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- ,* ,n; y DISCUSSION AND CONCLUSIONS-BY THE U.S. ATOMIC ENERGY COMMISSION DIVISIONS OF RADIOLOGICAL AND ENVIRONMENTAL PROTECTION
.AND REACTOR LICENSING l
PURSUANT TO APPENDIX D OF 10'CFR PART 50' l
SUPPORTINU THE ISSUANCE OF LICENSES I TO COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS AND ELECTRIC COMPANY AUTHORIZING 20 PERCENT OPERATION OF THE QUAD-CITIES STATION UNITS'l AND 2 DOCKET NOSL 50-25/4 AND 50-265 1
Issued: January 24, 1972 8709250138 870921 PDR- FOIA
-NENZ87-111 PDR
TABLE OF CONTENTS Page
- 1. INTRODUCTION............................................. 1
- 11. STATEMENT OF ENVIRONMENTAL CONSIDERATIONS . . . . . . . . . . . . . . . . A
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A. DESCRIPTION OF SITE AND ENVIRONS..................... 4
- 1. The Site......................................... 4
- 2. The Near-Site Aquatic Environment................ 5
- a. River Flow and Temperature................... 5
- b. Water Quality................................ 5 I c. Aquatic Ecology.............................. 10 1
B. DESCRIPTION OF STATI0N............................... 15
- 1. Reactor and Steam-Electric Systems............... 15
- 2. Effluent Systems................................. 15
- a. Heat Removal System.......................... 15
- b. Chemical and Sani t ary Was tes . . . . . . . . . . . . . . . . . 20
- c. Radioactive Wastes........................... 23 C. ENVIRONMENTAL IMPACT OF STATION OPERATION............ 25
- 1. Hea t Removal Sys tem E f fe c ts . . . . . . . . . . . . . . . . . . . . . . 25 2 Chemical Effects................................. 31
- 3. Radiological Effects............................. 34
- 4. Effects of Accidental Releases................... 36 III. FORECLOSURE OF ALTERNATIVES IN FACILITY DESIGN OR
.0PERATION................................................ 45 IV. E FF E CT S O F D E LAY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 V. CONCLUSIONS.............................................. 49 RE F E R E N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 B I B L I OG RAP HY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54
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l l 1. I NTRODUCT I ON The Quad-Cities Station (station) is a nuclear power generating faellity jointly owned by the Commonwealth Edison Company and the Iown-lllinois Gas and Electric Company (applicants). Applications by these two companies for operating licenses, which would authorize I the operation of Units 1 and 2 of the station at 2,511 megawatts thermal (MWt) each, are presently pending before the Atomic Energy Commission (Connission). On March 16, 1971, a notice of the pro- .
posed issuance of these operating licenses was published in the Fede ral Regis ter (36 FR 5008) . The notice offered an opportunity for a hearing, but there were no requests for a hearing.
On July 12, 1971, notice of the availability of the Final Detalled Statement on Environmental Considerations for Quad-Cities '
Station Units 1 and 2, prepared by'the AEC Division of Radiological i' nnd Environmental Protection, was published in the Federal Register (16 FR 13699). The detailed statement considered the environmental aspects associated with full-power operation of the station. It was prepared in accordance with the then current requirements of Appendix D to Title 10 Code of Federal Regulations Part 50 (10 CFR i Part 50) published' on December 4,1970, which implements the National Environmental Policy Act of 1969 (NEPA).
On August 25, 1971, the AEC regulatory staf f (staf f) completed ,
its review of the application for licenses and issued its Safety Evaluation in which it concluded that there was reasonable assurance that Units 1 and 2 of the station could each be operated up to full .
power (2,511 MWt) without endangering the health and safety of the public. However, on September 9,1971 the Commission revised Appendix D to 10 CFR Part 50 to comply with the decision of the Court of Appeals for the District of Columbia circuit in Calvert Cil f f s Coordinating Commi ttee et al. vs. the Atomic Energy Commission et al. The revised NEPA regulations provided inter alla for a supplemental NEPA review for facilities such as the Quad Cities Units.
A supplemental NEPA environmental review of the operation of Units 1 and 2 at full power (including preparation of a section 102(2)(C)
Impact statement) is presently in progress but has not as yet been completed in accordance with the requirements of Appendix D as re-vised September 9, 1971.
Appendix D provides a procedure in Section D.3 for issuance of an operating license authorizing the loading of fuel in the reactor core and limited operation of the facility. This procedure l may be applied to applications for an operating license for a. nuclear facility for which the Commission published a notice of opportunity for henring prior to October 31, 1971 and no hearing was requested.
The limited license may be issued by the Commission, pending the ,
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completion of an ongoing NEPA environmental review of a full-power license application, upon a showing that such licensing a: tion will q not have a significant adverse impact on the quality o f the environ- i ment, or af ter considering and balancing the factors described in j i;ection D.2 of Appendix D, and upon the Commission'= aaking appro-priate findings on the matters specified in 10 CFR Part 50.5 7 (a) .
On July 16, 1971, the applicants requested that the Commission j lasue an operating license for Unit 1 authorizing the loading of
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fuel in the reactor core and other activi. ties which require opera- l tion of Unit I not in excess of one percent (25 MWt) of full power. j in accordance with the provisions of Section D.3 of Appendix D of l 10 CPR Part 50, the low-power license requested by the applicants was ]
issued on October 1, 1971. The basis for that action was set forth i in a public document entitled, " Dis'cussion and Findings by the Divi-slon of Reactor Licensing, U.S. Atomic Energy Commission, Pursuant to Appendix D of 10 CFR Part 50, Supporting the Issuance of an Operating License to Commonwealth Edison Company and Iowa-Illinois ')
Gas and Electric Company Authorizing the Loading of Fuel and Opera- '
tion not in Excess of 25 MWt, Quad-Cities Station Unit 1, Docket No. 50-254."
On October 12, 1971(1) , the applicants requested the Commission, in accordance with the provisions of Section D.3 of Appendix D, to authorize limited power operation of Units 1 and 2 during the ongoing supplemental NEPA environmental review of their application for operation of both units at full power. Specifically, the applicants requested the Commission to issue an amendment to Operating License DPR-29 for Unit 1 and to issue an operating license for Unit 2 autho-rizing (1) fuel loading in Unit 2, (2) conduct of all necessary testing of each unit up to and including its full rated power, and (3) operation of the two units up to an aggregate level of 809 mega-watts electrical (equivalent to 2,511 MWt) until March 15, 1972. On November 18, 1971(2), the request was amended to extend the period of limi ted operation until such time as a full-power operating license in received. The applicants stated that the station will operate during the testing period at an average of less than 20 per-cent of full capacity (1,004 MWt of the station's full capacity of 5,022 MWt). The applicants submitted further that their request meets either of the two standards established by Section D.3 (summarized above).
A determination has not yet been made concerning the applicants' request to operate both units up to an aggregate total of 809 MWe (50 percent of the station capacity). The AEC regulatory staf f has l
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completed an environmental review pertaining to the fuel loading, !
testing and operation of each unit up to 20 percent ~(502 MWt) oof rated '
reactor power. Under Section D.3 of Appendix D, operation at any level j above 20 percent prior to completion of a full NEPA review may not be g authorized except upon specific prior approval of the Commissioners. }
4 l I This report.is based.upon data from the applicants and other. sources, )
including state and federal agencies, and the evaluation of the data by j the AEC regulatory staff. The following analysis and conclusions are limited to - the .20 percent- case' and cover the period ending June 1,1972, the date when' the final impact statement, based on the ongoing full NEPA review, is expected to be completed.
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- 11. STATEMENT OF ENVIRONMENTAL CONSIDERATIONS f
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l A wide range of factors was considered in this environmental ;
review. Because the station is essentially completed, the major '
environmental impacts of concern are those due to the operation of the once-through condenser cooling system and the radioactive effluents. i Thus, the entrainment effects from condenser operation, and the thermal, chemical, and radioactive discharges are the major points of this consideration for limited operation of each unit at 20 percent (502 MWt), of rated power pending completion of the full NEPA review on . lune 1, 1972. The discussion that follows includes a description of the f acility, the impact of its ef fluents, alternatives to the pro-posed action, and the effects of delay in facility operation upon the public i n t e re s t ., in accordance with the Commission's regulations in Sect lon D.2 of Appendix D to 10 CFR Part 50.
A. DESCRIPTION OF SITE AND ENVIRONS
- 1. The Site The quad-Cities Station is located in Rock Island County on the cast bank of the Mississippi River, about 3 miles north of Cordova, Illinois, and about 20 miles northeast of the Quad Cities-Bettendorf area. The Quad Cities are Davenport, Iowa; Rock Island, Moline and East Moline, Illinois. Bettendorf, Iowa, is an adjacent city to the northeast of the Quad Cities.
The 404-acre site is flat, with a grade level about 9 feet above the maximum recorded flood stage. Surrounding land areas are largely in agricultural use, with an industrial park directly north of the station. There are industrial concentrations in the city of Clinton, Iowa, 7 miles northeast of the station, and in the Quad Ci t ics-Be ttendorf area.
The geographical location of the station with respect to the upper Mississippi River system is shown on Fig. 1. Moline, Illinois, is I,ocated on the nap, and the station location is indicated south of Clinton, Iowa, on the Illinois side of the river. The location j of the site with respect to the locks and dams of the Mississippi River is shown in Fig. 2. Sections of river between dams are referred to as " pools" which are numbered consecutively southward from St.
Anthony Falls, Minnesota. Distances along the river are designated as " river miles" measured northward f rom the confluence of the Ohio River. The station is located about midway in Pool 14 at river mile 506.5, and at standard river elevation 572.0 feet. Pool 14 is approximately 25 miles long and 0.5 to 1.5 miles wide, i
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- 2. The Near-Site Aquatic Environment Mississippi River flow is controlled below flood stage throughout ita length by a series of locks and dams so that its channels are available for transportation. The river water in Pool 14 1s a source of municipal and industrial water and is also used for commercial and sport fishing. River shore development within a 25-mile radius of the station consists of residences, industrial plants, a wildlife refuge and recreational sites,
- n. River Flow and Temperature Mississippi River flows by month in Pool 14 are presented in Table 1. High flows result in the spring from melted snow in the Mississippi headwaters. Maximum flow usually occurs in April, the rec-ord being 307,000 cubic feet per second (cfs) on April 28, 1965. The lowest flows are observed in winter, usually in December or January.
The record low was 6,500 cfs during December 25 to 27, 1933.
1 Monthly maximum, average maximum and average water tem-peratures, during the period 1962-70, at the Davenport, Iowa, water plant are shown in Table 2. Similar temperature data for Pool 14 are not available. However, the temperatures in Pool 15 at Daven-port, are believed to be Iowa, 22ofmiles representative thosedownstream in Pool 14. from the station,(5,6)
Measurements in Pool 14 have Indicated temperatures up to 88'F in shallow backwater areas,
- b. Water Quality Although municipal and industrial waste discharge from the Clinton, Iowa area have occasionally resulted in excessive slime growths in the slough areas in the vicinity of the station, Pool 14 is a relatively unpolluted environment. Limited water quality analyses conducted by the applicants' consultant, Industrial Bio-Test Laboratories, i Inc. (Bio-Test)(5,bl, indicates evidence of nutrient enrichment pri-marily from agricultural runoff, but no large-scale pollution. Bio-Test studies during 1968-70 indicate that temperature, dissolved oxygen (DO) and ammonia nitrogen values in Pool 14 are less than maximum limits established by the Illinois Sanitary Water Board. gg As discussed infra, additional water quality data, including specific element analysis performed and evaluated by Bio-Test, suggest that suf ficient baseline information is available to determine any future water quality degradation.
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TABLE 1 Monthly Mississippi River. Flows
'7-day Low Flow Hean* 1-Day'90% Low Flow '" Once in 10 yrs..
Month efs efs cfs Jan. 25,800 17,000 15,900 Feb. 26,900. 16,800 15,800 Mdr. 49,000 24,800 20,500 Ap r'. . 94,000- .43,000 32,100 May 74,000 33,000- 24,000 June 62,000 26,200. 19,700-
.luly [52,200 20,500- 17,300
- Aur,. 35,000 17,800 15,700 Sept. 34,000 18,300 16,300 10ct. '34,300 18,000 15,400 Nov. 33,700 '
20,000 17,400 Dec. 27,000 17,500 16,100 Only the record since 1938, for the present system of locks and dams, is considered here. - These flows are measured at. Clinton, Iowa. ' Actual
. flows at the plant are about 1 percent higher, due to confluence of the Wapsipinicon River, b
The one-dny low flow which is exceeded 90 percent of the time for the period since 1938.
"The lowest daily flow since 1938 was approximately 11,000 cfs.
d I The low flow for a period of 7 consecutive days, the lowest such value expected on a frequency of once in 10 years; statistic for the period since 1938.
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' . TABLE 2 ,
Monthly , Maximum, Average Maximum and Average Water Temperature,.
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. 196'2-70, at Davenport, Iowa' Water Plant (4)
Maximum . Average Maximum- Average Month
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. Inn ua ry 36~ 35 33 34 -33 ;{
Ecbruary 38 March 54 44 37 April 63 56 49
-May 73 70 62
. lune 81 79 73
.luly. 85 81 78 i
August 83 81 76
~ September 80 75 69 69 64 57 October i
55 50 44 November 42 39 34 December
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- c. Aquatic Ecology Pool 14 encompasses a variety of aqdatic habitats and ,
communities In the vicinity of the station. A recent report (7) !
covers the general history and provides a description of aquatic ;
habitats from Hastings, Minnesota to Alton, Illinois. Major Missi- !
ssippi River habitats near the station are the channel habitat, off-channel habitat, near-shore habitat, running slough habitat and dead ;
slough habitat. These habitats are chiefly defined by location, depth, !
bottom material and vegetation.
The main channel in the vicinity of the station is char-acterized by a scoured sand bottom and the highest current velocity.
Directly below the station in the main channel border are several small islands with adjacent, relatively quiet, shallow water areas.
Further downstream, across from the main channel, are extensive areas of side channel and slough habitats.
The applicants initiated preoperational environmental studies for the station in 1968. A preliminary study (8) has been followed by a continuing physical, chemical, and biological moni-Loring program conducted by Bio-Test. !
Bio-Tes t 's firs t report was based on samples collected ;
at 22 locations in different habitats of Pool 14. from river mile 1 507.6 to river mile 501.3, during the months of August and November j 1969, and April 1970. Measurements were made of coliform bacteria j concentrations, phytoplankton, periphyton, and benthos populations, }
and various physical and chemical parameters. The results indicate !
that the benthos population density (animals per square meter) is ]
relatively low in the main channel, whereas population density and i species diversity is highest on rocky bottoms in areas of reduced l current. The number of benthic animals in the vicinity of the station is dominated by insects, with fewer crustaceans, oligochaetes, and molluscs. The phytoplankton population (cells per liter) is dominated by diatoms. Blue-green algae never formed a major part of the phyto-plankton.
i Bio-Test's second report (6) is based on physical, chemical, '
and biological data collected at 35 stations in July and October 1970. l The study covered an area in Pool 14 f rom 2 miles above the station !
to 13 miles downstream. This report is more comprehensive than the first in that additional water quality parameters were measured and the biological work included fish sampling and analysis of fish stomach contents as well as more intensive observations of phytoplank-ton, periphyton, and benthos populations. The report includes no zooplankton data but indicates that zooplankton and aquatic insects i
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predominate in the stomachs of small fish. Diatoms comprised at least 80 percent of the total phytoplankton cell concentrations during both .fuly and October 1970. No excessive growths of attached algae {
were reported. The benthos population appeared to be dominated by )
pollution-tolerant tubificid worms at a few stations but generally consisted of organisms such as burrowing mayfly nymphs that are con- l sidered to be indicative of relatively unpolluted water.
Other biological studies ~ have established the existence of relatively diverse and productive plankton, periphyton, and benthos communities supporting significant commercial and sport fisheries in ;
Pool 14 and other pools in the Upper Mississippi River.
The locks and dams on the Mississippi River system effectively isolate adult fish populations except during periods of flood. Ups tre am migrations of species are hampered, whereas downstream drift occurs between pools. Serious ecological disturbances in one pool could possibly cause subsequent changes in the ecology of downstream pools, particularly since downstream drift is a major mechanism in energy t rans fer and dispersal of organisms. Although ecological changes i resulting from locks and dams and industrialization have occurred, there remains a wide diversity of fish species in the river. In Pool 14 alone, 64 species have been identified. Recent surveys , however, have collected fewer fish species, suggesting that the diversity may have decreased in recent. years. ,
A considerable amount of sport and commercial fishing occurs in Pool 14, about equal in size of catch by pounds per acre to that of adjacent pools. The combined value of tg fishing was conserva-tively estimated at about $150,000 for 1968 , of which about one-third was commercial. It was estimated that 20,000 anglers spent 105,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at Pool 14 in 1967 to catch 104,750 fish. The 16-year (1953-68) average annual commercial catch was 318,650 pounds.
Primary sport species in Pool 14 in approximate order of fisherman preference are bluegill and crappie, cat fish, and sauger and walleye (Tabic 3). Certain sport species, such as the northern pike , yellow perch, walleye and sauger occur in limited numbers; they are more numerous further upstream (e.g. , Pool 4) . These species are apparently not well adapted to conditions in Pool 14 and are not as numerous there, although they do appear in pools as far downstream as Pool 18. Thus, there appears to be a succession of )
species composition occurring in a downstream direction as a result of changing environmental conditions.
Commercial catches (Table 4) are primarily composed of carp, buffalo, catfish, drum, and sturgeon, with catfish being the preferred species (highest market price).
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l The upper Mississippi River Vildlife and Fish Refuge, adminis-tered by the Bureau of Sport Fisheries and Wildlife, is located on the west bank of the river opposite the site. The Savannah-Clinton District of the refuge, which includes the northern half of Pool 14, 1 reported peak populations of 60,500 ducks and 2,500 geese 13 1965. ;
These populations were present in this district of the refuge a suffi-cient period of time to accumulate more than 2.5 million waterfowl-use days. A significant amount of food consumed by waterfowl using the re f uge is produced in the marshes along the river.
On the basis of the Bio-Test studies '
, it appears that the channel habitat in Pool 14 is the least productive in numbers of organisms and .does not serve as a major feeding or spawning area.
The of f-channel and slack water habitats show greater productivity j and probably provide a more favorable environment for reproduction !
and feeding. These habitats would be especially favorable to fish l because of the abundance of prey organisms, relatively weak river I currents, variable water depth and suf ficient cover for protection against predation. For the majority of fish species occurring in Pool 14, spawning b.egins in early spring and extends into summer and probably occurs to the greatest extent in the slack water areas. i Specific spawning times and locationa (e.g., the exact month and !
slack water site) for the fish species in this pool are not well known.
t DESCRIPTION OF THE STATION B. !
- 1. Reactor and Steam-Electric System The station has two forced-circulation boiling-water reactors and two turbine generators supplied by the General Electric Company.
Each reactor has a rated thermal output of 2.511 MWt and each turbine generator a net electrieni capacity of 809 MWe.
The reactor fuel consists of slightly enriched (2 or 3 per-cent by weight) uranium oxide pellets sealed in Zircalloy-2 tubes.
Water is both the moderator and coolant. Two recirenlation loops force reactor water through jet pumps up through the reactor core, where steam is generated at about 1,000 psi. The saturated steam passes through pipes to the turbine, where some of the thermal energy is converted to mechanical energy and, in turn, by means of the generator, to electrical energy. Exhaust steam is condensed to water 1 which is pumped through demineralizers back to the reactor vessel.
The condenser cooling water is in a separate system which does not come in contact with the reactor water steam.
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l; TABLE'3 Sport Catch Statistics'- Pools. 4,. 13, 14, 18 ' 13 } '
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% Total ' Catch. : ( ) : indicates ' fishermanL preference rank '
l Species- Pool . 4 ~ (1967)' Pool 13 (1967): (Pool 14. (1956-58) Pool .18 (1967) ,
Walleye.and . . .
Sa'uge r 33.3 (1) 1.9 (3).. 8.7.(3) 6.3'(3)~ I-Carp 0.2~ 2~3
. -2.2 3.0 Catfish -6.4 4.9.(2)L 6.8 (2) 40.5 (1)
Whitobass ; 7.0 .9 . 8 9.4'- . 8.9 , ;
Drum - 2.8 12.4. 9.9 12.3 Largemouth; bass :1.1 1. 9 .. 1. 6 , . '1.5 Bluegill-c rappie_ 44.3 (2) 57.4 (1)- :48.5 (1). .24.1 (2) I Yellow perch ~1.4 0.8. 0 .0 -
liullhead 0.2. . 8.3 7.8 3.2' Northern Pike 2.1 (3) 0.1 0- 0 'I Other 1.2 0.2 5.1 .,0.2.
-100.0 100.0.. 100.0 100.0.
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l TABLE 4 Commercial Fishery Statistics - Pools 14, 15, 19(
Total Catch (1bs) in 1968
,spe c ie s Pool 14 Pool 15 Pool 19 r
)- Carp 80,000 17,000 382,000 Buffalo 129,000 19,000 197,000 Cat fish 78,000 11,000 149,000 Drum 34,000 9,000 120,000
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- 2. Effluent Systems
- a. llent Removal Systems Approximately one-third of the heat generated by the station is converted to electricity. The remaining two-thirds is released to the environment by way of Mississippi River water which is passed through the station's condensers in a once-through cooling system and back to the river. Full power operation of both generating units at a total of 5,022 MWt will cause a 23'F temperature rise in 2,270 cfs of Mississippi River water, the maximum flow through the con-densers. At lower station power levels the temperature rise is proportionately lower (e.g., at 50 percent of full power, about 11.5'F temperature rise; at 20 percent of full power, about 4.6'F temperature rise).
(1) Condenser Cooling Water Intake The supply of cooling water for the condcasers is obtained through a short inlet canal with a routh about 180 feet wide and 12 feet deep. At the maximum flow rate of 2,270 cfs, the intake velocity is calculated to be about 1 foot per second. A flonting boom which extends 33 inches beneath the surface is pro-vided at the mouth of the canal to deflect floating material. It may also help to reduce the entrainment of floating fish eggs, g larvae and fry.
Between the floating boom and the condensers there is a row of vertical metal bars, commonly referred to as a trash rack. The bars are spaced 2-1/2 inches apart and extend from about 20 feet above the waterline to the bottom of the intake canal. The purpose of the trash rack is to collect and remove large pieces of debris that get past the floating boom.
Each condenser pump is further protected by a set of traveling screens with a 3/8-inch mesh. These screens change positions at preset time intervals or when activated by a buildup of pressure due to the collection of debris. The screens collect t he smaller bits of debris that get through the trash racks. They also prevent organisms larger than the mesh from passing through the pumps and condensers.
(2) Condenser j
Six pumps take the water from the intake canal and l force it through the secondary side of the condensers at 2,270 cfs.
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The cx'haust steam from.the turbines flows through the primary side of the condenser where it.is condensed back to water. This water is returned to-the-reactor.to be reheated. At 'the same time, the heat released by the ;
steam. heats the cooling water to 'a maximum of 23'F above the ambient tem-perature of the river. The. negative pressure in the~ turbine and in the primary side of the condenser assures that leakage in the condenser will not release radioactivity from the turbine to the river.
i The condenser ' tubes'are cleaned by periodically injecting sodium hypochlorite into the water.as it enters the condenser.
Details'of the sodium hypochlorite injection are given in the section on chemical and sanitary wastes.
,(3) Condenser Cooling Water Discharge System
~
' Cooling water from the condensers goes to the cooling !
water discharge canal, where it falls over, a 3 foot weir and then passes to the river through a canal'600 feet long and 75 feet wide.
The original plan called for this warmed water to be dispersed by a wing dam located immediately downstream from the discharge canal.
Upon further consideration, however, the applicants found this plan to be inadequate and it was discarded.
Af ter conducting studies of alternate cooling methods which included cants proposed ponds,system"(
a " jet-diffuser spray can g and cooling towers, the appli-
, Briefly, this system is designed to disperse the warmed water through a series of jets in a large pipe laid across the Mississippi River. At the present time, the Illinois pollution Control Board has accepted
- this ' system in principle (34) ,but the Iowa Water Pollution Control Commission has not. In any case, the jet diffuser system will require 8 or 9 months to construct and thus cannot be made .>perable before about September 1972.
- The Illinois Pollution Control Board granted the applicants a permit to operate the station at 50 percent of full power which extends for two years from November 15, 1971. This permit grants a temperature variance from the proposed State standards (35) until April 1, 1972 In essence this will permit operation at 50 percent of full power until April 1,1972.
After this date supplemental cooling will be required unless the power Icvel is lowered appropriately, since the proposed State standards require alimi{1 5'F after a 600 foot mixing zone. The Applicant's supplemental report provides modeling test data which indicate that operation at 50 l' percent of full power will violate the proposed State standards if the
" side jet" discharge system is the only cooling system used.
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When the applicants applied for an interim license for operation up to 50 percent of full power, an interim cooling water discharge system was proposed which consisted of narrowing the extt of the discharge canal to achieve a maximum amount of jet entrainment. This is referred to as the " necked-down, s discharge system (l) or the " side jet" discharge system ( gfe jet"
, which is considered by the applicants to be the most effective inter 1m method for reducing the area of heated water in the river.
According to the temperature rise contours derived from modeling experiments related.to 50 percent operation and full condenser cooling water flow (2,270 cfs), a river flow above 11.000 cfs forces the warm water against the east shore of the river and around the islands immediately downstream f rom the station. The temperature rise contour of water 5.8'F above ambient for the 50 percent case will likely extend a short distance beyond the island group immediately downst ream f rom the s tation (Fig. 3) . Below these islands, the main channel moves over to the east bank of the river (Fig. 4). We assume that the warm water will dissipate in this channel a short distance heyond. The area of warm water defined by the 5.8'F temperature rise contour is about 0.3 square-miles (1/5 mile by 1-1/2 miles long). This is approximately 5 percent of the estimated total area in the lower half of Pool 14 (1/2 mile wide by 12 miles long). Furthermore, the island area immediately dounstream from the site amounts to 10 percent or less of the total island area in the 5 mile section below the station.
The staff has estimated that operation of the station at 20 percent of full power, and full condenser cooling water flow (2,270 cfs), will result in similar warm water patterns surrounding the islands immediately below the site. This estimate indicates that the temperature rise contour which defines the warm water area will be more nearly 2.3*F as compared to the 5.8'F contour for 50 percent operation.
- b. Chemical and Sanitary Wastes Small amounts of chemicals from regenerating the demine r.ali ze rs (other than those used in liquid-radwaste treatment) and cleaning the condensers will be intermittently discharged to the ri ve r . Before they are discharged, all such aqueous effluents will be sampled and chemically analyzed for compliance with rules and regula-tions of the State of 1111nois.(35)
The regeneration of demineralized resins will result in an aggregate total of 2 ppm of sulfuric acid, magnesium sulfate, and calcium sulfate in the station condenser discharge for about I hour every 2 or 3 days. This concentration is based on a l
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lon'g-term average plant watac requirement of 600,000 to 900,000 gall cantg)perminute. Extreme conditions pointed out by the appli-could increase the concentration to 6 ppm.
Sodium hypochlorite solution is added to the condenser '
cooling water three times per day in 40-minute periods to reduce growth of bacteria and other microorganisms in the piping and the condensers. Present practice is to add the solution to each of the four condenser half-units (one at a time for 10 minutes each) every
' 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Ten gallons per minute of 15 percent sodium hypochlorite solution are injected with 525 cfs of water. This water is subse-quently diluted in the discharge canal and discharged into the river.
The concentration of chlorine (from sodium hypochlorite) in the cooling water of the condenser-half being treated is calculated by the staff, from the applicants' procedures, to be 3.7 ppm. The quantity was chosen by experience to yield a " typical" value of about 0.5' ppm (range 0.2to0.7)"fg) chlorine"*aftermixingwiththeunchlorinated half-condenser stream . The rate of addition will be modified in the light of experience to maintain this level of free chlorine, according to present plans.
In normal operation, the water from the condenser being treated will be diluted 2 to 1 upon mixing with the output of the other condenser, and will then flow into the discharge system.
Typically,'a substantial reduction in residual chlorine content can be expected to occur prior to discharge due to the reaction of chlorine with oxidizable material in the unchlorinated water. This reduction might be variable with time and with chlorine levels. Recent measurements during unheated operations have shown chlorine levels at the sampling station (perhaps two-thirds of the way down the discharge canal) of about 20 percent of the amount at the condenser center line during experiments at unusually high-free chlorine levels and at higher temperatures, the resultant greater excess of chlorine demand ** (over the free chlorine *
- The useful chlorine is present in the forms of the hypochlorite ion and hypochlorous acid, with the relative quantities determined by the pH of the water (1:1 at pH 7.5). The concentration of molecular chlorine in water that would have the same chlorine oxiding capacity as is present in the OCI - and HOCI is called the "f ree chlorine" level.
The 1 ppm free-chlorine half-condenser effluent will contain 0.5 ppm CL in the form of OCI- or HOCI, since in these forms the chlorine has twice the oxidizing capacity per gram as elemental chlorine (valence changes from 1 to -1 during reaction versus the change from 0 to -1). ;
the amount of free and combined chlorine that will react with oxidizable !
substances in the water. The substances that provide the chlorine demand vary from case to case, and the rates of oxidation of these substances vary over a considerable range.
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level) and the higher reaction rates can be expected to lead to greater chlorine reduction before discharge to the river.
In addition to reacting with the substances comprising the chlorine demand, free chlorine also reacts quickly (at the river water pil) with any dissolved ammonia present to form chloramine.
Typical river water levels of ammonia nitrogen (ca. 0.2 ppm) are stoichiometrically equivalent to 0.5 ppm chlorine in hypochloric acid (ur 1.0 ppm free chlorine); there is an excess above that required to react with the 0.25 ppm diluted free chlorine present at the beginning of the discharge canal. The extent of the reaction will largely depend upon the relative concentrations of ammonia and free chlorine, since the equilibrium constant for the reaction be-tween these substances favors essentially complete conversion to notstable{9eg3.theriverpH.
monochlora7 l The higher Any chloramine formed chloramines arewith will then react reportedly the chlorine demand cons tituents. Since this reaction is less than that reducing the free chlorine, quantitative estimation of the degree to which all residual chlorine (the sum of free chlorine and combined chlorine) will have dissipated before discharge to the river is difficult.
These considerations suggest the expected residual chlorine concentration in the coolant' discharged to the river to be substantially less than 0.25 ppm in a flow of 2,270 cfs. This concen-tration will be present, under normal full condenser flow, during three 40-minute periods per day. Dilution factors in the river will range from 7 at a minimum river flow of 15,400 cfs to 20 at the average flow rate of 46,800 cfs. Thus, the expected residual chlorine con-centrations diffused in the river during periods of chlorination will be substantially less than either 0.04 ppm during minimum flow periods or 0.01 ppm during average flow.
An additional amount of chlorine will be added to the discharge canal in the service water discharge. The service water is chlorinated for two 20 minute periods per day, during which the residual chlorine in the 67 cfs (30,000 gpm) discharge from the service water unit will be about 0.5 ppm (again expected to vary in the range 0.2 to 0. 7 ppm). When diluted in the condenser discharge cann1 at full operation, the service water contribution will be about 0.02 ppm during the chlorination periods, before natural decay as discussed above. The possible chlorine contribution to the river during a 20-minute period is about one-tenth that of the condenser chlorination.
- Lowes t average 7 day rate in 10 year period, see Table 1, pg. 8..
The station has an operable sewage treatment plant which is des igned for 15,000 gallons of sewage ef fluent per day. The plant is licenned by the State of Illinois and is under the supervision of a lleensed sewnge-treatment operator. It is currently operating at. about 5,000 gallons per day. The effluent is chlorinated according to the State standards.
- c. Radioactive Wastes In the operation of nuclear power reactors, radioactive material is produced by fission and by neutron-activation reactions of metals and material in the reactor system. Small amounts of gaseous and liquid radioactive wastes enter the effluent streams, which are nonitored and processed within the plant to minimize the radioactive nuclides that will ultimately be released to the atmosphere and the Mississippi River at low concentrations under controlled conditions.
The radioactivity that may be released during operation of both Units 1 and 2 at 20 percent of full power will be as low as practicable and in accordance with the Commission's regulations, as set forth in 10 CFR l' art 20 and 10 CFR Part 50.
(1) Caseous Wastes Present System During power operation of the facility, radioactive noterials released to the atmosphere in gaseous effluents (which arise from the non-condensable gases lef t af ter steam condensation from the turbine generator) include fission product noble gases (krypton and xenon), activated argon and nitrogen, halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products. Fission products are released to the coolant and carried to the turbine by the steam if defects occur in the fuel clad or if uranium is present as an impurity in the clad itself.
The systems of treatment of radioactive gaseous waste currently installed at the station are described in the Final Salety Analysis Report (19) and in the applicants ' Environmental Report.
The applicants' response of May 11,1971 (see ref 15, Appendix I) to l comments on the draf t Environmental Statement describes the system i proposed for future installation to maintain gaseous ef fluents at low levels during extended full power operation.
The major source of gaseous waste activity will be the condenser air eje: tor effluent. Other sources include the turbine building exhaust, recctor building exhaust, drywell purge and release
-~ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l from the gland seal off-gas system. Prior to release, the gases from the main' condenser air ejector are delayed in a 30 minute holdup pipe (to allow decay of activity of short-lived radioactive noble gases), filtered through high efficiency particulate filters and then discharged to the atmosphere through a 310-foot stack.
Turbine building ventilation exhaust contains low concentrations of activity, primarily from steam system leakage, and is discharged to atmosphere without treatment through the main stack. Like-wise reactor building ventilation exhaust contributes little activity, particularly at the 20 percent power level, and is discharged without treatment to the building vent stack. Drywell gases are normally purged and exhausted from the reactor building vent stack but can be processed through the standby gas treatment system if the activity level is high.
The small quantity of radioactive gases released by way of the gland seal off-gas system is delayed for about 2 minutes to allow decay of the major activation gases (N-16 and 0-19) prior to release through the main stack. All sources of gaseous waste are continuously monitored to assure that effluent releases are within applicable standards.
On the basis of operating experience with power reactors of similar design, it is expected that the off-gas system described above will keep release of gaseous radioactive wastes within small fractions of the limits specified in 10 CFR Part 20 at 20 percent power. In order to reduce these levels to the lowest practicable during extended full power operation which may entail local failures of fuel clad integrity, the applicants will install additional gaseous-holdup equipment. A modifi-cation to the present system will allow recombination of the hydrogen i and oxygen formed in the reactor coolant, a condenser to remove much of the water vapor, and an 8-bed charcoal system to provide additional re-tention time for the krypton and xenon and to provide additional absorption for particulate matter. These modifications will be operable within 2-1/2 years and should further reduce offsite exposures from gaseous radioactive releases from the condenser air ejector by a factor of about 40.
At power levels of 20 percent or less in each unit with the presently installed gaseous waste system, discharges will be at low levels since little fuel failure is expected at this low power and little diffusion of fission products from the fuel pellets will take place at low operating temperatures. On the basis of startup experience at other operating plants with similar gaseous waste systems, we anticipate activity releases at the rate of less than 2,000 pCi/sec from each unit l or a total of less than 4,000 pCi/sec from the station, primarily noble l
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releases at the rate of less than 0.25 Ci/'Some m. We anticipate iodines ma j from the stack and less 'than 0.01 Ci/ year year of I-131 from both units '
reactor building vent at 20 percent power. from both units from the
'(2) Liquid Wastes tanks, and floor drains are collected, filtered-Liquid radioactive wast prior to discharge to the Mississippi River. , and temporarily stored water'from the primary reactor system will be demineraliDuring normal opera in the condensate storage tank for reuse in the reactor zed and placed from the future off-gas system will also be placed in .
Theco d condensate n ensate storage.
regenerated but.are disposed of as solid radwaste. Spent resins and thus less addition of activity to thequid environmentregene wastes ting resins system were used in the same manner , than if a regen, era-plant process.
Both the condensate-demineralized .
system water cleanup system are designed to assure requisite purit or-levels to permit recycling of most of the plant waterythat radionuclides. and activity contains water that goes through~the liquid-radwaste systemRecycling is of fsite are from floor drains and sumps, laboratory , decontamina-drainsThe tion solutions (very inf requently), and laundry wast es.
and sampling, River. these vastes are diluted and discharged After filtration into the Mi ssissippi equipment will be installed in the liquid waste system g which discharges December to the Mississippi River to less than 12 curie 3, 1973. .
reduce s per year after presently very. low levels.installed liquid radwaste system,sodischarges be at will al plants at the ratewith similar floor drain systems, we yanticipate of' about
, ng releases activitOn curies per year from the station, primarilys activated corro i3 cu
- 1. css than 4 curies of tritium are also anticipated to be on products.
released.
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'(3) Solid Wastes
~ Solid wastes from the reactor operation are composites of'apent resins from the liquid-radwaste demineralized and precipitates are insoluble matter that comes from filters or is washed into the con-
_densate pha'se separator. The spent resins and the slurry-from the' condensate phase separator are dewatered in a centrifuge. . Separated liquid; waste returns to the' liquid-radwaste stream, whereas the solids are' mixed with concrete in drums for ' shipment offsite - to a licensed burial ground. The' drums will be shipped by vehicles with suitable shleiding in compliance with AEC and DOT regulations.
_ C. ENVIRONMENTAL IMPACT OF STATION OPERATION
- 1. IIeat Removal System Effects Ja.- Condenser Cooling Water Intake The floating. barrier at the mouth of the intake canal presents-a retarding influence on fish eggs and larvae as well as floating debris.
We have reviewed the applicants data as well as searched for additional data elsewhere but have found that there is no evidence available that indicates the effectiveness of the barrier in reducing the flow of fish eggs and larvae into the intake canal, thus protecting them from being entrained in the condenser cooling channel. Some rather large tree branches were observed on the trash racks during the site visit
- which indicated that the barrier is not completely effective in stopping large pieces of debris.
With all six intake pumps operating at full capacity (2,270 cra), we have calculated the linear velocity of the water at the floating barrier to be about 1 foot per second (fps). Since this velocity is nearly the same as current speeds in the river, all but immature fish and plankton will be able to enter and leave the intake canal at will.
Some fish and other organisms may enter the intake canal and establish semi-permanent populations. The canal may be an attractive habitat for a variety of reasons, i.e. , available food source, spawning sites and
- A site visit was made by AEC environmental protection staf f members to L aid in their independent review of the station and its effects. The site visit included detailed observation of the site environs, inspec-tion of the station, and discussions with the applicants' environmental consultants and staff, i
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protective cover. However, should concentrations develop to the extent
'that high densities result and persist over time, damage to fish may occur due to increased incidence of disease. A possibility exists that walleye and sauger, which are believed to spawn predominately in the rocky areas near the locks and dams, may utilize the rock-lined intake canal for spawning. Such an occurrence would probably result in entrainment of a large fraction of the annual spawn.
Trash rack bars, spaced 2-1/2 inches apart and extending to the bottom of the intake canal, are the first obstacle between the floating barrier at the entrance of the intake canal and the condensers. Such a mesh size will certainly permit the passage of small organisms. Small fish can pass between the bars and reach the traveling screens.
A set of traveling screens with 3/8 inch mesh protect the entrance to the pumps and condensers. These screens are normally stationary nnd change position at preset time intervals or when activated by buildup of pressure due to the collection of debris, Plankton will pass through these screens, as will fish eggs and larvae. The traveling acreens are not expected to mechanically damage the larger fish that swim through the trash rocks because the screens are not in continuous motion and the water velocity is still low at this point (we calculate about 1-1/2 fps).
There will be entrainment of phytoplankton, zooplankton and immature stages of fish. However, since plankton concentrations in the vicinity of the stations are not well known, and since the actual spawning locations have not been well identified, the percentage of aquatic life that will be entrained is impossible to estimate. Obviously, if the .
majority of the spawning adults of a particular fish species spawn 1mmediately above or within the intake canal, the reproductive success of that species will be reduced. The staff has taken account of these considerations in its overall assessment (see below).
In summary, the non-motile organisms (those which either do not swim or cannot overcome the current) which are small enough to pass through the traveling screens will be entrained. Those non-motile organisms which are too large for the screens vill be trapped on the screens and lost. Motile organisms, mostly fish, may be attracted to the area between the trash rack and screens and congregate in large numbers.
Such congregations could be detrimental to the fish (e.g., increased disease susceptibility) and to the operation of the station.
These problems will occur to some unknown extent, and deter-mination of the degree of occurrence and the need for remedial action, if called for, will be part of the environmental surveillance program.
- - _ _ _ - _ - _ _ - - _ d
- c. Condenser Cooling Water Discharge Although the mouth of the discharge canal has been necked-down to create a current-of 4.5 feet per'second, many species of fish will be able'to overcome the current and enter the canal. The velocity within the canal proper (2.5 fps)' is also well within the sustained swimming ability of many species. (23) Their presence in the canal makes them subject to the potential thermal and chlorine effects.
' Fish will be attracted to the canal or heated downstream areas when. temperatures there are preferable to ambient conditions, Each species typically has a preferred optimum and upper lethal temperature limit' based primarily on past acc11mation experience. Table 5 summarizes the laboratory and field works of several investigators relative to the temperature tolerances of several species, some of which are. common in
' Pool 14.
1 During periods of low river temperatures, fish that are at-tracted to the discharge canal or immediately below will become acclimated to warmer than' ambient river temperatures (see Table 2 on page 9). In the case of station shutdown, these fish will be exposed to a rapid return to amblent temperatures and will experier.ce cold shock, which may be a potentially greater threat to fish than increased temperature. Mortality resulting from'the inability of fish to acclimate o tempera tures in natural systems has been reported. 26yapidly , lowering
.Although the extrapolation of laboratory bioassay experiments to field conditions is somewhat speculative, the marked temperature ranges between acclimated and lower temperature limits in Table 5 suggest that a sudden decrease of 4.6*F would not cause any large scale fish mortality.
The heated discharge from the canal is likely to affect certain benthic species such as mayfly and stonefly nymphs and caddisfly larvae, and may also the mixing zone affect additional of the plankton, discharge. fish Cout ant (20,gggsand and larva other forms(24,26) workers within have reported the thermal effects observed in discharge canals and their near envitons for a number of operating plants. The most prominent effects noted were seasonal changes in animal diversity and total number of organisms present. At several stations during the summer months, animal diversity and numbers were reduced, indicating thermal stress in the immediate discharge area. During winter at these stations, diversity and numbers of organisms increased. Phytoplankton primary production has also been shown to be af fected by an increase in water temperature. (26) Depending on the ambient water temperature and other factors, production can be either increased or decreased.
The studies mentioned above show localized damage. No wide-spread changes of the nature described have been observed that clearly I
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i Indiente point sources of heat or brief chlorination: as the cause. Based on these data, nny of these localized effects obserred at the station will be minimal because of the relatively low temperature of the discharge water compared to ambient in Pool 14.
The canal discharge will result in a portion of the immediate downstream surface area being warmed. However, 'the temperature increarns in the pool downstream will be less than those occurring naturally as a result of daily (diurnal) fluctuations.
Downstream areas that will experience temperature rises consist primarily of the main channel and a small area of islands which comprises only 5 to 10 percent of the total downstream island and slough area and less than 5 percent of the total dow Although this Island area has been suggested (gstream habitat in Pool 14.7) to be a ma and residence, no evidence of these uses exists.
We have concluded that the small temperature elevations that wl11 occur over these islands and main channci (less than 4.6*F at 20 percent power) will not cause thermal fish kills based on our evaluation of the available data (compare Tables 2 on page 9 and 5 on page 28). Ex-amination of Table 2 indicates that the average tergerature of Pool 14 could be raised by 7 to 8'F during the summer without exceeding the temperatures that have occurred naturally. The " average maximum" column shows that a rise of 2 to 4*F could occur during summer without exceeding maximum ambient temperatures. An unlikely addition of 5'F to the maximum recorded tempera-tures would result in localized temperatures which do not exceed the upper thermal limits of the major species present in Pool 14 (Table 5). However, if such localized temperatures are not preferable te fish, the option of ;
retreat is available to them. Mount, et. al. (27) have suggested that damage {
(i.e. reduced reproductive success measured by occurrence of spawning, J percent of fertile eggs and percent normal larvae produced) to the walleye j and sauger could occur in the winter as a result cf increased water tem-peratures. Their results with yullow perch indicate a decrease in
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reproductive success at 43*F (35 percent fertile eggs and 31 percent normal larvae) compared to 39'F (70 percent fertile eggs and 53 percent normal l l
larvae). At temperatures greater than 43*F reprodue:ive success continued I to decrease. We have carefully examined this data la regard to its l applicability to Pool 14 and the 20 percent operatico under consideration.
l In this connection account must be taken of several factors: (1) the i
application of their experimental results to fish in pool 14 represents l an extrapolation from the laboratory to Pool 14 and a further extrapolation
} from yellcw perch to walleye and sauger; (2) the results of Mount et. al.
l apply to a 4*F temperature change while the temperature change around the
} islands below the station at 20 percent of full power will be appreciably j
less than 4*F; and (3) even assuming that there is a 50 percent reduction l
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a in fertile eggs spawned by some species in the immediate downstream island ]<
areas,. there is no evidence (see above) that this will. affect the ecological stability of Pool 14. These factors, as well as the extent of the total area'affected (as discussed above), indicate that the warm water J (resulting from station generation) around.the downstream islands will not have a measureable effect on the overall fish population of Pool 14 due to
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a decrease in normal reproduction of fish in that area.
The effects of small downstream temperature increases on other river biota will be minimal. Effects on phytoplankton are not likely to j be observed in terms of a reduction in primary production several hundred
' feet downstream. . Benthic populations will not be exposed to increased temperatures to. any extent since the heated water will be primarily a surface to mid-depth phenomenon. Slight' alterations in the hatching time of insect larvae could occur in the immediate area of the disc gg)but
.the major portions of the downstream areas will be unaffected.
In summary, there are several potential adverse efrects that could be caused by the Heat Removal System: .the congregation of fish in the intake canal and behind the trash rack; the degree of impingement and damaging of the congregated fish, if any, against the traveling screens; the combined chemical-mechanical-thermal ef fects on the organisms carried through the condenser; the congregation of fish in the discharge canal; the effects of chlorine residual and warm water on the fish in the discharge canal and aquatic biota in the canal outfall; and the effects of chlorine residual and warm water on the aquatic biota downstream.
Our conclusions are, as previously indicated, that while there may be adverse impacts on the quality of the environment resulting from some or all of these effects, the technical evidence cited in the discusoion indicates that these impacts .would not be substantial, that the af fected area will be small (i.e. at most, the area of the downstream islands, about 0.3 square mile), and that there will be no detectable' damage beyond the small affected area. Since, however, the extent of these impacts cannot be definitely determined at this time, the applicant will be re-quired to expand his environmental surveillance program to include an assessment of the areas of potential effects identified in the preceding paragraph.
- 2. Chemical Effects _
' The chemical effluents are those resulting from the regeneration of I the demineralized, chlorination from condenser cleaning and service water, and sewage. These have been described in section II.B. (pp . 20-22) .
" - - - ~ - - - - - . _ . _ . _ _ _ _ _ , _ _
4.
Table 6 Chemical Content 'of Water (Parts ,Per Million)
Quad Cities Drinking. Water (33) in 100.
Condenser Pool (5,6) Recommended Concentration in Limits of Largest Cities Discharge - (a) -14 Drinking Water = . Median- Maximum so g . <2 28 250(32) -26 .572
. Mg <2. 16 -50(33) 6 120 Ca !39 75 I33) 26 145
_< 2 -
(a)- These concentrations of the listed chemicals.are discharged for.
short fractions of the day and are diluted by the River.
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L of chlorinated streams with larger volumes of unchlorinated watar in the !
discharge system, lead to little or no chlorine discharge to the rivers-and lakes providing the cooling water. However, there are no known published data'which definitely establish this position. Because of the uncertainty j involved and the potential adverse effects, the applicant will be required {
to monitor the residual chlorine and aquatic biota for chlorine effects so 1 that' remedial action may be taken early if necessary. !
An additional amputt of chlorine will be added to the discharge canal in the service vacer discharge. As indicated in Section II B 2, the service water. is chlorinated for two 20-minute periods per day, during I which the residual chlorine in the 67 cfs (30,000 gpm) discharge from the service water unit will be about 0.5 ppm (like the condenser cooling water, it is expected to vary in the range 0.2 to 0.7 ppm). Possible contribution to the river, during chlorination, is about one-tenth that of the condenser chlorination. This is not expected to add a measurable amount to the chlorine released from the condenser cleaning. In any event, it will also be included in the discharge water that is monitored.
The station has an operable sewage treatment plant which provides primary and secondary t.reatment. The maximum amount of- effluent is 0.3 cfs.
This is chlorinated to less than 1 ppm by State regulation, but the small amount of total effluent (0.3 cfs compared to 2,270 cfs) is unlikely to be a noticeable source of adverse effects. The plant is licensed by the State of Illinois and is under the supervision of a licensed sewage-treatment operator.
Based on the foregoing, we have concluded that there is not likely I
to be an adverse effect on the quality of the environment due to chemical effluents from operation of the station. ;
- 3. Radiological Effects l The staff estimate of the exposure that may be incurred by the general public from plant operation under the proposed license is based on operation of each unit at 20 percent power.
(a) Exposure from Radioactive Materials Released to the Atmosphere
~
The radioactive materials released to the atmosphere in gaseous effluents include the fission product noble gases (krypton and xenon), halogens (mostly iodines) and particulate material including both fission products and activated corrosion products.
The concentration of radioactive materials in the environment depends on the meteorological conditions during the period of release.
a
t Release rate limits are defined by determining the average concentrations and dose rates to be expected at various locations outside the plant area where public access is not controlled by the applicant. The maximum release rate limit is established in accordance with 10 CFR Part 20. Conditions will be included in the Operating License to require the licensee to keep Jevels of radioactivity in effluents as low as practicable in accordance with 10 CFR Part 50.36a.
The maximum site release rate limit for noble gases for the station based on annual average meteorology has been determined to be 0.4 curie per second. This release rate would limit the annual exposure out- i doors at any location on the site boundary to not more than 500 millirems l per year.
1 Actual release rates will be substantially less than the maxi-mum allowable release rates and are dependent on fuel element performance.
Operation at 20 percent power is not expected to result in any significant fuel element failures. The actual release rate with new fuel is not expected to exceed about one percent of the maximum release rate limit. Under these conditions, the maximum exposure rate outdoors at the site boundary is expected to be no larger than 5 millirems per year. Actual exposures to individuals offsite, taking into account the distance individuals live from the site boundary and shiciding from living part-time indoors, would not exceed 2.5 millirems per year.
The dose from iodine in the thyroid of a child was calculated to be about 0.5 mrem per year by assuming an intake of one liter of milk per day produced by cows grazing at the site of maximum deposition for the three months of spring, t I
In order to reduce the levels of gaseous radioactivity to the lowest practicable IcVel, assuming that some fue.1 element f ailures will occur in the future at power levels higher than 20 percent, the Commission has informed the applicants that it will be necessary to install additional ,
gaseous holdup equipment in the station. The applicants plan a modification l' of the of fgas system, to be coapleted within 2-1/2 years. This modification will include on each unit a recombiner, a condenser, and an 8-charcoal-bed treatment system.
(b) Exposures from Radioactivity Released in Liquid Effluents It is estimated, from staff calculations based on experience with similar operating reactors, that the total quantity of radioactivity in liquid ef fluents will be less than 6 curies per year of primarily cor-rosion products. The expected annual avera e concentration in the i MississippiRiverisexpectedtobe2x10gO pC1/cc or less. j 1
i I
Below the station outfall, the annual dose to individuals who use the Mississippi River as their sole source of drinking water would be about 0.0003 mrem. The dose to an individual from consumption of 50 gm of fish per day (40 lbs per year) would amount to about 0.003 mrem per year.
(c) Doses to the Regional Population In 1963, the total fish cat Iowa, IllinoisandMissouriwas9.3x10ghfromthehussissippiRiverfor lbs. This amount of fish would represent a potential dose from the Quad-Cities' liquid effluents of 1 man-rem if consumed. The dose to the population within a 50-mile radius of the plant from drinking Mississippi River water will be about 0.2 man-rem, while the dose from gaseous effluents will be about 3 man-rem. Thus, based on our conservative estimates, the total man-rem dose from all pathways to the 600,000 persons who live within a 50-mile radius of the plant would be about 4 man-rem per year if the station is operated at 20 percent of full power.
By comparison, the natural background dose of about 100 mrem per year per person results in an annual total of 60,000 man-rem for this same population.
(d) Radiation to Other Species The average annual dose to fish, invertebrates, and plants living in the discharge canal would be less than 100 mrem per year. There is no evidence that dose rates of this magnitude will cause any detectable harm to these aquatic organisms.
(e) Conclusion We therefore conclude that radioactive gaseous and liquid ef fluents resulting from operation at 20 percent of unit power are expected to be well within 10 CFR Part 20 and Technical Specification limits. In addition, we have concluded that operation of the facility will contribute I only an extremely small increment to the dose that the area residents receive from natural background. Since fluctuations of the background dose may be expected to exceed this small increment, the dose will be immeasurable in itself and will constitute no meaningful risk.
- 4. Effects of Accident Releases With each unit operating at 20 percent of rated power, the AEC j staf f believes the probability of an accident in the station that could I have significant adverse effects is extremely small. This low probability results from conservatism in the design of the nuclear steam supply system, the reactor protection system and the engineered safety features that are ;
included in the plant, as well as the reduced power operating level. The l potential offsite consequences that could occur in the unlikely event of a
major' dent have been shown in the Quad-Citie Final Safety Analysis Report and the AEC staff's Safety Evaluation 31) to be well within the guf!eline values established by the AEC regulations for the evaluation i of power reactor sites when calculated by the very conservative methods used in such evaluations.
The environmental consequences of postulated accidents ranging from trivial to major have been evaluated for operation of each unit at 20 percent rated power. In making these evaluations, the guidance pre-sented in the Commission document
- entitled, " Scope of Applicants' Environmental Reports with Respect to Transportation, Transmission Lines, and Accidents," was followed. This document identified the nine classes of accidents shown in Table 7. In general, accidents in the high consequence end of the spectrum have a low occurrence rate, while those on the low consequence end of the spectrum have a higher occurrence rate. In contrast to the highly conservative assumptions and calculations used for safety evaluations, environmental consequences are determined in this report using assumptions as realistic as the state of technology permits. The staff's evaluation of these consequences in terms of population dose is shown in Tabic 8.
1he environmental consequences of Class 1 and 2 events were evalu-ated by the staff and have been found to have trivial consequences.
Furthermore, occurrences of Class 9 accidents are extremely unlikely in operation at 100 percent power.(31) They are even less likely at 20 percent ,
of power. In addition, defense in depth (multiple physical barriers);
quality assurance of design, manufacture, and . operation; continued sur-veillance and testing; and conservative design are all applied to provide and maintain the required high degree of assurance that potential accidents in this class are, and will remain, sufficiently remote in probability of occurrence that the environmental risk is extremely low.
- Enclosure in the letter f rom P.. L. Price to applicants dated September 3, 1971. .
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TABLE 8 l
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QUAD-CITIES NUCLEAR POWER STATION (UNITS 1 & 2) AT 20% POWER l
SUMMARY
OF RADIOLOGICAL CONSEQUENCES OF POSTULATED ACCIDENTS l DETERMINED BY THE A.' E. C.
Estimated Dose Estimated Fraction of to Population in-10 CFR Part 20 Limit at 50 mile Radius,- l Site Boundary"f man-rem Cinen Even t_ -
1.0 -Trivial incidents b/ b/
2.0 Small releases outside containment b/ b/
3.0 .Radweste system' failures 3,1 Equipment leakage or malfunction- .002 0.13 3.2. Release of liquid waste storage tank contents 0.02 0.5 3.3 Release of liquid waste storage Neg. Neg.
tank contents
.0 Fission products to primary system 4.1 Fuel cladding defects b/ b/
Of f-design transients that 0.007 0.17 4.2
- 5. 0 Fission products to primary and secondary systems (PWR) N . A. - N.A.-
6.0 Refueling accidents
-Fuel bundle drop 'O 0.01 6.1 Heavy object drop onto fuel in core ~0 0.011 6.2 7.0 Spent fuel handling accident 7.1 Fuel assembly drop in fuel storege
'O 0.01 pool
-0 0.004 7.2- Heavy object drop onto fuel rack 0.05 0.12 7.3 Fuel cask drop al Represents the calculated whole body dose as a fraction of 500 mrem (or the l' quivalent dose to organ). '
b) These releases will be comparable to the design objective indicated in the proposed Appendix I to 10 CFR Part 50 for routine ef fluents (i.e. , 5 mrem /yr to an individual f rom all sources).
j
Events included in Class 3 through 8 are considered in the appli-cants' Safety Analysis Report and our Safety Evaluation. These events, especially those in Class 8, are used together with highly conserva-tive assumptions and the design . basis events to establish the per-formance requirements of engineered safety features. But these highly conservative assumptions and calculations are not suitable for environmental risk evaluation. The probabilities and potential consequences of events in these classes have therefore been reevalu-ated on a realistic basis.
In evaluating these accidents, an important consideration is that each fac Zity will be operated at a fraction of full power. At low power levels, the potential consequences of accidents (e.g., the number of curies of radioactivity that could be released) are much less than at full power. As shown in Table 9, at 20 percent of full power and during typical operation (TO), the maximum fuel temperature is approximately 860'F (vs. 3470'F at full power) and the fuel rod heat transfer performance (average power per unit length) is 2.7 kW/f t (vs.13.4 kW/f t at full power).
TABLE 9 CORE THERMAL CHARACTERISTICS AT 20 PERCENT OF FULL POWER LEVEL OPERATION CORE PARAMETER BOL TO EC 1**
Maximum Power / Unit Length (kW/f t) 2.6 2.7 3.4 Power Density (kW/ liter) 6.0 5.2 7.9 Maximum Fuel Rod Volumetric Average Temperature. 'F 800 860 1010 _
Percent of. Fission Cases ,
Released from Fuel Pellets into Fuel Pin Cap * <0.01 0.01 1
- APED-5756, " Analytic Methods for Evaluating the Radiological Aspects of the General Electric Boiling Water Reactor," dated March 1969.
- BOL - Beginning of core life (Q4WD/T fuel exposure)
TO - Typical operation (7,350 MWD /T fuel exposure)
EC 1 - End of Cycle 1, Design Basis (11,650 MWD /T fuel exposure)
1 Under the above conditions, the probability of failures of the ' l
, fuel cladding either in normal operation or as the result of an '
accident is greatly reduced. In addition, the fuel would be operating much of the time at lower temperatures than for full power and end of ,
cycle 1, Design Basis (EC 1), conditions. Since the diffusion of '
fission products through the UO9 fuel matrix into the gap between the fuel pellets and the fuel eIement cladding is strongly dependent upon the operating temperature, the fission products contained within the gap (and thus available for release in the event of cladding i failure) will be less than 1 percent of that at full power. This '
combination of conditions (i.e. , few, if any, cladding failures and j low gap activity) means that the radioactive inventory within the '
main coolant system and in the radioactive waste systems will be very small. It will be due almost entirely to induced radioactivity of corrosion products. The corrosion resistance of the stainless steel systems involved will assure that this inventory is small. 1 As a result, this staff evaluation of all accidents in Classes 3, '
4, and 5 which involve releases of radioactivity from the radio-active waste system and/or the main coolant system indicated that the potential offsite radiological consequences are insignificant.
It is not anticipated that any irradiated fuel will be handled during the period of limited operat1on. However, if it is, the staff evaluation of the potential consequences of an accident during such handling (Class 6 and 7) indicates that these consequences would also be insignificant. The only radioactivity that could be released in such an accident would be the radioactivity that had previously been released from the UO, fuel into the fuel element gap, and this has been found to be small for the reasons discussed in the previous paragraph. When this source term is used in conjunction with realis-tic evaluations of the effects of decontamination from the water and steam within which the irradiated fuel elements are always submerged, the confinement and filtration systems provided, and meteorological diffusion factors, the calculated potential offsite radiological doses from these classes of accidents are less than one millirem to the whole body and the thyroid. These doses were, the re-fore, also found to be insignificant.
Class 8 events, which are considered in the applicants' Safety Analysis Report and the staff's Safety Evaluation, are used together with highly conservative assumptions as the design-basis events to establish the performance requirements for engineered safety features.
The highly conservative assumptions and calculations legitimately used for safety evaluations are not suitable for environmental risk
- - - - - - - - - - -------____a
3 s'1 Y> t 1 .,/ .
- 44 :-
evaluation'because the probability of oc'currence is so low for the
-unfavorable combination of circumstances used. 'For this reason, Class 8 events are evaluated. realistically and.would have'conse-quences predictedLin this way that are far less severe than'those i
given for hy)sameeventadescribedinSection'4.0ofourSafety<
Evaluation 3 . For example, the staff evaluation..of environmental effects.of.a. Class 8 event, assuming a postulated' loss-of-coolant accident, results in a calculated'2-hour' thyroid dose at the site boundary,of less than 1 rem, in contrast.to the 150. rem given in' n Table 4.0 of'our Safety Evaluation. -
- )
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It is therefore concluded.that no' accident during the limited' .
operations up to 20' percent of rated power would result in an ,
' adverse radiological impact on the environment. -
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c III. FORECLOSURE OF ALTERNATIVES IN FACILITY DESICN OR OPERATION The station has already been constructed on a particular site. Cons e-quently, there are ro reasonable or practical alternatives as to plant type or location. ..,
< Major changee in the conditiok of the station which could result from
' .authorii z ng t he operat ion of Units 1 end 2 up to 20 percent of full power would, for the period involved, be the discharge effluents, the consumption of enriched uranium and the production of small quantities of fission products.
However, such effluent discharges, consumption and fission product production
, would not foreclose the adoption of alternatives in plant design or operation Q of the type that may result, from the ongoing full NEPA review.
[. a-L While, as earlier indicated (p. 36), radioactive gaseous and liquid efflu-ents resulting from operation are expected to be well within 10 CFR Part 20 and Technical Specification limits, the applicants further plan to install a modified waste system to reduce radioactive effluents to levels meeting the requirements of the "as low as practicable" amendments to 10 CFR Parts 20 and
- 50. This is to be effected within the period provided in the amended regulations.
As earlier discussed (p.16), the applicants have also adopted or agreed to adopt (for the operational period beyond June 1, 1972) additional methods of limiting the effects of thermal discharges. Civil works have been initi-ated and components have been procured to build a pipe with diffuser nozzles for dispersion of heated condenser cooling water near the bottom of the Mississippi River channel. This system is expected to reduce the therral effects of the discharged water. Present operation will not foreclose thue changes; nor will it preclude any additional changes to accommodate requirements that may be imposed by the Commission as a result of its complete NEPA review.
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IV. EFFECTS OF DELAY IN FACILITY OPERATION UPON THE PUBLIC INTEREST .
A. POWER NEEDS The applicants have stated, with supporting submissions, that electric service in Chicago, Northern Illinois, and all of Iowa will be seriously jeopardized if the Quad-Cities generating capacity is not available to meet the 1972 summer peak load. In addition, the Commonwealth Edison Company states that its 75 percent share (1,214 MW) of Units 1 and 2 is needed prior to the summer season in order to schedule urgent maintenance of existing units. The importance of such maintenance is indicated by the loss of 1,664 MW in generating capacity that the applicant experienced on a peak load day in 1970 as a result of forced outages and restrictions. During a similar peak i load in 1971, there was a loss of 2,239 MW, and the situation, according to the applicants' submission, is likely to be worse in 1972 unless deferred maintenance is performed.
For the summer of 1972, the Commonwealth Edison Company estimates its peak load will be 12,520 MW. This is subject to an increase of up to 440 MW if the summer is hotter than average. Without either of the 809 MW Quad-Citles units or Zion 1 (a 1,050 MWe nuclear unit for which an operating itcense is also pending), this applicant's system capacity will be 13,189 MW, including firm purchases from other utilities. The reserve capacity would thus be 669 MW, only 5.4 percent more than the estimated peak load. This is far below the applicant's normal target of 14 percent reserve and further below the 20 percent reserve generally recommended by the Federal Power Commission (FPC).
Iowa-Illinois Gas and Electric Company has forecast a 1972 summer peak load on its system of 714 MW, which exceeds its dependable capacity of 568 MW. Instead of a reserve, this applicant will, therefore, have a defici-ency of 146 MW without its 404 MW share of Quad-Cities Units 1 and 2. The Iowa Pool, of which the applicant is a member, indicates that its reserve margin without Quad-Cities will be a negative 45 MW. With 404 MW from Quad-Cities, the pool's reserve would be 359 MW, which is 11.5 percent of its i predicted peak load.
The situation which faces the applicants is the subject of a staf f report by the FPC's Bureau of Power which was transmitted to the Atomic Energy Commission on December 10, 1971. In its report, the FPC views the situation as a potential power supply shortage throughout the midwest and concludes with the following: "The factors examined indicate that there is l
an emergency need for interim operation of the Quad-Cities Units 1 and 2, 1 assuming that the AEC can concurrently deal appropriately with environmental issues involved in such operation." A copy of the FPC report is appended to this document.
I L___ __ _
- 47'-
The Illinois Commerce Commission emphasized the urgent need for additional generating capacity in n recent letter to the AEC*, which statedt "It is' opparent that Illinois must put into operation some of the capacity now under construction before next summer or face the certainty of power outages. The un f tr. most able to contribute to the required capacity are Edison's Quad-Cities 1 and 2, because they are ready for testing and operation."
There is no way to assure availability of the Quad-Cities units for the summer peak load demand unless the applicants' power operation test program is undertaken and completed in advance of that time. Additional time should be allotted to remedy any deficiencies discovered during the test program. The applicants have indicated that testing one unit will-requirt ' weeks at the minimum, or 72 days for both units with some overlap in efforo. However, they estimate that 32 additional days will eventually be required for testing each unit to full power if operation to only 20 percent of full power is authorized at this time. Taking all of this into account we conclude that authorizing operation at 20 percent of full power of the Quad-Cities units at this time will save the applicants' about 2 monthe in the time it would otherwise take to start and complete the power operation test program subsequent to the completion of our ongoing NEPA review.
From this discussion it should be noted that there is a critical need f or power f rom the Quad-Cities units to help meet the area's summer peak load. Complete testing of the units and the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run at full power must be completed prior to the July-September peak load months.
110 wever, even this weald not be of help to meet the peak load demand unless operaticus up to 20 percent of full power were authorized now so that the fuel loading for Unit 2 and the test program for bcth units could begin.
B. AVAILABLE ALTERNATE SOURCES To make up their power supply deficiencies, the applicants would attempt to purchase the required capacity and energy from neighboring utilities.
However, it is uncertain whether power will be available from adjacent systems, as noted in the FPC report which states, 'Vithin the time available, there are no known c1 ternate additions of generating capacity which could be sub-st i t utec for the Quad-C i ties Uni ts . . . . Delays in commercial operation of bot h fossil and nuclear units are likely prospect s in adjoining regions; therefore, it would not be realistic to depend upon imported replacement puwer in this Instance."
- Letter dated October 26, 1971 to James R. Schlesinger, Chairman of the AEC from tae Illinois Commerce Commission (copy attached) .
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C. DELAY COSTS.
' For each week the Quad-Cities Station is not operating, .the applicants estimate .the full cos t of replacement power. at ' $1,200,000. The FPC report verifies this estimate as reasonable. Operation of both units at 20 percent or less would reduce this cost.by an amount approximately in proportion to
- the percentage of-rated output obtained.
- D. OTHER EFFECTS OF DEpY The applicants state that every megawatt not produced at Quad-Cities, diich can be replaced, will have to be produced by the oldest, most inef-fielent coal-fired units on the' applicants' systens. Such generation is
- estimated to result in adding 03out 70 pounds of sulfur dioxide and 3 pounds of particulate per megawatt-hour to the environment. The Illinois ' Pollu-tion' Control Board, in granting a variance from air particulate' regulations-for operation of 'several- coal-fired units which are to be retired upon com-pletion. of. Quad-Cities Unit 1, stated, "The present petition underlines the impi.n ance of placing Quad-Cities in use at the earlies t possible date."
(See PCB 71-165; Opinion of the Board. . September 16,1971.)
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V. CONCLUSION We have completed our radiological health and safety review of the operation of the Ntation up to full- power 'under the authority of the Atomic Energy' Act of 1954, as .amendeo, 'and are prepared to make all the necessary findings pursuant to the provisions of 10 CFR 50.57(a) for operntion of the station at 20 percent of full power. The results of t'hb radiological henith 'and safety review are set forth in the AEC regulat ory Staf f Safety Evaluation (31), dated August ' 25,1971.
We have reviewed the matter 6f 20 percent operation of Units 1 and 2 during the period ending June 1,1972 in the context of the following
- factors specified in 10 CFR Part 50, Appendix D Section D.2:
"(a) luiether it is likely that limited operation during the prospective review period' will give rise to a significant, adverse impact on the environment; the nature and extent of such ' impact, if any; and whether redress of any such adverse environmental !
Impact can reasonably be effected should modification or termina-tion of the limited license result from the ongoing NEPA review. ;
"(')
o Whether limited operation during the prospective review i period would foreclose subsequent adoption of alternatives in facility design or operation of the type that could result from the ongoing NEPA environmental review.
"(c) The ef fect of delay in facility operation upon the pubtle interest. Of primary importance under this criterion are the power needs to be. served by the facility; the availability of alternative sources, if any, to meet those needs on a timely aasis; and delay costs to the licensee and to consumers."
Based on aur evaluation of the data and analyses referred to, we have de te rmined that t
- a. Operation of both units at power levels up to 20 percent of rated power each, during the period ending about June 1,1972, will likely nive rise to on3v a minimal impact on the environment. As discussed above, this potential impact is due to chemicals, particularly chlorine and chlorine derivatives, and heat added to the condenser iooling water. This impact would be loca ized and is not likely to have a measureable ef fect on the overall aquatic population of Pool 14.
i Furthermore, should this proposed operation be terminated, recovery of l the aquatic biota in Pool 14 would be good and probably complete.
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- b. Operation of the station, at the'20 percent power level will not foreclose subsequent adoption of alternatives in the facility design or operation of the type that could be required as a result of the ongoing i supplemental NEPA environmental review.
- c. There will be- an adverse effect upon the public interest as a.
result of delay in facility. operation. The Federal Power Commission, in its December 20, 1971 letter, has stated that it'is essential
' -' that these units be available for power generation by this summer. Their 1ctter and supporting data confirms the applicants' contentions (with supporting submicsion) that an emergency situation exists with regard to ,
the public need for power.
In accordance with Section D.2 of Appendix D of 10 CFR Part 50, we !
therefore = conclude that, authorization of interim operation at a power Icvel up to 20 percent during the period ending June 1, 1972, should be granted.
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t REFERENCES
- 1. Letter from Mr. H. Nexon, Commonwealth Edison Co., to Dr. Peter Morris dated October 12, 1971.
- 2. Letter from Mr. W. Stied, Commonwealth Edison Co., to Dr. Peter Morris dated November 18, 1971.
- 3. Peterson, D. ' E. and R. T. Jaske,. Potential Thermal Effects of an Expanding Power Industry: Upper Mississippi River Basin, BNWL-1405 June 1970..
- 4. Illinois Pollution Control. Board - Hearing 71-20, May 24,1971 to
. June 9, 1971.
'5. Preoperational Environmental. Monitoring (Thermal) of the Mississippi River near Quad-Cities Station, July 1969-June 1970. Ind. Bie-Test Labs.,.Inc., Northbrook, Illinois, 1970, 46 pp.
6.- Prooperational Environmental Monitoring (Thermal) of the Mississippi River near Quad-Cities Station, July 1970-December 1970. Ind. Bio-Test
~
Labs., Inc., Northbrook, Illinois, 1971, 91 pp.
- 7. Steinberg, R. B. , " Upper Mississippi River Habitat Classification Survey-Hastings, Minnesota to Alton, Illinois," Minnesota Department of Natural Resources, St. Paul, Minnesota, March 1971.
- 8. Deer, L. P. , and Pipes, W. O. , A Practical Approach to the Preserva-tion of the Aquatic Environment: The Ef fects of Discharge of Condenser Water into the Mississippi River, Commonwealth Edison Company, Chicago, illinois, 1968, 210 pp.
- 9. Galstoff, P. S., 1924. Limnological Observations in the Upper Mississippi 1921, U. S. Bur. Fish. Bull. 39: 347-438.
- 10. Reinhard, E. C. , The Plankton Ecology of the Upper Mississippi, Minneapolis to Winona, Ecol. Monogr.1: 395-464, 1931.
- 11. Barnickol, P. B. , and Starrett, W. C. , Commercial and Sport Fishes of the Mississippi River between Caruthersville, Missouri, and Dubuque, Iowa, Bull. Ill. Nat. Hist. Survey 25: 267-350, 1951.
- 12. Carlander, K. O., et al. 1967. Populations of Hexagenia mayfly nalads in Pool 19, Mississippi River, 1959-1963, Ecology 48:
873-878. +
I
- 13. Wright , K. J. , 1970. The 1967-1968 Sport Fishery Survey of the Upper Mississippi River. Wisconsin Department of Natural Resources, Madison, Wisconsin. A Report of the Upper Mississippi River Con-servation Committee, 116 pp.
- 14. Cale, W. F. , and . Lowe, R. L. , Phytoplankton Inges tion by the Fingernall Clam, Sphaerium transversum (Say), in Pool 19, Mississippi River,' Ecology 52: 507-513, 1971.
- 15. Final Detailed Statement on Environmental Considerations USAEC, for the Quad-Cities Nuclear Power Station, Unit 1 and 2, July 2,1971.
- 16. Environmental Impact Report: Supplemental Information to the Quad-Cities Environmental Report - Docket Nos. 50-254 and 50-265, Volumes 1 and II - November 1971.
- 17. Baker, R. J. , Types and Significance of Chlorine Residuals, J. Am.
Waterworks Association, 41, 1185-90 (1959).
- 18. Corbett, R. E. , Metcalf, W. S. , and Soper, F. G. , Studies of N-Halogen Compounds, Part IV. The Reaction between Ammonia and Chlorine in Aqueous Solution, and the Hydrolysis Constants of Chloramines, J.
Chemical Soc. (London), 1953, 1927-29.
l
- 19. Final Safety Analysis Report, Sections 1-14, Appendices A-C, Amendments to Sections 1-14, Appendices A-F.
- 20. Coutant, C. C. , Biological Aspects of Thernal Pollution 1. Entrain-ment and Discharge Canal Ef fects, Chemical Rubber Company,1970.
- 21. Marcy, J r. , B. C. , Survival of young fish in the discharge canal of l J. Fish. Res. Bd. Canada, 28: 1057-1060, 1971.
a nuclear power plant.
- 22. Churchill, M. A. , and Waj takik, T. A. , Ef fects of Heated Discharges on tt.e Aquatic Environment - the TVA Experience,1969.
I 23. James E. Kerr, Studies on Fish Preservation at the Contra Costa Power Plant of the Pacific Cas and Electric Company , State of California
! Department of Fish and Game Bulletin No. 92, 1955.
- 24. Industrial Waste Guide on Thermal Pollution, U.S. Department of Interior, FWPCA, Northwest Region, Pacific Northwest Water Laboratory, Corvallis, Oregon, September 1968.
I
- 25. Coutant, Charles C. 1962. The ef fect of a heated water effluent upon the macroinvertbrate ripple fauna of the Delaware River. Penn-sylvania. Academy of Science. 37: 58-71.
- 26. Warinner, J. E. and M. L. Brehmer 1966. The effects of thermal effluents on marine organisms. Air and water pollution Int. J. 10:
277-289.
- 27. Mount, D. I. , Af fidavit in the U. S. Dis trict Court, Dis trict of '
Columbia (2207-71) November 24, 1971.
- 28. Nebeker, Alan V. 1971. Effect of high winter water temperatures on adult emergence of aquatic insects. Water Research 5:777-783.
- 29. Nebeker, Alan V. and Amond E. Lemke.1968. Preliminary studies on the tolerance of aquatic insects to heated waters. J. Kansas Entomological Society 41:413-418.
- 30. Sprague, J. B. , and Drury, D. E. , Avoidance reactions of sa 'monid l fish to representative pollutants, p. 169-179 in: S. N. Jenkins (Ed.), Advances in Water Pollution Research, Proc. 4th Int. Conf. , '
Prague, Pergamon Press, New York,1969.
- 31. Safety Evaluation, USAEC, August 25, 1971.
- 32. Public Health Service PHS-956, U. S. Department of Health, Education and Welfare, j j
l
- 33. The Water Encyclopedia, Water Inf ormation Center, Water Research !
Building Manhasset Isle, Port Washington, N.Y.1970.
- 34. Illinois Pollution Control Board Opinion, Case # 71-20 November 15, 1971.
- 35. Illinois Pollution Control Board Opinion, Case f 70-16 " Mississippi themal St andt.rds ," November 23, 1971. (Illinois Sanitary Water i Board Standards SWB-12 and SWB-13, amended by R-70-16 although not I yet approved by the Environmental Protection Agency are considered '
applicable by the Illinois Pollution Control ifoard, successor to the Sanitary Water Board.)
- 36. Quad-Cities Environmental Report, Supplement IV, December 30, 1971. j 4
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+ ,
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- ~ Bibliography (Dock.et Nos. 50-254- 6 50-265) 1 Plant Design Analysis , -Vol. I and II.
Safety Analysis Report,-Vol.'I and II and amendments.
Environmental Report, Quad-Cities Station Units 1 and 2, November 12, 1970.
Final Safety Analysis Report, $ actions 1-14, Appendices A-C, Amendments to Sections 1-14, Appendices A-F.
Illinois Pollution Control Board - Hearing' 71-20, May 24,1971,
' June 9,-1971.
Brief of Applicants, Illinois Pollution Control Board, Case # 71-20 i !
following 5/27-6/9 hearings.
Brief ofl Illinois Attorney General, Illinois Pollution Control Board hearing, Case # 71-20 in oppositten to the application.
Reply Brief of Applicants in support of their Joint Application under Title VI-A, Illinois Pollution Control Board hearing, Case # 71-20 September 8, 1971.
Environmental . Impact Report: Supplemental Information to the Quad-
. Cities Environmental Report - Docket Nos. 50-251 and 50-265, Vol. I and II, November 1971. (Environmental' Emport, Supplement III)
Final Detailed Statement on Environmental Considerations USAEC, for the Quad-Cities Station, Unit 1 and 2. July 2,1971. (Appendix I is Supplement I of the Environmental Report.)
Safety Evaluation, USAEC, August 25, 1971.
Technical Specifications (Appendix A to the Proposed Operating License DPR-29)
Letters from Mr. Byron Lee, Commonwealth Edison Co., to Dr. Peter Morris dated September 13 9ad 15,1971.
1 Telegrams from Mr. Byron Lee, Commonwealth Edison Co. , to Dr, Peter Morris dated September 13 and 15,1971.
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Letter 'from Byron Lee, Commonwealth Edison Conpany', to Mr. Lester Rogers
. dated. September 27,1971. (Environmental Report, Supplement'II).-
Telegram from Mr.-Wayne-Stiede,-Commonwealth Edison Co., to Mr. M. Grotenhuis dated September 10, 1971.
u Discussions'and findings' supporting the' issuance of an Operating License authorizing-the loading of fuel and operation not in excess of 1 percent (October 1, 1971).
Letter f rom Mr. H. Nexon, Commonwealth Edison Co. - to Dr. Peter' Morris dated October 12,1971.
Letter from Mr. W. ' Stiede Commonwealth Edison Co. , to Dr. Peter -
Morris dated November 18, 1971.
Quad-Cities Environmental Report, Supplement. IV, December 30, 1971.
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