Text

Monthly Operating Repts for Aug 1995 for Quad Cities Nuclear Station
	ML20092F449
Person / Time
Site:	Quad Cities
Issue date:	08/31/1995
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-95-083, LWP-95-83, NUDOCS 9509180193
	Download: ML20092F449 (21)
	v • d • e

.

Osmmonwealth filmin Company f'

Quad Citits Generating Station 22710 206th Asenue Nonh Curdova, IL 61212 9' 40 Tel.MN 65 6-22 61 LWP-95-083 d

September 8, 1995 i

1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i

Washington, D.C. 20555 4

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report l

NRC Docket Nos. 50-254 and 50-265 4

Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, 1

during the month of August 1995.

Respectfully, Comed Quad-Cities Nuclear Power Station

.I

( (f,( Q L. W. Pearce Station Manager LWP/dak Enclosure cc:

H. Miller, Regional Administrator C. Miller, Senior Resident Inspector STMGRiO6395.L%?

pn9q J. V L : Qag 9509180193 950831 gDR ADOCK 05000254 hF PDR

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1 A l'nicom Company

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT August 1995 COMMONWEALTH EDISON COMPANY AND j

MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

TirHOP3WRC\\MONELY.RPT l

1 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 TECHOP3\\NRC\\ MON'lHLY.RFr l

l I.

INTRODUCTION l

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 l

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.

TirHOP3\\NRC\\ MONTHLY RPT

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One spent the month of August 1995 at full power and has been on line for 230 days. A few load drops were performed, however the average daily power level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two started tiie month of August 1995 shutdown in Refuel Outage Q2R13. The reactor went critical on August 2, 1995 at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months and the generator was synched to the grid on August 4, 1995 at 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months . A manual scram was performed due to EHC leak on the #6 CIV. After repairs, the reactor went critical on August 17, 1995 at 1124 hours0.013 days 0.312 hours 0.00186 weeks 4.27682e-4 months and the generator was synchronized to the grid on August 18, 1995 at 0436 hours0.00505 days 0.121 hours 7.208995e-4 weeks 1.65898e-4 months . A load drop was performed on August 19, 1995 l

for Feedwater Regulating Valve Testing. On August 25, 1995 at 0848 1

hours a auto scram occurred during EHC Testing and the unit remained off line for the rest of the month.

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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 Acorcval There were no Tests or Experiments requiring NRC approval for the reporting period.

17. CHOP 3WRCudONDiLY.RPT

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IV.

LICENSEE EVENT REPORTS The following is a tabular summary or 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 Qtta Title of occurrence 95-005 8-12-95 1/2 B CR HVAC Unit will not start.95-006 8-18-95 1A Recirc Pump speed increased Rx thermal.

UNIT 2 Licensee Event Report Number Qata Title of occurrence 95-005 8/25/95 RX Scram during EHC testing.

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nruonsacWONTHLY.RN

e V.

DATA TABULATIONS The following data tabulations are presented in this report:

l A.

Operating Data Report B.

Average Daily Unit Power Level i

C.

Unit Shutdowns and Power Reductions 4

3 4

4 TECHOPnNRCWONWLY.RFT

6 APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNrr One l

DATE Sepseneer 8, j

1995 j

1 COMPLETED BY Kristal Moore i

l TELEPHONE (309) 654-2241 I

OPERATING STATUS

- 0000 080195

't

1. REPORTING PERIOD 2400 083195 GROSS HOURS IN REPORTING PERIOD: 744 1

l

2. CURRElfrLY ALITHORIZED POWER LEVEL (MWI): 251i MAX > DEFEND > CAPACfrY: 769 DESION ELECTRICAL RATING (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MOffrH YR TO DATE CUMULATIVE i

l S. NUMBER OF HOURS REACTOR WAS CRTriCAL 744.00 5599.80 158032.30 i

4

6. REACTOR RESERVE SHtTTDOWN HOURS 0.00 0.00 3421.90 j

7. HOURS GENERATOR ON LINE 744.00 5544.00 153367.90

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1858498.00 13422853.10

' 332578976.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 580513.00 4282885.00 107746739.00 1

{

l1. NET ELECTRICAL ENERGY GENERATED (MWH) 552522.00 4104599.00 101692765.00 i

12. REACTOR SERVICE FACTOR 100.00

%.03 77.09 l

13. REACTOR AVAILABILrrY FACTOR 100.00

%.03 78.76 i

14. UNrr SERVICE FACTOR 100.00 95.08 74.81

('

15. UNrr AVAILABILrrY FACTOR 100.00 95.08 75.26

16. UNrf CAPACfrY FACTOR (Using MDC)

%.57 91.54 64.51

17. UNrr CAPACfrY FACTOR (Using Design MWe) 94.12 89.22 62.87 f

l

18. UNrr PORCED OLTTAGE RATE 0.00 4.92 7.40

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

l

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

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

t l

FORECAST ACHIEVED l

INrr!AL CRITICALrrY INrrtAL ELECTRICrTY COMMERCIAL OPERATION 1.1 +9 l:

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APPENDIX C i

OPERATING DATA REPORT j

DOCKET NO.

50-265 1

UNrr Two DATE September 8, 3

1995 COMPLETED BY Kristal Moore 1

TELEPHONE (309) 654-224I OPERATING STATUS 0000 080195

1. REPORTING PERIOD: 2400 083195 OROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPAcrTY: 769 DEslON ELECTRICAL RATING (MWe-NET): 789 1

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

4. REASON 3 FOR RESTRKTION (IF ANY):

e i

THIS MONTH YR TO DATE CUMULATIVE i

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 444.60 1961.50 151737.35

6. REACTOR RESERVE SHtTTDOWN HOURS 0.0 0.00 2985.80 f

7. HOURS GENERATOR ON LINE 371.00 1885.90 147817.55 i

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90 I

9. GROSS THERMAL ENERGY GENERATED (MWH) 410387.C; 3773986.42 319714690.52

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 104828.00 1169199.00 102683100.00 I

11. NET ELECTRICAL ENERGY GENERATED (MWH) 93771.00 1106255.00 97262164.00 l

j

12. REACTOR SERVICE FACTOR 59.76 33.64 74 58

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13. REACTOR AVAILABILrrY FACTOR 59.76 33.64 76.05 1

14. UNrr SERVICE FACTOR 49.87 32.34 72.66 4

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15. UNrr AVAILABILrrY FACTOR 49.87 32.34 73.00 i

16. UNTT CAPACTTY FACTOR (Using MDC) 16.39 24.67 62.D

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17. UNrr CAPACITY FACTOR (Using Design MWe) 15.97 24.05 60.59 i

18. UNIT FORCED OUTAGE RATE 43.45 13.13 9.97

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

^

I

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 9-1-95

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

FORECAST ACHIEVED INTTIAL CRTTICALTTY 1

INTilAL ELECTRICfrY COMMERCIAL OPERATION 1.1 i-9 I

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE Seotember 8. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH.Auaust 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

743 17.

741 2.

745 18.

740 3.

743 19, 737 4.

745 20.

743 5.

719 21.

743 i

6.

749 22.

742 7.

750 23.

743 8.

751 24.

745 9.

753 25.

740 I

10.

753 26.

727 11.

750 27.

739 12.

747 28.

741 13.

739 29.

741 14, 740 30, 738 15.

741 31.

738 16.

742 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 1TCHOP3\\NRC\\ MONTHLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE September 8. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Auaust 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-9 17.

-9 2.

-9 18.

195 3.

-9 19.

336 4.

14 20.

308 5.

109 21.

419 6.

106 22.

409 7.

120 23.

408 8.

117 24.

419 9.

159 25.

151 10.

197 26.

-9 11.

273 27.

-9 12.

284 28.

-9 13.

-9 29.

-9 14.

-9 30.

-9 15.

-9 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 TECHOP3\\NRC\\ MONTHLY.RPT 1

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE Sect - %r 8.

1995 REPORT MONTH Auoust 1995 TELEPHONE 309-654-2241 cc OE g

s.

$8 g

0$

EO 50 Bi 5

TIC.-

DURATION 8

EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS None l

I TECHOP3\\NRC\\ MONTHLY.RPT

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1 APPENDIX D l

UNIT SHUTDOWNS AND POWER REDUCTIONS 1

i DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore i

DATE September 8. 1995 REPORT MONTH Auoust 1995 TELEPHONE 309-654-2241 1

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i LICENSEE O

4 DURATION EVENT CORRECTIVE ACTIONS / COMMENTS i

_NO.

DATE (HOURS)

REPORT Continued Redbel Outage Q2Rl3.

05-05 08-01-95 5

88.0 =

C 4

Manual Scram due to EHC L4ak on CIV M.

95-06 08-12-95 F

125.8 A

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Auto scram during EHC Testing.

95-07 08-25-95 F

159.2 3

3 95-005 i

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TBCHOP3\\NRC\\ MONTHLY.RPT i

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 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: Two Date: August 3, 1995 Valve Actuated:

No. & Tvoe of Actuation:

2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure 924 psig Descriotion of Events:

Surveillance Testing Unit: Two Date: August 12, 1995 Valve Actuated:

Equ & Tvoe of Actuation:

2-203-3B 1 Hanual 2-203-3C 1 Manual 2-203-3D 1 Manual Plant Conditions:

Reactor Pressure 941 psig Description of Events:

Surveillance Testing Unit: Two Date: August 12, 1995 Valve Actuated:

No. & Tvoe of Actuation:

2-203-3E 1 Manual Plant Conditions:

Reactor Pressure 944 psig Descriotion of Eventsi Surveillance Testing 1TCHor$\\NRC\\ MON 1HLY.RPT

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I 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.

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i 1ECHOP3\\NRC\\ MON 1MLY.RFr

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m RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL I

ROD DRIVES, FROM 01/01/95 TO 07/31/95 i

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l AVERAGE TIME IN SECONDS AT %

l MAX. TIME l l

l INSERTED FROM FULLY WITHDRAWN l FOR 90%

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! INSERTION !

DESCRIPTION l NUMBER i

5 20 1

50 90 l

Technical Specification 3.3.C.1 &

l DATE

! OF RODS ! O.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 fAveraae Scram Insertion Tipne) l l

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177 l 0.31 0.70 l

1.47 l

2.57 l

3.30 l

Post Maintenance after Q1F35 Seq A, B, Done i

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C4/28/95 l

1 l 0.29 l 0.65 l

1.42 l

2.48 2.48 l Q18840 to torque Scram Inlet Valve Packing.

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I L14 l

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06/24/95 l

1 l 0.30 l 0.65 ll 1.37 2.41 l

2.41 l Diagnostic Testing of U-1 H-9 l

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H-9 l

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l 07/03/95 l

172 1 0.31

! 0.71 l

1.55 t

2.71 3.15 BOC for Q2C14 l

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l K10 W

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l 03/05/95 l

20 0.30 j O.67 1.41 l

2.46 l

2.65 10% for new Tech Spec i

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K-2 l

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08/05/95 l

54 1 0.32 j 0.70 1

1.48 l

2.58 l

3.02 Remainder of BOC for Q2C performed.

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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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i QTP 300-S33 Revision 2 QUAD CITIES REFUELING October 1989

{

INFORMATION REQUEST 1.

Unit:

Q1 Reload:

13 l'

Cycle:

l 2.

Scheduled date for next refueling shutdown:

2/5/96 3.

Scheduled date for restart following ref'ueling:

5/15/96 4.

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

3 NO 5.

Scheduled date(s) for submitting proposed Itcensing action and i

supporting information:

7-4-95 I

6.

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

procedures:

1 232 GE10 Fuel Bundles will be loaded during Q1R14.

i 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 j

planned in number of fuel asseabites:

a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in licensed storage:

0 i

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the'present Itcensed capacity: 2006 APPROVED (finai)

DCT 3 099 14/0395t A.C.O.S.R.

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

1.

Unit:

Q2 Reload:

13 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 amendment:

i l

YES I

S.

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 changes in fuel design, new operating procedures:

i Approx. 200 Siemens 9X91X Power Corporation Fuel Bundles will be loaded during Q2R14.

1 1

j 7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 D.

Number of assemblies in spent fuel pool:

3377

)

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 assembites:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 4

9.

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

j APPROVED i

14/0353c C1.C.O.S.R.

e 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