ML20141C287

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1997 for Quad Cities Nuclear Power Station,Units 1 & 2
ML20141C287
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/30/1997
From: Pearce L, Sirles K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-97-052, LWP-97-52, NUDOCS 9705160227
Download: ML20141C287 (20)
v • d • e


Text

1 l

. . Oirnrnonwealth Ihn unnguny i

. Quad Cities Generating Station 22710 2CLth Avenue Nonh Cordova, 11.612(2 9740 i rei .um>s 4 22ii  !

l LWP-97-052 I

J May 6, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l 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, j during the month of April, 1997, i Respectfully, l

i Comed Qua /Ci ies Nuc ear Power Station i 1 (JAUL L.;W. Pearce Station Manager

,[

LWP/dak q,C Enclosure cc: A. Beach, Regional Administrator C. Miller, Senior Resident Inspector 160041

)}\\\\\\\f}\\f}\\{\\\]\\{\\h\

9705160227 970430 PDR ADOCK 05000254 R PDR ..

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

l l

e 1 l

l l

QUAD-CITIES NUCLEAR POWER STATION  !

I l

UNITS 1 AND 2 j i

MONTHLY PERFORMANCE REPORT APRIL 1997 i

COMMONWEALTH EDISON COMPANY AND I MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 i

LICENSE NOS. DPR-29 AND DPR-30 1

l i

l i

TECHOP3\NRC\ MON 1MLY.RIT

1 TABLE OF CONTENTS

1. Introduction 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 l

V. Data Tabulations A. Operating Data Report

8. Average Daily Unit Power Level ,

C. Unit Shutdowns and Power Reductions I l

VI. Unique Reporting Requirements 1

A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information i

VIII. Glossary TECHOP3\NRC\ MONTHLY.RPT

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 ,

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 Kristal Sirles and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

I 1

TECHOP3WRC\MONTMLY.RPT

S l

SUtWARY OF OPERATING EXPERIENCE II.

)

A. Unit One  ;

1 Quad Cities Unit One began the month of April 1997 on-line. On April I 6,1997 at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />, a load drop was performed to adjust the setpoint after receiving a high level alarm from the 103 Feedwater Heater. On April 9, 1997 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> a shutdown was initiated due to problems with 4KV Breaker Auxiliary Switches. At 2344 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.91892e-4 months <br /> the Main Turbine was taken off-line and Forced Outage QlF41 commenced. On i April 10,1947 at 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the reactor was manually scrammed. A design change was impicmented to repair the cracked mounting channels in the 4KV Breaker Auxiliary Switches. After successful testing, the reactor went critical on April 24, 1997 at 0334 hours0.00387 days <br />0.0928 hours <br />5.522487e-4 weeks <br />1.27087e-4 months <br />. Unit One exited Forced Outage QlF41 on April 24, 1997 at 1252 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.76386e-4 months <br /> when the generator was synchronized to the grid. A few other load drops were ,

performed, however the average daily power level remained at 80% or l greater.

B. Unit Two i

Quad Cities Unit Two was shutdown the entire month of April due to i Refuel Outage Q2R14. Start-up is scheduled for May 27, 1997. j i

1 l

l TFalOP3\NRC\ MON 1RLY.RPT

III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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

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

l l

i l

IKHOMWRC40NDU.Y,RFT j

l i

l l

IV. LICENSEE EVENT REPORTS i 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 i the reportable occurrence reporting requirements of 10CFR50.73. I UNIT 1 Licensee Event Reoort Number Eiltg Title of occurrence  ;97-003 3/26/97 Secondary Containment Volume Less than that Dascribed in FSAR. Downgraded to PIR 1-97-060 97-008 4/2/97 High Pressure Coolant Injection (HPCI) inoperable due to Turning Gear Failure.- 97-010 4/7/97 Train "B" Control Room HVAC System Inoperable due to Loss of refrigerant.97-011 4/9/97 The Residual Heat Removal Service Water System was made inoperable due i to uncertainties related to 4 KV Air l Magne-Blast horizontal Gas (AMHG) )

circuit breakers, which had 1 experienced cracks in the auxiliary switches mounting channels. '97-012 4/10/97 It is physically possible for the Unit 1 & 2 Refuel Bridge Monorail Auxiliary Hoists to perform core alterations without a Refuel Bridge Position Interlock actuation. This is outside the design basis which requires the i Refuel Position Interlocks for '

associated equipment to be operable when performing core alterations.97-013 4/16/97 RCIC Hi Temperature Isolation Switch 97-014 4/16/97 Safety Relief Valve not Tested.

NOTE: Sequence of LER Numbers is out of order due to reuse of numbers.

l l

1TCHOP3\NRC\MONTMLY.RPT

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

l .

j .

I UNIT 2 Licensee Event Reoort N"=her D11.t Title of occurrence

! There were no LER's for Unit 2 during the month of April, 1

i b

I l

l l

l

'1 l

l l

TBCNOP3\NRC\ MON 1HLY.RFT l

  • , l A

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

t A. Operating Data Report

8. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions I

i 1

1

)

i l

W 4

4

.)

TBCMOP3WacwoNngty gry

APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNIT Orw 4

DATE May 6,1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241

, OPERATING STATUS 0000 040197

1. REPORTING PEIUOD: 2400 043097 OROSS HOURS IN REPORTING PERIOD: 719
2. CURRENTLY ALTrHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY 769 DEslON ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVEL TO WHI'CH RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REAcrOR WAS CRrflCAL 379.50 2260,10 166760.30 i
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 345.80 2171.50 161700.40
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20 1
9. OROSS THERMAL ENEROY GENERATED (MWH) 727408.80 4946385.60 352119268.10
10. GROSS ELECTRICAL ENEROY OENERATED (MWH) 232367.00 1599937.00 114021367.00 l1. NET ELECTRICAL ENEROY GENERATED (MWH) 221261.00 1527940.00 107682909.00 !
12. REACTOR SERVICE FACTOR 52.78 78.50 75.94
13. REACTOR AVAILABILrrY FACTOR 52.78 78.50 77.50 j 14. UNTT SERVICE FACTOR 48.09 75.43 73.64 I
15. UNrr AVAILABILTTY FACTOR 48.09 75.43 74.05
16. UNrr CAPACTTY FACTOR (Using MDC) 40.02 69.01 63.77
17. UNIT CAPACTTY FACTOR (Using Design MWe) 39.00 67.26 62.15 IS. UNIT FORCED OtfrAGE RATE 51.91 24.57 7.76
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH): N/A
20. IF SHUrDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
21. UNTFS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)
N/A FORECAST ACHIEVED INIrlAL CRTilCALTTY INTilAL ELECTRICTTY COMMERCIAL OPERATION 1.10-9 TECHOP3\NRC\MorrIN11RPT

l

? . l I.

p .

APPENDIX C l

OPERATING DATA REPORT E

DOCKET NO. 50-265 UNfr Two DATE May 6,1997 COMPLETED BY Kristal Siries TELEPHONE (309) 654-2241 OPERATING STATUS 0000 040197 l

1. REPORTING PERIOD 2400 043097 OROSS HOURS IN REPORTING PERIOD: 719
2. CURREffrLY AlfrHORIZED POWER LEVEL (MWi): 2511 MAX > DEPEND > CAPACITY: 769 ~

. DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Ne0: N/A
4. REASONS POR RESTRICrlON (TF ANY): )

THIS MOtfrH YR TO DATE CUMULATIVE

5. NUMBEE ^* HOURS REACTOR WAS CRrrlCAL 0.00 1408.30 161994.85
6. REACTOR RESERVE SHlfrDOWN HOURS 0.00 0.00 2985.80
7. HOURS OENERATOR ON LINE 0.00 1407.70 157657.05 8.' UNrr RESERVE SHITrDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MVH) 0.00 '3477281.".0 343149370.02
10. GROSS ELECTIUCAL ENERGY GENERATED (MWH) 0.00 1118808.00 110135945.00 11 NIrr ELECTRICAL ENERGY GENERATED (MWH) 0.00 1076518.00 104396239.00

)

12. REAcrOR SERVICE FACTOR 0.00 48.92 74.30  !

l

13. REACTOR AVAILABILrrY FACTOR 0.00 48.92 75.67
14. UNrr SERVICE FACTOR 0.00 48.90 72.31
15. UNrr AVAILABaLrrY FACTOR 0.00 48.90 72.63
16. UNIT CAPACITY FACTOR (Using MDC) 0.00 48.62 62.26
17. UNrr CAPACfrY FACTOR (Uning Design MWe) 0.00 47.39 60.69
18. UNrr PORCBD OLTTAGE RATE 0.00 0.00 11.08
19. SHttrDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AN') DURATION OF EACH): N/A
20. IF SHtTfDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 5/27/97
21. UNTTS IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION): FIA

' FOREAST ACHIEVED INrrlAL CRTTICALTTY INITIAL ELECIRICfrY COMMERCIAL OPERATION 1.14-9 TECHOPS\NIKMdOPr!NLY.RFr

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

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE May 6. 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 __

-MONTH April. 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) ,

1. 781 17. -6
2. 785 18. -6
3. 785 19. -6 *
4. 784 20. -7
5. 736 21. -7
6. 648 22. -7
7. 561 23. -6 i
8. ._

636 24. -7

9. 599 25. 30 10.- -7 26. 141
11. -6 27. 535
12. -6 28. 758
13. -6 29. 783
14. -6 30. 782
15. -6 31.
16. -6 l 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 wholt a.s;awatt. 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.

1.16-8 113 CHOP 3\NRC\ MON 1MLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE May 6. 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 MONTH April. 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. -6
2. -8 18. -5
3. -8 19. -6
4. -8 20. -6
5. -8 21. -6
6. -8 22. -6
7. -8 23. -6
8. -8 24. -7
9. -8 25. -8
10. -6 26. -8
11. -5 27. -8
12. -6 28. -8
13. -6 29. -8
14. -6 30. -8
15. -6 31.
16. -6 INSTRUCTIONS On this form, list the average uaily unit power level in MWe-Net for each day 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 j 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

.i output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TECHOP3WIOMON1NLY.RPT

l 1

l l

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME gne COMPLETED BY Kristal Sirles DATE May 6. 1997 REPORT MONTH April, 1997 TELEPHONE 309-654-2241 I

h.

e '

H m O g 2 m $

C b h@ 28

$ LICENSEE ,

DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 97-07 4/6/97 F 4 B 5 --------- --- ---- Performed Load Drop to Adjust the $ctroint i aner receiving a High Level Alarm from the ID3 Feedwater Heater.

97-08 4/9/97 F 373.2 A 2 --------- --- ---- Forced Outage QlF41 due to Cracked Mounting Channels in the 4KV Breaker Auxiliary switches.

I I

l I~ i

, 1 l

l a l TECHOP3\NRC\ MONTHLY.RIT

_ .m.._.4 ..____. ._ _ m. - . _ _ _ . _ . , _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ . . . . _ _ _ . _ . . _ . _ . _ _ . _ . . . . _ _ _ . . _ _ _ . _ _ _ _ _ _

J 1

. I

. 1 i

j APPENDIX D )

. UNIT SHUTDOWNS AND POWER REDUCTIONS i

! I DOCKET NO. 50-265 i

, UNIT NAME Two COMPLETED BY Kristal Sirles l DATE May 6, 1997 REPORT MONTH Acril 1997 TELEPHONE 309-654-2241

-e O $, $

M M M  !

Ag o a N.h N0 0

to 8

1- LICENSEE .

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT I 97-03 4/1/97 5 719 C 4 .......... ... .... Continuation of Refuel Outage Q2R14.

  • 4 I

)

i ]

J J

l 1

l 1

i 1

TECHOP3\NRC\ MON 1MLY.RPT

VI. UNIOUE REPORTING RE0VIREMENTS The following items are included in this report based on prior commitments to the commission:

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 The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram timing for the reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG.

I l

TFfHOP3\NRC\ MONTHLY.RPT

VII. REFUELING INFORMATION i

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.

l l

l l

i i

' 1 i

e l

l TECHOP3\NRC\ MONTHLY.RPT

l QTP 0300-S32

. Revision 3 April 1997 I

QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit: 01 Reload: 14 Cycle: 15
2. Scheduled date for next refueling shutdown: 3/28/98 l
3. Scheduled date for restart following refueling: 5/29/98
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: ,

No l

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

5/9/98

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

7. The number of fuel assemblies.
a. Number of assemblies in core: 724
5. Number of assemblies in spent fuel pool: 1933
8. Thr. present licensed spent fuel pool storage capacity and the size of ary 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 1

(final) l I

i l

  • i ~

l '

QTP 0300-S32

. Revision 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit: 02 __ Reload: 14 Cycle: 15
2. Scheduled date for next refueling shutdown: 3/1/97 ,
3. Scheduled date for restart following refueling: 5/27/97 i
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: '

Yes i

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

Submittals began August 1996; ongoing process.

6. Important licensing considerations associated with refueling, e.g., new i or different fuel design or supplier, unreviewed design or performance

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

l l 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded during l Q2R14.

7. The number of fuel assemblies.
a. Number of assemblies in core: 0 l b. Number of assemblies in spent fuel pool: 3667
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:

I a. Licensed storage capacity for spent fuel: 3897 l

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

=

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

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

, LLRT - Local Leak Rate Test i

LPCI - Low Pressure Coolant Injection Mode of RHRs l LPRM - Local Power Range Monitor  !

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate

! MCPR - Minimum Critical Power Ratio l MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration

! MSIV - Main Steam Isolation Valve l NIOSH - National Institute for Occupational Safety and Health i

PCI - Primary Containment Isolation l PCIOMR - Preconditioning Interim Operating Management Recommendations  !

RBCCW -- Reactor Building Closed Cooling Water System i RBM - Rod Block Monitor i RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System l

RPS - Reactor Protection System l RWM - Rod Worth Minimizer l SBGTS - Standby Gas Treatment System

- Standby Liquid Control SBLC SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water Systea

! TIP - Traversing Incore Probe TSC - Technical Support Center P

11EllOP)\NRCWONTHLY.RPT

._

Retrieved from "https://kanterella.com/w/index.php?title=ML20141C287&oldid=2858356"