Text

Annual Operating Rept,1980
	ML20003C619
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/06/1981
From:	; PUBLIC SERVICE CO. OF COLORADO
To:	;
References
	NUDOCS 8103060605
	Download: ML20003C619 (50)
	v • d • e

.O t

4 # -[4 g~

i

% b

-2 wE

~

h [q h 3

s s

g m

s

!^1) " $ N ')

PUBLIC SERVICE COMPANY OF COLORADO FURT ST. VRAIN NUCLEAR GENERATING STATION ANNUAL OPERATING REPORT NO, 10 j

i 1980 l

E I

i

D

' 1 INTRODUCTION 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, Facility Operating License No. DPR-34.

i r

P h

1 p

5 k

1 I

I w

F 2

r i

e e

t 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE This report contains the highlights of Fort St. Vrain, Unit No.1, operation i

under the provisions of the Nuclear Regulatory Commission Operating License, DP R-34.

This report is for the year of 1980.

1.1 -January J

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

[

approximately 1.5% for primary and seconds.cy coolant system cleanup.

A reactor scram and Loop 2 shutdcwn 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 I

feedwater leakage at V-2256 and to stop the hydraulic oil leakage at

(

HV-2254.

l 5

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 i

L i

outage to replace the 1B circulator started on January 17, 1980.

l.2 February j

The outage for 1B circulator replacement continued through the month

[

of February,1980.

l Decay heat removal continued, utilizing Loop 2 steam generatort on t

condensate. Decay heat levels decreased to the point that secondary l

coolant flow could be removed for calculated periods of time to allow

[

calibration of instrumentation.

i f

The prestressed concrete reactor vessel was pressurl=ed to 94 psia on February 12, 1980, and primary coolant cleanup was started, j

l Maintenance was completed on Loop 1, and it was returned to service on

{

February 13, 1980.

r Auxill.Ary boiler #1 repairs were completed, and the unit was tested f

4 and proven operational.

The reactor was brought critical on February 18, 1980, and training 1

starts were accomplished by all licensed and license trainee person-l I

nel1 requiring reactor starts.

I While the plant was shutdown for the circulator replacement, many maintenance items were completed.

Maintenance work concentrated i

mainly on leaking valves.

[

t j

On February 25, 1980, a small fire started on the service air com-

[

pressure discharge header.

The fire was contained without damage to

[

l the plant.

j u

t t

y,

4 O,

-1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.2 February (Cont'd)

On February 28, 1980, the annual Radiological Emergency Response Drill was conducted in conjunction with the state and local entities. This drill tested many revisions instituted as a result of Three Mile Is-land-2, as well as the revised State Radiological Emergency Response Plan.

1.3 March At the beginning of the month, preparations were made for plant start-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, the turbine generator actual overspeed tests were performed. The unit i

was resynchronized af ter the test, and the electrical load was in-creased to 100 MW.

Excessive oxidant contaminants in the primary coolant helium, as well as various control system problems caused the electrical load capa-bility to be somewhat variable over the next several days of operation.

t Early in the morning of March 11, 1980, the east side return water distribution header on the main cooling tower ruptured.

Large amounts of circulating water spilled over the distribution box near the rup-4 ture onto the ground. The yard drainage system in this area did not have the capability to handle this quantity of water, allowing the water level in the surrounding area to reach a depth of several inches.

Some of this water entered the manhole containing cables and associ-ated conduits for the circulating water pump system. This water damaged several electrical motors of the circulating system. The main tu.-bine generator was tripped and the reactor scrammed when it was evident that condenser vacuum could not be maintained.

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

because of the damage to the circulating water pumps and the loss of acceptable feedwater chemistry, reactor power could not be int: eased above 2% until March 15, 1980.

The turb1ne generator was synchronized on March 16, 1980, and lead was gradually increased to 230 Mi on March 18 and remained at that level until March 21, 1980.

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 from high hot reheat temperature when attemperation was taken off Loop 1 and remained shutdown until March 23.

Low power operation con-r tinued until March 25, awaiting cleanup of secondary coolant.

On March 26, 1980, the turbine generator was synchronized and electric l

load increased to 225 MW.

l

. 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) e 1.3 Mar;h (Cont'd)

A leaking 1B circulator steam piping flange caused reactor power to be lowered to 50% on March 26. While IB circulator was off, LA cir-culator buffer seal malf unctioned. The 1A circulator and Loop 1 were shutdown manually and reactor power decreased to 2%.

The 1A and 1B i

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

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

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

190 FMe, and held approximately at this level pending cleanup of the 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 se rvice.

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 185 MR.

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

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 MRe 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 over the next few days between 30% and 65% as dictated by primary coolant oxidant levels. The 1B and 1C circulators were removed from service during this period (April 10 to April 18, 1980) to observe the effect, if any, on moisture ingress. No effect was observed.

l I

i k

i i

Q i

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE' (Cont'd) 1.4 ' April (Cont'd) r On April 18, 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 action of 1A circulator penetration rupture disk.

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

until April 21, 1980, to allow license candidates to complete required l

Nuclear Regulatory Commission reactor starts.

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

On this date,1B circulator tripped from seal malfunction problems. The circulator was restarted and power raised to 50% until an increase in oxidants required lowerin; region outlet temperature below 1200*F.

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

The loop was recovered and reactor power was increased to approximately 30%.

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 i

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 tank. Recovery of the loop was accomplished, and the load was increased to approximately 1301M.

1.5 Mav On May 1,1980,1B circulator tripped on loss of bearing water 'ie to an upset caused by changing the bearing water y-strainers. The 13 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 i

was adjusted to correct the problem.

During this event, activity was I

also detected in the Reactor Building due to valve packing leaks on the buffer helium dryer.

I I

O i.

1.0 NARRATIVE

SUMMARY

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 tj primary coolant oxidant levels. On May 7,1980, the pelton supply to the Loop 2 circulators was icolated 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 tempera-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 1

definite change was observed.

Operation continued to be limited by primary coolant oxidants being greater than 10 ppm through May 13, 1980.

On May 13, 1980, #5 feedwater heater developed a tube leak.

The secon-dary coolant flow path was routed to the emergency feedwater 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 powce was at approximately 50% and 130 !Me, and continued at that level until Iby 24.

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

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

On May 21, 1980, an on-site public meeting was held with the Nuclear Regulatory Commission 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 circulater, which was removed during the January,1980, shutdown, was examined by General Atomic Company at San Diego, 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 M4e, 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.

?

l i

g, i

l i

1.0 - NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) l 1.6 June (Cont'd) l

[

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

system capability.

On June 12, 1980, with reactor power at 68% and 194.fRe, main cooling tower blowdown was swapped from hot to cold side to comply with EPA temperature-limits.

On June 17,1980,1B helium circulator tripped due to high buffer-mid-buffer, and approximately three hours later, lA circulator tripped for the same reason, causing a loop shutdown.

The turbine generator was manually tripped. Activity increased in the low pressure separa-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-1 phragm on the pressure differential transmitter for the IB circulator t

main drain valve.

Loop 1 was recovered and reactor power was increased to 5%.

Reactor power was held at 10%, with 1A,1C, and 1D circulators oper-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.

1 On June 20, lA circulator tripped causing Loop 1 to shutdown. Power was redu. -d to approximately 10% and held. Moisture in the primary coolant lacreased in excess of 100 ppm, and activity was noted in the

?

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

d The operable main drain differential pressure transmitter from the lA helium circulator was installed on 1B helium circulator.

I I

Primary coolant moisture levels decreased, and Loop 1 steam generator was returned to service on June 21, with reactor power at 3.5% and I

i moisture down to 19 ppm. Power was increased to 8% and orifices were set.

Primary coolant moisture leveled out at 40 ppm.

f Reactor power was reduced to leis than 2% on June 23, and Loop 2 was shutdown to repair leaking va3 es.

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

l Valve repairs were completed June 24, and Loop 2 was recovered.

l 4

l On June 27, with the reactor at 7% power, the main drain differential pressure transmitter was re-installed on lA circulator. Primary coolant moisture increased rapidly when'lA circulator was brought up to speed.

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

moisture reduction.

4 i

i r-i.

~

m.

. w 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.6 June (Cont'd)

On June 29, reactor <,ower was increased to 20%, and on June 30, the turbine generator tas synchronized and power increased to 29% and 50 MWe.

Reactor power was increased to 45% with a turbine generator load of 125 MRe, but was later reduced due to an increase in primary coolant moisture.

1.7 July On July 1, 1980, with the reactor operating at 45% power (125 MWe), a gradual loss of vacuum necessitated a turbine generator load reduction during the period required for location and isolation of the condenser leak. A leaking valve was discovered to be the cause of the vacuum problem.

After condenser vacuum was recovered, the turbine generacor load was increased to the previous level of 45% (125 MWe).

Plant operation continued at approximately 45% and 125 MRe te hold the core region outlet temperature average below 1200*F, due to primary coolant oxidant levels greater than 10 ppm.

On July 4, 1980, L.ble Mountain Load Dispatch requested a 30 BMe recuction in turbine gener-ator output. This resulted in a reactor power reduction to approxi-mately 37%.

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 core region outlet temperature was greater than 1200*F at this power level; therefore, 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 brought critical on 'uly 9, 1980, and operated at a nominal 2% until July 17, 1980. The delay in escalation of power was due to the inability to complete a required annual Surveillance Test on the emergency diesel generator set lA.

During the performance of this surveillance, a leaking heat exchanger was discovered and was re-placed, but the main problem involved the governor control system and 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-t dary coolant system necessitated shutting down Loop 1 for repairs and a return to 2% power.

l I

h l

2

O e 1.0 NARRATIVE SU)DfARY 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% or July 22, at which time the turbine generator was synchronized and loaded to 125 MWe as power was.ncreased to 45%.

During this gower *;ise, 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 MWe.

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.

1.8 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 flow path was established through the emergency feedwater header de,e 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%, rer:ltin

, an average core outlet temperature of 1220.F, as primary coc ant oxidants had been re-duced to a total of 8.8 ppm. Operation continued with these con-ditions 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 unstable feedwater control caused by the feedpump speed control system.

Preparations for a reactor restart were made almost immediately, and criticality was attained at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on August 6, 1980.

On August 6, reactor power was increased to 27%, and on August 7,

.980, the main turbine generator was placed in service.

Reactor power 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 p?rt, due to the undersizing of the service water piping supplying the Reactor Building chillers. An additional condition that developed, which also limited plant operation, was nhe presence of a bad bearing on "A" circulating water pump.

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

. 1.0 NARRATIVE SUM'iARY OF OPERATING EXPERIENCE (Cop *;'d) 1.8 August (Cont'd)

Plant operation continued as dictated by conditions Jeacribed 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 feedpurp 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 steam turbine bypass valve (PV-2244) which necessitated iso-lating Loop 2 hydraulic oil system and Loop 2 group 2 secondary coolant loop. Reactor power was also reduced to 2%, and the reactor scrammed as prescribed by the Emergency Procedures.

During the shutdown for re-pair of the hydraulic oil leak and oil cleantp, the leaking "B" boiler feedpump normal feedwater header isolation valve was repaired, along with repair of "A" boiler feedpump 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 1.60 MRe.

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

Per Technical Specification requirements, these problecs must be corrected within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or an orderly 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 + 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 + 24 V power, the plant electricians inadvertently caused a turbine runback.

The resultant transient caused a circulator in each loop to be tripped by plant protective system action.

The turbine generator was manually 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 prestressed concrete re-actor vessel was depressurized to O psig and Loop 1 steam generators and circulators were cleared for maintenance.

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

?

main condenser.

I:

t 1.0 NARRATIVE SUOfARY OF OPERATIN,G, F7ERIENCE (Cont'd) _

[

G 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.

2 On September 13, the bypass flash tank drains were directed to the da-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 pumps. 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.

On 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-l 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 5c. The increased operating temperatures aided the cleanup of feedwater and primary coolant impurities.

An internal oil leak developed or lA helium circulator speed control

,j valve, and the solenoid valves were repaired.

I t

r t s k

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.10 October (Cont 'd)

On October 4, a pressure switch (PS-ll227) failure resulted in inter-space pressures equalizing with primary coolant pressures.

The pres-sure switch was repaired, and teactor power was increased to 8%.

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

A power level of 23% was attained on October 9, and the turbine gener-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 I

repaired and emergency feedwater restored to service.

Reactor gower was increased to 49%.

i On October 10, while the base mounting of the turbine generator main exciter bearing mount was being tightened, due to vibration problems, and an exciter control box was accidentally struck, causing the turbine i

generator to trip. The spike in voltage caused a trip of #3 non-inter-ruptible bus inverter.

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 aeduced to 29% to enable repair of buffer helium dryer valves.

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

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

on October 22, a Loop 1 shutdown occurred while testing ultrasonic pipe rupture detectors. Loop 1 was recovered and electric power gener-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.

On October 24, the hydraulic oil seals were repaired.

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

Ii

! i i

1.0 NARRATIVE

SUMMARY

OF OPEkATING EXPERIENCE (Cont'd) 1.10 October (Cont'd) l On October 25,~ power was increased to 28% and electric generation re-sumed.

On October 30, reactor power was increased to 49%,

Average core out-

{

let temperatures were held to less than 1200'F, due to primary coolant oxidant levels in excess of 10 ppm.

1.11 November t

At the beginning of the month, reactor power was 50%, and the turbine f

generator load was 140 MR, 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 l

time the total oxidants had decreased to approximately 6.6 ppm, and i

power escalation was resumed up to 60% reactor power with an electrical i

load at 170 MR(e). Primary coolant oxidants started trending upwards as a result of the increase in reactor power.

On November 5,1980, the thintenance Department started testing several I

vent stack 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 Noxamber 7,1980, r

at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months .

During this period, primary coolant oxicants decreased enough to allow power escalation to be resumed. Shortly thereafter, t

during an automatic transfer of buffer helium dryer towerr,, a high pressure condition occurred in the "off line" tower indic.ating leaking i

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, wh?n a power reduction to 40% was made in preparation for reactor core fluc-l j

tuation testing.

f l

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

l' with various core orifice configurations to satisfy test criteria.

[

Testing was completed on November 15, 1980, and resulting data for-warded to General Atomic Company for analysis. At the completion of i

i l

testing, reactor power and turbine generator loads were increased to i

66% and 208 MWe respectively. The dryer regeneration valve (HV-21352) again failed to close qroperly, causing a further increase in primary coolant oxidants. The problem was corrected by stroking the valve.

i F

l I

l 1

I s

1 l

I I

f

j

- 1.0 NARRATIVE SUMMAPJ 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 Maintenance 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 accumulator 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 aower escalation commenced.

The return to 69% power went very smoothly with only a slight delay at 30% power to put the main turbine generator on line and to verify the acceptability 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 heater due to suspected tube leaks. Plant conditions remained the same until power was reduced to 41% on December 12, 1980, to conduct fluctuation l

tests.

Upon completion of testing, moisture ingress into the primary l

coolant system required the generator to be taken off line, and reactor power was reduced to 8%.

Subsequent investigation found no source of l

moisture ingress.

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

I

. 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont'd) 1.12 December (Cont'd)

On December 27, 1980, a reactor scram on high reheat steam temperatures occurred due to control system problems experienced while increasing turbine load.

The reactor was taken critical the same day, the generator placed on line, and reactor power gradually increased to 68% by December 28, 1980.

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-ator trip. Loop 2 was recovered, and the generator was placed on line after the transmitter was repaired.

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

The stroke test failed to free the valve so the reactor was scrammed at this time, and the turbine generator tripped.

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

8

SICNIFICANT MAT?rrENANCE-

SUMMARY

~

TIME Il3NTI FICA-REQtfl RED EFFECT ON TION NUMBER SYSTEtt/

NATURE OF IUR SA W. OFERATION AND DATE OWE'ONI NT CALSE OF mal.FthCTION _

RESULTS OF MALFINCTION MAINTENANCF CORRECTIVE ACTION MlHPISTION OF 11tF. RFJLCn>R 78-2-231 SV-2110 Normal Wear Valve leaks through Co rrec-Replaced trim set.

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

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

Correc-Replaced valve.

8 Hours None t

11-6-79 tive 78-8-521 V-7296 Normal Wear Valve leaked through.

Co rrec-Replaced valve.

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

Correc-Replaced valve.

4 llours None 11-30-79 tive 79-5-84 3 liv-2217 Normal Wear 7alve leaked throt gh Co rrec-Rebuilt poppet 2 Days None 2-20-80 excessively, tive block and cylinder.

b 79-7-634 ilV-2224 Normal Wear Leal 5 between cylinder Correc-Installed new "O" 10 Hours None i

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

79-8-146 IIV-2224 Normal 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.

Correc-Replaced seal ring I Lay None 12-6-79 hinge pin on V-tive and hinge pin.

2256.

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

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

mately seat and disc 10 llours wear.

79-8-520 V-72102 Normal Wear Valve leaked through.

Correc-Replaced valve.

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

Correc-Replaced valve-16 Ilours None 11-4-79 tive L

79-9-13 ilV-2224 Normal Wear Bonnet ^ seal leaks.

Correc-Replaced bonnet 2 Days None 11-20-79 tive seal.

L

SIGNIFICANT MAINTENANCE

SUMMARY

1 T l HT.

I BGMTI FICA-REr}ti! RFD O ncT t W TION NDMBt'M SYSlat/

NATURE OF nlR SA R OPFRATION AND DATE COPCtWENT Call';E OF ntl.FtNCTION HESI:LTS OF HAltit4LTi(N HAINTENANCE rORRFCTIVE ACTION Cliff t.ETIIW OF 111F FEACTOR 79-9-30 ilV-2224 Normal 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 re c-Replaced seal.

2 Days None 2-2-80 tive 79-10-101 FE-1122 Normal Wear Incorrect flow indi-Correc-Replaced flow ele-3 Days None 6 80 cation.

tive ment with spare.

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

Co rrec-Repaired valve's Approxi-None 12-12-79 wear.

tive seat and disc.

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

Co rrec-Repaired seats.

Approxi-None 11-28-79 valve manifold.

tive mately 3 11ours a

i 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 IIV-Lights on ilS-21205, Co rrec-Replaced IIV-21205-1 llour None 11 79 21205-2.

21101. 2189-1, and tive 2.

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

79-12-401 CTI-BR4 Bad chip.

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

I llour 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 No rmal Wea r Leaky tubes on standby Correc-Plugged leaky 1 Month None 7-3-80 diesel generator air tive tubes.

i_

handling. unit. ________ _ ______....

SIGNIFICANT MAINTENANCE SUletARY TIME I ldN'II FI CA -

RFittil RED F.HECT eri TION NUMP.ER SYSTEM /

NATilRE OF FUR SAR Ol'ERATitre AN D DA1 E 045'd W3ENT CAtriE OF KU.f1t4CTION RESUI.TS OF MAI. Fit 4CTIu HAtNITNANCE CORRF(TIVE ACTION CitG'I ETI ON OF 111E REArTOR 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 MM-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 light pre-amp.

79-12-533 PDIS-21397 Plugged sense Faulty IB circulator Correc-Blew down instru-1 Day None 12-26-79 line and bad Y strainer differ-tive ment sense lines snubbers.

pressure gauge.

4 and installed new snubbers.

79-12-545 Pall-110 7-Bad alarm card.

Alarm Fall-1107-10 on Correc-Alarm card re-2 Hours None L

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.

Elour circulator.

79-12-573 PV-22167 Normal Wear Valve lecks through.

Co rrec-Repaired valve in-8 Hours None 9-25-80 tive ternals.

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

Guard helium flow high Correc-Repaired alarm 1/2 None 12-28-79 alarm energized on 1C tive card.

Ilour circulator.

79-12-576 IIV-9316-1 Bad solenoid.

Air blowing out of liv-Co rrec-Replaced solenoid 2 Ilours None 12-27-79 9316-1 and buzzing.

tive valve.

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

1B circulator brake Correc-Replaced llV-21205-1 Day None 12-28-79 and ceal 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

servo, tive guides and pre-amp.

guides and re-flected light

. pre" amp.

SIG11 FICAE4T MAINTENANCE

SUMMARY

TIME I IENTI FI CA-ret}UI RFD FFFECT IN Tite NUMBER SYSTErt/

NAlUNE OF R)R SAFE OPERATItri AND DATE OW1'tWLNT CAltSE OF MAI.nr44' TION RESUI.TS OF MITIM714r4 HAIN 11N Af4LE CURRECTIVE ACTlay4 O rtPI.ETi tM4 OFlilE RMrluR 79-12-644 tiL S-1115 Bad disc in PDV-MIS-1115 mirror temp-Correc-Replaced valve 1 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 Hours None 1 80 duit.

for P-9106X broken.

tive duit.

79-12-714 IIV-2254 Wo rn "O" rings.

IIV-2254 flange leakage Correc-Installed new "0" 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-lioned pin hole and 1. Day None 1-4-80 header check valve tive installed new seal.

leaking at pin.

e I

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

Air supply tubing to Correc-Replaced broken 4 Ilours None 1-2-80 liv-21416-1 broken.

tive tubing.

80-1-18 Region 2 Bad alarm card.

Ilopper pressure high Correc-Replaced alarm 2 Hours 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 None 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.

C.

,ec-Rebuilt valve.

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

Relay CR-17blA 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,

' Ilours None 1-8-80 and loose fit-tive tightened fittings.

tings.

SICNIFICANT !!AItNENANCE 'SUMRiRY l

YINE litHTI FI CA-I RD)tt! RFD EFtECT 4W TSON NUh8t.w SYSTE!!/

NATUNE OF D)R SAFY OPERATION AND DATt; O)Pf0NF.NT CALLE OF HALMNCTION R ES t!I.F F PtAt FLI4CTION MAIN TE N ANCE OutRFCTIVE ACTION 01f1Pl.ETION OF UIE Rth" TOR 80-1-81 B FS-218E Snubber leak, Snubber leaking oil.

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

tive tightened fittings.

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

Co rrec-Replaced and re-

\\pproxi-None 1-25-80 wear.

tive paired parts.

nately 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 IIV-222 3 Normal Wear Leaking oil.

Correc-Rebuilt ope ra to r.

2 Days None 2-20-80 tive 80-1-160 PS-11234 Instrument Drift Trip out of specifi-Co rrec-Replaced switch 1/2 None 2-9-80 cation.

tive and recalibrated.

llour i

80-1-168 ilv-2217 Normal Wear Valve leaked through.

Co rre c-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 9-24-80 tive 80-1-203 PDV-2551 Disc and seat Valve leaked past.

Co rrec-Replaced disc.

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

tive nately 4 llours 80-1-224 C-820lS No rmal Wea r Machine was noisy.

Co rrec-Overhauled com-5 Days None 2 80 tive pressor.

80-1-240 ilV-21236 Faulty "0" ring Valve would not open.

Correc-Replaced "O" ring.

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

tive

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

tive other snubber.

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

3 llours None 2-20-80 tain system pressure.

tive A

SIGNIr'ICANT MAINTENANCE SIDefARY TIME

!!1NTI FI CA-REQti! RED EFITc7 EN TI ON N UMBE R SYSTtJt/

NATUkE OF H)R SAIT (TLRATitN At40 DATL OttFONtNT CAtr.E OF HAI.HNCTION RESU).TS OF PtAI.HNCIltti MAI N TEN ANCE CORRFCilVE ACTION Otfl.ETION OF Tile REAPWR 80-2-120 P-910SX Normal Wear Ilydraulic leak at Correc-Rebuilt pump.

2 Days None 2 80

pump, tive 80-2-168 C-8203 Solenoid and "C" instrument air com-Co rrec-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 P V-22129/

Normal Wear Valves leaked through.

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

80-2-223 C-820 3 Normal Wear Air compressor inoper-Co rrec-Rebuilt the air 3 Days None 3-5-80 able.

tive compressor.

80-2-295 S-2115 Increased resis-Lost speed indication Correc-Replaced cable 2 Hours None 3-19-80 tance in con-for IB circulator tive connector and re-L nector.

water turbine drive balanced circuit.

'i' (1 channel only).

80-2-305 P-2105 Nor cal Wear Seal leakage excessive. Correc-Replaced pump seal. 16 !!ours None 9-25-83 tive 80-2-324 V-22184 Normal Wear Upst ream relief valve Correc-Replaced gasket.

I Day None 7-2n-80

_ leaking.

tive 80-2-332 RWP Logic, Failed chip Z48 IMP light would not Correc-Replaced chip.

1/2 None 2 80 ir, module - Nat-clear.

tive llour yral end of life.

80-2-338 P-9101X Shaft out of Pump motor burned 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 Co rrec-Replaced control 2 Ilours None 3 80 panel (Woodward gene rator would not tive panel with spare.

2301).

load properly.

80-3-61 IIV-222 3 No rmal Wear 011 leak f rom operator. Co rre c-Peplaced "0" rings 2 Days None 3 80 tive in ope rator,

.-.--..i.-.-...---..

SIGNIFICANT MAINTENANCE SUliffARY

!PE I ttNTI FICA-REQUIRED EFFTCT (W TicN NUMBER SYSTDt/

NATURE OF FOR SATE OFERATIEW

_AND DATE

. Q W ONLNT

_ CAUSE OF HAI.RHCT!oN RF.SIUS OF HAl FINCTI(W

,HAIN11 NANCE CottRECTIVE ACTION O HrIETION OFJtE RFAcMQ,,

60-3-95 liv-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 Hours None 6-23-80 tive gaskets.

80-3-122 TDSL-22105 Bad chip / normal Single channel trip Co rrec-Replaced chip.

2 llours None 3-10-80 end of life, for reheat temperature tive di f feren tial.

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

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

80-3-142 FE-1117 Normal Wear Moisture monitor flow Correc-Replaced flow ele-8 Ilours None 12-19-80 element failed.

tive ment.

L w

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

Co rrec-Replaced disc.

3 Hours None i

3-9-80 tive 80-3-140 TE-22144 Shorted out due The temperature chan-Co rrec-Replaced element.

2 llours None 3 80 to normal wear.

nel failed down scale.

tive 80-3-141 MM-1122 Normal Wear Insuf ficient flow for Correc-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 1.ost one speed channel Correc-Repaired bad con-3 llours None 3-12-80 for circulator trip.

tive nection at pin 24 of SM-21172.

Re-placed cable.

80-3-216 K-9203 Normal Wear "A" emergency diesel Co rrec-Replaced bad alarm 2 IIours N,one 4 80 generator high oil tive ca rd.

temperature alarms spuriously.

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

Correc-Rebuilt valve seat 16 Ilours None 8 80 tive and disc.

SIGNIFICAt3T MAINTENANCE SUftMARY TIME I DENTI FICA-REQUIWED EFFECT 008 T!ON NUMBER SYSTDt/

NATURE OF fDR SAFE OPF.PATION

_AND DATE u w CNENT

_ CAIGE OF HALHNCTION _

RESULTS OF HALFINCTION MAINTENANCE CORRECTIVE ACTION CtM t.ETION OF Tile IttAcIUR 80-3-271 SC-2111 Normal Wear Loss of circulator Co rrec-Repaired con-1 Hour None 3 80 speed signal, tive nection.

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

4 Ilours None 3-14-80 inoperable.

tive 80-3-247 SV-2111 Normal end of Valve went closed and Co r rec-Replaced solenoid.

2 Hours Fone 3-16-80 life for 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-Correc-Replaced 2" valve 16 Hours None e'4 5-16-80 21244 21243 and 21244.

tive trim with 1 3/8" Y

valve trim.

80-3-344 IIV-2303 Overload on Valve would not oper-Co rrec-Replaced overload.

Approxi-None 6-10-80 breaker stuck.

ate.

tive mately 2 Ilours 80-3-347 liv-2302 Normal Wear Valve would not close.

Co rre c-Rewound operator 32 Hours None 9-5-80 tive motor and replaced position switch.

80-3-348 MM-ll22 Normal Wear low sample flow indi-Correc-Replaced with 3 Days None 6-27-80 cation.

tive spare.

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 rrec-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 Hours None 3-25-80 Generator after being shutdown tive from Control Room.

g

SIGNIFICANT MAINTENANCE

SUMMARY

TIME I lt.NTI FI CA-REQUI RED EFITCT ON TION NtIMBER SYSTEft/

NATURE OF IT)R SAR Ol'ERATIIW4 AND DATE O H*t ttENT

(' ALEE OF HAI.FtNCTION RESUI.TS OF mal.FINCTitH HAI N1T NANtT CORRECTIVE ACTION 4Xt9't.ETI ON OF 1NE RFAGnR 80- F431 C-2102 No rmal Wear Steam leak at circula-Correc-Installed new flex 27 Ilours None 3-29-80 tor flange.

t*ve gaskets.

P't 4 3 3 P V-2124 3 Normal Wear Leakage through PV-Co rrec-Replaced trim in 4 Ilours None 5-16-80 21243.

tive valve.

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

Co rrec-Replaced teflon 4 Ilours None 3-28-80 tive valve seat.

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

Co rrec-Replaced Al on de-2 Ilours None 3-28-80 11 of life, tive tector pre-amp.

80-3-463 C-820lS Normal Wear 1B instrument air com-Co rrec-Performed 5-year 2 Weeks None 4-16-80 pressor noisy.

tive inspection.

Re-built and repaired parts as necessary.

6 v

I 80-3-464 FE-Ill7 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 Hours None 4-3-80 l i fe.

chip.

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

life.

correctly.

tive lifier and Q-102

_t_ran s i s t e r.

80-4-62 CC-2A1 Normal end of Low input voltage on Correc-Replaced Z-4 3 log-2 llours None 4-5-80 l i fe.

logic chip.

tive ic chip.

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

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

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

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

2 Ilours Nhne 5-1-80 scale.

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

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

SIGNIFICANT MAINTINANCE SUMFiARY TIME l id.NTI FI CA-REQUI RED EFtVCT (W TloN NUM8ER SYSTEHf NATURE OF FOR SA E OFFRATION AND IsATE Cott'ONENT CALEE OF HAI.RNCTION RESUI.TS OF MAI.FINCTitN MAINTENANCE CORRF.CTIVE ACTION 00FFIETION OF Tile REACTOR 80-4-130 SV-2115 Normal Wear Valve leaking through.

Correc-Replaced trim and 4 Ilours None 9-6-80

_tive calib ra ted.

80-4-131 SV-2116 Normal Wear Valvc leaks through.

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 Ilours None 4 80 valve of bearing water tive stem.

cooler will not turn.

80-4-148 V-21476 Normal Wear Loop 1 bearing water Correc-Repaired valve.

3 Days None 9-13-80 safety valve leaking tive th ro ugh.

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

Co rrec-Replaced bad motor. 3 Hours None L

5-16-80 tive y

80-4-170 CTI-BR4 Normal end of Low input voltage.

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

life, tive Z-37.

80-4-225 IIV-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 PV-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-1ency feedwater header.

80-4-254 P-9102X Normal Wear Pump vibrating exces-Co rrec-Replaced pump 1 Day None 5-2-80 sively.

tive coupling.

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

12 Ilours N:one 5-23-80 on pump.

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

and Z-32.

i

SIGNIFICANT MAINTENANCE

SUMMARY

~~

TlHE llCNTI FICA-REQttIRED EFPFCT (N Time NUMBER SYSTil1/

NAftlRE OF FOR SAFE OrFRAileN AND DATE cott'I Nt NT CALEE OF Mt.FINCT f 3N RESUI.TT. OF HALFINCTI(N HAIN ITN ANCE CORREt.TIVE ACTION Cut 1Pl.ETI ON or Tite RFA(~IUR 80-4-304 Ala rm Normal Wear loop 2 reheat steam Correc-Repaired faulty 1 llour 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 r rec-Repacked valve.

1 llour None 9-13-80 tive 80-5-66 ti-92835 Normal Wear Moisture trap on Correc-Installed new 1 llour None 5-5-80 starting air line for tive trap.

"B" diesel generator blew off petcock.

80-5-83 FfM-1115 Sample flow Samp.le flow control Correc-Replaced DC power 4 Ilours None 5-12-80 valve adjusting operating abnormally.

tive supply filter ca-pot operating pacitor.

poorly.

80-5-85 P V-21244-1 Normal Wear pV-21244 1 leaking at Co r rec-Replaced pipe 4 llours None 5 80 approximately 1/2 gpm.

tive downstream of valve.

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

Correc-Repacktzd valse.

2 Ilours None 9-3-80 tive 80-5-195 V-21268-1 Normal Wear Safety valve leaking Correc-Valve repaired and 16 Ilours None 5 80 t hro 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 r rec-Put devcon on gas-1 Day None 5 80 seat ring and body.

tive ket surface.

Re-placed valve.

d

SIGNIFICANT llAINTENANCE SUmiARY TIME IDENilFICA-

U' QUI RE D EFFt.CT (H TiuN NUNBER SYSTEN/

NATURE OF H)R SAFE Ol'ERATItW AND DATE CotFUNENT CAUSE OF mal.FINCTION RESULTS OF etAI.11NCTION MAI.Tn NANCE CORRECTIVE ACTION ritFl.ETinN OF Tile REA(*IOR 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-1175 Normal Wear Circulator inlet temp-Co rrec-Replaced CR-10 and 2 Ilours 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 Ilours None 6 80 ber.

tive and valve.

80-5-277 CC-2A1 Normal Wear Low voltage at input Co rrec-Replaced Z-44.

2 llours 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 flours None 5-23-80 to pin P.

tive 4

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

tive placed.

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

Rese rve shutdown bot-Co rrec-Replaced switch.

2 Ilours None 6-19-80 t1e lost pressure due t : ve, to leak.

-- =

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

1 Ilour None 5 80 completed due to tive chip.

80-5--306 SC-8201 No rmal Wear Purge flow on "A" in-Correc-Replaced llumistat 2 llours None 9-2-80 strument air dryer tive at sensing element.

not working properly, s

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

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

O

SIGNIFICANT MAINTENANCE

SUMMARY

{ 4:st:

TIME NTI FI CA-REQUlfd D EFfECT <W lON NUMBER SY STEtt/

NATURE OF FOR S AW Ol'E RATif W AND DATE Cots MENT CAltSE OF HAI.rtNCTION RESUI.TS OF MAIJtNCTION HAINTF N ANCE OiRRECTIVE ACTION CorflETION OF 11tE REACTOR 80- 5-349 CT-1BL3 Normal end of Low input voltage on Co r r< c-Replaced Z-9 chip.

Approxi-None 6-2-80 life.

chip inputs.

tive mately 2 Ilours 80-5-350 CTI-B R4 Normal end of Low input voltage on Co r rec-Replaced chip.

App ro xi-None 6-2-80 life.

chip's inputs.

tive mately 2 llours 80-6-6 FE/ FT-Normal Wear Faulty indication on Co r rec-Replaced upper 4 llours None 6-6-80 21138 1C helium circulator tive seal and force backup bearing water.

motor and cali-brated transmitt g.

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

trouble alarm woul !

tive CRll, CR9, C3.

not come up with I:

8w 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.

80-6-35 Il0S-30 Personnel using Snubber upside down Co rre c--

Filled snubber 4 llours None 6-3-80 equipment as (cylinder rotated).

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

fo rm.

80-6-45 ilV-46246-1 Normal Wear Valve would not oper-Co rrec-Reconnected valve Approxi-None 6-4-80 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 Co rrec-Replaced gauge App ro xi-None 6-10-80 life.

Indicate discharge tive calibrate.

mately p ressure.

2 Ilours 80-6-190 ilV-2217 Normal Wear Leakage on 5-valve Co rrec-Replaced seat and 1 Ilour None 6-11-80 manifold of IIV-2217.

tive "0" ring in 5-valve manifold.

Replaced L-valve.

SIGNIFICANT MAI?TTENAN' E

SUMMARY

l C

TlHE IIENTI FI CA-REQUIREli EFFECT E0 TION NUMBER SYSTEll/

NATUkE OF FUR SA W. OPERATI(W ANI) DATE OMS'tNENT CAUSE OF HAI.FthiCTION RESUI.TS OF HAI.FIHCTIf N HAIN TENANCE (X1RRECTIVE ACTION CEWS't.ETI(44 or 11tE REACTOR 80-6-197 IT-2211 Normal Wear Flow transmitter leaked Correc-Replaced fitting.

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

tive mately 2 Ilours 80-6-208 V-21298 Normal Wear Backup bearing water Co rrec-Repaired valve per 12 llours None 9-1-80 relief valve leaking tive procedure.

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 IIours 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 Correc-Replaced bellows Approxi-None, caused

[

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

assembly, mately loop shut-y allowing bearing Lool' 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-l down.

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

from plant protective tive new TE.

mately system.

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

Correc-Replaced motor.

Approxi-None 6 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 m.

SICNIFICANT MAINTENANCE

SUMMARY

l IthETIFICA-Tite Rt:QUINED.

EFtTCT tH TION NUMBER SYSTt2t/

NATURE OF PT)R SAFE OPERAThWI AN D l>A1 E O NONENT CALEE OF MALFINCTION RESul.TS OF HALFtHCTitW HAIN1ENANCE CORRECTIVE ACTION COMPl.ETION OF Tile RFALTOR 80-6-323 IIV-21193-2 Normal Wear Valve leaked by.

Co rrec-Replaced valve.

Approxi-None 6 80 tive mately 4 Ilours 80-6-324 V-2214 Normal Wear Valve leaks at flange.

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

80-6-346 IIS-2238 Normal Wear Spring broken on Co rrec-Repaired spring.

2 Ilours None 6-26-80

" spring-return" type tive handswitch.

80-6-350 C-8203 Normal fouling Instrument 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.

s 80-6-353 TS-8245 Normal Wear Temperature switch for Correc-Replaced and cali-2 Ilours None f

u 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% IMP trip out of Correc-Replaced amplifier Approxi-None 6-27-80

life, specified limits.

tive A51 (702) and mately calibrated per 1 llour procedure.

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

tive and one of the mately discharge valves.

5 Ilours s

80-6-3os ilv-22225 Normal Wear Valve leaks at flange.

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

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

Co rrec-Replaced valve 8 Hours 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 llour

SIGNIFICANT MAINTENANCE

SUMMARY

TlHE l itNTI FICA-RFQUIRED FFn:CT (W TION NUMBEat SY STEtt/

NATURE OF FOR SAFE (WERATIIN AN D DA1E n m WLNT CAUSE OF HAI.FthCTION RESULTS OF HAI FLHCTitH HAIN1YNANCE COHRFCTIVE ACTION CliHPIETION OF 11tE RF.AC1HR 80-6-404 CT-2A2 Normal end of luput voltage zero Co rre c-Replaced Qll in Approxi-None 7-1-80 life.

with no modules tive LRD-1.

Checked mately t rip ped.

operation per RP-2 llours 86, 80-6-405 L RI)-1 402-Normal end of Single channel trip on Correc-Replaced Qll in Approxi-None 7-1-80 P2 li fe.

ID circulator.

tive LRD-1 404-P2 and mately checked per RP-86 2 Ilours 80-7-29 FC-2205/

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

2 Ilours capaci to rs.

100 K1b/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 RP-433.

I flour 7

80 71 IIV-21352 liigh temperature Cross tower leakage Correc-Replaced teflon App roxi-Increased 7-7-80 and excess wear in the buffer helium tive disc with a brass mately moisture caused valve d ry e r.

disc.

2 Ilours level in lisc to leak.

the primary coolant.

80-7-96 ilV-22225 Normal Wear Valve blowing steam.

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

80-7-100 SV-2111 Normal Wear SV-2111 would not open Co rrec-Replaced solenoid 1 Day None 7-9-80 via SC-2111.

tive valve.

80-7-101 Alarms Normal Wear IB circulator penetra-Correc-Replaced chips in 1 llour 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 rrec-Replaced hydraulic 2 Ilours None 7 80 line.

tive flex lirse.

80-7-142 Plant Pro-Normal Wear Low voltage at logic Correc-Replaced chips in 1 Ilour None 7 80 tective inputs.

tive logic module.

System

O SIGNIFICANT MAINTENANCE SUMRTRY TIME IIGNTI FI CA-REQtil RElk F FFttT IN TION NLIMBER SYSTIB/

NATttRE OF DDR S AFT. Ol'ERATIIW AND I ATE Cl@t NENT CAllSE OF HALRNcTION RESIFLTS OF HAl.FINCTI(N HAIN1ENANCE CURRECTIVF. ACTION Ct W lETION OF lilE REAC1DR 80-7-144 K-9204X Normal Wear Af ter cooler leakage.

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

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

tive chip.

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

Co rrec-Replaced valve 4 llours None 9-24-80

/IIV-Il04-tive discs and packing.

27 80-7-173 V-11677 Normal Wear Region 27 "ff' valve Correc-Polished stem and 4 Days None 9-24-80 leakage makes helium tive seat, installed cylinder change-out new disc, and re-difficult.

Installed valve, d,

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

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

80-7-233 C-8201 Normal Wear "A"

instrument air Co r rec-Replaced capillary 4 ~liours None 7-24-E,0 comprescor tripping tive tube assembly.

due to high water t empe ra ture.

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

Co rrec-Lapped seat and 16 Ilours None 9-3-80 j.ive replaced disc.

80-7-257 PV-2216 7 Normal Wear Pilot valve leaks.

Correc-Rewelded pilot 16 Ilourt None 9-1-80 tive tubes.

80-7-296 Plant Pro-Loose connection.

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

veillance Test. _

80-7-297 V-211 '02 Normal Wear Valve leaks through.

Correc-Replaced valve.

8 Hours None 9-6-80 tive J

SIGNIFICANT f(AINTENhCE SUfIMARY II2NTIFICA-

~ RD}til RED FFFECT 4181 TIE 188 T,rtBER SYSTEN/

NAnfRF. OF FOR SAFE (WEftATitW AND DATE OWS*tWENT cat!SE OF mal.FtWCTitW REStTI.TS OF MAIJINCTitW MAINENANCE CORRECTIVE ACTitW Offl.ETitW oF 110E REACIOR 80-7-311 Reserve Normal Wear Brass fitting at re-Co rrec-Replaced fitting.

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

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

Co rrec-Replaced valve 8 Hours None 9-30-80 valve.

tive bonnet.

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

Co rrec-Replaced, valve.

8 Hours None 9-30-80

valve, tive bonnet,and stem.

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

Co rrec-Replaced con-4 Hours None 9-30-80 tive t rolle r.

80-7-320 Plan t P ro-Normal Wear Iow voltage on circu-Correc-Replaced chip Z-2 Hours None ts 7-28-80 tective culator trip module.

tive 28.

'r' System 80-7-321 Plant Pro-Normal Wear low voltage at circu-Co rrec-Replaced chip Z-2 Hours 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 9-15-8t) rework.

tive procedure.

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

tive valves.

80-7-374 V-21280-1 Normal Wear Valve leaks through.

Cprrec-Lapped valve seat 16 Hours None 9-23-80 tive and disc.

80-8-30 V-21268-1 Normal Wear I.cakage through safety Correc-Repai red 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 Leakage through safety Correc-Repaired seat, 1 Day None-8 80 relief valve V-21268-2.

tive disc, and valve L

bodL_ _

O SIGNIFICANT HAINTENANCE SIR! MARY IIENTI FICA-REQUIRED F.Fil.CT (H TION NUMBER SYSTEHf NATURE OF FUR SAE OPERATItW

_AND DATE O W ONENT CALEE OF HAJRWcTION RESULTS OF_ HALFINCTI(W

,H_AINffYNANCE CORkECTIVE ACTION

, p W I.ETRON g ylE REA,qlpR_

80-8-36 MM-1121 Normal Wear lleater power con-Co rrec-Replaced component 2 Hours None 8-5-80 troller for MM-1121 tive A2 and checked out blowing fuses.

per procedure.

80-8-57 liv-2245 Normal Wear IA circulator steam Co rrec-Installed new 4 Hours 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 llours None 9-18-80 tive I

80-8-68 Control Normal Wear Position indicator in-Correc-Changed 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 1

8-6-80 cation faulty for tive tested new K-23-1 i

region 23.

relay.

80-8-74 V-21453 Normal Wear Valve leaking through.

Correc-Lapped valve seat 15 llours None 9-10-80 tive and disc.

80-8-97 V-7216 Normal Wear Valve leaks through.

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

80-8.-100 IIV-2292 Normal Wear Ilydraulic oil leak on Co rrec-Replaced poppet 2 Ilours None 8-6-80 IIV-2292.

tive block "0" rings.

80-8-157 Plant Pro-Normal Wear Low voltage at circu-Correc-Repalced chip Z-2 Hours 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 Icaking Correc-Repaired valve 12 I!ours None 9-10-80 through.

tive seat and disc.

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

Correc-Repacked valve.

12 Hours None 9-19-80 tive

O SIGNIFICNIT MAINTENANCE

SUMMARY

TI PtE I IGNTI FICA-REQUIRED EFFECT tW TION NUMhER SYSTEtt/

NATURE OF R)R SA W. (WERATION AND DATE COPS *(WENT CALGE GV MALFINCTION RESULTS UF mal.FiHCTi(H HAIN1TNANCE CDRRFCTIVE ACTION Cot 1PI.ETitM OF TifE RFACTOR 80-8-191 SV-2110 Normal Wear Valve leaks through.

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

80-8-199 PV-2244 Inproper instal-011 line to PV-2244 Correc-Installed new pipe 4 Hours None 8-18-80

lation, b roken.

tive nipple and bushing.

80-8-221 tet-1115 Normal Wear MM-1115 heater failure.

Correc-Replaced fuse.

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

Correc-Replaced disc, 16 llours None 9-19-80 tive machined and lapped sdit.

80-8-275 Linear Bad solder joint.

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

tive joint. Checked d,

connection, reset

'j" RWP trips.

80-8-291 V-8218 Normal Wear "A"

inst rument ai r com-Co rrec-Replaced disc, 8 Ilours None 8-22-80 pressor discharge tive guide and guide relief valve blowing follower.

through.

80-8-298 Plant Pro-Normal Wear Low voltage input to Correc-Replaced chip Z-1 llour None 8-21-80 tective CC-2d2.

tive 43, checked module System per procedure.

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

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

80-8-303 Plant Pro-Normal Wear Low voltage at CT-1BL3. Correc-Replaced chip Z-9, 1 Hour None 8 80 tective tive checked module per System p ro cedu re.

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

2 Hours None 9-16-80 tole ran ce, tive

SIGIIFICANT MAltTTENANCE SUmtARY TlHE III NTI FICA-REQUI REI)

EF6ECT EN TION NUMBER SYSTEM /

NAll*E OF FOR SAIV. OPERATI(H AND thATE COPPtN4ENT CAtCE OF HAL FINCTION RESUI.TS OF HAIJutCTI(r4 HAINITNANCE CORRECTIVE ACTION Cir1Pt.ETION OF T11E RFACTOR I

80-8-342 diRS-129 Undetermined Snubber piston out of Co rrec-Repaired snubber 4 llours None 9-26-80 tol e rance.

tive per procedure.

80-8-343 IIRS-158 Undetermined Snubber piston out of Co rrec-Installed shim per 2 llours None 9-16-80 tolerance.

tive procedure.

80-8-351 CRS-262 Undetermined Snubber piston out of Correc-Removed 3/4" from 4 Ilours None 9-14-80 tolerance, tive piston red end and re-installed.

80-8 353

!!SS-421 Undetermined Snubber piston rod Correc,

Replaced with new 1 llour None 8-28-80

bent, ti C s snubber.

80-8-370 BFS-412 Under ermined Snubber piston out of Co rrec-Repaired snubber 4 Ilours None 9-16-80 tolerance.

tive per approved pro-

cedure, d,

T 80-8-373 V-2.1268-1 Normal Wear Relief valve leaks Co rrec-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 Correc-Replaced broken 5 llours None high discharge temp-tive

}dischargecheck

erature, valve.

s 80-9-73 Reserve Normal Wear Connector leaks.

Co rrec-Repaired con-3 llours None 9-18-80 Shutdown tive nector.

Bottle Connection 80-9-80 V-21522 No rmal Wea r Seat and disc of V-Co rrec-

!!achined valve 16 Ilours None 9-9-80 21522 required repair.

tive seat and disc.

80-9-91 C-8201S Normal Wear Discharge pressure low.

Correc-Replaced broken 5 llours None a

9-10-80 tive discharge valve.

e SIGNI FICANT ffAINTENANCE

SUMMARY

TIMf:

II:2MTI FI CA-RP QUI RED EFITc7 (N TRON NUPtnER SYSTEft/

NATURF. OF IhR SAlY OPERATitW AND DATE O#tTELNT CAtEE OF HALFINCTION REStfLTS OF HALFtNOTitW MAINTENANCE CORPECTIVE ACTION Cf1tS't.ETi tW OF Tile REACTOR 80-9-120 C-8201 Normal Wear "A" ins t rumen t ai r Correc-Replaced pressure 2 Ilours None 9-9-80 compressor loading /

tive switch and solen-unloading constantly, old.

80-9-121 liv-2187-2 Normal Wear Air regulator leaking Correc-Replaced leaking 2 Ilours None 9-9-80 on 11V-2187-2.

tive regulator.

80-9-123 pDE-1166 Normal Wear IC circulator dif-Correc-Replaced element 2 liours None 9-8-80 ferential pressure tive and calibrated.

element out of toler-ance.

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

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

80-9-170 TIC-75107 Switch wires Switch does not oper-Correc-Replaced thermo-2 Ilours None O

9-12-80 shorted out,

ate, tive stat.

I' 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 llours None 9-29-80 Operator tive phragm seal and replaced air tubing.

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

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

tive MSS-433 80-9-375 tilts-205 Undetermined Snubber piston out of Co r rec,

Extended stanchion 4 llours None 9-26-80 tolerance.

tive 1/4".

s 80-9-376 Il0S-10 Undetermined Snubber piston out of Correc-Installed new pipe 6 11ours None 9-27-80 tole rance.

tive stanchion.

80-9-389 Il0S-86 Undetermined Snubber piston out of Correc-Pipe clamp moved 2 llours None 9-27-80 tole rance.

tive 1 5/8" towards anchor pin.

SIGNIFICANT MAINTENANCE SlHMARY TIME I12NTI FICA-REQUIRED-EFRCT tW TION IsljMBER SYSTEN/

NATURE OF H)K SAFE OPF.RAtleWI AND DATE CutGMENT

_ CAUSE OF MALFtmCTION RESIILTS OF PLAI.FtNCTION

, MAIN'IENANCE CORRFCTIVE ACTION CutW'IETl00_l 0F THE REA,CMR_

80-9-390 VSS-123 Undetermined Snubber hitting I-beam Correc-Raised collar up 2 Hours None 9-27-80 interference.

tive 1/2".

80-9-400

!!V-2254 Normal Wear Switch inoperable.

Co rrec-Replaced switch.

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

2 Hours None 10 80 wrong.

tive 80-9-412 LC-21306 Normal Wear Controlled level 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 8

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

Co rrec-Rep, laced operator 4 Hours None s

10- % 80 Operator tive motor.

l 80-9-448 PI-21536-2 Normal Wear Indicated pressure Co rrec-Replaced gauge.

2 llours None 9-30-80 wron g, tive 80-9-460 IIV-4507 Normal Wear Valve leaks through.

Co rrec-Cleaned valve in-1 Hour None tive ternals.

80-9-471 PC-31213 Normal Wear Not controlling Co rrec-Repaired con-2 Ilours None 10-i-80 p rop e rly.

tive troller.

80-10-3 SV-2105 Normal Wear Ilydraulic oil leak at Co rrec-Repaired solenoid 7 Ilours None 10-1-80 valve operator.

tive valve.

80 32 K-9203 Ex-Normal Wear Switch failed to trip Co rrec-Replaced failed 1 Ilour None 10-3-80 haust Temp-engine during test.

tive relay.

erature Switch 80-10-35 P-2109 Normal Wear Pump output less than Correc-Replaced pump im-16 Hours None 10-9-80 acceptable limit.

tive peller and mechani-C d

cal seal.

- - ~ ~ - - -

SIGNIFICANT MAINTENANCE SUM 1ARY

=

I r7NTI FI CA-RFQUIRED E FFFrT en T!ON NUMBER SYSTLit/

NAitfRE OF Rtm SAfY. OPI:RATitN AND DATE Cf*SMEENT cat 1SE OF HAI.FINrTION REStII.TS OF MAI.FtHCTitN MAIN 1TN ANCE CORRECTIVE ACTION COttf'I.ETI ON OF 11tE REAC1DR 80-10-50 IIV-21205-2 Normal Wear Valve Icaks through.

Correc-Replaced valve.

4 Ilours None 10-7-80 tive.

80-10-59 IIV-21205-2 Normal Wear Valve leaks thro ugh.

Co rrec-Replaced valve.

4 Ilours None tive 80-10-93 SV-2105 Normal Wear Ilydraulic oil leak at Co r rec-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 dipe nipple.

80-10-150 E-8223X Normal Wear Knock out pot would Co rrec-Cleaned pot, re-12 flours 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 rrec-Replaced pipe nip-1 llour None y

w 10-13-80 filter housing.

tive -

ple.

80-10-241 ilV-2124 7/

Normal Wear Valves leaked through.

Co rrec-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 llours None 10-23-80 tive seat and disc.

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

Emer-Replaced "0" ring.

6 Hours None 10-23-80 Group 1 gency "O" Ring 80-10-247 V-9141 Valve handwheel Valve inoperable.

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

tive handwheel.

80-10-431 TE-22145 In ternal short.

Loss of temperature in-Correc-Replaced failed 8 Ilours None 10-24-80 dicattion.

tive thermocouple.

80-10-484 V-91696/

Normal Wear Valves leak through.

Correc-Replaced in kind.

4 Ilours Nonc 10-28-80 V-91697 tive 80-10-503 liv-21235 Normal Wear Valve leaks through.

Correc-Machined valve 16 Ilours None L

11 80 tive disc, lapped seat.

SIGNIFICANT MAINTENANCE SID! MARY I DENTI FICA-REQUIRFD EFFFcT LW TION NUMBLR SYSTEft/

MATUlef' 0F FOR SAfF. OFFRATION AND tiATE 0)Pf0NENT CALSE OF MALFINCTf 004 REStII.TS OF MAI.FINCTION MAIN 1TN ANCF.

CDRRECTIVE ACTION OrffETitW OF THE REACTOR 80-10-515 LV-21114 Normal Wear Valve operation er-Co rrec-Replaced valve 8 Hours None 11-6-80

ratic, tive operator diaphragm.

80-10-524 Plant Pro-Normal Wear Module failed tripped.

Correc-Replaced failed 4 Hours None 11-3-80 tective tive integrated cir-System cuits.

Module CT-1BR4 80-11-8

!!V-21192-4 Normal Wear Valve leaks 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 Ilours None 11-5-80

/21206-4 tive valves.

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

[

11-3-80 Engine Ex-engine during test, gency and input thermo-

?

haust couple.

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

Co rrec-Replaced bolt.

32 Hours None 12-1-80 llange r tive llR-136 80-11-67 LV-21114 Normal Wear Valve operator would Co rrec-Replaced ruptured 4 Hours None 11-6-80 Operator not completely close tive valve operator

valve, d iaph ra gm.

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.

Ope ra to r 80-11-170 Plant Pro-Normal Wear Module failed test.

Correc-Replaced failed 4 Ilours None 11-24-80 tective tive integrated cir-System cuit.

Module a-2 j

a

SIGNIFICANT MAINTENANCE SLMIARY TIME IltNTI FICA-PJytilRFD EFITcf (N Titwe Nurst.R SY STk.it/

NATURE OF DIR SAIY Ol'ERATira MD DATE 0)Prit4ENT CALSE OF MAIJtNCTION RF#111.TS OF PLAIJINCTi(N ttAIN TEN ANCE 01RRFCTIVF. ACT101 O til'lITl pN OF 11tE 9F.ArTUR 80-11-259 Plant Pro-Normal Wear Module failed test.

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

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

Co rrec-Replaced grounded 4 Ilours 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 sec tion.

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

Co r rec-Replaced "O" ring.

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

tive valve.

7 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-9105X Normal Wcar liydraulic oil pump Correc-Replaced pump and 5 Days None 12-10-80 rough and noisy, tive coup 1fng.

80-12-106 IIV-2293 Normal Wear 011 relief valve leaks.

Correc-Replaced valve.

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

tive "O"

ring.

Ope ra to r 80-12-256 Reserve Normal Wear Connection would not Correc-Replaced bottle 1 Ilour None 12-2F80 Shutdown seal.

tive connector.

Region 31 Bottle Connector.

SIGNIFICANT MAINTENANCE SILSIMARY TIME I[2NTI F1CA.

ItFQtti RIO EFFECT4W TIost N'stBEft SYSTEM /

NATURE OF DHt SAR. e47RATiaW AND MATE OwtONENT CAIGE OF MI.FINCTION RESUL.TS OF HAlftNCTith MAINTrNANCE CORRECftVE ACTION neft.ETION OF 114E RFACWR 80-12-299 C-8201 Normal Wear Ins t rumer.t ai r con 2-Co rrec-Repaired.

6 Ilours None 12-22-80 pressor trips on high tive af ter-cooler temp-eratur.

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

tive fitting.

80-12-359 PS-1106-20 Normal Wear Bourdon tube leak, Correc-Replaced switch.

2 Ilours None 12 80 tive 4

H 80-12-391 PV-2244 Normal Wear Indicated valve post-Correc-Replaced position 4 Ilours None 12-29-80 Position tion erratic.

tive element.

Indicator 4

V l

6 0

w.m.7.,in

-974,

-rys..~+m-q w

--,-ywe e------g.--r-r g

SIGNIFICANT fMIpTrNANCE SIMtARY IIENTI FI CA-REQUI El.D EFif.CT IN TION NUMBER SYSTut/

N ATtlRE OF IVR SAtt (YtRATitN AN D DATE CIMfiteENT CALEE OF KtI.RNCTION REStil.TS OF HAI.FLNCTitN KtlN TEN ANCE (11RRFCTIVE ACTIOPq Ctirtri.FTIt#1 ttF T1tE PDAct'OR 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 through Co r rec-Valve seat re-2 Ilours None 5-16-80 P V-2124 3.

tive paired.

s CWP 80-32 P V-2124 3 Normal Wear Valve leakage.

Co rrec-Weld repair of 8 Ilours None 10 80 tive valve seat.

CWP 80-34 V-21266-1 Normal Wear Valve body erosion /

Co r rec-Weld repair to 16 Ilours None 11-13-80 valve leakage.

tive valve body and seat.

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

Co rrec-Weld repair to 8 Ilours None L

10-28-80 tive valve gasket seal

'r area.

CLJP 80-45 IIV-31119 Normal Wear Leakage pas: seat and Co rrec-Repaired valve 4 Days None 9-24-80 disc.

tive seat and disc.

O

..~

-_-. - - - ~.. -..

u.

2.0 PLANT OUTAGES OR FORCED REDUCTIONS IN POWER g

I HAJOR SAFETY RADI Atl0N RElJ:ASE -

RElATED 0)R-ASSOCI ATED WITH OUT-CORRECTIVE ACTION RECTIVE MAIN-ACE WHIGI ACCtMelTS RElATED kE-TAKEN TO REDUCE TENANCE PER-FUR MORE THAN 102 PONTABLE TIE PROBA81LITT OF OPERATING FORE D DURING OF ALIInfAtlE Ale 6UAL NtBIBER Pit 011 MATE CAUSE SYSTol MAJOR OMfteiENT OCCUNRENCE RECURRENCE TIE IDST Tile offTACE VAttE 79-14 Maintenance Primary

- IIelium Circu-50-267/80-Replaced helium 1538.8 Replaced None and region Coolant lator 01/01-T-0 circula to r.

hours in helium cir-cons t raint 1980 culator.

device in-Replaced stallation speed shutdown cables on continued in lA, 1B, and 1980 for re-1D circula-placement of tors.

Re-liellum cir-paired

culator, leaking flV-2215 and ilV-2217.

80-01 Turbine Power Main Turbine None None 4.15 None None 8

over-speed Conver-llours test.

sion 80-02 Circulating Circu-Distribution None Repaired pipe.

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

56.8 None None scram.

P ro tec-Circuit flours tive Sys-tem 80-04 Loss of con-Conden-Boiler Feed-None Closed valve.

49.25 None None densate sate pump Turbine llours vacuum.

Drain 80-05 IIelium cir-Primary 1A llelium None None 53.2 None None

/

culator Coolant Circulator llours trip.

2.0 PLANT GUTAGES OR mRCED REDUCTIONS IN P(MER I

~

MAJOR S AFE tY RADI ATION REtIASE RELATED 0)R-ASSOCI A1TD WIT 11 OUT-0)RRECTIVE ACTION RECTIVE MAIN-ACE WHIOl ACCOUNTS RELATED RE.

TAKEN TO REDtKZ TENANCE PER-FOR MORE Tit #4 10%

PORTABII 11tE PROtlARILITY OF OPERATING IORPED DURING OF ALIJWABli ANNUAL hilMRE R PROXIMATE cat!SE SYSTEM MAJOR C(litP(NENT

_ OEURRENCE RECtfRRENCE TIME IDST 11tE OtrTAGE val.UE 80-06 IIelium cir-Primary lA IIelium None None 30.0 None None culator trip Coolant Circulator llours and loop shutdown.

80-07 liigh primary Primary 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.

L 80-09 Ile11 um cir-Primary llelium Cir-None None 118.7 None None Y

cula to r Coolant culator lA llours trip.

80-10 Spurious Plant Logic Module None Replaced 5.9 None None loop shut-P ro t ec-mo d ul e,

llours 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 llelium Cir-None Replaced 313.4 None None down from Coolant culator IA failed dif-llours helium cir-ferential pres-culator sure transmit-t rip.

t e r.

9

2. 0 PIANT OUTAGES OR FDRCED REDUCTIONS IN POWER MAJOR SAFETY RADI ATION RElIASE RELATED 0)R-ASSOCI ATED W1114 OUT-CORREt"flVE ACTION RECTIVE MAIM-ACE WHlut ACCOtMTS RELATED RE-TAKEN TO REDUCE TENANCE PER-It)R MORE TilAN 10%

PORTABLE T11C PROBASILITY OF OPERATING FORIED IMJRINC OF Altf1WABLE AletUAL NUMBER _

PROXIMATE CAUSE SYSTEM MAJOR CutW'ONENT OCCURRENCE RECtfRRENCE TIME LOST T?tE OttfACE VALLE 80-13 Reactor Secondary Feedwater None None 339.9 Emergency None scram.

Coolant System llours generator heat ex-changer leak repair.

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

Coolant zation Valve pressurization llours valve.

80-15 Excess feed Seconda ry Feedwater None None 65.2 Mone None water flow.

Coolant Pumps flours

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

line leak.

Coolant Bypass Valve 45/03-L-0

leak, llours 80-17 Electro-hy-Turbine 24 Volt Power None None 959.2 Pepaired None draulic tur-Supply llours purifica-bine control tion train failure.

inlet Scheduled valve.

Re-shutdown placed one started.

control rod drive.

Overhaul engine driven fire aater pump.

Repair leaking steam generator dump valve.

Repair hy' draulic y

snubbers.

h

l l

2.0 PLANT OITTAGES OR FORCED REDUCTIONS IN POWER l

MAJOR SAFETY RADI ATION REtEASE REIATED COR-ASSOCI ATED Willt OUT-CORRECTIVE ACTION RECtiVE MAIN-ACE Wilint ACCotMTS REtATED RE-TAKEN TO REDUCE TENANCE PER-Fnt MORE TilAN 102 PORTABtX lilE PROBARtLITY OF OPERATING FORPEG DURING OF ALIAIWABli Af000At.

NUMBE R PROUMATE CAUSE SYSTEM MAJOR Cult'fMENT OCCURRENCE RECtIRRENCE TIME IDST T1fE OUTACE VAltE 80-18 Turbine Seconda ry : #2 Stop Valve None Replaced solen-2.2 None None taken off Coolant Solenoid old.

Ilours line to check stop valve.

80-19 Exciter Secondary Exciter None None 30.5 None None breaker Coolant flours opened.

80-20 low primary P rimary llelium None Increased None None coolant pres-Coolant Inventory helium inven-sure.

t o ry,

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

Protec-Noise Trip after' testing, llours i

tive Sys-tem 80-22 Ilydraulic ilydraulic Blank. Flange None Replaced "O" 134.9 None None oil leak.

Power ring.

Ilours Unit 80-23 Testing P rimary Co re None None None None Coolant 80-24 Testing P rima ry Core None None None None Coolant 80- 25 Ilydraulic Secondary Circulator None Repaired 17.0 None None oil leak.

Coolant Speed Valve leaking line.

!!biars 80-26 Steam leak.

Secondary llot. Reheat None Rewelded line.

36.7 None None f

Coolant Drain Line llours 80-27 Testing Primary Core None None None None Coolant d.

,i w

.- - w

-u-w+

,-tvvr

-s

-+r,

-N,

,v.e e

w-w, m --

-tw w

rr

-w a

w

2.0 PLANT GUTAGES OR FORCED REDUCTIONS IN POWER I

~~

~

HAJOR SA R1Y RADI ATION REIIASE REIATED (Y)R-ASSOCI ATED WI111 OUT-CORRECTIVE ACTION RECTIVE K\\lN-ACE WHlol AC(XXINTS REIATED RE-TAKEN TO REDtICE TENANCE PER-FOR HORE TIIAN 10%

PORTABLE 1111: PROBAllit.ITY Or OPERATING FORtED ltRING CF AtllWABIE ANNUAL TUMBER_

PROXIMATE CAUSE SYSTEM HA IOR caw 9'ONENs OCCIIRRE NCE RECURRENCE TIME LOST 11IE otTTAGE VAlifE 80-28 Excessive Primary None 50-267/80- None 30.9 None None primary Coolant 75/03-L-0 llours coolant moisture.

80-29 Feedwater Secondary S team Gener-None Repaired valve. 15.0 None None leak.

Coolant ator Trim llours Valve 80-30 Reactor Plant ilot Reheat None None 27.3 None None scram.

P ro tec-Steam liigh llours tive Sys-tem

,w cc 80-31 Loop shut-Secondary Circulator None Repaired valve 5.7 None None 8

down.

Coolan t Bypass Valve position de-lloury tec to r.

s 80-32 Steam leaks.

Secondary Circulator None Repaired 6.9 None None Trim Valve leaking valves.

Ilours and Main Steam Drain Valve k

e

s D 3. 0 RADIATIO!! EXPOSURES During the report period, two personnel received exoosures in excess of 100 mrem. Below is a tabulation of the information required by Technical Specification AC 7.5.l(b)3.

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

100 mrem

.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.

No other personnel received exposures greater than 100 mrem / year for the report geriod.

4.0 FUEL EXAMINATIONS There was no indication of fuel failure found during examination of one irradiated fuel element.

l l

3 t

~

i:

I

. -.,. -- __-

ML20003C619

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML20003C619

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search