ML20062F660
| ML20062F660 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/30/1978 |
| From: | IOWA-ILLINOIS GAS & ELECTRIC |
| To: | |
| References | |
| NUDOCS 7812200188 | |
| Download: ML20062F660 (26) | |
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QUAD-CITIES NUCLEAR POWER STATION i
UNITS 1 AND 2 l
MONTHLY PERFORMANCE REPORT NOVEltBER 1978 COMl10tNEALTH EDISON COMPANY j
l AND l
10WA-ILLIN015 GAS & ELECTRIC COMPANY i
NRC DOCKET NOS. 50-254 and 50-265 l
I LICENSE NOS. DPR-29 and DPR-30 l
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i TABLC OF CON 1CNTS 1.
. introduction j
il.
Summary of Operating Experience 1
A.
Unit One l'
.B.
Unit Two lit. Plant or Procedure Changes,' Tests, Experiments, and_ Safety Related Maintenance A.. Amendments to Facility ' License or Technical Specifications 8.
Facility or Procedure Changes Requiring NRC Approval i
C.
Tests and Experiments Requirir.g NRC Approval j
D.
Other Changes, Tests and Experiments 4
1.
Facility Modifications 2.
Special Tests E.
Corrective Maintenance of' Safety-Related Equipment A
4 IV.
License Event Reports V.
Data Tabulations i
VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations j
D.
Control Rod Drive Scram Timing Data l
Vll. Refueling Information Vill. G los sa ry i
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1.
-lNTRODUCTICN-Quad-Ci ties Nucicar Power Sta tion is composec of two Bolling Vater Reactors, each with a Maximum Dependable Capacity lof 769 MWe. net, located in Cordova,
Illinois. The Station is. jointly owned by Commonweal th Edison Company and Iowa-j lilinois Gas & Electric Company.
The Nuclear Steam Supoly Systems are General Electric Company Boiling t!ater Reactors. The Architect / Engineer was Sargent 6 Lundy, Inc. and the primary construction contractor was United Engineers &
i Constructors.
The condenser cooling method is a closed-cycle spray canal, and the Mississippi River is the condenser cooling water source. The p lan t is subject to license numbers DPR-29 and DPR-30, issued October 1,1971' and i
March 21, 1972 respectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor criticali ties for Units 1 and 2 respectively were -
i October 18, 1971 and April 26, 1972. Commercial generation of power began on i
February 18, 1973 for Uni t I and March 10, 1973 for Unit 2.
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This report was compiled by David Hannum. Telephone number 309-654-2241, Ext. 252.
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SUMMARY
OF CPERATI.!;G EXPERIE.'lCE A.
Uni t One flovember 1 : Uni t One began the reporting period operatir.g at an electrical!
load of 411 MWe.
November 2.- 10:
Unit One held an average electrical load of 346 MWe due to spray canal load limitations.
November 11 - 125: Load was increased to 612 MWe and then held an average electrical load of:558 MWe.
f November 26: ~ Load was reduced to 400 MWs for main condenser flow reversal, and subsequently increased at' 50 MWe/hr te 550 MWe.
flovember 27 - 30: Unit one held an average elec'trical load of 550' MWe throughout the remainder of the reporting period.
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l' B.
Unit Two-November 1: Unit.Two began the reporting period operating ct an electrical load of 509 tue.
Noventer 2 - 3: Unit Two held an average electrical load of 525 P!4e.
November 4:
Load was reduced to 500 MVe for the weekly turbine tes t.
November 5 - 10:
Load was steadily increased to 687 MWe.
4 November li: Unit Two load was droppped to 407 ttle for control rod pattern adjustment.
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Uni t Two increased load on a preconditlening ramp of November 12 - 22:
l 3 MWe/hr until November 15 then held an average electrical load of 766 We through November 22.
November 23:
Load was reduced to 400 MWe for control rod pattern adjustnent.
}
November 24 - 26: Unit Two steadily increased load on a preconditioning 1
ramp of 3 hde/hr.
l November 27 - 30: Unit Two held an average electrical load of 783 MWe for the remainder of the reporting period.
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i lit. P lan t or ' Procedure Changes, Tes ts, Experimer.t s, and Safe ty Re lated _Mai ntcnonce
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A.
An-cndments to Technical' Specification during the reporting period incluce -
the revision Amendment No. 48 to OPR-29 The amendment revises Techniccl Specification to provide operating temperature and pressure limits in accordance wi th Appendix.G,10 CFR Part 50.
i B.
Facility or Procedure Chcnges Rcquiring NRC Approval 1.
There were no facility-modifications or procedure changes which took place during' the reporting period requiring approval.cf the -
NRC.
C.
Tests and Experiments Requiring NRC Approval 1.
There were no tests or experiments performed. during the repceting period requiring NRC approval.
D.
Other Changes, Tes ts, and Experiments 1.
There were no facility modifications requiring reporting' to the NR0 I
whi ch were comple ted this nonth.
2.
On Novemoer 29, 1978 the Calgon CL-144 injection functional test was co.c.p le ted.
The injection point was ' moved f rom the spray canal j
to the Uni t One intake bay.
E.
Corrective Maintenance of Safety-Related Equipment 1.
The following represents a tabular summary of. tha safety-related j
maintenance performed on Units 1 and 2 during the repor:Ing period.
~
The headings indicated in this summary include Nature of Malntenance and Work Request numbers, LER numbers, components, cause of melfunc-tions, results and ef fects on safe operation, and actions taken to prevent repe ti tion.
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UNIT 1
MAINTENANCE
SUMMARY
CAU3E RESULTS 6 f.FF EGfh W.r LER OF ON ACT f O'4 f:WEf t TO NUMdER NUMBER COMPONENT MALFCi1CT10N SAFE 0? ERAT 103 PRE'.'N MQlJ ITi Correc ti ve CRD 30-03 The pressure swi tch The alarm signal wceuld The swi tch was recalibratt 5065-70 Pressure Switch set point was out not cicar. Scram capa-(PSI-305-130) of calibra tion.
bility not a f f.:c t.-d.
Co r re c t i ve Diesel Generator The air regalator The diaphrara was leaking The diaphram was r eplaced.
5690-77 1/2-6601 diaphran was worn.
air.
Diesel was operable.
Corrective Diesel Generator The solenoid valve The solenoid valve was The valve was r dlAr.ed.
5695-77 1/2-6601 was de fec ti ve, holding the air motor engaged for s tart ing the diesel. Diesel was oper-able.
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UNIT
~2 ft%.iNTZNANCE
SUMMARY
p CAUSE Resulls & LFFLCId W.R.
LER
-OF ON ACTION TAKEN TG NUM3ER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVf.HT REPFitTICN Corrective Diesel Generator The cooling wtr run The indicating light the light was rsso}E.T 4967-78 Cooling Utr Pump light was broken Lwas inoperable. Diesel and replaced.
(2-6601) off in the socket. iwas operable.
Corrective llPC I Steam Supply The valve limits lThe vaive was tort;ued
'i he l i:a i t <. were rese; 5064-78 Viv (2-2301-5) were out of
' out, just orr th, closed and the viv was stro'.c<1 calibration.
seat position. HPCI 3 times, was still operable.
Corrective Refuel Bridge
'lhe tach drive l'cwer was off while lhe set screw was replaced.
5209-78 (2-834) generator coupling moving and lowerina.
set screw was worn. Travel was at fast speed only.
Corrective R0-78-37/03L-0 Rx Bldg. to The solenoid valve The vacuum bkr. valve The solenoid valve was 5276-78 Suppression was worn.
would not open from the replaced.
Chamber Vacuum control room. The Bkr. (2-1601-20A) reduriden t 2-1601-20B valve was opercble.
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IV.
LICENSEE EVENT FEP0r.TS 1he follo.ving is a tabular summary of all license event reports for Quad-Ci ties Uni ts Or.c and Two during the reporting period which were submitted to the com-mission pursuant' to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.S.2. of the Technical Specifications.
Unit One Licensee Event Da te of Re po r t Hu-b e r Occurrence Title cf Deviation R0-78-31/03L 11-22-78 EHC Fluid Pressure Switch Drift Unit Two Licensee Event Date of P.c oo r t Numbe-Occurrence Title of Deviation R0-78-37/03L 11-16-78 Reactor Saildina to Suppress on Chamber Vacuum B reaker A0 2-1601-20A R0-78-38/03L 11-25-78 Drywell vent Valse rail-ure A0 2-1601-23
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V.
DATA TABtlLATIC.1 The folloaing data tabulations are presented in this report.
A.
Operating Data Report.
B.
Average Daily Unit Power Level.
C.
Uni t Shutdowns and Power Reduct ions.
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DOC 1'.T.T ID.
050-254 U!!!T One DATE 12-5-78 COTLETE! DY D. Hannun (309) @ -2241 TELEPl!O:E CPFfATi!G STATUS 0001-781101 2400-781130
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F.eporting pcrio !:
Cro;s hours in ryerting Pc. Icd: 720 2.
Cu rr crit ly or tho, i ed pc..;er level (r.'lt ) :
2511 liax. depen;!. cepaci ty
{
t Dcsiyn cler.trical rct in[(33-N :t):
T.i 9
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(ti'., e-Nc - ). _
760.6.
3 Poviar 1cvt I to thich restricted (if cny) (IP.?e-l et): NA 4.
P.c a sen t, for restrictio., (if any):
This itonth Yr. to Dr.te C urr.ul a t i ve 5
- unber of hours recctor vc
- critic:'l 7_20 7717 __
_L(c.g 6.
P,cactor reserve shutdo.:., hours 0
0 3 3,2 9,.,{.,
720 7573.1 44198.9 7
Hours cen6rctor on lina 0
45.2 889.4 8.
Unit reser.e shutdoin h2urs.
1166192 15334974 07612049
.s 3,.
G ross ther.ma l energy genera tcc,, ( P.,,.,, f 349519 4785253 28208969 13.
Gross electrical cr.gercy Ocnc' rated (!'.llH) 11.
Not electrics! Energy Generated 310398
!d3953.L 26311109 12.
P.ecctor service factor 100.0 96.3 80.1 13 Peactor avr ilc'aili ty fac.ter pn n Q,
a g_
14 Unit service factor 100.0 94d_
76.p_.
15 Unit availability factor 100.0 95.0 77.5 16.
Unit capactly f actor (Usirc tiDC) 56.1
,,_J.1 _4_
JSu..
S 17.
Unit ct.pacity fector (U s i n;; De s. IP.h.)
5 4. 6_,,
61._6 _,
___,1l.J 10.
Unit f orc.<:d c 't c.'e re tc o,a.__
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O!!iT Two
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I:/,Tc 12-5-78 CO:1PLETED L'l D. Hannum 5
TELEPHO::E (309) (5 -2741
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o'EPAYI::G ETATUS 0001 781101 2400 781130 J.
Reporting period:
Gro:s hours in reportina Pc.Iod:720 2.
Currentl'/ author hed pcuer level (In!:):
51 1_
_ _ !ia,:. depene!. capaci t y (r.',l -t:e t) :
_ 7f..e.n Dc'.ign electrical ritinD (M'c-I!ct):.._J.b. 9--
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Pc,.: r level to (:hich rest ricted (if z ny) (inte-!!ct):
ilA h.
P.c a s on t.
for restrictica (if any):
Thi s licrith Yr. to Date Cunulatiue
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- ucher of hours recctor was critical 720 6427. L 41l'37 6.
Re ctor reserve shutdo.c., hours
- 0. 0 111J,,,,
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7 Ho.trs gendrator on lina 720.0 6281.1 (2]iS_.fi,_
C.
Unit reserve shutdc./.ia b:urs.
0.0 128.2 702.0
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- 1., Grc.:s the rr.n. l energy c,onc. rated (IM.'H) 1507661 13190712 37054905 10.
Gross electrical engerg'/ sencrated (.H) 467115 4122984 2795f-ho9 445196 3917502 26252850 11.
?;et electrical Energy Generated 12.
Ec:ctor service factor 100.0 80.2 78.0 13 P.ecetor cvailc. bill fy fector.
100.0 L (t.,
8 'L_4. _
10.
Unit scrvice factor 100.0 78.4 7_ 4 0. _ _.
i 15 Ur. i t cva11 ability fcctor 100.0 80.0 75 2..~.
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Unit capact iy factor (0:in; l100) 80.4 Q.6___
51._6_.. _
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17 Ur.it cet.ci ty f: ctor (Using Das. ra!c) 78.4 61.9 58.1 10.
L'n !. forc<.d ou:.r :2 rate Le_ _
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10.0 17.
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20.
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. June 1976
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Ural t 0,e bl Date 12-7-78 f.
Co:.ipleted by D. !!cnnu:n I
Tclophone. (309) (54-2241
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flovembe r v.
DAY AVERACE CAlLY POWER LEVEL' DAY AVERAGE DAILY POUER LEVEL (fiU3-Itct )
.)
(tjye-g;c g )
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351 37, 490 1
- i 2.
322 488 18-g 3.
296 gg, 49 n
4.
286 20.
509 o
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5.
297 21 540 4,,
6.
297 22.
49')
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7.
305 23.
490 u,
6.
302 24.
491
'l 290 tj 9.
25 485
'q 10.
295 26.
4 71 11.
478 27, 492 I
- 12. __
28.
532 478 t
13.
478 29.
519 n(J ia.
494 33.
47, 7
15 499 33, J
% i-e a u v - t 16, 492 n
Juil 2 0107J.
INST!!UCTIONS
Q,.
On this fann !ct the nerar: dey w.it pov.e: !:s.;; !n :y'<..'?ct for ca.h c'a in die rptim nE $~A~'m m d
ne.,at v.4m:c r..y war.
E6chC fl[UfLS Y.nii le L: sed Ist f v! :t pgaph fot (;;je ggppy;jf.g 11!;,f;d). 'lo!g* (ft s! g hegt g.,,3xjras.;n,87;;;nj;hjg,gp,,cjg ;
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/T APPENDIY 0 P.cv i s i on 4
{b AViRAGE DAILY UNil-PO. R LEVEL
. June 1976 i
Docket tio.
050-265 fo Unit Two Date 12-7-78 a
Completed by D. Hannum Telephone (309) 654-2241 1j M0fiTH November DAY AVERAGE CAlLY P0k!ER LEVEL' DAY AVERACE DAILY P01!ER LEVEL l
(title-fle t )
(MWe-fle t) a 1.
527 17.
721
~1 2.
498 18.
711 q
3.
513 gg, 712
-h 4.
457 20.
735 n 0 5-2i 76i 6.
532 22.
730
[.
7.
621 23 454 8.
623 24.
544 9
733 25, 610 l
10.
551 26.
688
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403 27 730 I
12.
467 28.
757 13.
546 29.
769 14.
612 30.
736 E'
15 691 31.
aeeauvEC 16.
725 JUN 2 01976 O
INSTRUCTIONS On this farra. l.st th: :verage du!y tmit power lael it..'!We Net for cach day in the r: porting nbrhk.,h:6biIIse ricatest whu!: :acpw.tt.
These li oro will te ined to I ut a paph for c.:.h reporting month. Note that when nuxirnum d:p nd:b!c car cityis t
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used ter the net deetrie.il r: ling et the umt. th:re cuy be otesaons when th.: ddly nerage power inct exceeds rh-1001 hoe (or the entrured Power lew! Enc). la sus cases, the.iverar.: d.i:!y umt pawer output sheet s'.ou!J Lc
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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.
B.
Control Rod Drive Scram Timing Data.
A.
Main Steam Relief Valve Operations 1.
There were no main steam relief valve operations performed during the reporting period.
B.
Control Rod Drive Scram Timing Data f.,r Units One and Two 1.
The basis for reporting this data to the Nuclear Regulatory Commission is speci fied in the surveillance requirements of Technical Spec!fications 4.3.C.1. and 4 3.C.2.
The following table is a complete summary of Units One and TWo Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.
AVERAGE TIME IN SECONDS AT Max. Time NUMBER
% INSERTED FROM FULLY WITHDRAWN for 90%
DATE OF RODS 5
20
> 50 90 Insertion DECSRIPTION Techni ca l Speci f icat ion 3 3.C. I. &
0 375 0 900 2.00 3.5 7
3 3.C.2. (Average Scram insert Tie:
11-3-/8 89 0.29 0.66 1.43 2 53 N-9 Hot Scram Time 5 95 Seq. B.
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a Vll. REFUELING INFORMATION The following information about future reloads at Quad Cities Station was re-
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quested in a January 26, 1978 licensing memorandum (78-24) f rom D. E. O'Brien to C. Reed et. al. ti tled "Dresden, Quad-Cities, and Zion Station - NRC request l
for refueling information dated January 18, 1978.
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QTP 300-532 Revision 1 QUAD-CITIES REFUELitiG Herch.1973 liiF0?J:ATIGt! REQUEST 1.
Unit:
1 Reload:
4 Cycle:
e 4
2.
Scheduled date for next refueling shutdo in:
Januarv 17. 1979 (Shutdown ECC4) i 3
Scheduled 'date for restart following refueling:
Apr'il 12, 1979 (starti:p 207 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 subnitting proposec! licensing action and supporting Informa tion: The QC1 R4 licensing submittal'Is scheduled for'llov. 11, 1978.
- 6. ~ Important licensing considerations 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:
Retrofit 8 x 8 fuel '(192) a) nat. U at bundle top and bottem. -
b). two l a rge r wa te r rods,
c) new enrichment distribution.
Last Test Assemblies (4)
~
for GE PCI-resistant design. development program.
7 The number of fuct assemblics.
a.
!! umber of assemblies in core:
724 b.
?! umber of assemblics in spent. fuel pool:
ISI 3.
The present l'icensed' 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 assemblie -
e a. Licensed storage capacity for spent fuel:.
t tM
{
~
licensed storage:
f!cne b.
Planned increase in 9
The projected dete of the Icst refueling that can be discharged to the spent fuel i col nss rain; U:e nresent licensed ccracity:
Last re fuel ing date with present cepecity:
March, SS.
(end of batch discharge c:,pabili ty) l
++
h W@
w g
QTP 300-533 RELOAD LICENSlilG PACKAGE Rcvi Sic;1 1 PREPARATION SCllEDULE liarch 1973 UNIT 0.1 ItELOAD ~~ h CYCLE
~'s t
- ACTIVITY DATE RESPONSIBILITY CENTER flFS receives draft Licensing Submittal f rom GE
'15/76 CE
!!FS Transmit copy of draft to Station for Comments l
flFS Transmit NFS and Site coarr.cnts/ questions to GE
/29/78 NFS De_ni n Tech. Sohc.bcnnes_, Sa fety Eva.lunt Ica_and Ceves-.Le t t a'~
(1 fifS receives final Licensing Submittal and answers to Ceco questions from CE U/30/73 NFS Complete final NFS revievi n f t_l cons i nn_ Sub,f r e.,1 anA snswar
_,n errA i m t. inn-1/1/78 ftFS Transmit complete package for on/off site ro.vl ew '
1/3/73 Statio[1 On-site review completed l1/6 //8 PSA 0Ff-site review comninend ANI NLA Completed licensinn nnekann enrofund by Mnc l
11/11/78 p.
1/12/79 Anticipated unit shutdown 90 days 28 days 1
i.
O 2/9/79
' Receipt of operating License i
3/9/79 Anticipated Unit Startup - Assumes 56 day outage 8
wecks i
NFS/0WR
~
. Prepared by nc Date' 12/23/77~.
PRELininARY CHECXLIST FOR RELCAD LICENSE AniMCM quad-Cities 1 i UNIT:
4 i RELOAD:
CYCLE:
5-}
Require Changes i
item page i.
Generalize wording and 4
X Scram Reactivity reference the submit.
HE00-XYXYY Hone. Adequate. pressure Safety Valve Setpoints 1.2/2.2-1 margin.
HA LSSS 1.2/2.2-2.3 Hone, if the' peak vessel pressure is 1325 psig. during HA Bases S.V. sizing trans.
3 2/4.2-14
' Change to (.65w+XX) as regid.
RBM Setpoints 3 2/4.2-7 Change operability to'XX%
X LCO 3.2/4.2-8 Change Reference 1 to NEDO-X
' Bases XXXXX.
Auto Flow Control Stability analysis not 3 3/4.3-5 Hone.
HA LCO limiting.
~'
3 3/4.3-11 None.
NA Bases g
i 1
MAPLHCR
- Revise curves to reflect Fig. 3 5.1 X
LCO
.-(shts. I to 3) new analyses.
~
3 5/4.5-14
- Change references to reficct
.new analyses of ME00-24046.
X Bases new values:
- l.XX (7 x 7) 3 5/4.5-10 1.XX (3 x S)
MCPR X'
LCO 1
3.5/4.5-14 ceneralize description of 1
B Bases limi ting tre.nsient(s).
l'..PLHGR r.h. gns a re being handled un de r separa te cover.CP? p2nalty f O t r:cludes addi t ional C.XX
( ':C ir;:ce in 1 i:.e::s i ng ; os i t i on).
.....,,.,. ;,., ; ; a. c a.n.. ;n.....
QTP 300-S32 s
Revision 1 4
QUAD-CITIES REFUELit!3 March 1978 i
I INFOP.MATION REQUEST i
?
A 1.
Uni t:
2 Reload:
4 Cycle:
s (next outage) 2.
Scheduled date for next refueling shutdown:
September 30,1979 (shutdc n EOC4)
I.'.
3 Scheduled date for restart following refueling:
Jahuary'20.1980 (Startup' BOC5) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: Simlar Tech. Spec. changes
~
to Re'ioad 3 Cycle 4.
Scheduled date(s) for submitting proposed IIcensing action and supporting 5
informa tion:
Reload Submittal to be provided approximately 30 days prior to shutdown.
Important licensing considerations associated with refueling, e.g., new or
. J.
- 6. ' different fuel design or supplier, unreviewed design or performance analysis methods,, significant changes in fuel design, new operating procedures:
New fuel designs:
Retrofit 8 x 8 fuel (approxicately 196).
t s.-
1 l.
'.7 The number of fuel assemblies.
a.
Ilumber of assemblies in core:
j724 745 -
b.
Number of assemblics in spent fusi pool:
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed s:orage capacity that has been requested or is planned in number of fuel assemblies:
Licensed stcrage capacity for spent fuel:
1460 a.
None.
b.
Planned increase in licensed storage:
S.
The projected da:e of the last refueling that c:n be discharced to the
~
spen t f uel root essuriing the present licensed capacity:
Last refueling dL:c.:ith
' y:
Sen:er:be r. 3 5_.
present cap,.
'WWW.
.m
---4 e
es
RELOAD LICENSING PACKAGE QTP 300-533 PREPARATION SCHEDULE Revision 1 O'll T OC 2 P. arch 1973 RELOAD 3
CYCLE 4
ACTIVITY DATE RESPONSIBILITY CENTER 10/6/77 CE NFS rcccives draf t Licensing Submittal from CE Transmit copy of draf t to Station
!!FS for comments.
NFS Transmit NFS and Site comments / questions to CE Begin Tech. Spec. changes, Safety 10/20/77 NFS F. valuation and Cover T,etter.
GE NFS receives final Licensing Submittal and answers to CECO questions from CE.
11/3/77 NFS Comnlete finni NFS review of T3censine Ruhmierni,na nnswers to CFCo nundrion.
11/8/77 NFS Transmit complete packac,e for on/off site review 11/16/77 Station On-si te review complored 11/18/77 PSA Off/ nite review complernd 12/1/77 NT.A Completed T,1censinn oncience recof vod by MM 90 days 1/16/78 Anticipated unit shutdown 28 days 3/5/78 Receipt of operating License Day outage j
Anticipated Unit Startup - Assumes 8
Weeks 3/1.5/78 Prepared by
.T A S.
NFS/ SWR Dr 2/?'l/ 73
, (final)
\\.
-PRELIMi.';A's.Y CHECKLIST FOR ?.ELOAD LICE!!SE ntEl:D."E iTS I
U llT:
0.ua6 Cities 2 RELCAD:
3' l CYCLE:
4" j I
Require Changes I t e.7 page a
1..X Scram Reactivity 4
Generalize vording and reference the submit,
!!E00-24063
~
s Safety Valve Setpoints 1.2/2.2-1
!!one. Adequate pressure
!;A L555
\\,
margin.
1.2/2.2-5,3 Clarify and add bounding X
Bases'"
peak pressure.
RBM Setpoints 3.2/4.2-14 Change to (.65w+42)
X LCO 3.2/4.2-7 Change operability to 30%.
3_.2/4.2-8 Change Reference 1 to
'X Bases
- t)EDO-24Cb3 Auto Flow Control trone. stability analysis
.3 3/4.3-5 IIA LCO not liraiting.
-i 3.3/4.3-11 t!one.
flA '
Bases -
1 1
MAPLHCR ARevise curves to reflect X
LCO Fig. 3 5.1
~
(shts. I to 3),
new analyses.
Change references to reflect-1:
3 5/4.5-14 X
Bases new analyses of ffEDD-24046.
,~
.A..
1 23.5/4.5-10
- ew values: 5*1.33 (7 x 7)
MCPR l.35 (8 x 6)
.X LCO 3 5/4.5-14 ceneralize description o' Cases A.
limiting :ransient(s).
I
- PLHO?. chme,;es are being handled undce separate co /cr. crror.4ccident In:Iudes addi tion 2! 0.XX CP?. penal ty fc.r Fu:1 Lead,in ;
b ~. I n te r i ra 1 i cca,i n'. ?r.IIIoA)-
..yy
. es
Vill 6LOSSARy The following abbreviation which may have been used in the liontN'y Report, are defined belos:
t Control Rod Drive System CRD Standby Liquid Control System SBLC Main Steam isolation Valve MSIV Residual Heat Removal System RHRS Reactor Core isolation Cooling System RCIC 4
High Pressure Coolant injection System HPCI Source Range Honitor SRM Intermediate Range Monitor IRM LPRM Local Power Range Monitor Average Power Range Monitor APRM Traveling incore Probe TIP RBCCU Reactor Building Closed Cooling Water System Turbine Building Closed Cooling Water System TBCCU Rod Worth Minimizer RWM SBGTS Standby Gas Treatment Systera HEPA High-Efficientry Particulate Filter Reactor Protection System RPS Integrated Primary Containment Leak Rate Test IPCLRT LPCI Low Pressure Coolant injection Mode of RHRS RBM Rod Block Monitor Boiling Uater Reactor bur In-Service Inspection ISI itaxinua Permissabic Concentration MPC l
..._.,.__.-___,_.y
Primary Containment isolation PCI Shutdoan Cooling Mode of RHRS SDC Local Leak Rate Testing LLRT Maximum Average Planar Linear Heat Generation Race
!!APLHGR Reportable Occurrence R.O.
Drysell DV Reactor RX Electro-Hydraulic Control System EHC Minimum Cri tical Power Ratio MCPR PCIOMR Preconditioning Interim Operating Management Recommendations Licensee Event Report LER American flational Standards institute ANSI National Institute for Occupational Safety and N10Sil Health Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Moni toring l
l l
I i
a f
gi r