ML20198L641

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Monthly Operating Repts for Dec 1997 for Quad Cities Nuclear Station,Units 1 & 2
ML20198L641
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1997
From: Cook D, Stockman D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SM-98-004, SM-98-4, NUDOCS 9801160081
Download: ML20198L641 (20)
v • d • e


Text

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,g O smmonw ralth 12hwin uemp:ny Quad Oters Grncreting Stt 6on 22710 Jtwith Asenur North Dinlin a, IL 612 42 97 to

^Irl MPH 4 4 22il SM-98-004 January 10, 1998 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTH: Document Control Desk

SUBJECT:

Quad Cities Nuclear Station "Jnits 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 cf December, 1997.

Res ectfully,

% hU-I Da/e Cook' Station Manager DBC/dak Enclosure cc A. Beach, Regional Administrator R. Pulsifer, Project Manager, NRR C. Miller, Senior Resident Inspector W. Leech, MidAmerican Energy Company D. Tubbs, MidAmerican Energy Company F. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records center office of Nuclear Facility Safety, IDNS '

DCD License M. Wagner. Licensing Comed , ,

idCO32 Bob Gansu , IDNS # ('

Deb Kelley, Quad Cities g h I

Dick Stockman, Quad Cities SM Letter File 9901160001 971231 PDR ADOCK 05000254 1i

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT 1

DECEMBER 1997 CCMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 ,

t LICENSE NOS. DPR-29 AND DPR-30 TFIHOP3\NRC\htONTHLY,RPT y . .

  • .s TABLE OF> CONTENTS.

I. Introduction  ?

II. Summary of Operating Experience A.- Unit'One B. Unit Two 4

III. Plant or Procedure Changes, Tests, Experiments, and Safety- ,

Related Maintenance A. Amendmer,ts to Facility License or Technical Specifications B. Facility or Procedate 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.

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-- TliCHOP3\NRC\ MON 1HLY.RIT

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e I, lHIllOT11CTION L

Quad-Cities Nuclear Power Staticn is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station-is-jointly owned by CoNmonwealth Edison Company and

-MidAmerican *.nergy Company. The Nuclear Steam Supply Systems are LGeneral-Electric Company Boiling Water Reactors. The Arch *tect/ 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 DPk-30, icsued 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 Dick Stockman and Debra Kelley, telephone: number 309-654-2241, ex'_ensions 3221 and 2240, respectively.

TBCHOP3WkC\ MONTHLY.RFT

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4 II.

SUMMARY

OF OPERATING EXPERIENQE A. Unit one Quad cities Unit one began the month of December 1997 on-line. On December-20, 1997 at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> the-turbine was tripped and at 1304 hours0.0151 days <br />0.362 hours <br />0.00216 weeks <br />4.96172e-4 months <br /> the reactor was nanually scrammed '

due to Fire Protection issues. Before the unit was taken off-line a couple of load drope were performed for Turbine Weekly Testing, however the average daily powcr level ,

remained at 80% or greater.

B. Unit Two Quad Cities Unit Two ren.ained shutdown for the month of December 1997 due to Q2P01 planned outage extension. )

' T1iCHOP NNINLY,RPT '

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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 Amendaents to the Facility-License or Technical Specifications for.the reporting period.

B. Facility or Procedure Chances Reauirina NRC Acoroval 5 There were no Facility or Procedure changes requiring NRC approval for the reporting period.

-C. Tests and Exoeriments Recuirina NRC Acoroval There wore no Tests or Experiments requiring NRC approval for the reporting period.

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TBCHOP3\NBCWONTHLY.RFT .

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-,a 5 IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two submitted during the reporting period.

UNIT 1 Licensee Event Submission Repert Number Date Title of occurrence 1-97-021 12/16/97 The Cause of Discrepancies

. Supplement 1 Found Between The Safe Shutdown (SSC) Procedures And The Fire Protection Report, Which Led To The Declaration That Nine SSD Paths Were Inoperable, In Unknown At This Time.

1-97-024 12/23/97 A Required 10CFR50.59 Summary Evaluation For A Change To the Updated Final Safety Analysis Report (UFSAR) Was Not Submitted To The NRC Due To An Administrative Oversight Error.

1-97-025 12/5/97 Units 1 And 2 Average l'ower

  • Range Monitors (APRM) Flow Bias Were Not Calibrated To A Flow Signal Within The Required Interval Due To Inadequate Change Management When Implementing Upgraded Technical Specifications (TS). In Addition, This Calibration Was Not Performed Prior To Entering Power Operation Mode For Units 1 And 2 Due To Misinterpretation Of TS.

1-97-026 12/2?/97 Technical Specification (TS)

Required Instrument Channel checks Were Not Documented Prior To Entering The Applicable Mode Due To Inadequate Procedure Development And Review.

I TECHOP3\N10 MONTHLY,RPT

UNIT 2'

. Licensee Event Submission Report Number Date Title of Occurrence 2-97-012 12/18/97 Loss Of Shutdown Cooling Due To The Loss Of Power To The Reactor Protection 3us 2B. ,

2-97-015 12/8/97 A Technical Specification Required-Surveillance _Was Not Properly Performed (i.e.

Inadequate VT-2) Due To An.

Apparent Unfamiliarity With 10CFR50 Appendix G Which.

Resulted In An Insufficient Test-Procedure.

TECHOP3\NRCG40lfDILY.RM -

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,- .t V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Average Daily Unit Power Level B. Operating Data Report C. Unit Shutdowns and Power Reductions TECHOPhMRC\ MONTHLY.RPT

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APPENDIX B

-AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO 50-254 +

UNIT- one DATE Januarv-10. 1998 OOMPLETED BY Dick Stock =an TELEPHONE f309) 654-2241 MONTH Dec " =r 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (MWw-Net)

1. 775 , 17. 775
2. 775 18.__ 775 c
3. 774 19. 750
4. 774 20. 80
5. 775 21. - 9
6. 741 22. -10
7. 776 23. -10
8. 776 24. -10
9. 776 25. -10
10. . 776 26. -

9 11, 775 27. - 7

12. 775 28. - 9
13. 765 29. -9
14. 776 30. -

8

15. 775 31. - 8
16. 776 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 reperting month. Note that-when maximum dependable capacity is used-for-the not 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 pcwer output sheet shocid be footnoted to explain the apparent anomaly.

1.14-8 TECHOPMNRC\ MONTHLY,Rrr a.

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B APPENDIX B

. AVERAGE DAILY UNIT POWER LEVEL ~

DOCKET NO 50-265 UNIT Twc DATE January 10. 1998

  • COMPLETED BY. Dick Stoch==n TELEPHONE DP91 654-2241

-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
4. -8 20. -9
5. -8~ .
21. -9 e
6. -8 22. -9
7. -8 23. -9
8. -8 24. -9 9.' -8 25., -9
10. -8 26. -8
11. -8 27. -P
12. -8 28. -9
13. -8 29. -9 ____
14. -8 30. -d
15. . -8 _ 31. -8

-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 reportir 1 month. Note that when maximum dependable capacity'in used for the not 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 TBCHOP)\NRC440BrTHLY RPr .

k 'L fl APPENDIX C OPERATING DATA 3EPORT -

DOCKST Noi 50 254 -

UNTT One DATE hauary 10,1998 COMPLETED SY Dick Stoclunen -

TELEPHONE - (309) 654-1241 OPERATING STATUS -

0000 120197 1.~ REPORTING PERIOD 2400 123197 OROSs HOUR $ IN REPORTING PIRIODji44

2. CURREPflLY AUTHORIZED POWER LEVEL (MWO: 2511 MAX > DEFEND > CAPACfrY: 759-DESIGN EL5CI'RICAL RATING (MWe-NET): 789
3. PCWER LEVELTO WHICH REWRICTED OF ANY)(MWe-Neo: N/A

'1 4. REASONS FOR RE311tlCTION OF ANY): -

THIS MON'1H YR TO DATE CUMULA17VE 5.- NUMBER OF HOURS REACTOR WAS CRTTICAL 469.10 7866.20 172375.40 6.' !tEACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 '.1421.90

7. HOURS OENERATOR ON LINE 465.20 - 7766.40 lo7795.30
8. UNTT RESERVE SHUTDOWil HOUR $ 0.00 0.00 969.20
9. GROSS THERMAL EHERGY GENERATED (MWH) 1848936.10 J 8264360,10 365437242.60

,10. GROSS ELECTRICAL ENFROY GENERATED (MWH) 369819.00 is31939.00 118253369.00 i1. NET ELECTRICAL ENERGY OENERATED (MWH) 351514,00 111720430.00 J565461.00

12. REACTOR SE2VICE FACTOR 63.05 89 8 76.45>

l3. REACTOR AVAILABILITY FACTOR - 63,05 89.80 77.97 s

14. UNTT SERVICE FACit)R 62.53 88.66 74.20
15. UNTT AVAILABILTTY FACTOR i 62.53 88.66 ~ 74.60 Jt6. UNTT CAPACTTY FACTOR (Using MDC) 61.e4 82.62 64.43

- 17. UNTT CAPACTTY FACTOR (Using Design MWe) 59.88 80.52 62.80 1,l. UNTT FORCED OUTAGE RATE J7.47 11.34 7.67

11. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF IMCH): Maintenance 9 QlKl 1/3/98 1/23/98
20. IF 5 PUTDOWN AT END OF REPORT PEIUOD< ESTIMATED DATE OF STARTVD: ItJ t/93 21; UNT?S IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A-p .

FORECAST ACHIEVED

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APPENDEX C - ,

OPERATINO DATA REPORT DOCKITT NO. 50 265 - ,

1 NIT- Two. .

1 DATE January 10,1998 =!

COMPLETED BY Dick SF ans i TELEPHONE (309) 654-2241 l OPERATINO STAWS 0000 120197 '

1. REPORTINO 6 4 2400 123197 OP.OSS HOURS IN REPORTING PERIOD 744 1
2. CURRENTLY AUTHuRIZED POWER I.EVEL(MWI): '2511 MAX > DEPEND > CAPACTTY: 769 DEsl0N ULECTRICAL RATINO (MWe-NET): 789 - .
3. POWER LEVELTO WellCH RESTRICTED (IF ANY)(MWe-Net): N/A
4. REASONS POR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE .

5. NUMBER OF HOURS REACTOR W AS CRTTICAL 0.00 3780.50 164367.05 j 6< REACTOR RESERVE SHUTDOWN HOURS 0.00 = 0.00 2985.50 .]
7. HOURS GENERAMR ON LJNE 0.00 3720.50 159969.35
8. UNTT RESERVE SHIJTDOWN HOURS 0.00 0.00 702.90 -)

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9. OROSS THERMAL ENEROY OENERATED HWH) 0.00 8654167.50 ' 348356256.32 j 0.00 2745407.00 111762544.00
10. OROSS ELECTRICAL ENEROY OENERATED (MWH) "

, I i1. NET ELECIECAL ENEROY OENERATED (MWH) 0.00 -2627737.00 105947458.00 .J

+ .!

12. REACTOR SERVICE F ACTOR 0.00 43.16 73.41 1
13. REACTOR AVAILABILTTY FACTOR 0.00 ' 43.16 74.74 i a
14. UNTT SERVICE FACTOR 0.00 42,47 71.44

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15. UNTT AVAILABILTTY FACTOR 0.00 42.47 71.76
16. UNTT CAPACTTY FACTOR (Uning MDC) - 0.00 39.01 61.53
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17. UNTT CAPACTTY FACTOR (Using Design MWe) 0.00 38.02 59.97
18. Ui4TT PORCED OLTTAGE RATE 0.00 11.90 11.19
19. PHUTDG'tNS SCHEDULED OVER NFXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): N/A - _
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 1/26/98
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): .j FORECAST  : ACHIEVED

. INTTIAL CRTTICALTTY a

. INTTIAL ELECTRICTTY -

COMMERCIAL OPERATION -

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l APPENDIX D

, UNIT SHUTDOWNS AND POWR REDUCTIONS DOCKET NO. 50-2E4 UNIT NAME One . COMPLETED BY Dick litockman DATE January 10. 1998 REPORT HONTH December 1997 TELEPHONE 309-654-2241 a:

m se ONh n o R- w noA l o:B u

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  • 8 LICENSEE 8 DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 97 17 971220 F 278.8 H 2 ..... .. ... Fire Protection issues QlF43

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.M TTrHOP3\NRC\ MONTHLY.RN

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY- Dick Stockman DATE p'anu4rv 30, 1998 REPORT HONTH December 1997 TELEPHONE 309-654-2241 a:

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8 LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NOo DATE (HotfRS ) REPORT 9716 971201 8 744.0 H 4 . -- ...- -- Continuation of Planned Outage Q2P01,

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TBCHOP3\NRC\ MON 1H1X.RFr

VI._ UNIOUE REPORTING REQUIREMENTE The.following; items are incladed in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Ooerations Relief valve operations during the reporting period are summarized in the following table. The table. includes informat.r ' as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: :One Date December 20, 1997 Valve Actuated: No. & Tvoe of Actuation:

1-0203-3B 1 Manual 1-0203-3C 1 Manual 1-0203-3D 1 Manual Plant Conditione: Reactor Pressure - 925 psig Description of Events: QCOS 0203-03 " Main Steam Reljef Valves Operability Test" Valves 1-0203-3A and 1-0203-3E will be tested on startup.

i B. Control Rod Drive Scrom Timina Data for Units One and Two There Wasyno Control Rod Drive scram timing data for Units One and=Two for the reporting period, f

'T11 CHOP 3\NRC\ MON 1MLY RPT.

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VII. PEFUELING INFORMATION The following infcrmation 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.

ThrHOP3tNRC\ MONTHLY.kPT

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'J QTP 0300-832-R3vioitn 3 April 1997 QUAD CITIES REFUELING i

  • INFORMATION REQUEST.

'1. . Units 01 Reload: 14 Cycle: 15

2. ' scheduled date for next refueling shutdown: 9/05/98
3. Scheduled date for restart following refueling: 10/15/98
4. Will refueling or resumption of operation thereafter require a Technical' specification change or other license amendment:

Yes

5. scheduled date(s) for submitting proposed licensing action and supporting information:

February, 1998 J

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 *uel design, new operating procedures:

Approx. 216 SPC 9X91X Fuel Bundles Q1R15 will be loaded.

7. The number of fuel assemblies.
a. -Number of assemblies in core: 724
b. Number of assemblies in spent fuel pools. 1933
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 3657 .
b. . Planned increase in licensed storage: O
9. The projected date-of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002

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.-- QTP 0300-832: i R vicion 3 l April-1997 l

QUAD CITIES REFUELING INFORMATION RtQUEST

1. -Units 02- Reload: 14 Cycle: 15 1
2. Scheduled date for next refueling _ shutdown:' 9/25/99 ~
3. Scheduled-date for restart following refueling: 10/31/99
4. Will-refueling or resumption of operation thereafter require-a Technical- _;

specification change or other license.aeondment:

4 Yes 4

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

August, 1998

. .6. Important licensing considerations associated with refueling, e.g., new --

or different fuel design or supplier, unreviewed design or perforinance

analysis methods, significant changes in fuel design, new operating procedures: ,

N/A 4

f

7. The number of fuel assemblies,
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pools 2943
8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has beer. requested or is

--planned in number of fuel assemblies:

a._ Licensed storage capacity for spent fuel: 389'i b.- Planned increase in licensed storages' O

-9. The projected-date of the last refueling that can

.be' discharged to the spent fuel: pool assuming

-the prosent licensed capacity:- _

2002

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. VIII. GLOSSARY I

The following~aboreviations.which may have been used in the-

~

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Nonthly Report, are defined below: ,

. ACAD/ CAM.- Atmospheric-Containment Atmospheric ,

Dilution / Containment Atmospheric. Monitoring  ;

ANSI- ; American. National-Standards Institute l

, APTM - Average PowercRange Monitor  !

ATWS- - Anticipated Transient:Without-Scram

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c BWR -LBoiling Water Reactor j CRD - Control Rod Drive-t

.1Dic - Electro-Hydraulic: Control SystemL fEOF - Emergency Operations Facility; LGSEP. - Generating Stations Emergency Plan

-i l HEPA -- High-Efficiency Particulate Filter; HPCI - High. Pressure' Coolant Injection Systam it 'HESS. - High Radiatior. Pampling System IPCLRT, - Integrated Primary-Containment Leak Rate. Tent ~ ,'

Ilut - Intermediate Range Monitor

- ISI - Inservice Inspection!

p -LER- --Licensee Event Report:

LLRT - Local Leak Rtte Test LPCI - Low Pressure Coolant. Injection Mode of RHRs

- Local Power Range Monitor  ;

1MPRM MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio g MFLCPR - Maximum Fraction Limiting Critic': 1 Power Ratio-

MPC- --Maximum Permissible Concentration F

MSIV -:- Main Steam Isolation Valve '

NIOSH - National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation ".

L PCIONR) - Preconditioning Interim Operating Management

. Recommendations RBCCW~- Reactor Building Closed Cooling Water System u

RBM. ~ - -Rod-Block Monitor RCIC 1- Reactor Core Isolation _ Cooling System

, .RHRS- -

Residual-Heat Removal _ System h  ;RPS, -

Reactor Protection System- ,

.RWM - Rod! Worth Minimizer SBCTSL- Standby: Gas 1 Treatment' System- >

lSBLC: - Standby Liquid Control SDC- - -i Shutdown' Cowling Mode of-RHRS

p. -

- .SDVi - Scram Discharge--Volume iSRM: - SourcelRange Monitorn-D .TBCCWf- Turhinn? Building-Closed < Cooling Water System O _ _

TIP' -

,TraversingLIncore_ Probe

, 1TSCE  : - Technical Support Center

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