ML19209C611
| ML19209C611 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/02/1979 |
| From: | Hannum D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19209C607 | List: |
| References | |
| NUDOCS 7910160483 | |
| Download: ML19209C611 (25) | |
Text
.
QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1979 -
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. OPR-29 and OPR-30 1168 002 7910160 L(T3 j'
TABLE OF CONTENTS
- 1. Introduction
- 11. Summary of Operating Experience A. Unit One B. Unit Two 111. Plant of Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Ammendments 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. License 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 Vlti. Glossary 1168 003
- 1. 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 Commonwelath Edison Company and lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Inc. and the primary construccion contractor was United Engineers & Constructors. The condenser cooling method is a closed-cycle spray canal, and 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 1 and 2 resoectively were October 18, 1971 and April 26 1972. Commercial generation of power began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.
This report was compiled by David Hannum, telephone number 309-654-2241, ext. 179 1168 004
- 11.
SUMMARY
OF OPERATING EXPERIENCE A. Unit One September 1: Unit One began the reporting period operating at 800 MWe.
September 2: Load was reduced to 700 MWe for weekly turbine testing.
September 3: Load was reduced to 450 MWe due to low system demand. The main condenser flow was reversed.
September 4-5: Load was increased to 800 MWe and held steady.
September 6: Load wa' r, educed to 500 MWe for main condenser flow reversal.
September 7-8: Unit One aeld an average load of 800 MWe.
September 9: Load was reduced to 450 MWe due te icw system demand. Weekly turbine testing was completed.
- September 10 - Unit One held a steady load of 800 MWe.
September 13:
September 14 - On September 14 at 2145 - Unit One turbine was manually trip-September 21:
ped. The unit was shutdown and all control rods were fully inserted at 0243 on September 15 Unit One was shutdown for a scheduled anchor bolt and piping restraint inspection in accord-ance with the requirements of NRC IE Bulletins 79-02 and 79-14.
On September 21 at 0255 the reactor was made critical and at 1626 Unit One was placed on-line. Load was increased to 200 MWe.
September 22 - On September 22 at 1340 a unit shutdown was initiated due to a September 26:
minor pipe crack in the 1A moisture separator drain tank vent line to the moisture separator. At 1706 on September 22 the turbine was manually tripped and the reactor mode switch was placed in HOT STANDBY. Following repairs, the uait was placed on-line on September 26 at 0105 Load was subsequently increased to 400 MWe.
1163 n0C ea
September 27 - Unit One steadily increased load to 800 MWe and held steady on September 30:
September 29 and 30.
1168 006
B. Unit Two September 1: Unit Two began the reporting period operating at 480 MWe. Load was reduced throughot?t the reporting period due to end of fuel cycle coastdown.
September 2-8: Unit Two held an average load of 475 MWe.
September 9: Load was reduced 80 MWe due to low system load demand.
September 10 - Un.t Two held an average load of 466 MWe.
September 15:
September 16: Unit Two began operating with one reactor feed pump. Load was reduced to 350 MWe and the 2A reactor feed pump was turned off.
This was done to prevent the 2 pumps from operating at excessive discharge pressures.
September 17 - Unit Two held an average load of 425 MWe.
September 23:
September 24 - On September 24 at 1055 Unit Two scrammed due to a false high September 25:
reactcr pressure signal curing an instrument calibration. On September 25 at 1055 the reactor was made critical and the unit was placed on line at 2204. Load was subseouently increased.
September 26 - Unit Two held an average load of 408 MWe.
September 30:
\\b0
l11. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specification There were no amendments added to the facility license or technical spec-ification during the reporting period.
B. Facility or Procedure Changes Requiring NRC Approval There were ao facility or procedure changes requiring NRC approval during the reporting period.
C. Tests or Experisents Requiring NRC Aoproval There were no tests or experiments performed during the reporting period requiring NRC coproval. -
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 head-ings 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, i163 008
UNIT ONE HAINTENANCE SLMMARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q00748 Rx Bldg Crane The digital load The dic 11 load read- The monitor was repaired (1-5800) monitor was out wa.. ,ot working a.1 calibrated.
defective. properly.
Q00761 CRD 50-57 The pressure The switch was sending The p essure switch was Pressure Switch switch was an alarm signa; with replaced and calibrated.
(1-300) defective. no abnormal conditions present.
Q00523 02 Analyzer The valve needed The valve would operate, The valve was lubricated Return Valve lubricating. but sluggishly. and cycled.
(1-8803)
Q00527 02 Analyzer The valve needed The valve operated, The valve was lubricated __
Return Valve lubricating, but sluggishly. and cycled.
(1-8804)
QOO767 RHR HEX Flow The aux contacts The valve would not The aux contacts were Revers.1 Valve were defective. reopen from the control replaced. The valve was (1-1001 ';A) room. The valve could operated 3 times.
be opened manually.
RHR was operable at all times.
Q00784 RHR HEX Flow The operator worm Normal mode of RHR The washers and worm Reversal Valve gear and washers operation was not gear were cleaned. The (1 - 1001 -186A) were dirty. affected. valve was stroked 3 times.
Q00819 Y2 Diesel Gen. The motor was The U-1 and U-2 diesels The motor was replaced Soak Back Oil defective. The were operable while and the coupling aligned.
Pump (1-6601) bearings were repairing i DG, making excessive noise.
Q00695 RHR Flow The Belleville RHR normal moda of The washers were cleaned Reversal Valve washers had operation was not and the valve cycled (1-1001-186A) excessive grease affected. 3 times.
](( buildup preventing the valve from C7' oneninn.
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- c. '
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! UNIT ONE MAINTENANCE
SUMMARY
, CAUSE RESULTS r, EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER C0iP0 MENT MALFUNCT10N SAFE OPERATION PREVENT REPETITION Q00553 CRD 02-35 The accumulator A high level alarm wa The accumulator and Accumulator and o-rings were received from the o-rings were replaced.
(1-302) defective. accumulator. The rod was scram timed.
t s
CD
( e.
A 0
l UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFFCTS i W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 962-79 IRM #18 A connector was The IRM was not reading The connector and (2-702) dirty. properly. Other IRM's range switch was were functional. cleaned.
3959-79 RHR Service The pump casing The casing was leaking. The pinhole leak was Water Pump was defective. Pump was still operable. sealed.
(2-100-65C)
Q00831 79-18/03L RHR Cont. Spray A rod connecting The valve would not The rod was replaced Valve the motor to the operate properly. The and the valve operated (2-1001-23B) valve body broke, red :.idant A loop of 3 times, containment spray was operable.
Q00863 D.G. Starting The connector Air was leaking on a The connector adapter Air (2-6601) l adapter was top off line upstream was replaced.
Jefective. of the air starting motors. The DG was operable.
Q00832 2C RHR Pump The aux contacts The closing coil The aux contacts were Suction Valve were defective. tripped when the valve replaced and the close (2-1001-7C) received a closed sig- torque switch was ao-nal. Valve fs normally justed. The valve was open. operated 3 times.
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e
IV. LICENSEE EVENT REPORTS The 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 6.6.5.1. and 6.6.B.2. of the Technical Specifications.
UNIT ONE Licensee Even. Date of Title of Report Number Occurrence Occurrence 79-26/03L 9-14-79 MSiv 1-203-2C Failure to Close 79-27/03L 9-21-79 Reactor Coolant Con-ductivity Exceaded -
10.4 umho Duri.,9 Starcup 79-28/03L 9-24-79 1 A Standby Liquid Control Relief Valve Lifted At Less Than 1275 psig.
79-29/03L 9-29-79 1A Reactor Building Vent Monitor Failed Upscale UNIT TWO Licensee Event Date of Title of Report Number Occurrence Occurrence 79-18/03L 9-05-79 RHR Valve 2-1001-23B Failed To Operate 79-19/03L 9-11-79 2A Reactor Building Vent Monitor Failed Downscale 79-20/03L 9-19-79 RHR/MSL/RCIC Snubbers Found Empty 79-21/03L 9-26-79 Unit Two Suppression Chamber Exceeded 5%
02 Content i168 0i2
V. DATA TABULATION The following data tabulat i ons are presented in this report.
A. Operating Data Report B. Avorage Daily Unit Power Level C. Unit Shutdowns and Power Reductions 1168 0i3
r c a.'s o u r ) : ,f i
, OPEisATI:lG DATA REPORT DOCKET NO. 050-254 U!!!T One _
O h\
,\ O DATE 10-2-79 D COMPLETED BY D. Hannum TEl.EPH0!!E (309) 654-2241, Ext 179 OPEP,ATl?iG STATUS
,, 0000 090179 J. Reporting period: Gross hours in reporting period: 720
- 2. Currently author ized power level (MWt) : 2511 Max. depend. capacity
. (MWe-lic t) : 76cm Design electrical rating (MWe-Ne t) : 789 .
. 3 Power level to which restricted (if any) (MVe-Met): NA .
I' 4. Reasons for restriction (if any):
e i .
This Month Yr. to Date Cumulative
' ~
e 5 Nunber of hours reactor was critical 575.8 5330.3 52663.2 a
- 6. Reactor reserve shutdown hours 79 3 79.3 3408.9 r
~ 7 Hours generator on line 477.0 5029.1 50035.0 _
J' 8. Unit reserve shutdown hours. 0.0 19.8 909.2
' 1025626 11082366 99890242 9., Gross thermal energy generated (MUH)
- 10. Gross electrical engergy generated (MWH) 328583 .
3520163 32092658 a
- 11. Net electrical Energy Generated 309829 3323312 29955885
.: 12. Reactor service factor 80.0 __
81.4 81.3
,_ 13 Reanor availabilify factor 91.0 82.6 82.6 I
i,
- 14. Unit service factor 66.2 77.7 77.2 i
15 Unit availability factor 66.2 78.0 78.6
- 16. Unit capactly factor (Using itDC) 56.0 ,66.0 60.1 17 Unit capacity factor (Using Des. MWe) 54.5 64.3 58.6 -
[
q 18. Unit forced outage rate 33.7 7.5 __
8.1 19 Shutdowns scheduledover next 6 months (Type, date, and duration of each):
- 20. I f shutdcwn at end of report period, estimated date of :,tartupj,. NA
~'
- The !1DC nay be lo'. er than 769 MUe during periocis of high ambiant temperature doa j to the thermal performance of the spray canal. ,
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. 1 (final) Q. ( c C . .. . .
t curuarj syi.
~
l s OPEM.TI:lG DATA REPORT DC CKET fiO. 050-265 _
. , U!ilT Two g DATE 10-2-79
. OOV COMPLETED BY D. Hannum s ~
TELEPH0!1E (-309) 654-2241, Ext .179 OPERATitiG STATUS 0000 090179
. 3. Reporting period: 2400 0930HGross hours in reporting period: 720 b 2. Currently author-b.ed po.ler invel (MW t) : 2511 Max. depend. capacity
,. (M'Je 'Je t) . 769e Design electrical rating V;'.le- f!c t ) : 789 , .
< m
- 3 Power icvel to which restricted (if any) (MUe-!
- e t) : NA .
- 4. Reasons for restriction (if any):
i.
This !!onth Yr. to Date Cumulative 4
~-
- 5 fiumber of hours reactor was critical 696.0 , 6424.9 51801.3 J
- 6. Reactor reserve shutdown hcurs 0.0 0.0 2985.8
=:
7 Hours generator en line 684.8 6367.5 49470.4 _
P-f 8. Unit reserve shutdown hours. 0.0 0.0 ,,7,02 9
' thermal energy generated (MWH) 1039496 12502262 101244386 9., G ro k 10. Gross electrical engergy generated (MWH) 30'4326 3855085 32-43462 Y
Net electrical Energy Generated 269351 3541611 30303071 li.
y.
.I.L 12. Reactor service factor 96.7 98.1 81.1 3
13 Reactor availabilify factor 96.7 _
98.1 85.8 I
iL, 14. Unit service factor 95.1 97.2 77.5 L
. 15 Unit availability factor 95.1 97.2 78.6
- 16. Unit capactly f actor (Using MDC) 48.6 70.3 61.7
- 17. Unit capacity factor (using Des. Mwe) 47.4 68.5 60.1 ,
i
.* 18. Unit forced outage rate 4.9 1.1 9.5
~
19 Shutde ins scheduled over naxt 6 months (Type, date, and duration of each)-.
'; , NA
- 20. If shutdown at end of report pariM , estimated date of startupy
~
- The it0C maf be lo.er then 769 MUc during periods of high ae.biant temperature d a '
i to the therrr.al parformance of the spray canal . ..,,..,.,f., t i (final) - 9u15 o. c w(33
' V. d.' d *,.:: U N i l - P ' '.. .. 3. f V E L June ty/o Docket No. ,
050-254 Unit One h Date 10-2-79 D @@D_ ug '
\
g Completed by D. Hannum Telephone (309) 654-2241 Ext. 179 MONTH _ September 1979 DAY AVERAGE DAILY POWER LEVEL- DAY AVERAGE DALLY POUER LEVEL (th-Net) (MWe-Net) .
- 1. 787 17 -12.2
- 2. 735 18. -11.9 3, 505 19. -11.9 4, 706 20. -12.3 ,
}5 _74] 21 40.0
- 6. 681 22. 139.4
- 7. 737 23. -16.5 i
- 8. 759 24. -18.1
- 9. 592 25 - r5. 6
- 10. __
755 26. 363
.I1. 762 , 27 489 l, 12. 754 28. 658 13 758 29 761
- 14. 581 30. 764 1 15. -12.7 31. ---
[ areauVED
- 16. -9.0 1
. JUN 2 01976 INSTRUCTIONS } On this form, list the avera[;e dii!y unit power !cvel in MWc. Net for cath day in the reportin ; mo9thkakx:t3hiSe nessest veho!c rnecawatt.
These fit .urc; will te used to plut a r.raph for cach reporting month. Note llut when nuxirnum dependable capacityis I used tur th nel ciectrical rating of the unit there may be occasions v heia the d.tily aver ce power level exceeds the 1004 line (or the restruted power lesel hac). In sucii cases, the aver.ar.e d.iity unit power output sheet shr u!J bc I footnoted to expl.m the apparent anoma y. - 1 (final)
. . _ . _ _ -. \_.\._6 8r,'g 6 -
W .n/c c ,.': UNil-P; .3 3.EVEL - "" O/u Docket No. , 050-265 Unit Two ig ,, . Date 10-2-79 9h Completed by D. Hannum Telephone (309) 654-2241 Ext. 179 MONTH September 1979 DAY AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY POUER LEVEL (!n-Net) (MWe-Net)
- 1. 424 17 382
- 2. 427 13 381
- 3. 427 I j .- 378
- 4. 418 20, 378 ,
386 !}5 6. ___}21 429 21
- 22. 379
! 7. 420 23 386 i
- 8. 421 . 24. 150 9 389 25 -22.9
, 10. 419 26. 358
- 11. _ 413 , 27 368'
- 12. 406 28. 356 13, 411 29 357
- 14. 409 30. 358 i 15. 437 31. ---
[ aresuVED
- 16. -
360 1
. JUN 2 01976 INSTRUCTIONS } On this farm, list the average daily unit power Icvel in MWc. Net for cach day in the reporting mbthkuh:t3tilEic nessest who!c inegawatt.
, Tiiese figures will te used to riot a paph for each reporting month. Note thu when nuxirnum dependab!c capacity is J used for ti. net electrical rating of the unit, there may be occasions when the d.tily average power level exceeds the 1004 line (or the iestruted power lesel line). In such c.ises, the aver.ir.c daily uma power output sheet shot,lJ be I footnoted to expl.nu the apparent anomaly. , 1 (final)
. _ . . . . - L~ -
e
.. - - - - a - w - -, - -. - ..-. .-
APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET N0. 050-254 , March 1978 UNIT NAME Quad Cities one COMPLETED BY D. Hannum DATE 10-2-79 REPORT MONTH September 1979 TELEPHONE (309) 654-2241, Ext. 179 m $ s m = Eb z 5 Ee 8 g LICENSdE yg gy . po' DURATION $ jn 3{ x$ EVENT y8 @: 8
"
- CORRECTIVE A:..ONS/LOMMENTS NO. DATE (HOURS) y5g REPORT NO. 8 9
2G 790914 S 163.0 H 1 NA NA NA Unit One was shutdown for anchor bolt and piping restraint inspections in accordance with NRC IE Bulletions 79-02 and 79-14. 21 790922 F 78.0 h 1 NA CC TURBIN Unit One was shutdown for repair of the 1A moisture separator drain tank vent line. s , CO g ..,
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APPENDIX D QTP 300-S13
- UNIT SHUTDOWriS AND POWER REDUCTIONS Revision 5 DOCKET N0. 050-265 , March 1978 UNIT NAME Qu d Cities Tw COMPLETED BY D. Hannum DATE 10-2-79 REPORT MONTil September 1979 TELEPHONE (309) 654-2241, Ext. 179 m 5 s
*- m = EU r 5
%e 8 gg$ LICEtlSEE gg gg ,
'p o DURATION $ p3 d EVENT p8 g:8
' "
- CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) w5@
z REPORT NO. 8 R NA NA Unit Two scrammed due to a false high reactor 12 790924 F 35 2 H 3 NA pressure signal during an instrument calibration. O'> ca o e D (finai)
VI. UNIQUE REPORTING REQUIREMENTS 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 o Type Plant Description Unit Date Actuated Actuations Conditions of Events 1 9-14-79 1-203-3A 1 Manual Rx Press T.S. 4.5.D.I.b - 1-203-38 1 Manual 960 psig 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E 1 Manual B. Control Rod Drive Scrara Timing Data For Units One And Two The basis for reporting this data to the Nuclear Regulatory Commission is specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2. i163 020
RESULTS CF SCR/.M TIMING MEACUR:MENTS PERFCRMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-79 TO 12-31-79 AVERAGE TIME IN SECONDS AT Nax,TI.ma HUPEER l' 3ERTED FRO t FULLY 'JITh% AU'l ror 90i; DATE OF RODS 5 1 20 l 50 90 {i n v er ton DESCRIPTl0?! Technical Spec?fication 3.3.C.I s 0 37)_ 0.900 2.00 35 7 Sec- 3,3.C.2 (Averege Scram insertion ri 0.24 0.97 1.72 Cold Scram Times, Unit one 2/10/79 177 O.47 N-9 Hot Scram Times, Unit One 2/27/79 89 0.30 0.68 1.46 2.57 3 34 Seq. B Refuel Outage H-7 Hot Scram Times, Unit One 3/2/79 88 0.29 0.67 1.45 2.54 3.03 Seq. A, Refuel Outage 3/25/79 1 0.28 0.64 ' 37
. 2.40 Unit 1 Changed Accumulator L-7 3/25/79 89 0 31 0.69 1.47 2.58 2.94 Unit 2 Hot Scram Times Sea. B L-10 Unit i Replaced Drive 4/30/79 1 0.27 0.49 0 93 1.61 L-10 Cold Scram L-10 Unit 2 Replaced Drive 4/30/79 1 0.36 0.79 1 74 2.91 L-10 Hot Scram A-9 Unit 1 Replaced Accum, o/3/79 1 0.26 0.62 1.33 2.34 2.34 Hot Scram
- E-13 Unit 1 Changed Driv.e 9/20/79 1 0.23 0.45 0.92 1.62 1.62 Cold Scram 3.00 Unit 1 Hot Scram Times 9/22/79 89 0.28 0.65 1.43 2.52 F-6 Seq. B 0
l i
' t I i ' i
Vil 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 . ti tled "Dresden, Quad-Ci ties, and Zion Station - NRC request , for refueling infornution dated January 18, 1978. 8 6 1163 022
qtr Juu-dje . Revision 1 QUAD-ClYlES REFUELING March 19/8 INFORrlATION REQUEST
- 1. Unit: 1 Reload: 5 cycle: 6
- 2. Scheduled date for next refueling shutdown. 8_q1.8n (shn+.ri' vin (E005)
Scheduled date for restart following refueling: 12-7-80(Startup BOC6) - 3
- 4. Will refueling o'r resumption of operation thereaf ter require a technical specification change or 1ther license amendment: No, Plan 10CFR50 59 reloads for future cycles of Quad Cities Unit 1. The review will be conducted in June, 1980.
5 Scheduled date(s) for submitting proposed licensing action and supporting
- . informa tion: June, 1980 for loCFR50.59 related changes a 90 days prior to shutdown.
~
- 6. Important licensing considerations aser,ciated 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: Retrofit 8x8 fuel 2.65 w/o% (^- 224) .
7 The number of fuel assemblies. ,_
- a. Number of assemblies in core: 724
- b. Number of assemblies in spent fuel pool: 596
- 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 -
9 The projected date of 'the last refueling that can be discharged to the ppent"
,end offuel batch pooldischarge assuming ~the present licensed capacity: September, 1985 capability)
WPPROVED APR 2.61973 Q.C.O.S.R. 1168 223
QTP 300-S32 .
- - Revision 1 QUAD-CITIES REFUEL!NC March 1978 lHFORMATION REQUEST
- 1. Unit: 2 Reload: 4 Cycle: 5
- 2. Schedul.ed date for next refueling shutdown:
11 4-79 (Shutdown E004' 3 Scheduled date for restart following refueling: 1-17-80 (Startuo BOC5)
- 4. Will refueling or resumption of operation thereaf ter require a technical specirication change or other license amendment: No, Plan 10CFR50.59 Reloads for future cycles of Quad Cities Unit 2. The review s111 be conducted by early Septerr.uer, 1979 5 Scheduled date(s) for submitting proposed licensing action and supporting
- . information
- Early August,1979 for 10CFR50.59 related changes s 90 g days prior to shutdown.
I I 6. Important licensing considerations associated with refueling, e.g., new or
'~
' different fuel desion or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: .
l I New Fuel Design: Retrofit 8x8 fuel (180) - a nat. U at bundle top and bottom
- ' b two larger water rods
}- e new enrichment distribution
. d prepressurized l This fuel design was previously used for Quad Cities Unit 1 C le 5 t and Dresden Unit 2 Cycle 7.
4"
; r g \
I 7 The number af fuei assemblies. 9 I a. Number of assemblies in core: 724 ._.
- b. Number of ass-mblies in spent fuel pool: 492 1
} 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 nu;nber of fuel assemblies:
I
- a. Licensed storage capacity for' spent fuel:
1460
- b. Planned increase in licensed storage: None 9 The projected date of ie last refueling that can be discharged to the l spent' fuel pool assuming the present licensed capacity: March. 1986
- (End of batch discharge capability)
XPPROVED
- APR 2 01973 j jg 024 Q. c. o. S. R.
- m ee e
Vil. 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 Rt.ioval System RCIC - Reactor Core l$c'ation Cooling System HPCI - High Pressure Coolar.t 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 Cooling Water System RWM - Rod Worth Minimizer SBGTS - Standby Gas Treatment ystem HEPA - High-Efficientry 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 - Boiling Watar Reactor ISI - In-Service inspection MPC - Maximum Permissable Concentration 116a3 025
PCI - Primary Containment Isolation SDC - Shutdown Cooling Mode of RHRS LLRT - Local Leak Rate Testing MAPLHGR - Maximum Average Planar Lirear Heat Generation Rate R.O. - 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 P.eport ' ANSI - Amer!can National Standards institute NIOSH - National Institute for Occupational Safety and Health ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring 1163 226}}