ML19351E126
| ML19351E126 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/31/1963 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011250639 | |
| Download: ML19351E126 (14) | |
Text
g.
.e f4~.hf
~ "
O.
(.,gr a 110 2 W kilu Copz &
YANKEE NUCLEAR POWER STATICN OPERATION PLPORT NO. 35 For tl.a month of NOVEMB1!R 1Q63 O
r O
S r ~
O
^>g G I-!
., tt.-i s,,..
Q(,V*'
~
a) p f/
q 1
g n;
W' / b ~',' \\';'
/
G_1r67' SubmLtted by YANKEE ATOMIC ELECTRIC COMPANY Boston Massachusetts December 31, 1963 r
l 0 677 8oueso
l l
This report covers the operation of the Yankee Atomic Electric O
Company plant at Rowe, Massachuset for the month of November 1%3.
t J
At the beginning of the 1 rting period the plant was in the cold, borated condition as repairs )
soth the control rod absorbers and On November 3, reassembly of drive shaft latch finger pins contint primary system components began and wt completed on November 7 On November 8, the CoreIII physics test program was reinstituted with emphasis on check out of the control rod drive mechanisms. On November 9, the main coolant system was brought to temperature and pressure and was followed by five days of hot physics testing during which measure-ments' were made of control rod worth, boron worth and temperature coefficient.
On November 13, the turbine was brought up to speed and manually
' O trippel. Shortly after the turbine had been tripped, a reactor scram was experienced. The scram was traced to a failed resistor in the scram sequence memory light control circuitry on the FN panel in the main control room. A more detailed description of the scram can be found in the Instrumentation and Control section of this report.
h Following repairs to the memory light circuit the reactor was brought to criticality, the generator phased, and plant load was raised to 120 We. On November lh, a successful overspeed trip test on the turbine was made following which it was allowed to roll to a stop with the throttle valves closed. During coastdown a severe vibration and rubbing noise was O
experie=ced ccame=c1=8 at a turb1 reed er raro=1 ate 17 13oo rr, the most pronounced vibration occurring at the No. h, or generator end, bearing.
The vibration continued throughout the remimier of the coastdown although the amplitude decreased as the turbine speed decreased. Once the machine had stopped it was placed on turning gear. After an hour on turning gear, during which no rubbing was heard, shaft eccentricity at No. h and 5 Os bearings was nearly zero. The low pressure turbine end blading was inspected and no damage was found.
Following discussions with the manufacturer, the turbine was again brought to operating speed. Vibration readings taken during the period were found to be normal.
On November lh, following rephasing of the generatcr, a self sustaining load test was performed. The plant generation was reduced to station service load and the breakers opened thereby isolating the plant from all outside ties. The plant responded perfectly to control as intentional load swings were made by operating large pumps. All such swings were accepted smoothly without need for operator control.
Following the overspeed trip test on November 3h, a reactor scram occurred. The cause of the scram was traced to a pressure surge on a pressure switch on the first stage shell drain of the turbine. The pressure switch is tied to the rod scram breakers through an agastat relay and is left open at power levels below 15 We due to increased flow through the shell drain. Fcr the overspeed test, steam is admitted to the turbine C]
through the poppet valves in the turbine throttle valves in order to limit the steam flow to the turbine. The quantity of steam admLtted appa p aly i
was sufficient to increase first stage pressure to the point where t%
pressure switch was actuated, causing a reactor scram.
l
. O v1 ant 1ead was raised to 150 - en Nevemher 15 and then te 168 Ne on November 16.
Rectrical output remained essentially constant at 168 We until November 20 when the plant, was shut down to trace and repair a main coolant leak.
- 'ollowing startup on November 15, airborne activity within the
-vapor container began to increase and on November 20 electrica1 grounds were noted on the operating coil stacks of control rods 17 and 18, thereby prompting a plant shutdown. The leak was traced to a small pinhole failure in the seal weld of the plug over shim position number 26 on the reactor vessel head. Repairs to the seal weld necestr' tated depressurization and cool down of the primary system.
The low pressure turbine again had excessive vibration during the coastdown after the turbine trip. As before, the vibration started at
.O 1300 rpm and continued during the coastdown.
While this problem is stil1 being reviewed by the turbine manufacturer, it appears that steam dumped from the high pressure turbine, gland steam regulator to a low pressure turbine extraction point resulted in a differential expansion condition. This, in turn, appears. to have l
caused rubbing at the turbine seal on the generator end of the low pressure turbine.
Following repairs to the sea 1 weld, the main coo 1 ant system was brought to temperature and pressure. The turbine was taken off turning p) gear, brought to 1800 rpm and allowed to coast down to 1000 rpm with no
(.
abnormal conditions noted. Ionowing this check out turbine speed was restored to 1800 rpm for phasing.
The generator was phased to the line on November 23 and plant p
load was raised to 100 We. The p1 ant was operated at 100 We for approximately two hours following which the generator was unloaded and the V
turbine speed a11 owed ta decrease to zero. No unusua1 conditions were noted as the turbine proceeded through-the 1300 rpm range. Thereafter the turbine was again brouglt to operating speed and the generstor was phased j
to the line, plant load being raised to 167 We where it remained throughout j
the ba1ance of the reporting period.
During the month three spent fr.a1 assemblies were ledc tested to ascertain the possible presence of clad failures. Two assemblies were spent Core i fuel that had been recycled in Core II to obtain extended burnup. The remaining assembly saw service in Core II and was scheduled for reuse in Core III. However, during refueling operations the assembly was. damaged and its use in Core III was deferred. Each of the three assemblies tested negative as no trace of fission products could ~ be found.
Plant Shutdowns Shutdown No. 62-2-lh 9/2/63 - 11/13/63 A continuation of the 1
Core II-Core III refueling
)
shutdown.
Shutdown No. 63-3-1 11/1h/63 A 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> shutdown to perform an automatic over-speed trip test of the turbine.
- m.
t-
. t p
\\ -
Shutdown No. 6h-3-2 11/20 - 11/23/63 A 70.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shutdown to repair a primary system leak. in a. seal weld of a shim position plug,on the reactor vessel head.
Shutdown No. 65-3-3 11/23/63 A.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> shutdown to observe vibration effects on the turbine during coast-down from operating speed.
Reactor Scrams Scram No. 39-3-1 13/12/63 An automatic reactor scram from Q
a power level of <JNt. The reactor scramed after receiving a low flow signal when two main coolant pumps were tripped out during noise analyses studies
]
with the permissive switch in the bypass position.
Scram No. h0-3-2 11/13/63 A spurious. reactor scram from a power level of f1Wt O
a=e to rai'.* r i tor in the nuclear instrumentation.
I Scram No. hl-3-3 11/1h/63 A spurious reactor scram from a power level of <1Wt due to a pressure surga in the first stage shell drain of the turbine.
Maintenance Following is a summary of major activities carried out by plant maintenance personnel during November:
1.
An increased chamfor was added to both ends of all sections of the rubbing straps on the 22 hafnium control rods.
2 The latch finger pins on all control rod drive shafts were rewelded.-
3.
Due to repeated operational diffi:,ulties with the packing gland on the pressurizer solenoid relief valve, the cap was seal welded.
- h. Repacked the pressurizer motor operated spray valve.
~ 5. _ Repacked No. 2 loop cold leg stop valve.
6.
A new steam calorimeter was installed on the right hand moisture spearator outlet piping.
i
.,_I
-h-r) 7.
The control rod drive cubicle was de-noised.
(
8.
The generator voltage regulator was inspected.
9.
No. 1 charging pump packing boxes were removed and new mechanical seal boxes installed.
- 10. The turbine gland steam regulator was adjusted.
- 11. Repiping of the air compressor cooling water lines was completed.
- 12. No. 2 auxiliary boiler was cleaned and made ready for inspection.
,m()
13.
No. 3 turbine gland seal was disassembled for inspection.
Ih.
No. h turbine gland seal was disassembled for inspection.
- 15. A leaking shim plug on the reactor vessel head was repaired.
16.
No. h turbine bearing was inspected.
Chemistry n
On November 10, a small quantity of resin fines.was. observed in V
the bottom of a sample bottle drawn from the main coolant bleed. To investigate further, flow was established from the bleed sample line through a 60 mesh screen. In a six hour period about 30 resin fines were collected. Also crud sa=nles collected during the past year were reviewed under a microscope.
a resin fines were found in one crud sample of (Vi shield tank cavity wa...r !.? ken during the Core II - III refueling. All other samples taken prior to that La were negative.
On November 15, resin was found in a sample of the low pressure surge tank. The tank was ::d.xed and flushed and purification flow directed so that all water drawn from the tank would pass through a filter before being charged to the main coolant system. On November 18, while adding makeup to the surge tank, resin was again found in the system. During the plant cooldown on November 20, four additional flushes of the tank were made. No evidence of resin was found on a continuous sample that was taken on the third and fourth flushes.
Since that time an intensiva d,vestigation has been under way to determine the leakage point by which n u can escape from the ion exchangers. It has been theorized that backwashing of the ion exchanger then in service took place at some time during the refueling shutdown through inadvertent opening of a valve in the ion exchanger inlet. The backwashing may have occurred from either the safety injection tank or shield tank cavity due to the head availahlein both tanks. A further study is now underway to review the purification system piping. It is expected
(,~')
tLit modifications will be made to improve the system and eliminate the possibility of resin release to the main coolant.
, O Ear 17 in the reportine veriod toe averase mas = coo 1 ant specific activity ranged between 2.1 and 7.7 x 10-4 pc/ml. After startup the specific activity increased to 1.h x 10-1 Sc/ml. Approximately 10% of the total non-gaseous specific activity is due to crud. The renmining 90%
is soluble and passes through 0.h5 micron millipore filter paper.
Throughout the reporting period the main coolant crud levels rar;ed between 0.90 and 0.58 ppm.
Main coolant oxygen levels varied 9 ween 0.09 ppm and undetectable.
A typical main coolant gas analysis made during the period indicated:
A - h1 1.66 pc/cc gas Ie - 135 6.6 x 10-1 pc/cc gas pd Ie - l' 3 5.6 x 10-1 pc/cc gas During the month three spent fuel assemblies were tested for cladding failure using a gas analysis technique.
Each assembly was individually inserted into a fuel shipment cask. A vacuum purg was then attached to the cask vent and the evacuated air sampled for Kr-85 analysis.
At the conclusion of testing no activity from the nuclide was detected in any of the samples collected. Water samples from within the cask were also tested and no fission products were detected.
Reactor Plant Performance The Core III physics test program began on November 7 The following is a summary of the program and the results obtained thus far.
As additional data is analyzed the results will be published in subsequent Operation Reports.
O
- 1. Operating coil traces were obtained on control rods Nos.18 and 20 at a main coolant temperature of 250eF. Withdrawal traces were normal while insertion traces showed slight abnormalities during the last five steps of insertion.
During insertion, the six inch position indicating light remained lit as the rod was driven to the zero position, as measured by the odometer. Similar testing was performed on rod groups 6, 5 and 2 at a main coolant temperature of $20eF.
These groups were selected since they are the controlling groups during normal operation. In the hot condition all control rod movements appearad normal.
- 2. All. 2h control rods were drop tested from the 90 6/8 inch position at n. main coolant temperature of 250eF. All drop times were noimal. All 2h control rods were drop tested from the 90 6/8 inch position at a main coolant tenperature of $20T. Drop times were normal.
- 3. Temperature coefficient and banked control rod worth data.
O were estained d==1 8 heatug of the maim coo 1aat sFatem from 200 FJ to $25 F.
~
.. h
- h. During ' dilution of the main coolant system from all rods out -
boron, 51h0, (1250 ppm)- the reactivity changes were F
followed by obt24ning rod oscillation data during 'just -
critical. traces as the contro1 rods were -inserted ~ to_
compensate for~the. effects of boron dilution. The rod I,
oscillations consisted of. cycling.the controlling rod groups
~ "in one step - out one step", that is, plus or minus
~
{
3/8 inches from the just. critical position.
5.
During the physics. test program, a representative of the.
primary system manufacturer recorded noise data from plant-instrumentation. From the data obtained it is hoped that conditions such as thermal and nuclear stability and' reactivity shutdowns can'be. evaluated.
.O 6.
Dor =,enerator uad=, data w-obtained using step changes in rod position to evaluate control rod worth, power coefficient and moderator temperature coefficient.
This was possible through use of an on-line anslag computer to solve the kinetics equations for core reactivity.
As discussed in the Operation Report for September 1%3, trans-verse wear had occurred on some Core II control rods due to contact with the upper guide block while at the fully withdraun position of-90 0/8 inches. To limit wear at any one point on the rods, a modified rod O-
' withdrawal program is in effect for Core III operation. Initially, an upper withdrawal limLt of 75 0/8 inches has been set, following which the rod groups will be moved individually one step at a time until the full out position is. reached. In this manner it is expected that the time spent by the rods at any one position will be greatly reduced, thereby ndnimLzing i
the amount of wear at a particular point on the vane surfaces.
O Due to the excess reactivity available in Core III initial operations will be with boron in the main coolant. At the end of the reporting period, the main coolant boron concentration was 312 ppa. This will be reduced to essentially zero as burnup of the core takes place.
Turbine Plant' Performance During two separate turbine coastdowns from operating speed, excessive vibration was measured at Nos. 3 and h bearings of the low pressure section. In both cases the vibration was first noticed at approximately 1300 rpm this being the critical range of the machine.
Following the plant shutdown on November 20,Nas. 3 and h gland seals were dismantled along with No. h bearing. Both No. 3 gland and-No. h bearing were found in satisfactory condition. However, No. h~ gland at the generator end-of the low pressure turbine was found damaged.
Alternate long sealing strips were found bent back toward the generator.
All deformed strips and bands showed evidence of severe wear. To effect-
- repairs new sealing strips were installed and their clearance was checked
.h.
and adjusted. It is felt that the seal %g strips were damaged as a result
- of differential expansion that accompanied the _ vibration during coastdown.
c
I V
p.
!(.'
- 7~-
l
[
l O
. No excessive vibration was recorded durses the startu.on November 23. An intentional turbine overspeed trip +est-Y ~ '
was performed-following startup and was. witnessed by representatives of I
the turbine manufacturer.-
l-Modifications were made to the end be11' covers on the service water pump motors to limit the amount of' recirculated cooling air to the
(
-motor. Similar modifications vere made to the condensate pumps earlier in the year.
l Following startup, a detailed performance test was -made on '.he' secondary plant. moisture removal system.
l The rsaults of a typical feedwater heater terminal difference measurement made during the period indicated:
@ 167 We 17" Hg. back pressure h65 psig throttle 515 F T avg.
i 0
No. 1 6.7 F No. 2 13.80F No. 3 8.50F During the refueling shutdown substantic.1 modifications were mada to the air removal system on the ' circulating water _ discharge lines.
A Included were additional air bleed taps along the discharge line and relo-W cation of the air-water receiver drain piping. The piping origi=117 terminated at the bottom of the discharge water boxes on the condenser -
2 has been relocated such that the receiver drains are now carried airectly into the circulating water discharge piping.
O' On November 20, test was performed to determine the ability.
of the modified air removal system to regain siphon once it has been lost in the circulating water discharge line. Air was bled into the circulating water discharge until the vacuum had dropped to' 8" Hg. on the east water-
~
box and 9" Hg. on the west waterbox. This condition was maintained for 27 minutes to saturate the system before attempting to recover the vacuum.
The permanent air removal system, now :aodified as explained previously,'
was used to restore the vacuum, this being accomplished in approximately 30 minates. The temporary air removal system, as described in previous Operation Reports, was not required. It has, therefore, been concluded that the most recent modifications to the system are successful, however final judgment can not be made until actt4 loss of vacuum due to warm water conditions occurs.
With these most recent modifications, one change in the operational.
aspects of the _ air removal system was noted.
Previously, ~ the air removal pumps operated via a level signal flom the receiver. With.the system as it stands now, very little water is drawn into the receiver'and consequently it had been necessary.to place the pumps on manual control.
1netrumentatien and centre 1
-O-During the month, the following maintenance items were carried out by the plant Instrumentation and Control group:
l
-~.-
.8
- h
' 1.
Recalibrated the narrow range' and wide range pressurizer-.
V level channals._
2.
Recalibrated the in-core thermocouple recorder..
4
- 3. _ checked and calibrated secondary plant' tenperature and.
j_
pressure instrumentation for startup calorimetric tests.
i F
k.
Calibrated _the power range gain controls'against a test.
i.
signal.;
j 1
5.
Placed the in-core instrumentation in service.
i 6.
Performed preventive maintenance on all primary plant recorders.=
7 lQ 7.
Repaired the hydrogen pressure regulat,or in the gas room.
8.
Replaced the filter on the incinerator stack dettctor.
9.
Repaired No. 3 boiler feed pump pressure transmitter.
i
- 10. - Inspected the condenser hotwell and vacuum primary tank i
controls.
i r
i
- n. Repaired the Health Physics smear counter.
f{
12 Repaired a broken detector linkage on the charging pump -
discharge pressure transmitter.
'~
4 i
- 13. Repaired the conduit and cable 'to the heater drain tank discharge thermocouple well._
O on m ember 13, with the reacter criticat in the intermediate range, the turbine was brought up to speed and manually tripped.
minutes after the turoine trip, the reactor scrammi.
Approximately four i
l The scram was caused by a loss of voltage to the load winMngs of the scram amplifiers. The voltage which supplies the alarm and scram
~
panel and scram amplifiers is' taken from the vital bus in FN cabinet A and fed into the alarm and scram panel. In this panel it is fused with a 2 amp fuse... After the fuses the feed splits,.with one.120 volt feed going to the scram-amplifiers and the other feed going to.theCtransformer-in?.the alarm l
and scram panel which provides the 70 volt DC power supply for the nuclear l
alarms, low power scram set relays, permLssive relagra, :eemory lights and 4
scram sequence circuit.
i When the turbine td.pped, the can switch on the left throttle valve closed, lighting the turbine trip memory light on a circuit from the i
70 volt DC power supply.' The resistor in the memory light control circuit was sized to permLt enough current for the firing of the memory light
- bistable, but was not-adequately sized for the wattage requirements. After
=
four minutasof current flow through the resistor, the resistor overheated
~ and failed in a short circuitry direction, causing the fuse on the power
~
supply primary side to blow.' Since this fuse also supplies the voltage i
which holds the' scram amplifiers in a fired condition,-_ the scram relays could no longer be held energized,-_and-the reactor seraissed.
i u_,____
u.
.c c
. (]
To prevent a recurrence of this incident, the turbine trip sequenco circuit will be removed from the 70 volt DC power supp17 and be rewired on a station battery circuit.
During the startup, a representative of the primary plant manufacturer was at the site with equipment t,o perform noise analysis on primary plant components. The work involved evaluation of cause and effect relatitmhips dealing with flow, temperatu e and pressure response of the main coolant system. The program now under way is a joint effort of Yankee and the primary system manufacturer. The results will be used to evaluate the ease with which the methods can be adapted to large power reactors.
Health and Safety During the month of November, 126 drums of so11d radioactive waste, containing approximately 192 me, were prepared.
136 drums containing a total activity of approximately 289 me were shipped from the site.
In addition, 8 Core I control rod dashpots were shipped off atte. The total activity equaled 5.5' curies.
Liquid waste containing a total activity of 0.35 me was discharged from the plant during November. No gaseous waste was discharged.during the period. At all times the concentration of waste products discharged from the site was well below the mav4== permissible.
O During the month radiation 1 eve 1s of the gee etripper in the waste disposal building have shown a slight increase. Ievels are h0 mr/hr at the entrance to the cubicle, 200 mr/hr contact at the tower base, h50 mr/hr contact apprnrimately nine feet above the tower base, and 500 - 600 mr/hr contact approximately six feet below the upper grating.
C>3 The cubicle has been posted a "High Radiation Area, Work Permit Required".
After draining the shiehl tank cavity, the area was decontaminated using comercial solvents reducing general contamination levels from
~ 10D dpm/ft2 to ~ 10h dpm/ft on the walls. General floor p d moat levels were reduced to 2 to 5 x 105 dpm/ft2 with a==v4== of IT dpm/ft2 in the northeast corner where the stacking plate was located. Smears of the cavity walls befere C1r aning showed the contaminant to be crud conisisting of Co-58'and Cc40.
During reassemb17 of the reactor vessel head, radiatun levels in the cavity prior to install 4ng masonite blocks and thermal shie1 ding were 35 to 75 mr/hr general area, 30 - 50 mr/hr at the neutron shield tank annulus, 28 - 35 mr/hr at the stud annnina, 35 - h5 mr/hr on the curved portion of the head and 15 mr/hr within portable personnel shielding equipment. Moat levels were 30 35 mr/hr at flange level, 70 - 80 mr/hr contact at the inner expansion ring and 90 - 100 mr/hr at the outer expansion ring.
On Novenher 1, while removing a control rod drive train from the -
O core to permit re;tirs to the absorber section rubbing straps, the top of the activated follower broke the surface of the cavity water resulting in'a radiation level at the edge of the cavity of ~ 70 R/hr and N30 R/hr at three feet from the cavity edge.
c. -
~]
'All personnel except a supervisor and the crane operator cleared
[
inundiately from the edge of the cavity. Return of the follower to an underwater position was hindered by the location of the adjacent guide -
tubes and it was necessary that the supervisor direct the crane operator to move the drive tr&in over the vescal flange in order to avoid-these obstructions.
Film badges of personnel involved-were' developed immediately following the incident.- Resulting information showed that although the doses received by some personnel. wore relatively high 060 nr mari==), no overexposures were recorded.
- During the month the. incinerator stack monitor showed a reading of 800 cpm due to contamination on the effluent side of the contaminant saturated cuno filtering. system. Replacement of the filter reduced the O
reading to 100 cpm.
Radiation levels measured in the low pressure surge tank cubicle after flushing the tank were; L,+rance - 200 mr/hr; general area -
-200 - 600 mr/hr; contact tank - 30 R/hr at bottom center and 1.16 R/hr at the bottom extremities.:
}
Radiation 1cvels measured at the steam generator blowdown tank were 30 mr/hr contact and 5 mr/hr at two feet. The tank and immediate i
vicinity were mated " Radiation Area'.
.O iirder=e activitz i= the vaner cc taaer varied deswee-5 x 10-9pc/cc and 2 x 10-0 pc/cc due to ths main coolant leak on the airborne activity to 5 x 10 gak and purging the vapor container air reduced reactor head. Saaling the l
/
.. Respirators were required to be
>>c cc i
worn by all personnel-entering the vapor container during the period of leakage.
' Radiation levels in the shield tank cavity during seal welding of the main coolant leak were;. general area 50 - 100 mr/hr, work area-I outside control rod coil stack air baffle 100 - 200 ar/hr, inside the air I
- baffle h00 600 mr/hr, and contact pressure housings Nos.17 and 18, with 1-the coil stacks removed,1.5_ r/hr.
All Co-60 and Sr 90 calibration sources were leak tested. No I
defects were found.
)
During the month, one drum containing a Core I dashpot with-failed latch finger pin welds was shipped to the primary system designer l
for analysis. Activity of the' shipment was 600 mLllicuries.
4 Personnel exposures for Yankee plant personnel as measured by
[
film badge for the month.of November -1%3 were:
4 270 mr Average for all s+ation personnel
=
920 mr M=v4 = = individtal exposure
=
.;o 4
W
'M*=
g
'W E'N'"
W "TTr-9W7 T T Y'
"'1r'"'T-"W#"
WT' T#TT*'#'
9 T
-FYF
^
M"'Y
'T
%WFT'T'T-*'TP8T ' 4*
'T'T-'-'r1**'F"'HF'Y*WT ' D' 99FT' T'9E"'"-C4"-T"MNM'Pf'#*T'S-91FFT*"9-'t-WTT'T"W' vie'TT""V'*W
Changes in Operating Procedures Previous Operation Reports lave mentioned two occasiens cd which the inner 0-ring seal on the reactor ressel head flange failed during a plant cooldown. The failures have 'oeen traced to differential thermal expansion between the vessel head and body.~ Acccedingly, revised versions of Operations Instructions 5014C2 have been issued lowering the allowable cooldown rate of the primary system.
Plant Operations Attached is a summary of plant operation statistics for the month of November -1963 and a plot of daily average plant load for the same
~
period.
O O
O O
i
, -. - _ _ ~ _... - -,,,..... <,,
. ~., _. =.. -
__m._.m O
o O
O O
+
YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
N01/EMBD1 1963 ELECTRICAL MONTH YEAR TO DATE Gross Generation KWH 51,983,800 886,569,800-2,588,0hl,800 Sta. Service (While Gen. Incl. Losses)
KWH 3,3hh,h5h 59,882,L36 190,639,503 Net Generation KWH h8,579,3h6 826,686,86h.
2,397,h02,297 Station Service 6.hh 6.75 7.37 Sta. Service (While Not Gen. Incl. Losses)
KWH 1,380,900 3,8hh,213 36,813,051 Ave. Gen. For Month (720 Ims.)
KW 72,116 Ave. Gen. Running (338.23 101S.)
KW 153,$16 PIANT PERFNMANCE Net Plant Efficiency 28.90 28.h2 h
Net Plant Heat Rate Btu /KWH n,809
_L2,008 N
Ibs. Steam /NetKWH 1h.27 1h.36 8
Circulating Water Inlet Temp.
Maximum F
h7 Minimum F
h3 Plant Operating Factor h3.23 67.19 6h.38 NUCIEAR MONTH CORE III TO DATE Times Critical 13 321 Hours Critical IRS h03.25 h3h.23 21,987.3h Times Scrammed 3
3 hl Equivalent Reactor Hours @ 5h0 MWt HRS 3 H.26 311.26 15,51h.56 Average Burnup of Core M'.ID/mtU 337.0 337.0 Control Rod Position at Month End Equilibrium at $ho Mle 51h F Tavg.
Group 1 Rods out-inches 75 3/8 Group 2 67 7/8 Group 3 75 3/o Group h 75 3/8 Group $
75 3/8 i
Group 6 75 3/8 Group 7 75 3/8 4
M.C. Boron Conc.
312 ppn
~
,0 o
o o
O YANKEE ' ATOMIC ELECTRIC COMPANY 4
DAILY AVERAGE LOAD for 210VEMBER 1963 I
1 150 -
I 6
g 5
(a) Shutdown No. 62-2-3h 100 -
l (b). Shutdown No. 63-3-1 l
g (c) Shutdown No. 6h-3-2 l
a (d) 9hutA~e-No. 65-3-2 o
E.:
(h) 4 50 -
U
~
~
O i
(a)
(d) 1 k
%h o-ii''
i i
5 10 15 20 25 30 4
DAYS 1
-