Text

Monthly Operating Rept for Aug 1994 for Quad Cities Nuclear Station
	ML20072V120
Person / Time
Site:	Quad Cities
Issue date:	08/31/1994
From:	Moore K, Scott A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	AMS-94-24, NUDOCS 9409190200
	Download: ML20072V120 (20)
	v • d • e

,

Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 AMS-94-24 1

l 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 i

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-261 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 August 1994.

I Respectfully, Comed Quad-Cities Nuclear Power Station b4, - [N, k

~

Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc:

J. Martin, Regional Administrator C. Miller, Senior Resident Inspector I

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9409190200 940831 PDR ADOCK 05000254 R

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QUAD-CITIES NUCLEAR POWER STATION i

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT August 1994 i

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\\ MONTHLY.RPT

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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 4

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 l

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 l

VII.

Refueling Information i

VIII.

Glossary l

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nruonwemosmur.arr 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 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 primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source..The plant is. subject to. license i

l 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.

I 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 began the month of August 1994 in cold shutdown.

The Refuel Outage Q1R13 ended on August 19, at 1408 hours0.0163 days 0.391 hours 0.00233 weeks 5.35744e-4 months when the reactor was made critical. The High Pressure Coolant Injection System was declared inoperable and the reactor was manually scrammed on August 21, at 0538. While repairs were being made to HPCI, the station decided to replace the seal on the IB Recirculation Pump. On August 25, at 2334 the reactor was again made critical and the generator was synchronized to the grid on August 28, at 1040 hours0.012 days 0.289 hours 0.00172 weeks 3.9572e-4 months .

B.

Unit Two Quad Cities Unit Two began the month of August 1994 at full capable power. On August 23, at 0827 hours0.00957 days 0.23 hours 0.00137 weeks 3.146735e-4 months a auto scram occurred when a Group 1 isolation occurred, which was caused by a spurious Main Steam Line high flow signal. The results of the root cause investigation was vibration on the instrument racks. On August 27, at 0445 the reactor was made critical and the generator was synchronized to the grid at 1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months . A forced load drop occurred on August 30, at 0006 due to loss of the 2A Recirc M-G set.

Inserted rods to below 70% Flow Control Line to avoid instability region. The unit was brought to full load on August 31, at 0925 hours0.0107 days 0.257 hours 0.00153 weeks 3.519625e-4 months .

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l 113 CHOP 3\\NRD. MONTHLY.RIT

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 Chances Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for -

the reporting period.

C.

Tests and Experiments Reauirina NRC Acoroval.

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

TECHOP3\\NRC\\ MONTHLY.RFr

IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-r 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.

4 UNIT 1 i

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l Licensee Event Report Number Date Title of occurrence i

94-006 08/08/94 Exposure from a Rad Source.94-008 08/20/94 HPCI IN0P.94-009 08/23/94 Inadequate review of source inventory.94-010 08/08/94 CR HVAC IN0P UNIT 2 Licensee Event Report Number Qalg Title of occurrence 1

94-006 08/23/94 Rx Scram from MSIV Closure.94-010 08/29/94 CRD D-11 Scrammed in.

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V.

DATA TABULATIONS I

The following. data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductiones i

i 1TCHOPnNRC\\ MONTHLY.RIT

a APPENDIX C j

OPERATING DATA REPORT DOCIG.T NO.

50-254 UNrr One l

DATE September 7, 1

1994 COMPLLTED BY Krimal Moors TELEPllONE (309) 654-2241 OPERATING STATUS 0000 080194

1. REPORTING PERIOD: 2400 083194 GROSS HOURS IN REPORTING Pf3tlOD: 744

2. CURRENTLY AUrllORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECIRICAL RATING (MWe-NET): 789 4

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

4. REASONS FOR RESTRICTION (IF ANY):

Tll!S MONTH YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRTTICAL 184.00 1890.00 151671.30

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 85.30 1768.20 147064.50

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 59524.80 3925318.90 317618506.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 12023.00 1277168.00 102975287.00

11. NLT ELECTRICAL flERGY GENERATED (MW10 4706.00 1211414.00 97129412.00

12. REACTOR SERVICE FACTOR 24.73 32.41 77.29

13. REACIDR AVAILABILTTY FACTOR 24.73 32.41 79.03

14. UNrr SERVICE FACTOR 11.47 30.32 74.94

15. UNrr AVAILABILITY FACTOR 11.47 30.32 75.40

16. UNrr CAPAcrTY 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 OUTAGE RATE 0.00 1.26 6.25

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EAC10:

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

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

FORECAST ACHIEVED INITIAL CRTTICALTTY INTTIAL ELECIRICrTY COMMERCIAL OPERATION 1.16-9 TirHOP3WRCWONTHLY.RFr

l APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 UNIT Two DATE September 7, 1994 COMPLLTED BY Kristal Moore TELEPHONE (309) 654-2241 l

OPERATING STATUS 0000 080194

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

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

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

4. REASONS FOR RESTRICTION (IF ANY):

j THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 651.70 4693.10 148594.15 1

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERA 7DR ON LINE 642.80 4616 3 0 144799.45 j

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWII) 1529260.50 10887670.20 313668632.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWII) 480868.00 3497100.00 100806870.00 i

11. NET ELECTRIC AL ENERGY GENERATED (MWH) 457714.00 3349445.00 95492005.00

12. PIACTOR SERVICE FACTOR 87.59 80.49 76.33

13. REACTOR AVAILABILITY FACTOR 87.59 80.49 77.86

14. UNIT SERVICE FACTOR 86.40 79.17 7438

15. UNrr AVAILABILrrY FACTOR 86.40 79.17 74.74

16. UNrr CAPACfrY FACTOR (Using MDC) 80.00 74.70 63.78

17. UNTT CAPACfrY FACTOR (Using Design MWs) 77.97 72.80 62.17

18. UNrr FORCED OLTTAGE RATE 13.60 20.82 8.98

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

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

21. UNTFS IN TEST STATUS (PR]OR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INrrIAL CRrrICALrrY INTrlAL ELECTRICrrY COMMERCIAL OPERATION 1.16-9 TECHOP3WRC\\MONDILY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One-DATE Seotember 7. 1994 COMPLETED BY Kristal Moore TELEPHONE- (309) 654-2241 MONTH Auaust 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

-8 2.

-8 18.

-8 3.

-8 19.

-8 j

4.

-8 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 7.

-8 23.

-10 8.

-8 24.

--10 9.

-8 25.

-10 10.

-8 26.

-13 11.

-8 27.

-12 12.

-8 28.

41 13.

-8 29.

113 14.

-8 30.

125 15.

-8 31.

161 16.

-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 TECHOP3iNRC\\MONTMLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE September 7. 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Auaust 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

~(MWe-Net)

(MWe-Net) 1.

752 17.

757 2.

753 18.

755 3.

752 19.

752 4.

751 20.

755 5.

749 21.

711 6.

754 22.

724 7.

721 23.

258 8.

753 24.

-9 9.

753 25.

-9 10.

756 26.

-12 11, 756 27.

135 4

12.

759 28.

732 13.

758 29.

747 14.

743 30.

232 15.

756 31.

508 16.

756 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 1TfHOP3\\NRC\\ MON"nILY.RPT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UN8T NAME One COMPLETED BY Kristal Moore DATE Senteniber 7, 1994 REPORT MONTH Aucust 1994 TELEPHONE 309-654-2241 1

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DURATION 8

EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS Continued Refuci Outage Q1R13 94-04 841-94 5

446.1 C

4 Manual Scram due to High Pressure Coolant 94-05 8-21-94 F

113.9 A

2 Injection System declared inoperable, i

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore I

DATE September 7, 1994 REPORT MONTH Auoust 1994 TELEPHONE 309-654-2241 l

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS a

NO.

DATE (HOURS)

REPORT Auto scram due to spurious Main Steam Line 94-11 8-23-94 F

923 A

3-Iligh Flow Signal Imd Drop due to 2A Recire MG Set Trip.

l 94-12 8-30-94 F

33.4 A

5 TECHOP3\\NRC\\ MONTHLY.RPT

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I VI. UNIOVE REPORTING RECUIREMENTS I

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, 1994 Valve Actuated:

No. & Tvoe of Actuation:

.1-203-3A 1 Manual

'i 1-203-3B 1 Manual l-203-3C 1 Manual i

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

920 psig Descriotion of Events:

Post maintenance.

Maili Two l

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Date: August 23, 1994 j

Valve Actuated:

2-203-3B ERV

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No. & Tvoe of Actuation: Automatic Plant Conditions:

Reactor pressure 1100 psig Descriotion of Events: Automatic actuation by pressure controller.

B.

Control Rod Drive Scram Timino Data for Units One and Two j

.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.

i 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.

i TECHOP3WRCiMON'!HLY.RPT

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

AVERAGE TIME IN SECONDS AT %

MAX. TIME j

INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION l

NUMBER l

5 20 1

50 90 Technical Specification 3.3.C.1 &

DATE I OF RODS I 0.375 ! 0.900 2.00 1

3.5 7 sec.

3.3.c.2 (Averace Scram Insertion Timel l

l 01-27-94 1

0.31 0.69 1.45 2.53 H-1 U1 for Maintenance 2.53 01-29-94 1

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0.33 l

0.73 1.51 2.58 L

M-10 U1 for Maintenance 2.58 01-29-94 177 l

0.32 0.69 1.46 2.56 H-3 U2 SEQ A & B for Tech Spec & Maintenance l

2.92 u

02-10-94 1

0.29 0.65 1.39 2.41 F-7 U1 F-7 for WR Q12855 l

i 2.41 l

02-19-94 1

0.31 0.69 1.45 2.53 H-1 U1 H-1 for WR Q14360 2.53 1

02-23-94 1

0.30 &

O.68 l'

1.45 2.62 J-3 U2 J-3 for WR Q14662 2.62 06-28-94 7

0.31 0.69 1.45 2.54 2.67 U2 H-5, H-3, E-5, D-13, H-11, D-5 L-3 for WR Q15111 SSPV 07-13-94 4

0.33 0.71 1.48 2.57 2.77 U2 K-13, B-7, D-7, E-4 08-31-94 177 0.30 0.68 1.45 2.54 2.80 l U1 BOC Q1c14 1

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VII.

REFVELING INFORMATION The following information about-future reloads at Quad-Cities Station was l

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 11GIOP3\\NRC\\ MONTHLY.RPr j

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QTP 300-532 Revision 2 0'AD CITIES REFUEL.ING October 1989 J

INFORMATION REQUE5T 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 licensing action and supporting information:

3-6-95 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:

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 capactty that has been requested or is planned in number of fuel assemblies:

a.

l.icensed storage capacity for spent fuel:

1657 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 cfinan 14/0395t DCT 3 01969 Q.C.O.S.R.

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

Unit:

Q2 Reload:

12 13 Cycle:

2.

Scheduled date for next refueling shutdown:

1-29-95 3.

Scheduled date for restart following refueling:

4-9-95 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.

S.

Scheduled date(s) for submitting proposed 11' censing action and supporting information:

7-28-94 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:

i 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 the present Itcensed capacity: 2006' APPROVED 4

(final)

M30N 14/0395t

- Q.C.O.S.R.

4 4

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