ML20027D520

Forwards Monthly Operating Repts for Feb 1980

ML20027D520
Person / Time
Site:	Quad Cities
Issue date:	03/03/1980
From:	Kalivianakis N COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML20027D521	List: ML20027D520 ML20027D524
References
NJK-80-75, NUDOCS 8211040437
Download: ML20027D520 (12)

Text

i C:mm:nw:alth Edis:n Outd Citizs Muctsar Power Station h) bN l *\ G 22710 206 Avinue North Corcova, Illinois 61242 Telephone 309/654-2241 NJK-80-75 March 3, 1980 Director, Office of Management Information and Program Control Directorate of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

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Gentlemen: k Enciosed 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 February, 1980.

Very truly yours, COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION

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N. J. Kalivianakis e Station Superintendent NJK/ san 8211040437 800303 PDR ADOCK 05000254 R PDR $g 3

1 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 ,

MONTHLY PERFORMANCE REPORT FEBRUARY 1980 COMMONWEALTH EDISON COMPANY AND 10WA-1LLIN0ls GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. DPR-29 and DPR-30

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TABLE OF CONTENTS

1. Introduction

11. Summary of Operating Experience A. Unit One B. Unit Two ll1. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Ammendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety-Related Equipment IV. License Event Reports V. Data Tabulations VI. Unique Reporting Requirements

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A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data Vll. Refueling information Vill. Glossary l

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1. INYRODUCTION Quad-Cities Nuclear Povier Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and towa-lllinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The 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, pursuant to Docket Numbers 50-254,and 50-265 ThedateofinitialreactorcriticalitiesforUnitsIand2rekp'ectively were October 18, 1971 and 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 compiled by Becky Brown, Telephone number 309-654-2241, extension 245 i

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One February 1: Unit One began the reporting operating at 779 MWe.

At 2200, load was reduced at a rate of 200 MWe/hr. due to an apparent condenser tube leak.

February 2: At 0130 Unit One load was held at 190 MWe while investigating condenser conductivity readings. Upon resolution of the problem, load was increased at the rate of 50 MWe/hr.

February 3: Unit One load continued to increase at 8 MWe/hr.

February 4-23: Unit One held an average load of 775 MWe.

Load was reduced on February 10 and February 16 for main condenser flow reversal. On February 23 at 2300 load was reduced at the rate of 200 MWe/hr for an on-line control rod sequence exchange.

February 24: The control rod sequence exchange was performed, and load was subsequently increased to 100 MWe/hr.

February 25: The 1-203-lB MSIV failed to close during testing.

Load was reduced to 300 MWe to investigate the problem. The exhaust restrictor on the MSlV exerc se poppet valve was foug,d plugged.

At 0700 the problem was resolved and load was increased at 100 MWe/hr.

to 400 MWe.

February 26-29: Unit one load was increased at 8 MWe/hr. From February 27-29 Unit One held an average load of 766 MWe.

B. Uni t Two February 1-29: Unit Two remained shutdown for End of Cycle Four Refueling Outage.

lli. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MA I NT ENA..' t, A. Amendments to Facility License or Technical Specification The following amendment was added to the Unit 1 Technical Specifications during the reporting peroid.

Amendment 55 The NRC issued Amendment No. 55 to Facility Operating License No. DPR-29, in response to letters dated January 24, 1980 and January 28, 1980. This amendment reduces the required number of operable ADS valves from five to four, and sets reduced MAPLHGR limits to ensure conservative peak clad temper-atures with the four electromatic ADS valves operable.

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 Repetition.

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q0 3387 80-03/03L RHR Valve (M0 The control t ra n s- RHR was availabe. LPCI The control transformer was 1-1001-36A) former was bad. mode was not affected & replaced & the valve was other cont. cooling loop operated three. times.

was available.

q0 3365 1/2 D.G. The air strainer The D.G. was available. The air strainer was 1/2-6601 was dirty. replaced.

QO 3377 RCIC Steam The solenoid coil The valve failed closed The solenoid coil was Line Drain was bad. with switch in open replaced & the valve was (1-1301-34) position stroked three times.

Q0 3384 1/2 B SBGT The filter was There was a higher than The filter was changed demister dirty. normal DP across the & SBGT was tested.

(1/2B-2501) demister. SBGT was available.

QO 3408 1/2 D.G. Fuel Tubing fittings were Minor fuel oil leakage. Tubing & Fittings were (1/2-5200) leaking. The DG was available, replaced.

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UNIT Tuo MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 2679 79-30/03L RHR service The operator was The isolation valve would The operator was rebuilt water vault bed worn. There was an not close on a high level & the air leak was fixed.

plate drain air leak. float signal. 'The valve was tested.

isolation valve (2-4999-59)

QC 2997 Solenoid valve The solenoid valve Air was leaking from the The valve was rebuilt.

(S0-2-1601-65) was worn. solenoid valve. 2-1601-56 A0-2-1601-56 was stroked For A0-2-1601-56 was operable. three times and timed.

Q0 3155 HPCI valve (AO- ~The air line was The valve was failed The air line was repaired 2-2301-65) above broken, closed in its fall- & the valve was s,troked seat drain valve. safe position. HPCI three times.

not needed.

Q0 3252 RCIC check valve The air supply The valve would not The air supply valve was (AO-2-1301-50) valve would not open from A0. Check repaired & the valve was open properly. function not affected. retested.

QO 2162 79-27/03L Torus cooling The valve was worn. The valve failed leak The valve was relapped &

valve (2-1001- rate testing. repacked. The valve was ler 36B) rate tested.

QO 2264 79-27/03L Drywell vent 'The valve was out The valve failed leak The valve was adjusted &

valve (AO of adjustment. rate testing. leak rate tested.

. 1601-23)

Q0 2302 CRD 18-23 An Air line was The CRD was available. The air line was repaired broken & leak tested.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q0 3119 Torus Vent valve The operator was The valve would not The operator was rebuilt (AO-2-1601-61) worn. open. - PCI not needed .6 the seats were cleaned.

at time of occurrence. The valve was cycled three times & leak rate tested.

QO 3120 79-27/03L Drywell vent The operator was The valve failed leak The operator wa's rebuilt bypass v'alve worn. rate testing. S the seats were cleaned.

(2-1601-62) The valve was cycled & leak rate tested.

40 3129 CRD 26-39 The diaphragm was The valve was , leaking. The diaphragm was repaired (2-305-127) cracked. The CRD was available, & checked for leaks.

and rod was inserted.

QO 3251 CRD Scram Diaphragm screws The CRDs were available The valves were replaced &

solenoids were stripped & rods were inserted. operated three times.

(54-15 & 58-27)

Q0 3337 CRD Scram The diaphragms were The valves operated The diaphragms were re.-

solenoid valves on the wrong side. slowly. The CRDs were installed & the valves 117 S.ll8 (46-47 available, and rods were tested.

& 42-07) were inserted.

QO 3352 79-27/03L RHRS suppression The torque switch The valve failed leak The torque switch was chamber spray was out of adjust- rate testing. adjusted. The valve was valve (M0 . ment. '

stroked three times &

1001-36B) leak rate tested.

QO 3448 D.G. fuel oil Three main contacts The pump did not run The contacts were replaced transfer pump were bad. when the D.G. ran. The & the pump was run.

(2-5203) ,,g, D.G. was available.

UNIT WO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF' ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 3541 80-03/03L Reactor Bldg. The relay was The vent system isolated The relay was replaced.

vent relay burnt. properly, & SBGTS auto-(2-1705-105) started.

3168-78 D.G. air start The valve was The isolation valve was The valve was rebuilt system. worn. leaking through. & the system was tested.

5762-78 D.G. Cooling The pump was D.G. cooling water The pump was rebul1t &

water pump worn. was available. tested.

(2-3903) 2282-79 D.G. Lube Oil A seal was bad. Oil was leakihg. The seal was replaced.

pump (2-6600) The D.G. was The diesel & pump were available. operated.

QO 3655 80-04/03L Auto Blowdown The timer was The timer took too The timer was adjusted &

Logic. worn out of long to time' out. tested, adjustment. The other timer was operable. ADS was operable.

Q0 3631 D.G. Soak back The motor & belt The motor was '

The motor was repladed &

pump. was bad. vibrating. 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.I. and 6.6.B.2. of the Technical Specifications.

UNIT 0NE Licensee Event Date of Report Number Occurrence Title of Occurrence 2-6-80 RHR Suppression Chamber 80-03/03L Dump Valvc M0-1-1001-36A Failed in Closed Position 80-04/03L 2-15-80 Reactor Low-Low Water Level Switch, Yarway LIS 1-263-72A failed to operate.

80-05/03L 2-24-80 IB MSIV failed o close.

UNIT TW0 12-13-80 Reactor Building Vent 80-03/03L System would not reset isolation.

80-04/03L 2-19-80 Auto Blowdown Timer Setpoint Drift.

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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.

C. Unit Shutdowns and Power Reductions.

VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission.

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A. Main Steam Relief' Valve Operations There were no main steam relief valve operations during the reporting period.

B. CONTROL R0D DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no control rod drive scram timing operations during the reporting period. g, Vill. REFUELING INFORMATION The following Information about future reloads at Quad-Cities Station was requested in a January 26, 1978 licensing memorandum (78-24) from D.E. O'Brien to C. Reed, et. al, titled, "Dresden, Quad-Cities, and Zion Station - NRC request for refueling information dated January 18, 1978. .

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