Text

Monthly Operating Repts for Nov 1981
	ML20042A699
Person / Time
Site:	Quad Cities
Issue date:	12/01/1981
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20042A691	List: ML20042A690; ML20042A699;
References
	NUDOCS 8203230692
	Download: ML20042A699 (20)
	v • d • e

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a QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT NOVEMBER 198I , ,

COMMONWEALTH EDISON COMPANY .-

AND IOWA-ILLIN0IS GAS & ELECTRIC COMPAIE NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 t,

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1 8203230692 811201 PDR ADOCK 05000254 R PDR

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 5pecifications 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 .

B. Average Daily Unit Power Level 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 S'

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I. INTRODUCTION

.- Quad-Cities Nuclear Power Station is composed of two Boiling

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Water Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located in CoxJova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systcms 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.

Commercial generation of power began on February 18, 1973 for Unit I 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. SU? DIARY OF OPERATING EXPERIENCE A. UNIT ONE November 1-2: The unit began the reporting period at 804 MWe. At -*-

1045 on November I, load was dropped to 700 MWe to backwash a Condensate Demineralizer for two hours; load was increased at 40 MWe/ hour for one hour and 5 MWe/ hour to 810 MWe by 0340, November 2.

November 3-8: At 0800, load was dropped to 780 MWe to make control rod pa t te rn changes. At 1045 load was increased at 40 MWe/ hour for one-hal f hour and 5 MWe/ hour to 806 MWe.

November 9-14: At 0010 the unit scrammed due to loss of the Essential Service System (ESS) Bus. This was due to an improperly placed jumper on the Unit Two Diesel Generator which de-energized 4KV Bus 13-1 and Bus 18 (480 VAC). Bus 18 is the normal supply to the ESS Motor-Generator set. The D.C. motor back-up also failed to auto-statt and drive the MG set. The unit was brought back on line by 1500 the same day at 120 MWe, and was holding at 500 MWe for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by the end of the day. At 0845, on November 10, load was increased at 50 MWe/ hour for one hour, 5 MWe/ hour for one hour, 50 MWe/ hour for one -

hour, and 5 MWe/ hour until reaching maximum load on November 11.

November 15-19: Laad was dropped to 700 MWe to run weekly Turbine tests. Load was increased to a load of 813 MWe by 1500 on November 15 November 20-24: On November 20, we started dropping load at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months to prepare for a scheduled maintenance outage. Novembe r 21, at C100, the unit was manually scrammed, per procedure. Major outage work included the Unit Two Battery Discharge Tests, completion of NRC commitments for RCIC and HPCI Systems, and to repair isolution valves on the Service Water Strainers.

November 25-30: The unit was back on line by 2300, November 25 at 400 MWe. At 0615, November 26, load was increased at 100 MWe/ hour for one hour then held load to make control rod pattern changes. At 2200 load was increased 5 MWe/ hour until a load of 813 nWe was reached at 0550, November 29 B. UNIT TWO November 1-30: The End of Cycle Five Refueling Outage is still in progress.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

. A. Amendments to Facil.ity License or Technical Specifications .___,_

There were no amendments to Facility License or Technical Specifications for the reporting period.

B. Facility or Procedure Changes Requiring 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.

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 Mal functions, Results and Ef fects on Safe Operation, and Action Taken to Prevent Repetition.

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i f-UNIT y t MAIMTENANCE

SUMMARY

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CAUSE RESULTS & EFFECTS W.R. LER OF ON f; UMBER ACTION TA' KEN TO NUMBER C0K-GN E tlT MALFUNCTION SAFE OPERATI0il PREVENT REPETITION Ql5714 ttain steamline riceds re-cal ibrated. Reading on me t e r is Calibrated A 0 C tiain Radiation not consistent with Steamline Radiation lion i to r A & C o t he r r.nn i to rs . T r i p i',on i to r s .

function not affected.

Q13778 Drywell Dirty control Valve 1601-59 would Cleaned control switch, flitrogen liake- switch, not stay in the open up Valve A0 position. Isolation 1601-59 function not a f fec t ed.

415869 31-14/03L I-1601-20A Faulty solenoid Valve would not open Replaced solenoid valve.

valve. when operated from the Control Room.

Ql5738 SI-22/03L 1/2 Emergency Engine bearing The Diesel Generator Installed new Diesel Diesel 1/2- overheated; the was inoperable. The engine and performed 6601 bearing cap Unit 2 Diesel was pre-op t'ests.

dimensions were wired to replace it.

out of specifications.

Q14821 CRD Accumu- 0-Ring on water- Accur.iulator 46-07 had Replaced CRD accumulator.

lator 46-07 piston side lealting high water alarm up.

by. Adjacent accumulators and CRDs were operable.

Q15855 1/2 Diesel Worn agastat relay. The Diesel would not Replaced relay TD-3 Gene ra to r trip on low cooling water pressure.

Q15857 RilR Shutdown The motor had burnt Cannot open valve Installed new notor on Cooling Suction up. from Control Room. valve.

Valve 1001-50 Breater trips.

Isolation function not af fected.

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UNIT 0 TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAkEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q15319 2-220-44 Recirc Misaligned The valve closure Adj usted indicating Sample Valve indicating time indicated to limit switch, switch. be greater than allowable. Unit shutdown for refueling.

Ql5726 2A Reactor Faulty solenoid. Vent isolation valve Replaced solenoid Building was sticking open.

Isolation Redundant isolation Valve valve was operable to provide necessary isolation.

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IV. LICENSEE EVENT REPORTS r

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.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 81-20/03L* 11-21-81 RHR Service Water Line Leakage 81-21/03L 10-27-81 EHC Low Pressure

Switch Setpoint Drift 81-22/03L 11-07-81 1/2 Diesel Generator ~

inoperable

81-20/03L was re-classified as a non-reportable occurrence (Monthly Performance Report of October 1981), therefore the number is being re-issued for November.

UNIT TWO 81-22/03L 11-03-81 HPCI Area Temperature Switch Setpoint Drift 81-23/03L 11-06-81 Off Gas isolation Timer Setpoint Drift 81-24/03L 10-19-81 RCIC Area Temperature Switch Setpoint Drift

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V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Operating Data Report .

D. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l

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( t N e - tie t ) : 76?K Design electrical rating ( t%'e -Ne t ) '"F

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" Gross : hermal snergy generated (MWH) 0 12?58041 13773Et3' O. Or9ss a l a c t r i. c a ). energy :; e n e r a t e d ' MWH ) O 09 344351 10AcC 'l_~ ' .-

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2. 748.4 18, 754.3

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APPEt1DlX D QTP 300-I,13 050-254 UtilT SilVTDOWfC AtJD POWER REDUCTIO llS Revision 5 DOCKET NO-March 1978 U!!!T tiAtiE Qu d-Cities Unit One '

COMPLETED BY E Weinfurter i 309-654-2241, DATE December 1, 1981 fl0VEM EER 1981 REPORT HONTil TELEPHONE ext. 194 A

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ge @ LICENSEE hg $g

[ DURATION $ 5 b; " EVENT m8 g: 3 NO. DATE '-

(HOURS) " yIy REPORT NO.

o 8 CORRECTIVE ACT10ftS/ COMMENTS n

31-29 811109 F 14.8 G 3 ED XXXAAX Reactor scram caused by' loss of Essential. Service Bus 31-30 811120 S 119.0 B 2 EC ZZZZZZ Maintenance Outage to run Battery Discharge

, Test, repai r Service Water Valves and to install RCIC, HPCI, and ACAD/ CAM Modifications for NRC Commitments .

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.' O [' I l f-9 APPENDlX D qTP 300-S13 050-265 UNIT tilVTDOWNS Arid POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 UtilT NAME Qu d-Cities Unit Two '

7 DATE December 1, 1981

REPORT M0tiTi{ NOVEllBER 1931 TELEPliONE e I4 oe b Ee @ h LICENSEE hg g C u-DURATION $

$" EVENT *3 g3 -

NO. DATE (Il0VRS) y5g REPORT NO.

3 CORRECTIVE ACTIONS / COMMENTS R

31-17 810907 5 720.0 C 4 RC FUELXX Continuation of End of Cycle Five Refueling Outage e

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o VI. UNIQUE REPORTING REQUIREMENTS The following i tems are included 'n this report based on prior commi tments to the commiss ion:

A. Miin Steam Relief Valve Operation's -

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Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Valves No. & Type Plant Description of Unit Date Actuated Actuations Conditions Events Rx Press 1 11-03-81 1-203-3A 8 Automatic 1115 Control Pressure 1-203-3A 2 Manual 1100 after Reactor Scram 1 11-21-81 1-203-3A 1 Manual 950 Surveillance T.S.

1-203-3B 1 Manual 4.5.D.l.b l-203-3C 1 Manual 1-203-30 1 Manual 1-203-3E I Manual . .

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B. Control Rod Drive Scram Timing Data for Uni ts One and Two There were no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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9 VII. REFUELING IhTORMATION 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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- QTP 300-532 Re.ision 1 f- ~

, QUAD-C! TIES REFUEllflG tiarch 1978 m

( If1 FORMAT 10tl REQUEST f4

1. Unit: 1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdewn: 9-12-82 (Shutdown EOCf4--

3 Scheduled date for restart following refueling: 12-5-82 (startup BOC7)

4. Vill refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: No, Plan 10CFR50.59 reloads for future cycles of Quad Cities Unit 1. The review will be conducted in August, 1982.

5 Scheduled date(s) for submitting proposed licensing action and supporting Information: August, 1982 for 10CFR50 59 related changes ~ 90 days prior to shutdown.

. 6. Important licensing considerations associated with refueling, e.g., new or

'different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: .

New fuel d.esigns:

7 The number of fuel assemblies.

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a. 11 ember of assemblies in core: 724 r

t b. tiumber of assemblies in spent fuel pool: 820

8. The present licensed spent fuel pool storage capacity and the size of any t

increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

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a. Licensed storage capacity for spent fuel: 1460

b. Planned increase in licen;ed storage: None c

9 The prbjected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: Seotember. 1985

[

(end of batch discharge capabi~iity) "'M q l(,, .'PFROVcv A

APR 2 01973 I Q. c. c. S. R.

I

QTP 300-s32 Revision 1 QUAO-C! TIES REFUELING March 1978 INFORMATION REQUEST

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1. Unit: 2 Reload: 5 Cycle: 6

2. Scheduled date for next refueling shutdewn: 8-30-81 (Shutdown E,0 CJJ,_

. 3 Scheduled date for restart following refueling: 12-20-81 (startuo BOC6)

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: No, Plan 10CFR50 59 Reloads for future cycles of quad Cities Unit 2. The review will be conducted by early August, 1981. -.

5. scheduled date(s) for submitting proposed licensing action and supporting

. Information: Early August, 1981 for 10CFR50 59 related changes esc 0 days prior to shutdown.

6. Important licensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: ^~

New Fuel Design: 1. Barrier Fuel

2. Control Cell Core 73 N

( 7 The number of fuel a,stemblies.

a. Number of assemblies in core: 724 i

i b. Number of assemblies in spent fuel pool: 672

8. The present licensed spent fuel pool storage capacity and the size of any l Increase in' licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 1460 i

b. Planned increase in licensed storage: None 9 The projected date of the last ' refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September, 1984 (End of batch discharge capability) -- '

APPROVED

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~~

APR 2 01978 Q. c. o. s. R.

I VIII. GLOSSARY The following abbreviations which may have been used in the 'Anthly Report, are defined below: ,

~~~~'"

ACAD/ CAM -

Atmospheric Containment Atmospheric Dilution / Containment ~

Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS -

Anticipated Transient Without Scram BWR -