ML19317E137
| ML19317E137 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/16/1969 |
| From: | DUKE POWER CO. |
| To: | |
| References | |
| NUDOCS 7912160009 | |
| Download: ML19317E137 (75) | |
Text
- - - w-N=-WW6 6--
.h$, -y
-3 :, <.g.,,
.r 9,, m 4' Q ' ^ ' y D.;- 4 j ', '
_fa; y. .
.4 L
- ' ^ ~
w As&Th &+,s[Qif*~
..,- - ,. w . . .r.
k
.em - k s f< 4 0is. As, ' E d5 . . kf"fh . _,
11?i. ~; -
Mff_
b
- c
- t , y, ..
sic"
+
j
', ,rA[ ) ' '
cr p + .
4rt f,;l4 'u e g.,,1.jfgr. '
~
.+
%g
'ic]m ,., & -
Yh k ,,,
g :: <
t
=,
, :ps. ' . < . . .
f a
- w. nu n i
Awwp ,
,I N
w l .I I
Dames *
- L tr Sa tu t'
3 I
=
'f Ti a
e'
-* /
d #
k
4
&/
hAL 6, % J Id'i o) -4 Y f 6 f' l' O , ,7 4 7 2.6 SEISMOLOGY g g ,9 w urop d f ' " W Regulatory File Cy.
No active or recent faulting has been recognized in the area of the proposed site. The closest known fault is the Brevard Zone, approximately 11 miles northwest of the site.
The Reactor Buildings' foundations are located on rock which has excellent strength properties and relatively small amplification of ground motion result-ing from an earthquake.
The structural design criteria for the maximum hypothetical earthquake are 0.10g and 0.15g for Class 1 structures founded on bedrock and overburden, respectively. The structural design criteria for the design earthquake is 0.05g.
A detailed Seismology Study is included as a part of Appendix 2B in the PSAR.
Additional information on seismology is included in Answers to Questions 2.7 and 8.5 of PSAR Supplement 1 and Question 11.3 of PSAR Supplement 4.
2.7 OCONEE ENVIRONMENTAL RADIOACTIVITY MONITORING PROGRAM 2.
7.1 INTRODUCTION
The purpose of the environmental radioactivity monitoring program is to measure and evaluate the significance of contributions to the existing environmental radioactivity levels from plant operations.
The program is divided into pre-operational and operational phases, with the assumption that pre-operational levels may provide a base line to which opera-tional levels can be compared. Such comparisons are complicated by additional nuclear weapons testing, seasonal and annual variations in fallout level, and discharges of radioactive material from other installations. However, pre-operational monitoring does document the existing radioactivity levels and their variability. Also the use of control locations well out of the influence of the plant can serve as a means of comparison for evaluating the plant's contribution to the environment during the operational phase.
During the operation of a nuclear power plant, the only contribution of radio-active materials to the environment will be due to the release of icw level radioactive vastes; that is, from controlled releases of radioactive gases, air-borne particulates, and liquid wastes. This activity, if it can be detected at all, is most likely to be found in the air and water beyond the plant where these g materials are dispersed and diluted by stream flow and wind. Air and water are therefore considered as primary samples. They serve as one of the earliest in-dicators of change in environmental radioactivity levels. Samples of secondary significance, in this regard, include river bottom and lake sediment, vegetation, fish and animals, and milk.
/h'"'
N . .
J\
f .l 'h Q g> , 'Q
'1 .
7; yhkJ% .l.% ; . gp (i
2-9 0 '
gc;.7 p
- 3314
2.7.2 THE PRE-OPERATIONAL PROGPX1
]
~
Table 2.1 describes the pre-operational environmental radioactivity monitoring program for the Oconee Nuclear Station. It lists the type samples, sampling locations,and the collection frequency. In general, the samples are counted for gross alpha and gross beta radioactivity. Gamma spectral analyses are also performed to identify the radionuclides involved. Specific analyses such as for tritium in water, cesium-137 and strontium-90 in milk, water, fish, and animal samples are also performed. The measurement of gamma dose and dose rate is considered as an appropriate sample to determine the radiation background of an area as well as to measure the effects of gaseous activity released during the operating period. Thermoluminescent dosimeters, environmental film badges, and beta-gamma survey instruments (geiger counters)~ are used for this measure-ment.
Criteria for the selection of the various sampling locations were as follows:
- 1. Water For comparison purposes water samples are collected:
(a) Upstream (b) Near liquid effluent release point (c) Downstream of Site and Exclusion Area Particular emphasis has also been given to water sampling to evaluate the effect of the filling of Lake Keowee.
- 2. Airborne Particulates, Comparison of on-site vs. off-site locations Rain and Settled Dust near towns and populated areas; consideration given to prevailing wind direction.
- 3. Radiation Dose and Comparison of on-site vs. off-site locations Dose Rate near towns and populated areas; consideration given to prevailing wind direction.
- 4. Silt For comparison purposes, silt samples are (River and lake bottom collected:
sediment; filtered solids from municipal (a) Upstream drinking water supplies) (b) Near liquid effluent release point (c) Downstream of Site and Exclusion Area
& 5. Terrestrial Vegetation Comparison of on-site vs. off-site locations; consideration given to prevailing wind direction.
- 6. Aquatic Vegetation, For comparison purposes, samples are collected:
Algae and Plankton (a) Upstream, from Lake Keowee (b) Downstream, from Hartwell Reservoir 2-10
/
- 7. Milk From local area dairies within 10 miles of site.
- 8. Fish and Animals Sanples are collected in accordance with the recommendations of, and in cooperation with, the S. C. Wildlife Resources Commission from:
(a) Lake Keowee (b) Exclusion Area (c) Hartwell Reservoir
- 9. Miscellaneous Investigation of special situations made to provide program flexibility and extended coverage; such as may be required due to nuclear weapons testing or unusual fallout conditions. Includes study of Lake Keowee
. tributary streams and modification as lake fills. Investigation of reported deposits of uranium or thorium in area of plant.
The sampling stations were established in the Oconee environs at the end of 1968, and a laberatory for the analysis and counting of the samples was also established at that time. The laboratory equipment includes a low background gas flow porporcional counter for measuring gross alpha and gross beta radio-activity and a 400 channel gamma scintillation spectrometer (multi-channel analyzer). In addition, some samples are sent to commercial laboratories for
~
analysis.
The full scale environmental sampling program was begun in January, 1969. Thus, two years of pre-operational monitoring data will be obtained prior to the opera-tion of Unit 1. Water samples from the Keowee and Little Rivers which flow by the site'and well water from private residences in the area have been collected, analyzed, and counted since late 1966. The results of this eatlJ sampling as well as the results for the first quarter,1969, are shown in Table 2-2.
The pre-operational environmental radioactivity program for Oconee has been discussed with the South Carolina State Board of Health, Division of Radiologi-cal Health,and the South Carolina Pollution Control Authority. The U. S.
Government Fish and Wildlife Service has also been advised of the program through their district office in Atlanta, Georgia. In addition, the program was dis-cussed with the South Carolina Wildlife Resources Department. This latter department is cooperating with Duke Power Company in regard to the collection of fish and animal samples. They have made recommendations as to what specimens
& should be collected and are supplying fish samples from the Hartwell Reservoir and Lake Keowee. They have also issued a special research permit to Duke Power Company for the collection of animal samples.
The results of the environmental radioactivity monitoring program to date are comparable to those reported from throughout the country by the U. S. Department of Health, Education, and Welfare (Public Health Service) in their " Radiological Health Data and Reports," for the same period. It is of interest also to note
, that radium daughter products have been observed, as a result of gamma analysis, i
to exist in considerable amounts in deep well water. Further investigation has shown that this condition seems to be peculiar to the. Piedmont area of the
- Carolinas.
2-11
'ee
)
2.7.3 THE OPERATIONAL PROGRAM The environmental radioactivity monitoring program will continue during the operating period. However, the operational program will be modified as indi-cated by experience, particularly by the kinds and quan*.ities of radioactive liquid and gaseous wastes released, as well as by environmental monitoring results. Prior to initial operation, the existing sampling station within the Exclusion Area will be supplemented by others in locations where the highest ground level concentrations of radioactivity from station vent. releases are expected to exist, based on site meteorological studies. Thermoluminescent dosimeters will be used to measure radiation dose at the station fence and at significant locations throughout the Exclusion Area.
Various authorities, including the Federal Radiation Council, state that the extent of surveillance activities should vary in accordance with environmental radioactivity levels. Therefore, additional monitoring stations will be es-tablished, both on-site and off-site, or the frequency of collection of existing samples will be increased, if the quantitites of radioactive waste effluents approach significant fractions of the average annual limits. Also, existing 4
sampling locations may be supplemented with continuous airborne particulate and iodine samplers or continuous water samplers if such sampling is indicated by waste releases. The extent of sampling may be decreased if warranted.
2.
7.4 CONCLUSION
The environmental radioactivity monitoring program for the Oconee Nuclear Sta- ,
tion is conducted by the station Health Physics Supervisor who is assisted by the station Chemist. The program is directed and reviewed by the Duke Power Company Staf f Health Physicist.
Environmental monitoring results will be correlated with information on station radioactive waste releases, site meteorological data, and radiological ~ controls and with information obtained from the installed process radiation monitortug sys-tem. Results will also be compared with published information from the national radiological surveillance programs reported by the U. S. Public Health Service and with environmental monitoring reports of other nuclear installations in the area.
Results of the Oconee Environmental Radioactivity Monitoring Program will be made available to the State of South Carolina and to the Federal agencies mentioned above who have a direct interest and concern in these matters.
It is expected that the results of the Environmental Radioactivity Monitoring a Program for the Oconee Nuclear Station will demonstrate the effectiveness of plant control over radioactive vaste disposal operations and of compliance with Federal and State regulations for the disposal cf these materials.
2-12 p a
g)g M h }M Q - h
)
. $ a $d a v.C E M( 0 E#) )
aO eOh L (
0 UMeU'd )
K O S S E c< (
u5$n 3" dU )
OE e .I" EU0"E J (
0 0 0 0 0 0 0 0 0 oI.a . xYS* UN3 )
EIU$ s0 om (1 0 0 0 0 0 0
)
uU8E . c0Y$I> H( 0 0 w0UE2A . e3$YE> )
C Q 0 0
(
)
3a3U$" ' I< F M M
(
)
C0e ,*5 iO%* 'c7a (E M M M A
=I.0 .$&" ' E E $" %m )D (
+ M M
M A A M M A A A
+
H mII* t% ' %m )C
( M M AS5 u3 0 . o. I.O M %m )B
( M M
,N4U4 s . U %m )A (
0 .
)
k e
e r
) C
. k
) e d k )
e k e e r k e e C o l r e ) o a Cr d n r n C e i C a r t a (
C a w e C d o l ( e a e r p n n C C m e d i
t
(( o m i C d r L
c e
W e e i B t n n r A n .
d d e B @
M n E i i h m.
r R A y C o .
r r B B 3
8 ) (
W @
y n G c ) S 1 e . w if O n M 3 3 60 d 0 y H 3 0 R e ( 8 8 . i e. 3 w 9 P P u 1 1 N. 1 y S k 1 H e I q u 1 w a ) e 3 V G e r w w y a H e t . 1 e v - y N N r h e e f e . t n C 1 e o K w E I F t N N i r y n i i 1 w e t 1 R c A v o s . p o K r l
- L O ) n n pe I o e S S e i n d 2 A T A o o n n e p l e K n o o r N I ( S o n o it p a v n o v a e O N e e e i o i O t o o m n r i
t y
l I O - t t - n s t S ( i e -
e o y e a b T M i i i u m a p K l c r s e
a A e S S e t l e t f 6 s o e y w o t
S c T R Y M 0 A l t s c t l m S o 1 o e o K r e R i E T p f f x o Sa le w N f i i t k h t b P I - - - m o o S x E t b t .
I a c & e e o t u f O V y
a E a u g y l L S g N f l l S O
- I y
S h h f n . f S S e w a .
d o P e E T l r t t o 3 t o W f y h R C y r l f e r r 8 i
h p i i r y h
c R. r i f y v t c
e f .
o t n P A O
l h
l a
o t n N o o s N iu 1 t e . o D E. .
d s l o l t L B W. n lp r i n
, E I E t
r u e e e n i R e o m p i l ( . o p i o t w l o e p t W N. l uI l J e E D D n a n p C e e d k o e N E h i h M u d m a o S B N A O o u n Y r r a a e r c M c S e a . . r e O R C M O A T s d d R L e c i . ,
n S e n D 7 t t o r k
- C r i i m n F t i a 5 c r o 2 M M e e a .
O o r r e e d e M M r h n e d l t t t C C.
t B B l c i d . B 7 ig o t n l . 5 5 e a n 4 i u r i l 5 0 c a a i y 7 2 M W I .
s t d Ml o B s o H O W b p w S S.
i s n e e V 4 8 : A S t 3 3 n V 1 2 1 K @ R a I
o l : : n l y i : l e a : o a t t :
m a e c y s r r a e e h w e r m t e c t l l o n w e n b o i a a e e e l e i
_ L S S W K S N C C L
~ o N 0 3 4 5 6 7 8 9 1 3 4 5 6 1 2 1 2 1 2 1 3 4 5 6 7 1 2 3 4 5 2 e 1 1 2 d 0 0 0 0 0 0 0 0 0 1 1 1 1 1 2 2 2 3 3 3 4 4 4 5 5 5 5 5 5 5 6 6 6 6 6 6 7 7 7 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 3 3 C 0 0 0 0 0 0 0 0 0 0 0 0 0 0_0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 -
o000000000200000 _
yHW
o
~
. e . .
>. t (Cont'd) % C 4
- a. .= -
Table 2-1 5 >. 3 s2 O e u 2 - e t 4 . *% .
OCONEE PRE-0PERATIONAL ENVIRONMENTAL c $ I U u E % I E*
- RADIOACTIVITY MONITORING PROCRAM S S $
E 3 U E- 3 .e U
% . t 4 A * "
. a a = T 3' E >. 24 E -
c00E I " 3 C 0 i
e e c '; 2 . 20 E Monthly -M quarterly - 0 Freque s O y
f g gl fg f f3 g g o, E
3
^"""'IIY -^ 5, 7 ,
i Type of Sample - (A) thru (II) o y
o y o ye y o
g u % R t Od f 5 5
- g g g Code No. Location [A) B) (C) (D) (E) (F) (C) (11) (1) (3) (X) (L)_ (M) 009 Six Mile. S. C.- Microwave Tower 11wy. 137 0 009.1 009.2 010 Pickens. S. C.- Branch Office Yard M 0 010.1 010.2
- Oil Floating Station: Subject to Chance with Conditions 0 01].1 011.2 012 Anderson. S. C.* Water Supply M M O 012.1 012.2
- y 013 Ilartwell Reservotr: 5.8 Mt. South of Keovce Dam 0 1 013.1 -
$ OL3.2 I Notes 1. 000.3 and 006.2 will be sent to outside services for NY analysis for 3H and 90S r (2 gals. each location). k )
- 2. Fish speciments will be collected alternately from Lake Keovee and Hartwell.
{ g
- 3. 001.3, 001.4, 005.4, and 005.5 will be collected once per year during rainy season.
M Note Location numbers that appear in Table 2-2 which are not shown above are results of special investigations at the general location indicated.
b W
W
. u.
- w /
- - . _ _ . - - . , _ _ _ ~ - . .
TABLE 2-2 StHMARY OF PRE-OPFRATIONAL MONITORINC Rest'LTS
- 1. Water Suspended Solide Dissolved Solids Totti Activity Tritium pC1/1 pC1/1 pCi/1 pC1/1 alpha beta alpha beta alpha
~
beta
(< 2.7x10-3=3.D) 1967 Keowee River At Site N.D. - 4.73 1.16 - 24.09 N.D. - 2.17 N.D. - 7.67 N.D. - 5.03 5.58 - 25.57 rante 2.02 8.21 0.75 3.20 2.78 11.41 averar < 2.7x 10-3 1967 Little River At Newry, S.C. N.D. - 3.19 N.D. - 6.80 N.D. - 5.36 4.59 - 16.73 0.34 - 6.74 6.11 - 20.18 rante 1.03 2.52 1.85 10.17 2.88 ,
12.68 averat' <2.7x10-3 1968 Keovee River At Site N.D. - 5.42 N.D. - 9.36 0.96 - 21.70 8.00 - 3P.20 1.45 - 23.78 11.19 - 43.57 range 1.31 4.52 5.75 17.75 7.04
- 23.33 ave rale. < 2. 7x10-3 1968 Little River At Newry. S.C. N.D. - 2.17 N.D. - 12.07 0.28 - 3.29 6.25 - 30.14 0.28 - 8.68 7.28 - 31.81 range 0.82 5.22 2.30 13.30 3.82 19.70 averafj *2.7x10-3 '
B. Open and Deep Wells at Residences Designation Year Y On-Sitaand in Surrounding Area H
- on-Site 1966 3.30 - 5.92 11.86 - 28.58 rante (3 locations,from 4.16 17.74 averagt 6 residences then existing)
Surrounding Area 1966 2.17 - 4.96 10.26 - 25.70 rance (3 locations,from 3.72 16.20 average residences still
, existing)
Y
- On-Site 1 1967 N.D. - 11.94 2.69 - 26.97 rante b 4.57 16.17 aversge <2.7x10-3 b---d On-Site 1 1968 N.D. - 33.64 9.85 - 62.46 range 7.82 25.00 average
~
h )
On-Site 2 1967 N.D. - 7.60 1.36 - 19.96 rance 2.70 10.40 average '2.7x10-3 b
On-Site 2 1968 N.D. - 4.91 10.17 - 34.78 rance 3.00 20.00 average Note 1. K sve measurements at 90% confidence level, based on natural uranium a*pha and " apparent Ceslum-137 beta activity." calibration standards,
- 2. N. D. = non-detectable
l i
TABLE 2-2 (Continued)
SUMMARY
OF PRE 4PERATIONAL MONITORINC RESULTS Averages For First Quarter 1969 ,
Camma
- 1. Water suspended solida Dissolved Solids Total Activity Analysis Results pC1/1 pC1/1 pC1/1 alpha beta alpha beta alphs beta Residences 000.1 - - - N.D. 3.55 Indications of 000.2 - - - N.D. 2.85 Radium daughter creduct s Municipal Water Supplies 006.1 Clemson-Pendleton raw water 0.12 (2) 0.64 (2) 0.08 (2) 3.80 (2) 0.16 (3) 4.78 (3) background finished water - - - - N.D. 2.62 s
012 Anderson raw water 0.08 (2) 0.49 (2) N.D. (2) 4.04 (2) 0.05 (3) 4.30 (3) background finished water - ' - - - N.D. 3.44 e Rivers and Lakes M
m 000.3 Site 0.11 0.07 0.83 (2) 0.08 3.20 (2) 0.13 3.56 (3) background 001.1 Sales 0.30 (1) 0.08 1.98 (1) 0.21 4.96 (2) background 001.2 0.15 N.D. (1) 0.08 1.90 (1) 0.29 2.63 (2) background
, 005.1 Newry 0.52 2.59 (2) 0.17 2.89 (2) 0.81 6.87 (3) background 005.2 0.16 0.98 (1) 0.08 1.90 (1) 0.64 4.93 (2) background 005.3
- 0.20 0.56 (2)- 0.08 3.10 (2) 0.29 3.81 (3) background 006.2 Clemson 0.24 0.45 (2) 0.21 2.75 (2) 0.44 4.19 (3) background Total Activity f 's o c1/ m4 0 l
- 2. Rain and Settled Dust Indications of b N fission products.
002 Walhalla 0.02 5.81 possibly C9 14 010 Pickens 0.03 6.73 Pr d '4 -
3, Terrestrial vegetation pC1/g b
u
)
. alphs beta 000 Site 2.38 558.6 Appears to be K 40 005 Newry 006 Clemson N.D.
3.06 1006.5 647.2 QJ NM b
V ,
p . .
TABLE 2-2 (Continued)
StHMARY OF PRE-OFERATIONAL MNITORINC RESL1.TS Averages for First Quarter 1969 Camma Total Activity Analysts Results a
pC1/g alpha beta PC1/3
- 4. Plankton 7. Animals 005.3 Newry 3.70 22.86 Appears to be K " 000 Site S r bone 006.2 Clemson 9.27 38.33 22.52 1 0.45 (Rabbit)
Cs I37 muscle 0.50 1 0.01
- 5. Sottom Sediment 8. Fish 3,50 c,137 %
000.3 Site. O.34 0.64 t,ake Hartwell 001.1 Salem 0.46 1.90 005.1 Newry 0.23 0.91 Carp (Adult) 1.52 1 0.13 005.3 1.36 7.12 0.08 1 0.02
- 006.1 Clemson 1.04 3.In 1.argemouth Bass 012 Anderson 1.19 1 0.07 0.36 1 0.04 0.61 2.4V (Fingerlings)
Y Cizzard Shad 0.3510.11 0.39 1 0.02
[ (Fingerlings)
- 6. Radiation Dose & Dose Rate Initial data indicates a gamma dose rate 9. Milk 0C1/1 pCf/rCa of 0.01 mR/h and a dose of approximately 000 Site 21 mrem /90 days for all locations, measured Cst 37 Srso Out Salem at three feet above the ground.
002 Walhalla 002 Walhalla 11.4 + 1.9 13.5 + 1. 7 Sr'8 11.9 + 1.5 003 Keovee (High School) ~ ~ ~
004 Seneca (Mem. Hosp.)
005 Newry g g 006 Clemson 007 Central Results of gamma analysis show natural K"'
as the predominant activity.
( )
008 - Liberty OIO Pickens 011 Lake Jocassee Area NOTE: Samples in categories 1 through 5 were measured at the 90Z confidence level, tased on rad +t; alpha, and " apparent CesiumI37 heta activity." calibration standards.
bh F.D. = non-detectable (1). (2), (3) refer to numbers of samples averaged.
. r
= . . , ; .
.@i .
g
SUMMARY
OF RESULTS RECEIVED TO DATE ON FISH MD t/ILDLIFE SAMPLES FROM OUTSIDE VENDORS ; i FISH pCi/g wet weight
% 3:
t, Date Collected Description o Locations Results Sr-90 Cs-137 ;.
' t 2-25-69 Carp (Adult) Lake Hartwell Homogenized Sample 1.52 1 0.13 0.08 1 0.02 Bass (Fingerling) " "
1.19 1 0.07 0.36 1 0.04 Shad (Fingerlings) " "
0.35 1 0.11 0.39 1 0.02 s
5-26-69 Carp (Adult) Lake Hartv 11 Hom genized Sample 0.7410.01 0.14 1 0.01 Bass (Adult) "
1.15 1 0.01 0.0210.00(4)
Shad (Fingerlings) " "
0.21 1 0.00(2) 0.02 1 0.00(3)
I 4
iT e+
. WILDLIFE .
3 fg M Date Collected Description F +3 Location Results - pCi/g Cs-137 { ,i dry weight vet weight .4 3-19-69 Rabbit t iid y Exclusion Area Tissue 0 50 0.01 d
- 0.15 1 0.01 i:P Y pCi/g Sr-90 ,j ashed weight wet weight i r
. . .'t .c.-
9 ' I. .)
- Bone 22.52 1 0.45 4.19 1 0.09
. J '," ')
./,.,.'I, .(f
, , ^
w 1- y. h r
)*
sq y, M' U; DCC1 b) !:1 ~4 - - - - - - -
i dl-a Q .! ;
~~
NJ : ! 2 u if r q'.
\,;# [, *
- ', /
.y/
l h, <a esy i
_ f g[.k' N ,
"v
ye / , , L F, ~ e f
w J w ]u
? (
t-=a
' yc 2 ) *, ts! 'l?
HYAg,9 $3 R;:stved w,ttr Cated N'Y-N ggg OCONEE NUCLEAR STATION .s File cgjMMARY OF INVESTIGATIONS OF THERMAL N Regulatory EFFECTS OF COOLING WATER DUKE POWER COMPANY July 25, 1969 Comprehensive studies of water behavior are, and have been, an integral part of our power plant engineering design for hydro as well as thermal stations. The results of
, our studies for each successive thermal plant are in the form of engineering calculations of simulated models of water bodies to forecast limnological, hydraulic, and thermal behavior. We have not had occasion to convert these studies to a form suitable for published reports.
For large thermal stations, we have been using our hydro lakes as a source of cooling water and for heat dissipation. in order to more fully understand the many inter-relationships between power generation and the many other uses of water resources, we established in 1959 a full time department cons,isting of administrative, laboratory and field personnel to conduct research on our hydro lakes. These efforts have been supplemented with valuable help from a number of consulting limnologists and biologists.
The results of these investigations have served as direct input to siting decisions and engineering design of our new power plants of all types. From the inception of this program ten years ago and continuing today, we worked very closely with the pollution control and the fish and wildlife agencies of North and South Carolina.
With regard to Oconce Nuclear Station, we did our thermal pollution homework in 1964 hafnre dactilnn en nrneaad with tha Kenwea-Tnwnwav Prniert nf which nennaa is a nart Using the research results developed by our water resources research group, plus the work of others in this field, a thermal model of Lake Keowee was constructed ter each month of the fear for examination of various combinations of heat dissipation. These studies, using criteria confirmed by fleid measurements or existing lakes in the area established that Lake Keowce could readily dissipate cooling-water heat from 7000 mw of thermal generating capacity distributed among three si tes. Two future sites would involve dissipation from the lake's surface, and the third site, selected for Oconee would utilize the heat sink of the hypolimnetic waters during the summer. Cooling water for Oconee Nuclear Station will come from the bottom of the lake under a skimmer wall across the intake canal at sufficiently low velocity to prevent breaking up the lake stratification. This water will be of such low temperature that, af ter the addition of heat in the condenser, it is returned to the lake below or near the naturally occuring summer temperature of the lake surface. A similar skimmer wall has been in successful service at Duke's most recent steam plant since 1965. As is done at our other plants, when Oconce goes into service, field tests will be made to coinpare results with the predicted behavior and serve as a further basis for the two additional thermal plants on Lake Keowee.
- Our application to the Federal Power Commission in early 1965 for a hydro license covering the Keowee-Toxaway project specified that one of the purposes of the Keowee hydro development was to serve as a source of cooling water for a 3000 mwe nuclear plant at the Oconee site, then known cs " Site L". We made it quite clear that we would not undertake the hydroelectric development unless the !icense specifically permitted this cooling water use. Our studies showing its compatibility with the environment were reviewed with the South Carolina Pollution Control Authority and the U S Fish and Wildlife Service to their full satisf action. Then Secretary of interior Udall retained Dr C J Velz and Associates to make an independent study. Their report issued in April 1966 was entitled " Report on Waste Heat Dissipation in Streams, 3314
2
, Ponds and Reservoirs with Application to the Duke Power Company Proposed Keowee- l Jocassee Developments", and was submitted by these consultants to the U S Fish and
- Ulldlife service in Washington. The report was in substantial agreement with our
- findings and Secretary Udall on April 7 1966 wrote the Federal Power Commission concluding
"In consideration of the cbove findings, We conclude that the thermal eff ects of the Site t
'L' 3000 MW plant would produce no detrimental effects upon the fishery resources within
! the Lakes Jocassee or Keowee.", and further, "We do not expect that this discharge would i
- affect a sufficient amount of the surf ace acreage of the reservoir to be deleterious to j . the recreation resources." The FPC license was then granted in September 1966, after i which we filed an application with the Atomic Energy Commission for the Oconee Nuclear
- S tation construction permit in December 1966. The point of this narrative is that we '
l . emphasize doing our environmental homework in advance of deciding to proceed with a p roj ec t.
4 Many of our activities have been reported in the literature, and the following enclosures
- may be of interest.
s
- 1. Copy of W S Lee's testimony from the record of Hearings before the Committee on
{ Public Works, House of Representatives, 91st Congress, First Session on HR4148 j and Related Bills.
i
- 2. " Diffusion of Cooling Water Discharge from Marshall Steam Station into Lake Norman," by R rred Gray and J Ben Stephenson (ASCE National Meeting on Environmental Engineering in Chattanooga Tennessee ~, May 13-17, 1968)
- 3. " Water quality and Power Plants," by Austin C Thies (General Session of eel Annual Convention, Portland Oregon, June 10, 1969)
< . , 4. "! prever:nt in qur!!ty er P.:: cry !- O!::h:r;:: thr ;h Turb;re; er Teilreca Aeration," by W S Lee (ASCE Specialty Conference, Research Needs in the Civil Engineering Aspects of Power Panel on Water Quality Control, Pullman Washington, j September 11-13, 1968)
] 5 " Nuclear Power at Oconee," by W S Lee and W H Rowand (American Power Conference,
- Chicago, Illinois, April 25, 1968) a
- 6. A brief description of a very comprehensive physical and biological study sponsored by the Edison Electric Institute on our 32,500 acre Lake Norman in the vicinity of our i
Marshall Steam Station. Due to the many different interests and disciplines involved in this project, each participant agreed at the onset not to make individual " piece j meal" releases of Interim findings or results. Enclosure #3, the paper by our Mr A C Thies, also describes some f acets of this project. Duke Power Company's I
costs in this study are ' estimated at $100,000.
e l W S Lee i
i, i WSL/s l
7-25-69
7pg;!;=>w
'g*g j (d,<1 j' $-$ 'c' 2?O
- ' ' ' 2. b, ,
f
.. .. Rasived w/Lir Datd 'd l' #' . . ,
i gep!:terj File Cy. -
f I FEDERAL VIATER FOLLUTI3i! COHTROL -
i a l ACT Ai,iEUDi3ENTS 1939 y.
3: 1,
^
s on-n -
&z.: . fl e/ :
- .' i .
e .
O-- -l HEARINGS Bl POllE TJIU g COMITTEE ON PUBLIC WORKS
' HOUSE OF REPRESENTATIVES NINETY-FIRST CONGRESS FIRST SESSION ON H.R. 4148 and Related Bills TO A11END THE FEDERAL WATER POLLUTION CONTROL ACT, AS A11 ENDED, AND FOR OTIIER PURPOSES t
FEBRUARY ::0, 27, MARCII 4,5,0,2003 Printed for the use of tbo Committee o't Publ'c Works
.~;
e **
U.S. C0 7ERNMENT PRINTING OFFICE 26-212 O WASl(INCTON : 1969 O
em Y 'NM 88&4M**e 4 4 % 4 % $ gweeuD 4 y e M es$a q pw e a,% i g , , , , ,g, , _
g 3314 l
- m. .,
i 53'T 1
and their steam clectric power producing applicant a in some arens Ihat.
I pnerisions. II.fi. should heed the rtrong objections to permitting liecusees to heat
- nt the navigable they
- .e. a :e-mila mne , up t he waterways. Such acquiescence is ma suf'icient-as in the caco
' of the Federil l'ower Commi--ion, we feel there shoubl be written Thh is a desired jna ut to S. L We into the law, perhaps a strengthening rection 11(b) of II.R.4118, die-and a prescription for nmn.-ure< to be taken piometion of our tating a review, study,
,-iderable cWeet on in order to comply wit h established water quality nandards of all a . far x award as license applicants by State and Federal conservation agencies, which
! eni.:nd to le miles would help solve t his problem.
,rns a < " willfully" The Sport Fi.shing in titute wishes to go on record as solidly behind
- the intent and purpo-e4 of II.R.414s as being in the greateit pt.blic it.hi(1) and (2) intere.st to America. with con <ideration given our . suggestions, noted ed application, or antrengthenine nwasures.
above,IIi.xrxnc.
Mr. Mr. William S. Lee, vice president engineering, Duhe
- e munor or '
Power Co., Charlotte, N.C., repreeenting Edison Electric Institute.
1 .rnox ;
STATEMENT OF WILLIAM S. LEE. VICE PRESIDEUT ENGINEERING,
,1m iv-ources and a DUKE POWER CO. CHARLOTTE, N.C., REPRESEUTING EDISON ELECTRICIRSTITUTE 11 r lli t m i i>nchpl!!icatins 9 Mr. Lun. Mr. Chainaan and members of the committee, mv name is f !b i [i [t
' William S. Lee ami, I am vice president, engineering of Duhe Power Co., headquartered in Charlotte. NC. I am appearing here today rep-4 (SES) and what "?nting the Ed,en Electrie Institute. Tms testunony, will review ienta can be deter- briefly the projected coohng water require,ments of electric generatmg perature standard, plants; the methods of providmg this conhng and what we know nh<mt
. ially t of IDG3 j 1.2 de:'. ca th e."r"+" wa+ * '1" "~ 1-noe thqt alrnndv ewt.< for
' report and recom, regulating t hen,' mal discharges; and,'of Fpecial intereft to this commit-ate water polhitinn tee, what utilities are doing these future power plants m,tofully a manner seecompatible to it thatwith coohng the en-can he pr,ovided th apjdicable water ,
vironment and at the same time couluette to makmg electricity avail-3enmt hv any Fed- able to the consumer at the lowert po.ut,lde cost.
icem as it rone to us
- The trend of powerplant eshetencies s important to any project, ion of i Fish aml Wildlife f""
1 ish desired controls ach.imievedcochng water remarkabic needs. Ovet unprovements 3
tl e years, m, powerplant the util,ity elheiency, and itmdustry is has State mechanism to ich application for nasona the nat,bic ional ato expect this trend to contume m the futtne. For example, vision, particularly - Power Conum,verage powerplant eihetency as reported by the Federalssio B.t.u. to the cooling water for each hilowatt-hour produced. Today,
, g we must live wit h, the average fossd powerplant discharge,s about 55 percent of the 10:13 must be desienated heat per kilowatt-hour. As this conumttee has heard, the currently hnology is ade unto available nucicar powerplant usmg a light-water reactor wdl reject oling towers, clowd aarentiv return dis, abcut 50 percent more heat to the coohne water per kilowatt-hour than 4
'. Certiin!v it costs the mojt modern fossd fuel plant : however. this is only 10 percent more hen pther' forms of heat rejection
' service today.perkilowatt-hour than the average of all, powerplanis inLo c visibic wastes and
.inms, as should the of light-v.ater nuclear phu3ts as well as fossd plants, plus the advent of breeder-typo reactors with much higher etliciency, are expected to ok n~very docmatic resume the downward trend of heat Fejection to cooling water per
- te water'discharees, kilowatt-hour. generated. h eglect mg t he possibility t hat generat ion will n 'become practicable by son 3e me
- us of direct convennon which rej,ects little or no heat to the environunent, it is reasonable to assuma that by l'ical convincedwastes.
the AEC Public g
. l f'
+"*** _ _ _
- g. .p- - - P'
, _ . . . . _ . - . - - - - . . . ~ . - . - . ~ . - . - ~ . . - - - - .- -. - ~.
i mo o q"T' I
5SS wo w Jka l the year cono the national average thermal plant. ediriency will unich In t!a .
the cilicienev of todavN mo.l. modern fo -il plant. This expected edi- conhne t.
{ ciency g.iin'will reen'h in a 2n. percent decrea-e of heat rejected per which il
, kilodatt-lumr compar.d to todayN average experience. Haded on this velocity ,
i assmnption and nann: a typical 1G* F. temperatinu rire of the cooling fl,me at,.:.1 water paving through the steam condenFers, the average energy pen. sun:la r h. .
. crated by 1.s hillion kw. of thermal capacity expected in 2000 will once d.,. :
require 500 billion gallons a day of cooling water. to the c..e f As has been outlined to this conunittee the heat load added to this cau-c a c..-
cooling water can he rejected to the tuvironment by natural surface the con.m cooling in the receiving stream, river, lake, or tidal water; or can be re. very q m i jected by a cooling tower to Ihe atmosphere. ofHdcN]
} Where. natural surface cooling is used, the heat is dicipated by a of the pre .
colnhination of radiation, conduction. advcetion, and surface evapora. any avail tion. Of these, only rurface evaporation causes a consumptive loss of wnh the er 4
[ water from the w: iter courre receiving the warmed water. The testi. Now lef 9
' mony of witness Kolflat' before this committee agrees with the find. achievice :
ings'of the U.S. Geoh,gical Survey 2 in their experiments on Lake water. The Hefner to the c!Tect that. in natural cooling about one-half the added thesucu ,.
heat is dissipated by evaporation and the balance is di+ipated hv the henhh and other nonconsumptive mechanisms. Under average weather conditions welfare in '
and with a typical 1G* F. rice through the condenter.e, the surface . manage:m .
evaporation portion of heat dissipation will cause a consumptive loss to make e' of about threc. quarters of 1 percent of the flow pawing through the . indu<
conden.ers. H3 the year 2v00, this flow is e-timated to be 800 billion '
qualn, try is gallons per dar, and if all this heat is disipated in the natural water 1 oloc'v.ywire ce courses, it wilf result in an evaporative loss of about G billion gallons and the de. ,
one day. mvestors w
[
In contrast, we see that the cooling mechanism in a cooling towet. ; blicht !
is quite ditrerent. Just as blowine on your wet lineer cools the fineer. ,
For ma:.
a coonng tower uses high-velocity an to cool by evaporatmn without j the flesten .
- 1 significant benefit. from the other cooling mechanirns. For the same
- mg plams I
average weather conditions and 1G* F. ri3e used in the above example. ! based large a cooling tower will evaporate about 1.5 percent of the throughput i Upper te:.
water. In addition, another 1 percent of the water is lost by " drift." j selected. wi which is the term applied to the small unevaporated water droplets : contrary en that are carried away m the airstream. Thus the total consumptive loss has been fu of water through a cooling tower is about 2.5 percent. If cooling towers it did not .
were applied to all of the catmeity in service b may be ed.
cooling water of 800 billion callons per dav.y we willthethrowyear awar 2000 intorequiring- several miF
' the atmosphere about 20 billion gallons p'er day which is 14 liillion biolori-t< :
gallons per dar greater loss than wouhl occur if we let nature do the heard testi
. work for whi'ch nature is so ably equipped. With many of our bad, alt).o::
towns and cities alreadv seekine additmnal sourecs of water supply cont rast. 1) to meet the need< of oiir rapidly growing population, it woubl lle j poin,ted "a foolhardy to waste 11 billion gallons per day wluch is equivalent to the ,
speci,es aly water sultply needs of a population of 110 million people. Further, viewmc l>r.
large coolmg towers will often cause heavy crtmnd fogs, with resulting of envirnm public discomfort and inconvenience, if'not hazard, to air trallic. C n
, h,arolina:
lsperinida 1Noldat.+statement Commute on Puhuebefore the Subcommittee workt reb. c.19cs.. ou Alt and water Po!!unou of the Senate fo'nid in P'.
. *
- narbeck. G.1: art, Jr U.S. ocolucical Surtcy Circular No. OS2.1953.
- 3!!'.ucJ+re 19C7 tt."
1 k
~ ~ - - ~ ~ ~ -
~. - . . ~ - - . - - . - - . - . ~ -
5S9 _=>
mcy,will match In the early staces of comeptual development is a ditTerent type is expected etli. cooling tower emploving humlreds of Ihonsuid, of small Iuhes tbrouch mt rejected pet- which the cooling wiiter would be paned in a scaled syrtem with high.
. Ilated on this ' velocity air blown mer the outside of the inhes to n move heat and ;
e of the cooling thus avoid consumptivelou nf water.This woubl operatc on a principle ige energy gen. similar to an enormo's automobile nullator. It has been estimated that, ed in 0000 will once developed. this drv. type eruding tower will add ri to .'n percent.
to the cos t of a 'powerplant. further raise the coat of its operation, and d added to this cau-e a conemmtam enh-tantial increase in the co<t of electricity to natural surface the con <umer. Onm developed. the dry type cooling tmver may find cr; or can be re. very special applications but it slumld nol be generally applied because
, of its expen<c to the public. Thue, the arbitrary we of coolmg towers
' of the pre =ent or future type is not the panacea if alternative solutions dissipated bv a urface evapdra. ! are availabh. the are in'the public interes.t and ot' crwiin compatible umptive loss of with Ihe environment.
- ater. The testi. Now let's look at what utilities have donc and are doing toward s with the find. achieving that compatibility with environment with respect to cooling i iments on Lako ' water. The utility indu try fullt under.-tands and appreciates that
. half the added the success of anv' electric compan't depend < directiv upon the economic issipated by the henith and welfiire of the people'in the area it rerves, and this public ither conditions welfare in turn requires freedom from pollution and wise and judicious t
ers, the surface managem.mt of environmental resomces. Ilecognizing there is no way onsumptive loss 4 to make electricity without involving the environnient, the electric ne ip ch the indiptry is deeply (involved in the areas o,f thermal discharg,es, water o tie t. Inlimn qua my com roi, mu er re-nu ten iv.-eaien, u n i,..n um.n wus.. ..m-e natural water t oloe'r, wire =prend public recreation, soil conservation, flood control, I billion gallons ( and the development of fish and wildlife facilitic.s. IIow attractive to investors would be an cicetric utility serving an aren stagnated by a cooling tower : blicht i cools the fmeer, For many years, this interest in the environment has influenced oration without ' the design and openition of co< ding wate: facilities at steam generat-4 For the same ing plants. It is true, however, that the desien criteria have been above example, baced largely on empirical experience with respect t o biological etTects.
the throuchput .
Upper temperature limits of cooling water discharges have been lost by "drifr!' selected, which, from long observation, do not hill fish, and on the
-water droplets : contrary enhance sport ficliing. Although as a general rule this method onsumptive loss l' has been fully succesful to date and compatible with the environment, i cooling towers it did not recognize the possibility of subtle changes in biota that renoo rerpiiring may be effected by thermal discharges mitil the pioneering wo.rk by
.hiow away imo '.. several utilities a few years ago. There is diangreement nmong aquatic 4
- ch is Ii liillion '
biolo~ists as to the etTect of thermal discharge.=. This committee has heanf testimony to the effect that thermal discharges are patently
~
t natum do the i many of our ,
bad, although any supportine evidence has not been made clear. In
>f water supply - contrast. Dr. Charles 11. Wurtz, biologi.-t of LaSalle College, has
- m. it woubt b'c pointed out* that fich food pinduction and propagation of most fish
- puvaient to the species are enhanced by water warmed to a reasonable extent. In re-
- wp!r. Further. viewing Dr. Wurtz' article, Dr. Charles M. Weiss. of the department s with resuhin- "
of enviromnental sciences and engineering at the University of North to air traille. Carolina, writts in private em e-p(nutence from which I quote with i his permi=sion,"In fact as Dr. T Turtz has pointed out and as has been
- m u erin ,s,..t. found in every attempt to carefully examine thermr.' pollution and l
L.
- t j 8 wurtt. Charlee n .-a==letant ernf**=or. t.inlace. f.aSa11a Concer. Philadelrihin. Ps
Silsunderstandings About Heated Dhcharget." Industrial Water 1;ngineering. September 3
10GT.
N w e- n--
7 _.
D"O CD l i
+ 500 6i5 Lh\}N an If there is m, ,v its effect on aquatic ecologv. outside of anv hmnediate area of die. ; March 10.
c!arge, no demon,irahle eli~cets have been found. If any are shown, -
(Sintements suba they app ar in inany instances to improve rather than degrade water
- qualitv.' As evidenced hv the emwded lianks and full erceh, sports smnnsr ev en.c.m-h>Lexinen well km,w that ti-b >cek out the warmed waters near the *'
i 1 steamplant conden-cr dischatee<. In two specific case <, utilities have Mr. chainnan ana :
! conm to ngreement u it h local intere-t to help minalic <life with warmed
' l '
1 water ln one ca v, a li-h hatchery will be made po . ible with v.ater otherw,ise too cold. aud in another the oy>ter crop is to be ,mereased by sr[>N raw nian.rm, h"iu"'[-[lll
,o,pd j
6peelalir.ing in halN rr g the beneficial elTect s o f Ihe warmed enviromnent, e ntrol lu general 1 ;
We do not, however, claim that the net etTeet it either good or had, 8
" , ' , ,8;'{
{
We need facts and the im,hPtry is to take whatever steps neteenry 'N#(I.
- l to prevent large *cale environmental changes as a result, of power m.elath.u for un "s :
Conferenw.
generation.To re-olte the ronflicting views of the experts our indu-t ry. I 'on n1*o Chairr e through the Edison Electric in t tute. i ha< undertaken a ma"ivo r Uf,M[* pefj, ,7 :
, 3rttint3whl,e re-en,rch prograin to determin,e the thermal efTert < upon portunny to u part .c l
- nquatie blota. M e have asked the hmlogical esperts to tell us not mutee. We have nnt.a
! 2 what we want to hear but tell u4 the fact <. The next witnew will tell congress. mnte tw. i 1 5 the conunist(c more about this research program. Usine the fact, $7,"j'y,3p ig y,p,
! gathered from thi tprogram. supplemented as needed,hy ,Jindy of the . I appear today to .
I specific local situntmn, we are con 6 dent that the appheation of sound ! beneve thn tLue om engineering principles will permit the dissipation of cordine water- forrnance and current .
l heat in a maimer that is fullv compatible wnh the environment and that best servesIhe public int crest in ihe broadest >cnce. ;
r One of the stated purpo<es of Ihis hearine is to determine the evtent ' I think it wouhl 1 ! !
to which additior.al legi<!atii n is needed to iv.mlat e thermal discha rge.
}
Regulation of thernml discharecs has alre'.ulv heen established by
'Igr"b[o*
d N "[$ 2
] wich tne inerca-e.i t law. The Federal M ater Quality Act of 1% reqmres each of the began to focu on u.a.
}- 50 States to develop water quality standarde. Under the authority in sewage treate-u .
d
! of this net. the Federal Water PolIntion Control Administnition hai nromulented Fedend guidelines to each of the r,n States. The water [l,'f,"lSld,y,j@
ny om i,,, y ,,,a n.
f, n . ; . .-
c....c. : . 6 ;-"*d a6.o, quahty standaros m earn . une I 'rhis research ha.
The States nre holding public hearines to revise their standards to .
active agent used ha n-conform to the guidelines and submitting them to the Department >
b ""
of the Interior for appmval. Sta,ndards of many States have i,mw [r"Mlrs$'idA"n ample one comp. y.
heen approved and enforcement is underway. Others are penihne. by suponero, ite nr -
Each State standard includes specific temperatmc regulations. The<e tory. It was a uram standards apply to warmed water whether emanatine imm nuclear '
',"ur'r#Ec"t0Et.El$E["vIf plants, fossil thant..= or nonntility sources. Yet. in the face of fl 1s 3 blodegradat.itity whe:,
established regulatory mechamsm, a proliferatmn of conflictmg bicis- over the next few lation haa been introduced thnt would add redundant regulation of mmat imod rco da thermal discharces hv the AEC.hv the FPC. hv a pmiwed National Resources Council, aini,hy a prophsed National Cotmeil on Environ- j ll"lty\,d$a'$dh-f In the carir n,.u the puhhe mterest would not he served by more Icgn- ~
cause a rapid advanc.-
ment. Clearly,ing regulation nircady established.
lation duplicat quiry orovided a t.4 l
l ihank the rommittee for its hind attention. 3*E*l,"fgjy{"fr.,y '
Mr'. Dr.vrm. We hnte statements of witneues scheduled here who manufacturere were a asked that. they be subm,itted for the record at the convenience of the based products ta 1.u committee, and without objection, w.ll the staff IUc in proper order N "H "*"P" first anticir<ated. I't f".rd-these statements.
to June 30. EN5. and .
.. -. +
1 .
1 .-
- - - - - , -- --s r- - -,,
e- g - p 4
y ( )4
-- A wm.m fl ou uaL gm u.:s
., c .ve r a-an Q# s n;:.sd *v Lir Dated /l '
Regulatery File Cy.
D, I
e )w JU D
a D
%'Yh
.UU DIFFUSICII 0F C00LIIG UATD1 DISCFJJtGE FROM MABSHALL STFAM STATI0Il IIfr0 LAKE IIOPGIT For Presentation at the ASCE I!ational Meeting on Environmental Engineering Power Division
& - + ' ~m ca. , '":rr.:::::
May 13-17, 1968 By R. Fred Gray and J. Ben Stephenson Duke Power Company Charlotte, Ilorth Carolina 3314
i t 4
DIFFUSION OF C00LIUG WATER DISCFJJ1GE i FROM P/d1SHALL STFE1 STATION IETO LAKE NORMAN By l . R. Fred Gray and J. Ben Stephenson i
- Introduction I
All practical methods for generating large quantities of electricity involve effects on the environment.
i With this in mind, we at Duke Power Company have made it a part of our business to become involved in such things as water quality control, water l- resources research, flood control, air pollution control, soil conserva-l_
tion, public recreat' ion, meteorology, development of fish and vildlife facilities and the study of our thermal discharges.
The design and operation of our hydro and steam generatiag plants have j L-.. ii.fluend e,wilj L-j cm intaran in Lhe ecc.i m nmeni.
I We do this as a matter of good citizenship; but we also do it as a mat-ter of good business because our long range success is closely related to the vise management of environmental resources in the area ve serve.
l EEI Cooling Water Studies Duke Power Company and other electric utilities have been conducting field studies on the heat dissipation patterns of power plant cooling water 1
- . discharges for several years.
l -
t
- 1 4
Environmental Test Engineer, Steam Production Department Duke Power Company, Charlotte, North Carolina l
(Now Deceased) Manager, Environmental Research, Duke Power Company, Charlotte, North Carolina; O
i
_y - y - -.= D P" T **
- I D
J i
- . t Realizing that there was a need for correlation between field surveys and theoretical analyses of thermal discharges, our industry initiated such a study at representative locations over the United States in 1966. This program is being carried out through the Edison Electric Institute and
~
i under the direction of the Department of Environmental Engineering Sciences of Johns Hopkins University. This research project, known as EEI RP-49,is i
a very comprehensive undertaking which includes studies of heat dissipation in tidal estuaries, rivers, cooling ponds, rnd deep inland reservoirs.
Duke Power's Marshall Steam Station was selected as one of eleven study 4
sites for the RP-49 project. At this site, our company collects the neces-sary temperature data to monitor the diffusion of the station's cooling 3 vater, and we also measure the various meteorological factors which have an i
c[ $s . O.'". Yw 11wOlhLb101..
Test data is collected weekly and forwarded to Johns Hopkins where it is accumulated in the data bank of a computer. This information vill be pro-cessed and studied along with the data from the other research sites.
Findings are expected to be of great value in predicting and analyzing heat dissipation characteristics. This special testing around the Marshall
- Steam Station has enabled us to thoroughly evaluate some cf the special features of this particular power plant location.
Site Features The Marshall Steam Station is located on Lake Norman approximately in the center of Duke Power Company's ' service area (Fig.1). Lake Norman has a sur-face area of. 32,500 acres and a volume of over 1 million acre-feet. Weather conditions are relatively mild' for this area; as shown in Table I.
l
_,Hw' m
, w -"v' e , , _y
l Marshall Steam Station presently has two units in operation with name-plate cape.citics of 350 W cach. Under construction are two 650 IG units
! which vill bring the total station capacity to 2,000 IG. This vill make it
- the largest generating plant on the Duke Power system.
In order to accomplish special testing for RP 49, we have established a series of synoptic and continuous temperature monitoring stations (Fig.2) which measure the diffusion of Marshall Steam Station's condenser cooling water.
1 A complete weather station records the following information: vind ,
i' speed and direction, solar radiation, relative humidity, rain fall, maximum and minimum veekly temperatures.
When Lake Norman is stratified during the su=ner months, Marshall's condensers are assured of cooling water that is 20 to 25*F cooler than the surface water of the lake.
i The two principle features that =ake this arrangement possible are:
1 (1) A submerged skimmer vier, (Fig. 3) which is located 17 miles down lake from Marshall Steam Station at the Cowans t Ford Hydro Plant. This vier allows the higher quality (dissolved oxygen) upper levels of the reservoir to be !
passed downstream; while holding back the colder bottom ,
vater. l (2) An inverted skimmer vall (Fig. 4 and 5) which is located i at the mouth of the intake cove, about a mile from the plant intake. The skimmer vall is a continuous barrier except for openings in the lower 10 feet. These openings e
l f-W T -p- -
s -
$ y -m- g- N gi + - - -p-
-4_
alloa water 60 to 70 feet be.ov lake surface to be drawn into the intake cove.
With the present two units in operation, there is a detention time of 2 to 3 days after this cold bottom vater is on the plant side of the skimmer vall. During the hot summer months, this is enough time for this cove to start to stratify as illustrated by data taken on July 12,1967 (Fig. 6).
On the above date the temperature profile at sampling station "A", located on the lake side of the skimmer, showed the surface water temperature to be 79'F and the average temperature of the water going under the skimmer to be 58.5'F.
The coldest wate recorded at the plant intake during the conditions shown in Figure 6 vac 61*F, at depths 15 through 30 feet. The condensers were receiving 62*F vater at this time. So, under these conditions. the plant cooling water was heated 3.5'F by solar radiation and conduction be-fore it entered the plant condensers.
t When the total capacity of 2000 141 is in operation, the intake canal detention time vill be reduced to approximately 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />. With this shorter travel time, intake water is expected to be closer to the temperature of the water coming under the skimmer vall.
i Diffusion Studies "
Marshall's discharge canal (Fig. 2), from station "F" to station "H" is 4,800 feet in length. At full pond elevation,' there are 60 acres of sur-face area between these two points. Reductions of 3 to 15'F in the plant's effluent'have been measured before it reaches station "H", its entrance point to Lake Norman. *
%e- e
The following temperature profiles, which are representative of the dif-
- ferent seasons and meteorological conditions throughout the year, show hov
! the cooling water discharge from Marshall Steam Station is dispersed in a portion of Lake Norman.
The synoptic survey that was conducted on December 14,1967 (Fig. 7) vea on an extremely mild day for that time of year. Consequently the parameters that speed heat dissipation were at a minimum. Average relative humidity was 85%. Air te=perature at the time of the survey was as high as 67'F.
{ Wind speed ranged from 1.0 to 4.5 mph.
With a plant load of 770 MR and a cooling water flow of 252,000 gpm, the discharge-temperature was 76*F; by the time this water had reached station j "H", it had cooled 1*F. The temperature profile shows there was little or no mixing below the 53' isotherm. In fact, the 60* isotherm indicates most of the heated water stayed in the top three feet of the reservoir.
But even under the adverse meteorological conditions that existed when this survey was made, the condenser cooling water had reached average lake j temperature before reaching stations "23" and "45".
The February 21, 1968 data (Fig.8) presents an altogether different J
story. During the preceding 24, hours a predominantly down lake vind averaged i,
9 5 miles per hour. Average air temperature was 34*F at the time of the sur-vey. Average relative humidity was 50%. In the vicinity of the plant in-take, the lake was: isothermal at a temperature of approximately 41*F. plant generation was at maximum capacity of 800 MR. Cooling water flow was 252,000 spm at a discharge-temperature of 68*F. The cold air temperature and e 3 y ,y, -e.-- (- vg ,,,i- g w 4 4 y , - g+p 9 g- r
l-vind had dissipated the heat from the discharde water so that the varmest water recorded at station "H" was 54 *F. This represents a 14 *F drop in tem-
) , perature in the 4800 foot length of the discharge canal.
The sharp dip in the 44* isotherm from station "H" to stations "I" and i
"J" indicates that a cold vind of moderate speed for a long duration can cause mixing. This mixing is more clearly shown by the 43 5*F isothermal 3
l condition at station "45" which is 2 5*F varmer than up lake stations "23" and "A".
The April 14,19$7 data (Fig. 9) shows that the ' ke has begun its sea-1 j
sonal stratification pattern. Surface temperatures are around 65*F vith i
bottom temperatures of 49 to 50*F. Up lake vinds of 6 mph appear to cause
- \
some mixing in the top ten feet of the lake between station "H" and "I".
This is indicated by the deprennion of +ha Ab *w d a.a+k r- t:t ::n th::-
stations. "
A possible reason for the upsving in the 64* isotherm at stations "23" and "A" is that the temperature of the inflow to the lake was 62*F.
The lake was in a state of complet'e stratification when the data was taken on June 28,1967 (Fig.10). There is a 25*F differential between surface and bottom temperatures.
4 3
With both units near maximum' load and intake water at 60*F and with.all four cooling water pumps :ba operation, there is a 16.5*F temperature rise across the condensers. Discharge water is only 76.5'F vhile the lake's t .
surface temperature is 80*F.
This 3 5*F temperature difference causes the plant's discharge to dip under the surface and settle to its appropriate density level. The bulging-1-
-of.the isotherms at the mouth of the discharge canal clearly illustrates this.
T s < - - - "'
7-Data recorded on August 31,1967 (Fig 11) shows the di rcharge water to be only 1 to 2*F cooler than the surface waters of Lake Norman. There is not enough difference in the densities of these two waters to cause separa-tion. Therefore, the discharge water blends with the lake surface water and stays in the top few feet of the reservoir.
By autumn, the cooler air temperature has caused vertical mixing an'd
-the lake is undergoing its natural pattern of destratification.
The synoptic survey that was made November 1,1967 (Fig.12) illu'strates this natural mixing and also shows the rapid dissipation of heat from the plant's effluent.
Water was discharged at 83*F but by the time this water had reached station "H" at the end of the discharge canal, its temperature was reduced -
by 7'F. There was no effect seen at the upstream stations. Very little, if any, effect was seen at station "45".
Conclusions Distinct advantages result from the Marshall Steam Station's location on a large reservoir where bottom water can be used for condenser coolin6 During the colder months of the year, the heated water spreads over the lai.e surface where it is quickly cooled by the air and vind. In the hot summer l
- months, use of the cold bottom vater for cooling results in discharge tem-peratures close to those of the lake surface water. "
Extensive temperature surveys have shovn' that only a small-part of Lake Norman's cooling capacity is required to dissipate the vaste. heat from the Marshall Steam Station.
/
e m 4*~m,-s~,
- m - -
Future Studies Although the only obvious effect of heated water discharges at our steam stations is a noticeable improvement in fishing, biologists have expressed conflicting views and theories regarding the effects of heated water dis-charges-Beginning in the summer of 1968, Duke Power vill carry out a comprehen-cive 3-year study of biological conditions in Lake Iorman to determine the effectc of the heated water discharged from the Marshall Station. Our study vill be coordinated with similar studies at other power plant locationc which are being supervised by Johns Hopkins University for the Edison Electric Institute.
We are confident that these studies will provide factual ansvers to the questions and speculations about the biological effects of heated water discharges.
O E
++6=
i I TAEE I METI:0ROLOGICAL COI:DITIO:'S*
. IIT THE VICIIIITY OF LAKE NOIC:AH 3
I l ,
- 1. Winds A. Speed Annual Averages Speed (knots) 0 1-3 4-6 7-10 11-16 17-21 22-33 3
Frequency (%) 8. 0 70 34.5 34.1 13 3 1.8 3 i
, B. Direction - Predominantly from northeast and southwest, but does 1 blow from all directions.
- 2. Air Temperatures 1
1 Range Percent Frequency ay r ana . Lower 1.0 25-50*F 29
. 50-70*F 35 l 70-95*F 34 1
95"F and over O.2
, 3 Rainfall - Occurs all during the year averaging 45 inches per year, monthly ranges are 2-1/2.to 5 inches.
$*0bservations made by U. S. Weather. Bureau at "ouglas Municipal Airport, Charlotte, North Carolina. Marshall Steam Station located 26.2 miles northwest of Charlotte.
b e.
P e
-k .
. . . , _ . , , __._.y-,,.. . . . . , , , , .. , e , ,_ =
VA.
1
- ,: C!: , -
.t
- ).1 'f ' - ^xq';.
- ij;E.w
- c. *
,, f;i ,, .
.s,.
- 1 .;. . ., : . .
.... y a, 4....,.
j . , n; - .- ch.tysyoi:,.S lE M..:' ,, *
. :.tt.h.U.4A. M, ~- J.'
.) l n .7, ';%, .. ' ' ' ,;*
- i' . . . . . . >
. . . . a 'N 0.*..,1*C : *
.. . l g. if.Y ; . . .
., .$'.f,[i SI . l.N;.[ 'I:9. j./l
~'..,:.
.~ ArQ..y.M.@
. . . TALL: v.
[r - ,l,.'.t,.l. y ' , /,
. r.i$,'[ .~
... ' 3.,:hj .. OY ; ,. ,.M,.
.. :. a d,ihdt.,D.YTE).
- N C-
. . n .: . . .r. , . -: ge d i . .
"sn.Ay,-
usee n-. ;.
U.'*C;; ?: 5.s.-;; m ..;
', *'..98..
'h; '(('.'?,*-
c e..; f: ,.}
J
' y,i 'lly.'.k-}.
'f. }.b.s. 'II:.
h ,[f,j,ht;-[T.'l '?"
M. yj k'.?%.
-.y! ,. .-m s,
>..n ws7. 4,'t.s.~'., -'-y:-p. $ ri.o 'n:? 1 li n')u....;- . . ,
6 * .~ ; 5. t = .,' , .,
':f.f. i;;.'{;;.
- n. :- . , =
S. C.
O 1
\ .
L DUKE POWER COMPANY SERVICE AREA FIG. l
M)
- cv 4 y -
i)e '
4l c lof a
n ag
? 8 Sc $g
,' sag '#%
, s .
- ,g
/ 'npA * '> '
3.; ' ,' ' ' ,
f S'" E
~ exiunta * * "
oisexame: cANA N ' 'sF [gg coccine waT*8 8"T*"' ,, m uggy Q[1.,P C4 s
- )
, a c LAKE VICINITY NORMAN OF MARSHALL STEAM STATION g%A gA n m% 3 p 3
%y g %
JpMM s' g\;
{
< c ,y' LAKE NORP.iAN cxercrto vaccity mmeurica U WS_EL % J60, l_
/
/
eowERuousE 3 q
)
- f. ,rn n -
7 '}. ."[
SUBMERGED SKE/.MER WElR N
/ g NTAKE I"j U
/
/
/ L \_O m nm ,..n.,,-, ,,,,,,,, ,,,, ;,=,,,_,a.nn,. ,.,, ,nn.nr,m.,-,
'f W , ,,, ,, m o u r " I g
G i_f c .,
llV44A flV/6 COWANS FORD DAM WITH WEIR FIG. 3 I
y
' $ e E
g
/ O g* 8 l ;
F A EARTH ADUT edElli .
ia g %_
'5,\, n g b o nd a \1 k 0 0l U I
O I' I' \ ' 0 Kl?>ME -
s WALL t 270' -
550' / / 1 ;: >
~
- 1. PIER M I l. PIER # 12
\\
- WI i ;_- ' - / _
5 N v0 b
~%
\. '
l (l l -
- '- SKIM LIER WALL -
APPROACH CHAN NEL ELEV.690 -
NN, -
~, -
'9 G h "'o
% i
\ h ~
w PLANT N 3
., MARSHALL *so
~
SKIMMER WALL
\ ' k_- J
\
\ FIG. 4
~e
O ej q = 11 SPAC IS CD 5 0'0": 5 50* C" > o -
o 4 N
g @
Q I d D I p w r w J
g w
$ $_ g n
- e Q F # e O k
2 E # # # # # # # # # # EU-ia. x m m m r e e e e e e WO o= E ew ir w w w w a w w w w w w .. O em
<r E E E E i E E E E E E Uh O2 b d 1C F" FIER PRECAST CONC 1ETE STOPLOG $3 0' 9'* ~ ~ THICKNESS a
Ij WALL l' 0"THIC V' -EL76 0.67 HANDRA IL 8 l
LjGHTING g 3 n 7yp
, , , , , , ,,,, , , , , , , , , , , , ,,,,,, ~. . , , , ,
i c .s i i
H
- ! vs ; I l p- r.rh,! ;
- - ._ l i A, :::f::d .u . -
, _s ; : <<.. _
I i ,_ _3 j - "'" ? W i
-O( - - ! E = M ,.u..>c - L ' Y, l ._ - R., n H..i.
g--+
. ; 1 ih : -
x ! .. ,- : i 2
Y- PIPE PILES . :-
Y s!.,
'" n
"' vf i..
- .. 2
( E L. 6 9 0.0 io'
- +
27O' !.
- l
)
DOWNSTREAM EL E VATIO N l PLANT M ARSH /iL L SKIMMER WALL l
II ,
al l FIG. 5.._,s i,'
DA T E - JU L'r 12 ,1967 o -- -- -
PLANT INTAKE LAKE SIDE Skit.1M E R 80 -
STATION "E" STATION "A" g 20 -
w 30 -
2 :
7 40 -
I H
o 50 -
l
'60 -
n OPEfilNG UNDER SKIMMER 70 -
2 I I i a e a 50 55 60 65 70 75 80 85 TEMPERATIJRE F b i
[
_FI G.,,G .i
. l TE MPE R ATUR E *F o 55 56 s 73 60 54
-- ~
-6C -
,o
~
1 --- 53 "
20 s 30 U
40 2
x 50 so n :
a 6o /
70 49 1
, l'3 80 .49 _
50 50 @@MMM
, TII56\\\\Y///O/A\\\\\DD\ Ilh%@ "
PLANT GENIERATION - 770 MW IN TA KE TEM 3E R ATURE - 50' F DISGH ARG E TE MPER ATURE - 76 F COOLING W/TER FLOW - 252,000 G. P M.
SCALE: I" = 3000 DATE: f2-84-67 ,
__ _3 i
FIG. 7
.-_.-)
TEN PE R ATURE 'F O 41 48 45 54 45 435
\ /
\ /
10 \ /
t /
\ 4 4 ' .# /
20 t
/
/
F 30 . . ,
/
to tL.
40 3
50 44
? ,
I 60 o ,
f,,-
70 s Al ll w j,
/ 4 80 / )/ -
, 41 , 13 o1 i (TT\ \V// / / /7[
'Mg\ \\\\ \ \ \ \\\ \ \ D \ \i Y45T TD ' ' ' '
PLANT GENERAT10N- 800 MW INTAKE TEN PERATURE-41 F DISCHARGE TE MPER ATURE- 68
- F COOLING WA TE R FLOW- 252,000 G.R M.
scar.: i"=3000' DATE: 2/21/60
.__=
FIG. O
T E M P E R ATU:lE *F O 65 65 66 71 65 65 10 _ -- 64 " .
20 H 30 ~60 -
w _
w ' ~
-5! > -
40 E
50 51
?
$ 60 f
o 70 A 50
'l{ n 17 80 50 49 ,
Ni\\\\\\\\\\\\\\\\\\\\\% TFITDTiP' PLANT GENER ATl0N - 790 MW INTAKE TEMPER ATUR E -51 F DISCH ARGE TEMPER ATURE- 74 F COOLING WAT Ef: F LOW - 316,000 G.P.M.
SCALE: I":3000*
DATE : 4/14/67 FIG. 9
7 _
9 5 G
@7 ~
~
5 /
0 2
/ 0
~~t
\ G
~ :
1
- \ E
\ T G
~ \ A D
I
~ \ F
\
- \
gt - M R.
i G o -- i F
Gg
' _ 4 l
5 L
i
- 0 0
WF560 NN
/ 70 r
' e M08 06 E3 E .
9 7EU R-R U
- RTW T
Rmg A
E o
-\
~
2 cN NL UAO N TR L O AE F IT RP P
M E
98 77 5 5
~ A EM R R P T E T . ~7 6 E .
M. ETA
, , P E TE W I
/ \
G EAN T KH L G
RG I
@8 0
~
5 S
/
N AC A
/
/
/
V
\
\
\
\
\
\
\
\ '0
\ 0
\ 0
\ 3 4 \ =
8
@11
- _* 5 5\
4 "I
E L
@8 '
- 5
/ A C
S O 0 0 0 0 o 0 0 0 1 2 3 4 S 6 7 8 .
$$ E xH$O i
TEl4PERATURE *F
@@ D @ @
O 82 si 82
~~
82 82 {@30 i
80 20 30 __
E 40 65-1 50 ,< / _ _ . -~~w..... - - - - - - - - - " ' '
l- \
- a. (1 i I
w 60 '
7 s
70 x 56 lll g'g[
l 55 80 .ss 5
/ 56 ///////\\
vg///g4\\\\\\\\\y//// I e//g\TbWV '" // ' ' "'
I PLANT GENER ATIOh - 790 M W INTAK E TEMPERATU F E - 63
- F DISCH ARGE TEMPER A' URE - 80 *F COOLI NG WATER F L C W - 38 0, 0 00 G. R M.
SCALE: I"=3000' DA TE 8 /31/G7 FI G. 11
w TEMPERAlURE *F
^@ ,
D .
0 65 65 65 76 70 66 Io 64--- --- % _ _ _ _ __ ,
20
-63# -- - -
so E
4o E
50 63 a 60
(
70 N 61
~'Ih j ^
i,G to . 58 57 s s7 I
'% n \ \ \ \ \ \ W//////// //& l'M/74\' '
PLANT GENER ATION -750 MW INTAKE TEMP 2RATUR E - 62 F DISCHARGE TE MPER ATURE - 83* F COOLING WATI:R FLOW - 316,000 G. P. M .
SCALE:l" = 3OOO ,
DATE II/ I /67 FIG.12
,, c . #4 / & 0f 6
~um.M 7 ? Q %u
- k. S'c;'W ,SC W)' Y WJ neceived w/Ur cM is // . r ?
Regulatory File Cy.
By Austin C. Thies Vice President, Duke Power Co., and Chairman, Water Problems Task Force, EEI Committee on Environment
{ Til,ITIES may spend up to S4 billion for un- is growing, thriving and permanent-industry must
[V needed control of thermal e:Tects by 1980, de- adjust to it."
!lending on what we do to itJiuence legislation with All over the cot.utry there is growing public concern
. ~.
ouet air anu water pouutton, ano narruy a wecic goes Secretary of the Interior Walter J. Ilickei has an- by that you do not see some reference to so-called ther.
nounced that l' resident Nixon will establish a new
~
mal "Ivhution" 1 rom power plants in your locsl news-interdepartmental environment quality council over paper or on your radio or television set. Whether we which he will personally preside na chairman. like it or not we live in a fishbowl. We are the largest The Rockefeller Committee in releasing it s report and most accessible target of those preservationists said, "The movement to promote environmental quality and others v ho would accuse us o
- doing great and per-
^ manent harm to the waters of th etion without hav. "
i,
,g "gd,',r'y,b,'g*,,',j,,s;ign,nuni comention of Edison Electric In- ing the facts. They have set out to block our proper use
~ . . .
/-. . : p r .~.. .
[ .
Every utility should give environmental matters a high
.p>1 priority in its corporate planning. As the use of water
(\ *
' }, -
multiplies and the industry concentrates in single units huge blocks of power, the problems of heat
- ( , release are certain to multiply.
t.
3.Wf l' I
{ j ' l
{ !(> !
- t\
b_.-- b 1 - .-.w 3314 J U N E-J U LY.' 19 69 201
r .er ,y -
m l, : n **..e e , <. . , 1 -
e -
s ,, . ~ ! *~ e ~,*~ *r*m -) . !
=9 5 ,s & 4 awa.e ,..' -e
.',em.4 .a yw,! ,* , p., .,. u.n.,-
= tm. .p s
- c. v,s- .
a
,1 s."
,j. .* r-*
- d
.- t.-..
fr>7.> s . - . ~ .- - .-
f
- .i 5%. 1 I %
. +
i
--1
- i f - a -. *
, s, 1
,+ . ' -
,. , . ~..-
. 2 I - - '
- -r.s. .,
l ,. :
s' - . , I~
..-.-....sa.. -
L .,_ t ---- =
u - . - . - ~ - - - . . " -
Figurc 1 Figurc 4
.e.
, y,
~ '
5, g- . .-. - ,. .. ... _ - .- -
4
' n t, i
{
. t I 6 f i
.- , , , t ,
,(' ,,."m" '
. ., .;Y'.
l ,
- . , ' .~ -
) - ~'
t y . b. 5.' $ ,.
-+
,e s __ ty. ,- - .i- % ~.
(
.., x w. ..- ,.
, , T -
g-
.r-'
i , s'. ,., , ' 'V l
E "'h.
Li - .. L T h . L .) Es.._ ._ -. ,...a. .. m w w i Figure 2 Figure 5 n . ._. . . - . , , - _ . , . . . . , . . . . , _ _ . _ _
4 4 a ..
~
. s,
.'< E' } { s.
s r, * \
); -
... , , .z . -Q^ Ns 4 ic -
4!
,N .
=: z
. e RO.,tm m,g ,! y '! a .
, ~%
t
+ -- ,
i} .,.r . . , ., .
.. ._...... ns .
, n
. . - , _f . . . . . . -
L. 3 . , -
.l.a H..a. . . . 1e.. mv =. ,
~~
,. ?;
i
.r~~~"~
- - < .4 c, . .-
- :.LY. .*
..e.. . ..
. . .(~ i
..y J
4- ',... --
. :.u . - .. .- - .:.~ ~ . ...n- ...*3 m c. .
..> 2 . .n ..
Figure 3 Figurc G 202 EDISON ELECTRIC INSTITUTE BULLETIN
- r. .y . y '
D TlgiU) g il(I # \
, dh J' l .3 of this necesary natural resource, even though we have
[*@ [y$$$ assured them that we will take whatever steps are nec-cuary imrrect any harmful & cts from warm water discharges.
N-- Certainly, eut industry, as it grows, will use ever-N g larger quantities of cooling water in its condensers; y,. t ,' ,
hmveter, we have been using part of this water for almost 90 years now, and the number of instances in g
- s. .
which power plants have been directly responsible for
. \,\r,\ harmful effect on any form of aquatie life could be N c,k li.<ted on a very short page. We are not, however, rest-
\ C* ing on our laurels. I am very proud of the genuine con-
\.J- cern of our industry-of what it has already done to
\.y..
, minimize the efTects of warm water discharges, and of what it is doing in the way of research to see that
}y,Q, reasonable temperatures aren't exceeded and to find a w3 out what the biological effects of slight changes in
\3
~_
, water temperature really are. We must and we will
. t protect our environment. Let's review the existing
. \.P. i situation.
Figure 7 What the ' dustry Has Done For some years, we have been huihling cooling towers where necessary, putting in cooling ponds, spray ponds, e ';
/ 'O building separate cooling lakes, and designing our in-take and discharge structures and locating them in n ,, , such a manner as to minimize the effect of the heat A
discharged to the receiving waters from our power
, in, / stations. EEI companies recently received a summary
& ~~ # of the environmental sindies on water problems being
~~
p d,
- . .h '.., '"' : . ,:.i. . .. ...J 'JC' .. !.., . ,,~..
- J .o s
q 7 a recent questionnaire from the Water Problems Task s, ,
' :' ,4 Force. This summary shows that 151 separate research
+
,^ W ?- studies have been completed; 114 studies are actively k
g y
"./ under way: and 44 research projects are proposed-a total of 309 studies of the effects of warm water dis 1 2
( '
charge made by industry. This information should be .
(~ ~~~'~ ~, )_~ - y, _' made available to your legislative, educational, and
.yurc 8 regulatory people who should be aware of the research the utilities are doing.
- ~ Phase II of EEI Research Project RP40, being con-ducted by The Johns Hopkins University, with support
- f - N ~~~~~
~ ,. , ' 'N ' d from a host of researchers from other campuses, covers g i ' . _ w ...- ; some immensely significant work that has to do with 4I (
,'_'~
([s.4
- ' . g the amlysis of surface heat exchange of power plant
, f., cooling ponds. A report on this phase, due for immedi-
"~c _.2.
- j;{T, (
f--- ; -
-g ate release, will resolve some of the discrepancies dis-(-*,d.."*~ ,
closed by previous investigators in the relationship be-y .' m. y ., - ,
tween the surface cooling rates and wind speed. This f p(. ~*
is nere, hard data backed up by three years of research
'A,. v. \,. ./ ]~i'r * * ." f 7.N O.
'\.I . ,. 3Q, ' % ,
' done on 11 power plant sitta in the United States that
' .. v/,.- ',- -;-
'M will show that cooling coeilicients can be quite ap-kE
- h.,i! '
p
}; .'s ' \ y,RW -
,r, . ., ; ...
preciable even with very low wind speeds. This con-
,( w' ,
.'.s.1 tradicts two out of three previous investigators who e
'% .r" ' -
v ( .W had deduced that cooling coeflicients became negligibly
- J r . . . .h k i . Y hd.# ^ small at 0 wind speed. This report also finds that at
, Figure 9 ' higher than average wind speeds, cooling coeflicients
' tend to be larger than would be predicted by using the findings of any. previous investigators. This nqw re-J U N E.J U LY, 196 9 203 e-=a- C --- --
w a w - - --.18 '-.i +.w. . ew vv
search information'is the kind that both industry and plants from warm water and how much?" EI:I's 8750,-
government never had available to them before. 000 investment will be more than matched by the ex-penses of participating companies and cooperating Three Year Project local agencies.
Phase III of EEI RP19 is a three-year, $750.000 Certainly additional research is needed to be sure project covering the biological effects of warmed water that we are protecting our water resources. Ecologists
. on biota at actual power plant sites. Many of our stand- speak of the " Chain of Life." We are involved in a ards are being established based on small-scale labora. chain of consumption or of use. I believe that we can tory studies that don't represent fiek! conditions. The learn much from the ecologists
- approach-they be-
. need for this fiehl research is great. One of the sites lieve. you know, that no animal or species should be selected for this research is Duke Power's Marshall viewed on its own. but ahvays in relation to other items Station on Lake Norman. I would like to show you in the environment which surround it. It seems to me some of the work on this project- that in loaking at the prob 1cm of thermal effects, it is Fig.1 is an aerial view of Marshall Station-water sensible to take a similar approach. Within our own intake maler the skimmer wall on the left and dis- p rtion of the chain of use, we should be sure that our charge on the right. The present capacity is 1151 meg. power plants have a minimal impact on the total en-awatts and ultimate capability is over 2 million kilo- vironment, but more than that we should be constantly watts. aware that the solutions which we devise to our own Fig. 2-The Division of Inland Fisheries of the U."
- may upset the balance of someone else's solu-North Carolina Wildlife Commission is cooperating tion to his particular problems, in this project by collecting and analyzing fish samples. For example, there is good evidence that adding large liere, two of their biologists are shocking and netting amounts of heat to water in itself is not likely to have fish to be tagged Fishermen are asked to return tags on harmful effects on the life in and around the water at fish they catch to study migration. The greatest percent low temperature levels; however, there is strong evi-of the returned tags have come from the plant dis- dence that protracted additions of warm water on a charge. In this and their gill net sampling, they have long series of very hot days at low river flows in areas two full-time biologists and one helper and a part-time where 8ewage wastes are being dumped will upset the fmoery supervmor on tms joo. bamuce or ute m amt aroumt the water in a variety of Fig. 3 is the meteorological island where we record ways, seme of which are harmful. This is the kind of wind speed and direction, relative humidity, maximum change that we must avoid at all costs, but who should and minimum temperatures, rainfall, and solar short- . pay f r the protection, the sewerage dumper or the wave radiation. utility? This is a very sensitive area to discuss.
Fig. 4 is one of four instrumentation rafts which con-Fish, Yrildlife, Recreation Problems tinuously record water temperature at six levels from top to bottom. Weekly synoptic surveys are made from The problems that our industry faces are mostly boats at various depths at 19 other locations. Note the related to fish, wildlife, and recreation rather than lead peroxide candle and dustfall jar used for air pollu- public health. I don't beheve the facts have established tion work. Also, located here are some biological pro- that warm water discharges from power stations cause ductivity slides. a direct health problem. So, what it boils down to-if Fig. 5 shows crews taking chemical, D O, and tem- you will pardon the pun-is how much investment can perature sample readings in the left boat-while the be Justified for what degree of total protection of fish boat on the right is collecting plankton samples by populations. Let's look for a moment at some of the
- pumping about 50 cubic feet of water from five dif- statements that are quoted as fact about cooling water
. forent levels through a plankton net about like par- discharges which are really more in the category of achute silk. half truths.
Some of this plankton are animal, like this "Kera- . Half truth ;H-Any heat added to rivers and lakes is .
, tella". (Fig. G), and some are plants, such as this "Me!- bad
- osira" ( Fig. 7). Actually, addition of heat can be beneficial in certain In the laboratory of the University of North Caro- circumstances as has been well documented in the tech-lina, at Charlotte, a local biologist identifies and counts nical press. The sun adds most of the heat anyway.;
plankton (Fig. 8J. . Half fritth 42-The utilities are' sitting back and In our laboratory,14 chemistry parameters are run doing nothing about thermal effects from their power on the 3G water samples on a bimonthly basis '(Fig. 9). stations because of the cost involved.
~
From RPID should come the answer to the question, Utility companies have spent many millions of dol.
"Is there obstantial toxicity to biota around power lars over the years to avoid undesirabic temperature 204 EDISON EtECTRIC INSTITUTE SultETIN
D**D *D oo ob ..k :2 changes. They are presently engaged in extensive na-Half truth #9-Dheases of fish are more of a threat tion-wide research tn determine wimt further degree as water tem;mrature increases.
of environmental pro!cetion is needed.
Conditions are more favoralee for disease-producing lialf-Truth No. 3 organisms at higher temperatures; however, Travelers Research Corp. reports that one researcher, m, d e-Huff truth =J-All organi<ms are hiiled in passing scribing his work with non-specific infections of fish, through the condenser.
concludes that the defenses of fish to infection vary Adams of PG&E at the American Power Conference with the temperature. At low temperatures fish may in April r(ported a very high survival rate of all not purge the bacteria from their systems, but at organisms that pass through condensers. Results of higher temperatures the defenses can climinate the experiments in the laboratory that hold specimens at disease organism. I understami that hobbyists com-set temperatures for 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> do not correlate with the monly put pet fish in warm water to cure their dis-same exposure to temperatures for a few seconds while eases, passing through the condensers and into the receiving waters. Field experience shows that the survival rate, Half truth #10-Fish kills caused by heated water i
is extremely high. A biologist recently told me of being discharged from power plants are common.
i in a glass-bottomed boat in Florida observing plant FWPCA reports approximately 10 fish kills which specimens that according to the textbooks could not they attribute to heated water discharge from power exist. at the temperature he was measuring. This points stations since they began keeping records. Certainly up the urgent necd for actual field data to prove that there have been very, very few instances in the 90-year organisms have great adaptability to specific environ. history of our industry. Fish can detect temperature mental conditions. and will swim away from undesirable locations.
Half truth #4-Cooling towers are the ultimate As our use of water multiplies and as we concentrate answer to heated water discharge problems. in single units large blocks of power, the problems Cooling towers may be the answer in some cases; of heat release are certain to multiply. This will be however, there may be problems associated with cooling partially offset by the trend to higher ef!Iciencies of towers that involve consumptive use of water, con. our new power stations-no doubt accelerated by high centration of salts and blowdown problems, icing, and fuel costs. Waste heat is abhorred by utility engineers.
weather problems that make cooling towers unaccept. We much prefer to convert to electricity every single able in certain applications. Btu possible. At present, in our fossil-fired stations,
- :: :,' .. .d.~ G *:,*n ,m.d . m. d u a, y d nnuun "' * * ""'" " * " Y " .'""^ ^ M ; f = =- ~ , - L power plants is low in dissolved oxygen, our nuclear stations, probably 30 percent.
Dissolved oxygen is essentially unchanged to some. What can be done to improve the utilization factor?
what higher in power station discharges. This has been Can we use the low-grade condenser heat for desalting reported much to the surprise of several utilities who plants, for fish farms, for hothouse farming? So warm-find that dissolved oxygen in their discharge canals is ed water can produce algae-how about doing some running higher than in the source water itself. algae farming since algae has 45 to 55 percent protein Half truth #6-Unless we can stop the addition of versus alfalfa's 20 percent protein-with alfalfa worth heat to our water now, we will do permanent damage. $40 per ton? Way-out thinking? Impractical? It may Assumm.g that there is some undes.irable damage be possible that some such wild idea might conceivably from warm water at a specific location, this damage provide an economic solution to some of our problems.
would be temporary, and if the water temperature IIow about the future use of the binary vapor cycles-was lowered the ecology wouki gradually be restored, magnetohydrodynamics, developments of breeder and Half truth #7-Once water is warmed, it cools very later fusion reactors-greater use of extraction tur-slowly. ,
bines furnishing steam for heating cities, or steam Research Project RP49 information inaicates that to nearby industries that will return condensate but
. water actually cools much more rapidly than originally not add heat to the natural waters? Further research suspected. Thermal stratification of warmer water t efforts are needed in such areas and many of these the surface results in rapid heat loss to the atmosphere. are being actively pursued.
The warmer the surface water, the quicker the heat Aren't Doing Damage is released.
Half truth #8-Nuclear plants discharge hotter Out of current research are coming results that in-water than coal-fired plants. dicate that we aren't doing significant damage and We know that there does not have to be a difference pr vide an excellent basis for future designs. Future in the temperature; however. statements made to the . research will give ~us and the regulatory agencies public indicating that nuclear plants reject 50 percent enough information to more completely answer the more heat, w ' hile true,' have confused the public since question of cause and effect and the degree of damage they do not realize that this is accomplished by using to the ecology. Oar rate payers should not be required 50 percent more water.
to carry tremendous financial burdens far beyond JUNE JULY,1969 20s
s ,a , ,,.m-D**D *D
~
oo .
Tl .. :3 reasonable uncial or economic cost-to-benefits ratio and who fall into the category of " doers" rather than based on someone's fear foi what might be. " talkers.*
For example, there are some who advocate the com-
. Put your public rMations house in order ne it re-pletely closed, water-to-air, automobile-radiator-type lates to thermal etrects. This can ho <b,ne in many ways cooling towers, which can cost $25 to .% per kilowatt -at least one company provish s fi.x hing infn.mation of capacity. To my knowledge, there is only eme such to the publh. where they pay their power bills.
device in service and it is in England cn a small unit of less than 200 megawatts and in a cool climate. .W own mmpary mendy cos; ducted a thermal ef-Further, it would cost millions more through ita detri- 8 nar to wM we u, mted members of the
' mental cfrect on plant ef!iciency, Designers shouhl con- press, TV nnd radto, editors of wihllife magazines, sider providing foundations in the initial layout for sports writers, and regulatory personnel. At this day-features such as alternative cooling facilities, multi- "" " ""**"I"""' #F " " **""""#""I U"*"
levelintakes, auxil.ary pumping equipment, or possible plant, the proce<ses were expha[ned, and this was future discharge arrangements where an individual I"wed by a seminar which covered the subject of warm site is marginal. water effects ns they are known today-what we do g ,g ,
Must Take Several Steps our waterways from damage from the heat from No matter how much we know or how right we are, work with we may not be permitted to do the reasonable and power """ stations.
O'wed by aApanel full description discussion wi e' ualth questio rational thing. There are several steps that we must from the audience. You wouhl be surprised nt how take if we are going to gain the understanding of the many of these people thought that the steam that we public and regulatory agencies to convince them that were condensing was at 212 degrecs instead of at body we will protect the environment: temperature, and that it was literally possible for us
. Every utility should give environmental matters to create very high temperatures in cooling water dis-
- charge' a high priority in its corporate planning. One of your most capable technical people should be assigned full If we expect our customers and the general public time to environmental matters and, in cases o' larger to have confidence that we are solving the environ-i companies, several people or a department may tx in mental problems which face us, we must tell them i' order. It is impossible for managers with responsibili_ what we are doing. A group of our companies has been ties in production, operation, design, and other com. describing its activities in a series of newspaper r.d-
_ nany function = to dovnt. ,o.md,.nt tima ant nr +lu.w vertisement. I .na f alan,1 T.i,A t n % +--
daily sched"les to give these complex matters proper slide presentation for schools and clubs on the use of attention, warm water for oyster nurserics. There are many ways
. Lend your f nancial support to research work of to tell our story. We should be telling it over and over the Edison Electric Institute and others. Conduct your again.
1 own research projects as they relate to siting of your . Our industry, through this Institute, should take specific power stations. This support should be gener- steps to cpen communication of research results with ous-the alternatives are more costly.
the Federal agencies. We all want the facts, and the
. Know your local university biologists, your state quicker both groups get the facts, the quicker we wildlife and regulatory people. Involve them in your will have truly equitable solutions to whatever water research projects at an early date One of the most problems do exist or may arise. Certainly we should discouraging things that has been observed around the oppose the approach certain persons have avowed that United States by persons involved in conducting EEI says, "If we don't know enough to set up limits, then i llesearch Project IIPID has been the time and effort we don't know enough to justify allowing these dis-spent on the part of some regulatory people just to charges at all."
prove a utility wrong. Conversely, one of the most en-
-couraging things has been to observe the progress that Must Plan for Future
. was made when, at an early stage in research projects, I believe it was John Galsworthy who said, "If you state agencies, local biologists, and power company do not plan for the future, you cannot have one." I am personnel get together, lay the cards on the table, and proud of the planning and work that our industry has
" shara information as it is developed through sharing done to protect our environment and I am confident we in the work responsibilities associated with water re- will measure up to future challenges. I offer these search projects. You should be careful to choose the thoughts for your consideration as you' involve your
- biologists from among those who are capable, object've, company ever more deeply in environmental matters.
W .y e in ,,- i j
e 206 EDISON ELECTRIC INSTITUTE 8ULLEf tN
~ >
- df '
?g Q N'h<d4W .
,rs c l f Y
- me:s w,ur :: tad M 4 - M p ht- y Fife Cy.
ASCE SPECI ALTY CollFERENCE RESEARCH !!EEDS IN THE civil ENGINEERING ASPECTS OF POWER PANEL ON WATER QUALITY C0t; TROL PULLMAtl, WASHINGTON, SEPTEMBER 11 - 13, 1968 IMPROVEMENT IN QUALITY OF RESERVOIR DISCHARGES THROUGH TURBINE OR TAILRACE AERATION W S Lee Vice President, Engineering Duke Power Company, Charlotte, N C
- 1. INTRODUCTION The need for increasing the dissolved oxygen in water releases f rom power dams can occur for several reasons. Depressed oxygen levels can be caused by inad-equate treatment (in which case artifical aeration should not be employed as a sub-stitute for adequate treatment) ; by the discharge of ef fluent from efficient tre.'t-ment plants into streams overloaded b'ecause of inadequate flow; or by the release of hypolimnetic waters degraded in dissolved oxygen through Icw level intakes, in considering alternative means of aeration, the value of the added dissolved oxygen must ce weigneu against tne c.ust or provicing it. tcicn soiution invoived capit.ei investment, power consumption, and/or operating and maintenance costs. Aeration techniques have been applied both upstream and downstream of power intakes.
- 2. INCREASING DISSOLVED OXYGEN UPSTREAM OF INTAKES Several methods have been applied upstream of dams to improve the quality of discharges. At several large power reservoirs submerged weirs have been successfully employed to selectively admit to power intakes oxygen-laden waters from the epilimnion
,2 of the stratified lake. Design criteria for submerged weirs have been well estab-lished so that predicted performance can be achieved with good accuracy in cases where the stratified pattern of the reservoir is defined. Submerged weirs involve substan-tial capital cost, but require little or no maintenance and negligible head loss.
Sub-merged weirs are in service at the Gaston and Roanoke dams on the Roanoke River and the Cowans Ford Dam on the Catawba River in North Carolina and are under construction at the Keowce and Jocassee Dams in the upper Savannah River B1 sin in South Carolina.
Similar in concept to submerged weirs ar e multi-level intakes which can be selectively controlled to draw from desired levels in the impoundment. Folsum dam in California has been equipped with controllable shutters over the intakes for this purpose.
DP"]D *]D T ooM o ju 1 A =
2 To aid reaeration, arti ficial vertical mixing has been employed to destroy strati fication and progressively expose all waters of the impoundment to the surface thus creating essentially homogeneous oxygen content. The energy required to vertically mix reservoirs and prevent stratification has been estimated by Kitrell. The use of mechanical pumps to create vertical mixing has met with moderate success on a reservoir ; and in the ship and sanitary canal of Chicago ;
and with improved results in a Kentucky lake during 1964 and 1965.6 Successful vertical mixing by admission of compressed air through perforated pipes on the 7
lake bottom has been reported by Riddick at a reservoir in Ossining, N Y and by 8
Ford at Lake Wohlford, California. Originally developed to prevent icing or
, control waves at dockside, the aerohydraulic gun has been used to break up reservoir stratification.9 These several means of breaking up stratification have been compar-atively analyzed by Thackson and Speece. Their successful application to date has been limited to relatively small reservoirs. Their application to large pcwer im-poundments would cause warming of otherwise cool hypolinnetic waters, and thus destroy the hypolimnion's potential use as a source of low-temperature condenser coolin'g water for thermal power plants.
- 3. AERATION TECHNIQUES DOWNSTREAM OF POWER INTAKES An attempt at improving downstream water quality by tailrace aeration was made by admitting compressed air through diffuser plates in the bottom of the tail-race with limited success. The use of mechanical pumps as surface aerators does not seem to have practical appilcation to tallraces. Other methods, such as aeration by pressure injection or "U-tubes" are suggested as possible aerction techniques on small streams , but not on the scale represented by hydro tailraces. Two aeration methods that may have tailrace application are turbine aeration and aerating weirs.
I In 1957, turbine aeration at the Pixley Dam on the Flambeau River in Wisconsin was found to be successful in increasing the tailrace dissolved oxygen. '3 These encouraging results led to the application of turbine aeration on seventeen additional dams on two other rivers in Wisconsin as a cooperative state-industry pro-gram. Where waterwheels are set above tallwater level, a vacuum often develops in the draft tube. For example, a vacuum of 10.7 to 11.6 in. Hg is produced in the Pixley Dam draft tubes throughout the range of gate openings. Many of these wheels were equipped with vacuum breakers to admit air, sometimes only at low loads, for s
e ~y , g -
3 vibration or cavitation control. Aided by the turbulence in draft tules ar.d tail-races, air admitted by vacuum breakers of ten results in significant increases in dissolved oxygen. Absorption efficiency is greatest when the initial saturation level of dissolved oxygen is 407 or less. Without a change in gate setting, admis-sion of air reduces the power output. Thus, increasing dissolved oxygen by turbine aeration has an associated energy cost. In the Wisconsin installations, from one-half to five tons of oxygen were absorbed per day for each 1000 cfs flow. This was at the expense of an energy loss ranging from 0.2 to 2.0 kwh per pound of oxygen ga.ined.11,14 At the Wylie Station on the Catawba River in South Carolina, turbine aeration experim;nts were made in connection with wheel operation for low ficw augmentation.15 in this case, the wheel settings are such that vacua are not pro-duced in the draft tube except at very low loads. For example, on these wheels rated at 15,000 kw, vacuum breakers are only effective at loads of 1,000 kw and below where wheel efficiencies are substantially lessened. An offpeak discharge of 1300 cfs can be passed through one of these waterwheels to develop an output of 5600 kw at which load no vacuum is produced in the draf t tube and turbine aeration will not occur. Alternatively, the same flow can be split between two wheels to J.. ..r 1000 k. mos;. nid,vovuum vi casei s iu s i y operat ive our. at a sacriesce ot 360 kw in power output for the same 1300 cfs flow. Operation of a wheel at 1000 kw has resulted in oxygen absorption ranging from 6 to 10 tons per day per 1000 cfs flow depending upon initial saturation deficit. However, due to the inefficient wheel loading to obtain ef fective vacuum breaker operation, this results in an energy loss of 4 to 7 kwh per pound .of oxygen absorbed.
For the many modern waterwheels set at or near tailwater level, no vacuum is produced in the draft tube except at very low loads if at all. Hence. turbine aeration by vocuun breaking is not possible in these installations. Theoretically, compressed air could be introduced in such cases into the distributor or draft tube for turbine aeration purposes, but associated costs are expected to be high. Oppor-tunities for turbine aeration will be largely limited to older installations having high wheel settings, and modern large capacity units will only be suitable for aeration where the setting established for other reasons is coincidentially appro-priate for aeration.
k Where discharges from dams have a large oxygen deficit and turbines are either inappropriate for aeration or do not exist at all, a icw weir across the tailrace may be justified if an oxygen gain has a high value. Gameson and 6
others developed an equation for reacration at a weir with a single free-fcil, and subsequent installation of weirs has confirmed the applicability of this equation over a wide range of circumstances. 7 For example, water at 20*C con-taining 2.0 mg/l of dissolved oxygen flowing ever a weir can result in an oxygen absorption of 5 tons per 1000 cfs per day with a free fall over the weir of 1.6 feet. Such a head lo',s has an energy equivalent comparable to the energy loss experienced at some of the Wisconsin turbine aeration locations producing a sim-
- ilar rate of oxygen absorption. The relative effectiveness of turbine aeration at three dans and of an aerating weir is shown on Table 1. Whereas the energy losses for the same oxygen absorption are comparable for the weir and Wisconsin' dams, an energy loss many times greater applies to the Wylie dam which must operate at inefficient loadings for turbine aeration to function.
s 4 UNKNOWN AREAS To determine whether turbine aeration can be practical and effective
,, . enor;fte avt=+1nn nr niannaA ince=11as inne roantres a hartar onderstandinn of I
the mechanism so that results can be predictable. Not clearly defined is the re-
- lationship between draft-tube vacuum and wheel setting, turbine type, draf t tube configuration, etc. A research need is also indicated for a sensitivity analysis of vacuum versus absorption effic'c.'cy and saturation deficit. Additional work on the aerating weir will be necessary to determine its effectiveness and applicability to tailraces of large-scale power installations. From.such future research, we may learn whether tailrace aeration devices represent an ef fective tooi in water re-sources management or an expensive substitute for adequate waste treatment.
e
l TABLE 1.
COMPARATIVE PERFORMANCE OF STREA84 AERATION DEVICES Theoretical i
Examoles of Turbine Aeration . Aeration Weir
-installation Pixley Dam Rothschild Wylie -
River Flambeau Wisconsin Catawba -
Date 1958 1958 9/14/59 -
Reference 11 14 15 16 Streamflow, cfs 317 1,762* 1,300 1,000 ,
02absorbed, Ib/ day 3,330 10,430 19,600 02 absorbed, Ibs/1000 cfs/ day 10,340* 5,920 15,080 10,000
) Energy loss, kwh/ day 1,040* 1,900 85,500 -
Energy loss, kah/lb of 0 C 2 0.31 0.184 4.9 0.275 Energy loss - absorption - flow ratio,
~
kwh/10,000 lb of 0 /2 day /1000 cfs 1,005 3,200 56,800 c 2,750 Equivalent head. loss'in tt/10,000 lb of 0 /d y/1000 cfs C
] 2 0.6 .l.9 33 1.6
]
- a. Data shown in reference listed in column above. All other values calculated by Lee using these and other data from respective references.
l b. 1720 kwh/ day is energy equivalent of 1000 cfs and I f t head at 85% efficiency.
4
- c. Using equation f rom reference 16, water temperature 20*C,. upstream ! dissolved oxygen
. 2.0 mg/l: r = 1 + 0. lla(1 + 0.046T)h Where: r = ratlo of. upstream saturation deficit to downstream saturation deficit, a = coefficient for water quality (1.25 for slightly polluted water, 1.0
.for moderately polluted water and used in above example, and 0.8 for
~
1 sewage effluent),
T = water temperature, 'C, and
!- h-= height of free fall over welr, in ft.
J T + t T' -V- $ q v -+' w-Ff e W-~
References
- 1. Ragone, Stanley & B J Peters. Water Quality Monitoring for Water Quality Control. Symposium on Strecmflow Regulation for Quality Control. Public Health Service Publ No 999-UP-30 (1965) 2 Lee, W S. Influence of Hydroelectric Reservoirs Upon Water Quality of the Catawba River. Proceedings of Tenth Southern Municipal and Industrial Waste Conference, Durham, N C, April 1961
- 3. Kitrell, F W. Effects or Impoundments ,' Dissolved-Oxygen Resources.
" Sewage Industrial wastes" 31:1065 (1959, 4 Hooper, Frank F; Robert C Ball, & Howard A Tanner. An Experiment in the Artifical Circulation of a Small Michisc.n Lake. Trans Am Fisheries Soc, 82:222 (1952) 5 Kaplovsky, A J, W R Walters, and B Sosewitz. Artifical Aeration of Canals in Chicago. This Journal, 36, 4, 463 (April 1964)
- 6. Symons, J M, W H t rwin, and G G Robeck. Impoundment Water Quality Changes Caused by Mixing. Jour,al of Sanitary Engineering Division, ASCE, Vol 93, No SA2, April 1967.
- 7. Riddick, Thomas M. Forced Circulation of Reservoir Waters. Water Sewage
'!:: != , !O!::23 ? '?L"7)
- 8. Ford, Maurice C, Jr. Air Injection for Control of Reservoir Limnology.
Jour AWWA 55:267 (March 1963) ,
- 9. Bryan, J B. Imp rov ement in the Quality of Reservoir Discharges Through Reservoir Mixing and Aeration. Symposium on Streamflow Regulation for Quality Control. Public Health Service Publ No 999-WP-30 (1965)
- 10. Speece, R E & Edward L Thackston. Supplemental Reaeration of Lakes and Reservoi rs. Journal American Water Works Association, Vol 58, No 10, October 1966,
- 11. Wisniewski, T F. Improvement of the Quality of Reservoir Discharges Through Turbine or Tallrar3 Aeration, Page 299. Symposium on Streamflow Regulation for Quality Control. Public Health Service Publ No 999-WP-30 (1965)
~
12 Speece, R E and E L Thackston. Review of Supplemental Reaeration of Flowing Streams, Journal Water Pollution Control Federation, October 1966
- 13. Scott, R H; T F Wisniewski; B F Lueck, and A J Wiley. Aeration of Stream Flow at Power Turbines. Sewage and Ind Wastes. 30: 1496, ' December 1958 l4 Wiley, ' A J; B F Lucck; R H Scott, and T F Wisniewski. Commercial-Scale Operation of Turbine Aeration on Wisconsin Rivers. Journal Water Pollution Control Federation, February 1960 .
- 15. Lee, W S. Discussion of Improvement of the quality of Reservoir Discharges Through Turbine or Tailrace Aeration. Symposium on Streamflow Regulation for quality Control. Public Health Service Publ No 999-WP-30 (1965)
- 16. Gameson, A L H, K G Vandyke, and C G Ogden. The Effect of Temperature on Aeration at Weirs. Water and Water Eng (Brit) 62, 489 (1958)
- 17. Barrett, J M, A L H Gameson, and C G Ogden. Aeration Studies at Fou r Weir Systems Water and Water Erg (Brit) 64, 407 (1960) 4
\
C
Y Lpy17.pf-ll$.-a-47
. . = , _
- j LAKE 1:0RMA" UA1ER RESFARCi! FROJLCT DURE FOWER CG:'J'ANY Rat,alved w/Ltr Dat b ._
-- i Regulatery Fi' *-
For a number of years, the Corrpany has had a Water Research Dcpartment concerning itself with water qt ality in our streans and reservcirs. Close
- liaison has been raintained uith state and local officials in our water nan-j ,
agement progrcms, and in 1965 the. Company began a major research project to study the offects of cooling watcr dis charge at its , Marshall Stcan Sta tion sit 4 on Lakc~ Norman. The first phase of this study involving heat dissipatica capability of receiving waters has been completed. The project's second phase, which includes a' study of the biological effects from cooling water discharge is now underway.
This national project is under the sponsorship of the Edison Electric Institute with Johns Hopkins University coordinating and directing the re-scarch. The Compary, the North Carolina Division of Inland Fisheries of the Wildlife Resources Commission, and consultants frce University or North Carolina branches at Chapel hill and Charlotte, are assisting in the collection 1 i.
1, and analyzing of speci: tens. The biological phase is expected to cover a period of at least three years and should produce important factual information con-cerning the effects of cooling water discharge on marine life. ,
s
.f' v ,-
1 Of
- t i ClC:.J ., c s
- p
-e' kp .
--.x - - - . . . . - . ~
s qu 4 el I l h .2 7Q ' L.0 ENCLOSURE No. 7 ;.;;:ig w,ur r-t;d/d d 4 F File Cy.
y&.tcrj LAKE KE0 WEE WATER MONITORING PROGRA}!
The purpose of this progran is to monitor the' physical and chemical .
characteristics of surface water *n the vicinity of Lake Keowee and the Oconee Nuclear Station.
The program was initiated in' the summer of 1965 with th'e establish-ment of 8 monitoring stations on the Keowee, Little River and Seneca River arms of the Hartwell Reservoir.
Samples are taken from a vertical profile (summer months l', S' thru 40', 50', 60' etc; winter conths l',10' 20' etc.) at each station.
The following parameters.are measured from each depth at each station:
temperature, dissolved oxygen, pH, turbity, total Fe and Kn. A con-posite (surface, mid-depth and bottom) B.O.D. is also measured at each station. -
Stations were sampled periodically in 1965 and 1967 (total of ten (10)
- times each station.) Since January of 1967, all stations have been monitored on a monthly basis.
The continuation of this program will include the establishment of
, appropriate sampling and monitoring stations in Lake Keowee after it fills. In addition, provisions are Deing made Ior tne installation of multi-point temperature recorders at the cooling water intake and unit effluent lines and in the connecting canal between the two arms of the lake, plus continuous temperature and dissolved oxygen measure-ments in the tailrace.
- DEV:RFG/pc .
September 10, 1969 e
QOd w s .: b.
1 1
~>
u
/
,0 2 %a ags\n\ wA -# .3 I
.g ( Y. fC3) ,
i '\
._, m n - ~ m Q ^?h ..?
l p ,a l Q .; .a.2 J s h 0'
~%'.
. . . . d.A '
24 vt 9.Fizet *
' hm%.
.pg %w e^'"~;%N bnM. g- [ .m wit.it De
, ~ . _ , - -
_ l'* ' J sw%A. ~,cM.%.$ij'r
~- -
- - ..%. <w_ ,z. ,
y 3g < 'p c
1 1
a >r l
h 9 4
f .
1, 4 -
,l p ,_ 3 _,, ' .
^
l_ _
. 4 .
n m;, '- 1 , .
- v. ~s Q
.y
_ s_ , 4' . % . ~_'
~ .
-~ -' '
%.gf y;. ;L . ..
~
/' ;
.4 17 .ng.. , 3; .N -
g j .;
,~
4( if .
N' ; -
- . - -. e; - ; . ; ;. , . .
- . . . r e . :
,,.~ .:
z_
. . - - .~
...,,nLM A_.__ g< . . .
- 1. r
'5 .
r 9
Nuclear Power at Oconee ,.:
1
l l
l Nuclear Power at Oconee 1 W. S. LEE Vice President Engineering Duke Power Compdny Charlotte, North Carolina W. H. ROWAND Vic,e President Nuclear Power Generation Depanment Babcock & Wilcox Barberton, Ohio Presented to AMERICAN POWER CONFER 3NCE Chicago, Illinois April 23,1968 Babcock & Wilcox ,
Introduction
+
The three-unit 2658 31we Oconee Nuclear Station of Keowee Station will have two conventional 70-31w
- Duke Power Company is the largest private utility hydroelectric generators. Construction of the 385
- nuclear power plant licensed for construction today. ft high Jocassee Dam will form upper Lake Jocassee 1
With an expected net station heat rate of 9,951 permitting installation of four 152.5 31w reversible
- Btu /kw-hr, it appears that Oconee will be the most pump turbines. When the initially committed con-
- efficient commercial light water reactor nuclear struction is completed in 1978, the Keowee-Toxaway ,
! plant in the world and the first to bceak 10,000 Project will represent an investment af $365,000,000 l Btu /kw.hr. When all three units are in commercial and a total generating capability of 3408 31w. Later, i operation in 1973, Oconee will represent 28 per cent two additional thermal plants are planned on Lake of the 9300 31w Duke system capability. Keowee plus further pumped storage upstream of As a part of the Keowee-Toxaway Project in Lake Jocassee which will bring Keowee-Toxaway's the Piedmont Carolinas, Oconee is located (Fig.1) ultime capacity to 8000 31w or more at a cost of
, in Oconee County, at the western end of the Duke over $700,000,000.
Power System in northwestern South Carolina near Consistent with Dulre's traditional policy, Lakes the North Carolina-South Carolina borders. Keowee and Jocassee wili be available for public The Keowee-Toxaway Projectl , was begun in recreation and as a water supply for neighboring 31 arch 1967 and will consist of two lakes used for communities. Property around the lakes will be i sources of cooling water, hydro power and pumped available for picnicking, camping, hunting, summer-
, storage capacity. The lower Lake Keowee is actu. home sites, wildlife resources, and other uses to ally two takes, connected by a canal, and is formed provide maximum public benefit through utilization
- by dams on the Little River and Keowee River, of 1 natural resources of the area.
J_.. Y m,6
, s.
q'
/ i .t[%
j . _
, w W ,x gj %
k STAIDI l
~
Y.
- 1. 2.
Station site Oconee Nuclear Stat!,n is located west of Keowee to document dispersion calculations used in environ- -
Dara and south of the canal connecting the two mental analyses. .
lov er lakes as shown in Fig. 2. The station tite takes full advantage of the
- i. posted one-mile exclusion radius will form the separation of the twin lakes forming Lake Keowee.
actual site boundary. Activitier within the site (Fig. 3) An intake canal south of the plant provides boundary are under the control of Duke Power Com. the inlet flow for condenser cooling from the Little
. pany and are limited to highway traffic, observers River arm of the lake while cooling water is dis-at the Dake Visitors Center located on a hill over. charged to the Keowee River arm of the lake.
looking the plant from the north, and recreation on Duke's experience with circulating water at Marshall the lakes. Steam Station has been incorporated in the design Total estimated population within a five-mile f Ocor.ee. Use of a skimmer wall there has improv-radius is about 2160 people, or approximately 28 ed summer station heat rate through use of cooler persons per square mile. By the year 2010 this water from lower depths of the cooling water source.
is expected to increase to about 2970, or 40 persons A skimmer wall for Oconee is being provided at the per square mile. With this low total population even entrance to the intake canal drawing water from projected to the year 2010, the site area qualifies as a depth of 7(, ft. Temperature of the circulatmg water is expected to be 15 to 25 F below the summer a low population zone and is beh.eved to be favor-surface water temperature. Limnological studies able among those h. censed to-date on the basis of .
, have shown that under the worst summer conditions, F3pulation density. the water discharged from the condensers into the Meteorology at the site is favorable for a nuc- Keowee River arm of the twin lakes will be at a lear plant under light wind conditions where the lower temperature than the lake surface. This ar-presence of the lakes will increase humidity and rangement is a means of controlling thermal effects wind speed. On-site meteorology is being recorded which have become an important subject to utilitics n
u M~; ewp?, . '25'
-- =f w~
z(9.;
1 !*5
-~ . p. k 25' _ -]=
m
+ n w.a s v m, .~e:.a r u w? y. - .
a -s&, 'g .. . %we'. Q ud m i ,
~3 w -
ur
- _ : 9a.; ,; ;, u Q;
.? : -
y 1 : a. g
'M - '-
- g. ~
,s N
3 ,,
"- , ~ -' ~ Xa- " a.y x
- v ;_ . A ~- g. g -
a , \s\ //
_ j- _
- gy;Q;5 ;[ y,ff
[ {---_7' 'kh _[=p M
- o A-.
N. h98CS e$ivh. M.& ,
pp'[.ww$hp$Nw/kgr D <
,3
_ w ,,49 M u t pg4,g yg Y-[,k. U
.m I)" hT3 ej~~~.~y sc U g "t gyhN"Th.k, w-/k,Q~' ~3 ,h.-.m S
u z s_ ;,.,, n z ,w. ~ ***M
.,. J5
_i ~~w -
- 'sh x.w=
fv( /#N ~
p"* ==I*f"#**P7"N W /,M M W
- 5. s
/ #' +*3$$% ' 6~
ra('.f
\;
~ . . -
v %(ca., ~ p%
_ g4'yf' .
w mj-A% '+mg.
b.:? ,w'Q',q st '+w.
~.L y\
Y t
i I 7 L.m M,;L. ct mo e;f 0J4 M C- @x(f( mm.* A D y l,.t . f:a% i, m& .,.% 5lr 4 ) 'y v%. m, s_/.I3 w 5
ins n /-
, o,
/_=,,-
'y ll %\
s j W-l > I -,
w .
4 c.J ' ', ,, ,'~~. s sit
~ s s '- Qj a 4/ ,y ff u,es'* *;, 7.e ,
1
i General station arrangement Layout 3
Each of Oconee's three nuclear steam systems is The station has 230 KV and 500 KV switchyards j
'! located in its own reactor building. A common fuel located east of the buildings. Emergency power handling building and storage pool for both fresh enters the station through an underground 13.8 KV )
and spent fuel serves Units 1 and 2 and is located line from Keowee Hydro Station and through a 10G I between the two reactor buildings. Unit 3 has a KV switching station located west of the buildings.
separate and independent fuel handling building and Other structures include an administrative build- i storage pool. A machine shop designed to handle ing connected to the no-th end of the auxiliary and '
and maintain slightly radioactive equipment is lo- turbine buildings, a 100,000 gallon elevated water cated next to the fuel storage pool for Units 1 and 2. storage tank, and a microwave tower also used for Support equipment and facilities for Units 1 and weather observations. i 2 reactors are housed in a nine-floor auxiliary build- Description l ing. Equipment includes pumps, heat exchangers, A composite plan view of three elevations is shown I tanks, instrumentation, and switchgear as well as laboratories, lockers, showers, a laundry, and health in Fig. 4. Unit i view is taken at the turbine oper-ating floor and the combined control room for Units physics facilities. The auxiliary building also houses 1 and 2. The turbine. generator is a six. flow machine a combined control room for Units 1 and 2 at eleva-with 38 in. last stage blading coupled to a 1,038,000 tion 822. A similar arrangement with its independ- KVA water cooled generator. Two 34 in. dieneter ent control room is used for Unit 3 in a separate steam lines carry 11,194,000 lb/hr of 925 psia steam but connected auxiliary building.
to the turbine.
A single turbine building located adjacent to The auxiliary building at this elevation contains the auxiliary buildings houses three General Electric ventilation equipment, the combined control room turbine. generators and support equipment for the for Units 1 and 2, and office space for shift person-steam, feedwater, and condensate systems. The building is about 800 ft long and 200 ft wide. The nel. The shielded control room contains the control console, nuclear instrumentation cabinets, engineered operating floor is located at elevation 822 to pro- safeguards cabinets, and computers for Units 1 and vide for easy access between the turbine operating 2. Each unit has its own computer utilized for tur-f! cot and the control rooms. bine cycle control, sequence monitoring, equipment
[
N .<
N. c. . >.
^h 0, h..
+
Im N N I yyy ***yE 9:W^- "
_ ., y --%*di m - -
3.%
j m e = g yp
.- - - i 6y = =c =
- - ,e co ,p w.#
c, u 4pr.
U ,
i i w eo , 7 2 . .
"se e o oo ~ c-S o e o 4 INM+ : i; g_y:ggg
.. . oe o: (-
11 _ ._, , . < ,- m . . -.
i 4 .- m t
E.F. A.a+71:doOI9miw -~ ,
~
~1 A A '6 6 T_ -
J
$ xth ~ .
- c. n
- }E m d
UNIT 1 Q O .
~ UNIT 2 UNIT 'l ELEV. 822 =
$ ELEV. 796 ELEV. 755 4.
c
status reports, controllable loss calculations, record- Fig. 5 is a cross-section of the building showing 7 ing of in-core instrumentation readings, core power the two once-through steam generators, the reactor _
distribution, and fuel management calculations. vessel, reactor coolant pumps, and the fuel transfer The area of each of the reactor buildings canal. Secondary shield walls around each coolant through which all of the electrical, instrumentation, loop and shielding floors protect personnel from and piping penetrations pass is enclosed by walls direct radiation. Areas between floors are accessible
.o form a room. In the unlikely event of a loss-of. during power operation.
coolant accident, followed by a release of fission products, a ventilation system consisting of fans and filters is started which produces a slight negative pressure in the room. Therefore, any leakage through the penetrations will enter the room and, after filtration, will be discharged to atmosphere through the Unit vent.
m The plan view through Unit 0 is taken at yard W grade, elevation 796. The turbine building at this h 11 elevation houses the upper portion of the conden- T sers, the four combined moisture separators, and STEAM reheaters for each turbine, turbine valves, and the GENERATOR -
r3 ant switchgear. The auxiliary building at this level m, eludes shippmg and receiving areas, equip.
N {%
Q y
PRESSURlZER a _
ment rooms, laboratories, health physics offices, locker rooms, and laundry facilities. PRIMARY -
- 6 ,
-l O *Q Unit 3 is shown at elevation 775. The turbine PUMP
- - REACTOR building houses the condensers, condensate polish. =i-y y ing and feedwater systems, service water, turbine driven feedwater, and emergency turbine driven q
[
h g ~
g q
feedwater pumps, and other turbine generator auxili. .
ary equipment. Condenser coeling water lines enter and leave the building just under the floor. In addi.
tion to the main condenser cooling water hnes, a small line is provided running from the discharge The openings at the top and bottom of each of each condenser to the tailrace of Keowee Hydro. of the secondary shielding compartments are sized Upon loss of circulating pumps or loss of power, a to permit the escap of steam in the unlikely event valve in this line opens and a gravity flow of cool- of a major loss-of-coolant accident. A 19 ft diameter ing water, sufficie:'.t to remove reactor decay heat, equipment hatch at the grade elevation of 796 per.
is initiated through the affected condensers. This mits easy access to the main floor of the reactor flow, coupled with turbine driven fetdwater pumps, building.
permits the removal of decay heat from the reactor
. without the need for electric power.
The auxiliary building at this level houses the purification system, decay heat removal system, and
- waste disposal system tanks. The elevations not shown house additional auxiliary and engineered safeguards equipment for the reactor coolant system.
Each reactor building is a pre-stressed post.
t:nsioned concrete structure with a steel liner. The
- Nilding has an inside diameter of 116 ft, a height of 208 ft, and is designed for a pressure of 59 psig.
General station arrangement The fuel handling system for each Unit is shown from the computer to the operator by means of a in Fig. 6. New and spent fuel assemblies are trans- refueling panel mounted on each of the bridges.
ferred between the reactor building and fuel storage IIowever, only the bridge operator has control of pool by dual transfer mechanisms. Within the re- bridge and tool movement. -
actor building fuel is carried by two handling bridges, Fuel assemblies are carried by a similar handl-one of which transports fuel assemblies between the ing bridge in the fuel storage building where they reactor core and the transfer mechanism. The other are stored in racks to await shipment. Crane facii-is free to rearrange fuel assemblies and control rods itics and building dimensions are sized for either a within the core. small two-assembly shipping cask or a large multiple-Fuel assembly accounting is me.intained by the assembly cask.
Unit computer. Information on the replacement and Each unit is supplied with identical handling relocation of fuel assemblies and control rods is fed bridges, handling tools, and storage facilities.
% _______. - n f
%[y , :d/
. -l.'
'y I ;
.- - N '
- y. .
aN u g An x b
b.h .
W
. . ' ,* . . . . /
-rJ 5
fN
'd 5
- f. ' .
.J>
,; , b Gv
[
g , *-
Vh.
A z,.l M
% '*i-
?;, l .
(( _
- c. .t . . .. .
.y. .: : .:-> --
.,9 . ,,.
y c y g_
., -s ..
,. g* f .
. . , ._ . x. ; >
m ., ..
^
N -
-. .. , . 7/.
l N % 4 l,5. /
- 6. . .
4 P
=
6
Unit performance A simplified cycle diagram is shown in Fig. 7. At low pressure turbine stages. The first reheat util-7 the nuclear steam system capability of 2568 Mw izes extraction steam at 537 psia while the second .!
thermal, the gross electrical generation is 922,000 reheat uses throttle steam.
Kw. A net unit heat rate of 9,951 Btu / kwhr is ex-Total unit steam flow is 11,194,000 lb/br of pected with zero make-up and one inch Hg conden-which 365,000 lb/ hr is used for the second stage of ser pressure. Feedwater is heated to 460 F by two g string of heaters, each consisting of four low pres-sure heaters and two high pressure heaters. Com. Powdex polishing demineralizers capable of bined moisture separators and reheaters provide two handling the full condensate flow of 6,558,000 lb/hr stages of reheat between the hirh pressure and are located downstream of the hotwell pumps.
131,000,000 L8/HR
-' 194,000 LB/HR LP 2200 PSI F ' 90 22,000 m I
hRBINE TURBINE j /
x x-
_ CONDENSR A 1" HG u o v
554 F ) STEAM MOISTURE Q' 16 REACTOR 2568 0
REHEATER
' I 6,558,000 Mt V MWt V L8/HR l FEB
- " " Pl!MP CONDENSA 922,000 N GENERATOR OUTPUT
-36,000 N AUXILIARY POWER 460 F HP HEATERS :
hJ _.,
886,000 N NET PLANT Ob7PUT 9,951 BTU /N-HR NET PLANT HEATRATE
, O TO
~ CONDENSER 7.
Station electrical system On completion of Unit 3, to ensure operating con- wee Hydro will be both automatic and remotomanual tinuity of station auxiliary equipment under all from the Oconee control rooms, which gives Gconee conditions, each unit at Oconee will have six sources operators complete control of its hydro power gen-of power. These consist of power from each of the eration as required for any conceivable emergency three nuclear units, a 230 KV switchyard, a 100 KV condition.
line, and a 13.8 KV underground line from Keowee Hydro. A single line diagram showing the multiple g , ,non ums sonn ams @ -
sources of power to station auxiliaries on 4.16 KV ! ,I k I k I k b " ""
busses is shown in Fig. 8. k N L k
Normal power for unit auxiliaries is carried con- '
k .h ) ) ) h c _ k. 5W ventionally from an auxiliary transformer connected "H " $ ~
4 4 4 4 %
~ ~ ~
$~
d to the generator bus. With the auxiliary transformer ~_~-
unavailable, power is supplied through the start up J, 1 ,, ,. --h o
transformer fed from the 230 KV busses. There are - m lI II I
12 power supplies to the 230 KV switchyard which " *1 *9""****
- include eight 230 KV transmission circuits, the three g ,g l h h :'k k k k :k , " f nuclear units, and the Keowee Hydro units. Both the auxiliary transformer and the start-up trans-ppp p pp gg,wt ,g former ratings are sufficient to carry full load ,,' g ,,,,
auxiliaries of one unit plus another unit's engineer- 1 ii ed safeguard systems- D u as w a ns& m m Ast If a unit auxiliary transformer or any of the 8-start-up transformers through loss of 230 KV are not available, power still can be supplied to auxil-iaries and engineered safeguards from one of the other Oconee units through its auxiliary transfor-mer.
Should power be lost from these sources, a sep-arate 100 KV line from Duke's " Central" 100 KV transmission system provides power to the 4.16 KT busses throu# a transformer sized to carry engi-neered safet gls of all units. Under emergency conditions, the 100 KV transmission line can be iso-lated from the 100 KV transmission system per-mitting any one of three 33,000 Kw gas turbine gen-erating units at Duke's Lee Station to supply power solely to Oconee.
In the highly unlikely circumstances of loss of power from all sources described above, Oconee has another unique and dependable source of emergency power from Keowee Hydro. The two 70 31w Hydro units are separately and redundantly connected to -
Oconee through an overhead 230 KV line to the 230 KV switchyard and a 4000 ft long 13.8 KV under-ground cable to a transformer sized to carry engi-neered safeguards for one unit plus orderly shut-down of auxiliaries for all units. Operation of Keo-
7 l
Q;d*
,9N*
a.,chese
') N> If ,f gb,? g
/ '[
s <
/// $( gy 9 e y,,,, 4/ /gs,, fk
\ IMAGE EVALUATION *%
TEST TARGET (MT-3) 1.0 !t"?!
i2 I32 m
2 l@l 2.2 l- 336 Ik U g2.0 l l.1 L I_ l.8 1.25 1.4 1.6 l
4 6" >
MICROCOPY RESOLUTION TEST CHART ll/
?
d~,7,,y,
'D
'4D)4 3,
f&
s
.x:3 A
Training Nuclear training at Duke Power Company began will undergo a five-phase training program spread over a decade ago when the Company started train- over about two years shown on Fig. 9.s The first ing engineers who would eventually participate in phase is classroom training in nuclear physics, math-nuclear power programs. Duke's participation in the ematics refresher, and introductory nuclear engineer-4 Parr project provided a means for continued train- ing.
ing of personnel. Phase two covers introductory reactor oper-Following the decision to design and construct ations conducted by B&W on the Lynchburg Pool a nuclear station at Oconee, Duke extended training Reactor. During this phase each trainee will con-through introduction of a nuclear engineering pro- duct a minimum of ten reactor startups.
gram in the fall of 1966.8 Babcock & Wilcox and During the third phase operators will gain act-Bechtel Corperation personnel conducted classes at- ual operating experience at the Saxton reactor.
tended by 80 of Duke's personnel.
The fourth phase will be detailed indoctrination Part of the technical support and operating staff in the design and operation of the Oconee reactors for the station are presently enrolled in graduate given by B&W engineers.
level nuclear engineering courses at North Carolina The last phase is on-the job training at Oconee.
State University. This training will be completed in In this phase the trainees will become thoroughly June 1968. These men will later teach basic theory familiar with the plant by assisting in preparation required by the station operating staff as the first of test and operating procedures and by plant oper-phase of the operator training program. ation during the pre-critical test program. AEC Personnel to be licensed for reactor operation operator exam. etre scheduled for October 1970.
1 1968 1969 1910 1
TRAIN KEY MEN '
BASIC THEORY l LYNCNBURG POOL i REACTOR TRNG.
l POWER REACTOR l
DPER'l TRNG.
B&W NSS DESIGN ON THE JOB TRNG.
I AT OCONEE i EMERGENCY TRNG.
B&W SIMULATOR "
\
AEC LICENSING a FUEL LOAOlNG
- 9.
1 l
l
Station construction schedule Significant m lestone dates in the station schedule Start of delivery of the major components is
_. I . ace indicated in Fig.10. The first bar is for Units scheduled for March 1,1969. Continuous erection 1,2 and 3 and the remainder of the schedule is for of the nuclear steam system will begin at that time Unit 1 only. Contract award date for Units 1 and 2 and is scheduled for completion one year later. ,
was June 20, 1966. Application for a Construction Turbine generator erection will begin Decem-Permit was filed December 1,1966. The award for ber 1,1969 and finish one year later. During the Unit 3 was made April 21, 1967 and on April 29 intermediate stages of plant construction, cold test-the application was amended to include Unit 3. ing of systems will be initiated as systems are com-Site grading began March 20, 1967, involved pleted. Major systems such as the reactor cool-the movement of 2,200,000 yards of earth and rock, ant, purification, decay heat removal, waste dis-and was completed November 1,1967. posal, and feedwater systems are scheduled for com-It became apparent in July 1967 that interven- U i n by June 1970 and pre-critical testing will begin then. All pre-critical testing is scheduled to ors would delay issue of the Construction Permit. To avoid delay in start of construction and provide flex- be completed by December 1,1970; operators w;ill ibility in the overall construction schedule, approval nsed by mat time and fuel lod,ng wiH kgin.
of the AEC was sought to initiate work on the A total of five months has been allowed from start tendon access gallery prior to issue of the Construc- I I" "U"" * ***rcial operation on May 1,
. R is Mcuh to anticipate what the exact tim-tion Permit. This was obtained and work began on . , ,
October 15, 1967, a little more than three weeks ing f events will be within this period. Approximate-before issue of the Permits for the three units on ly wo weeks are allocated for fuel loading and four November 7,1967. weeks for physics testing. Power operation with discreet tests at various levels is expected to take The reactor building is scheduled for completion eight weeks. The remaining seven weeks is contin-on May 15,1969. gency.
1966 1967 1968 - 1969 1970 1971 ORDERED UNITS NO.1 & 2 NO. 3
^""*' - " '"#'
CONSTRUCTION PERMIT AMENDED APPUCATION SITE GRADING Hl REACTOR BLDG. l' l NSS ERECTION , 5 5
.TURB. GEN. ERECTION l l PRE CRITICAL TESTING H FUEL LOADING p INITIAL OPERATION H l CGMERCIAL OPERATION F--
- 10. .
l
l l
I Status of site work i Construction progress to the end of March 1963 Des in of Oconee is by Duke's Engineering 4 l is shown in Fig.11. Excavation of the rock beneath Department with assistance from Bechtel as gen. _
l the reactor buildings is complete. The tendon access eral consultant and designer of the reactor building, i gallery and concrete mat have been poured on the As in the case of other Duke plants, construction, Unit I reactor building. Work has begun on the including equipment erection, is by Duke personnel reactor building side walls. in its Construction Department.
i i
- 3 hf M
~
% 0 D
- 1. A0 > K%
a sw ,..n . : ; w:.gl_
,_-Q ,% ;-Q.
i
. f. . , & , , g. * '
, . ' ' ' ' 'y fy Q. .f. u v. ^' g,g . _Z'*
_ ~^
9 *. -- .; 2
. ' h] .1
~
. .- ,_s._ _ ,.
N' M T'* *Jd? - _~'L I
.m.- 8
- . * % 39'.*bh ,
eL,g .
w,.
w,m# ,,s yw.' yh.y;. . 4
- n. u.s.,e :w m . ys+ g w.. - m w* w eet.= m "m g m. . mg .s?
n ~ .
N.
. ' 3 %' h'* ' s,e .
't Q . r .e . A*m.* g: :
- . ,1 / , . .
. . g. A ,s .
- b ~
~;
~ %4 I~ , ,.# - . >.n 7 f~
{E.- e n f
. ,w g; --
_.,g . .
~ 'j
- .;r^ .
- -~ _ ~5 Q
- f. h[ 'I ,.
. n_ .WZ
.,. ' .. ~' f,.' ,<~. ,, \
174 *R,*
Q:Q}y. . .l5, >' %+lx -Q j;}
y, f*'* ,t,*h '.e8 ;;
N .]
_'.-w
%n . .-s,y.w
. sw .
s .-
- *. . .h 2
- m. .,: .3 .
.,4 n a ' q. ..i
,[M. =duT .py.' .Ai%1,a.by"
~ . r > . %.
k- e'N. w.y.r.c U"MI
- ,h i s.
,, f ar.
2-t u9 ta. ., . i[.t nC%
14p g * -
W. NR -
.. kY y ,.;J,
.. ,s @5'w -
' N S a t..
y Owf fn.My' '9.y :
t % g ' .g#.;; ". wM,:
't
- b. -m.J,:
m b.:?. 4- w %j Ws, ah . v. .. m.u- .,: .,
. d,._
t-
- 4. w n ^ 7,ygf ww' **A. . 4 w *!"yW"'iW dr av5 ,Tg w:* w. m . y^j
'y .
i' Q
/..
W ;.W;
.4
..y.*. f a
- Q 4 g. ,. %
a .;i . As . *
. ' . . .;/f J
. , :c,4 r . .
' n y.c:>.u~M . W#* % n ...~+u' pq p,.d. .L.O f A[ , , , '] -
e s .
- . . . y & ' d'
(. : ,
- f * '4s S.g h ,. .gs,, ' w,' ;[. )
L i f..
N, y n:4 gygnG.A &m .,M;l 7' -
e ') -
.% .~
$i;
,. A h4
- i. .% , . . h f y .. ; u. .p. g . ,....,
- i. 4 . -
1 -
-e -
8 v, ' s y- s, .... * *
. y . s
- e. Y. ' , . .
g* . Q.,
p
- l. .'\ \ ,.... * **#
Ws. &u g
,,g .h, .
-sN j<g , . ', - . .
r , -
.;;a. - 4y. s qJ+ g ; x i. .J. . 33 ' %% . v.,Rgs .y. 3
, . u. , ..
3..La; m7 f{ i w. ....E.w;s\s.
.u y; s Q.. . .~, ...,t.
5
--.4.
,4
. m .' . .Q y 11.
Nuclear Steam System I '
B&W's participation in the Oconee project is the 2- design and supply of the three nuclear steam sys-tems, including auxiliary and engineered safeguards systems, technical direction of erection of this equip- .
ment, assistance in operator training, and establish.
ment of design criteria for the balance of plant equipment. In addition, B&W is responsible for de- .
livery of the 350-ton reactor vessel to the site through a combination barge and overland movement. Five cores covering complete fuel supply and three cores l of fuel fabrication only are also contracted for.
i i
e I
9
Reactor coolant system (nyd.agdgy"a L e it m Reactor vessel The Pressurized Water System is shown in Fig. The reactor vessel, shown in Fig.13, consists of a 12 and consists of the reactor vessel with two steam cylindrical shell 171 in. ID by 8-7/16 in. thick, generator loops. Each loop contains a straight tube supported by a cylindrical skirt. Sixty 6-1/2 in.
once-through steam generator and two reactor cool- diameter studs bolt the reactor closure head to the ant pumps. A pressurizer, connected to one of the loops, maintains the reactor coolant in a sub-cooled
. state. ..
Reactor coolant piping is 28 in. ID and 36 in. ID carbon steel pipe clad with stainless steel. Each out-4
.Q, ' -
ili -
let pipe contains a calibrated flow tube used to ,
"e." )
measure reactor cvolant flow during operation. Ill j i The entire rer ctor coolant system is designed for "Jj l. l,l,1l ' l. 5 2515 psia and 650 F. Reactor performance is listed in Table 1. Normal power operation will be at 2200
"*P.'r*( ' "
- psia and an average coolant temperature of 580 F. { N Design conservatism is shown in the average power density of 83.4 Kw/ liter, [d j
- l h [l ll h l Ll 'j fj '!
if[
j 4 mp 3 3 1 ? 1
, 4
.I 3
( W .-
O,.
e w,Ni ,
1 ;% ; ,
-? '
V %
.4 * * ., )
i -' 13. ,
5[!b,'f) l
, , 't
, REACTOR DATA
- Reactor heat output 2568 MWt
,, Reactor temperature average 580 F Reactor operating pressure 2200 psia
,, Reactor flow 131 x 108 lbs/hr Linear beat raie average 5.7 kw/fr.
s
- j Linear beat rare peak 18.4 kw/ft.
Volumetric power density 83.4 kw/ liter Fuel Weight 201.500 lbs/UO 2 No. of fuel assemblies 177 l No. of control rods 69 l 12.
Table I l
l l
l
Reactor coolant system 1 ! vessel, sealed by two metallic O-rings. Pressure psig and a temperature of 95 to 100 F, is designed i~' taps in the annulus between the seals permit hydro- for full reactor coolant system pressure.
static testing of the closure following refueling. Two Each pump is designed to deliver 88,000 gpm 10 in. emergency injection nozzles, located at the at a developed head of 370 ft. The squirrel cage, same elevation as the inlet and outlet nozzles, pro- induction motor requires a power input of approxi-vide a direct path to the vessel for the injection of mately 5400 Kw.
water.
- The reactor inte nals are designed to direct the Pressur.izer coolant through the core, support the fuel assem. As indicated in Fig.12, the pressurizer is connected blies, and provide guidance for the control rods. The to one of the reactor coolant loops with a 10 in.
surge h,ne. It is used to establish and maintam, upper assembly, located directly above the ccre, is ,
removable as a single component prior to fuel handl. reactor coolant pressure within prescribed limits and ing. The lower assembly is hung from the reactor to provide a surge chamber and water reserve to vessel flange and supports the fuel assemblies, ther- accommodate reactor coolant volume changes during mal shield, and in-core instrumentation guide tubes. temperature transients.
It can also be removed as a single piece for inspec. The pressurizer contains replaceable electric tion of the reactor vessel surfaces. heaters and a water spray to maintain the steam and water at the saturation temperature correspond-Steam generator ing to the desired reactor coolant system pressure.
The steam generator', Fig.14, is a vertical, straight Relief valves, mounted on the top of the pressurizer, tube-and-shell heat exchanger developed to produce funct. in to relieve any system overpressure. The superheated steam at constant pressure over the relief valves discharge to a tank containing a stored power range. Reactor coolant flows downward water supply to condense the steam. A recirculation through the tubes and steam is generated on the system is provided to cool the tank water following shell side of the heat exchanger. The tubes are any relief valve operation.
welded to tube sheets at both the top and bottom of the steam generator, and tube supports are pro-vided to hold the tubes in a uniform pattern along REACTOR COOLANT INLET the tube length.
Feedwater is sprayed into a feed heating an-nulus (downcomer) formed by the shell and the '
}
baffle around the tube bundle and is heated to sat- !
uration temperature by direct contact heat exchange.
Dry saturated steam is produced in the film boiling j ,
L
,-- STEAM OUTLET region in the u.,per section of the tube bundle. The '
remaining surface increases steam temperature to ,_f l-- FEEDWATER INLET about 35 F superheat at the outlet.
Reactor coolant punaps The reactor coolant pumps are vertical, shaft-sealed ,
units with a single-speed, water-jacketed motor.
Shaft sealing is accomplished with a throttle bushing and a mechanical seal. Seal water is in- .
jected ahead of the throttle bushing at a pressure '
approximitely 50 psi above reactor system pressure.
Part of the seal flow passes into the pump volute REACTOR COOLANT OUTLET while the remainder flows out along the throttle "'
bushing and is returned to the seal water supply system. The outboard mechanical seal, which nor-mally operates at a pressure of approximately 50
Reactor core The reactor core consists of three major compon. CONTROL ROD
'~
ents; 177 tuel assemblies, 69 control rods, and 52 ASSEMBLY v in-core detector assemblies. These components are LOCATION assembled into a 12-ft high uniform close-packed g%,
array with an equivalent diameter of 129 in. Fig.15, "h g%
a sectional view of the core, shows the arrangement of the fuel assemblies and control rods in the core. '
f
[4 El gm lig;)[334'
(
Reactor fuel is sintered pellets of low enrich- 3 * * *
- ' _*L . o , x '" - ,
ment uranium dioxide clad in Zircaloy-4 tubing. gi e ; o e * .
- x 14 Each fuel assembly, shown in Fig.16, consists of ~
- [sg ;j , , , , ;*f 208 fuel rods mechanically joined in a 15 x 15 array. y :..- p . o e a f The center tube accommodates the in-core instrumen- -
- ' ' * * * *P J tation. The remaining 16 positions contain Zircaloy d( .d , x. E$15* gg e -
tubes used as control rod guides. In those assem- % #
blies which do not contain a control rod, the guide -
f THERMAL tubes are blocked to mmimize bypass coolant flow. N CORE Fuel rods are positioned by spacer grids located SHIELD BARREL axially along the fuel assembly. The spaaer grids 15.
are designed to permit relative axial motion between the Zirca'oy fuel rod and the assembly structure.
h1 l Control rod assembly l [
Each control rod, consists of 16 control pins coupled to a single stainless steel spider. Silver-indium-cadmium in stainless steel tubing is used as the ?
ll J l
neutron absorber. The control pins are loosely coupl-ed to the spider to permit maximum conformity g with the channels provided by the guide tubes. a f Each control pin is guided for its full length in j n the fuel assembly and in the upper plenum assembly
- ,I above the core.
((f '
]a ll&
In-core detectors i l l The in-core detectors, consist of an assembly of self- ) l powered neutron detectors and a thermocouple po-sitioned within the center tube of fuel assemblies at pre-selected locations in the core.
The in-core neutron detectors have been under test by B&W for a number of years, including oper- i;
' ation of a prototype detector assembly in the Big f, Rock Point reactor. The detector assemblies are in-serted into the core through guide tubes which ex- (L tend from the bottom head of the reactor vessel to an area adjacent to the refueling canal. During refueling the in-core detectors will be withdrawn from the fuel assemblies.
16.
Engineered safeguards Engineered safeguards systems for Oconee fulfill emergency injection is contained in core flooding i I three functions in the unlikely event of a loss-of- tanks under nitrogen pressure. This coolant is in-coolant accident: jected directly into the reactor vessel should the a) Protect the fuel cladding system pressure drop below 600 psig.
b) Insure reactor building mtegrity
. . Emergency injection into the reactor coolant system is initiated at 1800 psig. The signal auto-c) Prevent uncontrolled leakage of reactor matically increases high pressure injution flow td' building contents to the atmosphere- the reactor coolant system by starting the standby Each of taese operations is performed by two or pumps which are switched to the suction of the more systems with multiple components to insure 360,000 gallon borated water storage tank. Valves operability. in the high pressure injection lines allow discharge Post-accident safeguards functions are perform, of the borated water directly into the reactor cool-ed with the equipment used in normal operation as ant loop through four lines.
its regular use provides the best possible means In response to the AEC licensing requirement for monitoring availability. In cases where equip- that cooling of the core be ensured following an ac-ment is used for post-accident conditions only, the cident in which the simultaneous loss-of-power and systems have been designed to permit periodic severance of the largest diameter pipe is assumed, testing. a core flooding system is provided. This system is composed of two flooding tanks, each directly con-Emergency injection systems nected to a reactor vessel emergency injection nozzle by a line containing two check valves. This system General arrangement of the emergency injec-does not require electrical power, automatic switch-tion system is illustrated in Fig.17. The principal ing, or operator action to ensure supply of emergency design basis for the emergency inject:on of coolant coolant to the reactor vessel. System volume is suf-water to the reactor core is to prevent clad melting for the entire spectrum of reactor coolant system ficient to recover the core hot spot assuming no liquid is contained in the reactor vessel. Gas over-leaks, ranging from the smallest to one with an pressure and flooding line sizes provide core reflood-area equal to that of the largest reactor coolant ing within approximately 25 seconds after the larg-pipe.
est pipe rupture has occurred.
High pressure injection is provt.ed to prevent The low pressure injection system is normally uncovering of the core for small lus and to delay maintained on standby during power operation.
uncovering of the core for intern.ediate-sized leaks. System pumps provide 3000 gpm supplemental core The core flooding system and the low pressure flooding flow during the accident through the two injection system are provided to recover the core core flooding lines after the reactor coolant system at intermediate to-low pressures to maintain core pressure reaches 135 psig. Emergency operation of integrity with intermediate and larger leaks. this system is initiated by a reactor coolant system Borated water pumped to the reactor coolant pressure of 200 psig.
system by the injection systems is supplied from a Low pressure injection with supply from the 300,000 gallon storage tank. Additional coolant for borated water storage tank will continue until a, e
low level signal is received from the tank. At this the reactor building pressure reaches 10 psig, re-time, the operator will open the valve controlling actor building sprays are initiated simultaneously suction from the reactor building sump and recir- with the air recirculation cooling. 'INvo 1500 gpm culation of coolant from the sump to the reactor pumps take water from the borated water storage vessel will begin. Low pressure injection coolers tank until this coolant source is exhausted. After will cool the recirculated flow, removing heat from the supply from the borated water storage tank is the reactor building. exhausted, the spray pumps can take suction from the reactor building sump recirculation line.
Reactor building cooling Redundancy of equipment within both cooling Air recirculation emergency cooling units and re- methods ensures protection of building integrity.
actor building sprays are provided to limit post. During the 30 to 40 minutes that the reactor accident building pressures. building spray pumps take their suction from the Each reactor building emergency cooling unit borated water storage tank, the spray system pro-has a rated capacity of 80 x 10* Btu /hr with 75 F vides more than 100 per cent of the heat removal cooling water at peak post-accident conditions. When capacity of the reactor building cooling system.
/
m CORE o BORATED E FLOODING E WATER j TANKSj .d STORAGE TANKS
- ~
^
W .
g yC00LERS r+e -
V ^
PUMPS 3 3 PUMPS P Lc' -
L
. ? -
' b I I SU MP 17.
1 Instrumentation and control 1
As is true with any utility operating plant, the signals of neutron power over the span from seven ,
.T' quality and capability of the instrument and con- decades below full power to approximately full power. '
trol and protective systems determine to a large The signals originate in two compensated ion cham- )
exter.t the ability of the plant to perform to its bers located on opposite sides of the core. The sourep j fuli capability. Table II lists the various instrumen- range has two logarithmic signals of neutron power ,
tation systems and their functions. over the span from source level to five decades I above source level. Signals originate in two pre-Nuclear instrumentation system portional counters located on opposite sides of the The nuclear instrumentation system monitors the core.
reactor neutron power from source level to 125 per cent of full power and supphes information to the operator, the reactor controls, and to the reactor When pre-determined conditions exist in the reactor protective system. or the coolant system, the reactor protective system The power range utilizes four linear channels acts to trip the reactor by fully inserting all control
- ds. Above 1.0 per cent of full power, four signals of neutron level over the range from approximately will trip the reactor; reactor power, power. flow ratio, 1 per cent to 125 per cent full power. Each channel reactor pressure, and reactor temperature. For each consists of three uncompensated ion chambers locat-ed outside the reactor vessel opposite each quadrant reactor coolant pump combination, there is a max-l "
of the core. One of the four channels is selected for e ce , $p t e reactor. I igh actor la use in the reactor control system while all four pressure will trip the reactor to prevent lifting relief channeis are used in the protective system. Tw valves. Low reactor coolant pressure and high re-out of four coincidence logic connects the overpower actor coolant temperature will trip the reactor to trip signals to the protective system. prevent reduction in margin to departure from nue-The intermediate range uses two logarithmic leate boiling.
SYSTEM h FUNCTION ARRANGEMENT NUCLEAR INSTRUMENTATION MONITOR REACTOR 2 SOURCE CHANNELS NEUTRON LEVEL 2 INTERMEDIATE CHANNELS 4 POWER CHANNELS REACTOR PROTECTIVE MONITOR REACTOR AND 2 0F 4 SENSORS EXCEEDING COOLANT SYSTEM FOR ABNORMAL LIMIT WILL CAUSE TRIP CONDITIONS ENGINEERED SAFEGUARDS MONITOR REACTOR 2 0F 3 SENSORS EXCEEDING SYSTEM FOR ACCI' LENT LIMIT WILL INITIATE CONDITIONS ENGINEERED SAFEGUARDS IN CORE INSTRUMENTATION MONITOR CORE DETECTORS READ BY FLUX DISTRIBUTION UNIT COMPUTER NON NUCLEAR INSTRUMENTATION MONITOR INDICATOR AND CONTROLS PLANT CONDITIONS AS REQUIRED Table II
Engineered safeguards protective system The engineered safeguards protective system initi. response of a boiler-following system to provide ,
ates operation of engineered safeguards equipment optimum response from the reactor. boiler turbine when an abnormal condition exists in the reactor unit. Fig.18 shows a simplified system arrangement.
, cooiant system or the reactor building. Iead demand from the system is compared Each protective action is provided with dual to the capability of the unit to maintain or change control channels. The channels are duplicates; each load. The modified load demand is then applied to
- containing a two-outef three coincidence logic net. the feedwater, reactor, and turbine controls in work, a separate power source, anu actuating relays. parallel.
An energized output from either of the two channels Turbine valves maintain control of steam pres.
initiates the intended protective action. sure. A change in load demand generates an error signal which is used to change the steam pressure In-core ,instrumentat,on i set point. Turbine valves change position to maintain In-core instrumentation consists of 364 self. powered steam pressure resulting in a fast load response.
neutron detectors divided into 52 channels. The out. As generation is matched to demand, the steam put of the detectors is processed by the plant com- pressure set point is returned to its original value.
puter to provide fuel management and core power Total feedwater demand is ratioed between the distribution information. two steam generators in proportion to their capa.
bility as modified by the number of reactor coolant Integrated control system pumps in operation. Feedwater is controlled in each The integrated control system, an adaptation of the loop in response to the modified demand. The result controls developed for Universal Pressure Boilers, of a change in feedwater flow is a positive and rapid controls the plant electric output. It combines the response on steam flow, steam pressure, and Mw stability of a turbine following system with tha fast generation.
s.l
<?
I I g- ,, -A f
CT U
V NEUTRON Ftux
. V STEAM REACTORC00lANT
. DEMAND I I OUTPUT is.
Instrumentation and control Proposed fuel cycles The capability of the Ocenee station repres.nts a the fuel removed from Unit 1 to be transferred to
~ significant block of power in tFa southeast. For the Unit 3 spent fuel pool for use in the initial load-thir. reason, unusual attention muso be paid to fuel ing for Unit 3. Any changes in Unit I capacity fac-management to insure shutdown periods for refuel- tor or operating considerations, that would shift the ing consistent with peak power demands. In addition, end of tne fuel cycle and refueling of Unit 1, can three duplicate units n' Ngle site present a chall- be accommodated in this time period. Fuel sharing enge in optimization of the tctal station fuel cycle between Units 1 and 2 was cor.sidered and rejected to reduce the first cycle fuel cost penalties usually as it would require a significant reduction in the associated with the startup of nuclear plants. Poten- first cycle of Unit 1.
tial economies through an increase in megawatt An independent cycle is planned for Unit 2 A days per metric ton and a reduction in the number I ng first cycle is planned to permit operation of fuel assemblies which have to be purchased initial-ly are possible through sharing of fuel between Units through the second summer peak with a refueling i and 3 as shown in Fig.19. period in the autumn.
The approximate one year interval between Following the first cycles, Units 1 and 3 will completion of the first fuel cycle on Unit 1 and com- have staggered refueling periods each spring and mercial operation of Unit 3 permits _a i.ortion of Unit 2 will be refueled each autumn.
MAY MAY MAY IEPT.
1971 1972 1973 1973 yygy j 1H NEW M NEW N NEW v, .
I I j I
UNIT 3 37 l
l i
l Vi l I i i i l l e ! i i i ; e i 8 e i '
i i i l in NEW N NEW DNii 2 l @ :, @
l l ! : .
19.
Conclusion In 1950 the Philip Sporn plant of Ohio Power Com- dict the heat rates that will be realized in the next pany became the first thermal plant to operate at two decades nor the advances in technology by which a heat rate below 10,000 Btu /kw-hr. It was a sig- they will be achieved. There can be no doubt though nificant milestone in power generation. When Oco- that utility requirements will continue to bring nee goes into operation in 1971 it will establish an- new challenges that the industry can look forward other equally significant milestone as the first large to with anticipation and which will continue to re .
nuclear fueled generating station to operate with a sult in new milestones of impivvement in power heat rate below 10,000 Btu /kw hr. We cannot pre- generation.
4 U
BIBLIOGR APHY n.# .
1 Keowee.Toxaway Project by W. S. Lee, American Power Conference, April 25,1967.
2 How Duke Power Trains Nuclear Plant Designers, POWER, December,1966.
3 Nuclear Training -- Duke Power Company, Southeastern Electric Exchange, Atlanta, Georgia, May 19, 1967, A. C. Thies.
4 D. K. Davies, Nuclear Steam Generators, American Power Conference, April 27, 1965.
J 4
e 1.
se ess.aua l
l l.
jp ' , e 1 r . ~ .
f '
. p f' &,l)'
_ ;uuh 1
l l
rg 6 p' 56*
- we .-
.~.c ggg&c. _ . ,,
w I
~ A,
- yj'n - if v q --
M - s o
vemg o.. ~.,,
~- msv:ng,e .- .. 1
.3 . __ ,, - e q. - ~ ;
-1 l
ww e
4M$ '
... ~-
' td '
a;v:
s
.; . c o .3e
' ; - Q_ Y... ~ -
+ l%: ,
. y. .;r.., . V .;- - ,
' yt -'
. zy
- 1e;
. . e v.' d' %...*. ~+
W. S. LEE .- =r .
.s. .
4j
- i - " c #j' -
Vice President ', - .
[- I.,N. ,[. 1 Engineering .
~,.-1;
.~ ' I #
- t n ..
Duke Power Company # -
- '. - -f? *- ,
Charlotte, North Carolina ;~
- J .-. ';,Ib'
' ~ '--
~
~
$jg-LS * .. . - [ . .
..'1 .' )'(. .
"-:..~js. :,
- /;
'l W. H. ROWAND _
? '
- }.
5 '
., , 3)~
~
Vice President ' . = ;' .. - .
.- . E .
.? , m t 1. . D Nuclear Power Generation Department -* . ..
sa g
..R' :,
Babcock & Wilcox ;
1.- .
! Barberton. Ohi - T,
.-A: -
.. '.g : ^ .. ,
s.
. - / '.... t. ~ 1,$9 v;g g y,
1
. ':ma p 3. ;;
.- - , ' s. J.
j 1
.l} . _ j .p ;. .m.f kgi- M
' .' 6 - I. p L_ j';k }.;-' '.h.. -
'I' -
$. .. 'l' :
. J '*
~
e.....
- 4. A ' .~ ; . ' . g. :
'1.-)...,,
.,. , W' . ' ?. - s:# *'
- I l ' %. '.,.
^
p... ;f
....?' ,
? a h.p, . '-.
~'......?p-l
'.'. Q ,. , ,.