ML19341A021
| ML19341A021 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/01/1981 |
| From: | Tubbs R COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19341A020 | List: |
| References | |
| NUDOCS 8101210465 | |
| Download: ML19341A021 (32) | |
Text
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J QUA'-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER 1980 COMMONWEALTH EDISON COMPANY AND.
IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 0101210
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l TABLE OF CONTENTS
- 1. Introduction
- 11. . Summary of Operating Experience A. Unit One B. Unit Two Ill. Plant or Procedur:e Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments '.o Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approvai D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data Vll. Refueling Information Vill. Glossa ry I
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- l. 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 Edison Company and lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The
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Architect / Engineer was Sargent & Lundy, incorporated and the primary con-struction contractor was United Engineers & Constructors. The condenser cooling method is a closed-cycle spray canal, ar.d the Mississippi River is the condenser cooling water source. The p! ant 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 critica11 ties 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 fo r Un i t Two.
This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 245 and 174.
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II.
SUMMARY
OF OPERATING EXPERIENCE A. UNIT ONE December 1-19: Continuation of End-of-Cycle Five Refueling Outage.
December 20-24: On December 20, the reactor was pulled critical at 0333 and the generator put on line at 1813 ending the Refueling Outage.
However, at 2110, the turbine was tripped off-line due to high vibration and was not back until 0150 on December 21. Load was in-creased until 150 MWe was reached at 0700, at which time scram timing was performed. On December 22 load was increased to 400 MWe and held ~
close to this level until on December 24 at 1640, when load was in-creased.
December 25-28: At 0236, the reactor scrammed on an APRM High-High signal caused by a Recirculation pump speed transient. The reactor was brought critical at 1427 and the generator put on line at 1443 on December 26. Load was then increased at various rates until 640 MWe was held at 1715 on Deceaber 28.
December 29-31: On December 29 a load of 646 MWe was held. The -
reactor scrammed at 0815 on December 30 due to a spurious low reactor vessel water level trip. The reactor was brought critical at 1346 and the generator put on line at 1725 Load was then increased ending the reporting period with a load of. 600 MWe increasing at 5 MWe/ hour.
B. UNIT TWO December 1-3: The unit began the reporting period holding an average load of 823 MWe, until 1350 on December 3 At that time, a reactor scram occurred from a Main Steam isolation valve closure scram signal which was caused by a spurious main steam line high flow signal.
December 4-6: The unit remained shutdown over this three day period to perform maintenance on the RHR System and various other items.
December 7-11: At :435, on December 7, the reactor was pulled critical only to scram at 1540 due to an IRM High-High signal caused by a pressure fluxuation while preparing to test an electromatic relief valve. The reactor was brought critical again at 1900 and the i generator put on line at 0245 on December 8. Load was increased at various rates until a load of 820 MWe was reached on December 11 at 0355 At 2327 the reactor scrammed due to a spurious main steam line low pressure signal which caused an MSIV closure.
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December 12-16: At 0615, on December 12, the reactor was brought critical and the generator was put on line at 1453 Load was increased
, at various rates until 550 MWe was reached at 0500 on December 13 On December 14, the control rod pattern was changed and the load was~
increased until 2036 on December 15 At this time, while at a load of 767 MWe, a tomb threat was received. A search was conducted, with no result, and the load increase was resumed at 2200. Load was held at 800 MWe on December 16, per an Administrative order issued as a consequence of the two previous unresolved spurious scram signals.
December 17-21: Dv?v this four day period, the ZA Recirculation Pump MG Set field brer w tripped on four separate occasions. Load was reduced to app .imately 360 MWe, the MG Set was restarted and load was increased antil 800 MWe was reached, or until the breaker tripped ~
again. Tha breaker tripped at the following date and times: December 17 at 0125; December 17 at 0457; December 19 at 1510; and December 21 at 1300.
December 22-26: Over this five day period an average load of 779 MWe was held.
December 27-28: In this two day period the 2A Recirculation Pump MG Set field breaker tripped three times with similar consequences as encountered previously. The breaker opened at 1020 on December 27, and at 1645 and 2250 on December 28.
December 29-30: Over this two day period an average load of 652 MWe was held with a derating due to the field breaker sporadic tripping problem.
December 31: On this last day of the reporting period load was dropped to repair 2A MG Set field breaker. After repairs were effected, load was increased ending the period at 732 MWe rising at a rate of 5 MWe/ hour.
Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications Amendment 61 to License DPR-29 On December 5, 1980, the NRC issued Amendment 61 to Unit One License DPR-29 This amendment provided Technical Specification changes related to startup and operation for Unit One Cycle 6. Minor editorial changes were also made.
Major changes were made as follows:
(1) FRP/MFLPD is now utilized to flow bias APRM rod block and scram t'ips, (2) Scram response time is reduc-d to 50 milliseconds.
t (3) New MAPLHGR curves are provided.
(4) TAF is 360" above vessel zero.
B. Facility or Procedure Changes Reauiring 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 safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
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UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q07289 CRD Accumulator Faulty disc. Water leaks by seat. Replaced disc, and Drain Valve lapped seat.
Q09464 RilR Test Return Loose connection Valve will not open with Remade loose connec-Valve (M0-I- on controller. control switch. '
tion and tested.
1001-36A)
Q09474 Suppression Faulty lug. Valve will not open. Replaced lug on C Chamber Test & Thermals keep tripping. Phase motor lead at Spray Valve (1- HCC; cable #12691; 1001-34A) tested.
Q09413 RHR Crosstle Bad contact. Auxiliary contact on Replaced control; tested.
Solenoid (M0 open coil bad.
1001-19B) .
Q09301 CRD H-12, 46-47 117 & 118 scram Rod does not sc' ram during Rebuilt 117 & 118 valves.
pilot valves had scram timing. Scram tested.
sticky operation.
Q08159 RilR H0-1-1001- Gears were worn Found bronze filings in Rebuilt motor operator 43B in the motor g rease . and installed on valve; operator. tested.
Q09425 Core Spray Pomp Dir+y contacts. Valve will not close Cleaned contacts; tested.
Disc Valve (1- from local station.
1402-24A)
Q09460 - Valve 1-1001-19B Loose connections. Valve will not close. Tightened connections at MCC; tested.
Q09465 Recirc Crosstle Misaligned con- Valve won't close with Realigned contacts on Loop Valve (MO- tacts. control switch. Thermals closing contactor;
_ l-202-98) keep tripping. tested.
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UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION i Q08090 RHR Valve (MO-l- Valve requires over- Valve sticks in seat Disassembled, cleaned <
1001-186A) hauling. ,. and requires 791 lbs. disk and guide. Re-to take of f seat. assembled; tested.
l Should not take over 440 lbs.
Q07817 SRM 21 Di sc rimi na, tor SRM 21 reading 100 cps. Adjusted voltage to 7 9 voltage out of No fuel in vessel. All VDC; tested.
. adjustment. Other SRMs downscale.
Q07457 80-21/03L MSiv (AO Worn seat and Failed Local Leak Rate Installed new disc, 203-10) disc. Test. pilot seat, lapped seat, welded case; tested.
Q07454 80-21/03L MSlV (AO-l- Vorn seat and Failed Local Leak Rate Lapped seat turned 203-2A) disc. Test. disc; tested.
Q07455 80-21/03L MSIV (AO Worn seat and Failed Local Leak Rate tapped seat turned 203-1B) disc. Test. disc; tested.
Q09339 80-21/03L MSIV (AO-l- Leaky valve. Failed Local Leak Rate Lapped disc and recut 203-1D) Test. the disc; tested.
Q07825 MSIVs 1-203- Updating limit Replace the la and 3a Replaced la and 3a I A. & IC & ID switches. limit switches with the on MSiv IA; replaced Snaplock model 740 type, 3a on MSIV IC;
- i. . and replaced seal tight replaced la & 3a on to these switches as MSIV ID; tested.
needed.
Q09447 1/2 Diesel Fuel filter was Change filter elements. Replaced fuel filters Generator Fuel plugged up. and tested.
Oil Filter 6602
UNIT y E MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER HUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q07824 All Inboard Switches needed Replace 2a & 2b limit Replaced limit switches MSIVs replacing. switches with the Snap- and fittings; tested.
l lock model 740 and replace seal.
Q09660 RHR Heat Faulty over load As valve closes, light Installed new overload l Exchanger Out- heater. ,
Indication goes out, then heater, taped motor lead let Valve back on when valve in motor operator limit ,
(H0-1-1001-5A) finishes closing. box; tested.
Q09615 Drywell Purge Speed control Valve did not close in Adjusted speed control Valve (AO out of adjustment. less than 10 seconds as valve; tested and timed. i 1601-21) required.
QO1005 Recirc Inboard Update solenoid Change ASCO or install Replaced solenold' valve; Sample Valve valve per NRC kit to ASCO valve to tested.
(AO-1-220-44) requirement. meet NP-l.
Q07867 MSIV Limit Switches needed Replace 2a and 2b switches Replaced limit switches Switches (1- replacing. with Snaplock model 740 and fittings; tested.
203-2A, 2B, and replace the seal 2C, 2D) tight.
Q07456 80-21/03L HSIV (AO Seat and disc Failed Local Leak Rate Lapped seat and turned 203-28) were not mating Test. disc. Replaced "E" &
p rope rl y. "0" ring; tested.
Q09617 Reactor Water Needs stroke reset. Valve closes in 59 Replaced one lug.
Cleanup Return seconds; should close in Reset valve limits; Valve (H0 30 seconds. tested.
1201-80)
UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION
.Q09795 Reactor Vessel Shims,needed Stabilizer readings Adjusted shims at Stabilizer (1-200) adjurting. were out of specifica- positions 2,3,9,14.
tions.
L Q09933 M0-1-1001-7B Faulty torque Failed test for WR Replaced switch.
switch. Q09699 Tested.
Q09873 Main Steam Jumper lift on Valve would attempt Removed jumper; testec Drain Valve between 3 and 34, to open with Group I (1-220-1) compartment D3, PCI signal present. . ..
, MCC 18-A.
Q09838 80/32-01T Drywell Steel Drilled holes in Install 2 machined installed plugs and Shell (1-1600) shell. plugs in drywell shell welded.
. to repair two 1/2 inch I
drilled holes.
, 009893 80/33-03L SBGTS Suction Valve operator Valve won't open. Adjusted interlock Valve (1-7503) contect out of contacts; tested. '
adjustment.
Q09457 Main Steam Valve operated hard Valve will not operate. Lubricated stem and Line Drain by hand. Continually trips adjusted; tested, inboard (1- breaker.
220-1)
Q08161 RHR HO Valve required Found bronze filings Rebuilt valve 1001-7B rebuilding. In grease. operator and tested.
Q09699 RHR M0 Faulty torque Valve opens only far Installed new torque 1001-7B switch. enough for dual in- switch; tested.
Ication.
UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q07481 RCIC Turbine Overspeed trip. Adjust overspeed trip Adjusted overspeed (1-1301) Needed adjustment. mechanism to allow trip.
trip to occur by 5600 rpm.
q09215 HPCI Speed Updating Replace plug-in Replaced plug-in Controller controller. ampli fier uni ts in amplifier units on lA and 2A amplifier IA and 2A boards; boards with new solid tested, state type.
Q09516 Target Rock Air leak. Investigate a leak at New solenoid valve Solenoid weep hole on top of installed in air (50-1-203-3A) valve when valve is line; tested.
open.
Q09211 HPCI Turbine Pinhole in Repair or replace Welded pinhole and (1-2302) cover. cover on HPCI stop installed on HPCI valve hydraulic Turbine; tested.
actuator.
Q09872 Off Gas Drain Solenoid pilot Valve would not close Rebuilt valve, re-Valve (AO valve was binding. on a Group i Main Steam installed; tested.
5408A) High Radiation signal.
Q07440 1A RHR Service Became too warm; Bearing needs to be Disassembled and in-Water Pump oil broke down. flushed out; turned spected bearing; Motor Bearing Cannot be drained gummy. replaced oil; tested.
- (1-1001-65A) out.
q08346 Hain Steam insulation on AC power plugs for Repaired broken in-Line Radiation conductors broken. monitors bad. sulation; tested.
Honitors (1-1705-2A r. B) ;-
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UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q09240 Electromatic Valve required Investigate high Rebuilt solenoid pump.
Relief Valve rebuilding. resistance across (1-203-3E) shorting bar on trip coII.
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UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q09599 Electromatic Faulty limit Valve does not show Replaced limit switches Relief Valve switches.. open Indication fo r and tested.
(2-203-3E) l switch in open position.
Q08781 Drywell-Torus Faulty Versa Valve requires about 30 Replaced Versa solenoid Vent to SBGT solenoid valve. seconds to start valve; tested.
(AO-2-1601-63) ,
closing. Once started, full close in less than 10 seconds.
Q09338 Reactor Recirc Leaky gasket Flange / bonnet leaking. Repumped flange with Suction Valve between valve Furmanite; tested.
(2-202-48) body and bonnet.
Q09654 RHR Pump (2- Worn beari'ngs. While running pump, it Replaced lower bearing 1002-B) started making noise on motor; tested, and smoking.
Q09578 80/33-03L RHR System Pinches wire Caused fuse to blow Repaired insulation; 2 Supply insulation on inhibiting auto ini- tested.
From Emergency Bus 24, Cubicle 1. tlat ion of "B" RHR loop.
Diesel.
Q09604 HPCI Test Dirty limit When closed valve has Cleaned limit switches; Return (MO switches. dual indication breaker tested.
2301-15) trips, goes hard on seat.
Q09611 2-1001-43A Faulty torque Valve will not operate; Replaced torque switch, keeps tripping the switch; tested.
thermals.
Q08531 IRM C. .ael 18 Faulty detector. Chassis spikes high and Replaced detector; high-high during startup. tested.
UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q09719 80/37-03L RHR Pump 2D-1002 Seal required Replace pump seal. Replaced scal; tested.
replacing.
Q08227 Core Spray Pump Uncalibrated Valve did not auto Calibrated PS-2-1464B; Minimum Flow- pressure switch. open when pump flow tested.
l d
bypass valve -
was reduced.
(2-1402-388) ,
Q09651 Recirc Pump Leaky gasket Water was leaking Repumped with Suction Valve between valve in drywell. Furmanite compound; (H0-2-202-4B) body and bonnet. tested.
Q09627 Electromatic Steam leaking past The relief valve The valve was replaced Relief Valve retainer plug.
would not open when with a rebuilt valve (2-203-3D) needed. and tested satisfactory.
Q09341 MSIV (AO-2-203- Faulty pilot. Valve will not close Changed 3 way pilot; IB) with TEST switch. tested.
Q05271 LPRh 48-33A Faulty connector. IPRM is spiking high. Replaced connector and
^
set in new current; tested.
l Q05278 LPRM 40-41A Faulty connector. LPRM reads zero. Replaced connector and set in new current; tested.
Q05276- LPRM 40-25A Faulty connector. LPRM reads zero. Replaced connector and set in new current; tested.
l
, UNIT TWO MAINTENANCE
SUMMARY
CAUSL RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUM 10N SAFE OPERATION PREVENT REPETITION 005275 LPRM 16-09B Faulty connector. LPRM reads zero. Replaced connector and
. set in new current; l tested.
Q05274 LPRM 40-09B Faulty connector. LPRM reads zero. Replaced connector and set in new current; tested.
Q09603 80/34-0IT HPCI Injection Faulty motor. Valve thermals trip Removed match off of Valve (MO-2-2301- when valve is opened. Unit I and replaced on
- 8) Unit 2; tested.
Q08614 LPRM 31-41D Connectors needed LPRM reads zero and Cleaned and checked cleaning, alarms downscale. both detector connector and cable connector; tested.
Q08613 LPRM 08-41A Connectors needed LPRM reads zero and Cleaned and checked cleaning. alarms downscale. both detector connector anc cable connector; tested.
Q05273 LPRM 24-09A Faulty detector LPRM is reading zero. Replaced detector connector. connector; tested.
Q08563 LPRM 40-25B Faulty cable LPRM reads zero and Checked power supply, connector, alarms downscale. detector connector, and replaced cable connector; test.ed.
w , m -7 -
_m m
UNIT TWO HAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT hALFUNCTION SAFE OPERATION PREVENT REPETITION Q08564 LPRH 40-25A Faulty cable LPRH reads zero and Checked power supply, connectori alarms downscale. detector connector, I and replaced cable connector; tested, q05497 LPRM 40-49C Faulty ca$le LPRM reads downscale. Checked de'ector connec to r.' connector and replaced cabic cennector; tested.
Q05496 LPRM 40-250 Faulty cable LPRM reads downscale. Checked detector connector. connector and replaced cable connector under
. vessel; tested.
l
l i
l IV. LICENSEE EVENT REPORTS Tho' following is a tabular summary of all license event reports for quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.
UNIT ONE .
Licensee Event Report Number Date Ti tle of Occurrence 80/32-01T 12-11-80 Holes drilled in Unit One Drywell
, 80/33-03L 12-17-80 SBGT Reactor Building Suction Valve failed -
to open UNIT TWO 4 80/33-03L 12-01-80 Automatic initiation I. of 'B' RHR Loop
! Inhibited 80/34-01T 12-03-80 HPCI MO-2-2301-8 valve failed to open l 80/35-03L 12-28-80 A0-2-2001-16 Isolation valve slow to close i
80/36-03L 12-03-C. Electromatic Relief Valve 2-203-30 would not open 80/37-03L 12-07-80 2D RHR pump bad seal
- 80/38-03L 12-10-80 2A Reactor Rectre pump trip 80/39-03L 12-30-80 RHR MO-2-1001-34A valve Inoperable
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 O
l
OPERATING DATA REPORT D OCKt:.1 Nu. 50-2T4 UNIT ONE DATE January 1, 1981 LOMPLETED BY- R-C-Tubbs-TELEPHONE 309-654-2241, ext.
- ,p -
OPERATING STATUS 0000 120180
-~ TER e p or tT6~g~p erWdT24 0 0~ 123i'8 0- ~Gr o ss h o u r s in reporting periodT 744
- 2. Currently authorized power level (Mut): 2511 Max. Depend capacity
-~~( MWe-Ne t )~: ' 769*-'D e s i~g n-~e re c t ric ol r o tTh g' TMWe~;-Ne t ) i 789' -~ ~- ~~
- 3. Power level to which restricted (if any)(Hue-Net): NA
- 4. Reasons for restriction (if any): ,
~~ Th~1 s M o r r gnUlotive
- 5. Number of hours reactor was critical 267.1 5992.2 60706,3
- 6. Reactor reserve shutdown hours 0.0 0.0 3421.9 77 H 'u. s~g e n e r~o t o r d h Tin e 219 _~8- 5842 7 57883.8 B. Unit reserve shutdown hours. 0.0 0.0 909.2
- 9. Gross thermal energy generated (MWH) 303389 11698107 116242088
~
10.-~ Gr oss elec trical energy generrited(MWH) 93007 3755853---~7737870 s
- 11. Net electrical energy generated (MWH) 83502 3441743 34857279
- 12. Reactor service factor 35.9 68.2 80.1 6 8 . 2 ~ ~ ~--- 8 4 76~~
13.~ Reactor o v ollob ili~t y~-~foctor 35 9
- 14. Unit service factor 29.5 66.5 76.4
- 15. Unit avoilobility factor 29.5 66.5 77.6 l ~ ~- T6. Un i t c op oc~iTV Toc t o r ~(Usin g Dis MWe~) 14.6 51.U 57 B i
! 17. Unit capacity factor (Using MDC) 14.2 49.7 58.3
- 18. Unit forced outoge rote 18.5 4.2 7.8 197Shu td owns ~schedu1Td o ver ne x t Thoinhs-(Type , Dote ,and Duro tion o f ecchT:
- 20. If shutdown at end of report period,estinated date of startup ____Na_________ _ _
IThe MDC nor be I m r than 769 Se dering periods of high anbiant tenperature due to the thermal perfernonce of the spray canal.
OPER ATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATE January 1, 1981
.__ ____._ __.. -~ CO MP LETED UY - R C Tubb s TELEPHONE 309-654-2241, ext.
p_______-_- _ _ _ _ _ _ _
OPERATING STATUS 0000 120180 G Rep or t ing perTodT240 0 123180- Gr'b s s- h o u r s in reporting per1od:
~~ -
744
- 2. Cufrently outhorized power level (Mut): 2511 Mox. Depend -capacity ~ ~ ~ ~ ~ ~ ~ ~ ' - - "
(MtJe-Ne t )T 769* De sign ~~Vrec tr IccT r o t ing' '(MWe;-Ne t ) : '789"
~
- 3. Power level to which restricted (if any)(MWe-Net): NA
- 4. Reasons for restriction (if any):
~ ~ ~ ~ - ~ - ~ ~ ~ ~ ~ - ~ ~ " ~ - - - - - - - - - - ' ~ - ~ ~ ~ ~ ~ ~ '~~ ~ ~ ~ ~ Th i s M o n t h '-'Yr '.~ t o ~Da t e ~ C u m u l o t i v e
- 5. Number of hours reactor was critical 647.1 5703.9 58832.8
- 6. Reactor reserve shutdowr. hours 0.0 0.0 2985._8
--- Ho u r s g e n e r a t o r on Tine ~ -
~619T7 6489.4 56281- 2
- 8. Unit reserve shutdown hours. 0.0 0.0 702.9
?. Gross thernal energy generated (MWH) 1331469 12184299 115200408
--- 10 . Gr oss e1~ec tricol- energ y gener~cted (NWH) -433391- -- 3858501--- 3672155i
- 11. Net electrical energy generated (MWH) 401447 3614427 34356952
- 12. Reactor service factor 87.0 64.9 78.6
~13. Reactor ovo1TobiTity factor
~
' - - - - ~ ~
87; 0-~ ~ 6 4 . 9 - '- ~ "-~ 8 2 6~
- 14. Unit service factor 83.3 62.5 75.2 15, Unit ovellobility factor 83.3 62.5 76.1 l
16".- Un i t' ^copac i t y Toc t oF TUsing Des .MWe )
~
7 0 2-- ' 53 5 59 /
- 17. Unit copocity factor (Using MDC) 68.4 52.2 58.2
- 18. Unit forced outage rote 16.7 8.3 9.2
' ~~ 19 ~. Sh u t'd o'wn s~ sch e d uled over next-~6 n o n t h s' tty p e'sDo t e , on d- ITu r o t i o n o f e o c hT:-~ --~
- 20. If shutdown at end of report period,estincted dote of startup NA I
- The ItDC nay be lower than 769 mit dering periods af high artient tenperature due 2e the thernal perfernance of the spray canal.
i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL a
DOCKET NO. 50-254 l
DATE January 1, 1981 COMPLETED BY R C Tubbs
~ ~ ~ -
~~~ TELEPHONE- 309-654-2241, Txt.
174 HONTH December 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
- 1. -14.8 17. -S.3
_9.____,____ .. g 3.
-1.3 -- . _ - _ . _ . - . _
- 19. -10.9
- 4. -6.2 20. -4.3
~ ' ~ ~3. -5.4 21. 1T2 ~4
- 6. -6.1 .
22, 253.7
- 7. -6.3 23. 341.8 U. -67 24. 3G9 7
- 9. _
-10.4 25. 37.6 _
- 10. -10.5 26, 61.8
-10T8 474.0
~
i1. 27.
- 12. -0.3 28, 580.5
- 13. -7.0 29. 615.5 f4. -6.5 30. 277.8
- 15. -8.3 31, 490.3 _
- 16. -6.7 INSTRUCTIONS ;
2n this fern, list the average jaily ' nit; power level in MWe-Net for each day in the reporting month. Compete to the 1 I
nearest whole negawatt.
These figerts Will be.ned to Jlst.a graph.for.eath. reporting renth..Nettthat_dhenactinn dependablttopacity.is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the itBI line (or the restricted power level line),In .soth cases,the average daily snit power setput sheet should be
- footnoted to explain the apparent anonaly l 1
l l APPENDIX U l AVERAGE DAILY UNIT POWER LEVEL J l _
DOCKET NO. 50-265
. - - - . _ - _ - - - - - 9 y g- _ 3 y 9 _ -- _ - - -- __.- ~
DATE January 1, 1981 COMPLETED BY R C Tubbs
_ _ _ _ . _._ __ .TELEP HONE-'309-654-2241,-~ex t .~ - ~ ~ ~
174 MONTH December 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ~
(MWe-Net) (MWe-Net)
- 1. 773.2 17, 611.9
. _ . - . . . _ . - - _ . . _ _ . - - ~ ~ ~
5 2 ~ ~ ~ ~~ ~ - ' ~ 7 B-~ ~ ~~~~ ~~~ 654'~9 ~ -~~ ~
- 3. 432.9 19, 645.4
. 4. -17.5 20, 711.9
_. 9_.____.__
- 6. -12.8 . 22. 751.8
- 7. -16.3 23. 704.8
- 6. 3 8 7 ~1 2 4--- ~~ ~ 7 HTO' 9.
615.8 25, 725.8
- 10. 669.2 26, 741.0
- 12. 120.9 28. 573.0
- 13. 516.5 29, 585.7 i
I ~4 -~~ ~ 487 7 30. 619- 2 l
15, 662.2 31, 576.3 lI 16, 738.9 lI i ~ INSTRUCTIONS-On this fernjlist the 1 erage daily snit power level in %-Net for each dap in the reporting month. Compete to the
' i
, nearest while negawatt.
.-- The<e figures will be ssed to plet_a graph.for.ecch reperting montheNote thatshen sozinen dependable ccpacitt_is used for the net electrical rating of the unit thtre may be occasions when the daily overage power level exceeds the
, 100% line (or the restricted power level line)3.In such cases,the average daily snit power output sher
- should be
- festnoted to explain the apparent aneraly P00RORSNL
(*\ '
(3 1 APPENDIX D QTP 300-S13 DOCKET NO. 50-254 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 March 1978 UNIT NAME Quad-Citles Unit One p
DATE January 1, 1981 REPORT HONTH December 1980. TELEPHONE 309-654-2241, eht. ll4 w 8 s
, m = Eu t 5 Ue 8 @ $ LICENSEE gg gg Co' DURATION $ p{3 " EVENT pg g8 NO. DATE (HOURS)
- y5g REPORT NO. *
- 8 CORRECTIVE ACTIONS / COMMENTS .
R 13 800831 S 474.2 C 4 RC FUELXX Continuation of End of Cycle Five Refueling Outage 14 801220 F 4.7 'A 5 HA TURBIN Turbine tripped off line due to high vibration 15 801225 F 36.1 A 3 CB XXXXXX " actor scrammed by APRH Hi-Hi due to recirculation pump speed transient 16 801230 F 9.2 A 3 IA INSTRU Reactor scrammed on spurious reactor vessel low water level signal
-l-(final)
(3 l ( '*) \
l i
APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revisio, 5 DOCKET NO. 50-265 March 1978 l
UNIT NAME Qu d-Cities Unit Two COMPLETED BY R C Tubbs DATE January 1, 1981 REPORT HONTH December 1980.
' TELEPHONE 309-654-2241,
- e'x t . 174 w 5 s
= = Eb x 5 Ee 8 8 $ LICENSEE pg gg 5{3" C '
DURATION $
EVENT *8 g3 NO. DATE (HOURS) y g ,= REPORT NO.
- 8 CORRECTIVE ACTIONS / COMMENTS '.
R 23 801203 F 108.9 A 3 lA INSTRU Reactor scram due to spurious main steam line high flow signal which caused an MSIV closure
~
24 801211 F 15.4 A 3 IA INSTRU Reactor scram due to spurious main steam line low pressure signal which caused an MSIV closurre 25 801217 F 0.0 A 5 CB CKTBRK Power reduction due to spurious tripping of 2A Recirculation Pump HG Set field breaker 26 801227 F 0.0 A 5 CB CKTBRK Power reduction and derating due to spurious tripping of 2A Recirculation Pump HG Set fleid breaker f
(final)
l VI. UNIQUE REPORTING REQUIREMENTS 1 1
l The following items are included in this report based on prior commitments to the commission:
A. MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation. ,
VALVES NO. & TYPE PLANT DESCRIPTION UNIT DATE ACTilATED ACTUATIONS CONDITIONS OF EVENTS RX PRESS 2 12-03-80 2-203-3A 3 Automatic 1115 opened to 2-203-38 1 Manual 1100 Control Rx 2-203-3C 2 Manual 1100 Pressure after 2-203-3D Failed to 1100 Group I Isola-Open tion and scram 2-203-3E I Manual 1100 2 12-03-80 2-203-3D 1 Manual 400 Low pressure test after failed to open 2 12-07-80 2-203-3D 1 Manual 350 Test after failed to open on 12-03-80 (replaced valve) 1 12-20-80 1-203-3A 1 Manual 400 Surveillance T.S.
1-203-3B 1 Manual 4.5.D.I.b.
1-203-3C 1 Manual (Refueling Outage 1-203-3D 1 Manual Startup) 1-203-3E I Manual B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifica-tions 4.3.C.I. 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.
l
o, . -
RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT ONE CONTROL ROD DRIVES, FROM l-1-80 TO 12-31-80 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%
Insertion DESCRIPTION
. NUMBER S 20 50 90 Technical Specification 3.3.C.i &
DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Tie 12-1 177 0.25 0.48 0.98 1.73 F-6 1.87 Cold Scram Timing Prior to Unit One Cycle 6 12-22 177 0.30 0.69 1.50 2.63 M-13 3.33 Hot Scram Timing Unit One Cycle 6 l
t
- c. ,. .
Vll. REFUELING INFORMATION .
The following information about future reloads at quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rom D.E. O'Brien to C. Reed, et. al., titled "Dresden, Quad-Cities, and Zion Station - NRC request for refueling information" dated January 18, i 1978.
1 e
8 i
] !
I j
\.
3.; l l
c- . . QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978
(..
- lNFORMATION REQUEST
- 1. Unit: 1 Reload: 6 Cycle: 7
- 2. Scheduled date for next refueling shutdewn: 9-12-82 (Shutdown EOC6) 3 Scheduled date for restart following refueling: 12-5-82 (Startup BOC7)
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license an.ancment: No, Plan 10CFR50.59 reloads for future cycles of quad Cities Unit 1. The review will be conducted in August, 1982. -
5 Scheduled date(s) for submitting proposed licensing action and supporting information: August, 1982 for 10CFR50.59 related changes r- 90 days prior to shuceern.
.6. Important liceraing censiderations 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:
New fuel designs:
9 k
7 The number of fuel assemblies.
- a. Number of assemblies in core: 724
- b. Number of assemblies in spent fuel pool: 820
- 8. The present licensed spent fuel pool storage capacity and the size of any t increase in licensed storage capacity that has been requested or is planned
- j in number of fuel assemblies
l1 ~
ll a. Licensed storage capacity for spent fuel: 1460 l
l b. Planned increase in licensed storage: None i 9 The projected date of the last refueling that can be discharged to the
- spent fuel pool assuming the present licensed capacity: Seotember, 1985 (end of batch discharge capability)
!l
{*- XPPROVED
. APR 2 01978 Q.c.c.S.R.
. 1 .
- c. - .
qTP 300-532 Revision 1
,f-. QUAD-CITIES REFUELING March 1978
( - -
INFORMATION REQUEST
- 1. Unit: 2 Reload: 5 Cycle: 6
- 2. Scheduled date for next refueling shutdewn: 8-30-81 (Shutdown ECCI; 3 Scheduled date for restart following refueling: 12-20-81 (Startuo SCC 6)
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: No, Plan 10CFR50 59 Reloads for future cycles of Quad Cities Unit 2. The review will be coneasted by early August, 1981.
5 Scheduled date(s) for submitting proposed licensing action and supporting
. Information: Early August, 1981 for 10CFR50.59 relate 1 -hanges -s90 days prior to shutdown.
- 6. Important Ticensing considerations associated with refueling, e.g., tsw or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
New Fuel Design: 1. Barrier Fuel
- 2. Control Cell Core
[,
rl7'- _ _
7 The number of fuel a.ssemblies.
- a. Number of assemblies in core: 724
- b. Number cf assemblies in spent fuel pool: 672
- 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: 1460
- b. Planned increase in licensed storage: None l 9 The projected d::e of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: Seotember, 1984 (End of batch discharge capability) l
(-
w A. ' P P R O V E D l 1 APR 2 01973 l
C3. C:. C). 55. R.
l
Vill. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
CRD -
Control Rod Drive System SBLC -
Standby Liquid Control System MSIV -
Main Steam Isolation Valve RHRS -
Residual Heat Removal System RCIC -
Reactor Core isolation Cooling System HPCI -
High Pressure Coolant injection System ~
SRM -
' Source Range Monitor IRM -
Intermediate Range Monitor LPRM -
Local Power Range Monitor APRM -
Average Power Range Monitor TIP -
Traveling incore Probe RBCCW -
Reactor Building Closed Cooling Water System TBCCW -
Turbine Building Closed Cool?ng Water System RWM -
Standby Gas Treatment System HEPA -
High-Efficiency Particulate Filter RPS -
Reactor Protection System IPCLRT -
Integrated Primary Containment Leak Rate Test LPCI -
Low Pressure Coolant injection Mode of RHRS RBM -
Rod Block Monitor .
BWR -
Bolling Water Reactor ISI -
Inservice Inspection MPC -
Maximum Permissible Concentration PCI -
Primary Containment Isolation SDC -
Shutdown Cooling Mode of RHRS LLRT -
Local Leak Rate Test MAPLHGR -
Maximum Average Planar Linear Heat Generation Rate RO -
Reportable Occurrence DW -
Drywell RX -
Reactor EHC -
Electro-Hydraulic Control System MCPR -
Minimum Critical Power Ratio PCl0MR -
Preconditioning interim Operating Management Recommendations LER -
Licensee Event Report ANSI -
American National Standards Institute NIOSH -
National Institute for Occupational Safety and Health ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ATWS -
Anticipated Transient Without Scram SDV -
Technical Support Center EOF -
Emergency Operations Facility HRSS -
High Radiation Sampling System GSEP -
Generating Stations Emergency Plan i
l l
- .. --