. ,
QUAD-CITIES tiUCLEAR i'0WER STATION
UNITS 1 AND 2
MONTHLY PERFORMAt4CE REPORT
JULY 1979
COMMONWEALTH EDISON COMPANY
AND
1OWA-ILLItiOIS GAS & ELECTRIC COMPANY
tlRC DOCKET t10S. 50-254 and 50-265
LlCENSE fiOS. DPR-29 and DPR-30
790823o4M
784a11
. .
TABLE OF CONTENTS
1. Introduction
11. Su:..na ry of Opera ti ng Experience
A. Uni t OneB. Uni t Two
Ill. Plant or Procedure Changes, Tests, Experiments, and Safety Rela *edMaintenance
A. Ammendments to Facility License or Technical SpecificationsB. Facility or Procedure Changes Requiring NRC ApprovalC. Tes ts and Experiments Requi ring NRC ApprovalD. Other Changes, Tests and Experiments
1. Facility Modifications2. Special Tests
E. Corrective Maintenance of Safety-Related Equipment
IV. License Event Reports
V. Data Tabulations
VI. Unique Raporting Requirements
A. Main Steam Relief Valve Operations
B. Control Rod Drive Scram Tining Data
Vil, Refueling Information
Vlli. Glossary
'2 @l3.'$.2
. .
1. INTRODUCTION
Quad-Ci ties Nuclear Power Station is composed of two Boiling Water Reactors,
each wi th a Maximum Dependable Capaci ty of 769 tiWe 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 construction contractor was Uni ted
The condenser cooling method is a closed-cycleEngineers & Constructors.
spray canal, and the Mississippi River is the condenser cooling water source.
The plant is subiect to license numbers DPR-29 and DPR-30, issued October 1, 1971
and itarch 21, 1972 respectively, pursuant to Docket Numbers 50-254 and 50-265
The date of initial reactor cri ticali ties for Units 1 and 2 respectively were
October 18, 1971 and April 26, 1972. Commercial generation of power began on
February 18, 1973 for Uni t I and tia rch 10, 1973 fcr Uni t 2.
This report was compiled by David Hannum, telephone number 309-654-2241,
ext. 179
"/64213
,
11. SUMMARY OF CPERATitiG EXPERIENCE
A. Unit One
July 1: Unit One began the reporting period opera ting at 547 MWe. Load
was increased to 650 MWe immediately after the main condenser
flow reversal was completed.
July 2 - 3: Load was steadily increased to 791 MWe and held.
July 4: Unit One was reduced to 550 MWe for main condenser flow reversal.
Load was subsequently increased to 750 MWe.
July 5 - 20: Uni t One held an average load of 791 MWe. On July 8 load was
reduced to 700 MWe for main condenser flow reversal . On July 14
load was reduced to 691 MWe for weekly turbine testing.
July 21: Electrical load was reduced to 150 MWe for an on-line control
rod sequence exchange. Upon successful completion of the
sequence exchange, load was increased at a rate of 100 MWe/hr
to 400 MWe.
July 22 - 31: Load was steadily increased to 790 MWe and the unit held an
average load of 775 MWe. Electrical load was reduced on July 27
and 28 to 635 Mye in order to remove a condensate demineralizer
from service to change the filter elements.
7 @i23_4
B. Unit Tv:0
July 1. Unit Two began the reporting period operating at 625 MWe.
July 2 - 24: Unit Two held an average load of 575 MWe. On July 4 load was
reduced 100 MWe due to 'ow systen electrical load demand.
July 25: The drywell was deinerted and load was reduced to 290 MWe for a
drywell entry. The torque switch on the MO 2-1301-16 RCIC
steam supply valve operator nalfunctioned and had to be replaced.
July 26 - 31: Unit Two held an average load of 550 MWe. On July 28 load was
reduced to 350 MWe for main condenser flow reversal.
r c s e, z ,),d O ' t fs.21
111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS
AND SAFETY RELATED MAINTENANCE
A. Amendments to Facility License or Technical Specification
There were no amendments to the f acility license or Technical Specifications
during the reporting period.
B. Facility or Procedure Changes Requiring flRC Aporoval
There were no f acility or orocedure changes requiring flRC approval during
the reportir.g period.
C. Tests Exoeriments Requiring flRC Aporoval
There were no tests or experiments performed during the reporting period
requi ring flRC approval .
D. Other Channes. Tests, and Exoeriments
1. There were no facility modifications completed this month which require
reporting to the NRC.
2. Special Tests
Special Test 1-44
Unit One Reactor Feed Pumo Minimum
Flow Line isolation and Valve Leakage Test
Purpose:
The purpose of this test was to qualitatively determine the magnitude
of feedwater leakage back to the main condenser through the minimum
flow lines and its impact on plant performance.
Summa ry of Sa fety Evalua t ion:
Basic feedwater operation was not altered during the test. Flo safety
related systems, structures, or componenets were involved in the test.
/@ie316
The normal feedwater flow path was not changed and in the event of a
feedwater problem, all ECCS was available to supply water to the
vessel. No Technical Specification itens were affected.
Special Test 2-15
MSIV Limi t Switch investigation
Purnose:
The purpose of this test was to outline the method used to investigate
the performance of the new 740 series MSIV limit swi tches , along wi th
the relocated MSIV limit switches on cutboard valve A0 2-203-2C.
Summary of Safety Evaluation:
The design function and intent of the MSIV's were not altered by this
test. The new switches and relocation have been previously evaluated,
and no new additions were nade to ccmplicate the indicating or protecti"e
functions of the valves. The 10% closure RPS setpoint was not changed
and no LlRT or PCI closure time values were reduced.
E. Corrective haintenance of Safety Related Equipment
The following represents a tabular summary of the safety-r lated maintenance
performed on Uni t One and Uni t Two during the reporting period. The
head!ags 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.
<>>ee((<j'i/# ?. s
UnlT ONE mal hTENANCL SU:'.hA!<Y
CAUSE RESULTS c EFFLCIS
'' R. LER OF CH ACTicN TAKEN TO..
NUMBER NUMBER COMPONENT MALFUNCTICH SAFE OPERATION PREVENT REPETITION
3306-79 79-22/03L Diesel Cen. Oil The fuel oil fil- The line was leaking. The gasket was replaced.Line (1-6600) ter gasket was The diesel was operable. DG was tested satisfac-
worn. tory.
364-79 Rx Bldg Crane The digital weight The digital weight The monitor was replaced
(1/2-5800) monitor was defec- indicator was inoperable. and calibrated.
f*vd.
3620-79 Core Spray Test An aux. contact The valve would not open. The aux. contact was
Valve (1-1402-4A) was defective. Core spray was operable. replaced.
3550-79 Of f Gas liigh Pressure switch The operator received The switch was calibratedPressure Switch needed calibration. the off gas high pres- and tested.
(PIS-1-5441-16A sure alarm. The off gas.
c B) system was operatingproperly.
%ICC?70.s.
do
UNIT T' 0 MAINTENANCE SUMMARY
,
CAUSL RESULlS S LFFtLib
k' . R . LER OF CN ACTION TAKEN TO
N U.'i3 E R NUMBER COMP 0"ENT MALFUNCTION SAFE OPERATICN FREVENT REPETITION
734-79 IRii Ch. 13 The pre-amp a.d Channel 13 was reading The pre-emp and powe r
(2-700) po.;er supply were incorrectly. Other IRM aupply were re-calibrated.out of calibration. channels were operable.
2076-75 CRD 34-15 The accumulator The water level was The accurulator was
(2-300) was defective. excessive. Scram replaced.operability was unaf-fected. __
3551-79 79-13/03L RHR Suction The thermals The valve would not open. The thermals were reset.Valve (2-1001-7C) tripped. This made the 2C n.R pump Amperage checks were made
inoperable. The 2A, 2B and the valve test oper-
and 20 pumps were oper- ated 3 times,
able and available ifneeded.
3593-79 RHR HX Bypass The the rmals t rip- The bypass valve failed The thermals were reset.Valve (2-1001- ped. closed. RHR was still Amperage checks were rade
163) operable with flow and the valve was cycled
through the HX. 3 t i rce s .
AICr4>709E"$.
%
IV. LICENSEE EVENT REPORTS
The following is a tabular sun. mary 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 Date of Title of
Report Number Occurrence Occurrence
79-23/03L 7-18-79 Electromatic ReliefValve 203-3A ControllerInoperable
79-24/03L 7-24-79 Suppression Chamber -Reactor Building Pres-sure Switch PS 1-1622BDrift
Unit Two
Licensee Event Date of Title ofReport Number Occurrence Occurrence
79-13/03L 7-12-79 RHR Pump Suction Valve
MO 2-1001-7C BreakerFailure
79-14/03L 7-23-79 RCIC Steam Supply ValveMO 2-1301-16 Failed toClose
79-15/0lT 7-24-79 Suporession Chamber -Reactor Building Pres-sure Switch PS 2-1622Aand B Dri f t
';B4220
V. DATA TASULATIONS
The following data tabulations are presented in this report.
A. Operating Data Report
B. Average Daily Unit Power Level
C. Unit Shutdowns and Po.,er Reductions
,
D* ' (, ". O f'7 4
4' O ' i / e k f.
I
Crtn ':A M U ID0s T
[ LIT f:9 050-2540
~ ' ' - ~ ~ ~ ~ ~
U::| i Onel g@nQRT A
ng7g 8-6-791 o
O C 0!!Pt.Ei i.D B Y D- H3' "
TELEN:0!!E (309) 654-2241,
Ext. 179c . T '''' '"g , o.. . ._ ; . -o .a m 0000 070179
2400 073179 7 4 ''J. P 2;.or t ing pe r iod : G r o s r. hours i i reporting period:.
2. Current 1' authorized po.ver level ( : tit) : 2511 liax. depend. capaci ty,
(.T1.-::e t) _ 769 Des ign elec t rical ra t inI;~0;Ue-f e t) : 709 .
'
3 F o.. .: r level to v.hich res t ric ted (i f any) (ti',|e-!:2t) . flA _,
h. F.easons for restrictica (if any)
This liont h Yr. to Date Curau l e t i ve.
5 I u- {ie r of hour s reector tras critical 744.0 4022.8 51355.7
6. P.cactor reserve shutdo.2n hour, 0.0 0.0 3329.0 _ , _ _
7 Ecurs geaarater cn line 744.0 3893.9 48836.8 __
0.0 19.8 9.39.2S. Unit re w rve shutdo.n hours.~
1755294 8344962 971523389., G ros s .he rna l c ae rgy gene ra teo. ( .<, ,. ,a, ).
t - . ,
10. Gro :s electrical engercy generated (!n!H) 558445 2642274 312.4769
11. Net electrical Enargy Generated 532587 2489725 29122298
I?. F, 'ac t or serv ice factor 100.0 70.I 81.1
13 P,ecc tor availabi l i ty fac tor 100.0 79.1 86.4
14 Unit service factor 100.0 76.5 77.1. _ _
15 Unit a va i l a b i l i t y .'a c'.t c r 100.0 76.9 78.6.
16. Unit capactiy factor (Using ::DC) 93.1 63.6 59.8
17. Unit capacity factor (Using Des. !n!2) .10.7 62.0 58.3 .
l ?. . U if t forced outc9 rate 0.0 3.7 7.9
19 S h u t d o..:n s sch2duled ovcr n= < t C r enths (lypu, date, an:1 dura t i on of er.ch):
20. If shutde..n at end of report pe riod , es t ina ted d :ta of s tartup;- ilA.* 8
Th2 ti3C r' rf la 1 0.. fr t h r. n 7 9) F.' ' ' d u - i rj p r r i o:i n of hi:;h :.tiaat t e .,1 ? r a t u r e c' i j
|to th' th2rcal p ; .- f o r . o . . c . cf t i. s; rc , cc:.a i , - ,,, ,
1 (i i n < ') % '3 9c,9 G,. tG Gr t in,4 w % ~
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g,;riT t:3. 050-265F Gi 7 ' DD
bd U!:lT hom 1
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G k b HATE 8-6-79lu u Q>.,J u JU J
- -
aCO.MPLET'JD DY D. Hannun
~
TELrpng"; (309) 654-2241,.
Ext. 1790'ERATI:;3 STATUS
0000 070179
3. n_.;:orting period:2400 073179 Gross hours in reporting period: 744_
2. Currently <._ SoH ud poaer level (MWt) : 2511 Max. depend. cepacity(%-::ct) . _yg.; Design elect ri cal r3 ting ( U ffot): 719 .
3 ro..er level to vhich restricted (if any) (mle-!:e t ) : flA _.
4. Ecasons for restriction (if any)-
This ".on+h Yr. to Date C um i e c i ve.
.50361.35 I:un'eer of hours recctor veas. critical 74; a 4984.9 0
6. Reactor reserve shutdo.>n hours 0.0 0.0 2985.8
7 Ecurs generater on 1ine _744.0 4938.7 L30h1.6
0.0 0.0 32.9C. Unit resnrve shutda.n hours..
1400204 10191972 989340969., Gross the rra l ene rgy gera ra ted ("'-|H)-
10. Cro s electrical engercy generated (M'!H) 424099 3168662 31657039
3S2556 2929367 2969082711. !i a t electrical Energy Generated
12. R actor service fcctor 100.0 98.0 80.7=
13 R ector availabili Cy factor 100.0 98.0 85.5
I4 Unit service factor 100.0 _9] .1 77.0
15 Unit availability facter 100.0 97.1 78.1_
IG. Unit capactly factor (Us ing ";c) 66.9 74.9 61.9
17 Unit capacity factor (u . i n a oc,. mtz) 65.2 73 0 60.3
13. Ulit forcc' outa3t rate 0.0 0.7 9.7
19 Shutdo.n: sch2dulud ove r nc x t t conths (Typ", date, and duration of ead)
20. If shutdo-, at e n c' of re,.nrt peri <?d, esti.otel date c f star tu;>: NA<
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bbo 3. - 8-6-7a'-
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g n g l,' }3 @ u(0) s b 3 ceagtet..d by D. Hannum
.
Teleahoae (309) 654-2241,
Ext. 179
II Julvm _9 791*
P .i ; '/ E R AC E C A i L': PC'sER t.EV EL- D AY /,'!ERACE D A ll Y PO!!ER LEVEL
(m. 'e -t ' e t ) (h'Je-fle t )
1. 585 17 755
2. 720 18. 751
756 1 ^u . 7602s.
i. 617 20. 741i
748 21 371'. , .
6 751 22. 587
/. 769 23 722
743E. , 728 24.
_
741 25 749-o
.
744 p .5 7451- __
_
1i. 749 27 678
12. 742 28. 718_ _ _ _
i). 752 29 734
l ', . 750 761
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Doc!ce t I?o. ,0_50-265
) * Unit T.so[)
Date 8-6-79n'
. O ". _y0 1
A Completed by D. Hannumr k-
oJ L( . JL _.]
Telephone J309)654-2241,
Ext. 179.
liONTil July, 1979
DAY AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY POWER LEVEL
(fiUe-Me t ) (fiWe-fle t)
1. 562 17 510
2. 554 18. 513
3 555 19.. 513
5014. 498 20,
5 21 500) 5- _.___f@ .
4886. 550 22.
552 23 4947
- . _
8. 519 - 24. 518
9 '131 25 476
10. 524 26. 503
11. 526 27. 507
12. 522 28. 496
42813 518 29
50514. 522 30,
507 08915 31. n is is aOVE16, 513 ,.~ S oo s,.(ava-a ytjy .2 01976
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VI. UNIQUE REPORTING REQUIREMENTS
The following items are included in this repo r t based on prior commitments to
the Commission.
A. "ain Steam Relief Va. e Ooerations
There were no main steam relief valve actuations during the reporting
period.
B. Control Rod Drive Scram Timing Data For Units One and Two
There were no control rod drive scram timing exercises performed during
the reporting period.
.
# .
1 ' quv .
.
OTP 300-532Revisica 1
QUAD-CITIES REFUILING March 1970INF03 MATT 0N REqu2ST
1. Unit: 1R , l o n. d : 4 Cycle: 5
2. Scheduled date for next re f uel ing shu tdo'...,: J;in u a rv 12. 1979 (ShutdownEOC4)
3 Scheduled date for restart following refueling: Aoril 1?, 1979 (Startup 80C5)
technicaltii l l refueling or resunptica of operation thereafter require a'
specification changa or other license amendment: Yes; See attached checklistfor Tech. Spec. and License Amendment.
Scheduled data (s) for subnitting proposed licensing action and supporting5i n f orma t i on : The QC1 R4 licensing submittal is scheduled for Nov. 11, 1978.
6. Irport:nt licensing considerations associated with refueling, e.g. , new ordif ferent fuel design or supplier, unreviewad design or performance analysismethods, significant changes in f uel desi gn , new opera ting procedures :
New fuel designs: Re t ro fi t 8 x 8 fuel (192)
a) nat. U at bundle top and bottom,b) two larger water rods,
c) new enrichment dist ribution.
Last Test Assemblies (4)
for GE PCI-resistant design development program.
7 The number of fu21 assemblies.
c. Number of assemblies in core: 724
b. Number of assemblies in spent fact pool: 486
? The present licensed spent fuel pool storaga capaci ty and the size of anyincrease in licensed storaga capacity that has been requested or is plannedin number of fu21 assemblies:
Licensed storage capacity for spent fual i r160a.
b. Plann .! increat in licensed storage. None_.
The projea J datt of th la .t refueling that can be dischargad to ths.
spent foal cual .ssuning U.2 present licensed capacity: Last re fue l i n gdate with present capacity: March, 85 (end of batch discharge capability)
-1-
- 3 300r;Pjges&w)g
PRELIMINARY CHECKLIST FCR RELCAD LICENSE AMENDMENTS
UNIT: Quad Ci ties 1RELOAD: 4
CYCLE: 5
'Require ChangesI ''Iten page
Generalize wording and ref.
X Scram Reactivity 4 the submit, NED0-24063
Safety Valve SetpointsNA LSSS 1.2/2.2-1 flone. Adequate pressure marg in.
X Bases 1.2/2.2-2,3 Clarify and add bounding peakpressure.
RBM SetpointsX LCO 3.2/4.2-14 Change to (.652+42)
3.2/4.2-7 Change operability to 3043.2/4.2-8 Change reference I to NED0-
24063X Bases
Auto Flow ControlNA LC0 3.3/4.3-5 None. Stability analysis
not limiting.
NA Bases 3.3/4.3-11 tion e .
MAPLHGR
X LC0 Fig. 3 5-1 5 Revise curves to re flect new(shts. 1 to 3) analyses.
X Bases3.5/4.5-14 '': Change references to re fl ect
new analyses of NED0-24046
MCPR 3 5/4.5-10 New values:**1.33 (7x7)1.35 (8x3)X LCO
Bases 3 5/4.5-14 Generalize description of-
) liniting transient (s),.
MAPLHGR changes are being handled under separate cover.*
"* locludes additional 0.XX CPR penalty for Fuel Loading Error Accident(NRC in terin licensing pos i tion) .
Values unknown at this time are i nd i ca ted a s "XX . . ." .)''
RELC AD L I CE""> l"3 PAC KAGE QTP 300-S33Revi'iel I
a. ' ' O.1P;'.EP/. RAT ION C CHEDULE
March 1973r ~. t_ C l.D ___4
CYCLE 5
D/.T E ?.ESPONS!DlLITY CENTER ACTIVITY .
i
!
!
9/15/78 ! CE NFS receives draf t Licensing Submittal from GE! N FS Transmi t copy of dra f t to Station for Comments||
NFS Transmit NFS and Si te comments / questions to CEnd-Ccv2r Lott"-9/29/78 NFS Benin Toch. S endnge..._S;tf_e t'g_.Eva l u n t ien '
GE NFS receives final Licensing Submittal and answers to CECO questions from GE10/30/78 NFS Canalete final NFS r< view of I i cons i ng subnt e r,1 ,nd :n;wur: to FFI^ ""'"ri'"
-
11/1/78 NFS Transmi t complete package for on/off site reviewi
11/3/73 ! Station on-site review completed -
11/6 B8 PSA Off-site review complcluid\
'
11/11/73 NLA Completed 1* censing onckaca corni ind hy HRC lA
1/12/79 - Anticipated unit shutdown \ 90 days28 days ,
t
i
'
2/9/79 - Receipt of operating LicenseJ, N
wi
CC 1
f.3- Anticipated Uni t Sta rtup - Assumes 56 day outage'
3/9/798 weeks'+'
v -' ;-__ ,m, -
.
_
NFS/Ct/RPrepared by Mr
Date 12/23(11_.
. -1-(final)
QTP 300-532. .
Revision 1C:UAD-C IT I ES '< eft:iL i h0 tiarch 1973
t h,~0RMAT I O:. P.Er U ESTs
1. Unit: 2 Reload: 3Cycle. 6 (o,+ ,ge in progress)
2. Schedulen date for next refueling shutdo.in: Januarv 15. 1478 ( shutdownEOC 3)
3 Sch2duled date for restart folic.Ing refueling: March 15. 1978(Startup BOCh) (In progress; See below for next outage)
l. Uill refueling or resumption of operation thereaf ter requira a technicali
specificatica change or other license emendment: Yes; See at tachedchecklist for Tech. Spec. and License Amendments.
5 Scheduled date(s) for submitting proposed licensing action anc supportinginforration: The QC2 R3 licensing package was t ransmi tted on Dec. 2, 1977
6. loportant licensing considerations associated with refueling, e.g. , new ordifferent fuel design or supplier, unreviewed design or performance analysisra thod s , signi fican t changes in fuel design, new operating procedures:
None. (180 2.62 w/0% 8 x 8's) .
7 The nu ber of fuel assenbites.
a. Nu.ber of assemblies in core: 724 (before EOC4 discharge)
b. Number of assemblies in spent fuel pool: 230 (before EOC4 discharge)
S. Tha present licensed spent fuel pool storage capacity and the size of anyi n c r e.-i s e in licensed storaga capacity that has been requested or is plannedin nun % r of fuel assemblies:
a. Licensed storage capacity for spent fu21- 1460 *
None.b. Planned increase in licensed storage:_
D. T he praject H date of t;. last refueling that can be discharged to th2
spent fuel pNI a,suling th2 pres 2nt IIuJ:nsed capacity: Last refueling date with
present capacity: September, 85
-1-*,
b 's rs c,( /s d
-,_
P ELIMINARY CNECKLIST F03 RELOAD LICEN5E /'tENDMENTS. .
"
UNIT: 0.uad-Cities 2'
RELCAD: 3
CYCLE: 4
'Require Changes'1 ten Page
Scram Reactivity 4 Generalize wording and<
reference the submit,
NEDO-24063
Safety Valve SetpointsNA LSSS 1.2/2.2-1 None. Adequate pressure
margin.
X Bases 1.2/2.2-2,3 Clariff and add boundingpeak pressure.
RBM SetpointsX LC0 3.2/4.2-14 Change to (.65w+42)
3.2/4.2-7 Change operability to-30%.X Bases 3.2/4.2-8 Change Reference 1 to
NEDO-24063
Auto Flow Control% LCO 3.3/4.3-5 None. Stability analysis
not limiting.
NA iases 3.3/4.3-11 None.
s
MAPLHGRX LC0 Fig. 3.5.1 & Revise curves to reflect
(shts. I to 3) new analyses.
X Bases 3.5/4.5-14 5 Chance references to reflectnew analyses of NECO-24046.
MCPR , 3.5/4.5-10 New values: 21.33 (7 x 7)1.35 (8 x 8)X LCO
Bases 3.5/4.5-14 Generalize description of'
liniting transient (s),a
' ftiPlilGR ch anga are bein,, handled under separate cover.I n cl udes .::dd i t i ona l 0. XX CPP, penpity for En:1 loadin, Error Accident(NTC in terir: l i c en . i n e, :m i ti on)
r 9 'r, o a'' #U ik''
;8'.JS U ll'-' il ' |n d t thi< ti . ire i r J i c. te'J as ''XX.
Rt. LOAD LICENSING PACKAGE QTP 300-533vi' ion 1
': | T OC 2 PP7.PARATl0 S C H E DlJ L t i.
"arce 1973_ A2 -- 3<
s.'
;Y C '_ E 4
DATE RESPONS!BILITY CENTER ACTIVITY.
|.
10/6/77 i CE' NrS receives draft Licensing Subnittal from GE Transmit copy of draft to Station ,
| UFS for co= lent s .I
!,
t'i'S Transmit flFS and Site comments / questions to CE 13egin Tech. Spec. channes, Safety10/20/77 I NES Evaluation and Cover Letter.
I GE til/S receive 1 final Licencing Submittal and answers to CECO questions f r or.i C E .
__11/3/77 f "FS Camplete final tir9 revi eg_c f I (c.gnyino 9ub"Irrn1 w1 an tam r s t o Pfro <murrinni
; 11/8/77 i NFS Transmit complete packae,e for on/off site review
11/16/77 Station on-site reviou compiered
PSA Offesite review comnleted!,_ ___ _11/18 / 7 7,
12/1/77 NLA Completed Licensino packnee receiver 1 by NRP
[90 days
1/16/78 - Anticipated unit shutdown,
i| 28 daysi
.
j 3/5/78 - Receipt of operating License
!.
Day outaget ,i
;' 3/15/73 - Anticipated Unit Startup - Assumes 8 Weeks.
il M ,
!L @,~,
N -
[, Prepared by JAS . NFS/UWR-
Date 2/23/78,
. -1-(final)
