ML20207M762
| ML20207M762 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/30/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO., IOWA-ILLINOIS GAS & ELECTRIC |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RAR-88-47, NUDOCS 8810180359 | |
| Download: ML20207M762 (23) | |
Text
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QUAD-CITIES NUCLEAR P0HER STATION UNITS 1 AND 2 MONTHLY PERFORMANC'
' PORT SEPTEMBER, 1988 COMMONHEALTH EDISON COMPANY AND IOWA-ILLINOIS GA5 & ELECTRIC COMPANY NRC DOCKET N05. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND DPR-30 l
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8810180359 880930 PDR ADOCK 05000254 R
FDC 0027H /(>361 Z n.
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TABLE OF CONTENTS I
j I.
Introduction II.
Sumary of Operating Experience A.
Unit One j
B.
Unit Two l
III.
Plant or Procedure Changes, Tests. Experiments, and Safety Related Maintenance l
A.
Amendments to Facility License or Technical Specifications l
B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experirrents Requiring NRC Approval I
D.
Corrective Maintenance of Safety Related Equipment l
IV.
Licensee Event Reports V.
Data Tabulations i
i A.
Operating Data Report l
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B.
Averane D&11y Unit Power Level j
C.
Unit Shutdowns and Power Reductions l
VI.
Unique Reporting Requirements
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A.
Main Steam Relief Valve Operations l
B.
Control Rod Drive Scram Timing Data l
VII.
Refueling Information VIII.
Glossary i
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f 00 7H/0061Z 1
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INTRODUCTION i
i Quad-Ctties Nuclear Power Station is composed of two Bolling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in j
Cordova; 111tnols.
The Station is jointly owned by Commonwealth Edison i
Company and towa-Illinois Gas & Electric Company.
The Nuclear iteam Supply
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Systems are General Electric Company Botilng Water Reactors.
The Architect / Engineer was Sargent & Lundy, Incorpcrated, and the primary construction contractor was United Engineers & Constructors.
The Mississippt i
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River is the condenser cooling water source.
The plant is subject to license l
l numbers OPR-29 and OPR-30, issued October 1, 1971, and March 21, 1972, t
respectively; pursuant to Docket Numbers 50-254 and 50-265.
The date of i
t initial Reactor criticalttles for Units One and Two, respectively were October
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r 18, 1971, and April 26, 1972. Comercial generation of power began on f
February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was complied by Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
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0027H/0061Z i
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One Unit One began the month of September operating in Economic Generation Control (EGC). On September 4 at 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />, a power reduction to 450 MWe was taken at the request of the Chicago Load Dispatcher. On September 5 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, Mad was increased to 805 MWe. At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, a power reduction to 520 MWe was taken at the request of the Chicago Load Dispatcher. Power levels were held constant untti September 6 when, at 0600, load was increased to 786 MWe, At 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />, the unit was placed in EGC.
The unit operated in EGC or was maintained near full power with minor Interruptions to perform routine surveillances until September 23.
At 0820, the unit was taken off of EGC and a power reduction to 360 MWe was taken as a result of a seal leak in the 1A Reactor feed Purna.
The pump was taken out-of-service while repairs were made. At 1745, the pump was returned to service and at 1750, a load increase to full power was taken. 806 MWe was achieved at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />. On September 24 at 1907, power levels were adjusted and the unit was placed in EGC. On September 25 at 0225, a power reduction to 610 MWe was taken at the request of the Chicago Load 01spatcher. At 0735, power levels were adjusted and the unit was plac?d in EGC.
Normal operational activities continued untti September 28 when, at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, the unit was taken off of EGC and a power reduction to 470 MWe was taken to make repairs on the ICI heater normal drain valve.
At 0510, work was completed and an ascent to full power was begun.
At 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, 815 MWe was achieved. On September 29 at 1435, power levels were adjusted and the unit was placed in EGC.
The unit operated in EGC for the remainder of t'ie month.
B.
Unit Two Unit Two began the month of September operating to Economic Generation Control. On September 4 at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />, the unit was taken off of EGC and a power redu: tion to 444 MWe was taken at the request of the Chicago load Dispatcher.
Power levels were held constant untti September 5 when at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, a load increase to full power was taken. At 2205, a power reduction to 430 MWe was taken at the request of the Chicago Load Dispatcher. On September 6 at 0440, load was increased to full power (815 MWe). On September 7 at 2345, a power reduction to 448 MWe was taken per the L.D.
At 0600, load was increased to full power.
From September 7 to September 12, power levels were adjusted at the request of the load Dispatcher. At 1710 the unit was placed in EGC.
The unit operated in EGC or was maintained near full power untti September 16 when a load reduction to 295 MWe was taken to perform a Rectre pump ramp test. On September 17 at 0520, a load increase was taken to 750 MWe, On September 18 at 1014, the unit was placed in EGC. On September 19 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, the unit was taken off of EGC and an ascent to full power was taken to perform a TIP set.
Full power was held until September 21 when power levels were adjusted and the unit was placed in EGC.
For the remainder of the month, the unit operated in EGC or was maintained near full power with minor interruptions to perform routine surveillances.
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PLANT OR: PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE A.
Amendments to Tacility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.
B.
Facility or Procedure Chances Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.
Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment 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.
t 0027H/0061Z
UNIT 1 MAINTENANCE SUMHARY WORX REQUEST NO.
Q62123 LER NUMBER:
87-016 COMPONENT:
System 1600 - X-4 failed LLRT.
Removed hatch.
Cleaned bolts.
Installed new gaskets.
CAUSE OF MALTUNCTION: This malfunction was due to the seal on the Drywell Head Access Hatch. X-4, had lost its pliability due to thermal stress.
RESULTS & EFFECTS ON SAFE OPERATION: This event has minimal safety consequences.
Since the total leakage determined does not represent a probable leakage from the primary containment during accident conditions.
ACTION TAKEN TO PREVENT REPETI'.' ION The seal is not replaced on a regular basis.
Therefore, to prevent any recurrence of this type of failure, the seal will be replaced during each refueling outage.
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f WORK REQUEST NO.!
Q62318 LER NUMBERI N/A f
COMPONENT 4 System 6600 - Removed air duct assembly, inspected turbo charger i
on 1/2-6601 (1/2 D.G.). Found 0.K.
CAUSE OF MALFUNCTION This was not a malfunction.
This work request was written to inspect the turbo charger af ter a piece of aluminum was found in the air box. The turbo charger was determined to be in good condition.
RESULTS & EFFECTS ON SAFE OPERATION:
This event had no results or effects
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on safe operation because it was not a malfunction but an inspection.
i ACTION TAKEN TO PREVENT REPETITIONt No further corrective action was necessary.
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f k'ORK REQUEST NO.: Q62372
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LER NUMBER 87-016 COMPONENT 4 System 1000 - Failed LLRT.
Installed new spring cast cap on RRR Drywell Iso Valve M0-1001-26A.
c CAUSE OF MALFUNCTION 8 The spring cartridge cap was replaced with a like-for-like replacement. The torque switch was also reset to its maximum setting.
l RESULTS & EFFECTES ON SAFE OPERATION: This event has minimal safety consequences since the total leakage determined does not represent a probable leakage f rom j
the primary containment during accident conditions.
ACTION TAKEN TO PREVENT REPETITION:
The valve will be disassembled and inspected during the next Unit One refueling outage to further attempt to l
discover the cause of the increased leakage.
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3 UNIT 2 MAINTENANCE SNMARY f
j WORK REQUEST NO.t Q64492 I.
LER NUMBER: 87-030 l
COMPONENTI System 263 - Installed supports for ATWS sensing lines near l
U2 2202-6 rack.
j CAUSE OF MALFUNCTION: The cause of this event was attributed to cognitive
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i personnel error and inadequate design.
The original hanger support design i
j was inadequate, therefore, temporary supports were installed. Due to
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personnel error, the modification test was signed off without having the supports installed. As a result, a new design was not issued and the 3
1 proper supports were not installed prior to declaring the modification I
j operational.
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l RESULTS & EFFECTS ON SAFE OPERATION:
The ATWS is designed to act as a
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j backup to the Reactor Protection System.
The Reactor P.otection System t
was operable for both Unit One and Two while the ATWS senting lines were j
in the condition and would have shutdown the reactor if required. Also.
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the Standby Liquid Control system was available to shutdown the reactor j
j if necessary.
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~l ACTION TAKEN TO PREVENT REPETITION: To prevent reoccurrence. BWRED now requires a dimensional verification be performed by a certified Quality Control Inspector for all Safety Related modifications involving the j
insta11ation or modifications of Saf ety Related load carrying members.
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Resolution of deficiencies will be accomplished before the modification
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j test may be signed off as completed.
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i WORK REQUEST NO t Q64493
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LER NUMBERt 87-030 j
i COMPONENT:
System 263 - Installed supports for ATVS sensing lines.
CAUSE OF MALFUNCTION: The cause of this event was attributed to cognitive personnel error and inadequate design. The original hanger support design was inadequate, therefore, temporary supports were installed. Due to personnel error, the modification test was signed off without having the supports installed. As a result. a new design was not issued and the proper supports were not installed prior to declaring the modification operational.
RESULTS & EFFECTS ON SAFE OPERATION: The ATVS is designed to act as a backup to the Reactor Protection System. The Reactor Protection System was operable for both Unit One and Two while the ATWS sensing lines were in the condition and would have shutdown the reactor if required. Also, the Standby Liquid Control system was available to shutdown the reactor if necessary.
ACTION TAKEN TO PREVENT REPETITION:
To prevent reoccurrence. BWRED now requires a dimensional verification be performed by a certified Quality Control Inspector for all Safety Related modifications involving the installation or modifications of Safety Related load carrying members.
Resolution of deficiencies will be accomplished before the modification test may be signed off as completed.
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LICENSEE EVENT REPORTS
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i There were no Licensee Event Reports for Unit One and Two for the month of September.
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V.
DATA TABULATIONS The following dita tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 0027H/00612
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APPENOlX C l
l OPER ATING DATA REPORT 00CKET No.
50-254 s
One i
UNIT OATg 10-6-88 COMPLETED ilY Lynne Deelsnyder TELEPHONE 304-654-2241 t
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l OPGRATING STATUS 0000 090188 720 f
g,gg,ggy,,,pgn, 2400 093088 Gross MouRs IN REPORTING PeR600:
769 2511 WAm. OSPONS CAPACITY (=M
- 3. CURRENTLY AUTHORIIED Powem LEVIL (Wwd:
08864N OLOCTRICAL RATINe tMWpNs4:
784 N/A
- 3. POWOR L8V8L TO WMICH RetTRICT80 llP ANY) tWwe pesti:
l 4 REASONS POR RSSTR6CTION (IP ANY)t f
TMit MONTH VR TO Daft CVWULAtlWE S. fouute'Pl 0F MOUA8 REACTOR WA4 CRITICAL,.............
7 20. 0 6326.2 11 n90,1 0.0 0.0 u?1 R 4
- 6. REACTOR R 888RVs SMUTOOWN MOURE...................
6072.2 111530.4
- 7. MOURO GENER ATOR ON UNt......................... 7 2 0. 0 0.0 0.0 909.2 j
- 8. UNif RElemyt SMUT 00WN MOURS......................
............. 1683242 13484710 236825467 l
- 9. GROSS TMERMAL ENEROY CENER Af t0 tMwMi i
541754 4346789 76770291
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- 10. GR005 ILOCTRICAL ENERQY otNER Afl0 twwMi.......,....
............. 517701 4141835 72046124 I
- 11. NET TLOCTRICAL INFRGY 08NER Af t0 (WWMI 100.0 96.2 60.3
100.0 96.2 82.7_
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- 13. R E ACTOR AV AILA tiLITY P ACTOR.......................
92.4 77.6
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it. UNIT AV AILAtiLITY P ACTOR..........................
t 93.5 81.9 6%.2 to. UNIT CAPACITY P ACTOR tuant WCC1.....................
9I*I 79 63.6
- 17. UNIT CAPACITY P ACTOR lug 0emen MWel.................
0.0 5.2 5.4 its UNIT PORC4 0 0WTA44 RAf t..........................
- 19. SMUTOOWN8 SCM40VL50 0VER ktxt S WONTHS ITYPt. DAf t. ANO DURATION OP E ACMit i
- 30. IP SMUT 00wN AT END OF REPCRT PEmiOO 85TIWATED 04T8 0F ffARTVP.
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P0 mica 3T ACMity80 l
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INITI AL CRITICALITY nktTIAL eLSCTRICITY COMMERCI AL QPtRAT104 l
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I APPENDlX C OPERATING DATA REPORT 00CKETNO.
50-265 UNIT Tm 10-6-98 DATE 1.ynne Deelsnyder COMPLETED NY 309-654-2241 TEl.tPHONg OMRATING STATUS 0000 090188 720 2400 093088 CRCas HOUR 8 IN ROPORTING Pim100:
- 1. RSPORTING PtAl00:
769
- 2. CURR0NTLY AUTHORIIGO POwtR LEVIL (Wumb 251I M A A. 0tPENO. CAP ACITY (hReedeeil.
048104 ILSCTR6 CAL RATING (WietNeil:
764 N/A
- 3. POW 9R LIVEL 70 WMPCM RESTRICTIO (lP ANY1 (ww,Neil:
- 4. AtASONE POR RS8TRICTION (17 ANY):
THitMONTH YR 70 OATE CUwuLATive 720.0 414A.8 108805.9
- 5. NUMetR OF HOUR $ RfACTOR WAS CRITICAL...............
0.0 0.0 2485.8
- 4. REACTOR R SSERVE SMUT 00nN MOURS...........,.......
720.0 4066.9 105602.2
- 7. HOUR 8 OtNERATOR ON UNE............
0.0 0.0 702,9
- 8. UNif RESIRVE SHVTOOWN HOUR 8
............. 1612805 8625252 225995819
- 9. GROS 8 THERMAL ENERGY GENERAf t0 (WWH1 527857 2773758 72331542
- 10. CR0tt ELECTRICAL ENERGY GENER ATED (wwHl.............
505170 2642102 6 R 202127
- 11. NET tttCTRICAL INERQY CENLR Af to (WWHI 6.1 76.2
- 12. ' t ACT O R SE Rv lC E P ACTOR...........................
100.0 63.1 78.3 1
- 13. R E ACTO R AV AILA tt W TY P ACTOR.......................
100.0 _
61.9 73.9
- 14. UNITitRVICE P ACTOR..............................
100.0 61.9 74.4
- 15. UNIT AV AILA tluTY P ACTOR.............
91'2 b2
62 I
- 14. UNIT CAP ACITY P ACTOR IUuset WDC1.....................
88.9 50.9 60.5
- 17. UNIT CAP ACITY P ACTOR IM 0eme Weel.................
i t U4tT P ORC 8 0 0UT A44 RATE..........................
14.1 8.6 0.0
- 19. SHUT 00nN8 SCM60VL80 OvtR NExT 4 WONTHS ITTPt. DA18. AND OURAft0N OP I ACMit
- 20. IF SMUT DOWN AT END OP REPORT Pim:00. 85TiwAf f 0 0Aff CP STARTuP.
- 21. UNITS IN TEST ITATus (PRIOR TO COMM tmCI AL OPERATIONI.
PORICAST ACMifv80 INITI AL CRITICAUTY INITI AL ELICTRtCITY COMM8RCIAL Cet AATiON l
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ID/5A APPENDIX D QTP 300-513 I
tlNIT SNtfTDOWIES AIID PohER REDUCTIONS Revision 6 DOCKET NO. 50-254 August 1982 INIIT NAfE Quad Citten Unit One Coltt2TED BT L. Deelsnyder DATE REFORT NOIITN SEPTEMBER. 1988 TEI2PHOIE 309-654-2241 E6" w
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$ fkR LICENSEE m@
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DLEATICII 3
g EVENT gu gu No.
DATE (NotRS)
REP 00tT NO.
U CORRECTIVE ACTIostS/ Col 9ENTS 88-23 880923 F
0.0 13 5
Cil PUMPIX Power Reduction Taken Due to Seal Leak on Reactor Feed Pump Flex Line APPROVED AUG161982 (final) yC.OSN
i ID/5A APPENDIE D QTP 300-S33 UIIIT !DIUTDOIAIS AND F0tER REDUCTIO 8BS Revision 6 DOCKET NO.
50-265 August 1982 UNIT NAE Quad Cities Unit Two COMPIITED 5' L. Deelsnydee DATE October 6, 1988 REPOItT N00lTN SEPTEMBER, 1988 TEIZPIBONE 309-654-2241 A
M E
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LICENSEE w
DiMATICII E
'q EVENT gu u
NO.
DATE (NOLRS)
RE. PORT NO.
u enenFCTIVE ACTIostS/C0f9ENTS 88-13 880910 F
0.0 11 5
ZZ ZZZZZZ Power Reduction Taken at the Request of lead Dispatcher 88-14 880924 F
0.0 11 5
CB PUMPXX Power Reduction Taken Due to 2B Rccirc Pump 011 Bearing Problem i
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APPROVED AUG161982
-I-(finsI) yCusN
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APPENDIX 5 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-254 0"'
UNIT DATE 10-03-88 COMPLETED BY Lynne Deelsnyder TELEPHONE 309-654-2241 September MOg DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MW4t)
(MWeNet) 683 725 g
gy 728 714 2
gg 77I 3
19 4
_. 702 y
71g gg 21 730 k
642 702 698 6
22 7
23 555 710 754
'53 24 8
699 804 g
g 743 722 10 y
698 730 gg 27 783 12 3
6R0 13 3
771 751 755 761 14 30 750 15 y
701 16 INSTRUCTIONS On this form, list the aversy daily unit power level in MWe. Net for eat.h day m the reponing month. Compute to the neassst whole megawatt.
These figures will be used to plut a graph for cash reportang month. Nute Iliat when truximura dependable capacity is used tur the net clestncal rating ut the unit, there may be osessions wiieri the daily aversy power level exceeds the IfCA Ime (or the restrwted power Icsel Ime). In such cases, the average daly urut power ontput sheet should be foutnoted to czplaua the apporrat anumaly.
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APPENDIX B AYERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-265 UNIT Two DATE 10-01-88 COMPLETED BY tynne Deelsnyder TELEPHONE 309-654-2241 gg September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWeNet)
(MwNet) 699 634 1
gy 748 3
727 gg 712 g,
75A 3
4 707 gg 791 5
622 21 760 6RO g
725 g
728 728 23 y
421 3
677 24 g
814 2g 469 825 tg 554 26 709 l
11 6R4 27 778 20 724 12 713 3
7 /. o 13 758 14 69R 30 l
15 762 31 16 701 i
INSTRUCTIONS On this form, list the aversy daily unit power level m MWeNo: foi sach day in the reporting month.Cempute to the neasslt whole megawatt.
Thew figures wdl be used to plut a i;taph for cash repurung mt..s Nute that when rneunum dependable capacit uwd for the nel clestncal ratmg ut the unit, there may be ossasions wher the daily aversy power level exceeds the i
I 100J lice (oe the rntn.ted power itsel hnc). In such casas. the average d.4 unit power output sheet should be footacted to capLua the apparent anumaly.
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,c VI. UNIQUE REPORTING REQUIREMENTS'.
The following items are' included in this report based on prior commitments to the commission:
t A.
MAIN STEAM RELIEF VALVE OPERATIONS 4
There were no Main Steam Relief Valve Operations for the reporting period, s
B.
CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO 1
The basis for reporting this data to the Nuclear Regulatory Commission
- are specified in the surveillance requirements of Technical Specifications 4.3.C.1.and 4.3.C.2.
The following tabic is a complete summary of Units One and Two Control'
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Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.
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RESULTS OF SCRAM TIMING MEA 6UREMENTS PERF0fWED ON UNIT I & 2 CONTROL 4
ROD DRIVES, FROM l-l-88 TO 12-31-88 AVERAGE TIME IN SECONDS AT %
MAX. Tile INSERTED FROM FULLY WIT 10RAWN FOR 90%
INSERTION DESCRIPTION NLABER 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 (Average Scram insertion Time) 5-16-88 89 0.29 0 f.7 1.45 2.56 3.D7 Unit 1. Hot Scrr.m Timing A Sequence (G-II) l 6-17-88 2
0.30
- 0. G 1.49 2.55 2.60 Unit 1 G-7 and P-7 Ilot Scram Timing i
(P-7)
(P-7 had probe replaced.)
6-27-88 177 0.31 0.68 1.44 2.52 2.96 Unit 2 Ilot Scram Timing (11-5) 7-2-88 1
0.29 0.63 1.35 2.36 2.36 Unit 2. P-Il Hot Scram Timed after (P-II) accumulator work.
8-24-88 1
0.27 0.o3 1.40 2.47 2.47 Unit 2. B-8 Ilot Scram Timed after (B-8) accumulator work, Q68923 9-8-88 1
0.32 0.71 1.48 2.61 2.'61 Unit 2. F-ll Hot Scram Timed after (F-11) accumulator work, Q69472 4
0027H/0061Z
VII.
REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (76-24) 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.
0027H/0061Z
QTP 300-532.
Revision 1 QUAD e,lTIES REFUELING March 1978-INFORMATION REQUEST 1.
Unit 01 Reload:
9 Cycle:
10 2.
Scheduled date for next refueling shutdown:
6-10-89 3.
Scheduled date for restart following refueling:
9-2-89 4.
Will refueling or resumption of operation thereaf ter require a technical speelfication change or other IIconse amendment:
NOT AS YET DETERMINED.
5.
scheduled date(s) for submitting proposed licensing acticn and supporting Information:
MARCH 10, 1989 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:
NONE AT PRESENT TIME.
7.
The number of fuel assemblies.
a.
Number of assemblies in core:
724 l
b.
Number of assemblies in spent fuel pool:
1773 j
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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 in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3657 b.
Planned increase in lleensed storage:
0 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 l
APPROVED 1 APR 2 01978 Q.C.O.S.R.
r QTP 300-532 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST s
l.
Unit: _
02 Reload:
9 Cycle:
10 2.
Scheduled date for next refueling shutdown:
12-2-89 3.
Scheduled date for restart following refueling:
3-3-90 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendawnt:
NOT AS YET DETERMINED.
5 Scheduled date(s) for submitting proposed licensing action and supporting Information:
SEPTEMBER 2, 1989 6.
Important licensing considerations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, signiffc. int changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7 The number of fuel assemblies, a.
Number of assemblies In core:
724 b.
Number of assemblies in spent fuel pool:
1475 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been recuested or is planned In number of fuel assemblies:
a.
Lleensed storage capacity for spent uel:
3897 b.
Planned increase in lic'ensed storage:
0 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 APPROVED APR 2 01978 Q.C.o.S.R.
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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report,-
are defined below:
Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Honitoring ANSI American National Standards Institute Average Power Range Monitor APRM Anticipated Transient Hithout Scram ATHS Boiling Hater Reactor BHR CRD Control Rod Drive EHC Electro-Hydraulle Control System Emergency Operations Facility EOF Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter HEPA HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS IPCLRT Integrated Primary Containment Leak Rate Test Intermediate Range Monitor IRM ISI Inservice Inspection Licensee Event Report LER LLRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio Maximum Fraction Limiting Critical Power Ratio MFLCPR MPC Maximum Parmissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Hater System RBCCH RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHRS Reactor Protection System RPS RHM Rod Horth Minimizer Standby Ga3 Treatment System SBGTS Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC SOV Scram Discharge Volume Source Range Monitor SRM Turbine Building Closed Cooling Hater System TBCCH Traversing Incore Probe TIP Technical Support Center TSC 0027H/00612
Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654 2241 RAR-88-47 September 27, 1988 Director of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Mall Station PI-137 Washington, D. C.
20S55 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 September, 1388.
Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION h Robey R. A.
Services Superintendent RAR/vmk Enclosure Y
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0027H/0061Z i