Text

Monthly Operating Repts for Mar 1982
	ML20054B815
Person / Time
Site:	Quad Cities
Issue date:	04/06/1982
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20054B812	List: ML20054B811; ML20054B815;
References
	NUDOCS 8204190225
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND ?.

MONTHLY PERFORMANCE REPORT MARCH 1982 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 820019022S 820401 PDR ADOCK 05000254 R PDR

4 TABLE OF CONTENTS i

I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant of Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications l 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 l A. Main Steam Relief Valve Operations 1

B. Control Rod Drive Scram Timing Data VII. Refueling Information

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VIII. Glossary i

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i I. INTRODUCTION l

1 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 j by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect /Fngineer was j Sargent & Lundy, Incorporated, and the primary construction i

contractor was United Engineers & Constructors. The condenser cooling method is a closed cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject '

to license numbe rs 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 1 j and 2 respectively were October 18, 1971, and April 26, 1972.

I Canmercial generation of power began on February 18, 1973 for Unit

! I and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Erich Weinfurter, i telephone number 309-654-2241, extensions 127 and 192.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE March I-6: The unit started the month holding at maximum attainable load as coastdown began for the September, 1982, end of cycle six refueling outage. On March 6, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , a load drop was initiated at 100 MWe/ hour to 700 MWe for weekly Turbine tests. At 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months , load was increased 50 MWe/ hour to 760 MWe then 5 MWe/ hour to 785 MWe which was obtained Marcn 6 at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months .

March 7-13: The unit continued to coastdown at maximum attainable load until March 12 at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months when a load drop to 700 MWe at 100 MWe/ hour was initiated for weekly Turbine tests. On March 13. at 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months , load was increased 50 MWe/ hour for one hour, then 5 MWe/ hour until 760 MWe was achieved at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months .

March 14-21: On March 19, at 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months , a load drop was initiated to reduce load to 600 MWe by 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months on March 20. Weekly Turbine tests were completed along with control rod pattern movenents by 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months .

Load was increased 40 MWe/ hour for one hour, then 5 MWe/ hour to maximum attainable load at this point in coastdown.

March 22-31: The unit was holding at a load of 700 MWe, on March 29, when condenser vacuum started to decrease due to an empty ioop seal in the steam seal piping. A load drop to 300 MWe was initiated in an attempt to increase the condenser vacuum. At 0733 hours0.00848 days 0.204 hours 0.00121 weeks 2.789065e-4 months , March 29, the Reactor scrammed on low condenser vacuum. The Reactor became critical at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months , and the Generator was put on line at 1645 hours0.019 days 0.457 hours 0.00272 weeks 6.259225e-4 months . At 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months all control rods were fully withdrawn and load was increased to 777 MWe by 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months , March 31.

B. UNIT TWO March 1-5: Unit Two began the nonth continuing to increase load at 5 MWe/ hour until March 3 when the unit was holding load for Xenon build-up. The load increase began at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , March 3, at 5 MWe/ hour until 0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months March 4, when a maximum attainable load of 810 MWe was achieved.

March 6-12: On March 6, at 0704 hours0.00815 days 0.196 hours 0.00116 weeks 2.67872e-4 months , the unit scrammed when the "B" Feedwater Regulating valve failed in the open position causing a Reactor high level. This caused a Turbine trip and subsequently a Reactor scram. The Reactor became critical at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months and the Generator was on line by 1813 hours0.021 days 0.504 hours 0.003 weeks 6.898465e-4 months . Load was increased 100 MWe/ hour to 500 MWe then 50 MWe/ hour to 550 MWe where it was held for a Xenon build-up. Load increases were continued at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months on March 7 until a maximum achievable load of 815 MWe was obtained.

March 13-15: On March 13, from 2302 hours0.0266 days 0.639 hours 0.00381 weeks 8.75911e-4 months to 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months March 14, a core flow drop test was conducted in order to complete the Cycle 6 Start-up Program. The unit dropped load at 50 MWe/ minute to 460 MWe.

Load was then increased at 350 MWe/ hour to 700 MWe. The weekly Turbine test was completed and a fuel preconditioning ramp continued to 800 MWe.

On March 15, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , condensate demineralizer problems necessitated a load drop to 700 MWe; by 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months , load was initiated to 805 MWe.

March 16-28: Maximum attainable load was held except for two load drops for Turbine tests on March 20 and March 27 Load was increased ;

in accordance with normal preconditioning ramp.

March 29-31: Due to the "A" Feedwater Regulating valve locking up, the "A" Feedwater valve was isolated and load was dropped to 520 MWe, at 1215 hours0.0141 days 0.338 hours 0.00201 weeks 4.623075e-4 months on March 30. By 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months , load was increased 200 Mwe/ hour to 700 MWe, 20 MWe/ hour for one and one-half hours, then 5 MWe/ hour to a maximum attainable load of 810 MWe.

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III. PLANT OR PROCEDURE CHANCES, TESTS, EXPCRIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical

, Specifications 1

On December 18, 1981, the NRC issued Amendments 75 and i

' 68 to licenses DPR-29 and DPR 30, respectively. This amendaent provides the Technical Specification changes 3

needed to allow Units One and Two to be operated with the "A" loops of the RHR Service Water System cross-

tied, These changes will be in effect until June I,1982.

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B. Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure Changes requiring NRC approval for the reporting period.

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

D. Corrective Maintenance of Safety Related Equipaent The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in

' this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects .

on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT OrlE MAINTENA!1CC SUMMARV CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13537 LPRt1 16-33B Connector dirty & Intermittent readings. Cleaned & tightened Channel 1 loose. connector.

Q13538 LPRit 37-40D Cable connector LPRit reading downscalc. Cleaned the connector Channel 3 under the Reactor and returned to service.

vessel was dirty.

Ql4122 LPRM 16-25A The' cable connector LPR1 is spiking down- Replaced LPR!! cable Channel 6 was corroded. scale. connector under vessel .

Ql5930 LPRM 48-49A The cable connector LPRft reading 11% at Replaced LPRM cable was corroded. zero power. connector under vessel.

Q15931 LPRM 16-25C The cable connector LPRli reading at zero Replaced LPRM cable was corroded. power. connector under vessel .

Q14576 81-16/03L "A" SBGT Train The damper lever Lever damper on the The counterweight was 1/2-7506A counterweight was discharge of blower adjusted and the damper out of adj ustment. does not work. The operates freely.

SBGT Train was still ope rab l e.

Q14577 81-16/03L "B" SBGT Train The damper level Lever damper on the The counterweight was 1/2-7506B counterweight was discharge of blower adjusted and the damper out of adjustment. does not work. The operates freely.

SBGT Train was still ope rabl e.

UNIT ONE MAINTENANCE SUMMARf CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Ql5004 Battery 125 VDC Grounded wire When Control Room The ground was traced siren #57 operator sounded the and repaired.

fi re warning horn in the Control Room, the 125 V ground alarm came up. The battery was still operable.

Q16146 18 MSL Rad A faulty circuit The monitor spikes Repaired chassis; Monitor board was found. downscale, calibrated and re-1-1705-28 installed.

Q18055 Core Spray Low The flow switches The low flow valves do The switches were Flow Switch were out of not auto-open on recalibrated and the FSI-1-1464A & B calibration. decreasing Core Spray valves were stroked.

flow.

Q18201 18 ttSL Rad The monitor it was reading less than Calibrated and functionally Monitor indication was the other three monitors. tested.

1-1705-2B out of calibration.

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UNIT TWO MAINTENANCE SUMMARV CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q16643 I;P C I Bad outboard seal Outboard seal on llP Replaced outboard seal 2-2302 and shaft nut. stage. Leaks badly and replaced the shaf t when llPCI is running. nut.

Ql7296 RiiR Pump Suction The valve operator The valve will not open The valve operator was Valve 2-1001-7B was faulty. or close f rom Control replaced with the Room. The Reactor was operator from the 2-shutdown at the time. 1001-438. The 43B

. valve was taken out of service and the inter-lock was jumpered out.

Ql7882 Shutdown Cooling Dirty Bellville Breaker trips when the Installed a grease Suction Valve washers in motor valve closes. bypass line and cleaned 2-1001-43A operator. Bellville washers.

Ql7898 Limit Switch The slide contacts Limit switch which Replaced slide contacts MSIV 2-203-2A & stationary block indicates valve less & stationary contact on the limit switch than 90% full open is block on limit switch was worn. sticking. and tested.

Q17735 82-3/0lT CRD 42-07 Pitting was found The line is spraying Ground out the existing insert / Withdrawal on the I.D. of the water where the line seal weld between the Line withdraw line where meets the flange. The pipe and flange. The it fits into the Reactor was already withdraw line was fillet CRD housing flange. shutdown when the welded to the back side leak was discovered. of the flange.

Ql7911 Main Steam Line The monitor Reading veries as much Recalibrated A - D monitor.

Rad Monitor calibration dri f ted as 20 di fference RE-1734 A - D slightly. between the monitors.

UNIT Tl!0 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCT10N SAFE OPERAT10N PREVENT REPETITION Q17609 MO-2-2301-8 \ lorn torque swi tch The valve was still Replaced torque swi tch, HPCI Supply in the valve operable. limit switch, and motor.

Valve operator.

Q17244 82-1/0lT Clean-up Suction A crack was found The Reactor was shut- The isolatable portion Q17140 Piping 2-1202-6A in the heat affected down immediately of the pipe was replaced zone of one of the following discovery of with low-carbon stain welds. A subsequent the leak. Primary less steel. The non-ultrasonic inspection Containment integrity isolatable portion was revealed several was maintained at all repaired using sleeves linear indications. times. and weld overlays.

Q09171 250 VDC Battery The breaker and The breaker trips when A larger breaker and Charger Feed cable was under- a large load is cable were installed from MCC 29-2 sized for the required from the to carry the requi red new larger-capaci ty battery charger. current.

charger.

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IV . LICENSEE EVENT REPORTS 1 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.l. and 6.6.B.2. of the Technical Specifications.

UNIT ONE

. Licensee Event l Report Number Date Title of Occurrence 82-4/03L 03-07-82 RCIC lsolation - High Flow /DP 82-5/03L 03-25-82 RCIC Trip on Overspeed UNIT TWO There were no Licensee Event Reports for Unit Two for the reporting period.

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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

OPERATING DATA REPORT

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DOCKET'NO. 50-254 UNIT' ONE DATEAcril 06 1982

. COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 030182 -

1. Reporting period 2400 033182 Gross hours in reporting period: 744

2. Currently authorized power level __(MWt): 2511 Max. Depend.copacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

This Month Yr.to Date Cunulative

5. Number of hours reactor was critical 738.8 2144.4 71243.5

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 734.8 2134.7 60266.2

0. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thernal energy generated (MWH) 1686197 5006518 140064877

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10. Gross electrical energy generated (MWH) 547656 1639540 45168473

11. Het electrical energy generated (MWH) 505623 1521233 42105317

12. Reactor service factor 99.3 99.3_ 82.2

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13. Reactor avo11ob111ty factor 99.3 99.3 86.i

14. Unit service factor 98.8 98.8 78.7

15. Unit ovo11ob111ty factor 98.8 98.8 79.8

16. Unit capacity factor (Using HDC) 88.4 91.6 63.2

17. Unit capacity factor (Using Des.MWe) 86.1 89.3 61.6

18. Unit forced outage rate 1.2 1.2 7.0

19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of each):

20. If shutdown at end of report period,estinated date of startup ___yA ___,,__,

The MDC ney be lewr than 769 Nie dering periods of high onblent tenperatere due to the thernal perfernance of the spray canol.

l OPERATING DATA REPORT

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DOCKET NO. 50-265 UNIT TWO DATEApril 06 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 030182

1. Reporting period:2400 033182 Gross hours in reporting period 744

2. Currently authorized power level (MWt): 2511 Max Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

This Month Yr.to Ddte Cumulative

5. Number of hours reactor was critical 736.8 1099.7 65951.5

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generotor on line 732.9 1079.8 63321.0

8. Unit reserve shutdown hours. 0.0 0.0-. 702.9

9. Gross thermal energy generated (MWH) 1750579 2378293 130265376

10. Gross electrical energy generated (MWH) 567002 766i77 41472417

11. Net electrical energy generated (HWH) 542600 722760. 38847344

12. Reactor service factor 99.0 50.9 76.9

13. Reactor avo11ob111ty factor 99.0 50.9. 80.4

14. Unit service factor 98.5 50.0 73.8

15. Unit ovellability factor 98.5 50.0 74.6

16. Unit capacity factor (Using MDC) 94.8 43.5 58.9

17. Unit copocity factor (Using Des.MWe) 92.4 42.4 57.4

18. Unit forced outage rate 1.5 50.0 9.7

19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of each):

20. If shutdown at end of report period,estinated date of stortup ___f_A ________

The MDC not be lower than 769 MWe dering periods of high anbient tenperature die to the thernal perfernance of the spray canel.

l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATEApril 06 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92 HONTH March 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 738.6 17. 684.5

2. 739.1 18, 681.4

3. 732.4 19. 672.7 4, 731.4 20. 634.5 5, 747.5 ~21. 701.9

6. 700.2 22, 665.5

7. 728.0 23. 672.5

8. 722.9 24. 673.8

9. 714.7 25. 669.2

10. 707.3 26, 657.5

11. 710.0 27. 685.3

12. 706.1 28, 658.7 13, 703,9 29. 30i.8

14. 684.0 30, 578.7 15, 686.0 31, 692.1

16. 684.5 INSTRUCTIONS On this (ern, list the overage daily enit power level in MWe*t for each day in the reporting nenth.Conpete to the nearest whole negewett.

These figeres will be sted to plot a graph for each reporting nenth. Note that when posinen dependable capacite is es d for the net electrical rating of the snit there ney be occasions when the daily overage power level excee4s the 10$1 line (or the restricted power level line)!!n sich cases,the overage daily snit powr setpet sheet sheeld be festnoted to esplein the opperent onenely

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. APPENDIX B

, AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEApril 06 1982 COMPLETED BYErich Weinfurter

. TELEPHONE 309-654-224ix192 HONTH March 1982 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 7 (MWe-Net) (MWe-Net)

1. 513.3 17. 779.3

2. 723.5 . 18. ' 777.3

3. 731.4 19, 775.8

4. 771.0 20. __ 764.9 5, 794.0 21, 782.4

6. 209.7 ,

22. 759.8

7. 583.7 23. 774.1

8. 723.O'- ~24. 777.5

9. 775.5 25. 765.2 10, 771.0 26. 769.8

11. 775.9 27. 624.8 12, 779.8 28. 731.8 L3. 777.4 29. 759.0 L4. '714.0 30, 759.5

15. 741.6 31. 769.7 ,

L6. 771.3

' INSTRUCTIONS On this forn, list the overage dolly wait power level in IWe-Met for each day in the reporting nenth. Compete to the H erest uhele m esuett.

These figeres will be esed to plot a graph for each reporting month. Note that whgn no inen dependeble Copecito is used for the net electrical rating of the salt there ney be occasions when the detly everage power level excetes the its1 line (or the restricted power level line),In sich cases,the everage dolly voit power setpet sheet shoold be feetnoted to esplein the apperent eneaely l

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APPENDIX D QTP 300-513 050,254 UNIT SilVTDOWNS AND POWER REDUCTIONS Revisie, 5 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit One COMPLETED BY E Veinfurter DATE April 1, 1982 309-654-2241 REPORT MONTil March 1982 TELEPHONE ext. 192 o

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m z Eb z 5 E'oc 8 @-$ LICENSEE pg gg C u-DURATION $

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5 h a: EVENT *8 gg NO. DATE (fl0URS) gxy REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS R

82-8 820306 5 0.0 B 5 N/A ilA TURBIN Load reduction to perform Turbine tests.

82-9 820312 5 0.0 B 5 N/ A - IIA TURBlh Load reduction to perform Turbine tests.

82-IC 320319 S 0.0 8 5 N/A RD C0!! ROD Load reduction to perform Turbine tests and perform control rod maneuvers.

82-11 820329 F 9.2 A 3 N/A IlJ XXXXXX Reactor scram on Condenser Low Vacuum due to loop seal blowing through.

(final)

n M M M M M M M M M M M M I'"1 M T' ("~ T ""'~ '

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APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AtlD POWER REDUCTIONS Revisio1 5 DOCKET NO. 050-265_.

March 1978 UNIT NAME Quad-Cities Unit Tw COMPLETED BY E Weinfurter Ap r i l 1, 1982 309-654-2241, DATE REPORT MONTH tiarch 1982 TELEPHONE ext. 192 oe $

w 5 oEN LICENSEE bw Ew NO.

h u-DURATION $

hhN EVENT hh hh DATE (HOURS) yIy REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS R

82-4 820306 F 9,1 A 3 rl/A Cli VALV0P Reactor scram on Vessel liigh Water Level due to "B" Feedwater Regulating valve failing in the open posit 1on.

82-5 820313 S 0.0 B 5 !!/A CB XXXXXX Load reduction to perform flow drop test and perform Turbine tests.

82-6 820315 F 0.0 A 5 fl/A WC DEltl!!X Load reduction due to Demineralizer problems.

82-7 820320 5 0.0 8 5 N/A IIA TURBill Load reduction to perform Turbine tes.ts.

82-8 820327 5 0.0 B 5 ll/A RB' C0f1RO D Load reduction to perform control rod maneuvers.

82-9 820330 F 0.0 A 5 N/A CH VALV0P Load reduction to isolate "A" Feedwater regulating valve when the valve started to drift open.

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VI. UNIQUE REPORTING REDUIREMENTS The following items are included in this report based on prior.

commitments to the conmission:

A. MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B. CONTROL ROD DRIVE SCRAM TIMING DATA EUR UNITS ONE AND WO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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VII. REFUELING INFORMATION i

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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, l Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

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' QTP 300-S32 1 J '.- ! Ravision 1 I I QUAD-CITIES REFUELING i

March 1978 6, , INFORMATION REQUEST

.~ 1. Unit: 1 Reload: 6 Cycle: 7

" 2. Scheduled date for next refueling shutdown: Sept 12 1982 3 Scheduled date for restart following refueling: Dec 4, 1982 -

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{ 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

r YES u

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

{ in forma tion:

!. ' JULY 26, 1982 E'

j* 6. Important licensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis

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/ methods, significant changes in fuel design, new operating procedures:

L litPLEt1ENTATION OF TH'E ODYN TRANSIENT ANALYSIS CODE AND RESULTS .

(itCPR SCRAM TiliE DEPENDENCE) 1 s, .

I 1.

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7 The number of fuel assemblies.

j' a. Number of assemblies in core: 224 new/724 total after the

b. Number of assemblies in spent fuel pool: outage 1940

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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 2- in number of fuel assemblies

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a. Licensed storage capacity for spent fuel: 2920

b. Planned increase in licensed storage: 4636 new/7556 total 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

g, LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 A' P P R O V E D 4- LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2 01973

. Q. c. O. S. R.

,. **mee e,m,. . e,.c emme = e .ee e

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QTP 300-S32

! R2 vision 1 n

,-, I QUAD-CITIES REFUELING March 1978 I

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INFORMATION REQUEST o 1. Unit: 2 Reload: 6 Cycle: 7 n 2. Scheduled date for next refueling shutdown: Feb 27,1963 3 Scheduled date for restart following refueling: April 23, 1983 r-

{ 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

v' No a

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

{

L N0llE t-j~ 6. Important licensing considerations associated with refueling, e.g. , new or

'different fuel design or supplier, unreviewed design or performance analysis 7 / methods, significant changes in fuel design, new operating procedures:

NONE F .

D v

i a.

s' L 7 The number of fuel assemblies.

a. Number of assemblies in core: 192 new/724 total a, after the

b. Number of assemblies in spent fuel pool: outage 2132 i g -.

, 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:

L' a. Licensed storage capacity for spent fuel: 2920

b. Planned increase in licensed storage: 4636 new/7556 total 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/0!:

LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APPROVED APR 2 01978 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 EOF -

Emergency Operations Facility CS EP -