ML20137B658

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Monthly Operating Rept for May 1978
ML20137B658
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/31/1978
From: Graves R, Kokoszka C
CONNECTICUT YANKEE ATOMIC POWER CO.
To: Volgenau E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20137B401 List:
References
FOIA-85-723 CYH-78-156, NUDOCS 8511260324
Download: ML20137B658 (11)
v • d • e


Text

i-CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTilLY OPERATING REPORT NO. 78-5 FOR Tile MONTH OF MAY, 1978

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L PIANT OPERATIONS 1-

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4 The following is a chronological description of plant operations for the month of May 1978.

5-1-78 Commenced load reduction at 2100 hrs. to remove IB Steam Generator feed pump from service. With Load at 275 MWe the steam generator feed pump was j '

at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br />.

shutdown at 2316 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.81238e-4 months <br />.

Increased load to 300 MWe 5-3-78 Following repair of the inboard motor bearing (IB steam generator feed pump) a load increase was started at 0235 with full power being attained at 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br />.

An automatic reactor and turbine trip occurred due to a simulated loss of flow on #1 and #2 RCP's while turning 4160 voltmeter selector switch from position 1 to 2.

The simulated flow signal was caused by circuit interference.

5-3-78 Reactor returned to criticality at 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br /> and turbine rolled and generator phased to line at 1651 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.282055e-4 months <br /> on 5-3-78.

j) 5-4-78 Full. power was achieved at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br />.

i 1-5-9-78 "B" Charging Pump was removed from service to repair I

a leak in the recirculation orifice bypass valve.

The pump was returned to service on 5-10-78.

5-15-78 IB Isolated Phase Duct Cooling Fan was out of service (0945 to 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br />) to inspect the motor bearing.

5-17-78 The diesel fire pump was taken out of service (0800 to 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />) to inspect the radiator. The t

radiator passed. inspection and the pump was returned i

to service.

5-19 "B" Isolated Phase Duct Fan was taken out of service at 2350 on 5-19-78 to 1315 on 5-20-78 for maintenance to change the motor bearing.

t 5-20-78 Tested EC-2A and EC-2B following plant design change

  1. 276 on 5-20-78.

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i 5-22-78 Shifted operation of the main lube oil cooler I

from "B" cooler to "A" cooler due to an oil leak on "B" cooler.

5-23-78 River effluent monitor out of service (1245 to 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />) for cleaning.

5-24-78 Motor on fire main MOV-31 installed and tested.

5-30-78 Emergency diesel generator 2B out of service (0930 to 1505) for maintenance check of redundant systems.

5-31-78 Emergency diesel generator 2A out of service (0700 to 1441) for maintenance check of redundant systems.

Added resins to #1 and #2 water' treatment capsules.

1B charging pump out of service 0700 on 5-31-78 to 1305 on 6-1-78 for'recire valve replacement and pressure gage isolation valve weld repair.

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1 CHE4ISTRY DATA FOR MONTH OF MAY 1978 Reactor Coolant Analysis Minimum Averace Wximum Ph 8 25 C( 2.0E-01) 6.60E+00 6.70E+00 6.45E+00 Conductivity, unhos/em( 25) 9.707.+00 1.47E+01 1.90E+01 Chlorides, enm( 7.0E-02) 3.0 E-02 3.0 E-02 3.0 E-02 Dissolved Oxveen, nob (tS.0E+00) 00 E+00 00 Et00 00 E+00 Boron, com ( 25)

7. 01E+ 02 8.28E+02 8.99E+02 Lithium, com ( 55) 1.12E+00 1.39E+00 1.85E+00 Cross Decassed Act.,pCi/ t1( 2,0E-02) 1.16E+00 2.42E+00 5.02E+00 Iodine-131,uci/m1( 35)

'6.71E-02 1.47E-01 6.80E-01 I-131/I-133 Ratio 2.59E+00 3.77E+00 8.08E+00 Crud, mg/1( 1.0E-02) 5.00E-01 7.33E-01 1.00E+00 Tritium, uCi/m1( 5.0E-02) 3.05E+00 3.56E+00 4.35E+00 Ittd rogen, ce /k c( t2. 0E+00 )

2.06E+01 2.79E+01 1.46E+01 Aerated liquid vaste processed:

8.83E+04 gallons Waste liquid processed through Boron Recovery System:

0.00E+00 gallons Average primary plant leak rate:

.106 gpm Primary to secondary leak rate:

0.00E+00 gpm e

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MALFUNCTION St --

TAKEN TO PREVENT FOR REAR 9 1 SAFETY.

CCMPCNE CAUSE RESULT OPEhe.< ION REPETITION DURI.

R2 PAIR

. f Nuclct;r Instrumentation Failed Offset D' rift in % Full None Replaced Coriplete NIS Power By Procedure M 8.2-1

'i Sy; tem Channel 33 Power Adjustment Power Display Range Drawer

" Nuclear Instrumen'ta-IRanE2 Drawer Potentionmeter tion Drawer Replace in the Full ment".

g Power Amplifier Circuit Board.

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SYSTm ON CQRRECTIVE ACTION TAKEN TJ PROVIDE l!

0-MALFUNCTION S*

TAKEN TO PREVENT FOR REAR 9R S4FETY.

l CCMPO M.7 CAUSE REStJLT OPENION REPETITION DURIs. REPAIR 1;

, j ' Firo Main HOV 31 Misadjustei Motor Burned Up None Replaced Motor And Adjusted None Required l

Limit Switch Limits

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lj W:ste Gas Decay Tank Improper Release Valve None Replaced Valve None Required TK-60 B release Scating ll60-B-2 li i Valve #1160-B-2 Leaking By I

- B'Chtrging Puma Eresion of Leaking Bypass None Replaced Valve Ran Other I

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Orifice Bypass Valve Bypass Valve Valve Charging Pump Body, seat &

to prove operability' I

plug of redundant systems t

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OPERATING DATA REPORT DOCKET NO 50-213 DATE t>/ 6/ 7 8 COktPLETED By C. Kokoszka TELEPilONE (203) 267-2556 OPERATING ST ATt*S i

Connecticut Yankee Not*5 1

1. Unit Name:
2. Reporting Period:

Ffay, 1978 1825

3. Licensed Thermal Power iNibri:

600.3

4. Nameplate Ratin;IGross Nibe s.

575 l

5. Design Electrical Rating eNet \\1Wei:

577

6. Stasimum Dependable Capacity eGross.1Wel:

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7. 5!admum Dependable Capacity iNet Sthen:
6. If Chan;es Occur in Capacity Ratings iltems. Number 3 Through 7) Since Last Report. Gise Reasons:

None

9. Fower LeselTo which Restricted.lf AnvINet SIWei:

None S ne

10. Reasons For Restrictions.!f Any:

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This Stonth Yr. to.Date Cumulatise

11. Hours la Reporting Period

_ 744.0 3,623.0 91,295.0

12. Number Of Hours Reactor was Critical 742.4 3,548.3 78,585.6
13. Reactor Resene Shutdossn Hours 0.0 74.8 832.5 I
14. Hours Generator On Lin, 741.2 3,446.9 74.494.3
15. Unit Resene Shutdown Hour, 0.0 74.8 74.8
16. Gross Thermal Ener2y Gecerated tilwH, 1,321,761 6.056.119 127,878,678 434,440 1,997,293 42,091.592
17. Gross Electrical Ener;> Generated iat%He
18. Net Electrical Energy Generated <>thHe 415,071 1,904,894 40,032,356
19. Unit Senice Factor 99.6 95.1 81.6 99.6 97.2 82.5 j
20. Unit Asailability Facto,
21. Unit Capacity Factor itsing ilDC Nei, 101.4 95.6 81.4 97.0 91.4 75.3
22. Unit Capacity Fae:or sLsir.g DER Nets 0.4 2.5 8.3 i
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Oser Nest 6 Stonths eType.Date,and Duration of EJehi:

None

25. If Shut Down 4: End Of Report Period. Estimated Date of Startup.

N/A

25. Units in Test St2tus iPrior to Commercul Operations.

Forecast rehiesed (Not Rer{uired)

INITI \\ L CRITICA LITY

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INITI \\L ELECT RICITY COttstERCI L L OPER \\ TION (9 t*

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' 4, AVEREGE D tlLY L* NIT PO%ER LEVEL DOCKET NO.

50-213 Conn. Yankee t,g37 Iladdam Neck l

DATE 6/6/78 COMPLETED BY C. Kokoszka TELEPHONE (203) 267-2556 May, 1978

. MONTH DAY AVERAGE D AILY POhER LEVEL DAY

\\VERAGE D AILY POhER LEVEL 4

e MWe-Net s sy w,.yes, I

561 604 2

342 is 604 3

530 604' 3,

4 439 20 603 592 602 5

604 600 6

604 7

,3 600 3

g 603 599

,4 603 600 9

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10 602 599

,6 602 600 603 598 12 g

13 603 596 2,

603 591 34 30 604 587 15 3

16 604

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INSTRL'CTIONS

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v UNITSliUllC. INS ANI.*0'VER RE3UCT10NS EKET NO.

50-213 i.

I UN*T NMIE Conn. Yankee DATE 6/6/78 May, 1978 COMPLETED ilY C.

Knkoc.7 h REPOR illON111 1 El.l.PilONE (203) 267-2556 i

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78-05-04 F'

2.8 H

3 b'hile turning 4160V Bus voltmeter switch from "0FF" to position i

1 & 2, fuses supplying Loop #1 & #2 flow indication blew causing loss of flow reactor trip.

Replaced blown fuses.

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I.n.cJ Reamn; k'elluml; I. !nhis G. Ins :usen.nis S LI.cJ a.!cil A-1:ipnpment I ailine Il.splain) 14! annat l'.

Pacpause.in ut Data l

Il41.sintenansc.is l'est

.' Alannal Ses ant.

I nte>.Slicces f.n l isernce C Relucimg

.t. Ant nnatic Strain.

I sent 1(ep.no il I !(l! ile (NilRIE D Regnist.n) Restsletzun

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L REFUELING INFORMATION REQUEST I ~

1.

Name of facility.

Connecticut Yankee Atomic Power Company 2.

Scheduled date for next refueling shutdown.

February, 1979 3.

Scheduled date for restart following refueling.

Approximately six weeks from shutdown date.

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

No.

Connecticut Yankee Technical Specifications are reload independent.

If answer is yes, what, in general, will these be?

N/A If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes, see answer to 4 above.

If no such review has taken place, when is it scheduled?

N/A 5.

y Scheduled date(s) for submitting proposed licensing action and supporting information.

There are no scheduled dates because of (4) above.

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.

None 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 157 (b) 288 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.

1168 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

1994 or 1995

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2 i C' CONNECTICUT VANKEE ATOMIC POWER COMPANY tIADDAM NECK PLANT L L ir 1. DOX 1270. CAST HAMPTON. CONN. 06424 June. 13, 1978 CYH-78-156 Docket No. 50-213 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 ATTENTION:

Mr. Ernest Volgenau

Dear Sir:

In accordance with reporting re.:quiremente the Cennecticut Yankce Ifadda:r. Neck !!onthly Operating Report 78-5, covering operations J

for the period of May 1, 1978 to May 31, 1978 is hereby forwarded.

Very truly yours,

/W'~

R. II. Graves Station Superintendent RilG:QB/mts Enclosures cc:

(1) Director, Region I Division of Inspection & Enforcement U. S. Nuclear Regulatory Co:tmit: ion 631 Park Avenue King of Prussia, Pennsylvania 19/.06 (2) Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Cotc.minsion Washington, D. C.

20555 ID m,. '

CONNECTICUT YANKEE ATOMIC POWER COMPANY

/

HADDAM NECK PLANT RR 41. DOX 127E. EAST H AMPTON. CONN 06424 b,

January 11, 1980 CYli-80-004 Docket No. 50-213 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 ATTENTION:

Mr. Victor Stello

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Monthly Operating Report 79-12, covering operations for the period of December 1, 1979 to December 31, 1979 is hereby forwarded.

Very truly yours,

/

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/L, R. H. Graves Station Superintendent Rl!GrRPT/mts Enclosures cc:

(1)

Director, Region I Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2)

Director,*0ffice of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 ll

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY SPERATING REPORT NO. 79-12 FOR Tile MONTil 0F DECEMBER, 1979 A_ A

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s PLANT OPERATIONS The following is a chronological description of plant operations for the month of December, 1979.

At the beginning of this report period the plant was operating at 100% power, 607 MWe.

On 12/16/79 the load was reduced to 400 MWe to perform a turbine stop trip valve test. The plant returned to full power the same day and remained at full power throughout the month.

On 12/16/79 while returning to full power by diluting the Reactor Coolant system, the rupture disc on the Degasifier was

-ruptured due to malfunction of degasifier effluent valve. Approximately 800 gallons of coolant was pumped to primary vent stack releasing its gas content to the atmosphere. This resulted in a Prompt Report to U.S.N.R.'C. and notification to public on the basis of an event of high public interest.

On 12/24/79 EG2A was out of service due to damaged generator neutral cable insulation. Cable repaired and EG2A in standby status on same day.

On 12/28/79 the fire system piping was Hydroed after several modifications and tie ins for new systems.

On 12/31/79 lost control air pressure in the containment due to faulty solenoid pilot valve on pressurizer solenoid relief 570.

Replaced pilot valve same day and air system returned to normal.

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EFFECT SYSTEM-SPECIAL PRECAUTIONS ON CORRECTIVE ACTION TAKEN T0' PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT l

_ _ _CAUSE RESULT OPERATION REfEITIION DURING REPAIR _.

PORV 568 Solenoid Diaphragms lost Excessive air None -' valves Replaced diaphragms and Tagged valve closed'and flexibility due comsumption failed closed ordered new Hi temperature shut off air to prevent to heat solenoid valves opening "A" Aux. Feed Pump Misalignment Vibration None Realigned pump per "B" pump available J.0. #MA 0788 procedure M 8,5-40 S.I. HCV 1881 RWST Loose lock nut Valve would not None Relocked stem by None required rceirc. valve operate properly tightening lock nut J.O. 0796 Ralay contacts Contacts stuck Shut off de- "

Unplanned gas Replaced relay with a mere None LS-115 3BX closed gasifier trans-released reliable type fer pump 4160V cable from EG2B Contractor work-Damaged 4160V None -

The pre work checkoff has Redundant system avail.

diesel to control cab, ing in area cables from Redundant been improved to require y

broke thru EC2B to control system avail, closer print review and PVC conduit cabinet additional precautions 6

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CONNECTICUT YANKEE REACTOR COOLANT DATA NONTH* 12-79 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM e....................................................................

rn w-25-DEGREES-C 6T40E+00-:

6T60Ef00 :

6T76E-+00 ;

CONDUCTIVITY (UMHOS/CM) 1.05E+01 :

1.49E+01 :

1.90E+01 :

CHLORIDES (PPM)

<4.00E-02 ! <4.00E-02 : <4 00E-02 :

-DISS0tVED-OXYGEN-( PPB P

---<5. 00E+ 00 -
-<5. 00Ef 00 -:--<5.-00E+00 ;

BORON (PPM) 3.06E+02 :

3.47E+02 :

3.86E+02 :

LITHIUM (PPM) 7.50E-01 :

1.29E+00 :

1.70E+00 :

-TOTAL--G AMM A-ACT.

tfC7ML) 6796E-+00-8745Ef00 6 7T50C+00 4 10 DINE-131 ACT. (UC/ML) 4.29E-02 :

4.90E-02 :

5.53E-02 :

I-131/I-133 RATIO 7.70E-01 :

8.81E-01 :

1.28E+00 :

-CRUL-tMG7LTTER) 6 a.00E302 i

4. 65 E=0 i 6 3./SE-vA 4 TRITIUM (UC/HL) 2 53E+00 :

3.00E+00 :

3.50E+00 :

HYDROGEN (CC/KG) 2.05E401 :

2.26E+01 :

2.68E+01 :

t AERATED LIQUID WASTE PROCESSED (GALLONS):

6.37E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

2 14Ef04 AVE R AG E-PRI M A R Y -L E A K-R A T E ( G A L L O NS-P ER-M I N U T E t-;

4r70E-02 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00Ef00 e

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          • fiRC OPERATitlG STATUS REPGtT CortPLETD BY P.EACT0ft DClf1EUtttE*****
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a 1 _t2.IT 14A;1E....cK24. YAtaZC AtAllC MAE.LQL 000tET ID.-M-213 -

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dEPu:tTIIc PE,ttoo...-recember 1979 OATE 1/11/80 3.

LICDc.Ca TitEcut PG E,t t.1 T)... 1325 '.

CI1T-LETED BY.. Reactor Engir.eering t.

I..CPt. ATE.uTI;4G(G:033 s tC)....Geo.3 TELEPHut:C- (293 ) 2G7-2556 - ---

b.

.CSIC. ELECT.tlCAL.tATI:UCtET it.E)... 575 6

P.'at;ut 6EPDJulE CAPACITYG;1us3 tt:E)... 577 Z._

h'al:tal uCPCA AOLE CAPACITYCIET IL.E)... 550 6.

IF Onl6Es UCCOt III CAPACITY ltATif4G0(ITD15 3 TIIROUGI 7)SiflCE L*diT REPortT, CIVE REASO!S....lsene l

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_P.1.Ea LEvCL To tJilOt."EST;tlCTE3.

IF. Af.1i(f:ET.st.t)

.Non-1.s. Heli,vl3 Fait itELiellCTlu:4 IF A!4Y....Not applicable THIS REP 01TifG PDtt0D YR. TD DATE CutUt.ATIVE T3 DATE

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11.

ItutS If4 ICPutTirG.PGtt03 7%.0 8750.0 105102.0 14.

f.utLt W IUdts Tite I(EACToit itAS CRITICAL 74.0 7541.2 9119G.7

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"rAfToa ItEGONE LliUTDLxJ!i 10Jts 0.0 25f 5 1152.6 * - -

14.

luJts GE!OtATut Ori Lif4E 74.0 7f.27.G 860t.u.2 =

15.

vi.!T.tEGL4VE Libiutr.J!3 IUutS 0.0 233.5 349.9 lu-t.e41: S Titt.4%L D.DtGY t.E!45tATC) OtJI) 135G111.

132020CG.

-150141113. - -.---.- a 17.

Cro;J ELECT:tlCAL EliOtGY GUS!ATO CtJ1) 4507'J0 4322052.

4035%CG.

14.

f2ET ELECTalCAL ErCRGY GEt0 TATE 3 CIAl) 430745.

411G339.

4G95r.7G3.' ~

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19; ut.!T tit.IVICC FACTJt 100.0 84.8 32.G e 40.

J:;lT AVAILA3ILITY FACTU.t 10J.0 87.5 83.0

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OralT CAPACITY FACTGR (JSillG ICC IIET) 105.3 85.4 82.6 e '

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  • 1tT.CAPActTY FACTal (Jtil!JC DER f:ET) 100.7 al.7

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23.

U4tT F0 ACED OUTAGE.1 ATE 0.0 0.4

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S!UTI21.Jr5 SQtCDUALED UVER ICXT G 110!!T1tS(TYPC,DATE AfD DURAT10fl 0F EAQl).... Refueling. May 1930. Approximately 8 to 12 weeks 45.

IF blOTUGJri AT DD OF 6:EICITirc PERIOD, ESTI %TED DATE OF STARTUP.... Not Applicable zu.

:ITs.Iti.TEUT.5TATJs(l".tlDit-TJ C0r401CI AL.0?CRATIO 1),m l'ot Applicable t

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  • sitCE DATE W C37CICI AL CPGt"TIort 1-1-G3

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE 1/11/80 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH:

December, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 582 17 581 2

582 18 578 3'

582 19 578 4

583 20' 579 5

581 21 579 6

583 22 579 7

583 23 580 8

582 24 581 l

9 581 25 580 10 582 26 580 t

11 583 27 580 12 583 28 580 13 583 29 5.80 14' 583 30 579 15 582 31 580 J

16 564 s

INSTRUCTIONS On this format, list the average daily unit power icvel in HWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

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DOCKETNO. S0-213 e

UNITSl!UltOWNS AND l'0WER REDUCTIONS UNIT NAME C nn. Y nkee DATE 1/11 #1

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Deceraber 1979 COMPLF El Y REPORT MONTil

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6 No unit sh6tdowns or significant l

power reductions during the month 8

of December, 1979 reporting period. l s

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r REFUCLING INFORMATION REQUEST 1.

Name of facility Connecticut Yankee. Atomic Power Company 2.

Scheduled date for next refueling shutdown.

May, 1980 3.

Scheduled date for restart following refueling.

Approximately eight to 12 weeks from shutdpun date.

4.

(a) Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

No technical specification changes are anticipated at this date.

(b)

If answer is yes, what, in general, will these be?

N/A (c) If answer is no, has the reload fuci design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? When the above stated documents are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety questions are associated (d) If no such review has taken place, when is it scheduled?

with the core reload N/A 5.

Scheduled date(s) for submittind proposed licensing action and supporting information.

There are no scheduled _ dates because of (4) above.

6.

Important licensing considerations associated with refueling, e.g., new or different fuci design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

~

(a) 157 (b) 340 8.

The prescat licensed spent fuci pool storage capacity and the size any increase in licensed storage capacity that has been requested ot or is planned, in number of fuct assemblics.

1168 9.

Die projected date of the last refueling that can be discharged

-to the spent fuel pool assuming the present licensed capacity.

1994 to 1995

.

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