ML19282A660

Annual Operating Rept 8 for 1978.

ML19282A660
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/27/1979
From:	PUBLIC SERVICE CO. OF COLORADO
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION ANNUAL OPERATING REPORT NO. 8 1978

!; 790305 o3m

INTRODUCTION This report is submitted in accordance with Section AC 7.3.1.b of the Tech-nical Specifications of the Fort St. Vrain Nuclear Generating S tation, Unit No.1, Facility Operating License No. DPR-34.

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE This report contains the highlights of Fort St. Vrain Unit No.1 opera-tion under the provisions of the Nuclear Regulatory Com=ission Operating License, DPR-34. This report is for the year of 1978.

1.1 January Repair of the leaking steam generator tube reported last year was delayed due to an unsatisfactory weld on one of the four tube plugs.

Af ter removal of the plug and faulty weld, a new plug was success-fully welded, and the secondary closure cap was installed on Jan-uary 8,1978, completing the steam generator repair work (refer to Reportable Occurrence Report No. 50-267/77-42/01-T-1 for further details).

The reactor was taken critical on January 9th and held at 2% power for feedwater chemistry cleanup. On January 10th, che reactor power was increased to 12% and held at about this level until the primary coolant moisture level was reduced to acceptable conditions.

On January 12th, reactor power was increased to 28% and the main turbine generator loaded to 5 MWe. About one half hour af ter loading, a turbine trip occurred due to loss of 125 volt DC to the electro-hydraulic control system. Following recovery from the ensuing tran- ,

7 sient, the main turbine generator was restarted on January 13th.

Reactor and electric power were increased until 421 MWt (50%) and 150 MWe were reached on January 15th. Stable operation at this power level was continued for about a week. -

During the power increase to 50% reactor power, base data required to investigate the primary and secondary system temperature fluc-tuations previously reported at reactor power levels above 53% of  ;

rated, was gathered. On January 19th, tests which included rapid i adjustment of helium flow orifice valves and several load changes ,

between 50% and 60% reactor power at rates between 0.5 and 5.0 per- .

cent per minute, were initiated in an atte=pt to induce primary and secondary system temperature fluctuations. These tests and load changes did not cause any temperature fluctuations. Sequence 53 of SUT B-0 at 60% reactor power was completed es planned on Janu-ary 22nd, and the reactor power was increased to 68% on January 23rd in accordance with SUT B-0.

About two hours after reaching 68% reactor power, a malfunction ,

of the Loop 2 bearing water surge tank level controller caused flooding of the surge tank. The surge tank overflow entered the buffer helium system causing disruption of buffer helium return flow from all four helium circulators and a circulator trip in each loop. Bearing water was injected into the primary system throug;h the auxiliary system of the two remaining operating circu-

{ lators which continued core cooling. The injection of bearing water into the primary system initiated an automatic reactor scram.

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (continued) 1.1 Januarv (continued)_

High pressure in the buffer helium system caused the relief valves of the low pressure separator and helium dryer to open and primary Following this coolant to be released into the reactor building.

release, the reactor building stack iodine monitors initially in-dicated a large iodine release outside the reactor building, re-quiring the plant emergency radiological response plan to be initi-ated. Subsequent analysis has shown that the release of radio-  ;

activity was small - about 4.5 microcuries of I-131 and four curies of noble gas. High background from the noble gas present in the stack release accounted for the anomolous indication of the iodine It is estimated that 100 to 150 pounds mass of primary monitor.

coolant escaped to the reactor building and 150 to 200 gallons of See bearing water entered the primary system during this event.

Reportable Occurrence Report No. 50-267/78-03/01-T-1 for further details.

By Nuclear Regulatory Commission request, the reactor remained shutdown to accomplish the following items:

1. Repair all damage from this event.

2. Complete and implement a program which provides for in-creased surveillance of all instruments and controls of the helium circulator auxiliary system and subnit program to Nuclear Regulatory Commission staff for review.

remote isolation, from

3. Co=plete modifications which permit the control room, of the helium dryer in the helium circu-lator auxiliary system.

4. Replace the surge tank level controller that f ailed, and functionally check all four surge tank level controllers, including the valves which they control.

5. Provide to the Nuclear Regulatory Commission staff the f ailure modes and effects analysis for the helium circu-lator auxiliary system which Public Service Company of Colorado used to determine the consequences of single failures in the system.

1.2 Februarv At the beginning of the month the reactor remained shutdown as a result of the helium circulator auxiliaries system upset of Janu-ary 23rd. Dryout of the PCRV internals proceeded with feedwater isolated from the steam generators to maximize primary coolant j temperatures and moisture removal rate through the purification system. Operation in this mode continued until February 13th.

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1.0 NARRATIVE SOf!ARY OF OPERATING EXPERIENCE (c 1.2 Februarv (continuedl i ion In a letter dated February 9th, the Nuclear Regulatory levels not Com= ss specified conditions for reactor operation at power flow was feedwater to exceed 2% of rated, and on February 13th, The reactor was re-established and the reactor taken feedwater flow critical.temperature operated at approximately 1.5% power with and moisture removal rate. Operation at about 1.5%

the steam generators was again isolated. temperature temperature power with no feedwater flow produced a core o l of approximately 450*F. val By maximizing primary coolant temperature and 0 ppemoisture on ding remo rate, the primary coolant moisture was reduced from February 1st, increase in average core outlet temperature from f the items identi-At the end of February, Items 1, 3, 4, and 5 o fled in the Nuclear Regulatory Commission February 9th letter (see Section 1.1 for listing) were completed.

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, On February 24th, the first 172 of a total 245 Thefuel elements elements were be used in the first refueling were received.

secured in the Fuel Storage Building.

Loop 2 At the request of the Nuclear Regulatory Commissicn, the d on bearing water surge tank level controller whi replaced with an identical spare.

1.3 March less At the beginning of the month the reactor was operating iction imposed at than 2% of rated power in accordance with the restrThe steam generators r l t temperature by the. Nuclear Regulatory Commission.mained isolate and moisture removal race. iig Reactor power was reduced on March 7th to permit operator he t startups and was shutdown on March 8th in order to inspect tDu main condenser and plug leaking tubes.following safe 1.

New helium circulator bearing water main drain controll were installed and tested, to correct leakage e

2. Main steam relief valves were rebuilt f

problems.

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SUMMARY

OF OPERATING EXPERIENCE (continued)

1. 3 March (continuedl

3. The oearing water makeup pump was removed and rebuilt (see Reportabic Occurrence Repo rt No. 50-267/78-06 for i details). f

4. Three Class I hydraulic shock suppressors were rebuilt -

with new cylinder seals (see Reportable Occurrence Report  :

No. 50-267/78-04 for details) .

During the shutdown the condensate system was inedvertently contam-insted with firewater through the circulator bearing water system. None Cleanup of the condensate system required about one week.

of the firewater came into contact with the steam generators. i Following completion of the shutdown maintenance, the reactor was taken critical on March 23rd, and operated at less than 2% of rated power through March 29th, when the Nuclear Regulatory Commission gave permission for the resumption of the Startup Test Program at power icvels up to 70%. The Nuclear Regulatory Commission re-  :

lease for continued testing was issued upon their concurrence with ,

a proposed program providing for increased surveillance of all instruments and controls of the helium circulator auxiliary sys-  !

tem. This was the final open item resulting from the event of Jan- ,

uary 23,1978.

On March 30th, while at approximately 5% power, the reactor scrammed because of a spurious Plant Protective System moisture monitor .I trip. The reactor was restarted the same day and power was raised to about 13% and held there until primary coolant system chemistry required to permit reactor operation at higher power and tempera-ture levels was achieved.

On March 1st, the final 73 of a total of 245 new fuel elements to  !

be used in the first refueling were received. The elements were secured in the Fuel Storage Building.

1.4 Ap ril During the first week of April, the reactor power level was slowly The slow rate of power increased from 13% to 28% of rated power.

increase was to allow high primary system moisture levels to sub-side. The turbine generator was loaded on April 4th, and remained on line except for overspeed tests performed on April 6th.

On April 8th, a turbine trip occurred from 32% reactor power.

The turbine was reloaded about six hours later. On April 9th, a

• second turbine trip occurred from 25% reactor power. The turbine vas back on line within two hours. Turbine trip tests from 23%

l (45 MRe) were performed on April 12th to inves tigate the unplanned

• turbine trips of April 8th and 9th. The cause of the unplanned trips was found to be the fast closing intercept valve test circuit j

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (continued) 1.4 April (continued) which was actuated by electrical noise from normal operation of relays in the electrohydraulic conttol system. The test circuit had previously been inoperable due to failure of the 8th stage  ;

pressure sensor which provides a pe:: missive for test circuit opera- i tion. When a replacement sensor was installed the test circuit was made operable and when actuated by the electrical noise, caused ,

the turbine trips. Arc suppression diodes have been installed j on electrohydraulic relays to suppress the noise. No further trips from this cause have occurred.

i The plant transients following the turbine trips of April 8th and  ;

9th, resulted in excessive drop of reactor power and steam tempera- ,

ture. The cause for this transient response was recent modifica- ,

tion of the reheat cteam temperature control system. The modifi-  ;

cation was intended o program the reheat temperature setpoint .

as a function of feedwater flow. Additional tuning and modifica- l tion of the control system corrected the problem.

Following the turbine tests, reactc r power was increased to 48%

(145 MWe) on April 13th. On April 14th, Loop 2 was shutdown to repair the feedwater isolation valve which had excessive seal ring l leakage. Since a test of plant transient response to a loop shut-down at this power level ic part of the startup test program, the -

loop shutdown was accomplished by sequentially tripping both he- i lium circulators in Loop 2. The transient- response to the auto-  !

matic loop shutdown that resulted, was acceptable.

The plant was operated at about 25% reactor power (65 MWe) on Loop i 1 until April 17th, when reactor power was increased to 30" (83 l NWe). Single loop operation was limited to this power level due  ;

to high primary system oxidants (see Reportable Occurrence Report i No. 50-267/78-12/03-L-0 for details) . The turbine was unloaded l and reactor power reduced to 6% or. April 20th to allow restart of ,

the shutdown loop. The main turbine was off line about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the loop recovery. l l

Following recovery from the Loop 2 shutdown reactor power was in- l creased to 55% on April 21st, and to 60" on April 22nd. After the -

increase to 60%, reactor temperature fluctuations recurred. Reduc-tion of power level to 53" stopped the fluctuations. A tes t pro-gram to further investigate and evaluate reactor fluctuations at ,

Fo rt S t . Vrain was formulated by General Atomic Company.

Helium circulator lA tripped durit.g surveillance testing on April 22nd, due to a Plant Protective System logic component fail-ure, causing power reduction to 30". The faulty module was re-

paired and the plant returned to 68% power for continued startup j program testing and remained there through April 30th.

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3-1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (cont 1.5 May power resumed on May 2nd andlbyding May 4t' Startup testing at about 68:all of the 68% steady power te '

an automatic load change from 68The plant power. i control m andsystem wa ,

i the newly installed automatic programming of the ma n steaThe resu hot reheat setpoints with load. l were acceptable. '

reactor power Later on May 4th, a circulator trip test from 68: This was fol-  !

was performed as part of the startup test program.also part of the test pro loved by a loop shutdown test, Reactor The results of these transient tests were acceptable.During the single i power was adjusted to 37% on one loop operation a Loop 2 steam generator module was repaired.

Reactor power was reduced to 7% on May 6th and th was restarted.

On May 8th, during the return to 68% power, primaryd system ction temper ture to 57%.

fluctuations started and were stopped by a power r loop the minimum core pressure drop configuration, an unplannedThe shutdown and reactor scram occurred.

loop shutdovt was traced to a faulty test meter being used to per-form Plant Protective System routine testing.

The turbine generator was resynchronized on May High primary system 9th approxima moisture 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> af ter the reactor scram.

levels required power reduction and eventual unloading of the tur-bine on May 10th. The high primary system moisture level was dryer (see traced to malfunctioning of the circulator buffer helium 30-267/ 7 Reportable 13/03-L-0).

Occurrence ReportsEqualizing the buffer Reactor helium power levelsupply an reduced the primary system moisture levels. lith, was increased and the turbine generator resynchronized on May about 13.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after shutdown.

Reactor power level was increased to 65% (200 MWe) h dryeron May 1 the circulator buffer helium dryer out of service while t e desiccaat was replaced and regenerated.

Helium circulator 1C penetration primary seal interspace The leak leak raterate has increased above its previous " normal" quantity.

appears to be a function of circulator inlet temperature as was 50-observed previously (reference Abnormal Occurrenc

! 267/76-25B).

" amount allowed for this penetration.

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SUMMARY

OF OPERATING EXPERIENCE (continued)_ i 1.5 May (continued) l j

Primary system fluctuations occurred at 69* reactor power on May 19th and May 20th. In both cases, The reduction of the power to about 60%

fluctuations occurred at a core pres-  !

stopped the fluctuations. j sure drop which was less than the previously observed threshold, and is attributed to the core orifice valve positions not being Adjustment of the l

i adjusted for the best temperature distribution.

orifice valves to approximately the previous stable configuration re-established stability at 67% reactor power. '

Planned startup testing up to 70% power was essentially cocplete at this time.

On May 24th, an unplanned automatic Loop 1 shutdown occurred due i' to a f ailure of the feedwater flow controller. Operation on one loop at about 30% reactor power continued until May 26th when the main turbine generator was shutdown to recover the shutdown loop.

The main turbine was resynchronized on May 28th, about 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> af ter it was taken off.  !

I 1.6 June A test was initiated cn June 2nd to investigate the primary system temperature fluctuations. This test consisted of partial insertion i

of a nu=ber of control rods to flatten the core power distribution '

and adjustment of the region helius flow orifice valves On to minimize June 3rd, inter-regional variations in differential pressure.

while making these adjustments at 50% reactor power, te=perature j

fluctuations appeared. Reactor power was reduced to 35%, stopping j the fluctuations and the remainder of the orifice adjustments com-l pleted on June 4th. The test then called for an increase from j 40% to 45% reactor power at a rate of 5% per minute in an attempt to initiate fluctuations. Fluctuations were observed The which required test was in-l a reactor power reduction to 34% to terminate.  !

conclusive with respect to demonstrating the relationship between inter-regional differential pressure and temperature fluctuations.

The plant operated normally at about 65% reactor power (203 MWe) j except as described above, until June 6th, when an unplanned auto- i matic shutdown of Loop 2 occurred during surveillance testing. j The plant was shutdown at this time and remained shutdown until 1 June 10th for operator licensing ernminations.

The plant returned to power operation and the main turbine genera-tor synchronized to the system at 28 reactor power on June 12th.

Plant output was then increased to 65".

On June 14th, an unplanned trip of the "D" circulator occurred l' during surveillance tesing. The shutdown circulator was restarted and the plant returned to 65% power within three hours.

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SUMMARY

OF OPERATING EXPERIENCE (continued)_ 1 1.6 June (continued)

A test of the redesigned cold reheat attemperators orifices was perormed, with acceptable results.

Slightly higher than acceptable primary system moisture and total oxidant levels were experienced during this period (see Reportable Occurrence Report No. 50-267/78-18/03-L-1 for details), and were  ;

traced to leakage past the buffer helium dryer, air operated, by-  ;

pass valve. A modification was initiated to provide manual iso-lation valves and a bypass around the air operated valve to f acili-tate repair during operation. During the installation of the modi-fication, the leaking valve was repaired.

The plant operated between 57% (170 MWe) and 67% (212 MWe) reactor power until June 29th. During this period the plant load was limited  ;

by condenser vacuum because one of the circulating water pumps was out of service to effect repair of the motor.

On June 29th, power was lost to non-interruptable instrument bus two. This event resulted in a perturbation of the helium circula- ,

tor auxiliaries, an automatic isolation and steam water dump of l the Loop 2 steam generator, and a reactor scram. Two blown fuses The were found in the inverter for the f ailed instrument bus.

loop shutdown and steam water du=p was caused by high moisture on Loop 2 primary coolant, resulting from the circulator auxiliary system upset. i 1

1.7 Julv i i

The buffer helium dryer bypass modification described in the pre- j vious month was installed. i j

The reactor was taken critical June 30th and returned to power as rapidly as the moisture concentration in the primary coolant per- ,

mitted.

The turbine generator was resynchronized with the system on July 4th i at a reactor power of 28%. Plant operation was restrictedHelium by the availability of only one helium circulator in each loop. i circulator lA was out of service due to an inoperable operator on the inlet steam isolation valve, and circulator 1C in Loop 2 was indicating high buffer-mid-buffer differential pressure with the main drain controller in automatic.

The buffer-mid-buffer problem on "C" circulator was cleared by increasing the circulator speed. Helium circulator LA inlet, steam isolation valve was manually opened and the circulator returned

! The reactor power level was increased to service on July 6th.

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' to 40% (110 MWe) on July 6th and to 52" (162 MWe) on July 8th.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (continued) 1.7 Julv (continued)

On July 7th, a localized fire occurred in the turbine building I at a hydraulic valve operator that leaked hydraulic fluid on the i hot reheat steam piping. The fire was readily extinguished using l hand held fire extinguishers. No permanent da= age was done by the  ;

fire.

The reactor power was increased to 58 (175 MWe) on July lith and operated at this level until July 14th, when an unplanned trip of circulator ID occurred during surveillance testing of the Plant Protective System. Failure of an integrated circuit chip caused this trip. During the recovery of 1D circulator, circulator 1C l spuriously tripped causing loss of primary coolant flow through the Loop 2 steam generators. The reactor was manually scred following this occurrence.

The plant was returned to power, the turbine generator resynchro-nized and power increased to 58% (175 MRe) on July 17th.

Problems with high primary coolant total oxidants continued.

- Two trips of instrument bus inverter 1C occurred during this peri-od, (July 13th and July 14th). These trips were caused by failed silicon controlled rectifiers (see Reportable Occurrence Report No. 50-267/78-26/03-L-0 for details).

During this period, additional thermocouples were installed in the core region outlet thermocouple ass emblies. Two modified control rod drive and orificing assemblies were received on site for inser-tion into the core at the first refueling if additional information is required in the investigation of the primary system temperature fluctuations.

The plant operated between 45% (133 MWe) and 65% (195 MRe) until July 31st. During the evenings, with lower system power demands, the power level was decreased to 45 to reduce the core outlet temperature below 1,200*F. This mode of operation reduced the total time of operation above the 1,200*F, which is the threshold for the 10 ppm total oxidants conditional limit on primary coolant i= purity levels.

The cause for the high primary coolant impurity levels continues to be investigated. Operation with nor=al circulator buf fer he-lium flows results in an increase in primary coolant impurity levels.

However, with equal buffer helium supply and return flows, reduced but higher than expected, i= purity levels are s till experienced. j E  !

1.0 NARRATIVE SMNARY OF OPERATING EXPERIENCE (continue 1.7 Julv (continuedl On July 31st, a winding f ailure and insulation fire occurred d in The i 480 volt transformer 1A and the plant was manually scramme . i l

loss of the 480 volt transformer caused an upse Nc. 50-267/78- t the primary system (see Reportable Occurrence Report  !

i 28/01-T-0 for details). i i

i 1.8 _ August i The reactor was taken critical on August 5th and in Further increase operated power wasat power ?

levels between 2% and 6% of rated. l restricted by high levels of moisture in the primary coolant.

l The moisture level in the primary coolant was between 230 ppe an l 800 ppm.

The source of the high primary system moisture was the i  !

circulator buffer helium upset of July 31st which occurred dur ng I the loss of a 480 volt transformer.

Approximately 60 gallons of water were removed from system during August.

cleanup of the primary system moisture included:

1. Operation at low power levels to increase the cold gas temperature within the PCRV.

2. Cycling of the reactor pressure.

3. Operation with various combinations of circulators (opera-tion of the "A" circulator incraaed the primary system moisture level).

4. Increasing the temperature of the PCRV liner cooling sys-tem.

The reactor power was increased to 25% of rated on August 16th, resulting 130 ppm to 190 ppm.

in an increase in primary system moisture lev Reactor power was increased to 29% and the decreased to 80 ppm. The tur-main turbine generator was synchronized on August 17th.

bine was taken off line two hours later and the reactor power was reduced to 26% of rated due to increased primary system moistu (see Reportable Occurrence Report No.

tails.

The main turbine generator was resynchroai:ed and loaded to 45 MRe on August 18th. On August 20th, an automatic reactor scram

!* and steam water dump of the Loop 2 steam generator occurred due

l 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (continue .

1.8 Augus t (continuedl h low to a noise spike on a high level moisture monitor with t eThe reactor was level monitors previously tripped.

28% power and the main turbine generator reloaded to 45 MWe on August 21st. On August 22nd, a turbine trip occurred due to an upset in the turbine first stage pressureThe andmain main steam turbine tec:pera-genera-ture following a system frequency spike.

tor was back on line about one hour later.

While operating at 28% reactor power af ter August 18th, 30 the ppm pri-mary system moisture level remained fairly constant in the into ingress  ;

to 50 ppm range, indicative of a continuous moisture the primary coolant system.

"A" was placed in service On August 23rd, main helium circulatorOperation of helium circulator and "B" circulator was shutdown.

"A" resulted Thein an increase in primary system moisture from 50 ppm main turbine was manually tripped of f for about to 80 ppm.

five and one half hours and the power level was reduced to preventOn Augu exceeding limits of the primary system moisture level. The a turbine trip occurred due to an electronic noise spike.On August 26th, turbine was returned to service about one hour later. 2% of the turbine was manually tripped, reactor power reduced to rated and steam generator Loop 2 was taken out of service to re-The reacto August 27th.

pair a hydraulic oil system flange leak.to 28% of rated and t Through August 30th, the reactor was held below 30%

Operation with of rated due circulator ,

to high primary system moisture levels.

"A" operating and shutdown demonstrated that the source of"A". moisture into the pri=ary system is associated with helium circulator Operation with helium circulator " A" shutdown reduced and thethe primary reactor moisture level to less than 9 ppm on August 31st, power level was subsequently increased to about 39% of rated (15

!Ee) .

This increase in reactor power resulted in an increase in primary system it: purity levels which gradually decreased.

1.9 seotember f

The reactor power was increased to about 49% of rat on Septer:ber 1st. The primary system increase in primary system impurity levels.

i= purity levels subsequently decreased to about 4 ppm moisture an Operation with the " A" circulator shutdown 13 ppm total oxidants. continued through September 8th to reduce the The buffer helium supply flow to the ture and impurity levels.

E circulators was reduced to approximate the buf fer helium retur l flow for about 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

levels was observed indicating that the source of moisture circulatorwas not shut-from the circulator buffer helium system with "A" down.

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (continued) '

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1.9 September (continued)

I The reactor power was increased to about 58% of rated (170 MWe) on September 7th. This resulted in an increase in primary system impurity levels to 5 ppm moisture and 16 ppm total oxidants.

On September 8th, an unplanned trip of the "B" circulator occurred. l Since the " A" circulator was self-turbining and not at speed, the l crip of the "B" circulator initiated an automatic shutdown of the The trip o f the "B" circulator was {

Loop 1 steam generator system.

traced to a noise spike in the Plant Protective System which gave .!

a f alse signal to the Plant Protective System logic system indi-cating that the "A" circulator was at speed and thus, changed the feedwater flow / circulator speed mismatch trip pointthen circulator to the "two tripped circulators in operation" mode. The "B" on high speed relative to the existing feedwater flow. +

l A shutdown for surveillance testing and maintenance was scheduled This shutdown was moved forward one day due l for September 9th -

to the unplanned circulator trip and loop shutdown of September 8th. l The shutdown progressed as planned until September 18th when damage  !

to the internals of the Loop 2 main steam desuperheater was dis-  !

covered. Similar damage was identified in the Loop 1 main steam The return to operation was de- ,

desuperheater on September 19th. .

layed about one week while the two desuperheaters were repaired. t i

Release was obtained from the Nuclear Regulatory Com=ission on  ;

September 26th to allow the performance of additional fluctuation Identifi-  !

testing at reactor power levels less than 70% of rated.

• cation of the tests to be performed is presently under evaluation.  !

The reactor was taken critical and the reactor power level was in-creased to 2* of rated, on September 28th in preparation for re-turn to power. Cleanup of the feedwater chemistry for operation at temperatures above 400'F required that the reactor power level be held to about 2* for two days. Reactor power level was increased to about 12% of rated on September 30th. This increase in reactor power increased the primary system moisture level into the limited acceptable range of LC0 4.2.11 (primary coolant dew point above

-20

• F) .

1.10 October At the beginning of the month, the plant was holding at about Power10%

was reactor power for cleanup of primary coolant moisture.

increased to 25" on October 4th and on October 5th, the turbine generator was placed on line with reactor power at 28%.

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? The reactor power level was increased to 38% on October 7th with a turbine / generator output of 110 (MRe) . The plant was restricted

', to this output until October 12th due to high primary system im-

' purity levels for moisture and the reaction products of the mois-

ture with the primarv system craphite comoonents.

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1.0 NARRATIVE SL'4 MARY OF OPERATING EXPERIENCE (continued) i t

1.10 October (continued) l l

On October 12th, the primary system total oxidant level had decreased About to below 10 ppm and an increase in load was initiated.

one half hour later, a signal for a half load runback of the main turbine generator occurred (from loop shutdown Thecircuitry) turbine but loadno de-loop shutdown took place, or was called for.

creased from 120 (MJe) to 90 (MNe) and then increased to 145 (

The turbine then tripped off followed by an automatic shutdown of Loop 1 on low main steam temperature.

The cause of the initial l loop shutdown signal to the main turbine apperas to have been a f faulty logic chip in the Plant Protective System while a logic l channel was being powered down for surveillance testing. 1 I

The " A" helium circulator was placed in service for nine and one half hours on the morning of October 13th, and the primary system i moisture level increased at an initial rate of about one ppm per  !

hour.

and the main turbine resyn-The reactor power was returned to 28:The power was increased to 28:  !

chronized later on October 13th. On October 16th,  !

with 110 (MJe) generator output on October 14th.  !

the primary system impurity levels had decreased below 10 ppm and a load increase to 50% reactor power was initiated.

On October 17th, the "A" 480 volt essential bus transformer tripped i

off causing the turbine to be tripped and the reactor was manually scra=med. The transformer was replaced later on October 17th and the reactor was returned to 2% power on October 18th.

The plant was operated at reactor power levels up to 12% of rated until October 31st. The "A" circulator operated at speeds up to 6,400 rpm with the "B" circulator at steam drive warmup conditions.

This mode of operation was used to remove moisture from the primary system prior to operation at core outlet temperature where the mois-ture would cause oxidation of the primary system graphite components.

On October 29th, the moisture levels began to trend downward and reached 4 ppm on October 31st (see Reportable Occurrence Report No.

50-267/ 78-18/03-X-3 for details).

~

1.11 Novemb er Tests to investigate the primary system temperature fluctuations were performed Nove=ber 1st through November 4th. A nu=b er o f low amplitude fluctuations were experienced at reactor power levels between 38% and 50% of rated and with core pressure differential of 2.9 psid. These fluctuations were initiated by orifice valve A tur-

• motions, circulator speed changes, and power level changes.

bine trip occurred on November 2nd on low main steam camperature

[

' during circulator speed changes for these tests.

I i

i

w. - . - . - .

I l

1.0 NARRATIVE StiMM.W OF OPERATING EXPERIENCE (continued) l 1.11 November (continued)_ I Ihe fluctuation which occurred on November 3rd resulted in exceeding the test limits set forth by RT-500. Consistent with the test pro-visions, further fluctuation testing or planned reactor operation in the fluctuation mode was terminated pending investigation of the fluctuations and subsequent release by the Nuclear Regulatory Commission to perform additional tests.

On November 6th, an inadvertent opening of a 480 volt breaker caused a temporary loss of power to some plant equipment and a reduction in plant load. The plant was returned to normal a short time later.

The reactor was operated at approximately 60% power, with an electrical output of 190 to 195 MR until November 13th. Main steam / reheat steam temperatures were 1,000/1,000 and primary coolant oxidants were less than 10 ppm and slowly decreasing.

On November 13th, reactor power was raised to 62% at 8:15 am.

At 1:45 pm, "C" helium circulator tripped due to a drain malfune-tion. Load was reduced to less than 30% power in order to recover the circulator.

Shortly thereaf ter, No. 2 bearing on the main The turbine generator started indicating excessive vibration.

That same evening, turbine tripped from high vibration at 4:38 pm.

problems were encountered with off gassing of oxidants from the helium purification system back into the primary coolant due to The main turbine generator liquid nitrogen system malfunction.

was returned to service on November 15th and by 11:00 pm on Novem-ber 16th was back to 60% reactor power and 195 MWe, Primary coolant oxidants were again under 10 ppm and the plant operated until Novem-ber 27th at these conditions.

On November 27th, a fire occurred on Loop 1 bypass system trap drain  !

line as a result of a hydraulic oil leak and i=pingement of this oil '

on the trap drain. The fire was i= mediately extinguished with no  ;

permanent damage incurred.

i On November 28th, a main condenser leak developed on the north side of the water box with resultig deterioration of condensate water quality. Approximately 1,000 tubes were plugged in this side of the condenser as was done on the south side approximately six months 9

ago. The north side water box was put back in service on Decem-ber 5th with no apparent leaks.

On November 29th, "B" helium circulator tripped f rom loss of bearing water during a filter change over which caused a momentary low dif-ferential pressure spike to the Plant Protective System sensors.

5 "B" circulator was restored to service in approximately ten minutes.

3

~ ,

i

~

. e -- _ _ _ _ _

i l

l i

1. 0 NARRATIVE SLT!ARY OF OPERATING EXPERIENCE (continued) 1.11 November (continued)_ I On November 29th, service water ingress to the buffer system"B" from a breach in a 1.elium recovery compressor cooler resulted in and "C" circulator trips.

In addition to the circulator trips, the breach caused overpressurization of the low pressure separator and release of primary coolant to the reactor building atmosphere.

The reactor building stack tonitors downstream of the filters and charcoal adsorbers, showed no increase in activity indicating no re-lease of activity outside the reactor building. The reactor was manually scremd when the turbine tripped from spurious noise to the f ast closing IV circuit caused by arming of the runback circuit when "B" and "C" circulators tripped.

On November 30th, repair of "A" and "B" helium recovery compressors and clean up of the secondary coolant continued in preparation for restart of the reactor.

1.12 December The return to power operation was delayed until December 9th due to feedwater chemistry cleanup. The plant was held at 42% power and 1,200*F core helium outlet temperatures until December lith due to high primary coolant system oxidant levels (see Reportable Occurrence Report No. 50-267/ 78-37/03-X-1 for details). The reac-tor power was then increased to 50% of rated on December lith and to 67% of rated on December 12th.

At a reactor power level of 67% of rated (218 MRe) on December 12th, low level primary system temperature fluctuations were observed.

A change in the orifice position of core region 35 alteredThe the low nature of these fluctuations but did not terminate them.

level fluctuations were terminated by a reduction in reactor power to 64% of rated. As a result of this inadvertent fluctuation, new l reactor operating limits were established to ensure reactor opera-tion in the non-fluctuating mode. l The plant operated at about 64% of rated (206 MRe) until Decem-ber 20th when reactor power was reduced to about 50% for repair u to a small leak at the flow element associated with Loop 2 cold reheat attemperation line. The plant was returned to 64% of rated w

~ following repair.

Reactor power was reduced to about 30% of rated on December 24th for maintenance to the buf fer helium dryer (see Reportable Occur-rence Report No. 50-267/ 78-39/03-L-0 for details) . Upon comple-tion of the dryer repair on December 25th, the reactor power was j increased to approximately 64% (206 MRe) and remainted there through the end of the month.

k

1.13 >DHT ST. Vi(AIN SICNI FICANT PIA D(f ENANCE SifMMANY I F

l l T i m.2 IJ.mt a f lu- Required Ef fe ct on -

t ion Nund.e r System / Nature of for S.sfe Oper.it!<m me.1 IL r e Cmagum. ut Cause of Halfunctl.m Result s of Hal f unct ion Haintenance Cue sert ive Act f un Costl etloo of alie Neactor 1~2:35T-76 SEsrce horma Fuse. RealticM pump capa- Correc- Rebullt pump'In- F None 3-20-78 Water city. tive t e rna l s . rkin t hs Supply .

Pumps _  !

_4-354-77 V-2110 73 Normal use. Valve leaks through. Correc- Replaced with spare 5 llours None 4_-28-78 Live valve.

6-295-77 Station Normal use. One cell has low Correc- Replaced cell in 2 Ilours None 3 78 Battery til specific gravity. Live k_i n d .

7-235-77 PDI-23149 Normal use. Reading incorrect. Correc- Returned PDI to 8 ,None 4-5-78 tive f ac to ry for repair; ffonths re-installed. g 7-242-77 V-2174 3 Normal use. Check valve leaking Correc- Replaced valve 16 None .

1-17-77 t h rough . tive hinge pins llours l 7-292-77 PV-2229 Normal use. Valve leaks through. Correc- Repaired valve seat 2 Weeks None 3_2-78 tive and disc.

8-174-77 V-2l1017 Normal use. Valve leaks through. Correc- Replaced valve 1 Day None -

2- 3-78 tive with spare. Reactor i

_ Shutdown ,

8-217-77 V-2399 Normal use. Hellows sealed valve Co rrec- Replaced valve 1 Week None I 11-6-77 bellows leak. tive bellows. .

9-201-77 V-21292 Normal use. Valve leaks th ro ugh . Correc- Replaced valve 8 Ilours None - .

2- 3-78 tive with spare. Reactor k

_ Shutdown

• 9-287-77 Line 3/4" E r ro r. 1.ine was partially Correc- Replaced section 8 Ilours U ne -

2-2-78 1.- 21600D13 cut through. tive of line. Reactor

__ _ Shutdown 10-279-77 IIV-2250 Normal use. Ilydraulic oil leak Corree- Replaced operator 1 Week Ee 2-22-78 Ilydraulic at ope ra tor. tive poppet blocks.

Ope ra to r Il-45-77 P V-2124 3- 1 Normal use. Valve leaks through. Co rr ec- Replaced valve 1 Day None Il-5-77 tive stem and sea *.

11-260-77 FS t.- 2212-1___ Normal use. Output relay failed. Correc- Replaced relay. 2 llours None ,

7-12-78 tive (

11-281-77 V-21268-1 Normal use. I.caks a t top adjust- Co r ree- Cleaned, rebuilt 3 Days None - 3 2-2-78 ment cap. tive cap and seat, re- Reactor y_ laced gasket. Shutdown  ;

12-78-77 IIV-2241 Normal use. Internal oil leak Correc- Replaced two 10 Days None - '

l-9-78 Ilydraulic through opera tor. tive poppet blocks. Reactor Ope ra tor Shutdown  !

12-135-77 TE-22144 flechanical fa il ure. Thermocouple broken Correc- Replaced with 2 luys None -

1-4-78 during removal for Live spare. Reactor '

ca l ili ra t.i on . Shutdown

FUNT ST. VRAIN SIGNIFICAPtr HAltifLNANCE

SUMMARY

F l Time I .len IfIca lie <lu i r cJ Elfcct on t lose hus6er Systena/ Nature of for Sale operatton an.l stat e component _ cause of H,alfunction Resul t s of H.al t unct ion Haintenance Cos s ect i ve Acelon ignyletion of tiie Reartos i 12-306-77 TT-9 34 73 No rma l use. Indicated temperature Correc- Replaced failed 4 Ilours None -

l-4-78 9 high. tive power supply Reactor capacitor. Shutdown i, 1-67-78 11-1301 Normal use. TV cooling valve Correc- Replaced valve 4 Nours None , j 1-5-78 leaking through. tive with spare. l  ;

l-174-78 IIV-2241 Normal use. Valve would not Correc- Replaced failed 1 Iby _None - l l-11-78 Ilyd raulic open. tive oli solenoid Reactor i Ope ra to r valve. Not at Power _

L-19 7- 78 Sti-21166 Normal use. Indicated speed in- Correc- Replaced cable. 4 Ilours None - Re-1-11-78 correct. tive dundant Instrument Operable l L-210-78 IIellum Cir- Cround wire omitted Accumulator fired Correc- Installed ground 2 Days None -

t-30-78 culator during circuit unnecessarily. tive wire. Safe Dir-Hea ri ng chan ge. ection Water Accu- Failure I mulator Con- y .

trol System ,

L-223-78 Ile11um Cir- Normal use. I,oss o f speed indi- Correc- Replaced failed 8 Ilours None 5-11-78 culator cation. tive connec to rs . l Speed Cables 1-283-78 V-2244 Normal use. Valve leaked a t seal Correc- Temporary repair 8 Ilours None -

L-21-78 ring. Live by Fermanite pro- Feedwater cess. Flow Not Effected 1-307-78 TE-22137 Normal use. Thernucouple f ailed. Correc- Replaced thermo- 4 llours None - Re- '

t-15-78 tive couple with spare. dundant I ns t ru men t

_ Ope rab le L-371-78 C-8203 Normal use. Unloader would not Correc- Replaced valve 4 Ilours None - Re-1 78 Unloader load. tive solenoid. dundant Compres-sors operable 1-423-78 FT-2222-4 Normal use. Valve leaks through. Correc- Replaced valve 2 Days None 5-23-78 Drain Valve tive with spare.

L-4 56- 78 FT-222-6 Normal use. Valve leaks through. Correc- lieplaced valve 2 Days lidne 5-23-78 Isolation Live with spare. }'

Va lve l

DORT ST. VRAIN htGNI FicAt(f nAltff tMANCE StittttARY -

) Time Iden( I t a c.a- Required Effeet ou c lois Nua.il,e s System / Nature of for Safe opes.ation

.su,1 D.it e Component c.ause of NI f unct f un Ressul t s of Hal f unt t lun Halnten.ance con s ect I ve Act t on comyletton of _t, lie Beatt or, 1-503-78 V-9161 Normal use. Valve stem bent. Correc- Installed new bon- 2 Ilours None -  !

2-1-78 tive net and stem as- Reactor l sembly. Shutdown 1-543-78 IIV-2216 Normal use. Ilydraulic oil leak. Correc- Replaced poppet 1 Month None 3-1-78 Ilydraulic tive block.

Ope ra to r _

1-545-78 V-21108 System overpres- Valve leaks. Correc- Rebuilt valve. I Day None -

2-10-78 surized. tive Reactor i Shutdown 1-548-78 RT-93250-10 Wa ter in detector RT inoperable. Correc- Drained and dried 8 Ilours None -

1--27-78 housing. tive detector and Reactor cabling, replaced Shutdown failed transistor. I 1-553-78 IIV-21352 Valve sof t seat Valve leaks through. Corree- Replaced valve 2 Days None -

1-30-78 e rro de d. tive disc and seat. Reactor Shutdown 1-455-78 P V-22168 Normal use. Valve leaks at Correc- Replaced seal, re- 1 Day None - - l l

2-2-78 bon.wt. tive worked seal sur- Reactor to '

o faces. Shutdown ,

I l-607-78 V-9170 Normal use. Valve stem broken. Correc- Installed new _2 Ilours None -

2-1-78 tive bonnet and stem Reac to r assembly. Shutdown 2-25-78 IIV-2202 Normal use. Opera tor solenoid Correc- Replaced solenoids. 1 Day None - ~

2-8-78 Ilyd ra ulle valves leaking tive -

Rea c to r l Ope ra to r through. Shutdown '

2 78 P-2105 Normal use. Pump noisy. Correc- Replaced pump 36 None - l' 2-8-78 tive bcarings and seals. Ilou rs Reac to r Shutdawn 2 78 C-8203 Normal use. Compressor not Correc- Replaced unloader 2 Ilours None -

2- 7-78 Unloader loading properly, tive solenold. Reactor ,

Shutdown  !

2-68-78 V-2244 Normal use. I.eak a t gas ke t s ea l . Correc- Replaced seals and 2 Days 'Iione 1 3-8-78 tive gasket.

2 .103-78 IIV-2189-3 No rma l use. I.eaking air line. Correc- Replaced leaking 1 llour None -

2-10-78 opera to r tive fitting. Reactor Air 1.ine ,

Shutdown  ;

2-111-78 1.CV- 213 5-1 Normal use. Valve stuck open. Correc- Removed metal 8 Ilours None - {

2-9-78 tive wedged in valve Reactor seat, machined Shutdown valve seat and

.____ disc.

==

talkT ST. VRAIN SIGNI FirAhi itAlt(MANG SUMMA _RV F T i sse l

Identifica- Required Effect nei _

t ime Hood,c r Sy s t eim/ Nature of for Safe ogie r a t s oes an.1 Int u im>}<,urnt Cause of PLitfunction Result u of Hal f unct ion Hai nt eriance cor re ce I ve- Ac t Igi hiejalet ion of alie Re a :t or 2-14-78 SV-2105 Normal use. 011 leak. Correc- Replaced "O rings. 24 None I 8-16-78 Ilyd ra ul ic tive llours Ope ra t o r 2-120-78 V-21268-2 Normal use. Valve leaks through. Correc- Rebuilt valve in- 3 Days None 3-3-78 tive ternals.

2-124-78 FV-21333 Normal use. Studs broken on dia-_ Co r rec- Replaced studs. 4 Ilours None -

2-9-78 ph ra gm. tive Reactor Shutdown 2-162-78 V-21299 Normal use. Valve leaks through. Correc- Rebuilt valve 3 Days Nane l

3-3-78 tive internals.  ;

2-233-78 P-9105X Normal use. Leak from fitting. Correc- Repatred leak. 1 Ilour None p 2-16-78 tive 2-239-78 V-9102X Normal use. Ven t fitting leaking Correc- Replaced fitting. 1 Ilour 'None  ;

2-18-78 ~ oil, tive 2-266-78 PV-22153 Normal use. Excessivc leakage at Correc- Repacked valve. 2 Weeks None f 3-15-78 packing gland. tive L 2-300-78 L-91105 Normal use. Line failure. Correc- Repatrul line. I Day None I j

2-23-78 tive p 2-301-78 Plant Pro- Normal use. Module Inoperable. Correc- Replaced failed 2 Ilours None ,

2-22-78 tective Sys- tive integrated circuit tem Module chip.

CT-1 2-317-78 IIV-21338 Normal use. Solenoid loose and Correc- Remounted solenoid 2 Ilours None 2-27-78 Air air tubing crimi.ed. tive and replaced l

Solenoid tubing.

2-321-78 Main Normal use. Valves leaks through. Correc- Rebuilt valves. 2 Weeks None  ;

4-6-78 Steam tive Safety e Valves  !

2-387-78 Il-130 L Normal use. Inflatable seal Correc- Replaced Inflatable 1 Week None I 4-18-78 failed. tive seal.

l 3-30-78 Ilyd raulic Normal use. Lcaking cylinder Correc- Replaced seal. 1 Week None g 3-2 L- 78 Snubber seal. tive CRS-Cl-6 3 78 Ilyd raul ic Normal use. Cylinder seal leak. Co rrec- Replaced cylinder 1 Week None i 3 78 Snubber tive seal. I CRS-C4-6  !

3-33-78 Ilydraulic Normal use. Cylinder seal leak. Co r re c- Replaced seal. 1 Week None 1 3-21-78 Snubbe r Live CRS-C 3-5 -

k I

M f_S.T _1R,A{N 3 Sli;Hi{lCAN HAltifD4ANCE St!HnARY N' i

j Time I.len t i f i t .s- Re.g u l a cel Elfect .... -

t J..en ' Numl.e s Syulem/ De Natere of for S.a f e i e < f 8. n an,1 diat e Cosg ,nent Cause of H.altuncil us kemult s of Haltun( t lon H.alutenance Co r s e et 19.. Artlon Completi_op o f _,t 9i e t- .os 3-49-78 PS-1106-35 Normal use. i.eak in bourdon tube. Correc- Replaced with new 2 llours None 3-11-7'J tive switch.

3 78 P-2105 Normal use. Discharge pressure Correc- Replaced failed 2 Weeks None 3-21-78 low. _

tive _

bowls. _

3-72-78 IIV-21191-1 Normal use. Solenoid valve Correc- P.ebu il t valve. 3 Weeks None 3-28-78 sticky. tive 3-81-78 P-210lS Normal use. Mechanical seal Correc- Replaced mechanical 3 Days None 3-9-78 1enks. **ve seal. j 3-112-78 K-9203X Nc rmal use. Inope rabl e thermo- Correc- Rcplaced thermo- 2 Ilours None l .

3-5-78 Exhaust couple, tive couple.

Temperature Switch 3-132-78 Diesel Normal use. Cylinder #4 Injector Co rre c- Replaced injector. 26 None 3-14-78 Gene ra to r plugged. tive llours

_Enjii _ne " D" 3-229-78 IIV-2120 3-1 Normal use. Valves leak through. Correc- Rebuilt valves. I Day None  !

3-14-78 IIV-2120 3- 3 tive I 3-293-78 MM-1121 Normal use. I.i gh t level low. Correc- Replaced moisture i Day None y 3-16-78 tive monitor head with ,

Jipare. _

3-451-78 RI S-9 32 50-10 Normal use. liigh voltage circuit Correc- Replaced failed 2 Days None  ;

3-27-78 failed. tive t ra ns i st o rs in high voltage power supp ly .

3-476-78 ilV-2202 Normal use. Oil leak at filter. Correc- Repai red leak. 2 llours Noae i 3-28-78 ope ra tor tive '

Oil Filter 3-508-78 P-2107 Normal use. Reduction in pump Co rree- Rebuilt pump. 45 Days None 5-12-78 capacity. tive 3-554-78 IIV-2253 Normal use. Oil leak at solenoid Correc- Replaced "O" ring. 4 Ilours None 3-30-78 Ily draull e valve. tive fpe ra tor _ _ _ _ _ _

3-579-78 1.ine One Normal use. Pin hole in line. Correc- Ground out and re-_ 4 Ilours____ _ None 3-31-78 inch 21175 tise welded.

3-600-78 V-92108 Normal use. Valve packing leak Corree- Replaced valve 10 Iione 4-5-78 caused by bent valve tive with spare. Ilou rs stem.

I I i

i i

I!LRE lill y{A_IN SIGNigICANT ,HA BNitNUQSilHMARY '

F 11 ese l

Iden t i f i c.e - Reelu t t rJ klicca ou '

t Ion Number System / N.ature of for S.af e Hpee at lose

.no4 Itar e gaponent r.ause of H.alfunction Result s of H.al f unel lon Haintenance Cot t er t i ve Action completioni of tlie Reactor 4-3-78 SSil-21168 Normal use. Single channel trip Correc- Repaired burnt foil 6 Ilours None .

4-1-78 ala rm on fo r "D" cir- tive on PCB and replaced I c ula to r. relay on SSil-21168. l Also repaired burnt [ {

foil on LRD-1, 701, i l

p4, PCB and re-  !

placed K-10, A-2, A-4, and Q-10.

4-8-78 CT-2A2 Normal use. "A" logic low feed- Co r re c- Replaced chip 241. 1 Ilour None 4-1-78 water flow trip wil3 tive l no t clea r. l 4-9-78 FE-1115 Normal use. Inadequate sample _ Co rrec- Replaced FE-1115. 12 None 4-2-78 flow rate at greater tive llours ,

than 20% power.

4-45-78 SSil-21168-1 Normal use. Switch did not trip Corrac- Replaced failed 4 Ilours None 4-3-78 as required. (tive transistor.

4-99-78 IIV-2254 Normal use. Oil leakage at Correc- Replaced "O" ring 4 Ilours None 1 4-5-78 Ilyd raull e poppet block. tive under poppet block. g

. Op e ra to r _ ,

4-101-78 IIV-2189-5 No rmal us e. Bonnet to body leak. Correc- Replaced bonnet __ 8 Ilours None  ;

6-8-78 tive gasket. __ _

j 4-139-78 Replaced solenoid _

~

C-820 3 No rmal use. Compressor not Correc- 2 Ilours None I.-6-78 Unloader loading properly. tive valve and pressure l switch. l 4-155-78 SS-21166 No rma l us e . Indicated speed in- Correc- Replaced sensor 4 Ilours None t 4-7-78 correct. tive cable with spare.

4-191-78 IIV-2202 Normal use. i.eak at valve seal Correc- Replaced seal ring. 2 Ikiya None 8-24-78 ring. tive 4-202-78 CT-2A2 PPS Normal use. Ik>dul e failed. Correc- Replaced failed 2 Days None 4-8-78 Nodule tive futegrated ctreuit.

4-304-78 M-92814 Normal use. Glass filter bowl Correc- Replaced bowl . 2 Ilours Ene 4-11-78 hurst. Live 4-311-78 TS-8208 Normal use. l Switch failed to Correc- Replaced with 4 Ilours None '

4-12-78 _

l operator as designed. Live spare.  !

4-381-78

^

FE-21140 Normal use. Weld leak, Corree- Replaced pipe sec- 1 Day None 4-18-78 tive tion.

4-360-78 V-21537 Normal use. I.eak at valve flange. Correc- Replaced flange 8 Ilours Nonc 6-8-78 _ _t i ve _ gasket.  !

4-466-78 int- 1121 Normal use. Reflected 1ight Correc- Replaced amplifier 4 Ilours None  :

4-21-78 amplifier unstable. Live with spare. ___

l

toNr 5f. VNAIN $IGNIFiCANT HAIflIHIANCE SilHnARY F, Ido ifica- Fe <gu i r =J t.f f et t en 4 inn Hund,er S y a t u nm/ Natune of Safe operatfem for an.I lut e Coaymeen t Cause el Halfunctton Results of Halfunctton Halutenance rosrective Ac t lon (innp l ett_lon of jac f:e tc l u s.

4-563-78 Plant Normal use. Circulator trip Correc- Replaced failed 4 Ilours None i 4-24-78 P rot ec tive during surveillance tive integrated circuit.  ! k' ISystem tes t .

l l tiodule  ;

CC-2 _.

4-611-78 RIS-93251-10 Normal use. Detr; tar tube failed. Carrec- Replaced detector 2 llaurs None 7-15-78 tive tube.

4-625-78 TSil-8249 Normal use. Tempera ture switch Correc- Replaced switch. 2 Ilours None 4-27-78 capillary tube tive  !

b rok en.

5 78 ZS-22115 Normal use. Micro switch failed. Correc- Replaced switcli 4 llours None 5-4-78 tive with spare.

5-141-78 SH-21164 Normal use. Indicated circulator Correc- Replaced failed 4 Ilours None 5-7-78 Cable speed incorrect. tive cable.

5-142 ~8 IIV-2293 Normal use. Oil leak on operator. Correc- Replaced "O" rings. 3 lloors Ene 5-7-78 Ilyd ra ulic tive  ;

Ope ra to r I -

5-189-78 V-22188 Normal use. Valve stem and disc Correc- Replaced stem and 3 llours None w I 6-8-78 separated. tive disc. ,

5-214-78 XT-93455C Normal use XSil-93455C would Correc- Replaced failed A2 4 Ilours None '

l 5-11-78 not trip. tive amplifier in XF-934550.

5-269-78 IIV-2224 Normal use. Ilydraulic oil leak. Correc- Installed temporary 4 Ilours None i

}

5-15-78 Ilyd raul ic tive patch.

Operator Oil Return Flex Ilose 5-277-78 liv-229 3 Normal use. Valve operator not Correc- Replaced operator 4 llours 'IiiIne 5-26-78 Ilydraulic holding valve post- tive solenoid valves.

Operator tion.

5-278-78 H-72100 Normal use. Trap leaking through. Correc- Replaced trap seat 6 Ilours None 7-14-78 tive and disc.

5-379-78 IIV-2202 Normal use. 011 leak at operator. Correc- Repaired oli leak. 1/2 Hone 5-24-78 liyd raulic tive llour Ope ra to r 5-416-78 S-8201 Normal use. Compressor failed to Correc- Replaced unloader 4 Ilours thine 5-18-78 Unioader load properly. tive solenoid and l

switch. ,

5-433-78 V-91454 Normal use. Pressure erratic. Correc- Replaced valve. 1.5 lione I 5-19-78 tive llou rs i

IlL8I SIL3M{N SIGNQICANT HAINTFNANCE SLRittARY "

g T i sae lit. n( I t a c.s- 8equ i s ed kilene on t ion Nn.Jier System / Nature of for Sale prenatton an.1 lut e romponent Cause of Kal f untt lose Result s of Ral f unct ion Ma i nt enanc e ros s ect i ve Ac t ion tespletion of slee Re.at t ur F74F 78 V ill691 4 Normal use. Valve leaks through. Co r rec- Replaced valve with 1/4 None 5-20-78 _ __

tive spare. Ilo u r 5-457-78 FCV-2151 Normal use. Valve leaks through. Correc- Replaces soft disc. 4 Nours None 5-22-78 _tive 5-529-78 HM-1121 Normal use. I.ow li gh t level . Co rrec- Replaced detector 8 Ilours None 5-30-78 tive head with spare.

5-532-78 FC-2205 Normal use. I,oop 1 feedwater flow Correc- Replaced failed 4 Ilours None 5-24-78 control valve closed, tive transister in FC- i loop tripped. 2205, recovered shutdown loop. '

5-533-78 NSil-1136-i Normal use. Switch failed to trip Co rrec- Replaced failed in- 2 llours None 1 5-26-78 at setpoin t. tive tegrated ci rcui t. .

5-616-78 IIV-21345 Normal use. Valve leaks through. Correc- Replaced soft disc. 4 Ilours None i  !

5-29-78 tive g 5-619-78 V-91403 Normal use. Valve not adjustable Co r rec- Replaced valve 4 Ilours None

• 5-31-78 to greater than 3000 tive with spare. +

psig. l l l 5-620-78 V-91404 Normal use. Valve setpoint not Co r rec- Replaced valve 4 Ilours None ta 5-31-78 adjustable. wi th s pa re . *  !

tive 6-209-78 P-9105X No rma l use . '

Motor bearing failed. Co rrec- Replaced motor. 8 Ilours None '

6-15-78 flo to r tive 6-228-78 IIV-21185 Normal use. Valve not following Correc- Replaced XEP. 4 Ilours None 6-9-78 XEP controller. tive 6-231-78 P DI S-21179 Normal use. Microswitch failed. Correc- Replaced micro- 4 llours 'IIdne i 6-10-78 _tive switch. t 6-271-78 SE-21169 Normal use. Cable failed. Corree- Replaced cable 1 Ilour Hone 6-12-78 Cable tive with spare. _

6-331-78 SSil-21162-1 No rma t use. Module would not Correc- Replaced failed 2 Ilours None 6-13-78 trip in test. tive IC chip _.

6-360-78 TE-1173 Normal use. Indica ted tempera- Co r re c- Tightened loose 2 llours None 7 78 ture incorrect. tive connection. ,

6-364-78 PPS Module _ Normal use. Circulator tripped Co r rec- Placed failed IC 4 Ilours None ,

6-14-78 CT-1BR4 durlug surveillance tive chips. >

test.

6-412-78 IIV-21352 Normal use. Valve leaked through. Correc- Replaced valve 4 Ilours None 6-16-78 tive disc.

6-477-78 V-82493 No rmal use. Valve leaks through. Correc- Cleaned valve. 2 Ilours None 8-4-78 tive 6-478-78 V-8235 Normal use. Valve leaks through. Correc- Cleaned valve. 2 llours None f

8-4-78 tive ,

i i

I @ l ll: 3_R_AIN B ENIfjEAp[flAfgfNANCE Sl!MMARY '&

l l Time idcu t il l e.e- RequireJ Effect om -

tion Numi,e System / Natuse of for S.efr operation i 4en.3 is.it e Cangenent _C.suse of nalfusictfun Resul t s of H.el f mact ion H.a l n t e n.mc e t'or gret I ve Ac t loss Completlou of t l.a ste es tos , j 6-482-78 V-82492 Normal use. Valve leaked through. Co r rec- Iapped valve seat 10 None ,

6 78 tive and disc. Ilo u rs

,6-483-78 V-82445 No rma l us e. Valve leaked through. Correc- 1.apped valve seat 10 None 6-22-7F tive and disc. Ilours 6-484-78 V-82473 No rnal use. Valve leaked through. Co rrec- Replaced with spare. 10 None g 6-22-78 tive llours l

6-521-78 liv-21192-4 Nornal use. Valve leaked through. Co rrec- Rebuilt valve. 4 llours None ,

6-22-78 tive 6-526-78 TE-22136 No rnul use. Indicated temperature Correc- Replaced faulty TE. 8 Ilours Ene . .

7 7E above actin 1. tive 6-670-78 RIS-93252-Il Normal use. Erroneous high Correc- Replaced detector 2 Ilours lione i 6-30-78 reading. tive tube. -

6-682-78 V-2215 No rmal use. Valves leaked Correc- Repaired valve 2 Days None l l 10-2-78 and th ro ugh. tive seats and discs. l V-2216 6-695-78 'llV- 212 60 No rnal use. Air solenoid valve Q)rrec- Rebuilt solenoid 4 llours None 7-3-78 Operator leaking. Live valve. ' l j

6-705-78 IIV-224 5 Normal use. Valve would not Correc- Replaced failed 2 Days None M j 7-13-78 Ope ra t o r open. tive drive sleeve. ,

7-110-78 V-21298 Normal use. Relief valve lifts Correc- Rebuilt relief 2 Ilours None t 7-11-78 below setpoint. tive valve.

7-14 3-78 IIV-2253 Normal use. Oil leak. Correc- Replaced failed 8 Ilours None 7-14-78 Ilyd ra ul i c tive "O" ring. l

_ Ope ra to r __ _ l 7-144-78 11-72101 No rnal use. Trap leaking through. Correc- Replaced trap seat 1 Day None 7-14-78 tive and disc.

7-253-78 Mf t-l l l 6 No rnal use. Low reflected light Correc- Replaced moisture 8 Ilours None 7-15-78 at moisture monitor Live nonitor head with .

head. spare.

7-259-78 " C" Instru- Normal use. Compressor not Correc- Replaced unloader.

f 4 liours ~I1Ane 7-14-78 ment Air loading properly. tive  !

Oimp resso r  ;

7-268-78 SV-2112 Normal use. Indicated position Co r re c- Replaced I.VDT. 8 Ilours None 7-15-78 Position i nco r rec t . tive i I.V DT 7-271-78 PPS 11odule Normal use. Module failed sur- Correc- keplaced failed 8 Ilours Itine j 7-15-78 CRlHR4 veillance test. Live IC chip. i 7-276-78 PPS 11odule Nornul use. Failed surveillance Co r rec- Replaced falled 4 Ilours None 7-15-78 T1.T- 1 test. tive IC chip. i

H*l'ST.jRAIN SIGNI Flr_ ANT _, Hall 4 U4ANrE Sut1HARY

• F IJun a f f t .e - RequirrJ Ellert on  ;

t ione Ninabe r Sym a ess/ Nature of for Sale W eration  !

.eu.1 in.st e rosajaunt nt r.usse of fiell etion Result s of H.alf unct ion Hainten.ance ros a rs' t J ve A.-tion Otet l etlop o f flee Re.eClor 7-298-78 Spare Normal use. Outlet line broken. Correc- Welded broken line. 8 liours None 7-20-78 this ture tive ik>ni to r [

llead  !

7-301-78 PS-1106-30 Normal use, llelium leak in Correc- Replaced bourdon 4 Ilours None , ,

7-17-78 hourdon tube. tive tube. '

7-317-78 Reserve Normal use. I.eaki ng at fitting. Correc- Replaced fitting. 1 Ilour None 7-18-78 Shutdown tive Bottle

• Connection _

7-328-78 N i ti-1134 Normal use. Discontinuous Correc- Replaced potenti- 2 Ilours None 7-18-78 po ten ti ome te r. tive ometer.

l r

~

7-462-78 PDIS-21397 Norna l use. Indicated differen- Correc- Replaced high and 4 llours None l 7-24-78 tial pressure in- tive low side flow correct. restrictors.

7-475-78 S V-2105 No rmal use. Oil leak at operator Correc- Replaced shaft I ikny None 8-16-78 Ilyd ra ulic shaf t seal. tive seal. I 3

Op e ra to r o 7-477-78 PPS t!odule Normal use. Failed surveillance Correc- Replaced failed IC 2 Ilours None 7-25-78

[

CTIAR4 test. tive chip.

7-489-78 lT-21428 Normal use. Failed diaphragm. Co rre e- Replaced diaphragm. 4 Ilours None 7-26-78 tive '

7-500-78 TSil-22137 Normal use. Indicated temperature Correc- Replaced terminal 2 flours None 7-26-78 '

incorrect. Live boa rd s c rews .

7-509-78 SSI.-21162-1 Normal use. Speed switch tripped Correc- Replaced failed 4 Ilours None 7-26-78 SSI.- 2 L l62-2 low with circulator tive amplifier.

at speed. .

7-556-78 FT-21426 No rnal use. Diaphragm f ailed. Correc- Replaced diaphragm. 4 Ilours None i 7 7_8.__

tive 7-569-78 IIV-2253 No rmal use. Oil leak. Correc- Replaced solenoid 8 Ilours None 8-23-78 Ilyd ra ul 1e tive valve.

Ope ra t o r

(

7-580-78 TSI.-22 26 Normal use. Switch failed to Correc- Repaired had con- 2 Ilours None 8-1-78 ope ra t e . Live nection tu switch.  !

8-11-78 V-22187 No rmal use. Packing leak. Correc- Repacked valve. 1 Ilour None '

8-1-78 tive 8-29-78 K-9203X Normal use. I.eak a t weld. Correc- Repaired weld. 3 llours None 1 8-9-78 Cooling tive Water Fill I.ine l

I IN[ Ela_ Vital.N SIGNI FIC_ANI' }IAllMANrymituity

• l Time Identiftsa- Itequired Eficct on j tlun Ni.mber System /

.u..I Iter e Congoucut Cause of Halfunctlun Itesult s of Hal f unct ion Nature of Hafntenance Cor r ec t I ve Actton for S,ste ryerat ion Completlou of t he fleact or j

8-75-78 V-9163 No nna t use. Valve stem bent. Correc- Replaced valve 4 llours None i 8-4-78 tive stem. I 8-94-78 S11-21164 Nonnal use. Speed signal in- Correc- Replaced undule 4 Ilours None j 8-5-78 correct. Live with spare.

8-153-78 V-75640 Normal use. Packing leak. Correc- Replaced valve. 3 llours None 8-1-78 tive 8-154-78 SV-2105 __ Normal use. Valve would not open. Correc- Replaced solenoid 1 Day None 8-14-78 Ilydraulic tive valve. .

j ope ra to r i 8-183-78 liv-2245 Normal use. Valve stroke limited. Correc- Replaced torque 2 Ilays None 8-12-78 tive switches on i op e ra to r.  ;

8-200-78 V-82473 Normal use. Valve sticking. Correc- Replaced valve. 2 Hours None l 8-14-78 tive .

8-225-78 Plant Pro- Normal use. Erroneous rod uit h- Co rrec- Repaired had 2 llours None  !

8-15-78 tective Sys- drawal prohibit. tive solder jolut.

tem Module I

• 101-P- 3 g ,

3-292-78 Pfi-2212-1 Normal use. Indica tion erroneous. Correc- Replaced failed 7 Ilours None _ _ _ _ _

I i

8-18-78 tive parts (IC chip and  ;

capacitors).

8-333-78 C-2801 Normal use. Compressor not Correc- Replaced solenoid 2 Ilours None 8- 21-78 loading. tive valve. _

8-347-78 f f?l-1122 Normal use. Spurious trips. Correc- Replaced moisture 3 Days None g 8-25-78 tive monitor head and light guide. l

~

8-350-78 IIV-229 3 Normal use. Seal ring Icak. Correc- Rebuilt valve. 3 Days None 10-5-78 tive 8-411-78 Ilyd ra ul ic Normal use. Oil ler Co rrec- Replaced failed 8 Ilours None '

8-26-78 011 System tive "O" ring. f Pipe Fl an ge 8-415-78 P-9102X No rntil use. Ileari ng failed. Co rrec- Replaced motor. 6 Ilours None 8-30-78 Flo to r tive g 8-451-78 P-2103 No rma l use . Excessive leakage Correc- Rebuilt pump, re- 4 None )

12-22-78 at mechanical seal. tive placed seal. tionths l 8-481-78 CT-I AI.1 Normal use. Spurious trips. Co r rec- Replaced failed 4 Ilours None I 8-30-78 PPS tiodule tive integrated cir- 4 cults.

8-517-78 V-7232 Normal use. Valve leaked through. Correc- I.apped valve seat 20 None 9-21-78_ tive and replaced plug. Ilours I,

4 DONT ST. VRAIN SIGNIFICANT HAltflFNANCE SlHtHANY

,I a

tis e .

I.I.:nl 1 I i t a- Be<tial e ed kiiect on t ion Nued.cr S y u t eis/ Nature of for Safe operation l

6 gn 1 p..t e O. poncut cause of H.si f unct ion Reuult s of Hal f unct ion Haint enance

• cara cct i ve Ar t ion costl ethm o f. _t 3t e Heat t o r_,

9-19-78 V-9115 Normal use. Pressure control Co r rec- Replaced valve in 4 Ilours None l 9-5-78 erratic. tive kind. ___ l 9-27-78 IIV-2217 Normal use. Oil leak. Correr - Replaced failed 6 Ilours None i 9-6-78 Ilydraulic '"

tive ring.

Ope ra tor I 9-82-78 MM-1118 Normal use. Thermocouple circuit Correc- Repai red thernn- 6 Ilou rs None l 9-7-78 Thermo- open. tive couple connector. , ,

couple _

~

9-103-78 Ilv-2253 Normal use. Oil leak. Correc- Replaced failed 12 None l 9-9-78 Ilydrauli c tive "O" rings. Ilou rs Ope ra to r __

9-116-78 PDT-21295 Normal use. Valve leaks through. Correc- Replaced valve. 1 Da y None i 10-5-78 Dra in tive l f Valve _ - l 9-119-78 TE-22137 Normal use. Thermocouple opeu. Correc- Replaced IC with 3 llours None  !

9-8-78 tive spare. '

9-136-78 V-7228 Normal use. Valve leaks through. Co r r ec- 1,apped valve seat 16 None 1 9-24-78_ tive and disc. Ilou rs g 9-156-78 P-9105X Normal use. Motor bearings Correc- Replaced bearings, 3 Days None ,

9-16-78 Motor failed. tive rehuilt end bell and rotor.

9-159-78 MM-1120 Normal use. Indicator lights Co r rec- Replaced failed 2 Ilours None 9-13-78 ino pe ra bl e. tive relay in test module.

9-170-78 RIS-6314-2 Nornal use. Compressor not Correc- Replaced com- 6 Ilours None 9-19-78 Compressor pumping. tive pressor.

9-187-78 CT-1 AI,3 PPS No rma l us e . Module caused Correc- _ Replaced failed 2 llours None 9-15-78 Module spurious trip. tive IC chips.

9-237-78 SM-21162 No rma l us e . No indicated speed Correc- Replaced failed 2 Ilours None 9-17-78 signal. tive IC chip.  :

9-280-78 SM-21172 Normal use. No speed Indication. Correc- Replaced failed 2 Ilours None 9-25-78 tive 1C chip. .

9-283-78 V-21446 Normal use. Valve leaks through. Correc- Replaced valve stem E ours None 10-27-78 rive and disc.

9-316-78 Ilv-22 53 Normal use. Safety valve on oil Co rrec- Replaced safety 2 Ilours None l 9-25-78 Ilydraul f c side leaks. tive valve.

Operator 9-371-78 P-2110 Normal use. I.cak a t pipe nipple. Correc- Replaced pipe 2 Ilours None 9-29-78 Pressure tive utpple.

Tap I

r IU_l H SE:J MIN _ Sy;Nify M l__jn g(({ NANCE St!HitARY M l l Tl ase I.l.:nl i f tu. Required Effect on ,

eson Nueecs Systead Natiste of for Sale ayeast ion an.1 lut e Cause of Halfunctfun l Cosimucut Results of Kilfunction Hal nt enance Coerective Act ion Coet tet loan of tlee Reattot 9-384-78 PDT-21293 Normal use. Valve leaks-through. Correc- Replaced valve. I Day None i 9-29-78 Drain tive I Valve {

9-391-78 IIRS-13 L Normal use. 011 leaks from Correc- Replaced reservoir 2 Ilours None l 9-27-78 Snubber reservoir. Live seals.  ! j 9-421-78 IIV-229 3 Normal use. 011 leak. ' Correc- Replaced solenoid 3 Days None  !

10-5-78 Ilyd raulic tive valve and poppet Operator block.

10-7-78 11V- 220 3 Normal use. Oil leak. Correc- Replaced poppet 1 Day None l 10-3-78 ope ra to r tive block and "O" ring.

10-52-78 FV-21333 No rma l use . Valve diaphragm 3 rrec- Replaced diaphragm. 4 Ilours None -

10-16-78 _Op e ra to r broken. tive l 10-71-78 C-8201 Normal use. Compressor short Correc- Replaced solenoid 2 Ilours None  !

10-5-78 Unloader cycling. tive valve.10-101 P-2106 Normal use. Excessive leakage Correc- Replaced mechanical 2 Days None

-78 at pump seal. tive seal. I 10-12-78 u

-o 10-114 fifFil18 Normal use. Loss of scattered Correc- Replaced light 4 llours None ,

-78 and reflected light. tive source.

10-6-78 10-168 C-8201 No r ma l use . Pressure switch Correc- Replaced pressure 2 Ilours A ne

-78 linloader actuating at too tive switch.

10-9-78 Pressure low a pressure. ,

Switch i 10-187 121-1122 Normal use. Loss of scattered Correc- Replaced light 4 llours None  !

-78 and reflected light. ti ve '

source.

10-10-78 i 10-197 PDT-2133 Normal use. Leak at weld. Co rre c- Repaired weld. 2 Days None l

-78 Instrument tive 12-7-78 I. i ne 10-235 FDbil21 Normal use. Light source Co rrec- Replaced light 4 Ilours None

-78 failure. tive source.

10-12-78 10-295 l

480 Volt Normal use. Transformer failed. Co r rec- Replaced with 24 None

-78 Essential Live spare. Ilou rs 10-17-78 Bus 1 Trans fo rme r 10-429 till-1118 Normal use. 1.ight level low. Correc- Replaced moisture 4 liours None t

-78 tive monitor head with '

11-1-78 _syare. i

I.l'.E.EIrpf[N Sl{M[FICANI HAlifII. HANCE SantnARY .-

l l Time Iden t i f lus- I Regia i r ed Eifett on tion Nna6er System / Nature of for Safe operation ~l

,uy.i pa t e _

, tjimgioncnt . cause of Halfunction lienul t s sof Hal f unct lon Halutenarue Cor ree t tve As t Ion Cosiiplet lon of t im e k<*ac e n t 10-469-78 Cable 25590 Normal use. Cable indicated open. Correc- Cleaned up ter- 4 Ilours None 10-27-78 Between TE- tive minals at junction 93448 and box.

XSil-93448 10-503-78 Plrf-21295 Normal use. Valve leaks through. Correc- Replaced valve in 8 Ilours None ,

10-31-78 Drain Valve tive kind.

10-507-78 PPS ffodule Normal use. }lodule tripped with Correc- Replaced failed 4 llours Ee 10-31-78 CT-2n1 normal input. ti ve integrated circuit.

11-36-78 V-21298 Normal use. Valve leaks t h rou gh . Correc- Overhauled valve. 5 Days None l 12-6-78 tive 11-37-78 V-21268-1 Normal use. Valve leaked through. Co rrec- Rebuilt valve 2 Days None 12-1-78 and tive seats and discs. .

V-21268-2 ,

11-38-78 V-21543 Normal use. Valves leaked Correc- Rebuilt valve 2 Days None +

L2-1-78 and through. tive seats and discs.

V-21523 l l- 110- 78 SSI.-21161 Normal use. Cable failed. Correc- Replaced with 4 llours None I 11-8-78 Cable tive spare. g  !

11-141-78 IIV-22227 Normal use. Valve leaking. Co r rec- Repaired valve 2 Weeks None , l 12-11-78 tive seat and disc. ,

11-188-78 PPS Module Normal use. False trip. Co rrec- Replaced failed 4 llours None l ;

11-14-78 GTillR4 tive integrated circuit.

L 1-191- 78 PPS tiedule Normal use. Module failed Correc- Replaced failed 4 Ilours None 11-14-78 CTIBL3 tripped. tive integrated ci r-cul ts .

11-198-78 PPS liodule Normal use. Module fa iled Correc- Replaced failed 4 llours Ene '

11-15-78 GC- 2H2 tripped. tive integrated cir-

~ cult.

11-301-78 PPS tiodule Normal use. tkidule failed Correc- RepInced failed 4 Ilours None 11-16-78 CT1-AL3 tripped. Live lu tegra ted ci r-cult. . _ _ _ ,

[1-303-78 PPS tiodule Nornul use. Module fa il ed Correc- Replaced failed 4 Ilours None 11-16-78 CT-2A2 tripped. Live integrated cir-  !

cult.

11-360-78 Stt-21164 Normal use. Cable failed. Correc- Replaced cable. ~4 Ilours None 11-20-78 Cable ~

tive 11-518-78 V-2264 Normal use. Valve leaks at Correc- Replaced seal ring. 4 Ilours None  !

12-6-78 seal. Live  !

L1-542-78 TE-22140 No rmal use. Failed open. Co rrec- Replaced TE with 4 Ilours None f i t-2 7- 78 tive spare._ i

i I'!.34.EI:. VyAIN SICNI}ICAy[3It(fQAgi I[ Et,lHyA '-

Tl sne IJen linca- Itequ i t ed Effect on t ien N.nees S y s t ess/ Natuse of for Safe opesation  !

au.I lute romysyneut C,euse of Halfunction Results of Halfunctfun Ha i nt e-nanc e Coe rect I ve Ac t s on Coayletion of the Beactos 11-564-78 P- 4202 Normal use. Worn bushing. Co rre c- Replaced bushing. 24 None 11-30-78 tive liou rs 11-575-78 PPS Module Normal use. tbdule failed test. Correc- Replaced failed 4 Ilours None i 11-27-78 CCr-2, B2 tive integrated ci rcuit. __ l 11-590-78 IIV-22133 Normal use. Air line fi t ti ng Co rrec- Replaced failed 1 Ilour None 1 11-29-78 Air 1.ine failed. tive fitting. _

l' 12-37-78 V-211003 No rmal use. No flow through Co rrec- Replaced valve in _ 2 Ilours None 12-2-78 valve. tive kind.

12-40-78 XDIS-21157 _ Normal use. Switch failed Co rr ec- Replaced switch. 4 Ilours None 12-2-78 tripped. tive ,

[2 78 XDI S-21151 No rma l use . Failed tripped. Correc- Replaced switch. 2 liours None 12-4-78 tive ,

12-103-78 M-21830-1 No rmal use. Valve threads worn. Correc- Replaced valve. 2 liours None j 12 78 l '

tive 12-184-78 TE-22106 Normal use. Lead broken. Co rrec- Repaired lead. 1 Ilour None  !

12-9-78 tive 12-249-78 V-2244 Normal use. Seal ring leak. Co r rec- Repaired leak. 8 llours None i 12-14-78 tive ~

u i 12-255-78 PPS Module No rma l use. Indicated temperature Correc-12-13-78 Ilo t Rehea t low. tive Cleared short at terminal board 4 Ilours None

'[

S cram for the rmocouple.

12-263-78 IIV-1] l 70 Normal use. Valve leaking Correc- Replaced crimped 2 Ilours None l 12-13-78 ope rato r th ro ugh. tive air line on  ! -

op e ra to r .  !

12-292-78 V-21522 No rmal use. Leaks at flange. Co rrec- Replaced flange 2 Ilours None 12-15-78 rive gasket.

12-298-78 M-72103 Normal use. Steam trap blowing Co rrec- Replaced t rap seat 4 Ilours None ,

12-14-78 through. Live and disc. l 12-306-78 PPS lbdules Normal use. !bdules failed. Correc- Replaced failed 4 Ilours None  !

12-14-78 CT-1 AI.3, tive integra ted cir- i CT-2A2, cuits. i CT- 1 Ill. 3, CT-2112 12-318-78 V-91404 Normal use. Pressure con trol 3 rrec- Replaced valve in 1 Ilour None 12-18-78 erratic. tive kind.

12-473-78 TE-22144 Normal use. Indicated tempera- Correc- Tightened loose 2 Ilours None 12-29-78 ture in erro r. tive connection.

l I

I t

4 m

2.0 fl. ANT UtttAQ.S OH tuki:ED RElstk.TlW44 I N l'tiLJ EH l

_ _ _ _ _ _ . _ , ,_. _ _ _ _ _ _ _Kilor Sa f et y Radiation. Release e Related Ger- Associated uitti out-unsrective Action sective Halu- age whitta Accounts  ;

Helated Re- Taken to Redore tenance Per- for more than 10%

portable el.e Paubahtlity of operattug form.ed Lauring of Alluuable Annual N un_d,ee r___ , l_Qalaeate Cause Systcae_ _ .Kj or Component .Occurtence Recurrence Time 1.ost ,the outage Value 77-29 Steam Geneaator Secondary Steam Generator 50-267/77- Plugged Subheader 756.6 Blouis Flugged Sub- None Tube i.ea k Coo l.ne t thidule B-t-l 42/03-T Cuntaining 1.e.ik ing (1977) header Cun-Tube 286.1 llours (1978) talning 8.eaking Tube l{

1,042.7  ;

(Tutal) i 78 01 Spueloos Hain ILein Tur- Electruhydsau- None None 18.8 theurs None None Tusbine Trip hine Gen- l a c unnt rol  !

esator System

_ . . _ _ 4 18-02 nif finict son of alellum f.evel 50-267/78- Replaced f.evel 1.709.8 Replaced I.evel None nearing W aer Circulatur Gentsoller 03/01-T Cont oller llours Contsoller Susge Tae.k Auxil-i.evel Cuntaulter taries '

w i

-_ . - _ 6a 1H 0) Tushine over- Kiln nain Turbine None None 1.4 llours None None speed Test Generatur 75-04 Spua loins Ka l u Hain Electrohydrau- None None 5.8 Ilours None None Tushle.e Trip Tuabine lic umtrol l System l

/H 05 Spurious tLain H.a l n Electruhydsau- None Hone 1.8 Ilouse None Hone Tusblue Trip Tushine lic unntaul System 18 06 Tushine Talp Rain Electruhydran- t3o ne None 0.8 Ik>usu Hone Nonc l>ur i ng t' llc Tu r te l ne lic uminut System Test System 1H-01 Trip of nain na i n Electrohydrau- None None 6.7 Ilouis None None Tusblue During Tuibine lic Contaul EllC Test System I

i e

t

tLijor Safety kaJiations Helcase kelated ti>r- Associat ed with Out-Corrective Action s ec t i ve fis in- age whirt Arcosmitu Helated ke- Taken tu iteJuce tenance Pen- for mere thais 101 po r t atile t he P a ol>a bi li t y o f operating fosawd During of Allowable Annu.at

_N,ua.lg t __ P a n x i s_ms t e Caiss e Sy s i c ui tLijor gegeneist Occuvience Recurrence Time f.ust the Outage Value 18-08 Trip of ttain Tur- Pla i n Tur - Electsuhydraulic Hone None 1. ) Eksur s None Houe blue Durisig EllC bine tient rol System Test

_ _ _ _ _ _ . _ . _ . _ .. _ . _ _ _ ._ 1

/8-09 Feedwater luo- Second.a n y Feedwater loo- None Repaired I.cak Power ke- None Nois e j l.stion Valve Coolant latlun Valve Jiiction '

l.c.s k tur I19 i

Ilius e s .

18-10 Pl.s i n Tu r te l ne Hain Tur- Feedwater Valve None None 22.9 Ilouis None None Slau t akewu to He- blue cover 1.uop Shut- i i t

ik>wn to Hepair i Feedwater Valve e

78-11 Power Medisced to Secondasy Steam Tenyera- None None 8.) Ilours None None th>Ji f y fla t ri usolant y g ture timt soller S t rain Teenpe r a- e i

t un e th>nt aniler 18-12 l'ower Reduct ion Second.ary Feedwater Hone Hepaired I.eaking 12.3 llours None None to Nep.s l a Feed- (iso l an t Staalues S t raine r '

w.s te r St raisse r

_ _ _ . _ . . _ _ _ . . _ _ . . . i i

78-11 'l ui t. i ne Tak es: 01f Secund.ary Feedwates None None 35.5 Hourn None None I. lin e to Recover Coolant Strainer 1.nop Shutdown for Feedwater i

Strainer 18-14 Spurious Sciam l'la n t Pao- Fa ul t y Tes t None None 35.1 lioners None Nonie tective l ea st s umen t System

)

-- -- - - - . -_.-_- t 18-15 Buf f er llelline licilius Ca r- Buffer Dryer 50 2f>7/78- Repaireil Bsifer 11. 4 liois u n Dayer Hepair Hone i s yer PLal f ause- c's t at o r I f>/0 3 -I.-0 Dryer tlon C.aused liigh Auxillaries the l s t u r e in Pri-m.a s y tiso l an t n

Kijor Saf ety Radiatlute Release .

RelatcJ Cor- AssociatvJ with Out-Corsectlve Action sective H.nin- age whicls Arrouutu Related Re- Takei* to RcJuce tenance Per- for unse e tis.ma 10%

portable - the Probability of Operating f o s med I)ur ing of Allowalile Annual N umi,e r P ro,lm.a t e C.ause System _t Q r Coatwinent Occurrence . Recurrence Time lost the Outage Value 18- I f, loop Fredwat er Secondary teelwater Valve None Repaired Valve 53.7 Ilouru Hone None Gnitso! Valve Coolant Qantsuller Controller Clumed 18-17 Tini,ine Taken of f Secondasy Feedwater Valve None None 12.7 Ilouru Hone None

!. i ne to Recover Coolant O>ntsulter 1.oop Shut down By Feedwater Valve D>utsoller Fal l ut e 1H-!8 Shutdown for NRC None None None None I)).? Ifousa None None I.lces se Examina-t lans e

18-19 loss of Instiu- I sis t r umen- Bus II Inverter Hone Repaired Inverter 118.7 Houru Repalted in- None g ment Bus t a t losa verter ,

78-20 Spus ions Kalu Kain Gen- Electrohydraulic None No ene 1.1 llouru Hone None Tais t.i ne Ta ly erator Osntaol System 18-21 Kanu,el Tus hine Plant Pso- Plant Psotective None Repaired Plant 60.9 lhous s Hepair of None 1 rip Following tective System it>Jule Psotective Sye- Plant Pro-1.oup Shutdown System tem Kidule tertive System H.Jule 18-22 Power Rediaction Primary Primaany Coolant 50-267/78- None 109.8 None None line to P r ieu r y Osoluut (heml ut ry 18/03-1.-0 llouts Coolant Ontdant 1.evel 1H 21 ha l l u s e o f 4 M0 480 Volt 41f4 to 460 Volt 50-267/78- Replated Trans- 415 Iluures None Noeie Volt Transfosmer Electrical Transformer 28/01-T-0 fo r me s 18-24 liigh oxidants in P a l ma r y Palaussy Goolant 50-267/78- None  !?.2 alouse teone Houe P s i nu s y Cool. ant Coolant themistry 1 H/0 3 -l.-0

P O

Fisjos Safety R.aJiation Helcame ,

Rel.ated Cor- AssociatcJ with Out-Corrective Action s ec t i ve Plain- age whlti. Accounts Melated Be- Takes to ReJure ten.ince Per- f or mass e t h.in tot f o r t al>l e t he Probability of ope r a t i sig foa mcJ thering of Allowable Annual N iu. die s Peomim.ete Cause System ita lo r Componen t ,0ccurrence Recurrence Time Ins t _ the outage Value ,_

l JE 25 Spurious kractor Plant l'ro- tbnisture tbnitor None None 12.8 Ilours None None Scram tective I System  !

7H-26 Tusbine Genera- ttain Tur- Company litut ri- None None 0.9 Ilours None None sur Talp From bine 1.ut ton Sys t em i Syn ti-m IIpset 18-21 H a gli Pa lma n y P r i m.ar y Primasy Coolant 50-267/78- None 5.4 Hours None hone Geolant Dald.anta Coolant Chemistry 18/03-I.-0 18-28 Tust,ine Genesa- Ins t rumes - Pisin St eam Tem- Hone Recalibrated De- 0.8 Ilouas None None tur Spurious tation perature Det ec- tector Tsip tur 18-29 HyJaaulic ull Replaced Flange '8 llydraulle Pipe Plange Hone 31.4 Ilouss Flange Repair None ,

System f.eak 011 System Casket 18- k) Hout lue ShutJuwn None None None None 635.5 None None f or itslutenance Hours

.an.1 Testing 18-14 Tushine Genesa- Plai n Tur- Elertsoleydraulle None None 29.3 tiouse None None to: Spurious hine Control System Tsip 16- Il 480 Volt Tsanu- 480 Volt 4160/460 Volt None Replaced Trans- 151.M Heplaced Trans- None foemer Falluse Electrical Trastatoimer former flou r s foamer System 13- 11 Tusblue Trip Due lustrumen- 1.ow Pla i n S t eam None None 0.4 Hours None None I t u 1.ow tLa t si tatlun l Tenperature Tur- 1 i Steam Tempera- t.Ine Trip Cir- '

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. ture Caused by cult ,

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_ _ _ _H.njos Safety _ _ _ _Raillation Release _ _ _ _ _ .

HelatrJ Cor- Assur lst eil wi tti uut-Corrective Action sective Hain- age winicle Acto uat u kelated Re- Takein to Reduce t enance rer- for nose t h.in fut luistable tl.e Prol, ability of apperattug foa med Ikstjug of Allowable Anusu.at N uml.e r Paoximate Casese D aten nj or Comimnent occurrence Recurrence Time inut the Outa g value 18 - 14 To blue Talp Hain Tur- Vibration Trip None None 19.9 llours Nasie Niine C.suscJ lay liigli blue Cis cuit Vibsat lon Fol-luulug 1.oad RcJuctfun 18-15 Euf fer tic!!aus llellum fiellum Hecovery None Repsised Recovery 198.6 None Nolee Sys t ess hal f unc- Claculator Op9:essor Compressor liipe r s t ions C.a used Auxillaries i Tus taine Trip 18-36 load Reduction lle l lium ruige Valve 50-267/18- Repaired Purge 94 llouse RepaireJ Purge Hone fus Mepair of Ci rcula t u r 19/03-1.-0 Valve Valve Buffer lit ye r Auxillarieu Purge Valwe a

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- ._._ w _. _ _ _ _ ____ . . _ _ . . . _ _ _ _ _ . - _ - _.

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3.0 RADIATION EXPOSURES No personnel at Fort St. Vrain received radiation exposure greater than 100 mrem / year during the report period.

4.0 FUEL EXAMINATIONS No exa=1 nation of irradiated fuel was co=pleted during the report period.

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