ML19351E186
| ML19351E186 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/20/1967 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E185 | List: |
| References | |
| NUDOCS 8011260111 | |
| Download: ML19351E186 (10) | |
Text
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'55 Formal pyy, g.
y YANKEE NUCIIAR tBIH1 STATION OPERATION REPORT NO. 73 For the month of JANUARY 1967 O
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Submitted by YANKEE ATOIEC ELECTRIC COMPANY Boston Massachus etts l
February 20, 1967 i
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This report coverc the operation of the Yankee Atemic Electric Company plant at Rowe, Massachusetts, for the menth of January 1967:
At the beginning of the period the plant was operating at approximately 139 MWe, The plant load was gradually increased to lho MWe by the end of the period as circulating water temperature decreased from hl F to approximately 37 F, and as a result of' refinements to the thermal power calculations for three loop operation.
Two shipments of spent fuel were made during the month, on January 5 and January 27 These shipments are tne seventeentn and eighteenth in the series of spent fuel shipments, bringing the number of elements shipped in the ten element cask to 175 and the total number of elements shipped to date to 191.
On January 25, the monthly control rod exercise was performed. All rods functioned normally.
The second Core VI, air charge to the vapor container was started on u/
January 30 and continued through the end of the reporting period on a daily basis. The charge will be terminated when the total weight of dry air in the vapor container is approximately 66,000 lbs.
The vapor container air leakagt rate was normal throughout the report-ing period.
No plant shutdowns or reactor scrnms occurred during the month of January.
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Plant Maintenance The following ic a list cf the major plant maintenance iten: performed by the plant staff during the month of January 1967:
1.
The control rod operating coil stack removed from the reactor
(,,
head during the Core V-VI shutdown was disassembled and inspected.
v 2.
No. 1 and No. 2 charging pumps were repacked.
3.
The steam generator diaphragm seal weld cutter was modified by installation of a grinding wheel in lieu of a cutter and changing to an air drive for finer control.
h.
A steam generator diaphragm strongback was fabricated as were main coolant pump removal guide studs.
The latter two items were accomplished as part of the prepara-tiens for the anticipated steam generator leak repair.
Instrumentation and Control The following is a list of the major instrumentation and contrcl maintenance items performed by the plant staff during the month of January,1967 1.
Two leaks in the charging pump flow transmitter were repaired.
. 2.
A broken drive string and defective solenoid were replaced on the turbine bearing temperature recoruer.
3.
The teleflex drive motor control circuits were tested and several circuit repairs effected.
h.
A new remote station for the refueling intercom was fabricated.
Reactor Plant Performance Core reactivity depletion subsequent to three loop operation us normal at approximately 0.63%'A K/K per 1000 MWtD/MTU.
Four control rod absorber sections and their associated follever sections, re=oved frcm the reactor during the Core V-VI shutdown were inspected in the spent fuel pit for wear or unusual conditions at the latch joint. No abnormalities were observed. The history of these rods is as follows:
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Absorber Absorber Absorber Associated Follower Section
{ ore Historv Mst uial Follower Section Core History A 50 III, IV, V f Inconel Clad F 28 II,III, IV, V A 51 III, IV, V lag-In-Cd F 26 II,III, IV, V A 81 V
f Stainless Steel F 56 V
A 82 V
tClad Ag-In-Cd F 50 V
In addition, a radiation survey of one H control rod used during f
d Core III, IV, and V operations was conducted. Witn the detector one foot from the control rod (in wateri levels of 100 - 300 mr/hr were seen from the top end to three feet from tra lower end. The lower three feet showed levels of 15 - 75 r/hr.
Inspection of the two Core V, zircaloy fuel elements was started on January 20 and ccmpleted January 28.
The inspection involved gamma scanning of the removable fuel tubes and evaluation of the possibility of relaxation of the inconel retaining springs. Analysis of the data had not been completed by the end of the period. However, the only singularity observed was an inverted peak in the gamma scan of one fuel tube.
The following parameters were determined by means of incore instrumenta-tion at hh9 MWt, 527.0 F Tavg, 1290 ppm boron and control rod groups A, B, C and D at 87 3/8.
2.48
=
Fq 1*98 A
H
- 1. 18 Minimum DNER
=
592.5 F Maximum Outlet Temperature
=
ff 6
'p' m Secondary Plant Performance Feedwater heater terminal difference at 138 MWe, 1.0" Hg backpressure a
and 527 F Tavg:
- 1 - 6.9 r
- 2 - 16.0 F
- 3-1h.6 F Condens#r termin d difference:
2k.8 F Chemistry Approximately tvo _eeks after the isolation of No. k loop from the main coclant system, a slowly increasing primary to secondary leak was observed in the operating loops.
Gross activity measurements indicated that the major leakaCe was in the No.
3 steam generator. At the end of the period the average leakage was 142 gpd.
l j As reported in Operation Report No. 72 (December 1966), the boron b
concentration in the operating main coolant loops was somewhat erratic following isolation of No.
h loop.
This condition occurred as a result of leakage of main coolant into the isolated loop, (borated at shutdown concentra-tion) and the subsequent bleed from the isolated loop to the low pressure surge tank in order to maintain reduced loop pressure. To alleviate this situation a change to the Technical Specifications was requested in Proposed Change No. 78. This provided for reduction of boron concentration in the isolated loop to that of the main coolant system following loop isolation, removal of pump and loop isolation valves from service and mechanical prevention sj of operation by lock and key.
A.E.C.
approval was granted January 6, 1967 at which time the change was implemented.
The main coolant boron concentration decreased from 1392 ppm to 1232 ppm during the period.
The average system crud level was 0.lh ppm.
Coolant iodine - 131 average specific activity was 8.6 x 10 spc/ml; I-131/I-133 atomic ratio was 0.66.
The silver - 11Ca nuclide again was detected in the analysis of coolant crud _ samples. Several crud samples that had been previously collected during Core V operation were analyzed for this nuclide; no silver was detected.
The_ pressurizer vent test program for Core VI was initiated. Testing during Core V operations indicated the possibility of gas stratification in the vessel vapor phase.
During the Core V - VI refueling, the upper narrow range, level tap was adapted for use as a vent and sample location. Current testing vill involve the use of the narrow range and the upper head vent locations to determine the validity of the stratification hypothesis.
Vapor was sampled from the upper head on January 10; the capillary vent at this location had been in operation since Core VI startup. Following sampling, the upper head vent system was isolated and the ne"ov range vent system placed in opera +1on and sampled on January 11 and 12.
Thereafter, all venting was discontinued until January 26 when the narrow rmge vent was reestablished. The narrow range vent was sampled on January 26 and 27 and noting was discontinued on January 27 Test results are as follows:
h-Upper Head Vent System Harrow Range Vent System 7
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Date 11-30-66 1-10-67 1-11-67 1-12-67 1-26-67 1-27-67 Steam Flov, lbs/hr 33.1 21.0 36.1 36.1 37.8 37.4 Gas Conc.,cc/Kg 320 62')
564 bo 1270 785 0.12 0.17 0.31 0.33 0.08 0.24 02%
H %
10.0 13.2 18.3 19.2 98 16.6 2
dh.9 86.6 81.h 8r,5 90.1 83.2 H2g The main coolant crud samples had the follow:ing radiochemical analyses:
77 L,!
dp:/mg crud:
Date Cr-51 Hf-181 Mn-54 Fe-59 Co-60 Ag-110m 6
5 6
5 1-3-67 1.6 x 10 1.2 x 10 1.h x 10 9 0 x 10 2.0 x 10 6.2 x 10 5
6 5
6 1-16-67 5.5 x 10 3.9 x 10 1.1 x 10 6.1 x 10 1,7 x 1g 5.6 x 10 co-58 6
1-3 67 h.4 x 10 v
D 1-16-67 2.8 x 10 A main coolant gas sample collected on January 2h had the following radiochemical analyses:
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Xe-133 5 9 x 10
-3 Xe-135 7.k x 10
-1 A h1 2.6 x 10 Health and Safety Two shipments of radioactive vaste were made during the period.
'l 'e shipments accounted for a total of 110 drums with a total activity of 422 me.
Two shipments of spent fuel were made din'i!.g the period. Shipment No. Seventeen consisted of ten elements with a tctsl activity of 1.41 mega-curies. Gama radiation levels, on contact with the cask were less than 2 mr/hr with a maximum of 8 mr/hr at the valve box.
Fast neutron radiation levels at one meter were approximately 0.h mrad /hr. E3ta-gamma contamination levele 2
were 2.5 x 10-9 curies per 100 cm, maximum. Shipment No, eighteen consisted of nine elements with a total activity of 1. M3 megacuries. Gamma radiation levels, on contact, were generally less than 2 mr/ar with a maximum of 140 mr/hr at the valve box. Fast neutron radiation levels at one meter vere upproximately 2
0.5 mrad /hr. Beta-gamma contamination levels were 1.5 x 10-9 curies per 100 cm.
No slow neutron radiation levels or alpha contamination was detectable on either shipment.
. 01 January 11 and 12 spent filter cartridges were removed from filter capsules "L~
and "F" and the capsules transferred to the storage building for cleaning.
Radiation levels (in air) prior to cartridge removal vere as e
follows:
Capsule From Side Above Top (atl3')
D 60 r/hr at 2 "
225 mr/hr (cover on) 300 mr/hr at 24' 600 mr/hr (cover off)
F 45 r/hr at 2" 170 mr/hr (cover on) 120 mr/hr at 24' h50 mr/hr (cover off)
The estimate of the total activity contained in capsules "D" and "F" were 16 curies and 9 curics, respectively.
During January the vaste disposal liquid releases totaled 232,000 gallons containing 5 cc of gross beta-ga=ma activity and 219.45 curies of x
tritium. Gaseous vaste releases during the same period tJtaled 196 me of
(,)
gross beta-grr-n activity.
In addition to the above liquid vaste releases a total of 279,000 gallens of water were discharged from the secondary plant. The total gross beta-gasma and tritium activities released from the secondary plant were 48 uc and 6.72 curies, respectively.
Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of January,1967 were:
Average accumulated exposure dose 119 mrem Maximum a cumulated exposure dose 328 mrem.
The following is a su= mary of all liquids, gases, and solids released, discharged or shipped frem the plant during the year 1966.
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Waste Disposal Liquid:
1,28h,030 gallons containing a total beta-gamma activity of 36.lh me and 1,872 curies of tritium.
Gas:
A total beta-gamma activity of 2.4 curies and 11 curies of tritium.
Airborne Particulate: A total of 26.11 uc of beta-gamma activity.
Solids for Disposal:
khl drums containing a total activity of 2.886 curies and 10 casks containing a total activity of 489.290 curies.
Secondary Plant Liquid:
2,321,748 gallons containing total beta-ga=ma and tritium activit?
of less than 0.2 me and 50.22 curies, respectively.
Fuel Shipments During 1966 there were 14 spent fuel shipments totaling 136 elements with a total activity of 39 516 megacuries.
. Operations The following Maintenance Instruction was revised and reissued during January:
MI 506 B2 Decontamination System Operation Attached is a su:=ary of plant c.perating statistics and a plot of daily average load for the month of January, 1967 O
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O oo YANKEE ATOMIC ELECTRIC COMPANY -- OPERATING
SUMMARY
January 1967 ENTH YEAR TO DATE EIN;TRICAL WH 103,h36,600 103,h36,600 6,h65,897,100 Sta. Service (While Gen. Incl. Losses)
Of 6,1hl,835 6,1hl,835 h36,16h,657 Gross Generation L :i 97,29h,765 97,29h,765 6,o29,732,hh3 5
5 9h 5 9h 6.75 Net Output Sta. Service (While Not Gen. Incl. Iossea)
WH 0
0 23,795,h67 Station Service Ave Gen. For Month (7hh hr.)
W 139,028 Ave. Gen. Running (7hh hr.)
W 139,028 PIANT PEHFORMANCE 291h 29.1h 28.h7 Net Plant. Efficiency Bru/WH 11,712 11,712 11,987 7h.78 7h.78 71.39 7
Net Plant Heat Rate Plant Operating Factor Reactor Plant Availability 100.00 100.00 82.2h 10lfrH CORE VI
.grAL NUCLEAR HRS 7hh.00 2,085.29 h5,810.97 Hours Critical 0
2 Sh Times Scrammed Burnup MD/MrU 669.50 2,150.21 Core Average ND/MrU Region Average 657,826 2,171,790 18,9hh.29 A (INNER)
B (MIDDLE) 799,862 2,582,538 10,257.83 C (00T]iR) 538,h06 1,715,10h 1,715 10
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-9 CORE VIREION IOCATIONS REIGN C R E Il)N B REION A O
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