ML20076G583

Monthly Operating Repts for Sept 1994 for Quad Cities Nuclear Station Units 1 & 2

ML20076G583
Person / Time
Site:	Quad Cities
Issue date:	09/30/1994
From:	Moore K COMMONWEALTH EDISON CO.
To:
Shared Package
ML20076G581	List: ML20076G577 ML20076G583 ML20076G591
References
NUDOCS 9410200087
Download: ML20076G583 (20)

Text

,

y-1 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT 1

September 1994 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECHOP3\\NRC\\MONTELY.RIT 9410200087 941004 PDR ADOCK 05000254 R

PDR

TABLE OF CONTENTS 1.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related M41ntenance 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 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 TD3mPhNm3MOYnn.YJPT

]

I.

JBIR0 DUCTION 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 Comn.onwealth 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 priinary 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.

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TFrHOP3\\NRC\\ MONTHLY.RPT

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.II.

SUMMARY

OF OPERATING EXPERIENC.E A.

Unit One-Quad Cities Unit One was on-line the entire month of September 1994, but did not reach full capable load until September 24.

There were no significant load drops.

B.

Unit Two Quad Cities Unit Two was on-line the entire month of September 1994 at full capable power. On September 11, C MSIV's were closed for maintenance on dP switch, load drop to 340 MWe. On September 20, a load reduction was performed to monitor a hot spot on B phase of main transformer.

Several other load drops were performed, but did not cause the average daily power level to decrease by greater than 20%.

TECHOP3\\NRC\\ MON 1RLY.RPT

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

i-1 TEC} LOP 31NRC\\ MON'DiLY.RIT

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 6.6.8.1 and 6.6.8.2 of the Technical Specifications.

UNIT 1 Licensee Event Reoort Number Qalg Title of occurrengg 94-011 08-29-94 CRD Failed Scram.

UNIT 2 Licensee Event Report Number Q11g Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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TECHOP3\\N RC\\ MONTHLY.RPT

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l 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 TToiOIS\\NRC\\ MON 1HLY.RPT

APPENDDC C OPERATING DATA REPORT DOCKET NO.

50-254 UNrr One DATE October 7,1994 COMPLETED BY Kristal Moore TELEPilONE (309) 654-2241 OPERATING STATUS 0000 090194

1. REPORTING PERIOD: 2400 093094 GROSS HOURS IN REPORTING PERIOD. 720

2. CURRENTLY AITrilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACrrY: 769 DESIGN ELECTRICAL RATING (MWe-NLT): 789

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

4. REASONS FOR RESTRICrlON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUM11ER OF IIOURS REACTOR WAS CRrTICAL 720.00 2610.00 152391.30

6. REAC. OR RESERVE SHttrDOWN HOURS 0.00 0.00 3421.90 T

7. IIOURS GENERATOR ON LINE 720.00 2486.90 147783.20

8. UNTT RESERVE SillTrDOWN IIOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1468502.40 5393821.30 319087008.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWif) 465065.00 1742233.00 103440352.00

11. NET ELECTRICAL ENERGY GENERATED (MWil) 443013.00 1654427.00 97572425.00

12. REACTOR SERVICE FACTOR 100.00 39.84 77.37

13. REACTOR AVAILABILrrY FACTOR 100.00 39.84 79.11

14. UNrr SERVICE FACTOR 100.00 37.96 75.03

15. UNrr AVAILABILrrY FACTOR 100.00 37.96 75.49

16. UNrr CAPActrY FACTOR (Using MDC) 80.01 32.84 64.42

17. UNTT CAPAcrTY FACTOR (Using Design MWe) 77.98 32.01 62.79

18. UNrf FORCED OtrTAGE RATE 0.00 0.90 6.22

19. SIIUrDOWNS SCHEDULED OVER NEXT 6 MONTils (TYPE, DATE, AND DURATION OF EACH):

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

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACIIIEVED INrr!AL CRrTICALrrY INITIAL ELECTRICrTY COMMERCIAL OPERATION 1.10-9 TIrHOM\\NRC\\ MONTHLY.RI'r

APPENDIX C OPERATING DATA REPORT DOCKET NO.

50 265 UNrr Two DATE October 7,1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-224I OPERATING STATUS 0000 090194

1. REPORTING PERIOD: 2400 093094 GROSS HGURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTiiORIZED POWER LEVEL SfWt): 2511 MAX > DEPEND > CAPACITY: 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 IIOURS REACTOR WAS CRITICAL 720.00 5413.10 149314.15

6. REACTOR RESERVE Sl!UTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GFNERATOR ON LINE 720.00 5336.30 145519.45

8. UNrr RESEkVE SillTfDOWN HOURS 0.00 0.00 702.90

9. GROSS TIIERMAL ENERGY GENERATED (MWH) 1742027.30 12629697.50 315410659.40

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 548805.00 4045905.00 101355675.00

11. NET ELECIRICAL ENERGY GENERATED (MWH) 524203.00 3873648.00 96016108.00

12. REACTOR SERVICE FACTOR 100.00 82.63 76.41

13. REACTOR AVAILABILrrY FACTOR 100.00 82.63 77.94

14. UNrr SERVICE FACTOR 100.00 81.46 74.47

15. UNIT AVAILABILfrY FACTOR 100.00 81.46 74.83

16. UNrr CAPACfrY FACTOR (Using MDC) 94.68 76.89 63.90

17. UNIT CAPACfrY FACTOR (Using Design MW )

92.28 74.94 62.28

18. UNrr FORCED OLTTAGE RATE 0.00 18.54 8.94

19. SHITTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACil):

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

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACillEVED INrrtAL CRTTICALTTY INrflAL ELECTRICITY COMMERCIAL OPERATION

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1.10 9 TirHOPhNRC\\ MONTH 1.Y.Rii

i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE October 4. 1994 i

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTil Seotember 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

168 17.

655 2.

346 18.

657 3.

333 19.

654 4.

415 20.

721 j

5.

413 21.

758 6.

499 22.

761 7.

556 23, 768 8.

487 24.

775 9.

429 25.

773 10, 561 26.

773 11.

569 27.

775 12.

660 28.

755 13.

660 29.

760 14.

662 30.

775 15.

663 31.

16.

663 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. Ttese 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 TirHOP3\\NRC\\MONTHl.Y,RPT

i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE October 4. 1994 COMPLETED BY Kristal Moore

-s TELEPHONE (309) 654-2241

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MONTH September 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

747 17.

747 2.

751 18.

725 3.

744 19.

730 4.

626 20.

562 5.

639 21.

701 6.

729 22.

750 7.

745 23.

742 8.

757 24.

757 9.

758 25.

750 10.

744 26.

756 11.

569 27.

762 12.

753 28.

758 13.

753 29.

761 14.

"152 30.

763 15.

749 31.

16.

l'4 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 te 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 powcr level line).

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

1.16-8 TicirPnNRt Af0NTHLY.RPT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE October 6, 1994 REPORT MONTH September 1994 TELEPHONE 309-654-2241 17'

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DURATION EVENT a

NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS None

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l

DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE October 6, 1994 REPORT MONTH September 1994 TELEPHONE 309-654-2241 i

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$8

$8 LICENSEE 8

DURATION 8

EVENT CORRECTIVE ACTIONS / COMMENTS 24 0.

DATE (HOURS)

REPORT C MSIVs Cosed for Maintenance on dP H-13 09-11 94 S

0.0 5

Switch.

Imd Reduction to Monitor Ilot Spot on B 96 14 09-20 94 S

0.0 5

Phase of Main Transformer.

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TirHOPhNRC\\ MONTHLY.RFT

VI. UNIOUE 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 period.

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.

TFfHOP3\\NRC\\ MONTHLY.RPT

RESULTS OF SCRAM TIMING MEASUREI2NTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 l

l AVERAGE TIME IN SECONDS AT %

! MAX. TIME l l

l INSERTED FROM FULLY WITHDRAWN l FOR 90%

l

! INSERTION !

DESCRIPTION l NUMBER j

5 20 50 90 l

Technical Specification 3.3.c.1 &

DATE

! OF RODS

! 0.375 ! 0.900 2.00 1

3.5 7 sec.

3.3.c 2 (Averace Scram Insertion Time) i i

l l

l 01-27-94 l

1 O.31 !

0.69 l

1.45 l

2.53 H-1 U1 for Maintenance l

l 2.53 i

i l

l 01-29-94 l

1 0.33 l 0.73 1

1.51 l

2.58 M-10 U1 for Maintenance l

2.58 i

01-29-94 l

177 l

0.32 l 0.69 l

1.46 l

2.56

'l H-3 L U2 SEQ A & B for Tech Spec & Maintenance l

l l

l l

2.92 l

l 1

l 02-10-94 1

l 0.29 l 0.65 1.39 l

2.41 F-7 U1 F-7 for WR Q12355 l

l l

2.41 I

l l

l H

O2-19-94 1

l 0.31 j 0.69 1.45 2.53 H-1 Ul H-1 for WR Q14360 l

l 2.53 l

l l

02-23-94 l:

1 l

0.30 l 0.68 l

1.45 l

2.62 l

J-3 U2 J-3 for WR Q14662 l:

l l

2.62 1

06-28-94 l

7 l

0.31 !

0.69 l

1.45 2.54 l

2.67 U2 H-5, H-3, E-5, D-13, H-11, D-5 l

l l

l L-3 for WR Q15111 SSPV l

l l

07-13-94 4

l 0.33 0.71 l

1.48 2.57 2.77 U2 K-13, B-7, D-7, E-4 l

l 08-31-94 l

177 l

0.30 l 0.68 ll 1.45 l

2.54 2.80 l U1 BOc Q1c14 1

09-28-94 1

0.32 0.69 1.47 l

2.55 2.55 U1 M-10 Q18064 L

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l 09-30-94 l

2 ll 0.28 l 0.61 l

1.27 l

2.24 l

2.26 l U2 F-1, B-5 for WR Q18123, Q18116 l

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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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TTCHOP3\\NRC\\ MON 1HLY.RfT

QTP 300-532 Revision 2 QUA0 CITIES REFUEL 8NG October 1989 INFORMATION REQUEST 1.

Unit:

Q1 Reload:

13 Cycle:

2.

Scheduled date for next refueling shutdown:

9-6-95 3.

' Scheduled date for restart following refueling:

12-24-95 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 itcensing action and supporting information:

I 3-6-95 1

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:

1 7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1717 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:

Licensed storage capactty for spent fuel:

a.

16s7 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:

2006 APPROVED 14/0395t 30W C).C.O.S.R.

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

Unit:

Q2 Reload:

12 Cycle:

2.

Scheduled date for next refueling. shutdown:

1-29-95 3.

Scheduled date for restart following refueling:

5-21-95 4.

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

YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel.

Change TS at end of Cycle 13 operation.

5.

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

Approved June 10, 1994 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:

144 GE10 fuel bundles will be loaded during Q2R13.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2583 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 1

9.

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

2006 APPROVED i

14/0395t 1-G.C.O.S.R.

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VIII. GLOSSARY r

The following abbreviations which may have been used in the Monthly Report, are defined below:

1 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

- Boiling Water Reactor CR0

- Control Rod Drive i

EHC

- Electro-Hydraulic Control System l

EOF

- Emergency Operations Facility GSEP

- Generating. Stations Emergency P1an HEPA

- High-Efficiency Particulate Filter HPCI

- High Pressure Coolant Injection System HRSS

- High-Radiation Sampling System IPCLRT

- Integrated Primary Containment Leak Rate Test IRM

- Intermediate Range Monitor L

ISI

- Inservice Inspection LER

- Licensee Event Report LLRT

- Local Leak Rate Test LPCI

- Low Pressure Coolant Injection Mode of RHRs 1

LPRM

- Local Power Range Monitor MAPLHGR

- Maximum Average Planar Linear Heat Generation Rate MCPR

- Minimum Critical Power Ratio MFLCPR

- Maximum Fraction Limiting Critical Power Ratio MPC

- Maximum Permissible Concentration MSIV

- Main Steam Isolation Valve NIOSH

- National Institute for Occupational Safety and Health PCI

- Primary Containment Isolation PCIOMR

- Preconditioning Interim Operating Management Recommendations RBCCW

- Reactor Building Closed Cooling Water System RBM

- Rod Block Monitor RCIC

- Reactor Core Isolation Cooling System RHRS

- Residual Heat Removal System RPS

- Reactor Protection System RWM

- Rod Worth Minimizer SBGTS

- Standby Gas Treatment System SBLC

- Standby Liquid Control SDC

- Shutdown Cooling Mode of RHRS SDV

- Scram Discharge Volume SRM

- Source Range Monitor TBCCW

- Turbine Building Closed Cooling Water System TIP

- Traversing Incore Probe TSC

- Technical Support Center TECHOP3\\NRC4f0NTHLY RfT

APPENDIX C j

OPERATING DATA REPORT DOCKLT NO.

50-154 UNrr One DATE October 7,1994

]

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 080194

1. REPORTING PERIOD: 2400 083194 GROSS IlOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL 184.00 1890.00 151671.30

6. REACTOR RESERVE SilUTDOWN HOURS 0.00 0.00 3421.90

7. IlOURS GENERATOR ON LINE 84.00 1768.20 147064.50

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MW10 59524.80 3925318.90 31761 3 06.10

10. GROSS ELECTRICAL ENERGY GENERATED (MW10 12023.00 1277168.00 102975287.00

11. NET ELECTRICAL ENERGY GENERATED (MW10 4706.00 1211414.00 97129412.00

12. REACTOR SERVICE FACTOR 24.73 32.41 77.29

13. REACTOR AVAILABILTrY FACTOR 24.73 32.41 79.03

14. UNTT SERVICE FACTOR 11.47 30.32 74.94

15. UNTT AVAILABILTTY FACTOR 11.47 30.32 75.40

16. UNTT CAPACTTY FACTOR (Using MDC) 0.82 27.02 64.36

17. UNrr CAPACITY FACTOR (Using Design MWe) 0.80 26.33 62.73 18 UNrr FORCED OITTAGE RATE 0.00 1.26 6.25

19. SHUrDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACID:

20. LF SillTIDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNTFS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INTTIAL CRITICALITY INrrIAL ELECTRICfrY COMMERCIAL OPERATION s.16-9 TIrHOP3\\NRCat0NuiLY.RIT l