ML19351E230

Operation Rept 142 for Oct 1972

ML19351E230
Person / Time
Site:	Yankee Rowe
Issue date:	11/30/1972
From:	YANKEE ATOMIC ELECTRIC CO.
To:
References
NUDOCS 8011260295
Download: ML19351E230 (9)

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i h4 hQ YANKEE NUCLEAR POWER STATION bb OPERATION REPORT NO. 142 g

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YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts

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This report covers the' operation of.the-Yankee Ato' ic Electric ~

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Company at Rove, Massac1usetts for the month of October, 1972.

At the start 'of the ' period plant load was 149.4 We.

One.

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_ unscheduled plant shutdown occurred on-October 18.

See Abnormal Occurrence r.

No. 72.17, this report. A second, scheduled plant shutdown commenced on-October 20 for the purpose of replacing.22 coatrol rods in the reactor core.

The turbine generator was-separated from the high line,at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> that date;~the main coolant was borat,ed; and the. plant was placed in a cold shutdown condition as of October 21.

The third, Core X vapor container air leakage surveillance l

period was. terminated coincident with the reactor shutdown on October 20.

No abnormal' leakage was noted-during this period.

Vapor container integrity was broken at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on October 21.

Purging of the vapor container was comnenced at this time, continuing

.through the duration of the report period.

Removal of the reactor head closure studs was completed on October G

26; the reactor head was removed October 27; and the shield tank cavity was

. filled to ahutdown level on October 30.

On October 30 curing the-lift of the upper core barrel in prep-9 aration for the control rot inttrchange, Zircaloy fuel assembly No..A-421 was lifted out.of its D9 core position. The assembly was observed hanging l

by its upper noszle from the upper core support plate grid with the top of l

-the assembly approximately eight feet above the core. During efforts.to reinsert the assembly into the core.it became dislodged from the grid and dropped several inches, coming to rest on the top of adjacent fuel assemblies, and. leaning against the upper core support barrel in a nearly vertical.

position. 'A chemical analysis indicated no release of fission products to the main coolant or-the vapor container atmosphere. The cause of the

. assembly hang'up in the upper core support plate is being investigated.

j On October 31 the fuel assembly was restored to a vertical position

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and transferred to the Spent Fuel Pit for inspection.

Plant Abnormal Occurrences Abnormal Occurrence No.'72-16, " Failure of No. 3 Diesel to-Start".

On. October h at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> during routine surveillance testing

~ he Nc..3 diesel generator failed to start. The operator standing by the t

diesel observed no. motion of the governor operating lever. This lever which regulates the flow of fuel oil was held partially open and the diesel started.

l Subsequently, three: restarts of the diesel were successfully performed I

without manual adjustment of the governor operating lever.

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, I Abnormal Occurrence No. 72-17, " Plant Trip".

9 C October 18 at 13h0 hours while operating at 498 MWt, a ground developed on station battery No. 1.

A sequential isolation of various battery circuits was conducted in accordance with written procedure to l

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locate the ground ~. During the isolation of circuit breaker No. 6 a reactor scram and turbine trip occurred.

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I When the operator opened circuit breaker No. 6, identified in the procedure as a spare, but marked "M.C.

FLOW CAB A", the trip occurred.

l Removal of the battery supply to Cabinet A caused the four lov flow pro-I i.

tection relays to fail safe. This caused an indicated loss of main coolant i

flow which automatically initiated a plant trip.

A survey of plant equipment and systems indicated no adverse or unsafe conditions. The reactor was taken critical and the plant returned to power.

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Abnormal Occurrence No. 72-18, " Failure of Control Rod No. 19 to Fall Completely Into the Core".

On October 18 at 13h0 hours during the reactor scram and turbine j

g trip described in A.O. No. 72-17 atove, control rod No.19 failed to fall 1

W completely into the core; dropping fron 90 inches to approximately 2h inches.

l Since the plant is operated in accordance with the provisions of Change No.100, the decision was made to withdraw the safety group "D" including control rod No. 19 to 90 inches and return the plant to service.

Atnormal Occurrence No. 72-19, " Failure of Trip Solenoid, S0V-432

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to Operate",

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On October 27 at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> during a surveillance test of the l

Vapor Container Isolation Valves Trip System, the solenoid operated valve SOV 432 failed to operate when energized by the Master Trip WL Relay. The l

solenoid valve controls the air supply to four trip valves m. che secondary steam supply. Failure of the solenoid valve to operate prevented the four trip valves from clesing.

The latch of the solenoid operated valve was repaired. During a j

retest of the Vapor Container Isolation Valve Trip System, the solenoid l

operated valve performed correctly and caused the four trip valv% to close.

i Plant Load Reductions There were no plant load reductions during the report period.

I Plant Shutdowns 1

l Shutdown No. 132-10-72:

10/18/72, plant trip due to loss of battery supply volte4;e for Main Cool. Loss of Flow Trip, cabinet A.

Total outage time:

3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 1 minute.

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-Shutdown No. 133-10-72:

10/20/72, scheduled plant shutdown for replace-x/

ment of control rods.. Outage continuing.at end of report period.

Plant Maintenar.ce The following is a list of pertinent plant maintenance items performed by the plant staff during the month of Octobe. 1972, 1.

The No. 1 charging pump was repacked.

2.

Construction and. test of a shearing tool for the unitized control rods-was completed.

3.

The new control rods were unloaded and lift tested.

h.

Work was commenced on the " October 20, 1972 Shutdown Work List" items.

At the end of the report period all such work was in progress.

Instrumentation and Control The following is a list of pertinent instrumentation and control g_j maintenance items performed by the plant staff during the month of October, 1972.

['Si 1.

The High Pressure Safety Injection f1ce transmitter was replaced and

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the system was recalibrated.

2.

The Vapor Container Isolation Valve Trip test was performed.

3.

All primary channel " Fail Safe" relays were tested.

h.

The Low Pressure Surge Tank vent valve, PCV-201 was relapped.

Secondary Plant Performance Feedvater heater terminal differences were as follows:

No. 1 = h.h F No. 2 = 6.3 F No. 3 = 5.2 F The condenser performance was as follows:

151.5 MWe; 1.93" Hg B.P.; h9h.3 MWt; 6h.3 F C.W. in; TTD = 20.9 F; Cleanliness factor = 63 9%.

Chemistry

('N The main coolant boron concentration was reduced from 1176 ppm to NJ 1097 ppm on October 20 to compensate for normal core depletion. On October 21 the main coolant system was borated to a cold shutdown concentration of j}

2343 ppm and averaged 2380 ppm for the remainder of the period.

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G The main coolant system pH averaged 5.59 until.the system was borated to shutdown. concentration. Subsequantly the pH averaged 5.33.

-1 The main coolant beta-gnnma specific activity averaged 1.23 x 10 uc/ml through October 20 and 1.35.x 10-2 uc/ml during the balance of the l

report period. The crud level averaged 0.05 ppm during the period.

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The main coolant tritium concentration averaged 7 56 x 10 ue/ml until plant shutdown on October 20.

Makeup water added duri shutdown diluted the tritium concentration to an average of h.63 x 10- ue/ml.

l' Filling of the shield tank cavity, which commenced October 27, further diluted the tritium concentration to 5.5 x 10-2 uc/ml.

Prior to the shutdown on October 20, the iodine-131 specific I

activity averaged 2.33 x 10-3 ue/ml and the iodine 131/133 atomic ratio averaged h.70.

At the end of the report period the iodine-131 specific activity had decreased to 1.83 x lo-> ue/ml.

A crud sample for t.he month collected on October 3, had the following radiochemical analyses: dpm/mg crud i

g Cr-51 Mn-Sh Fe-59 co-58 7

5 5

6 W

l.73 x 10 3.01 x 10 7.28 x 10 3.61 x 10 l

Zr-95 sb-12h l

Co-60 4-110Mg 6

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l 9.h7 x 10 6.99 x 10 3.35 x 10 1.51 x 10 l

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An average of the main coolant gas samples collected during the period October 1 - 20 had the following radiochemical analyses: uc/cc gas Xe-133 Xe-135 Ar bl

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-2 h.29 5 13 x 10 2.88 x 10 Health and Safety

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i One shipment of radioactive vaste, consisting of 55 drums and

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containing a total activity of 240.7 me, was made during the report period.

I Waste disposal liquid releases totalled 53,589 gallons containing O.612 me of gross beta-gamma activity and 79.53 curies of tritium. Oaseous releases during the period totalled 12.620 curies of gross beta-gamma activity and 0.Thl curies of tritium. Secondary plant water discharged totalled 209,871 gallons containing 0.009 se of gross beta-gamma activity and 0.108 curies of tritium.

Radiation exposure doses for Yankee personnel, NEPSCo personnel; l

and Outside Contractor personnel as measured by film badge for the month of l

October, 1972 were as follows:

1.

l Yankee Plant Personnel Average accumulated exposure dose: 119 mrem Maximum accumulated exposure dose: h50 mrem

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G NEPSCo. Personnel

.l Average accumulated exposure dose:

'223 mrem, i

Maximum accumulated exposure dose:

8h0 mrem-l l

j Outside Contractor Personnel 3

l Average accumulated exposure dose:

225 mrem Maximun accumulated exposure dose: 1140 mrem l

i Operations I

Attached is a su= mary of plant operating statistics and a plot j

of daily average load fue the month of October 1972.

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YANKEE ATOMIC ELECTRIC COMPANY - OPERATING

SUMMARY

October 1972 MOTM.!

YEAR TO DATE ELECTRICAL Gross Generation KWH 72,075,100 690,113,200 13,705,989,100 Sta. Service (While Gen. Incl. Losses)

KWH 4,768,381 45,629,191 886,698,805 KWil 67,306,719 6hh,484,009 12,819,290,295 Net Output Statien Service 6.62 6.61 6.47 Sta. Service (While Not Gen. Incl. Losses) KWH 290,633 5,754,996 38,859,388 Ave. Gen. For Month (Th5)

KW 96,745.1 Ave. Gen. Running (h75.02)

KW 151,730.7 PLANT PERFORMANCE Net Plant Efficiency 28.73 28.80 28.50 Net Plant Heat Rate btu /KWHll,878.70 11,8h9.83 11,97h.55 P1arrt Capacity Factor 52.h2 50.95 75.09 ln Reactor Plant Availability 63.95 66.08 83.96 MONTH CORE X TOTAL NUCLEAR Hours Critical HRS h76.45 3,75h.15 89,239.1h 1

9 70 Times Scrammed i

Burnup MWD /MTU 500.52 3,726.81 Core Average MWD /MTU Region Average A (INNER) hh9 29 3,279.05 21,63h.55 B (MIDDLE) 543.37 h,080.6h 14,051.99 f

C (OUTER-ZIRCALOY) h57 77 3,380.h3 3,380.h3 l

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