ML20099G990

Monthly Operating Repts for Jul 1992 for Quad Cities Units 1 & 2

ML20099G990
Person / Time
Site:	Quad Cities
Issue date:	07/31/1992
From:	Michael Benson, Tietz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GCT-92-33, NUDOCS 9208180073
Download: ML20099G990 (22)

Text

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Commonwealth Edison

. ouad Cities Nuclea Power Station

' r 110 206 Avenue North L# Cordova, (!Iinois 61242 Telephone 309/6s4-2241 GCT-92-33 ek August 4, 1992 b

U. S. Nuclear Recclatory Commission ATIN: Document Control Desk H&3bington, D.C. 20555  ;

1

SUBJECT:

u .iear Station Units 1 and 2 mance Report j we.LaoL5.0-2513nd.30:265 Enclosed for your ir.fors;ation is the Month.y Performance Report covering the

'r 'at'er of Quad-Cities Nuclear Power Station, Units One and Two, during the na ' i a, July 1992.

Respectfully, COMMONWEALTH EDISON COMPANY QUAS-CITIES NUCLEAR POWER STATION L$2snY Gerald C..Tletz

$ Y$ U f k C

Technical Superintendent GCT/MB/dak Enclosure cc: A. B. Davis, Regional Administrator T.-Taylor, Senior Resident Inspactor P

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UNITS 1 AND 2

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MONTHLY PERFORMANCE REPORT-JULY 1992 COMMONHEALTH EDISON COMPMY AND IOWA-ILLIN0IS GAS & ELECTRIC-COMPAt>

NRC DOCKET NOS. 50-254 AND 50-265 LICENSt NOS. DPR-29 AND DPR-30 l

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4 TABLE OF CONTENTS I

l I. Introduction II. Summary of Operating Experience

-A. Unit One B. Unit Two 1

-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 es

-IV. Licensee Event Reports V. Data Tabult.tions A. Opera +1ng Data Report.

B. .Werage 0111y Unit Power Level C. Unit Shutdowns and Power Reductions

.VI. : Unique Reporting Requirements A. Main Steam Relief Valve 0.oerations B. Control Rod Drive Scram Timing Data VII. Refueling Infort!ation.

VIII. Glosrary-TS 14 '

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l I. IRIRODUCIION Quad-C1+1es Nuclear Power Station is composed of two Boiling Hater Reactors, each with a Maximum Dependable Capacity of 769 MHe Net, located in Cordova, Illinois. The S'ation is jointly owned by Cote)nwealth 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 Mi'ssissippt l 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 Matt-Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

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i II. .SUtiMARY OF OEIRAIMGlXPERIENCE A. - Uni t One Quad Cities Unit One was in coast down for the month of July in

-preparation for the upcoming refuel outage.

Only two significant load reductions were-ordered by Chicago Load Dispatch (CLD) in-July; July 3 to 450 MWe, and July 21 to 500 MWe.

Nunierous other load reductions of less than 20% were performed per CLD '

but not reported.

B. Unit Two l

l Quad Cities Unit Two reduced power to 200 MWe on July 10 in preparation i

for a Main Steam Isolation Va!ve (MS V) room entry. -A one half group one isolation had been received from a failed main steam tunnel temperature switch.-

Chicago Load Dispatch requested the following load reductions for Unit i Two for the month of July; Data 1.otd 7-2-92 490 MWe.

7-3-92 450 HWe-7-4-92 470 MWe 7-5-92 450 MHe 7-6-92-- 450 MWe-7-7-92 470 HWe 7-9-92 -500 MWe 7-9-92 -497 MWe 12-92 495 MWe, 13-92 600-MWe 7-14-92 450 MWe 7-16-92 551 MWe 7-16 478 MWe 7-20-92 58t MWe-7-2! 485 MWe 7-22-92 535 MWe 7-23-92 462 MWe

, 7-24-92 600 MWe 7-26-92 450 MWe 27 -

550 MWe 7-28 550-MWe 7-29-92 550 MWe 7-30-92 660 MWe

. 7-31 650 MWe -

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t III. P1&MLDILEROCEDURLCHANGES,_LESIS., EXEERIBENIS..

AND SAFETY REL& LED E lulENANCE A. Amendments to Far111ty_Lirensear_lerhniral_ Specifications Technical Specification Amendment No. 135 was issued on July-24,-1992 to facility Operating License-DPR-29 and Amendment No. 131 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. These amendments consist of administrative changes to revise the types of procedures that require review by the onsite review and investigation

-function (OnSR&IF), specifies the level of review ano approval for procedures governed by the propsed technical review and control process, and clarifles the authority assigned to the OnSR&IF.

B. facility or Procadgre_ChangeLRequirfngRC_Aparny.al There were no Facility or Procedure changes requiring NRC approval for

, the reporting period.

'C. leits and Exogriments_BeguirjngEC_Apprayal There were no Tests or Experiments requiring NRC approval for the reporting period.

D. CorreIllye_&ti ntRnance_of_S afely_Relat ed_Eq ulE'ReDI The following represents a tabular summary of the major safety related maintenance performed on Units Onn and Two during the reporting period .- This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action.Taken to Prevent Repetition.

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UNIT 1 MAINTENANCE

SUMMARY

.HORK'RE00EST' SYSTEM EID DESCRIPTION HORK-PERFORMED -

Q01996- 1140- Replace burned out light bulb. As.Left: Replaced bulb.

QO2060 6641 Recalibrate or replace As t.c' t: InstalledLnew' switch.

temperature switch.

QO2102. 2300 Adjust HPCI MGU:high speed stop As Left: Adjusted approximately 3/32" from the

11:n1t switch. mechanical stop. ,

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' UNIT 2 MAINTENANCE'

SUMMARY

HORK REOUEST SYSTEM- EID DESCRIPTIONL HORK PERFORMED

-Q02103- '2202 Investigate and repair panel. 'As Fo':nd: Found short'in level.. switch wiring. As

-accumulator monitor. Left: Replaced level switch..

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I IV. LICENSELEVEMLREEORIS The following is a tabular summary of all licensee event reports fo,'

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 c' E.2 of the Technical Specifications.

There were no Licensee Event Reports for Unit 1 and Unit 2 for this report ng period.

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'V, DATA - TABULAUDRS The following data' tabulations are presented in this report:

A. Operating Data-Report li B. -Average Daily Unit Power Level

- C. Unit' Shutdowns and Power Reductions l

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1 l APPENUD C I ,

OPERATING DA1A REPORT DOCKET N0 50-254 UNIT Qpe DATE A.yggsL5 _1992 COMPLETED BY tigtLfenson TELEPHONE L3021_L54-2241 OPERATING STATUS 0000 070i92

1. REPORTING PFx!OD: Z_43D._ D13192_ GROSS HOURS IN REPORTING PERIOD: 144

2. CURRENTLY SUTHORIZED POWER LEVEL (MWt): Zh1] HAX, DEPEND. CAPACITY: Zh9 DESIGN ELECTRICAL RATING (MWe-Net): 73 9

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

4. REASONS FOR RESTRICTICH (If ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS kEACTOR WAS CRITICAL . .. .. 744.00 471hdQ 141226JQ

6. RIACTOR RESERVE SHUTDOWN HOURS ... ...... ....... QA OdL 342119_

7. HOURS GENERATOR ON LINE .... ..... .......... . _ _7.44JQ . d61620 1369 % 30

8. UNIT RESERVE SHUTDOW HOURS . .... ......... ... QJ_ 0. q_ 909.2

9. GR0SS THERMAL ENERGY GENERATED (MWH) . . . . . . . . .... .14a1409 tf-Q 1Q210511.12 29433315L2Q

10. GROSS ELECTRICAL ENERGY GENERATED (MWM)...... . _417QLB A _35294Qld _.95603737.0

11. NET ELECTRICAL ENERGY GENERATED (MWH)... ........ .444Q32 A _333a9BB1Q_ _30103355J_

12. REACTOR SERVICE FACTOR., ........ ...... ..... . 10HaQ 92.26 79.35

13. REACTOR AVAILABILITY FACTOR................ .. .. 10QJQ _.,__32226 81.21 a

14. UNIl SERVICE FACIOR ...... .. .................. LQD JQ ___ 91.41 _ 76.92

.5. UNIT AVAILABILITv ACTOR .......... ............. _luQ100 91d1 ZZd3

16. UNIT CAPACITY FACTOR (Using MDC) ........... ... 77 62 Bhd3 6h&4

17. UNIT CAPACITY FACTOR (Using Design MWe) . ..... 75 15 84 2 04 17

18. UNIT FORCED OUTAbE RATE ... .. . ..... ,. .... QdQ B254 5.B2

19. SHUIDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATIDH OF EACH):

20. IF SHUTDOWN AT END OF AEPORT PERIOD ESTIMTED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY __

INITIAL ELECTRICITY COMMERCIAL OPERATION To t. - 1.16-9

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APPENDIX C

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OPERATING DATA REPORT DOCKET to. 50-?65 UNIT Iwo

-DATE Augu1L5J992 .

COMPLETED BY tiatL62MDr.

TELEPHONE 1202) 654-2241 OPERATING S1ATUS 0000 070192

1. REPORTING PERIOD: _Z400 113]AZ_ GROSS HOURS IN REPO': TING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND CAPACITY. 769 DESIGN ELECTRICAL RATING (MWe-Net): lE9

3. POWER LEVEL TO milch RESTRILhD (IF ANY) (HWe-Net): N/A .

4. REASONS FOR RESTRICTIOP (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAt. ..... .. . . 7.44,20 ,_. 2019,55 135501125

6. REACTOR RESERVE SHUTDOWN iOURS .................. __A1 Q.1 _. 2985 1  ;

7. HOURS GENERATOR OL LINE ...................... .. 74420G _ _19A M 5 131968.45

8. UNIT RESEkVE SHUTDOWN HOURS ..................... _, OA _Q A 702 1

9. GROSS TPERPul ENERGY GENERATED (MWH)............. 1651154 40 AQ32211hlQ E84116157.ZA

10. GROSS ELECTRICAL ENERGY GENFPATED (M41)....,..... __53561L90 1301478.QA _2123166a,DA i- 11 1. NET. ELECTRICAL-ENERGY GENERATED (HWH)............ 510633.Q2 J216824.00 Ad350A2240 ,

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' 12. : REACTOR SERVICE FACT 0R........................... __ 100.00 39 51 76161 13.-REACTOR AVAILABILITY FACTOR...................... 100.00 39,51 1 5A

- 14 UNIT SERVICE-FACTOR................... ... .... . 100.00 ,_

'38.12 74.8q lI

-15. UNIT AVAILABILITY FACTOR ........................ 1 &QA., 38.12 75.20

.:I16. UNIT CAPACIT iACTOR (Using HDC) ......... - _ ,_&2f_. 30.96- 63 45

17. U:41T . CAPACITY FACTOR (Using Design MWe) . . . . . . . . . 87.00_ 30.17 6Z,DA

18. UNIT. FORCED OUTAGC RATE ......................... 0.0 0.0 7.98 e '

lh 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE t.ND DURATION V EACH):

L 20.-IF SHUTDOWN AT END OF REPORT. PERIOD ESTD%TED DATE OF STARTUP:

l~ 21. l,' NITS IN TEST STATUS (PRIOR' TO COMMERCIAL OPERATION):

s I FORECAST ACHIEVED INITIAL CRITICALITY

- IN' TI AL - ELECTRICITY 1

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. APPENDIX B AVERAGE DAILY UNIT P0H'.'P LEVEL DOCKET N0 50-25.4 UNIT One DATE AugusL5,_1.992 COMPLETED BY H Q h g50n TELEPHONE _(309L553-2 41 MONTil J 0y 1992 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MWe-Net) (MWe-Net)

. 1. 672 17. 609

2. 660 18. 601

3. 604 _ 19. 599

4. 427 20. 610 . . _

5. 442 21. 598

- 6. 598 22. _.

524

7. 65a - 23. 553 4

8. _654 24. 577

- 9. 65_4 25. 561

10. 645 - 26. 510 1 l '. 643 27. SEB

12. 623 28, 576

.12 634' 29, 605

14. 616 30. 600

15. 590 31. _ SIB _

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INSTRUCTIONS .

. On-this form,: list the average oatly unit power level in MWe-Net for each day in th? 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 fcr the net electrical rating of the unit, th'.rt may be occasions-when the daily average power level exceeds

., the 1007..line (or-the restricted powe; level line). In such cases, the average daily unit power. octput sheet should be footnoted to exclain 'tha apparent anomaly.

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APPENDIX B

. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-2f5 _ _ -_

UNIT Iwq DATE Augu? L5.m1992_

COMPLETED BY Malt _Jenson TELEPHONE D091_654-22_41__ _

MONTH Ju]y_1992__

DAY AVERAGE D?ILY POWER L7. VEL DA) AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 119 _

17. 681

c. _771 14. _ _ 772_

3. __ 144 19. _ 777

4. 529_ 20. _ _118______

5. .3 20 21. 7.15

6. 658 22. _ 1 68

7. .__ 6fi0 23. 473

8. - 618 _._ 24. 679

9. 724 25, 110 _ _ _ _

10. 453 26. 646

11. 551 . 27. _ 696

12. 713 28. 70E _ .

13. 118 2f 715

14. 149 30. 711

15. 698_ 31, 727

16. 73 2 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, thers may be occasions when the daily average power level exceeds the 100% line (or the_ restricted power level line). In such ;ases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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VI. Utll0VE_REEORI1NG_REQUIREtiBLS The following items are included in this report based on prior commitments to the commission:

A. MAlR_St.eam Re1ief Valy t0perations There'were no Main Steem Relief Valve Operations for the reporting period.

B. lontroLRodJr_tyLicram_Ilm.inglatLfor_.UnitL0Ae lad _ho The basis for rep ( .Ing this data to the Nuclear Regulatcry Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

-Tne'following table is a complete summary of Units One and Two Control Rod.

Drive Scram-Timing for-the reporting-period. All scram timing was performe" with reactor pressure greater than 800 PSIG.

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RESULTS OF' SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL R00' DRIVES, FROM 1-1-92 TO 12-31-9R AVERAGE TIME IN SECONDS AT 1 MAX. TIME INSERTED FROM FULLY HITHDRAWN FOR 90%

INSERTION DESCRIPTION 5 20 50 90 Technical Specification 3.3.C.1 &-

NUMBER 3.3.C.2 (Average Scram Insertior. Time)

CATE OF RODS 'O.375 0.900 2.00 3.5 7 sec.

0.28 0.67 1.43 2.48 J-2 Drive Replacement (J-2), Scram Valve N-7 2-19-92 2 2.55 0.32 0.69 1.45 2.45 N-5 -Scram Valve Work N-S 2-20-92 1 2.45 0.31 0.69 1.47 2.58 L-13 Start-up Scram Timing Unit Two 5-12-92 177 I. 3.43 0.31 0.65 1.37 2.35 H-5 Scram Valve Work 6-02-92 1 2.35 0.62 1.32 2.32 C-12 ACCUM C-13, N-7 6-26-92 2 0.27 2.26 88 0.28 0.63 1.35 2.36 K-13 Unli 1 "B" Sequence 7-13-92 2.79 0.29 0.64 1.36 2.41 D-2 127 Diaphragm 0-2 Unit 2 7-22-92 1 2.43 1

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.VII, REfyELifEJffE0RMAUDE

.The following information about future reloads at Quad-Cities Station was requested in a January 26. 1978, licensing memorandum (78-24) from

'D. E, 0'Brien-to C. Reed, et al,, titiec "Dresden,: Quad-Cities and Zion

-: Station--NRC Request for Refueling Information", dated January 18, 1978.

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QTP 300-532

• Revision 2

-QUAD CITIES REFUELING Cctober 1989

, (NFORMATION REQUEST Ll.- ~ Unit: Q1 Reload:- 11

_ Cycle: __ 12

2.. Scheduled date for next refueling shutdown: 9-20-92

-3.

Scheduled date for restart following refueling: 12-12-92 1, 4.-

?- Will: refueling or resumption of operation thereafter e'equire a Technical Spoc1fication cnanto or other -license-amendment:

1. Modification _ to HPCI turbine exhaust steatn line.

S.

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

1. 06/30/92-6.

Important--Il_ce7 sing considerations associated with refueling, e.g., new or different fuel design or. supplier, unrev ewed design or performance analysis methods,- significant charges in fusi design, new operating procedures:

No:iE AT'PRESENT TIME.

7. The number of fuel assemblies.

a.

Number of assemblies in core: 724

_b. ' Number of assemblies in spont _ fuel pool: 1405

8. The present licensed spent fuel _ pool _. storage capaciiy ar.d the size of any-increase-in licensed storage capacity that has been requested or 1s-

~

' planned _1_n number of fuel assemblies:

a. Licensed storage cacacity for spent fuel: 3657-

b. Planned increase in 11 censed storage: O c 9.- The' projected'date rf the last refueling that can be discharged to the ,

spent fuel pool assuming _ the..preserit licensed capacity: 2009 f

APPROVED ,

(final) 14/0395t - 00T 3 01989 Q.C.O.S.R.

2 _

QTP 300-532 Revision QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q2 _ Reload: 11 Cycle: 12

2. Scheduled date for next refueling shutdown: 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 amendment:

NOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

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.

7. The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 2434

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. Licet:"d 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 APPROVED ,

(final) 14/0395t OCT 3 01989 Q.C.O.S.R.

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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containment Atoospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute APRM - Average Power Range Monitor ATHS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CR0 -

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 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 Hc_t Generation Rate MCPR - Minimum Critical Power Ratio MFLCPP. - Maximum Fraction Limiting Critical Power Re.tio 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 RBCCW - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC - Reactor Core Isolation Ccoling 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 - 1raversing Incore Probe TSC - Technical Support Center TS 14

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