 RRWO.6MOQ 2/10/97
<233
<11
<12
<25
<13
<10 RRWO.6MO 2/25/97
<237
<9.7
<11
<20
<11
<10 RRWO.6MO 3/10/97
<415
<6.3
<7.8
<13
<6.9
<6.2
. RRWO.6MO 3/25/97
<210
<10
<11
<25
<13
<11 RRWO.6MO 4/7/97
<210
<10
<11
<22
<12
<10 RRWO.6MO 4/22/97
<160
<11
<11
<24
<13
<10 RRWO.6MO 5/5/97
<160
<8.5
<9.8
<18
<10
<9.4 RRWO.6MOQ 5/5/97-
<160
<3.5
<3.7
<8.0
<4.2
<3.7 RRWO.6MO 5/20/97
<390
<11
<12
<27-
<13
<11 RRWO.6MO 6/2/97
<390
<11
<11
<22
<12
<8.9 RRWO.6MO 6/17/97
<170
<7.6
<8.5
<16-
<9.5
<7.8 RRWO.6MO 6/30/97
<190
<8.4
<9.1
<18
- '11
<8.3 RRWO.6MO 7/14/97
<200
<9.9
<18
<20
<11
<8.4 RRWO.6MO 7/29/97
<220
<7.4
<8.2
<14
<8.7
<6.8 RRWO.6MO 8/11/97-
<240
<8.8
<13'
<21
<11
<9.7
)
RRWO.6MOQ 8/11/97
<240
<3.9
<4.0
<8.1
<4.8
<3.8 RRWO.6MO 8/26/97
<230
<3.2
<3.5
<7.1
<4.3
<3.1 RRWO.6MO 9/8/97
<200
<3.8
<4.2
<7.1
<4.7
<3.6 RRWO.6MO 9/23/97
<200
<11
<14
<22
<13
<11 RRWO.6MO 10/6/97
<220
<8.6
<9.8
<19
<11
<9.1 RRWo.6MO 10/21/97
<190
<3.7
<4.4
<7.2
<4.3
<4.0 -
RRWD.6MO 11/4/97
<200
<3.3
<3.7
<7.1
<4.1
<3.1 l
RRWO.6MOQ 11/4/97
<210
<4.0
<4.2
<8.6
<5.1
<5.3 RRWO.6MO 11/18/97
<180
<3.2
<3.8
<7.4
<4.3
<3.3 RRWo.6MO 12/2/97
<180
<9.6
<12
<22
<12
<10 RRWO.6MO 12/16/97
<200
<10
<12
<21
<12
<10 RRWO.6MO 12/30/97
<202
<9.46
<9.40
<22.1
<12.0
<9.61 l
Rcncho Seco Nuclear Station F-12 1997 AREOR
\\
\\
\\
r TABLE F-9 1997 SURFACE WATER Monthly Grab / Monthly Composite (pCi/L)
Simple ID Collection Date Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RSW1.3FO 1/28/97
<456
<22
<23
<46
<2,7
<22 RSWO.7NO 1/28/97
<436
<27
<22
<43
<i3
<18 RSW1.8NO 1/28/97
<437
<18
<25
<37
<21
<17 RSW3.7NO 1/28/97
<456
<18
<22
<40
<18
<18 RSWO.3MO 1/28/97
<458
<22
<21
<47
<28
<21 RSW1.3FO 2/25/97
<237
<6.7
<8.1
<13
<7.5
<6.4 RSWO.7NO 2/25/97
<242
<3.0
<3.6
<6.1
<4.1
<3.1 RSW1.8NO 2/25/97
<239
<7.8
<9.3
<17
<9.9
<8.1 RSW3.7NO 2/25/97
<228
<3.5
<4.1
<7.4
<4.8
<3.5 RSWO.3MO 2/25/97
<229
<4.2
<4.6
<8.4
<5.3
<3.8 RSW1.8NOQ 2/25/97
<230
<8.6
<8.8
<18
<10
<8.9 RSW1.3FO 3/31/97
<200
<9.7
<10
<20
<11
<9.1 RSWO.7NO 3/31/97
<200
<3.6
<4.3
<8.0
<4.7
<3.7 RSW1.8NO 3/31/97
<200
<8.7
<8.4
<19
<9.9
<8.3 RSW3.7NO 3/31/97
<200
<8.6
<10
<17
<9.2
<8.1 RSWO.3MO 3/31/97
<200
<9.5
<10
<21
<11
<9.0
_,RF' V1.3FO 4/29/97
<160
<9.1
<10
<19
<11
<10 t
A/0.7NO 4/29/97
<160
<11
<12
<24
<12
<11 RSW1.8NO 4/29/97
<160
<9.6
<11
<22
<12
<10 RSWO.3MO 4/29/97
<160
<3.4
<3.7
<6.8
<4.1
<2.8 RSW1.8NOQ 4/29/97
<160
<7.8
<11
<15
<8.8
<8.0 RSW3.7NO 5/27/97
<390
<9.0
<11
<17
<10
<8.5 RSWO.3MO 5/27/97
<380
<9.0
<10
<21
<11
<9.6 RSWO.7NO 5/27/97
<380
<3.3
<3.8
<7.9
<3.6
<3.6 i
RSW1.3FO 5/27/97
<390
<8.0
<7.8 -
<19
<9.4
<8.7 l
RSW1.8NO -
5/27/97
<390
<11
<13
<23
<12
<9.5 RSW3.7NO 6/30/97
<190
<4.4
<3.9
<7.6
<5.2
- <4.0 RSWO.3MO 6!30/97
<200
<7.7
<9.3
<21
<12
<10 RSWO.7NO 6/30/97
<190
<10
<10
<22
<12
<10 RSW1.3FO 6/30/97
<200
<7.9
<10
<16
<9.2
<7.7 RSW1.8NO 6/30/97
<200
<6.8
<7.0
<12
<7.6
<6.2 I
Rancho Seco Nuclear Station F-13 1997 AREOR
TABLE F-9 (continued) 1997 SURFACE WATER Monthly Grab / Monthly Composite (pCi/L)
' Sample ID Collection Date Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RSW3.7NO 7/29/97
<220
<7.0
<7.0
<14
<8.0
<6.7 RSWO.3MO 7/29/97
<220
<2.8
<3.0
<6.1
<3.8
<2.8 RSWO.7NO 7/29/97
<220
<7.7
<10
<17
<10
<8.5 RSW1.3FO 7/29/97
<210
<8.3
<10
<16
<11
<8.4 RSW1.8NO 7/29/97
<220
<8.0
<8.0
<17
<8.4
<7.4 RSW1.8NOQ 7/29/97
<220
<3.1
<3.4
<6.2
<4.3
<3.1 RSW3.7NO 8/26/97
<230
<9.7
<12
<22-
<12
<10 RSWO.3MO 8/26/97
<220
<4.0
<4.2
<8.4
<5.2
<3.9 RSWO.7NO 8/26/97
<220
<10
<9.4
<20
<11
<11 RSW1.3FO 8/26/97 -
<210
<4.0
<4.5
<8.0
<5.0
<3.5
'RSW1.8NO 8/26/97
<220
<8.8
<8.9
<19
<10
<9.9 RSW3.7NO 9/30/97
<220
<8.0
<8.9
<18
<8.7
<8.3 RSWO.3MO 9/30/97
<220
<14
<16
<29
<16
<13 RSWO.7NO 9/30/97
<210
<3.5
<4.2
<8.4
<4.4
<3.9 RSW1.3FO 9/30/97
<210
<9.2
<9.9
<20
<11
<9.7 RSW1.8NO 9/30/97
<210
<3.9
' <4.6
<9.1
<4.5
<3.9 RSW3.7NO 10/28lJ7
<200
<4.0
<4.0
<8.5
<4.8
<3.7 RSWD.3MO 10/28/97
<200
<8.9
<9.7
<19
<11
<9.3 RSWO.7NO 10/28/97
<190
<6.8
<8.1
<16
<8.6
<6.7 RSW1.3FO 10/28/97
<200
<6.5
<7.9
<16
<8.4
<7.5 RSW1.8NO 10/28/97
<200
<3.0
<2.8
<5.7
<3.5
<2.6 RSW1.8NOQ 10/28/97
<190
<9.8
<11
<22
<11
<9.3 RSW3.7NO 11/25/97
<180
<3.9
<4.1
<8.8
<4.8
<3.5 RSWo.3MO 11/25/97
<180
<3.4
<3.9
<7.8
<4.5
<3.2 RSWO.7NO 11/25/97
<180
<11
<12
<22
<11
<9.4 RSW1.3FO 11/25/97
<180
<6.4
<8.9
<16
<8.0
<6.3 RSW1.8NO 11/25/97
<180
<6.6
<7.3
<15
<7.6
<6.9 l
RSWO.3MO 12/23/97
<208
<9.46
<12.4
<22.0
<11.8
<9.75 RSW3.7NO 12/23/97
<205
<8.99
<10.5
<18.2
<11.2
<10.1 RSWO.7NO 12/23/97
<207
<3.70
<3.82
<8.40
<4.89
<4.09 RSW1.3FO 12/23/97
<208
<9.37
<11.6
<22.2
<11.5
<9.48 l
RSW1.8NO 12/23/97
<206
<8.89
<9.84
<20.6
<11.3
<10.0 Rincho Seco Nuclear Station F-14 1997 AREOR -
- m
l TABLE F-11 1997 Rain Water Seasonal (pCi/L)
Sample ID Collectio Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 n date RRNO.8DO 1/21/97
<186
<11
<13
<20
<14
<10 RRNO.8DO 2/18/97
<236
<7.3
<8.7
<14
<7.7
<6.8 RRNO.8DO 2/3/97
<220
<8.8
<8.9
<17
<9.7
<S.8 RRNO.8DO 3/18/97
<211
<8.5
<11
<17
<9.1_.
<7.9 RRNO.8DO 4/22/97
<160
<9.5
<10
<19
<11
<9.4 RRNO.8DO 5/27/97
<380
<3.1
<3.4
<7.2
<3.8
<3.3 RRNO.8DO 6/30/97
<200
<8.7
' <9.7
<19
<10
<9.8 RRNO.8DO 10/13/97
<200
<9.1
<12
<20
<10
<8.9 RRNO.8DO 11/18/97
<180
<9.8
<12
<25
<12
<11 RRNO.8DO 12/2/97
<180
<9.1
<13
<23
<12
<9.1 RRNO.8DO 12/16/97
<200
<3.9
<3.8
<9.5
<4.9
<3.9 l
i l
R:ncho Seco Nuclear Station F-16 1997 AREOR
TABLE F-10
'1997 Drinking Water Monthly (PCi/L)
Sample ID Collection Date Gross Beta Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RDW1.8FP 1/28/97 5.43
<197
<8.9
<9.5
<20
<11
<9.4 RDWo.1GO 1/28/97 1.75
<206
<7.6
<7.8
<15
<8.8
<7.6 RDW1.8FP 2/25/97 3.28
<232
<9.4
<9.5
<18
<11
<8.4 RDWO.1GO 2/25/97 6.36
<230
<7.7
<8.1
<17
<9.2
<7.6 RDWO.1GO 3/31/97 7.63
<202
<3.0
<3.5
<6.8
<3.8
<30.
RDW1.8FP 3/31/97 5.47
<200
<3.2
<3.9
<7.0
<4.4
<3.5 RDW1.8FP 4/29/97 6.5
<160
<9.0
<9.5
<20
<11
<10 RDWO.1GO 4/29/97 3.1
<160
<3.6
<3.3
<8.0
<4.8
<3.6 RDWO.1GO 5/27/97 6.8
<400
<9.5
<10
<21
<12
<9.9 RDW1.8FP 5/27/97 5.6
<390
<4.2
<4.2
<8.2
<5.0
<3.9 RDWO.1GO 6/30/97 6.1
<190
<15
<15
<23
<16
<14 RDW1.8FP 6/30/97 5.2
<190
<6.0
<6.1
<13
<7.3
<5.9 RDWO.1GO 7/29/97 6.5
<220
<9.9
<8.9
<20
<10
<8.9 RDW1.8FP 7/29/97 5.6
<210
<3.9
<3.9
<7.6
<5.2
<3.8 RDWO.1GO 8/27/97 6.0
<220
<9.2
<13
<22
<11
<10 RDW1.8FP 8/27/97 5.4 -
<220
<9.5
<12
<21
<12
<9.7 RDWo.1GO 9/30/97 5.6
<210
<3.4
<4.1
<8.0
<4.1
<3.6 RDW1.8FP 9/30/97 5.5
<210
<11
<13
<25
<14
<10 RDW1.8FP -
10/28/97 5.5
<200
<9.0
<10
<21
<11
<9.3 RDWO.1GO 10/28/97 7.49
<200
<3.8
<4.0
<8.2
<4.7
<3.8 RDWO.1GO 11/25/97 1.88
<180
<13
<13
<24
<14
<10
_RDW1.8FP 11/25/97 4.51
<180
<9.1
<11
<23
<11
<9.6 RDWO.1GO 12/23/97 6.97
<210
<3.8
<4.2
<8.3
<4.6
<4.1 RDW1.8FP 12/23/97 5.88
<220
<9.5
<11
<23
<10
<10 Rtncho Seco Nuclear Station F-15 1997 AREOR
APPENDIX G 1997 MISSED SAMPLE REPORT in accordance with the requirements REMP manual section 3.1, the following samples are being reported as not being collected for the reasons indicated during 1997. Corrective action as required by the REMP manual is as indicated.
AIR FILTER (Atmospheric pathway)
Location RASO.1CO, PAP Building (indicator)- On June 30,1997, the air sample cartridge was found on the ground next to the air sampler enclosure. The air sample cartridge had unscrewed off of the gooseneck fitting. The air sampler was repaired and lock tight compound was applied to the threads for this connection and the connection on the other three air sampling locations. The particulate filter was sent to the analysis vendor for analysis. No volume was recorded, therefore a volume of one (1) cubic foot was used. No data will be available from this location for this sample period. PDQ 97-0040 was written to document the incident. No further action is required.
Location RAS 1.SFP, Rancho Seco Reservoir Well Enclosure (control) - On September 2,
'i997 the air sampler at this location was found not running. The air flow indicator indicated a total volume of 200 cubic feet. The problem was identified as an electrical problem with the elapsed timer. The timer was repaired and the air sampler was retumed to service. The air filter was sent to the analysis vendor. The gross beta activity was abnormally high due to the.
Iow sample volume. This location is not a REMP required location for air sampling. No further action is required.
TLD fDirect radiation pathway)
Location # 17 RTL8.2KO, Elliott Cemetery (control)- On October 2,1997, the TLDs at this location were missing dunng the rou3ne changeout. Fourth quarter 1997 TLDs were restored at this location. No TLD data will be available for this location for the third quarter 1997. No further corrective action is required.
Location # 33 RTL3.8MO, BLM entrance to Folsom South Canal Pumping Station (indicator)- On Janury 6,1997, the TLDs at this location were missing during the routine changeout. First quarter 1997 TLDs were restored at this location. No TLD data will be available for this location for the fourth quarter 1996. Due to the fact that this is the second occurrence of the TLDs being removed in less than a year, this location was moved to the south side of Hwy 104 adjacent to the old location. No further corrective action is required.
Rancho Seco Nuclear Station G-1 1997 AREOR
APPENDlX G 1997 MISSED SAMPLE REPORT (continued)
Alaae (Aoustic pathwav)
Location RAGO.3MO, Plant Effluent, (indicator)- On March 31,1997 the algae sample at this location was not available. Water flow was to fast to permit algae to grow. No data will be available for this sample period from this location. No action required, administrative sample.
Location RAG 0.6MO, Site Boundary, (indicator)- On March 31,1997 the algae sample at this location was not available. Water flow was to fast to permit algae to grow. No data will be available for this sample period from this location. No action required, administrative sample.
Location RAG 1.8NO, Hadselville/ Clay Creeks, (indicator)- On March 31,1997 the algae sample at this location was not available. Water flow in this creek system was to fast to permit algae to grow. No data will be available for this sample period from this location. No action required, administrative sample.
1 Location RAGO.3MO, Plant Effluent, (indicator)- On September 11,1997 algae sample at this location was not available. Water flow was to fast to permit algae to grow. No data will be available for this sample period from this location. No action required, administrative sample.
Location RAGO.6MO, Site Boundary (indicator)- On September 11,1997 algae sample at this location was not available. Water flow was to fast to permit algae to grow. No data will be available for this sample period from this location. No action required, administrative sample.
Surface Water (Water Dathway)
Location RSWo.3MO, Plant Effluent, (indicator) - On April 29,1997 the composite sampler at this location was found incorrectly assembled. The water sample was not collected in the sample container, but had been collected in the sampler enclosure. The sample was collected and sent to the analysis vendor. The sampler was tested, found to be operational and retumed to service. Results from this sample were within normal values. PDQ 97-0022 was initiated for this incident. No further action required.
Location RSW3.7NO, Folsom South Canal, (control)- On April 29,1997 the composite sampler at this location was found in a standby condition. No composite sample was collected for this sample period from this location. The sampler was tested, found to be operational and retumed to service. No data will be available from this location for this sample period. PDQ 97-0022 was initiated for this incident. No further action required.
1 Rancho Seco Nuclear Station G-2 1997 AREOR f
l i