ML19351E304
| ML19351E304 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/22/1970 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E303 | List: |
| References | |
| NUDOCS 8011280053 | |
| Download: ML19351E304 (8) | |
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OPERATION REPORT NO. 114 s'
For the Month of June 1970 lb;h*!
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Submitted by YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts July 22, 1970
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This report covers the operation of the Yankee Atomic Electric Ccmpany at Rowe, Massachusetts for the month of June, 1970.
During the period plant load varied between 183.3 MWe and 186.0 MWe as the circulating water inlet temperature fluctuated between 52 F and h5 F.
During the period the primary to secondary leak rate increased from 97 to 153 gallons per day.
One scheduled plant shutdown occurred on June 12 for the purpose of location and repair of a suspected leak from the primary plant into the i
vapor container atmosphere. During plant load reduction for the purpose of this shutdown, a reactor scran and turbine trip occurred at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on i
June 12.
This plant trip is discussed as Abnormal Occurrence No. 70-3, this l
report.
Inspection, subsequent to reactor shutdown, revealed a lear from the seal welded manway diaphragm in the inlet side of the No. 1 steam 'enerator.
Following 1 cop isolaticn, cooldown, and draining, a crack, approximately one
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inch long was found in the diaphragm seal veld.
The crack was ground out and a successful reveld was completed on June IL.
During heatup of the isolated 1 cop, surveillance of the repair area at up to 2000 psig, revealed no further leak age.
The turbine generator was phased on the line on June 15 at 0035 l
hours, with 1cading completed to Sho MWt at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />. The plant was fully loaded to 600 !%'t at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br /> on June 15.
On June 21 an increase in the vapor container air particulate monitor ccunt rate alerted operating personnel to a possible leak from primary side to atmosphere.
Inspection revealed a pinhole leak in the main coolant bleed line variable orifice valve body.
The leak was on the downstream side of the break ( own portien of the valve.
Bleed flcw was transferred through the fixed flow 20 gallons per minute orifice.
Pepair of the leak was effective, however the variable orifice valve will be maintained as backup until a new valve body is installed.
l The fifth Core VIII vapor container air leakage surveillance period I
continued throughout the report period.
Leakage during the period was normal.
Plant Abnormal Occurrences I
Abnormal Occurrence No. 70-3 " Plant Trip" On June 12, 1970 a scheduled olant shutdown ias in progress when at 2213 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.420465e-4 months <br /> the reactor scrammed; and the turbine tripped, from a load of approximately 18 MWe.
The plant trip occurred when the operator changed the reactor power scram cet switch from the High to the Low set position without first adjusting the fine gain on the power range channels to below an indicated 35%. No adverse conditions resulted from the plant trip. The Plant was maintained e
previously.
in a hot standby condition for the balance of the shutdown period as described N
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e Plant Load' Reductions' June 3
-(1500-20h0):
. Load reduction to 150 !&e'due to electrical storm.
' June-3-h' (2150--0615 ) d Load reduction to 100 !We for reason of electrical maintenance in the Harriman Station switchyard.
June 18 (05h5-0Th5):
Load reduction to'1h8 K4e due to electrical storm.
June 18 (1955-2210):
Load reduction to lh8 K4e due to electrical:
storm.
June 21' (0755-1230):
Lead reduction to 125 fue.during repair of the leak in the main coolant bleed'line variable orifice valve body.
Plant Shutdowns Shutdown No. 110-8-70:
6/12/70 to 6/15/70, scheduled plant shutdown to permit repair of leaking seal velded-diaphragm in inlet side manway of No. 1 steam generator.
Plant Maintenance The following is a list of pertinent plant maintenance items i
performed by the plant staff during the month of June,1970.
1.
One efurbished plunger was installed in the No. 1 charging pump, and the pump was repacked.
2.
Major items performed during the June 12 - 15 shutdown included revelding the No. 1 steam generator inlet side manway diaphragm; reconnecting the stem leakoff line on No. h main coolant loop bypass valve; and stoning the exciter commutator and replacing 20 brushes.
.Instrunentation and Control The following is a list of pertinent instrumentation and control-maintenance 16 ems performed by.the plant staff during the month of June,1970, 1.
.The start-up panel indicators and transmitters were recalibrated.
2.
Preparatior. was initiated of a new triaxial cable penetration to the vapor container.
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I Reactor Plant Performance The following parameters were determined by means of incore instrumentation:
7 593.7 MWt; 526.8 F Tavg; Control Rod Group A @ 88, B,C,D @ 89 ;
124 ppm boron.
F
= 1.9 2.0 F
=
H Minimum DUER = 3.h l
Maximum Outlet Temperature = 595 1 F l
l Secondary Plant Performance Feedwater heater terminal differences were as follows:
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i No. 1 = 5.63 F No. 2 = 11.31 i No. 3 = 5.62 F i
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The Condenser performance was as follows:
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18h.2 MWe; 1.8h" Hg. B.P. ; 593.2 MWt; 53.5 F C.W. in; TTD = 2L.28 F; cleanlines: factor = 73.27%.
Chemistry l
The main coolant boron concentration was decreased from 2h8 ppm to 118 ppm during the period to compensate for normal core depletion.
The average main ecolant pH was G.67
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The main coolant average gross beta-gamma activity vas 1.03 x 10 l
uc/cl. The main coolant crud level averaged 0.03 ppm, except following the f
shutdown on the 13th when a value of 0.2h ppm was recorded.
9.h8x10{hemainecolanttritiumconcentrationdecreasedfron1.63uc/mlto 1
- uc/ml during the period due to dilution.
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The average iodine-131 specific activity was 3.h3 x 10 ue/ml and
~5 the iodine 131/133 atomic ratio was 0.51 indicating the absence of detectable fuel defects.
A representative crud sample for the contP collected on June 3, had the following radiochemical analyses:
dp /mg crud.
l Cr-51 Mn-Sh Fe-59 I
6 2.12 x 10 h.ll x 10 8.92 x 10 Co-58 Co-60 Ag-110M 7
6 3.36 x 10 6.65 x 10 6.00 x 105 i
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'.A main coolant gas sample for the month, collected on June 10, 9
had the:following radiochemical analyses:
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uc/cc. gas.
l Xe-135 Ar-bl l
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k.05'x 10 A.Th x 10
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' Health and Safety Waste disposal-liquid releases totalled 65,610 gallons.containing 0.0hl.mc of gross beta-gamma activity-and.126.2h curies of tritium. Gaseous l
f releases'during the period-totalled 1.549 curies of gross beta-gamma activity
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and 83.5 me'of tritium. Secondary water discharged totalled 375,735 gallons
.containing 3.791 me of gross beta-gamma activity 18.26 curies of tritium.
.i Radiation exposure. doses.for. Yankee plant personnel, as measured
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by film badge, for the month of June,1970 were.as follows :
LAverage accumulated exposure dose: 125 mrem i
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' Maximum accumulated exposure dose: 580 mrem Operations
-I Attached _ is a summary of plant operating statistics and a plot-
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of-daily average load for the month 'of. June,1970.
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(fM 88030) GYUI 20VEIAY II1YG:
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i YANKEE ATOMIC ELECTRIC COMPANY - OPERATING SUf P' E June 1970 ELECTRICAL MONTH YEAR TO DATE i
Gross Generation KWil 121,896,100 727,199,h00 10,942,857,900 Sta. Service (While Gen. Incl. Losses)
KWH 7,2hl,058 43,161,116 713,165,980
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Net Output KWH 114,655,0h2 684,03d,28h 10,229,691,920 h.
Station Service 5.9b 5.9h 6.52 Sta. Service (Whik* Not Gen. Incl. Locsec) KWil 313,h88 1,538,h83 30,hh6,412
, Ave. Gen. For Month (720)
KW 169,300
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Ave. Gen. Running (669.63)
KW 182,035 g
l PLANT PERFORFANCE Net Plant Erriciency 29.39 29.58 28.h8 j
Net Plant Ifeat Rate btu /KWH 11,612 11,537 11,983 i
l Plant Capacity Factor 90.31 88.74 75.4h I
l Reactor Plant Availability 99.66 93.63 8h.36 j
NUCLEAR MONTH CORE VIII TOTAL l
l liours Critical llRS 717.55 6,h94.h2 72,314.20 Times Scrammed 1
4 61 Burnup 9
Core Average FMD/hffU 782.36 7,397.20 Region Average FMD/hfrU A (INNER) 762.9h 6,808.17 26,739.07 B (MIDDLE) 886.2h 8,h7h.70 20,510 76 C (OUTER) 680.45 6,360.15 6,360.15 D (ZIRCALOY) i i
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