ML19261A434
| ML19261A434 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/31/1979 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML19261A433 | List: |
| References | |
| ENVR-790131, NUDOCS 7901180169 | |
| Download: ML19261A434 (27) | |
Text
.
O VIRGIL C. SUMMER NUCLEAR STATION OPERATING LICENSE ENVIRONMENTAL REPORT AMENDMENT 4 INSTRUCTION SHEET The following instructional information and check list is being furnished to help insert Amendment No. 4 into the Virgil C. Summer Nuclear Station OLER.
Since in most cases the original OLER contains information printed on both sides of a sheet of loose leaf paper, a new sheet is furnished to replace sheets containing superseded materials. As a result, the front or back of a sheet may contain information that is merely reprinted rather than changed.
Discard the old sheets and insert the new sheets, as listed below. Keep these instruction sheets in the f ront of Volume I to serve as a record of changes.
REMOVE INSERT Pages 3-111 -
3-iv Page 3-111 iv 3.3-2 3.3-2 Figure 3.3-1 Figure 3.3-1 Pages 3.6 3.6-6 Pages 3.6 3.6-6 3.6 3.6-8 3.6 3.6-8 6.1 6.1-34 6.1 6.1-34 6.1-34a 6.1 6.1-61 6.1 6.1-61 Responses to Questions May 22, 1978 (insert behind tab and behind responses to questions July 25, 1978)
AMENDMENT 4 ME M g
TABLE OF CONTENTS (Continued)
Section Title Page 3.6.3 Steam Generator Blowdown 3.6-6 3.6.4 Ion Exchange Regenerant Wastes 3.6-6 3.6.5 Startup Wastes 3.6-7 3.6.6 Condensate Polishing Wastes 3.6-8 3.6.7 Concentrations in Circulating Water Discharge 3.6-8 4
3.6.8 References 3.6-8 3.7 SANITARY AND OTHER WASTE SYSTEMS 3.7-1 3.7.1 Sanitary Treatment Facilities 3.7-1 3.7.2 Storm Drainage 3.7-2 3.7.3 Non-Radioactive Gaseous Ef fluents 3.7-3 3.8 REPORTING OF RADIOACTIVE MATERIAL MOVEMENT 3.8-1 3.9 TRANSMISSION FACILITIES 3.9-1 3.9.1 South Carolina Electric & Cas Company Tranmission Lines 3.9-1 3.9.1.1 Lines Proximal to the Virgil C.
Summer Nuclear Station 3.9-1 3.9.1.2 Summer-Graniteville 230 kV Line 3.9-5 3.9.1.3 Pineland-Summer-Denny Terrace Lines 3.9-8 3.9.1.4 Structure of Lines outside the Project Area 3.9-11 3.9.2 South Carolina Public Service Authority Transmission Lines for the Virgil C. Summer Nuclear Station 3.9-12 3.4.2.1 Summer-Newberry Line 3.0-12 3.9.2.2 Summer-Blythewood Transmission Line 3.9-15 3.9.2.3 Auxiliary Facilities 3.9-18 3.9.2.4 Impact from Noise and Electromagnetic Rad ia t ion 3.9-20 3.9.3 References 3.9-20 3-111 AMENDMENT 4 JANUARY 1979
LIST OF TABLES Table Title Page 3.1-1 Stack Release Information 3.1-4 3.2-1 Turbine Heat Rate Variation with Back Pressure 3.2-2 and Load O
3.3-1 Flow Rates 3.3-2 3.4-1 Average Monthly Data 3.4-15 3.4-2 Thermal Performance Study - Summary of Meteoro-3.4-16 logical Data Used in LOCA Studies 3
3.4-3 SWP Thermal Performance Studies - Maximum Service 3.4-17 Water Intake and Discharge Temperature 3.5-1 Specific Activities in Principal Fluid Steams -
3.5-36 Gale Code Model 3.5-2 Tritium Production 3.5-40 3.5-3 Calculated Releases of Radioactive Materials in 3.5-41 Gaseous Effluents from Virgil C. Summer Nuclear Station 3.5-4 Calculated Releases of Radioactive Materials in 3.5-42 Liquid Effluents from the Boron Recycle System 3.5-5 Calculated Releases of Radioactive Materials in 3.5-43 Liquid Effluents from the Liquid Waste Processing System AMENDMENT 3 3-iv OCTOBER 1978
TABLE 3.3-1 FLOW RATES (GPM)
Maximum Power Minimum Anticipated Temporary Item Operation Power Operation Shutdown 1.
Circulating Water (total) 534,000 400,000 400,000 2.
Main condensers (480,000)
(366,000)
(366,000) 3.
Other Coaling Services (54,000)
(34,000)
(34,000) 4.
Service Water (total) 12,000 12,000 12,000 5.
Component Cooling Ileat Exchangers (9,000)
(9,000)
(9,000) 6.
Other Cooling Services (3,000)
(3,000)
(3,000) 7.
Steam Generator 250.0 30.0 30.0 8.
Sanitary Wastes 15.6 8.0 8.0 9.
Miscellaneous Non-Nuclear Drains 66.0 10.5 10.5
- 10. Water Treatment Sludges 20.0 2.1 2.1 10a. Condensate Polishing Wastes 340.
2.17 2.17 4
- 11. Ion Exchange Regenerant 11.1 2.1 2.1
- 12. Reactor Grade Water 0.14 0.14 0.14
- 13. Nuclear Plant Drains 0.93 0.93 0.93
- 14. Laundry and llot Showers 0.31 0.31 0.31
- 15. Potable Water Usage 15.6 15.6 15.6 (1) Numbers refer to Figure 3.3-1.
AMENDMENT 4 3.3-2 JANUARY 1979
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V a.rgel C. Summer Nuclear Stof. ton Water Use Diagram Figure 3.3-1
7.
Non-biodegradable organic Negligible 8.
Surfactants Negligible 9.
Phosphorus and nitrogen Negligible 10.
Toxic compounds Negligible The amount of waste generated is estimated from the following dosage levels and raw water conditions:
1.
Clay 2 grains / gal.
2.
Soda ash 2 grains / gal.
3.
Alum 4 grains / gal.
4.
Suspended solids in raw water 50 mg/ liter These levels are based on experience relative to performance of similar operations.
The water treatment plant wastes are treated to remove suspended solids.
By removing the suspended solids, the BOD concentrated in the clarifier sludge is removed also.
The method of treatment is to provide two lagoons that are operated on a batch basis.
These lagoons are provided with variable level discharge f acilities to allow decantation of the supernatant as the lagoon is filled.
It is assumed that after two to five years of filling the lagoon, it will be retired from service and the sludge allowed to compact. After sufficient compaction has taken place, the sludge will be removed to a landfill site.
These lagoons are also to be used to treat the plant startup wastes and condensate 4
polishing waste.
The suspended solids and BOD levels of the lagoon treated effluent are based on operation of a similar facility (Shormont, N.Y., Water Treatment Lagoon) (1).
Average effluent values were:
1.
BOD 16 mg/ liter S
2.
Suspended solids 24 mg/ liter 3.
Settlable solids Trace 3.6-5 AMENDMENT 4 JANUARY 1979
O The settled solids ranged from 1.5 to 15 percent in suspended solids content.
3.6.3 STEAM GENERATOR BLOWDOWN The Steam Generator Blowdown System continuously purges the steam gener-ators of concentrated impurities, thereby maintaining secondary side water chemistry. The steam generator blowdown is essentially demineral-ized water with small amounts of chemicals added to act as oxygen scav-engers and to maintain the water quality within specifications. The cooled steam generator blowdown can be directed to either the circulat-ing water discharge or the Nuclear Blowdown Processing System (NBPS).
Effluent from the NBPS is recycled to the main condenser hotwell, an alternate path being to the penstock of the Fairfield Pumped Storage Facility. The characteristics of the cooled blowdown fluid are tabu-lated in Table 3.6-1.
O 3.6.4 ION EXCHANGE REGENERANT WASTES The ion exchange demineralizers used to treat makeup water for purified water to the steam generators and the primary coolant for the reactor are regenerated with sodium hydroxide and sulfuric acid.
The sodium hydroxide and sulfuric acid regenerant waste are combined and the pH adjusted between 6 and 9.
The neutralized wastes are discharged at 250 gpm to the circulating water discharge with a rate ranging from about 11,000 to 16,000 gpd.
The pH of the neutralized waste is contin-uously monitored. Discharge is automatically terminated if the pH value exceeds the specified range of 6 to 9.
Characteristics of the neutral-ized wastes discharged are shown in Table 3.6-2.
Seasonal and operational variations in the discharge are minimal.
Regen-eration frequency is not expected to vary.
Constituents in the neutral-O 3.6-6
ized wastes could vary slightly with seasonal changes in ground water quality, but changes are not expected to be significant.
3.6.5 STARTUP WASTES Prior to the startup of the nuclear station, the plant equipment, piping, etc., is cleaned to remove rust, mill scale, welding rods, and debris re-sulting from construction. The cleaning operation consists of the fol-lowing approximate water volumes:
1.
Water flush 10 million gallons 2.
Alkaline phosphate detergent flush 200,000 gallons 3.
Final water rinse 600,000 gallons.
The characteristics of the plant startup wastes are given in Table 3.6-3.
All of the plaat startup wastes are pumped to the lagoons that normally are used for the water treatment plant wastes.
During the initial plain water flush, the lagoons operate as sedimentation basins for removal of trash and suspended solids. At the completion of the plain water flush, the lagoons are decanted to the debris layer. The detergent phosphate wash and the final rinse are then accumulated in the lagoons and treated on a batch basis.
Treatment consists of pH adjustment, phosphate precipitation with alum, and possible oil removal. The treatment continues until analyses indi-cate that the waste is treated to a quality acceptable for discharge to the Monticello Reservoir. After treatment, the supernatant is decanted off to the Monticello Reservoir. The sludge accumulation, if signifi-cant, is allowed to deuater to a condition acceptable for disposal at a sanitary landfill.
3.6-7
3.6.6 CONDENSATE POLISilING WASTES The Condensate Polishing System is operated durint; startup, shutdown, and required during condenser leakage to maintain acceptable water chemistry as purity levels.
The polishing system consists of powdered resin filter /de-mineralizers.
System waste is normally discharged to one of two lagoons for settling prior to ultimate discharge into Monticello Reservoir (refer to Section 3.6.2).
3.6.7 CONCENTRATIONS IN CIRCULATING WATER DISCIIARGE Expected increases in concentrations in the circulating water discharge as a result of passage through the plant are shown in Table 3.6-4.
3.
6.8 REFERENCES
4 1.
O'Brien & Gere, " Waste Alum Sludge Characteristics and Treatment,"
New York State Department of liealth, Research Report No. 15, Dec-ember 1966.
O O
O 3.6-8 AMENDMENT 4 JANUARY 1979
and construction phase surveys and will form the basis for assessing the impacts of operation of the Virgil C. Summer Nuclear Station. Changes in bird populations will be determined primarily through comparison of indicator species populations.
Indicator species used to assess results collected by auto survey and strip census techniques will include the mockingbird, loggerhead shrike, eastern meadowlark, cardinal, pine warbler, rufous-sided towhee, Carolina chickadee, and mourning dove.
The great blue heron, belted kingfisher, and wood duck will serve as 1
indicator species in evaluating results of the waterfowl survey data.
A standard Chi-square test will be applied to each set of data.
The results of this statistical analysis may show whether any significant dif ferences in bird populations exi~;t between control and test popula-tions and whether any significant changes may have occurred during the period just prior to operation of the nuclear plant.
6.1.5 RADIOLOGICAL MONITORING The environmental radiological monitoring program for the Virgil C.
Summer Nuclear Station is designed to: 1) analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the surrounding environment and 2) to es-tablish correlations between leveis of environmental radioactivity and radioactive ef fluent from plant operation. This program utilizes the concepts of control-indicator and preoperational-operational intercom-parisons in order to establish the adequacy of source control and to realistically verify the assessment of environmental levels and result-ant human radiation dose as demonstrated by both the in-plant effluent monitoring program and the environmental monitoring program.
Signifi-cant upgrading of program scope and sensitivity has occurred as a result of the review of more comprehensive site-specific baseline environmental and land use data which had been unavailable at the construction permit stage.
AMENDMENT 1 6.1-33 APRIL 1978
The sample types, criteria for selection, collection frequencies, loca-tions, and analyses which are perfor=ed are presented in Table 5.1-15 1
and Figures 6.1-4 and 6.1-5.
Site related dispersion characteristics, demography, hydrology, land use, anticipated source terms, and critical pathways have been considered in the selection of sample media, sampling d
and analysis frequencies, sample locations, and types of analyses (see Chapters 2 and 5).
The cor waponding individual program elements set forth in Table 6.1-15 are irlicated en Figures 5.2-3 and 5.2-4, as are 1
normalized anticipated br<eatages of dose commitment by the particular pathways.
D, tailed examination of possible critical pathwayr and site related spec.4fic acn2 estimates are presented in Section 5.2.
The re-sults of this analysis assure that reasonably conceivable pathways to man and the environment are monitored with frequencies justified on the basis of potential doce.
Locations are selected on the basis of site e,cacific characteristf as.'
Anticipated maximum lower limits of detection 1
far the analyses are gresented in Table 6.1-16.
he radiological monitoring program implemented in the preoperational phase assures that the minimum amount of baseline data acquired describes i
the samples of interest for those time periods reflected 2a Table 'o.1-53.
1 Preeperational tampling and sample measurements indicate the exist. m fluctuating background levels of radioactivity due to I aturally occur-l ring and manmado radionuclides. The methodology 1wd frequency of sampl-ing and analyses.as been reviewed ani optimized (as necessary) during the preoperar.ional phase to obtain a realistic qualitative and quantita-tive ekcimate of the radiological environnent.
Experince gained through the use of analytical procedu:ces and quality control reviews provides tpe basis for appropriate analytical modifications. Annual reviews yf site spe ific existent exposure petszaays provide a basis for the eval-s uathn cf possible changes in sampling and sample site selections (see Section 6.2.4).
'1he laboratories of the licensee and licensee's contractors which perform 4
mialyses shall participate in the Environmental Protection Agency's (EPA's)
/
r 6.1-34 AMENDMENT 4 JANUARY 19N
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Environmental Radioactivity Laboratory Intercompar isons Studies (Crosscheck)
Program or equivalent program. This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the annual report.
If the results of a determination in the EPA crasscheck program (or equivalent program) are outside the specified control limies, the laboratory shall 4
investigate the cause of the problem and take steps to correct it.
The results of this investigation and corrective action shall be included in the annual repcrt.
The requirement for the participation in the EPA crosscheck program, or similar program, is based on the need for independent checks on the pre-cision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for envrionmental monitoring in order to demonstrate that tne results are reasonably valid.
V The operational phase of the radiological moaitoring program will be an extension of the preoperational phase.
Raw data is analyzed and presented o
6.1-34a AMENDMENT 4 JANUARY 1979
kg..
TABLE 6.1-15 i
RADIOLOGICAL ENVIRONMENTAL MONt
'NG PROGRAM VIRGIL C.
SUMMER NUCLEAR STATION Page 1 of 9 Sample Locations Exposure Pathway Criteria for Selection of San.pling and Loca-Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion (l) Mi/Dir Ana lys i s AIRBORNE I.
Pr
..ulates A 3 Indicator samples to Continuous sampler 2
1.1 SW Gross beta following be taken at locations operation with 5
1.3 SE filter change; Monthly (in different sectors) weekly collection.
10 2.4 NNE composite (by location) beyond but as close to for gamma isotopic.
the exclusion boundary as practicable where e
the highest offsite g
6, sectoral ground level N
concentrations are anticipated.(2)
B 1 Indicator sample to be 6
1.1 ES E taken in the sector be-yond but as close to the exclusion boundary as practicable correspond-ing to the residence having t :e highest anticipated offsite ground level 2) concentra tion or dose.
C 1 Indicator sample to be 14('}
5.2 W 4
taken at the location of 1
oneofthedairiesmos{g 4) gy likely to be affected.
cz
>d WX k: M Z
wH k
e
TABLE 6.1-15 (Continued)
Page 2 of 9 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca7y)
Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis
- AIRBORNE, D 2 Control samples to be 17 24.7 SE (continued) taken at locations at least 10 air miles from 16 28.0 W the site and not in the 1
most prevalent wind directions.(2)
II.
Radioiodine A 3 Indicator samples to Continuous sampler 2
1.1 SW Gamma isotopic screening be taken at two loca-operation with weekly 5
1.3 SE of all five indicators tions as given in I.A cannister collection.
10 2.4 NNE with conjunctive screen-above.
ing of the two controls.
If screening is positive, 7
each sample will be sub-jected to isotopic analysis for iodine.
B 1 Indicator sample to 6
1.1 ESE be taken at the lo-cation as given in I.B above.
C 1 Indicator sample to be 14 5.2 W 4
taken at the location as 1
given in I.C above.
D 2 Control samples to be 17 24.7 SE taken at locations similar in nature to A-C 16 28.0 W l
above.
UR cz
,< mz H H to M k
TABLE 6.1-15 (Continued)
Page 3 of 9 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca71)
Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion MI/Dir Analysis
- AIRBORNE, (continued)
Monthly exchange.(5)
- 's 2, 5, 6, Camma Jose monthly (5)
III.
Direct A 5 Indicator samples to 4
be taken at the loca-Two or more dost-10, and 14.
tions as given in I.A meters at each loca-through D above.
tlon.
B 3 Additional indicator 1
1.3 S samples to be taken in 4
1.2 NW sectors different from 8
1.3 ENE III.A above, beyond but as close to the exclusion g
boundary as practicable.
v C Control samples to be 16 28.0 W taken at the locations 17 24.7 SE as given in I.D above.
1 D 1 Additional control 18 16.5 S sample to be taken at a location as set forth in I.D above.
WATERBORNE IV.
Surface A 1 Indicator sample to be Time composite sa ples 21(3) (6)2.7 SSE Gamma isotopic with Water taken at a location with collection every quarterly composite e v which allows for mixing month (corresponds to location) to be anal; m and dilution in the ul-USGS continuous samp1-for tritium'(7) 4 Pg timate receiving river, ing site).(5) u em c: ~A
> C1 WX MM
'A H H e
%J &
TABLE 6.1-15 (Continued)
Page 4 of 9 Sample Locations Exposure Pathway Critetia for Selection of Sampling and Loca Type and Frequency of
)
and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis WATERBORNE, B 1 Control sample to be 22( )
12-15 NNW L
(continued) taken at a location on the receiving river, suffi-ciently far upstream such that no effects of pumped storage operation are anticipated.
C 1 Indicator sample to be Grab sam ling 23(
<1 E As in V above.
1 4
taken in the upper reser-monthly ( )
voir of the pumped stor-P age facility.
r di vi D 1 Indicator sample to be 24(3) 4.7 N
'I taken in the upper reser-voir's non-fluctuating recreational area.
E 1 Control sample to be 18(3) 16.5 S taken at a location on a I
separated unaf fec ted water-shed reservoir.
V.
Ground Water A 2 Indicator samples to Quarterly (p)rab 26 Onsite Gamma isotopic and 1
4 be taken within the ex-sampling.
27 Onsite tritium anal ses clusion boundary and in quarterly.(7 the direction of poten-tially affected ground water supplies.
- b
&m dz B 1 Control sample from an 16 28.0 W 1
h unaffected location.
z ba
TABLE 6.1-15 (Continued)
Page 5 of 9 Sample 1.ocations Exposure Pathway Criteria for Selection of Sampling and Loca Type and Frequency of and/or Sample Sample Number and 1.ocation Collection Frequency tion Mi/Dir Analysis WATERBORNE, (continued)
Monthly (5) gamma isotopic VI.
Drinking A 1 Indicator sample from Monthly prab 28 1.3 ESE Water nearby public ground samplingl5) and gross Beta analyses I
water supply source.
and quarterly (7) tritium analyses 4
I 17 24.7 S Timecom$osite B 1 Indicator sample irom sample (6 with monthly a location immediately upstream of the nearest collection (5) downstream municipal water supply.
INGESTION A 1 Indicator sample to Semi-monthly when 14(4) 5.2 W Gamma isotopic and f-131
~
VII.
Milk (5)
~
be taken at the loca-animals are on analysis semimonthly (8)
I 4
tion o f one o f the pasture,(8) monthly when animals are on dairies most likely to other times.(5) pasture; monthly (5) at be affected. (2) ($)
other times B 1 Control sample to be 16 28.0 W 1
taken at the location of a dairy 10-20 miles dis-tant and not in the most prevalent wind direction.
C 1 Indicator grass (for-Monthly when available(5) 6 1.1 ESE Gamma Isotopic 1
4 age) sample to be taken at one of the locations beyond but as close to the exclusion boundary as 50 practicable where the highest offsite sectoral
E ground level concent ra-5H tions are ant icipated. (2)
~w c
TABl.E 6.1-15 (Continued)
Page 6 of 9 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Locazy)
Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis INGESTION, D 1 Indicator grass (for-14(4) 5.2 W (continued) age) sample to be taken at the location of V.:II.A above when animals are on pasture.
E 1 Control grass (forage) sample to be taken at the location of VIII.B above.
16 28.0 W VIII.
Food A 1 Indicator sample to be Annually at the 6
1.1 ESE Gamma isotopic on edible Products taken at a nearby garden approximate median portion. Radioiodine on 1
likely to be affected.
harvest time for green leafy vegetables.
the area.
- Samples, 7
if available, will d
include:
green leafy, fruit, and grain.
4 B 1 Control sample for the 18( )
16.5 S same foods taken at a location at least 10 miles distant and not in the most prevalent wind di-rection.
IX.
Fish A 1 Indicator sample to be Semi annual collec-23( )
0.3-5 Gamma isotopic on edible 1
taken at a location in tion of the following portions semi-annually 4
the upper reservoir.
specie types if available.
bass, bream, crappie; catfish, cU carp; forage fish (shad).
>c k z wd Nd e
ym TABLE 6.1-15 (Continued)
Page 7 of 9 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca g Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tien MI/Dir Analysis INGESTION, B 1 Indicator sample to be 21( )
1-3 1
(continued) taken at a location in the lower reservoir C 1 Indicator sample to be 24(3) 4-5 N 1
taken at a location in the upper reservoir's non-fluctuating recreational area.
I 4
.as Y
D 1 Control sample to be 22(3) 12-15 NNW 1
taken at a location on the receiving river, sufficiently far up-stream such that no effects of pumped storage operation are anticipated.
AQUATIC
)
X. Sediment A 1 Indicator sample to be Semi-annual grab 23 0.3-4 Gamma isotopic 1
taken at a location in sample (9) the upper reservoir.
4 "b
hm c: z
.< m Z
$~n 50
TABLE 6.1-15 (Continued)
Page 8 of 9 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca77)
Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis I}
AQ' ATIC B 1 Indicator sample to be 24 4-5 N 1
J (continued) taken in the upper reser-voir's non-fluctuating recreational area.
C 1 Indicator sample to be 21(
1-3 1
taken on the shoreline of the lower rerervoir.
D 1 Control sample to be 22(
12-15 1
P' taken in receiving river, 7
sufficiently far upstream such that no effects of pumped storage operation are anticipated.
1 4
(1) Location numbers refer to Figures 6.1-3 and 6.1-4.
(2) Sample site locations are based on the meteorological analysis for the period of record as presented in Chapters 5 and 6.
(3) Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment 1
yyg sampling is done at the same location whereas biological sampling sites are generalized areas in order to y gj reasonably assure av.tilability of samples.
E$
-. 4 5"
TABLE 6.1-15 (Continued)
Page 9 of 9 (4) Milking animal and garden survey results will be analyzed annually.
Should the survey indicate new dairying activity of a significant nature (5 or more cows milking) In a quadrant (s) other than W or NW and closer than 4
5-7 niles, the owners shall be contacted with regard to a contract for supplying sufficient samples.
If contractural arrangements can be made, the site (s) will be added for additional milk sampling.
(5) Not to exceed 35 days.
(6) Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) relative to the compositing period.
(7) At least once per 100 days.
(8) At least once per 18 days.
(9) At least once per 200 days.
NOTE: Deviations from this sampling schedule may occasionally be necessary if sample media are unobt_ nable P'
due to hazardous conditions, seasonal unavailability, insufficient sample size, malfunctions o;.iuto-7 matic sampling or analysis equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
Deviations from sampling-analyses schedule will be described in the annual report, bD GR C Z
>C WX KM Z W H Ne e
TABLE 6.1-16 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS MEDIA / DETECTION CAPABILITIES Lower Limit of Detection (LLD)(
Airborne Particulate Fish, Meat Water of Gas or Poultry Milk Vegetation Sediment Analysis (pCi/1)
(pCi/m3)
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pci/kg, dry) gross beta 2(2)
(1 x 10 ")
4 3
2000 (1000)(
g 54 15 130 g
59 30 260 Fe 58,60 15 130 Co 7
C 65 0
260 Zn 95 15 Zr-Nb 131 1
( 7 x 10- )
1 60( )
7 4
134,137 15(10) 18 (1 x 10- )
130 15 80 150 Cs 140 15 15 g_g Direct TLD measurements should have de* ~ tion sensitivities approaching 10 mrem /yr.
(1)The nominal lower limit of detection is defined in IIASL 300 (Rev. 8/74), pp. D-08-01, 02, 03 at the 95%
confidence level.
The LLD levels are decay corrected to the end of the total sampling period. The LLD for radionuclides analyzed by gamma spectrometry will vary according to the number of radionuclides en-countered in environmental samples.
These LLD levels will be used as minimum criteria for objectives for instrumentation and analytical procedure selection.
(2)LLD for Drianng Water
(
LLD for Green Leafy Vegetables AMENDMENT 4 JANUARY 1979
RESPONSE TO REQUEST FOR ADDITIO:iAL IhTORMATION May 22, 1978 Submitted January 19 79
1.
As stated in Subsection 2.1.1 the personnel of the Fairfiele Pumped Storage Facility are located inside of the Summer Nuclear Station's exclusion area boundary. These workers are employees of SCE6G and subject to administrative controls of the company.
If you do not intend to implement the requirements of 10 CFR Part 20 for these workers, we will have to consider them members of the general public.
Under these conditions, the workers would be subject to the require-ments of 10 CFR Part 50, Appendix I and we would require the follow-ing information:
Locations (distances and directions) which will be occupied by a.
the workers of the Fairfield Pumped Storage Facility inside the exclusion area boundary, and b.
Annual occupane/ (number of hours per year) of a worker at each location described in item (a) above.
Approximate distance and direction of major components of the Fairfield Pumped Storage facility (FPSF) from the centerline of the nuclear plant containment building are listed in Table 1.
Table 2 lists estimated annual occupancy of various worker classifications at each of the points identified in Table 1.
In addition, doses to a FPSF worker conservatively assumed to spend full time on a dam located in the west-northwest sector at a distance of 0.5 mile from the containment building were calculated. Plume, ground deposition, and air inhalation pathways were investigated. Methodology utilized was that specified in Regulatory Guides 1.109 and 1.111 for dose and meteorological calculations, respectively. No credit for building shielding was taken.
Results were as follows:
Total Body Dose 0.26 mrem /yr (Plume & Ground Pathways)
Skin Dose 0.69 mrem /yr (Plume & Ground Pathways)
Thyroid Dose 0.18 mrem /yr (Air Inhalation Pathway)
Thus, these results indicate the design of the Virgil C.
Summer Nuclear Station conforms to the guidelines set forth in 10 CFR 50, Appendix I, wt an FPSF workers are considered members of the general public.
2.
Table 2.1.7 does not contain any information on the locations of the nearest meat animals. However, in Subsection 5.2.4.2, statement is made that exposure from consumption of meat was evaluated at the same location as that for cow milk.
Please confirm whether the 1
JANUARY 1979
TABLE 1 FPSF Direction Approximate Component Sector Listance (miles)
Powerhouse WNW l.0 Intake Structure WNW 0.8 Nearest Dam WNW 0.4 Dam Near Intake Structure WNW 0.7 Frees Creek Dam NW l.1 TABLE 2 Hours per year spent at indicated component of Fairfield Pymped Storage Facility Dams Within Exclusion Power-Intake Area Worker Type Number house Structure Boundary Utility Men 3
2000 0
0 Operators 5
2000 0
0 Clerk 1
2000 0
0 Supervisor
- 1 1500 0
40 Assistant Supervisor
- 1 1500 0
40 Ground Supervisor
- 1 100 0
150 Ground Utility Man
- 6 30 0
150 Electricians 2
1950 30 0
Mechanics 2
1950 50 0
Instruction Technicans 2
1950 50 0
- Note: All remaining time spent outside the exclusion area.
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JANUARY 1979
implication of this, that there are no meat animals at closer loca-tions than the nearest cow locations given in Tables 2.1-7, is true.
An additional survey to locate vegetable gardens and meat and milk animals was conducted in January of 1978.
The results of this survey supercede those presented in the OLER and are presented in the attached table (Table 3).
3.
For the purposes of independence checks and quality assurance of Radiological Environmental Monitoring Program, the Branch Technical Position (March 1978), An Acceptable Radiological Environmental Monitoring Program, of the Radiological Assessment Branch requires that the laboratories of the licensee or licensee's contractors which perform analyses shall participate in the EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program or equivalent program. Please describe your plans for such participation.
See Amendment 4, Section 6.1.5, pages 6.1-34 and 6.1-34a of the OLER.
4.
Please define " Time composite sample with monthly collection" stated under the column heading Sampling and Collection Frequency in Ta-ble 6.1-15 item V1.B.
Staff would require drinking water samples to be composite samples collected with equiment which are capable of collecting an aliquot at time intervals which are very short (e.g.,
hourly) relative to the compositing period (e.g., monthly).
See revised Table 6.1-15, page 9 of 9, page G.1-60 of Amendment 4 of the OLER.
Monthly gross Beta analysis also should be performed for drinking water.
See revised Table 6.1-15, page 5 of 9, page 6.1-56 of Amendment 4 of the OLER.
5.
Staff would require frequency of milk sample collection and analysis af I-131 in milk semi-monthly when the milk animals are on pasture.
This should be included in Table 6.1-15.
See revised Table 6.1-15, page 5 of 9, page 6.1-56 of Amendment 4 of the OLER.
6.
Since gross Beta analysis would be performed for drinking water, please include the LLD for gross Beta in drinking water in Table 6.1-16.
See revised Table 6.1-16, page 6.1-61 of Amendment 4 of the OLER.
3 JANUARY 19 79
TABLE 3 VEGETABLE GARDEN, MILK AND MEAT ANIMAL SURVEY CENSUS COMPLETED JAMUARY 4 - JANUARY 10, 1978 SECTOR CARDEN BEEF CATTLE MILKING ANIMAL (Cows)
Distance
- Distance
- Total Number Distance
- Total Number (in miles)
(in miles)
(in miles)
NORTIl 4.2 NNE 3.5 3.7 20 4.5 3 (3)
NE 1.9 3.5 6
ENE 1.7 3.7 20 EAST 1.2 ESE 1.5 5.0 1
SE 2.7 2.2 20 5.5 L (4)
SSE 2.5 5.7 1 (3)
SOUTil 3.7 SSW 3.7 SW 2.6 2.6 45 WSW 2.7 5.0 20 WEST 2.2 2.2 12 WNW 4.0 4.0 5
NW 4.2 4.2 5
NNW 2.8 2.8 13
- Distance scaled from map as estimated from centerline of reactor building.
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