ML19340A198
| ML19340A198 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/02/1971 |
| From: | Thies A DUKE POWER CO. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001140800 | |
| Download: ML19340A198 (11) | |
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DUKE POWER COMPANY Powrn Bu Lorwo 4aa Sourn Cuuncu Srazzr, CuAntorTz, N. C. asson A
C. THIES p, Q. Box 2178 samon vecs passicant PeoDUCfiCm AND T=Ansasission g
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' N J' Dr. Peter A. Morris, Director
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Division of Reactor Licensing
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's Atomic Energy Commission
,s 7920 Norfolk Avenue Bethesda, Maryland Re: Oconee Units 1, 2, and 3 Supplemental Environmental Report Docket Nos. 50-269, -270, and -287
Dear Dr. Morris:
Duke Power Company is submitting herewith Revision No. I to its Supplemental Environmental Report for the Oconee Nuclear
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Station. Three hundred copies of the Supplemental Environ--
mental Report were submitted with our letter of October 18, 1971 in support of Duke Power Company's Application for Licenses for the Oconee Nuclear Station which is under con-struction pursuant to Provisional Construction Permits CPPR-33,
-34, and -35 issued by the Commission on November 6, 1967.
Please insert revised pages 19, 21, 68, and Table 5 as replace-ments for existing pages in the 300 copies of the document entitled, " Supplement to Environmental Quality Features of Keowee-Toxavay Proj ect," and dated October,1971.
Please note that vertical lines in each margin and the revision numbe.r in the left margin identify portions revised unless otherwise noted at the bottom of the page.
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Having been duly sworn, I hereby certify that I am a Senior Vice President of Duke Power Company; that I am authorized on the f f,0 {lh h $
Page 1 of 2
e Dr. Peter A. Morris Page 2 November 2, 1971 part of said company to sign and file this revision; and that all matters set forth therein are true and correct to the best of my knowledge, information, and belief.
By Senior Vice President ATTEST:
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e Assistant Secretary A. C. THIES has subscribed and sworn to the above statement before me, a Notary Public in and for the State of North Carolina and County of Mecklenburg, this 2nd day of November, 1971.
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Notary P' lic My Commission Expires:
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March 16. 1975 Page 2 of 2
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period at 435 gpd during which time all fission and corrosion products are allowed to decay.
6.
Specific activities are shown as a total of " Reactor Coolant Coolant Systed' and " Liquid Wastes" discharged to and diluted by the Keowee Hydro Plant tallrace flows of 30 CFS for a minimum leakage and 1100 CFS for average tallrace flow. Fractions of MPC for yearly discharge at the average tallrace flow are also shown.
7 Tritium values shown are based on a 2.75 a c/ml specific activity level for the total quantity of liquid discharged as defined in FSAR Table li.la.
No holdup time or removal is considered for tritium.
It is possible that trace quantitles of solid elements, such as cesium, molybdenum, and yttrium can get into the reactor coolant system. The analysis of Section 11.1.1.3.1 of the Oconee FSAR assumed conservatively a zero removal efficiency for molybdenum and yttrium and 90 percent removal efficiency for cesium.
It has since been determined, however, that removal efficiencies of at least 90 percent could be attained for cesium, molybdenum, and yttrium.
Letdown reactor coolant is sent to the bled holdup tank.
Depending on its activity the contents of the bleed holdup tank may then be sent to the miscellaneous waste holdup tank, high activity waste tank, or the coolant treatment evaporator. Waste in the first two of these is held up for decay and/or processed by the evaporator.
Liquid wastes may be sent to the low activity waste tank f rom the miscellaneous waste holdup tank and high activity tank. Other liquid wastes such as cooler drains, floor drains, pump vents (including the turbine room sump drain), etc, desin to ;he low activity, high activity or miscellaneous waste tanks depending on their potential activity.
Inputs to the low activity waste tank are filtered through a filter of approximately 40 microns and can be discharged to the Keowee tallrace after monitoring.
The liquid waste discharged is sampled for gross beta-gamma activity and/or isotopic activity concentrations.
The frequency of these isotopic determina tions may be found in the Oconee FSAR, Section 15, Table 4.1-3 While no further sampling is required by the Technical Specifications, there will be operating procedures for alpha activity measurements in the waste discharge, 19
/%
Low level gaseous waste activity is vented. The gaseous waste 3,
vents are straight vertical cylinders which have a 5 foot, 11-3/8 inch inside diameter exit. The top of the stacks are at an elevation of 995.9 feet above sea level- (220:9 feet above the ground elevation at the plant and approximately 9 feet above the highest building in the area). The location of vents for each unit is shown in Figure 1-8 of the Oconee FSAR.
Figure 2-5 of the FSAR indicates relative elevations.
Figures 5 and 17 show the plan view of the buildings near the stacks giving their shape and roof heights.
The effluent velocity f rom the stack is 211+0 feet per minute. The stack flow is composed of 52,000 SCFM of exhausted ventilation air f rom the Auxiliary Building, 32 SCFM f rom the waste gas system, and 60 SCFM/ unit (design) f rom the air ejectors.
Intermittently, 50,000 SCFM will be dis-charged f rom the Reactor Build ing purge system.
Normal discharge temperature will be 95*F.
Table 6 is a list of all radionuclides which may be emitted up the stack and the total amount released of each (in curies).
Gaseous fission products were calculated assuming plant operation with one percent fuel defects-for one year and a holdup of 20 days, except for the Reactor Building purge. The one percent fuel. defects is a maximum design condition and is not expected for normal operation. The 20-day holdup is the minimum allowable by Technical Specification 3.9 3.6 of the Oconee FSAR.
The design calcula-tions of Section 11 of the Oconee FSAR list data on gaseous releases based on the assumption of no holdup. Also included in the table is a breakdown on the sources of the radionuclides emitted.
Section 3.9.3.1 of the Technical Specification specifies the maximum gaseous release rate allow ele.
The values listed in Table 6 cre an annual average composite since certain gaseous releases are intermittent while others are continuous.
Auxi-
~liary Building ventilation is a continuous release.
The Reactor Building purge 1
is an intermittent release as is the release of the waste gas decay tanks.
One mechanism of waste gci production is fuel failure or cladding defects. The model used to generate design basis reactor coolant fission I
product. inventories is discussed at length in the Oconee FSAR Section 11.1.'l. 3.
The AEC/ORL question 6.7, dated Aoill 18, 1967, and Duke's answer to j
the question included in Supplement 2 of the Oconee Preliminary Safety i
Analysis Report deals with the subject of radioactive gas buildup in the 20
s p.
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reactor coolant and can be consulted for further detail.
A Babcock & Wilcox computer code calculates the reactor coolant activity level as a function of time and the equations used in this code are presented in the Oconee Preliminary Safety Analysis Peport.
Charcoal. is used in filters at the Oconee Nuclear Station to limit releases. The following is a list of the filters utilizing charcoal, the type of charcoal used and the flow rate through the filter:
1.
Reactor Building Purge Filters Mine Safety Applicances 85851 Carbon 40 to 45 ft/ min 2.
Penetration Room Filters American Air Filter Barneby Cheny 727 Carbon 40 to 45 f t/ min 3
Reactor Building Hydrogen Purge Filters Barneby Cheny 727 Carbon 40 to 45 f t/ min 4.
Waste Gas Filters Barneby Cheny 727 Carbon 40 to 45 ft/ min 5.
Control Room Air Conditioning MSA 85851 Carbon 40 to 45 ft/ min Any filters in the gas discharge systems that become radioactive will be taken to a drumming station and packaged for off-site disposal.
Table ll-la of the Oconee FSAR tabulates predicted amounts of solid radioactive waste to be produced at the Oconee Nuclear S tation.
The plant should produce approximately 350 cubic feet per year of demineralizer resin 5
(with activity of 6x10 curies /yr) and 2500 cubic feet per year of evaporator 5
bottoms (with activity of 2x10 curies /yri.
It is expected tha t one-hundred 55-gallon drums of low level contaminated solid was-tes will be produced annually f rom each unit.
Solid radioactive wastes will be packaged and shipped to licensed disposal facilities by licensed waste handling contractors.
For normal operation there will be no smoke or chemicals discharged to the atmosphere. The only possible source is an auxiliary space heating boiler, which will be used only when Unit 1 is down for refueling and for startup prior to operation of Units 2 and 3 The emissions will be the usual products of combustion from the use ot d2 fuel oil.
The auxiliary boiler will not be used when Units 2 and/or 3 are available to supply this steam.
21
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50ll CONSERVATION Duke's new construction activities often involve large scale land
's clearing and earth excavation operat ions.
For years it has been company practice to restore grass and tree cover to such disturbed areas in early stages of construction to reduce erosion and downstream siltration.
Roadway banks, earth borrow pits, slopes of dams, banks of canal and other earth structures are thus provided with vegetation cover and restored to a stable condition a.J pleasing appearance.
Duke Power's comprehensive, scientifically-managed forestry pro-gram plays a vital part in the preservation and restoration of the Piedmont-Carolina's environment. The company land surrounding Lake Keowee that is not devoted to recreation or other purposes is under a continuous forestry management program. Any open or idle land has been or will shortly be planted with trees. The woodlands are operated under a sustained yield concept where the mature timber stands are harvested and the harvested areas prepared and replanted with trees suitable to the site.
These young forests supply more oxygen to the atmosphere than the mature and over-mature trees that are being replaced.
If a stand of trees is left to grow too long, it becomes decadent and stagnant, consuming more oxygen than it releases.
In Duke's timber harvesting program the protection of the soll from erosion is of primary importance.
Care is taken in locating the logging road system so as to keep the streams f ree of sit t.
Following the logging operations, precautions are taken to correct any possible sources of e ros ion. Water turnouts are built into the logging roads and skid trails.
These roads then are seeded in perennial grasses and/or lespedeza.
In addition to this comprehensive forestry program, Duke has underway a watershed management program. To make sure the land for this program is definitely separated f rom the land for utility purposes, Duke has transferred it to a wholly-owned subsidiary, Crescent Land and Timber Corporation.
Crescent implements the policies of watershed management by planting about 400,000 seedling trees per year at the Keowee-Toxaway P roj ec t.
Besides providing soil stability and erosion control, each acre of planted southern pine returns between two and three tons of organic matter to the soll each year.
HISTORICAL SALVAGE Du-ing preliminary investigation of the Keosee-Toxaway project it became apparent to Duke Power Company that the Keowee basin contained
'22
6 b'ut consequences shown require coolant activity prior to event) and "I"-(not likely to occur but' consequences are presented from one event in one year during' the ll'fe ~of the plant). '
i
.in. order,to put.the-consequences of-_these accidents in perspective,
. the resul' ting dose shown in Table 18 would'be' in addition to the naturally occurring-background radioactivity. This background radioactivity at Oconee has been' measured and found to be about 130_ mrem per year.. Even the largest
- value shown In Table 17, 2.'l x 10 mrem, would. only ' increase the-exposure
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to 130.021 mrem. This increase is insignificant and leads to the conclusion
- hat' none of the accidents examined endanger the health and safety,of the J
j general public.
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.(l) American Public Health Association; Standard Methods for the Examination of Water and Waste Water (13th Edition); APHA, AWWA, WPCF; New York, New York; 1971.
(2) Holt, Perry b (ed); Highlands Biological Station, !nc; Highlands North Carolina.-
(3) U S Study Commission Report; " Southeast River Basins"; Accendix 1, p 4-39; 1963.
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(4)
S C ' Parks, Recreation and Touri sm Depa rtment; " Impact Study for Proposed Extension of South Carolina Scenic Highway 11"; Mimeo, Columbia; 1969.
l (5)
S C Parks, Recreation and Tourism Department; " Travel and South Carolina Business in 1969"; Louis C Copeland; Department of Statistics, College of Business Administration, Universi ty of Tennessee.
(6)
Jansma, J D; Secondary Effects of Upstream Watershed Development; Unpublished doctoral dissertation; Okalhoma State Universi ty; p 68 (7)
Contract No. DACW21-67-C-001 between the United States of America and Duke Power Company.
(8)
Office of Appalachian Studies, Corps of Engi neers, Department of the Army;
" Development of Water Resources in Appalachia"; Main Report, Part III, Pro-Jact Analyses; Cincinnati, Ohio; p 111-5-87.
(9) Adair, W D and Looper, J B; " Lake James Investigation"; North Carolina Wi ldli fe Resources. Commi ssion; 1968, l
(10)
Sport Fi shing insti tute; "$
Value of Fish"; Bulletin No 227; p 8; 1971.
(II) Hayne, W Don; Hall, Gordon E and Nichols, Hudson M; "An Evaluation of l
Cove Sampling of Fish Populaticns in Douglas Reservoir, Tennessee";
l Reservoi r Fishery Resources Symposium, Southern Divi sion, American Fisheries l
Society; 1969 (12)
Stanberry, Fred W; " Future Role of Reservoirs in State Fisheries Management Programs"; Reservoir Fishery Resources Symposium, Southern Division.
American Fisheries Society; 1969 (13)
Bureau of Sport. Fisheries and Wildlife; " Sport cishing - Today and Tomorrow"; Outdoor Recreation Resou, ces Review Commission Study Report No 7; U S Department of the Interior.
(14)
Outdcor Recreation Resources Review Commission; " National Recreation Survey"; Study Report No 19; 1962.
(15)
Sport Fi shi'ng institute; " Fish Conservation Highlights, 1963-1967"; 1969.
.)
69 x
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,y TABLE 5 ESTIMATED ANNUAL RELEASES BY ISOTOPE FROM THREE UNITS
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Corrosion Products, Normal Operation, No Fuel Def ects s
Specific Activities.In Liquid Waste Discharge uc/mi Dilution.by Hydro
.DilutionbyAverage Fraction of MPC in Waste Annual Reluase Plant Leakage Only Hydro Plant Flow
. Discharge'with A,verage isotope uc (30 CFS)
(1100 CFS)
Hydro Plant Flow CoS8 4.91 x 10
-1.84 x 10 I 5 02 x 10 I2 5.02._x 10_8 2
lo co60 2.74 x 10.
1.02 x 10-2.79 x 10 557x10l0 3
^
cr51 7.89'x 10 2.96 x lo, 8.06 x'10 4.03 x 10 9
, Mn54 -
9.62 x 10, 3.60 x 10 9.82 x 10_ig 9.82 x 10_9
-12
-Fe59 9.22 x'10 3.45 x-10_go 9.41 x 10 1.57 x 10 2
-12
-8 Zr95 6.13 x 10 2.29 x to 6.26 x 10 1.04 x to Add to Corrosion Products for 1% Fuel Defects in One Unlt
-3
-15.
-17
-ll Rb88 3.86 x 10 1.44 x 10 3,9q x go i,33 x go-Sr89 8.57x10[
3.20x10]
8.73x10M 2.91 x 10_7 Sr90 8.88 x 10 3.32 x 10 9.05 x 10 3.02 x to r
-12
-N
-10 Sr91 6.03 x 10 2.26 x 10 6.16 x 10 8.80 x 10
-3
-I3
-15
-11 Sr92 6.68 x 10 2.50 x 10 6.81 x 10-757x10_f g,73 x 3o 3
1 131 2.23 x.l0 8.34 x 10 2.27 x 10_
I 132 1.40 x 10 5.23 x 10 1.42 x 10-7.43 x 10_6
}.
1.78 x 10 2
I 133 5.62 x 10_
2.72 x to 7.43.x 10_
I 134
-7.29 x 10 ;
2.73 x 10-2.02x10ll2 5.08x10]
9 7.44 x 10 3.72 x 10 2
4.29x10lI9' 3.40x10_l t 135
.l.97 x 10 csI36
.l.15 x 10 4.92 x 10-1.17 x 10 1.30 x 10
-II
-7 3
l.34 x 10 6.70 x 10 cst 37 1.32 x 10-3
-I'
-15
-9 csl38 5.42 x 10 2.03 x 10 5.54 x 10 1.85 x 10 N
-8
-10
-6 Mo99 8.78 x IO 3.29 x 10 8.98 x 10 4.49 x 10
-12
-IN
-8 Bal39 7.08-x 10 2.65 x 10 7.23 x 10 2.41 x 10 2
-II
-12
-8 i
Bal40' l 83 x 10 6.83 x 10 1.87 x 10 6.21 x 10 I
-II
-0
.Lal40 4.18 x 10 2.42 x 10 4.28 x 10'I3 2.14 x 10 3
-9'
-II
-6 Y 90 8.43 x 10 3.15 x 10 8.61 x 10 4.30 x 10 3
-9
-II
-6 Y 91 3.88 x 10 1.45 x 10 3.96 x 10 1.32 x 10 cel44 1.26 x 10 4.70'x 10
-I3
-8
-12 H3 1.2' x 10 4.5 x 10-1.28 x 10 1.28 x 10 '
10
-15 1.23 x 10 4,3 :x 10
TABLE 6 OCONEE 1 DESIGN CONDITION ANNUAL RELEASED RADIONUCLIDES' (CURIES)"
Startup Reactor Lifetime Expansion Building-Tank isotope Shim Bleed
& Dilution Purge' Venting' Total
-I 2.5.x 10'I 2 5 x lo Kr85m 3
4 2
3 Kr85
'523 x 10 3,y x 39 i,7 x 39 1.0 x 10 1.7 x_to 4'.0 x 10"
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4.0 x 10
- Kr87, 2.9 x 10'-l
-I 2.9 x to 2
2 I
I 3
)
Kr88 s.
Xel31m-4.0 x 10 6.3 x 10 2.0 x 10 9.3 x 10
- 1. l ' x 10 0
0 0
-I-I Xel33m 3'7 x 10 2.0 x 10 6.0 x 10 2.9 x 10 1.2 x 10 4
3 3
4 Xel33 1.0 ' x' 10 1.2 x 10 1.2 x 10 1.8 x 10 2.5 x 10
-3
-3.
9.3 x 10 9.3 x 10 Xel35m.-
0 2.3 x 10 2.3 x 10 Xel35 4.0 x 10 4.0 x-10 Xel38 3
3 TOTAL 1.6 x 10 2.3 x 10 1.4 x 10 2.0 x 10 4.3 x 10 "L i f e t ime S h i m B l eed" i s a l l t he gas f rom 14,600 f t of r ctor coolandI) decayed for 20 days.
"S tartup Expansion 2, Dilution" is all the gas from 29,600 ft3 of reactor coolandI) decayed for 20 days prior to and 7 days during release.is all the gas f rom a 10 gal / day ) reactor coolant 0) decayed during a l'
O
" Reactor 3uilding Purge" 30 day buildup.
" Tank Venting" is an appropriate f raction of all the gas in the reactor coolant system determined
=
f rom' Henry's Law and decayed during discharge for 7 days af ter 20 days holdup.
II)See FSAR Table II-3 (200 day values used)
(3)FSAR Section 11.1.2.5.2 (2)See FSAR Table Il-la
- Note that Kr85 activity is not constant as assumed, and in fact only about 2.6 x 103 curies / year.
- are leaked into the reactor coolant with 1% fuel defects.
M. Assuming.one percent f ai led fuel.
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