Text

Monthly Operating Repts for Feb 1996 for Qcs Unit 1 & 2
	ML20101D182
Person / Time
Site:	Quad Cities
Issue date:	02/29/1996
From:	Moore K; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20101D175	List: ML20101D174; ML20101D182; ML20101D196; ML20101D209;
References
	NUDOCS 9603200097
	Download: ML20101D182 (19)
	v • d • e

.

. -. =.

QUAD-CITIES NUCLEAR POWER STATION 4

UNITS 1 AND 2 4

MONTHLY PERFORMANCE REPORT February 1996 1

4 COMMONWEALfH EDIS0N COMPANY l

AND MID-AMERICAN ENERGY COMPANY i

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

i 1

0 9603200097 960308 PDR ADOCK 05000254 R

PDR j

nrHOP3\\NRC\\ MONTHLY.RIT

r l

l l

I TABLE OF CONTENTS l

l I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit luo III.

Plant or 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 l

l 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 I

l l

TECHOP3WRC\\ MONTHLY.RPT

4 I

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 j

Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Mid-American Energy 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 i

United Engineers & Constructors. The Mississippi River is the condenser 1

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 One and Two, respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit One and l

March 10, 1973 for unit Two.

This report was compiled by Kristal Moore and Debra Kelley, telephone i

number 309-654-2241, extensions 3070 and 2240, respectively.

4 l

i 4

6 l

i TECH 0P3u?RciMONTHLY.RPT

i i

l II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One began the month of February 1996 coasting down due to fuel depletion. On February 7,1996, a load drop was performed to troubleshoot 101 heater tube side relief valve leak.

The turbine was tripped on February 10, 1996 at 0309 hours0.00358 days 0.0858 hours 5.109127e-4 weeks 1.175745e-4 months and the reactor scrammed at 0408 hours0.00472 days 0.113 hours 6.746032e-4 weeks 1.55244e-4 months to commence refuel outage Q1R14.

l B.

Unit Two Quad Cities Unit Two remained on line for the entire month of February 1996. One load drop was performed on February 18, 1996 to allow a control rod deep / shallow swap.

1 UrHOM\\NROMONDiLY.ITT j

t III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

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

B.

Facility or Procedure Chanaes Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC. approval for the reporting period.

C.

Tests and Experiments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

l 1TDIOP3\\NRC\\ MON 1NLY.RPT

IV.

LICENSEE EVENT REPORT.i The following is a tabular summary of all li:ensee 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 1 Licensee Event Report Number Dalg Title of occurrence 96-002 2/21/96 Control Room Ventilation Logic is deficient.96-003 2/22/96 U1 Diesel Generator Auto start after the overspeed test.96-005 2/3/96 Due to the Cold Weather the Control Room HVAC was declared IN0P.96-006 2/11/96 Entry into Tech Spec 3.0 (Limiting Conditions for Openation) due to LLRT testing. This was a voluntary LER.96-008 2/25/96 Control Room "B" Train IN0P from a freon leak.

UNIT 2 Licensee Event Report Number Datg Title of recurrence There were no licensee event reports for Unit 2 for this reporting period.

uruonmanwornuty.nv

r V.

DATA TABUL6TIONS 1

l The following data tabulations are presented in this report:

l l

A.

Operating Data Report l

\\

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions l

TECHOP3\\NRC\\ MONTHLY.RIT

APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNrr One DATE M m h 3,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATdS 0000 020196

1. REPORTING PERIOD: 2400 022996 GROSS HOURS IN REPORTING PERIOD: 6%

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 220.10 964.10 161427.60

6. REACTOR RESERVE SHUTDOWN HOJRS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 219.20 963.20 156722.40

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 462971.00 2288399.50 340694197.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 146269.00 734396.00 110348477.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 135686.00 699244.00 104173620.00

12. REACTOR SERVICE FACTOR 31.62 66.95 77.10

13. REACTOR AVAILABILITY FACTOR 31.62 66.95 78.73

14. UNrr SERVICE FACTOR 31.49 66.89 74.85

15. UNrr AVAILABILrrY FACTOR 31.49 66.89 75.29

16. UNrr CAPActrY FACTOR (Using MDC) 25.35 63.15 64.70

17. UNIT CAPActrY FACTOR (Using Design MWe) 24.71 61.54 63.06

18. UNrr FORCED OUTAGE RATE 0.00 0.00 7.54

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Refuel,2/10/96 thru 4/28/96

20. IF SHITTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A j

1 FORECAST ACHIEVED INrrlAL CRrflCALITY I

INTTIAL ELECTRICrTY COMMERCIAL OPERATION 1.1u-9 TirHOP3\\NRC\\ MONTHLY.RPT

...--.... -.. _. ~ -.- _

=

J 1

f APPENDIX C OPERATING DATA RTPORT DOCKET NO.

50-265 i

)

UNIT Two DATE March 8,19%

4 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 1

0000 0201 %

l. REPORTING PERIOD: 2400 022996 GROSS HOURS IN REPORTING PERIOD: 6%

i

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 l

DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe. Net): N/A i

f

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 696/O 1440.00 155510.45

]

6. REACTOR RESERVE SIIUTDOWN HOURS 0.00 0.00 2985.80 l

7. HOURS GENERATOR ON LINE 696.00 1440.00 151339.55 l

8. UNTT RESERVE SHIJTDOWN HOURS 0.00 0.00 702.90 j

9. GROSS THERMAL ENERGY GENERATED (MWH) 1727598.50 3534626.80 327875847.72

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 556207.00 1136620.00 105282155.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 534972.00 1091339.00 99744225.00

12. REACTOR SERVICE FACTOR 100.00 100.00 74.83

13. REACTOR AVAILABILTTY FACTOR 100.00 100.00 76.27

)

14. UNTT SERVICE FACTOR 100.03 100.00 72.83

15. UNTT AVAILABILTTY FACTOR 100.00 100.00 73.16

16. UNTT CAPACTTY FACTOR (Using MDC) 99.95 98.55 62.42

17. UNTT CAPACTTY FACTOR (Using Design MWe) 07.42

%.06 60.83 l8. UNTT FORCED OLTTAGE RATE 0.00 0.00 10.22

19. SHITTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): N/A

20. IF SHtrTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: N/A

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTTICALTTY INfTIAL ELECTRICTTY COMMERCIAL OPERATION 1.19-9 TECHOP3\\NRC\\MONDil.Y.RPT

E e

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE March 8. 1996 COMPLETED BY Kristal Moore TELEPHONE.Q09) 654-2241 MONTH February 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

717 17.

-8 2.

713 18.

-8 i

3.

709 19.

-8 4.

707 20.

-8 5.

702 21.

-8 6.

628 22.

-8 7.

512 23.

-8 8.

619 24.

-8 a

9.

491 25.

-8 10.

10 26.

-8 11.

-8 27.

-8 12.

-8 28.

-8 13.

-8 29.

-8 t

14.

-8 30.

15.

-8 31.

16.

-8 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day

.i in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TTCHOP3\\NRC\\ MONTHLY.RFT

l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE March 8. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH February 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

773 17.

770 2.

774 18.

643 3.

775 19.

775 4.

775 20.

775 5.

773 21.

777 6.

774 22.

777 7.

774 23.

777 8.

773 24.

768 9.

773 25.

740 10.

773 26, 777 a

11.

766 27.

778 12.

773 28.

776 13.

773 29.

777 14.

772 30.

15.

774 31.

4.

16.

773 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TECHOP3\\NRC\\ MON 1HLY.RIT

i i

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE March 8.

1996 REPORT MONTH February 1996 TELEPHONE 309-654-2241 l

a:

%!!8 e

m

=

x o <

na Es tu 8

go M

08 2 8 W

E g

r

=

LICENSEE DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 9641 02/07/96 F

0 A

Troubleshooting ICI Heater Tube Side Relief Valve bak.

9642 02/10/96 476.8 C

2 Commenced Refuel Outage Q1R14.

i l

TirHOP3\\NRC\\ MONTHLY.Rli

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE March 8, 1996 REPORT MONTH February 1996 TELEPHONE 309-654-2241 x

e.

8 00 m

X:

as<

n:

5:

ho E

E E

28 8

A 5

Hm m

E

$W LICENSEE O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS No.

DATE (HOURS)

REPORT 9642 02/18/96 S

0 H

5 Control Rod Deep / Shallow Swap.

I l

11rHOP3\\NRC\\ MONTHLY.RPT

s VI. UNIQUE REPORTING RE0VIREMENTS The following items are included in this report based on prior commitments to the commission:

A.

Main Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting peciod.

B.

Control Rod Drive Scram Timina Data for Units One and Two The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram timing for the reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG.

TECHOP3\\NRC\\ MON 1MLY.RM

. ~

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 er 2 CONTROL ROD DRIVES, FROM 01/01/96 TO O2/29/96

+

l l

AVERAGE TIME IN SECONDS AT %

l MAX. TIME :

l l

INSERTED FROM FULLY WITHDRAWN FOR 90%

l

! INSERTION !

DESCRIPTION l NUMBER S

20 50 90 l

Technical Specification 3.3.C.1 E DATE

! OF RODS 0.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 (Averaoe Scram Insertion Time) l l

l l

l 1/13/96 29 0.339 l 0.708 l 1.459 l 2.538 l

2.91 l

Scram Time Test for Viton Issue j

j l

l (K10) l l

l l

2/09/96 l

30 j 0.325 l 0.691 l 1.436 l 2.495 l

2.71 l

Scram Time Test for Viton issue l

l (M-8) at EOC U1 l

l 2/25/96 l

18 l 0.349

, 0.722 l 1.496 l 2.577 l

3.07

!l Scram Time Test for Viton Issue U-2 l

l l

l (M-8) l l

l l

l ll l

l l

l ll l

l l

l l

l l

ll l

l l

l:

l l

l l:

l l

l ll l

l l

l ll l

l NRC/SCR. GIME FR. f I

. m m

.. mm m.

..m m -

m

+--

VII.

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.

l l

i j

TirHOP3\\NRC\\ MON'n{LY.RIT

QTP 300-532

~

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST l.

Unit:

01 Reload:

14 Cycle:

15 2.

Scheduled date for next refueling shutdown:

2/10/96 3.

Scheduled date for restart following refueling:

4/28/96 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

4 NO 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

3-15-96 6.

Important Ilcensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, signtficant changes in fuel design, new operating j

procedures:

232 GE10 Fuel Bundles will be loa'ded during Q1R14.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 i

b.

Number of assemblies in spent fuel pool:

1701 The present licensed spent fuel pool storage capacity and the size of 8.

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

Licensed storage capacity for spent fuel:

3657 a.

b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

APPROVED (fina1) 14/0395t OCT 3 01989 Q.C.O.S.R.

o

'.. ' [. '

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

02 Reload:

13 I'

Cycle:

2.

Scheduled date for next refueling shutdown:

~

1-6-97 3.

Scheduled date for restart following refueling:

3-30-97 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendmend YES 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

November, 1996 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant enanges in fuel design, new operating procedures:

Appr 224 Siemens 9X91X Power Corporation Fuel Bundles will be loau.:

uring Q2R14.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2727 8.

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

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can be discharged to the sper.t fuel pool assuming the present Ilcensed capacity:

APPROVED (final)

OCT 3 01989 la/0395t Q.C.O.S.R.

1

+

t VIII. GLOSSARY The following abbreviations which may han been used in the isonthly Report, are defined below:

j ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI