ML20059K080

Monthly Operating Repts for Oct 1993 for Quad-Cities Nuclear Power Station Units 1 & 2

ML20059K080
Person / Time
Site:	Quad Cities
Issue date:	10/31/1993
From:	Michael Benson, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-93-12, NUDOCS 9311150185
Download: ML20059K080 (23)

Text

{{#Wiki_filter:. Commonwe:Ith Edison Guad Cities Nuclear Power Station - }' 22710 206 Avenue North A Corcova, I!!inois 61242 N Teler, hone 309/654-2241 AMS-93-12 November 2, 1993 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. 50-234 and 50-265 Enclosed for your information is the Monthly Pe.rformance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of October 1993. Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc: J. Martin, Regional Administrator T. Taylor, Senior Resident Inspector Y TiiCHOP3 SRr.MOND!LY.RPT d) 15110'l ' 2225 285 932o32 /' PDR ADOCK 05000254 R PDR (

[.' i I t .i QUAD-CITIES NUCLEAR POWER STATION -1 I UNITS 1 AND 2 l r L MONTHLY PERFORMANCE REPORT .[ t; i F October 1993 i e COMMONWEALTH EDISON COMPANY i I AND i IOWA-ILLINOIS' GAS & ELECTRIC COMPANY I NP.C DOCKET NOS. 50-254 AND 50-265 1 LICENSE NOS. DPR-29 AND DPR-30 t r e '5 a t i i i 'l TECHOP?WROMONTHLY.RPT i

L 4 .1 i TABLE OF CONTENTS i I. Introduction j II. Summary of Operating Experience f A. Unit One B. Unit Two i III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance j t 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 IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions I i i VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary y I J l TEQlOP3'XRCMONTHLY.RPT

i + i i 'I t I. INTRODUCTION f Quad-Cities Nuclear Power Station is composed of two Boiling Water ~ t Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is 3intly owned by Commonwealth Edison l I 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 Mississippi 1 River is the condenser cooling water source. The plant is subject to license 1 numbers DPR-29 and DPR-30, issued October 1, 1971, and 74rch 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 powar began on i 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. 'i i TECHOPT.NRCMONDILY.RFT 4 x.

l t II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One began the month of October 1993 at full power. i On October 16, Unit One was reduced to 25% power so a.drywell entry could be made to test the torque switch settings of the recirculation 1-0202-5A.alve. Concern over the 1-0202-5A valves ability to close under design basis differential pressure lead to the test. l B. Unit Two Quad Cities Unit Two began the month'of October 1993 at full power. On October 1, Unit Two reduced power and took the turbine off line due to a hot cable in the Main Power transformer cabinet. The cable was replaced and the generator was back on line less than 5 hours later that same evening. On October 17, Unit Two was reduced to 25% power so a drywell entry could be made to test the torque switch settings of the recirculation 2-0202-5B valve. Concern over the 2-0202-5B valves ability to close under design basis differential pressure lead to the test. J 1 i EEHOP3WRCMON"UILY.RMI l I

b I l l III. PLANT OR PROCEDURE CHANGES.-TESTS. EXPERIMENTS, AND SAFETY RELATED MAINTENANCE } i A. Amendments to Facility License or Technical Specifications i There were no Amendments to the Facility License or Technical Specifications for the reporting period. [ B. Facility or Procedure Chances Recuirina NRC Accroval 'i .t There were no Facility or Procedure changes requiring NRC approval for the reporting period. { C. Tests and Experiments Reauirina NRC Approval l There were no Tests or Experiments requiring NRC approval for the [ reporting period. D. Corrective Maintenance of Safety Related Eculement The following represents a tabular summary of the major safety related maintenance performed on Units One 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. 4 ) 6 i i I ? i l t i 1 1 TECHOP3'NRCMONTHLY.RPT

UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q10057 1000 1-1001-34B Install new motor, Replaced limitorque with new pinion, and worm shaft motor, worm shaft, and pinion. gear for 1B torus spray / torus cooling stop valve. Q10142 1400 1-1402-57 Troubleshoot / repair ESS Found filter clogged. Replaced fill system pump. entire pump / motor assembly. Motor temperature observed high. Q10171 1100 1-1100 Adjust heat tracing for Adjusted heat tracing to standby liquid control acceptable range. piping. Q10275 203 1-203-1B Troubleshoot / repair 1B Replaced and adjusted limit MSIV. Dual indication switch. received. Q10396 5700 1/2-5741-Repair pressure Removed gauge, recalibrated, and 335 indicator for "B" reinstalled. control room HVAC corcpressor discharge. Q10519 756 1-756-6 Troubleshoot / repair Replaced voltage regulator. APRM #6. Positive voltage out of tolerance. Q89660' 8350 1/2-8350 Investigate / repair Installed new relays and circuit 250VDC charger. boardo. .~

UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q07630 1000 2-1001-65C Repair RHR service Replaced casing ring and rebuilt water pump as required. pump. Q08627 300 2-305-125-Replace nitrogen / water Replaced accumulator with a new 1043 accumulator. Water is

one, leaking past piston.

009529

263, 2-263-Repair /recalibrate Calitrated both "A"and "B"

600 100A,B reactor water level loops. 152A,B indicators. 2-640-29B,3B 2-646B 009837 220 2-220-62B Repair "B" feedwater Replaced seal ring and tightened header 1st outboard bolts to 1 1/2 times normal check valve. Seal. ring torque., Reduced leakage from 3 leaks. and 1/2 gal / min to 1 quart / min. Q09997 203 2-203-1A Repair 1A inboard MSIV. Replaced live load assembly and Did not fail safe packing assembly. during surveillance'. Q09998-203 2-203-1D Repair ID inboard MSIV. Unpacked valve and repacked Did not fail safe valve with a new carbon spacer. during surveillance. Q10092 750 2-750-7G Investigate / repair IRM Replaced preamplifier. spiking full scale. Q10107 1000 2-1001-34A Troubleshoot RHR torus Replaced motor, worm shaft, spray / dump shutoff pinion, and overload heater. l valve.

a-NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q10218 2300 2-2301-3 Investigate / repair leak Replaced valve stem, seal ring, on HPCI turbine inlet valve sleeve, and packing valve. assembly. Q10361 1000 2-1099-75C Repair 2C RHR service Found valve exterior badly water pump upstream corroded and valve stem frozen seal isolation valve. in the closed position. Took valve apart, cleaned, and reinstalled. Q10363 1000 2-1099-76C Repair 2C RHR service Found valve exterior badly water pump downstream corroded and valve stem frozen seal isolation valve. in the closed position. Took valve apart, cleaned, and reinstalled. Q10542 1700 2-1705-3B Troubleshoot / repair "B" Replaced printed circuit board steam jet air ejector with correct type. log rad monitor. Q106D8 590 2-590-108D Repair SCRAM relay. Installed plunger post back into Aux contact arm was plunger arm. disengaged from main relay. Q10788 300 2-305-101-Repair CRD insert valve Found packing bolt broken off 1831 leak. and valve leaking. Installed new valve, bolt, and nut.

i .j ? IV. LICENSEE EVENT REPORTS i l The following is a tabular summary of all licensee event reports for Quad-l 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. l UNIT 1 i There were no licensee event reports for Unit 1 for this reporting period. .l t UNIT 2 Licensee Event Report Number Date Title of occurrence f 93-022 10-07-93 RCIC declared INOP when floor drain check valve failed test. I t k I f r 't i 'l TBOIOPLNRCMONDiLY.Ryf

i l .l V. DATA TABULATIONS i The following data tabulations are presented in this report: A. Operating Data Report t i B. Average Daily Unit Power Level i t Unit Shutdowns and Power Reductions t I i T [ .i

t

.i h i e t [ L h i 4 I 1 L i I 1 1 . TEQlOP3WRCMONTMLY.RPT 1

i i APPENDIX C l} OPERATING DATA REPORT DOCKET NO. 50-254 UNTT One j DATE November 4, 1993 l r COMPLETED BY ' Matt Benson TELEPHONE. (309) 654-2241 OPERATING STATUS 0000 100193 3 4

1. REPORTING PERIOD: 2400 103193 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET); 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 CRTTICAL 745.00 6494.20 149255.10

6. REACTOR RESERVE SIIUTDOWN HOURS 0.00 0.00 3421.90 i

'7. IlOURS GENERATOR ON LINE 745.00 6428.80 144820.40 {

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWHJ 1756263.00 15052293.30 312634117.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 574387.00 4932446.00

'101351536.00 I

11. NLT ELECTRICAL ENEROY GENERATED (MWH) 549380.00 4718622.00 95594134.00

12. REACIOR SERVICE FACTOR 100.00 89.01 78.99

13. REACTOR AVAILABILTTY FACTOR 100.00 89.01 80.80

14. UNTT SERVICE FACTOR 100.00 88.11 76.64 i

15. UNTT AVAILABILTTY FACTOR 100.00 88,11 77.13

16. UNTT CAPACTTY FACTOR (Using MDC) 95.89 84.10 65.79

17. UNIT CAPACTTY FACTOR (Using Design MWe) 93.46 81.97

~' 64.12 I8. UNTT FORCED OUTAGE RATE 0.00 ' 11.89 6.10

19. SilUTDOWNS SCHEDULED OVER NEXT 6 MofffHS (TYPE, DATE, AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTLMATED DATE OF STARTUP:

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

FORECAST ACHIEVED [ t INITI AL CRTTICALTTY l t INITIAL ELECTRICITY i COMMERCIAL OPERATION 1.16-9 TECHOP3WRC%f0NTHLY.RfT i 8

f 9 APPENDIX C OPERATING DATA REPORT DOCKET NOf 50-265 UNIT Two DATE November 4, 1993 t COMPLETED BY Matt Benson - I TELEPHONE (309) 654-224I OPERATINO STATUS t 0000 100193

1. RElaORTING PERIOD: 2400 103193 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 f

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION GF ANY):

i t THIS MONTH YR TO DATE CUMULATIVE t

5. NUMBER OF HOURS REACTOR WAS CRITICAL 745.00 3965.50 143140.75

6. REACTOR RESERVE r.<sUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 740.30 3781.40 139422.85 l

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

-i

9. GROSS THERMAL ENERGY GENERATED (MWH) 1732716.00 8269142.00 300932551.20 t

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 577251.00 2688045.00 96713306.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 552497.00 2545349.00 91576092.00

12. REACTOR SERVICE FACTOR 100.00 54.35 76.39

+

13. REACTOR AVAILABILITY FACTOR 100.00 54.35 77.98 l

14. UNIT SERVICE FACTOR 99.37 51.83 74.40

15. UNTT AVAILABILTTY FACTOR 99.37 51.83 74.78

16. UNrr CAPACTTY FACTOR (Using MDC) 96.44 45.37 63.55

17. UNIT CAPACITY FACTOR (Using Design MWe) 93.99 44.22 61.94

{ l8. UNIT FORCED OUTAGE RATE 0.63 29,13 8.53

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED D ATE OF STARTUP:

21. UNTTS IN TEST STATUS (PRJOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INTTIAL CRTTICALITY INITIAL ELECTRICTTY a l COMMERCI AL OPERATION l.16-9 + TEGIOP3WRC\\ MONTHLY.RPT [

+ 'I 't 'f -APPENDIX B AVERAGE DAILY UNIT POWER LEVEL 'i DOCKET NO 50-254 UNIT One f I DATE November 4. 1993 COMPLETED BY Matt Benson .i TELEPHONE (309) 654-2241 MONTH October 1993 v DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) ' (NMe -Net) .. j 5 1. 761 17. 660 2. 7C2 18. 757 ? 3. 727 19. 761 j t 4. 760 20. 760 5. 754 21. 758 6. 758 22. 760 7. 755 23. 729 l 5 8. 756 24. '755 9. 760 25. 757 i 10. 758 26. 758 11. 754 27. 759 t 12. 757 28. 757 -l 3 13. 750 29. 761 14. 760 30. 760 15. 734 31. 760 -I 1 16. 280 INSTRUCTIONS On dhis 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 i 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. t 1.16-8 L TEGIOP3WRCMONDE.Y.UT - i e

m. _ ...m. ~., .i l i ,i AVERAGE DAILY UNIT POWER LEVEL j APPENDIX B -DOCKET NO 50-265 UNIT Two -[ DATE-November 4.'1993= COMPLETED BY Matt Benson' l TELEPHONE' (309) 654-2241' -j MONTH _Qctober 1993 [ DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL b '{ (MWe -Net) (MWe-Net) 'f 1. 503 17. 400 l 2. 697 18. 754 3. 766 19. 760 l 4. 768 20. 763 5. 769 21. 765 6. 766 22. 765 7. 766 23. 765 .i 8. 764 24. 761' 9. 765 25. 762 10. 766 26. 765 11. 766 27. 764 4 12. 763 28. 765 I 13. 755 29. 766 .i 14. 761 30. 766 f ' 15. 765 31. 765 A 16. 747-i 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 nonth. Note that when maximum dependable capacity is used for the net-electrical rating of the unit, there .l may be occasions when the daily average power level-exceeds the'100%,line J (or ; ) the restricted power. level line). In such cases, the average daily unit power. output sheet should be footncted to explain the apparent anomaly. j 1.16-8 TEC'dOP341RCMONTHLY.RPT

l i

5

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l f DOCKET NO. 50-254 UNIT NIJE One COMPLETED BY Matt Benson DATE October 6, 1993 REPORT MONTH October 1993 TELEPHONE 309-654-2241 N rn g O@

q M

O MM $M AN HQ $Q '40 en O O -1 H pJ MU hU LICENSEE O I DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 9154 10-15-93 F 17.8 B 5 LPCI Mode INOP because of Recirc 5A Velve Torque Switch setting. i 1 1 3 6 I i \\ i 5 e 9 I I l i { L TECHOP3.NRC\\ MONTHLY.RPT i

.1 . l ) APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Matt'Benson .l t [ DATE Novebmer 4. 1993 REPORT MONTH October, 1993 TELEPHONE 309-654-2241-i a: i M Z E @M W O MW Oh f* O O

4. N MO O

O O i g SU [ pc-3 MU w m $M$ LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 93 16 1001-93 F 4.7 B 5 Ilae Cable on TR2 Cabinet. [ 93-17 10-16-93 F 13.5 B 5 Li'CI Mode INOP because of Recirc 5B Valve Torque Switch Setting, e i i f .i e i i ^! i i f'! V 1 t TIf}10P3iNRC,MONTilLY.RPT t k

7g i VI. UNIOUE' REPORTING REOUIREMENTS 'l t i The following items are included in this report based on prior commitments to the commission: A. Main Steam Relief Valve Ooerations i There were no Main Steam Relief Valve Operations for the reporting period. B. Control Rod Drive Scram Timinct Data for Units One and Two I l The basis for reporting this data to the Nuclear. Regulatory Commission.are specified in the surveillance requirements of Technical-Specifications f 4.3.C.1 and 4.3.C.2. l. 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 i performed with reactor pressure greater than 800 PSIG. l ? I I i n 1 ~b i 9 .i I i l ) l.; j } i a ~l i '. TEGIOP3'.NRC. MONTHLY.RPT I

e RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES. FROM 01/01/93-TO 12/31/93 ~ i AVERAGE TIME IN SECONDS AT % MAX. TIME i INSERTED FROM FULLY WITHDRAWN FOR 90% INSERTION' DESCRIPTION NUMBER 5 20 50 90 Technical Specification 3.3.C.1 &- DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Averacte Scram Insertion Time) 01-28-93 1 0.30 0.67 1.42 ^5 H-12 For Accumulator Replacement 2.15 02-12-93 1 0.33 0.72 1.54 2.77 D-5 Accumulator Replacement U2 005404 2.77 '02-26-93 1 0.32 0.69 1.46 2.61 K-7 Scram Inlet Valve U2 Q05593 2.61 05-28-93 177 0.32 0.705 1.49 2.60 D-9 U2 Start Up Scram Timing Q2R12 3.47 07-13-93 4 0.33 0.73 1.51 2.60 D-9 For WR Test Q08085 Q07146 2.69 U2 Q08364 Q07147 07-23-93' 90 0.31 0.69 1.45 2.53 -D-8 U1 SEQA & Q08229 3.4 I '07-29-93 1 0.32 0.71 1.51 2.66 F-10 U2 Q08629 Accumlator 2.66 08-07-93 1 0.28 0.64 1.37 2.39 F-15 U1-Q09059 Scram Solenoid 2.39 08-19-93 1 0.28 0.60 1.26 ~ 2.19 A-8 U1_Q09374 Di'aphragm 2.19 09-24-93 1 0.32 0.68 1.41 .2.46 C-11 U2 Q08627 Accumulator 2.46 10-23 1~ 0.34 0.71 1.45 ~2.51 D-4 U1 Q11022 Scram Valve 2.51 10-28-93 1 0.28 0.65 1.42 2.52 J-12 U1 Q11231, Q11151 2 WR 1 CRD 2.52 i NRCISCRMT1htE.FRM

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1 1 I VII. REFUELING INFORMATION i .i The following information about future reloads at Quad-Cities Station was l requested in a January 26, 1978, licensing memorandum (78-24) from D. E. j O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC j Request.for Refueling Information", dated January 18, 1978. l 6 i + 3 I f l I i I - 1 9 i L i i i A b ) TIGIOPt.NROMONTHLY.RPT E I r ,-m 4

3 QTP-300-532 Revision 2 QUAD CITIES REFUELING October 1989' INFORMATION REQUEST l. Unit: 41 Reload: 12 Cycle: 13 2. Scheduled date for next refueling shutdown: 3-14 ' 3. Scheduled date for restart following refueling: 6-13-94 4. Will refueling or resumption of operation thereafter require a Technical. Specification change or other license amendment:- YES. Safety Limit MCPR to be cbanged from 1.06 to 1.07 due to GE10 Fuel. 5. Scheduled date(s) for submitting proposed licensing action and supporting information: l 11-19-93 i 6. Important itcensing 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 i procedures: 160 GE10 Fuel Bundles will be Icaded during Q1R13. 7. The number of fuel assemblies. a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 1557 l 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 i planned in number of fuel assemblies: i a. Licensed storage capacity for spent fuel: 3657 b. Planned increase in licensed storage: 0 4 9. The projected date of the last refueling that can be discharged to the-spent fuel. pool assuming the present licensed capacity:2009 i I i APPROVED i-14/0395t Q.C.O.S.R. l T

~- 3'I QTP 300-532 i Revision 2 QUAD CITIES REFUELING October 1989 1 INFORMATI0ii REQUEST 1. Unit: Q2 Reload: 12 I3 Cycle: -2. L.heduled date for next refueling shutdown: 09-24-94 l 3. Scheduled date for restart following refueling: l'2-04 ! 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: j YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel. 5. Scheduled date(s) for submitting proposed licensing action and supporting information: ) 5-13-94 I 6. Important licensing considerations associated with refueling, e.g., new j or different fuel design or supplier, unreviewed design or. performance analysis methods, significant changes in fuel design, new operating procedures: GE10 Fuel will be loaded during Q2R13. l 7. The number of fuel assemblies. i a. Number of assemblies in core: 724 -{ b. Number of assemblies in spent fuel pool: 2583 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: 2009 j APPROVED 14/0395t O.C.O.S.R. 1 j

r .- j! t l 4 t I VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, h are defined below: l I ACAD/ CAM - Atmospheric Containment Atmospheric (! Dilution / Containment Atmospheric Monitoring'

f ANSI

- American National Standards Institute APRM - Average Power Range Monitor ll ATWS - Anticipated Transient Without Scram ,l BWR - Boiling Water Reactor CRD - Control Rod Drive f EHC - Electro-Hydraulic Control System [ EOF - Emergency Operations Facility l GSEP - Generating Stations Emergency Plan l HEPA - High-Efficiency Particulate Filter l HPCI - High Pressure Coolant Injection System l HRSS - High Radiation' Sampling System j IPCLRT - Integrated Primary Containment Leak Rate Test l IRM - Intermediate Range Monitor ISI - Inservice Inspection .j LER - Licensee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode of RHRs LPRM - Local Power Range Monitor l ~ - MAPLHGI4 - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration l MSIV - Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and. Health Primary Containment Isolation PCI PCIOMR - Preconditioning Interim Operating Management Recommendations Reactor Building Closed Cooling Water System ') RBCCW .~' RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System ,1 RWM - Rod Worth Minimizer ~I 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 System TIP - Traversing Incore Probe TSC - Technical Support Center TEcHoP3WitcMONTHLY RPT i I ,) .}}