ML20148A320
| ML20148A320 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/29/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RAR-88-09, RAR-88-9, NUDOCS 8803180093 | |
| Download: ML20148A320 (24) | |
Text
QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT FEBRUARY, 1988 COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET N05. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND DPR-30 f'U\\
l 0027H/00612 8803180093 880229 PDR ADOCK 05000254
)
R DCD
TABLE OF CONTENTS 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 4
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 B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary 0027H/0061Z
1 I.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.
The Station is jointly owned by Commonwealth Edisor 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 February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
l This report was compiled by Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
0027H/0061Z
II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One February 1-29 Unit One began on the first of the month operating at 600 MHe and power was later increased to 800 MHe. On February 2 at 0750 the unit was placed in Economic Generation Control (EGC). At 1053 on February 4, the unit was taken off of EGC and a load reduction to 380 MHe was taken due to an oil leak in the IB Recirculation Motor - Generator Set.
This power le/el was held while work was performed to repair the oli leak. At 1330 a load increase was begun.
800 MHe was reached at 1515 and on February 5 at 0735 the unit was placed in EGC.
From February 5 to February 14 unit load was maintained near full power, or operated in EGC with only minor interruptions to perform weekly surveillances. On February 15 the Unit' was taken off of EGC because of main computer problems. After these problems were resolved, the unit operated near full load or operated in EGC for the remainder of the month, with brief interruptions to perform routine surveillances.
B.
Unit Two February 1-29 Unit Two began operations at full po?er level, then decreased slightly at 0806 in preparations for Economic Gene n tion Control (EGC).
The unit was then placed in EGC. On February 3 at 2130 Unit Two was taken off of EGC and a load reduction to 700 MHe was taken due to problems with the Master Controller. At 2241 an ascension to full power was made and held until February 4 when problems with the master contrslier recurred.
The controller was placed in individual manual, then removed by Instrument Maintenance for repairs. At 1400 the mas +.er controller was returned to service. At 1450 power levels were adjusted and Unit Two was placed in EGC. From February 5 to February 29 unit load was maintained near full power, or the unit operated in EGC, witri brief interruptions while routine surveillances were perforned. Main computer problems occurred intermittently between February 14 and 15 but were resolved by the Nuclear Engineering Group without any affect on Unit Two's operations or power levels.
0027H/0061Z
III.
PLANT OR PROCEDURE CHANCES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications Technical Specification Amendments 104 and 101 were issued on February 3, 1988, to Facility Operating Licenses DPR-29 and DPR-30.
These amendments revise the Technical Specifications to now require the discharge lines of the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems to remain filled by maintaining a certain Contaminated Condensate Storage Tank level without reliance upon an active fill system pump.
B.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requirim; 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 There were no Deviation Reports or License Event Reports associated with the Safety Related Work Request Log this month for Unit 1 or Unit 2.
t:
1 IV.' LICENSEE EVENT REPORTS l
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 6.6.8.2. of the Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title of Occurrence 88-003 1-25-88 RCIC 48 valve failure to open during valve op.88-004 1-26-88 Line 1-0216-1/2" Does not meet FSAR Analysis Criteria 88-005 2-1-88 CR HVAC Isolation 88-006 2-9-88 Both Diesel Fire Pumps Inoperable / Deluge Actuation UNIT 2 88-002 2-23-88 HPCI inoperable -
l Loss of room cooler t
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r 0
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l l
0027H/0061Z l
V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report
- 8.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions *
- Revisions made to Unit Shutdowns and Power Reductions for January and also Operating Data Report for Unit One in December and for Unit One and Two in January.
0027H/0061Z
j APPENDlX C OPERATING DATA REPORT DOCKET NO. 50-254 UNIT be DATE March 7, 1988 COMPLETED BY 309-654-2241 TELEPHONE OPERATING STATUS 0000 020188 696
- 1. REPORTINO PERICO: 2400 022988 GROSS HOUR $ 1N REPORTINQ PERICO:
769 2511 MAX. OEPEND, CAPACITY (MWe Not):
- 2. CURRENTLY AUTHOR 1280 POWER LEVEL (MWtt:
DESIGN ELECTRICAL RATING (MWe. Net):
789 N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANYI (MWo. Net):
- 4. REASONS FOR RESTRICTION (IP ANYl:
THIS MONTH YR TO OATE CUMULATIVE
- 5. NUMSER OF HOURS REACTOR WAS CR'.TICAL...............
.0 3421.9
- 8. REACTOR RESERVE SHUTDOWN HOURS...................
696.0 1433.I
_106R91.1
- 7. HOURS GEN ER ATOR ON LINE.......................
0.0 0.0 909.2 S. UNIT RESERVE SHUTOOWN HOURS......................
1646232 3402696 226743453
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 540522 1112295 73535797
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWHI.............
517899 1064816 68968105
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 100.0 100.0 79,8
- 12. r E ACTOR SE RVIC E F ACTOR.......................
1
.0 100.0 82.2
- 13. R E ACTO R AV AILA BILITY P ACTOR.......................
100.0 99.5 77.2 l
100.0 99.5 77.8 I S. U NIT AV AI L Ati LITY F ACTOR..........................
96.8 96.2 64.7 it. UNIT CAPACITY F ACTOR (Using MDCI.....................
94.3 93.7 63.1
- 17. UNIT CAPACITY P ACTOR (Using Deseen MWel.................
O.0 0.5 5.4 i t. UNIT F O RC E O OUT AGE RAT E..........................
i
- 19. SHUTDOWNS SCHEOULEO QvER NEXT E MONTHS (TYPE. DATE. AND DURATION OF EACHl l
l
- 20. IF SHUT DOWN AT END OF REPORT PERIOO ESTIMATED DATE OF STARTUP.
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED l
INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.169
r APPENDlX C OPERATING DATA REPORT 50-265 00CKET NO.
WO UNIT March 7, 1988 DATE L. DEELSNYDER COMPl.ETED BY 309-654-2241 TELEPHONE OPER ATING STATUS 0000 020188 2400 022988 696
- 1. REPORTING PERICO:
GROSS hours IN REPORTING PERIOO:
r yax. ospeso. Capacity tuw u,,i:
769 2511
- 2. CURRENTLY AUTHORIZED POWER LEVEL (
M DESIGN ELECTRICAL RATING (MWo. Net):
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWo. Net):
- 4. REASONS FOR RESTRICTION (IP ANY):
THIS MONTH YR TO DATE CUMUI.ATIVE 696.0 1344.0 106001.I
- 5. NUMSE!4 OF HOURS REACTOR WAS CRITICAL,..............
O.0 0.0 2985.8 S. REACTOR RESERVE SHUTOOWN HOURS...................
696.0 1327.9 102863.2
- 7. HOURS GEN ER ATOR ON LINE.......................
O.0 0.0 702.9_
- 8. U NIT R ESERV E SHUTDOWN HOURS......................
............. 1671576 3095976 220466543
- 9. GROSS THERMAL ENERGY GENER ATED (MWH) 541129 1004486 70562270
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWH).............
519297 963044 66523069
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 100.0 93.3 77.0
- 12. 8' E ACTOR SE RVICE P ACTOR..........................
100.0 93.3 79.2
- 13. REACTOR AV AILABILITY P ACTOR................
100.0 92.2 74.7
- 14. U NIT S E RVIC E P ACT O R..............................
100.0 92.2 75.2
97.0 87.0 62.8
- 15. UNIT CAPACITY P ACTOR (Using MDC).....................
94.6 84.8 61.2
- 17. UNIT CAP ACITY P ACTOR (Using Deegn MWe).................
0 7.8 _
- 8. 4 _
- 18. UNIT P O RC E D OUT AG E RAT E..........................
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
- 20. IP SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OP STARTUP:
21, UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIONI:
PORECAST ACHIEVED INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I
l I
1.16 9
l APPENDlX C OPERATING DATA REPORT AMENDMENT 00CKET NO.
50-254 UNIT ONE DATE MARCH 7,
1988 L. DEELSNYDER COMPl.ETEO gy TELEPHONE 309-654-2241 i
OPERATING STATUS 0000 010188 744
- 1. REPORTING PERIOD: 2400 013188 GROSS HOUR $ lN REPORTING PERICO:
l
- 2. CURRENTLY AUTHORIZED POWER LEVEL (
).
2511 MAX. OEPEND CAPACITY (MWe Neti: 769 89 DESIGN ELECTRICAL RAtlNG (MWpNetti N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWeNet):
- 4. REASONS FOR RESTRICTION (IP ANY):
THIS MONTH YR TO OATE CUMULATIVE 744.0 744.0 109808.3 S. NUMSER OF HOURS REACTOR WAS CRITICAL...............
- 0. 0 0.0 3421.9
- 6. REACTOR RESERVE SHUTOOWN HOURS...................
737.1 737.1 106195.3
- 7. HOURS GENER ATOR ON LINE..........................
0.0 0.0 909.2
- 8. UNIT R ESERV E SHUTDOWN HOURS.....................
1756464 1756464 225097221*
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 571773 571773 72995275
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWH)...,,.......
546917*
546917* 68450206*
- 11. NET ELECTRICAL ENERGY GENERATED (WWH) 100.0 100.0 79.7
100.0 100.0 82.2
- 13. R E ACTOR AV AILABILITY F ACTOR,.....................
99.0 99.0 77.0
99.0 99.0 77.7
95.6*
95.6*
64.6*
- 18. UNIT CAPACITY F ACTOR (Using MDCI.....................
93.2*
93.2*
62.9A
- 17. UNIT CAPACITY F ACTOR (Us.no Deegn MWel......
O. 9_
0.9 5.4
- 18. UNIT FORCED OUTAGE RATE..................
- 19. SHUTDOWNS SCHEDULED OVER NEXT S MONTHS (TYPE DATE. AND OURATION OF EACH):
- 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION):
FORECAST ACHIEVED INITI AL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPERATION l.16 9
APPEN0lX C OPERATING DATA REPORT AMENDMENT DOCKET NO.
50-265 UNIT TWO DATE JfARCH 7, 1988 COMPl.ETED BY L. DEELSNYDER TELEPHONE 309-654-2241 OPERATING STATUS 0000 010188 744 2400 013188 GROSS HOURS IN REPORTING PERICO:
- 1. REPORTING PERIOD:
2511 MAX. Of PEND. CAPACITY (MWo. Net):8
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWti:
DESIGN ELECTRICAL RATING (MhNot):
789 N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe.Neti:
- 4. REASONS POR RESTRICTION (IP ANYl:
THIS MONTH YR TO DATE CUMULATIVE 648.0 648.0 105305.I
- 5. NUMOER OF HOURS REACTOR WAS CRITICAL,..............
0.0 0. 0_
1985.8 S. REACTOR RESERVE SHUTDOWN HOURS...........
631.9 631.9 102167.2
- 7. HOURS G E N ER ATOR ON LIN E,.........................
0.0 0.0 702.9
- 8. UNIT R ESERV E SHUTDOWN HOURS......................
- 9. GROSS THERMAL ENERGY GENERATED (MWH)............. 1424400 1424400 218794967 463357 463357 70021141
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWH).............
443747*
443747*
66003772*
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 87.1 87,1_
76.9
- 12. r E ACTOR SE RVIC E F ACTOR..................
87*I 87*I 79*I
- 13. R E ACTO R AV AILA t!LITY F ACTOR.......................
00*9 00 9 70*6
- 14. UNIT SERVICE F ACTOR.............................
84.9 84.9 75.1
- 15. UNIT AV AILA BILITY P ACTOR........................
77.6*
77.6*
62.7*
- 16. UNIT CAPACITY PACTOR (Using MDC) 75.6*
75.6*
61.1*
- 17. UNIT CAP ACITY P ACTOR (Uning Design MWel.................
15.2_
15.2_
8.3
- 18. UNIT FORCED OUTAGE RATE......
- 19. SHUTDOWNS GCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACHl:
- 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMriRCIAL OPERATION):
FORECAST ACHIEVED INITI AL CRITICALITY INITI AL E LECTRICITY COMMERCI AL OPERATION 1.16 9
I APPENDlX C j
l OPERATING DATA REPORT AMENDMENT DOCKET NO, 50-254 UNIT ONE DATE MARCH 7, 1988 COMPLETED BY I,.
DEFI,SNYDER l
TELEPHONE 309-654-2241 OPER ATING STATUS 0000 120187 744 2400 123187 GROS $ HOUR $ 1N REPORTING PERIDO:
- 1. REPORTINO PERIOD:
- 2. CURRENTLY AUTHO912ED POWER LEVEL (MWth 2511 MAX. DEPEND. CAPACITY (6h 769 DESIGN ELECTRICAL MATING (MWo. Net):
769 N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe. Net):
- 4. REASONS FOR RESTRICTION (IF ANYl:
THIS MONTH YR TO DATE CUMULATIVE 218.0 6251.6 109064.1-
- 5. NUMOER OF HOURS REACTOR WAS CRITICAL...............
O0 n.O_
1491 g_
- 4. R EACTOR RESERVE SHUT 00WN HOURS..................
125.0 6141.7 10545R.2
- 7. HOURS G E N ER ATO R ON LI N E.......................
0.0 0.0 404.2
- 8. UNIT RESERVE SHUTOOWN HOURS.....................
110607*
14282939* 223340757*
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 30467 4670118 72423502
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWH).............
25806 4456087 67903289
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 29.3 71.4 79.6
- 12. r EACTOR SERVICE F ACTOR......
82.I
- 13. R E ACTOR AV AILA BILITY F ACTOR......................
16.8 70.1 76.0
- 14. UNIT S ERVIC E F ACTOR........................
16.8 70.1 77.6
4.5 66.1 64.4_
- 16. UNIT CAPACITY P ACTOR (Using MDC) 4.4 64.5 62.8
- 17. UNIT CAPACITY F ACTOR (Us ng Design MWel.................
12.7 0.6 5.4
- 19. SHUTOOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND OURATION OF EACHh
- 20. IF SHUT DOWN AT END OF REPORT PERIOD ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIONh FORECAST ACHIEVED INITI AL CRITICALITY INITI AL E LECTRICITY COMMERCIAL OPERATION 1.16 9 l
'l APPENDlX 8 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT 0"*
DATE M rch 7, 1988 COMPLETED BY L. Deelsnyder 309-654-2241 TELEPHONE MONTH Februarv DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 750 745 1
37 728 720 2
3, 722 730 3
3, 0
734 4
20 736 743 5
31 I0 l02 6
n 727 746 7
23 8
24 769 791 I30 10 2e 733 751 11 gy 757 781 12 13 29 715 14 y
736 15 33 757 16 INSTRUCTIONS On this form, list the average daily unit power level in MWe. Net for each day in the reporting rnonth. Compute to the neassst whole megawatt.
These figures will be used to plot a g,raph for cash reporung month. Note that when nuximum dependable capacityis used f or the net cleetncal rating ut the unit there may be oscasions wheri the daily average power level exceeds the 100'A line (or the rninered power Iciel hnc). In such cases, the a crage daily unit power output sheet should be footnoted to explaus the apparent anomaly.
l.16 8
.s
APPENDlX B AVERAGE DAILY UNTT POWER LEVEL DOCKET NO.50-26s UNIT ho
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DATE. March 7 1988 COMPLETED BY L. Deelsnyder 309-654-2241 TELEPHONE ggg FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 787 772 9
g7 723 755 2
g, 729 741 3
734 4
20 760 5
21 738 734 4
22 729 741 y
23 785 8
24 717 750 g
25 753 753 10 3
745 751 99 27 759 738 12 40 745 13 29 701 14 y
745 i
15 39 16 i
l INSTRUCTIONS On this form, list the average datly unit power level in MWe Net for each day in the reporting month. Compute to the neatsst whole megawatt.
Thne figures will be used to plot a graph for cash reporting month. Note that when rmximum dependable capacity is uad for lhe net electncal rating ut the unit, there may be owasions when the daily average power level exceeds the 100'A line (or the rntruted power lesci line). In such cases, the average d.uly urut power output sheet should be footnoted to caplatu the apparent anumaly.
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ID/SA APPENDIX D QTP 300-S13 UNIT SHlTTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET No.
50-265 AMENDMENT August 1982 UNIT NAME QUAD CITIES UNIT TWO COMPLETED BY L. DEELSNYDER DATE FEBRUARY 3, 1988 REPORT MONTil JANUARY 1988 TELEPHONE 309-654-2241 5
m g
5
$EE gm Wm w
h@
Q h@
LICENSEE m@
DURATION EVENT o"
w O
NO.
DATE (IlOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS l
88-1 880105 0.0 II 9
CC VAI. VEX Power Reduction Due to Drywell Leak Inspection a
9 88-2 880111 F
112.1*
A 3
94-2-88-00]
EB CENERA Reactor Scram on Generator / Turbine Load
~
Mismatch - Main Generator Ground
\\
1 APPROVED AUG 161982 (final) ycg3g j
ID/SA APPENDIX D QTP 300-SI3 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
50-254 1
Augus t. 1982 UNIT NAME QUAD CITIES UNIT ONE COMPLETED BY L. DEELSNYDER DATE MARCH 7, 1988 REPORT MONTH FEBRUARY 1988 TELEPHONE 309-654-2241 5
w w"
5 EE gm
$w a
M LICENSEE m@
w DURATION EVENT U"
o" g
NO.
DATE (HOURS)
"g REPORT NO.
u CORRECTIVE ACTIONS /COtMENTS NONE 1
APPROVED i
AUG161982
-I-(final) y g, g g g
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ID/SA APPENDIX D QTP 3OO-S13 i
UNIT SHUTDOWNS AND POWR REDUCTIONS Revision 6 DOCKET NO. 50-265 August 1982 UNIT NAME QUAD CITIES UNIT TWO COMPLETED BY L. DEELShTDER DATE MARCH 7, 1988 REPORT MONTH FEBRUARY 1988 TELEPHONE 309-654-2241 1
5 m
w" EE gw hw a
g@hM g@
Q LICENSEE m@
w DURATION M
EVENT o
"g o
NO.
DATE (HOURS)
REPORT NO.
u CORRECTIVE ACTIONS /COfffENTS i
NONE i
l l
1 1
i i
i APPROVED AUG161982 (final) ygg3g
VI. UNIQUE REPORTING REQUIREMENTS 1
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 Operatins for the reporting period.
B.
COTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
0027H/0061Z
VII.
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.lanuary 18, 1978.
1 0027H/0061Z
QTP 300-S32 Revision i QUAO-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
Q1 Reload:
9 Cycle:
to 2.
Scheduled date for next refueling chutdown:
6 24_g9 3.
Scheduled date for restart following refueling:
9-17-89 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting Information:
MARCH 24, 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 b.
Number of assemblies in spent fuel pool:
1773 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 nomber of fuel assemblies:
Licensed storage capacity for spent fuel:
a.
3657 b.
Planned increa',e 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: 2008 APPROVED APR 2 01978 C). (:, C). S. R.
=.
QTP 300-532 Revision 1 QUAD
- CITIES REFUEllHG March 1978 INFOP,MATION REQUEST
.?
1.
Unit:
02 Reload:
8 Cycle:
o 2.
Scheduled date for next refueling shutdown:
4-9-88 3.
Scheduled date for restart following refuel!ng:
6-18-88 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license ameridment:
YES. TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED 70R NEW FUEL TYPES (MAPHLCR CURVES). CHANGE T LIMIT AND OPERATION AT INCREASED CORE FLOW / FINAL FEEDWATER TEMP. REDUCT 5.
Scheduled date(s) for submitting proposed licensing action and supporting in forma t ion:
March 4, 1988 6.
Important licensing considerations associated with refgeling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes In fuel design, new operating procedures:
FIRST RELOAD OF GENERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHGR LIMIT OF 14.4 KW/FT.
7 The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1311 S.
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:
Licensed storage capacity for spent fuel:
a.
38o7 b.
Planned increase in licensed storage:
o 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 CD. C C). S. R.
t i
e 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 t
Average Power Range Monitor APRM ATHS Anticipated Transient Hithout Scram BHR Bolling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter HEPA High Pressure Coolant Injection System HPCI HRSS High Radiation Sampling System Integrated Primary Containment Lehk Rate Test IPCLRT IRM Intermediate Range Monitor Inservice Inspection ISI 3
Licensee Event Report LER LLRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI Local Power Range Monitor LPRM MAPLHGR Maximum Average Planar Linear Heat Generation Rate i
MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratto MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve l
l 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 RHRS Residual Heat Removal System Reactor Protection System RPS Rod North Minimizer RWM SBGTS Standby Gas Treatment System Standby Liquid Control SBLC SDC Shutdow1 Cooling Mode of RHRS SDV Scram Discharge Volume 1
SRM Source Range Monitor 3
TBCCW Turbine Building Closed Cooling Water System Traversing Incore Probe TIP TSC Technica.1 Support Center i
1 0027H/0061Z i
~
,1 Comm:nwealth Edison e
22710 206 Avenue Nodh ouad Cities Nuclear Power Station Cordova, Illinoir 61242 Telephone 309/654 2241 RAR-88-09 March 1, 1988 U.S. NRC Office of Nuclear Reactor Regulation Washington, D. C.
20555 Attn:
Document Control Desk 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, 1988.
Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 8h-04 l
R. A. Robey v Services Superintendent l
vk Enclosure
?"d i
l t
l l
kk l
0027H/00612 l
.