ML20027D505
| ML20027D505 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/05/1980 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| Shared Package | |
| ML20027D506 | List: |
| References | |
| NJK-80-147, NUDOCS 8211040394 | |
| Download: ML20027D505 (15) | |
Text
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Outd CitiIs Nuct:ar Pow;r Station 22710 206 Avenue North Corcova Illinois 61242 Telephone 309/654-2241 NJ K 147 May 5, 1980 Director, Office of Management Information and Program' Control Directorate of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of April 1980.
j Very truly yours, COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION 4 s' r
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,,e N. J. Ka ivianakis Station Superintendent bb Enclosure l
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8211040394 800505 Ig PDR ADOCK 05000254 R
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QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 MONTHLY PERFORMANCE REPORT APRIL 1980 COMMONWEALTH EDISON COMPANY AND l0WA-ILLIN0IS GAS t, ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 i
LICENSE N3S. DPR-29 and DPR-30 i
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i TABLE OF CONTENTS i
1.
Introduction ll.
Summary of Operating Experience A.
Unit One B.
Unit Two Plant or Procedure Changes, Tests, Experiments, and Safety Related Ill.
Maintenance Amendments to Facility License or Technical Specifications'.
i A.
Facility or Procedure Changes Requiring NRC Approval B.
C.
Tests and Experiments Requiring NRC Approval D.
Corrective Maintenance of Safety Related Equipment IV.
Licensee Event Reports V.
Data Tabulations VI.
Unique Reporting Requirements I
A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data j
Vll. Refueling information Vill. Glossary A
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1.
INTRODUCTION i
Quad-Cities Nuclear Power Station is composed of two Bolling Water l
Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, 111inois. The Station is jointly owned by Commonwealth Edison Company and lowa-lilinois Gas & Electric Company. The Nuclear Steam The Supply Systems are General Electric Company Boiling Water Reactors.
Architect / Engineer was Sargent & Lundy, Inc. and the primary construction contractor was United Engineers & Constructors. The condenser cooling method is a closed-cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively, l
pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor criticalities for Units 1 and 2 respectively were October 18,1971,afd April 26, 1972.
Commercial generation of power began on February 18, 1973 for Unit 1 and March 10, 1973 for Unit 2.
This report was complied by Becky Brown, telephone number 309-654-2241, l
extension 245
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One April 1-3: Unit One began the reporting period holding load at 806 MWe, and held an average load of 795 MWe. At 2330, on April 2, load was reduced at a rate of 100 MWe/ hour to a level of 650 MWe.
At this level, the main condenser flow was reversed and a control rod pattern change was performed. At 0200 on April 3, load was increased at a rate of 50 MWe/ hour.
At 0430, the rate increase was reduced to 5 MWe/ hour until a level of 810 MWe was achieved.
April 3-6:
Unit One held an average load of 805 MWe. At 2330, on April 5, load was decreased at a rate of 100 MWe/ hour to a level of 700 MWe to perform weekly turbine-generator test, reverse main condenser flow, and change-over condensate and reactor feed pumps. At 0400, on April 6, load was increased at a rate of 5 MWe/ hour until a load of 810 MWe was achieved at 1840.
April 6-12:
Unit One held an average load of 789 MWe.
At 0120, on April 12, load was decreased at a rate of 100 MWe/ hour to a level of 700 MWe to perform weekly turbine generator test and reverse main condenser flow. At 0400, the load was increased at a rate of 50 MWe/ hour. At 0500 the rate of increase was changed to 8 MWe/ hour until at 1010 4 load of 788 MWe was achieved.
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April 13: At 2000, load was reduced to 700 MWe to reverse main con-denser flow.
At 2215 load was increased at a rate of 50 MWe/ hour until a load of 772 MWe was achieved at 1115 on April 14.
April 13-20: Unit One held an average load of 760 MWe.
At 2215, on Ap ri l 19, load was reduced at a rate of 40 MWe/ hour to 700 MWe to per-form weekly turbine generator test and reverse main condenser flow. At 0105, on April 20, load was increased at a rate of 30 MWe/ hour to a level of 738 MWe.
April 21-27: Unit One held an average load of 720 MWe.
At 0500, on April 27, load was reduced at a rate of 100 MWe/ hour to a level of 595 MWe to perform weekly turbine generator test and reverse main condenser flow.
At 0635 load was increased at a rate of 50 MWe/ hour to 665 MWe.
At 0800 the rate of increase was reduced to 8 MWe/ hour until a load of 717 MWe was echieved.
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April 27-29: Unit One held an average load of 713 MWe at 1550 on April 29 The IAI Recirculation M-G Set oil pump tripped, causing the "A" Reci rc pump H-G Set to trip. The "B" M-G Set was reduced to minimum speed, causing a decrease in load to 360 MWe. The "A" M-G Set was subsequently re-started. At 1640, load was increased at a rate of 100 MWe/ hour to a level of 560 MWe, the rate was then reduced to 8 MWe/ hour until a level of 723 MWe was reached at 0510 on April 30.
April 30: Unit One finished the reporting period holding a load of 715 MWe.
B.
Unit Two April 1-19:
Unit Two remained shutdown for End of Cycle Four Re-fueling Outage.
April 20: At 0715, on April 20, the reactor mode switch was placed to startup.
At 0725 the first control rods were pulled, and criticality was achieved at 0855 April 21: At 0150, the Unit Two generator was placed on-line.
At 0230, load was increased at a rate of 100 MWe/ hour until a level of 200MWewasreached;atthislevelanumberofstartuptestswerek' performed.
At 1800 the reactor shut down procedure was begun in order to replace 3C electromatic relief valve, which had failed to operate properly in the startup testing surveillances. At 1840 the generator was taken off-line.
April 22: At 0521 the reactor mode switch was placed in shutdown to replace the electromatic relief valve.
At 1430, after maintenance on the electromatic relief valve had been completed, the reactor mode switch was switched to startup; reactor criticality was achieved at 1955 April 23: At 0346 control rods were inserted to lower reactor power level and pressure in order to test the 3C electromatic relief valve.
At 0906 the reactor mode switch was switched to the RUN position.
j At 1005 the generator was synchronized.
April 24: At 0350 load was increased at a rate of 100 MWe/ hour to a level of 400 MWe to perform a transversing in-core probe (TIP) test.
At 1750 load was decreased at a rate of 20 MWe/ hour due to the inability to produce a differential pressure between the drywell and the suppression chamber. At 1855 the load was decreased at a rate of 75 MWe/ hour.
At 2342 the generator was taken off-line.
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April 25: At 0100 the reactor mode switch was placed in the START-UP mode and at 0350 to the SHUTDOWN mode.
April 26-27:
Uni t Two remained shutdown to perform maintenance on the drywell to suppression chamber vacuum breakers. At 1347 on April 27, the reactor mode switch was switched to the STARTUP mode.
At 1850 reactor criticality was achieved.
April 28: At 0245 the reactor mode switch was switched into the RUN mode.
At 0350 control rods were inserted due to high con-ductivity of the reactor water. At 0435 the reactor mode switch was placed back into the STARTUP mode. At 0545, reactor water con-ductivity decreased to within the allowable limits. At 0557, the reactor mode switch was placed into the RUN made.
At 0647 the main generator was synchronized. At 0700, load was increased at 50 MWe/
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hour until at 1645 a load'of 430 MWe was reached.
Startup test surveillances were performed at this level.
Ap,ril 29: At 0800 load was increased at a rate of 5 MWe/ hour, this rate was then changed to 8 MWe/ hour at 1745, and then returned to 5 MWe/ hour at 0500 on April 30.
April 30: At 1530 load was leveled at 714 MWe due to a high dif ferential pressure across the Condensate Demineralizers.
Unit,.,
Two ended the reporting period holding a load of 714 MWe.
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i Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications There were no Amendments to Facility License or Technical Specifications during the reporting period.
B.
Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC approval.
C.
Tests and Experiments Requiring NRC Approval There were no tests or experiments performed during the reporting period.
D.
Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period.
The headings indicated in this summary include Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repeti ti on, j.
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UtlIT ONE MAINTENANCE SUMt4AkV i
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C/puSE RESULTS & EFFECTS W.R.
LER j0F ON ACTIGN.TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 4578 1/2 Diesel The heater element The breaker kept The heater element was Generator Soak was bad.
tripping.
Diesel replaced & the D.G.
Back Pump Generator was was tested, operable.
QO 4581 80-09/03L RHR Valve The close torque The breaker kept The torque switch was (1-1001-36B) switch was out of tripping.
adjusted & the valve adj us tmen t.
was stroked three times.
QO 4611 Reactor Bldg.
Relay CRI was The main book would Relay CRI was cleaned.
Overhead Crane dirty.
not go up.
QO 4771 HPCI Flow A 500 amp The manual / ratio The potentiometer was Controller potentiometer, signal could not be replaced & the system was bad.
adjusted.
HPCI was was tested.
available & operable.
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v UillT TWO MAINTENANCE SUNMARY CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION-TAKEN TO NUMBER HUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 0834 Refuel Bridge The cable was worn.
The main power cable The cable was replaced (2-833) needed to be replaced.
& the interlocks were checked.
QO 1835 250V Batteries The lugs were The batteries still The cells.:ere replaced
- corroded, maintained their
& the batteries were rating capacity.
tested.
q0 2074 79-27/03L MSIV The valve was The valve failed The valve was rebuilt &
(2-203-2A) worn.
LLR testing.
LLR tested.
q0 4331 Channel A There was a bad There wa's a 1/4 The connection was Scram Relay connection on a scram on'the channel repaired & the relays relay coll.
A relays.
were tested.
QO 4450 IRM 17 The detector The IRM spiked during The detector connectors connectors were withdrawal, giving a were replaced.
faulty.
1/2 scram.
Other IRMs were operating properly, q0 2078 79-27/03L Main Steam The valve was The valve failed LLR The valve was rebuilt &
Line Drain
- worn, testing.
LLR tested.
Valve (MO 220-2)
Q0 4015 RHR Min. Flow The valve was worn.
The valve was leaking The valve was rebuilt Valve (MO through., RHR was
& stroked three times.
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1001-18A) available.
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UNIT TWO MAINTENANCE
SUMMARY
V CAUSE RESULTS & EFFECTS W.R.
LER OF.
ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 4644 Containment The valve was dirty Air leaked through the The valve was cleaned, Vent to SBGTS
& the 0 rings were cylinder when the valve the 0 rings were replaced
( AO 1601 - 63) worn.
was in the full closed
& the valve was stroked position.
Valve closure three times.
not affected.
Q0 2019 HPCI (2-2303)
Amplifier 1A or 2A HPCI started with full The amplifiers were was bad.
flow at 0 control replaced with a new type pressure.
and HPCI was tested.
QO 3058 SRM Ch. 23 The cable was The detector cable was A new section of cable damaged.
damaged.-
was spliced in & the SRM was tested.
QO 3044 SRM Ch. 23 Drive tube was Drive tube was bent.
The drive tube was bent.
replaced and the SRM was tested.
QO 3943 RHR Suc. Water A piece of insula-The valve would not The insulation was.
Pex Rev Viv tion was between open.
removed & the valve was (M0-2-1001-the contacts.
tested.
185A)
QO 4427 HPCI Test The brush in-Operating the valve The brush insulator was Return Valve sulator was di rty.
caused a 250 VDC cleaned & the valve was (M0-2-2301-15) ground alarm.
HPCI stroked three times.
availability not affected.
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UNIT TWO MiJNTENANCE SUMMARV
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CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 3663 MSiv (2-203-lA)
The 0 rings were Air was leaking between The 0 rings were replaced bad.
the pilot valve mani-
& the valve was stroked fold & the valve cyl-three times inder.
QO 4387 MSIV (2-203-2D)
The pilot solenoid The valve would not The pilot solenoid was was worn.
rebuilt. The valve was open.
stroked three times and timed.
QO 4447 Refuel Bridge The hoist Jam The hoist Jam needed The hoist Jam was was out of adjusting.
adjusted & tested.
adjustment.
Q0 3818 MSIV (AO The solenoid valve The solenoid valve The solenoid valve was 203-2A) was bad, was leaking air.
replaced & tested.
Q0 4777 HP'Cl Turbine The gaskets were Oil was leaking.
The gaskets were Oil Line worn.
HPCI was operable, replaced & the line was checked.
QO 4762 IRM Ch. 18 The detector was The channel was The detector was replaceo bad.
spiking high.
and tested.
Q0 4775 80-11/03L Electrcmatic The valve was bad.
The relief valve The valve was replaced Relief Valve would not open.
Other and tested.
(2-203-3C) relief valves were
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QO 4789 1RM Ch. 12 The IRM was out of The IRM did not show The IRM was calibrated calibratiog,;,
enough overlap to the and tested.
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- e UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF.
ON ACTION-TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q0 4755 Vacuum Breaker The disc was out Vacuum breaker would The disc was adjusted (7-1601-33A) of adjustment.
not seat.
& the vacuum breaker was tested.
QO 4756 Vacuum Breaker The disc was out The vacuum breaker The disc was adjusted.
(2-1601-32D) of adjustment.
would not seat.
The seat was replaced,
& the vacuum breaker was tested.
Q0 4758 Vacuum Breaker The disc was out The vacuum breaker The disc was adjusted (2-1601-33E) of adjustment.
would not seat.
and the vacuum breaker was tested.
QO 4186 80-06/01L Core Spray B-The line had The line was leaking, The line was replaced.
Loop Line (2-crack indications.
as observed during 1404-10")
vessel hydro.
QO 2919 IRM 16 N/A The detector had to The detector was be replaced.
replaced & tested.-
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IV.
LICENSEE EVENT REPORTS The following is a tabular summary of all license event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.l. and 6.6.B.2. of the Technical Specifications.
UNIT ONE Licensee Event Date of Report Number Occurrence Title of Occurrence 80-09/03L 4-10-80 RHR Valve 1-1001-368 Breaker tripped.
80-10-03L 4-23-80 Low EHC Fluid Press.
Switch Drift.
80-II/03L 4-29-80 NCC 19-1 trippe,d.
IAReactorRechr'c.MG 80-12/03L 4-29-80 Set tripped.
UNIT TWO 80-10/03L 4-24-80 Failure to obtain torus N2 Inerting and torus.
drywell d/p.
80-11/03L 4-20-80 Failure of 3C Electro-matic Relief Valve during testing.
i 80-12/03L 4-28-80 Reactor Water Conductivity excessive.
80-13/03L 4-28-80 MO-2-1001-36A would not open.
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V.
DATA TABULATIONS The following data tabulations are presented in this report.
A.
Operating Data Report B.
Average Daily Unit Power Level D.
Unit Shutdown and Power Reductions 1
1 4+
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