ML19351E183
| ML19351E183 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/17/1967 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011260108 | |
| Download: ML19351E183 (9) | |
Text
,
3GCKET R So-27 Rc"m.
'y Formal ptra YANKEE h"J' LFAR POlm STATION OPEATION REPORT NO. 7h For the month of FEBRUARY 1967 g
o) c O
O L
i wn2a mi.2 j
LL m:nc amy
~
g GElb:.1
'TX, s 10fi$$
N/ /':
/
N/NI n
t
\\
.C f.' -
/.:5. '
- J
. o ss7 - d; Ti O
4 w.mni unt : :T't
/
{
i Submitted by YANKEE ATOMEC EIECTRIC CO (PANY Boston Passachu setts Parch 17, 1967 8011260,O,I 833
h This report covers the operation of the Yankee Atomic Electric Company plant at Ecve, Massachusetts, for the month of February 1967 1
At the beginning of the period the plant was operating at approximate 3y lho MWe and remained at that level until February 28 I
when the average main coolant temperature was lowered to S1h F.
Consequently, plant load was reduced to approximately 139 MWe. Main coc'snt average temperature was decreased in order to minimize the het load on No. 2 main coolant pump bearing; the temperature of which had increased during the past two months from the normal of 1h00F to 0
approximately 170 F.
2 One shipment of spent fuel was made February 20.
This shipment is the nineteenth in the series of spent fuel shipments, bringing the number of elements shipped in the ten element cask to 183 and the total number of elements shipped to date to 199 On February 16, control rod groups B, C, and D vere banked at 67 6/8" as the third step of the Core VI maximum withdrawal limit-ations program for distribution of guide block vear. The monthly control rod exercise was performed Fdbruary 2h.
All rods functioned normally.
On February 8 the 1967 operator Training Course was started.
The first phase of the course for Reactor Operator candidates,
encompassing basic physics, tathematics and engineering, in addition to primary systems design, was 80% complete at the end of the reporting period. The succeeding two phases for both, Reactor Operator and Senior Raactor Operator candidates, vill be started upon completion of the j
forthcoming mairtenance shutdown.
A routine visit and inspection of records was made by a member of the International Atomic Energy Agency on February 16 and 17.
O The second, Core VI, air charge to the vapor container was terminated on February 2 when the weight of dry air in the vapor container was approximately 66.h00 lbs.
The vapor container air leakage rate was normal throughout vhe reporting period.
l 3r plant shutdowns or reactor scrams occurred during the l
month of February.
Plant Maintenance The following is a list of the major plant maintenance items performed by the plant staff during the month of February,1967:
1 The head ganket, piston and rings on No. 2 control air compressor were replaced.
, h 2.
A bearing en the turbine generator hydrogen sral oil pump was replaced.
l 3.
No. 2 charging pump packing and plungers and the inner and outer crosshead oil seals were replaced.
k.
No. 2 service water pump was repacked, the shaft repaired by metal spraying and the throat bearing replaced.
5 No. 1 battery charger motcr generator set commutator was stoned, the windings cleaned and painted and the bearings replaced.
l 6.
A water erosion leak in the drain line between No.1 and No. 2 feedwater heaters was weld repaired.
7 Rubbing straps and ends of the two spare hafnium control rod absorber sections were removed to facil-j i
itate modification to unitized rods.
8.
No. 2 boiler feedpump outboard end shaft sleeve was replaced and the balancing drum, repaired during the i
Core V-VI shutdown, was inspected.
9 No. 1 feedwater heater drain pump motor was installed on the loop decontamination pump for use during the forthcoming shutdown.
Instrumentation and Control The following is a list of the major instrumentation and control maintenance items performed by the plant staff during the O
month of February, 1967:
1.
The air ejector radiation monitor detector tube was replaced and the monitor recalibrated.
l 2.
No, h feedwater flow transmitter was cleaned and calibrated.
3 Operational tests were conducted on the shutdown instrumentation.
h.
The Health Physics control point hand and foot counter trahsformer and rectifier were replaced and the counter recalibrated.
Reactor Plant Performance Core reactivity depletion was normal at approximately 0.63% A K/K per 1000 MWtD/MTU.
ja( l\\ _
Up 7"
- I l
The following pa rameters were determ' 'ed by means of incore j
1: strumentation at h50 MWt, 51h.0DF Tavg,1144 ppm boron, control od groups B, C, and D at 87 6/8 and g.oup A at 65 5/8:
p,L F
=
q F
1.9 A
=
n l
b.8
)
Minimum DN3R
=
577.2 F i
Maximum Output Temperature
=
i i
Secondary Plant Performance Feedvater heater terminal difference at 138.5 MWe, 0.9" Hg backpressure and 526.5 F Tavg:
- 5.i F
- 2 - 17.1 F
- 3 - 14.8 F i
Ccndenser terminal difference: 25.6 F Chemistry During February the prinary to secondary leak rate in No. 3 eteam generator slowly increased from lh2 gpd to approximately kok gpd by the end of the reporting period.
ihe main coolant boron concentration decreased from 1232 ppm to 1346 ppm during the period. The average system crud level was 0.08 ppm., Main coolant icdine-131 average specific activity was 8.67 x 10-o pc/ml and the I-131/I-133 atomic ratio was 0.69 The silver-110m nuclide was again detected in the analysis O
of the primary coolant crud samples. However, the concentration has centinued to shcw a decreasing trend which may be indicative of an isolated silver centamination condition on the exterior of the control rods, or a celective plating out of the silver in the main coolant system.
Further knowledge and a determination of the scope of the problem sbauld be gained during the forthcoming shutdown.
I The pressarizer vent test program for Core VI was continued throughout the reporting period.
Flow through the narrow range pressurizer capillary was established on February 16 after a sixteen day period in the non venting condition. The pressurizer vapor phase was sampled at a normal operating water level of 120 inches.
After the sampling, the level was raised to, and maintained at,145" to 150".
At this level the narrow range sample point is approximately
)
8" to 13" above the water line. After sa:Iling the gas phase at the 1
interface periodically a sample was taken through one of the top capillaries to determine if there was any marked difference between the two creas. The results of this phase of the pressurizer test program were as follows:
I h-Sample Pressuriner EO N
H' Remarks Time Level (inches) 2 2
2 2-16 67 08h0 120 Ibrrow range capillary valved in 12h5 1h5-150 Rais ~ level to lh5" - 150" 1320 1h5-150 0 5h 29.6 69.9 Sample line not in equilbrium 1h20 1h5-150 1.68 Th.9 23.h 1510 1h5-150 1.68 75 0 23.3 2-17-67 1255 1h5-150 1.83 80.4 17.8 2-20-67 1015 1h5-150 0.hh 26.1 73.5 After venting far four days 2-21-67 H'## " "'"6*
" Pill *#7 ""I'*d 0910 out and top capillary valved in 1500 120 0.29 19.9 79.8 The main coolant crud samples had the following average radio-chemical analyses:
dp:/mg crud:
Hf-181 1/n-5 h Cc-58 Co-60 t
b 6
6 6
5.05 x 10 1.16 x 10 3.06 x 10 1.95 x 10 Cr-51 Fe-59 Ag-110m 5
6.01 x 105 6.07 x 10 3.12 x 10 A main coolant gas sample collected on February 20 had the following radiochemical analyses:
uc/cc gas:
-3 Xe-133 5.75 x 10
-3 Xe-135 6.88 x 10
-1 Ar 41 2.58 x 10
Health and Safety One shipment of radioactive vaste consisting of ' 0 drums with 3
a total activity of 289 me was made during the period.
One shipment of spent fuel was made during the period, consisting of eight assemblies with a total activity of 12.5h mega-curies. Gamma radiation levels on contact with the cash were gen-erally less than 1.5 mr/hr with a maximum of 10 mr/hr at the valve box.
Heutron radiation levels au one meter were approximately 0.h trad/hr fastwithnodetectablesicwneutrogdoserate.
Beta-gamma contamination 2
levels showed a maximum of 1 x 10 curies per 100 cm.
No alpha contam-ination was detectable.
During February the vaste disposal liquid releases totaled 265,800 gallons containing 19.46 me of gross beta-gamma activity and 65 10 curies of tritium, caseous vaste releases during the same period totaled lhB.h millicuries of gross beta-gamma activity.
In addition tc the above liquid releases a total of 21k,000 gallons of water were discharged from the secondary plant. The total O
gross beta-gamma nd tritium activities releaced from the secondary plant were 51.60 pc and 14.75 euries respectively.
Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of February, 1967 were:
1 Avera accumulated exposure dose hO mrem.
Eximum accumulated exposure dose
[ O b mrem.
Operations Attaohed is a cummary of plant operating statistics and a plot of daily average load for the month of February, 1967.
O I
I
l l
O O
O i
l YANKEE ATOMIC ELECTRIC COMPANY -- OPERATING SIWMARY February 1967 ELECTRICAL MONTII YEAR TO DATE Gross Generation KWII 93,908,h00 197,.AS,000 6,5 "'3 o^c,500 Sta. Service (While Gen. Incl. ' ocses )
KWil 5,546,794 11,688,629 4 41,.1, h 51 Net Output 10 0I 88,361,606 185,F36,371 6,118,094,049 Station SerTice f.
5.91 5.92 6.73 Sta. Service (While Not Gen. Incl. Loss ;s) IGli 0
0 23,795,467 Ave. Gen. For Month (672 Ilours)
KW 139,7hh Ave. Gen. Runnind (672 Ilours)
KW 139,744 PLANT PERFORMANCE l
I Net Plant Efficiency 29.28 29.21 28.h8 Nee Plant Heat Rate BIU/KWII 11,656 11,683 11,983 P:.snt Operating Factor Th.8h Th.81 71.h8 Beactor Plant Availability 100.00 100. c's 82.69 NUCLEAR MONTil CORE VI TOTAL Hours Critical IIRS 672.00 2,757.29 h6,h82.97 Times Scrammed O
2 Sh Burnup Core Average
!GD/MTU 605 20 2,755.41 Region Average
!GD/MTU A(INNER) 615.146 2786.936 19,559.44 B(MIDDLE) 718.79h 3301.332 10,976.62 C(OUTER) 490 ?m 2205.h23 2,205.h2 i
i i
i I
=
_7_
OM W
W
~
O Z
O W
4EO U
p O
E S
S 0
N C
M C
D ra x
p LA p
O H
O ci r4 4
E
% 3 q
O N
E4 t :i t
x EC C
W M
~
Z OH O
m 6
M l
f tn m
6 m
O O
O O
O O
in O
in CJ eA ed (PR SSOID)
GV0'I 20Vd3AV 1.'IIVG l
_8 g
CORE VIREIGN IDCATIONS REIGN C REIGN B REION A O
--