ML20116H723

Monthly Operating Repts for Quad Cities Nuclear Station Units 1 & 2 for Oct 1992

ML20116H723
Person / Time
Site:	Quad Cities
Issue date:	10/31/1992
From:	Michael Benson, Tietz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GCT-92-43, NUDOCS 9211130246
Download: ML20116H723 (21)

Text

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. Commonwealth Edison ovad C: ties Nuclear i >*er Station 22710 206 Avenue North Corcova. Vlinois 61242 )

Telephone 009/654-2741 GCT-92-43 November 2, 1992 U. S. Nuclear Regulatory Commission ATTH: tocument Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units I and 2 Honthly Performance Report NRC..Dochet_Nosu50-254..anL50-265 Enclosed for your information is the Monthly Perforniance Report covering the operetion of Quad-Cities Nuclear Power Station, Units One and Two, during th6 month of October 1992.

Respectfully, COMMONHEALTH EDISON Ct.vANY Q'JAD-CITIES NUCLEAR P0HER STATION h Y-} n . \

terald C. Tietz Technical Superintendent GCi/HB/dak Enclosuie

<c: A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector l

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9211130246 921031 \

PDR ADOCK 05000254  !

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT October 1992 COMMONHEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE N05. DPR-29 AND DPR-30 t

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. TABLE Of CONTENTS i

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 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 M 14

1. IRIRQDUC110R

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Quad-Cities Nuclear Power 9tation is composed of two Bolling Hater Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illir.ois, ihe Station is jointly otaed by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Hater Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary constructiori 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 critica11ttes 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 Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

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II. SUMMARLQL0ERAllHG_EXEERIENCE A. Unit One Quad Cities Unit One continued with refuel outage Q1R12 for the entire month of October. The Unit was taken off line September 20 and is ,

scheduled to return to service on December 20.  !

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D. Unit _lyo Quad Cities Unit Two reduced power to 340 MHe on October 12 when the 2B

, reactor feed pump and 28 motor generator set tripped off line. The

! trip occurred while testing control power on bus 22. Two MSIV room l entries were made on October 15 and 16 requiring power reductions to 200 MHe on both occasions. Power was also reduced on October 23, to 675 MHe, when a feed water heater transient occurred. Power was reduced further, to 315 MHe, for feed water heater work on October 24.

Chicago Load Dispatch requested the following load reductions for Unit Two for the month of October; Date Load 10-04-92 600 MHe i 10-06-92 600 MHe 10-10-92 625 MHe 10-11-92 300 MHe 10-14-92 465 MWe 10-28-92 492 MHe 10-29-92 666 MHe Seven load drops of less than 20% power also occurred for various reasons during the month of October for Unit Two.

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III. E LA!1 L0fLP ROC E DUR L C HAfiG E S.._IES IS ._EXP ERI M E RIS ,

3 ANDJiAfEILRELA1EDEINIElBNCE

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A. Amendme n t s _tola tility_ Llc en s e_or_It chnic aLS p e cif_lc a tlons i Technical Specification Amendment No. 138 was issued on October 19, i 1992 to Facility Operating License DPR-29 and Amendment No. 134 to l Facility Operating License No. DPR-30 for Quad Cities Nuclear Power

• Station, Units 1 and 2, respectively. These amendments revise the Technical Specifications that will:

1. Revise the diesel generator operability requirements;

2. Revise the 125 volt DC battery availability and testing requirements;

3. Eliminate some redundant emergency core cooling testing

, requirements for Quad Cities; 1 4. Modify the electrical feedback requirements for Quad Cities; and

5. Incorporate various administrative changes primarily associated with the above changes.

B. EaclittyAfrocedur.e_ Changes _Beaultlng_NRC Approval There were no facility or Procedure changes requiring NRC approval for the reporting period.

C. J eit Land _E nerheniL Res ultin g_HRC_Appron1 There were no Tests or Experiments requiring NRC approval for the reporting period.

D. .Corte.ttive Maintenance of Safety Rehindlguioment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Hork Request Numbers, Licensec Event Report Numbers, Components Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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1 UNIT 1 MAINTENANCE

SUMMARY

l WORK REQUEST SYSTEM EID DESCRIPTION HORK PERFORMED 002998 1001 Repair Unit 1 1 solation valve to Replaced isolation valve and tubing form the l PS 1-1001-89A switch to the valve.

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088730 7800 Replace circuit breaker. As Found: 3reaker had cracks and chips with pieces missing. As Left: Removed damaged circuit breaker and installed a new one.

j Q90486 263 Repair packing leaks on valves of Removed old valve and installed a new one.

reactor vessel level transmitter 1 instrument isolation manifold.

(1-263-578) 1 i 090487 263 Repair packing leaks on valves of Installed new manifold valve. No leaks were found.

! reactor vessel level transmitter l instrument isolation manifold.

(1-263-588) 099598 261 Replace throttle steam shutoff Replaced isolation valves on all four pressure i 4

valves 1-261-30A, 1-261-308, switches. No leaks were found after testing.

l 1-261-30C, and 1-261-300.

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UNIT 2 MAINTENANCE

SUMMARY

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i j WORK REOUEST SYSTEM EID DESCRIPTION WORK PERFORMED -

i 001674 5700 Repair rocker switch for Unit Replaced Unit 2 switch with like switch from 2-2A RHR room cooler controls. Unit 1.

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1 IV. LICERSEElVERLREI'ORIS l

, 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.

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i Licensee Event ReportJumber DAte lille_of_0ttureate

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{ 92-02S 10-02-92 Control Room vent toxic gas analyzer INOP.92-026 10-27-92 RCIC flow transmitter out of calibration, j 92-027 10-9-92 U-1 HPCI room cooler failed.

i 92-028 10-16-92 SBGT outside of design basis (If Instrument Air is lost).

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l UNIL2 Licensee Event Reporiliumb.er Date Ittle_of_0ccutence 92-022 09-25-92 2B RHRSH Pump INOP due to plug leaking.

(Description should be)

, Locked hi rad area not controlled l'-1 & U-2 RBEDT.92-023 10-01-92 ECCS Pump Room check valve failures.

)92-024 08-23-92 HPCI fire Protection 005 > 14 days.

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V. DATA TABULATI0115 i The following data tabulations are presented in this report:

A. Operating Data Report t

) B. Average Daily Unit Power Level l C. Unit Shutdowns and Power Reductions 1

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{ APPENDIX C OPERATING DATA REPORT

DOCKET NO $Q-254 UNIT Qne 1 OATE heder_L 1991_

l COMPLETED BY tiait.Denson 1[ttPHONE 13Q91 f & Z241 1

l OPERATING STATUS i 0000 100192

! 1. REPORTING PERIOD: 24J0 1031VL GROSS HOURS IN REPORTING PERIOD: 145 j

l 2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND. CAPACITY: If9 l DE$1GN ELECTRICAL RATING (HWe-Net): 2B9

3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): tuA

4. REASONS FOR RESTRICTION (If ANY):

t THIS HONTH YR TO DATE CUtfJLATIVE l S. NUMBER OF HOURS REACTOR WAS CRITICAL . . . . . . . . . . . 0A, _ _3839t0.0 142110dQ i

6. REACTOR RESERVE SHUTDOWN HOURS .................. 0.0 0.0 _ 3421.9 -

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7. HOURS GENERATOR ON LINE ......................... 0.0 __il & EQ 13&Q12.t3D

8. UNii RESERVE SHUIDOWN HOURS ..................... 0,L Ja 90L Z_

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9. GROSS THERMAL ENERGY GENERATED (HWH)............. O,L lZalf6Q9t6 196B&363ZihA

, 10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... 0.Q_ 4121111J 9519M41A l 11. NET [LECTRICAL ENERGY GENERATED (HWH)............ 0.L 395514ait _SQLG481LQ_

12. REACTOR SERVICE FACT 0R........................... 0.L 79.77 79.00

13. REACTOR AVAILABILITY FACT 0R...................... 0.3 79.71 _BD,9D

14. UNIT SERVICE FACTOR ............................. 0.0 79.05 76.60

15. UNIT AVAILABILITY FACTOR ........................ 0.0 79.Q5 77.10

16. UNIT CAPACITY FACTOR (Using HDC) ................ 0.0 70.27 65.43

17. UNIT CAPACITY TACTOR (Using Design HWe) ......... AQ_ 6049 63.11

18. UNIT FORCED OUTAGE RATE ......................... 0.0Q 8.34 5.83 i

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

20. IF SHuiDOWN AT END OF REPORT PERIOD. ESilMATED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY  ;

l . 1 i INITIAL ELECTRICITY <

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! COMMERCIAL OPERATION  ;

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! APPENDIX C l . OPERATING DATA REPORT j

I DOCKET NO 50-165

UNii in l DATE Na m btL54._.1932_

4 COMPLETED 8Y MaLLBensoft f IELEPHONE 1303_)_f 54-2241

! OPERATING STATUS 1 0000 100192

1. REPORTING PERIOD: _24Q0 10319L GRO$$ HOUR $ IN REPORTING PERIOD: 745 a

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND. CAPACITY: 769 l DESIGN ELECTRICAL RATING (HWe-Net): 789 j 3. POWER LEVEL 10 WHICH RESTRICTED (IF ANY) (HWe-Net): N/A

4. REASONS FOR RESTRICTION (If ANY):

] THl$ HONTH YR TO DATE CUMULATIVE

,' S. NUMBER OF HOUR $ REACTOR WA$ CRITICAL ............ 745AQ _.__42Z0255 _.13.Z1.1L25

. 6. REACTOR RESERVE $HUTDOWN HOUR $ .................. 0.Q 0.0 . _ 22S520) 4

7. h0VR$ GENERATOR ON LINE ......................... 745.00 4157.55 __ll41Z.LA5

8. UNIT RESERVE $HUTDOWN HOUR $ ..................... Ot0_ DJ, 702,9D 1

9. GROS $ THERMAL ENERGY GENERATED (HWH)............. 16.10264.00 9152816.80 28913EZQ2JQ t

10. GROS $ ELECTRICAL ENERGY GENERATED (HWH).......... _524483.00 1936765.00 .2286195510D i

11. NET ELECTRICAL ENERGY GENERATED (HWH)............ SQ51Q100 231Za6HiQA 87461643.00 I 12. REACTOR SERVICE FACT 0R........................... . ._100,QL 57.77 77d9

13. REACTOR AVAILA81LliY FACT 0R...................... 100.00_ is1J1 78.76

14. UNIT SERVICE FACTOR ............................. 100.00 _lsdq 75.12

15. UNIT AVAILA8ILITY FACTOR ........................ . 10010h 5620 75.51

16. UNIT CAPACITY FACTOR (Using FOC) ................ QJ2._ 41.35 63 11

17. UNIT CAPACITY FACTOR (Using Design HWe) ......... 8. 6L 40.3D 62J5 l 18. UNIT FORCED OUTAGE RATE ......................... 0.0 0L 2 7.86 i

19. $HUTDOWN$ $CHEDULED OVER NEXT 6 HONTH$ (TYPE DATE, AND DURATION OF.EACH)

20. IF SHUIDOWN AT END OF REPORT PERIOD. ESTlHATED DAiE OF STARTUP*

21. UNIT $ IN TEST STATUS (PRIOR TO C0ttERCIAL OPERATION):

FORECAST ACHIEVED f INITIAL CRITICALITY l

l INITIAL ELECTRICITY COMMERCIAL OPERATION l

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254-UNIT One_

DATE liovemberl_199L_.

COMPLETED BY Halt _Denson TELEPHONE 13091_.654-2241 MONTH __0Clober_1992 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MWe-Net) (HHe-Net)

1. -8 17. -8

2. -8 18. -j __

3. -B 1 9 . __ _ -8

4. -8 20. -8

5. -8 21. -8

6. -B - _ 22. -8

7. -8 23. -8

8. -8 24 -8

9. -8 25. -7 ,

10. -8 26. -8

11. -8 _ 27. -8

12. -8 28 -8

13. _ -8 29. -B

14. -8 30. -8

15. -8 31. -8

16. -8 INSTRUCTIONS On this form, list the average daily unit power level in HWe-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 1001. 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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I I . APPENDIX B i AVERAGE DAILY UNIT POWER LEVEL 4

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i DOCKET N0 ..-265

, UNIT Dwo

DATE HQEembe tS, 1992 COMPLETED BY Matt _fenson TELEPHONE D03L65_4-2241 l

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MONTH 0M obtr_1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(MHe-Net) (MHe-Net) i 1. 767 17. 138

2. 769 18. 336

3. 784 19. 711 i 4. 7.20 20. 162

, 5. 183 _ 21. 788

6. 727 22. 793

7. 779 23. 684

8. 761 24. 341

9. 778 25. 503

10. 7J2_ 26. 782

11. 503_ -

27. 781

! 12, 699 28, 721

13. 783 29, 775

14. . 64 5 30. 722

- 15. 525 31. 790

16. 475 i INSTRUCTIONS On this form, list the average daily unit power level in MHe-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 monti. Note 4

that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily avera34 power level exceeds-the 1001. 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, ts u 1.16-8

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t APPENDIX D ,

UNIT SNUTDOWNS AND POWER REDUCTIONS

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i UNIT NAME Unit Two COMPLETED BY Mathew Benson l DATE November 5, 1992 REPORT NONTH October 1992 TELEPHO'IE 309-654-2241

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• fa3 O Q ** Ea3 fa3 8 9 LICENSEE m@ g@"

! ., DURATION b EVENT $" O NO. DATE (HOURS)

• REPORT NO. u CORRECTIVE At.TIONS/ COMMENTS 8

i l 92-74 10-03-92 S 9.1 F 5 ---- -- ----

Load Drop Per Chicago Load Dispatcher 92-75 10-05-92 S 6.5 F. 5 ---- -- ----

92-76 10-10-92 S 7.0 F 5 ---- -- ----

i 92-77 10-10-92 S 19.3 F 5 ---- -- ----

" " " i 92-78 10-12-92 F 2.1 A 5 ---- -- ----

2B MG/ SET (RECRIC) and 2B RFP TRIPPED L.eing Control Power Test

, on Bus 22 92-79 10-13-92 S 6.1 F 5 ---- -- ----

Load Drop Per Chicago Load Dispatcher 92-80 10-14-92 S 12.3 F 5 ---- -- ----

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, 92-81 10-16-92 F 67.4 A 5 ---- -- ----

MSIV Room Entry For HPCI & RICI Repairs 92-82 10-23-92 F 62.9 A 5 ---- -- ----

Dropped For FW Heaters Transient and Repair:

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l 92-83 10-28-92 S 5.5 F 5 ---- -- ----

Load Drop Per Chicago Load Dispatcher 92-84 10-29-92 S 2.8 F 5 ---- -- ----

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VI. UNIQULBEORIIMlE0VIRWEMIS The following items are included in this report based on prior commitments to the consission:

A. Main _1t e amlR11ef_ValYe_0nerailoni There were no Main Steam Relief Valve Operations for the reporting period.

B. Con t toLRod_ Drly e_5 cam _Il ming _Dala_for_UnLtL0ne_and_ho There was no Control Rod Drive scram timing data for Units One 'nd Two for the reporting period.

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VII. RELVELIE_lEORMEl0N 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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l QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989-INFORMATION REQUEST l

1. Unit: 01 Reload: 12 Cycle: 12

2. Scheduled date for next refueling shutdown: o-20-92*  !

• Actual Shutdown at 0104 hrs. '

i 3. Scheduled date for restart following refueling: 12-14-92

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

1. Modification to HPCI turbine exhaust steam line.

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! 5. Scheduled date(s) for submitting proposed licensing action and i supporting information:

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1. 06/30/92

~, 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:

. NONE AT PRESENT TIME.

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7. The number of fuel assemblies.

a. Number of assemblies in core: 0

b. Number of assemblies in spent fuel pool: 2281

8. The present licensed spent fuel pool storage capacity and the size off 2

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

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:

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APPROVED ~

(final) 14/0395t _i_ OCT 3 01989 J

O.C.O.S.R.

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

1. Unit: Q2 Reload: 11 Cycle: 12

2. Scheduled date for next refueling shutdown:

l 03/06/93

, 3. Scheduled date for restart following refueling: 06/05/93 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amer.dment:

NOT AS YET DETERMINED.

5. Scheduled date a for submitting proposed licensing action and supporting information:

NOT AS YET DETERMINED.

6.

Important licensing considerations associated with refueling, e.g., new 4

or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

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7. The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 2'.30 l 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed st: rage 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

.9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2009 i

APPROVED 14/0395t -l OCT 3 01989

! Q.C.O.S.R.

VIII. GLOSSARI i

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 ATHS - Anticipated Transient Hithout Scram BHR - Bolling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations facility GSEP - Generating Stations f trgency Plan HEPA - High-Efficiency Part slate Filter HPCI - High Pressure Coolar injection System HRSS - High Radiation Shmpiing System IPCLRT - Integrated Primary Containment Leak Rate Test 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 PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCH - Reactor Building Closed Cooling Hater System i RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System I

RPS - Reactor Protection System

RHM - Rod Horth Minimizer

, SBGTS - Standby Gas Treatment System l SBLC - Standby Liquid Control

. SDC - Shutdown Cooling Mode of RHRS l SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCH - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center l

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