ML20062B224
| ML20062B224 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/30/1978 |
| From: | COMMONWEALTH EDISON CO., IOWA-ILLINOIS GAS & ELECTRIC |
| To: | |
| References | |
| NUDOCS 7810250111 | |
| Download: ML20062B224 (25) | |
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QUAD-CITIES tlVCLEAR POWER STAT 10ft UNITS I AND 2 MONTHLY PERFORMAf;CE REPCRT SFPTEMBER 1978 COMM0fa!EALTH E3!507; CCMMi1Y AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY
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, NRC DOCKET !!05.and 50-254'I 50-265
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, LICENSE f!05. DPR-29 and DPR-30
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TABLE OF CONTENTS
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- l. Introduction
- 11. Summary of Operating Experience A. Unit One B. Unit Two Ill. Plant or 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 Appro' val D. Other Changes, Tests and Experiments
- 1. Facility liodi fications
- 2. Special Tests E. Corrective Maintenance of Safety-Related Equipment IV. License Event Reports V.. Data Tabulations .
VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations
- G. Control Rod Drive Scram 11 ming Data Vll. Refueling Information Vill. Glossa ry l'y l
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- 1. INTRODUCTION Quad-Citics !!ucicar Power Station is composed of two Boiling Water Reactors, cach with a Maximum Dependabic Capacity of 769 MNe net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Icwa-Illinois Cac & Electric Company. The Nucicar Steam Supply ~ Systems are Cencral Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent
& Lundy, Inc. and the primary construction contractor was United Engineers &
Constructors. The condenscr 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, purnuant to Docket Numbers 50-254 and 50-265. The date of initial reactor critica11 ties fer Units 1 and 2 respectively ware October 18, 1971 and Lyril 26, 1972. Com=creial generation of poeter began en February 18, 1973 for Unit 1 and March 10, 1973 for Unit 2.
This report was compiled by David Hannum. Telephone nutber 309-6,54-2241 ext. 252.
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ll. _ Summary or Operatinq Esnerience The follow.ing is a chronological description of plant operation for the month of September, 1978.
A. Unit one September 1: Unit One bcgan the reporting period operating at an electrical load of 600 MUe.
September 2-4: Load was reduced to 400 MVe for main condenser flon reversal.
September 5-7: Unit one averaged an electrical load of 633 MWe.
September 8-9: Load fluctuated between 704 and 558 tiWe due to high back pressure in the main condenser.
September 10: Load was reduced to 400 tiWe to perform the tiSlV biweekly test and perforin main condenser flow reversal.
September 11-16: Unit One averaged an electrical load of 608 MWe.
September 17: Load was reduced to 500 nWe for condenser flow reversal.
September 18-20: Unit One averaged an electrical laod of 675 MWe. ,
September 21: Load was reduced to 600 ftWe due to high spray canal temperature.
September 22-23: Load was held at 675 MWe.
September 24: Load was reduced to 500 ftwe for condenser flow reversal.
September 25-30: Unit One remained on line the remainder of the month operating at an average electrical load of 632 Hue, i
l y\ B. Unit Two l September 1-3: Unit Two began the reporting period at an electrical load of 780 nue and held steady.
l September 4-5: At 0102 on September 4 Unit Two turbine was ranually
- tripped and left in Hot-Standby in order to repair on EHC oil leak. On i
Septeraber 5 at 0117 the generator was put on line and load was increased to 360 MWe. Upon completion of the v.cekly turbine test load continued to increase toward 500 MWe.
September 6-3: Load increased at 3 MWe/hr up to 798 fiWe.
September 9-10: Load was reduccd to 633 fMe in order to perform M51V monthly and weekly turbine tests.
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I September 11-13: Unit Two operated bet'crcen 746 cnd 794 Mue.
September 14-16: On September 14, load was . educed to 6GO MVe in order to perform turbine tests. Upon completion of the tests, load was again
, Increased and held at 780 MUc for the next two days.
September 17: Load was reduced to 700 ftWe for condenser flow reversal.
. September 18 .'8: The average electrical lead for Unit Two was 800 f tWe.
On September 20, load was dropped to 680 NWe for backwashing the condensote demineralizers. On September 23, load was reduced to 700 MWe for s,cekly turbine testing.
September 29-30: At 1500 on September 29, load was reduced at 100 MWe/hr and at 2316 the generator was tripped. At 0655 on Scotember 33 the node switch was placed in SHUT 00'.!N for a planned maintenince cutogo to replace an electror.atic relief valve, to inspect hydrculic snubbers in the drywell, and to perform control rod scram timing after start up.
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Plant or Procedure Chcnges. Tests. Exocriments and Safety-Related Mainteccccc 1
A. Amendments to facility license of Technical Specification.
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Amendments'to Technical Specifications during the reporting period Include the revision Amendments No. 47 to DPR-29 on' September 20, 1978.
C. Restrictions 1
' Reactor power level shall be limited to maintain '
pressure margin to the safety valve set points
' during the worst case pressurization transient.
i The magnitude of the power limitation, if any, and the point in the cycle at which it shall be-l applied is specified in the Reload No. 3 licensing
{ submittal for Quad-Cities Unit No. 1 (NEDO-21489).
j Plant operation shall be limited to the operating plan described therein. Subsequent operation in j
the coastdown mode is permitted to 40% power.
s B. Facility of Procedure Changes Requiring NRC Approval.
l There were no facility nodifications or procedu're. changes which took place during the reporting period requiring approval,of the NRC.
i C. Tests and Experiments Requiring NRC Approvai.
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j There were no tests or experiments performed during the reporting period requiring NRC approval.
D .- Other Changes, Tests and Experiments. '
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There were no facility modifications requiring reporting to the NRC which were completed this month.
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- 2. There were no other changes, tests, and experiments performed during the reporting peroid.
O O E. Corrective Maintenance of Safety-Related Equipment.
The following represents a tabular summary of the safety-related maintenance performed on Units I and 2 during the reporting period. The headings ,
Indicated in this sutrary include Nature of na'ntenance and Work Recuest numbers, LEP. numbers, components, cause of calfunctions, results and I
effects on safe operation, and actions taken to prevent repetiticn.
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UNIT 1 MAINTENANCE
SUMMARY
1 CAUSE RESULTS & EFFECTS
- tl . R . LER - 0F CN ACTION TAKEN TO MUMSER NUM3ER 'CCMPCNENT MALFUNCTION SAFE OPERATION PREVENT REF:TITION Corrective RX Bldg. Crane Inching motor "SC" The relay would not The contact alignment 3369-77 (1/2-5800) relay contacts were always pick up the was corrected.
out of alignment. contacts.
Corrective 1096-76 Refuel Bridge The main grapple The main hoist motor The main grapple control (1-833) control switch was was not working control switch was defective. properly. replaced.
Corrective RCIC cooling The "M" coil would The valve was open and The air gap on the "M" 4026-78 water valve not pick up, would not close. RCIC coil was adjusted.
(I-1301-62) was still operable.
Corrective 3902-78 MSIV The limit switch The valve showed dual The arm on the limit (1-203-2A) was out of indication. Scram fun- switch was replaced.
adjustment. ction not affected.
Corrective LPRM 24-09 The card was The LPRM was pegged The card was replaced 4226-78 (1-756) defective. downscale. APRM inputs and a shorted connector were still adequate. pin was repaired.
Corrective CRD 46-35 Scram The "0" rings were The valve was leaking. The "0" rings were 4111-78 solenoid valve defective. Scram capability not replaced.
(1-305-117) affected.
UNIT 2 MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS U.R. LER - 0F ON ACTION TATEN TO
!!UMCER NUMCER 5 COMPONENT MALFUNCTION SAFE OPERAll0N PREVENT REPETITIC" Corrective 1099-73 Refuel Bridge Magnetic reed switch The book closed indi- The proximity switch (2-834) was defective. cation mechanism was was replaced.
Corrective R0 78-30/03L-0 MSL "D" rad 4005-78 monitor (2-1705-020) The monitor needed The radiation monitor The monitor was adjusting. was reading downscale, recalibrated.
Corrective 4152-78 R0-78-31/03L-0 MSIV The limit switch The relay would not give The set screws on all the (2-203-2C) trip lever was 1/2 scram. Other MSIV's trip levers were tightens loose. trip logic were intact.
Corrective 4531-78 R0-78-33/03L-0 Snubber on Tgt. The seals were The snubber was leaking. The snubber was replaced.
Rock viv. defective.
(Mark #175)
Corrective 3978-78 Standby liquid The packing was The pump was leaking at The pump was repacked, control pump worn. the stuffing box. Pump (2A-ll02) , was still operable.
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IV. LICEll5EE EVEllT REPORTS ,
The follo, sing is a tabular summary of all licensee event reports for
) Quad-Cities Units One and Two during the reporting period which were i
submitted to the commission pursuant to the reportable occurrence reporting ie requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
4 Unit One e
Licensee Event Date of Report flumber Occurrence Title of Occurrence R0-78-26/03L 9-20-78 RHR Room Watertight Door not Closed.
' R0-78-27/03L 9-28-78' '
U-l Diesel Generator Inoperable to repair fuel line. .
R0-78-28/03L 9-29-78 #1 off gas monito*r 4
failed.
Unit Two Licensee Event Date of Report flumber Occurrence Title of Occurrence R0-78-31/03L 9-10-78 2C MSIV failed to p give 1/2 scram.
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V. DATA TASULATIO!!S The fo!!owing data tabulations are presented in this report.
A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions d
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CPEP..*sTli;G D/iTA T.EPLET DOCKET I:3. 35g-75h-pgg 2%
UtilT _01c DATE 10-10-78 __,_.
C0llPLF.TED DY D. Hannum
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TELErito!!E (309)-654-2241 OPERATI::G STATUS 0001 780901 2400 730930 J. Reporting period: _ Gross hours in reporting period: 720
- 2. Currently authorized power level (ni.!t ) : 2511 ,_ Max, depend. capacity l (nWc-l!e t) : 7 @,2 Cesign electrical rating (ii.!c-Ile t ) : 729 '. __. I t
3 Power level to which restricted (if any) (tiW-::et): ilA .
- 4. Reasons for rcstriction (if cny): .
.This t;onth Yr. to Date C ur.n: l e t ' v:.
5 tionber of hours reactor was critical 72.0 Ja0_ A51M9_b
- 6. Reactor reserve shutdcwn hcurs 0 q,0 _. 332SJL 7 Hours gencirator on 1ine 720 6108,1 477_33.9 Unit rc serve shutdown hours.
- 8. 0 4 5. 2___, 889.4 ,
Gross thermal energy generated (liWH) 1435674 12849772 85126847
- 10. Gross electrical engergy generated (MWil)437461 4043356 2746LoJ2 I1. h'et scicctrical Energy Cencroted 399889 3739628 25651146
- 12. Reactor service factor 100.0 95.4 79.6
- 13. P.ccctor availabili fy fcctor- 100.0-- 8%5 9 5 .
- 14. Unit service factor 100.0 93.2 7s.4
- 15. Unit availability factor 100.0 93.9 77.0
- 16. Unit capactly f actcr (Using MDC) 72_.2 74.2_ S S,,8
- 17. Unit capacity factor (using Des. tu!:) __7_2, A 70__4_ .__57-3
- 18. Unit forced cutzge rate .0.0. ___ .. A.8_ __ _ 8.6_ __
19 shutde.. ,- sc h W' C s. .e n et 6 .c.n br. (Ty, , 6 . . cr ' 3e et N. of e:c:.
- 20. I f sht.tdc..n a t cr.d of repnet rcried, esticated chuc of stcreep;,, [!A ,_,
A The MDC ray be Ic..sne th ,n 763 MUe during perio.is of high a,biant tc : p:rstu re du to the th:.rr.nl performanc'. of th2 tr_rm/ ccnal. . , , . , , ,, l 1 (Tim i) u,. c ,-
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. OPEi:ATli.G b.'UA It p0M D00KET !!O. 050-265-DPR-30 Uf!!T Two
. DATE 10-10-78 C01PLETED OY D. Hannum ..
TEl.EI'l:0!!E (309)-654-2241 .. ..
0001 780901 O~ PERATit:3 STATUS 2400 780930
, J. Reporting period: , Gross hours in reporting period: 720
- 2. Carrently authortecd power level ( lilt) : 2511 ,_, liax, depend. cr.paci ty (mle-l!c t) : 76ql l'esign elect rical rating 0_"Je-!!et): 7fi,9 ', .
3 Power Icvel to which restricted (if any) (i:1le-1:2t): NA ,
, h. Reascas for restriction (if any): .
- This lionth Yr. to Date Cumulative
$. tiunber of hours rccctor wcs critical 695.0 4978J., )_3Jjl2.,9 5._,
. 6. 11eactor reserve shutdown hcurs 0, _, 113.1 ESS,J_._ ..
- 7. liours generator ran 1ine 695.0 L871.9 }_0333J_..,_,
, 8. Unit reserve shutdown hours. 0 128.2 _7,02 d
., Gross ther:.al energy ser. crated (liin!) 1581477 10139342 84003535 ._
- 10. Gross electrical cncergy generated (:WH) 502322 3179652 2701167 l
fl. !!ebelectricalEnergyCencrated 479079 ,
30!9095 25354043 _
- 12. Reactor service factor 9 6_. 5_ 76.0 77.4 ..
. 13. Reactor availabilify factor g4_ 77.7 82.8
- 14. Unit service fo.; tor 96.5 74.4 13 2
! 15. Unit availibility facier o rs-5_. 7L't 74.7
- 16. Unit capcctiy factcr (Using !:DC) 8 C . 3__ 59.9 59.I
- 17. Uni t ecpaci ty factor (using Des.1:'.lc) 81,,3_ s8.4 .__ 52d__ _
- 18. Unit forcer
- ca t c.; 2 rate ____3 A 21. a .l L 2_.
I '. . S N:de.:,3<d._'ulm',.cc. : xt 6 c : . i.s ('. ; :, c d ., ca.r' d....!.n ei" :a-:};
- 20. If shutde..n at ent of report parie.f, cstir.ated dat e of startup o- . .10-2-73 , _ ,
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- The !;0C n y be leta- th:,n 763 n'.h during period of high ::abiant temperature ch [
to t he t he rr.a l p.-r Tr," u:: e o f th a 3,3 ray c.n n:1 , , ", - . !
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APPEllDIX B P.wisica 4 AVERAGE DA LY Ufl1T-POWER LEVEL June 1976 Docket flo. 050-254' DER-29 Unit One
-Date 10-10-78 Cornpleted by D. Hcnnum r
Telephone _(309)-654-2241 MONTH Septenher DAY AVERAGE DAILY PCVER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mus-!;et) (MWe-fie t)
- 1. 597 17 580
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2.- 583 -
- 18. 6s8 3 413 19 679
- 4. 427 20. 671
- 5. 629 21 644 .
- 6. 629 '
- 22. 657
- 7. 637 661 23
- 8. 647 24, 593 9 584 25 Au
- 10. 529 '
- 26. 652
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- 11. t 611 27 608 12, 586 28. 612 13 6ng i 29 ,, -
- 14. 606 30. 639
- 15. 601 -
31.
- 16. 603 ' ~ .
INST!!CT:PNS On ll..s f., . . tiu crerste d2. y t.r *. pr. :. :: b ei ir. .'..'A. ,':t fer e:.; h 3 ly 1.: ** r, e r , 9:' .; in :.:h. G.: . :: :
riens vit v.!;u!: : .c32 w 1:t .
These firure v4 e used ta piet a g :qh fer c; s reparar; : m th we i!ut when na>: " a:i tJ:pe,.!:' :.: c2r w i' -
u:ed f or !!.; i::: c're:nul rahng or n: und. !;.et: uy L: .w .a;na.s c:a :he da ly :se: cc p. .;r I:sei e s:fe;; **
l ifG3 lice f or !! r.stoircJ p.r.ur Mel hac). h we c :.05. ;;c ser. l. t'.. It '.ait p ;wcr ou!;:ut s!sen 3! . _'l 50 (cutno!cd to :n;!.:;> the .-p;ur:n: ..nu:. :.!> . , , ,
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Revision 4 APPEllDIX B June 1976 AVERAGE DAILY UttlT-POWEP. LEVEL,
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Do-ket !!o. 050-265-Dr:1-30 Unlt Tvo Date 10-10-78 ,
,' Completed by D. Hannum Telephone (3cgn654-2241 MONTH %qtembe r-DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY POVER LEVEL (flVe-ile t )
(MWe -Net )
17 7or
- 1. 763
- 2. 773
- 18. pnn 19 png 3 769
- 4. 638 20. 7;;7 391 21 82 5
- 6. 567 22. 798 641 23 783 7.
24, 791 .
- 8. 748 749 25, 795 9
- 10. 7,g 26. 791 g.
- 27 773
- 11. 778 i
- 28. 775 i 12. 767 29 489
, 13 784 30, 128
. IE, 768
- 15. 775 31. _
- 16. -7% .
INST.'R:CTIONS Orith.sfa . ! *. :h: c. :;p. d; . ur. : ; a c.:t le.e! ia .'.rJ. --N:t f ar enL d iy ia !:,c r:rcr: c tr:r.:h. Co ; * :o t i oc.uot wiu !: n. c.:wT!t.
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S APPENDIX D QTP 300-513 UNIT SliUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. m-MS-nno-?n March 1978 UNIT tlAftE _Ouad-citles Two , C0liPLETED CY 0. Ilannu, DATE Oct ber 10, 1978 REPORT HONTH September 1978 TELEPtONE (309) 654-7"41 I w 5 s ye m = Eb = 5 8 @g$ LICENSEE pg 5g po DURATION $ %gd EVENT *8 E8 NO. ' "
DATE (!!0URS) y5g REPORT NO. m g CORRECTIVE ACTIONS / COMMENTS R
22 9-4-78 F 24.25 8 1 NA ilA NA Unit Two was shut down for an EllC oil leak rep.
23 9-30-78 S 0.73 D 1 Nk CC VALVEX Unit Two was shut down for an electromatic relief valve replacement, heater leak test, and condenser tube sheet inspectlon.
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.I VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments i to the commission.
A. Main Steam Relief Valve Operations.
The main steam relief valve operations during this reporting period are as follows:
9-29-78 2-203-3A 1 Hanual Rx Press.
. 2-203-3B 1 Manual 980
! 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E I Manual B. Control Rod Drive Scram Timing Data for Units One and Two.
No control rod drive scram timing tests were performed during the reporting period.
VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station ,
was requested in a January 26, 1978 licensing memorandum (78-24) from .
D. E. O'Brien to C. Ree,d et al. titled, "Dresden, quad-Cities and Zion Stations - NRC Request for Refueling Information," dated January 18, 1978.
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. QTP 300-532 Revision 1 QUAD-CITIES REFUILING Mcrch .1978
- INFORl:ATION RCQUEST
- 1. Unit: 1 Reload: A Cycle: 5
- 2. Scheduled date for next refueling shutdown: January 12. Ic79 Nhutde.n ECC4) 3 Scheduled 'date for restart following refueling: Aor'il 12 1979 (startup C;;5
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: Yes; See attached checklist
.for Tech. Spec. and License Amendment. .
5 Scheduled date(s) for submitting proposed licensing action and supporting
. informa tion: The QC1 R4 licensing submittal is scheduled for Mov. 11, 1978.
6." inportant licensing considerations associated with refueling, e.g., new cr
- dif ferent fuel design or supplier, unreviewed design or performance analysis methods, sigaificant changes in fuel design, new ope. rating procedures:
Retrofit 8 x 8 fuel (192)
Hew fuel designs:
a) nat. U at bundle top and bottom,- l b). two larger water rods, c) new enrichment distribution.
Last Test Assemblies (Il s ~
for GE PCI-resistant design development program.
- 7. The number of fu21 assemblics.
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- a. Number of assemblies in core: 724 t,
- b. Number of assemblies in spent, fuct pool: 151
- 3. The present licensed' spent fuel pool storage capacity and the size of any increase in licensed storaga capacity that has been requested or is planned in number of fuel assemblies: .
a .' Licensed storaga capacity for spent fuel: t ido
- b. Planned increase in licensed storage: None 3 The projected date of the icst refueling that can be discharged to the spc.i t f tia l j'co l u s', in; the cresent l icensed c;.; aci t y: L- . : re fue l in -
date with present capacity: liarch, $5 (cnd of batch discharg, caprilli,:y)
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RELCAD LiCEl'S!NG PACKAGE QIP 300'33 PREPARAT!ON SCHEDULE RevisiGa I U::1T 0.1 March 1970, RELOAO - ~I, CYCLE 5
- ACTIVITY DATE RESPONSIBILITY CENTER i/73 GE N~S receives draf t Licensing Sobmittal f rom CE MFS Transmit copy of draf t to Station for Comments NFS Transmit tiFS and Site ccmments/ questions to GE 9/78 NFS Ben i n Tec_h . __Sp_cachangn, S., f e ty Eral.natica anLCovwl"' ' ~ ~
GE ilFS receives final Licensing Submittal and anst:crs to CECO questions fra.n CE 30/73 NFS Conpicte final flFS reviaw of I f roncing Rubmi + +,1 n A mm , s en r r c A c u :.s.t.!.m 1/78 flFS Transmi t complete packaoe for on/of t site review' --
'3/73 Station on-site review connieted ---
' '6 //3 PSA Of f-s I te review ccmnlerad AN "oc I
'11/78 NLA Coroleted licensinn nnet,cn enmi end h ~ ~ '
p, i 12/79 -
Anticipated unit shutdown . !
50 days 28 days 'I j
. i 3/79 -
' Receipt of operating License Jj \"
i 9/79. .
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Anticipated Unit Startup - Assumes 56 day outage
'.,.' 8 yceks
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. Prepared by , nr - NFS/BWR s ,
. ; Date' '32/3]l?7'; -
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PREllill:tARY Cl!ECKLIST
, .. FOR .RELO*D LICE::3E Anit:DME:ITO .
ung7: Quad-Citics 1 l 4i !
RELOAD:
CYCLE: 5} .. . ....... .. .. ....
I '
Require Changes I Iten pag,
=
' X Scrcm Reactivity 4 Generalize verding and reference the submit.
HE00-YYYYY ,
Safety Valve Sctpoints None. Adequate pressure -
NA LSSS 1.2/2.2-1 margin.
!!A Bases 1.2/2.2-2,3 11one , if the' peak vessel ~
pressure is 1325 psig. during
- S.V. sizing trans.
~ .
RBM Setpoints X LCO 3 2/4.2-14 ' Change to (.65w+XX) as regid.
- 3.2/4.2-7 Change operabillty to' XX?;
X ' Bases 3.2/4.2-8 Change' Reference 1 to NECO-XXXXX. , ,
Auto Flow Control .
HA LCO . 3.3/4.3-5 hone. Stability analysis not
' limiting.
NA Bases 3 3/4.3-11 lione. .
' I
. HAPLHCR
- Revise curves to reficct X LCO Fig. 3.5.1 (shts. I to 3) new analyses.
X Bases 3 5/4.5-14
- Change references to reficct
,new analyses of MEDO-2401.6.
HCPR 3 5/4.5-10 . New values: **1.XX (7 x 7)
X, LCO 1.XX (8 x 6)
B Cases 3 5/4.5-14 Generalize description of
- limiting t ran s i en t (s) .
- l'!.PLHOP, ch agas are being handled under separa te cover.
" I n cl udes a:'d i t ic.,a l 0. XX CP.T p2aaity for Fuc1 Loading Error Acciden'.
(MRC interir- licensirg . nitioni.
.. l u c , ,. C ..> . i a t thi , t art i n .f i ; a ' e d a s " /. E . . . "
. QTP 300-532
's
'- Revision 1 Harch 1978 i QUAD-CITIES RIFUELING ' '
I INFORMATIO! REQUEST i .
't b
' Reload: 4 Cycle: q (next outage)
'1. Unit: 2 .
- 2. Scheduled date for next refueling shutdown: September 30, 1979 (shutdowr.
EOC4)
Scheduled date for restart following refueling: January *20,1980 (Startup 3
B005)
. 4. Will refueling or resumption of operation thereaf ter require a technical spectfication change or other license amendment: Simlar Tech. Spec. changes - -
to Reload 3 Cycle 4.
i f
5 Scheduled date(s) for submitting proposed licensing action and supporting
. Information: Reload Submittal to be provided approximately 90 days prior -
i; to shutdown.
l .0 6. Important licensing censiderations associated with refueling, e.g., new or
'different fuel design or supplier, unreviewed design or performance snalysis
< methods, significant changes in fual design, new cperating procedurer:
- .~ Hew fuel designs: Retrofit 8 x 8 fuel (approximately 196). ,
i - -
I'
[
t a* -
l 4 .
- 7. The number of fuel assemblics. .
a.1 !! umber of assemblics in core: .2?4 Number of assemblics in spent fuci pool: 745 -
. b.
8'. The pre 3cnt licensed spent fuci pool storage capacity and the size of any increase in licensed storage capacity that has-been requested or is planr.ed '
in number of fuel assemblies: ,
i o a. Licensed stcrcge capacity for spent fuel: 11:40 -
- b. Planned increase in licensed storane: None.
S. The proiected date of the Itst refueling that can be discharged to the spent f u ! ;.:.,0 ! a r. t.n i n.; tha -rescnt l i:.ccsed capaci ty: Last refea'ing de:e with present capacity: Sep;cnher. 85
, - _ _ ~ , _ ,
RELOAD LICENSlHG PACKAGE QTP 300-533 bMIT oC 2 PREPARATION
- SCHEDULE 4' vision 1 RELOAD 3 March 1970 CYCLE 4
) ATE RESPONSIBILITY CENTER ACTIVITY f
10/6/77 CE NFS receives draf t Licensing Subnittal from CE Transmit copy of draf t to Statica NFS for comments.
NFS Transitit UFS and Site cc:r.mcnts/ questions to CE Dcgin Tech. Spec. changes, Saft ty g 10/20/77 N FS Evaluation and Cover Letter.
CE NI'S receives final Licens.ing Sub::iittal and answers to CECO questions from CE.
NFS complete final NFS revicu of Ticenqina 9.shn f e r,1 i ,4 answors t o CFCo ner~-t ion _
11/8/77 HFS Transnit complete packace for on/off site revicu 11/16/77 Station on-nite review connleted 11/13/77 PSA Off/ site review completed _,
12/1/77 NLA Completed T.icensine paelen co recaived hv NR r' 90 days 1/16/78 -
Anticipated unit shutdown .
28 days 3/5/78 -
Receipt of operating License Day outage j 3/15/78 -
Anticipated Unit Startup - Assumes 8 Weeks
. Prepared by .TAS - NFS/BWR Date 2/23/78 f f!nal) *
. PREll llllj\RY ti!EC!'. LIST FOR P.ELOAD LICE;15E /J:E!!DMEllTS I
U;!!T: Quod l cities 2 .
RELOAD: 3' l -
CYCLE: 4- [ .
Rcquire Chac I l ,
Iten Page I
Scram Reactivity 4 Generalize ';e.
- X
~
referencc. the .
flE00-24063 Safety Valve Sctpoints .
fiA LSSS 1.2/2.2-1 !!one. Adequate pressure
\. margin. ,
X Bases 1.2/2.2-2,3 Clarify and add bounding
~
. peak pressure.
RBH Setpoints X LCO 3.2/4.2-14 Change to (.65w+42) 3.2/4.2-7 Change operability to 30%.
X Bases 3.2/4.2-3 Change Reference 1 to
!!EDO-24063 .
l i
1 Auto Flcw Control flA LCO .3 3/4.3-5 ilone. stability analysis not limiting.
s
~
'llA Bases 3.3/4.3-11 !!one.
l 11APLl!GR ,
X LCO Fig. 3.5.1 . ARevisc curves to reflect (shts. I to 3). new analyses.
X Bases 3 5/4.5-14
- Change references to reflect
- - new analyses of flECO-240L6.
.t
!!CPR
'3.5/4.5-10 tiew values: **1.33 (7 x 7)
. .X LCO 1.35 (S x 6)
Cases 3.5/4.5-14 Generalize description of
~
- limiting transient (s).
- P.APLHSR changes are being handled under separate cover.
- Includes addi:lon:1 0.XX CPR penalty for Foci Loading Error Accident (NRC in tcria liccasing p:;i tion) .
i "a l *:cs u.. r.o .n a t this :ir.c .,rc injicu*ed ss ";:..."
Vill GLOSSARY j The following abbreviation & hich may have been used in the floatFJy Report, are defined below:
CRD -
Control Rod Drive System SBLC -
Standby Liquid Control System HSIV -
Main Steam isolation Valve RHRS -
Residual Heat Removal System' RCIC - Reactor Core isolation Cooling System IIPCI -
liigh Pressure Coolant injection System.
SRM -
Source Range lioni tor
/
IRM -
Intermediate Range Moni tor LPRM - Local Power Range Monitor .
APRM -
Average Power Range Monitor TIP -
Traveling incore Probe RBCCU -
Reactor Eullding Closed Cooling Vater System TBCCU -
Turbine Building Closed Cooling Vater System RVM -
! IIEPA -
High-Ef ficientry Particulate Filter RPS - Reactor Protection System IPCLRT -
Integrated Primary Containment Leak-Rate Test LPCI - Low Pressure Coolant injection tiede of RHRS RSM -
Rod Block t!oni tor -
SWR -
Boiling Water Reactor 151 -
In-Service inspection itPC -
tiaxiraum Permi ssaS ie Concentra tio.
l
.- _ _ - . - ~. - - . _ _ . - . ~ . . ~ . . . . . . . . - . . . _ . . -.
. . \
\
PCI -
Primary Containment Isolation SDC - Shutdown Cooling tiode of RilRS LLRT - Local Leak Rate Testing i g MAPLHGR -
Maximum Average Planar Linear Heat Generation Rate R.O. -
Reportable Occurrence Dif -
Drysell RX -
Reactor EHC -
Electro-Hydraulic Control System i
Minimum Cri tical Power Ratio
, llCPR --
j PCIOMR - Preconditioning Interim Operating Management Recommendations LER - Licensee Event Report i AtlS I -
American flational Standards Institute i
! til0SH - National Institute for Occupational Safety an/
q Health
- ACAD/ CAM - Atmospheric Containment Atmospheric Dilution /Containnant-
! Atmospheric tionitoring l
l 4 i
i r
f 4