ML19296D145

Annual Operating Rept 9 for 1979.

ML19296D145
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1979
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19296D144	List: ML19296D143 ML19296D145
References
NUDOCS 8002290405
Download: ML19296D145 (37)

Text

.

PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION ANNUAL OPERATING REPORT NO. 9 1979

~

a i

e 8 0 02 290kOS

4 INTRODUCTION This report is subritted in accordulce with Section AC 7.5.1.b of the Tech-nical Specifications of the Fort St. Vrain Nuclear Generating Station, Unit No.1, Facility Operating License No. DPR-34.

i 4

a s

b O

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE This report contains the highlights of Fort St. Vrain Unit No.1 operation under the provisions of the Nuclear Regulatory Commission Operating License, DPR-34. This report is for the year of 1979.

1.1 January The 1D helium circulator experienced another unplanned trip on Janu-ary 2, 1979. Four plant protective system logic chips were found to be failed af ter this trip. These chips had been tested to be functional the previous day. The plant was returned to 64% reactor power (200 We) on January 4,1979, following cleanup .sf the primary system helium. Later on January 4,1979, the primary coolant moisture levels increased because of a valve failure in the circulator buffer helium dryer system. Due to the primary coolant oxidant it: purity level exceeding 10 ppm, the reactor power level was reduced to 30%

of rated.

The reactor power level was increased as the helium impurity levels allowed and reached 60% of rated (190 We) on January 7,1979. On January 5,1979, the "C" boiler feed pump was taken off line due to high vibration. The pump casing was found to be eroded and the plant was to be limited to about 195 We during the eight weeks estimated to repair the pump.

The plant operated at 63% power (195 We) until January 19, 1979.

At that time it was decided to reduce power to less than 30% and shutdown Loop 2 to repair a secondary coolant leak on steam generator trin valve TV-2228-1. The fur =anite leak repair process attempted previously in the week did not work. As the power reduction was in progress, a problem developed with Loop 2 main steam bypass valve PV-2230 which resulted in loss of control of the secondary coolant flow. The main turbine generator was tripped off the line at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />.

As a result of the turbine trip, t'ae reactor power was reduced to 2% awaiting the repair of TV-2228-1 and PV-2230.

~

Reactor power was increased to 25% on January 22,1979, at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> and to 30% at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. Power was held at that level until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on January 24, 1979, awaiting primary coolant oxidants to reach acceptable levels to increase power. Power was increased to 63%

(195 We) at that time.

A problem occurred with the helium dryer which necessitated bypass operation during repair. Operation with the helium dryer bypassed caused primary coolant oxidants to increase beyond acceptable limits for operation at 63% power and power was reduced to 42% for cleanup.

!* Cleanup was achieved on January 30, 1979, and power was increased to 60%.

3

,w <

9 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.1 Januarv (Cont'd)

A reactor scram occurred at 1338 hours0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br /> on January 30, 1979, duc to a dip in instrument bus 2 voltage caused by a short circuit during repair of a Gaitronica communications unit.

The reactor was restarted and returned to critical on January 30, 1979, at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br />. A problem developed in "B" feed water pump which caused it to be declared inoperable.

This problem, in conjunction with the inoperable "C" feed pump, did not permit continued operation at power.

1.2 Feb ruary The reactor was shutdown for refueling on February 8,1979, af ter all required practice starts by licensed persennel and license candi-dates were completed. Shutdown had previously been scheduled for March 1,1979, but due to boiler feed pu=p problems which could not be repaired in time to permit any significant power operation prior to March 1,1979, the decision was made to start the refueling shut-down early.

Helium circulator C-2103 (lC) which had been scheduled for removal for inspection, was removed on February 28, 1979, and the spare circu-lator was prepared for installation.

The main turbine generator overhaul was started on March 5,1979, as scheduled, with coc:pletion scheduled for May 4,1979. General Electric Company was the prime contractor for the job with three erectors on site.

Primary coolant circulation was maintained by one water turbine driven circulator. Mo tive force was the condensate header through the con-densate/ firewater booster pumps. Several tests were run to verify proper core cooling under those conditions which proved satisfactory cooling could be achieved with that mode of operation. . Us e o f the motor driven feed pump for water turbine motive force would have been -

necessary prior to the addition of the condensate /firevater booster pumps.

Decay heat removal was by the secondary coolant via the decay heat exchanger. Secondary coolant flow was limited to Loop 1 at that time.

as Loop 2 was shutdown and isolated for maintenance.

The main condenser was cleared out and drained in preparation for the main turbine generator overhaul. Eddy current testing and acid j cleaning of the condenser tubes was scheduled for that period.

1

.i

1.0 NARRATIVE SL. MARY OF OPERATING EXPERIENCE 1.2 Februarv (Cont'd)

Installation of the additional te=porary auxiliary boiler was com-pleted with testing in progress at the time to allow placing the new Soiler into service. This was to be accomplished by March 9,1979.

Fuel loading was continually hampered by problems encountered with the fuel handling equipment, particularly the fuel handling machine itself. At that time, removal of the fuel. and required reflectors from region 35 had been completed. Tests, RT-520 (Region Cons traint De vices) , P.T-518 (Region 35 Inspection), and RT-518B (Region 35 Reflector Block Graphite Specimen), were also completed in con-junction with Refueling Procedure RF-1. _

1.3 March Refueling shutdown progressed on schedule. Regions refueled at the end of March included Region 35, Region 5, Region 21, and Region 28.

Region 17 and Region 10 still required refueling. Region 27, Region 24, Region 30, Region 22, and Region 25, required insertion of layer 12 reflector element containing a PGX graphite sample and a fuel test element. A complete inspection of Region 13 down to the core support block was also planned. Of the 1,280 activities to be completed during the refueling shutdown, 716 had been completed.

The main turbine generator overhaul completion date of May 4,1979, was reported by General Electric to have slipped to May 24, 1979.

Completion of the installation of helium circulator C-2103 was esti-mated to be approximately three weeks away.

The main condenser cleaning was completed by Dowell contract with what appeared to be good results. Eddy current testing of the tubes indicated tube failures continued and plans were made to plug an ad-ditional 400 tubes.

Repair and cleaning of the circulating water cooling tower was getting started and was scheduled to be completed in approximately three weeks. __

Valve repacking on Loop 2 secondary coolant piping, condensate header, 150 pound steam headers A and B, and the deaerator piping system com-prising some 1,300 valves, was completed. Valve packing on Loop 1 secondary coolant completion was scheduled for April 30, 1979.

System 91 (hydraulic oil for valve operation) Loop 2 shutdown mainte-nance and system revision activities were completed and System 91 Loop 1 was shutdown and undergoing the same process.

3 I

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.4 Ap ril Refueling shutdown continued to progress on schedule. The six regions scheduled for refueling were completed. Fuel test elements were placed in Region 27, Region 24, Region 30, Region 22, and Region 25. The PGX graphite saeple in the layer 12 reflector elements was also placed in those five regions. An inspection of the Region 13 core support block was planned. A test of the installation of the region con-straint devices was performed on Region 18 for the purpose of identi-fying any problems prior to the scheduled installation of region con-straint device test later in the year. Following completion of the region constraint devices, the stylus block for the scratcher assembly was inserted into Region 18. The modified control rod drive work was completed with one modified drive placed in Region 35 and one placed in Region 5.

Installation of helium circulator C-2103 continued.

The main condenser eddy current testing indicated wall thinning and/

or leaks in 648 tubes. Plugging of the tubes was in progress.

Cleaning of the circulating water cooling tower was completed.

Loop 1 and Loop 2 secondary coolant piping, valve, and control system overhaul was completed in April and both loops r ceived flow from the condensate system at the time.

System 91 (hydraulic oil system) overhaul and system modification were essentially completed by April 25, 1979, and these systers were being returned to service. The additional auxiliary boiler was placed in service on April 5,1979, and final testing was completed.

1.5 May The first refueling of the reactor was completed with an inspection of Region 13 core support block. This inspection was performed at the request of the Nuclear Regulatory Coccission. The core support block was free of any questionable markings.

RT-523A, Region Constraint Device Handling Test, was completed. Region constraint devices were installed on the core and removed without difficulty. Several diagnostic devices were installed to assist in trouble-shooting the core fluctuation problem. A relative mor. ion detector (scratcher and pad) was installed in the upper plenum to detect relative motion between Region 18 and Region 35. Also, modi-fled control rod drives with special instrumentation were installed in Regions 5 and 35.

2 3

I

.b

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.5 May (Cont'd' Core fluctuation data system using the multiplexing technique was being installed and checked out.

All three boiler feed pumps were disassembled and were in various stages of repair at the end of May.

The 1C circulator change-out was extended approximately two weeks when the internal piping was discovered to have a bent steam inlet baffle plate. Spare intemals assembly was subsequently installed and 1C circulator change-out was completed on May 29, 1979.

The permanent two loop dump modification to the plant protective sys-tem was incorporated and the functional tests revealed that high moisture trips would occur on restoration of power following a loss of bus voltage. Modification of the dew point moisture monitor switching module was determined to be required to correct the high moisture trips on restorat.on of power. The time delay relays which were re-moved from Loop 1 as a temporary fix were to be re-installed until that problem could be properly evaluated.

The reactor was taken critical at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> on May 26,1979, with a reactivity discrepancy of +.002 ap. Following criticality, the reactor was shutdown, and shutdown margin was demonstrated with the instrumented control rod drives installed and the maximum worth con-trol rod drive withdrawn. The reactor was operated at approximately 0.1% power for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

The control data computer was upgraded to a new System 17 Control Data computar. The new computer utilizes CRT displays and sof t disc packs.

Main turbine generator overhaul continued. Dye penetrant checks of the throttle valve seats revealed cracks in the #1, #2, and #3 valve seats. Considerable difficulty was encountered in removing the throt-tie valve seats. Commercial Machine Works from Illinois was contracted to remove them by pulling with hydraulic hand jacks.

1.6 June -

The reactor was operated intermittently at various power levels, not exceeding 2% of rated power during the month of June.

Main turbine generator overhaul was completed, with the pinning of the three throttle valve seats and the installation of the outer insu-lating material.

3 The installation of the time delay relays in the Loop 1 steam / water dump valves control circuitry was completed per Change Notice 1066.

I 8

-.%,. . . - - - - e-a=* -

9 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.6 June (Cont'd)

The time delay relays ensure that a two loop dump cannot occur and allow the plant to be operated at power. The installation or' the time delay relays was required when the functional tests revealed that high moisture trips occurred on restoration of power following a loss of bus voltage.

Reheat attemperation valves FV-22119, FV-22120, PV-22151, and PV-22152, were removed and two Masonellan single high pressure drop flow con-trol valves (one per loop) were installed. The single stage reheat spray water pressure and flow control valves tended to oscillate in the automatic mode for flows less than 2CK pounds per hour. The multi-stage, critical service valves provide better flow control and longer life.

Nuclear Regulatory Commission testing of the license candidates was accomplished on June 11 and 12, 1979. The testing consisted of bringing the reactor critical and the Control Room portion of the walk around.

Main turbine generator stop valves were removed for inspection and lapping af ter excessive leakage was observed in the area of the valve stems. Af ter re-installation, the valves continued to leak around the valve stems. General Electric representatives advised that the leakage rate was acceptable. No further action is planned.

Emergency condensate check valves V-2256 and V-2257 tended to stick shut. Disassembly of the check valves revealed that the disc and seat area appeared to be in good condition. At the recommendation of the manufacturer, the seat angle of the disc was increased from approximately 20 degrees to approxi=ately 22 degrees by machining.

The check valves were tested after re-assembly and did not exhibit any tendency to stick shut.

The testing of all Class I snubbers was successfully completed on June 18, 1979.

On June 26,1979, at 1724 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.55982e-4 months <br />, 480 volt switchgear 5 tripped due __

to a short circuit caused by water spray from a hose which was being used for resin barrel flushing. Two phases of the transformer shorted accompanied by yellow and gray smoke. The plant had been operating at approximately 1.5: of rated power. The fault on the 480 volt switch-gear 5 was reflected into tha 4160 volt buses and 480 volt buses and resulted in a decrease in the essential 480 volt bus voltage before the high and low side breakers on switchgear 5 tripped to isolate the transformer. As a result of the voltage drop on the 480 volt buses, the operating bearing water pumps tripped in both loops and i all four circulators tripped on loss of bearing water. Backup bearing l water was not in service, nor required by applicable LCO's 4.2.1 and

~

4.2.2. A Loop 1 shutdown and two loop trouble scram automatically i occurred. The temporary auxiliary boiler tripped, which caused an 2

., ,a -- -+

4 1.0 NARRATIVE SmfMARY OF OPERATING EXPERIENCE 1.6 June (Cont'd) interruption of steam flow to the lA boiler feed pump and subsequent decrease in feedwater flow to Loop 2 steam generators. Condenser vacuum was lost as was control of both etarcup bypass valves, PV-22129-1 and PV-22130-1. The primary coolant flow was interrupted for a period of 15 minutes. This event was determined to be a reportable occur-rence per fort St. Vrain Technical Specification AC 7.5.2(a)5. Damage to equipment as a result of the short circuit to the load center

1. 5 transformer was limited to the transformer and the 2/0 feeder cable between the 4160 switchgear and the #5 load center. The trans-former and 2/0 feed cable were replaced and load center #5 was returned to service. Calibration checks of the associated protective 4160 _

relays were completed by the Relay Department. All protective relaying components were found to be accurately calibrated and functioning properly.

1.7 Julv The turbine generator was placed on line at 1416 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.38788e-4 months <br /> on July 23, 1979. This was the first time the generator had been placed on line since the scheduled outage which began the first week of February.

The turbine generator was manually tripped at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> on July 24, 1979, due to a generator field ground alarm. The problem was traced to a faulty field tempettue transducer which had shorted and pro-vided a path from the field windings to ground. A faulty field ground detection relay was also discovered. It was subsequently repaired and re-installed. The field temperature transducer was on order and was to be installed as soon as it arrived on site. The turbine generator was again placed on line at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> on July 26, 1979.

Turbine temperatures were allowed to stabilize and the turbine over-speed tests were completed with General Electric Company representatives on graveysrd shif t on July 27, 1979. The turbine generator tripped automatically at 0814 hours0.00942 days <br />0.226 hours <br />0.00135 weeks <br />3.09727e-4 months <br /> on July 28, 1979, due to high vibration of the #3 bearing. The reheat bypass valves closed due to low con-densate header pressure and the hot reheat electromatic relief valves opened. A Loop 2 shutdown occurred at 0817 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br /> when the operator re-opened the reheat bypass valves and closed the reheat electromatic _

relief valves. This action caused circulators 1B,1C, and ID to change speed in excess of the feed water flow / circulator speed limits which resulted in a circulator steam turbine trip. The turbine and the supervisory vibration instrumentation were given a thorough checkout by General Electric Company representatives. No problems were dis-covered. The turbine generator was placed on line at 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br /> on July 30, 1979. All instruments indicated normal turbine operation.

3 5

3 8

4 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.7 Julv (Con t' d)

An automatic Loop 2 shutdown, reactor scram, and turbine trip occurred on July 31, 1979. The action was initiated during a transfer of the turbine generator from full are to partial are admission mode. The transfer caused a decrease in main steam pressure and an increase in feedwater flow which resulted in a trip of 1B,1C, and ID circu-lators due to a mismatch in circulator speed versus feedwater flow.

The trip of 1C and ID circulators caused the shutdown of Loop 2 feed-water flow at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />. At 1016 hours0.0118 days <br />0.282 hours <br />0.00168 weeks <br />3.86588e-4 months <br />, a two loop trouble scram i occurred due to a Loop 1 superheat steam temperature low. An auto-matic turbine trip occurred at 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br /> which was initiated by the reactor scram. An investigation into the cause of the upset revealed that the turbine ventilator valve had not been electrically connected subsequent to the turbine generator overhaul. This provided a direct path from the #4 gland seal packing directly to the main condenser bypassing the turbine. The open ventilator valve had a direct effect on turbine generator output versus reactor power and was the major contributor in the upset in transferring from full arc to partial are admission mode.

Buffer helium dryer problems were traced to an apparent breach in a 12-mesh wire screen. This wire screen is located at the bottom of the dryer tower and is designed to contain the desiccant within the tower. The breach in the wire screen had allowed the desiccant to be carried dovnetream of the dryer towers and collected in the downstream filters. This requires that the filters be changed frequently as the dryer differential pressure increases due to abnormal operating conditions. A temporary on-line fix was made to both towers to allow continued operation. Replace =ent of the 12-mesh wire screen requires disassembly of the tower which is a coded vessel. The temp-orary fix consisted of installing a 14-mesh conical screen internal to the heater tube. Several alternatives are being explored to ef-feet a permanent fix during the next scheduled outage.

Reactor power level was reduced from 8% to 2% on July 10, 19 79, to repair a bonnet seal leak on HV-2224, Loop 2 main steam stop check __

valve. The repair and re-assembly was completed on July 14, 1979.

On July 23, 1979, a leak in the hydraulic oil supply to HV-2224 re-sulted in a small insulation fire which was readily extinguished by plant personnel using hand held fire extinguishers. The hydraulic oil supply to the valve was isolated and no permanent damage was done by the fire. The oil leak was traced to a failed "0" ring at a flanged connection of the bypass line. HV-2224 developed an oil leak at the lower operator cylinder head on July 30, 1979. The operator was disas-sembled and scheduled to be repaired when plant conditions are such that process pressure may be removed from the valve.

3 i  :

3 8

, ,_. ,y_ .-. - . ~ + - + -

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.7 July (Con t' d)

The helium circulator removed from 1C penetration was shipped to General Atomic Company in San Diego on July 26, 1979. The circulator was scheduled to be disaesembled and inspected per the requirements of Technical Specification Surveillance Tests SR 5.2.17 and 5.2.18, re-furbished, and returned to Fort St. Vrain.

Fif ty-one irradiated elements from the Cycle 1 core (49 fuel blocks and two reflector blocks) were surveyed per RT-5 25. Five of the elements were examined as part of the prescribed PIE program under the auspices of the DOE funded progran. The survey was to determine the exact dimensions of the elements and was performed in the plant _

hot service facility. The dimensional checks were performed with a robot specifically designed by General Atomic Company for this pur-pose. Results of the inspection were reported as a part of the DOE p rogram.

1.8 August The Turbine generator was placed on line at 1504 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.72272e-4 months <br /> on August 3, 1979, and remained on line until 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br /> August 11, 1979. At that time, a reactor scram, turbine trip, and Loop 2 shutdown was precipi-tated by a loss of speed sir *nal to 1D helium circulator.

The Turbine generator was placed on line at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> August 12, 1979. The plant was operated at reduced power levels (150 We) due to continuing problems with helium circulator speed circuitry.

On August 17,1979, a Loop 1 shutdown, two loop trouble scram, turbine trip, and an approximate three minute loss of forced cooling occurred at 1523 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.795015e-4 months <br />. The plant shutdown was caused by an inadvertent grounding of the 120 volt AC power feed to cabinet I-36B.

The Turbine generator was placed on line at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on August 20, 1979, and remained on line until 1518 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.77599e-4 months <br /> August 24, 1979. Power was reduced and the turbine was taken off line due to hMh primary coolant oxidant levels. -

The turbine was placed on line at 1253 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.767665e-4 months <br /> August 26, 1979, and remained on line until the plant was shutdown on September 1,1979, to evaluate seismic qualification of Class I 2-1/2 inch and larger piping and hangers.

Testing consisted of core region thermocouple traverses - RT-524, base data on FM fluctuation data system at 46% power - RT-486, reheat steam attemperation tuning - RT-501, and fluctuation testing - RT-

!* 500F. PCRV deflection measurement was completed at 625 psia PCRV pressure on August 9,1979. Fuel element surveillance program was coupleted, equipment decontaminated, and shipped to General Atomic

! Company in San Diego.

I i.

.+

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.8 Augus t (Con t' d)

Maintenance was performed on the following valves: V-21268-2, backup s bearing water header relief valve, V-2256, condensate check valve, and HV-2224, main steam stop check valve.

The overhaul of "C" boiler feedpump was completed. The boiler feed-pu=p was test run and returned to service.

1.9 September The plant was shutdown September 1,1979, and essentially remained -

in a shutdown condition for the month of September.

The plant shutdown was necessary to resolve problems discovered in

- ;.mple audit of Class I 2-1/2 inch and larger piping and hangers which was conducted in response to I & E Bulletin No. 79-14.

Fluctuation testing (RT-500F) was completed up to 50% power prior to shutting down.

The reactor was taken critical at 0543 hours0.00628 days <br />0.151 hours <br />8.978175e-4 weeks <br />2.066115e-4 months <br /> on September 15, 1979, and remained at less than 2% power until September 28, 1979. Rise to power after hanger discrepancies were resolved was hampered by loss of condensate through leaking relief valves. Water recovery systems were devised to recover condensate. These relief valves will be repaired at the next scheduled shutdown. Reactor power remained at less than 11% for the remainder of September,1979.

1.10 October The turbine generator was placed on line at 1303 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.957915e-4 months <br /> October 2, 1979. Rise to power above 30% was hindered by condensate water con-ductivity and inadequate condensate in storage tanks to regenerate the demineralizer beds. The generator remained on line until 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> October 14, 1979. At that time, attempts to repair a faulty buffer helium dryer on line resulted in a complete plant shutdown. -

Rise to power commenced on October 18, 1979, and was delayed several days due to secondary water chemistry problems. The generator was synchronized and placed on line at 2303 hours0.0267 days <br />0.64 hours <br />0.00381 weeks <br />8.762915e-4 months <br /> on October 23, 1979.

Calibration of instrumented control rod drives in Regions 5 and 35 was completed per RT-486, Part III, at 60% power. Fluctuation testing per RT-500G was completed in the 60 to 70% power range prior to the scheduled plant shutdown on October 26, 1979.

s 3

3

l.0 NARRATIVE

SUMMARY

OF OPERATING EXPFRIENCE 1.10 October (Cont'd)

Surveillance tests were accomplished at various plant conditions during the orderly shutdown.

The main conder. 'er was isolated in preparation for condenser tube replacement and ;aop 2 was isolated for the Loop 2 outage items.

The reactor vessel was depressurized and refueling floor equipment checked out in preparation for the installation of the region con-straint devices.

1.11 November The Fort S t. Vrain outage which started on October 29, 1979, con tinued through the month of November. The outage was about 75% complete at the end of November. Major accomplishments to this point were:

Installation of all core region constraint devices was completed on November 25, 1979. Eighteen core regions were entered for the installation of 84 region constraint devices.

Change Notice 473 manual isolation valves, V- 11615 and V-211616, installed in Loop 1 and Loop 2 pelton wheel supply header.

Buffer helium dryer valves were disassembled. The valve seats were inspected and repaired. Desiccant was removed from all valves and lines. The dryer towers were removed and disassembled.

The center stand pipe in both towers was found to be distorted, apparently due to thermal stress. The dryer towers were repaired and re-installed.

Loop 2 outage items were completed. Loop 1 was isolated for work on November 24, 1979.

Main condenser retubing continued. Retubing in the north water box was completed. All of the tubes were inserted in the south water box. The rolling of tubes was in progress. --

1.12 De cemb er Primary coolant moisture levels had incresed during the month, fol-lowing the flooding of 1C circulator bearing cartridge The water ingress was attributed to work being done on the low pressure sepa-rator.

The 1B circulator would not self-turbine following an extended shut-

, down period. Unsuccessful attempts were made using condensate and g emergency feedvater to the pelton wheel. The circulator was finally

, rotated by using a combination of increased bearing water flow while l* applying emergency feedwater to the pelton wheel.

s 0

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1.12 December (Cont' d)

The Fort St. Vrain maintenance outage, whic started on October 29, 1979, and continued through the month of hovember, was completed on December 17, 1979, when the main condenser was returned to service.

Normal plant valve lineups were verified and the reactor was taken critical on December 25, 1979. Reactor power was held at approximately 1.5% for primary and secondary coolant system clean-up. A reactor scram and Loop 2 shutdown occurred on December 30, 1979, following the operation of IC circulator at speed. High moisture levels were attributed to the ingress which occurred on December 7,1979. Fol-lowing this shutdown, maintenance on two major Loop 2 components was

~

started.

~

4 C

N

~

i

t FORT ST. VRAIN SIGNIFICANT MAIMrENANCE ;

SUMMARY

TI'HE I IDENTIFICA- REQUIRED EFfYCT UN TION IEUMBER SYSTDf/ NATURE OF FOR SAFE OFtRAfl0N AND DATE cOFFONENT cAIME OF HALFLNCTION RESULTS OF HAI.FINCTION HAIN17. NANCE c0RRECTIVE ACTI(W c(tfl ETION OF 111E REACIOR 77-10-64 CRS C3-5 Normal use Oil leak. Correc- Replaced faulty 8 Ilours None 5-15-79 Pipe Snub- tive parts.

ber 78-1-199 V-31872 Normal use Valve leaks at bonnet. Correc- Replaced bonnet 4 llours Nane 4-16-79 tive gasket. _

78-4-426 IIV-2249 Normal use Seal ring leaks. Correc- Replaced seal ring. 1 Month None 5-26-79 tive 78-6-702 PV-22168 Normal use Valve fitting leaks. Correc- Repaired fittings. 8 Ilours None 2-26-79 tive 78-7-182 V-46722 Normal use Bonnet leaks. Corre c- Replaced bonnet 4 liours None 4-7-79 tive gasket.

78-8-283 TV-2228-1 Normal use leaking boimet flange. Correc- Replaced bonnet 8 llours None 2-27-79 tive gasket.

78-10-90 TT-2225-2 Normal use Output oscillating. Corre c- Rcplaced failed 2 Days None 1-16-79 tive magnetic amplifier and capacitor.

78-10-103 V-2214 Normal use Valve leaks through. Correc- Lapped seat and 24 Ilouro None 5-5-79 h tive disc. y 78-10-339 V-23271 Normal use Valve leaked through. Correc- Repaired valve 3 Days None 2-23-79 tive seat and disc.

78-10-466 PV-22168 Normal use Leaking at pilot valve Correc- Repaired valve 8 Ilours None 2-27-79 flange, tive flange.

78-11-293 V-21743 Normal use Valve leaks through. Co rrec- Rebuilt valve. 1 Week None 4v17-79 tive 78-11-410 PV-2230 Normal use Packing leak. Correc- Replaced packing. '8 Ilours None 3-15-79 tive 78-11-415 PV-22130 Normal use Packing leak. Correc- Repacked valve. 8 Ilours None 3-15-79 tive 78-11-420 IIV-2224 Normal use Packing Icak. Co rre c- Repacked valve. 3 !!ours None

, 3-23-79 tive 78-11-425 PV-22154 Nort:al use Packing leak. Correc- Repacked valve. 8 Ilours None 3-15-79 tive -

78-12-356 PT-9105 Normal use Leak at welded fitting. Correc- Repaired fi tting. 8 Ilours None 4-28-79 Instrument Live Line 79-1-1 SM-21161 Normal use Loss of circulator Correc- .Jumpered to oper- 1 Day None 1-2-79 Cable speed indication. tive able cable.

79-1-25 PPS Module Normal use Indicator trip at all Co rrec- Replaced failed 2 llours None 1-2-79 FSL-2212-1 times. tive integrated circuit.

.l -

L..

I i

I I '

l FORT ST. VRAIN SIGNIFICANT MAINTENANCE

SUMMARY

I TIHE IDENTIFICA- REQUIRED EFFECT ON TIOtt NUMBER SYSTEHf NATURE OF FOR SAFE DPERATION AND DATE COW OFENT CAUSE OF HALFtMCTION RESULTS OF HALFINCTION HAINTElANCE CORRECTIVE ACTION COHPI.ETION OF 11tE REACTOR 79-1-36 PPS Module- Normal use Failed tripped. Correc- Replaced failed 2 llaurs None 1-3-79 CT-1BR4 tive integrated circuit.

79-1-45 PPS Module Normal use Failed tripped. Correc- Replaced failed 2 flours None

. )-4-79 CT-1AR4 tive integrated circuit.

'9-1-46 PPS Module Normal use Failed tripped. Corre c- Replaced failed 2 Ilours None i1-4-79 CT-2B2 tive integrated circuit.

79-1-4 7 PPS Module Normal use Input circuit bad. Correc- Replaced 5 failed 2 llours None 1-4-79 CT-1BR4 tive integrated cir-cuits.

79-1-48 PPS Module Normal use Failed tripped. Correc- Replaced failed 2 Ilours None 1-4-79 CT-2A2 tive integrated circuit.

79-1-49 PPS Module Normal use Failed tripped. Correc- Replaced failed 2 llours None 1-4-79 CC-2A2 tive integrated ci r-cuits.

79-1-149 RIS-93252- Normal use Failed to alarm during Correc- Repaired bad soldel 2 Ilours None 1-8-79 10 test. tive loint.

79-1-178 PPS Module Nonnal use Indicator lights did Correc- Replaced fuse and None 1-9-79 XDIS-21328 2 llours 4

not operate when tive failed integrated p tripped during test. circuit.

79-1-239 V-7220 Normal use Valve leaking through. Correc- Machined valve disc 1 Week None 4-17-79 tive and lapped seat.

79-1-248 C-8203 Normal use Compressor output low. Co rre c- Replaced unloader 4 liours None 1-15-79 tive pressure switch i and solenoid valve. l 79-1-262 V-7263 .. Normal use Valve leaked through. Correc- Repaired valve 8 Ilours None 4-17-79 tive seat and disc.

79-1-263 V-72173 Normal use Valve leaked through. Cor re c- Repaired valve 8 Ilours None 4-11-79 tive seat and disc. i 79-1-371 IIV-22227 Normal use Packing leak. Correc- Repacked valve. 4 Ilours None i

1-20-79 tive 79-1-379 TE-22140 Normal use Spurious single chan- Correc- Replaced failed 4 Ilours None 1-20-79 nel scram. tive temperature ele- ,

ment.

' 0-1-382 *

,-/1115 Normal use Valve stem broken. Correc- Rebuilt valve stem 2 Days None 6-21-79 tive and disc assembly.

79-1-384 P-2109 Normal use Excessive seal leakage. Correc- Replaced mechanical 24 llours None 2-20-79 tive seals.

79-1-402 PV-2230 Normal use ' Valve would not respond Correc- Replaced servo 4 Ilours None 1-22-79 Ilydraulic to controller. tive valve.

Operator

} ,

I .

I l

FORT ST. VRAIN SIGNIFICANT MAINTENANCEi SUtefARY TIME IDENTIr1CA. REQUIRED EFFECT W TION NUMBER SYSTEHf NATURE OF FOR SAFE OPERATION AND DATE COFF0NENT CAUSE OF HALF 1MCTION RESULTS OF HALFINCTim MAINTENANCE CORRECTIVE ACTION Cfitfl.ETION OF T1tE REACTOR 79-1-411 PPS Ifodule Normal use Input circuit bad. Correc- Replaced failed 2 Ilours None 1-22-79 CT-2B2 tive integrated circuit.

l 79-1-439 SSL-21172 Normal use Switch indicated low Correc- Repaired cable con- 8 Ilours None 2-8-79 Cable speed with circulator tive nector.

operating.

79-1-513 C-8203 Normal use Compressor tripped at Co r re c- Replaced switch. 1 Day None 1-29-79 liigh Dis- normal temperature, tive charge Tempera-ture Switch 79-1-535 Con trol Normal use Ceramic insulator Correc- .Poplaced ceramic 2 Ilours None 1-2 8-79 and Ori- broken. tive insulator in kind.

ficing As-sembly #43 Electrical Connector e e-a 79-lv540 IIV-2204 Normal use Oil. leak. Correc- Replaced failed "O" 2 llours tione Y 2-16-79 Ilydraulic tive ring.

Operator 79-1-556 IIV-21352 Normal use Leaking through. Co rre c- Replaced valve 1 Day tione 1-31-79 tive disc.

79-1-564 IIV-2204 Normal use Oil leak. Correc- Replaced f ailed "0" 2 Ilours fione 2-13-79 Nydraulic tive rin g.

Operator 79-1-572 P-9102SX Normal use Motor failed. Cor re c- Replaced motor. 8 Ilours fione 1- 30-79 Motor tive 79-1-580 T-2122-3 Noviral use Valve threads stripped. Correc- Replaced valve in 2 Ilours rione 2 79 Gas tive kind.

Charging Valve 79-2-7 PSL-1110-1 Normal use Switch failed tripped. Correc- Tightened loose 1 Ilour !!one 1-31-79 tive connection.

79-2-21 Control Normal use Indicated position in-2-4-79 Correc- Replaced pot in 4 llours !ione and Ori- co rre c t , tive kind.

fice As-sambly #9 Orifice Position Pot ,

i I

i , . I

. . i

, j I

FORT ST. VRAIN SImIFICANT MAINTENANCE f

SUMMARY

l TlHE IDENTIFICA- REQUIRED ErlTCT Cli TION NUMBER SYSTEH/ HATURE OF FOR SAFE OPERATION AND DATE COFFONENT CAUSE OF HALFtNCTION RESifLTS OF HALYtNCTION MAINTENANCE CORRECTIVE ACTION cOHPLETION OF lit % REACTOR 79-2-38 In-Li ntit Normal use Relays sticking. Correc- Replaced relay. 4 Ilours None 2-6-79 Relay for tive Region 3 Control Rod Drive 79-2-71 PPS Normal use Modules failed test. Correc- Replaced failed 4 Ilours None 2-5-79 Modules tive integrated cir-CT-1B R4, cuits.

CT-2B2 79-2-75 TS-8249 Normal use Switch failed. Correc- ~ Replaced switch. 4 Ilours None 2-6-79 etye

! 79-2-110 C-2101 Normal use Steam leak. Correc- Replaced gasket. 8 Ilours None 4-28-79 Steam tive '

, Flange

{ 79-2-191 V-4508 Water froze in Valve broken. Correc- Replaced valve. 4 Ilours None 7-15-79 valve. tive 79-2-214 V-211002 Normal use Valve would not open. Correc- Replaced bonnet as- 4 llours None s

{ 4-16-79 '

tive sembly and lap y valve disc.

79-2-216 IIV-2204 Normal use 011 leak. Correc- Replaced solenoid 4 Ilours None j 2-21-79 Ilydraulic tive valve. i operator 79-2-222 C-8201S Normal use Breaker trips errone- Correc- Rglaced broken 4 llours None

2-20-79 Electrical ously. tive control device.

} Breaker 79-2-243 C-8201 Normal use Solenoid failed. Correc- Replaced solenoid. 4 Ilours None 2-16-79 Unloader tive Solenoid 79-2-280 Control Normal use Indicated position in- Correc- Replaced position 8 Ilours None 2-2-79 and Ori- correct. tive pot.

ficing As-sembly #20 ,

4 Control Rod Po-sition Po_t 79-2-281 Control Normal use Indicated position in- Correc- Replaced pot. 8 Ilours None 2-3-79 and Ori- correct. tive ficing As-sembly #43 Orifice J, Valve Po-i sIET5h Pot P

l

l t I  ! l I  : I -

l FORT ST. VRAIN SIGNIFICANr HAINTENANCE SUtDfARY TIME IDENT!rlCA- REQUIRE D EFFt.CT m T1000 AUNRER SYSTEHf NATURE OF FOR SAFE oPERATim AND DATE COff0NENT CAIJSE OF HALMNG10N RESULTS OF HALFtNCTION HAINTENANCE CORRECTIVE ACTION COHrLETION OF 11tE REACTOR 79-2-286 IIV-2253 Normal use liydraulic oil leak. Correc- Replaced leaking 4 Ilours None 2-21-79 liydraulic tive relief valve.

Operator

~

79-3-81 IIV-2201 Normal use Valve leaking through. Correc- Replaced valve 8 llours None 5-1-79 liydraulic tive seat.

Operator Filter Valves 79-3-120 liv-2 364 Normal use lland jack inoperative. Correc- Replaced worn 8 Ilours None 3-9-79 tive sleeve.

t 79-3-153 RIS-7324-1 Normal use Pump seized. Correc- Rebuilt pump. 1 Week None 4-2-79 Sample tive Punp 79-3-257 11-1301 Normal use Valve leakage. Cor re c- Repaired leak. 1 Day None

, 10-17-79 tive 79-3-385 DC Bus Normal use Bus indicating a Correc- Cleared ground. 2 Ilours None 5-19-79 ground. tive '

l 79-3-456 PS-1106-1 Normal use Pressure switch setting Correc- Replaced pressure 4 Ilours None j 3-29-79 out of tolerance, could tive f

switch and cali-not be reset, brated.

79-3-462 IIV-2292 Normal use Relief valve leaks Correc- Replaced valve. 3 llours None 3-29-79 liydraulic through. tive Operator Relief Valve 79-3-509 IIV-22134 Formal use Weld crack. Correc- Rewelded. 4 Ilours None 4-2-79 Yoke tive 79-4-40 llV-2293 Normal use Filter leaking. Correc- Replaced "O" ring. 4 Ilours None 4-4-79 liydraulic tive Operator 011 Filter 79-4-41 P-2110 Normal use Excess leakage at pump Co rre c , Replaced pump 3 Ifours None <

4-16-79 gland seal. tive mechanical seal.

79-4-194 P-2109 Normal use Pump noisy. Correc- I Replaced pump seal. 4 Ilours None 5-29-79 tive 79-4-352 P- 21.' 0 Normal use Leaking shaf t seal. Correc- Replaced seal. 6 Ilours None 4 79 tive 79-4-372 HIS-1121 Normal use Test circuit failed. Correc- Replaced failed 4 Ilours None 4-21-79 tive photo resistor.

I

e

, FORT ST. VRAIN SIGNIFICANT MAINTENANCE

SUMMARY

TlHE IDENTIFICA. REQUIRED EFFECT ON TION NUHBER SYSTEH/ NATURE OF IVR SAft OPERATION AND DATE COtf0NENT CAIEE OF MALFINCTION RESULT 3 OF MALFtMCTI(M MAINTENANCE CORRECTIVE ACTTON c(ffLETTON OF THE REACTOR 79-4-423 P-4602S Normal use Breaker operation er- Correc- Overhauled breaker. 8 Ilours None 6-8-79 Pump ra tic, tive

.I Breaker 79-4-477 PI-21301 Normal use Indicated pressure in- Correc- Replaced pressure 4 Ilours None j 4-26-79 co rrec t . tive indicator with i spare.

79-4-500 IIV-2202 Normal use Oil leak at tube fit- Correc- Tightened fitting. 1 Ilour Nor.e 5-17-79 Ilydraulic ting. tive

! Operator 79-4-612 V-9165

~

Normal use Va1ve s tem broken. Correc- Replaced stem, 4 llours None 5-1-79 tive I. 79-5-6 V-9170 Normal use Valve stem bent. Correc- Replaced stem. 4 llours None 5-1-79 tive 79-5-18 P-9102SX Normal use Motor tripped, running Correc- Replaced motor. 1 Week None i 5-10-79 Motor hot. tive 79-5-21 P-9102SX Normal use Pump motor breaker Correc- Replaced motor. I Week None 5-10-79 Motor trips, tive r

79-5-36 Ilydraulic Normal use Will not hold pressure. Cor re c- Replaced valve. 4 Ilours None 5-9-79 System Ac-

?

tive cumulator 3A i

79-5-59 IIV-2189-3 Work in area Air line broken. Co rre c- Replaced air line. 4 llours None

{ 5-10-79 Air line tive 79-5-158 IIV-22207 Normal use Air tubing broken. Correc- Replaced tubing. 8 Ilours None 5-29-79 Operator tive 79-5.171 V-21285 Normal use Valve leaks through. Correc- Rsplecad valve in 8 liours None 5-26 79 _

tive kind.

79-5-175 Refueling Normal use Leak at secondary seal. Correc- lioned seal sutfice 2 Days None 5-16-79 Pene- tive and cleaned "0" tration ring.

125 Seconda ry -

Seal 79-5-182 IIV-2215 Normal use Internal bypass flow. Correc- Ee'placed "0" ring. 4 Ilours None 5-25-79 Ilydraulic tive Operator 79-5-198 P-2110 Normal use Shaft seal leakage is Correc- Replaced seal. 18 Ilours None 5-11-79 excessive. tive 79-5-263 P-2109 Normal use Shaf t seal failed. Correc- , Replaced shaft 24 liours None 5-29-79 tive seal.

I

I  !

! , i

~

FORT ST. _VRAIN_SIGNIFICANT MAINTENANCE l SUMMA _RY TIME IDENTIFIcA- REQUIRED EFFECT ON TION NUMBER SYSTEN/ NATURE OF FUR SAFE OPERATION Ano DATE coer0NENT CAUSE OF HALFtNCTION , RESULTS OF HALFtNCTHN HAINTENANCE CORRECflVE ACTION COPFf.ETION _0_F 11tE REACTOR 79-5-313 PS-21358 Normal use Switch would not cali- Correc- Replaced in kind. 8 Ilours None i 5-11-79 brate. tive l 79-5-314 PS-21359 Normal use Switch would not cali- Correc- Replaced in kind. 8 Ilours None 5-11-79 brate. tive 79-5-319 Ilydraulic Normal use Nitrogen leak at bottom Correc- Replaced "O" ring. 3 Days None j 5-21-79 Power Sys- head seal. tive l tem Ac-cumulator 3A j 79-5-326 IIV-2201 Normal use Oil leak. Correc- Replaced leaking 4 llours ihne

5-15-79 tive "0" ring.

79-5-395 P-2110 Normal use Shaft seal failed. Correc- Replaced shaft 1 Week None 2-10-79 tive sgal.

79-5-454 P-2110 Normal use Motor bearing failed. Correc- Replaced motor 5 IIaurs None 5-26-79 Motor tive bea ri ngs.

79-5-606 MM-ll21 Normal use lleater power level con- Correc- Replaced failed 8 Ilours None

, 2-21-79 troller failed. tive transformer.

79-5-724 l3 1

PI-21536- Normal use Indicated pressure in- Co r re c- Repair gauge 2 Ilours None 6;'

5.23-79 1 correct. tive linkage.

79-5-823 'V-ll677 Normal use Valve leaks through. Correc- Replaced valve 1 Week None 5-30-79 tive disc.

79-5-895 21/SV-210C Normal use Valve would not stroke.'Correc- Replaced !KX1G servo 2 Ilours None 6-8-79 tive controller.

79-5-902 V-211575 Normal use Valve leaks at seal Correc- Replaced seal ring 4 llours None 5-31-79 ring. tive and repaired cut valve bonnet.

79-5-908 11/V-ll755 Normal use Yoke turned when valve Correc- Replaced tack 2 Ilours None 6-1-79 was operated, tive welds.

79-5-910 IIV-2250 Normal use llydraulic oil leak. Correc- Replaced "0" ring. 4 Ilours None 5-31-79 Ilydraulic tive Operator Filter -

79-6-31 P-9102X Normal use Motor breaker tripped. Correc- Replaced motor. 2 Days None 6-5-79 Motor tive 79-6-133 22/IIV- Nornal use Broken shear pin. Correc- Repaired operator. 1 Day None 6-21-79 2247 tive 79-6-144 FV-21333 Normal use _l Packing leak. Correc- Repacked valve. 6 Ilours None 8-9-79 tive 79-6-179 V-21522 Normal use Valve leaks at gasket. Correc- Replacui gasket. None j 6-9-79 tive 4 Ilours ,

I I

I i

l I

FORT ST. VRAIN SIGNIFICANT MAINTENANCE :S UMMARY TINE IDENTIFICA- REQUlkED FFFECT ON TION NUMBER SYSTEH/ NATURE OF FO R SAFE OPERATION AND DATE _Cn6f0HENT CAUSE OF HALFtMCTION RESULTS OF HALFLNCTION HAINTENANCE CORRECTIVE ACTION Cr40't.ETION OF THE REACTOR 79-6-197 V-211245 Normal use Gasket leak. Correc- Replaced gasket. 3 llours None 6-11-79 tive 79-6-256 ilV-31119 .

Normal use Packing leak. Co r re c- Repacked valve. 4 Ilours None 6-15-79 tive L

79-6-263 Circulator, Normal use Indicated temperature Correc- , Rewelded broken 8 Ilours lioIe 6-13-79 Inlet in co rrect. tive leads.

Thermo-couples 79-6-268 P-910lX Normal use Low output f r ;in pump. Co rrec- Replaced pump with 2 Days None 6-28-79 tive spare.

79-6-294 IIV-2292 Normal use Leaking safety valve. Correc- Replaced safety i Ilour None 6-12-79 Ilydraulic tiva valve.

Operator 79-6-303 V-2256 Normal use Valve stuck shut. Correc- Remachined valve 4 Days None

~

6-14-79 tive seat and disc.

79-6-328 V-22185 Normal use Leak at bonnet gasket. Correc- Replaced gasket. 8 llours None i 6-15-79

! 79-6-410 P-9106X tive b Normal use Pump leaks at gasket. Correc- Replaced cover and 1 Ilour None Y 6 79 tive gasket.

79-6-421 liv-2292 Normal use Relief valve leaking Correc- Replaced leaking 1.5 None

, 6-19-79 Ilydraulic oil, tive valve with spare. Ilours Operator 79-6-436 FT-2214 Normal use V.tive leaking. Correc- Replaced valve, 2 Hours T6iie 6-20-79 Instrument tive Valve 79-6-451 P-910lX Normal use Pump output low. Correc- Replaced pump. 4 llours None 6-26-79 tive 79-6-486 IIV-21206- Normal use Valves leak through. Co rre c- Replaced valves 8 Ilours None 6-22-79 2, -4 tive with spares.

79-6-514 P-9106X Normal use E' ass seal leakage. Correc- Replaced pump in 8 Ilours None 8-11-79 tive kind.

79-6-516 P-9105X Normal tse Motor connections Correc- Repaired / replaced 3 llours None 6-23-79 Electrical burnt. burned connections.

Con-nections 79-6-519 SV-2111 Norinal use Switch failed to oper. Correc- Replaced switch 1.5 None 6-26-79 Limit ate. tive spting. Ilours Switch 79-6-537 V-91697 Normal use Valve leaked. Correc- Replaced valve with 1 llour None 6-25-79 tive spare.

L

{ >

FORT ST. VRAIN SICNIFICANT 11AINTENANCE SUMFIARY r

I TIME IDENTI FICA- EFFECT ON REQUI RED TION NUMBER SYSTEH/ NATURE OF FOR san! OPERATION AND DATE COtPONENT CAUSE OF HALFtWCTION RESULTS OF HALFtHCTION HAIN11sNANCE CORRECTIVE ACTION CottPI.ETION OF lllE REAC1Y)R 79-6-590 H-21813 Normal use I.eak at flange. Co r re c- Replaced gasket. 8 Ilours None 6-28-79 tive 79-7-21_ C-9201S_ Normal use Compressor would not Corr ;- ~ Replaced breaker. 4 Ilours None 7-2-79 B reake r start. tive 79-7-38 22/IIV- Normal use Seal ring packing leak Co r re c- Replaced seal 3 Days None 7-15-79 2224 on valve. tive ring.

79-7-79 PPS RWP Normal use Failed test. Correc- Replaced failed IC 2 Ilours None 7 79 Hodule tive chip.

, 79-7-89 101-1120 Nomal use Mirror heater tripped. Co rre c- Replaced heater 4 Ilours None 7-10-79 tive power controller

{

wi th spare.

79-7-92 P-9102X Normal use Flange leak. Co rrec- Replaced failed 6 Ilours None 7-27-/9 Flange tive "O" rin g .

79-7-99 V-21268-2 Normal use Valve leak through Correc- Repai red / reb uil t 4 Days None 8-2-79 body wall. tive valve body and in-te rnals .

, 79-7-202 FSL-2213- Normal use Setpoint pot erratic. Co rre c- Replaced worn pot. 2 Ilours None b 7-13-79 1 Setpoint tive Y

Pot 79-7-341 IIV-21226 Normal use Valve operator broken. Correc- Replaced broken 8 Ilours None 8-20-79 tive spring barrel .

79-7-358 _.22/IIV- Normal a.se 011 return line on llV- Co rre c- Replaced flex 1/2 Day None 11-15-79 2242 _

2242 leaking oil. tive hose.

79-7-407 V-21115 Normal use Valve ope rator not Correc- Reconnected valve 2 Ilours None 8-2-79 _

operating valve. tive op e ra to r.

79-7-448 S-8201 harmal use Moisture in exit air. Correc- Replaced heeter 8 Ilours None 7-26-79 tive and screen.

79-7-496 22/V-2247 Normal use Valve leakage. Co rre c- Rebuilt valve. 7 Week None 10-3-79 tive 79-7-538 V-21283 Normal use Valve leaks through. Correc- Replaced valve in 8 Ilours None 8-3-79 . tive kind.

79-7-581 PPS ".odule Normal uce Instrument failed to Co rre c- Replaced failed 4 llours

~

None '

7-27-79 FSL-2212-1 trip during test. tive relay, IC chip, and ambde pin.

79-7-598 IIV-1102- Norral use Valves 1.ak through. Correc- Replaced valve 4 Ilours None 8-13-79 27 & ilV- tive seats.

1104-27 79- 7-635 IIV-2292 Normal use Valve leaks through. Co n- Replaced valve in ^ 1 Ilour None 7-31-79 Ilydraulic tive kind.

Operator d Relief Valve l

FORT ST. VP'IN SIgiIFICANT MAINTE?q1CE SU! DIARY IDENTI FICA- REQUIRED EFFECT ON TION NUMBER SYSTEH/ NATURE OF R)R SAIE OFERATION AND DATE COPPONENT CAUSE OF HALFLNCTION RESUI.TS OF HAI.FLNCTION HAINTENANCE CORRECTIVE ACTION C0tFF.ETION OF 113E PEACTOR 79-7-643 C-8201 Normal use Compressor short Correc- Replaced unlonder 4 Ilours None 8-1-79 cycling. tive solenoid ano con-trol switch.

79-8-32 21/V-21542 Normal use Valve body leaking. Correc- Repaired valve noz- 2 Days None

, 10-17-79 _ tive zle and disc.

79-8-37 ^l'1S-1120 Normal use Indicated failed . Correc- Replaced failed 2 Ilours None 8-8-79 thermocouple. tive in tegrated circuit.

l 79-8-47 V-82493 Normal use Valve leaks through. Cc. re c- Rebuilt valve seat 8 s,ays N?ne 8-11-79 tive at;d disc.

79-8-119 PPS Module Ncrmal use Module failed test. Correc- Replaced failed 2 Ilours None 8-6-79 CT-2B2 tive integrated circuit.

79-8-130 liv-22 '}8 Normal use Leak at hinge pin. Correc- Replaced hinge pili 8 Ilours None 9-19-79

~

j tive seal.

j 79-8-153 LCV-4218-1 Normal use Packing leak. Correc- Repacked valve. 4 llours None 8-8-79 tive 79-8-188 LSil-21234 Normal use Suitch operation er- '

Correc- Replaced gear 2 Ilours None 8-16-79 ratic. tive movement. L l

79-8-226 SH-2112 Normal use Lost; circulator speed Correc- Connected spere 2 Ilours None 7 8-27-79 indication. tive signal cable.

79-8-229 SM-210 6 ' Normal use Lost circulator speed Correc- Conntected spare 2 llours None >

8- 27-79 .

indication. tive signal cable.

79-8-232 V- 7209 Normal use Packing leak. Correc- Repacked valve. 2 llours None 8-18-79 tive 79-8-295 SSL-21161 Normal use Lost circulator speed Correc- Replaced speed 2 Ilours None 8-15-79 in dica t ion. tive signal cable.

79-8-336 SSL-21161- Normal use Speed signal lost. Correc- Replaced speed 4 Ilours None 8-28-79 1/-2 tive signal cable.

79-8-344 C-820lS Normal use Piston loose. Correc- Tightened piston 2 Ilours None 8-16-79 tive nut.

79-8-389 91/IIV-2251 Normal use 011 leak at ilV-2251. Correc- Replaced "O" rings 11 llours None 8-19-79 tive in poppet block.

79-8-399 MIS-ll21 Normal use Reflected light low. Correc- Replaced light 4 Ilours None 8-21-79 t' ve source. i 79-8-403 C-8201S Normal use Compressor would not Lotecc- Replaced failed 1 Day None 8-23-79 pump. tive discharge check valve.

79-8-434 PPS Module Normal use Module failed test. Correc- Replaced failed 2 llours None B-21-79 XDIS-2117.1 tive integrated circuit chip.

l

FORT.ST. VRAIN SIGNIFICANT MAINTENANCE iStlMMARY TIME IDENTIFICA- REQUIRED EFFECT OH TION NUMBER SYSTEtt/ NATURE OF FOR SAFE OPERATION AND DATE CoWONENT cAUSE OF HALFINCTION RESULTS OF HALFtHCTION MAIN 1YNANCE CORRECTIVE ACTION CottPIETION OF lilE REACIBR 79-8-483 22/PV- Normal use Lower flange of valve :orrec- Replaced seal ring 2 Ilours None j 3-23-79 22168 leaks. tive & follower on main

valve; plug seal ring on pilot valve.

79-8-497 IIV-2202 Norinal use Ilydraulic oil Icak. Jorrec- Replaced failed "0" 4 Ilours None ll 79 Ilydraulic tive ring.

Operator 79-8-504 22/IIV-2202 Normal use Slight oil leakage on :orrec- Replaced cylinder 1 Day None tl-23-79 lower "0" ring of cylin- tive rin gs , "0" rings, der. and barrel of cylin-der.

79- 8-580 PDT-21392 Normal use Indicated differential Co rrec- Replaced failed 24 Ik,rs None 9-28-79 pressure incorrect. tive bellows and strain

gauge.

! 79-8-600 45/V-45077 Normal use Electrical fire pump Correc- Replaced float and 1 Day None 10-19-79 air release valve leaks tive adjusted float arm.

water. t 79-8-625 S-2101, Normal use Dryer bypassed and Correc- Replaced failed 2 Ilours None y 8-31-79 TDR-8 would not reset. tive relay.

Relay 79-8-630 22/IIV-2292 Normal use Steady oil leakage. Correc- Replaced relief 6 Ilours None 10-31-79 Live valve.

79-9-11 22/ilV-2223 Normal use Valve seal leakage. Correc- Replaced seal ring. 2 Days None 9-14-79 tive 79-9-109 21/SV-2105 Normal use Rod end seal leak. Correc- Replaced seal. 8 Ilours No' ie 9-28-79 Ilydraulic tive Operator 79-9-111 27/IIV-2250 Normal use Operator cylinder to Correc- Instal;>d new "0" 1 Day None 12-17-79 block "0" ring leaking. tive ring, pist on seal, ,

and rod seal.  ;

79-9-123 25/IIV-2524 Normal use Valve leaks through. Co r rec- Stem length ad- 4 Ilours None 11-28-79 tive justed to seat .

valve. Stem clamp and operator nut tightened.

79-9-171 CRS-262 Normal use Snubber inoperable. Correc- Installed new 8 Ilours None 9-14-79 Ilydraulic tive piston rod eye pin.

Snubber 79-9-177 13/11-1303 Normal use Slight leak in upper Correc- Replaced seal in 8 Ilours None 1

10 79 seal of RIV. tive kin d . .

.A w I , ,

i i

l FORT ST. VRAIN SIGIFICANT MAINTENANCE! SIRetARY IDENTIFICA- 3 REQ ED EFFECT (N TION NUMBER SYbfEH/  ;

NATURE OF FOR SAFE OFERATION AN9 DATE COFFONENT CAUSE OF MALMHCTION RESU1.TS OF MALFINCTI(N MAINTENANCE CORitECTIVE ACTION C0ffi,ETION OF T1tE RF>c!UR 79-9-188 V-211069 Normal use Valve leaks through. Correc- Replaced valve in 1 Week None 9-18-79 tive kind.

! 79-9-272 NIH1135-1 Normal use Spurious scram on Correc- Replaced failed 8 Ilours None 9-17-79 single channel. tive component.

79-9-357 48/K-4803 Normal use Governor oil leak. Correc- Repaired leak. 1 llour None 9-21-79 tive i 79-9-370 V-82473 Normal use Check valve leaked back. Correc- Replaced valve in 4 Ilours None 9-20-79 rive kind.

79- 9-376 LS-21287 Norpal use False low level alarm. ~Co rrec- Repaired broken 4 llours None 9-20-79 tive terminal.

79-9-382 }01-1117 Normal use Spurious trip. Correc- Replaced light 4 Ilours None 9-20-79 tive riou rce .

. 79-9-389 C-8203X Normal use Compressor not pumping. Co rrec- Replaced failed 1 Day None

{ 9-21-79 tive discharge valves.

79-9-418 91/P-9102X Normal use Illgh vibration. Co rrec- Replaced pump. 6 Days None 10-3-79 tive 79-9-439 22/FT-2205 Normal use Flow control drift. Correc- Replaced force 8 Ilours None b j 9-26-79 , tive motor on trans- i mitter.

79-9-445 Instrument Normal use Line leaks. Cor re c- Rewelded line. 8 Ilours None 9-25-79 Line for tive PT-9137-4 79-9-462 11/IIV- Normal use Valve will not drive Correc- Replaced motor and 12 Ilourt None 10-2-79 11145-2 closed with handswitch tive all in ternals in in position #1. kind.

79-9-466 21/V- Normal use V-21268-2 (emergency Correc- Replaced disc seat 1 Day None 10-16-79 21268-2 feedwater safety) tive and blowdown gas-leaking through. kets and rings.

Velded on body and disc holder.

79-9-467 PDT-21390 Normal use Indicated dif ferential Co rre c- Replaced failed 4 llours None 9-27-79 pressure incorrect. tive transistors. '

79-9-470 22/PV- Normal use PV-22167 leaking Correc- Replaced seat and 1 Day None 11-27-79 22167 through. tive installed new disc, 79-9-489 13/11-1301 Normal use R-drive retract limit Correc- Replaced switch in 1 Day None 10-17-79 , switch not operating tive kind and reset.

properly.

79-9-539 FDI-1120 Normal use Spurious trip. Correc- Replaced failed 8 Ilours None 9-30-79 tive light source.

J -

i

} I

i

• FORT ST. VRAIN SIGN 1FICANT MAINTENANCE:

SUMMARY

l l TIKE i

l IDENTIFICA- REQUIRED EFFECT m Tion uunnta sYsTEn/ NATURF OF H)R SAFE OPERATION AND DATE COWONENT CAUSE OF HALFit'CTION REStfLTS OF MALFINCTION HAIN1YNANCE CORRECTIVE ACTION CUffPl.ETION OF T11E REACTOR 79-10-24 98/IIRS-194 Normal use . No oil showing in Correc- Filled snubber 1 Ilour None

, 10-2-79 reservoir - hydraulic tive reservoir.

snubber inoperable.

+

79-10-73 13/11-1302 Normal use Broken connector and Correc- Rewire and repair 8 Ilours None 10-11-79  !

internals on RIV. tive broken connector, j 79-10-82 98/Il0S-29 Normal use '

Reservoir lock nut Correc- Tightened lock nut. 1 Ilour None i 10-5-79 loose; anubber reser- tive

! voir out of position.

79-10-93 21/IIV- Normal use Valve leaked through. Correc- Replaced valve 8 Ilours None 10 79 21352 tive disc.

79-10-124- 92/M-92815 Normal use Air leakage around sedi- Cor rec- Replace "0" ring 3 llours None 10-10-79 trent bowl to M-92815. tive and bowl filters.

79-10-134 82/V-82758 Normal use Air leak at valve. Co rre c- Repaired air leak. 1 Ilour Not.e i 10-8-79 tive I

79-10-161 93/XDIS- Normal use During voltage verifi- Correc- Chip Z-9 at CF 4 Ilours None 10-9-79 21176 cation at 406-P9, low tive AL3 replaced.

voltage was observe.d. E 79-10-162 93/SSL- Normal use Low yoltage at 506-P9. Correc- eplaced chip Z-35 4 llours None Y 10-9-79 21172-1 tive a CT-1-bR4.

79-10-235 93/RIS- Normal use Monitor readiug upscale. Correc- Replaced detector 4 llours None 10-15-79 93252-10 tive tube-calibrated RIt 79-1(i-241 22/ilV- Normal use Lower valve body flange Correc- Replaced gaskets 3 1/2 None 11-24-79 22225 leakage on Loop 1 main tive in kind.  !!ours steam bypass trap iso-lation.

79-10-260 21/V- Normal use Leakage on safeties on Correc- Seat and disc 8 Ilours None 10-lC 79 21268-1 emergency feedwater tive replaced.

header.

79-10-263 9 3/ CT Normal use Low voltage on CT-1-Bd4 Correc- Replaced ships, 4 Ilours None 10-15-79 BR4 400 bay - plant pro- tive verify operability tective sys tem.

79-10-274 21/PV- Normal use Valve and outlet pipe Correc- Replaced operator 2 Days None '

10-18-79 21243-1 cold with line pres- tive "0" rings.

surized at power.

79-10-282 21/IIV- Normal use Valve leaked through. Correc- Replaced valve 8 !!ours None 10-15-79 21352 '

tive disc.

79-10-283 21/IIV- Normal use Valve leakage in buffer Correc- Replaced disc, 1/2 Day None 11-28-79 21345 helium dryer , valve. tive checked stroke,

, and repacked.

d A l _ _

FORT ST. VRAIN SIGNIFICANT MAINTENANCE SIIM?tARY TIME IDENTIFICA- EFFECT 04 REQUIRED ftON NUMBER SYSTEHf NAftlkE OF FOR S4FE OPERAT10tt AND DATE COtFONENT cAUSE OF HALFINCTIGi RESULTS OF HALFINCTI(N HAIN1YNANCE CORP.ECTIVE ACTION CONP LEf t 0*f 0F file BEACTOR 79-10-306 21/IlV- Normal use Valve and cross tower Correc- Replaced disc, 1/2 Day None l 11-28-79 21346 leakage on buffer heli- tive checked stroke, and

um dryer system. repacked.

79-10-307 21/l!V- Norral use Valve and buffer helium Correc- Replaced disc, 4 Ilours None 11-28-79 21347 dryer cross tower tive checked stroke, and leakage via llV-21347. repacked.

{ 79-10-308 21/IIV- Normal use Valve and buffer helium Correc- Replaced disc, ,4 Ilours None l 11-28-79 21348 1ryer cross tower tive checked stroke, and leakage. repacked.

79-10-309 21/IIV- Normal use Valve and buffer helium Correc- Replaced disc, 4 Ilours None 11-28-79 21349 dryer cross tower tive checked stroke, and leaka ge. repacked.

79-10-310 21/IIV- Normal use Valve and buffer helium Correc- Replaced disc, 4 Ilours None

11-28-79 21350 dryer cross tower tive checked stroke, and Icakage, repacked.

_79-10-311 21/llV- Normal use Valve and buffer helium Correc- Replaced disc, 4 Ilours None 11-28-79 21351' dryer cross tower tive checked stroke, and ,83 lealsage. repacked.

79-10-312 21/IIV- Normal use P Valve and buffer helium Correc- Replaced disc, 4 llours None 11-28-79 21352 dryer cross tower tive checked stroke, and j leakage. repacked. Built up stem and machined new threads.

79-10-313 21/llV- Normal use Valve and buffer helium Correc- Replaced disc, 4 llours None

, 11-28-79 21353 dryer cross tower tive checked stroke, and

leakage, repacked.

79-10-314 21/IIV- Normal use Valve and buffer helium Co rrec- Replaced disc, 4 Ilours None 11-28-79 21354 dryer cross tower tive checked stroke, and leakage. repacked.

79-10-315 21/IIV- Normal use Valve and buffer helium Co rrec- Replaced disc, 4 Ilours None 11-28-79 21355 dryer cross tower tive checke.d stroke, and leakage. repacked. '

79-10-316 21/IIV- Normal use Valve leakage. Correc- Replaced disc, 4 Ilours None 11-28-79 21225 tive checked stroke, and repacked.

79-10-317 21/IIV- Normal use Valve leakage. Correc- Replaced disc, 4 llours None 11-28-79 21226 tive checked stroke, and repacked.

79-10-331 21/FT-216! Normal use Continuous alarms on Co rrec- Replaced strain 1/2 Ilay None 11-26-79 "B" circulator buffer tive gaue,e on FT-2169 supply flow due to and calibrated y

l ground in current loop. 1. .rument.

FORT ST. VRAIN SIGNIFICANT ltA,INTENANCE_Sitt iARY ,

TIME REQU1 RED E P FECT ON I DENT! FICA- FOR SAFE OPERATION NATURE OF TIOtt MUHBER SYSTEH/ CotFI F7 ION OF THE REACTOR

.SULTS OF HAI.FildCTION HAINTEN ANCE CORRECTIVE ACTION AND DATE (XMf0NENT CAUSC OF mLFueCTION corree- Installed new 1 Day None 79-10-339 21/P-2103S Nornal use Pauting leak on inboard L1-15-79 packing gland of P- tive packing gland.

2103S. Repaired crack in pump casing.

Correc- Replaced seal. 6 Ilours None 79-10-359 22/IIV- Normal use casket seal ring leak -

L 1- 6-79 22228 valve blowing steam, tive Correc- Replaced manual 1 llour None 79-10-396 82/ V-8218 Normal use Safety release arm for 10-22-79 V-8218 safety relief tive trip mechanism.

worn through.

79-10-420 93/Cr-2B2 Normal use Iow voltage at 606 P1 Co rrec- Replaced chip, Z-4'J 4 Ilours None (CT-2B2) . tive verified instrument 10-23-79 operability.

79-10-424 21/V- Normal use Valve leakage. Correc- Replaced vent valvo 2 Days None tive assembly.

10-25-79 211074 1/2 Day None Correc- Replaced light 79-10-437 11/MM-1120 Normal use Ml' tripped on low re-10-23-79 flected light. tive source.

79-10-455 82/C-8201S Normal use Ins trument air com- Correc- Ins talled new 5 Days None h 11-5-79 pregsor providing in- tive piston, piston rod y sufficient output. and 4 discharge valves, and rebuilt 4 valves per quarterly in-spection.

79-10-466 21/SSil- Normal use Speed switch reading Correc- Replaced "C" circu- 4 Ilours None 21162-2 erratic. tive lator speed cable 10-24-79 in kind.

RIS-932 52- 10, Loop 1 Correc- Replaced capacitor 4 Ilours None 79-10-467 93/RIS- Normal use 93252-10 hot reheat activity tive in kind.

10-29-79 nenitor trips on spuri-ous noise. ~

79-10-534 22/IIV-2224 Normal use Both "open" and "close" Correc- Installed new limit 4 llours None 10-27-79 position lights lit tive switch.

with valve closed.

Emergency condensate Correc- Cleaned and lubrI- 8 Ilours None 79-10-539 22/V- Normal use 12-3-79 22370 bypass check valve was tive cated shaft and stuck closed. valve.

Correc- Replaced pre-amp. 1 flour None 79-10-615 11/ NIM- Normal use. Low output f rom chan-10-31-79 1131 nel. tive Normal use Of f-line helium dryer Correc- Replaced stem as- 4 Ilours None i 79-11~-21 21/FCV-12-10-79 2151 pressurization with tive sembly, spool, and .

I purge shut off. bonnet. Calibrated valve.

~

FORT ST. VRAIN SIGNIFICANT HAINTENANCE

SUMMARY

TIME I DENTI FICA-TION NUMBER SYSTEN/

REQUIRED EFITCT W NATURE OF FOR SAFE OPL6aTION AND DATE COW ONENT CAoSE OF HALFtNcrION RESULTS OF HALFINCTI(E; HAINTENANCE CORRECTIVE ACTION CUHPl.ETION OF 11tE REACTOR 79-11-57 11/NR- Normal use Pinched high voltage Correc- Repaired cable. 2 Ilours None 11-5-79 1133-1 cable resulting in low tive count rate.

79-11-128 93/XT- Normal use Instrument out of Correc- Adjusted instru- 1 Ilour None 11-8-79 93471C tol e rance. tive ment, i 79-11-129 93/XT- Normal use Instrument out of Correc- Re-adj usted and 1 Ilour None 3

11-8-79 93471B tolerance, tive recalibrated as

_ _. _ required 79-11-130 93/ M- Normal use Instrument out of Correc- Recalibrated and 1 Ilour None 11-8-79 93471A tolerance, tive re-adjusted.

79-11-137 82/C-8201 Normal use Short cycling of com- Correc- Re-adjusted un- 1 llour None 11-9-79 pressor. tive loader.

79-11-140 93/XT- Normal use Instrument out of Correc- Recalibrated and 1 Ilour None l 11-9-79 93470C tolerance. tive re-adjusted.

79-11-144 93/XE- Normal use Did not respond to Co rrec- Repaired solder 1 llour None 11-9-79 93470B ultrasonic calibrator. tive joint.

79-11-145 93/XE- Normal use Did not respond to Correc- Repaired solder 1 Ilour None 11-9-79 93470A ultrasonic calibrator. tive joint.

i 79-11-153 82/V-8233 Normal use  ?

V-8233 (discharge of Co rrec- Check valve re- 8 Ilours None 12-6-79 C-8201) leaks through. tive placed with re-built valve.

79-11-160 82/V-82473 Normal use Leaking discharge checl< Correce Installed new T Day None 11-25-79 valve on "C" instrue tive , check valve.

ment air compressor.

79-11-161 82/V- 82492 Normal use Isolation valve on "C" Correc- Valve disassembled , 24 None 11-26-79 instrumen t air com- tive cleaned, and llours pressor leaking througl . returned to servici .

79-11-163 93/XE- Normal use Would not respond to Correc- Repaired solder 1 llour None 11-9-79 93479A ultrasonic calibrator. tive joint.

79-11-167 98/BFS-412 Normal use Snubber inoperable due Co rrec- Refilled oil reser. 1 llour None 11-9-79 Snubber to empty oil reservoir, tive voir.

79-11-193 45/P-4501S Normal use Diesel fire pump would Correc- Repaired battery 1 Ilour None -

11-13-79 not start in automatic, tive terminal.

79-11-195 98/CR-154 Normal use Broken hanger. Correc- Repaired broken 8 Ilours None 11-22-79 tive hanger.

79-11-197 11/ Control Normal use Control rod drive #6 Correc- Repl. aced seal in ~1 Day None 12v2-79 Rod Drive penetration secondary tive kind.

Pene- seal leakage too high tration #6 to meet specifications, y Secondary Seal ,

! I l

FORT ST. VRAIN SICNIFICANT IIAINTENANCE SUmfARY oExTI FICA- RE U ED EFFECT UN TION NUMBER SYSTEHf  ; NATURE OF FO R SAFE Ol'ERATION AND DATE CfMf(NENT CAUSE OF HALFINCTION RESUI.TS OF HALFLNCTICN HAIN1YNANCE CGRRECTIVE ACTION CotFIETION OF 11tE REACTOR 79-11-199 11/ Control Normal use Control rod drive #25 Correc- Replaced seal in 1 Day None 11-20-79 Rod Drive. penetration secondary tive kind.

Pene- i seal leakage too high tration -

to meet specifications.

1. 25 Secon-dary Seal 79-11-213 82/C-8201 Normal use Loaded erratically. Correc- Replaced pressure 1 llour Hone i'

11-16-79 tive switch.

79-11-238 21/IIV- Normal use Leakage on llV-21352. Correc- Existing threads on 1 Day None 11-23-79 21352 tive valve stem built up and rethreaded.

79-11-275 13/11- 0 01 Normal use Fuel handling machine Co rrec- Fuel handling 1/2 Day None 11-17-79 grapple probe failed to tive machine repaired remain in receive po- per procedure.

sition.

79-11-307 93/IIV- Normal use Powering plant pro- Correc- Replaced both 1 Day None 12-5-79 21203-3 & tective system logic tive valves with re- [,

ilV-21191-3 up and down causes a built valves. y decrease in "A" brake and seal supply bottle pressure fue to valve leakage.

79-11-310 13/11-1301 Normal use Fuel handling machine Correc- Repaired faulty 3 Days None 11-26-79 grapple head rotation tive regulator, problem.

79-11-311 22/ Pipe Normal use Pipe elbow leakage on Correc- Replaced coupling. 7 Ilours None 11-26-79 pipe between V-22320 tive and PDT-22232-2.

79-11-318 82/S-8201 Normal use " A" ins trumen t air Correc- Freed up stuck 1 Day None 11-26-79 dryer off line tower tive check valve and won't depressurize cleaned dessicant properly, from solenoid .

valve.

79-11-331 82/C-8203 Normal use C-8203 instrument air Correc- Replaced defective 8 Ilours None 11-28-79 compressor trips on tive exhaust valves.

high discharge air tempe ra tu re .

79-11-351' 11/ Con trol Normal use Region 27 secondary Correc- Replaced gasket ?n 1 Day None 12-2-79 Rod Drive seal leakage exceeds tive kind.

1. 27 Secon- specifications.

dary Pene , ,

~ ~ ~ ~ ~ ~

tration )

n ., I ,

FORT ST. VRAIN SIGNIFICANT MAINTENANCE

SUMMARY

~

TIME IDENTI FICA- REQUIRfC EFFECT ON TION NUMBER SYSTEH/ NATURE OF FOR SAFE OPERATION AND DATE COFF0HENT CAUSE OF MAI.MNCTION RESUI.TS OF HA1.FINCTION HAINTENANCE CORRECTIVE ACTION 00tfl.ETION OF TitK REACTOR 79-11-352 11/ Region Normal use Region 37 secondary Correc- Replaced gasket in 1 Day None 11-26-79 37 Secon- seal leakage exceeds tive kind.

t dary Seal specifications.

79-11-362 21/llV- Normal use Air leaking through "O" Correc- Replaced "O" ring. 1 Day None 12-1-79 2154-1 ring and up stem of air tive l

operated valve.

79-11-363 21/P-2103S Normal use Outboard motor bearing Correc- Outboard hearing 4 Days None 11-27-79 on pump runs hot. tive and oil seal replaced.

79-11-375 46/IIV- Normal use llandjack will not dis- Correc- Removed stuck pin. 2 Ilours None 12-3-79 46248-2 engage due to stuck pin tive 79-11-387 22/IIV-2223 Normal use Packing leak. Correc- Replaced packing. 8 Ilours None 9-14-79 tive 79-11-438 98/CR-125 Normal use Bolt missing in pipe Co r rec- Bolt re-installed. 1/2 Ilour None 12-13-79 _

clamp for CR-125. tive 79-12-49 91/P-9105X Normal use Inboard seal leak on Correc- Installed new pump 4 Days None 12- 8-79 hydraulic power supply tive punp, P-9105X.

and coupling. 6 79-12-63 Y 02/K-9204X Normal use "A" diesel carrying an Correc- Changed injectors 4 Ilours None 12-9-79 inordinate amount of tive on K-9204X and ad-load. J usted governor.

79-12-79 ' 11/MM-1120 Normal use Dirty moisture monitor Correc- Cleaned mirror and 1 Day None 12-7-79 mirror and light guide tive windows. Replaced windows. Bad manifold seals.

"V" seal and window seals.

79-12-86 31/IIV- While manually Broken on valve Co rrec- Replaced valve 2 Ilours None 12 79 31121 closing valve, a operator, tive operator housing nut snapped off cover, the operator.

79-12-148 91/P-9106X Normal use Worn pun:p coupling on Co rrec- Changed out pump 1 Day None

~

12-13-79 hydraulic power supply tive coupling. '

punp.

79-12-150 91/P-9102) Normal use Pump coupling needs Co rrec- Replaced pump 8 Ilours None 12-21-79 replaced. tive couplin g.

79-12-190 92/K-9201 Normal use No voltage output at IA Correc- Replaced surge sup- 5 llours None 12 79 diesel generator (K- tive pressor.

9201).

79-12-192 21/IIV- Normal use Air line to ilV-2153-1 Correc- Repaired broken 2 Ilours None

~

12-10-79 2153-1 operator loose and tive line.

leaking.

I

FORT l ST. VRAIN SICNIFICANT MAINTENANCE'

SUMMARY

TIME IIENTIFICA. REQUIRED EFFECT ON TION NUMBER SYSTEN/ NATURE OF FOR SAIE OFERATIGt AND DATE COtPONENT CAUSE OF HALFINCTION RESULT!! OF HALFINCTIOM MAIN 1TNANCE CORRECTIVE ACTION C0t1PI.ETION OF 11tE RFACR)R 79-12-212 ' 91/IIV-2293 Normal use Stainless steel line Correc- Replaced relief 1 Day None 12-12-79 leaking oil on llV-2293. tive valve.

79-12-280 21/IIV- Normal use Air line to diaphragm Correc- Repaired line. 2 Ilours None 12-13-79 2153-1 for operator on llV- tive 2153-1 damaged.

, 79-12-308 25/IIV, Normal use Valve leaks through. Correc- Adjusted stem 4 llours None 12-14-79 2524 tive length. Cali-brated XEP.

79-12-317 91/IIV-2250 Normal use "B" valve on 5-valve Correc- Installed new "O" 2 llours None 12-17-79 manifoled of IIV-2250 tive ring.

leaks.

79-12-389 23/IIV-2301 Normal use IIV-2301 inoperable. Co rrec- Shortened actuator 1 Day None  :

12-18-79 tive drive shaft.

l 79-12-402 93)CT-2B2 Normal use Low voltage in 506 P1 Correc- Replaced Z-43. 1 Ilour None 12-19-79 Y. tive 79-12-421 21/PDIS- Normal use Switch does not oper- Correc- Replaced stripped 1 Ilour None 12-21-79 21173 ate, tive out locking de-vice. Recali-i y

brated switch.

79-12-435 21/IIV- Normal use Broken conduit to llV- Correc- Repaired conduit. 4 Ilours None 12-26-79 21252-2 21252-2. tive 79-12-462 21/V- Normal use Esaergency feedwater Correc- Repaired valve. 2 1/2 None 12-24--79 21543 relief valve leaking tive Days th ro ugh.

79-12-463 21/V- Normal use Emergency feedwater Correc- Repaired valve. 2 1/2 None 12-24-79 21523 relief valve leaking tive Days through.

79-12-464 21/V- Normal use Relief valve leaks Correc- Replaced disc and 1 1/2 None 12-21-79 21522 through. tive disc holder. Re- Days machined nozzle.

79-12-465 21/V- Normal use Relief valve leaking Correc- Machined nozzle 1 1/2 None 12-21-79 21542 through. tive and disc. ' Days i ,

s a

I

FORT ST. VRAIN SIQlIFICANT MAINTENANCE SU!! MARY P

} TIME ' a IDENTIFICA- REQUI RED EFFELT (H TION NUMBER SYSTEfff NATukE OF FUR SAFE OPERATI(W AND DATE CMfGENT cAttSE OF Hall 1NCTION RESULTS OF HAI FINCTIGI _ttAI NTE N ANCE . CORkECTIVE ACTitwt 4: tit 0'I.ETION OF THE BFACTOR WA 674-93 93/ Steam Mismarked docu- Erroneous documentatic 1 Co r rec- Junction boxes 1 Day None 4-16-79 Rupture mentation. and field cable routing. tive labled and cables Detection rerouted as Circuitry req ui red .

i t

8  !

tJ t k l 8

i o

9 1

e I' $ , g '

EW vge -- .-.sua_,__,ww,__ _

^ 'l ' M #w ' 8 "P **# '

' Ng ', {*g *] g o y y g g ; g , _ g-g g y .

' ' * ~

-%7f , j, ; g g f w% , _~ ~ -

g a

(

o HA IOR S AFE1Y NADI ATION RELEASE kEl.ATEll G) A- ASSOCI ATill Willi OLTT-CORRECTIVE ACTION RECTIVE HAIN- AGE W!!!Of ACColN15 FF. LATED RE. TAKEN TO REDUCE TENANCE l'ER- FOR re0RE 111AN 10%

PORTABLE Tile PROBARILITT OF OPERATING H)RHtiD DURING OF AllflWAbt.E ANNUA!.

NL91RE R 1*k0XIHATE CAtlSE SYSTEM HA LOR OH'(NENT OCCt!PRENCE RECT!NRENCR TIHli IDST 11tE OlrrACE val.tlE i

79-01 Circulator IIelium "D" llelium None None None None None trip during Circu- Circulator routine sur- lators veillance.

7 resulting in reduction of reactor power and generator load.

79-02 Faulty steam Steam Feedwate r None Valve was 70.8 None Nore gene rator Gener- Valve repaired , llours valve re- ators quired re-pair. .

79-03 Voltage

• Electri- "B" In- None None 14.8 None None transient. cal strument Bus llours i 79-04 Feedwa ter "B" Boiler 50-267/79-Two inoper- Feedpumps 4134.4 Refueling None

d' able boiler Feedpump 03/03-L rep ai re d. Ilou rs and turbine f ee dp unps . gene rator overhaul.

79-05 Field ground Electri- Relay None Replaced relay. 47.5 None None relay prob- cal llours lems.

79-06 Turbine over- Itain liain Turbine None None 1.9 None None speed test. Generator flours 79-07 liigh vi- Main Bea ring None None 53.0 None None bration Turbine llours caused tur-bine trip.

79-08 Drop in liain Throttle None None 76.8 None None throttle Turbine P ressure llours ,

pressure and

. load de-crease ; tur-bine t rip.

79-09 Ilot reheat Not Ap- Not Ap- None None 24.1 None None reactor scram plicable plicable llours suid turbine trip.

. .i , , .

r. v.*;<yem m n n . . n , - . ..w > - - m , v ~. - . - . . . .- . .. --

- ~ . - - - -m- ru

i

, T

--- gg --

kEi.ATED O)R- ASSOCI ATED Willt OUT-0)RkECTIVE ACTION RECTI VE HAIN- ACE Will(21 ACOMIN13 REIATED RE- TAKEN TO REDUCE TFNANCE PER- FI)R PktRE THAN 10%

PORTABLE 11IE PROBARILITY OF OPERATING FORHED DURING SF ALIJMABl.E ANNUAL NimitE R PROXIMATE cat 1SE SYSTEN HA. LOR OWR *0NENT OCCUR RENCE REC 11RRENCE TIME IJET 111E OlfTAGE vat t!E 79-10 Ins trumen t Electri- Instrument 50-267/79- Evaluation in 68.4 None None panel shorted cal Panel 28/01-T p rogress . Ilou rs to ground and t ripped.

79-11 Reduce power Primary Not Ap- None None 45.9 None None due to high Coolant plicable llours p rimary coolant moisture.

79-12 Piping Not Ap- Not /p- 50-267/79- Ilanger audit 743.4 None None hanger incon- plicable plicable 35/01-T in progress. Ilours sistencies.

79-13 Turbine trip Hain Not. Ap- None None 231.0 None None on low steam Turbine plicable llou rs tempe rat ure.

79-14 Scheduled Not Ap- Not Ap- None None 1600.5 Instal- None a plant shut- plicable plicable llours lation of $'

down. region con-straint de-vices and retuliing of l main con-denser.

i l

i o .. , , .

g .yp w uu , : . . . .. ~ .

< ,- . t~ - -- .. , , ... - - - - - - - , ; ^ ' - = = -

o J

3.0 RADIATION EXPOSLTES During the report period, two personnel re.:eived exposures in excess of 100 mrem. Below is a tabulation of the information required by Tech-nical Specification AC 7.5.l(b)3.

Number of Total Man-Rem Dose Assign-Pe rsonnel Exposure Exposure Duty Function ment 1 190 mrem .19 Results Testing 100%

1 170 nrem .17 Contractor Testing 100%

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

4.0 FUEL EXAMINATIONS No examination of irradiated fuel was completed during the report period.

f

~

c I

.