ML20027D493
| ML20027D493 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/01/1981 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| Shared Package | |
| ML20027D494 | List: |
| References | |
| NJK-81-358, NUDOCS 8211040367 | |
| Download: ML20027D493 (10) | |
Text
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C:mm:nwealth Edis:n C--
Quad Cities Nucisar Power Station
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22710 206 Avsnua North Cordova,1;linois 61242 Telephone 309/654-2241 NJK-81-358 October 1, 1981 Director, Office of Management Information and Program Control Directorate of Licensing U. S. Nuclear kegulatory 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 Septe:iber 1981.
4 Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
/M N. J. Kalivianakis Station Superintendent bb Enclosu re 8211040367 811001 (rp PDR ADOCK 05000254 R
a QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PEREDRMANCE REPORT SEPTEMBER 1981 i
j COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 i
LICENSE NOS. DPR-29 AND DPR-30 l
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TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two III. Plant of Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.
Amendments 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.
Licensee Event Reports V.
Data Tabulations A.
Operating Data Report
,,.4 B.
Average Daily Unit Power Level j
C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII. Glossary
I.
INTRODUCTION Quad-Cities Nuclear Power 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 Iowa-Illinois Gas & Electric Company.
The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, 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. The date of initial reactor criticalities for Units 1 and 2 respectively were October 18, 1971, and April 26, 1972.
Canmercial 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 and Robert Tubbs, telephone number 309-654-2241, extensions 127 and 174.
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
UNIT ONE September 1-4: The Unit began the reporting period holding a load of 792 MWe.
Power was held at that level until September 2, when Recirc flow was increased to the maximum control valve position, equal to 798 MWe, Load was held steady through September 4.
September 5-8: On September 5, load was dropped to 500 MWe, to change the rod pattern and concurrently to perform the weekly Turbine tests.
Load was then increased at various rates, including a xenon soak, until 801 MWe was achieved and held at 2220 on September 8.
September 9-22:
Over this 14 day period, load was held at the maximum achievable; approximately 795 MWe.
The two exceptions to this were on September 13 and 20, when load was dropped briefly to 700 MWe to per-form the weekly Turbine tests.
Also, on September 20, load was further dropped to 550 MWe due to a minimum load condition.
September 23-26: At 0338, on September 23, the Reactor scrammed on Condenser Low Vacuum.
The loss of Condenser Vacuum was due to the*
wrong procedure being used to transfer water from the Suppression $nd Pool to the Condenser.
The Reactor was brought critical at 1127 the Unit put back on the system at 1515 that same day.
Load was increased over the next three days until it was held at 800 MWe at 0240 on September 26.
September 27-30: On September 27, load was dropped to 700 MWe to perform the weekly Turbine tests.
On the last three days of the month, load was held at 800 MWe, and the Unit ended the reporting period in that status.
B.
UNIT TWO September 1-6:
Unit Two began the month holding maximum attainable load, 506 MWe, in the coastdown for the refueling outage.
The Unit remained at maximum until 2000 on September 6, when load was dropped in order to commence the outage.
September 7-30: At 0020, on September 7, the Unit was tripped off-line to start the End of Cycle Five Refueling Outage.
The outage is scheduled to last until December 29, 1981. Major work items to occur during the outage include: Torus Internal Modification, High and Low Pressure Turbines Overhaul, and install Hangers in the Drywell.
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Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications i
On August 21, 1981, Amendnents 74 and 67 were issued to DPR-29 and DPR-30, respectively.
These Amendments consist of changes in the Technical Specifications for each of the two units which require the presence of a Shift Technical Advisor with specialized training in Reactor technology related to emergency operations.
It also updates the shift manning chart listing the requirements for the Shift Technical Advisor.
B.
Facility or Procedure Changes Requirir.g NRC Approval There were no Facility or Procedure Changes Requiring NRC approval for the reporting period.
C.
Tests and Experiments Requiring NRC Approval There were no Tests and Experiments Requiring NRC approval for the reporting period.
4" D.
Corrective Maintenance of Safety Related Equipment k
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.
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UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER
.0 F ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q14383 Main Steam Line The B and D monitors The monitors were Recalibrated the B Radiation Monitors read different than still functional and and D monitors.
RE 1743 B,0 the A and C monitors.
capable of performing their design function.
Q14625 24/48 VDC Battery Chargers did not The batteries were Replaced the equalize Chargers IAl and function in the fully charged, if mode timer.
182 equalize mode.
needed.
The chargers were still capable of supplying DC out-put in the float mode.
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I UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS V.R.
LER 0F ON ACTION TAKEN TO i
NUMBER NUMBER COMPONENT MAEPtmCTION SAFE OPERATION PREVENT REPETITION i
Q11262 RCIC Steam Line The high trip Any one of the three Replaced the faulty High Flow DP switch would not other switches in the switchangperformed Switch 2-1360-1B function.
logic system were a functional test.
capable of initiating a Group V lsolation, if needed.
Q14425 Main Steam Failed Local Leak The other inline MSIV Replaced valve Isolation Valve Rate Test due had an acceptable packing.
2-203-2A to packing leak.
leakage rate.
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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee 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 Report Number Date Title of Occurrence 81-16/03L 9-2-81 SBGT Inoperable UNIT TWO 81-16/03L 9-6-81 HPCI Inoperable--
oil leak 81-17/03L 9-7-81 3E Electromaitc Relief Valve failed to open 81-18/03L 9-8-81 Local Leak Rate Test Failure 81-19/03L 9-29-81 RHR Service Water Vault--Penetration Failures
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V.
DATA TABUIATIONS The following data tabulations are presented in this report:
A.
Operating Data Report l
B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 9
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