ML19320C003
| ML19320C003 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/01/1980 |
| From: | Hafera T COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19320C000 | List: |
| References | |
| NUDOCS 8007150625 | |
| Download: ML19320C003 (4) | |
Text
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57 THIS DOCUMEf!T C0ilTA!l13
P0OR QUAUTY PAGES QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 MONTHLY ?ERF0 MANCE REPORT
- JUNE 1980
.COMMCNWEALTH EDISON COMPANY AND l0WA-ILLINOIS GAS & EuCTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. DPR-29 and DPR-30 t
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8007150625
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TABLE OF CONTENTS
.l. Introduction ll. Summary of Operating Experience A. Unit One B. Unit Two Ill. 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 VI. Unique Reporting Requirements l
!' A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data Vll. Refueling information Vill. Glossa ry
O O
- 1. INTRODU; TION quad-Cities Nuclear Power Station is composed of two Bolling Water Reactors,
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each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and towa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors. The Architect / Engineer was c argent & Lundy, Inc. and the primary construction 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 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 I and 2 respec-tively were October 18, 1971 and April 26, 1972. Commercial 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 Tom Hafera, telephone number 309-654-2241,~ extensions 245 and-176.
' ll.
SUMMARY
OF OPERATING EXPERIENCE A. Ut:IT ONE-June 1-7: Unit One began the reporting period holding a load of.624 MWe, and held an average load of 617 !Le. At 0400 on June 7,' load was reduced at a rate of 100 MWe/ hour until a load of 500 MWe was achieved and held at 0500. This time. the main condenser flow was reversed. At 0600 the load was increased at a rate of.50 MWe/ hour, at 0700 the rate was changed to 25_ MWe/ hour, and at 0800 the rate was changed to 8 MWe/ hour. At 1240 load was held at 607 MWe.
June 8-20: Unit One held an average load of 597 MWe. At 2210 on June 20, load was reduced due to low vacuum on the main condenser. At 2223 the reactor scrammed on low condenser vacuum.
June 21-23: At 0802 on June 21 the reactor was brought critical and the reactor mode switch was placed in the HOT STANDBY position. The reactor remained in HOT STANDBY until at 1430 on June 23 when the reactor mode switch was'placed in the RUN position. At 1556 the generator was synchronized.
At 2220 load was held at 430 MWe for fuel preconditioning.
June 24: At 0600 the load was ' creased at a rate of 50 MWe/ hour. At 0855 the load was held at 500 MWe te .hange the control rod pattern. At 1030 the load was increased at a rate of 25 MWe/ hour, at 1230 the rate was changed to 8 MWe/ hour.
June 25: At 0040 load was held at 643 MWe. At 1600 load was reduced at a rate of 100 MWe/ hour until at 1745 a load of 400 MWe was held to repair a steam leak on the IB reactor feed pump.
June 26: The steam leak was repaired and the load was increased at a rate
- of 100 MWe/ hour at 0912. At 1015 the rate of increase was changed to 25
> MWe/ hour, and at 1120 the rate was changed to 8 MW e/ hour. At 1830 full load was achieved and held at 597 MWe.
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June 27-30: Unit One held an average load of 568 MWe, and finished the reporting period holding a load of 569 MWe.
B. UNIT TWO June 1: Unit Two began the reporting period holding load at 797 MWe. At 0300 load was reduced at a rate of 100 MWe/ hour until at 0525 a load of 555 was achieved and held. At this load, the main condenser flow was reversed.
At 0700 the load was ' increased at a rate of 50 MWe/ hour, at 1000 the rate of increase was changed to 8 MWe/ hour. At 1810 the load was reduced 65 MWe due to high vibration.on the 2B condensate pump. Af ter a change of '
condensate pumps was performed, at 1845 the load was increased at a rate of 8 MWe/ hour. At 1030 on June 2 full load was achieved and held at 796 MWe.
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- June 3-8: Unit Two held an average load of 800 MWe. At 0100 on June 8 load was reduced 100 MWe to perform the weekly turbine tests. At 0300 load was increased at a rate of 50 MWe/ hour for one hour; the rate of increase was then changed to 5 MWe/ hour until at 1825 a full load of 813 MWe was achieved and held.
June 9-10: At 2020 on June 9 the output breaker on the "A" Reactor Protection System Motor-Generator Set tripped. Load was reduced to 650 MWe. . The breaker trip was reset at 2050 and the load was increased at 2120 at a rate of 55 MWe/ hour. At 2220 the rate of load increase was changed to 25 MWe/ hour, and at 2320 the rate was changed to 8 MWe/ hour until a full load of 804 MWe was achieved and held at 0800.
June 11-12: At 0830 on June 11- Icad was increased at a rate of 3 MWe/ hour in orcer to establisn fuii reactor recirculation flow. At 1030 full recirculation flow was achieved and the load was held at 810 MWe.
June 13: At 0745 load was reduced to a level of 730 MWe to repair the 2C reactor feed pump. Af ter a change-over from the 2C to the 2A reactor feed pump was completed, at 1115, load was increased at a rate of 8 MWe/
hour. At 1915 load was reduced at a rate of 100 MWe/ hour due to a seal water line leak on the 2A reactor feed pump. At 2000 the rate of load reduction was increased to 150 MWe/ hour until at 2210 a load of 400 MWe was achieved and held.
Jun* 14-15: At 0630 on June 14, af ter the reactor feed pumps had been repaired, tne ! cad was increased at a rate of 50 MWe/ hour, at 1100 the rate of increase was changed to 8 MWe/ hour. At 1930 on June 15 a full load of 805 MWe was achieved and held.
June 16-19: Unit Two held an average load of 804 MWe. At 0100 on June 19 load was reduced 50 MWe in one-half of an hour in order to change condensate
- pumps. After the pumps had been changed, at 0200 the load was increased at a rate of 10 MWe/ hour until a full load of 805 MWe was achieved and held at 0700.
June 20-22: Unit Two held an average load of 807 MWe. At 0130 on June 22 load was reduced at a rate of 100 MWe/ hour for two hours and held at 600 MWe in order;to reverse the main condenser flow. At 0645 the load was in-creased at a rate of 50 MWe/ hour; at 0745 the rate was changed to 25 MWe/ hour, and at 0845 the rate was changed to 8 MWe/hcur.
June 23: At 0700 full load was achieved and held at 804 MWe. At 1240 the load was reduced lat a rate of 25 M"e/ hour in order to test the HPCI
- emergency oil pump for leaks. No leaks were found, and'at 1315 load was increased at a rate of 8 MWe/nour until a full load of 795 MWe was achieved and. held at 1425
s.
June 24-27: Unit TWo' held an average load of 791 MWe. At 1418 on June 27, load was reduced 50 MWe in one-half of an hour due to high condenser backpressure.
June 28: At 1300 load was reduced 50 MWe in one-half of an hour due to high condenser backpressure.
June 29: At 0210 load was reduced at a rate of 100 MWe/ hour due to a steam leak on a turbine control valve. At 0610 the load was held at 300 MWe to repair the steam leak. At 1020 control rods were inserted to shut down the unit. At 1155 the turbine was manually tripped and at 1215 the reactor mode switch was placed in the HOT STANDBY position.
June 30: At 0805 the reactor node switch was placed in the RUN position, the generator was syncnronized at 0944. Load was increased until a load of 425 MWe was achieved and held at 1240. Unit Two finished the reporting period Folding load at 425 MWe for fuel preconditioning prior to full load.
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Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specification Amendment 56 to License Number DPR-29 was issued on June 26, 1980. This amendment allows operation of Unit One in the coastdown mode to 40 percent power. Also, should off-normal feedwater heating be necessary for extended periods durin coastdown, a safety evaluation must be performed to determine if the MCPR operating limit and calculated peak pressure for the worst case abnormal operating transient remain bounding for tt.e new condition.
B. Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC apprcval.
C. Tests and Experiments Requiring NRC Approval There were no tests or experiments performed during the reporting period.
D. Corrective Maintenance of Safety Related Ecuionent The folicwing 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.
$I A. 4.*- % +.4 -. 4
- UNIT' ONE in!NIEtt/.f1CE
SUMMARY
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CAUSE RESULTS & EFFECTS
-W.R. -LER OF ON ACTION TAKEN TO
._ NUMBER NUMBER- COMPONENT- MALFUtlCT10N SAFE OPERATION PREVENT REPETITION 105250 HPCI Turning The antor was The turning gear. did - The motor was Gear Motor shorted, not engage. repaired anl. tested.
(1-2303).
Q06064- 1/2 D.G. Sub- The heater was The heater would not The heater was replaced mersion Heater shorted to work; the D.G. was and tested.
ground, available. '
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UNIT TWO- MAINTENANCC
SUMMARY
CAUSE RESULTS & EFFECTS zW.R. LER' 0F ON ACTION TAKEN TO.
NUMBER ' NUMBER COMPONENT t4ALFUNCTION SAFE OPERATION PREVENT REPETITION QO1198 - CRD C-6 The seals were N/A The CRD was replaced.
bad.
-Q01204 .CRD C-10 Q01205- CRD G-9 CRD 11-11 " " " " " " " "'
Q01839 Q01840 CRD F-11 Q01841 CRD K-Il QO3813 .CRD M-12
" " " The rod did not latch at The CRD was replaced Q04864 CRD L-12 00 during scram timing. and tested.
I " " " The timing could not'be The CRD was replaced Q04865 CRD J-9 adj us ted. and tested.
" " " The CRD was replaced Q04866 CRD G-8 The timing could not be adjusted. and tested.
CRD M-6 " " " The rod did not latch at The CRD was replaced Q04875 1 00. and tested.
UNIT ,TWO Mall!1EllANCC
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO
' NUtiDER NUMBER COMPONENT ltALFUllCTI0ff SAFE OPERATION PREVENT REPETITION Q05714' ilPCI Steam A actol"t was The line was leaking. The sockolet was-Line Test worn. plugged and a new one (2-2305-10") was installed & tested.
Q03986 80-06/0lT Core Spray A weld w.is The line was leaking. The line was replaced Line (2-1403- cracked. The other core . spray and tested.
10") subsystem was avall-able.
Q05995 Drywell Floor The control The valve would not The switch was repaired Drain Sump switch was open from the Control and the valve was Pump Discharge defective. Rocm. stroked three times.
Q06094 ilPCI Emergency The line was The line was leaking. The line was repaired Pump Discharge cracked. IIPCI was available. and checked fr.P leaks.
Line (2-2302) 2822-79 Cable From MCC The cable was The cable had to be re- The cable was re-routed 28 to MCC 28-2 routest wrong. routed. and affected equipment was tested.
3432-79 IRM Ch. 13 The detector was The IRH Ch. 13 failed The detector was bad. Ill-Hl; the other IRMs replaced and tested, were available.
9
IV. LICENSEE EVENT REPORTS The -following is a tabular summary of all IIcensa 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. I. and 6.6.B.2. of the Technical Specifications.
UNIT ONE
-Licensee Event Report Number Date Title of Occurrence 80-16/03L 6-21-80 aslV l-203-2C failed to close UNIT TWO 14/03L 6-23-80 HPCI out of service for oil leak 80-15/03L 6-04-80 HPCI Inop to repair leak 4
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V. ' DATA TABULATIONS'
- 'The following ' data tabulations are presented in this report.
A. Operatin'g Data' Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions t
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OPERATING: DATA REPORT
' Sn-254 DOCXET NO. __
UNIT O N F.
i D ATE _ July 1,1980 E
l' COMPLETED E4Y T. Hafera TELEPHONE 309-654-2241, j' Extension 1/6 OPERATING STATUS .
0000 060180 -
- 1. Rep orting period :24nn - 063nRO Gross n o9rs in reporting period: 720
=2.-Carrently ou Qar ::cd powar level (MWt): 2511 Max, Depend capacity (hWe-Net): 769* Deston electrical roting-(HWe-Net): 789
- 3. Power' lev.t1 to-abich restricted (if any)(MWe-Net): NA
-4 . Reasons f or-. rectriction -(if any):
This Month Yr.to Date Conulative
- 5. Number.of hours reactor was critical 710,4 4357,4 59071,5
- 6. Reacter rcserve shutdown hours 0,0 0.0 3421.9 7- H 7 n r e 7:r.c r 2 + - A -line Ac;4 , a 4p89,2 56330,i 8.-; Unit reserve-shutdown. hours. 0.0 0.0 909.2
- 9. Gross-thernal energy generated (MWH) 1192667 9291377 113835358
- 10. Gross electrical energy generated (MWH) 378942 3017325 36640379 Li.-Net electrical energy generated (MWH) 340669 2815289 34230825 12 .-Reactor service factor, 98.7 99,8 c2,8
- 13. Reactor-ovoilobility factor- 98.7 99,8 87,6
- 14. Unit serviceffcetor 90.9_ 98.2 78.9
- 15. ' Un it _ uvo11ob ili t y. f ac t or '
90.9 98.2 80.2 L6.. Unit copocity factor (Using Des.MWe) 61.5 83,8 62.4 17.. Unit capacity factorf(Using_MDC) 60.0 81,7 60,8 LtG. Unit forced outoge' rote' 9 . i' i.8 7,7
'i9.. Shutdowns scheduled over next 6 nonths.(Type,Date,ond Duration of-each):
. 3 0. : _If snutdown'ot: end _of. report p er i od , e s t inc t ed d at e o f s t ar t up _____NA.______
- The MC nay be lever than 769 :%ie during periods of hign cnbion: temperatste due I l
T h thE thermal performace of the spray canal, i
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p OPERATING DATA'itEPORT Ii DCCl(ET NO . ' 0-? 65 UNIT TWO DATE July 1, 1980 COMPLETED BY T. Hafera TELEPHONE 309-654-2241, t.xtension I/o OPERATING STATUS 0000 060100
- 1. Reporting period:2400 063080 Gross hours in reporting period: 720
- 2. Currently uuthorized power level (i1W t ) : 2511 Max. Depend copccity (MWe-Net): 769 t: Design electeical rating (MWe-Net): 7G9
- 3. Power level to which restricted (if any)(Mue-Net): NA
- 4. Reu=une Tor restriction (if any):
Tn ts rion th Yr.to Date CumuloTive
- 5. Nuecer of nours recctor was critical 709.3 1550.7 54687.6 m . A:2 . i ;. eor r c a r_ . v e shutdown hour 3 a ' " .a 7" 4
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$3 . Unit reserve shutdown hours. 0.0 0.0 ~'02.?
- 9~-Gross thernal energy' generated (MWH) 1652033 3267415. 106283564
~ 1 'J . Gross electrical energy generated (MuH) 928?27 int 82io 7 ~sont268 li.' Net electrical energy generated (MWH) 505246 947821 31690346
- 12. React or -service f act or- 98.5 35.7 77.6
- 13. Recctor.ovallobility factor 98.5 35.7 81.9
- 14. Unit service factor 96,6 32.8 74,1
- 15. Unit lavullabilitvEfocto'r 96.6 32.8_ 75.1
- 16. Uni.t capacity ~ factor (Using Des.MWe) 91.3 28.2 58.5
'17. Unit copocity' factor (Using MDC) 88.9_ 27.5 57.0 18 Uni.t' forced: outage rate 3.4 13.5 9.4 19... Shutdowns' scheduled over next 6 months (Type, Dote ,and Duration of each ):
J 2 0 '. If shutdownLot'end of.. report period,estincted date'of startup ____ M____,___
? 8The IOC my be lowr ther 769 MWe daring periods of high abiet temper' start due-ts the ~therml_ ctrference of the' spray canal.
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AP?CNDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATE July 1, 1980
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COMPLETED BY T. Hafera TELEPHONE 309-654-224h F.XECn5 8 0n i/0 NONTH June 1980 DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
- 1. 562.7 17, 526,1 _
- 2. 559.0 18, 522,3
- 3. 359.7 19. 521.9
- 4. .
554.7 20, 480.4
- 5. 550.5 21. -30.8
- 6. 545,3 22. -36,1 7.- 528.3 23 _
75.9 0, 553.5 24, 475,8
- 7. 545.5 25, 469.3 LO. 544.9 26, 454.5
- 11. 541,6 27. 515.5 12, 552.1 28. 502.8
- 13. 51'6.9 29, 497.0
. t4. 531.2 30, 523.3 L5. 5'39.8 .
- t 5'. _529.3
--. INSTRUCTIONS-On' this fern, list the overage daily unit power level in 1%ie-Net for eact, day in the reperting month.Congste to the
- ntGrtst Whelt meCMtt.
- Thest figeres will be sstd te plot a oroph for each reperting nonth. Note that when notinen dependoble ccpacity as used for the net electrical rating of'tne snit,there nov be occasions when the d2ily overage power level exceeds the
. 100I line (erstre restricted power level line).In sach cases,the averagt daily snit power' estpst shett shevid te
- festnoted to explsin the cppurent anomaly ha
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I apornn'v 9 l AVERAGE DAIL: UNIT PGWER LEh
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DOC'(ET NO . C0-205 tjNIT TtIO DATE _ July 1,1980 COMPLETED SY T. Hafera ,
TELEP H0!!E_309-654-2241, Extension 176 HONTH June 1980
- { DAY AVERACE .;9.:L: N2%'E..
LAY AVERAGE DAILY PC'JE?. .2 VEL . EVEL
- i (MWe-ile r ) . . ; .a. ,1 c ( ,
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.i . 472 5 17. 76a.4
, 2. .
752.1 19. 765.4
- 3. 753.0 19. '0.6
- 4. 758.0 20. 767.8
< 3. '52,3 2i. 776.4
- o. _ ' 0.8
- 22. sc 3
- 7. :3. 3 T.i . " i. 0 . .
Is. 747.0 24, 752.0
-9 , _ 752.8 25. .
748.8 t0. 762.7 26. 719.9
,i 11, 770.0 27, 725,3
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,, - 12 , 791.7 28. 682.3 II- 13. '669,6 29. 185,9
- 14. 508.1 30. 229.5
- 15. 709.6 s
- 16. 760.5 INSTRUCTIONS Cn this fern, list the average daily snit power level'in Mie-Net Ur eeth det in the reporting sonth. Compute to the necrest whole noc9att.
These figures will be sted to plit a craoh for each rtoorting month. Note that . hen notinun denendable capacite is esec far the net electrical rating of'the unit there not te occasions when the daily cuerage oever level exceeds the 100% 12.e (or the restricted power level line).,In such ::ses,tt.e sverige daily anit power output sheet shsvid be festnoted to explain the tpparent ensecly
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Al'PCflDIX D ,
QTP 300-S13 ff0CRET fl0. 50-254 UNIT SilUTD0Vils AtlD POWER REDUCTIONS Revisici 5
- March 1978
.::11 NA!!E . quad-Cities Unit One COMPLETED BY T. Hafera
-PATC July 1, 1980 REPORT N0!!Til TELEPHONE 309-654-2241,
_JUtlE 1980 Extension 176 .
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LEno r !.:i i
'e'.'e e 8 @p$ LICEllSEE ;'l pj {} 'd ,
f: ) DUf:ATION $
$[_;* EVElli o0 0: 3 l'O . DATE (l!OURS) 'y3 ,3: REPORT !!0. '^
O CORRECTIVE ACTIONS /T.0MMErlTS o
n 8 800620 F 65.6 A 3 NA flA NA Reactor. scram due to low main condenser vacuum 4
9 800625 F 0.0 ~A NA NA
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IIA NA . Load reduction due to a small leak on the IB Reactor Feed Pump
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() I (3 APPENDIX D QTP 300-S13 -
UNIT SilVTD0VNS A!!D POVER REDUCTIO.1S Revision 5 DOCKET NO. 50-265 Harch 1978 .
qu d-Citles Unit Tw U.!1IT NAME COMPLETED B) T. Ha fera DATE July 1, 1980 REPORT t'.0:!Til TELEPliONE 309-654-2241, JUNE 1980
, , Extension 376
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m = Hb = 0 8'e. 8 g; g LICENSEE pg [] M p DURATION $ pye EVErlT ~ *8 9,: 8
!"J . DATE ' (HOURS) "
- yIg REPORT !!0. 8 CORRECTIVE ACTIONS / COMMENTS o
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7 800609 F O'. 0 A NA NA NA NA Load reduction due to output breaker on A Reactor
. Protection MG Set Trip.
8 800613 F 0.0 A NA NA NA NA Load reduction due to seal water line leak on the '
2A Reactor Feed Pump 9 800629 F 24.8 A 1 NA flA NA Shutdown to repair steam leak on Turbine Control Valve
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VI. UNIQUE REPORTING REQUIREMENTS 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 during the reporting period.
B. Control Rod Drive Scram Timing There were no control rod drive scram timing operations during the reporting period.
4
Vll. REFUELING INFORMATION 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.
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.-c n i r n .-t n ..d March C N InF00.."t.iR 1 RECUEST
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1 P,eload : 5 __ cycle: 6 .
- 1. Unit: _
Scheduled date for next refueling shutdown: 8-31_"Fn (Sh*%'n (2005;
- 2. ' -
- t Scheduled date for restart following refueling: 12-7-80(Startuo EOC6)
-3 " '
- 4. Vill refuelinD o'r resumption of opera' 'on thereaf ter No, require a technical Plan .100FR50 59 ' reloads
. s p e, cification change or other 1 ice,se mendment:
for future cycles of Quad Cities Unit 1. The review will be conducted in June, 1980. .
-5 scheduled date(s) for submitting p.oposed licensing action and supporting
. in forma tica: Juna, 1980 for 100FP50.59 related changen m 90 day =
prior to shutdcwn. . .
e.g., new or '
- 6. Important ' licensing considerations associated w'ith refueling,
' di f ferent fuci desig'n or supplier, unreviewed design 'or performance 5nalysis -
methods, significant changes in fuel design, new operating procedure.s:
Ucw fuel designs: Retrofit 8.7 3 fuel 2.65 w/o,4 (^ 224) 7 The number of fuel assemblics. . _ , ,
- a. ; Number of assemblics in core: 724
- b. ' Number of assemblies in spent fuel pool: 596 S. 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. fuei assemblies: ,
.a.
2 Licensed storage. capacity for ' spen't fuel: 1460 . .
.. .s.
- Planned increase in licensed storage:
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- b'. ,
S. The ' projected date of the last refueling' that can be discharged to the
- licensed capacity: Septeh.ber. 1985 f pent' fuel (end of bagool assuming the presdntch discharge' capability) j WPPROVEO l l
APii 2.01973 Q. C. O. S. R.
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- "'*m*haoi....,
QTP 300-S32
+
Revislon !
QUAD-CITIES REFUE!.InG- tiarch 1973 ,
.,,. ,INFORMATION REQUEST
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- 1. Unit: 2 Reload: 4 Cycle: 5' T
- 2. Scheduled date for next refueling shutdown: .
11-4'-79 (Shutdo.in Z004 i j
- 3 Scheduled date for restart folicwing refueling: _1-17-80 (Startuo E005)
. 4. ' Will refueling o'r resumption of operation thereaf ter require a technical-specificaticn change or other license ' amendment: No, Plan 100FR50.59 Reloads foi' future cycles of Quad Cities Unit 2. The review will be conducted- '
i by early. September,1979
.t..
- 5. Scheduled date(s) for submitting proposed licensing action and supporting
( . informa tion: Early lugust,1979 for 10CFR50 59 related changes % 90 ,
t days prior to shutdown. ,
1 '
I- 6. Important licensing considerations associated with refueling, e.g., new or '
' ' ' different fuel desigh or supplier, unreviewed design or performance snalysis methods, signi ficant changes in fuel design, new operating procedures: -
l New Fuel Design: Retrofit 8x8 fuel (180)
S '
a nat. U at bundle top and bottom b two larger water rods s, .
}' c new enrichment distribution d
. . propressurized
!. This fuel design was previcualy used for Quad Citieh Unit 1 Cycic 5 '
i and Dresden Unit 2 Cycle 7.
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7 The number of fuel assemblies. .
!. a. Number of assemblies in core:
724
{
- b. Number of assemblies in spent fuel pool: 492 i
{ 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 t in number of fuel assemblies: '
- a. ' Licensed storage capacity for' spent fuel: _
1460 .
~
I b. Planned increase in licensed storage: None '
9 The projected date of the last refuelinD that can be discharged to the spent fuel ~ pool assuming the present licensed capacity: March,' 1986
~
[ '(End of batch discharge capability)
A
.'P P R O V.E' D
- APR 2.01973 e.
. C. C. O. S. R.
Vill. GLOSSARY The follcwing abbreviation which may have beer, used in the Monthly Report, are defined below:
CRD - Control Rod Drive System SBLC -
Standby Liquid Control System MSIV -
Main Steam isolation Valve RHRS - Residual Heat Removal System RCIC - Reactor Core isolation Cooling System HPCI - High Pressure Coolant injection System SRM - Source Range Monitor IRM -
Intermediate Range Monitor LPRM - Local Power Range Monitor APRM -
Average Power Range Monitor TIP - Traveling incore Probe RBCCW - Reactor Building Closed Cooling Water System TBCCW -
Turbine Building Closed Cooling Water System RWM -
Rod Worth Minimizer SBGTS - Standby Gas Treatment System HEPA - High-Efficiency Particulate Filter RPS - Reactor Protection System IPCLRT -
Integrated Primary Containment Leak Rate Test LPCI - Low Pressure Coolant injection Mode of RHRS RBM -
Rod Block Monitor BWR -
Boiling Water Reactor ISI -
In-Service Inspection MPC -
Maximum Permissible Concentration
PCI --. . Primary' Containment isolation SDC -
Shutdown Cooling Mode of RHRS LLRT -
Local Leak Rate Testing MAPLHGR: -
Maximum Average Planar Linear Heat Generation Rate R.O. -
Reportable Occurrence DW -- Drywell
_RX -
Reactor
.EHC. -
Electro-Hydraulic Centrol System .
MCPR -
Minimum Critical Power Ratio PC10MR -
Preconditioning interim Operating Management Recommendations -
LER -
Licensee Event Report ANSI -
American National Standards institute NIOSH -
National institute for Occupational Safety and Health ACAD/ CAM - Atmospheric Containment Atmospheric Diluticn/
Containment Atmospheric Monitoring
..