ML19351E330
| ML19351E330 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/19/1969 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E329 | List: |
| References | |
| NUDOCS 8011280121 | |
| Download: ML19351E330 (10) | |
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Regulatory File Cy.
YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. 107 neeerved w/ttr D.ead M' For the Month of 1
Nove:aber 1969 1
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3 f!00M 016 Submitted by YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts December 19, 1969 8011280l y
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O This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts for the month of November,1969.
During the period plant load varied between 181.7 K4e and 185.9 K4e as the circulating water temperature fluctuated between 520F and h20F.
On November 2L, representatives of the International Atomic Energy Agency replaced their existing seals on the reactor head missile shield.
One shipment of spent fuel containing a total of nine assemblies remeved during the Core VII - VIII refueling period, was made on November 14 This fuel shipment was the 28th in the series, bringing the number of assemblies shipped in the ten assembly cask to 262, and the total number of assemblies to date to 278.
The second Core VIII air charge to the vapor container was initiated Hovember 26 and was still u progress at the end of the report period. Air le akage fren the vapor container during the first Core VIII air charge sur-veillance period was calculated to te 0.0355 per day.
During the report period, the primary to secondary leak rate increasea from 3h to 89 gallons per aay.
Surveillance of the leakage indicated the No. 1 steam generator tc be the prine offender.
During the monthly control rod exercise, rods 30. 7 and no. 17 were found to be cut of step.
During the exercise when one half of Group D was cycled from 90 0/8" to 84 0/8" and back to 90 0/8", control rod No. 17 would not withdraw beycnd 87 0/8".
Ecd Ho. 17 was exercised singly, in and out to 90 0/8", successfully. Fod No. 17 was then recycled with Group D with no detectable abnormalities. When control rods 5, 6, 7, and 8 vere withdrawn i
from SL 0/8" to 90 0/8", rod no. 7 would not withdraw beyond 87 0/8".
Further efforts to withdraw this rod beyond 87 0/8" were unsuccessful. Upon completion of the exercise, control rod No. T was lef t one step out of phase at 87 0/8".
i Plant Abnormal Occurrencea l
Abnormal Occurrence Ho. 69-7 " Inadvertent Gas Eelease From Low l
Pressure Surge Tank".
j The pressurizer capillary vent line routes steam condensate, and non-condensable gases from the pressurizer steam phase to the low pressure surge tank.
A valved tee connection in the line is used to divert the flow through a cooler and to the sample hood where measurements of f cw rate and samples of the effluent can be obtained. The normal s ampling procedure involves closing the valve to the L?3T and opening the valve to the sanple hood, which in turn exhausts to the primarr vent stack.
The diverted flow is taintained for about two hours in ceder to establish equilibrium flow conditions prior to l
sampling.
On November 18, the pressurizer capillary vent was in normal operation valved to the low pressure surge tank.
The vent valve to the low pressure surge tank was closed and the bypass valve to the sample hood was opened to purge the line preparatory to s ampling the effluent.
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LUperations personnel, during a~ routine inspection, noticed that the vent valve to the lov cressure surge' tank was closed, and being' unaware that sampling'eperation was in progress, opened the valve at 1hh5 hours. This.
etion cross tied the~ LPST gas phase to the sample hood and resulted in an nadvertent discharge ' of gas to the primary vent stack.
Further investigation of the valving discrepancy confirmed that back flow was taking place. The valve to'the LPST was secured at 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br />.
i An estimated 47.6 cubic feet of gas was dist narged from +he low pressure surge tank-during: the 40 minute release period.
The total activity released due to the misvalving was 19.22 milli-curies. The concentration of the released gases after dilution and when averaged over a 2h hour ' period, was 3.1 x 10-12 ue/ce.
Normal plant tagging procedures have been made applicable to. the two valves involved to assure cptrator cognizance of any valving operation in this vent system.
Plant Load Reductions.
There were no plant load reductions durin'g the month of November,1969 t
Plant Shutdowns I
There were no plant shutanvns during the month of November,1969 The following is a list of pertinent maintenance items performed by the plant staff during the month of Hovember, 1969 l'. New internal components were installed in the No. 3 charging pump relief valve, consisting of the disc with attached bellows and the nozzle with
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attached seat. :-The packing in this pump was-also renewed.
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A new set cf teflon rings, head gasket, and reconditioned valves were
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installed in the No. 2 control air comuressor.
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The steam generator blevdown tank level control valve seats and spool were
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The gravity drain tank No. 2 pump impeller was replaced.
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A new mechanical seal was installed on the shutdown cooling pump.
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Lubrication oil low pressure alarms have been installed on No. 1 and No.
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I charging pumps. ' Installation of the alarm on No. 2 pump is in progress.
Instrumentation and Control j
The following is a list of pertinent instrumentation and control aintenance items performed by the plant staff during the month of November,1969
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A temperature control. valve was installed on the coagulator water heater.
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A level indicator was installed in.the ion _ exchanger shield water tank.
Reactor Plant Performance The following parameters were determined by means of incore instrumentation:
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i 590.0 tut; 526.9 Tavg; Control Rod Group A @ 82', B, C, D @ 87 ;
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986 ppm boron.
F 2.3
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Q F
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2.1 t.h.
Minimum DNER
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3.25 Maximu outlet temperature 596.9
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Secondary Plant Performance Feedwater heater terminal differences were as follows :
6.50F No. 2 No. 1 12.2cF No. 3
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5.3 F
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I The condenser performance was as follows :
186.0 MWe; 1.80" Hg. B.P. ; 590.6 MWt; L8.loF C.W. in; TTD 32.3 F;
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j cleanliness factor 60.0%
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i Chemistry The main coolant boron concentration was decreased from 1028 ppm to j
930 ppm during the period to compensat_ for normal core depletion. The average main ' coolant pH was 5.2 The main coolant average gross beta-gamma activity and crud level were 7.51 x 10-2 ue/ml and 0.02 ppm respectively.
The main ecolant tritium concentration averaged 3.93 ue/ml during the period.
The average iodine-131 specific activity was 2.2 x 10-5 ue/ml and the iodine 131/133 atomic ratio was 0.h3,-indicating the absence of detectable fuel defects.
l A' representative crud sample for the month, collected on November 2h, had the fellowing radiochemical analyses : dpm/cg crud Cr-51 Mn-Sh Fe-59 3.96 x 106 5
9 54 x 10 3.48 x 106 O
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O l-i h-l, Co-58 co-60 Ag-110M 6
2 90 x 10 1,45 x 106 1.53 x 105 i
A main coolant gas sample collected on November 12 had the following
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radiochemical analyses: ue/cc gas I
i Xe-133 Xe-135 Ar-41
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3.22 x 10-3 6.58 x 10-3 h.82 x 10-1 l
Health and Safety One shipment of 52 drums of low level radioactive waste was made j
du"ing the period, containing a total activity of 127.6 me, i
One shipment of spent fuel containing a total activity of 20.3 j-megacuries, was made during the period.
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Waste disposal liquid releases totalled 23,8ho gallons containing 0.029 me of gross beta-gamma activity and 74.67 curies of tritium.
Gaseous releases during the period totalled 263.1 me of gross beta-gamma activity and l
13.5 curies of tritium. Secondary plant water discharged, totalled 206,300 j.
gallons containing 1.hh me of gross beta-gamma activity and 33.35 curies of l
i Radiation exposure doses for Yankee plant personnel, as measured y film badg e, for the month of November,1969 were as follows:
Average accumulated exposure dose:
81 mren Maximum accumulated exposure dose:
520 mrem i
Operations a
j Attached is a summary of plant operating statistics and i plot of j
daily average load for the month of November,1969.
Included in this port are revised " Operating Summary" sheets for i
the months of September an October,1969, correcting errors in the Nuclear -
Burnup - Pegion Average - A, B, and C - Total - To Date.
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I YAdKEE ATCMIC ELECTRIC COMPANY - OPERATING
SUMMARY
NOVEMBER 1969 ELECTRICAL MONTH YEAR TO DATE i
Cross Generation KWH 133,030,600 1,073,955,100 10,077,716,900 Sta. Service (While Gen. Incl. Lossec)
KWil 7,860,292 67,290,799 661,885,058 Net Output KWil 125,170,308 1,006,66h,301 9,415,831,842 Station Service 5 91 6.27 6.57 Sta. Service (While Not Gen. Incl. Losses) KWH 0
2,62h,279 28,907,929 i
O Ave. Gen. For Month (720)
KW 18h,765 i
i Ave. Gen. Running (720)
KW 18L,765 1
PLANT PERFORMANCE 1
Net Plant Efficiency 29.56 28.58 28.39 Net Plant Heat Rate btu /KWH 11 5h5 11,9h1 12,021 7
Plant Capacity Factor 90.01 73.24 7h.43 m
Reactor Plant Availability 100.00 81.86 83.71 j
NUCLEAR MONTH CORE VIII TOTAL i
Hours Critical HRS 720 1,6hl.17 67,h60.95
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Times Scrammed 0
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8ere P Core Average M4D/MTU 8h8.99 1,873.hT Region Average M4D/MTU A (INNER) 787.38 1,7h2.h4 21,673.34 i
B (MIDDLE) 986.59 2,174.03 14,210.09 C (OUTER) 717 91 1,583.93 1,583.93 D (ZIRCALOY)
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YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
j September 1969 j
ELECTRICAL MONTH YEAR TO DATE a
Gross Generation KWH 2h,260,600 811,520,000 9,815,281,800 f
Sta. Service (While Gen. Incl. Losses)
KWH 1,542,6hh 51,501,256 6h6,095,515 l
Net Output KWH 22,717,956 760,018,7hh 9,169,186,285 t
Station Service 6.36 6.35 6.58 Sta. Service (While Not Gen. Incl. Losses) KWH 1,066,79h 2,h98,586 28,782,236 Ave. Gen. For Month (720)
KW 33,695 Ave. Gen. Running (1h3.75)
KW 168,769 l
l PLAhT PERFDRMA' ICE l
l Net Plant Efficiency 27.61 28.h6 28.38 Net Plant Heat Rate btu /KWH 12,361 11,991 12,029 s
Plant Capacity Factor 19.05 67.9h 73.98 i
Reactor Plant Availability cl.65 77.87 83.k1 NUCLEAR MONTH CORE VIII TOTAL i
Hours Critical HRS 1E6.70 186.70 66,006.h8 l
Times Scra==ed 0
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Burnup Core Average M4D/?EU 16h.98 16h.98 Region Average M4D/?RU i
l A (INITER) 169.3h 169.3h 20,100.2h
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B (MIDDLE) 190.88 190.88 12,226.9h l
l C (OUTER) 138.51 138.51 138.51 D (ZIRCALOY) l j
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- Note: Reported in error in September 1969 Creraticn Report No. 105 t
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1 YA"KEE ATOMIC ELECTRIC COMPANY - CFERATING SLTMMARY r
l October 1969 ELECTRICAL MONTH YEAR TO DATE l
Gross Generation KWH 129,h0h,500 9ho,92h,500 9,9hh,686,300 Sta. Service (While Gen. Incl. Locaes)
KWH 7,929,251 59,h30,507 65h,02h,766 l
j Net output KWH 121,475,2L9 881,h93,993 9,290,661,53h Station Service 6.13 6.32 6.58 Sta. Service (While Not Gen. Incl. Leases) KWH 125,693 2,624,279 28,907,929 Ave. Gen. For Month (7h5)
KW 173,697
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Ave. Gen. Running (726.8h)
KW 178,037 i
PLANT PERFORMANCE Net Plant Efficiency 28.3h 28.LL 28.38 Net Plant Heat Rate ETu/KWH 12,0h2 12,000 12,025
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Plant Capacity Factor 95.90 70.t1 7h,po l
Reacter Plant Availability 99.L3 80.07 83.56 I
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NUCLEAR MONTH CORE VII' TOTAL l
Hours Critical HRS 73h.h7 921.17 66,Tho.95
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Times Scra==ed 1
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Burnup
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bMD/MTU 859.50 1,02h.h8 Core Average l
Regicn Average FMD/MTU (INNER) 786.82 956.16 20,885.96 a
I B (MIDDLE) 997.95 1,188.83 13,223.50 l
C (OUTER) 728.53 S67.0h 866.02 1
D (ZIRCALOY) i l
- Note: Reported in error in October 1969 Operation Report No. 106.
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