Text

Monthly Operating Repts for Aug 1996 for Quad Cities Nuclear Station Units 1 & 2
	ML20117N648
Person / Time
Site:	Quad Cities
Issue date:	08/31/1996
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-96-066, LWP-96-66, NUDOCS 9609200030
	Download: ML20117N648 (22)
	v • d • e

--

' Commonwealth lilien Comp.iny Quad Citics Generating Station 22710 206th Asenuc North Cordova, ll. Li 212-97 i')

j Tcl MF1M i-22 il l

LWP-96-066 September 10, 1996 i

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units I and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 Enclosed for your information is the Monthly Performance Report covering i

the operation of Quad-Cities Nuclear Fower Station, Units One and Two, during the month of August 1996.

Respectfully, Comed Quad-Cities Nuclear Power Station i

..(

II$AR

t. W. Pearce Station Manager LWP/dak Enclosure cc:

A. Beach, Regional Administrator b

C. Miller, Senior Resident Inspector 9609200030 960031 PDR ADOCK 05000254 R

PDR STMGRMM696.LWP A linicum Company

i

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 i

2 MONTHLY PERFORMANCE REPORT AUGUST 1996 COMMONWEALTH EDISON COMPANY AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECHOP3\\NRCu(ON1NLY.RIT

i TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance 1

A.

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 4

VI.

Unique Reporting _ Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

l

' 11 CHOP 3\\NBC\\ MON 1MLY.RFT

I.

INTRODUCTION i

i 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 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 United Engineers & Constructors. 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 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 March 10, 1973 for unit Two.

This report was compiled by Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

TECHOPMNRCG40NTHLY.RFT

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One was off-line the entire month of August 1996. On August 24, 1996 at 2140 hours0.0248 days 0.594 hours 0.00354 weeks 8.1427e-4 months the reactor went critical. On August 25,1996 at 0448 hours0.00519 days 0.124 hours 7.407407e-4 weeks 1.70464e-4 months a manual scram was inserted due to a procedural issue. The procedural issue was resolved and start-up activities resumed. The reactor went critical at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months on August 25, 1996.

B.

Unit Two Quad Cities Unit Two started the month of August 1996 shutdown in Forced Outage Q2F41. On August 10, 1996 at 0239 hours0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months the reactor went critical. On August 11,1996 at 2107 hours0.0244 days 0.585 hours 0.00348 weeks 8.017135e-4 months a manual scram was inserted due to excessive leakage from the HPCI 2301-7 valve. After successful repairs to the valve, the reactor went critical on August 14, 1996 at 2117 hours0.0245 days 0.588 hours 0.0035 weeks 8.055185e-4 months . The generator was synchronized to the grid on August 15, 1996 at 1214 hours0.0141 days 0.337 hours 0.00201 weeks 4.61927e-4 months and at full load on August 17, 1996 at 2145 hours0.0248 days 0.596 hours 0.00355 weeks 8.161725e-4 months .

TECH 0P3\\NitC\\MONDILY.Rrr

.~

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE i

A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical i

Specifications for the reporting period.

B.

Facility or Procedure Chanaes Reauirino NRC Acoroval i

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

4 C.

Tests and Exoeriments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period, ncnonsnauomuuaer J

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

UNIT 1 Licensee Event Report Number Dalg Title of occurrence 96-012 6/20/96 Diesel Fuel Oil Transfer Piping in an Unanalyzed Condition Due to an Incomplete Safety Classification Upgrade.96-013 08/08/96 Zebra Mussels Found on Fire Pump Suction Strainers.

j 96-015 08/16/96 Discrepancies identified between as designed and as installed 1

baseplate / concrete expansion anchor installations for Quad Cities Unit 2 Jet Impingement Restraint No. JIHP-3.96-016 08/23/96 Rx Building blowout panel broken bolts.96-017 08/25/96 Manual Reactor Scram when the turbine bypass valves came open.

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

TECHOP3\\NRC%dONTHLY.RIT

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 1

t 1

TECH 0P3WRCudON1MLY.RPT l

._. ~..

4 APPENDDC C OPERATING DATA REPORT

?

DOCKET NO.

50-254 i

a UNrr One DATE September,10, 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS j

0000 0801 %

i

1. REPORTING PERIOD: 2400 0831% GROSS HOURS IN REPORTING PERIOD: 744 i

1

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

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Ne0: N/A

4. REASONS FOR RESTRICrlON (IF ANY):

i THIS MONTH YR TO DATE CUMULATIVE 4

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 152.60 1116.70 161580.20 i

1 i

6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90

)

7. HOURS UENERATOR ON LINE 0.00 963.20 156722.40

8. UNrr RESERVE SHtTTDOWN HOURS 0.00 0.00 909.20 l

9. GROSS THERMAL ENERGY GENERATED (MWH) 662.40 2289061.90 340694859.50 i

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 734396.00 110348477.00 l1. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00

12. REACTOR SERVICE FACTOR 20.51 19.07 75.58

13. REACTOR AVAILABILrrY FACTOR 20.51 19.07 77.11,

14. UNrr SERVICE FACTOR 0.00 16.45 73.31

15. UNrr AVAILABILrrY FACTOR 0.00 16.45 73.73

16. UNrr CAPACfrY FACTOR (Using MDC) 0.00 15.53 63.36

17. UNIT CAPACfrY FACTOR (Using Design MWs) 0.00 15.14 61.76

18. UNrr PORCED OtfrAGE RATE 0.00 0.00 7.54

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrIAL CRrflCALITY INITIAL ELECTRICfrY COMMERCIAL OPERATION 1.11-9 1TCHOP3\\NRC\\MONDILY.kPT

4 1

4 APPENDDC C

{

OPERATING DATA REPORT DOCKET No.

50-265 l

UNTT Two j

DATE September 10, 1996 COMPIETED BY Kristal Moore TELEPHONE (309) 654-2241 1

OPERATING STATUS i

0000 080196

1. REPORTING PERIOD: 2400 083196 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICrlON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTilCAL 453.20 3587.10 157657.55

6. REACIOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 395.80 3520.80 153420.35

8. UNTT RESERVE SHITTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 906823.60 8594967.50 332936188.42

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 279744.00 2745492.00 106891027.00

11. NET ELECTRICAL ENERGY GENERATED G4WH) 262841.00 2632010.00 101284896.00

12. REACTOR SERVICE FACTOR 60,91 61.27 74.29

13. REACTOR AVAILABILrrY FACTOR 60.91 61.27 75.69

14. UNIT SERVICE FACTOR 53.20 60.13 72.29

15. UNrr AVAILABILrrY FACTOR 53.20 60.13 72.62

16. UNrr CAPAcrTY FACTOR (Using MDC) 45.94 58.46 62.06

17. UNrr CAPACTTY FACTOR (Using Design MWe) 44.78 56.97 60.49

18. UNrr PORCED OUTAGE RATE 46.80 39.87 11.30

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH): 2/1/97

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRrflCA!JTY INfrIAL ELECTRICrrY COMMERCIAL OPERATION 1.10-9 TliCHOP3\\NRC\\ MONTHLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE September 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Auaust 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-9 17.

-8 2.

-9 13.

-9 3.

-9 19.

-8 4.

-9 20.

-8 5.

-10 21.

-9 6.

-9 22.

-9 7.

-9 23.

-9 8.

-9 24.

-9 9.

-9 25.

-9 10.

-11 26.

-9 1

11.

-13 27.

-9

)

12.

-10 28.

-9 13.

-9 29.

-9 14.

-9 30.

-9 15.

-10 31.

-9 16.

-9 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 TECHOP3WRCudONTHLY.RIT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE September 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Auaust 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-9 17, 491 2.

-9 18.

748 3.

-9 19.

753 4.

-9 20.

752 5.

-9 21.

747 6.

-9 22.

741 7.

-8 23.

748 8.

-8 24.

747 9.

-9 25.

730 10.

-10 26.

747 11.-

-12 27.

745 12.

-9 28, 746 13.

-9 29.

740 14.

-9 30.

740 15.

42 31.

739 16.

121 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 TECHOPS\\NRC\\ndONTMLY RIT

.i APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 1

1 UNIT NAME One COMPLETED BY Kristal Moore DATE Sect -har 10, 1996 REPORT MONTH Auoust 1996 TELEPHONE 309-654-2241 l

M b

O@

g to M

i M

MM W

E M

s E

LICENSEE o

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 9642 08/01/96 5

744.0 C

4 Continuation of QlR14 Refuel Outage.

1TCHOP3WRCudON1MLY.RPT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Sootember 10, 1996 REPORT MONTH Auoust, 1996 TELEPHONE 309-654-2241 a:

00 m

m e,

a n

D 9

e$

08 8

4 LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 9645 541-M F

348.2 H

2 Continuation of Force Outage Q2F41.

4 4

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4 TECHOP3\\NRC\\ MON 1HLY.RIT

VI. UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Operations 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.

Unit:

One Date:

August 29, 1996 Valve Actuated:

No. & Tvoe of Actuation:

1-203-3A 1 Manual 1-203-3B 1 Manual 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E 1 Manual Plant Conditions:

Reactor Pressure 300 psig Description of Events: Routine Testing B.

Control Rod Drive Scram Timino 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\\ MONTHLY.RIT

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 &'2 CONTROL ROD DRIVES, FROM 01/01/96 TO 08/31/96 l

AVERAGE TIME IN SECONDS AT %

l MAX. TIME l l

INSERTED FROM FULLY WITHDRAWN l FOR 90%

]

INSERTION !

DESCRIPTION j NUMBER l

5 20 50 90 l

Technical Specification 3.3.C.1 E DATE

! OF RODS

! 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 fAveraoe Scram Insertion Time) i

-l l

1/13/96 29 j 0.339 0.708 1.459 2.538 2.91 l

Scram Time Test for Viton Issue f

l (K10) l l

l 2/09/96 30 l 0.325 l 0.691 l 1.436 l 2.495 l

2.71 Scram Time Test for viton issue j

l (M-8) j at EOC U1 I

2/25/96 f

18

' O.349 1 0.722 1.496 ll 2.577 l

3.07 f

Scram Time Test for Viton Issue U-2 l

(M-8) l

\\.

1 0.32 0.69 y 1.46 2.54 2.54 PMTV for Scram Valve Leak on U-2 4/22/96 l

l L

(K-5)

'l u

l l

i 5/05/96 177 0.308 ! 0.713 1.543 2.700 3.03 l

Beginning of Cycle for U-1 (N-7) l l

8/16/96 l

177 j 0.330 O.707 ll 1.473 2.569 1

2.85 l

PMTV for SSPV Maintenace

]

(F-16) l 8

l i

.i l

l l

1 l

I l

l l

1 I

micacawnutraw w

1 s

VII.

REFUELING INFORMATION l

The following information about future reloads at Quad-Cities Station was i

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.

1 1

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111 CHOP 3\\NRC\\ MON 1MLY.RPT

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

Unit:

01 Reload:

14 Cycle:

15 i

2.

Scheduled date for next refueling shutdown:

2/10/96 3.

Scheduled date for restart following refueling:

8/19/96 4.

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

NO 5.

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

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:

232 GE10 Fuel Bundles were loaded during Q1R14.

7.

The number of fuel asseabiles.

4.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1933 8.

The present Itcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is g

planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3657 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 Ilconsed capacity:

APPROVED (final) 00T 3 01989 14/0395t

Q.C.O.S.R.

W

m.

I QTP 300-532 Revision 2 1

QUAD CITIES REFUEL!NG October 1989

)

INFORMATION REQUEST 1

[

1.'

Unit:

02 Reload:

13 Cycle:

14 2.

Scheduled date for next refueling shutdown:

2/01/97 3.

Scheduled date for restart following refueling:

4/23/97 4.

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

YES S.

Scheduled date(s) for submitting proposed Itcensing action and supporting Informat!Jn:

August 1996 6.

Important Ilcensing 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:

Approx. 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded during Q2R14.

7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

7797 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 N

planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 b.