ML20151V260
| ML20151V260 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/31/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RAR-88-36, NUDOCS 8808220197 | |
| Download: ML20151V260 (24) | |
Text
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sw, QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY, 1988 COMMONHEALTH EDISON COMPANY AND ICHA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND OPR-30 3
0027H/0061Z 8808220197 880731 DY PDR ADOCK 05000254 R PDC
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3 CIABLE!0FiCONTENTS
.I . Introduction ;
, II. Summary of Operating Experience ;
A. Unit One l B. Unit Two t 4
III. Plant or Procedure Changes, Tests. Experiments, and Safety i 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 Reiated Equipment ,
IV. Licensee Event Reports l V. Data Tabulation: l
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1 A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shatdowns and Power Reductions ,
t VI. Unique Reporting Requirements ;
A. Main Steam Relief Valve Operations i B. Cor. trol Rod Drive Scram Timing Data l l VII. Refueling Information ,
1 VIII. Glossary :
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N c Z 1.J INTR 000CTION c;
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Quad-Cities Nuclear Power Station is composed of-two Bolling Water t 1
i Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located.in t
! Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors. The
] Architect / Engineer'was Sargent & Lundy, Incorporated, and the' primary 3 1
construction contractor was United Engineers & Constructors. The Mississippi ,
i River is the condenser cooling water source. The plant is subject to license i numbers OPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, 1
- respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of
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initial Reactor criticalities for Units One and Two, respectively were October j
,. 18, 1971, and April 26, 1972. Commercial generation of power began on '
1 February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
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. This report was compiled by Verna Koselka and Lynne Deelsnyder, telephone i !
- number 309-654-2241, extensions 2240 and 2185. .
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SUMMARY
OF OPERATING EXPERIENCE A. Unit one Unit One began the month of July operating at full power. At 1710, the unit was placed in Economic Generation Control (EGC). The unit operated in EGC or was maintained near full power until July 6. At 1820, a load reduction vaa taken to 555 MWe due to high river temperatures. On July 7, at 1530, another power reduction was taken to 476 MWe, again attributed to high river temperatures. Load was held constant until July 8, when at 0807, a power increase was taken to 650 MWe. At 1215, a power reduction was taken cs 300 MWe due to high river temperatores.
Power levels were held constant until July 9. At 1100, a load increase ,
However, at 1500, a power reduction was taken to was taken to 625 MWe.
278 MWe due to high river temperatures. Power levels were held constant until July 12 when a load increase to full power was taken with control rods and recirculation pumps. At 1835, 750 MWe was reached. Power levels were held constant until July 14 when a load reduction was taken at 0025 to perform Main Steam Isolation Valve monthly Surveillance. At 0225, the MSIV testing was completed, and load was held constant until July 15, when at 1100 a reduction was taken due to high river temperatures. At 1325, 350 MWe was reached. At 1440, an ascent to full power was begun.
At 1530, 772 MWe was reached and another load reduction was taken due to high river temperatures. On July 16, at 1325 power level was at 200 MWe and held constant until July 20. At 0730, a load increase was taken to 400 MWe and power level was maintained ur.til July 21. At 1015, another load increase was taken to 710 MWe. At 2330, a load reduction 525 MWe was taken per the Chicago Load Dispatcher. Power levels were held constant until July 22. At 0530, an ascent to full power was begun. At 0945, full load was achieved. On July 23, at 2130, power levels were adjusted in preparation for EGC operation. At 2158, the unit was placed in EGC. On July 24 at 0030, EGC was tripped to perform weekly turbine testing. At )
0050, several alarms were received in the control room due to a feedwater 1 heater trip. Power level was held at 575 MWe while investigations were j made into the heater problems. Once the problem was resolved, power levels were adjusted for EGC operation. At 1740, the unit was placed in EGC.
The unit operated in EGC or was maintained near full power for the remainder of the month with minor interruptions to perform routine surveillances.
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. B. Unit Two -
Unit Two began the month of July operating at 413 MWe. At 0100 on July 1,
- a powar ascent to full load was begun with control rods and recirculation pumps. 705 MWe was reached at 1020. Due to high river temperatures, a
load reduction to 595 MWe was taken at 1130. Power levels were held constant at the Chicago Load Dispatcher's request until July 5. At 1051, an ascent
, to full power was begun and at 1216, the unit reached 798 MWe. Load was held constant until July 7 for Traversing In-Core Probe ret. At 1500, a power reduction was taken to $20 MWe due to high river temperatures.
On July 8, at 0700, a load increase to full power was taken and 795 MWe was reached at 0920. At 1130, a power reduction was taken due to.high river temperatures. 351 MWe was reached at 1500. Between July 8 and July 23 several fluctuations in power levels occurred due to high river a temperatures. Routine surveillances were performed and normal operational activities occurred during this time. .On July 22, at 1645, a Generator / :
Exciter Field Ground alarm was received in the control room. At 1705, it was discovered that the relay for the Main Generator Field Ground war ;
tripped and would not reset. At 1745, a load red 6ction was taken to try j and clear the alarm. Attempts to clear the alarm were unsuccessful and -
1 on July 23 at 0300, another load reduction to 600 MWe was taken. At 2032, a power reduction to hot standby was begun with control rods and recircu-lation pumps. On July 24. at 0350, the main turbine was tripped and further investigations were made into the generator ground. At 1519, the mode switch was placed in SHUTDOWN and the reactor was manually scrammed. i l The unit was shutdown for the remainder of the month and investigations '
l were made into the main generator ground.
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4 III. PLANT OR PROCEDURE CRANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendmer.ts to Facility License or Technical ecifications Technical Specification Amendment Nos. 107 and 104 were issued ~'
on June 23, 1988 to Facility Operating Licenses DPR-29 and DPR-30.
These amendments delete the upper tolerance of the Reactor Low-Lov Water Level setpoint and correct typographical errors in the bases.
Technical Specification Amendment Nos. 110 and 106-were issued I on June 30, 1988 to Facility Operating Licenses DPR-29 and DPR-30.
These amendments revise the trip setpoint for refueling floor radi-ation monitors used at the Quad Cities Nuclear Power Station, and j elevate the level of management authorization required for approving I changes to plant operating procedures.
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B. Facility of 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 l
I 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 i reporting period. This summary includes the followingt Work l Request Numbers, Licensee Event Report Numbers, Components.
l Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition. l l
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UNIT 1 MAINTENANCE
SUMMARY
There were no Deviation Reports or Licensee Events Report associated with the Safety Related Work Request Log this month.
UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST NO.: Q62003 LER NUMBER: 87-019 COMPONENT: System 1000 - Cold load setting reset on spring can, 1009A-M-207.
CAUSE OF MALFUNCTION: The cause of the piping supports to be in noncompliance with the Final Safety Analysis Report is due to a design error. During a 1980 modification as-built configurations were not accurately documented on drawings used for the original piping stress analysis.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel were not affected during this event. The systems were analyzed and determined to be vperable.
ACTION TAKEN TO PREVENT REPETITION: Spring can load settings were revised, a new support was installed and another support was reinforced as corrective action for this event to prevent recurrence. The stations engineering department now requires a dimensional verification be performed on all Safety Related Modifications as part of the new modification program, implemented in April, 1987.
WORK REQUEST NO.: Q62004 :
1 LER KUMBER: 87-019 l COMPONENT: System 1000 - Cold load setting reset on spring can, 1009A-W-208.
CAUSE OF MALFUNCTION: The cause of the piping supports to be in noncompliance with the Final Safety Analysis Report is due to a design error. During a 1980 modification as-built configurations were not accurately documented on ,
drawings used for the original piping stress analysis. )
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel were not affected during this event. The systemt. were analyzed and determined j to be operable. ;
I ACTION TAKEN TO PREVENT REPETITION: Spring can load settings were revised, j a new support was installed and another support was reinforced as corrective ;
action for this event to prevent recurrence. The stations engineering department j now requires a dimensional verification be performed on all Safety Related Modifications as part of the new modification program, implemented in April, 1987. ;
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WORK REQUEST NO. Q62005 LER NUMBER: 87-019 COMPONENT: System 2300 - New support installed, 2325-M-201.
CAUSE OF MALFUNCTION: The cause of the piping supports to be in noncompliance with the Final Safety Analysis Report is due to a design error. During a 1980 modification as-built configurations were not accurately documented on drawings used for the original piping stress analysis.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel were not affected during this event. The systems were analyzed and determined to be operable.
ACTION TAKEN TO PREVENT REPETITION: Spring can load settings were revised, a new support was installed and another support was reinforced as corrective action for this event to prevent recurrence. The stations engineering department now requires a dimensional verification be performed on all Safety Related Modifications as part of the new modification program, implemented in April, 1987.
WORK REQUEST NO.: Q62441 LER NUMBER: 87-019 COMPONENT: System 2300 - Reinforced support on line 2-2310-4".
CAUSE OF RALFUNCTION: The cause of the piping supports to be in noncompliance with the Final Safety Analysis Report is due to a design error. During a 1980 modification as-built configurations were not accurately documented on drawings used for the original piping stress analysis.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and pt;sonnel were not affected during this event. The systems were analyzed and determined to be operable.
ACTION TAKEN TO PREVENT REPETITION: Spring can load settings were revised, a new support was installed and another support was reinforced as corrective action for this event to prevent recurrence. The stations engineering department now requires a dimensional verification be performed on all Safety Related Modifications as part of the new modification program, implemented in April, 1987. j 1
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i IV. LICENSEE EVENT REPORTS The following is a tabular sumary of all licensee event reports for Quad-Cities Ur.its One and Two occurring during the reporting period, pursuant to '
the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2 of the Technical Specifications.
There were no Deviation Reports or Licensee Event Reports associated with the Safety Related Work Request Log for the month of July for Unit 1 or Unit 2.
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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two . curring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title of Occurrence 88-009 6-10-88 HPCI Inoperable due to hot aux. oil pump motor.
88-010*Now listed as 6-21-88 1/2 D.G. Autostart 88-024 under Unit 2 88-011 6-25-88 RCIC Inoperable UNIT 2 4
88-014 . 4-20-88 Deviation from Process l . Control Program 88-015 5-30-88 ESF Actuation due to Blown Fuse 88-016 6-1-86 Partial Group 2 Isoir. tion -
Blown Fuse
!88-017 6-7-88 MSIV Air Line Hanger not meeting FSAR rqeuirements j 88-018 6-9-88 Spurious Group III Isolation /
EST two times88-019 6-11-88 EST Actuation - when fuse in [
4 902-40 panel removed i
' l 88-020* Reclassified as 6-19-88 TIP #3 Failed to Withdraw on nonreportable. a Group II Isolation 88-021*Now listed as 6-20-88 ECCS Initial Signal due to 88-020 Valving error 88-022*ggwgjstedas 6-22-88 Failure of Bue 28/29-5 hi 013*Nov listed as 6-26-88 HPCI Isolation i 88-021 88-024*Was listed as88-010 6-21-88 1/2 D.G. Autostart under Unit 1
- These have been renumbered since the report in June dua to reclassifying of LER 88-020 under Unit 2.
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V. DATA TABULATIONS L The following data'. tabulations are presented in this report:
A. Operatt.c Data Report ,
B. Average "'1h Unit Power Level C. Unit Shutdowns and Power Reductions 1
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APPENDIX C OPERATING DATA REPORT 00CXET No. 50-254 UNIT One OATE August 9. 1988 COMPLETED BY 1.vnne Deelsnyder TELEPHONE 309-654-2241 OPEMATING Sb'fUS 0000 070188 2400 073188 GRosE HOURS IN REPORTINO PSR600:
744
- 1. REPORTING PGRICO:
2511 MAX. 0EPt NO. CMACITY tuwe.Ned:
769
- 2. CURRSMTLY AUTHORIZEO POWER LEVEL tMWti:
08860R ELECTRICAL RATING (MWe.Neet 789 N/A .
- 3. POWSR L8 VEL TO WHICH ResTR4iTED (IP ANY) (MWo. Nee:
4, REA000e8 POR RSSTRICTION tip ANY):
THIS MOstTM VR TO OAft CUMULATIVS 744.0 4862.2 113926.5
- 5. NUMSSR OP HOURS REACTOR WAS CRITICAL . . . . . . . . . . . . . . .
0.0 0.0 3421,9 _
- 8. REACTOR RESERVE SHUT 00WN HOURE . . . . . . . . . . . . . . . . . . .
744.0 4608.2 110066.4
- 7. HOUR 6 0tN ER ATOR ON LINE . . . . . . . . . . . . . . . . . . . . . . . . . .
0.0 0.0 000.?
- 8. UNIT RESSRV8 SHUT 00WM HOUR 8 . . . . . . . . . . . . . . . . . . . . . .
- 9. GROSE THERMAL ENERGY GENERATED (WWM) ............. 1435960 10464382 233805119
- 10. GR008 ELECTRICAL ENERGY GENER ATED (WWMI . . . , . . . . . , . . 450157 3389521 75g13093 427044 3231321 71134610
- 11. NET ELECTRICAL ENERGY GENERATED (WWM) ..,,..,,,,,,,,
11 ' E ACTOR SE RVIC E P ACTOR , . . . . . . . . . . . . . . . . . . . . . . . . . .
100.0 95.1 80.I
.0 95.1 82.5
- 13. R E ACTOR AV AILA slLITY P ACTOR . . . . . . . . . . . . . . . . . . . . . . . _
100.0 90.2 77.4
90.2 78.0
- 15. UNIT AV AILASILITY P ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . 100. 0 74.6 82.2 65.1
- 16. UNIT CAP ACITY P ACTOR tuelnE MOCl . . . . . . . . . . . . . . . . . . . . .
- 17. UNIT CMACITY P ACTOR tuumE 0sega MWel . . . . . . . . . . . . . . . . .
72.7 80.1 63.4
. 6.8 5,5
- 18. U NI T P ORC 8 0 0UT AG E RAT E . . . . . . . . . . . . . . . . . . . . . . . . . .
- 19. SHUTDOWN 8 SCH40UL50 CVER NEXT 4 WONTHS (TYPE. DATE. AND OURATION OF E ACHl
- 20. IP SHUT DOWN AT END OF REPORT PER:00. ESTIM ATED DATE OF STARTUP:
- 11. UNIT 3 IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION); PORECAST ACHIEV60 ,
INITI AL CRITICALITY INITIAL ELECTRtCITY -
COMMERCIAL OPERAT6081 1.1M
i APPENOlX C l OPERATING DATA REPORT l J
' 00CKET NO. 50-265 UNIT Tvn DATE August 9, 1988 COMPLETED SY Lvnne Deelsnyder TELEPHONE 309-654-2241 l
OPERATING 8TATUS 0000 070188 2400 073188 anogg sogngis napontino panicot 720
- t. REPORTING PERICO: f 769
- 2. CURRtMTLY AUTHORIISO POWGR LEVEL (Murt)? 2511 M AX. ORPtNO. CAPACITY (MWo Net):
OtslGN ELECTR6 CAL RATING (MWs.Nool W l N/A ,I
- 3. POWGR L8 VEL TO WH6CM RttTRICTIO (IP ANY) (MWeNeti:
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- 4. REASONS POR RESTRICTION (IP ANYl i f
THit MONTH VR TO DATE CUMULATIVE 3008.3 107665.4
- 5. NUMetR OF HOUR 8 REACTOR WA8 CRITICAL . . . . . . . . . . . . . . 56 7. 3 0.0 0.0 2985.8_
- 8. R EACTOR ROS8RV E SHUTDOWN MOUR8 . . . . . . . . . . . . . . . . . . . ;
2941.7 104477,L ;
- 7. MOUR8 GINER ATOR ON UNE . . . . . . . . . . . . . . . . . . . . . . . . . 5 5 5. 8 0.0 0.0 702.4 1
- 8. UNIT R ttlR VE SMUTDOWN HOURS . . . . . . . . . . . . . . . . . . . . . .
6224580 223595147
- 9. GROS 8 THERMAL INERGY Of NERATIO (WWH1 ............. 968550 2001600 71559384
- 10. GR088 ELECTRICAL ENERGY 08NER ATIO (WWM) . . . . . . . . . . . . 301041 1907322 67467347 I 11. Ntf rLICTRICAL ENERGY CINERAftD (WWH1 . . . . . . . . . . . . . 284596 58.9
- 12. P EACTOR SERVICE P ACTOR . . . . . . ................... 76.3 _ 76.2_
58.9 78.3
- 13. R E ACTOR AV AILAtluTY P ACTOR . . . . . . . . . . . . . . . . . . . . . . 7 6. 3
- 14. U NIT S E RV IC E P ACT OR . . . . . . . . . . . . . . . . . . . . . . . . . , , , , 7 4 . 7 _ 57.6 73.9 57.6 74.4 l 15. U NIT AV A I LA tl LITY P ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . 7 4 . 7 48.5 62.1 i 18. UNIT CAPACITY P ACTOR IUsintMOCl .................... 49.7
- 17. UNIT CAPACITY P ACTOR tuweg osop WWel . . . . . . . . . . . . . . . . 48. 5 47.3 __60.5
. .3 8.4
- 18. U N I T P O RC I D OUT AG E RAT E . . . . . . . . . . . . . . . . . . . . . . . . . .
, 19. SHUTDOWN 8 SCHGD'JLIO QVER Ntxt 8 WONTMllTYPt.DATE. AND OURATION CF EACHl:
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) M. IP SMUT 00WN AT END OP REPORT PERIOD. ESTIMAf tu OATE OF STARTUP.
~, 21. UNITS IN TEST ITATUS (PRIOR TO CCWWERCI AL OPERAT10N1; PQRECAST ACMitVSO .
INITI AL CRITICALITY INITIAL ELICTR6C1TY COMMSRCIAL OPSRAT1000 l
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APPEN31X 3 AVERAGE DAILY UNIT POWER I2 VEL l l
. j DOCKET NO. 50-254 UNIT ONE DATE ^"R""t 3' 1988 !
COMPLETED BY ivnne Deelanvder l TELEPHONE 309-654-2241 i yo g JULY, 1988 l
WER LEVEL DAY AVERAGE gPOWER12 VEL DAY AVERAGE gig 733 gy 203 1 _
716 g 229 i 2
' 227 3 13 749 327 4 gg 727 540 5 21 _
0I 647 0 23 I
525 745 1 n l g
4I3 72' I 24 g
314 g 698
- 277 g 680 10 gg 357 gy 758 482 766 II 3 705 y 759 13 760 g 703 -
14 o38 33 73g 18 294 16 l l
l INSTRUCTIONS On thts form, hat the averap daily ut.it power level in MWe Net for each day in the reporting month.Covnpute to the r.aaasst whole megawatt.
Thew figures will be used to plut a graph for cash reporting month.Nute Iliat when maximum dependable capacity is uwd tot the not ettetncal rstmg ut the umt, there may be owasions whern the daily averap powet letcl enceeds the 1001 lice (or the entn(ted power lesel hnc). In such c.aies. tha aver 4p duly unit power output sheet should be footnoted to captaisi the appetent anomaly.
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APPENOlX B AVERAGE DAILY UNrf POWER L2 VEL
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l DOCXET No. 50-265 UNIT m DATE August 3, 1938 COMPLETED BY 1vnne Deelanvder i TELEPHONE 309-654-2241 I
l MoptrH JurL 1988 DAY AVERAGE DAILY 19WER LEVEL DAY AVERAGE DAILY l9WER LEVEL (MWHet) (MWHet) g 537 gy 214 l 520 gg 236 g
230 3 it 521 315 4 M l 667 gg 542 l 5
g 755 639 22 655 676 7 -. 23 :
5 17 )
8 34 g 392 g _to 549 y _o j 10 466 y _g 11 13 578 , 7 13 716 39 -R .-
754 , .g .
14 gg 635 _to i 33 _
1 296 4 16 --- )
INSTRUCTIONS On this form, hst the average daily unit power level m MWeMt for each day m the aporting enonth. Compute to the
, twnaest whole megawatt, ;
These figures wal be used to plut a stoh for ca h reporting month. Nuie eiut whea nwtimum hpendabla upsetty a uwd for the tiet tiestncal rating ut the unit. there may be oscat:ons the . a. ply t=*ettu pew rf level tzetsds the 1003 hee for the rnithled [viwer lesel hne). In such cases, the aves s
- pcx; 11741 shtt< ahould te 1 foutnoted to e aplan the apparent anomaly, l.l H
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ID/SA APPENDIX D QTP 300-S13 UNIT $NUTDOWIIS AND FOWER REDUCTIOKS Revision 6 DOCKFT NO. 50-254 August 1982 13fl T 18Arli QUAD-CITIES UNIT ONE COMPIETED BY L. DEELSNYDER 1
DATE August 9 1988 REPORT MOIf118 JULY, 1988 TEIEF9100E 309-654-2241 s 5 g
.= 5 EU o
g$ . do gg g O LICElISEE = @$
NO. DATE s, EURATICIf E Sii EVEIIT $ $"
U (II0tRS) REPORT NO.
CORRECTIVE ACTICIIS/C0ffENTS 88-13 880707 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-14 880708 F 0.0 H 5 ZZ ZZZZ1Z Power Reduction Taken Due to High River Temperatures 88-15 880709 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-16 880716 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-17 880717 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures l
l APPROVED
.. AUG161982 l (final) yC.OSk
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1 ID/5A APITJIDIX D QTP 300-S13 UNIT $1RTTDOWISS AND POWER REDUCTIOIIS Revision 6 DOCKET NO. 50-265 August 1942 LBilT MAfE QUAD-CITIES UNIT TWO ColTIETED BY L. DEELShTDER DATE August 9. 1988 REPORT NOIITH JULY, 1988 TEIIPMOIIE 309-654-2241 h 5 g w
5 a C g- E!-
g g O h LICENSEE m@
g g"8 31 0 . DATE
% DURATICII g EVENT E" 5 O
(HOUltS) REPORT NO.
CORRECTIVE ACTIOffS/C0f9ENTS 88-7 880708 F 0.0 11 5 ZZ ZZZZZZ Power Reduction Taken Due to Hig's River Temperatures 88-8 880709 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-9 880716 F 0.0 11 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-16 8807I7 F 0.0 H 5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-11 880724 F 188.2 A 2 HA CENERA Reactor Manually Scramed Due to Main Generator Ground Fault 4
APPROVED
~ AUG161982
-I-(final) ygu3g
VI. UNIOUE REPORTING REQUIREMENTS ,
-The-following iteas are included in this report. based on' prior commitments to the commission:
A. MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.
B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND Tk'O 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 table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.
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I RESULTS OF SCRAM TI: LNG MEASUREWEUS .-
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PERF0ftED ON UNIT I & 2 CONTROL .
ROD DRIVES, FROM I-1-88 TO 12-31-88 l AVERAGE TIE IN SEC0feS AT % MAX. TIE l INSERTED FROM FULLY WIT N FOR 90%
INSERTION DESJtlPTION NLASER S 20 50 90 Technical Specification 3.3.C.1 &
DATE OF ROOS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 5-16-88 89 0.29 0.67 1.45 2.56 3.07 Unit 1. Hot Scram Timing A Sequence l (G-11) l 6-17-88 2 0.30 0.68 1.49 2.55 2.60 Unit 1 C-7 and P-7 Hot Scram Timing (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-11 Hot Scram Timed -
(P-11) accumulator work.
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VII. ' REFUELING INFORMATION 1
- 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 l
Station--NRC Request i'or Refueling Information", dated January 18, 1978.
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QTP 300-532. !
Revision 1 QUAD-CITIES MEFUELING March 1978 INFORMATION REQUEST s
- 1. Units 01 Reload: 9 Cycle: to
- 2. Scheduled 'dat's 'for next refueling shutdown: 6-10-89 i
- 3. Schsduled date for restart following refueling: 9-2-89 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled Information:date(s) for submitting proposed licensing action and supporting !
U MARCH 10, 1989 6.
Important licensing considerations associated with refueling, e.g., new or !
different fuel design or supplier, unreviewed design or performance analysir '
methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
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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: 1773 B. 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 assemelles:
-1
- a. Licensed storage capacity for spent fuel: 3657
- b. Planned increase in licensed storage: ,,,
0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 APPROVED APR 2 01973 Q. C, O. S. R.
- QTP 300-$32 Revision i QUAD-CITIES REFUELIN3 March 1978 INFORMATION REQUEST o
e
- 1. Unit 02 Reload: 9 Cycle: _ 10
- 2. $cheduled 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 tuchnical speelfication change or other license amendment:
SOT AS YET DETERMINED.
5.
scheduled information:date(s) for submitting proposed licensing action and supporting SEPTEMBER 2, 1989 6.
Important licensing considsrations associated with refueling, e.g., new or dif ferent 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 assemblles,
- a. Number of assemb!!es in core: 124
- b. Nu-ber of assemblies in spent fuel pool: l 1475 S. The present licensed spent fuel pool storage capacity and the size of any increase in licensed etorage capacity that has been requested or is planned 3 in number of fuel asse-biles:
- a. Licensed storage capacity for spent fuel: 3897
- b. Planned increase in licensed storage: 0 9.
The projected date of the last refuel!ng that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 3 j
APPROVED l APR 2 01078 Q.C.O.S.R.
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! 'VIII._' GLOSSARY 1
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.. ~ 1The- following abbreviationsewhich:may have been tised in the Monthly. Report. l are defined below: !
ACAD/ CAM - Atmospheric Containment Atmospheric Dilutton/ Containment Atmospheric Monitoring i ANSI - American National Standards Institute '
, APRt4 - Average Power Range Monitor ATHS - Anticipated Transient Without Scram
, BWR - Bolling Water Reactor !
CR0 - Control Rod Drive '
4 EHC - Clectro-Hydraulic Control System '
, EOF - Emergency Operations Facility !
GSEP - Generating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter l HPCI - High Pressure Coolant Injection System !
HRSS - High Radiation Sampling System ,
Integrated Primary Containment Leak Rate Test IPCLRT -
Ii<M - Intermediate Range Monitor :
ISI - Inservice Inspection
! LER - Licensee Event Report .
LLRT - Local Leak Rate Test '
, LPCI - Low Pressure Coolant Injection Mode of RHRS d
LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate >
- MCPR -
Minimum Critical Power Ratio i MFLCPR - Hallmum Fraction Limiting Critical Power Ratio ,
- PPC -
Maximum Permissible Concentration i MSIV - Main Steam Isolation Valve i NIOSH - National Institute for Occupational Safety and Health 4 PCI -
Primary Containment Isolation .
PCIOMR - Preconditioning Interim Operating Management Recommendations i RBCCW - Reactor Building Closed Cooling Water System RBM - Rod Block Monitor !
Reactor Core Isolation Cooling System RCIC -
RHRS - Residual Heat Removal System l RPS - Reactor Protection System j i RWM -
Rod North Minimizer ;
SBGTS - Standby Gas Treatment System i
. SBLC - Standby Liquid Control '
SDC - Shutdown Cooling Mode of RHRS SDV - Scram Olscharge Volume !
SRM - Source Range Monitor ;
TBCCW - Turbine Building Closed Cooling Water System ,.
TIP - Traversing Incore Probe !
TSC - Technical Support Center ;
0027H/0061Z
e ouad oit'rs Nuclear Power Station
- ' O Commonwealth Edison 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RAR J -36 July 27, 1988 Director of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D. C. 20555 Enclosed ,er your informat'on is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of July, 1988.
i Respectfully, 1 COMMONWEALTH EDISON COMFANY QUAD-CITIES NUCLEAR POWER STATION fR. A. Robe Services Superintendent RAR/vmk Enclosure Y
I 0027H/00612
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