ML19338E425

Semiannual Operating Rept,Jan-June 1972

ML19338E425
Person / Time
Site:	Dresden
Issue date:	06/30/1972
From:	COMMONWEALTH EDISON CO.
To:
References
NUDOCS 8009290551
Download: ML19338E425 (63)

Text

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DRESDEN NUCLEAR POWER STATION UNITS #1, #2, AND #3 SEMI-ANNUAL REPORT JANUARY 1,1972 IHROUGH JUNE 30, 1972 ing innessn Section 6.6.D of the Dresden Unit 2 and Unit 3 Technical Speci-fications requires that a semi-annual report be submitted to the Atomic Energy Commission. To provide for a more logical, complete and concise report, and to eliminate duplication, the semi-annual reports for Dresden Units 1, 2 and 3 for the period January 1,1972, through June 30, 1972, have been combined in this document. The document is divided into four sections: Section I - Dresden Unit 1 Operations and Maintenance;Section II - Dresden Unit 2 Operations and Maintenance;Section III - Dresden Unit 3 Operations and Maintenance; and Section IV - Dresden Station Radioactive Wastes and Environmental Monitoring.

4

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e DRESDEN NUCLEAR POWER STATION 3

SEMI-ANNUAL REPORT JANUARY 1. 1972 'tHROUGH JUNE 30, 1972 SECTION I: DRESDEN UNIT 1 OPERATIONS AND MAINTENANCE I.

Unit #1 A.

Introduction Dresden Nuclear Power Station Unit I returned to operation February 1, following its seventh partial refueling outage. Following a brief period of early cycle physics testing, the unit operated at full power for a short thme. The unit was then base loaded, operating between 80% and 90% power. The 10% and 20% power derratings were imposed to minimize off gas activity release. At the end of the report period, the unit was base loaded at approximately 80% power.

B.

Operating Data A brief summary of the nuclear and electrical operating data for the first half of 1972 is presented below. A more detailed summary.

on a monthly basis, is provided in Table I-A and Figures I-A through I-F.

A listing of all reactor scrams and shutdowns, and their causes, is provided in Table I-B.

Unit downtime following these shutdowns is also included.

Gross thermal generation 78,885.3 MWDt Gross electrical generation 592,136.36 MWHe Net electrical generation 561,978.90 NHHe Number of criticals 21 Number of scrams from critical 7

Hours generator operated 3,388 Hrs. 28 Min.

' C.

Nkintenance A tabular summary of maintenance on systems and components designed to prevent or mitigate the consequences of nuclear accidents is set forth in Table I-C.

D.

Facility Changes Pursuent to the reporting requirements of paragraph 50.59 (b) of 10CFR Part 50, a brief description of facility cbc.ges made during the first half of 1972 without prior commission approval follows:

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1.

Core Spray Installation A core spray system is in the process of being installed on Unit 1. - This system is part of Commonwealth Edison's program to meet the AEC's adopted interha acceptance criteria for the performance of emergency core cooling systems (ECCS) for light water reactors with which we will have to comply by July 1, 1974. Completion of the system and operational checkout is not expected to be until late 1972. The description and design yes covered in proposed change No.17 to License DPR-2 dated October 10, 1968.

2.

Vessel Level Sensor Installation The old float-type Magnetrol reactor low water level sensors have been replaced by Yarway (indication type) level sensors.

The magnetrol devices have been replaced because they had a history of unreliability due to crud accumulation which impaired the switch operation. Also, the Yarways have an additional set of contacts which will be used to initiate the core spray system that is being installed. No new safety item is involved since the reliability of the system has been increased.

3.

Relocation of Motor Operators From a past history of motor failure due to excessive heat, the motor operators on the emergency condenser condensate return lines, valves MO-101 and MD-109, were removed from the steam drum compartment to the Emergency Condenser (649')

level.

The movement of thess motor operators does in no way effect the safety function of these valves. It does allow access to the operators during unit operation.

I

4 TAEff. IA

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Dresden Unit 1 Opera tino, Sutmr.ary - 1972 Ilours' Co're Cross Het Hours Concrator Thermal Electric Electric Number Duration of Critical On-Line Pouer Pouer Pouer of Scrair.s Number of Downtime lionth Ilrq:ltin lirs:ltin

.IMDt inille

!!Ulle

& Shutdowns Times critical Hrs: Min January 0

0 0

3.67

-1,929.2 0

0 744:00 February 665:46 602:46 11,439.3 85,161.0 80,128.7 5

16 30:14 March

.744:00 744:00 18,783.0 139,290.25 133,190.3 0

0 0

April 716:41 712:10 17,426.0 133,020.79 127,171.8 1

1 2:19 May 702:14-680:10 16,397.1 124,410.34 118,580.2 3

3 41:46 June 664:51 649:22 14,839.9 110,250.31 104,837.1 1

1 55:09 Totst 3,4(33:32 3,388:28 78,885.3 592,136.36 561,978.9 10 21 873:28' N

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TABL T-B

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Critical Suberitical Mte Time Date Time Scram Down Time Reason for Shutdown 752 Hr. 3 Min.

Reactor Scram attributed to spurious 2/1 0803 2/1 0836 Yes 6 Ilr.27 Min.

undervoltage relay trip. Cause undetermined.

2/1 1503 2/1 1545 No Low Power Physics Testing 7 Hr.45 Min.

2/L 2330 2/2 0039 No Low Power Physics Testing 11 Min.

2/2 0050 2/2 0234 No Low Power Physics Testing 16 Min.

2/2 0250 2/2 0327 No Low Power Physics Testing 9 Min.

2/2 0336 2/2 0526 No Low Power Physics Testing 19 Min.

Reactor scram due to low condenser vacuum.

2/2 0545 2/2.

2055 Yes 3 Hr.35 Min.

Loss of turbine seal steam pressure.

Reactor scram due to low condenser vacuum.

2/3 0030 2/3 0239 Yes 1 Hr.14 Min.

Loss of turbine seal steam pressure.

2/3 0353 2/3 0542 No Low Power Physics Testing 1 Min.

2/3 0543 2/3 0552 No Low Power Physics Testing 5 Min.

2/3 0557 2/3 0604 No Low Power Physics Testing 11 Min.

2/3 0615 2/3 0620 No Low Power Physics Testing 1 Min.

2/3 0621 2/3 0650 No Low Power Physics Testing -

7 Min.

2/3 0657 2/3 1010 No Low instrument air pressure allowed scram valve on D-7 to open slightly resulting in the drive drifting fror. 12 to O taking 1.5 Min, the reactor suberitical.

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TAE I-B (CCnt'd)

Critical Suberitical Reason for Shutdown nate Time Date Time Scram Down Time Reactor scram due to primary drum low 2/3 1025 2/14 1125 Yes water level caused by apparent sluggish 1 Hr.35 Min.

feedwater control valve operation.

Reactor scram due to voltage surge 2/14 1300 4/17 0948 Yes 2 Hr.19 Min.

caused by switchyard electrical malfunction.

Maintenance and Control Rod Driva 4/17 1207 5/12 2235 No 32 Er.53 Min.

testing shutdown.

Reactor scram due to low condenser 5/14 0728 5/14 2250 Yes vacuum caused by a leaking heater 8 Hr. 8 Min.

shell relief valve.

Reactor scram during startup due to 5/15 0658 5/15 1025 Yes insufficient condenser vacuum with 200 45 Min.

psig reactor pressure.

Scheduled shutdown for maintenance, 5/15 1110 6/9 2344 No surveillance, and control rod drive 55 Hr. 9 Min, testing.

6/12 0653 Total 873 Hr.28 Min.

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s 4 4 s TABLE I-C DRESDEN UNIT 1 MAINTENANCE

SUMMARY

1972 Effect Action Taken to On Safe Type of Cause of Effect of Preclude Operation Time for Month System Component Maintenance Na1 function Mal function Recurrrence Of Reactors' Completion 1 January 5 E1cetrical Diesel Corrective Low Diesel Failure of Repaired thermo-None 10 Hrs. Generator Oil Temp, Diesel to statically controlled In shutdown start. cooling valve and installed chain on radiator louvers. 7 Reactor "A" cleanup Corrective Tube leaks Primary system Installed new heat None 1500 Auxiliary heat exchanger leakage to exchanger and assoc-closed cooling lated piping. system. 9 Control Rod Pr + 200 Corrective Calibration Incorrect Calibrated pressure None 3 Drive Pressure Drift setting regulator. Regulator 10 Reacto: Neut ron mon-Corrective Calibration Indicating Adjusted setting None 2 Safetv itor channel Drift high

1. 11 calibrate switch.

11 Containment Sphere exhaust Corrective Incorrect No control Adjusted position None 2 valve A0-501 position room. position switch arm position switch switch setting. indication 11 Electrical Diesel gener-Corrective Low battery Low battery Replaced battery None 4 ator battery voltage voltage alarm 12 Monitoring Stack gas Corrective Faulty tube Indicated full Replaced tube socket None 2 monitor recorder socket scale s

69*

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y w _ TABLE .I-C (cont'd) DRESDEN UNIT 1 MAINTENANCE

SUMMARY

1972 Etfact Action Tr. ken to On Safe i Type of Cause of Effect of Preclude-Operation Time for Month System component Maintenance Malfunction Na1 function Recurrrence Of Reactors Completion January 13 Control Drive C-8 Corrective Faulty pos-No position Replaced position None 4 Hrs. Rod Drive position ition probe indication probe. probe 13 Control Drive G-9 Corrective Fanity pos-No position Replaced position None 4 Rod Drive position ition probe indica tion

probe, probe 13 Control Drive B-5 Corrective Faulty pos-No position Replaced position None 4

Rod Drive position ition probe

1. 12 indication probe.

probe 13 Control Drive accum-Corrective Loose wiring No alarm Tightened connection .None 2 Rod Drive ulator #9 connection function water alarm 13 Control Accumulator Corrective Faulty switches No control Replaced switches None 2 Rod Drive level switches room alarm 2, 17, 23 14 Control Scram dump Corrective Faulty indi-Incorrect Replaced motor and None 3 Rod Drive tank pressure cator motor indication calibrated indicator indicator coil 18 Emergency "B" post Corrective Plugged bubbler Full scale Cleaned bubbler Mone 4 Core cool-incident tubing indication tubing ing. L1-505B 0 4 o y f.

~ / TABLE I-C DRESDEN UNIT 1 MAINTENANCE

SUMMARY

1972 Effect Action Taken to On Safe Type of Cause of Effect of Preclude Operation Time for Month System Component Maintenance Malfunction Malfunction Recurrrence Of Reactors Completion January 26 Monitoring Composite Corrective Frozen suction No water sampic Thawed suction fione 4 Hrs. sample pump line. line 28 Reacroc Neutron mon-Correct ive Faulty slide-Improper Replacel bracket None 2 Safety itor channel wire holding s tandardiz ing and calibrated

1. 7 recorder bracket standardizer standardizer 29 Primary' Reactor vessel Corrective Leak in " donut" Primary system Replaced " donut" None 22 Piping vent line flange leak.

with standard flange flange. ?ebruary 1 Reactor Scram circuit Preventive None None Surveillance None 6 Safety and safety system Io Reactor Incore 116A Corrective Faulty resis-Instrument Replaced resistor None 2 Safety scram light tor on range scram indicated selector switch 4. Reactor Incore 114A Corrective Detector Indicated full Decreased readout None 2 Safety sensitivity scale sensitivity high 5 Containment Sphere exhaust Corrective Faulty valve Slow valve Replaced diaphragm None 4 valve AO-501 diaphragm operation diaphragm s n o

) T/.BLE T-C (cont'd) DRESDEN UNIT U 1 l'/.II*T2").NCE SUl2'ARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month Systen Component Ib intenance }'31 function Malfunction Recurrence Of Reactors Completion Psbruary 11 Reactor Neutron Corrective Failed tube Erratic oper-Replaced tube None 2 Hrs. Safety monitor ation. channel #7 12 Reactor Incore 106C Corrective Faulty auc-Zero indica-Replaced auctioneer None 3 Safety

tioneer, tion.

18 Emergency Diesel fire Corrective Exhaust line Fumes in crib Replaced exhaust line None 8 Core pump engine leak house with flexible pipe. Cooling March 6 Electrical, Diesal gen-Preventative None None Replaced batteries None 4 erator batteries 23 Emergency Emergency con-Preventative None None Surveillance None 2 Core denser level Ccoling transmitter and indicator. 23 Reactor Neutron mon-Corrective Dirty slide Erratic oper-Cleaned slide wire None 2 Safety itor channel

wire, ation.

91 recorder April 7 Emergency Diesel fire Corrective Faulty tach-Incorrect Installed new tach-None 5 Core pump tachometer ometer and speed ometer and cable. Cooling

cable, indication b

'O e e ji

~ .~ I r e TABLZ I-C DRESdEN UNIT 1 NAINTENANCE SU)O1ARY 1972 Effect Action Takt.a to On Safe Type of Cause of Effect of Preclude Operation Time for Month System Component Maintenance Malfunction Mal function Recurrrence Of Reactors Completion April Insula ted socket None 3 N rs. 12 Control Drives D-1 Corrective Shorted bulb Blew fu.ts Red and E-1 socket Drive 12 Reactor Neutron mon-Corrective Calibration Incorrect Calibrated standard None 2 Safety itor channel drift indication

1. 6 standard-ization s5 stch 12 Poison Poison system Corrective Amplifier and Erratic Calibrated amplifier None 3

temp. recorder recorder out indica tion and : ecorder. of calibration 20 Reactor Neutron mon-Corrective Faulty power Erratic Replaced power supply None 4 Safety itor channel #6 supply operation !.O Reactor Neutron mon-Corrective Faulty ampli-Spurious Replaced faulty tubes None 2 Safety itor channel #1 fier tubes signals 27 Reactor Neutron mon-Corrective Faulty power Spurious trip Replaced power supply None 4 Safety itor channel #1 supply May 3 Monitoring Stack gas Corrective Dirty recorder Erratic Cleaned slidewire and None 3 monitor slidewire and operation changed battery recorder low battery voltage 9 g

.~ d TAELE I-C (cont'd) DRESDEN UNIT #1 MAINTE!L'sNCE SU12'.ARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month Sys tera Component Ma intenance Malfunction Malfunction Recurrence Of Reactors Completion May 9 Emergency Diesel Fire Corrective Engine setting Failure to Engine overhaul Mone 30 Hrs. Core pump engine and tolerance start Cooling change. 15 Monitoring River dis-Corrective Faulty chart Incorrect Replaced chart None 3 charge drive motor response drive motor recorder 17 Dew Cell Dew Cell Corrective Oversized Motor. failed Installed new pump None 5 Sampling sample pump vacuum pump and motor. June 10 Electrical Diesel gen-Preventative Replaced all batteries 6 erator batteries 10 Electrical Diesel gen-Corrective Faulty Diesel coolant Replaced mechanical None 4 erator water mechanical. leakage. seal. circulation Pump. 11 Containment "A" sphere Corrective Valve seat Valve leakage Replaced valve seat None 12 inlet ventil-torn and lation valve cracked. a ri

DRESDEN NUCLEAR POWER STATION SEMI-ANNUAL REPORT JANUARY 1 1972 THROUGH JUNE 30. 1972 SECTION II: DRESDEN UNIT #2 OPERATIONS AND NAINTENANCE II. UNIT #2 A. Introduction Dresden Nuclear Power Station Unit #2 continued to be base loaded at 500 MWe until February 19, 1972 when the unit was shutdown for its second refueling outage. Major efforts during the cutage in-cluded replacement of 509 fuel assemblies, replacement of 15 LPRM strings, reworking 80 control rod drives, turbine inspection and modification, numerous plant modifications, torus painting and primary system inservice inspection. A containment in.tegrated leak rate test was performed and the unit was returned to service on May 10, 1972, upon completion of the outage. The reactor was made critical and power was subsequently increased in a stepwise fashion to 100% power in accordance with the startup test program. B. Operating Data A brief summary of the nuclear and electrical operating data for the first half of 1972 is presented below. A more detailed summary, on a monthly basis, is provided in Table II-A and Figures II-A through II-F. A list of all reactor scrams and shutdowns, and their causes, is provided in Table II-B. The unit down time following these shut-downs is also included. Gross Thermal Generation 158,492.5 MWDt Gross Electrical Generation 1,232,302.0 MWHe Net Electrical Generation 1,161,839.0 MWHe Number of Criticals 12 Number of Scrams from critical 10 Hours Generator operated 2192.0 hours C. Maintenance A tabular summary of maintenance on systems and components designed to prevent or mitigate consequences of nuclear accidents is set forth in Table II-C. D. Facility Changes Pursuant to the reporting requirements of paragraph 50.59 (b) of 10 CFR Part 50, a brief description of facility changes made during the first half of 1972 without prior commission approval follows:

1 I

1) Reactor Building Door Interlock By-Pass Switch r

A weatherproof type door interlock by-pass switch was installed outside door #75 (on turbine building roof side) and wired in series with the existing by-pass switches. This bypass switch will prevent personnel from being trapped on the turbine building roof if the door interlock malfunctions. This change does not involve any safety related components or equipment.

2) Feedwater Control Valve Air Accumulator The feedwater control valves have had larger air lines and air accumulators installed to increase the air supply and thereby eliminate spurious low pressure lock-up of the valves.

With the present settings, no air pressure problems have been experienced. This modification presents no safety problems that have not been reviewed. 3), HPCI Turbine Stop Valve Position Indication The HPCI turbine stop valve not reset and control valve full closed condition is now observable from the main control room on panel 902-3. An indicating light was installed with appro-priate markings in order to inform operations when a HPCI turbine may be initiated. This change does not involve an unreviewed question since it does not degrade the HPCI system but does provide the operator with additional information regarding system operability.

4) Fire Protection For T.C. Bearing #10 and Exciter The outboard turbine generator bearing #10 and exciter are now protected against fire by the Cardox Fire Protection System.

To insure proper pressurization of the concerned bearing area, metal cover plates were attached to the floor opening around the outboard portion of the bearing to eliminate any escape route for the CO. This modification presents no safety problems that 2 have not been reviewed.

5) CRD Drain Vacuum Valve The scram discharge volume was developing a partial vacuum in the line while being drained down af ter a scram. This problem resulted in allowing trapped water in the line to run back into i

the scran discharge volume and reinitiate the high level alarm. The vacutm relief valves were installed treediately down stream of the C!tD vent valves; they are spring loaded, carbon steel, ball check valves which are normally closed and operate only in the event of vacuum build-up in the line. The valves and piping are in the low pressure portion of the system and are of the same quality and material specifications as the existing equipment.

( Installation of this hardware does not compromise system operation or constitute an unreviewed safety item.

6) Corrosion Test Loop Valves Necessary wiring changes were made to provide an interlock to corrosion test loop valves 5001-1,2,3, & 4 that will close the valves or prevent their opening when there is a group 3 isolation signal present. This change does not involve safety related components or equipment.

7) Automatic Reactor Feed Pump Trip In order to provide safeguards against overfilling of the reactor vessel, the necessary logic was installed to auto-matica11y trip the reactor feed pumps when a high water level in the reactor occurs. This function is a 2 out of 2 logic circuit.

A RFP trip " override" switch will be provided. I This change does not involve safety related components or equipment.

8) Refueling With Cadolinia Bearing Fuel The replacement fuel used consisted of 509 DN type pasemblies containing 2 gadolinia rods per assembly.

A detailed description, analyses and safety evaluation is pre-sented in References 1 and 2. l Following reconstitution of the core, shutdown margin tests were satisfactorily conducted as required by the Technical Specifica-tions. m l ) i

TABi.C II A Dresden Unit 2 Operating St.a.ary - 1972 llours-Core Cross Uct ilours Generator Themal Electric Electric Number Duration of Critical On-Line-Pouar Power Pouer of Scrams Number of Downtime 1tonth 11rn: Min lirs: Min IMDt IMI!n 13111e & Shutdowns Times critical Hrs: Min ~ Jnnuary 744:00 744:00 49,258.5 380,968.0 361,560.0 0 0 0 Fabruary 438:15 436:20 28,907.9 219,691.0 206,037.0 1 1 257:45 March 0:00 0:00 0.0 42.0 -4,150.0 0 0 744:00 April 0:00 0:00 0.0 25.0 -2,250.0 0 0 719:00 May 489:42 438:17 27,560.2 212,955.0 200,552.0 6 6 254:18 Junn 609:04-573:21 52,765.9 418,621.0 400,090.0 5 5 110:56 Totals 2281:01 2191:58 158,492.5 1,232,302.0 1,161,839.0 12 12 2085:59 9 e a w sp a it.-

s. ..) TAB TI-B Critical Subcritical i Date Tice Date Tima Scram Down Time Reason for Shutdown { Second refueling outage. 2/19 0515 No l 257 hrs.45 min. l 2/24 0600 2/24 0700 No Shutdown margin checks, second refueling outage. 1677 hrs.04 min. Trouble with control rod insert / withdraw switch. 5/09 2204 5/09 2305 No 2 hrs.10 min. 5/10 0115 5/10 1916 Yes Reactor scram from IRM Hi Hi signal - trouble shooting EHC system opened and closed bypass 1 hra.29 min. valves. 5/10 2045 5/18 2200 Yes Turbine trip from 75% power. (Startup Testing) 32 hrs.48 min. 5/20 0648 5/23 0933 Yes Group I isolation resulting from trouble 3 hrs.47 min. shooting #3 control valve. 5/23 1320 6/12 1035 No Condenser tube leak. 41 hrs.30 min. 6/16 0405 6/16 1051 Yes Spurious turbine tr ip. 9 hrs.57 min. 6/22 0958 6/22 1615 No Reactor scram - Low EHC oil pressure senests at the turbine control valves caused the" load reject' . relays to operate - EHC oil pressure oscillation 9 hrs.43 min. during turbine surveillance. 6/23 0455 6/25 0941 Yes Steam leak in X-area. 12 hrs.40 min. Reactor scram from Group I isolation. Broken 6/26 2247 fitting on test pilot bled the air off the valve 37 hrs.06 min, operator causing 1B MSIV to close. TOTAL DOWNTIME 2085 hrs.59 min.

TABLE II-C DRESDEN UNIT #2 PAINTE';ANCE

SUMMARY

1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Opera tion Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completto: Dac:mbar 27/71 Electrical 250 volt bat-Corrective A bad diode and Charger inop-Replaced diode and None-other 16 hr. tery charger. resistor in

etable, resistor with new charger charger.

ones. remained operable. January 3 Pric:ary Electromatic Corrective Control switch Valve would Switch replaced Nona-still 16 hr. 203-3C malfunction not operate had manual in auto and auto blwdown capability. 6 Electrical 2B recire. Preventative Brushes on MG None Replaced the None 4 hr. pump MG set, set shorted. brushes. 13 Electrical 2/3 diesel Preventative None None Routine Inspection None 18 hr. generator 18 Electrical 2 diesel Preventative None None Routine Inspection None 5 hr. generator February 28 Containment Reactor vessel Corrective Manufacturing Failed ultra-Replaced with new None 10 hr. head nut #25 defect sonic test. nut. March 2 Electrical 2 diesel Corrective Lower air motor Diesel vould Lower air motor Mone-unit in 16 hr. generator had bad rear not start was replaced, cold shutdown bearings. in automatic. 8

P 2 TABLE II-C (cont'd) DRESDEN UNIT #2 NAllTTENANCE SU12tARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude wpera tion Time For Month System Component Maintenance Malfunction }!al funct ion Recurrence Of Reactors Completion March 4 Containment Torus vacuum Corrective Bushings of Several valves Bushings were None 200 hr. breaker check valves were were stiff and removed, cleaned valves. dirty. would net ope r-and machined where ate freelv, needed. 6 Emergency LPCI valve Corrective Improper post-Position indi-Position switch None 48 hr. Core 1501-25B tion switch cation incor-reset. Cooling indicating setting. rect. light. 6 Primary MSIV 203-1B Corrective Closed Position Improper pos-Repaired switch None 16 hr. limit switch ition indi-cation. 6 Containment Condenser off Corrective Valve would Valves would Disassembled valve None-unit 32 hr. gas valves sometimes over-not close. operator and in-in cold 5401-A&B travel in open stalled a slug in shutdown position and open direction bind. (shortened open stroke by 1"). 15 Reactor Rod block Corrective Bad proportion-Gave rod Proportional None-failure 5 hr. Protection monitor #8 al amplifier in blocks amplifier was in safe System driver card. replaced;RBM direction. recalibrated. 15 Reactor APRM Corrective Drilling by Spurious trip Investigation-Bone 1 br. Protection Channel #6 electrical gave a half no instrumentatices System contractors in scram. problem could be a nearby panel. identified. O g g

m TABLE IT-C (cont'd) DRESDEN UNIT #2 MAllTTENANCE SUtMARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion March 22 Control Rod Accumulators Corrective Inside of accu-Accumulators Accumulators were None 32 hr. Drives 30-03&22-31 mulators were leaked by and replaced pitted and rough would not hold charge. 22 Control Rod Scram valve Corrective Teflon seat Valve leaked Valve was removed None 8 hr. Drives for 22-31 was bad, through causing and a new seat drive to drift. installed. 23 Control Rod 2B CRD pump Corrective Bushings worn, Pump was pull-A new rotating ele-None 200 hr. Drives casing rings ing high amps ment was installed worn, & impel- & running hot. with new style bush-1er wearing ings and bearings. rings worn. 23 Emergency Core spray Corrective Zero drift Gave indica-Rezeroed the indi-None 3 br. Core flow meter. on meter. tion with no cator and checked Cooling flow on calibration of the system. meter with its trans-mitter. ~ 26 Electrical

1. 2-250 volt Corrective Bad diodes Charger would Replaced bad diodes None 12 hr.

battery not charge. charger. 27 Electrical

1. 2/3-250 volt corrective Bad diode Charger would Replaced bad diode None 16 br.

battery charger not charge. 28 Primary Pilots & sol-Preventativo None None Cleaned pilo't pis-Hone 32 hr. enoids on MSIV ton and pilot sleeve. 203-1D.

k TABLE IT-C (cont'd) DRESDEN UNIT #2 UAINTENANCE

SUMMARY

1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Co:nponent Maintenance Malfunction Nalfunction Recurrence Of Reactors Completion March 28 Primary Pilots & sol-Preventative None None Cleaned pil't.pis-None 32 hr. o enoids on MSIV ton and piston 203-2A. sleeve. Replaced core assembly, disc holders & gaskets. 28 Primary I"'nts & sol-Preventative None None Replaced core assen-None 32 hr. e. . Ads on MSIV bly, disc holders & 203-2B. gaskets. 4 28 Primary Pilots & sol-Preventative None None Cleaned pilot piston None 32 hr. enoids on MSIV & sleeve. Replaced 203-2C. core assembly, disc holders & gaskets. 28 Primary Pilots & sol-Preventative None None Cleaned pilot piston.None 32 hr. enoids on MSIV Replaced core assen-203-2D bly, disc holder & gaskets. 31 Emergency LPCI valve Corrective Improperly Valve stays Replaced time delay Mone 6 hr. Core MO-1501-21A set time delay open too long. relay. Cooling relay. April 4 Primary Pilot & sol-Preventative None None Cleaned piston None 32 hr. enoids on MSIV sleeve. Repaired 207' limit switch. ) i 4 's iI

k TABLE II-C (cont'd) DRESDEN UNIT 42 tiAINTEMANCE SUl?tARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time Fo. Month Systen Component Maintenance }!alfunction Malfunction Recurrence Of Reactors Completion April 4 Primary Pilot & sol-Preventative None None Cleaned piston & None 32 hr. enoid on MSIV piston sleeve. 203-1B. Replaced core assembly, disc holders & gaskets. 7 Primary Pilot & sol-Preventative None None Cleaned pilot pis-None 32 hr. enoid on MSIV ton. Replaced core 203-1A assembly, disc holders & gaskeis. 10 Control Rod Accumulator Corrective Pressure in Pressure The gauge was re-None 2 hr. Drive. 946-19 pres-accumulator was indication of calibrated and the sure gauge. zero. Accumu-zero on gauge, accumulator recharged. lator was not charged. 11 E.mergency LPCI service Corrective Improper cali-Incorrect Recalibrated all None 7 hr. Core water dp bration of dp indication four dp transmitters. Cooling indication. instrument. on meter. 12 Electrical 2 diesel Preventative None None Routine Inspection None 16 hr. generator.. 18 Containment Vent valve Corrective Rubber seat Allowed leakage. Cleaned parts. None-sech-80 hr. 1601-20B cracked & torn. Replaced valve anical valve with rebuilt 'from in series factory. Replaced was operable, gaskets. b g g g

TABLE II-C (cont'd) DRESDEN UNIT #2 MAINTENANCE SU}S'.ARY 1972 Effect Action Taken To On Safe Type Of uuse Of Effect Of Preclude Operation Time For Month System component }!a int enance }!al funct ion }!alfunction Recurrence Of Reactors Completion April 20 Primary Electromatic Preventative None None Cleaned & lapped None 16 br. relief 203-3A seat. Cleaned parts. pilot valve. Peplaced gaskets. 20 Primary Electromatic Preventa tive None None Cleaned & lapped None 24 hr. relief 203-2B seat. Cleaned pilot valve. parts. Replaced gaskets. 20 Primary Electromatic Preventative None None Cleaned & lapped None 32 hr. relief 203-2C seat. Cleaned pilot valve, parts. Replaced gaskets. 20 Primary Electromatic Preventative None None Cleaned & lapped None 16 hr. relief 203-2D seat. Cleaned pilot valve. parts. Replaced gaskets. 20 Primary Electromatic Preventa tive None None Cleaned & lapped None 24 hr. relief 203-2E seat. Cleaned pilot valve, parts. Replaced gaskets. 21 Containment Vent valve Corrective Rubber seat Allowed Cleaned parts. Would have 80 hr. 1601-56 cracked & torn. leakage. Replaced valve permitted with one from some leakass Quad Cities Sta-to the second-tion. Replaced ary containment gaskets. in the event of an accident. i

TAELE II-C (cont'd) DRESDEN UNIT #2 MAIhTENANCE SUM!tARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month Sys rera Component Maintenance ralfunction Malfunction Recurrence Of Reactors Completion April 21 Containment Vent valve Corrective Rubber seat Allowed Cleaned parta. Would have 80 hr. 1601-22 cracked & torn. leakage. Replaced valve with permitted rebuilt from fact-some leakage ory. Replaced to the second-gaskets. ary containment in the even't of an accident. 21 Containment Vent valve Corrective Rubber sePL Allowed Cicaned parta. Would have 80 hr. 1601-21 cracked & torn. leakage. Replaced valve with permitted rebuilt from fact-some leakage cry. Replaced to the second-gaskets. ary containment in the event of an accident. 23 Emergency LPCI valve Corrective Limit switch Valve would Cleaned limit None 8 hr. Core MO-1501-20A found open not open. switch. Cooling 33 Primary Safety valve Preventa tive None None Replaced valve with Mone 80 hr. 203-4A rebuilt. Cleaned & replaced gaskets. 23 Primary Safety valve Corrective Ruptured dia-None Cleaned & replaced None 16 hr. 203-4B phragm ruptured diaphragm. 25 Emergency 11PCI valve Corrective Dirty contact Valve failed Cleaned contacta leone 6 hr. Core 2-2301-4 to open. Cooling s iv

} TABLE II-C (cont'd) DRESDEN UNIT 42 MAINTEMANCE SU17!ARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Opera tion Time For Month Sysrca Component Maintenance lialfunction 1:alfunction Recurrence Of Reactors Completion April 23 Prinary Safety valve Preventative None None Replaced valve with None 80 hr. 203-4C. rebuilt. Cleaned and replaced gaskets. 23 Primary Safety valve Corrective Ruptured dia-None Cleaned & replaced None 16 hr. 203-4E phragm. rup,tured diaphrag:n. 23 Primary Safety valve Preventative None None Replaced valve with None 80 hr. 203-4F rebuilt. Cleaned and replaced gaskets. 23 Primary Safety valve Preventative None None Replaced valve with None 80 hr. 203-4H rebuilt. Cleaned and replaced gaskets. 25 Emergency LPCI valve Corrective Worm gear in Valve would Replaced worn parts None 32 hr. 4 Core MO-1501-13A operator worn not operate for worm gears. Cooling out. 25 Standby Emergency Preventative None None Test and Inspection Mone 48 hr. Liquid Explosion Control Valves May 2 Emergency HPCI turbine Corrective Loose wire to Tu'rbine would Loose wire recon-None 12 hr. Core turbine reset not reset. nected. Cooling solenoid. 1 Containment "C" TIP machine Corrective Insufficient Valve would Increased sp' ring Mone 24 hr. ball valve, spring tension not close tension on valve. on valve. h

table TI-C (cont'd) DRESDEN UNIT C2 NAILTERWCE SmMARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For i Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completio May 6 Reactor IRM Cha.#14 Corrective Zener diode False reading Zener diode CR-3 None 8 br. Protection in calibrate on the IRM was replaced. System and logic unit failed. 6 Reactor IRM Cha.#11 Corrective Loose input False readings Loose input cable None 2 hr. Protection cable connection on recorder was tightened. f.ystem and meter. 6 Control Rod CRD module Corrective Inutnal damage Unable to Repaired conduit None 18 hr. Drive 46-15 to nitrogen . charge box and nitrogen valve 177 and accumulator valve. damage to con-duit box. 6 Primary Pilot and sol-Corrective Pilot valve Air leaking Removed and cleaned None 16 hr. enoid for MSIV solenoid leak-out of exhaust internals of solenoid. 2-203-2D ing air out port. Replaced copper tubing. exhaust port. 6 Isolation Isolation Corrective Packing no Valve packing Repacked valve and None 16 hr. Condenser condenser good. leak. lubricated stem. valve 1301-14 9 Standby Explosive Preventative Mona None Test and Inspection Mons 40 hr. Liquid valves. Control. l h

TABLE TI-C (cont'd) DRESDEN UNIT fi2 MAINTEMANCE

SUMMARY

1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For ionth System Corr.ponent Maintenance m it'inction Malfunction Recurrence Of Reactors Completion MY 9 Containrent valve 220-62B Corrective Improper seat Would not hold Changed val'e Remote poss-300 hr. v to dise fit. for air test. trim, machined ibility of seal ring, leakaga to cleaned parts, secondary containment in avant of an accident. 9 Conta inment valve 220-58B Corrective Improper seat Would not hold Lapped disc to seat, Remote poss-150 hr. to disc fit. for air test. lapped seal ring, ibility of cleaned parts. leakage to accondary contairmaant in event of an medident. 9 Primary Valves 202-Preventative None None Reinforced bonnet None 80 hr. 6A&6B leak off lines. 12 Electrical

1. 2 diesel Preventative None None Routine Inspection None 16 hr.

generator 16 Standby B Squib Valve Corrective Light bulb out False Replaced bulb. None 6 hr. Liquid in B Squib annunciation. Control alarm. None 8 hr. fill con-Required fre-Replaced N2 17 Control Rod Accumulator Corrective N2 Drive 46-19 nection leaking quent charging. connection.

=

9 6 ]c 6 4

= - =.- TABLE TT-C (cont'd) DRESDEN UNIT #2 UAINTENANCE SU! NARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Opera tion Time For Month Systect Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion May 19 Containment Drywell outer Corrective Door hard to Mone Cleaned and lubri-None-inner 8 br. door on per-operate. cated door parts, door. leak-sonnel lock. adjusted anotor and tight. micro switch. 19 Standby A&B standby Corrective Pump cover Slight leakage.' Cleaned covers and Mona 8 hr. Liquid liquid control gaskets leaking Pumping capac-replaced 4 cover Control

pumps, ity atill gaskets.

within Speca. 9 19 Isolation Isolation Corrective Bad packing Packing leak Repacked valve, Mons 16 hr. Condenser Condenser replaced gland valve 1301-44 studs and nuts. 19 Isolation Isolation Preventative None None Tighten packing Mons 4 hr. Condenser Condenser valve 1301-15 19 Emergency HPCI steam Corrective Deteriorated Steam leak Removed and cleaned Nons 8 hr. Core line drain bonnet gasket steam trap, installed Cooling

pot, new bonnat gasket.

19 Emergency EPCI testabis Corrective Bad'paciting Packing leak Rapacked with new mone 32 hr. ~ Core check 2301-7 packing, replaced cooling flexitalic Baskat. l 19 Control Rod Acetumulator Corrective leaking fit-Accumulator E2 Tighten up on thraa Eons 15 br. Drive 46-19 tings charge bleads fittings on H2 *Id** down about once par shift. e I g

I \\ TABLE IT-C(cont'd) DRESDEN UNIT #2 NAINTENANCE

SUMMARY

1972 Effect "' Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time F - tonth System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion lay 19 Containment 2B torus purge Corrective Burned out No indication Replaced light None 4 hr. fan breakar. light bulbs for indication. 20 Secondary Interlock doors Corrective Door operator Door would not Installed new type Mona 64 hr. Containment 517' level-failure. open. door operator. north door. 22 Emergency LPCI valve Modifica tion None None-Installed new Rone 32 hr. Core 1501-21 worm gear and Cooling motor. 24 Emergency HPCI turbine Correction Limit switebes Turning gear Adjusted limit Nome 8 hr. Core turning gear out of adjust-position indi-switches. Cooling indicating ment. cating lights lights. not working. 26 Control CRD module Corrective Damaged bonnet Valva leak Replaced packing, None 8 hr. Rod Drive 30-11, valve disc, "O" rings and 302-111 remachined bonnat. s.: ', June 1 Control Accumulator Corrective Broken "O" Frequent High Installed new "O" Bons 16 hr. Rod Drive 46-07 rings. water alarms. rings and teflor. tings. e .. r. 1 Isolation Isolation Modification lione None Installed new worm lione. t 16 hr. Condenser condenser gear and motor.

• • /',

valve 1301-10 \\ 6 5, e 4.. le .ll 'J s

I ( m TABLE TI-C (cont'd) DRESDEN UNIT #2 UAINTENANCE

SUMMARY

1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Opera tion Time For Month System Component Ibintenance Malfunction Malfunction Recurrence Of Reactors Completion Jun2 1 Emergency LPCI valve Modification None None Installed new None 16 hr. Cora 1501-19B wona gear and Cooling motor. 1 Emergency LPCI valve Modification None None Installed new None 16 hr. Core 1501-19A worm gear and Cooling motor. 1 Emergency LPCI valve Modification None None Installed new None 16 hr. Core 1501-13B worm gear and Cooling motor. 1 Emergency LPCI valve Modification None None Installed new Bone 16 hr. Core 1501-13A woon gear and Cooling motor. 6 Electrical

1. 2/3 diesel Preventative None None Routine Inspection None 16 hr.

generator 12 Electrical

1. 2 diesel Preventative None None Routine Inspection None 8 hr.

generator 13 Reactor Recirc. flow Corrective Flow mismatch APRM-flow Flow transmitter Eone 8 hr. Protection transmitter due to zero bias scram was replaced with System dPT-2-261-6C drift in trans-setpoint spara transmitter. mitter. drifted low. O 's I s' ; e

j TABLE II-C (cont'd) DRESDEN UNIT #2 MAINTENANCE SUINRY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion Jun2 13 Reactor Pressure Corrective Sensing line Leakage Removed damaged None-Reactor 36 hr. Protection switch 261-was damaged. line from system in cold System 30-C test and replaced with shutdoun. line. new line. 14 Containment NSIV 203-1B Correct ive Failed test Valve went New test solenoid None 10 hr.

solenoid, fully closed was installed, and then re-opened auto-matically during test.

14 Emergency HPCI high Corrective Bad gasket Steam leak Replaced with None 6 hr. Core pressure new gasket. Cooling steam trap. 19 Control Rod D-13 rod Corrective Dirty switch. Boa would not Cleaned button Nona 6 hr. Rot. Drive selector move from pos-contacts with matrix button. ition 46 to spray cleaner, position 48. 25 Primary MSIV 203-1B Corrective Broken nipple Air leak, valve Repaired broken llona 16 hr. on pilot, test closure, and nipple, cleaned pilot sticking. reactor scram. test pilot assembly. 26 Containment Clean up sys-Corrective Loose packing. Packing leak. Tighten packing. Rons 2 ' hr. tem valve 1201-1. 26 Containment Shutdown cool-Corrective Loose packing. Packing leak. Tighten packing. Ilone 1 hr. ing valva 1001-lA. f', y

TABLE II-C (cont'd) DRESDEN UNIT 621%INTENANCE

SUMMARY

1972 Effect' Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion -Jun) 26 Containment Shutdown cool-Corrective Loose packing. Packing leak. Tighten packing. Nona 2 hr. ing valve 1001-1B. 26 Containment shutdown cool-Corrective Improper torque Valve would Changed torque None 8 hr. ing valve switch settings. not open. avitch' settings. 1001-1B. 27 Containment Steam drain Corrective Breaker over-Valve motor Reset overload, Mona 8 hr. isolation load was trip-would not extended reset valve 220-2 ped, reset operate. button. button to short to function. 27 Emergency HPCI valve Corrective Interlock 2301-4 would Removed jumper Nona 8 hr. Core MO-2301-4 between 2301-open even Cooling 4 & 2301-5 through 2301-5 was jumpered, was shut. t i E i I I ( O

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v DRESDEN NUCLEAR POWER STATION SEMI-ANNUAL REPORT JANUARY 1. 1972 IMROUGH JUNE 30. 1972 SECTION III: DRESDEN UNIT #3 OPERATIONS AND NAINTENANCE III, IDCIT #3 A. Introduction Dresden Nuclear Power Station Unit #3 operated the entire reporting period base loaded at 800 MWe. The unit did, however, operata at varying power levels when dictated by system requirements, equipa ment operation, and routine testing. B. Operating Data A brief summary of the nuclear and electrical operating data for the first half of 1972 is presented below. A more detailed summary, on a monthly basis, is provided in Table III-A and Figures III-A through III-F. A listing of all reactor scrams and shutdowns, and their causes, is provided in Table III-B. Unit down time following these phutdayne is also included. Gross thermal generation 297,679.5 NWDe Gross electrical generation 2,494,955.0 MWe Net electrical generation 2,388,372.0 MWe Number of Criticals 14 Number of Scrams from Critical 4 Hours generator operated 3574.8 hours C. Maintenance A tabular summary of maintenance on systems and components designed to prevent or mitiate the consequences of nuclear accidents is set forth in Table III-C. D. Facility Changes Pursuant to the reporting requirements of paragraph 50.59 (b) of 10CFR Part 50, a brief description of facility changes made during the first half of 1972 without prior cammission approval follows: 1. Reactor Building Door Interlock By-pass Switch: Described in Section II.D.1 of this report. 2. Feedwater Control valve Air Accumulator: Described in Saction II.D.2 of this report. lD 'l D ~WV D "k A\\ Ju" 5. JC * = i e

9 3, EPCI Turbine Stop Valve Position Indication: Described in Section II.D.3 of this report. a 4. Fire Protection Por T.G. Bearina #10 and Exciter: Described in Section II.D.4 of this report. 9 O 9 9 1 * / l ~ Q

r. n. t TABLE 3II A Dresden Unit 3_Operatina Susssary - 1972 Hours Core Cross Net Number Hours Generator Thermal Electric Electric of Scrams Duration of Critical On-Line Power Power Power and Number of Downtiza Month Rrs: Min. Hrs: Min. HWDt MWHe NWHe Shutdowns Times Critical Mrs: Min. Jcr.uary 598:14 562:05 42,672.4 362,331.0 345,729.0 4 4 145:46 Fabruary 645:29 579:57 46,612.3 390,903.0 373,723.0 1 1 50:31 s March 744:00 719:56 64,378.0 540,406.0 $19,133.0 0 0 0:00 April 491:45 482:49 41,545.9 347,433.0 332,065.0 1 1 227:15 May 644i26 622:01 53,481.6 444,818.0 426,121.0 1 1 99:34 June 649:24 608:00 48,989.3 409.064.0 391.601.0 4 4 70:36 3,773:18 3,574:48 297,679.5 2;494,955.0 2,388,372.0 11 11 593:42 l l I

Tablo III-3 Critical Suberitical Reason for Shutdown Date Time Date Time Scram Down Time The reactor was shutdown due to a leak. 1/1 0640 on the isolation condenser vent line to 14 hrs. 5 min. the main steam line. Reactor scram as a result of APRM Hi Hi 1/1 2045 1/14 2139 flux following a power increase due to 49 hrs. 6 min. a rapid increase in 3A recire. pump flow. Reactor scram as a result of low water 1/L6 2245 1/21 1245 level. The low water level occurred following the loss of the essential servica }c set, which caused the feedwater regu-63 hrs.27 min. lating valves to lockup. Reactor was shutdown to repair standby 1/24 0412 1/24 0423 19 hrs. 8 min. liquid control manual valva. Reactor was shutdown to repair valve 1/24 2331 2/11 0523 packing leaks in the drywell. The two valves which were leaking were the cleanup Isolation valve MD-3-1201-1, and the 3B recire. pump discharge bypass 50 hrs.31 min, valve 3-202-73. Reactor was shutdowc to repair a main 2/13 0754 4/14 1025 227 hrs.15 min. condenser tube leak. 4/23 2140 5/4 0901 Spurious reactor scram. The reactor remained shutdown to repair insulation 99 hrs.34 min. and replace the safety valve that lifted. The reactor was shut down to repair a 5/8 1235 6/1 '0908 high temperature condition in the main 12 hrs. 2 min. transformer isolated phase bus ducts. The reactor was shut down to complete 6/1 2110 6/10 0210 transformer repairs and add oil to 29 hrs.45 min. "B" recircul'ation pump. I I

l 1 1 l Tablo III-D (cont'd) l Critical Suberitical l Dato Tine Date Time Scram Down Time Reason for Shutdown Reactor scram as a result of low stam= i 6/11 0755 6/24 1055 line pressure. The servo motor on #2 turbine control valve failed causing the control valve to go open. When load'was dropped, the low steam line pressure isolation 24 hrs.52 min. occurred. Reactor scram due to turbine-trip on load 6/25 1147 6/26 0033 reject due to high high level on 3C 3 hrs.57 min. moisture separator tank. 6/26 0430 TOTAL DOWN TIME 593 hrs. 42 min.

1. TABLE III-C DRESDEN UNIT #3 l'.AI1rrEMANCE SUINARY 1972.. Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For 11on th System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion J nuary ? 2 Electrical 250 volt Emergency Failed resis-Chargur Replaced failed None - Unit 10 br. battery tor and diode tripping out resistor and diode shutdomma 'ger 7 Standby oystem Preventative None Nona Tighten valva Nona 16 hr. Liquid valves packing Control 11 ECCS LPCI valve Corrective Untalanced Valve would Ballanced poten-None 36 br. 3-1501-3A potentiometer not open tiometer. 14 Electricat Diesci Preventative None None 31onthly inspection None 36 br. generator 26 Electrical Battery Preventative None None Replaced dioda Mone 32 hr. charger February 11 Containment Equipment Corrective Relay 2253-411 A0-2001 Cleaned valve and None 100 hr. drain semp open coil still vould not replaced coil. recircula-DOS. open. tion valve AO-2001-4, t 22 ECCS NPCI low Corrective Design error HP'CI pumqp switch wired None 20 be. suction would properly and pressore have tripped prints changed. trip switch at 30 psig PS-3-2360. vice 9.4" Ng

TABLE III-C { cont'd) DRESDEN UNIT #31 AINTEMANCE SU12tARY 1972 Effect Action Taken To On Safe Type Of Cause of Ef fect Of Preclude Operation Time For <onth Systen Cmnponent Maintenance Halfunction Malfunction Recurrence Of Reactors Completion March 1 Standby Injection Preventative None None Repieced packing None 48 hr. Liquid pumps in pump i Control ' 15 Primary Main steam Preventative None None Repacked valves mone 40 hr. System line drain s valves 3-220-3, 3-220-4. 29 Primary Main steam Corrective Minadjusted Relay 590-Adjust limit None 15 hr. System isolation Lizait switch. ,102C failed switch. valve limit to energiza switch 3-203-113 29 ECCS LPCI system Corrective Square root False indica-Calibrate square Nona 6 hr. III flow converter out tion of flow root converter indicator of calibration 30 ECCS LPCI cooling Corrective Flow gage out Cage indica-Flow gage calibra-None 4 br. water of calibration ted no flow. ted and snubber and snubber cleaned. clogged. 30 Monitor-Radwaste to Corrective Transmitter Flow reading Calibrate flow None 6 hr. ing system river hi flow, output high high transmitter 31 Reactor I.PRM panel Corrective Indiestor No indication Replace bulbs Eone 4 hr. Protection display bulbs burned on dispisy System out.

r. TAP.LE III-C(cont'd) DRESDEN UNIT #3 MAINTEW.NCE SU121ARY 1972 Effect Action Tahen To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion April 16 Containment Torus to Prerentative None None Clean and lubricate None 16 hr. System drywell bushings. vacuum breaker 3-1601-32E 16 Conta inment Torus to Corrective Bushing thrust Valve would Nachine thrust face None 16 hr. System drywell face binding not operate to design tolerance. vacuum breaker freely. 3-1601-32F 16 Containment Torus to Corrective Bushing binding._ Valve would Machine bushing Mona 16 br. System drywell on shaft. not oparate to design tolerance, vacuum breaker freely. 3-1601-32C 16 Containment Torus to Corrective Bushing binding Valve would Machine bushing Mone 16 br. System drywell on shaft, not operata to design tolerance vacuum breaker freely. 3-1601-33C 16 Containment Torus to Preventative None None Clean and lubricate None 12 hr. System drywell bushings. vacuum breaker 3-1601-32D 16 Contaitument Torna to Traventative None Bone Clean and lubricate Mone 12 br. System drywell bushings. vacuum breaker 3-1601-33A J

e, f. k TABLE TII-C (cont'd) DRESDEN U!!IT U3 1*.AI?.'r2?'A?!CS ST2%In' 1972 Effect Act ion Taken To Du Safe Type Of Cause Of Ef fect Of Preclude Cperation Ti=c For Month Systen Component !bintenar.cc l'.a l func t ion ?!al funct ion Pecurrence Of Reactors Coepletica April 10 Reactor Group.I "B" Corrective i 15 volt Group 1 "B" i 15 volt regula-None 2 hr. Protection level LPRM's regulator out-level LPRM's replaced. System put high read down-scale. 13 Electrical Diesel Preventative None None Monthly inspec-None 32 br. tion. generator 15 Contain-Torus to Corrective Bushing thrust Valve would Nachine thrust None 16 hr. ment d-fwell face binding not operato face to design ireely. tolerance. System ,cuum breaker 3-1601-33B a 15 Contain-Torus to Corrective Bushing bind-Valve would Machine bushing None 16 hr. ment Sys-drywell ing on shaft. not operate to design toler-tem. vacuum

freely, ance.

breaker 3-1601-33D 15 Contain-Torus to Correctim Bushing bind-Valve would Yachine Bushing None 16 he ment drywell ing on shaft. not operate to design System vacuum freely. tolerance. i breaker 3-1601-32B 15 Contain-Torus to Corrective Dushing bind-Talve vould Nachine Bushing None 16 hr. ment drywell ing on shaft. not operate to design System vacuum breaker

Yreely, tolerance.

3-1601-32A. e m m

r e t t TAELE III-C (cont'd) DRESDEN UNIT #311AINTENANCE SU}2tARY 1972_ 9 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion April None 12 hr. 16 Containment Torus to Preventative None None clean and lubricata System drywell bushings. vacuum breaker 3-1601-33E 16 Containment Torus to Preventative None None Clean and lubricate None 12 hr. System drywell bushings. vacuum breaker 3-1601-3 3F 16 Rod Position Rod position Corrective Defective micro No indication Replace defective None 4 hr. Indication indicator switches in for positions probe. System for control probe. 08-18-28-38. rod F-7. 17 Reactor LPRM 24-57D Corrective Dirty cable LPRM reading Clean connector None 6 hr. Protection connector full scale System 18 ECCS HPCI drain Corrective Diaphragm in Valve would Replace diaphragm None 16 hr. bypass A.D. air operator still operate 3-2301-28

leaking, properly.

18 Primary 203-4E safety Corrective Rupture dise None Replaca ruptura Hone 16 hr. System valve rupture ruptured disc. disc. 19 Reactor TRM f17 Corrective Open cable IRM 917 rea8-IRN 917 connected None 31 hr. Protection at penetration ing downscale to spara TRM ' ahle c at penetration. System l ~ -m m

r. I TABLE III-C (cont'd) i DRESDEN UNIT #3 MAILTSNANCE SUTARY 1972 3 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion 1 April 23 Primary 3-202-4B Corrective Cate frozen in valve would valve disassembled None, Reactor 350 hr. Systen suction valve valve seat. not open. and cleaned. Changed was in shut-torque settings on down. valve operator. 25 Standby Low tempera-Corrective Switch cali-Low tempera-Temperature switch None 6 br. Liquid ture switch bration drift. ture alarm recalibrated to Control TS 1149 would not specified setpoint clear. of 760F. 26 Control' Rod Scram valve Corrective Valve leaking. Control Rod Adjusted stem down None 16 hr. Drive System on control through. C-7 would not one half of a turn. rod C-7 hold position. M*1 1 Reactor LPRM 40 f9A Corrective Defective LPRM High indica-Replace defective None 2 hr. Protection module. ting light on LPRM module. System panel 903-3 illuminated but no high light on panel 903-37. 4 Reactor RBM channel 8 Corrective RBM Channel 8 Intermittent Recalibrata RBM None 6 hr.~ Protection out of align-rod blocks. Channel 8 l System ment. 3 ECCS NPCI valve Corrective Valve packing 1 tone Itapact valva None ' 31 ht. 3-2301-3 leak. ,. ). ~

i r. t. TABLE III-C l I DRESDEN UNIT #2 NAINTENANCE SUfEARY 1972 l I Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Opera tion Time For lionth System Component Maintenance Malfunction Malfunction Recurrence Of Reactors Completion May 5 Primary 3-203-2A Corrective Defective micro No alarm in Clean and repair None 16 hr. System electromatic switch. control room micro switch. relief when valve was open. 6 Primary 3-203-4A Corrective Valve relieved Pressurifa Replaced valva Rone 200 hr. System safety valve below setpoint. drywell to with a spare 2.5 psig. valve. 6 Isolation Isolation Corrective Low torque Isolation Reset torque mone 32 br. Condenser condenser setting, no condenser and adjusted System valve 3-1301-3 contact vipe inoperable contact vipe. on N. C. contact in series with open contactor x 6 Containment Reactor clean-Corrective Valve packing None Repack valve Wone 80 hr. System up system leak. HO-3-1201-1 6 Containment Reactor clean-Corrective Crack in 3/4" None Crack velded in None 64 hr. System up system S.S. sch B0 accordance with valve 3-1291-2B pipe next to procedura CS-16

weld, and dye penetrant checked.

6 Primary Main steam Corrective Position indi-30 closed Replaced position Hone 32 ht. System isolation cation switch indleation indication switch valve 3-203-2A are bmt, arm. 4 m

t TABLE III-C (cont'd) DRESDEN UNIT #3 MAI':TENA!!CE SU12iARY 1972_ j Effect Action Taken To On Safe Type Of Cause Of Effect Of Proclude Opera tion Time For Month System Cmponent Ma intenance 1:al funct ion Malfunction Recurrence Of Reactors Completion May 7 Containment Torus to Corrective Bushing bind-Valve would Nachine bushing None 16 hr. System drywell ing on shaft. not operate to design tolerance. vacuum breaker freely. valve 3-1601-32F. 8 Reactor Reactor level Corrective Switches burn-High level Replaced defect-None, unit 3 hr.. Protec t ion scram Yarway ed open during isolstion ive switches. in shutdown. System switches _LIS-testing of the would not l 3-263-57B RPS relays, clear. LIS-3-263-58B 8 Primary Safety valve Corrective Rupture dise None Replace rupture None 16 hr. System 3-203-4F ruptured. disc. rupture disc. 8 Primary Safety valve Corrective Rupture disc None Replace ruptura None 16 hr. System 3-203-4B ruptured. disc. rupture disc. 8 Primary Safety valve Corrective Rupture disc None Replace rupture None 16 hr. System 3-203-4C

ruptured, disc.

rupture disc. 8 Reactor Relay 590-Corrective Wire discon-Low vacuum Replace wire Mone 1 hr. : Protection 10K nected from scram on I System

relay, channel "A" 11 Electrical Unit #3 Preventative None Rone Monthly inspection.

Mone 32 hr.I diesel Benerator I t l l

af s. J TABLE III-C (cont'd) DRESDEN UNIT #3 IIAIhT211ANCE SU121ARY 1972 Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month Systen Component Ita in t enance !!al function Malfunction Recurrence Of Reactors Completion May 15 ECCS Core spray Corrective Lov torque Valve would Adjust torque None 20 hr. valve MO setting, not close. setting. 1402-4A. 18 ECCS LPCI heat Corrective Vibration No indication Replaced pointer None 8 hr. exchanger and calibrated dif ferential

switch, pressure switch.

19 ECCS LPCI valve Corrective Wear in motor Valve would Installed new None: Valse 48 hr. 3-1501-19B

operator, not operate vorm and worm was opened

remotely, gear.

manually and remained in the open condition. 23 Primary Main steam Corrective Relay 595-112A Test switch Energized relay None 4 hr. System isolation de-energized, would not 595-112A. 1A,1B,1C,1D initiate the test. 107. closure test. 24 ECCS LPCI valve Corrective Loss of manual Valve could Replaced key

Nona 16 hr.

3-1501-38B handle. not be oper-stock and added atied manually. set screws. 24 ECCS HPCI turning Corrective Limit switches No indica-Adjusted limit None 16 hr. Bear indi-out of adjust-tion. switches. cating lights, ment.

)

a, i. TABLE ITT-C (cont'd) l DRESDEN UNIT 03 W.I?.'TENANCE SU!T.ARY 1972_ Effect Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month System Component !!a intenance 1:alfunction }!alfunction Recurrence Of Reactors Completion May 25 Reactor LPRM-32-49B Corrective Fission chamber LPRM Reading Fission chamber None 2 hr. Protection APRM ch.#1 not conducting. zero. shocked into conduction. June 1 ECCS LPCI valve Corrective Wear in motor None Replaced motor None 32 hr. 3-1501-19A operator vorm operator with and worm gear. modified worm and worm gear. 1 ECCS LPCI valve Corrective Wear in motor None Replaced motor Mone 32 hr. 3-1501-19B operator worm operator with and worm gear, modified worm and worm gear. 1 ECCS LPCI valve Corrective Wear in motor None Replaced motor None 32 hr. 3-1501-13A operator worm operator with and worm gear. modified worm and worm gear. 1 ECCS LPCI valve Corrective Wear in motor None Replaced motor Mone 32 hr. 3-1501-13B operator worm operator with and worm gear. modified worn and vorm gear. 1 Isolation Isolation Corrective Wear in motor Mone Replaced motor None 32 hr. Condenser Condenser operator worm operator with System valve 3-1301-10 and vorm gear. modified worm, and worm gear. =

e, e TABLE III-C (cont'd) DRESDEN UNIT #3 tiAIMTEMANCE SUl}1ARY 1972 Effee. Action Taken To On Safe Type Of Cause Of Effect Of Preclude Operation Time For Month Systen Component Maintenance 11alfunction 1:alfunction Recurrence Of Reactors Completion June Excessive air La}, ped heads and None 32 hr. 1 Containment Drywell air Corrective Increased 02 System compressor in drywell. in leakage. Installed new heads. gaskets. 2 ECCS HPCI turning Corrective Vibra tion Light on Adjusted limit unna 16 hr. gear disengage panel 903-3 switch. Light. inoperable. 5 Standby Sparging air Corrective Bolt missing Air leak Replace bolt None 8 hr. Liquid, regulator, from regulator Control 19 Electrical Diesel Preventative None None Yearly inspection None 300 hr. generator repair broken aux. relay arm. 23 Rod position Drive CS Corrective Defective No position Replaced defective None 6 hr. indicating No position relay (K1-display. relay. system display. 10-19) (

u r T/.I'll? III-C (cont'd) DRESDE?; U :IT ii3 FI.I:'TZ?:f."CE St'!rRY 1972 Effeet /.ction Taken To Cn Scfc Type O'. Ccuse Of Effect Of Preclude Cperation Tice For Month System Component Fainteance 1:a l funct ion !:a lfuac t ion Recurrence of neactors .Completto-Juna 27-Isolation Isolation Corrective Dirty contact No red light Clean contacts None 8 hr. Condenser condenser indication on Mystem fill valve valve control. 3-1301-10. 30

ECCS, 3-D LPCI Corrective Wear of Leaking Repack pump None 16 hr, containment

packing, packing.

cooling pump packing leak. i e I i s..

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