AECM-84-0263, Annual Environ Operating Rept for 1983
| ML20126B454 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1983 |
| From: | Mcgaughy J MISSISSIPPI POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| AECM-84-0263, AECM-84-263, NUDOCS 8506140107 | |
| Download: ML20126B454 (137) | |
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PREFACE This report presents the information and data obtained from the implementation of Grand Gulf Nuclear Station's (GGNS) Environmental Protection Program, Appendix B to the GGNS Low-Power Operating License (NPF-13) for the period January 1, 1983, through December 31, 1983.
Historical information has also been included where applicable for comparison purposes.
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TABLE OF CONTENTS PAGE PREFACE.........................................................
11 LIST OF FIGURES.................................................. v
-LIST OF TABLES................................................... vi Section Topic 1
INTRODUCTION........................................... 1-1 2
ENVIRONMENTAL SURVEILLANCE ACTIVITIES 2.1 Smoke Control....................................
2-1 2.2 Erosion Control..................................
2-1 2.3 Transmission Line Surveys......................... 2-1 2.4 Chemical and Solid Waste Management............... 2-4 2.5 Land Management and Wildlife.....................
2-5 2.6 Groundwater Monitoring...........................
2-6 2.7 NPDES............................................
2-12 2.8 Thermal Monitoring...............................
2-12 2.9 Cooling Tower Dritt.......................
....... 2-13 2.10 Meteorological Data............................... 2-19 2.11 Environmental Evaluations......................... 2-21 3
OBSERVATIONS AND DISCUSSIONS 3.1 Smoke Contro1....................................
3-1 3.2 Erosion Control..................................
3-1 3.3 Transmission Line Surveys........................
3-1 3.4 Chemical and Solid Waste Management............... 3-3 3.5 Land Management and Wildlife...................... 3-5 3.6 Groundwater......................................
3-5 3.7 NPDES............................................
3-12 3.8 Thermal Monitoring...............................
3-14
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3.9 Cooling Tower Drift............................... 3-15 3.10 Meteorological Data..............................
3-33 3.11 Environmental Evaluations......................... 3-37 4
INCIDENTS 4.1 Reportable Incidents.............................
4-1 4.2 Nonreportable Incidents..........................
4-1 iii 12RESlay
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APPENDICES PAGE
-Appendix'I 1983 Generator and Facility Hazardous Waste Reports...............................
1-1 Appendix II Hydrographs for Perched Groundwater Wells.......................................
II-1 Appendix III Environmental Evaluations....................III-l i
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I LIST OF FIGURES FIGURE NUMBER PAGE 1-1 General Area Map................................. 1-2 1-2 Property Boundary................................ 1-4 2-1 Local Drainage Basins............................ 2-2 2-2 Transmission Line Routes.........................
2-3 2-3 Regional Groundwater Well Locations.............. 2-8 2-4 Location of Construction Dewatering &
Observation Wells (Perched Groundwater)......... 2-10 2-5 Salt Deposition Station Locations................ 2-15 2-6 Salt Deposition Control Station.................. 2-16 2-7 Meteorological System Location................... 2-20 v
12RESlay
1 LIST OF TABLES TABLE NUMBER PAGE 2-1 Regional Groundwater Well Locations In Figure 2-3.................................... 2-9 2-2 Perched Groundwater Well Locations In Figure 2-4....................................
2-11 2-3 Salt Deposition Station Location In Figure 2-5 and 2-6............................ 2-17 3-1 GGNS Runoff Data (1983).......................... 3-2 3-2 Regional Groundwater Monitoring Data (1983)...... 3-6 3-3 Perched Groundwater Monitoring Data (1983)....... 3-8 3-4 Precipitation Measurement (1982-1983)............
3-11 3-5 Salt Deposition Data............................. 3-16 3-6 Salt Deposition Rainfall Data.................... 3-20 3-7 Summary of Analysis of Variance.................. 3-23 3-8 Summary of Analysis of Variance (Based on Composition Data)...................... 3-25 3-9 Salt Deposition Data (5 Locations, 4 Periods).... 3-26 3-10 Summary of Analysis of Variance (No Interaction Between Period and Location)..... 3-28 3-11 Environmental Factors............................ 3-30 3-12 Summary of Regression Analysis................... 3-31 3-13 Joint Frequency Distribution, 50 Meter Level (1983).................................... 3-34 3-14 Joint Frequency Distribution, 10 Meter Level (1983)....................................
3-35 3-15 Percent Bad Data Report (1983)................... 3-36 3-16 Environmental Evaluations -
1983 Summary Sheet.............................. 3-38 vi 12RESlay
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SECTION 1 INTRODUCTION I-r a
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1.1 INTRODUCTION
The environmental impact of Grand Grand Nuclear Station (GGNS) construction and operational activities between January 1 and December 31, 1983, was measured by the Environmental Surveillance Program.
The results of the Environmental Surveillance Program contained in the following sections indicate the. environment has not been adversely impacted by GGNS.
Factual information about GGNS and its operation is provided in the remainder of this section.
Location GGNS is a nuclear power station owned by Middle South I'.
Energy, Inc. and South Mississippi Electric Power Association (SMEPA) and operated by Mississippi Power & Light Company (MP&L).
An area map showing the geographical location of the facility is provided in Figure 1-1.
GGNS is located in Claiborne County, Mississippi, on the east bank of the Mississippi River, approximately 25 miles south-southwest of Vicksburg and 37 miles north-northeast of Natchez.
Grand Gulf Military Park borders a portion of the north side of the property, and the small community of Grand Gulf is approximately 1-1/2 miles to the north.
The town of Port Gibson L
is about 6 miles southeast of the site.
Two lakes, Gin Lake and Hamilton Lake, are located in the western portion of the site.
These lakes were once the channel of the Mississippi River and average about 5 to 7 feet in depth.
1-1 12RESlay
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Site and Its Environs The site and its environs consist primarily of woodlands
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The western half of the site is in the alluvial plain of the Mississippi Rivers the eastern half is in the Loess or Bluff Hills.
The elevation of the site varies between 60 and 80 feet above Mean Sea Level (MSL) in the alluvial plain region, while the Loess Hills portion varies from 80 to more than 200 feet above MSL.
The property line shown in Figure 1-2 encompasses the 2376 acres originally purchased by MP&L.
However, due to erosion activity of the Mississippi River along the western boundary of the site, this acreage figure continually decreased until the river bank from the barge slip to the north boundary of the site was stabilized through the U. S. Army Corps of Engineer's shoreline modification program.
The present acreage figure for the site due to erosion is 2300 acres.
The site boundary is the same as the property line except in the southeast and west-southwest sectors as shown in Figure 1-2.
A 2-acre residential property within the southwest sector is privately owned.
There are no industrial, commercial, institutional, or residential structures within the site boundary.
There are no railroads or waterways that traverse the site.
An unpaved county road runs through the site in the south-southeast, south, south-southwest, and southwest sectors.
This road provides access to Hamilton and Gin Lakes and the Mississippi River from the Port Gibson-Grand Gulf Road.
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Access The site area is accessible by two major highways: U. S.
Highway 61 and State Highway 18, which connect Port Gibson (6 miles southeast of the site) with Natchez, Jackson and Vicksburg.
History of Operation and Present Status The Station consists of two Boiling Water Reactors (BWRs) rated at 1250 MWe each.
Unit I received a Low-Power Operating License on June 16, 1982.
Fuel loading began on July 1, 1982, and was completed on August 6, 1982.
Initial criticality was achieved on August 18, 1982.
Low-power testing began on September 25, 1983 and was discontinued on November 8, 1983, with 995.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of operation at less than 5 percent power recorded for Unit 1.
Low-power testing resumed on April 22, 1984, and commercial operation is planned for late 1984.
The following list summarizes significant dates associated with the operation of Unit 1:
o Low-Power Operating License June 16, 1982 o
Initial Criticality August 18, 1982 o
Began Low-Power Testing September 25, 1983 o
Discontinued Low-Power Testing November 8, 1983 o
Resumed Low-Power Testing April 22, 1984 Unit 2 is in a construct' ion phase and was 33.0% complete as of December 31, 1983.
1-5 12RESlay
SECTION 2 ENVIRONMENTAL SURVEILLANCE ACTIVITIES 2-L 12RESlay
2.1 SMOKE CONTROL Open burning of waste materials at GGNS is not permitted.
Wastes are burned in a pit utilizing an air curtain incinerator destructor which blows air over the fire to insure complete combustion of ignitable material.
This process reduces particulate emissions to the environment.
Daily inspections of the' burn pit are made by Environmental Surveillance Program personnel.to insure compliance with the State of Mississippi's regulations on burning.
2.2 EROSION CONTROL Erosion control at GGNS is a major priority because of the proximity of GGNS to the Mississippi River, the hilly terrain, the average annual rainfall of approximately 50 inches and the loess soils which are extremely susceptible to erosion.
The methods utilized to control erosion are:
o Immediate revegetation of disturbed areas o
Utilization of concrete chutes and flumes which channel runoff into two sediment basins, A and B (Figure 2-1).
Sedimentation occurs in the basins which minimizes ecological effect on the two oxbow lakes (Hamilton and Gin) and the Mississippi River.
2.3 TRANSMISSION LINE SURVEYS There are four transmission lines associated with GGNS (Figure 2-2).
A 115 kV transmission line from Port Gibson, Mississippi, supplies construction power and emergency power to GGNS.
The Baxter Wilson and Franklin lines are 500 kV transmission lines which terminate in Warren and Franklin 2-1 12RESlay
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The fourth line, Ray Braswell, is a planned-500 kV transmission line which will connect GGNS to an existing 500_kV transmission line in Warren County.
A semiannual aerial survey of these lines is conducted to observe vegetation growth and to monitor for erosion.
When problem areas are identified, ground patrols are sent in to make a closer observation.
Recommendations are then made to the Mississippi Power & Light Company (MP&L) Engineering Department for corrective action.
These areas are closely monitored during follow-up serial surveys to determine the effectiveness of the corrective actions.
Techniques designed to minimize erosion are used to reclear and control vegetation on these transmission lines.
All highway, river and stream, and railroad crossings are hand cut, usually leaving buffer strips adjacent to the crossing.
The use of heavy equipment in clearing right-of-ways is limited to piling brush and pushing brush piles.
Potential erosion areas are seeded and mulched.
The long growing season in this area provides excellent early root formation which helps prevent damaging erosion.
Synthetic erosion prevention material is utilized when necessary.
2.4 CHEMICAL AND SOLID WASTE MANAGEMENT Liquid wastes such as chemicals, fuels, lubricants, bitumens and flushing solutions, are deposited or discharged into tanks for salvage or subsequent removal to appropriate off-site locations.
Adequate care is taken to avoid the handling or storing of liquids in close proximity of major drainage areas to avoid potentially damaging spills to site streams.
2-4 12RESlay
Construction scrap and debris are collected in designated on-site areas for salvage, incineration or burial.
Unuseable, combustible materials are incinerated onsite in an air curtain destructor burn pit.
Emission levels and operation of the burn pit incinerator is in accordance with Mississippi Air Quality Regulations.
Emissions and odors are kept at an acceptable minimum and all control devices are maintained in good working order.
Noncombustible solid wastes are buried at designated landfill areas on the site.
2.5 LAND MANAGEMENT AND WILDLIFE Approximately 2300 acres owned by MP&L makes up the GGNS site 94 acres are fenced in the immediate plant area, with an additional 37 acres set aside for permanent structures.
The remaining acreage, which is excellent habitat for Mississippi wildlife, is productively utilized, keeping wildlife enhancement in mind.
Several agricultural leases with local farmers have been established at GGNS.
Some lands have been leased to an area farmer for grazing purposes.
The farmer uses every available resource to have a productive operation while meeting the GGNS criteria for wildlife enhancement.
Other areas are leased for the production of hay and soybeans.
The hay fields serve as open areas and the soybeans attract wildlife year round.
2-5 12RESlay
Fringe areas and open fields are mowed a minimum of two times during each growing season.
This keeps open areas from being overtaken by scrub vegetation.
After the growing season, a series of small food plots are planted in these open fields to help sustain wildlife populations through the winter and early spring.
A small fruit orchard and garden are maintained on site by Environmental Surveillance Program personnel.
This provides fruit and vegetable samples necessary for the GGNS Radiological Environmental Surveillance Program broadleaf sampling requirements.
Two lakes located on the site, Gin and Hamilton, are used for sport and commercial fishing.
Operation of the station has had no apparent ecological effect on the fish population in these lakes.
Utilization of the lakes and surrounding local lands by water dependent species (waterfowl) is seasonal, with most activity occurring during the fall and winter migrations.
Hunting on the site is limited to bow hunting for deer by members of the MP&L Bow Hunting Club.
Other hunting activities are prohibited on the GGNS site.
2.6 GROUNDWATER MONITORING A groundwater monitoring program has been established at GGNS to:
o Provide data on the seasonal flunctuation of the regional groundwater table o
Define the cone of depression caused by plant pumping operations o
Monitor the level of the perched groundwater table in the Unit I and 2 Power Block areas.
2-6 12RESlay
= -. - _ _
Location of Monitoring Wells Twenty-seven wells are used to monitor the regional and perched groundwater underlying GGNS:
o 12 wells monitor the regional groundwater levels in the site area o
15 wells monitor the perched groundwater levels in the Power Block areas.
Locations of monitoring wells are shown in Figures 2-3 and 2-4 and listed in Tables 2-1 and 2-2.
Regional Groundwater Wells used to monitor the regional groundwater levels (Figure 2-3 and Table 2-1) are measured twice a month.
Fluctuations in the regional groundwater table levels have indicated that maximum groundwater levels occur in June through August, with minimum levels occurring in November through January.
These seasonal fluctuations correspond to those of the Mississippi River.
No indications of groundwater depletion have occurred since the inception of the program.
Perched Groundwater GGNS Units 1 and 2 have a monitoring and dewatering system (Figure 2-4 and Table 2-2) located around the power block and the Standby Service Water Basins to monitor and dewater the underlying perched aquifer.
Seven wells (MW-1 through MW-7) monitor the water levels in the perched aquifer and eight wells are in place to dewater the aquifer if water levels approach or exceed 109 feet Mean Sea Level (MSL).
Water levels in perched aquifer wells are observed and recorded once per month.
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REGIONAL GROUNDWATER WELL LOCATIONS IN FIGURE 2-3 LEGEND WELL NUMBER SECTOR LOCATION DESCRIPTION 1
P5, OWS B
NW Laydown Area - Unit 2 Bluff behind Unit 2 2
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Bluff North of Switchyard 4
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West end Met Tower Field County Road - Adjacent to 5
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Stream A West Laydown Area -
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Unit 2 Field - Northside Haul 7
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Road Unit 1 Cooling Tower 8
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Across the South Plant Access Road and east of Basin B i.
2-9 12RESlay
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TABLE 2-2
' PERCHED GROUNDWATER WELL LOCATIONS IN FIGURE 2-4 WELL NO.
UNIT NO.
LOCATION DESCRIPTION MW1 2
North end Unit 2 Turbine Bldg.
MW2 2
Northwest Corner Unit 2 Auxiliary Bldg.
MW3 1
Northeast of SSW B (between fences)
MW4 1
Southwest side SSW A MW5 2
Northeast MP&L Maintenance Shop MW6 1
North of Condensate Storage Tank MW7 2
East of Unit 2 Turbine Bldg.
DW1 2
East of Unit 2 Turbine Bldg.
DW2 2
Corner Auxilliary Bldg. - Turbine Bldg.
Unit 2 DW3 2
Northwest Corner Unit 2 Auxiliary Bldg.
by Electric Panels DW4 2
Southwest Corner of Unit 2 Auxiliary Bldg.
DW5 1
In front of Diesel Generator Bldg.
(under man-hole)
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Corner Unit I Turbine Bldg - Auxillary Bldg.
DW8 1
Behind Radwaste Bldg. - Unit 1 2-11 12RESlay L
2.7 ' NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT National Pollutant Discharge Elimination System (NPDES)
Permit No. MS 0029521 was amended and reissued to GGNS on June 1, 1982.
The Permit was issued in accordance with the provisions of -
the Mississippi Air and Water Pollutant Control Law (Section 49-17-1, Mississippi Code of 1972) and the regulations and standards adopted and promulgated thereunder, and authority granted to the Mississippi Pollution Control Permit Board pursuant to Section 402(b) of the Federal Water Pollution Control Act.
The Permit allows GGNS to discharge waste water in accordance with NPDES regulations into Hamilton Lake and the Mississippi River.
NPDES reporting requirements are established by the State of Mississippi.
Reports of all outfalls are generated on a quarterly basis and sent to the Mississippi Department of Natural Resources and the U. S. Nuclear Regulatory Commission.
2.8 THERMAL MONITORING PROGRAM l
Grand Gulf Nuclear Station's NPDES Permit requires that GGNS effluents and the Mississippi River mixing area be monitored on a
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semiannual basis to determine what effects, if any, will result from GGNS' heated discharge into the river.
The NPDES Permit states that "the receiving water shall not exceed a maximum water temperature change of 2.8'C relative to the upriver temperature outside a mixing zone not exceeding a maximum width of 60 feet from the river edge, and a maximum length of 6000 feet 2-12 12RESlay
downstream from the point of discharge as measured at a depth of five feet."
To initiate the thermal monitoring program and obtain baseline data, the river bank was surveyed to establish and permanently mark 72 reference points 100 feet apart.
Sixty-six of the reference points are located downstream of the Station's discharge into the river, and the remaining 6 are located upstream of the discharge.
Calibrated digital thermometers are used to obtain temperatures at a depth of 5 feet and at the surface.
At each reference point, measurements are taken 100 feet from the river bank, then at 10 feet intervals until reaching the bank.
This provides 20 temperature data points for each reference point.
2.9 COOLING TOWER DRIFT PROGRAM The Environmental Protection Plan requires that a study be conducted to determine the environmental effects of salt deposition from cooling tower drift.
MP&L elected to conduct a quantitative and qualitative cooling tower drift study which would identify the salts deposited on vegetation in the surrounding environment and determine the quantity of each salt.
The study utilizes seven fallout collection buckets located four to five feet above the ground, fitted with bird rings, and covered with fine mesh screens te exclude insects and leaves.
2-13 12RESlay
Salt Deposition Station Locations Six of the seven Salt Deposition Stations (SDS) are located in areas where maximum salt deposition is predicted.
These areas were extrapolated from a Salt Deposition Model developed for MP&L.
Two of the stations (Stations 2 and 5) have two replicate sampling devices, with one of the replicates at each location being a dry collector (Stations 2b and 5b).
The seventh station is a control located south of Raymond, Mississippi.
The location of the SDS sites are identified in Figures 2-5 and 2-6 and listed in Table 2-3.
Sample Analysis and Collection Samples are collected quarterly and analyzed for ten constituents.
o Calcium o
Sodium o
Iron o
Phosphate o
Nitrate o
Chloride o
Fluoride o
Sulfate o
Total dissolved solids These parameters were selected because past analyses have shown them to be prevalent in the Plant Service Water system.
Salt constituents are determined for the demineralized water used in the initial setup of the collection buckets.
Rainfall data is recorded for each sampling site.
Screens are washed with deionized water and the wash water volume is measured and deposited in the collector on a quarterly basis.
The volume of water in the collector is then measured, and a composite sample of the collector's contents is placed in a clean cubitainer, sealed and labeled with the date of removal, 2-14 12RESlay
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- um um ov/er MISSISSIPPI POWER & LIGHT COMPANY GRAND GULF NUCLEAR STATION UNITS 1 & 2 SOUnCE: Omaisi highway mop Louissene (19701 Omcent hechmey map Manis**Pp' (1971) j l
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Salt Deposition Control Station 2-16 i
TABLE 2-3 SALT DEPOSITION STATION LOCATIONS IN FIGURE 2-5 AND 2-6 LEGEND ID NO.
SECTOR DESCRIPTION 1
SDS 1 P
Heavy Haul Road - Adjacent to Basin B 2
SDS 2, 2A, 2B A
Fenced Storage Area by Met Tower 3
SDS 3 C
Catwalk on truck bypass Road 4
SDS 4 E
Maggie Jackson residence -
Waterloo Road 5
SDS 5, 5A, 5B J
MP&L Training Center -
Waterloo Road 6
SDS 6 L
Glodjo Residence - Waterloo Road 7
SDS 7 N/A Smith Residence - Raymond, MS (control) 2-17 12RESlay
total volume in the collector and location of the station.
This information is also recorded on the appropriate data sheets.
Salt Deposition Rate Calculation Salt deposition rates (SDR) are calculated on a
. constituent-by-constituent basis from:
o The total volume of water contained in the sampling bucket o
The concentration of a constituent in thin water o
The volume of demineralized water placed in the sampler initially o
The concentration of the constituent in the demineralized water o
The sampling area of the bucket.
Therefore, for a particular constituent, SDR = (V C )
(V C )
TT DD A
SDR = Salt Deposition Rate (mg/m / period) where:
VT = final sample volume V
= seeded volume of demineralized water D
V
= final sample constituent concentration T
V
= demineralized water constituent concentration D
A = sampler area (m )
l 2-18 12RESlay
2.10 METEOROLOGICAL SYSTEM The GGNS meteorological tower with base elevation of 160 feet above MSL is approximately 5,000 feet northwest of the GGNS Unit I reactor building, which has a finished grade 132 feet above MSL.
The location of the meteorological tower is shown in Figure 2-7.
The area around the tower is flat and grass covered.
The nearest bluffs are 362 feet to the west of the tower with trees 35 feet high along the bluffs.
Approximately 400 feet to the east are trees 50 to 60 feet high along with a hill about 30 feet higher than the base of the tower.
To the south, the nearest trees 50 to 60 feet high are 690 feet from the tower.
A county road passes the meteorological tower 400 feet to the north.
The tallest structure, the GGNS Unit 1 natural draft cooling tower, is 522 feet high and is situated approximately 5,750 feet south-southeast of the meteorological tower.
Due to its location in a relatively open area and its proximity to GGNS, the tower site is expected to accurately represent the same meteorological characteristics as the region into which any airborne material will be released from the plant.
The following parameters are monitored at the 133 and 33 feet levels of the tower:
o Wind Direction o
Wind Speed o
Temperature o
Change in Temperature ( A T) o Dew Point l
o Surface Precipitation 2-19 12RESlay
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The data for the Meteorological Program is included in the Semiannual Effluent Release Reports submitted to the U. S. Nuclear Regulatory Commission. 2.11 ENVIRONMENTAL EVALUATIONS The Environmental Protection Plan (EPP) for GGNS permits changes in station design or operation and the performance of tests or experiments that affect the environment, provided they do not involve a change in the EPP or an unreviewed environmental question. This means that changes, tests or experiments which do not affect the environment are not subject to the requirements of the EPP. Also, the requirements of the EPP do not relieve GGNS of the requirements in 10 CFR 50.59, " Changes, Tests and Experiments," which address the question of safety associated with proposed changes, tests and experiments. Grand Gulf Nuclear Station personnel review changes in plant design or operation and the performance of tests and experiments for the possible effects they might have on the environment. When the review determines that the change test or experiment may affect the environment, an Environmental Evaluation is prepared and recorded by Radiological & Environmental Services staff before additional construction or operational activities associated with the change, test or experiment are begun. However, the EPP excludes changes, tests or experiments from the evaluation: o If all measureable environmental effects are confined to onsite areas previously disturbed during site preparation and plant construction, or 2-21 12RESlay
If they are required to achieve compliance with other o Federal, state, or local requirements. Review of changes, tests and experiments at GGNS is conducted by one of three groups: o Nuclear Plant Engineering o GGNS Plant Staff o Radiological & Environmental Services (R&ES) All three groups perform an applicability determination of proposed changes, test or experiments to ascertain if the activity might affect the environment. Only those which have the potential to affect the environment receive Environmental Evaluations. Since R&ES controls the EPP, it is their responsibility to perform Environmental Evaluations. Nuclear Plant Engineering has the authority to perform Environmental Evaluations, but R&ES have final responsibility to provide concurrence once the evaluation is completed. 2-22 12RESlay
SECTION 3 OBSERVATIONS AND DISCUSSION 3-1 12RESlay
3.1 SMOKE CONTROL-Daily inspections of the burn pit were conducted by Environmental Surveillance Program personnel in 1983. During the, year 18 opacity violations were noted. Timely corrections were made on each occasion. No other smoke control problems were identified during 1983. The operation and construction of GGNS has contributed insignificant smoke emissions to the environment surrounding GGNS. 3.2 EROSION CONTROL During 1983 73.94 inches of rainfall were recorded at GGNS. Runoff samples were taken during periods of heavy rainfall at the influent and effluent of each basin to determine the sediment load and the efficiency of each basin. The results, reported in Table 3-1, indicate an overall reduction in sediment loading coming into the Basins. This may be attributed to the stabilization and revegetation of the majority of disturbed areas on site. 3.3 TRANSMISSION LINE SURVEYS (1983) The semiannual aerial surveys of the GGNS transmission lines identified no major problem areas during 1983. Reclearing was completed on the Franklin Line with the exception of a swampy area near the Homochitto River. No additional reclearing was done on any other GGNS lines. Some minor erosion was identified on the southern end of the Baxter Wilson Line. A ground survey will determine the extent of the erosion and corrective action will be taken. 3-1 12RESlay
TABLE 3-1 GRAND GULF NUCLEAR STATION RUNOFF-DATA i RUNOFF DATA 1983 Rainfall Basin A Inf Basin A Eff Basin B Inf Basin B Eff Date (inches) TSS (mg/1) TSS (mg/1) TSS (mg/1) TSS (mg/1) 01/21/83 2.87 95.30 115.30 12.40 71.50 02/02/83 2.28 1037.50 216.20 17.20 198.70 02/09/83 1.83 350.20 39.90 70.30 134.00 02/10/83 1.15 279.50 203.60 28.10 165.70 ~02/22/83 1.33 143.00 30.80 29.30 127.90 03/24/83 1.85 179.50 81.60 15.50 78.10 1 ~04/06/83 6.30 10567.00 1387.50 390.90 278.40 04/07/83 1.60 318.30 369.00 41.10 143.80 i 04/08/83 0.16 118.60 235.20 28.90 118.10 04/25/83 2.60 222.90 295.30 113.30 266.20 05/16/83 3.47 46.80 247.20 43.90 139.30 05/19/83 2.44 1328.80 262.40 144.30 199.20 05/20/83 3.80 942.60 530.80 114.95 112.30 06/16/83 2.57 -347.10 114.60 21.60 149.90 06/23/83 0.63 20.10 15.90 70.30 184.60 06/24/83 2.30 226.50 281.20 27.20 114.90 11/23/83 2.60 1000.00 1040.00 180.00 380.00 11/28/83 1.15 100.00 220.00 30.00 60.00 12/06/83 1.90 200.00 420.00 10.00 140.00 12/22/83 0.86 119.90 113.30 52.00 79.00 12/27/83 0.25 38.00 13.00 178.00 53.00 12/28/83 1.34 229.00 321.00 10.00 104.00 .3-2 12RESlay
Minor erosion due to off-road travel by area hunters was evident on the southern end of the Franklin lina. These areas are being monitored closely. No herbicides were used in controlling vegetation on GGNS transmission lines during 1983. 3.4 CHEMICAL AND SOLID WASTE MANAGEMENT 3.4.1 Solid Waste Solid waste generated at GGNS during 1983 did not present any unanticipated problems or adversely affect the environment. Office waste, rubble and debris were incinerated or buried onsite without incident. Solid waste activities at GGNS in 1983 were in compliance with Mississippi Department of Natural Resource, Bureau of Pollution Control, " Solid Wastes Disposal Law of 1974." 3.4.2 Chemical Waste Nonhazardous Waste GGNS did not incur any serious problems or incidents with chemical waste control in 1983. Chemicals of a nonhazardous nature (resins, silica gel, charcoal) were successfully disposed of onsite. Chemicals which were suitable for re-use were recycled through local contractors and nonprofit organizations. Other nonhazardous chemicals (borate water, phosphates) were discharged through National Pollutant Discharge Elimination System outfalls and reported accordingly. 3-3 12RfSlay
A few items concerning chemical waste control in 1983 are identified below: o A minor chemical spill (200 gallons) occurred on January 30, 1983 when a flange leaked on the Betz 2020 tank. The spilled material was cleaned up with no apparent environmental damage, o On April 7, following a heavy rainfall, a small oil sheen was noted at the head of Sediment Basin B. Since the amount observed was small, no action was taken. The probable cause of the sheen was determined to be site runoff. o The Mississippi Department of Natural Resources granted MP&L permission in May, 1983, to dispose of 84 fifty-five gallon drums of nonhazardous wastes through the oil / water separator at NPDES Outfall 008. Monitoring of the discharge was conducted, with no adverse environmental impact
- observed, o
A lube oil spill occurred in September following the Diesel Generator fire. The lube oil was contained in Sediment Basin "B" with no oil evident below the dam. No ecological damage occurred from this spill. o Less than five gallons of-50% NaOH was spilled in October. The spill was quickly contained and neutralized with NaHC0. No adverse environmental 3 effects were evident. Hazardous Waste Hazardous wastes or chemicals (acids, sealants) were collected and stored in GGNS' Hazardous Waste Storage Area. The Department of Natural Resources inspected the Hazardous Waste Storage Area and related activities in 1983. They found the storage area and GGNS generally in compliance with the Interim Status Standards of the Resource Conservation and Recovery Act (RCRA). GGNS prepared its Part B Hazardous Waste Permit Application in 1983 and expects to receive a 3-4 12RESlay
4 } permit before the end of 1984. Copies of GGNS' Generator and Facility Annual Hazardous Waste Reports are included in Appendix 1. Polychlorinated Biphenyls (PCBs) Sampling of dielectric fluid for PCBs was completed in 1983. Dielectric fluid units contaminated with PCBs have been properly marked and identified. No known releases or exposures related to PCBs occurred in 1983. 3.5 LAND MANAGEMENT AND WILDLIFE Two endangered species, the American alligator (Alligator mississippiensis), and the Bald Eagle (Haliaetus 1. leucocephalus), were both reportedly observed on or near GGNS property during 1983. Alligators are known to inhabit both Hamilton and Gin Lakes and their tributaries. The eagles were reportedly observed during the unseasonably cold December weather. During the 1983 bow hunting season (October, 1982-February, 1983) 15 deer were killed. There were 124.6 hunting hours per deer killed for a hunter success ratio of 2.9% for the season. The operation of the station has had no apparent ecological effect on the wildlife population or vegetation in the GGNS , vicinity. 3.6 GROUNDWATER Regional Groundwater Regional groundwater monitoring data is presented in Table 3-2. Water levels occurred at expected elevations. Fluctuations in well water elevations were attributed to flooding of the 3-5 12RESlay
TABLE 3-2. 1983 Regional Groundwater Monitoring Data-r_______________________________________________________________________________________________________ 1 2 2 3-ell No. Year Formation Min (Month) Max (Month) Average L_________________---__ DW4 1983 A 65.4 MAR 77.0 JULY 70.7 l DW4A 1983 A 61.8 NOV 72.1 JULY 66.8 l DW29A 1983 T 51.7 JAN 63.2 JULY 58.8 l DW209A 1983 T 72.6 JAN 90.0 DEC 83.7 l P5 1983 C 66.1 JAN 72.1 AUG 69.7 l DW7 1983 T 60.1 JAN 68.3 AUG' 64.3 l P4 1983 C 58.6 NOV/DEC 65.2 JULY 61.9 l OW69A 1983 A 47.8 OCT 63.1 JULY 58.3 l OW202 1983 T DRY JAN-MAY 78.8 JUNE 76.8 SEPT-DEC 'W5 1983 T 64.6 JAN 70.7 AUG 68.4 0 l OW10 1983 C 68.5 JAN-MARCH 144.4 DEC 85.4 209 1983 C DRY JAN-DEC DRY DRY l A = Alluvium; C = Catahoula;,T = Terrace Deposits 2 Water Level Elevation (Feet Above MSL) 3 Average Elevation for Non-Dry Readings (Feet Above MSL) 3-6 12RESlay L
4 e' Mississippi River. The 1983 data was consistent with preoperational and 1982 data. Perched Aquifer Perched groundwater data is presented in Table 3-3. A hydrograph for each perched aquifer well is provided in Appendix II. Unusually heavy rainfall during the fall of 1982 and spring c of 1983 caused the water level in the perched aquifer to rise. From January through August 1983, dewatering well DW-8 slightly exceeded the design basis groundwater elevation for GGNS of 109.00 feet above MSL. No safety-related equipment was affected by this temporary increase above the design basis groundwater elevation. The details and a prescribed course of action involving this event are outlined below: The power block area and Standby Service Water (SSW) L-basins for GGNS-Units 1 and 2 were constructed within an .open excavation that extends from yard grade at elevation 132.5 feet above MSLito the Catahoula Formation at approximately 87 feet above MSL. Seepage of groundwater and rainfall into the excavation area from the terrace deposits overlying the Catahoula Formation was initially controlled by pumping water from sumps. However, as construction proceeded, these sumps were replaced with a Construction Monitoring and Dewatering System to continue the removal of seepage from the excavation area and to monitor water levels in the perched aquifer. 3-7 12RESlay
TABLE 3-3 PERCHED GROUNDWATER MONITORING DATA YEAR: 1983 MONITORING WELL - WATER LEVEL DEWATERING WELL - WATER LEVEL MONTH DATE MW1 W2 MW3 MW4 MW5 MW6 MW7 DW1 DW2 DW3 DW4 DW5 DW6 DW7 DW8 JANUARY 1-28-83 DRY 94.87 100.6 103.5 DRY 107.77 87.7 87.7 96.3 98.9 101.1 102.5 94.44 109.91 FEBRUARY 2-15-83 DRY 92.07 100.8 104.2 DRY 107.27 91.3 91.5 88.7 96.8 101.5 107.4 95.44 110.21 MARCH 3-11-83 DRY 99.47 100.7 104.2 104.67 97.1 97.2 99.6 99.9 101.0 105.2 93.54 109.01 APRIL 4-22-83 DRY 99.27 101.0 104.8 DRY 105.37 97.9 97.9 99.4 99.7 102.1 106.0 106.34 109.61 MAY 5-24-83 DRY 99.17 100.9 104.5 104.0 105.67 104.6 104.6 99.5 99.5 102.0 105.5 107.14 109.41 JUNE 6-16-83 DhY 99.17 101.9 104.3 103.2 105.57 101.6 101.6 99.8 99.9 101.7 105.5 105.64 109.51 JULY 7-20-83 DRY 98.87 101.4 103.4 DRY 105.27 97.03 97.0 100.8 99.5 101.4 105.1 106.44 109.21 AUGUST 8-24-83 DRY 99.77 100.9 102.9 DRY 104.67 97.03 97.0 99.6 99.6 100.9 104.1 105.54 107.91 I SEPTEMBER 9-22-83 DRY 99.67 100.6 102.5 DRY 103.77 97.83 97.2 99.9 100.0 100.6 103.8 104.84 107.41 OCTOBER 10-27-83 DRY 99.77 100.4 101.6 101.5 DRY 98.03 98.3 95.44 99.9 100.0 100.3 103.7 104.54 106.96 NOVEMBER 11-18-83 DRY 99.67 DRY 101.9 101.6 DRY 98.43 98.7 99.34 99.8 99.9 100.3 103.4 104.44 107.31 i DECEMBER 12-14-83 DRY 99.77 DRY 103.5 101.6 103.07 99.93 99.4 101.24 99.9 99.8 100.8 103.3 104.94 107.91 l l 1, Wat r Level Missing Data e 3-8 12RE51ay
This Construction Monitoring and Dewatering System at GGNS consists of eight dewatering wells and seven monitoring wells. The dewatering wells are 10 inches in diameter and are located around the power block of Units 1 and 2. Four wells (DW1-4) are located on the Unit 2 side of the power block, three wells (DW6-8) are on the Unit 1 side area and one well (DW-5) is located adjacent to the SSW basins which are common to both areas. The Units 1 and 2 dewatering wells are located in the excavated area between the tie-back wall and station structures as shown in Figure 2-4. This area has been refilled and covered with a clay seal in the case of Unit 1, but it is still open on the Unit 2 side. The Unit 1 dewatering wells and SSW basin well have not been operated since the completion and turnover of Unit 1 to MP&L in April, 1982. The Unit 2 wells are still operational. The seven monitoring wells (MW-1 through MW-7) are composed of 6-inch diameter PVC pipe installed within the backfill. Their locations are also identified in Figure 2-4. Water levels in these dewatering and monitoring wells have been measured at least monthly since their installation in 1976, with the exception of the. periods from April 4 to September 24, 1982 and November 19, 1982 to January 28, 1983. During these periods, only the Unit 2 wells were measured. This monthly monitoring program has indicated that for the period of January 28, 1983 through August 24, 3-9 12RESlay
~ 1983 the. design maximum groundwater elevation of 109.0 feet above MSL was exceeded in the vicinity of dewatering well DW-8. The primary cause of this high groundwater elevation was attributed to the unusually heavy precipitation which occurred in the area from December, 1982 through June, 1983 (Table 3-4). Precipitation measurements recorded by GGNS's meteorological system indicated that 69.81 inches of rainfall fell on the area during these months. This is 200 percent above the long-term mean rainfall for this time of year as determined by the National Weather Service in Jackson, Mississippi. The values in Table 3-3 reflect how the perched aquifer responded to this increase in rainfall. An increase of 4 to 5 feet in water levels measured in wells on the Unit 1 side of the power block was common during this time period. With two exceptions the rise in water levels was not reflected in a concurrent rise in Unit 2 observation well water levels. This is because levels in the Unit 2 area were controlled by operation of the Unit 2 dewatering wells in response to rising water levels. The two exceptions were DW-1 and MW-7 which are located adjacent to each other on the east side of Unit 2. Due to operational problems with the pump in DW-1 which serves this area, it operated only intermittently from February through June, 1983, resulting in an increase in water level for both DW-1 and MW-7. 3-10 12RESlay
4 TABLE 3-4 PRECIPITATION MEASUREMENT GRAND GULF NUCLEAR STATION AND JACKSON, MISSISSIPPI 1 2 OBSERVED AT SITE LONG-TERM 1982-1983 MEAN PERIOD INCHES INCHES December 16.21 5.47 January 1.51 4.97 February 6.58 4.69 March 6.56 5.67 April 14.36 5.39 May 14.31 4.59 June 10.28 3.74 3 TOTAL 69.81 34.52 1 Rainfall measurements from Meteorological System at Grand Gulf Nuclear Station. 2 U. S. Weather Service, Jackson, Mississippi for 1909-1981, 3 200.2 percent above the Long-Term Mean. 3-11 12RESlay
4 a l~ The GGNS Architect / Engineer is studying this problem to determine the cause of the event and a possible solution. The 'information derived from this study and a potential course of action is expected to be identified by January 1, 1985. As an~ interim measure the Unit 1 dewatering wells will be reactivated to preclude recurrence of this event. 4 ' 3.7' NPDES d The 1983 results for all permitted outfalls were reported in the NPDES Quarterly Reports. The Mississippi Department of Natural Resources and the U. S. Nuclear Regulatory Commission received copies of these reports. Several items noted during 1983 and included in the quarterly reports are summarized below: o The Plant Service Water System (PSW) was shut down for the majority of January; therefore, temperature information for .0utfall 001 was not available during that time. o A violation of the NPDES Permit occurred for Outfalls 004 and 005 in January, when the Standby Service Water Basins discharged measureable amounts of chlorine for greater than-120 minutes. Actions were taken to preclude a recurrence of this violation. o A discharge;of Outfall 006 (Low Volume Waste Basin) occurred in January without an oil and grease sample being analyzed by the approved U. S. Environmental Protection Agency (EPA) method. However, a sample of the discharge which was viewed under an ultraviolet light indicated no visible oil sheen. o Permission was received from Mr. Larry Hamil of the Mississippi Department of Natural Resources to sample Outfalls 007, 008 and 009 at a confluent location. This was ' initiated in January 1983, with the results reported on the Discharge Monitoring Report for Outfall 007. 1 1 3-12 12RESlay
y-- o Approximately 400 gallons of water /demineralizer resins (Ecodex) mixture was inadvertently emptied into the storm drain at Outfall 009 on June 8, 1983. A sample was collected at the confluence of Outfalls 007, 008, and 009 and analyzed for total suspended solids and for oil and grease. o Outfall 001 was shut down for maintenance from June 20 to June 23, 1983. o Outfall 002 discharged 11,000,000 gallons of water from April 26 to May 10, 1983. The discharge was continuous and had no detectable residual chlorine. o A discharge of Outfall 006 occurred in May without being analyzed for oil and grease by the approved U. S. EPA method. However, a sample of the discharge, when viewed under an ultraviolet light, indicated no visible oil sheen. o The flow gauge installed at the confluence of Outfalls 007, 008 and 009 was washed away in May, 1983 as a result of a series of heavy rainfalls. The gauge design was modified and a new gauge was installed on July 7, 1983. o.In April and May, 1983, the cooling water for a diesel generator was discharged into Outfall 007 on three occasions. Samples were collected at the Outfall of Basin B and analyzed for nitrites; no detectable nitrites were determined to exist. In May, permission was received from Mr. Larry Hamil of the . o Mississippi Department of Natural Resources to empty.84 drums of non-hazardous waste into the oil / water separator at Outfall 008. Samples were collected and analyzed prior to discharge, o Outfall 004 overflowed August 8, 1983, due to an incorrect valve alignment. Approximately 6000 gallons of water overflowed onto the ground. Samples were collected and analyzed for NPDES parameters. On September 4, 1983 a fire in the Diesel Generator Building o caused oil to be released through Outfall 007. The oil was contained in Basin B and samples were taken and analyzed for oil and grease, Water was discharged from Outfall 006 on September 10, 1983 o without being analyzed for oil and grease by an approved U. S. EPA method. However, samples that were taken showed no visible oil and grease when viewed under an ultra-violet light. Sampling is now being conducted on a weekly basis rather than a discharge basis to assure compliance with the NPDES Permit. 3-13 12RESlay j
w o An incorrect valve alignment resulted in the discharge of approximately 100 gallons of diesel fuel through the confluence of Outfalls 007, 008 and 009 on September 16, 1983. o Standby Service Water Basin B (Outfall 005) overflowed on ~ December 1, 1983 when site power was lost. 87,000. gallons + flowed into a storm drain and then into Sediment Basin A (Outfall 013). o Approximately 6 million gallons of cooling tower water was released into Sediment Basin B (Outfall 014) on November 13-14, 1983. An additional 5 million gallons of cooling tower water was released via Outfall 001 on November 13-14, 1983. The flow rate for the quarterly report for Outta11 001 was adjusted to include the 6 million gallon release on November 13-14, 1983. Higher than normal total suspended solids occurred on i o November 23, 1983 at Outfalls 007, 008 and 009. This was due in part to heavy rainfalls preceding the sample collection. 3.8 THERMAL MONITORING Environmental Surveillance Program personnel performed monitoring to determine baseline winter thermal conditions on -February 17, 1983 and baseline summer thermal conditions July 26-28, 1983.. Thirteen of 72 points (51-64) were underwater during the winter monitoring -therefore, no data was available' for those points.- All 72 points were monitored during the summer. The results were organized.and plotted so that temperature changes could be noted at specific distances from the river bank at all accessible reference points. Additional information such as river flow, ambient temperatures and effluent temperatures were also recorded. The baseline data indicates that the turbulence of the river mixes the water such that only a small variation in temperature occurs between the surface and a depth of five feet. Since GGNS l 3-14 12RESlay
Z,,,_w-- .laa- <=wa + A=a n A4 w-- A Am. 1 A -41 L -,\\s,-2a ,-m-----Aum A a, a 4 has.not released a substantial heated discharge, no differences in water temperatures between the mixing area and the areas beyond the mixing zone were noted. Baseline summer and winter data will be used to compare preoperational and operational thermal monitoring data following the startup of GGNS. The results will be reported to the Mississippi Department of Natural Resources as required by the NPDES Permit. 13.9 COOLING TOWER DRIFT Table 3-5 gives the calculated Salt Deposition Rates (SDR) .for all seven monitoring stations in the GGNS Cooling Tower Drift Program. Table 3-6 presents the cooling tower drift rainfall data. Statistical Development Presently, the data base is not yet extensive so the validity of some of the data could'be questioned. This is F especially true for the October-through-December, 1983 sampling period as can be seen by examining the total dissolved solids rates in Table 3-5. Nevertheless, data analysis is possible to obtain . quantitative estimates of the precision of the data and the relative importance of the various factors which can potentially influence salt deposition rates. The former can be quantified by .. estimating confidence limits for the various datas the latter by statistically analyzing the data by Analysis of Variance (ANOVA). The present statistical analysis uses a two-factor ANOVA which 3-15 12RESlay
TABLE 3-5 Salt Deposition Data ~ SodiumDepos{tionRate IronDeposit{onRate CalciumDeposigionRate ag/m ag/m mg/m Pariod Fndings-5-12-83 7-20-83 10-10-83 12-29-83 5-12-83 7-20-83 10-10-83 12-29-83 5-12-83 7-20-83 10-10-83 12-29-83 ............................n.................. -......................................................... c SDS #1 218.2 286.3 43.2 192.3 35.4 123.2 70.0 485.9 415.5 683.9 576.4' SDS #2 326.2 297.7*** 43.4** 140.1 55.9 97.2 20.2*** 76.6 538.5 364.1 79.0*** 126.0 SDS #2A 301.6*** 297.7 43.4*** 181.2 28.0 36.4 18.4 59.5 460.0 142.9 86.4 146.6-SDS #2B 277.1 297.7** 43.4 166.7 32.6 69.6 21.9 33.2 377.8 301.4 71.6-128.8 SDS #3 2 38.5 471.9 51.6 156.7 144.4 '57.0 23.0 61.9 457.1 94.9 85.5 174.0 SDS #4 263.6 431.4 36.3 220.8 172.9 115.1 21.9 90.4 403.7 184.0. 81.5 202.5 SDS #5 238.5 332.8 19.8 205.2 76.7 37.1 12.5 100.6 414.4 245.6 88.1 211.6-1
- SDS #5A 267.0 412.7 55.3 225.8 58.9 32.1 29.6 59.5 478.5 170.3 101.4 263.0 SDS #5B 269.8 404.3 161.8 204.4 154.7 216.9 27.7 16.0 423.9 229.5 104.1 248.6 SDS #6 302.5 241.2 35.5 140.8 134.8 35.3 27.5 112.9 396.0 138.8 52.6 160.3 l
4 SDS #7
- 325.5 505.1 162.5 238.6 70.5 96.8 6.9 33.4 375.3 334.7 37.6 184.7 l
i l l D:tes shown depict the end of the collection period.
- Repeat Analysis
- Biased
- Pseudo-Data Point (See Statistical Model) e 3-16
- Biased
TABLE 3-5 (Cint'd) 1 Salt Deposition' Data FluorideDeposgtion' Rate-NitrateDeposgtionRate ChlorideDeposgtionRate- .ag/m ag/m ag/m 1
- Psriod Ending:
5-12-83 7-20-83 10-10 12-29-83 5-12-83 7-20-83 10-10-83 12-29-83 5-12-83 7-20-83 10-10-83 12-29-83s SDS #1 0.0 0.0 1.0 0.0 0.0 0.0 10.3 49.7 ~ 308.2 444.3' 201.4 346.6' 'SDS #2 0.0 7.85*** 5.65*** 0.0 0.0 0.0 12.0*** 58.2 320.0 482.6*** 206.3-223.3 SDS #2A 0.0 0.0 11.3 0.0 0.0 0.0 12.5 54.8 337.8 335.3 341.8-257.5 ) 'SDS #2B 0.0 15.2 0.0' O.0' O.0 - 0.0 11.5 37.7 289.4 629.2 70.8 221.2 SDS #3 0.0 0.0 0.0 0.0 0.0 0.0 62.0 53.4 303.6 565.1 73.5 225.5 1 SDS #4 0.0 0.0 0.0 0.0 0.0 0.0-58.4 71.2 339.2 533.6 95.4 246.9 i SDS #5 0.0 0.0 0.0 0.0 0.0 0.0 17.4 44.5 303.6 441.4 60.4 257.5 SDS #5A 0.0 0.0 0.0 0.0 0.0 0.0 16.7 41.1 303.6 472.3 87.0 257.5 i j SDS #5B 0.0 0.0 0.0 A 0.0 0.0 16.4 48.0 300.0 483.2 165.8 272.6 1 l SDS #6 -0.0 0.0 0.0 '0 0.0 0.0 99.4 39.5 314.8 421.6 80.6 237.0 SDS #7 0.0 0.0 0.5 0.0 0.0 0.0 2.9 21.4 390.4 393.6 254.5 293.2 l Dates shown depict the end of the collection period. i
- Repeat Analysis
- Biased
- Pseudo-Data Point (See Statistical Model) l 3-17 i
- Biased
i
TABLE 3-5 (Crnt'd) Salt Deposition Data Magnesium Depogition Rate SulfateDepos{tionRate Phosphate Depogition Rate ag/m ag/m mg/m P;riod Ending: 5-12-83 7-20-83 10-10-83 12-29-83 5-12-83 7-20-83 10-10-83 12-29-83 5-12-83' 7-20-83 10-10-83 12-29-81 ............................... =........... =.................................................................................... SDS #1 7.4 142.2 139.7 74.5 1029.3 630.8 204.3 1062.1 0.0 46.3 11.4 77.0 SDS #2 80.1 115.2 30.7*** 23.7 1522.2 807.1 164.1*** 1051.2 80.6 52.7 11.1*** 0.0 SDS #2A 55.1 33.7 34.0 20.3 1410.3 666.7 203.0 486.2 66.6 0.0 16.2 0.0 SDS #2B 54.4 60.4 27.3 17.1 1289.5 1030.5 125.1 713.7 44.5 0.0 5.9 0.0 SDS #3 113.6 44.2 20.0 28.2 4280.0 2156.8 377.7 887.5 21.4 0.0 29.7 0.0 SDS #4 85.1 55.9 29.0 24.7 5305.8 1572.1 156.6 1065.6 0.0 0.0 7.9 0.0 SDS #5 63.7 39.3 12.5 23.7 2848.2 623.7 264.0 993.0 21.4 50.1 7.3 43.2 SDS #5A 60.1 43.0 23.9 23.7 3517.8 1019.6 191.2 503.3 21.4 0.0 6.5 50.0 SDS #5B 74.2 41.4 28.1 24.0 2873.8 710.9 237.3 744.5 21.3 46.4 8.5 17.1 SDS #6 73.4 37.5 16.1 16.2 2224.0 924.5 290.2 538.2 25.8 0.0 10.6 41.4 SDS #7 58.2 79.9 20.0 17.5 2699.6 597.2 346.9 734.4 25.8 91.3 43.8 23.6 D:tes shown depict the end of the collection period.
- Repeat Analysis CC Biased 200 Pseudo Data Point (See Statistical Model) 3-18
TABLE'3-5 (Cont'd)' Salt Deposition Data Total-DissolvedSolidsgepositionRate .mg/m Period' Ending:- 5-12-83 7-20-83 10-10-83, 12-29-83 ...............................m............... SDS #1
- 5534.3 5454.4 2135.2 3471.2 SDS #2 4205.5 5863.0 3473.7-0.0 SDS #2A 4054.8 5863.0 6213.0 0.0 SDS #2B 3411.0 5863.0***
734.3 0.0 SDS #3
- 4972.6 6095.2 1075.5 0.0
+ i SDS #4 2835.6 6372.6 974.0-0.0 SDS #5 1411.0 3906.0 948.0 0.0 SDS #5A 1767.1 5293.2 937.0 0.0 SDS #5B 1407.1 4324.1 1424.7 0.0 SDS #6
- 4412.6 6369.9 742.2 0.0 SDS #7.
- 2561.6 5062.3 3776.7 1736.7 i
Dates shown depict the end of the collection period.
- Repeat Analysis
- Biased
- Pseudo-Data Point (See Statistical Model) i e
- Biased
3-19
TABLE 3-6 Cool,ig Tower Drif t Rainfall Data Salt Deposition Total Rainfall Station Period Ending (Inches) SDS #1 5-12-83 21.5 SDS #2 5-12-83 21.0 SDS #3 5-12-83 21.0 SDS #4 5-12-83 21.3 SDS #5 5-12-83 21.2 SDS #6 5-12-83 20.8 SDS #7 5-12-83 20.3 SDS #1 7-20-83 23.5 SDS #2 7-20-83 23.0 SDS #3 7-20-83 20.2 SDS #4 7-20-83 23.5 SDS #5 7-20-83 24.0 SDS #6 7-20-83 22.1 SDS #7 7-20-83 16.0 SDS #1 10-10-83 7.5 SDS #2 10-10-83 5.8 SDS #3 10-10-83 7.1 SDS #4 10-10-83 8.1 SDS #5 10-10-83 7.5 SDS #6 10-10-83 7.1 SDS #7 10-10-83 6.5 SDS #1 12-29-83 17.4 SDS #2 12-29-83 16.7 SDS #3 12-29-83 17.4 t l SDS #4 12-29-83 17.5 SDS #5 12-29-83 17.0 SDS #6 12-29-83 16.0 SDS #7 12-29-83 17.8 3-20 1
3 involves calculating F-factors and conducting significance tests for the major potential influences (period, location and the interaction of the two). Statistical Model The basic statistical model selected for the analysis here is as follows: u+Pg+L3 + PLg3 + e (ij ) Dijk = k Where Dijk = basic SDR (Salt Deposition Rate) data u= mean SDR contribution due to sampling period P = g contribution due to sampling location L = 3 g3 = contribution due to sampling period and location PL interactions e (ij ) err r due to sampling, analytical, etc. techniques = k and other, unaccounted for, factors Interactions and " experimental" error can be separated in a multiple-factors experiments only if multiple observations are taken at various combinations of sampling periods and sampler locations. Determining confidence limits for the basic SDR data depends on the estimate of " experimental" error for the model; this estimate, in turn, depends on the availability of replicate samples. Since the latter were obtained only for SDS locations 2 and 5, this statistical analysis will consider only these two locations. Also, the " wet" (2, 2A, 5 and 5A) and " dry" (2B and 5B) sampler results will be pooled in the model as providing comparable estimates. For simplicity's sake a complete balanced 3-21 12RESlay
block design will be considered; that is, 3 replicate SDR's for each combination of periods.(four) and locations (two), or a total of 24 SDR data points for each constituent. The actual data block is incomplete since some SDR data are either not available or are obviously biased. Pseudo-data points have been estimated to complete the data block by minimization of the error sum-of-squares for the model; this is generally a good approximation for a data block with only a small number of missing data points. Table 3-5, giving the SDR data, include these pseudo-data points. Analysis of Variance (ANOVA) A computer program for the two-factor analysis of variance (ANOVA) of the data according to the described model has been developed. Basically, the progran calculates the sum-of-squares for each of the factors of interest (period, location, period-location interaction, and error). The F-factors for period, location and period-location interaction relative to basic error are determined as well as an estimate of the confidence limits for the average SDR for any given period and location. For the purposes of this analysis, 95% confidence limits and 95% significance critical F-factors have been - considered; of course, using standard student - t and F distribution tables, other levels of significance are readily determinable, if required. Table 3-7 summarizes the results of f this analysis. 3-22 12RESlay
TABLE 3-7
SUMMARY
OF ANALYSIS OF VAR 1ANCE Average 95% Confidence F - Factors Deposition Rate (1) Interval For Period For Location For Interaction Parameter og/m3/ Period mg/m2/ Period Calc (2) Crit (3) Calc (2) Crit (3) ~ Calc (2) Crit (3) ~ 1. Sodium 217.2 +/- 51.0 55.0 3.59 3.75 4.84 2.74 3.59 2. Iron 57.2 +/- 58.9 1.71 3.29 1.35 4.54 0.45 3.29 3. Calcium 241.8 +/- 68.4 44.9 3.29 0.33 4.54 2.35 3.29 4. Fluorides 1.66 +/- 4.4 1.79 3.34 5.14 4.60 1.79 3.34 5. Nitrates 15.5 +/- 5.2 169 3.29 0.02 4.54 1.56 3.29 6. Chlorides 296.7 +/- 98.5 16.5 3.34 0.63 4.60 0.71 3.34 7. Magnesium 42.1 +/- 20.5 9.66 3.29 1.33 4.54 1.21 3.29 8. Sulfates 1000 +/-276.1 90.9 3.29 21.1 4.54 20.8 3.29 9. Phosphates 23.8 +/- 21.8 3.79 3.29 0.03 4.54 5.36 3.29 10. TDS 2546 +/1410.0 21.2 3.41 10.9 4.67 1.47 3.41 NOTES 1. For all samples (4 periods, 2 locations, 3 replicates) 2. Calculated F-f actor (relative to mean square for error) 3. 95% Critical F-Factor I { 3-23 l 1 1
As noted earlier,-it is necessary to use replicate salt deposition rates to separate " experimental error" (error between the replicates) from interaction influences. The use of composition in ANOVA instead of salt deposition rates may aid in this process as well as provide additional information regarding potential sourcec of the salt. Composition for an individual parameter (e.g. for sodium, for location 2, period 1, and replicate 1) is determined by dividing the valme of the salt deposition rate for the parameter by the sum of the corresponding values for all other constituents other than TDS. A two-factor ANOVA with 3 replicates is then conducted for 2 locations (f2 and
- 5) and 4 periods.
Table 3-8 provides a summary of the ANOVA based on composition. Results of the ANOVA (Table 3-7) for sampler locations 2 and 5 (with replicate samples) indicate that the interaction between sampler location and sampling period is not significant for all parameters other than sulfates and phosphates. Therefore, the two-factor ANOVA (without replicates) can be performed for the other parameters. Table 3-9 shows salt deposition data (5 locations, 4 periods) for sodium, iron, calcium, fluoride, chloride, magnesium, and total dissolved solids (TDS) for the ANOVA analyses without interaction. A computer program (similar to the previous program for ANOVA) calculates the F-Factors. Table 3-10 summarizes the results of the simplified ANOVA. t To analyze impacts of environmental factors such as rainfall, wind speed, prevailing wind direction and resultant 3-24 12RESlay
TABLE 3-8
SUMMARY
OF ANALYSIS OF-VARIANCE ~ (Based on Composition Data) Parameter F - FACTORS For Feriod For Location' For Interaction F1 F2 F' crit F1 F2 F crit F1 F2 F' crit 1. Sodium 55.0 3.63 3.59 3.75 0.24 4.84 2.74 1.29 3.59 2. Iron 1.71 1.16 3.29 1.35 0.26 4.54 0.45 0.19 3.29 3. Calcium 44.9 2.31 3.29 0.33 0.03 4.54 2.35 4.96 3.29 t 4. Fluorides 1.79 2.38 3.34 5.14 5.18 4.50 1.79 2.38 3.34 5. Nitrates 169 67.1 3.29 0.02 .009 4.54 1.56 2.5 3.29 6. Chlorides 16.9 9.2 3.34 0.63 5.37 4.60 0.71 2.46 3.34 7. Magnesium 9.66 14.7 3.29 1.33 7.57 4.54 1.21 1.33 3.29 1 8. Sulfate 90.9 14.8 3.29 21.1 2.93 4.54 20.8 3.74 3.29 9. Phosphate 3.79 0.31 3.29 0.03 0.26 4.54 5.36 6.25 3.29 NOTES: 1. F1 is the F factor for ANOVA based on salt. deposition rate i 2. F2 is the F factor for ANOVA based on composition 3. F crit is 95% Critical F-Factor 3-25 1
TABLE 3-9 SALT DEPOSITION DATA (5 Locations, 4 Periods) . Sodium Deposition Rate, ag/m2/ Period P riod Ending SDS #1 SDS #3 SDS #4 SDS #6 SDS #7 05-12-83 218.2 238.5 263.6 302.5 325.5 07-20-83 286.3 471.9 431.4 241.2 505.1 10-10-83 43.2 51.6 36.3 35.5 162.5 12-29-83 192.3 156.7 220.8 140.8 238.6 Iron Deposition Rate, ag/m2/ Period 05-12-83 35.4 144.4 172.9 134.8 70.5 07-20-83 123.2 57.0 115.1 35.3 96.8 10-10-83 70.0 23.0 21.9 27.5 6.9 12-29-83 75.3 61.9 90.4 112.9 33.4 Calcium Deposition Rate, ag/m2/ Period 05-12-83 485.9 457.1 403.7 396.0 375.3 07-20-83 415.5 94.9 184.0 138.8 334.7 10-10-83 683.9 85.5 81.5 52.6 37.6 12-29-83 576.4 174.0 202.5 160.3 184.7 Fluoride Deposition Rate, ag/m2/ Period 05-12-83 0 0 0 0 0 07-20-83 0 0 0 0 0 10-10-83 1.0 0 0 0 0.5 12-29-83 0 0 0 0 0 Nitrate Deposition Rate, ag/m2/ Period 05-12-83 0 0 0 0 0 07-20-83 0 0 0 0 0 10-10-83 10.3 62.0 58.4 99.4 2.9 12-29-83 49.7 53.4 61.2 39.5 21.4 3-26 . ~,, y
4 TABLE 3-9 (Cont'd) SALT DEPOSITION DATA (5 Locations, 4 Periods) Chloride Deposition Rate, ag/m2/ Period Pariod Ending SDS #1 SDS #3 SDS #4 SDS #6 SDS #7 05-12 308.2 303.6 339.2 314.8 390.4 '07-20-83 444.3 565.1 533.6 421.6 393.6 10-83 201.4 73.5 95.4 80.6 254.5 12-29-83 346.6 225.5 246.9 237.0 293.2 Magnesium Deposition Rate, ag/m2/ Period 05-12-83 7.4 113.6 85.1 73.4 58.2 07-20-83 142.2 44.2 55.9 37.5 79.9 '10-10-83 139.7 20.0 29.0 16.1 20.0 ~ 12-29-83' 74.5 28.2 24.7 16.2 17.5 Total Dissolved Solids Deposition Rate, ag/m2/ Period 12-83 5534.3 4972.6 2835.6 .4412.6 2561.6 ^ 07-20-83 5454.4 6095.2 6372.6 6369.9 5062.3 10-83 2135.2 1075.5 974.0 742.2 3776.7 12-29-83 3471.2 0.0 0.0 0.0 1736.7 3-27
' TABLE 3-10
SUMMARY
OF ANALYSIS OF VARIANCE (No Interaction between Period and Location) Average 95% Confidence .F. Factors Deposition Rate (1) Interval For Period For Location Parameter ag/m2/ Period ag/m2/ Period Calc (2) Crit (3) Cale(2) Crit (3) i 1. Sodium 228.1 +/- 61.7 28.5 3.49 3.32 s3.26 l 2. Iron 75.4 +/- 46.6 3.24 3.59 0.658 3.36 'l 3. Calcium 276.2 +/-127.4 '3.85 3.49 .6.47 3.26 4. Fluorides 0.08 +/- 0.24 2.25 3.49 1.0 3.26 5. Nitrates 23.4 +/- 22.9 8.27 3.49 1.38 3.26 j 6. Chlorides 303.5 +/- 71.5 21.9 3.49 0.71 3.26 4 7. Magnesium 54.2 +/- 44.2 1.08 3.49 1.11 3.26 8. Sulfates 1354.2 +/-894.5 11.18 3.49 2.02 3.26 9. Phosphates 22.8 +/- 27.6 0.32 3.49 1.88' 3.26 l
- 10. TDS 3179
+/-1349 16.0 3.49 0.95 3.26 NOTES: 1. For all samples (5 locations, 4 periods) 2. Calculated F-Factors (relative to mean square for error) l 3. 95% Critical F-Factor i 3-28
wind direction, regression analyses may be performed as follows: (1) Cumulative rainfall for the period versus the salt deposition rate for that period (for all salt deposition rates for sampler locations 2 and 5) (2) Average wind speed for the period versus the salt deposition rate for that period (as above) (3) Prevailing wind direction for the period versus salt deposition rates for that period (as above) (4) Resultant wind direction for the period versus the salt deposition rate for that period (as above) For each of the four sampling periods, data for rainfall and the frequency distributions for wind speed and direction have been obtained by reduction of GGNS weather data. Table 3-11 summarizes these four environmental factors. Data points for a regression analysis on a SDR parameter consist of data pairs as follows - an environmental factor for a period and corresponding SDR value of the parameter for the period. The SDR data from sampler locations f2 and #5 were used for the regression analyses. Table 3-12 gives the correlation coefficients (for each SDR parameter with each environmental factor) as obtained from the regression analyses. Conclusions o Data for total dissolved solids for all but two sampler locations for the fourth quarter are suspect because salt deposition rates (based on TDS) are zero. o Results of ANOVA (Table 3-7) based on salt deposition rates indicate the following: Interaction between sampler location and sampling period has no significant influence for all SDR parameters other than sulfates and phosphates. Sampling period has significant influence on all SDR parameters except for iron and fluoride. 3-29 12RESlay
y TABLE 3-11. ENVIRONMENTAL FACTORS Average Prevailing Resultant Period Rainfall Wind Speed Wind Direction Wind Direction g Ending in/ period MPH Degrees Degress 05-12-83 12.80 3.75 0 334.5 07-20-83 15.12 2.79 135 308.1 10-10-83 26.21 2.64 112.5 290.4 12-29-83 14.76 3.40 112.5 310 Degrees from North = 0 in clockwise direction 9 3-30
TABLE 3-12
SUMMARY
OF REGRESSION ANALYSES Correlation Coefficient Average Wind Prevailing Resultant Parameter Rainfall Speed Wind Division Wind Division. 1. Sodium -0.71 0.24 -0.16 0.55 2. Iron -0.40 0.16 -0.05 0.28. 3. Calcium -0.70 0.72 -0.78 0.90 4 4. Fluorides 0.18 -0.32 0.22 -0.22 5. Nitrates 0.05 0.13 0.34 -0.29 6. Chlorides -0.56 0.03 0.06 0.33 7. Magnesium -0.32 0.26 -0.35 0.56 8. Sulfates -0.61 0.72 -0.77 0.83 9. Phosphates -0.40 0.39 -0.41 0.49 10. TDS -0.04 -0.26 -0.05 0.11 l 3-31
Sampler location has significant influence only on fluorides, sulfates, and TDS. Sodium (+/-23%), Calcium (+/-28%) and Sulfate (i27.6%) data are relatively precise, while Iron (+/-103%), Fluoride ( /-265%) and Phosphate (+/-92%) data are relatively imprecise. If sources of depositing salt were the same and variations o in SDR were only due to sampler location, period and their mutual interaction, then ANOVA based on composition would be expected to show no dependence on the three factors. For sodium, calcium, and sulfates, at least five fold reductions in F-factors for location and period are apparent, indicating less dependence on the two factors. However, no clear trend has been established. Therefore, different sources of salt affect samplers at different locations differently for each period. (Please see Table 3-8). o Results of ANOVA (Table 3-10), assuming no interaction and without replicate samples, show similar trends for the influence of sampling period on SDR as previously with replicates, but show no clear trends for sampling location, o Results of regression analyses (Table 3-12) demonstrate the following: As expected, SDR tends to decrease with increasing rainfall during a sampling period. Sodium and calcium exhibit the most significant correlation coefficients with rainfall (-0.71 and -0.7 respectively). Correlation coefficients for both calcium and sulfate SDR's versus average wind speed are 0.72. Both parameters also show significant correlation coefficients for prevailing wind direction and resultant during the sampling periods. The above results may be interpreted as indicating the existence of a significant, general source of sodium salts (particularly sulfate and chloride) as well as a specific source of calcium sulfate (most probably) which are impacting the salt deposition samplers. Inspection of the site wind data indicates that the specific source is probably located to the north or northwest of the GGNS. Future Considerations The TDS data from the fourth sample collection period will o probably be discarded if used for any future data analyses. 3-32 12RESlay
o A qualitative, semi-quantitative or quantitative phenomenological model describing salt deposition in a general sense may be developed to utilize the monitoring . program's data appropriately. Which of the 3 levels of a model developed will depend on the uses to which the -analytical results will be put, the-precision and sensitivity required in assessing impacts. o As more data becomes available on SDR's, regression analysis will be considered using the data for individual locations. Also, regression analyses for multiple factors may be carried outs these can be useful in relating the various parameters as are ANOVAs. o To obtain better quantification of random sampling / experimental errors, the number of replicate samples obtained may be increased. o Covariance analyses may also be valuable for some SDR data to determine the effect of different variables at different locations. o If interrelationships between various constituents become important (e.g., for ascertaining whether sources are providing particular salts as opposed to separate ionic constituents), a generalized 3-factor block design may be formulated for ANOVA. Along with a phenominological model, this would provide a means by which impacts due to plant operations could be estimated more precisely. 3.10 METEOROLOGICAL DATA Meteorological Data for the 1983 reporting period was included in the Semiannual Effluent Release Reports submitted via AECM-83/0513 and AECM-84/0150 to the U. S. Nuclear Regulatory Commission on August 26, 1983, and February 29, 1984, respectively. Data contained in these reports is summarized in the following tables: o Joint Frequency Distribution, 50 Meter Level (Table 3-8) o Joint Frequency Distribution, 10 Meter Level (Table 3-9) o Percent Bad Data Report.(Table 3-10) l I 3-33 12RESlay
TABLE 3-13 JOINT FREQUENCY DISTRIBUTION 50 Meter Level PERIOD OF RECORD: 1/ 1/83, 000. 12/31/83, 2400 WIND SPEED (M/S) AT 50-M LEVEL 18 AVG 02 35 68 9 11 12 14 15 17 AND UP TOTAL SPEED h 3.6 3.1 4 0 0-0 0 7.2 .2 NNE 4.1 2.2 .1 0 .0 .0 .0 6.4 2 NE 3.9 2.4 1 0 0 0 .0 6.3 2 EN t. 2.9 1.8 0 0 0 0 0 4.7 1 DE 3.3 4.0 1 0 .0 0 0 7.5 .2 I ESE 4.0 5.6 4 1 .0 0 .0 10.1 3 R 56 3.7 4.4 6 1 .0 0 .0 8.7 3 W E SSE 2.9 3.6 5 0 0 0 .0 7.1 2 ICS 2.7 2.8 2 0 .0 0 .u 5.7 2 N T SSw 3.1 2.4 4 1 .0 0 .0 5.9 .2 0 I SD 3.2 1.9 4 0 .0 .0 0 5.6 .2 0 WSW 2.9 1.6 4 0 0 0 0 4.9 .1 NW 2.0 1.2 3 0 0 0 .0 4.2 .1 WNW 2.5 1.2 3 0 .0 0 .0 4.0 .1 NW 2.b 1.4 2 .0 .0 0 .0 4.4 .1 NhW 3.1 2.4 5 0 .0 0 .0 6.2 .2 CALM 3.1 1.1 TOTAL b2.5 42.0 4.9 5 0 0 0 100.0 2 504. HOURS OF BAD OR HISSING DATA OR 5.8 PERCENT FOR 8759 HOURS 3-34
TABLE 3-14 JOINT FREQUENCY DISTRIBUTION 10 Meter Level PERIOD OF RECORD: 1/ 1/83, 000. 12/31/83, 2400 WIND SPEED (M/S) AT 10-M LEVEL 18 AVG 0-2 35 68 9 11 12 14 15 17 AND UP TOTAL SPEED N b.4 6 .0 0 .0 0 0 6.0 .1 NNE 5.1 3 .0 0 0 0 .0 5.3 .1 NE 6.9 2 0 0 .0 0 .o 7.1 .1 ENE 7.1 .1 .0 0 .0 0 .0 7.1 1 DE 5.3 0 0 0 0 0 0 5.3 .1 I ESE 4.6 .1 0 0 .0 0 0 4.7 .1 R SE b.1 6 0 0 0 0 0 5.8 .1 d E SSE 4.8 1.4 1 0 .0 0 0 6.3 .1 1CS 4.5 1.2 .1 0 0 0 .0 5.8 .1 N T SSn 4.7 5 0 0 .0 0 0 5.2 1 D I SU 3.9 4 0 0 .0 0 0 4.3 1 0 USri 3.2 .1 .0 0 .0 0 .0 3.3 0 HH 2.6 .1 0 0 .0 .0 .0 2.8 .0 UN# 3.2 2 0 0 .0 0 0 3.3 0 Nh 3.7 .3 0 .0 0 0 .0 4.1 .1 hN4 4.1 1.0 0 0 0 .0 .0 5.1 .1 CALM 4.1 18.3 TOTAL 92.6 7.1 2 .0 0 .0 0 100.0 .1 546. HOURS OF BAD OR MISSIhG DATA OR 6.2 PERCENT FOR 8759 HOURS O 3-35
TABLE 3-15 PERCENT BAD DATA REPORT REPORT COVERS 6759 HOURS HOURS PERCEt!T 50M DIRECTION 176. 2.01 50M WIND SPEED 223. 2.55 10M DIRECTION 161. 1.84 10M WIhn SPEED 271. 3.09 TEMPERATURE 282. 3.22 DEd POINT 2775. 31.66 DELTA T 447. 5.10 PRECIPITATION 372. 4.25 3-36
3.11 ENVIRONMENTAL EVALUATIONS During 1983, no unreviewed environmental questions were found and no changes were made to the EPP. Radiological & Environmental Services staff performed 11 Environmental Evaluations and Nuclear Plant Engineering performed three during the reporting period. A completed copy of each Environmental Evaluation performed in 1983 is included in Appendix III. Table 3-16 summarizes each evaluated item. 3-37 12RESlay
TABLE 3-16 ENVIRONMENTAL EVALUATIONS 1983 Summary Sheet Identifying Number Description PS0-83-005/TA 820680 A temporary temperature element was installed to record PSW temperature at the discharge flow recorder. PSO-83-025/TA 820689 Annubars were installed in the SSW to provide flow measurement. PS0-83-027/TA 820535 A lead which short-circuited in the SSW computer system was reterminated. PS0-83-033/TA 820717 The flow and equipment drain system was modified to include a temporary radwaste/demineralizer system. PSO-83-040/TA 820672 Gauges and annubars were installed in the PSW to provide data collection points for flow balance and to furnish NPE additional data. PS0-83-084/TA 810842 40 HP motors with space heaters were replaced with 50 HP motors that did not have space heaters in the Containment Cooling System Fan Coil Units. PS0-83-098/TA 820138 Temporary alterations were made to allow testing the T48 system while waiting for design change documents to be issued. PS0-83-100/TA 820152 A temporary change was made to allow construction and preoperational testing of the Offgas System without energizing blowers and heaters. PS0-83-101/TA 820153 Changes were made to prevent inadvertent starts of the acid transfer pump for the SSW system. PSO-83-103/TA 820175 Elimination of unnecessary trips of the Offgas System by the Radiation Monitoring System. ODCM Rev. 1 The ODCM was changed to maintain consistency with GGNS and Standard Technical Specifications and to correct errors in the pathway and ingestion dose commitment factor tables. DCP-82/0607 Modification to increase instantaneous flow but not concentration or yearly average. DCP-81/0003 Change in amount of chemical added to treatment system. DCP-80/0015 Addition of Betz 492 in water treatment operations. 3-38 12RESlay i
i 't ? l l l SECTION 4 INCIDENTS J i t i i t f 4-1 12RESlay
4'.1 REPORTABLE INCIDENTS There were no reportable incidents observed during the reporting period. 4.2 NONREPORTABLE INCIDENTS Several minor events which occurred during the reporting period are outlined below: On March 2, 1983 a fish kill was reported in Basin A. An o investigation upstream and downstream of Basin A did not reveal any dead or dying fish. Water analyses of the basin revealed a pH of 8.3 and dissolved oxygen (D.O.) of 4.1 mg/1. Analyses were also performed on the water below the dam: pH - 8.2, D.0 - 3.6 mg/1. Visual examinations of the basin and its influent and effluent points were conducted through March 7, 1983. Mississippi Power & Light Company and the Mississippi Bureau of Pollution Control concurred that an algal bloom associated with abnormally warm temperatures could have been responsible for the fish kill. o On March 22, 1983 foaming was observed in Basin B where composite Outfalls 007, 008 and 009 enter the basin. No incident of foaming was observed in the discharge pipe. Nitrate analyses results were within allowable levels. o A volume of 110,000 gallons of water drained from Standby Service Water (SSW) Basin A to SSW Basin B when a drain valve was inadvertently left open on March 30, 1983. No adverse effects were realized. On June 2, 1983 a barge carrying drums of oil split when it o hit a support on the Mississippi River Bridge at Vicksburg. This resulted in a massive oil spill in the Mississippi River. Environmental Surveillance Program personnel surveyed the area around the plant including Gin and Hamilton Lakes and the Heavy Haul Road area on June 3, 1983. No signs of any oil were noticed in the lakes. This was probably due to the swif t river current which kept the oil in the main river channel. Arrangements were made by government agencies to collect the oil down river. 4-1 12RESlay
o 'On July 26, 1983, foaming was observed in the barge slip. A boom was placed at the confluent of the barge slip and the Mississippi River. The foaming was caused by trisodium phosphate (TSP) used in GGNS laundry facilities. The use of TSP has been replaced with a Department of Natural Resources-approved low phosphate, biodegradable detergent. o. On August 7, 1983 Standby Service Water (SSW) Basin B overflowed. An estimated 6000 gallons of water was discharged through an unpermitted outfall. The Mississippi Department of Natural Resources was notified of the discharge. Measures were taken to prevent a recurrence. o On September 4, 1983 a fire occurred in the Division I diesel generator, causing oil to leak into Outfall 007. This resulted in oil being discharged into Sediment Basin B. Two booms had been previously placed in the basin. The first boom contained 90% of the oil. The remainder of the oil was contained by the second boom. Analyses of the basin's effluent indicated no levels of oil and grease above allowable limits. No oil was present at the county crossroad ditch, the barge slip or the river. The cleanup operation was completed on September 5, 1983 and new booms .were deployed as a precaution. o On September 16, 1983 a valve misalignment caused 100 gallons of No. 2 diesel fuel to be discharged into the storm drain, resulting in an oil spill into Sediment Basin B. All of the oil was contained by the first boom. Analyses of the basin's effluent indicated no levels of oil and grease above allowable limits. The cleanup operation was completed the same day and new booms were deployed, o On September 29, 1983 a blown pump seal at Radial Well No. 1 resulted in the spill of about one gallon of oil through the french drain into the river. Cleanup operations were concluded on September 30, 1983. o On October 18, 1983 approximately five gallons of 50% sodium hydroxide was spilled or the ground at the south end of the Water Treatment Building. Neutralization and cleanup of the spill were completed the same day. o The Unit 1 Cooling Tower was drained through an unpermitted outfall beginning on November 13, 1983. The Mississippi Department of Natural Resources was notified of this violation on November 16, 1983. Operations personnel were instructed to discontinue this practice. 4-2 12RESlew
APPENDIX I 1983 GENERATOR AND FACILITY ANNUAL HAZARDOUS WASTE REPORTS I-i 1?RESiny
P MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi ( P. O. BOX 1640, J ACKSON, MISSISSIPPI 39205 February 28, 1984
- sWCLE AR PROOWCTIO*e OEPaRTutest Ms. Undine Johnson Mississippi Department of Natural Resources Bureau of Pollution Control Post Office Box 10385 Jackson, Mississippi 39209
Dear Ms. Johnson:
SUBJECT:
Grand Gulf Nuclear Statier Units 1 and 7 File: 0290/15329 Harardous k'aste Generator end Facility Annual Reports APO-84/0145 Fnclosed are Mississippi Power 6 Light (MP&L) Company's Gencrator Annual Hazardous k*aste Report and the Facility Annual Hazardous Waste for Grand Gulf Nuclear Station. A total of 11,926 pounds of hazardour waste, consisting of five different vaste types, were generated Report onsite during 1983, with to offsite shipnent occurring. Please address questions or corrnents concerning these reports to 969-2677. Mr. G. O. Snith, Supervisor of Environmental Services, at Yours truly, L. F. Dale Manager of Nuclear Services l JDB/LRM:aly Attachments Mr. J. B. Richard (w/o) cc Mr. J. P. McGaugby (w/o) Mr. T. E. Reaves (w/o) Mr. J. E. Cross (w/o) Mr. J. F. Pinto (w/o) Mr. T.11. c)nninger (w/o) Mr. M. D. Archdeecon (w/o) MSS Nuclear Activities (w/a) File (Plant) (w/a) File (Project) (w/a) I 51 1-1 MYMYY2JXhTXn South Utilities System
.i ENERATOR ANNUAL HAZARDOUS WASTE REPORT This report is for the calendar year ending December 31, 1983 I. GEllERATOR'S EPA I.D. NUllBER f *SD0006 4 4617 II. RAME OF INSTALLATION Grand Gulf Nucidar Station III. INST ALLATION MAILING ADDRESS Post Office Box 1640 Street or P. O. Box Mississioni 3 con;
- Jackson, State Zip Code City or Town LOCATION OF FACILITY (if different than section III above)
IV. Waterloo P.ad Street or Route number Minninnieni w1sn Port Gibson, State' Zip Code City or Town V. INSTALLATION CONTACT McKay, Dr. Larry R., Manacer Radiolocical & Envirnnmnntn1 cres, Name (last and first) (601) 969-2432 Phone No. (area code a no.) VI. CERTIFICATION I certify uder penalty of law that I have personally examined and as familiar with the information submitted in this and all attached documents, and that based on my inquiry of those individuals immediately responsible for obtaining the infomation, I believe that the submitted I an aware that there are information is true, accurate, and complete. significan3 penalties for submitting false information, including the sei ility of fine and imprisonment. a \\ f\\ r FEB 2 71934 J. P. EGa h Vice President-Nuclear ~ Date FrintfypT ame 7 1tle .Tignature F Authorised Representative I-2 GAR 1 of 2 _ ~ -.
NISSISSIFFI DFARTMENT OF NATURAL RESOURCES GENERATOR ANNUAL NAZARDOUS VASTE REPORT (CONT.) This report is for the calendar year ending December 31, 1983 VIII. FACILITY NAME (specify VII. GENERATOR'S EPA I.D. 30. facility to which all
- MSD000644617 wastes on this page were shipped)
- 1 II. FACILITY'S EPA I.D. 30.
- MSD000644617
- 1. FACILITY ADDRESS
- II. TRANSPORTATION SERVICES USED (List the name and EPA identification numbers of all transporters whose services were used during the reporting period.
This section to be completed only once. Do not repeat on supplemental sheets.) l
- See Section XIII III. WASTE IDENTIFICATION B. DOT C. EPA Hazardous D. Amount E. Unit A. Description Basard Waste No.
of of Line # of Vaste Code (see instructions) Waste Measure 1 oncrete Scalani (Toluene) ORM-E U-220 3230.9 P 2 PVC Ceraent (Furan & Cyclo, 08 U-213 & UO57 1376.1 P I 3
- oncrete Sealant Naphthalene ORM-E U-165 1834.8 P
4
- oncrete Sealant Cyanides ORM-E P030 4128.3 P
spent hcl D002, D004, D006
- lean Solution 02 D_0_07. D008 1376.1 P
6 7 8 9 10 11 ~2 1 I-3 IIII. CONMENTS (enter information by section number - see instructions)
- 3 Thnam6 fee caste was shipped of fsite during 1983.
J FACILITY ANNUAL BAZARDOUS VASTE REFORT 31, 1983 This report is for the calendar year ending December f I I. FACILITY EPA I.D. NUMBER ) MSD000644617 II. NAME OF FACILITY i Grand Gulf Nunione C:ta&4 - III FACILITY MAILING ADDRESS Post Office Bny 163n $treet or F. O. Box Mineimmin - ,o inn Jackson. Sfa'te Zip' Code City or Town LOCATION OF FACILITY (if different than section III above) IV Waterloo Road Street or Route number Missisminni loi nn Port Gibson State Zip Code City or Town Y. FACILITY CONTACT l McKay, Dr. Larry R., Manacev. pnaininm4rni a rnvivn-n-4-,- c"ns. Name (last and first) ~ (601) 969-2432 Phone Eo. (area code a no.) VI. COST ESTIMATES FOR FACILITIES N/A $ 26,750.00 Cost Estimate for Cost Estimate for Facility Closure Post Closure Monitoring & Maintenance (disposal facilities only) VII. CERTIFICATION I certify under penalty of law that I have personally examined and as l familiar with the information submitted in this and all at responsible for obtaining the information, I believe that the submitted I am aware that there are information is true, accurate, and complete. significant penalties for submitting false information, including the 9 O p ity of fine and imprisonment. 2I O ice Presionnt-Mncione Date J. P cGa g Signature of Authorized Representative Print $ype Name Title I-4 > anne 2
e 0 NISSISSIPPI DEPARTMENT OF EATURAL RESOURCES FACILITY ANNUAL RAZARDOUS VASTE REPORT (CONT.) O 31, 1983 This report is for the calendar year ending December VIII. FACILITY'S EPA I.D. 30. 1. GENERATOR EAME (specify MSD000644617 generator from whom all wastes on this page were II. GENERATOR'S EPA I.D. E0. received) "ON-SITE" 11 GENERATOR ADDRESS 31, 1983 TOTAL VASTE IN STORAGE ON DECEMBER (Complete this section only once for your facility; see section III III. of instructions for 1983 changes) SO3 SO2 501 11926.2 _UOM Amt. of Waste UOM Amt. of Waste UOM p _Aste of Waste SO5 SO4 _ UOM Amt. of Waste UOM Amt. of Waste IIII. VASTE IDENTIFICATION 3. EPA Hazardous C. D. E. Vaste No. Handling Amount Unit of A. Description Line # of Vaste (see instructions) Nethod of Vaste Neasure 1 Concrete Sealant Sol 171 n 4 v tr 99n (Toluene) U-213 & UO57 2 VC Pipe Cement 1976.1 p P (Tetrahvarnfuren & ('ve i nhovan nno t en1 3 Concrete Sealant (Naphthalene) U165 Sol 1834.8 P 4 Concrete Sealant (Cyanidos) P030 S01 4128.3 P 5 Spent hcl Cleaning D002, D004 Solution D006, D007 S01 1376.1 P D008 6 7 8 9 10 12 I-5
APPENDIX II HYDR 0 GRAPHS FOR PERCHED GROUNDWATER WELLS B l II-i \\ 12RESlay 1
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WELL NO. b b 1881 __4_j. _ .. L.- __._4. _, _e 10 \\ rem..M 4 eg e..._im.. sq._.4_ _g,gm_, !i! . i ! A I 8.,_PM'.,_M'h. du. _p._.y emu.um...au-qm.mu.um i ..>g-ed _n_.e 'Ip.eum. Imp.m ..e. m._p mu.. .Ip-m.m.m m.m __Whum. .u. .pp., m.- Pul.= esq esqp .amm_ m s __ __.__ _-.T-- ~Y - --- ~fi ~+-~ itt-r i i ! y -.g__ .__ _, __2___.a_._. .u. q _; !j;,. g_ _ _ 4. _+ _._._ ____..uq.. i _4 2 >: 103 -~~~ ~- ~- - i l! o m_ _ _] __31 i O TI 2 -.-_- a_ g .j._- q_..._._ __.{._ -h _.y..._44_ g_._.- ._u _._a+ i 4_ p~ Z.Z J:~?_7: - ' J :.. _.._%._ y.m .ga+ f_--I-t-t- ~~" - - Z ~: Z _ ____J::::
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WELL NO. N k 109 _w.__a. i i k_ _.} _.. . 9. ,m _-_2_;__
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APPENDIX 111 ENVIRONMENTAL EVALUATIONS III-i 12RESlay A
ie' I GWD GRE MICIIJe STATICN tEIT GE OIANGS, hh OR DG-EMNEI.'rS SAFT1T MO DNIlOMENTAL EVA111ATIO4 fUM Originator J. D. Barlow - R6ES Description A temporary temperature element is to Docurnent Evaluated PSO-83-005/TA 820680 e _ installed to record PSW temperature at the discharge References EPP flow recorder. FER Attachients Pso-83-005/TA 820680 s I. SAFL'IY EVAIMATIOl l TECllNICAL SPECIFICATIO4S A. O YIs O NO
- 1. InPlas'entation or performance of the action cescribed in the. evaluated docment will require a change to the GGNS Urtit One Technical Specifications.
Basis: I UNREVIE.'ED SAFTlY QUESTICN 8. Implepentation or performance of the action described in the evaluated hmt will O YES O no 1. increase the probability of occurrence of an accident previously evaluated in the j FSAR. j Basis: j O YES O NO 2. increase the comscvs of an accident previously evaluated in the FSAR. i Basis: O YEs O No 3. increase the preility of a malfunction or equipment isportant to safety L 1 previously evaluated in the PSAR. Basis: O YEs O no 4. increase the m:-scms of a malfw=Aion or equipient 2nportant to safety i previously evaluated in the FSAR. i Basis: 1 4 .l 111-1
O YES O No 5. create the possibility of an accident of a different type than any already eval-uated in the FSAR. Basis: .~ O Yts O NO 6. create the possibility of a malfw.ction or equipient iaportant to safety dirrer- - ent than previously evaluated in the FSAR. Basis: l i O YES O NO 7. rar% the margin of safety as defined in the basis for any t dnical specifica-tion. Basis: , II. DNI1ONENTAL EVAWATICN DNIJOMNTAL PROTECTICN PIAN A. O YES (3 NO 1. will require a change in the Dwirersnental Protection Plan. Basis: Temnerature elemant is beine inarnited on a ramnnrnrv ha=in en raninc, inoperative downstream elemont which is inaccecnible dun en avsrom nnorneinn-Tamperature nn D. UNREVIDED DWI3DNENTAL QLJrsnCN m nit ring nquimd h the N Pemit will not be compmmised, i O YE5 [3 NO 1. concerns a setter which may result in a significant increase in any adverse environmental 2mpact previously evaluated in the Final Dwirormental Statement (ITS) as modified by the NRC staff's testimony to the Atanic Safety and i Licensing anad (ASta), supplanents to the fTS, envirormental 2mpact appraisal, 4 or in any decisions of the ASIS. Basist Replacement of the original temperature element will allow the integrity of the recording system to be maintained. Consequently, there will be no adverse effect. O YES S NO 2. concerns a significant ch s.y: in effluents or power level (in accordance with i 10CFR51.5 (b) (2)). Basis: There will be no effluent or change in power level. l l, l III-2 .i i
D YES E NO 3. concerns a matter not previously reviewed and evaluated in the Ana% specified in B.1. above, which may have a significant adverse envirormental 13' pact. Basis: Effluent temperature monitoring was J dressed in the NPDES Permit. Temperature recording which is necessarf lor)enpronmentat monitoring is aueaoy in place. Y f-/2-8 luated by/Date! e.v. - Reviewed / Approved: A 1 f_. %-- T-12-d 1 isor/Da Reviewed / Approved: Manager /Date y ! SAFT1Y AND LICENSING REVIFW neviewed: Reviewed / Approved: Reviewed / Approved: Reviewing Supervisor of Nuclear Manager of Safety and mgineer/Date Safety /Date Licensing /Date RADICEIGICAL & ENVIRG@1DiTAL SERVICES REVIEW Reviewed: Revimaad/ Approved: Reviewed / Approved: Reviewing Supervisor of Man.vjer of-Radiological & Dgineer/Date hvirornental Services /Date Envirornental Services /Date 9 III-3 N..
__s / C. i GRAPD GHF WCIIAR STATIN WIT WE i OIANGES, 'ITSTS OR D}ERIMk2.'rS SAETIY AND DNIHO4 ENTAL EVAIDATIm EU44 s Description System number P41. Sennahv servi, une r Originator J. D. Barlow - R&ES Docunent Evaluated PSO-83-025/TA 820689 Installation of nnnubars in the "e'i e n nenv<a, rinu References EPP mome.romone FER Attactments PSO-83-025/TA 820689 I I. SAFETI EVAIDATIO3 TECINICAL wtLinCATIWS
- 1. Inplenentation or performance of the action cescribed in the. evaluated doctament will A. O YES O NO require a change to the GGNS Unit One Technical Specifications.
Basis: UNREVIR.'ED SAFETY QUESPIm Inpleentation or performance of the action describad in the evaluated humarkt will: B. O YE:S O No 1. increase the probability of occurrence of an accident previously evaluated in the FSAR. Basis: i I incraaw the consequences of an accident previously evaluhted in the FSAR. j O YES O NO 2. Basis: O YES O NO 3. increase the prhility of a malfunction of equirient inyurtant to safety previously evaluated in the FSAR. Basis: O YES O NO 4. increase the consequences of a malfunction of equipient 2mportant to safety previously evaluated in the FSAR. Basis: 1 i l l 1 III-4 i
1 l O YES O No 5. create the possibility of an accident of a different type than any already eval-uated in the FSAR. I Basis: O YES O No 6. create the possibility of a malfunction of equipent wportant to safety differ-ent than previously evaluated in the FSAR. Basis: l O YES O NO 7. rartna the margin of safety as defined in the basis for any technical specifica-tion. l Basis: II. DNIBCNMENTAL EVAIIETICN EVIRCIMNTAL PROTECTICN PLAN A. O YES G NO 1. will require a change in the Enviremental Protection Plan. Basis: Monitoring to evaluate the effects of the SSW on the environment is already in place. A change in the EPP will not be necessary. D. UNREVID.'ED DNIR0tMENTAL QJESFFICN O YES G NO 1. concerns a matter which may result in a significant incramme in any adverse enviromental inpact previously evaluated in the Final Envirormental Statement (FES) as nodified by the NRC staf f's testimony to the Atomic Safety and Licensing Board (ASIB), supplanents to the FES, envirorsnental spact appraisal, or in any decisions of the ASIB. Basis: Annubars will assist in the monitoring of plant operations. Therefore, there will not be an adverse environmental impact. O YES CD NO 2. concerns a significant change in effluents or power level (in accordance with 10CFR51.5 (b) (2) ). Basis: There will be no effluents or change in power levels. III-5 l i 1
o O YES Q NO 3. concerns a matter not previously reviewed and evaluated in the h e specified in B.I. above, which may have a significant adverse erwironmental 6Basis: This is an experiment to monitor flow in the SSW. It will not effect-plant operation. There will not be an a @erge e M ronmental impact. f-/2 ~83 Draluated by/Date we j Reviewed / Approved: C) d 9 - Q -13 S isor/Date ~ l Reviewed / Approved: Manager /Date / I SAFTIY MO LICDISING REVIEW ! Reviewed: Revi M / Approved: Reviewed / Approved: i l Reviewirq Supervisor of Nuclear Manager of Safety and t Digineer/Date Safety /Date Licensing /Date RADIMDGICAL & DNIDODENTAL SERVICES RD/IDi Reviewed: Reviewed / Approved: Reviewed / Approved: Re: Viewing Supervisor of Manager of Radiological & Dwirarsnental Services /Date Envirormental Services / Data Engineer /Date r i I l i 1 1 1 i l i III-6 4 4
+ GRMO CUIF MK3 EAR STATICN UNIT CNE OlANGES, TESTS OR D}EKIME2.TS SAFTIT NO DNIlOMENTAL EVA111ATICN EUM J Originator J. D. Barlow - R&ES Description System number P41, Standby Service Water. DoctEnent Evaluated PSO-83-027/TA 820535 Reterminate a lead for a computer point which short - i circuited. Change is needed to restore system to l Heferences EPP i FER original state. Att&Ctsments PSO-83-027/TA 820535 I. SAFETI EVAlllATIGI TECINICAL detElriCATICNS
- 1. Inplernentation or perfonnance of the action described in the evaluated doctment will A. O YES O NO require a change to the GGNS Unit One 'Nchnical St.ecifications.
Basis: 1 UNREVID.'ID SAFEIY QUESTICN Implementation or perfonnance of the action described in the evaluated docssment will: i j B. O YES O NO 1. increase the probability of occurrence of an accident previously evaluatal in the FSAR. Basis: O YES O No 2. incraaw the consequences of an accident previously evaluated in the EsAR. Basis: l O YES O NO 3. increase the prcbability of a ma11 unction of equirient iv tant to safety i r previously evaluated in the FSAR. Basis: l O YES O NO 4. increase the consequences of a malfunction of equipient important to safety previously evaluated in the FSAR. i Basis: i l l III-7
p e ~ O YES O NO 5. create the possibility of an accident of a different type than any already eval-uatal in the FSAR. Basis: O YES O NO 6. create the possibility of a nulfunction of equipient sportant to safety differ-ent than previously evaluatal in the FSAR. Basis: O YES O Ho 7. reduce the trargin of safety as defined in the basis for any technical specifica-tion. Basis: II. DWIRCNMDEAL EVAI11ATICN ELVIIOiXREAL PHOIECTICN PLAN A. D YES O NO 1. will require a change in the Enviromental Protection Plan. Basis: Change is necessary to restore system to original state. System will not be altered in any way. The EPP will not need to be changed. B. UNREVID.E DWIRCNeffAL CUESTICN O YES @ NO 1. concerns a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the Final Dwiromental Statarent (FES) as modified by the NHC staf f's testinony to the Atcmic Safety and Licensirv3 Board (ASIB), suppleents to the FES, enviromental spact appraisal, or in any decisions of the ASIE. Basis: System is being restored to original state. No adverse environmental impact will occur. O YES @ NO 2. concerns a significant change in ef fluents or power level (in amnroance with 10CFR51.5 (b) (2) ). Basis: There will be no effluents or change in power levels. III-8
= p o. concerns a matter not previously reviewed and evaluated in the h umaries O YES [9 No 3. specified in B.I. above, which may have a significant adverse envirorusental inpact. Basis: Since system is being restored to original state. any necessary review ~~ j and evaluation has already been completi(d thior to this date. "/1 ~83 - / a '- Ev61uited by/Date Reviewed / Approved: 4 -r2 -f 3 S isor/Date 7-NJ1 Reviewu$/ Approved: Manager /Date [ SAFE 1Y AND LICDiSING RLVHW Reviewed / Approved: Reviewed / Approved: Manager of Safety and Deviewed: 4! Supervisor of Nuclear Licensing /Date-Beviewirq Safety /Date Enaineer/ Data RAD 1053GICAL & DNIBONENTAL SEWICES REVIEW Deviewed/ Approved: Reviewed / Approved: Manager of Radiological & Beviewed: Supervisor of Dwiremental Services /Date A Reviewing Ertvirormental Services /Date Engineer /Date 7 9 5 1 i ~ ' (, 1 O 4 III-9
7 ~ a a GRAM GJIF 1RICTIAR STATICN UKIT GE OIANGES, TESTS OR DG Ek1ME2.TS SAF1mf Ato DNIHOMENTAL EVALLIATIO4 fTEM Description Modification of the flow and equipment Wiginator J. D. Barlow - 1&ES Document Evaluated PSO-83-033/TA 820717 drain system to include a tamnnrmrv raaumet, f41cor/ demineralizer system. Beferences EPP FER AttaciunentsPSO-83-033/TA 820717 l I. SAFETI EVAlllATIGI l TECINICAL SPECIFICATICNS
- 1. Inplenentation or perfonnance of the action described in the evaluated document will l
A. O YE5 O NO require a change to the G34S Unit One Technical Specifications. j Basis: UNREVIR?ED SAFT1T QUESTICN Implanentation or perfonnance of the action described in the evaluated docusent will: increase the p W hility of occurrence of an accident previously evaluated in the i B. O YES O NO 1. FSAR. Basis: increase the consequences of an accident previously evalunted in the FSAR. O YES O NO 2. Basis: increase the prhility of a malfunction of equipient wrtant to safety O YES O NO 3. previously evaluated in the FSAR. Basis: increase the consequences of a malfunction of equipent 2mportant to safety O YES O nO 4. previously evaluated in the FSAR. Basis: III-10
O YEs O No 5. create the possibility of an accident of a ditterent type tien any alrundy eval-uated in the FSAR. Basis: l O YES O No 6. create the possibility of a malfunction of equipent wportant to safety dirrer-ent than previously evaluated in the FSAR. j Basis: l a= the margin of safety as defined in the basis for any t :c.dcal specifica-O YES O No 7. r I tion. Basis: l l n. Durmeertz nrAumrrm i DNIMMNTAL PRO 11LTIW PIJN A.O Hs O No 1. will require a change in the Dwirormental Protection Plan. s Basis: This is a sunnlement to an existine system. The NPDER Permit addresnen l the system involved. j i D. WREVID;ED DNIROMENrAL QUESTIN O YIs gg No 1. concerns a matter Wiich may result in a significant increase in any adverse I envirormental inpact previously evaluated in the Final Dwircreental Statement (ITS) as modified by the NRC staf f's testiNony to the Atomic Safety and Licensing Board (ASIB), supplements to the FTS, envircreental impact appraisal, or in any decisions of the Asia. Basis: This is a temporary pretreatment of an existing waste stream. There will be no increase in system flow or concentration. Rndioloeien1 imnact of this nystem was O YES Q No 2. concerns a significant dange in ef fluents or power level (in accordai.c= with addressed in l 10 Celt 51.5 (b) (2) ). the FES. Basis: This is a suoolementary filtration system. There will not be an increnne l in effluent levels or concentrations. l J 9 III-11
M .? t concerns a matter not previously reviewed and evaluated in the ana e O YES [3 No 3. specified in B.I. above, which may have a significant adverse envirornantal inpact. Basis: Radiological impact of plant effluents to the environment was addressed in the FES. A N ?Wf3 w. Evaluated by/Date Reviewed / Approved: O ?R q.Q k3 Su isor/Da Reviewed / Approved: Manager /Date r SAFEIY AND LICDiSING REVIFW Reviewed: Reviewed / Approved: Reviewed / Approved: l Reviewirq Supervisor of Nuclear Manager of Safety and Engineer /Date Safety /Date Licensing /Date RADImmICAL & DNIROMENTAL SERVICES REVIEW Reviewed: Reviewed / Approved: Reviewed /Apptoved: l kviewing Supervisor of Manager of Radiological & Dwiummiental Services /Date Envirormental Services /Date Engineer /Date I i 4 r I III-12
- e e
lh d l lt i , e v l i i wn c o o i r t w i t y y t v p r d t nd e o n m ee R t e S t a = = t A e f a S f a = h h_l u F a s t s e E s a e o n r c a a n v h o t P u l n de t t E l b a t . n b f e ty n t n B n a n d e 4 a r t al i n a M 4 w n a us a t P d o m u l u d t r n l r l ao e r o r a f n a vi t o p e f v. ev a y n i m b s W n es e u n m e S i n er l i u g P eo hp a t n u a hi t v t n a r t tt t e n e e v o n a nn e p i E g f A nc ie y u f ii d l g i a o s i f di s i u F i t n di ec u u q n n n ec bc o q e r E m o i n be ia i e ip r v f e i o i t t p t rS cn e f o Im c sa r o E s a i y l n d sl e p n S l o d ea df n o M a i n cc o t o i 4 t t i n n i t 4 s c F nn oe e t c F. U o n e P oh ic d c n n E i I l M ic tn i n u l te ce c u f O t S p.o h cT ar c f l i c c a r a l. a. T Em e eu aR mR 3 T r i E T c e n n en hc n mA A I I r 1 I t e r hO tc a S aS E U e a n u t o aF F I M A s ( L D W d f t f f r I I fi of o f e oe I K m L A on o oh h E U e s t st } V I A D e cy e y e T cS nt c tn cn S R A nN ai n ii ni T I O r aG ml e l e i nG ri u id ud o q be qe R A b D n fh e at et oe r s ba sa 1 I 1 4 fh e n ou nu W I 2 rt ml K e pr o rl C a po p c pa 0 1 t r v v I N r oe e ee ee E 5 D oe h h h h 2 2 g nt t ty ty I l l U 7 mn o C V. O 6 a ie e es es N 0 i h ts s su su A r ao ao D G a 2 t c aa.s es eis ei s t e N i 8 a 2 t a nrRi ri rvi rvi R T A 7 n m ecA s c s ce s ce s nS a n a nr a nr a G L ST 6 ee miFB i B ipB i pB F E/ 0 S nr : I A &0 2 si s T i W S R4 8 el ui S p. u 0 I pq s E n h A T ne a U I1 2 3 4 3 T A I rB Q w 8 / C x o 0 t n l O 4 1 r r S 0 r n a P r m B 3 A d 8 l t i eP R O S O O O o P S h t P E O I o D N N N M D t aE F S , s E T u P 'l O O O O 1 l A A a 1 C O J 1 l v S 1 I I rEs t A N V o e n V E t tc e E D R S S S S E S N E E E E ann i I TE U Y Y Y Y a nee ir r M T Y icf t F O .O O O O gue 2 E roe t A ODB A S B A o. I ll llIif .l
a l l O YES O No 5. create the possibility of an accident of a different type than any already eval-uatal in the FSAR. l Basis: O YES O NO 6. create the possibility of a malfunction of equipent sportant to safety differ-ent than previously evaluatal in the FSAR. Basis: O YES O NO 7. rarha the margin of safety as defined in the basis for any technical specifica-tion. Basis: ' II. DNIBCNMENTAL EVAIIITCIN DWIR[livDfrAL PNIN PLAN A.O YES G NO 1. will require a change in the Enviromental Protection Plan. Basis: NPDES Permit considers the PSW. Consequently, a change in the EPP is not necessary. I B. UNREVIB;ED DNIRCREENIAL QUESTIN O YES Q NO 1. concerns a matter which may result in a significant increase in any adverse enviromental impact previously evaluated in the Final Dwirarinental Statment I (FES) as modified by the NRC staff's testimony to the Atanic Safety and Licensing Board (ASIB), supplanents to the FES, enviromental spect appraisal, i ) or in any decisions of the ASIB. l Basis: This additional data above and beyond the present requirement. Data is needed to provide a flow balance. O YES Q NO 2. concerns a significant change in ef fluents or power level (in accordarmit with 10&R51.5 (b) (2) ). j Basis: There will be no effluent or power generation. s 4 i ) 1 4 e III-14
1 s t cxmoerns a matter not previously reviewed and evaluated in the Anne O YES E NO 3. specified in B.1. above, dtich may have a significant adverse envirarsuantal isipact. - e Basis: PSW is addressed in the NPDES permi k f ) e ihhd P-/1.-B.s C Tuated by/Date Deviewod/ Approved: AO 1__ L lk q_et-I3 i r/Da d Deviewed/ Approved: Manager /Date r SAFETY AND LICDISING REVIEW paviewed: Reviewed / Approved: Reviewed / Approved: Supervisor of Nuclear Manager of Safety and Licensing /Date Reviewirq Digineer/Date Safety /Date RADIowGICAL & DNIROMDrfAL SERVICES REVIEW Reviewed / Approved: Baviewed: Reviewed / Approved: Manager of Radiological & Supervisor of Dwirornental Services /Date k view 2.ng Dwirarsnental Services /Date Engineer /Date O III-15
i I GRAPD GHF WCIEJe STATICN LEIT GE OlAM2S, TESFS OR D}kA1742.*rS SAETTY APO DNIHOMDFTAL EVA111ATIO4 E05M I Originator J. D. Barlow - R&ES Description During construction 40 HP motors containtne i Doctarent Evaluated PSO-83-084/TA 210842 space heaters were replaced with 50 HP motors that did l Deferences EPP not reauire space heaters. This chance occurred in FER system M 41. Containment Cooline System Fan Coil-Unfra. )! Attactments PSO-83-084/TA 810842 i 1 j I. san.1Y EVALUATIO! TECINICAL SPECIFICATIGIS A. O YES O NO
- 1. Inplementation or perfonnance of the action described in the evaluated doctment will i
require a change to the GGIS Unit One Technical Specifications. I Basis: j UNREVIR.'ID SAFTIY QUESTICN Impleentation or perfonnance of the action descrihowi in the evaluated document will: l B. O YIs O NO 1. increase the probability of occurrence of an accident previously evaluated in the i FSAR. I Basis: O YES O NO 2. incraa w the consequences of an accident previously evalusted in the FSAR. l Basis: i O YES O No 3. increase the prrhability of a Walfunction of equipcht anyurtant to safety previously evaluated in the FSAR. Basis: D YES O No 4. incra== the consequences at a malfunction of equipient invortant to safety l .previously evaluated in the FSAR. Basis: 1 i i l 1 1 1 III-16 1 8
O YES O NO 5. create the possibility of an accident of a different type than any already eval-uatal in the FSAR. Basis: O YES O NO 6. create the possibility of a malfunction of equipent inw tant to safety differ-r ent than previously evaluatal in the FSAR. Basis: O YES O NO 7. rachvw the nargin of safety as defined in the basis for any tecinical specifica-tion. Basis: II. DNIRCAMWTAL EVAI1ETICN ILVIBCEMAL PBundICN PIAN A. D YES O NO 1. will require a change in the Envircranental Protection Plan. Basis: Motors were replaced in an existing system. It was determined that the space heater reouirement was not necessarv. ConsequentIV nchance in the EPP is not necessag B. UNREVIBE DNIRCNMAL QUESTICN concerns a matter which may result in a significant increase in any adverse O YES O NO 1. envirorunental inpact previously evaluated in the Final Envirorunental Statment (FES) as nodified by the NIC staf f's testinony to the Atanic Safety and Licensing Board (ASIB), supplements to the FT:S, envirorsnental inpact appraisal, I or in any decisions of the ASIB. Basis: Existine system is beine updated. Any necessary review or evaluation was considered in the FES. O YES 0 NO 2. concens a significant change in ef fluents or power level (in accordana with 10CFR51.5 (b) (2)). Basis: This change will not generate effluents or power. III-17
e. O YES @ NO 3. concerns a matter not previously reviewed and evaluated in the Annamarif.s specified in B.I. above, which may have a significa t adverse envirormental spact. Basis: This is an existing system which was considered in the FES. fh r F--/z-Ar , aluated by/Date w. Reviews.d/ Approved: O q n pg S isor/Da Beviewed/ Approved: Manager /Date y i SAFEY AND LICENSING REVIDi Reviewed: Reviewed / Approved: Reviewed / Approved: Review mg Supervisor of Nuclear Manager of Safety and Engineer /Date Safety /Date Licensing /Date i RADIM&-ICAL & DNIRO91DirAL SERVICES REVIDi Reviewed: Reviewed / Approved: Reviewed / Approved: Beviewing Supervisor of Maruger of Radiological & Engineer /Date Divirornental Services /Date Envirossental Services /Date e III-18
GUeD WIF M1 M. MATIN LEIT GE I owes, Ests on causwrs i SAETlY MO DNIKEGENrAL EVAlllATIN EUM .q l i Description Desian error in virina for Foxboro 4 f Niginator J. D. Barlow - R&ES instruments nest for T48 system. Alterations will j Doctament Dpaluated PSO-83-098 #A 820138 correct errors to allow system testine while waitina Deferences EPP for desien change documents to be issued. 1 FER httactments PSO-83-098/TA 820138 j i f i I. SAFETI EVAlllATIGI 'ITONICAL SPBCIFICATIWS1. Implementation or pertan==nce of the action descriw in the evaluated docimien i
- l A. O YEs ONo require a change to the GGNS Unit One 'hx:hnical Specifications.
Basis: l Implanentation or performance of the action described in the evaluated doctament will: l UNREVIB E SAFTIT QUESTIW increase the probability of occurrence of an accident previously evaluated in the B. O ifES O NO 1. FSAR. i Basis: l increase the conseqiscius of an accidia t previously evaluhted in the FSAR. [ O YES O NO 2. Basis: i increase the preility of a salfunction of ee :-w.t i--grtant to safety I s I-O YES O no 3. i l previously evaluated in the FSAR. Basis: ie-the conseqt=us of a malfur.ction of wipient i=prtant to safety l O YES O No 4. previously evaluated in the FSAR. f Basis: l l l I l III-19
O YES O NO 5. create the possibility of an accident of a ditterent type than any already eval-uated in the FSAR. Basis: O YES O NO 6. create the possibility of a rnalfunction of equipnent inportant to safety differ-ent than previously evaluated in the FSAR. Basis: O YES O NO 7. rMa the wargin of safety as defined in the basis for any ta.iudcal specifica-tion. Basis: i II. DP/IRCNORAL EVAIEATICE ENIIONAL PBundICN FIAN A. O YES O NO 1. will require a change in the Envirersnental Protection Plan. Basis: Wirine error in original design is being corrected. Change will allow l system to function an originally intended. This system was considered in the development of the EPP. l I D. LNREVIB;ED DWIRCNDKAL CUESTICE O YES Q NO 1. concerns a matter which may result in a significant increase in any adverse envirorstental inpact previously evaluated in the Piral Envirormental Statment (FES) as modified by the NHC staff's testinony to the Atanic Safety and Licensing Board (ASla), supplenents to the FES, environmental impact appraisal, i or in any decisions of the ASla. Basis: Correctine a wiring design error in an existing system which was taken l into consideration in the FES. O YES @ NO 2. ooncerns a significant change in effluents or power level (in accordance with 10CFR51.5 (b) (2) ). Basis: This channe will not generate effluents or power. 111-20
o, O YES E) no 3. concerns a matter not previously reviewed and evaluated in the h = aries specified in B.l. above, which may have a significant adverse envirormental irrpact. Basis: System was considered in the FES. A / )c f-/2-f3 aluated by/Date a' Ileviewtxl/ Approved: h _M 9 -it-p 3 ~ isor/Date 9Vf42 14eviewed/ Approved: Manager /Date [ i l SAFETt AND LICENSDG REVIEW 4 I Heviewed: 34evi M /ApprDYed: Reviewed / Approved: Beviewirq Supervisor of Nuclear Manager of Safety and Engineer /Date Safety /Date Licensing /Date RADIGOGICAL & DNIIOMENTAL SERVICES REVIEW Deviewed: Daviewed/ Approved: Ineviewed/ Approved: Ikwiewing Supervisor of Manager of Radiological & Engineer /Date Divirornental Services /Date Envirumental Services /Date i l i I III-21
1 4 .r GRAPD GAP 3R.lCIIJR STATIO4 (EIT GE s CIAhES, '1TS15 OR DTERIft2.'rS SAIT!T AfD DNING8 ENTAL EVAulATIG4 EUM i Description Change will allow testing of the offgas l Originator -J. D. Barlow - R&ES Doctment Evaluated.PSO-83-100/TA 820152 svstem withnut anarofr<na hinw r= mna h. e r._ Th<- i Ihtferences EPP chance is for construction and nrannormefanal emerine. FER t Attachments PSO-83-100/TA 820152 i I i j I. SAFETt EVAU WrIOl l TECINICAL SPECIFICATIGIS l A. O YES 0 880
- 1. Implesmentation or perforence of the action described in the evaluated docssment will regture a change to the GGIS tlnit One Technical Specifications.
I Basis: I tion or perfonnance of the action described in the evaluated document will: B increase the probability of occurrence of an accident previously evaluated in the O YES O suo 1. l FSAR. i Basis: i O YES O too 2. incraa-the consequences of an accis.t previously evalusted in the f5AR. 1 t Basis: l 1 O YES O nao 3. increase the probability of a saltunction of equipment asportant to safety l previously evaluated in the f5AR. i Basis: I l O YES O pio 4. incr=a= the consequences of a malfunction of equipient 2avortant to safety 4 l previously evaluated in the FSAR. Basis: a I l III-22 ~
l* i O YIs O No 5. create the possibility of an accident of a different type than any already eval-uated in the FSAR. Basis: i O YES O No 6. create the possibility of a malfunction of equipment urportant to safety differ-ent than previously evaluated in the FSAR. I Basis: O YES O No 7. rar== the margin of safety as defined in the basis for any telmical specifica-tion. I Basis: i i I II. DNI1ONENTAL EVALLUCIN l HNIJOMNTAL PROTECTIN PUN A. O YES O NO 1. will require a change in the Enviavinatal Protection Plan. l Basis: This changeinvolves construction and preoperational testing of modifications 1 to an carnblished system. This system was considered in the develonment of the EPP. i B. WREVIB.TD DWIIONENTAL QJESTIN l O YES E} NO 1. concerns a matter which may result in a significant increase in any adverse envirornental inpact previously evaluated in the Firal Dwirornental Statasmant j (FES) as modified by the NIC staff's testimony to the Atcsaic Safety and Licensing Board (ASIB), supplements to the FES, envircreental utpact appraisal, j or in any decisions of the ASIB. j Basis: Testine an cristino system that was previousiv evaluated for environmental innact. O YES O NO 2. concerns a significant change in ef fluents or power level (in accordance with This change is for preoperational testing. There will not be a change i i in effluents nor will there be any cover zeneration. 1 1 x l i I l 1 III-23
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?. Si n an t f n =r 8-m o s oe fn m hi oe rr v z c eo n / 9 ri gr e eL ai 9-g nv e a an he r ~ n ME ts a ah ne e h M d t e iv /( e a d v D ~ t d o da / e D e r yb tt / e v p b r t o p an S ua E o a r A M l c F / s D p / i / p d ai O n e / w vf e t r A e r ei h au n t g d e n h l dg a e i a ni n t n w v as i S a e e M i R da d v e e e e t ev e d d R a we r D ia d e e vh i v v r / e s o o a s ry n r r e e a o p p l c ym c F p c i 4 l A A u v 2 sh s / / N r f e I d l uc a oi w u e f oS II ih w w oe vw t e e t rl e e i i ra oa r, a v v oD st pe m e e s/ in v r D R iy ve vt rm to i re er ob =f po a ur na l R;S a Si r. c v i n e I. g E t tB o d a l mn o e i i v d d e a d o D v d a r se R p I o p V r ni. A E p rfMi / R p ei s d A cc e S / ne s w E d op a e C e cs B i I w v V e e R i R E v 3 S eR LA M T e e F E t D t a N a D D O q/ O g/ R nr E r r. i I ie N wa N we en en M G D ii iivg vg en ei BD S I BE L I E A Y C M I
- d G
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i
- GRAPD CUIF DEJCIIAR STATICN tEIT GE i
OIAICES,1ESTS OR D}tADt2.*tS SAFTIT AIO DNIloeENTAL EVA113ATIO4 fuM s* (riginator J. D. Barlow - R&ES Descriptim Channe is nece== mrv to nrev.ne in.avore.ne j Doctament Evaluated PSO-83-101/TA 820153 starts on the acid tran=fer nn-a fnr eh em .e.- ~ l Ikeferences EPP l FER Attactanants PSO-83-101/TA 820153 i { I. san _TI EVAI11ATIGI l TECNICAL SPECIFICATICNS A.Om DNQ
- 1. Implementation or perra =ame of the action descriw in the evaluated docment will l
require a change to the GCMS Unit One Technical Specifications. i Basis: i LNREVID.'ED SAFT1Y QUESTION C. Implementatim or perfonnance of the actim described in the evaluated hmt will-l i O YES O No 1. increase the probability of nem rrence of an accident previously evaluated in the j rSAR. Basis: i i Om O No 2. increase the consequences of an accident previously evaluated in the f5AR. j I Basis: O YES O No 3. increase the prembility of a salfunction of equipment 2sportant to safety previously evaluated in the ISAR. I Basis: O YES O NO 4. increase the consequences of a malfunction of equipment 2mportant to safety previously evaluated in the FSAR. l Basis: l 4 I i L 1 111-25
l. 1 create the possibility of an accident of a ditferent type than any already eval-O YES O No 5. uated in the FSAR. Basis: O YES O No 6. create the possibility of a malfunction of equipent WM to safety differ-i ent than previously evaluated in the FSAR. Basis: 1 O YES O No 7. rarkw= the margin of safety as defined in the basis for any tw.-dcal specifica-tion. Basis: i i I ! II. DWIDCN4ENrJJL DTAIECICN EhVIIOMNTAL PRCFITCTIG4 PIJW l A. O YES E NO 1. will require a change in the Dwirorsnental Protection Plan. I Basis: NPDES Permit requirements have established monitoring for the SSW. l i Addit ional monitorine will not be necessarv. l o. uaav. ia.in InvuneewraL aussrIm O YIs E ND 1. concerns a matter dtich may result in a significant increase in any adverse envirormental appact previously evaluated in the Final Dwia%Ra1 Statssent (fYE) as undified by the NRC staf f's testipOny to the AtGRiC Safety and Licensing anard (ASIB), supplanents to the FTS, envizurunental impact appraisal, or in any decisions of the ASIE. Basis: Modifying an existing system which was considered in the FES. O YES E NO 2. concerns a significant change in ef fluents or power level (in e-rdern= with i 10CFR51.5 (b) (2)). Basis: This change will not generate effluents or power. I III-26 L
O YES [] NO 3. concerns a matter rot previously reviewed and evaluated in the Ann = artes specified in B.I. above, which may have a significant adverse envircemental Impact. Basis: SSW system was considered in the FES. m D ?-/2 8 l .e ,,1 aluated by/Date Reviewod/ Approved: O 1M Ct-n _.Q isor/Date Reviewed / Approved: Manager /Date [/ SAFm AND LICENSING REVIfW Reviewed: Reviewed / Approved: Reviewed / Approved: Review 2rq Supervisor of Nuclear Manager of Safety and Digineer/Date Safety /Date Licensing /Date RADIGIEICAL & DNIRCPMDrfAL SERVICES REVIIM Reviewed: Revie.ed/ Approved: Reviewed / Approved: Faniewing Supervisor of Manager of Radiological & Divirormental Services /Date Environmental Services /Date Digineer/Date III-27
CRMD CUIF PRJCIEJe STATICN LEIT GE QIAfCES, TESIS OR D}DtI2t2.TS SAFTIY MO DNIlO44 ENTAL D/A11]ATIO4 IUM Originator J. D. Earlov - R&ES Description Change is necessary to eliminate unnecessary Doczrent Evaluated PSO-63-103/TA 820175 trips of the offgas system by the radiation monitorine References EPP system. Fliminnees ciennic frne vndineinn manienrino FER which shur F060. F045. F140 ned nnen F119. AttactWents PSO-33-lO3/TA 820175 I. SAFITI DIAIIIATT.OI TTIJNICAL wtLinCATICNS A. O YES O NO
- 1. Inpleientation or perfonnance of the action described in the evaluated doctament will regtnre a change to the GGNS Unit One Technical Specifications.
Basis: UNWH2D SAFEN 07EICN Implenentation or perfonnance of the action descrihad in tie evaluated dOCLEhent will: D. O YES O NO 1. increase the prnhability of occurrence of an accident previously evaluated in the FSAR. Basis: O YES O NO 2. increaw the consequences of an accident previously evaluated in the TSAR. Basis: O YES O No 3. 2ncrease the preility of a malfunction of equir-rit wrtant to safety e previously evaluated in the FSAR. Basis: O YES O No 4. increase the consequences of a malfunction of equipient inportant to safety previously evaluated in the FSAR. Basis: III-28
l, O YES O No 5. create the possibility of an accident of a ditferent type than any already eval-uatal in the FSAR. Basis: O YES O No 6. create the possibility of a nelfunction of equipent wportant to safety dirrer-ent than previously evaluatal in the FSAR. I Basis-i O YEs O No 7. re the nargin of safety as defined in the basis for any technical specifica-i tion. Basis: II. DWINN1ENTIJL EVAIDATIN DWIIEYINTAL PPOITCTIN PIAN A. O YES S NO 1. will require a change in the Envirornental Protection Plan. Basis: Intent of system des.gn will not be compromised. Original design was considered in the development of the EPP. C. INL5VIH;ED DWIRQ4DTAL QUEErrIN l O YIs G No 1. concerns a matter which may result in a significant increase in any adverse envirornental inpact previously evaluated in the Final Dwirarmental Statment (ETS) as modified by the NRC staff's testinony to the Atmic Safety and 3 Licensing Board (ASIE), supplements to the FIS, envirornental upact appraisal, or in any decisions of the ASIB. Basis: Radiation impact was considered in the FES. l O YES @ No 2. concerns a significant change in etfluents or power level (in accordance with 10CFR51.5 (b) (2)). i l Basis: Neither effluents nor power will be generated by this change. I, l l l 1 I III-29
J 4 0 YES 3 NO 3. concerns a matter not previously reviewed and evaluated in the h e specified in B.I. above, which may have a significant adverse erwirormental 13' pact. Basis: Mattern pertaining to system N64 (offeas) were reviewed in the FES. f' 3 m sh P-n-P.r bEvaluatedtyf/Date ^- I Reviewud/ Approved: O 9 - l L -) S Supervisor /Date Reviewtsd/ Approved: k Marager/Date l Sum no ucoene mv1m Beviewed: Bevimed/ Approved: Reviewed / Approved: 1 Review 2ng SLpervisor of Nuclear I4anager of Safety and mgineer/Date Safety /Date Licensing /Date RADIowGICAL & DNIsomDerAL SEWICES REVIIM ] i l Reviewed: Revia-d/ Approved: Reviewed / Approved: Beviewing Supervisor of Malapr of Radiological 6 Engineer /Date Dvirarmental Services /Date Envirornental Services /Date i I i 1 I i I i I l III-30
5.5 - 55 & 1 QWD CCIF fn3I;dt STATIO4 LEIT OE r OAM, TESTS OR D}Ek1ML2.TS SMTIY AND DUDGMDfrAL LVAIEATICN ETAM [ d_(w/// Description 77/a,//[tsdede d O AM/77 APs ad/I* Originator DOCLEnent EvaTutad t1/Tek % lAfe.Ad$u'd rW(W.) J AHark_=.s / r Beierences fE2,. A PP Attachments p/ w,# _f 4 m ua r>tfbOQ/7/ I. SAFP!"? EVAIEATIGI l TEI3NICAL SPtunCATIQ;S
- 1. Impleentation or perfonnance of the action cescrilwl in the evaluated document will A. O YES O NO require a change to the GGNS Unit One 'Ibchnical Specificatiors.
1 Basis: l tr3D/ID5D SAETW Q.ESTION Implementation or perfonnance of the action described in tre evaluated doctment will: D. increase the probability of mrrence of an accident previously evaluated in the O YES O NO 1. FSAR. I Basis: I O YES O NO 2. increase the consequences of an accident previously evaluated in the FSAR. Basis: O YES O NO 3. increase the prhility of a nalfunction of equipnent nyortant to safety previously evaluated in the FSAR. Basis: 1 O YES O NO 4. increase the consequences of a malfunction of equiptent 2nportant to safety previously evaluated in the FSAR. Basis: l 3 i 4 111-31
O YES O NO 5. create the Fossibility of an accident of a different type than any already eval-uat4sl in the FSAR. Basis: O YES O NO 6. create the possibility of a malfunction of equagment asportant to safety differ-ent than previously evaluated in the FSAR. Basis: O YES O NO 7. rechace the sargin of safety as defined in the basis for any techrucal specifica-tion. Basis: II. DNIBCNENr;< DmTICN mv1BEmffAL PHO1TLTIN PUH A.O Yts E NO 1. will require a change in the Envirormental Protection Plan. Basis: D. IEREVIE2D DNINTAL QJESFFIN O YES g NO 1. concerns a matter tddch may result in a significant increase in any adverse envirorumental impact previously evaluated in the Firal Envirormental Statement (FES) as endified by the NRC staff's testimony to the Ataalc Safety and Licensing Board (ASIB), supplesments to the FES, envirt:sumental aspect appraisal, or in any decisions of the Asta. Basis: O YES S NO 2. concerns a significant change in effluents or power level (in accordance with 10CFR51.5 (b) (2)). Basis: O e III-32
D YES S NO 3. concerns a iratter not previously reviewed and evaluatxd in the &n _nts specified in D.I. above, Weh any have a significant achwrse envirormental inpact. Basis: .O 9b2ll3 Evaluated by/Date Reviewod/ Approved: Su isor/ -- Beviewed/ Approved: f fM Manager /Date Q SAFEN R;D LICD3I?C REVIDi i Beviewed: Bevi d / Approved: Beviewed/ Approval: levieware Supervisor of Nuclear Manager of Safety and Engineer /Date Safety /Date Licensing / Data i RADIowGICAL & DNIJOMENTAL SERVICES REVIDi Bevised: 9-anReviM/ Approved: Nb 7!/2 h 1 Beviewed/ Approved: h Beviewing Supervisor of Manager of BadAflogical & Dv3 neer/Date Dwironmental Services /Date Envirornental %Ivices/Date i i e 111-33
Nuclest flent Engin22 ring Grcnd Gulf Nucicnr Section DCP _ 89/n e/p Rav. A#, c., g.. 3 / 44 S.ff. } ' e,,- / Environmental Review Evaluation i 1. Concerns a. matter which may result in a significant increase in any adverse environmental impact previously evaluated in the Final En-vironmental Statement (FES) as modified by the NRC staff's testimony to the Atomic Safety and Licensing Board (ASLB), supplements to the FES, environmental impact appraisal, or any decisions of the ASLB7 re v. ewed ,i +4 e. Yes )( No, Because: 7L 3 s,3 T1:s c%, ,.,w.,$el fe,*er b f%e. Fe8 sl'FES. t revisas. Also sffneed etw yWe. N/ M l &*#1. 2. Concerns a significant change in effluents or power level (in accor-dance with 10 CFR 51.5 (b)(2) or (3)? Yes )( No. Because: e U/.,*8 eolu.-es See nr,f, ' g,,, f,, )Yo eA%;s. .s c b ;e,/ e4..,j e 3, 3. Concerns a matter not previously reviewed and evaluated in the documents specified in question number 3 above, which may have a significant ad-verse environmental impact? Yes J( No, Because: lairs lle v;ewed FcA i FCs WillachangeinEnvironmentalProtectionPla[n(AppendixBtoFacility ( 4. License No. NPF-13) be required? Yes No. 5. Wi 1 a change in the Final Environmental Report be required? Yes No. 3/pp/g 3 / Date Environmental Reviewer: f V f I e D 9 111-34
iO W Nuc1ccr Plent Enginscring Gr:nd Gulf Nuc1ccr Stction DCP 1//c ^o.3 R:v. og t Environmental Review Evaluatien t 1. Concerns a matter which may result in a significant increase in any adverse envir.onmental impact previously evaluated in the Final En-vironmental Statement (FES) as modified by the NRC staff's testimony to the Atomic Safety and Licensing Board (ASLB), supplements to the FES, environmental impact appraisal, or any decisions of the ASLB7 Yes I No Because: Tt..'s ,44.8,- m/Jo/ be
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che & (We.y/ eaf4d as Ie $ *'s DCP .s de a a.J + A de aw n 2. Cencerns a significant change in effluents or power level (in accor-dance with 10 CFn $1.5 (b)(2) or (3)? Yes Y No. Because: 'Yk C. $"*d IS Mt~ dsya &,,e & g 's ; ,s ri ve'enh e d iA h FcT, p Concerns a matter not previously reviewed and evaluated in the documents 3. specified in question number 3 above, which may have a significant ad-verse environmental impact? Yes No, Because: w.s k.ewed al-ga re g.jpg mj,4,, 59,, 4 Will a change in Environmental Protection Pla (Appendix B to Facility License No. NPF-13) be required? Yes ho. g Will a change in the Final Environmental Report be required? _ Yes 5. _ No. l / Date_ c2f ,3 Environmental Reviewert ,~ 7, 111-35 l J
I, Nuclear Plent Engineering Grcnd Gulf Nucicer Station DCP QJ/4(,o7 Rev. C O Environmental Review Evaluation 4 1. Concerns a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the Final En-vironmental Statement (FES) as modified by the NRC staff's testimony to the Atomic Safety and Licensing Beard (ASLB), supplements to the FES, environmental impact appraisal, or any decisions of the ASLB? Yes )( No, Because: T4. s DCP ,.'// - e //s J d%35-yaeafu +'/a os M., 5%s p e e v. *n des ynej bf
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b~ b - d doIe ee e e 2. C neerns a significant ch ge in effluents or cover level (in accor-dance with 10 CFR 51.5 (b)(2) or (3)? Yes )( No. B ause: h/n'nY TAe oneacay ak fle o o.'ll not' ~efbrei pe pteJ o noi eV He s.'fe k= day be caus e Tech Spe e-prec e ds o ra c re che-f e d. TA s
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t.ja. t;e <H, J.-(feagaf.hC.!**><eu enl ed e /~W will ** t be y Concerns a matter not previously reviewed and evaluated in the documents 3. specified in question number 3 above, which may have a significant ad---J 73e - verse environmental impact? Yes 4 No Because: loj.,,i J p>fffuesdg d, gg. paar or yen caacub'a b en ftom -> ;// of ak y e. h., Ht paev 4 ev./~.kJ. Will a ghange in Environmental Protection Plan (Appendix B to Facility 4 License No. NPF-13) be required? Yes[ No. Will a change in the Final Environmental Report be required? [ Yes 5. No. 74,g gja y'a, wl// be ,e ads du,3 ff e, g, f,,,y tdam 3laje Ch h. desip cieny. Date 8 1/,(3 Environmental Reviewer ( t 111-36 .... ~. - -... L I
( __ D 1G pi k[ A SSISSIPPl POWER & LIGHT CO Helping Build Mississippi P. O. B O X 164 0. J A C K S O N, MIS SIS SIP Pl 3 9 2 0 5 j p { *. A 1 27, 1984 j JAMES P. MCG AUGHY. JR. u g y",s W f/M8 vsCE Passicasef U. S. Nuclear Regulatary Commission J Region II l 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30303 Attentiion: Mr. J. P. O'Reilly, Regional Administrator
Dear Mr. O'Reilly:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 f License No. NPF-3 File: 0260/15322 Annual Environmental Operating Report for 1983 AECM-84/0263 In accordance with Grand Gulf Nuclear Station's (CGNS) Environmental Protection Program, we are enclosing one copy of the Annual Environmental Operating Report for the period January 1, 1983 through December 31, 1983. Questions concerning the technical content of this report should be referred to Dr. L. R. McKay, Manager of Radiological & Environmental Services, at (601) 969-2432. / Yours truly, h b I JPM:aly Attachments cc: Mr. J. B. Richard (w/a) Mr. R. B. McGehee (w/o) Mr. N. S. Reynolds (w/o) Mr. G. B. Taylor (w/o) 0 MM Mr. Richard C. DeYoung, Director (w/a) d *. h 6 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Document Control Desk (w/18) J ,i U. S. Nuclear Regulatory Commission I Washington, D. C. 20555 ggC@l t Member Middle South Utilities System g /g j}}