ML20093E514

Monthly Operating Repts for Sept 1995 for Quad Cities Nuclear Station

ML20093E514
Person / Time
Site:	Quad Cities
Issue date:	09/30/1995
From:	Moore K, Pearce L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-95-091, LWP-95-91, NUDOCS 9510160261
Download: ML20093E514 (20)

Text

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Commonwealth lason Company Quad Citics Generating Station 22710 2G6th Avenue North Cunhn a, 11.61242 97-10 Tei.unt s 122 ii LWP-95-091 October 5, 1995 4

U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 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 September 1995, i

Respectfully, Comed Quad-Cities Nuclear Power Station L. W. Pearce Station Manager LWP/dak Enclosure cc:

H. Miller, Regional Administrator C. Miller, Senior Resident Inspector STMORW9195.L%T T [$O 7

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PDR ADOCK 05000254 s

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.PDR A Unicom Company

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- s' QUAD-CITIES NUCLEAR POWER STATION 4

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT September 1995 COMMONWEALTH EDISON COMPANY i

AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECHOP3\\NRC\\MONTMLY.RPT J

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s' 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 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 VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary TECHOP3WRC\\MONTMLY.RPT

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 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.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One spent the month of September 1995 at full power and has been on line for 260 days. A load drop was taken on September 14, 1995 to perform Control Rod Pattern Adjustment. After the Control Rod Pattern Adjustment was completed, the Prime Computer failed affecting Core Monitoring Code.

Therefore, the scheduled load drop revolved into a forced load drop.

B.

Unit Two Quad Cities Unit Two started the month of September 1995 shutdown in a Forced Outage due to a auto scram that occurred during EHC Testing in the month of August. The reactor went critical on September 1,1995 at 2141 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.146505e-4 months <br /> and the generator was synched to the grid on September 2, 1995 at 1511 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.749355e-4 months <br />. A few load drops were performed, however the average daily level remained at 80% or greater.

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Snecifications Technical Specification Amendment No.157 was issued on June 23, 1995 to Facility Operating License DPR-29 and Amendment No. 153 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments would revise the Technical Specification Section 3/4.10 (Refueling Operations).

These changes are part of the Technical Specification Upgrade Program (TSUP).

Technical Specification Amendment No.158 was issued on July 27, 1995 to Facility Operating License DPR-29 and Amendment No. 154 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would revise the Technical Specification Section 3.3 (Reactivity Controls). These changes are part of the Technical Specification Upgrade _ Program (TSUP).

Technical Specification Amendment No.159 was issued on September 11, 1995 to Facility Operating License DPR-29 and Amendment No. 155 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments revise the Quad Cities Nuclear Power Station, Units 1 and 2, operating licenses to reflect the transfer of the Iowa-Illinois Gas and Electric Company's (IIGEC) 25 percent undivided ownership to Mid-American Energy Company.

i l-Technical Specification Amendment No.160 was issued on September 18, 1995 to Facility Operating License DPR-29 and Amendment No. 156 to l

Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would revise the Technical Specification l

Section 3/4.9 (Electrical Power Systems). These changes are part of the Technical Specification Upgrade Program (TSUP).

I Technical Specification Amendment No.161 was issued on September 20, i

1995 to Facility Operating License DPR-29 and Amendment No. 157 to l

Facility Operating License DPR-30 for Quad Cities Nuclear Power i

Station.

The amendments would revise the Technical Specification Section 3/4.1 (Reactor Protection Systems). These changes are part of l

the Technical Specification Upgrade Program (TSUP).

Technical Spacification Amendment No.162 was issued on September 21, 1995 to Facility Operating License DPR-29 and Amendment No. 158 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments would revise the Technical Specification Section 3/4.6 (Primary System Boundary). These changes are part of the Technical Specification Upgrade Program (TSUP).

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE B.

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

C.

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

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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 QAlg Title of occurrence 95-006 8-18-95 1A Recirc Pump speed increased Rx thermal.

This LER was downgraded.

UNIT 2 Licensee Event Reoort Number Qalg Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period.

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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 4

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNTT One DATE October 5,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 090195

1. REPORTING PERIOD: 2400 093095 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEFEND > 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 CRfriCAL 720.00 6319.80 158752.30

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 720.00 6264.00 154087.90

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1755983.00 15178836.10 334334959.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 557809.00 4840694.00 108304548.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 533277.00 4637876.00 102226042.00

12. REACTOR SERVICE FACTOR 100.00

%.47 77.17

13. REACTOR AVAILABillTY FACTOR 100.00

%.47 78.83

14. UNTT SERVICE FACTOR 100.00 95.62 74.90 1

15. UNTT AVAILABILTTY FACTOR 100.00 95.62 75.34

16. UNTT CAPACTTY FACTOR (Using MDC) 96.32 92.06 64.62

17. UNIT CAPACITY FACTOR (Using Design MWe) 93.87 89.73 62.98

18. UNTT FORCED OUTAGE RATE 0.00 4.38 7.36

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

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

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

FORECAST ACillEVED INTTIAL CRTTICALTTY INTTIAL ELECTRICITY COMMERCIAL OPERATION

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APPENDDC C OPERATING DATA REPORT DOCKET No.

50-265 UNrr Two DATE October 5,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 090195

1. REPORTING PERIOD: 2400 093095 GROSS HOURS IN REPORTING PERIOD: 720

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

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

4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 698.30 2659.80 152435.65

6. REACTOR RESERVE SHIJTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 680.80 2566.70 148498.35

8. UNrr RESERVE SHIITDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1423117.50 5197103.92 321137808.02

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 442821.00 1612020.00 103125921.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 422180.00 1528435.00 97684344.00

12. REACTOR SERVICE FACTOR

%.99 40.60 74.66 4

13. REACTOR AVAILABILITY FACTOR 96.99 40.60 76.13

14. UNrr SERVICE FACTOR 94.56 39.18 72.74

15. UNIT AVAILABILITY FACTOR 94.56 39.18 73.08 4

16. UNrr CAPACrrY FACTOR (Using MDC) 76.25 30.34 62.22

17. UNrr CAPActrY FACTOR (Using Design MWe) 74.32 29.57 60.64 l

18. UNIT FORCED OIITAGE RATE 5.42 11.21 9.95 j

19. SHlfrDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE AND DURATION OF EACH):

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

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

FORECAST ACHIEVED INrrlAL CRTTICALrrY INITIAL ELECTRICfrY COMMERCIAL OPERATION 1.10-9 TECHOP3\\NRC\\ MON 1HLY.RIT

1 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE October 5. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Seotember 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

739 17.

742 2.

739 18.

740 3.

747 19.

756 4

4.

750 20.

723 5.

752 21.

767 6.

754 22.

720 7.

754 23.

688 8.

756 24.

753 9.

755 25.

737 10.

751 26, 768 11, 754 27.

768 12.

760 28.

766 13, 754 29, 770 14.

557 30.

723 15.

712 31.

4 16.

749 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.

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE October 5. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Seotember 1995 j

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(NWe-Net) 1.

-9 17.

653 2.

38 18, 619 3.

301 19.

656 4.

373 20.

646 5.

333 21, 664 6.

423 22, 652 7.

514 23.

714 8.

593 24.

714 9.

661 25.

720 i

10.

652 26.

769 11.

667 27.

754 12.

668 28.

765 t

13.

667 29.

719 14.

660 30.

679 15.

657 31.

l 16, 657 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 l

may be occasions when the daily average power level exceeds the 100% line (or l

the restricted power level line).

In such cases, the average daily unit power l

output sheet should be footnoted to explain the apparent anomaly.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 l

UNIT NAME One COMPLETED BY Kristal Moore DATE October 5.

1995 REPORT MONTH Sent-her 1995 TELEPHONE 309-654-2241 a:

N O$h R-to e8 9

na a

n.

6 us LICENSEE i

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS Control Rod Pettern Adjustment 95 <)

9/14/95 s

0 H

5 i

Prinw Computer Failed Affecting Core 95-09 9/14/95 F

0 A

5 Monitoring Code TBCHOPS\\NRC\\ MON 1HLY RPT

e APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS i

DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE October 5.

1995 REPORT MONTH Sectamber 1995 TELEPHONE 309-654-2241 h

H oE x

=

MW M

M. o:

H0 p

0 po LICENSEE f

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT Cominued Forced Outage.

9543 941-95 F

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VI.

UNIOUE REPORTING REQUIREMENTS s

The following items are included in this report based on prior commitments to the commission:

A.

Main Steam Relief Valve Onerations l

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 Dater September 10, 1995 Valve Actuated:

No. & Tvoe of Actuation:

1-203-3A 1 Manual 1-203-3B 1 Manual 1-203-3C 1 Manual 1

1-203-3D 1 Manual 1-203-3E 1 Manual Plant Conditions:

Reactor Pressure 1002 psig Description of Events:

Surveillance Testing 4

i B.

Control Rod Drive Scram Timina Data for Units One and Two 4

There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.

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.s 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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QTP 300-S32 4

Revision 2 i

WAD CITIES REFUELING October 1989

)

INFORMATION REWEST 1

l 1.

Unit:

01 Reload:

13 I'

Cycle:

i 2.

Scheduled date for next refueling shutdown:

2/5/96 3.

Scheduled date for restart fo11owing ref'veling:

5/15/96 j

j 4.

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

no 4

i 5.

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

4 4

7-4-95 l

i 6.

Important Ilconsing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysts methoes, significant changes in fuel design, new operating j

procedures:

232 GE10 Fuel Bundles will be loaded during Q1E14.

1 i

7.

The number of fuel assemblies.

j a.

Number of assemblies in core:

724 j

b.

Number of assemblies in spent fuel pool:

1717 4.

The present licensed spent fuel pool storage capacity and the size ol' any increase in licensed storage capacity that has been requested or is l

Planned in number of fuel assemblies:

l a.

Licensed storage capacity for spent fuel:

3657

{

b.

Planned increase in licensed storage:

0 i

g.

The projected date of the last refueling that can be discharged to the i

{

spent fuel pool assuming the present Ilconsed capacity: 2006 i

?

APPROVED

\\

(finai)

OCT 3 08W 3

14/03gst.

Q.C.O.S.R.

' l-s QTP 300-532 Revision 2

@AD CITIES REFUELING October 1989 INFORMATION REWEST 1.

Unit:

Q2 Reload:

13 I'

Cycle-2.

Scheduled date for next refueling shutdown:

1-6-97 3.

Scheduled date for restart following refueling:

3-30-97 I

4.

Will refueling or resumption of operation thereafter require a Technical i

i Specification change or other license amendment:

YES l

J 5.

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

November, 1996 6.

Important Ilconsing 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. 200 Siemens 9X9IX Power Corporation Fuel Bundles will be i

loaded during Q2R14.

i 4

i 7.

The number of fuel assemblies.

{

a.

Number of assemblies in core:

724

{

b.

Number of assemblies in spent fuel pool:

3377 f

l 8.

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

planned in number of fuel assemblies:

l 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:

E APPROVED 14/0395t NE G.C.O.S.R.

e,

.,v VIII.

GLOSSARY The following abbreviations which may have been used in the Monthly 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

- Boiling Water Reactor CRD

- Control Rod Drive EHC

- Electro-Hydraulic Control System EOF

- Emergency Operations Facility GSEP

- Generating Stations Emergency Plan HEPA

- High-Efficiency Particulate Filter HPCI

- High Pressure Coolant Injection System HRSS

- High Radiation Sampling System IPCLRT

- Integrated Primary Containment Leak Rate Test 4

IRM

- Intermediate Range Monitor ISI

- Inservice Inspection LER

- Licensee Event Report LLRT

- Local Leak Rate Test LPCI

- Low Pressure Coolant Injection Mode of RHRs 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 PCIONR

- 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 TliCHOP3\\NRC\\ MON 1MLY.RIT

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