Text

Monthly Operating Repts for May 1997 for Quad Cities Nuclear Station Units 1 & 2
	ML20148K489
Person / Time
Site:	Quad Cities
Issue date:	05/31/1997
From:	Pearce L, Sirles K; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-97-066, LWP-97-66, NUDOCS 9706180146
	Download: ML20148K489 (20)
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Commonw ealth litison Company Quad Citics Generating Station

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22710 206th Avenue North Cordova, 11.61242-9710 l

Tel MPMS 122 4 I l

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LWP-97-066 l

l June 10, 1997 l

l U.S. Nuclear Regulatory Commission ATTN: Document Control Cesk Washington, D.C. 20555 I

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SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l

Monthly Performance Report j

NRC Docket Nos. 50-254 and 50-265 i

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 May,1997.

Respectfully, l

J.

Comed f }/ /

Quad-C_ities Nup ar Power Station fg

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LA W. Pearce l

Station Manager I

LWP/dak Enclosure i

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A. Beach, Regional Administrator C. Miller, Senior Resident Inspector I

9706180146 970531 PDR ADOCK 05000254 R

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1q0043 111111111.1111.11H.11 OI:llI.ll A l'nicum Compan)

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y QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY 1997 COMMONWEALTH EDIS0N COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TBCHOP3\\NRC\\ MONTHLY RFT

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TABLE OF CONTENTS j

l I.

Introduction l

l II.

Summary of Operating Experience I

l A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications i

B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval j

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

TBCHOP3\\NRC\\ MON 1HLY.RIT

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INTRODUCTION i

Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Midamerican 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 Erlineers & 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 Sirles and Debra Kelley, telephone number 309-65a-2241, extensions 3070 and 2240, respectively.

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F, II.

SUMMARY

.0F OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One was on-line the entire month of May 1997. On May 16,1997 at 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months , a load drop was performed to repair a leak on the Reactor Core Isolation Cooling (RCIC) 1301-17 valve. After completion of seal ring repairs, Unit One began increasing from 240 MWe to full power on May 19, 1997 at 1140 hours0.0132 days 0.317 hours 0.00188 weeks 4.3377e-4 months . A few other load drops were performed for Turbine Surveillances, however the average daily power level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two was shutdown the entire month of May 1997 due to Refuel Outage Q2R14. Start-up activities commenced on June 8, 1997 and were terminated on June 9,1997 due to a failure of one stage of the 2B Reactor Recirc Pump seal.

Start-up is now scheduled for June 12, 1997.

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1 III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications Technical Specification Amendment No.176 was issued on May 1,1997 to a

Facility Operating License DPR-29 and Amendment No. 172 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The an,endments would change the Technical Specifications by increasing the load test values of the Emergency Diesel Generators in Surveillance Requirments 4.9.A.8.h from between 2625 kW and 2750 kW to 2730 kW and 2860 kW.

Technical Specification Amendment No.173 was issued on May 2,1997 to Facility Operating License DPR-30 for Quad Cities Nuclear Power J

Station.

Changes to allow operation with Siemens Atrium 9B Fuel in i

Modes 3, 4, 5.

Technical Specification Amendment No.174 was issued on May 22, 1997 to Facility Operrting License DPR-30 for Quad Cities Nuclear Power Station. Changes to allow operation with Siemens Atrium-9B Fuel above Mode 3.

Technical Specification Amendment No.177 was issued on May 23, 1997 to Facility Operating License DPR-29 and Amendment No. 175 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

l Changes to allow operation with Siemens Fuel above Mode 3, l

B.

Facility or Procedure Chanaes Reauirina NRC Anoroval I

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

C.

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

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TECHOI4WRC\\ MON 1HLY.RPT

l IV.

LICENSEE EVENT REPORTS l

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 of 10CFR50.73.

UNIT 1 Licensee Event Report Number Q11.g Title of occurrence 97-003 5/1/97 HPCI declared Inoperable.97-009 5/4/97 Both Trains of Standby Gas Treatment System inoperable due to Operator fuse replacement error.97-016 5/30/97 HPCI CCST Suction Check Valve failure.

NOTE: Sequence of LER Numbers is out of order due to reuse of numbers.

UNIT 2 Licensee Event Report Number Qalg Title of occurrence 97-004 4/14/97 MSIV 2-203-1A Limit Switch Outside of i

Tech Spec. Downgraded on 5/9/97 to PIR 2-97-018

)97-004 5/12/97 The Drywell Equipment Drain sump and the Drywell Floor Drain sump covers were constructed not in accordance with design drawings, which affected the accurate measurement of the Technical Specification for primary containment leakage, due to an original construction error.97-007 5/22/97 Drywell Torus Vacuum Breaker Cycling (Engineering Safety Feature Actuation).

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l V.

DATA TABULATIONS l

l 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 l

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I APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 j

UNrr One DATE June 10,1997 COMPLETED BY Kristal Sirles

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l TELEPHONE (309) 654-2241 OPERATING STATUS 0000 050197 l

1. REPORTING PERIOD: 2400 053197 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION GF ANY):

TH13 MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 3004.10 167513.30

6. REACTOR RESERVE SHtrrDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 744.00 2915.50 162444.40

8. UNTT RESERVE SHITTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENEROY GENERATED (MWH) 59809284.00 64755669.60 di1928552.10

10. OROSS ELECTRICAL ENERGY GENERATED (MWH) 564852.00 2164789.00 114586219.00 1

11. NET ELECTRICAL ENERGY GENERATED (MWH) 541949.00 2069889.00 108224858.00

12. REACTOR SERVICE FACTOR 100.00 82.92 76.02

13. REACTOR AVAILABILITY FACTOR 100.00 82.92 77.58

14. UNrr SERVICE FACTOR 100.00 80.47 73.72

15. UNrr AVAILABILrrY FACTOR 100.00 80.47 74.14

16. UNIT CAPActrY FACTOR (Using MDC) 94.72 74.29 63.87

17. UNIT CAPACrrY FACTOR (Using Design MWe) 92.32 72.41 62.25 i

18. UNIT FORCED OUTAGE RATE 0.00 19.53 7.73

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

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

21. UNTT3 IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FCRECAST ACHIEVED l

INrr!AL CRrrlCALrrY INTTIAL ELECTRICTTY COMMERCIAL OPERATION f

1.10-9 TECHOPS\\NRC\\ MONTHLY.Pfr

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W APPENDDC C OPERATING DATA REPORT DOCKET NO.

50-265 UNrr Two DATE June 10,1997 COMPLETED BY Kristal Sirles j

TELEPHONE (309) 654-2241 OPERATING STATUS 0000 050197

1. REPORTING PERIOD: 2400 053197 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY ALTillORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN E" UCTRICAL RATING (MWe-NCT): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 0.00 1408.30 161994.85

6. REACTOR RESERVE SHUTDOWN HOURS

').00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 1407.70 157657.05

8. UNir RESERVE SHUTDOWN HOURS 0.00 0.00 702.90 l

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 34772%I.20 343149370.02

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 1II 8808.00 110135945.00

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I1. NLT ELECTRICAL ENERGY GENERATED (MWH) 0.00 1076518.00 104396239.00

12. REACTOR SERVICE FACTOR 0.00 38.87 74.04

13. REACTOR AVAILABILrrY FACTOR 0.00 38.87 75.41

14. UNrr SERVICE FACTOR 0.00 38.85 72.06

15. UNTT AVAILABILrrY FACTOR 0.00 38.85 72.38

16. UNTT CAPACrrY FACTOR (Using MDC) 0.00 38.64 62.05

17. UNrr CAPActrY FACTOR (Using nesign MWe) 0.00 37.66 60.48 l

18. UNrr FORCED OUTAGE RATE 0.00 0.00 11.08 l

19. SHttrDOWNS SCHEDULED O*/ER NEXT 6 MONTils (TYPE DATE. AND DURATION OF EACil): N/A l

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20. IF SHirrDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: 6/12/97

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INfflAL CRrrICALrrY INrrtAL ELECTRICfrY COMMERCIAL OPERATION 1.1u-9 Tl! CHOP 3\\NRC\\MONTHI.Y.RI'r

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1 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE June 10. 1997 j

COMPLETED BY Kristal Sirles i

TELEPHONE (309) 654-2241 MONTH May. 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) j 1.

783 17.

258 2.

782 18.

225 3.

773 19, 400 4.

782 20.

738 5,

781 21, 775 6.

779 22.

775 7.

779 23.

775 8.

778 24, 766 9.

782 25.

773 10, 773 26.

776 11.

778 27.

775 12, 780 28.

776 13.

778 29.

777 i

14.

778 30.

777 15.

780 31.

739 16.

._ZZ5 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% lir,e (or the restricted power level line).

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

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l -g APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE June 10. 1997 COMPLETED BY Kristal Sirles TELEPHONE 1309) 654-2241 MONTH May. 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i

(MWe-Net)

(MWe-Net) 1.

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-8 2.

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-8 19.

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-8 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 neaomsacwonnexarr i

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l APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS I

DOCKET NO.

50-254 l

l UNIT NAME One COMPLETED BY Egistal Sirles

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l' DATE June 10, 1997 REPORT MONTH May, 1997 TELEPHONE 209-654-2241 a:

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i DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 97-09 5/17/97 F

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5 Performed Load Drop to repair leak on the l

Reactor Core Isolation Cooling 1 1301-17 j

Valve.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Sirles DATE June 10, 1997 REPORT MONTH May 1997 TELEPHONE 309-654-2241 A@

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 97-03 5/1/97 5

744 C

4 Continuation of Refuel Outage Q2Rl4.

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

I A. Main Steam Relief Valve Operations l

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

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.

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RESULTS OF SCRAM TIMING MEASUREMENTS T'

PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/97 To.05/31/97 l

l AVERAGE TIME IN SECONDS AT %

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l INSERTED FROM FULLY WITHDRAWN l FOR 90%

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DESCRIPTION l NUMBER 5

20 50 90 l

Technical Specification 3.3.C.1 E DATE

! OF RODS O.375 ! 0.900 2.00 3.5 7 sec.

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

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14 l 0.314 l 0.712 l 1.528 l 2.671 l

3.010 l STT for Viton Issue U-1 (Core Wid Ave. Times) l l

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3/29-31/97 21 l 0.316 l 0.708

' 1.513 2.645 3.010 l STT for Tech Spec (19) (Core Wide Ave. Times) l (J-14) l PMTV (2) l l

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ll 0.29 0.64 l 1.37 l: 2.4 3.010 l Post Maintenance Test for Accumulator Replacment l

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(J-14)

Unit 1 L

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14 0.354 0.725 1.497 l 2.576 2.77 STT for Viton Issue - U1 l

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.o; 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.

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g oJ QTP 0300-S32 Revision 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST 1.

Unit:

01 Reload:

14 Cycle:

15 2.

Scheduled date for next refueling shutdown:

3/28/98 3.

Scheduled date for restart following refueling:

5/29/98 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:

5/9/98 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 j

procedures:

Approx. 216 SPC 9X91X Fuel Bundles Q1R15 will be loaded.

7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1933 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:

3657 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can i

be discharged to the spent fuel pool assuming the present licensed capacity:

2002 (final)

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'J, QTP 0300-S32 Revision 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST 1.

Unit:

02 Reload:

14 Cycle:

15 2.

Scheduled date for next refueling shutdown:

3/1/97 3.

Scheduled date for restart following refueling:

6/12/97 4.

Will refueling or resumption of operation tre-ufter require a Technical Specification change or other license amendment:

Yes 5.

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

Submittals began August 1996; ongoing process.

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Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance j

analysis methods, significant changes in fuel design, new operating

\\

procedures:

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:

1933 l

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 spent fuel pool assuming l

the present licensed capacity:

2002 l

(final) 2 1

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