ML19351E292
| ML19351E292 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/20/1970 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E291 | List: |
| References | |
| NUDOCS 8011260456 | |
| Download: ML19351E292 (8) | |
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YANKEE NUCLEAR POWER STATION 4
OPERATION P.EPORT NO. 118 For the Month of October 1970 3
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l Submitted by i
YANKEE ATOMIC ELECTRIC COMPANY l
Westboro Massachusetts November 20, 1970
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This report covers the operation of the Yankee Atomic Electric Company at Rove, Massachusetts, for the month of October, 1970.
On October
'.5, a codium tracer was introduced into the main coolant system for the purpose of checking the primary to secondary leak rate. Analysis of the resul'.s of the test corroborated that the No. 4 steam generator was the ma. jar offender with negligible leakage from No.'s 1, 2 and 3 steam generators'. The leak rate at time of reactor shutdown on October 2h was 122 gallons per day.
On October 2h at 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br /> the turbine generator was separated from the high line for the Core VIII - IX refueling and maintenance shutdown.
Plant load at the time of shutdown was 131.2 MWe, reduced from 154.0 MWe at the start of the report period due to continued plant stretchout operation.
The total electric generation for Core VIII was 1,567,753,000 KWh.
During the Core VIII period, reactor availability and the plant capacity factor including stretchout operation but exclusive of refueling shutdown time were 94.99% and 89.96%, respectively.
The seventh ' Core VIII vapor container air leakage surveillance period was terminated coincident with reactor shutdown on October 24.
Leakage during the period was normal.
On October 23 and 24, a 45,000 gallon continuous dilution of the main coolant was performed to reduce the system tritium inventory. Tritium 9
concentrations before and after the dilution were 5.68 x 10-1 uc/ml and 7.09 x 10-2 uc/ml, respectively.
Routine vibration testing of the four main coolant pumps was performed at the onset of the outage period. No abnormal conditions were detected.
A turbine oil pressure, simulated overspeed trip test, and an actual turbine overspeed trip test were performed following separation from the high line. Results of both tests were satisfactory.
All main steam line safety valves were tested on October 23.
Following plant shutdown, the main coolant was borated and system cooldown was initiated. The plant cooldown was completed on October 25 Vapor container integrity was broken on October 25 at 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> and work was commenced preparatory to removal of the reactor vessel head.
Purging of the vapor container was commenced at this time and was continued throughout the report period.
The fuel transfer train was tested extensively with satisfactory reaults.
Components in the transfer train had been damaged previously (See Operation Report No. 104) with repairs performed in the interim period.
Filling of the spent fuel pit with demineralized water was commenced following completion of the test on October 31.
. 4 Removal of reactor head closure studs was commenced on October 31 and continued through the end of the report period.
Plant Abnormal Occurrences There were no plant abnormal occurrences during the report period.
Plant Load Reductions i
October 4 (1600 - 2020):
Load reduction to lho MWe due to electrical storm.
October 15 (2235 - 2325):
j October 23 (0800 - 1508):
Load reduction to 130 MWe for testing of steam I
generator safety valves.
Plant Shutdowns l
Shutdown No. 112-8-70:
October 24, 1970.
Scheduled Core VIII - IX refueling shutdown.
Core VIII - IX Major Work Items Work was commenced on the master list of major work items to be i
l completed during the current shutdown period. The one major item completed l
during this report period was the installation of a new "T" shaped inflatable seal between ths reactor vessel and the neutron shield tank. At the end of 9
the period, work was in progress preparatory to removal of the reactor vessel closure head and subsequent flooding of the shield tank cavity.
Inspections 1.
Both water boxes of the main condenser were inspected. No abnormal conditions were detected.
2.
The feedwater heater drains tank was inspected and found to be in good condition.
3.
The condenser vacuum priming tank was ;pened for inspection. A protective sealant was applied to the inner surface.
h.
The main transformer oil coolers were inspected. All tubes in the four l
coolers were cleaned with rubber plugs.
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5.
The low pressure surge tank No's. 3 and h safety valves were removed, inspected and tested, and reinstalled.
Instrumentation and Control The following is a list of pertinent instrumentation and control 3
maintenance items performed by the plant staff during the month of October, 1970, 1.
The proportional counting detectors in thimbles No. 2 and No. 6 were replaced.
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. -- _ i 1 2.
The signal cables from the detectors in thimbles No. 1 and No. 6 were replaced.
3.
The narrow range temperature channels were recalibrated.
h.
The wide range level receivers and feedvater flow transmitters for steam generators 1, 2 and 3 were recalibrateu.
5.
The three primary pressure channels were recalibrated.
6.
Work was continued on installation of the atmospheric temperature gradient measuring system.
7.
The boiler feed pump pressure transmitters were recalibrated.
4 Reactor Plant Performance The following parameters were determined by means of incore instrumentation:
3 488 MWt; 501.0 F Tavg; Control Rod Groups A, B, C and D @ 90 ;
8.1 ppm boron.
1.8 F
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F 2.0 AH h9 Minimum DNER
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Maximum Outlet Temperature = 553.h F Secondary P] ant Performance Feedwater heater terminal differences were as follows:
3.8 F No. 2 9.h F No. 3 No. 1 h.8 F
=
=
=
The Condenser performance was as follows:
146.1 MWe; 1.86" Hg. B.P.;
485.5 MWt; 58.55 F C.W. in; TTD = 23.6 F; cleanliness factor = Sh.1%.
Chemistry The main ecolant pH and ammonia concentration averaged 9.4h and 15.5 ppm respectively until October lh when ammonia pumping was stopped because of the sodium test.
By the 2hth the m=monia and sodium had been removed from the system by a combination of ion exchange, radiolytic de-composition and dilution, thereby resulting in a neutral pH.
Following reactor snutdown on October 24, the main coolant was borated to a concentration of 2956 ppm.
During the balance cf tha report period the boron concentration averaged 2931 ppm.
-h-During the October period of reactor operation, the main coolant average gross beta-gamma specific activity was 7.Th x 10-2 ue/ml, and the crud level was 0.03 ppm.
The beta-gamma specific activity averaged 1.0h x 10-2 uc/ml during the balance of the report period.
During the period of power operation the iodine-131 specific l
activity was 4.88 x 10-5 uc/ml and the iodine 131/133 atomic ratio was 0 75.
l At the end of the report Ieriod, the iodine-132 upecific activity had decreased to 1.08 x 10-6 uc/ml.
A representative crud sample for the month, collected on October 17, had the following radiochemical analyses: dpm/mg crud cr-51 Mn-Sh Fe-59 6
6 4.h9 x 107 h.03 x 10 3.8? x 10 Co-58 co-60 Ag-110M 6
h.05 x 107 6.88 x 10 h.83 x 105 A main coolant gas sample for the month, collected on October 13, i
had the following radiochemical analyses: uc/cc gas i
Xe-133 Xe-135 3r-bl 3 5h x 10-3 7.88 x 10-3 3.14 x 10-2 Health and Safety Three shipments of radioactive vaste were made durir.g the period, totaling 162 drums containing a total activity of 915.2 me.
j Waste disposal liquid releases totaled 6h,780 gallons containing 0.087 me of gross beta-gamma activity and h7 51 curies of tritium. Gaseous i
releases during the period totaled 0.145 curies of gross beta-gamma activity and 5.ho me of tritium. Secondary water discharged totaled 332,065 gallons l
containing 0.316 me of gross beta-gamma activity and 5.13 curies of tritium.
In addition to the above releases 0 539 curies of tritium as a vapor was discharged to the environs during the period.
I Radiation exposure doses for Yankee plant personnel and UEPSCo personnel as measured by film badge, for the month of October, 1970 were:
Yankee Plant Personnel Average accumulated exposure dose:
200 mrem Maximum accumulated exposure dose: 800 mren NEPSCo Personnel Average secumulated exposure dose:
188 mrem Maximum accumulated exposure dose: 790 mrem Operations Attached is a summary of plant operating statistics and a plot of daily average load for the month of October, 1970, i
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SUMMARY
October 1970 ELECTRICAL M0!."I'H YEAR TO DATE Gross Generation KWH 83,764,600 1,143,115,700 11,358,774,200 Sta. Service (While Gen. Incl. Losses)
KWH 5,70h,670 69,802,744 739,807,608 Net Output KWH 78,059,930 1,073,312,956 10,618,966,592 Station Service 6.81 6.11 6.51 Sta. Service (While Not Gen. Incl. Losses) KWH 202,925 2,361,004 31,268,933 Ave. Gen. For Month (745)
KW 112,h35.7 Ave. Gen. Running (574.20)
KW 145,880 5 PLANT PERFORMANCE Net Plant Efficiency 5
28.14 29.16 28.h8 Net Plant Heat Rate btu /KWH 12,128 11,704 11,983 Plant Capacity Factor 62.07 84.08 75 50 i'
Reactor Plant Availability 77.21 91.21 84.47 NUCLEAR MONTH CORE VIII TOTAL Hours Critical HRS 575.25 9,083.09 74,902.87 Times Serammed 0
5 62 Burnup Core Average MWD /MTU 556.38 10,141.64 Region Average MWD /MTU A (INNER) 562.07 9,543 95 29,474.85 B (MIDDLE) 631 95 11,582.06 23,618.12 C (OUTER) 480.03 8,741.85 8,741.85 D (ZIRCALOY)
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