ML20064F113

Monthly Operating Repts for Feb 1994 for Quad-Cities Nuclear Power Plants Unit 1 & 2

ML20064F113
Person / Time
Site:	Quad Cities
Issue date:	02/28/1994
From:	Michael Benson, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-07, AMS-94-7, NUDOCS 9403150164
Download: ML20064F113 (29)

Text

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Commonwealth Edison Quad Cities Nuclear Power Station O 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 1

AMS-94-07 March 2, 1994 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 HRC Docket Nos. 50-254 and 50-265 6 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 February 1994.

Respectfully, i

COMMONWEALTH EDISON COMPANY I QUAD-CITIES NUCLEAR POWER STATION l

,4b UY Anthony M. Scott System Engineering Supervisor AMS/dak l

Enclosure cc: J. Martin, Regional Administrator  !

T. Taylor, Senior Resident Inspector nrHOl%kCWONTitt.Y.RFT p I

9403150164 940228 '

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PDR ADOCK 05000254 y R PDR

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT February 1994 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECitOP3\NRC\MONTHI.Y RPT

TABLE OF CONTENTS i I. 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 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 VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations 1 B. Control Rod Drive Scram Timing Data l

VII. Refueling Information j VIII. Glossary l

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I. INTRODUCTION 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 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 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 .

l February 18, 1973 for unit One and March 10, 1973 for unit Two. )

l This report was compiled by Matt Benson and Debra Kelley, telephone number !

309-654-2241, extensions 2995 and 2240.  ;

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I II.

SUMMARY

OF OPERATING EXPERIENCE  !

A. Unit One Quad Cities Unit One began the month of February 1994 at full capable load and remained on line through out the month. The unit was in coast down as it approached the refuel outage scheduled for March 13.

1 Numerous load drops were performed on request from Bulk Power Operations (BPO) and for administrative reasons but none caused the average daily unit power level to drop by 20% or greater.

B. Unit Two Quad Cities Unit Two began the month of February 1994 at full load and remained on line through out the month. One load drop, to 200 MWe, was made on February 12 at 20:55 hours, to allow a drywell entry. The RHR system was periodically alarming high pressure due to leakage through two manual test tap valves on the Low Pressure Coolant Injection (LPCI) line.

Numerous load drops were performed on request from Bulk Power Operations (BPO) and for administrative reasons but none caused the average daily unit power level to drop by 20% or greater.

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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. l AND SAFETY RELATED MAINTENANCE l

1 A. Amendments to Facility License or Technical Specifications  !

There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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

C. Tests and Experiments Requirina NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Eauipment 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, System Component Description and work performed.

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UNIT 1 & 1/2 MAINTENANCE

SUMMARY

! NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED i

l -' 008022 0300 1-8300-1B-1 Remove grounds at After extensive troubleshooting,

! 125VDC battery and found water intrusion into the charger. fire eyes and wiring on trasformer 11. Lifted cable going to the fire eye.

008641 0756 1-0756- Repair LPRM. Replaced LPRM card with a new 56-25B one.

Q09791 2200 1/2-2212- Investigate / repair Replaced timer meter with a new 29B problem with SBGT run one.

time meter.

2 Q10910 0300 1-0305-2203 Calibrate CRD HCU Replaced switch with a new one.

pressure switch. ,

Q10933 2500 1-2540-10B Investigate ACAD flow Found capacitor in the power

- 15B controller incorrect supply was bad. Replaced with a

-26B indication problem. new capacitor. Found Q4_on the 1-2541-10B output board was also bad.

-17B Replaced with new Q4.

- 8B  ;

Q11499 1000 1-1001-3D Repair 1D RHRSW-pump Found wedge laying cocked on  ;

discharge valve. Valve guides without stem connected.

travels only 1.5". Reassembled valve.

Q12654 2500 1-2501 Investigate / repair Calibrated 1-2540-20 trip unit ,

1-2540-12 ACAD compressor. and 1-2540-12 pressure indicator.

-20 Compressor does not ,

, 1-2541-20 start normally. ,

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_ _ _ _ _______________m_ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - . _ . _ _ - _ m-...

i NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q13261 2500 1-2540-13B Investigate / repair Found capacitor in the controller

-25B valve stroke time in bad. Replaced with a new .

-6B the required action capacitor. Found calibration of 1-2541-2B range. E/P 1-2541-6B way off. ,

-6B Recalibrated E/P. Adjusted 1-2599-5B calibration of 1-2540-25B. I Q13778 3900 1/2-3941-27 Investigate / repair Flushed line to remove debris. '

DGCWP incorrect Indication returned to normal.

indication.

Q14205 0300 1-0305-126- Investigate / repair rod Adjusted lift pressure for stem 3003 drifting from position on 127 scram outlet valve.

1-0305-127- 48 to position 14. ,

3003 Q14392 2300 1-2301-31 Repair diaphragm leak Found diaphragm blown through.

on HPCI steam trap Replaced diaphragm.

I, drain line bypass valve.

Q14421 0756 1-0756-5 Investigate / repair Replaced APRM circuit board and fluctuations on APRM power supply circuit board.

1. 5.

Q14458 1700 1-1705-2B Repair / replace MSL log Replaced with new log rad radiation monitor monitor.

digital display.

Q14654 5700 1-5741B Inspect / repair reactor Replaced pilot valve, check building vent valve, drain valves, and fittings isolation damper. and tubing as required.

Q14655 5700 1-5742A Inspect / repair reactor Replaced 1 ball valve, 2 check building vent return valves, and the 2-way valve.

isolation damper. ,

--- - -------- -- --+------ - ..er - m s,.,,-- , , .

NWR# SYSTEM -EPN# WORK REQUESTED WORK PERFORMED Q14656 5700 1-5742B Inspect / repair reactor Installed new tubing, 2 check building vent return valves, and 1 ball valve.

isolation damper

, actuator.

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UNIT 2 MAINTENANCE SUMMA.Y R -

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 007572 0220 2-0220-118A Replace root valve. Replaced valve.

Q08004 0756 2-0756- Repair LPRM. LPRM Replaced circuit board.48-41D failed to alarm when hi alarm was reached.

Q08886 0300 2-0305-126- Investigate scram Adjusted the scram inlet valve 1435 discharge volume not seating pressure.

drained alarms.

Q08917 2300 2-2302 Repair oil leak on HPCI Replaced cover gasket and pump north outboard installed new flange bolts.

bearing.

, Q09252 0020 2-0020B-RHR Repair submarine door. Replaced hinge pin torsional

Door does not close spring and pin.

properly.

Q09693 2500 2-2599-10B Investigate / repair Found ACAD to SBGT valve 2-2599-

-15B failed test QOS 2500-4. 10B sticking. Replaced valve

-16B plug and stem. Repacked valve

-5B and installed a new bonnet gasket.

Q10006 0261 2-0261-30A Replace test fittings Replaced tubing tee and tubing for main steam line low plug.

pressure switch.

Q10011 0203 2-0203-1D Repair 1D inboard MSIV Found some blockage in the actuator. Valve failed exhaust restrictor. Rebuilt to reposition. valve with repair kit and .

cleaned exhaust restrictor.

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j NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q10187 2300- 2-2302 Repair various oil Replaced piping and. installed i 2-2303 leaks on HPCI pump and new round gasket.

turbine. ,

Q10254 1400 2-1402-9A Repair 2A core spray Replaced 3 cap screws. ,

testable check valve. '

Q10442 8700 '2-8741-30 Repair torus D/P Replaced E/P converter with a pressure control valve new one.

E/P transducer.

Nitrogen make-up flow ,

will not respond to controller.

!- Q10577 0203 2-203-3B Replace pilot valve. Replaced pilot valve assembly.

High tailpipe l temperatures observed.

Q10684 1000 2-1001-16A Replace damaged Replaced damaged sealtite with a sealtite on RHR heat new one.

i exchanger bypass valve

operator.

Q11079 0755 2-0751A,-B, Perform diagnostic Cleaned connector at IRM 11.

, C,D testing on all IRM's Cleaned input and output l 2-0755 and S RM' s . connectors on pre-amp and 2-760A,B,C, cleaned' input. connector on D,E,F, chassis for SRM 21.

G,H Q11185 5700 2-5747 Noted high DP on HPCI Replaced header gaskets, baffle room cooler. Clean gaskets, air filters, and cap cooler. screws.

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED -

Q11584 2300 2-2301-31 Inspect / repair HPCI Found disc and seat badly steam steam trap drain line cut. Also found diaphragm was i

bypass valve during brittle. Installed rebuilt special test. operator and a new trim set on valve.

Q11949 3900 2-3903 Replace incorrect DGCWP Replaced coupling with correct coupling with correct coupling.

coupling.

{ Q12626 0203 2-0203-1B Repair / replace 2-way Cleaned and installed rebuild valve on 1B inboard kit.

MSIV.

Q12627 0203 2-0203-1A Repair / replace 2-way Cleaned and installed rebuild valve on 1A inboard kit.

MSIV.

Q12628 0203 2-0203-1C Repair / replace 2-way Cleaned and installed rebuild valve on 1C inboard kit.

MSIV.

Q12670 1100 2-1154 Investigate / repair Changed setpoint from 78 degrees contact chatter on SBLC to 83.5 degrees.

temperature indicating controller.

Q12849 4600 2-4699-225 Repair DG starting air Installed new ball valve.

shutoff valve. Unable 4

to determine valve position.

Q13010 0203 2-0203-3D Repair broken off ERV Installed new line.

above seat leakoff line.

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V NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q13147 1000 2-1001-5A RHRSW heat exchanger Lubricated anti-rotation keys. '

discharge control valve ,

will not close beyond L 45%.

Investigate / repair.

i Q13235 1600 2-1601-33B Repair sealtite for Replaced sealtite. ,

torus to drywell vacuum breaker indication. l Q13441. 2300- 2-2301-6 Repair HPCI pump CCST Found declutch pin broken off in suction. valve cap. Installed new pin in cover  !

limitorque. and reinstalled.

Q13575 7800 2-78282-C3 Replace broken handle Replaced breaker.

on MCC 28-2 cubicle C3, main hydrogen seal oil l pump breaker.

Q13579 2300 2-2399-66 Repair HPCI turbine Polished disc to remove minor exhaust line vacuum pitting. Cleaned and assembled breaker check valve. valve with a new gasket.

Valve failed to close during test.

Q13580 2300 2-2399-67 Repair HPCI turbine Polished disc to remove minor

. exhaust line vacuum pitting. Cleaned and assembled breaker check valve. valve with a new gasket.  !

Valve failed to close-during test.

Q13691 2300 2-2308 Investigate ground on Dried out motor. Installed new HPCI auxiliary oil pump winding in motor from a spare motor. motor.

Q13726 0300 2-0305-125- Repair chronic high Replaced nitrogen / water

-5027 water alarns on accumulator.

accumulator.

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NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q13972 4600 2-4641-40 Repair broken fitting Replaced fitting with a new one.

on diesel starting air j low pressure switch.

Q14089 0203 2-0203-2A Repair / replace 2A Cleaned 2-way valve and outboard MSIV. Valve reassembled valve with a rebuild failed QCOS 250-8. kit.

Q14243 2300 2-2303 Repair oil leak on Found fitting loose. Tightened fitting below the HPCI fitting and verified no leakage.

motor speed changer.

Q14295 1300_ 2-1360-13 Repair steam leak at Cleaned sealing surfaces, RCIC drain pot level installed a new gasket, and switch. tightened magnetrol at tank connection.

Q14394 0300 2-0305-111- Replace 111 valve and Changed out accumulator and 4211 nitrogen charging cap. cartridge valve.

Q14489 1600 2-1640-10A Calibrate torus wide Found 5A and 5B transmitters out

-10B range level indicators. of cal low. Recalibrated both  !

2-1641-5A transmitters. ,

-5B Q66089 2300 2-2301-35 Replace "open" push Installed new switch.

button switch for HPCI pump downstream torus suction valve operator.

Q97494 6600 2-6601 Replace spring on Replaced cap brush holder with a diesel generator brush new one.

holder cap. ,

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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 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.

UNIT 1 Licensee Event Report Number Qate Title of occurrence 94-004 02-01-94 RCIC INOP when Trip Throttle Valve is tripped.

UNIT 2 Licensee Event Report Number Date Title of occurrence 94-003 01-31-94 HPCI IN0P when room cooler declared IN0P.94-004 02-08-94 TS Surveillance for Instrument Response when Control Rod withdrawn not done in a timely manner.

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

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions L

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l APPENDIX C OPERATING DA"a*A REPORT DOCKLT NO. 50-254 UNIT One DATE March 3,1994 COMPLETED BY Matt Benson TELEPIIONE (309) 654-2241 OPERATING STATUS 0000 020194

1. REPORTING PERIOD: 2400 022894 GROSS IlOURS IN REPORTING PERIOD: 672 l

2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 MAX > DEFEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWo-NET): 789

3. POW 12 LEVEL TO WHICil RESTRICTED (IF ANY) (MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTl! YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRTTICAL 672.00 1( M 00 151197.30

6. REACTOR RESERVE SlitTTDOWN HOURS 0.00 0.00 3421.90

7. IIOURS GENERATOR ON LINE 672.00 1393.40 146689.70

8. UNIT RESERVE SilUTDOWN HOURS 0.00 0.00 909.20

( 9. GROSS TIIERM AL ENERGY GENERATED (MWII) 1547105.00 3243608.50 316936795.70

10. GROSS ELECTRICAL ENERGY GENERATED (MWif) 507760f0 1062432.00 102760551.00

11. NET ELF 47RICAL ENERGY GENERATED (MWil) 4860(M.00 1016641.00 96934639.00

12. REACTOR SERVICE FACTOR 100.00 100.00 78.82

13. REACTOR AVAILABC.!TY FACTOR 100.00 100.00 80.60

!4. UNIT SERVICE FACTOR 100.00 98.40 76.47

15. UNIT AVAILABiLTTY FActu~t s00.00 98.40 76.94

16. UNIT CAPACTTY FACTOR (Using MDC) 94.05 93.36 65.71

17. UNrf CAPACTTY FACTOR (Using Design MWe) 91.66 91.00 64 04

18. UNTT FORCED OUTAGE RATE 0.00 1.60 6.26

19. SilUTDOWNS SCIIEDULED OVER NEXT 6 MONTils (TYPE, DATE, AND DURATION OF EACil):

20. IF SP yWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

l.

21. UNTIs U TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACilIEVED INTTIAL CRTTICALTTY INITIAL ELECTRICTTY

.r COMMERCIAL OPERATION g 1.1&9 I TIDIOPhNRC\ MON 1HLY.RPT K:.

N- __ _ _ _ _ _ _ - _ _ _ _ - _

t APPENDIX C l- OPERATING DATA REPORT i

IX)CKET NO. 50-265 UNIT Two DATE March 3,1994 f COMPLLTED BY Matt Benum TELEPif0NE (309) 654-224I OPERATING STATUS 0000 020194 l 1. REPORTING PERIOD: 2400 022894 GROSS IiOURS IN REPORTING PERIOD: 672

2. CURRENTLY AlfTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 l'

DESIGN ELECTRICAL RATING (MWe-NET): 789

3. TOWER LEVEL to WHICll RES11tICTED OF ANY)(MWe Ns0: N/A

4. REASONS FOR RESTRICTION OF ANY):

Tills MONTl! YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRITICAL 672.00 831.40 144732.45

6. REAC. TOR RESERVE Sl(UTDOWN llOURS 0.00 0.00 2va5.80

7. IlOURS GENERATOR ON LINE 672,00 803.20 140986.35

8. UNIT RESERVE SilUTDOWN llOURS 0.00 0.00 702.90

9. GROSS TilERM AL ENERGY CENTRATED (MWil) 1602399.00 1781920,90 304562882.80

10. GROSS ELECTRICAL ENERGY GENERATED (MVW) 523738.00 578301.00 97888071.00

11. NLT ELECTRICAL ENERGY GENERATED (MWl'.) 501644.00 548362.00 92690922.00

12. REACTOR SERVICE FACTOR 100.00 58.71 76.07 .

l 13. REACTOR AVAILABILTTY FACTOR 100.00 58.71 77.64 i

14. UNTT SERVICE FACTOR 100.00 56.72 74.10

15. UNTT AVAILABILTTY l' ACTOR l* 56.72 74.47 )

16, UNTT CAPACTTY FACTUR (Using MDC) 91- 50.36 63.35

17. UNIT CAPACTTY FACTOR (Using Design MWe) 94.61 49.08 61.74 l

18. UNTT FORCED OUTAGE RATE 0.00 43.28 8.85  !

19. $11UTDOWNS SCllEDULED OVER NEXT 6 MONTlis (TYPE, DATE, AND DURATION OF EACil):  ;

20. IF SilUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:

21. UNI 1

[EST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACillEVED INTTIAL CRTTICALITY ,

I INT 11AL ELECIRICTTY COMMERCIAL OPERATION 1.16-9 _

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APPENDIX 8 l AVERAGE DAILY UNIT POWER LEVEL '

DOCKET NO 50-265 UNIT Two DATE March 2. 1994 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH February 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,

1. 764 17. 755

2. 762 18, 728-

3. 7_50 19. 729

4. 747 20. 753

5. 763 21. 755

6. 753 _

22. 752

7. 765 23. 739

8. 760 24. 754

9. 759 25 754

10. 760 26. 756

11. 757 27. 756

12. 739 28. 752

13. 549 29.

14. 752 _

30.

15. 756 31.

16. 757 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.

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE March 2. 1994 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH February 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net)

1. 750 17. 727

2. 744 18. 694

3. 739 19. 702 4, 738 20, 697 5, 713 21. 722

6. 739 22. 716

7. 729 23.___ 713

8. 726 24. 711

9. 722 25. 705

10. 742 26. 705

11. 746 2' 70t

12. 741 2 698

13. 717 25.

14. 739 30.

15. 732 31.

16. 728 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.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTION"-

Df/:KET No. 50-254 UNIT NAME One COMPLETED BY Matt Benson DATE March 3, 1994 REPORT MONTH February 1994 TELEPHONE 309-654-2241 0:

4 O H m 2 O H g 2

$ cr: O O N$ $

s $  !=E $8 $8  :

$ $ LICENSEE 8 DURATION 8 EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT None for February w

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8 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCVET NO. 50-265 UNIT NAME Two COMPLETED BY Matt Benson DATE March 3, 1994 REPORT MONTH February 1994 TELEPHONE 309-654-2241 x m_

a:

A o O id m 2 O gg g

$ v. b @ g 4 N$ g$

Z e

O <

y m e

mg 20 ru m

DURATION

$$ LICENSEE O 8 EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (l!OURS ) REPORT o4 02 02-12>>8 l' 9.0 11 5 - ------ --- ----- Load Drop for Drywell Entry.

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

A. Main Steam Relief Valve Operations 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 4 specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

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

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 l AVERAGE TIME IN SECONDS AT % l MAX. TIME l INSERTED FROM FULLY WITHDRAWN j FOR 90%

!  ! INSERTION DESCRIPTION

, NUMBER l 5 1 20 1 50  ? 90 i Technical Specification 3.3.C.1 &

DATE OF RODS I 0.375 ! O.900  ! 2.00  ! 3.5 1 7 sec. 3.3.C.2 (Averaoe Scram Insertion Time) l l l l 01-27-94 1 j 0.31 0.69 l 1.45 2.53 H-1 U1 for Maintenance 2.53 i 1 01-29-94 1 0.33 l 0.73 1.51 j 2.58 1 M-10 l U1 for Maintenance 1 2.58 i 177 01-29-94 l 0.32 0.69 1.46 2.56 H-3 U2 SEQ A & B for Tech Spec & Maintenance l ll 2.92 1

02-10-94 l 1 0.29 l 0.65 1.39 2.41 F-7 Ul F-7 for WR Q12855 l l .

2.41 i I ,

02-19-94 1 0.31 '

O.69 1.45 l 2.53 H-1 U1 H-1 for WR Q14360

! 2.53 l l l 1 02-23-94 1  ! 0.30 0.68 l 1.45 l 2.62 'l J-3 U2 J-3 for WR Q14662 l l 2.62 i  !  !

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I VII. REFUELING INFORMATI0f] i i

l The following information about future reloads at Quad-Cities Station was I requested in 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 Request for Refueling Information", dated January 18, 1978. l 1

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QTP 300-S32 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q1 Reload: 12 Cycle: 13

2. Scheduled date for next refueling shutdown: 3-12-94

3. Scheduled date for restart following refueling: 7-2-94 4.

Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment:

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:

11-19-93 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:

144 GE10 Fuel Bundles will be loaded during QlR13,

7. The number of fuel asremblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1557

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: 2009 l

APPROVED ,

(final) 14/0395t OCT 3 01989 C).C.O.S.R.

4

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMA"^9 REQUEST

1. Unit: 02 Reload: _

12 Cycle: 13

2. Scheduled date for next refueling shutdown: 2-19-95

3. Scheduled date for restart following refueling: 6-19-95

4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

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:

10-10-94 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:

GE10 Fuel will be loaded during Q2R13.

7. The number of fuel assemblies.

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 dischaiged to the spent fuel pool assuming the present licensed capacity: 2009 APPROVED ,

(final) 14/0395t OCT 3 01969 Q.C.O.S.R.

( ..

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 ANSI - American National Standards Institute APRM- - Average Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System E0F - 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 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 PCI - Primary Containment Isolation 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 j RPS - Reactor Protection System RWM - Rod Worth Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control ,

SDC - Shutdown Cooling Mode of RHRS l SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System l TIP - Traversing Incore Probe 1 1SC - Technical Support Center 11dCllOl%NRCaf0N11111Rf7 l

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