ML20154G226
| ML20154G226 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/31/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RAR-888-42, NUDOCS 8809200289 | |
| Download: ML20154G226 (23) | |
Text
. _ _ _
r QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1988 COMMONNEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY r
NRC DOCKET NOS. 50-254 AND 50-265 e
LICENSE NOS. DPR-29 AND DPR-30 i-l l
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TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two
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III.
Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance l
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 A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements i
i A.
Main Steam Relief Valve Operations t
B.
Control Rod Drive Scram Timing Data VII.
Refueling Informattor.
i VIII.
Glossary l
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INTRODUCTION i
Quad-Cities Nuclear Power Station is composed of two Bolling Water Reactors, each with a Maximum Dapendable Capacity of 769 MWe Net, located in
- ordova, Illinois. The Station is jointly owned by Commonwealth Edison C
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, Incorporatea, 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 critica11tles for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial 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 L
number 309-654-2241, extensions 2240 and 2185.
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One Unit One began the month of August operating in Economic Generation Control (ECC). At 0827, the unit was taken off of EGC and at 1200, a load reductior.
was taken to 200 MWe due to high river temperatures.
Between August I and 9, power levels fluc*uated because of high river temperatures. On August 9, at 0100, a load reduction was taken to 200 MWe at the request of the thicago Load Dispatcher.
From August 10 to 14, the unit operated at full power.
On August 14, at 0215, a load reduction to 651 MWe was taken at the request of the Chicago Load Dispatcher. On August 15, at 0545, a load decrease was taken to 200 MWe due to high river temperature.
Power levels fluctuated on the sixteenth and seventeenth, and then were held constant at approximately 230 MWe until August 20.
Ietween August 20 and 24 power levels were adjusted at the request of the Chicago Load Dispatcher. On August 24, at 0903, 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.
B.
Unit Two Unit Two began the month of August still in the shutdown mode due to the main generator ground fault occurring at the end of July.
Investigations were made into the problem and repairs were performed until August 11 when the mode switch was placed in REFUEL. On August 14 at 0830, the mode switch was placed in STARTUP.
Control rod 1,atterna were adjusted and the reactor became critical at 1133. At 1900, the mode switch was placed in RUN. On August 15, ut 0251, the generator was synchronized to the grid, 200 MWe was reached at 0500. Power levels wece held constant due to high river temperatures until August 16 when load was increased to 650 MWe.
On August 17, at 2055, a load reduction was taken to 200 MWe due to high river temperatures and held constant until August 20.
At 0720, an ascent to full power was begun.
700 MWe was reached at 1245 and held constant due to high river temperature.
For the remainder of the month the unit operated near full power with power level adjustments made at the request of the Chicago Load Dispatcher and routine curveillances were performed.
0027H/00612
III.
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Spicifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.
P.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.
Tests and Experiments Re_ quiring 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.
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UNIT 1 MAINTENANCE
SUMMARY
l WORK REQUEST NO.
Q61813 LER NUMBER:
87-024 COMPONENT: System 0020 - Repaired drywell steel connection per ECN QC-87S-20.
CAUSE OF MALFUNCTION: Cause of malfunction was due to inadequate verification of the as-built configuration against design drawings during original construction.
RESULTS & EFFECTS ON SAFE OPERATION: Sargent & Lundy performed an analysis j
thst revealed 13 connections not meeting FSAR design requirements but were meeting operability requirements. Therefore safety implications were minimal.
ACTION TAKEN TO PREVENT REPETITION:
Immediate corrective action was to repair the 13 connections under engineering change notices QC-87S-24 and 27. To prevent reoccurrence, the Eugineering department now requires a dimensional verification for all safety related verifications under the modification program as of April, 1987.
WORK REQUEST NO.: Q62057 LER NUMBER:
87-16 COMPONENT:
System 2000 - Cleaned and lapped seats and disc on 1-2001-4.
CAUSE OF MALFUNCTION: This malfunction was caused by dirt and corrosion products in the process line being transferred to the valve seat.
RESULTS & EFFECTS ON SAFE OPERATION: Leakage limit in this event has minimal safety consequences since the total le.kage determined does not represent a probable leakage from the primary containment during accident conditions.
ACTION TAKEN TO PREVENT REPETITION: Valve (2001-3 and 4) seats were cleaned and lapped. Also, the disc was ground on valve 2001-4. Previous failures of these valves have initiated Action Item Record No. 88-29 to determine a more suitable type of valve for this application.
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WORK REQUEST No.: Q62058 LER NUMBER 87-16 COMPONENT System 2000 - Cleaned and lapped seats on 1-2001~,.
CAUSE OF MALFUNCTION: This malfunction was caused by dirt and corrosion products in the process line being transferred to the valve seat.
RESULTS & EFFECTS ON SAFE OPERATION:
Leakage limit in 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 REPETITION: Valve (2001-3 and 4) seats were cleaned and lapped. Also the disc was ground on valve 2001-4.
Previous failures of these valvea have initiated Action Item Record No. 88-29 to determine a more suitable type of valve for this application.
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UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST NO.: Q58943 LER NUMBER: N/A COMFONENT:
System 2300 - Rem'oved old HPCI steam trap, 2-2301-1, and reinstalled new trap and piping.
CAUSE OF MALFUNCTION: This deviation report was not written due to a malfunction, j
but to document a planned evolution.
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RESULTS & EFFECTS ON SAFE OPERATION:
Since no malfunction occurred, there were no results or effects on safe operation.
ACTION TAKEN TO PREVENT REPETITION: There was like-for-like replacement of the steam line drain trap 2-2301-1 and associated piping.
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IV.
LICENSEE EVENT REPORTS The following is a Abular summary of all licensee event reports for Quad Cities Units L..a 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 :he Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title cf Occurrence 86-010 6-14-88 Nylon butt splices in PAM instruments88-012 8-7-88 1/2A SBGT high flon 88-013 8-22-88 1A Core Spray Room Cooler inoperable / making RCIC inoperable 88-014 8-24-88 HPCI steam high flow outside Tech Specs Unit 2 88-025 8-23-88 HPCI isolation during preparation for special test 0027H/00612
V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 0027H/0061Z
APPENOlX C OPERATING DATA REPORT 00CKETNO.
50-254 UNIT ONE DATE September 9, 19d8 COMPLETED ilY T.vnne Declanyder l
TELEPHONE 309-654-2241 OPEf4ATING STATUS 0000 080188 744 2400 083188 QNott HOUR 8 IN REPORTINS PSRIOJ:
- 1. RSPORTifee P8miOO:
2511 MAN. OSPONO. CAPACITY (MWe40sel, 769
- 3. CURRtNTLY AUTHORIEGO POWGR LEvik (y9 08000M iLICTRICAL RATING IMusteesels
- 3. POW 9A LSVGL TO WHICH RAITRICTS0 IIP ANY1(Ml4 Noelt N/A
- 4. REA00est POR RSITRICT6088 llP ANY11 THit MO8tTH VR TO Daft CUMULATIVE L NUMetR OF HOURS REACTOR WAS CRITICAL.............. 744. 0 5606.2 114670.5 00 0 0-3421.9 -
- 4. R EACTOR A SSERVE SMUTOOWN HOURE...................
- 7. MOUR6 00 N E R ATOR 088 U NE......................... 7 4 4. 0 5152.2 110810.4 00 0.0 909.2
- 8. UNIT R ett RV E SMUTDOWN HOURE......................
............. 1337086 11801468 735142225
- 9. OR000 THERMAL ENERGY GENtR AT80 (WWM) 415514 1805015 76228537 p
- 10. CRott ELICTRICAL ENERGY OENER Af t0 (WWMI.............
393813 3625134 71528423 I
- 11. htf fLICTRICAL ENERGY QiNER ATED (WWM)
..,100.0 95.8 80.2
95.8 82.6
- 13. R E ACT O R AV AI LA tl u T Y P ACTOR...................... 10 0. 0 91.4 77.5
- 14. UNIT l8 RVIC E P ACT OR............................. 10 0. 0 91.4 78.2
- 14. Ut44T CAP ACITY P ACTOR lueenG MOCl.....................
67.1 78.5 61.4
- 17. UNIT CAP ACITY P ACT0R lum osowi uvent.................
0.0 5.9 5.4 S L UNI T P ORC 0 0 0UTA44 RAf t..........................
J it. SHUT 00WN4 SCHEDULE 0 0VER NtxT 8 MCNTH8 lTvF1. DATE. ANO DURATION OP EACHit
- 20. IF SMUT DOWN AT IN0 0P REPORT PERICO d5TlWAf t0 CATE OF STARTVP.
- 31. UNITS IN YtET STATVS INil0A TO COWWERCIAL OPERATIONl; PORICAST ACHIEVED IN4TI AL CRITICAUTV f
INITIAL ELECTRICITY COMMEPCS AL OPG RAT 1000 t
1.1 M 1
,WENDIX C OPURATING DATA REPORT OOCKET NO.
50-265 UNIT TWO DATE September 9, 1988 COMPLETED BY fvnne Deelsnyder l
TELEPHONE 309-654-2241 OPERATING STATUS 0000 080188 744 2400 083188 GROSS HOURS IN R0 PORTING PERICO:
- 4. M0 PORTING PGR600:
769
- 2. CURRtNTty AUTHORitt0 POWGR LEVEL (tagelt 2511 M Ax. ORPgNO. CAPACITY (Mues.Neel M
08860M OLSCTRICAL RATING (Mut>Neel:
N/A
- 3. POWSR LIVOL TO WM*CH ROSTRICT80 (IP ANY) (Mut>Neel:
- 4. RSASONS POR RESTRICTION llP ANY1:
THIS MONTH YR TO Daft CUMULATIV3
- 5. NUM00R OF HOURS RSACTOR WA8 t,RITICAL.............. 4 20. 5 3428.8_
108085.9 0.0
- 0. 0_
2985.8
- 8. REACTOR Res4RVE Shut 00WN hours...................
- 7. H0048 6ENER ATOR ON LING......................... 4 0 5. 23346'9.
1048R2.2 0.0 0.0 702.9
- 8. UNIT R ESGRVs SMUT 00WN HOUR $.......................
............. 787867 7012447 224383014 R, OR008 THERMAL ENERGY GENER ATIO (WWM) 2245901 71803685
- 10. OR008 ELECTRICAL ENERQY GENER ATIO (WWM)............ 2443L
- 11. NIT ELECTRICAL ENERQY QENERATED (WWMI............. 229610 2136932 67696957 56.5
- J 76.1
56.5 58.6 78.2_
- 13. R E ACTOR AV AILA tiLITY P ACTOR.......................
54.5 57.2 73.8
54.5 57.2 i
- 15. UNif AV AILAtit.lTY P ACTOR..........................
74.3, 40.1 47.5 62.0 it. UNIT CAPACITY P ACTOR (Veg MOCl.....................
39'I "b.3_
60.4
- 17. UNIT CAPACITY P ACTOR tuwiE Osop wWel.................
45.5 16.8 8.7_
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- 14. UNIT PORC8 0 0uT A4E AAf t..........................
- 19. SMUTOOYMS SCH49WL50 0VER NEXT 4 uCNTH8 tTYPt. 0 ATE. ANO DURATION OP (ACMI:
- 11. UNITS IN TEST STATVS (PRIOR TO COMMERCI AL OPERATIONI; FORECAST ACNIEVIO i
INITI AL CRITICALITY INITIAL ELECTRtCITY COMMERCIAL UPGRAT10N l.16 9
APPENDIX 3 AVERAGE CAlLY UNIT POWER LEVEL DOCKET No.
50-254 UNIT ONE J
DATE September 9,1988 COMPLETED BYIvnne Declanvder TELEPHONE 309-654-2241 W NTH AUCt's T - 94 A A DAY AVERAGE gggWER LEVEL DAY AVERAGE DgPOWER LEVEL 500 461 q
gy 372 203 2
gg 398 325 3
264 497 4
gg I94 604 5
M 184 639 g
g 187 581 7
3 3
269 24 819 692 372 g
g 671 710 gg g
786 27 721 gg 730 g
648 12 703 72%
g3 3
679 721 14 g
446 y
711 g
445 14 INSTRUCTIONS On this forra, hat the awrega daily unit power level in MWe Net for each day m thc reporting month. Compute to the nessest wh >ie reegawatt.
Thew figuret will be used to plut a graph for ca.h reportang month. Note that when masamum dependable capacity a weed tot the net tiestncal rating ut the unit. there may be owmons when the daily aurage power levci exceeds the 100A lee (or the rattweed powet Icsel hac). In such cases, the aurage d.uly unit power output sheet should be fowmoted to c spha the appatest anomaly.
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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
sn-96s UNIT n'o
)
DATE Sept mber 9, 1988 COMPLETED BY tvnno neeinnvder TELEPHONE 309-654-2241 MO M AucOST. 1988 DAY AVERAGE DAI.I,Y.MWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mm eO (a:WeNee)
-9 459 1
gy
-8 203 3
gg
-6 3
gg 33n
-6 4g4 4
gg
-5 s
21 59'
-5 g
g 667
-5 y
23 656
-1 720 g
24 g
-2 3
7e 751
.-5 g
gg
-9 697 11 21
-8 13 3
669
-10 13 3
66R "I3 14 N
733 718 186 99 g
421 gg INSTRUCTIONS On this foten, hat the averop dady umt power level m MWeNet for each day m the reponmg month, Compute to the nea.sst wie atlawatt.
These figures will be used to plot a grnh for cash reporting month. Nute th4t when masamum dependable capacity is und for the nel tiestncal rating ut the unit, these miy be ossmons when the daily avetop power levtl esteeds the 1003 hee toe the rntncted power tciel hinct in s'.ch cases, the average duly urut powet output sheet shodd be toutaeted to e aplan the 4ppstent anomaly.
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1 C/5A APPENDIX D QTP 300-S13 12flT $P!';fDOWS AND PotER REDUCTIostS Revision 6 DUCEET NO.
50-254
- p. gust 1982 IAflT NAtE OPAD-CITIES INIT O.E CUffLETED MT
- 1.. Deelsnyder DATE September 9. 1988 REPORT It00f7N AUGUST. 1988 TEIIPIWIE 309-654-224I w
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NO.
DATE (NOURS)
REP 00tT No.
u enmarCTIVE ACTIOsts/C009ENTS I
88-18 880802 F
.0 H
5 ZZ ZZZZZZ P er Reduction Taken Due to High River Temperatures 88-19 880804 F
0.0 H
5 ZZ 7'/ 77'/7 Power Reduction Taken Due to High River Temperatures 88-20 880805 F
0.0 H
5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures 88-21 330815 F
0.0 H
5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatur(s 88-22
,830818 F
0.0 H
5 ZZ ZZZZZZ Power Reduction Taken Due to High River Temperatures APPROVED AUG161982 l. (final) yno3x 6
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ID/5A APPEaWII D QTP 300-S13 tallT SMffD0tAIS AND F0tER EEDUCTICIIS Revision 6 DOCKET No.
50-265 August 1982 LaflT MAME QUAD-CITIES L* NIT TWO CO WIETED BY L. Deelsnyder i
DATE September 9 1988 REPORT HOIfTM AUGUST, 1988 TEI2PMOOK 3M-654-2241 l
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2 LIrm ar og gg g
DLEATICII 3
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No.
DATE OIOURS)
RLW NO.
u rnaaFCTIVE ACTICIIS/COMENTS 88-11 880801 F
338.8 A
4 HA CENERA Main Generator Ground Fault 88-12 880818 F
0.0 H
5 ZZ ZZZZZZ Fower Reduction Taken Due to High River Temperatures 7
I APPROVED I
AUG161982
- (final)
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i VI. UNIQUE REPORTING REOUIREHENTS
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The following items are included in this report based on prior commtements to the commission:
A.
MAIN STEAM RELIEF VALVE OPERATIONS
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There were no Main Steam Retief Valve Operations for the reporting period.
t B.
CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO I
The basis for reporting this data to the Nuclear Regulatory Commission
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are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.
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The following table is a complete summary of Units one and Two Control 4
Rod Drive Scram Timing for the reporting period. All scram timing was l
performed with reactor pressure greater than 800 psig.
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i RESULTS OF SCRAM TCING EASUREMENTS E
PERF0fBED ON UNIT 1 5 2 CONTROL
-i ROD DRIVES. FROM I-t-88 TO 12-31-88 4
AVERAGE T!bE IN SECOIOS AT %
MAX. Tite Ib INSERTED FRubi FULLY WITIGIAWN FOR 90%
l INSERTION DESCRIPTION pamFR 5
20 50 90 Technicai Specification 3.3.C.1 &
DATE OF ROOS 0.375
_O.900
?.00 3.5 7 sec.
3.3.C.2 (Aversge Scram insertion Time) 5-16-86 89 0.29 0.67 1.45 2.56 3.07 Unit 1. Hot Scram Timing A Sequence (G-11) 6-17-88 2
0.30 0.68 1.49 2.55 2.60 iTait 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 Hot Scram Timing (H-5) 7-2-88 1
0.29' O.63 1.35 2.36 2.36 Unit 2. P-11 Hot Scram Timed after (P-11) accumulator work.
8-24-88 1
0.27 0.63 1.40 2.47 2.47 Unit 2. B-8 Hot 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-11 Hot Scram Timed atter l
(F-11) accumulator work. Q69472 j
0027H/0061Z 1
A' VII.
REFUELING {NFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from O. E.
O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Informction", dated January 18, 1978.
0027H/0061Z
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QTP 300-532, Revision 1 QUAO CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
01 Reload 9
Cycle:
to 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 specificatico change or other license amendpunt:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting in forma tion:
MARCH 10, 1989 6.
Important IIcensing e.onsiderations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance acalysis methods, significant changes In fuel design, new operating procedures:
NONE AT PRESENT TIME.
7.
The number of fuel assemblies.
a.
Nurber of assemblies in core:
72a b.
Number of assemblies in spent fuel pool:
1773 3.
The present licensed spent fuel pool storage capacity,nd 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:
1657 b.
Planned increase in licensed storage:
0 9.
The projected date of the last refueting tnat can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 APPROVED APR 2 01978 Q.C,O.S.R.
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QTP 300-532 Revision I QUAD-CITIES MEFUELING March 1978 INFORMATION REQUEST 1.
Unit:
02 Reload:
9 Cycla:
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 amendment:
NOT AS YET DETERMINED.
5.
Schecuted date(s) for submitting proaosed licensing action and supporting informa tion:
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, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7.
The number of feel assemblies.
4 Number of assemblies in core:
7 2 *,
b.
Nu-ber 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 requested or is planned in number of fuel assemelles:
a.
Licensed storage capacity for spent fuel:
3897 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: ;008 APPROVED APR 2 01078 C). c: C). S. R.
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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Repoii, are defined below:
Atmospheric Containment Atmospheric Dilutton/ Containment ACAD/ CAM Atmospheric Monitoring American National Standards Institute ANSI Average Power Range Monitor APRM Anticipated Transient Without Scram ATWS Bolling Water Reactor BNR Control Rod Drive CRD Electro-Hydraulle Control System EHC Emergency Operations Facil1ty EOF Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter i
HEPA High Pressure Coolant Injection System HPCI High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRN Inservice Inspection ISI Licensee Event Report LER LLRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI 4
Local Power Range Monitor LPRM Maximum Average Planar Linear Heat Generation Rate l
MAPLHGR Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR MPC Maximum Permissible Concentration Main Steam Isolation Valve MSIV Natlodal Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIONR Reactor Building Closed Cooling Water System RBCCW RBM Rod Block Monitor l
RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHRS i
Reactor Protection System RPS RNM Rod Worth Minimizer Standby Gas Treatment System SBGTS Standby Liquid Control 58LC Shutdown Cooling Mode of RHRS l
SOV Source Range Monttor SRM Turbine Building Closed Cooling Water System TBCCW Traversing Incore Probe TIP Technical Support Center TSC i
0027H/00612
- - - - - ~. - - - - - -, -
e Commonwealth Edison ound Cities Nuclear Power Station 22110 206 Avenue North Cordova, Illinois 61242 Telephone 309/654 2241 RAR-88-42 August 31, 1988 Director of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Hall Station P1-137 Wasnington, D. C.
20555 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 August, 1988.
Respectfully, COMMONNEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R.A,liSbey R. A. Robey Services Superintendent RAR/vmk Enclosure d
gG 0027H/00612 l I i