ML20096E944

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Dec 1995 for Quad Cities Nuclear Power Station
ML20096E944
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1995
From: Moore K, Pearce L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-96-002, LWP-96-2, NUDOCS 9601230110
Download: ML20096E944 (19)
v • d • e


Text

, - _ -_ - . . _ . - -. - .. . . - ,,

, Commonwealth Edimn Company Quad Cities Generating Station

, 22710 206th Avenue North

. Cordova, 11.61242 9740 1cl .409M 6 2241 LWP-96-002 January 9, 1996 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 December 1995.

Respectfully, Comed Quad-Cities Nuclear Power Station

'. 0A L L. W. Pearce Station Manager LWP/dak Enclosure cc: H. Miller, Regional Administrator C. Miller, Senior Resident Inspector a n e.71"L'2*12 9601230110 951231 PDR ADOCK 05000254-R PDR

. w n m,m o,mnan, 562V q,

... - .. .. . _. . _ . . . . . . - . . . - . . - - -~~ . . . .. - -- .

QUAD-CITIES NUCLEAR POWER STATION t

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT l

December 1995 COMMONWEALTH EDISON COMPANY I

1 AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 l

LICENSE NOS. DPR-29 AND DPR-30 i

TscuoPhNRCWONWLY.RFT

i l

I TABLE OF CONTENTS  ;

l I. Introduction i l

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 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 TECHOP3\NRC\ MONTHLY.RPr

1

. l I. INTRODUCTION l l

i l

l 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 Mid-American 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 initial Reactor criticalities for Units One and Two, respectively 'ere 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, respectively.

4 TECHOP3\NRCG40N1HLY.RIT Li_. - _ _ , _ . _ _ _ - _ _ . ..

II. SU M RY OF OPERATING EXPERIENCE i

A. Unit One Quad Cities Unit One began the month of December 1995 at full power and remained on-line for the entire month. A load drop was perf ormed on December 23, 1995 due to Feedwater Heater troubleshooting.

B. Unit Two Quad Cities Unit Two remained on-line for the entire month of December 1995. A few load drops were performed, however the average daily power level remained at 80% or greater.

i i

TTCHOP3\NRC\MONHILY.RPT

III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications Technical Specification Amendment No.165 was issued on November 27, 1995 to Facility Operating License DPR-29 and Amendment No. 161 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained the proposed upgrade of Section 3/4.7 (Containment Systems) of the Quad Cities Technical Specifications.

Technical Specification Amendment No.166 was issued on December 19, 1995 to Facility Operating License DPR-29 and Amendment No. 162 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained the proposed upgrade of Section 3/4.8 (Plant Systems) of the Quad Cities Technical Specifications.

Technical Specification Amendment No.167 was issued on December 19, 1995 to Facility Operating License DPR-29 and Amendment No. 163 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained some of TSUP open items from previous Quad Cities Technical Specifications amendemnts issued by the  !

NRC.

Technical Specification Amendment No.168 was issued on December 27, 1995 to Facility Operating License DPR-29 and Amendment No. 164 to facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained the proposed upgrade of Section 3/4.5 (Emergency Core Cooling) of the Quad Cities Technical Specifications.

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

C. Tests and Experiments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the j reporting period. i l

l i

4

'ECHOP)\NRC\ MON 1HLY.RFT

IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad- 1 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.

I UNIT 1 Licensee Event Report Ni=her Qgig Title of occurrence 95-008 12/06/95 HPCI stop valve in the required action range. (Voluntary LER)  ;

1 95-009 12/19/95 HPCI Design Function not met.

UNIT 2 Licensee Event Report Number Qg.tg Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

i 1TCHOP3\NRC\ MONTHLY.RPT

- - - _ _ _ - . - - - ,- ,,s _ , .

- . . . . = . _. . . . . . . . - .. . ... - -. - ..- - - . . . . - . . . ...- .

I V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Operating Data Report l

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

.I l

1 l

l 1

l TICHOP3\NRC\b40N1HLY.RIT

. . ~.._ _ _ .._..m..~._.._. . _._ . _ . - _ .. - ._ __ _ ... _ ...._..._ _ _ - ___. . . _ _. _ _ ___... _ __ _ . . . _

I i

APPENDIX C OPERATING DATA REPORT DOCKErNo. 50-254 UNrr One DATE Sanuary 9,1996 COMPLETED BY Krissal Moore TELEPHONE (309) 654-2241 OPERATING STATUS .

0000 120195

1. REPORTING PERIOD 2400 - 123195 GROSS HOURS IN REPORTING PERIOD 744
2. CURRENTLY ALTTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Ne0: N/A
4. REASONS POR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrICAL 744.00 8031.00 160463.50
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 744.00 7935.30 155759.20
8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20
9. GROSS THERMAL ENERGY GENERATED (MWH) 1848577.00 1924 % 74.20 338405797.60
10. GROSS ELEC11tlCAL ENERGY GENERATED (MWH) 595634.00 6150227.00 109614081.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 571167.00 5886210.00 103474376.00
12. REACTOR SERVICE FACTOR 100.00 91.68 77.17
13. REAcrOR AVAILABILrrY FACTOR 100.00 91.68 78.82
14. UNTT SERVICE FAcrOR 100.00 90.59 74.91
15. UNrr AVAILABILrrY FACTOR 100.00 90.59 75.35
16. UNrr CAPACfrY FACTOR (Using MDC) 99.83 87.38 64.71
17. UNIT CAPACfrY FACTOR (Using Design MWe) 97.30 85.16 63.07
18. UNrr FORCED OLTTAGE RATE 0.00 9.41 7.59
19. SHUTDOWNS ACHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH): Refuel,2/3/96 i thru 4/21/96 I
20. IF SHUTDOWN AT END OF REPORT PEIUOD < ESTIMATED DATE OF STARTUP:
21. UNTFS IN TEST STATUS (PRIOR TO COMMFJtCIAL OPERATION):

PORECAST ACHIEVED INrrIAL CRTTICALrrY INTTIAL ELECTRICITY COMMERCIAL OPERATION 1.1 +9 7ECHOP3\NICMONTHLY.RPr

i 9

l APPENDIX C l OPERATING DATA REPORT l

DOCKET NO. 50-265 j UNIT Two l DATE January 9,1996 COMPLETED BY Kristal Moore l l

TELEPHONE (309) 654-2241 j OPERATING STATUS ,

0000 120195

1. REPORTING PERIOD 2400 123195 GROSS HOURS IN REPORTING PERIOD 744
2. CURRENTLY AttrHORIZED POWER LEVEL (MWL): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECIRECAL RATING (MWe-NET): 789
3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A
4. REASONS POR RESTRICTION (IF ANY): ,

THis MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrriCAL 744.00 4111.90 153887.75
6. REACTOR RESERVE SHirrDOWN HOURS 0.00 0.00 2985.80 l
7. HOURS GENERATOR ON LINE - 744.00 3967.90 149899.55
8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 1849886.10 5400516.82 324341220.92
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 596012.00 2631634.00 104145535.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 571746.00 24 % 977.00 98652886.00
12. REACTOR SERVICE FACTOR 100.00 46.94 74.57
13. REACIDR AVAILABILrrY FACTOR 100.00 46.94 76.01
14. UNrr SERVICE FAcrOR 100.00 45.30 72.64
15. UNtr AVAILABILrrY FACTOR 100.00 45.30 72.98
16. UNrr CAPACfrY FACTOR (Using MDC) 99.93 37.07 62.16
17. UNrr CAPACfrY FACTOR (Using Design MWe) 97.40 36.13 60.59
18. UNrr FORCED OtfrAGE RATE 0.00 22.19 10.30
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A I
21. UNTFS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INirlAL CRrrlCALTTY INrrlAL ELECTRICrrY COMMERCIAL OPERATION j
1. i +9 TIiCHOPS\NBCudON1MLY.RFr l

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE January 9. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH December 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 777 17. 774
2. 767 18. 775
3. 775 19. 774
4. 775 20. 775
5. 775 21. 774
6. 774 22. 775
7. 774 23. 609
8. 773 24. 776
9. 774 25. 777
10. 774 26. 742
11. 774 27. 776
12. 774 28. 776
13. 771 29. 775
14. ___

775 30. 767

15. 774 31. 776
16. 755 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 TECHOP3\NRC\ MON 1MLY.RIT

. )

l

'~

APPENDIX B l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 i UNIT Two DATE January 9. 1996 J COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 i MONTH December 1995 i i

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

1. 772 17. 767 ,
2. 771 18. 774
3. 750 19. 773

]

4. 774 20. 774

'5. 774 21. 750 I

'6. 773 22. 775

7. 776 23. 774
8. 775 24. 776
9. 775 25. 745
10. 774 26. 775 i
11. 774 27. 744 f
12. 774 28. 773 i i
13. 772 29. 771 i
14. 775 30. 723
15. 774 31. 764 ,
16. 767 INSTRUCTIONS i On this form, list the average daily unit power level in MWe-Net for each day i 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 i TECHOPS\NRC440NTMLY.RFT ,

. j APPENDIX D I

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE Januarv 9. 1996 REPORT MONTH Dec-har 1995 TELEPHONE 309-654-2241 K

to Ol :g n

m.  ! < n:  :-

no- g an LICENSEE as 29 n

$ O DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 95-11 12/23/95 P 0.0 A 5 --------- -- --- Feedweier Heater Repairs I

l TICHOP3\NRC\ MONTHLY.RIT

_- . - - . ~ . ... - . - . . - .. . . _ ..- -

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.19-265 j UNIT NAME Two COMPLETED BY Kristal Moore DATE Januarv 9. 1996 REPORT MONTH Dec- M r 1995 TELEPHONE 309-654-2241 l

a:

m OEh lC ish

! His 5

$x M LICENSEE il li m E O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT None for the month of December.

l l

TFfHOM\NPr\ MONTHLY.RIT

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 Ooerations 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 and Two for the reporting period.

l l

1 l

l l

4 nrHOP3\NRC\ MONTHLY.Rii

i

( VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested '9 a January 26, 1978, licensing memorandum (78-24) from D. E.

! 0'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC i Request for Refueling Information", dated January 18, 1978.

i i

l TIGIOPMNitCWONTHLY.RPT

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

1. Unit: Q1 Reload: 13 Cycle: 14
2. Scheduled date for next refueling shutdown: 2/3/96
3. Scheduled date for restart following refueling: 4/21/96
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

NO

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

1 7-4-95 l

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

232 GE10 Fuel Bundles will be loaded during Q1R14.

7. The number of fuel assemblies.
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 1701
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:

APPROVED ,

cfinai) 14/0395t OCT 3 01969 O.C.O.S.R.

QTP 300-S32 l Revision 2 I QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 02 Reload: 13 Cycle: 14 '
2. Scheduled date for next refueling shutdown: 1-6-97

)

3. Scheduled date for restart following refueling: 3-30-97
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:

November, 1996 i

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:

Approx. 200 Siemens 9X9IX Power Corporation Fuel Bundles will be loaded during Q2R14.

7. The number of fuel assemblies,
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 2727
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:

APPROVED ,

14/0395t (final)

W30M C1.C.O.S.R.

j 1

i 1

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

1 i ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute APRM - Average Power Range Monitor j ATWS - Anticipated Transient Without Scram l BWR - Boiling Water Reactor  ;

CRD - Control Rod Drive ,

EHC - Electro-Hydraulic Control System i EOF - Emergency Operathns Facility GSEP - Generating Stations Emergency Plan i HEPA - High-Efficiency Particulate Filter i HPCI - High Pressure Coolant Injection System  !

- High Radiation Sampling System HRSS i 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 l PCI - Primary Containment Isolation l 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 1TCHOP3\NRC\ MONTHLY.RFT l

-- - - . _ _ - -

Retrieved from "https://kanterella.com/w/index.php?title=ML20096E944&oldid=2783274"