Text

Annual Operating Rept 10,1980
	ML20003C417
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/04/1981
From:	; PUBLIC SERVICE CO. OF COLORADO
To:	;
References
	NUDOCS 8103050276
	Download: ML20003C417 (50)
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i PUBLIC SERVICE COMPANY OF COIDRADO I

FORT ST. VRAIN NUCLEAR GENERATING STATION i

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i ANNUAL OPERATING REPORT t

NO. 10 1980 t

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INTRODUCTION i.

This report is submitted in accordance with Section AC 7.5.1.b of the Technical Specifications of the Fort St. Vrain Nuclear Generating Station, Unit No. 1,

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Facility Operating License No. DPR-34.

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! P 1.0 ' NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE This report contains the highlights of Fort St. Vrain, Unit No. 1, operation under the provisions of the Nuclear Regulatory Commission Operating License, DP R-34.

This report is for the year of 1980.

l 1.1 Janua ry I

The reactor was taken critical on December 25, 1979, and power held at f

approximately 1.5% for primary and secondary coolant system cleanup.

A reactor scram and Leop 2 shutdown occurred on December 30, 1979, following the operation of 1C circulator at speed. High moisture levels were attributed to an ingress which occurred on December 7, 1979. During this shutdown, maintenance was performed to correct the feedwater leakage at V-2256 and to stop the hydraulic oil leakage at HV-2254.

r The reactor was taken critical again on January 5,1980, but on Janu -

ary 8,1980, ' the 1B circulator primary seal was discovered to be in-operable, and the reactor was placed in a shutdown condition. The outage to replace the 1B circulator started on January 17, 1980.

1.2 Feb ruary The outage for 1B circulator replacement continued through the month of February,1980.

t Decay heat removal continued, utilizing Loop 2 steam generators on condensate. Decay heat levels decreased to the point that secondary coolant flow could be removed for calculated periods of time to allow calibration of instrumentation.

The prestressed concrete reactor vessel was pressurized to 94 psia on February 12, 1980, and primary coolant cleanup was started.

Maintenance was completed on Loop 1, and it was returned to service on February 13, 1980.

Auxiliary boiler #1 repairs were completed, and the unit was tested and proven operational.

The reactor was brought critical on February 18, 1980, and training starts were accomplished by all licensed and license trainee person-nel requiring reactor starts.

While the plant was shutdown for the circulator replacement, many i

maintenance items were completed.

Maintenance work concentrated mainly on leaking valves.

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On February 25, 1980, a small fire started on the service air com-pressure discharge header.

The fire was contained without damage to j

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) i i

'1.2 February (Cont'd) l On February 28, 1980, the annual Radiologichl Emergency Response Drill was conducted in conjunction with the state and local entief es.

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drill tested many revisions instituted as a result of Three Mile Is-

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land-2, as well as the revised State Radiological Emergency Response Plan.

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1.3 March At the beginning of the month, preparations were made for plant start-i up.

On March 5,1980, at 0250 bours, the turbine generator was syn-chronized, and the electric load increased to 80 MW.

On March 6, 1980, I

f the turbine generator actual overspeed tests were performed. The unit was resynchronized af ter the test, and the electrical load vas in-creased to 100 MW.

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Excessive oxidant contaminants in the primary coolant hellun, as well as various control system problems caused the electrical load capa-l j

bility to be somewhrt variable over the next several days of operation.

j Early in the morning of March 11, 1980, the east side return water h

distribution header on the main cooling tower ruptured.

Large amounts of circulating water spilled over the distribution box near the rup-

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ture onto the ground. The yard drainage system in this araa did not l

have the capability to handle this quantity of water, allowing the i

water level in the surrounding area to reach a depth of several inches.

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Some of this water entered the manhole containing cables and associ-i ated conduits for the circulating water pump system. This water

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damaged several electrical motors of the circulating system. The main i

turbine generator was tripped and the reactor scrammed when it was j

evident that condenser vacuum could not be maintained.

Repairs were made and the reactor was brought critical again on the same day, but i

because of the damage to the circulating water pumps and the loss of

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acceptable feedwater chemistry, reactor power could not be increased above 2% until March 15, 1980.

t The turbine generator was synchronized on March 16, 1980, and load was t

gradually increased to 230 MW on March 18 and remained at that level until March 21, 1980.

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Loop 2 shutdown due to a failed chip in a hot reheat radiation module of the plant protective system on March 21, 1980. The reactor scrammed r

from high hot reheat temperature when attemperation was taken off l

Loop 1 and remained shutdown until March 23.

Low power operation con-tinued until March 25, awaiting cleanup of secondary coolant. On March 26, 1980, the turbine generator was synchronized and electric j

load increased to 225 MW.

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s 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.3 March (Cont'd) i A leaking 1B circulator steam piping flange caused reactor power to be lowered to 50% on March 26.

While 1B circulator was off, lA cir-culator buffer seal malfunctioned.

The 1A circulator and Loop 1 were j

shutdown manually and reactor power decreased to 2%.

The 1A and IB i

circulators were restored to service and Loop 1 was recovered on March 29.

Reactor power was increased to 45%, and the *urbine gener-ator loaded to 140 MWe.

i 1.4 April On April 1,1980, the reactor power was increased from 45% to 60%,

190 MWe, and held approximately at this level pending cleanup of the 4

primary coolant oxidants.

The "D" circulating water pump expansion bellows ruptured and required isolation pending repair.

On April 2,1980, problems developed with the backup bearing water system, which was traced to improperly working control valves.

The problem was corrected and backup bearing water system was returned to service.

l On April 4, 1980, reactor power was being maintained at 68% when total oxidants increased sharply to approximately 50 ppm.

Electrical load was reduced to 195 MR.

The sudden increase in oxidants is believed to have been caused by a malfunctioning helium recovery conpressor.

The buffer flows to all circulators were reduced, and the recovery com-pressors vented. By April 5, primary coolant oxidants were reduced to 40 ppm, with reactor power being maintained at 56%.

During this per-iod,1B circulator buffer knockout pot draining resulted in tripping 1B circulator off line. The 1B circulator was recovered for normal operation. At this time (April 7), it was decided to take 1B circu-lator down to investigate what ef fects it might have on the ability to reduce total oxidants.

On April 8, 1980, while operating at 150 MRe, a loop shutdown was received during an attempt to restart 1B circulator. The loop was recovered, and reactor power was increased to support 65 MWe load on April 9, 1980. Region outlet temperatures were held below 1200*F un-til total oxidants decreased below 10 ppm.

Reactor power was changed r

over the next few days between 30% and 65% as dictated by primary coolant oxidant levels. The 1B and 1C circulators were removed from i

service during this period (April 10 to April 18, 1980) to observe the effect, if any, on moisture ingress. No effect was observed.

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i 1.0 NARRATIVE SID0!ARY OF OPERATING EXPERIENCE' (Cont'd) 1.4 April (Cont'd)

On April la,1980, while operating at 35% power, a turbine trip oc-curred from a spurious signal from the plant protective system while changing out a logic module. The same day, a Loop 1 shutdown occurred when buffer supply was disturbed to Loop 1 circulators by the relief I

action of 1A circulator penetration rupture disk.

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The reactor remained in a relatively low power condition (2% to 10%)

until April 21, 1980, to allow license candidates to complete required Nuclear Regulatory Commission reactor starts, j

Reactor power was raised to approximately 30% on April 23.

On this i

date,1B circulator tripped from seal malfunction problems. The i

circulator was restarted and power raised to 50% until an increase in i

oxidants required lowering region outlet temperature below 1200*F.

t On April 25, a loop shutdown occurred, caused by a faulty plant pro-tective logic module.

The loop was recovered and reactor power was l

increased to approximately 30%.

e The plant was shutdown to one loop operation on April 28, 1980, again due to a malfunction in the plant protective system.

Investigation revealed a failed chip in a logic module. The loop was recovered and load increased to 130 MW.

On April 30, 1980, another loop shutdown occurred when "A" and "B" bearing water pumps tripped of f as a result of construction work being performed in the area of the Loop 1 surge tenk.

Recovery of the loop was accomplished, and the load was increated to approximately 130 MR.

1.5 May On May 1,1980,1B circulator tripped on loss of bearing water due to an upset caused by changing the bearing water y-strainers. The IB circulator was returned to service, the main turbine generator syn-chronized, and power was increased to 52%. primary coolant oxidants then increased above 15 ppm, and reactor power was reduced to 45% and 130 MRe, with average region outlet temperature less than 1200*F.

Radioactivity was detected in the low pressure separator with the source of the activity being 1D circulator buffer return flow, which t

was adjusted to correct the problem.

During this event, activity was also detected in the Reactor Building due to valve packing leaks on the buffer helium dryer.

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l.0 NARRATIVE SLTfARY OF OPERATING EXPERIENCE (Cont'd) 1.5 May (Cont'd)

The plant continued to operate between 45c and 53% over the next seven days with power level dictated by primary coolant oxidant levels. On May 7, 1980, the pelton supply to the Loop 2 circulatars was isolated to repair a steam leak on the pressure control valve piping. Plant conditions on May 8 were as follows; 46% power,135 MRe, primary coolant oxidants greater than 10 ppm, average region outlet tempe ra-ture less than 1200*F. As little progress was being made to reduce total primary coolant oxidants by the purification system, it was de-cided to change out the helium dryer desicant and observe what effect, if any, this change would have on total primary coolant oxidants.

No definite change was observed. Operation continued to be limited by primaqr coolant omddants being greater thaa 10 ppm through Fby 13, 1980.

On luy 13, 1980, #5 feedwater heater developed a tube leak. The secen-dary coolant flow path was routed to the emergency feedwatar header.

Operation continued in this manner through the remainder of this month.

On May 15, 1980, the backup bearing water bearing header was isolated to repair the backup bearing water safety valves.

Reactor power was at approximately 50% and 130 !Me, and continued at that level until

!!ay 24.

At that time, total primary coolant oxidants were 7.5 ppn and power was raised from 50% to 67% over a period of the next three days.

Operation continued at approximately 200 MRe for the remainder of this month.

On May 21, 1980, an on-site public meeting was held with the Nuclear Regulatory Co= mission staff to discuss the Fort St. Vrain Radiological Emergency Response Plan.

Spent fuel shipping started with the first shipment on May 28, 1980.

The helium circulator, which was removed during the January,1980, shutdown, was examined by General Atomic Company at San Llego, Cali-fornia, and confirmed to have a ruptured shaf t seal bellows.

1.6 June Reactor power was 54% with generator at 150 MRe on June 1,1980.

On June 2,1980, reactor power was increased to 60% with generator load of 172 MRe, followed by an increase to 68%, 200 MRe on June 3.

On June 5,1980, purified helium leakage rates of the Loop 2 steam generator penetration approached Technical Specification limits.

A variance was received from the Nuclear Regulatory Commission to in-crease LCO 4.2.9 limits from 400 pounds per day to 700 pounds per day.

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>7-1.0 NARRATIVE SLWRY OF OPERATING EXPERIENCE (Con:'d) 1.6 June (Cont'd)

I On June 11, 1980, reactor power was reduced to 68% and 195 MRe because high ambient temperatures reduced the service and circulating water r

system capability.

On June 12, 1980, with reactor power at 68% and 194 MWe, main cooling tower blowdown was swapped from hot to cold side to comply with EPA i

temperature limits.

l On June 17,1980,1B helium circulator tripped due to high buffer-i mid-buffer, and approximately three hours later, lA circulator tripped j

for the same reason, causing a loop shutdown.

The turbine generator was manually tripped. Activity increased in the low pressure separa-l tor as did moisture in the primary coolant.

Reactor power was reduced to 2% to recover Loop 1.

The problem was traced to a ruptured dia-i phragm on the pressure dif ferential transmitter for the 1B circulator i

l main drain valve.

Loop 1 was recovered and reactor power was increased i

to 5%.

l Reactor power was held at 10%, with 1A,1C, and ID circulators oper-1 ating and both loops in service on emergency feedwater on June 18.

On June 19, reactor power was increased to 25% and the turbine placed on line.

Heater #6 and the normal feedwater header were returned to service after repair of a leaking tube side vent valve.

On June 20, lA circulator tripped causing Loop 1 to shutdown. Power was reduced to approximately 10% and held.

Moisture in the primary coolant increased in excess of 10' pm, and activity was noted in the

.l low pressure separator. Power was reduced to 2% to recover Loop 1.

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The operable main drain differential pressure transmitter from the 1A helium circulator was installed on IB helium circulator.

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Primary coolant moisture levels decreased, and Loop 1 steam generator was returned to service on June 21, with reactor power at 3.5% and moisture down to 19 ppm. Power was increased to 8% and orifices were j

set.

Primary coolant moisture leveled out at 40 ppm.

f Reactor power was reduced to less than 2% on June 23, and Loop 2 was shutdown to repair leaking valves.

Power was subsequently reduced to 10-3% with condensate cooling Loop 2.

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Valve ** pairs were completed June 24, and Loop 2 was recovered.

t On June 27, with the reactor at 7% power, the main drain differential pressure transmitter was re-installed on lA circulator. Primary l

coolant moisture increased rapidly when lA circulator was brought up to i

speed.

Reactor power was held steady at 8% awaiting primary coolant l

moisture reduction.

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1.0 NARRATIVE StiMMARY OF OPERATING EXPERIENCE (Cont'd) 1 1.6 June (Cont'd)

On June 29, reactor power was increased to 20%, and on June 30, the

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turbine generator was synchronized and power increased to 29% and 50 MWe.

Reactor power was increased to 45% with a turbine generator

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load of 125 MWe, but was later reduced due to an increase in primary coolant moisture.

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1.7 July

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On July 1,1980, with the reactor operating at 45% power (125 MWe), a gradual loss of vacuum necessitated a turbine generator load reduction l

during the period required for location and isolation of the condenser t

leak. A leaking valve was discovered to be the cause of the vacuum problem. Af ter condenser vacuum was recovered, the turbine generator load was increased to the previous level of 45% (125 MWe).

i Plant operation continued at approximately 45% and 125 MWe to hold the j

j core region outlet temperature average below 1200*F, cue to primary j

j coolant oxidant levels greater than 10 ppm. On July 4, 1980, Table 1

Mountain Load Dispatch requested a 30 MRe reduction in turbine gener-ator output. This resulted in a reactor power reductica to approxi-i mately 37 i

On July 7,1980, reactor power was increased to 65% (145 MRe), re-sulting in an increase of primary coolant oxidants to 55 ppm. The

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core region outlet temperature was greater than 1200*F at this power level; therefote, af ter experiencing the oxidant spike, reactor power was reduced sufficiently (approximately 33%) to obtain less than 1200*F outlet temperature.

As a result of this power reduction, the feedwater control system became somewhat unstable, causing a steam turbine trip of all four circulators and a two loop trouble scram.

The reactor was brougnt critical on July 9,1980, and operated at a r

nominal 2% until July 17, 1980. The delay in escalation of power was l

due to the inabilit" to complete a required annual Surveillance Test I

on the emergency diesel generator set 1A.

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this surveillance, a leaking heat exchanger was discovered and was re-placed, but the main problem involved the governor control system and I

this took several days to resolve. Reactor power was increased to 8%

on July 17, 1980, but shortly thereafter, a leak in the Loop 1 secon-dary coolant system necessitated shutting down Loop 1 for repairs and a j

return to 2% power.

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SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.7 July (Cont'd)

Upon completion of the Loop 1 repairs, the reactor power was increased to 5% on July 20, 1980, 23% on July 21, and 29% on July 22, at which time the turbine generator was synchronized and loaded to 125 MRe as power was increased to 45%.

During this gover rise, a turbine trip occurred when the bypass valves inadvertently opened, causing low steam pressure at the main turbine. The main turbine generator was immediately returned to wervice at 125 MRe.

Plant operation for the remainder of July,1980, continued in the range of 45% to 57%.

Reactor power levels were principally dictated by grimary coolant oxidant levels.

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l.8 Augus t At the beginning of this month, the plant was operating at a reactor power level of approxmately 50% and 135 MRe.

The secondary coolant r

flow path was established through the emergency feedwater header due to feedwater heater #5 tube leaks. The average core region outlet temp-erature was maintained below 1200'F, as the primary coolant oxidants were greater than 10 ppm.

At approximately 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months on August 1, 1980, reactor power was increased to 52%, resulting in an average core outlet temperature of 1220.F, as primary coolant oxidants had been re-duced to a total of 8.8 ppm.

Operation continued with these con-dicions until 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months on August 4,1980, when a plant protective system action resulted in a reactor scram, steam turbine trip of all four circulators, and Loop 1 shutdown. The cause of the above upset was unsreble feedwater control caused by the feedpump speed control system.

i Preparations for a reactor restart were made almost innediately, and criticality was attained at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on August 6, 1930. On August 6, reactor power was increased to 27%, and on August 7, 1980, the main turbine generator was placed in service.

Reactor powe r level was in-creased to 47%, but a load decrease was necessary to hold the Reactor Building temperatures within acceptable limits, as the heat load ex-ceeded the capability of the chilled water system. This problem was, for the most part, due to the undersizing of the service water oiping i

supplying the Reactor Building chillers. An additional condition that developed, which also limited plant operation, was nhe presence of a bad bearing on "A" circulatics water pump.

This condition, coupled with the hot weather, caused high back pressure in the condenser, thus limiting turbine generator load.

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. 1.0 NARRATIVE SUFCfARY OF OPERATING EXPERIENCE (Cont'd) 1.8 August (Cont'd)

Plant operation continued as dictated by conditions described above until August 12, 1980, when a turbine runback occurred as a result of an improperly set vacuum switch.

This switch action is believed to have caused an upset in the feedpu=p control portion of the secondary coolant control system.

Recovery from the turbine runback was made, and plant conditions remained stable until August 16, 1980.

On August 13, a public meeting was held with representatives of FEMA, Region VIII to discuss the State Radiological Emergency Response Plan.

On August 16, 1980, a hydraulic oil leak developed on the Loop 2 cir-culator stear turbine bypass valve (PV-2244) which necessitated iso-lating Loop. hydraulic oil system and Loop 2 group 2 secondary coolan :

loop.

Reactor power was also reduced to 2%, and the reactor scrammed as prescribed by the Emergency Procedures. During the shutdown for re-pair -f the hydraulic oil leak and oil cleanup, the leaking "B" boiler feedpump normal feedwater header isolation valve was repaired, along with repair of "A" boiler feedpu=p speed control. Af ter completion of this work, preparations were made to bring the reactor critical, and criticality was achieved on August 18, 1980, at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months .

Reactor power was increased to 28%, and the turbine generator synchro-nized at 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months on August 20.

As soon as feedwater chemistry was within specification, the power level was increased to 57% and turbine generator loaded to 1601Me.

On August 25, 1980, during the piping snubber surveillance, it was dis-covered that 12 snubbers were inoperable.

Per Technical Specification requirements, enese problems must be corrected within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or an c rderly plant shutdown is required within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months af ter expiration of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

During this grace period on August 29, 1980, a problem developed with the electro-hydraulic control system for the main tur-bine generator with a loss of i 24 V power.

The main turbine generator continued to operate on the permanent magnet generation. At 1335 hours0.0155 days 0.371 hours 0.00221 weeks 5.079675e-4 months , while attempting to determine the cause of the loss of i 24 V posar, the plant electricians inadvertently caused a turbine runback.

The resultant transient caused e :irculator in each loop to be tripped by plant protective system action.

The turbine generator was manually l

tripped at this time.

Since the 12 inoperable snubbers discovered on Augus t 25, 1980, could not be repaired within the allotted time, the

" plant shutdown" planned for September 1,1980, was initiated.

1.9 September On September 1, with the reactor shutdown, the prestresseu concrete re-actor vessel was depressurized to O psig and Loop 1 steam generators and circulators ware cleared for maintenance.

Core cooling continued with Loop 2 steam generators and circulators discharging heat to the main condenser.

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. 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIE! 3 (Cont'd) 1.9 September (Cont'd)

On September 9, all core forced cooling was stopped to verify core heat rise calculations.

Calculations proved to be adequately conservative and core cooling was re-established.

On September 13, the bypass flash tank drains were directed to the de-cay heat exchanger, and on September 14, the condenser was taken out of service for maintenance.

On September 15, core forced cooling was stopped for approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to replace valves on the 150 psig header and on the condensate pump s. The main condenser was returned to service on September 16.

On September 17, core forced cooling was stopped for about 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for instrument calibration.

^n September 18, Loop 1 steam generator and circulators were placed in service and Loop 2 was shutdown.

Pressurization of the prestressed concrete reactor vessel was begun, and on September 20, the helium purification train was placed in ser-vice at approximately 100 psig.

On September 24, core forced cooling was stopped for 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months to work on the Loop 1 main steam power operated relief pilot valve.

On September 25, Loop 2 steam generator and circulators were placed in service, and Loop 1 was shutdown again to complete work on the qilot valve.

On September 26, Loop 1 was placed back in service, and on Septem-ber 27, af ter work was complete on snubbers and the required surveil-lances were complete, the reactor was taken critical.

Ecolochem arrived on site to make-up water to the condensate system, and on September 28, reactor power was increased to 2% to facilitate water cleanup. Power remained at this level through the end of the month.

1.10 October With reactor power at 2% following the scheduled maintenance period, power was increased to Sc.

The increased operating temperatures aided the cleanup of feedwater and primary coolant impurities.

An internal oil leak developed on lA helium circulator speed control 5

valve, and the solenoid valves were repaired.

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i 1.0 NARRATIVE SUK!ARY OF OPERATING EXPERIENCE (Cont'd) 1.10 October (Cont'd) i i

On October 4, a pressure switch (PS-11227) failure resulted in inter-l space pressures equalizing with primary coolant pressures. The pres-l sure switch was repaired, and reactor power was increased to 8%.

On October 8, the solenoid valves of 1A helium ~ circulator speed valve developed additional leaks and were again repaired.

l A power level of 23% was attained cn October 9, and the turbine gener-l ator placed on line.

The emergency feedwater supply to the helium cir-culators was removed from service to fix a small leak. The leak was repaired and emergency feedwater restored to service.

Reactor gower was increased to 49%.

on October 10, while the base mouncing of the turbine generator main exciter bearing mount was being tightened, due to vibration problems, i

and an exciter control box was accidentally struck, causing the turbine generator to trip. The spike in : ltage caused a trip of #3 non-inter-ruptible bus inverter.

i On October 11, the #3 non-interruptible bus inverter was placed in service, and the turbine generator was placed on line. Reactor power was increased to 27%.

On October 12, reactor power was increased to 60%, but later reduced to 40% due to an increase in primary coolant contaminants.

On October 14, reactor power was neduced to 29% to enable repair of buffer helium dryer valves.

Reactor power was raised to 57% on Octoler 16, following repair of the dryer valves.

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Due to a rise in primary coolant impuritf as to greater than 10 ppm, reactor power was reduced on Octcber 21 11 order to lower average core outlet temperatures to less than 1200*F.

On October 22, a Leop 1 shutdown occurred while testing ultrasonic pipe rupture detectors. Loop 1 was recovered and electric power gener-l ation was resumed.

On October 23, reactor power was reduced to 2% to repair hydraulic oil leaks on System 91 accumulator blind flange seals of Loop 1.

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On October 24, the hydraulic oil seals were repaired.

Reactor power was raised to 5%, at which time a reactor scram occurred during cali-3 bration of hot reheat steam temperature elements. The reactor was brought to criticality and raised to 2% power.

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. 1.0 NARRATIVE SLW!ARY OF OPERATING EXPERIENCE (Cont 'd) 1.10 Ocpober (Cont'd)

On October 25, power was increased to 28% and electric generation re-svaed.

On October 30, reactor power was increased to 49%. Average core out-let temperatures were held to less than 1200*F, due to primary coolanc oxidant levels in excess of 10 ppm.

1.11 November At the beginning of the month, reactor power was 50%, and the turbine generator load was 140 MW, with the average core region outlet temp-erature being maintained at less than 1200*F. Power was limited be-cause of a high level of primary coolant oxidants.

Plant conditions remained the same until November 5, 1980, at which time the total oxidants had decreased to approximately 6.6 ppm, and power escalation was resumed up to 60% reactor power with an electrical load at 170 !M(s.).

Primary coolant oxidants started trending upwards as a resule of the increase in reactor power.

On November 5,1980, the Etintenance Department started testing several vent : Lack snubbers.

The snubbers were inoperable while they were re-moved for testing, and no further power increase was made until all the snubbers were returned to service.

The vent stack snubbers were returned to service on November 7,1980, at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months . During this period, primary coolant oxidants decreased enough to allow power escalation to be resumed. Shortly thereafter, during an automatic transfer of buffer helium dryer towers, a high pressure condition occurred in the "off line" tower indicating leaking valves. The leakage between towers was nraced to a regeneration valve (HV-21352).

The problem was corrected, and reactor power was main-tained at the same level until the morning of November 12, 1980, when a power reduction to 40% was made in preparation for reactor core fluc-tuation testing.

The next three days were spent at reactor power levels from 40% to 70%

with various core orifict configurations to satisfy test criteria.

Testing was completed c.n November 15, 1980, and resulting data for-warded to General Aton.c Company for analysis. At the ccepletion of testing, reactor power and turbine generator loads were increased to 66% and 208 MWe respectively. The dryer regeneration valve (HV-21352) again failed to close qroperly, causing a further increase in prim:Iy coolant oxidants. The problem was corrected by stroking the vcive.

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. 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.11 November (Cont'd)

By November 18, 1980, primary coolant chemistry had improved suf fici-ently to allow reactor power to be increased to 69% with a turbine generator load of 220 MR.

These conditions were maintained until the evening of November 24, 1980, when a power reduction was initiated to repair an oil leak on lA circulator steam speed valve operator (SV-2105). The 1bintenance Department was able to repair this leak by early morning of November 25, and reactor power and turbine generator loads were returned to their previous levels.

Turbine generator load was again reduced on November 27, 1980, and the generator taken off the line to repair a steam leak in Loop 1, steam generator / hot reheat header drain line.

During the power reduction, the Loop 2 preflash tank pressure control valve failed to operate prop-erly, causing the Loop 2 main steam safety valves to relieve. The problem was due to a loss of ccumulator pressure on the valve operator and was corrected with the use of the main steam bypass valve to main-tain pressure in the interim period.

Reactor power continued to be reduced to approximately 2%, at which time Loop 1 reheater was isolated and drained for repair.

Loop 2 re-heater and the evaporator, economizer, and superheater sections of each steam generator were maintained in service with one helium circulator in each loop at a "self-turbining" condition.

The repair took approxi-mately eight hours to complete. Loop 1 reheater was restored to ser-vice and power escalation commenced.

The return to 69% power went verf smoothly with only a slight delay at 30% power te put the main turbine generator on line and to verify the acceptabi'.ity of primary coolant and feedwater chemistry. Reactor power reached 69% and a turbine generator load of 218 MW on the evening of November 30, 1980.

1.12 December At the beginning of the month, the plant was operating at 69% power and generating 215 MRe.

It was necessary to bypass #5 feedwater heatar due to suspected tube leaks. Plant conditions remained the same until power was reduced to 41% on December 12, 1980, to conduct fluctuation tests.

Upon completion of testing, moisture ingress into the primary coolant system required the generator to be taken off line, and reactor power was reduced to 8%.

Subsequent investigation found no source of moisture ingress.

Reactor power was gradually increased to 68% as pri-mary coolant oxidants permitted. Plant conditions remained the same until December 26, 1980, when power was reduced to 2% to repair a feed-water leak on a Loop 2 feedwater trin valve. Af ter repairs, the re-j actor power was increased to 30%, and the generator was placed on line.

I I

i

+

[

t 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) i 1.12 Dpcember (Cont'd) l I

Oa December 27, 1980, a reactor scram on high reheat steam temperatures l

cccurred due to control system problems experienced while increasing i

turbine load.

l The reactor was taken critical the same /

7, the generator placed on line, and reactor power gradually increased to 68% by December 28, 1980.

[

l On December 29, 1980, a faulty position transmitter on the Loop 2 cir-culator steam bypass valve caused a Loop 2 shutdown and turbine gener-5 ator trip. Loop 2 was recovered, and the generator was placed on line af ter the transmitter was repaired.

During the turbine generator load increase, #2 reheat intercept stop i

valve became jammed in the mid position.

On December 31, 1980, in an

{

effort to move the. valve, the generator load was reduced to 10 MRe.

r The stroke test failed to free the valve so the reactor was scrammed at I

this time, and the turbine generator tripped.

1.13 Safety Related Maintenance i

i Safety related maintenance not associated with plant outages or power reductions is tabulated on the following pages.

l I

1 I

i

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f I

L I

!I s

E i

r i

m.., _ _ -,

S ICNIl'1 CANT MAI f(I'IN ANCE;

SUMMARY

TlHE ILENTIFICA-FEQUI RED EFFECT (W TION NUMBER SYSTEft/

NATURE OF inM SAW.(WERAlltH AND DATE OME'a t4ENT CAUSE OF ttAI.FINCTit N RESUL1S OF ttAl. FIN (TIEW MAIN 1f. NANCE CORNEtTIVE Af* TION Cs etPI.ETION OF 111F RF.AC1DR 78-2-231 SV-2110 Normal Wear Valve leaks through Co r rec-Replaced trim set.

I Day None 9-24-80 when controller calls tive for it to be closed.

78-8-518 V-7295 Normal Wear Valve leaked through.

Co r rec-Replaced valve.

8 Ilours None 11-6-79 tive 78-8-521 V-7296 Normal Wear Valve leaked through.

Co rrec-Replaced valve.

16 I?ours None 11-4-79 tive 79-4-373 V-4642 Normal Wear Valve leaks through.

Correc-Replaced valve.

4 Ilours None.

11-30-79 tive 79-5-843 IIV-22i?

Normal Wear Valve leaked through Co r rec-Rebuilt poppet 2 Days None 2-20-80 excessteely.

tive block and cylinder.

79-7-634 IIV-2224 Normal Wear Leals between cylinder Correc-Installed new "O" 10 llours None i

2-20-80 and bottom block, tive rings.

79-8-146 IIV-2224 Norma! Wear Excessive leakage.

Correc-Repaired seat and 2 Days None 11 20-79 tive disc.

79-8-487 V-2256 Bad seal ring and Valve leakage.

Co rrec-Replaced seal ring I Day None 12-6-79 hinge pin on V-tive and hinge pin.

2256.

79-8-501 IIV-2217 Valve leaked Leaking valve.

Correc-Repaired seat and Approxi-None 12-6-79 through due to tive disc.

raately seat and disc 10 llours wear.

79-8-520 V-72102 No rmal Wea r Valve leaked through.

Co rrec-Replaced valve.

18 Ilours None 11-6-79 tive 79-8-521 V-72103 Normal Wear Valve leaked through.

Co rrec-Replaced valve.

16 Ilours None 11-4-79 tive 79-9-13 ilV-2224 Normal Wear Bonnet seal leaks, Correc-Replaced bonnet 2 Days None 11-20-79 tive seal.

L

e SIGNIFl_ CANT MAINTENANCE SU! DIARY i

TIME IDENTIFICA-RD)lfl RED EFFECT (W TION NUMllER SYSTEll/

NATURE OF HaR SAFE OPERATION Afin DA1E CO;/Ot4E N T CAllSE OF mal.FttHTluN llid til!!b OF HAI. Fit 4(Titti MAINTE: NANCE O)RRF(TIVE ACTitel Cittri.ETI ON OF Tile REM"nHt 79-9-30 IIV-2224 Normaal End of 011 leaks at operator.

Co rrec-Replaced all "0"

2 Days None 11-20-79 life.

tive rings.

79-9-116 SV-2112 Normal Wear Rod end seal leaked.

Co r rec-Replaced seal.

2 Days None 2-2-80 tive 79-10-101 FE-1122 No rmal Wea r Incorrect flew indi-Co rrec-Replaced flow ele-3 Days None 6-25-80

cation, tive ment with spare.

79-10-286 IIV-2215 Seat and disc Valve leaked through.

Co rrec-Repaired valve's App ro xi-None 12-12-79

wear, tive seat and disc.

mately 10 Hours 79-11-109 IIV-2217 Seat wear in 5-Valves leaked through.

Correc-Repaired seats.

Approxi-None 11-28-79 valve manifold, tive mately 3 Ilours u

e 1

79-11-269 V-21115 Bad disc and Valve leaking through.

Correc-Replaced disc and 8 Ilours None 11-28-79 bent stem.

tive straightened stem.

79-11-270 V-21116 Bad valve disc.

Valve leaking through.

Co rrec-Replaced disc.

1 Day None 11-28-79 tive 79-11-308 IIV-21205-2 Bad coil in llV-Lights on llS-21205, Correc-Replaced llV-21205-1 Ilour None 11-21-79 21205-2.

21193, 2189-1, and tive 2.

2189-2 did not operate when circulator was tripped and brake and seal set.

79-12-401 CTI-B R4 Bad chip.

Low voltage at input Correc-Replaced chip Z-9.

I flour None 12-19-79 discovered during tive test.

79-12-449 IIV-9 316 Bad air solenoid Air solenoid valve to Co rrec-Replaced solenoid 1 Day None 12-27-79 valve.

IIV-9316 leaking, tIve valve.

79-12-493 S-7540 Normal Wear Leaky tubes on standby Correc-Plugged leaky 1 Month None 7-3-80 diesel generator air tive tubes.

L ha nal ina.un t i x __...

{

SIGNIFICANT ttAINTENANCE

SUMMARY

IlWNTI FICA-Rit}UI RFil FFFECT til TION NUMhER SYSTt.fi/

NATilRE OF FOR SAR 4fERATlf te At4D DA1E COTS'4 N4F NT CAtKE OF P.U.F194CTION RESHI.TS tlF HAI.Ht4CTitre ttu NTt. NANCE CORRFCTIVE ACTION Ca rD't.ET i s W4 OF T1tE REA("tolt 79-12-526 MIT-1120 Broken fitting.

MIT-1120 thermocouple Correc-Replaced thermo-3 llours None 12-26-79 failure light lit.

tive couple fitting at MM-1120 head.

79-12-532 M?t-1120 Bad reflected MM-1120 would not Correc-Replaced light 1 Day None 1-9-80 and source light servo and was icing tive guides and pre-guides and re-up, amp.

flected Ifght pre-amp.

79-12-533 PDIS-21397 plugged sense Faulty IB circulator Co rrec-Blev down instru-1 Day None 12-26-79 line and had Y strainer differ-tive ment sense lines snubbers.

pressure gauge.

and installed new snubbers.

79-12-545 Pall-1107-Bad alarm card.

Alarm Pall-1107-10 on Correc-Alarm card re-2 Ilours None 5

1-3-80 10 I-21C would not clear.

tive paired.

p 79-12-554 Fall-21378 Bad alarm card.

Guard helium flow high Correc-Replaced alarm 1/2 None 12-29-79 alarm energized on IC tive card with spare, llou r circulator.

79-12-573 PV-22167 Noriaal Wear Valve leaks through.

Correc-Repaired valve in-8 Ilours None 9 '.3-80 tive ternals.

79-12-574 FIS-21378 Bad alarm card.

Guard helium flow high Co rrec-Repaired alarm 1/2 None 12-28-79 al n r.1 energized on 1C tive card.

IIour circulator.

79-12-576 IIV-9 316-1 Bad solenoid.

Air blowing out of IIV-Co rre c-Replaced solenoid 2 Ilours None 12-27-79 9316-1 and buzzing.

tive valve.

79-12-586 ilV-21205-2 Bad valve.

IB circulator brake Correc-Replaced llV-21205-1 Day None 12-28-79 and seal bottle pres-tive 2 with a rebuilt sure decrease.

valve.

79-12-602 MIT-1120 Bad reflected MIT-1120 would not Correc-Replaced light 1 Day None 1-10-80 and source light se rvo.

tive guides and pre-amp.

guides and re-flected light 6

.. p re-a mp.

SIGNIFICANT MAINTENANCE

SUMMARY

TlHE IlJLNTI FICA-REQUIRED EFFECT (M TION NUhBER SYSTEft/

NATUNE OF n)R SAFE UPERATI(M AND DATE CoWONFNT CAllSE OF HALFINCTION RESilLT!i OF HAl Fit 4CTitri MAIN 1ENANCE CORRECTIVE ACTION CitrLETION OF 111E RFA("}UR 79-12-644 MIS-1115 Bad disc in PDV-MIS-1115 mirror temp-Correc-Replaced valve L Day None 1-9-80 2549.

erature below setpoint tive disc.

and constantly de--

creasing._

79-12-711 P-9106X Broken flex con-Flex conduit to motor Correc-Replaced flex con-2 Ilours None 1-2-80

duit, for P-9106X broken.

tive duit.

79-12-714 Ilv-2254 Worn "0" rings.

IIV-2254 flange Icakage Correc-Installed new "O" 2 Days None 1-4-80 inside protective tive rings in inlet cover.

piping to poppet blocks.

80-1-4 V-2256 Bad seal.

Emergency' condensate Correc-tioned pin hole and 1 Day None 1-4-80 header check valve tive installed new seal.

leaking at pin.

,8 T

80-1-8 IIV-21416-1 Broken tubing.

Air supply tubing to Correc-Replaced broken 4 11 w,rs None 1-2-80 IIV-21416-1 broken.

tive tubing.

80-1-18 Region 2 Bad alarm card.

Ilopper pressure high Correc-Replaced alarm 2 llours None 1-4-80 CRD light would not come on tive

card, when tested from panel.

80-1-27 IIV-31207 Bad valve seat.

IIV-31207 not operating Co rrec-Replaced valve 1 Day Nono 1-5-80 properly, apparently tive seat, cleaned stem due to bad seat, and disc, and re-placed "O" rings.

80-1-49 IIV-2215 Normal Wear Valve leaked by.

Correc-Rebuilt valve.

1 Day None 2-20-80 tive 80-1-65 CR-173-1A Bad chip.

Relay CR-173-1A Correc-Put in spare XCR.

2 llours None 1-9-80 sticking.

tive Replaced Q-2.

80-1-73 BFS-219E Leaky snubber Snubber leaking oil.

Correc-Repaired leak, 4 Ilours None 1-8-80 and loose fit-tive tightened fittings, tings.

b

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.4me s

s-ge.

e

-s us

-T**-

F-

-'t--wa9

-M--

T-w--r-

CTC g- * * - --- _ + -

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SIGNIFICANT MAlyrENANCE hUMMARY l

T IPfE IICNTI FICA-REQUI RFIJ t.i tFCT 884 TRON NUPtHER SYSTFJi/

NATUFE OF D)R S AR opt.RA TION AND IlATE COPIPuNENT CAlt;E OF HAl.FIINCTION RESUI.TS OF HAI.HRH'Titt'.

Pul N I'E N ANCE CORRECTIVE ACTION CIWFl.ETION OF IIIE REM" TOR 80-1-81 B FS-218E Snubber leak, Snubber leaking oil.

Correc-Repaired leak, 3 llours None 1-9-80 loose fittings.

tive tightened fittings.

80-1-104 PV-2229 Seat and disc Valve leaked through.

Co rre c-Replaced and re-

\\pproxi-None 1-25-80

wear, tive paired parts, aately 10 llours 80-1-105 PV-2230, Worn seats and Valves leaked through.

Co rrec-Repaired or re-

\\pproxi-None 2-15-80

22130, discs.

tive placed parts.

nately 22154 10 llours 80-1-152 llV-222 3 Normal Wear

1. caking oil.

Correc-Rebuilt ope ra to r.

? Days None 2 80 tive 80-1-160 PS-11234 Instrument Drif t Trip out of specifi-Co r rec-Replaced switch 1/2 None 2-9-80 cation.

tive and recalibrated.

llour 80-1-168 IIV-2217 Normal Wear Valve leaked through.

Co rrec-Rebuilt valve.

2 Days None 2-20-80 tive 80-1-193 FV-21333 Normal Wear Valve leaked through.

Correc-Lapped valve seat. B llours None 9 80 tive 80-1-203 PDV-2551 Disc and seat Valve leaked past.

Correc-Replaced disc.

\\pproxi-None 1-28-80 wear.

tive aately

'. Ilours 80-1-224 C-820lS No rmal Wea r Machine was noisy.

Co r re c-Overhauled com 5 Days None 2-7-80 tive pressor.

80-1-240 llV-212 36 Faulty "O" ring Valve would not open.

Corree-Replaced "O" ring.

\\pproxi-None 1-25-80 in operator.

tive nately 2 Ilours 80-1-293 VSS-117 Normal Wear I. caking oil and inoper-Co r re c-Replaced with an-1 Day None 2-18-80 able snubber.

tive other snubber.

80-2-22 V-91454 Normal Wear P-9106X could not main-Correc-Replaced.

3 llours None 2 80 tain system pressure.

tive

SIGNIFICANT MAINTENANCE

SUMMARY

I TtHE I Dt'NTI FICA-R):Qttl REI)

F.FFt cT UN TION Nt!HBER SYSTEll/

NATillE OF H)R S AIT, (trFRAf ten AN11 DA1E O WS*HNENT CAllSE OF HAI. FUNCTION EESUI.TS OF MAI.FINCTitti HM N TEN ANCF CtiRRECTIVE ACTION Cit 9'IETION OF 11E MANK 80-2-120 P-910SX Normal Wear Ilydraulic leak at Co r rec-Rebuilt pump.

2 Days None 2 80

pump, tive 80-2-168 C-8203 Solenoid and "C" inst rument ai r com-Co r rec-Replaced solenoid 3 llours None 2-19-80 pressure switch pressor would not load.

tIve and pressure failed due to switch.

normal wear.

80-2-213 PV-22129/

Normal Uear Valves leaked through.

Co r rec-Replaced seats, 12 llours None 2-23-80 22153 tive plug, and stem.

80-2-223 C-8203 Normal Wear Air compressor inoper-Co r re c-Rebuilt the air 3 Days None 3-5-80 able.

tive comp resso r.

80-2-295 3-2115 Increased resis-Lost speed indication Correc-Replaced cable 2 llours None 3-19-80 tance in con-for 115 ci rculator tive connector and re-23 nector.

wate,r turbine drive balanced circuit.

7 (1 channel only).

80-2-305 P-2105 Normal Wear Seal leakage excessive.

Correc-Replaced pump seal. 16 Ilours None 9-25-80 tive 80-2-324 V-22184 Normal Wear Upstream relief valve Correc-Replaced gasket.

1 Day None 7-20-80 leaking.

tive 80-2-332 INP Logic, Failed chip 248 IMP light would not Correc-Replaced chip.

1/2 None 2-29-80 in module - Nat-clear.

tive Hour ural end of life.

80-2-338 P-9101X Shaft out of Pump motor Lurned up.

Co r re c-Replaced motor.

2 Days None 3-3-80 alignment.

tive 80-3-44 K-9201 Faulty control "A" emergency diesel Correc-Replaced control 2 Ilours None 3-3-80 panel (Woodward generator would not tive panel with spare, 2301).

load prope rly.

80-3-61 IIV-222 3 Normal Wear oil leak f rom operator. Co rre c-Replaced "O" rings 2 Days None 3-5-80 tive in operator.

SIGNI FICANT MAINTENANCE SU!d!ARY I fit.NTI FI CA~

REtFil RFD FFtIcT eel TION NUMBED SYSTEn/

NATURE OF IDR S A DY Ort.RAllelN AND DATE CO?t'llNFNT CAlfSE OF HAI. Fit 4CTION RESUI.TS OF mal Fit 4CTIE1N HAlN1LNANCE OiRRECTIVE ACTION O t1PDITitti OF 11tE RFAC111R 80-3-95 IIV-2251 Normal Wear Valve leaks at seal Correc-Replaced seal ring 150 None 10-8-80 ring.

tive and honed seating flours surfaces.

80-3-107 IIV-22222 Normal Wear Valve leaked.

Co rrec-Replaced seat and 4 Ilours None 6-23-80 tive gaskets.

80-3-122 TDS L-22105 Had chip / normal Single channel trip Co rrec-Replaced chip.

2 llours None 3-10-80 end of life.

for reheat t empe ra ture tive d i f fe ren t ial.

80-3-125 llV-2215 Normal Wear Valve leaks through.

Corree-Repaired valve 96 Ilours None 10-8-80 tive seat.

80-3-142 FE-111/

Normal Wear Moisture monitor flow Correc-Replaced flow ele-8 Ilours None 12-19-80 element failed.

tive ment.

,8, u

I 80-3-126 IIV-21353 Normal Wear Valve leaks through.

Correc-Replaced disc.

3 llours None 3-9-80 tive 80-3-140 TE-22144 Shorted out due The tempernture chan-Co rree-Replaced element.

2 llours None 3 80 to normal wear.

nel failed down scale.

tive 80-3-141 MM-1122 No rmal Wea r Insufficient flow for Co rrec-Replaced flow ele-Approxi-None 6-25-80 moisture monitor.

tive ment and cleaned mately unit up.

2_ Days 80-3-188 SM-21172 Normal Wear Lost one speed channel Correc-Repaired had con-3 llours None 3 80 for circulator trip.

tive nection at pin 24 of SH-21172.

Re-placed cable.

80-3-216 K-9203 Normal Wear "A" emergency diesel Co r rec-Replaced bad alarm 2 Ilours None 4-1-80 generator high oil tive ca rd.

temperature alarms spuriously.

80-3-224 PV-21244 Normal Wear Valve leaked through.

Co rrec-Rebuilt valve seat 16 Ilours None 8-27-80 tive and disc.

Q SIGNIFICANT MAINTENAiCE

SUMMARY

TIME

!!ENTI FICA-REQUIRED EFFECT ON TION NUMBElt SYSTEHf NATURE OF FOR SAFE OPERATION AND I) ATE OWS'ONENT CAttSE OF HAI.FINCTION RESUI.TS OF HAl.FINCTidN MAINTENANCE 0)RRECTIVE ACTION Cotfl.ETION OF 71tE REA(,70R 80-3-271 S C-2111 Normal Wear Loss of circulator Co rrec-Repaired con-1 llour None 3 80 speed si gnal, tive nection.

80-3-232 V-82473 Normal Wear Air compressor C-8203 Co rrec-Valve replaced.

4 Ilours None 3-14-80 inoperable.

tive 80-3-247 SV-2111 No rmal e..d o f Valve went closed and Co r rec-Replaced solenoid.

2 llours None 3-16-80 li fe fo r a di -

would not open.

tive rectional sol-enoid.

80-3-334 V-9172 Normal Wear Valve inoperable.

Correc-Replaced valve Approxi-None 7-2-80 tive stem and handle.

mately 3 Hours 80-3-343 PV-21243/

Normal Wear Valve leakage on PV-Co rre c-Replaced 2" valve 16 Hours None e',

5-16-80 21244 212/ 3 and 21244.

tive trim with 1 3/8" Y

t valve trim.

80-3-344 IIV-2303 Overload os Valve would not oper-Co r re c-Replaced overload.

Approxi-None 6-10-80 breaker s

-2te.

tive mately 2 Ilours

,._ _ -- 9 --

80-3-347 IIV-2302 Normal year Valve would not close.

Co r rec-Rewound operator 32 Ilours None 9-5-80 tive motor and replaced position switch.

80-3-348 MM-1122 Norinal Wear Low sample flow indi-Correc-Replaced with 3 Days None 6-27-80 cation.

tive' spare.

i 80-3-377 P-2109 Normal Wear Large leak in mechani-Correc-Repaired seal.

1 Day None 4-2-80 cal seal on emergency tive booster pump.

80-3-378 P-2110 Normal Wear Pump carrier bearing Co rree-Replaced bearings, 18 Hours None 4-9-80 making excessive noise.

tive seals, and cask.

80-3-382 1A Diesel Normal Wear Unit remained running Correc-Replaced relay.

2 llours None 3-25-80 Gene ra tor af ter being shutdown tive 6

from Control Room.

SIGNIFICANT MAINTENANCE

SUMMARY

~

TIME I DENTI FICA-REQUIRED EFFECT ON TION NUMBER SYSTEn/

NATURE OF FOR S AW Ol'ERATilti AND DATE COMhWD.NT rAllSE OF HAl.FtNCTION REStil.TS OF MALFtHCTION HAIN1ENANCE rORRECTIVE ACTION O RG't.ETI ON OF 'nlE RFACTOR 80-3-431 C-2102 Normal Wear Steam leak at circulr.-

Correc-Installed new flex 27 llours None 3-29-80 tor flange.

tive gaskets.

80-3-433 PV-21243 Normal Wear Leakage through PV-Co rrec-Replaced trim in 4 llours None 5-16-80 21243.

tive valve.

80-3-435 IIV-21352 Normal Wear Valve leaks.

Co r rec-Replaced teflon 4 flours None 3-28-80 tive valve seat.

80-3-436 RIS-93252-Normal end of No fail light out.

Correc-Replaced Al on de-2 Ilours None 3-28-80 11 o f life, tive tector pre-amp.

80-3-463 C-8201S Normal Wear 1B instrument air com-Correc-Performed 5-year 2 Weeks None 4-16-80 pressor noisy.

tive inspection.

Re-built and repaired parts as necessary.

4 s

c 80-3-464 FE-1117 Normal Wear Flow element failed.

Correc-Replaced flow ele-8 Ilours None 4-8-80 tive ment.

80-4-19 CT-2A2 Normal end of Low Input voltage on Correc-Replaced Z-41.

2 llours None 4-3-80

_l i fe,

chip.

tive 80-4-61 SS L-21167-Normal end of Switch would not t ri p Correc-Replaced A-101 amp-3 Ilours None 4-5-80 2

li fe.

co rrec tly.

tive lifier and Q-102 transister.

80-4-62 CC-2A1 Normal end of Low input voltage on Co rrec-Replaced Z-43 log-2 Ilours None 4-5-80 life.

logic chip.

tive ic chip.

80-4-119 IIV-2224 Normal Wear Ilydraulic oil leakage Correc-Replaced "O" rings.

1 Day None 4-11-80 at ilV-2224.

tive 80-4-124 ME-9308 Loose connection.

Mi-9308 pegged down-Co rrec-Repaired wire.

2 llours tiene 5 80 scale.

80-4-129 SV-2109 Normal Wear Valve leaks through.

Co rrec-Replaced timer on 16 Ilours None 9-26-80 tive valve.

SIGNIFICANT_ MAINT'ENANCE

SUMMARY

II)ENTI FICA-REQUIRED EFRCT (W TION NUMBER SYSTFJt/

NATURE OF FOR

- SAW, Ol'ERATI(W AND DATE Cots *0NENT CAUSE OF HAl.FtNCTION RESUI.TS OF MALFINCTitM MAINTENANCE OHtNECTIVE ACT10t Cots'lJ: TION

'OF Tile REACIUR 80-4-130 SV-2115 Normal Wear Valve leaking through.

Co rrec-Replaced trim and 4 Hours None 9-6-80 tive calib ra ted.

80-4-131 SV-2116 Normal Wear Valve leaks th rough.

Correc-Replaced trim set 1 Day None 9-19-80 tive on annual calibra-tion.

80-4-147 V-46297 Normal Wear Service water outlet Co rrec-Freed up valve 2 Hours None 4-16-80 valve of bearing water tive stem.

cooler will not turn.

80-4-148 V-21476 No.nal Wear Loop 1 bearing water Correc-Repaired valve.

3 Days None 9-13-80 safety valve leaiIng tive t h ro ugh.

80-4-160 P-9106X Normal Wear Pump tripped.

Co rrec-Replaced bad motor. 3 Hours None L

5-16-80 tive

'(

80-4-170 CTI-B R4 Normal end of Low input voltage.

Co rrec-Replaced Z-35 and 3 Hours None 4-16-80

life, tive Z-37.

80-4-225 HV-21205-4 Normal Wear 1B circulator brake Correc-Replaced valves.

1 Day None 4-25-80

/21193-4 and seal bottle deple-tive tion.

80-4-226 P V-21244-1 Normal Wear Valve cycling and cre-Co rrec-Rebuilt and cali-1 Day None 5-12-80 ating pressure fluctu-tive brated valve.

ations on Loop 2 emer-gency feedwater header.

80-4-254 P-9102X Normal Wear Pump vibrating exces-Co rrec-Replaced pump

'l Day None 5-2-80

sively, tive coupling.

80-4-264 P-2109 Normal Wear Mechanical seal leakage Correc-Replaced seal.

12 Hours None 5-23-80 on pump.

tive 80-4-297 CS-1A2 Normal Wear Loop shutdown while at-Correc-Replaced defective 1 Hour None 5-2-80 tempting to reset.RIS-tive components Z-48 9325-11.

and 2-32.

L g-vw ve m eni

= ew e>q9%

SICNIFICANT MAINTENANCE

SUMMARY

TlHE I DENTI FICA-REQUl kED EFRCT (M TION NUMBER SYSTEff/

NATURE OF FOR SAW OPERATIEN AND DATE COW 4WENT CAUSE OF HALHNCTION HESULTS OF HAl.FLNCTitN HAIN TEN ANCE CORRECTIVE ACTION COHl'I.ETI ON OF THE REACTON 80-4-304 Alarm Normal Wear Loop 2 reheat steam Correc-Repaired faulty 1 flour None 4-25-80 pressure high-low tive alarm card.

alarms when between setpoints.

80-5-17 V-2245 Normal Wear Valve leaks through.

Correc-Rebuilt valve 16 Ilours None 10-10-80 tive seat and disc.

80-5-29 V-21958 Normal Wear Packing leak.

Co rrec-Repacked valve.

1 - llour None 9-13-80 tive 80-5-66 t!-92835 Normal Wear Moisture trap on Co rrec-Installed new 1 Hour None 5-5-80 starting air line for tive trap.

"B" diesel generator blew of f petcock, i

N 80-5-83

% 1115 Sample flow Samp.le flow control Co rrec-Replaced DC power 4 Ilours None T

5-12-80 valve adjusting operating abnormally, tive supply filter ca-por operating pacitor.

poorly.

80-5-85 PV-21244-1 Normal Wear PV-21244-1 leaking at Co r rec-Replaced pipe 4 Hours None 5-9-80 approximately 1/2 gpm.

tive downstream of valve.

80-5-179 V-75600 Normal Wear Packing leak.

Co rrec-Repacked valve.

2 Ilours None 9-3-80 tive 80-5-195 V-21268-1 Normal Wear Safety. valve leaking Correc-Valve repaired and 16 Hours None 5-16-80 th ro ugh.

tive adjusted.

80-5-196 V-21268-2 Normal Wear Safety valve leaking Correc-Valve repaired and 16 Ilours None 5-16-80 t h ro ugh, tive adjusted.

80-5-224 PV-21243 Normal Wear Valve leaking between Co rrec-Put devcon on gas.

1 Day None 5-16-80 seat ring and body, tive ket surface.

Re-placed valve.

_ - - =

SIGNIFICANT MAINTENANCIC

SUMMARY

I DENTI FI CA-REQlli RED EFfl.CT ON T10N Nt!M11E14 SYSTEft/

NATURE OF BIR SAlY OPF.RATI(N AND DATE CutlPONENT CAtEE OF MAI.FINCTION RESUI.TS OF MAI.FtHCTitN MAINTENANCE CORRECTIVE ACTION 01t1Pl.ETION OF Tile REA(TOR 80-5-234 TI/TC-2226 Normal Wear Low indication on TI-Correc-TT-2226-3 repaired, 2 llours None 8 80 2226 and to TC-2226.

tive calibrated, and re-installed.

80-5-248 TSL-ll75 Normal Wear Circulator inlet temp-Co r ree-Replaced CR-10 and 2 Hours None 5-20-80 erature low alarm tive checked module.

function not working.

80-5-259 MSS-149 Normal Wear Low oil level in snub-Co r rec-Rebuilt cylinder 4 llours None 6 80 ber.

t it '

and valve.

80-5-277 CC-2Al Normal Wear Low vol tage at input Co r re c-Replaced 2-44, 2 11ours None 5-23-80 to pin Y.

tive 80-5-278 CT-1AC2 Normal Wear Low voltage at input Co rrec-Replaced Z-37, 2 Ilours None 5-23-80 to pin P.

tive L

80-5-287 IIV-229 3 Normal Wear 011 ' leak from line Co rrec-Relief valve re-1 Ilour None 5-28-80 west of valve body.

tive placed.

80-5-293 PS-1106-7 Switch leaks.

Rese rve shutdown bot-Correc-Replaced switch.

2 Ilours None 6-19-80 tle lost pressure due

tive, to leak.

80-5-305 CT-1AR2 Normal Wear Testing could not be Correc-Replaced Z-31.

1 flour None 5 80 completed due to tive chip.

80-5-306 S C-8201 Normal Wear Purge flow on "A" in-Co r rec-Replaced llumistat 2 Ilours None 9-2-80 s t rumen t ai r d rye r tive at sensing element.

not working properly, s

80-5-312 LAllL-21135 Normal Wear Loop 1 bearing water Co r rec-Repaired and reset 3 llours None 5-27-80 surge tank level tive alarm card.

alarming continuously with tank level 3" above low level alarm.

I

SIGNIFICANT MAINTENANCE

SUMMARY

TlHE I DENTI FI CA-Rt.Qttl RF D EFItcT ON TION NUMBER SYSTFH/

NATUNE OF FOR SAFE OPERATlHN AND DATE Ott9WlENT CAllSE OF HAl.FtWl' ION RESUI.TS OF HAI.FIHCTION MAIN 1ENANCE OIRRECTIVE ACTION Olt9't.ETf 0N OF Tile REAt." TOR 80-5-349 CT-1BL3 Normal end of Low input voltage on Co r rec-Replaced Z-9 chip.

Approxi-None 6-2-80 life.

chip inputs, tive mately 2 llours 80-5-350 CTI-BR4 Normal end of Low input voltage on Co r rec-Replaced chip.

Approxi-None 6-2-80 life.

chip's inputs.

tive mately 2 Ilours 80-6-6 FE/ FT-Normal Wear Faulty indication on Co rrec-Replaced upper 4 Ilours None 6-6-80 21138 1C helium circulator tive seal and force backup bearit., water.

motor and cali-brated transmitter.

80-6-12 ISL-93207-Normal Wear "A" dump system logic Co rrec-Replaced K1, Q1, 4 llours None 6-9-80 1

trouble alarm would tive CRil, CR9,, C3.

not come up with ISL-Iw 93207-1 energized.

p 80-6-18 11-1301 Normal Wear Faulty impact limiter.

Correc-Impact limiter re-1 Day None 6-4-80 tive paired.

80 35 110 S - 3 0 personnel using Snubber upside down Correc-Filled snubber 4 Ilours None 6-3-80 equipment as (cylinder rotated),

tive with oil and in-stepping plat-stalled correctly.

fo rm.

80-6-45 IIV-46246-1 Normal Wear Valve would not oper-Co rrec-Reconnected valve Approxi-None 6 80 ate because the valve tive stem to operator, mately stem separated from 2 Ilours operator.

80-6-158 Pi-4216 Normal end of Local gauge failed to Correc-Replaced gauge App ro xi-None 6-10-80

life, indicate discharge tive calibrate.

mately fressure.

2 Ilaurs 80-6-190 IIV-2217 Normal Wear Leakage on 5-valve Correc-Replaced seat and 1 Ilour None 6-11-80 manifold o f IIV-2217.

tive "0" ring in 5-valve manifold.

Replaced L-valve.

g

SIGNIFICANT MAllffENAtkE

SUMMARY

TlHE IIENTI FICA-REQtil ret)

EFFECT (N TLON NutmER SYSTEff/

NATURE OF FOR SAIY OPERATION AND DATE Cotrt WENT cat!SE OF HALFilNCTION RESUI.TS OF HAI.FtHCTI(H ttAINTEN ANCE (XlRRECflVE ACTION COMPl.ETlON OF ' ole REACIUR 80-6-197 FT-2211 Normal Wear Flow transmitter leaked Co r re c-Replaced fitting.

Approxi-None 6-16-80 at blowdown fitting.

tive mately 2 Hours 80-6-208 V-21298 Normal Wear Backup bearing water Co rrec-Repaired valve per 12 Ilours None 9-1-80 relief valve Icaking tive p rocedure.

t h ro ugh.

80-6-224 1" L21606-Wear at pipe Pipe leaked.

Co rrec-Replaced elbows.

Approxi-None 6-16-80 D21

elbow, tive mately 4 Ilours 80-6-225 PV-21243 Normal Wear Inability to maintain Correc-Devconed under 4 Ilours None 6-18-80 setpoint on PV-21243.

tive seal ring gasket.

80-6-236 PDT-2177-1 Bellows of PDT-Buffer helium upset on Co rrec-Replaced bellows Approxi-None, caused 4

6-27-80 2177-1 failed, Loop 1 and trip of tive assembly.

mately loop shut-y allowing bearing Loogi I circulators.

3 llours down and in-water into the creased buffer helium moisture in system.

the primary coolant, but would not prevent a safe shut-down.

80-6-256 TE-22139 Normal end of Single channel scram Co rrec-Replaced TE with Approxi-None 6-17-80

life, from plant protective tive new TE.

nately system.

2 Ilours 80-6-259 P-9105X Normal Wear Pump unable to operate.

Correc-Replaced motor.

App ro xi-None 6-24-80 tive mately 5 Days 80-6-293 V-7221 Normal Wear Valve leaks through.

Co rrec-Replaced valve.

24 Ilours 9-9-80 tive 0

SICNIFICANT MAINTENANCE

SUMMARY

TIffE I I,tNTI FI CA-REQUIRED EFFFCT ON TION NDH8ER SY STEtt/

NATURE OF FOR SAFTi Ol'tRATION AN D I)A1 E COHl'ONENT CAUSE OF HAl.FtNCTION RESul.TS OF HAI.FINCTitx4 HAINTENANCE

RHDTIVE ACTION CortPl ETION OF Tile RFACIOR 63-6-323 ilV-21193-2 Normal Wear Valve leaked by.

Correc-Replaced valve.

Approxi-None 6-25-80 tive mately 4 liours 80-6-324 V-2214 Normal Wear Valve leaks at flanbc.

Correc-Repaired valve 16 Ilours None 10-10-80 tive flange.

80 L346 IIS-2238 Normal Wear Spring broken on Correc-Repaired spring.

2 Hours None 6-26 80

" spring-return" type tive handswitch.

80-6-350 C-8203 Normal fouling Inst rument air com-Co rrec-Acid cleaned the Approxi-None 6-27-80 of the water pressor tripped on tive cooling water mately cooling system.

high discharge temp-line.

8 Ilours erature.

I 80-6-353 TS-8245 Normal Wear Temperature switch for Correc-Replaced and cali-2 llours None g) w 8-25-80 "C"

instrument air tive brated new switch, compressor broken at tempera ture element.

80-6-363 System 93 Normal end of 30% RWP trip out of Co rrec-Replaced amplifier Approxi-None 6-27-80

life, specified limits.

tive A51 (702) and mately calibrated per 1 Ilour p ro cedu re.

80-6-370 C-8201 Normal Wear Packing leaked air and Correc-Replaced packing Approxi-None 6-30-80 a knock was detected.

tive and one of the mately discharge valves.

5 llours s

80-6-384 IIV-22225 Normal Wear Valve leaks at flange.

Co rrec-Repaired valve 16 Hours None 9 80 tive seat, disc, and flange.

80-6-393 V-9170 Valve stuck Valve stem broken.

Correc-Replaced valve 8 Ilours None 7-2-80

closed, tive bonnet and stem.

80-6-400 PC-22192 Normal end of Controller would not Correc-Replaced auto-Approxi-None 7 80 life for auto-go into automatic oper-tive manual relay, mately d

manual relay, ation.

1 Hour

e SIGNIFICANT MAINTENANCE

SUMMARY

TIME IDENTIFICA-REQUI RE D EFFECT (W TION NUMBER SYSTFJt/

NATtfRE OF FOR SAFE OPERATIEW Anis DATE Curt'tWENT CAUSE OF MAI.FtNCTION RESUI.TS OF H.il.FtHCTIIN MAI N1YN ANCE CORRECTIVE ACTION Coru'tE.TI ON OF 11tE REACIOR 80-6-404 CT-2A2 Normal end of Input voltage zero Co rre c-Replaced Q11 in App roxi-None 7-1-80 life.

with no modules tive LRD-1.

Checked mately t rip ped,

operation per RP-2 Hours 86.

80-6-405 LRD-1 402-Normal end of Single channel trip on Co r re c-Replaced Q11 in Approxi-None 7-1-80 P2 life.

1D circulator.

tive LRD-1 404-P2 and mately checked per RP-F6.

2 llours 80-7-29 FC-2205/

Normal end of The Loop 1 and Loop 2 Correc-Replaced capaci-Approxi-None 7-3-80 2206 life of several feedwater flows sepa-tive tors and a re-mately electrolytic rated approximately sistor.

2 Ilours capaci to rs.

100 Klb/hr.

80-7-60 CT-2A2 Normal end of Low voltage on chip Correc-Replaced Z-42 and App ro xi-None 7-5-80 life.

inputs.

tive checked RP-80 and mately t,

RP-433.

1 Ilour 7

80 71 IIV-21352 liigh temperature Cross tower leakage Co rre c-Replaced teflon App roxi-Increased 7-7-80 and excess wear in the buffer helium tive disc with a brass mately moisture caused valve dryer.

disc.

2 llours level in disc to leak.

the primary coolant.

80-7-96 IIV-22225 t'ormal Wear Valve blowing steam.

Correc-Repaired steam 2 llours None 7-10-80 tive leak.

10-7-100 SV-2111 Normal Wear SV-2111 would not open Co rrec-Replaced solenoid 1 Day None

? 80 via SC-2111.

tive valve.

0-7-101 Ala rms Normal Wear IB circuletor penetra-Correc-Replaced chips in 1 Ilour None 7-24-80 tion pressure high tive CT-2 module.

alarm would not clear.

80-7-115 SV-2105 Normal Wear Broken hydraulic return Co r rec-Replaced hydraulic 2 Hours None 7 80 line.

tive flex line.

80-7-142 Pl an t P ro-Normal Wear Low voltage at logic Correc-Replaced chips in 1 Ilour None 7-24-80 tective inputs.

tive logic module, System g

SIGNIFICANT ttA LNTENANCE SUMM,TRY TlHE Ilt:NTI FI CA-REQIIIRED EFITCT ON TION HIIPM.it SYSTEtt/

NATIIRE OF HIR SAFE OPERATit1N AND 11 ATE O RE'OrlENT cal!SE OF 11ALFINCTION RESill.TS OF flAIJINCTION MAIN 1ENANCE CultRF.CTIVE ACTION CottPI.ETf 0N OF 11tE REACillR 80-7-144 K-9204X Normal Wear Af ter cooler leakage.

Co rrec-Replaced after 3 Days None 7-28-80 tive cooler per service manual.

80-7-145 Plant Pro-Normal Wear 1.ow voltage at logic Correc-Replaced logic 1 llour None 7-14-80 tective module.

tive chip.

System 80-7-172 IIV-1102-27 Normal Wear Valves leak through.

Correc-Replaced valve 4 flours None 9-24-80

/ilV-1104-tive discs and packing.

27 80-7-173 V-11677 Normal Wear Region 27 "tf' valve Co rrec-Polished stem and 4 Days None 9-24-80 leakage makes helium tive seat, installed cylinder change-out new disc, and re-di f fical t.

installed valve.

d, w

0 80-7-218 IIV-2245 Normal Wear Valve inoperable.

Correc-Replaced valve 2 llours None 8-20-80 Operator tive operator motor.

80-7-233 C-8201 Normal Wear "A" instrument air Correc-Replaced capillary 4 Ilours None 7 80 compressor tripping tive tube assembly, due to high water t empe ra ture.

80-7-255 V-22184 Normal Wear Valve leaks through.

Correc-Lapped seat and 16 Ilourt None 9-3-80 tive replaced disc.

80-7-257 PV-22167 Normal Wear Pilot valve leaks.

Correc-Rewelded pilot 16 llourt None

_ 80 tive tubes.

9 80-7-296 Plant Pro-Loose connection.

Channel A and B single Correc-Repaired loose 2 Ilours None 7-25-80 tective channel scram did not tive connection and System energize during Sur-retested.

veillance Test.

80-7-297 V-211002 Normal Wear Valve leaks th ro ugh.

Co rrec-Replaced valve.

8 Ilours None 9-6-80 tive d

SICNIFICANT f tAINTEN'ANCE SIMMARY TIME I DENTI FICA-REQUIRED FFncT UN TION NUMBER SYSTEtt/

NATURE OF FOR SAE ol'ERATItta AND DATE Cott'ONENT CAUSE OF HAIJUNCTION RESUI.TS OF MAI.flNCTION HAIN11: NANCE CORNECTIVE ACTION C(21Pl.ETinN OF THE RF. ACTOR 80-7-311 Reserve Normal Wear Brass fitting at re-Co r re c-Replaced fitting.

1 Ilour None 7-25-80 Shutdown serve shutdown system tive System bottle connection Bottle leaks.

Connection 80-7-314 V-45200 Truck ran over Valve bcoken off.

Co rre c-Replaced valve 8 Ilours None 9-30-80 va1ve.

tive bonnet.

80-7-315 V-45203 Truck ran over Valve broken o f f.

Co rrec-Replaced, valve 8 Ilours None 9-30-80 valve.

tive bonnets and stem.

80-7-319 TIC-75107 Normal Wear Controller inoperable.

Correc-Replaced con-4 llours None 9-30-80 tive t ro lle r.

80-7-320 Plan t Pro-Normal Wear Low voltage on circu-Correc-Replaced chip Z-2 Ifours None b

7-28-80 tective culator trip module.

tive 28.

'f System 80-7-321 Plant Pro-Normal Wear 1.ow voltage at circe-Correc-Replaced chip Z-2 llours None 7-28-80 tective lator trip module tive 35.

System during Surveillance Test.

80-7-330 PV-21243 Normal Wear Valve body requires Correc-Repaired valve per 1 Day None 9-15-80 rework.

tive procedure.

80-7-346 C-8201S Normal Wear Compressor stays loaded Co rrec-Replaced discharge 1 Day None 7-28-80 and heats up.

tive valves.

80-7-374 V-212 80-1 Normal Wear Valve leaks through.

Co rrec-I.apped valve seat 16 Ilours None 9-23-80 tive and disc.

80-8-30 V-21268-1 Normal Wear I.ea ka ge through safety Correc-Repaired seat, 1 Day None 8-6-80 relief valve V-21268-1.

tive disc, and valve body.

80-8-31 V-21268-2 Normal Wear I.eakage through safety Correc-Repaired seat, 1 Day None 8 80 relief valve V-21268-2.

tive disc, and valve b

body._

SIGNIFICANT 11AINTENANCE SIRetARY l

TlHE I DENTI FICA-l PEQUIRED F.FFECT (W TION NUHnER SYSTEll/

NATURE OF IUR S A>Y. OPERATION AND llATE (XH'ONENT CAUSE OF HAl.FINCTION HESUI.TS OF HAI.FINCTluN MAINTENANCE

- CORRECilVE ACTION CurtPl.ETION OF Tile REAc11)R 80-8-36 21-1121 No rmal Wear llea ter power cou-Co rrec-Replaced component 2 Hours None 8-5-80 troller for mi-1121 tive A2 and checked out blowing fuses.

per procedure.

80-8-57 IIV-2245 Normal Wear lA circulator steam Co rrec-Installed new 4 Ilours None 8-19-80 inlet valve will not tive motor and tested open.

valve.

80-8-67 V-7209 Normal Wear Valve leaks through.

Co rrec-Replaced valve.

16 Hours None 9-18-80 tive 80-8-68 Control Normal Wear Position indicator in-Correc-Chan.ted out con.

3 Days None 9-15-80 Rod Drive operable for region 23 tive trol rod drive.

Region 23 control rod drive.

80-8-69 K-23-1 Normal Wear In-limit position indi-Co rrec-Installed and 1 Hour None s' >

B 80 cation faulty for tive tested new K-23-1 7

region 23.

relay.

80-8-74 V-21453 Normal Wear Valve leaking thrm ao.

Co rrec-

_wped valve seat 15 Ilours None 9-10-80 tive and disc.

80-8-9 7 V-7216 Normal Wear Valve leaks through.

Correc-Removed, repaired, 16 llours None 9-18-80 tive and re-installed valve.

80-8-100 81V-2292 Normal Wear liydraulic oil leak on Co rrec-Replaced poppet 2 Ilours None 8-6-80 llV-2292.

tive block "O" rings.

80-8-157 Plant Pro-Normal Wear Low voltage at circu-Correc-Repalced chip Z-2 llours None 8-13-80 tective lator trip module tive 36 and Z-37.

System during Surveillance Test.

80-8-161 V-21268-2 Normal Wear Valve V-21268-2 leaking Correc-Repaired valve 12 llours None 9-10-80 th rough.

tive seat and disc.

80-8-190 V-22185 Normal Wear Valve packing leaks.

Correc-Repacked valve.

12 Ilours None 9-19-80 tive

.A

SIGNIFICANT f*AINTFRANCE SUf 41ARY IIENTI FICA-REQUIRED EFfECT UN TION NUMHER SYSTEft/

NATURE OF FOR SAFE Ol'ERATifti AND llATE COMI'UNtNT CAUSE OF HALFit4CTION RESlH.TS OF HAI, FIR 4CTIOri HAIN1T N ANCE CURRELTIVE ACTION CutiPl.E1 I ON OF 'IllE REACTOR 80-8-191 SV-2110 Normal Wear Valve leaks t hro ugh.

Correc-Reslaced trim set 1 Day None 9-19-80 tive during annual cali-bration.

80-8-199 PV-2244 Inproper instal-011 1ine to PV-2244 Co rrec-Installed new pipe 4 Ilours None 8-18-80 lation.

b ro ken, tive nipple and bushing.

'0-8-221 tef-1115 Normal Wear te!-1115 heater failure. Correc-Replaced fuse.

1/2 None l n--18-80 tive llour 80-8-264 V-2246 Normal Wear Valve leaks through.

Correc-Replaced disc, 16 Ilours None 9-19-80 tive machined and lapped sdht.

80-8-275 Linear Bad solder joint.

RWP trip received at Correc-Repaired solder 2 Ilours None 9-1-80 Channel IV 24% indicated power.

tive joint.

Checked i3 connection, reset T

RWP trips.

80-8-291 V-8218 Normal Wear "A" inst rumen t ai r com-Correc-Replaced disc, 8 Ilours None 8-22-80 pressor discharge tive guide and guide relief valve blowing follower.

through.

80-8-298 Plant P ro-Normal Wear Low voltage input to Correc-Replaced chip Z-1 llour None B-21-80 tective CC-2B2.

tive 43, checked module System yer procedure.

80-8-302 Plant Pro-Normal Wear Low voltage at CC-2A2.

Co rrec-Replaced chip Z-1 Ilour None 8-21-80 tective tive 43, checked module System per procedure.

80-8-303 Plant Pro-tJormal Wear Low voltage at CT-1BL3. Correc-Replaced chip Z-9, 1 llour None 8-21-80 tective tive checked module per System p ro ced u re.

80-8-340 MSS-191 Undetermined Snubber piston out of Correc-Installed shim.

2 Ilours None 9-16-80 tole rance.

tive

. - - - - - - - - - - -. - - - - - ~ - --

SIGNIFICANT MAINTENANCE

SUMMARY

T iffE I DENTI FICA-REQUI RED FFFECT sin T!ON NUMBER SYSTEH/

NATURE OF IUR SAfY. OPERATION AND DATE COFE'ONENT rat!SE OF HALFUNCTION RESULTS OF HAl.FtNCT!Utf MAINTENAh"E CORRECTIVE ACTION COttPI.E TION OF lilE REACTOR 80-8-342 IIRS-129 Undetermined Snubber piston out of Co rrec-Repaired snubber 4 llours None 9-26-80 tolerance.

tive per procedure.

80-8-343 ilRS-158 Undetermined Snubber piston out of Correc-Installed shim per,2 Ilours None 9-16-80 toleraate, tive procedure.

80-8-351 CRS-262 Undetermined Snubber piston out of Correc-Rennved 3/4" from 4 llours None 9-14-80 tolerance.

tive piston rod end and re-1nstalled.

80-8-353 MSS-421 Undetermined Snubber piston rod Forrec-Replaced with new 1 Ifour None 8-28-80 bent.

tiVe' s anubber.

80-8-370 IIFS-412 Undetermined Snubber piston out of Correc-Repaired snubber 4 Ilours None 9-16-80 tolerance, tive per approved pro-cedure.

T 80-8-373 V-21268-1 r cmal Wear Relief valve leaks correc-Repaired valve 20 llours None 9-16-80 through.

tive seat and disc.

80-8-395 P-9102X Normal Wear Coupling on P-9102X Correc-Replaced coupling.

1 Day None 9-13-80 had.

tive c

80-8-406 IIV-2302 Normal Wear Valve stuck closed.

Correc-Repaired manual 16 Ilours None 9-25-80 tive override.

80-9-33 C-8201S Normal Wear Compressor trips on Co rrec-Replaced breken 5 alours None high discharge temp-tive discharge check

erature, s

valve.

80-9-73 Reserve N^rmal Wear Connector leaks, Co r re c-Repaired con-3 Hours None 9-18-80 Shutdown tive nect or.

Ilottle Connection 80-9-80 V-21522 Normal Wear Seat and disc of V-Correc-Machined valve 16 llours None 9-9-80 21522 required repair.

tive seat and disc.

80-9-91 C-8201S No rn-.1 Wear Discharge pressure low.

Correc-Replaced broken 5 llours None g

9-10-80 tive disc---.h.a rh>e...va lve.

e SIGNI F1 CANT MAINTENANCE

SUMMARY

TlHE Ilt:NflFICA-REQUIRED EFFECT UN TION NUMBER SYSTEH/

NATtikE OF FOR SAFE Ol'ERATitW AND DATE COWuNENT CAllSE OF MALFlWcTION RESHI.TS OF mal.FLNCTitW MAIN TENANCE CORRECTIVE ACTION COMPl.ETitW OF THE REACTOR 80-9-120 C-8201 Normal Wear "A" i ns t rumen t ai r Correc-Replaced pressure 2 Ilours None N -B3 compressor loading /

tive switch and solen-unloading constantly.

old.

80-9-121 IIV-2187-2 Normal Wear Air regulator leaking Correc-Replaced leaking 2 Hours None 9-9-80 on IIV-2187-2.

tive regulator.

80-9-123 PDE-1166 Normal Wear 1C circulator dif-Correc-Replaced element 2 Ilours None 9-8-80 ferential pressure tive and calibrated.

element out of toler-ance.

80-9-125 IIV-46259-2 Normal Wear llandwheel slips.

Correc-Replaced handwheel 2 Hours None 10-9-80 tive key.

80-9-170 TIC-75107 Switch wires Switch does not oper-Correc-Replaced thermo-2 Hours None i,

9-12-80 shorted out,

ate, tive stat.

Y 80-9-230 C-7521 Normal Wear Motor burned up.

Correc-Found short in 4 llours None 10-2-80 tive moton and repaired, 80-9-244 IIV-22113 Normal Wear Operator leaks air.

Co rrec-Tightened dia-4 Hours None 9-29-80 Operator tive phragm seal ar,d r ) laced air tuoing.

80-9-349 llydraulic Normal Wear Snubber lower reser-Correc-Tightened' seal.

4 Ilours None 10-10-80 Snubber voir seal leaks.

tive MSS-433 80-9-375 llRS-205 Undetermined Snubber piston out of Correc,

Extended stanchinn 4 Ilours None 9-26-80 tolerance.

tive 1/4".

80-9-376 IIOS-10 Undetermined Snubber piston out of Correc-Installed new pipe 6' Hours None 9-27-80 tolerance, tive stanchion.

80-9-389 HOS-86 Undetermined Snubber piston out of Correc-Pipe clamp moved 2 Ilours None 9-27-80 tolerance.

tive 1 5/8" towards anchor pin.

g

-_.ie'wwh-e>-lumiwme-w==ieee-sq,-ww=amerg uweow w=w y v wwwwwum--ww-ww w-ww wegv w w-m'T wyhy-g ye-y-'*rwi=>wsw veaw'y m 7 9

'y C'ww'y y w-vv t--@.,

SIGNIFICANT MAINTENANCE

SUMMARY

_- ~

IDENTI FICA-REQUIRED EFFECT IN T!ON NUHRER SYSTEH/

NATURE OF FOR SAW. OPERATitN AND DATE Cott'ONENT CAUSE OF HAl RNCTION REShl.TS OF HAl.FINCTitM MAINTENANCF.

CORRECTIVE ACI' ION C(MS*I.ETI ON OF Tile REACTOR 80-9-390 VSS-123 Undetermined Snubber hitting I-beam Correc-Raised collar up 2 Ilours None 9-27-80 interference.

tive 1/2".

+

80-9-400 IIV-2254 Normal Wear Switch inoperable.

Co rrec-Replaced switch.

1 IIour.

None 9-29-80 Position tive Switch 80-9-401 PI-21248 Normal Wear Indicated pressure Correc-Replaced gauge.

2 Ilours Not.a 10 80 wrong.

tive 80-9-412 LC-21306 Normal Wear Controlled IcVel too Correc-Retubed con-2 Ilours None 9-27-80 high.

tive troller.

80-9-430 SV-2111 Normal Wear Valve will not open.

Cirrec-Replaced valve 8 Ilours None 10-2-80 llydraulic tive operator solenoid.

Operator i'

80-9-431 IIV-2245 Normal Wear Valve inoperable.

Correc-Replaced operator 4 llours None 10- 3-80 Operator tive motor.

'a 80-9-448 PI-21536-2 Normal Wear Indicated pressure Correc-Replaced gauge.

2 IIours None 9-30-80 wrong.

tive 80-9-460 ilV-4507 Normal Wear Valve leaks through.

Co rrec-Cleaned valve in-1 IIour None tive t ernals.

80-9-471 PC-31213 Normal Wear Not controlling Co rrec-Repaired con-2 Ilours None 10-1-80 properly.

tive troller.

80-10-3 SV-2105 Normal Wear llydraulic oil leak at Co rre c-Repaired solenoid 7 Hours None 10-1-80 valve operator.

tive valve.

80-10-32 K-9203 Ex-Normal Wear Switch failed to trip Correc-Replaced failed 1 Ilour None 10-3-80 haust Te mp-engine during test.

tive relay.

e ra ture Switch s

80-10-35 P-2109 Normal Wear Pump output less than Correc-Replaced pump im-16 Ilours None d.

10-9-80 acceptable limit.

tive peller and mechani-g

- - ----, cal seal.

- - ~ ~

SIGNIFICANT_ MAINTENANCE SUM?tARY TIMI:

I DENTI FICA-REQUIRED EFfECT ON TION NUMBER SYSTEtt/

NATURE OF R)R SAFY OPEPATHr4 AND DATE COMPONENT CAUSE OF MAI. Fit 4CTION RESUI.TS OF MAIJttiCTitti MAINTENANCE CORRECTIVE ACTION CittPl.ETION OF Tile RFA("lDR 80-10-50 IIV-21205-2 Normal Wear Valve leaks through.

Correc-Replat.ed valve.

4 Hours None 10-7-80 tive.

80-10-59 IIV-21205-2 Normal Wear Valve leaks t h ro ugh.

Correc-Replaced valve.

4 llours None tive 80-10-93 SV-2105 Normal Wear Ilydraulic oil leak at Co rrec-Replaced operator 12 Ilours None 10-8-80 valve operator, tive solenoid valve.

80-10-118 1" L21605-Normal Wear Line leaks.

Correc-Replaced half inch 10 llours None 10-9-80 D2B tive t>ipe nipple.

80-10-150 E-8223X Normal Wear Knock out pot would Co r rec-Cleaned pot, re-12 Ilours None 10-11-80 Knock Out not drain, tive placed eroded pipe Pot nipple.

I 80-10-162 V-21909 Unknown Vent valve broken of f Co r rec-Replaced pipe nip-1 llour None y

w 10-13-80 fl1ter housing.

tive ple.

80-10-241 IIV-21247/

Normal Wear Valves leaked through.

Co r rec-Replaced valve 8 Ilours None 10-15-80 21248 tive disc.

80-10-402 V-21268-1 Normal Wear Valve leaks through Co r rec-Replaced valve 12 Ilours None 10-23-80 tive seat and disc.

80-10-409 Loop 1 Normal Wear Ilydraulic oil leak.

Emer-Replaced "O" ring.

6 Ilours None 10-23-80 Group 1 gency "O" Ring

'80-10-247 V-9141 Valve handwheel Valve inoperable.

Co rrec-Replaced valve 1 liour None 10-24-80 missing.

tive handwheel.

80-10-431 TE-22145 Internal short.

Loss o f tempera ture in-Correc-Replaced failed 8 Hours None 10-24-80 dicattion.

tive thermocouple.

l 80-10-484 V-91696/

Normal Wear Valves leak through.

Correc-Replaced in kind.

4 Nours None 10-28-80 V-91697 tive -

80-10-503 ilV-21235 Normal Wear Valve leaks through.

Correc-Machined valve 16 Ilours None 11 80 tive disc, lapped ueat.

l l

SIGNIFICANT MAINTENANCE Sil!! MARY -

e TIPE I DENTI FICA-REQUIREli EFFFCT UN TIO98 NUMBER

$751Erl/

NATUltr OF

'mR SAFE OPFRATION l

AND DATE COMPO(4ENT CAUSE OF HA1.FINCTION RESUi.TS OF ttAl.FtN("FluN HAIN11 NANCE CORRECflVE A(' TION CUHPl.ETION OF 118E RF.Ac!DR I

80-10-515 1.V-21114 Normal Wea.

Valve operation er-Correc-Replaced v'lve 8 Hours Pone a

l 11-6-80

ratic, tive operator diaphragm.

80-16-524 Plari P ro-Normal Wear Module failed tripped.

Co rrec-Replaced failed

- 4 Hours None 11-1 30 tretive tive integrated cir-System cuits.

elodule CF-1BR4 80-11-8 IIV-21192-4 Normal Wear Valve Icaks through.

Co rrec-Replaced valve.

4 Hours None 11-5-80 tive 80-11-9 ilV-21194-4 Normal Wear Valve leaks through.

Correc-Replaced both 8 Hours None 11-5-80

/21206-4 tive valves.

80-11-27 Diesel Normal Wear Switch failed to trip Emer-Replaced switch 3 Hours None L

i 11 80 Engine Ex-engine during test, gency and input thermo-

?-

haust

couple, i

Temp-erature Switch 80-11-63 llot Reheat Normal Wear "U" bolt broken.

Co rrec-Replaced bolt.

32 Ilours None 12 80 Hanger tive IIR-136 00-11-67 LV-21114 Normal Wear Valve operator would Co rrec-R(otaced ruptured 4 Hours None 11-6-80 Ope ra tor not completely close tive valve. operator valve.

diaphragm.

80-11-119 SV-2105 Normal Wear 011 leak in return Co rrec-Replaced failed 16 Hours None 11-24-80 llydraulic

line, tive return line.

O_pe ra to r 80-11-170 Plan t P ro-Normal Wear Module failed test.

Co rrec-Replaced failed 4 Ilours thone 11-24-80 tective tive integrated cir-System cuit.

Module CT-2 C

,-,g-ggy

-mr-

.T'

-t-"-"^?"--***-I' T

^~*-

N-'--

- 1S

-~

-N'

~t-M'W

- - """e' um

m^=4 m^-1v-N

-'w

>M-eer

+ee*w a

w aaJ y---

--.m-.

w

O SIG4LFICAs1T MAINTENANCE

SUMMARY

TIME l

!!*NTI FI CA-REQtJI REI)

EFECT (W I

TION NUMBER SYST Ef f/

NATliRE OF FOR SAW. OPERATION AND DATE Cott't t1ENT CAUSE OF HAIJt!NCTION HEStil.TS OF HAI.FtteCTION HAINTENANCE CORRECTIVE ACTION Cit 1P t.ETION OF Tile REACTOR 80-11-259 Plant Pro-Normal Wear Module failed test.

Co rrec-Replaced failed 2 llours None 11-21-80 tective tive integrated cir System cuit.

Module 80-11-265 TSil-22135 Normal Wear Spurious trip.

Correc-Replaced grounded 4 llours None 11-24-80 tive thermocouple with spare.

80-11-318 Line 1"L Thermal growth.

Line cracked.

Emer-Replaced failed 3 Days None 11-28-80 22171-D3 gency line section.

80-11-342 IIV-2224 Normal Wear 011 leak at "O" ring.

Co rrec-Replaced "0" ring.

4 llours None 11-28-80 80-11-373 IIV-2292 Normal Wear 011 leak at cylinder Co rrec-Replaced relif 4 liours None 5-11-30-80 llydraulic relief valve.

tive valve.

Y Operator 80-12-7 TDSL-22103 Normal Wear Instrument indication Correc-Cleaned electrical 4 Ilours None 12 80 erroneous, tive contacts.

80-12-60 P-910SX Normal Wear Ilydraulic oil pump Co rrec-Replaced pump and 5 Days None 12-10-80 rough and noisy.

tive coupling.

80-12-106 ilV-2293 Normal Wear 011 relief valve leaks, Co rrec-Replaced valve.

2 llours None 12-6-80 llydraulic tive Operator 80-12-108 SV-2111 Normal Wear 011 leak at poppet Co rrec-Replaced failed 5 licurs None 12-16-80 llydraulle block.

tive "0"

ring.

Ope ra to r 80-12-256 Reserve Normal Wear Connection would not Correc-Replaced imttle 1 llour None 12-23-80 Shutdown

seal, tive connector.

Region 31 lio t t1e Connector.

O SIGNIFICANT !!AlflTENANCE

SUMMARY

T i ttK -

I DENTI FI CA-REQUIRED EFFECT ON TION NUMBER SYSTEH/

NATURE OF FUR SAFE OPERATitH AND DATE Cutt'ONENT CAtGE OF HAl.FttiCTION RESUI.TS OF HAl.FINCTION HAINTENANCE

' CORRECTIVE ACTION C(tW'I.ETI ON OF TifE RFACTOR 80-12-299 C-8201 Normal Wear Inst rument ai r com-Co r rec-Repaired.

6 Ilours None.

12-22-80 pressor trips on high tive af ter-cooler temp-erature.

80-12-334 TV-2228-2 Normal Wear Water Icak at grease Co rrec-Replaced grease 1 llour None 12-26-80 fitting.

tive fitting.

80-12-359 PS-1106-20 Normal Wear Bourdon tube leak.

Co rrec-Replaced switch.

2 Ilours None 12-31-80 tive 80-12-391 PV-2244 Normal Wear Indicated valve posi-Correc-Replaced position 4 Ilours None 12-29-80 Position tion erratic.

tive element.

Iudicato r ik Y

l l

l-

'a

O SIGNI FICANT !!AINTENANCE SIRefAltY TIME I IE.NTI FI CA-REQUIRED F.FFECT (N TION NUttilER SYSTE!!/

NATURE OF R)R S AE OPERATION AND DATE Cut 9'ilHENT CAUSE OF Half TINCTION HEStil.TS OF HAI.FtNCTION MAIN TENANCE CORRE('TIVE A(7 ION C(4tPl.ETI ON OF 11tE REACTOR CWP-465 C-2102 Sockets cut down Sockets require weld Co r rec-Weld circulator 48 Ilours None 2-27-80 during circulator buildup.

tive steam outlet pipe

removal, in upright posi-tion.

CWP-486 PV-21243 Normal Wear Valve leakage Llirougli Co r rec-Valve sea t re-2 llours None 5-16-80 P V-2124 3.

tive paired.

CWP 80-32 PV-2124 3 Normal Wear Valve leakage.

Correc-Weld repair of 8 Ilours None 10-1-80 tive valve seat.

CWP 80-34 V-2126 8-1 Normal Wear Valve liody erosion /

Co rrec-Weld repair to 16 II,urs None 11-13-80 valve leakage.

tive valve l>ody and seat.

CWP 80-35 PV-22167 Normal Wear Valve leakage.

Correc-Weld repair to 8 Ilours None 1

10-28-80 tive valve gasket seal y

area.

s CWP 80-45 !!V-31119 Normal Wear Leakage past seat and Co r rec-Repaired valve 4 Days None 9-24-80 disc.

tive seat and disc.

o 2.0 PLANT OUTAGES OR FORCED 1:1: DUCTIONS IN POWEP, t

MAJOR SAFE 1Y RADI ATION RELEASE RELATED OTR-ASSOCI ATED W1111 OUT-CORRECTIVE ALTION REcTIVE tu!N-

/R Willut ACCOUNTS REl.ATED RE-TAKEN TO REDUCE TENANCE PER-IDR SkME 111AN 10%

PORTABLE Tile PROBABILITY OF OPERATING FORMED DURINC OF ALI.(MABl.E ANNUAL NUMBE R PROX 1 HATE CAUSE SYSTEM MA.10R ColfMt1ENT OCCURRENCE RECURkENCE TlHE IDST 111E OITTAGE VAI.llE 79-14 Maintenance P rimary llelium Circu-50-267/80-Replaced hellun 1538.8 Replaced None and region Coolant lator 01/01-T-0 c i rc ula to r.

hours in helium cir-cons t rain t 1980 culator.

device in-Replaced stallation speed shutdown cables on continued in IA, IB, and 1980 for re-ID circula-placement of t o rs.

Re-helium cir-paired culator.

leaking IIV-2215 and ilV-2217.

,n>

80-01 Turbine Power Main Turbine None None 4.15 None None over-speed Conver-llours test.

sion a__

80-02 Circulating Circu-Distribution None Repaired pipe.

123.8 None None water tower lating Pipe (Wood) llours pipe rupture. Water 80-03 Spuritas Plant Integrated None heplaced chip.

56.8 None None scram.

Protec-Circuit flours tive Sys-tem 80-04 Loss o f con-Conden-Boiler Feed-None Closed valve.

49.25 None None densate sate pump Turbine llours vacuum.

Drain 80-05 lle1 Lum cir-Primary 1A !!elium None None 53.2 None None culator Cool an t Ci rcula to r llours trip.

5

(

2oO PLANT OUTAGES OR 1GP.CED REPUCTIONS IN POWER

/

I

~

~~

HA.IOR S AFT.1Y RADIATION ImLEASE REl.ATF.D 01R-ASSOCI ATED W1111 OtTT-CORRECTIVE ACTION RECTIVE MAIN-ACE WillOI ACCut!NTS REI.ATED RE-TAKEN TO REDtKE 7trNANCE PER-FOR HORE THAN 10%

PORTABl.E lite PROHARILITY OF OPERATING FORft:D DURING OF All>WABIE Ata4UAI, NtlHBER PROXIMATE cat lSE SYSTEM HA.10R Cit 1PONENT OCCUR RE NCE RECilRRENG TlHE IJGT 11tE otrrACE val.UE 80-06 IIelium cir-Primary l A IIelium None None 30.0 None None culator trip Coolant Circulator llo urs and loop shutdown.

80-07 liigh primary P rimary None None Intentional None None coolant oxi-Coolant power reduc-dants.

tion.

80-08 Spurious Plant logic Module None Replaced 0.6 None None turbine Protec-module.

Ilours trip.

tive Sys-tem.

I s~

v.

80-09 llelium cir-P ri mary llelium Cir-None None 118.7 None None I

culator Coolant culator IA Ilours trip.

80-10 Spurious Plant Logic Module None Replaced 5.9 None None loop shut-Protec-module.

Ilours down.

tive Sys-tem 80-11 Loop shut-Primary Bearing None None 18.8 None None down from Coolant Water Surge llours helium cir-Tank culator trip.

80-12 Loop shut-Primary IIelitun Cir-None Replaced 313.4 None None down from Coolant culator l A failed dif-liours helium cir-ferential pres-g culator sure transmit-trip.

ter.

h

o 2.0 Pl. ANT OUTAGES OR IT)RCED REDUCTIONS IN POWER e

HAJOR SAFETY 4ADIATION RElr.ASE RELATED o)R-ASSOCI ATED WIT 11 OUT-CURRECTIVE ACTION RECTIVE IMIN-Af.T Wilidi ACCOUNIS FELATED RE-TAKEN TO ret >UCE TENANCE PER-FUk HORE TilAN 10%

PORTABLE 111E PROBARILITY OF OPERATING 50 RED DURING OF AllAMABl.E ANNUAL N UM,qliN.,

. PROXIMATE CAtISE SYSTEM

_ HA.IOR Cutti'ONENT OCCURRENCE RECIIRRENCE TIME I.OST 11tE otrTAGE val.IIE 80-13 Reac to r Secondary Feedwater None None 339.9 Emergency None scram.

Coolant System llours generator heat ex-changer leak r_ epa i r.

80-14 Low steam Secondary Depressuri-None Reclosed de-0.4 Mone None pressure.

Coolant zation Valve pressurization llours valve.

80-15 Excess feed Secondary Feedwater None None 65.2 lone None water flow.

Coolant Pumps llours z~

80-16 Ilydraulic oil Secondary Circulator 50-267/80-Repaired oil 102.7 None None i

line leak.

Coolant hpass Valve 4 5/ 03-L-0 leak.

Ilours 80-17 Electco-hy-Turbine 24 Volt Power None None 959.2 Repaired None draulic tur-Supply llours purifica-bine control tion train failure.

Inlet Scheduled valve.

Re-shutdown placed one started.

control rod

<trive.

Overhaul engine driven fire water pump.

Repair leaking steam generator tiemp valve.

Repair hy' Jraulic snubbers.

4

2. 0 PLANT OlffAGES OR FORCED REDUCTIONS IN POWER e

t HA AN S AFE1T RADIATION REtIASE kEl.ATED Q)R-ASSOCI ATED Willi OUT-CORRECTIVE ACTION RECTIVE MAIN-AGE W11101 ACCOtINTS kELATED RE-TAKFN TO REDtkZ TENANCE PER-FOR HORE TilAN 10Z PORTADif.

Tile PROBABIIITY OF OPERATING B)RW D DURING OF AIJA1WABl.E ANNLfA',

NLIMhE R PROXIHATE CAttiE SYSTEH HA. LOR COf fPf1NENT OCCilRRENCE RECtIRRENCE TlHF. IDST T11E Ut4 AGE VAI.UE 80-18 Turbine Seconda ry #2 Stop Valve None Replaced solen-2.2 None None taken off Coolant Solenoid old.

Ilours 1ine to check stop valve.

80-19 Exciter Secondary Exciter None None 30.5 None None b reake r Coolant flours opened.

80-20 Low primary P rimary llelium None Increased None None coolant pres-Coolant Inventory helium inven-

sure, tory.

I 80-21 Spurious loop Plant Ultrasonic None Restored system 1.9 None None shutdown.

Protec-Noise Trip after testing.

Ilours I

t tive Sys-tem 80-22 Ilydraulle llydraulic Blank Flange None Replaced "0" 134.9 None None oil leak.

Power ring.

Ilours Unit 80-23 Testing P ri mary Co re None None None None Coo lan t 80-24 Testing P ri ma ry Core None None None None Coolant 80-25 llydraulic Secondary Circulator None Repaired 17.0 None None oil leak.

Coolant Speed Valve leaking line.

liburs 80-26 Steam leak.

Secondary llo t Reheat None Rewelded line.

36.7 None None Coolant Drain I.Ine llours 80-27 Testing Primary Core None None None None a

Coolant

,ni

(

T L

T EI 51A SO1 0U A 1 N1 t e

I1 U l

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E rn d n cS d n d

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PC SC PP t t SC S

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o 0 ;

3. 0 RADIATION EXPOSURES During the report period, two personnel received exposures in excess of I

100 mrem. Below is a tabulation of the information required by Technical Specification AC 7.5.1(b)3.

Number of Total Man-Rem Dose Assign-Personnel Exposure Exposure Dutv Function ment 1*

100 mren

.1 Portable radiation instrument 100%

calibration.

Number of Extremity Man-Rem Dose Assign-Personnel Exposure Exposure Duty Function ment 1*

120 mrem

.12 Portable radiation instrument 100%

calib ration.

1 250 mrem

.25 In-core thermocouple traverse.

100%

1 230 mrem

.23 In-core thermocouple traverse.

100%

Same individual.

To other personnel received exposures greater than 100 mrem / year for the report geriod.

4.0 FUEL EXAMINj.TIONS There was no indication of fuel failure found during anmf nation of onc irradiated fuel element.

I r

f l

l 2

l.

i I

r l

~

i

ML20003C417

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