ML20072D722

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Monthly Operating Repts for July 1994 for Quad-Cities Nuclear Station Units 1 & 2
ML20072D722
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/31/1994
From: Moore K, Scott A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-21, NUDOCS 9408190208
Download: ML20072D722 (20)
v • d • e


Text

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l Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Corclova, Illinois 61242 )

Telephone 309/854-2241 l

l AMS-94-21 August 4, 1994 >

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 July 1994.

Respectfully, i Comed Quad-Cities Nuclear Power Station Anthony M. Scott System Engineering Supervisor s

.AMS/dak-Enclosure .

I cca J. Martin, Regional' Administrator .

C. Mllier, Senior Resident Inspector i

100077 TECHOP3WRCalOKn{LY,Rrf 9408190208 940731 PDR

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R-ADOCK 05000254 PDR

i QUAD-CITIES NUCLEAR POWER STATION l 1

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i UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT July 1994 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 t

TIDlOP3bNRCufOND{LY.RPT l

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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 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 1

A. Operating Data Report ,

B. Average Daily Unit Power Level l 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 i

VIII. Clossary l

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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 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 numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, I

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 entire month of July 1994 shutdown in Refuel Outage QlR13. The scheduled startup for. Unit One is August 13, 1994.

B. Unit Two Quad Cities Unit Two began the month of July 1994 in cold shutdown as repairs were made to Transformer 22. The unit was made critical at 0639 hours0.0074 days <br />0.178 hours <br />0.00106 weeks <br />2.431395e-4 months <br />, and synchronized to the grid at 2130 on July 12.

On July 22, power was reduced to perform QCOs 5600-4, cIV testing.

The average daily power level remained above 80% of full power.

A load drop was performed on July 30, as requested from Bulk Power Operations (BPO) which caused the average daily unit power level to drop by 20%.

Several other load drops were performed per Bulk Power Operations (BPO) which did not cause the average daily power level to decrease by greater than 20%.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Soecifications Technical Specification Amendment No. 148 was issued on July 6, 1994 to Facility Operating License DPR-29 and Amendment No. 144 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments add new hydraulic enubbers on the main steam lines to the Technical Specifications (TS) and also change the snubber visual inspection interval and corrective actions in TS Section 3.6.1 and 4.6.1 to the format and content of Boiling Water Reactors (BWR)

Standardized Technical Specifications (STS), as revised by Generic Letter 90-09.

Technical Specification Amendment No. 149 was issued on July 13, 1994 to Facility Operating License DPR-29 and Amendment No. 145 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments revise Technical Specification 3/4.7.D, " Primary Containment Isolation Valves" by adding check valves installed in the i reference leg instrumentation line to the Limiting Condition for Operation (LCO) statement of the Technical Specification. The valves have been installed as part of the modifications required to meet NRC Bulletin 93-03, " Resolution of Issueu Related to Reactor Vessel Water Level Instrumentation in BWR".

B. Facility or Procedure Chances Recuirino NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Exoeriments Recuirina NRC Acoroval l

There were no Tests or Experiments requiring NRC approval for the I 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 Ronort Number Date Title of occurrence 94-007 04/01/94 HPCI Restricting Orifice plugged.

UNIT 2 Licensee Event Poport Number Date Title of occurrence 94-005 06/21/94 Manual Rx Scram Due to EHC Oil Leak.

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I 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 l

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l APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNrr One DATE August 4,1994 COMPLLTED BY Kristal Moore TELEPIIONE (309) 654-2241 OPERATING STATUS 0000 070194

1. REPORTING PERIOD: 2400 073194 GROSS IlotJRS IN REPORTING PERIOD: 744
2. CURRENTLY AUTilORIZED POWER LEVEL (MWy: 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NLT): 789
3. POWER LEVEL TO W}{ICil RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (!F ANY):

TIIIS MONTil YR TO DATE CUMULATIVE

5. NUM11ER OP llOURS R.EALTOR WAS CRTTICAL 0.00 1706.00 151487.30
6. REALTOR RESERVE SIIUTDOWN IIOURS 0.00 0.00 3421.90
7. IlOURS GENERATOR ON LINE 0.00 1682.90 146979.20 8, UNIT RESERVE SillTTDOWN IIOURS 0.00 0.00 009.20
9. GROSS TIIERMAL ENERGY GENERATED (MW10 0.00 3865794.10 317558981.30
10. GROSS ELECTRICAL ENERGY GENERATED (MW10 0.00 1265145.00 102963264.00
11. NLT ELECTRICAL ENERGY GENERATED (MW10 0.00 1206708.00 97124706.00
12. REACTOR SERVICE FACTOR 0,00 33.54 77.49
13. REACTOR AVAILABILITY FACTOR 0.00 33.54 79.24
14. UNrr SERVICE FACTOR 0.00 33.08 75.18
15. UNrr AVAILABILrrY FACTOR 0/.0 33.08 75.65
16. UNIT CAPACirY FACTOR (Using MDC) 0.n0 30.85 64.60
17. UNrr CAPACirY FACTOR (Using Design MWe) 0.00 30.07 62.97
18. UNrr FORC6D OUTAGE RATE 0.00 1.33 6.25
19. SilUTDOWNS SCIIEDULED OVER NEXT 6 MONTils (TYPE, DATE. AND DURATION OF EACIO:
20. IF SilUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 8-13-94
21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRrrlCALTTY INrrlAL ELECTRICrrY COMMERCIAL OPERATION 1.16-9 TECl10P3\NRC\MONTlfLY.RIT  ;

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APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNTT Two DATE August 4,1994 COMPLETED BY Kristal Moore TELEPilONE (309) 654-224I OPERATING STATUS 0000 070194

1. REPORTING PERIOD: 2400 073194 GROSS llOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWo-NLT): 789
3. POWER LEVEL TO WlilCII RESTRICTED GF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION GF ANY):

TIIIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRfflCAL 473.40 4041.40 147942.45
6. REACTOR RESERVE SIIUTDOWN HOURS 0.00 0.00 2985.80
7. IIOURS GENERATOR ON LINE 458.50 3973.50 144156.65
8. UNTT RESERVE SliUTDOWN HOURS 0.00 0.00 702.90 l
9. GROSS TilERMAL ENERGY GENERATED (MW10 1093753.80 9358409.70 312139371.60
10. GROSS ELECTRICAL ENERGY GENERATED (MW10 343525.00 3016232.00 100326002.00
11. Nirr ELECTRICAL ENERGY GENERATED (MWlO 327200.00 2891731.00 95034291.00 i
12. REACTOR SERVICE FACTOR 63.63 79.45 76.28 i
13. REACTOR AVAILABILrrY FACTOR 63.63 79.45 77.82
14. UNIT SERVICE FACTOR 61.63 78.11 74.33 j
15. UNrr AVAILABILTTY FACTOR 61.63 78.11 74.69
16. UNrr CAPACTTY FACTOR (Using MDC) 57.19 73.92 63.72
17. UNTT CAPACrrY FACTOR (Using Design MWe) 55.74 72.05 62.11
18. UNTT FORCED OtfrAGE RATE 38.33 21.88 8.96
19. SlitTTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EAC10:
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED D ATE OF STARTUP:
21. UNTFS IN TEST STATUS (PRIOR TO COMMTRCIAL OPERATION):

FORECAST ACHIEVED INTrtAL CRrrlCALITY INTilAL ELECTRICITY COMMERCIAL OPERATION 1.16 9 TTCllOP3\NRC\ MON'ntl1RPF

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE Auoust 4. 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH July 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. - 5 17. - 8
2. -7 18. - 8
3. -6 19. - 8
4. -6 20. - 8
5. -5 21. - 8
6. -5 22. - 8
7. -6 23. - 8
8. -5 24. - 8
9. -5 25. -

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10. -7 26. - 8
11. -9 27. - 8
12. - 10 28. - 8
13. -8 29. - 8
14. -8 30. - 8
15. -8 31. -

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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 i output sheet should be footnoted to explain the apparent anomaly. I 1.16-8 TDNIOPMNROMONDILYJWT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE Aucust 4, 1994 COMPLETED BY Kristal Mpore TELEPHONE (309) 654-2241 MONTH July 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -4 17. 744
2. -6 18. 721
3. -6 19. 747
4. -6 20. 753
5. -5 21. 754
6. -4 22. 745
7. -5 23. 754
8. -5 24, 694
9. -5 25, 754
10. -7 26. 757
11. -8 27. 743
12. -1 28. 735
13. 490 29. 742
14. 698 30. 638
15. 730 31. 753
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 TirHOP3\NRC\MONUR.Y.Rii

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOcttET NO. 50-254 UNIT WAME One COMPLETED BY Kristal Moore DATE Aucust 4, 1994 REPORT HONTH July 1994 TELEPHONE 29,9-654-2241 M

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H g na $8 38 DURATION

$$ LICENSEE EVENT O

@ CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 944)4 74)l-94 S 744.0 C 4 ------- -- --- ---- Continued Refuel Outage Q1R13 l

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APPENDIX 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Aucust 4. 1994 REPORT MONTH July 1994 TELEPHONE 309-654-2241 N H m m 00 X

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$ 08 @8 8 DURATION

$$ LICENSEE EVENT 8

CORRECTIVE ACTIONS / COMMENTS 8

NO. DATE (HOURS) REPORT 94 4 741-94 F 285.5 A 2 ---- ---- -- ---- Continued Cold shutdown to repair T-22.

94-10 7-30-94 S 5.4 F 5 --------- --- -- Load Drop request from Bulk Power Operations. (BPO).

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l VI. UNIOUE REPORTING REOUIREMENIS The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Ooerations Relief valve operatione 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: July 12, 1994 Valve Actuated: 2-203-3E No. & Tvoe of Actuation: 1 Manual Plant conditions: 920 psig Description of Events: Post maintenance testing on unit startup.

1 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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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 l l AVERAGE TIME IN SECONDS AT % l MAX. TIME l l l INSERTED FROM FULLY WITHDRAWN l FOR 90%  !

!  !  ! INSERTION ! DESCRIPTION j NUMBER  ! 5  ! 20  ! 50  ! 90  ! l Technical Specification 3.3.C.1 &

DATE  ! OF RODS ! O.375 ! O.900  ! 2.00 ! 3.5  ! 7 sec.  ! 3.3.C.2 (Averace Scram Insertion Time) l l i  ! l l t 01-27-94 l 1 l 0.31 l 0.69 1.45 l 2.53 i H-1 l U1 for Maintenance '

l l l l l 2.53 l l l l l  !  ! l 01-29-94 l 1 l 0.33 1 0.73  ! 1.51 ! 2.58 M-10 l U1 for Maintenance l l l j 2.58

! I 01-29-94 l 177 l 0.32 l 0.69 l 1.46 '

2.56 l H-3 l U2 SEQ A & B for Tech Spec & Maintenance I l l l l } 2.92 l i l l l 02-10-94 , 1 l 0.29 0.65 1.39 ll 2.41 . F-7 l U1 F-7 for WR Q12855 l l l ll l l 2.41  !

! l l l l l 02-19-94  ! 1 l 0.31 l 0.69 1.45 1 2.53 l H-1 l U1 H-1 for WR Q14360

!  ! .  ! l 2.53 l

!  !  ! l ll l; O2-23-94 l 1 1 0.30 l 0.68 1.45 2.62 J-3 ll U2 J-3 for WR Q14662 l l l 2.62 l l l ,

06-28-94 l 7 l 0.31 l 0.69 1 1.45 l, 2.54 2.67 l U2 H-5, H-3, E-5, D-13, H-11, D-5 l !_ l l l l L-3 for WR Q15111 SSPV i i  !

07-13-94 l 4 l O.33 . 0.71 1.48 l 2.57 2.77 U2 K-13, B-7, D-7, E-4 l l l l  ! ,

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, . l VII. REFUELING INFORMATION )

I 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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- ' OTP 300-532 Revision 2

' QUAD CITIES REFlJELING October 1989 INFORMATION REQUEST

1. Unit: 01 Reload: 12 Cycle: 1
2. Scheduled date for next refueling shutdown: 3-13-94
3. Scheduled date for restart following refueling: 8-13-94
4. W111 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. This change has already been implemented.

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

11-19-93 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 have been loaded during Q1R13.

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:
a. Licensad storage capacity for spent fuel: 3657
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 -1 OCT 3 01989 C1.C.O.S.R.

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, . . QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 12 13

1. Unit: Q2 _

Reload: 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.

5. Scheduled date(s) for submitting proposed licensing 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:

a. Licensed storage capacity for spent fuel: 3897
b. Planned increase in licensed storage: '0 4

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9. The projected date of the last refueling tilat can be discharged to the spent fuel pool assuming the present licensed capactty: 2006~

APPROVED ,

cfinai) OCT 3 01989 l 14/0395t l Q.C.O.S.R.

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a 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 CSEP - Generating Stations Emergency Plan HEPA -

High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System

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IPCLRT -

Integrated Primary Containment Leak Rate Test l IRM - Intermediate Range Monitor ISI -

Inservice Inspection l LER - Licensee Event Report l LLRT -

Local Leak Rate Test l LPCI -

Low Pressure Coolant Injection Mode of RHRs l 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 l MPC -

Maximum Permissible Concentration l 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 11rHOPl\NRC\Moh~ntLY.RIT

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