SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2

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Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2
ML20216F061
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 03/31/1998
From: Sager D, Sirles K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-98-128, NUDOCS 9804160405
Download: ML20216F061 (20)
v • d • e


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, Commonwealth 1:dnon Comguny i ,

Quad Citics Generating . station

. 22710 200th Avenue North Cordova. 11.61212 9740 Tel .409M i 22 61

,SVP-98-128 April 10, 1998 l

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

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SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l Monthly Performance Report l NRC Docket Nos. 50-254 and 50-265 1

l l Enclosed for your information is the Monthly Performance j l Report covering the operation of Quad-Cities Nuclear Power '

Station, Units One and Two, varing the month of March, 1998.

! If you have any questions corcerning this letter, please l contact Mr. Charles Peterson, Regu.'atory Affairs Manager, at l (309) 654-2241, extension 3609. I l i

! Respectfully, 4]/ja David .

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Sager j l

l Site V e President Quad ies Station l Enclosure l

l cc: A. Beach, Regional Administrator l R. Pulsifer, Project Manager, NRR l 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 Bob Ganser, IDNS Deb Kelley, Quad Cities Kristal Sirles, Quad Cities SVP Letter File

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9804160405 980331 PDR i I

ADOCK 05000254 R ppg svr9sasi2:4,r , b A l'nicom Company r n

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MARCH 1998 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 Tscwonacwowmtv.an

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I TABLE OF CONTENTS I. Introduction ,

II. Summary of operating Experience A. Unit one J 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 IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l l

VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information l

VIII. Glossary l

1TCHOP3\NRC\ MON 1MLY.RPT

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. f I. INTRODUCTION Quad-Cities Nuclear Power Station 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 Commonwealth Edison Company and MidAmerican Energy 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, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of i

initial Reactor criticalities for Units One and Two, respectively I

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.

l I g This report was compiled by Kristal Sirles and Debra Kelley,

! telephone number 309-654-2241, extensions 3070 and 2240, respectively.

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9 II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit one was off-line the entire month of March 1998 due to a unplanned extension of maintenance Outage Q1P01.

B. Unit Two Quad Cities Unit Two remained shutdown for the month of March 1998 due to a unplanned extension of maintenance outage Q2P01.

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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

l AND SAFETY RELATED MAINTENANQE A. Amendments to Facility License or Technical Soecifications Technical Specification Amendment No. 180 was issued on March 6, 1998 to Facility Operating License DPR-29 and Amendment No. 178 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would change the Quad Cities Technical Specifications (TS) to clarify the applicability, action and surveillance requirements for the Standby Liquid Control System (SLCS). The proposed changes would make the current TS requirements for the SLCS consistent with the Standard Technical Specifications (STS) contained in NUREG-143, " Standard Technical Specifications General Electric Plants, BWR/4."

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

C. Tests and Exoeriments Reauirina NRC ADoroval There were no Tests or Experiments requiring NRC approval for the 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 submitted during the reporting period.

UNIT 1 Licensee Event Submission Report Number Date Title of Occurrengg 1-98-005 03/06/98 Failure To Complete Periodic Visual Inspections for Reactor Coolant Sources Outside Primary Containment, as Required by Technical Specifications (TS),

Were Due to a Programmatic Breakdown in Scheduling and Tracking of System Inspections and Ineffective Program Oversight.

1-98-009 03/12/98 Method Of Daily Temperature Verification of Standby Liquid Control System Pump Suction Heat Tracing Operability Using Installed Temperature Switches Did Not Account For Calibration l Tolerance Which Allowed Use of Temperature Switch Settings That Did Not Support the Technical Specification Requirement .

Resulting in Inability To Ensure l Suction Line Temperature Was Above The Minimum Allowed Value.

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i 1-98-010 03/16/98 Technical Specification (TS) l Surveillance Interval for Snubber Visual Inspections Was Exceeded Due to Personnel Error When An Incorrect Surveillance  :

Credit Date Was Entered into the EWCS Predefine Schedule as a Result of a Change in Frequency Codes for Conversion to the ,

Upgraded Technical j Specifications. '

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TFfHOPMNRC\MONDILY.RFr

UNIT 1 CONTINUED Licensee Event Submission ReDort Number Date Title of Occurrence 1-98-12 03/30/98 The Unit One Reactor Bottom Head Drain Line Developed A leak Due to Apparent Cracking of a Piping Coupling Weld, The Cause of Which is Unknown At This Time.

1-98-13 03/30/98 Insufficient Clearance between the Unit One Core Spray Test Return Valve and Pressure Suppression Chamber (Torus) may have caused Interference during Loss of Coolant Accident (LOCA)

Conditions Due to Inattention to Detail in the Original Design.

1-97-30 R1 03/30/98 Instrument Line Excess Flow Check Valves Testing Was Performed At Less Than Nominal Reactor Pressure Due To Inadequate Assessment of the EFCs ASME Code Required Testing and Inadequate Assessment of the In-Service Testing (IST) Program Plan Implementation.

UNIT 2 Licensee Event Submission Report Number Date Title of Occurrenge 2-98-01 3/25/98 Technical Specification (TS)

Surveillance for Source Range Monitors (SRM) Was Not Performed Within the Required Interval for Unit 1 and Unit 2 Due to l Inadequate Identification of the i TS Requirement in the l

Surveillance.

TECHOP)\NRC\ MONTHLY.RTT

l 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 e

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT one DATE Acril 10. 1998 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 .

l AONTH March 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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

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7. -7 23. -

6

8. -7 24. - 6
9. -7 25. -

6 1 4

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10. -6 26. - 6 t
11. -7 27. - 7
12. -6 28. - 7 l 13. -7 29. - 7 l 14. -7 30. -1 l

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15. -7 31. ,

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16. -7 INSTRUCTIONS On this form, list the average daily unit power level in HWe-Net for each day i in the reporting month. Compute to the nearest whole megawatt. These figures l will be used to plot a graph for each reporting month. Note that when maximum l dependable capacity is used for the net electrical rating of the unit, there i 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 nrHOM\NRc\ MON 1ELY.RIT l.

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 .

l UNIT Two DATE Aoril 10. 1998 COMPLETED BY ]$r.i.ptal sirles TELEPHONE (309) 654-2241 MONTH March 1998

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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1. -8 17. -6
2. -8 18. -6
3. -8 19. -6 4
4. -8 20. -6
5. -7 21. -5
6. -7 22. -5
7. -7 23. -5 j
8. -7 24. -6
9. -7 25. -6 l
10. -7 26. -6
11. -7 2 7. _ -8 1 l
12. -7 28. -8 {
13. -6 29. -8
14. -7 30._ -7
15. -7 31. -6
16. -6 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. i 1

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APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNrr One DATE April 10,1998 COMPLETED BY Kristal Sirles TELErilONE (309) 654-2241 OPERATING STATUS 0000 030198

1. REPORTING PERIOD: 2400 033198 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY ALTTHORIZED POWER LEVEL (MWL): 2511 MAX > DEPEND > CAPACrrY: 769 DESIGN ELECTRICAL RATING (MWe-NLT): 789
3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 0.00 0.00 172375.40
6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 0.00 0.00 167295.30
8. UNrr RESERVE SHLTfDOWN HOURS 0.00 0.00 909.20
9. GROSS THERMAL ENERGY GENERATED (MWil) 0.00 0.00 365437242.60
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 118253369.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 106154969.00
12. REACTOR SERVICE FACTOR 0.00 0.00 75.72
13. REACTOR AVAILABILrrY FACTOR 0.00 0.00 77.23
14. UNrr SERVICE FACTOR 0.00 0.00 73.49

!$. UNrr AVAILABILTTY FACTOR 0.00 0.00 73.89

16. UNrr CAPACITY FACTOR (Using MDC) 0.00 0.00 60.64
17. UNrr CAPACITY FACTOR (Using Design MWe) 0.00 0.00 59.10
18. UNrr FORCED OLTTAGE RATE 0.00 0.03 7.19
19. $11UTDOWNS SCHEDULED OVER NEXT 6 MOKrils frYPE, DATE. AND DURATION OF EACH):
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: QlP01 Ready to Start $/12/98
21. UNrr$ IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST AcillEVED INITIAL CRITICALTTY INITIAL ELECTRICTTY COMMERCIAL OPERATION 1.16-9 TI! CHOP)\NRC\MONTdLY,RFr

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l APPENDIX C OPERATINO DATA REPORT DOCKET NO. 50-265 UNrr Two DATE April 10,1998 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030198

1. REPORTINO PERIOD: 2400 033198 OROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AtrTHORIZED POWER LEVEL (MWt): 2511* MAX > DEPEND > CAPACirY: 769 DESIGN ELECTRICAL RATINO (MWe-NET): 789
3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe Neo: N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrflCAL 0.00 0.00 164367.05
6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 2985.80
7. HOURS GENERATOR ON LINE 0.00 0.00 159969.85
8. UNIT RESERVE SHITTDOWN HOURS 0.00 0.00 702.90
9. OROSS THERHAL ENEROY GENERATED (MWH) 0.00 0.00 348356256.32
10. OROSS ELEClltlCAL ENERGY GENERATED (MWH) 0.00 0.00 111762544.00 ll. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 105947458.00
12. REACTOR SERVICE FACTOR 0.00 0.00 72.70
13. REACTOR AVAILABILrrY FACTOR 0.00 0.00 74.03
14. UNIT SERVICE FACTOR 0.00 0.00 70.76 15, UNrr AVAILAP!LTTY FACTOR .____ __ _

0.00 0.00 71.07

16. UNrr CAPActrY FACTOR (Using MDC) 0.00 0.00 60.94
17. UNTT CAPACITY FACTOR (Using Design MWe) 0.00 0.00 59.40
18. UNIT FORCED OLTTAGE RATE 0.00 0.00 11.19
19. SHtTTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACIO: N/A
20. IF SHlTTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: Q2P01 Ready to start 4/20/98
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACillEVED INITIAL CRrrlCALrrY INrrlAL ELECTRICrrY COMMERCIAL OPERATION 1.1u-9 TFCHOP3\NRC\ MONTHLY.RPT J

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Sirles DATE Acril 10, 1998 REPORT MONTH March 1998 TELEPHONE 309-654-2241 a:

M 5 5. hw E8h. 8 sr.

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Ba ta es DURATION R$ LICENSEE EVENT O

NO. DATE 8

(HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 9842 980301 5 744.0 B 4 ..... .. ... Continuation of Maintenance Outage QlP01 (UnplanneJ Extension).

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCRET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal sirles DATE Anril 10. 1998 REPORT MONTH March 1998 TELEPHONE 309-654-2241 to O$

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n8 l l8 n a LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS t NO. DATE (HOURS) REPORT i M41. 900M1 8 744.0 3 4 ....... .... -. Conunuation of Maintenance Outage Q2P01 (Unplanned Extension).

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1 VI. UNIOUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission: l A. Main Steam Relief Valve Operations 1

There were no Main Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram Timina Data for Units One and Two There was no Control Rod Drive scram timing data for Units One l and Two for the reporting period. l

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1 VII. REFUELING INFORMATION 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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  • QTP 0300-S32 1 Rsviolon 3 )

April 1997 )

I QUAD CITIES REFUELING INFORMATION REQUEST ,

1. Unit 01 Reload: 14 Cycle 15
2. Scheduled date for next refueling shutdown: 11/07/98
3. scheduled date for restart following refueling: 12/17/98
4. Will refueling or resumption of operation thereafter require a Technical specification change or other license amendments Yes I

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

Approved i

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance j analysis methods, significant changes in fuel design, new operating procedures:

Approx. 216 SPC 9X9IX Fuel Bundles will be loaded.

7. The number of fuel assemblies,
s. Number of assemblies in core 724
b. Number of assemblies in spent fuel pools 1933  ?

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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: 0
9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002 (final) 1

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- , QTP 0300-S32 Rsvision 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST

1. Units 02 Reload 14 Cycle: 15
2. Scheduled date for next refueling shutdown: 1/8/2000
3. Scheduled date for restart following refueling: 2/17/2000
4. Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendments yes

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

August, 1999

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:

N/A

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 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: 2002 (final) 2

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l l l VIII. GLOSSARY l The following abbreviations which may have been used in the

! Monthly Report, are defined below: i ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute APRM - Average Power Ranga Monitor

, ATWS -

Anticipated Transient Without Scram l BWR -

Soiling Water Reactor )

CRD -

Control Rod Drive EHC -

Electro-Hydraulic Control System EOF -

Emergency Operations Facility j GSEP -

Generating Stations Emergency Plan l HEPA -

High-Efficiency Particulate Filter l HPCI -

High Pressure Coolant Injection System HRSS -

High Radiation Sampling System l

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 i 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 l

PCI -

Primary Containment Isolation PCIONR - Preconditioning Interim Operating Management )

Recommendations RBCCW - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor i 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 I SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP -

Traversing Incore Probe TSC - Technical Support Center I

TEQ4GM\NitC\ MON 1MLY.RIT I

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