ML19351E026
| ML19351E026 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/25/1965 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011250462 | |
| Download: ML19351E026 (10) | |
Text
_ _. _ _ - _ _
l bd E
80"d7
"*1'k? "'"6 YANKEE NUCLEAR F0WIR STATION OPERATION REPORT NO. 53 For the month of MAY 1965 0
0 0
Submitted by YANKEE ATOMIC EIETRIC COMPANY Boston Massachusetts June 25,1%5 m
g D
e[$'.N 3
DOCHETED um L;
" N2 S igs53 C
\\{.:)'
n:vurny
'S V
Q"nucnu
'$Ltux e
-4 e
~8 0 212 3 0 0 : q
- a~
N This report covers the operation of the Yankee A.tomic Electric Company plant at Rowe, Massachusetts for the month of May 1965 At the beginning of the reporting period the plant was operating at a power level of 163 FWe.
Plant load continued to drop off at a fairly uniform rate of ~ 2/3 FWe per day as burnup progressed with slight variations due to circulating water inlet temperature fluctuations being recorded.
The Operation Report for May discussed a decrease in secondary plant performance due in part to an increasing circulating water inlet temperature but more so to the silty conditions of tne water resulting in fouling of the condenser heat transfer surfaces. As condenser heat transfer worsened during the month necessarily resulting in a higher back pressure a load cutback to permit tube cleaning was scheduled.
fn Between 0700 and 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on May 16 load was reduced to V
35-50 FWe to permit alternate cleaning of each half of the condenser.
A significant improvement in condenser back pressure was obtained resulting in an increase of some h.7 We gross in plant capability.
For the balan:e of the reporting period " stretch-out" operations continued with gradual reductions in main coolant average temperature and power level accompanied by corresponding reductions in plant turbine e
capability and generator output.
At the end of the reporting period, plant capability had decreased to approximately lh0 FWe thus holding to the predicted drop off rate of ~ 2/3 FWe per day.
On May 20 all control rods were withdrawn one step to the 90 3/8 inch position resulting in a net increase of 0.2 F in T average.
0 Repair work on the Ion Erchange Pit continued during the month with all work completed by May 25. The repair consisted of chipping and j
repacking of fhulty concrete and the placement of a tar and felt liner on the ficor and approximately two feet up each of the four walls.
A new four inch thick concrete floor was poured to protect the water-proofing fabric from damage by ion exchange capsule support legs. Wall support for the fabric was afforded utilizing concrete block.
On May 19 the 10 element spent fuel shipping cask was received at the sita.
Refurbishing and fitting out of the cask is now in progress in anticipation of spent fuel shipments which are now scheduled for mid-June.
No plant shutdowns or reactor scrams occurred during May.
Plant Maintenance Following is a sumnary of major activities carried out by the plant maintenance staff during May:
l.
The spare set of rsactor vessel studs have been stripped of silver end sent off site for Parkerizing.
r
. /
i w/
2.
Installed a temporary filter in the waste liquid transfer room in the Waste Disposal Building.
3 Installed conduit from the switchgear room to the decontamination pad for a power supply to the fuel shipping cask.
h.
Repaired a weld in the chemical injection line to the charging pumps.
5.
Initiated f abrication of new neutron detector containers.
6.
Tested the control rod drive shaf t handling fixture.
Stops, gage and hand wheel operations were checked satis-factorily.
N_)
7.
Cleaned condenser tubing during the scheduled load cutback on May lo.
8.
Repaired a leak on the coagulator agitator gear box.
9 Installed a new diaphram on a monitored waste tank valve.
S 10.
The yard area crane was inspected and lubricated.
11.
Completed changes in seal water piping and connections in the evaporator cubicle. The change permits establishing seal water flow to the reboiler pump and liquid transfer pump without entering the cubicle.
12.
Repaired the motor contactor on No.1 vapor container cooling fan.
(
)
~
13 Removed the spent fuel pit manipulator boom for repair of a failed gear and inspection of the telescoping sectior..
Ih. The separan tank and piping in the water treatment plant was cleaned.
- 15. The purifiestion system was made ready for service with the installation of an ion exchrnger and filter into their respective operating
_ sitions.dn the Ion Exchange Pit.
- 16. Installed new hoses on the ash drum in the waste disposal plant.
1 Chemistry 7'~x Throughout the reporting period the main coolant oxygen levels 6,
were below the point of detection.
s N,/
e
( - }
V The average ammon19 concentration was held to 10.0 + 1.5 ppm with no main coolant purification.
Typical main coolant crud increases, with no purification, cxperienced following weekly control rod exercising were 0.57 to h.h ppm, 0.h6 to 2.h3 ppm and 0 33 to 2.31 ppm.
The main coolant flashed gas was analyzed and found to contain 72% H2 and 28% N
- 2 The average main coolant gross gamma activity was measured at 1.0 x 10-1 pc/ml.
During the month a micro-organism problem was discovered in the waste liquid storage system. Varying quantities of soluble iron, hydrogen sulfide and colloidal material were detected in several tanks oU with unidentified bacteria having been observed in samples at 2001. In the past, traces of hydrogen sulfide odor were detected but no other signs of bacteria were evident. A gross examination of the system indicated that the worse condit? ons exist in the gravity drain tank, with lesser concentrations in the waste holdup and activity dilution decay tanks, no bacteria having been found in the primary drain collecting tank.
Later in the month local heating was applied to the activity e
dilution decay tank, gravity drain tank and waste holdup tank.
Throughout the month the main coolant purification loop remained secured due to the maintenance work in progress in the Ion Exchange Pit.
A typical main coolant crud analysis performed on $/17/65 indicated
(')
dpm/mg - crud v
cr - $1 5 2 x 106 Mn - $h 5.h x 1060 Fe - 59 3.9 x 10 co - 58 h.7 x 107 co - 60 9 5 x 106 Hf - 181 5.9 x 105 In - 116 m none detected (sample $/$/65)
A typical main coolant gas analysis performed on $/27/65 indicated:
Xe - 133 h.3 x 10-3 mc/cc of gas 3.2 x 10-3 le - 135
?.h x 10-3 mc/cc of gas mc A - hl
/cc of gas n
s l/
4
-h-3 k
j Reactor Plant Performance The results of a four wire flux wire irradiation were:
@ $10 Wt 50h F T avg.
all rods @ 90 0/8" 2.8 F
=
q F
H q DNBR 3.7
=
0
$62 F Max. outlet temp.
=
Turbine Plant Performance By May 13 the condenser back pressure had increased to 3 3" Hg.,
being approximately 1.0" Hg. higher than expected for the existing
(~,
operating conditions. The cause was traced to poor heat transfer across k/
the condenser due to tube fouling. Following condenser tube cleaning on May 16, a review of operational data, corrected to constant conditions, showed an improvement in condenser back pressure of 0.8" Hg. This improvement resulted in an increased output of approximately h.7 We gross.
Later in the month a further reduction in back pressure was achieved by the introduction of cooler water to the circulating water 8
system.
Limited operation of upstream and downstream hydroelectric stations, whose output has been sharply curtailed due to the drought conditions in the Northeast, resulted in a lh reduction in inlet temperature, a 1" Hg. improvement in back pressure and an increase in gross electric output of 6.8 We.
Instrumentation and Control g
Following is a summary of major activities carried out by q,i the plant Instrumentation and Control group during May:
1.
Recalibrated the four TCNR temperature channels to conform with existing plant temperature ranges during " stretch-out."
2.
Modified the new refueling preamps to overcome the short term calibration drif ts.
3.
Replaced a leaking fitting on the charging flow detector.
h.
Tested new equipment to be used for main coolant level indication during refueling.
5.
Repaired the primary vent stack radiation monitor.
6.
Recalibrated the ion exchange flow system.
l i
7.
Checked operation of the control rod lif t coils by
,/
recording the applied voltage to each on the visicorder.
.o
. _s
\\
i
[
l
' /
8.
Reinstalled the river temperature recorder downstream of the plant.
9 Measured the resistance and inductance of all the spare control rod indicator coils.
- 10. Repaired No. 2 and No. 3 main coolant pump bearing temper-ature indicators.
11.
Repaired the narrow range pressurizer level recorder.
- 12. Recalibrated the gland stea> pressure transmitters and indic ators.
Health and Safety
/^()}
During the month of May 1965 the following solid radioactive wastes were prepared and shipped off site for disposal:
1.
50 drums containing a total activity of 501.7 me.
2.
h poly-wrapped packages cantaining rails and sample plug from the ion exchange pit. The total activity was 8
0.h me.
Liquid wastes containing a gross beta-gamma activity of 0.03 me of gamma emitting isotopes and 39 9h curies of tritium were discharged during May. Oaseous waste containing a total activity of 3 37 me were discharged during the same period.
Two of the previously pumped out resin capsules were internally decontaminated using ammoniated citric acid. Generally, the radiation (7
levels were reduced by a factor of approximately ten. Typical readings before and after were CAPSULE 18 CAPSULE 20 Location on Capsule Before After Before After Top 300 50 100 30 Top horizontal weld 150 17 70 30 Supporting " ears" 350 20 210 30 Screen level 850 300 800 90 Bottom 1500 300 1000 200 (Readings are in mr/hr @ la from surface).
A shield wall of concrete bricks, $' 6" high, 8' 8" long and 8" thick, has been erected immediately in front of the evaporator in an
'T attempt to reduce the radiation levels in this general area of the cubicle.
\\
)
a
. c. '-
/
(
/
'~'
Leak tests were performed on three gamma and one neutron sealed calibration sources. The " dummy" fuel assembly in the inf ormation center was also leak tested.
No evidence of leaks was discovered.
Personnel expost
.or Yankee plant personnel as measured by film badge for the month of May 1965 were:
Average for all station personnel = 130 mr Maximum individual exposure
= $30 mr Plant Operations Att, ached is a summary of plant operation statistics for the month of May 1965 and a plot of daily average plant load for the same period.
L' The following minor differences were detected during this period and this months numbers have been corrected to reflect the same April 196h Reported as, Corrected to e
Gross generation llh,125,900 11h,125,900 Station service 7,215,700 7,215,697 Net generation 106,910,200 106,910,203 August 196h Reported as Corrected to Gross generation 2,622,700 2,622,700 n()
Station service 275,670 275,671 Net generation 2,3h7,030 2,3h7,029
,y s
i
)
x,,/
/
(
.j YANKEE ATOMIC ELECTRIC COMPANY -- OPERATING
SUMMARY
4 MAY 1966 ELECTRICAL MONTH YFAR TO DATi, Gross Generation WH 108,212,100 62h,706,600 4,$87,822,800 Sta. Service (While Gen. Incl. Losses)
WH 7,39h,377 38,h50,880 318,112,989**
Net Generation NH 100,817,723
$86,255,720 h,269,709,811**
Station Service 6.83 6.16
- 6. 93 Sta. Service (While Not Gen. Incl. Iosses)
WH 0
15$,936 19,9$h,387 Ave. Gen. For Month (7hh HRS.)
W lh$,hh6 Ave. Gen.
Running (7hh HRS.)
W 1h$,hh6 PIANT PERFORMANCE Net Plant Efficiency 26.82 28.50 Net Plant Heat Rate Btu /WH 12,725 11,9h9 Lbs. Steam / Net WH 1h.82 lb 02 Circulating Water Inlet Temp.
,a Maximun F
08
)
Minimum F
hl Pl nt Operating Factor 8h.19 9h.hh 71.77 Reactor Plant Availability 100 99.o3 83.30 NUCLEAR ENTH CORE IV TO DATE Times Critical 0
20 Jh6 Hours Critical HRS 7hh thj8.02 3h,239.31 Times Scrammed 0
hg F4uivalent Reactor Hours @ 600 Wt HRS 626.h0 0081.70 2h,970.h0 Average Burnup of Core WDhntU Control Rod Position at Month Ehd Fquilibrium at h78 nit a h95.0 F T avg.
REGION
- MONTH TO TA L BU4W r>
Group A Rods out-inches 90 3/8 Group B 90 3/8 INNER 816.28 lo,62h.03 Group C 90 3/8 MIDDLE 906.67 13,87h $h Group D 90 3/8 OUrtR
$97.2h 5,027.79 E-6 709.31 28,826.11
%mn < 1 r pn Tre::c figures 1. ave tu.r. ecrrec ted to aiow the ninor change as reported on page e of this report,.
n
)
,='
0 4
3 i
5 i 2 O
Y N
A 0
P i 2 M
OC i
D C
A OL I
O i
S R
L Y
T A
i C
E D
E G
A r
E R
o 1 e
E f
C V
Y 5
I A
A 1
M M
O Y
i T
L A
I A
E D
i G
iN i
O AY 0
1 i
i e
, 5 i
i i
(-
e 0
0 0
0 5
0 5
1 1
E::2S QSBaW U2o l
9-CORE IV REION LOCATIONS OUTER REDION I
MIDDLE O
ano1ou
'Y y
INN R 8
RED::0N E-6 O
i E-6 Assembly No. A-8 i
l L ----
,