ML20151E368

Monthly Operating Repts for June 1988 for Catawba Nuclear Station

ML20151E368
Person / Time
Site:	Catawba
Issue date:	06/30/1988
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8807260039
Download: ML20151E368 (17)

Text

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o CFERAT!h5 CATA FEFCRT DOCKET N3 50-413 OATE July 15. le89 OPERATIN3STAM CCMPLETED EY J. A. Feavis TELEfh3E 704-373-7567

1. Unit hase: Catasha 1

2. Reporting Feriod: June 1, 1983-June 30, 1953

3. Licensej Thersal Foner (MWt):

3411

4. Naseplate Ratin; (Gross Pae):

1305i Notes oase;1ste Ratirg

5. Design Electrical Ratir.g (Net W e):

1145 (Gress Mse) calculated as

6. Marisus Dependable Ca;acity (Eress Mee):

1192 1450.000 MVA r.99 ptwer

7. Marisus Dependable Capacity (Net PWe):

1129 facter per Pa;e iii,

8. If Changes Occu-Capacity Retirgs (Itess Liber 3 Threugh 7) Since Last NUCES-0020.

Repc-t. Give Feasons:

9. Power Level To Which Festricte1, If Any (Net Mie):

10. Reasen For Restricti)ns, if v y:

This Month Yr.-tc-tate Cusalative

11. Hcurs In Re;crting Fericd 720.0 4367.0 26352.0

12. N ster Of Mcurs Feacter Was Critisal 720.0 40B0.7 19194.4

13. Feactor Reserve Stutd:wn Hours

--0--

--0--

--0--

14. Heurs Eereratcr Ot-line 720.0 4037.5 13135.6

15. Unit Feterie Shutdenn Mcurs

--0--

--0--

--0--

16. Grcss Thereal Erergy Eenerated (NH) 239(237 13136537 59191371

17. Gross Electrica Energy Gererated (PsH) 246221 4!$4353 20755475

18. Net Electrical Energy Eeserated ( SH)

E01230 004406 19405251

19. Unit Service Facter 100.0 9?.5 70.7

20. Unit Availability factor 100.0 92.5 70.7

21. Unit C4;a:ity Factor (Usir; MOC het) 92.6 69.3 64.5

22. Unit Ca;acity Factor (Using IER Net) 97.2 EE.1 64.3

23. Un:t Forced Cutage Kate 0.0 7.5 16.1

24. Shuthen Scheduled Over Nest 6 P.cnths (Type, Cate, and turation of Each):

Refueling - November 11, 1988 - 8 weeks

25. If Shut hun At EM Uf Report Period. Estinated Date of Startup:

26. t; nits In Test Status (Frict to Ceasercial C;eration):

Forecast Achieved IN!T'AL CRIT! A !TY INITIAL ELECTRICITY COPIERCIAL CFEFATION O

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. k 0FERAilh'6 OATA REPORT DOCKETNO

$0-413

UNIT Catanba 1 DATEJuly 15. 1988 COMPLETED BY - J. A, Feavis TELEPHONE-704-373-7567 MONTH June,1988 DAY AVERASE DAILY PCWER LEVEL Lq

' AVERASE DAILY FDE R LEVEL (M'de-Ne t )

(MWe-het) 1 1115 17 1116 2

_1115 18 1113 3

~ 1118 li '

1054 4

1124 20 1090 5

1123 21 1112 t.

6 1118 22 1113 7

1117 23 1111 B

1115 24 1111 9

1113 25 1113 10 1120 26

)

11 1118 27 1118 i

12 1120 29 1124

)

13 1108 29 1119 14 s116 30 1122 15 '-

1117 i

16 1115 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-413 UNIT NAME CATAWBA 1 l

l DTTE 07/15/98-REPORT MONTH June 1988 COMPLETED BY J.

A.

REAVIS TELEPHONE (704)-373-7567-(1)

(2)

(3)

(4)

(5)

R MET-E HOD T

A OF LICENSE i

N Y

S SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NC.

CODE CODE PREVENT RECURRENCE Hd VALVEX REDUCTION DUE TO STEAM GENERATOR 36-p 88-6-13 F

A

'1C' FEEDWATER REGULATING VALVE CONTROL CARD FAILURE B

HB VALVEX POWER REDUCTION FOR CONTROL VALVE 37-p 88-6-18 S

MOVEMENT TEST l

A HB VALVEX HOLDING POWER FOR TROUBLESHOOTING 38-p 88-6-19 F

l OF TURBINE CONTROL VALVE #1 I

39-p 88-6-19 F

A CH INSTRU POWER REDUCTION TO PROVIDE ADEQUATE CONTROL ON S/G

'C' LEVEL I

(1)

(2)

(3)

'(4)

F Forced Reason:

Method:

Exhibit G - Instructions.

S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For LicenseG C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)

Exhibit I - Same Source-H-Other (Explain)

DOCKET NO:

50-413 UNIT:

Catawba 11 DATE:

07/15/88 NARRATIVE

SUMMARY

T t

Month: June,[988 1

Catawba Unit 1 began the month of June operating at 100% full power. On 6/13 at

~

0535, the unit reduced power to 98% when a Feedwater Regulating Valve Control Card failed. The unit then re*urnedito 100). power at 2027 the same day.. The-unit-reduced power to 90% on 6/18 to perform control Valve Movement Tests.

.On.

the return to 100% full' power, the unit held at 91% for troubleshooting of Turbine Control Valve //1. The unit then held at 96% power to provide adequate Steam Generator level control. The unit returned to 100% full power on 6/21 at 0845 and operated there for the remainder of the conth..

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I MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: November, 1988 3.

Scheduled restart following refueling: January, 1989 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 132 8.

Present licensed fuel pool capacity: 1418 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity: September, 2011 DUKE POWER COMPANY DATE: July 15, 1988 Name of

Contact:

J. A. Reavis Phones 704-373-7567 j

4 l

OPERATINS DATA REF0RT 4

DOCKET KO 50-414 DATEJuly 15. 1989

-OPEFATINS STATVS CDP 1LETED BY J. A, Reavis TELEPHONE 704-373-7567

1. Unit Nase Catauba 2

- 2. Reporting Feriod: June 1, 19BB-June 30,1983

3. Licensed Theraal Feuer (MWt):

3411

4. Naseplate Rating (6ross MWe):

13056 Notes sNaseplate Rating

5. Design Electrical Rating (Net MWe):

1145 (Gross MWe) calculated as

6. Marisua Dependable Capacity (Gross MWel:

!!92 1450.030 MVA

.90 pener

7. Mailsus Dependable Capacity (Wet MWe):

!!29 factor per Page 111,

8. If Changes Occur in Capacity Ratings (!tess Naaber 3 Through 71 Since Last N'dE64020.

Report. Give Reasons:

s l

9. Pener Level To Which Restricted, If Ar,y (Net MWe):

10. Ruson For Festrictions, if any This Menth Tr.-to44te

-Coeulative

11. Hours In Reporting Ferted 720.0 4367.0 16368.0

12. Nusber 0f Hours Feactor Was Critical 661.6 2252.4 10857.9 l

13. Reactor rieserve Shutdenn Hours

--0--

--0--

--0--

14. Hours Generator On-Line 633.0 2225.8

-10470.4

15. Unit Reserve Shutdenn Hours

--0-- -

--0--

16. Gross Thereal Energy Generated (MWH) 1743286 5862403 31587896

17. Eress Electrical Energy Generated (MWH) 602324 2037453

!!!!4481

18. Net Electrical Energy Generated (MWH) 560675 13533B6 10325083

19. Unit Service Fatter 59.6 48.7 64.0

20. Unit Availability Factcr 63.6 49.7 64.0

21. Unit Capacity Factor (Using MDC Nat) 69.0 37.7-55.3

22. Unit Capacity Factor (Using DER Net) 69.0 37.2 55.1

23. Unit Forced Datage Rate 11.4 22.3 27.7

24. Shutdtwn Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Stut Denn At End Of Report Feriod. Estisated Date of Startup:

26. Units in Test Status (Frior to Comaercial Operation):

Ferecast Achieved INit!ALCRITICALITY INITIALELECTRICITY t

C0V ERCIAL OFERATION i

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OPERATING DATA REPOR.T -

DOCKET NO 50-414

~

UNii Catamba 2 DATEJuly 15. 1989 COMPLETEDBY J. A Feavis TELEPHONE 704-373-7567

. MONTH June,1988 CE AVERASE DAILY F0WER LEVEL

[E AVERASE DAILY FOWER LEVEL 2

(MWe-Net)

(MWe-Net)'

I 8 59 17 986 2

1131 16 643 3

984 19 645 t

4 0

20 365 5

320 21 364

.r 6

316 22 110e 7

0 23 life 8

794 24 1123 9

113?

25 1133 10 1032 26 1083 D5 27 8

12 401 28 547 13 989 29 1130 14 till 30 1t37 15 1140 l

16 1141

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l i-UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414-UNIT NAME CATAWBA 2 DATE 07/15/88 REPOR" MONTH June 1988 COMPLETED BY J.

A.

REAVIS TELEPHONE (704)-373"7567 l (4)

(5)

(1)

(2)

(3)

R MET-E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE

{ A HOLDING ^PU'ER FOR INVESTIGATION OF.

HE TUPLIN W

,42-p 88-6 F

~

STEAM LEAK ON MAIN TURBINE PIPING IE INSTRU HOLDING POWER FOR NUCLEAR 43-p 88 1 S

B INSTRUNENTATION CALIBRATION HB VALVEX POWER REDUCTION FOR CONTROL VALVE 44-p 88-6

.3 S

B MOVEMENT TEST 45-p 88 3 F

A HE PIPEII REDUCTION TO REPAIR STEAM LEAK ON MAIN STEAM PIPING 11 88 3 F

22.28 A

2 HB

'fURBIN MANUAL REACTOR TRIP DUE TO LOSS OF STEAM PRESSURE TO THE

'2B' i

FEEDWATER PUMP TURBINE 46-p 88 4 S

A CH HTEXCH

' HOLDING POWER'FOR FEEDWATER NOZZLE SWAP (1)

(2)

(3)

(4)-

F Forced Reason:

Method:

"Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram-Entry Sheets For Licensed C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5) i l

G-Operator Error (Explain)

Exhibit I

.Sams Source 1

H-Other (Explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414-(

UNIT NAME CATAWBA 2 DATE 07/15/88 REPORT MONTH June 1988 COMPLETED BY J.

A.

REAVIS TELEPHONE (704)-37347567 s

l l

(1)

(2)

(3)

(4)

(5)

R MET-E HOD e

T A

OF LICENSE l

N Y

S SHUT EVENT

.SYS-CAUSE AND CORRECTIVE

(

O P

DURATION O

DOWN REPORT TEM COMPONENT ACTION TO L

DATE E

HOURS N

R/X NO-CODE CODE PREVENT RECURRENCE l

47-p 88 5 S

F ZZ ZZZZZZ HOLDING POWER PER DISPATCHER REQUEST i

48-p 88 6 F

A HH PUMPXX HOLDING POWER DUE TO INABILITY TO TRIP

'2A' FEEDWATER PUMP FROM I

I CONTROL ROOM 12 88 6 F

17.62 A

3 RB CONROD REACTOR TRIP DUE TO BLOWN FUSE ON ROD CONTROL STATIONARY COIL 'N09' 49-p 88 7 F

A HH VALVEX HOLDING POKER'FOR MAIN FEEDWATER l

CONTROL VALVE CONTROL REPAIR l

l 13 88-6

.7 F

4.92 A

2 HA VALVEX TURBINE GENERATOR TAKEN OFF-LINE i

DUE TO HYDRAULIC OIL LEAK AT 1'

TURBINE CONTROL VALVES B

HH VALVEX POWER HOLD FOR FEEDWATER REGULATING 50-p 88 7 F

VALVE CONTROL CALIBRATION l

~A l

(1)

(2)

(3)

(4)

F Forced Reason:

Method:

Exhibit G - InstructionsL S Scheduled A-Equipment Failure (Explain) 1-Manual

.for Preparation of Data i

B-Maintenance or test 2-Manual Scram Entry Sheets For Licenseg C-Refueling 3-Automatic Scram Event' Report (LER)

D-Regulatory Restriction 4-Other (Explain)

-File.(NUREG-0161) y E-Cperator Training & License Examination l

F-Administrative (5)

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain) l I

I l

' UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414 UNIT-NAME CATAWBA 2 DATE 07/15/88 REPORT MONTH June 1988 COMPLETED BY J.

A.

REAVIS l

l TELEPHONE (704)-373"7567 (1)

(2)

(3)

(4)

(5) l R

MET-E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTICN TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURREFCE 51-p 88 8 S

B IE INSTRU POWER HOLD FOR NUCLEAR INSTRUMENTATION CALIBRATION HJ VALVEX REDUCTION DUE TO '2C1' HEATER DRAIN j

52-p 88 9 F

A TANK PUMP DISCHARGE CONTROL VALVE l

PACKING LEAK F

ZZ ZZZZZZ POWER REDUCTION PER DISPATCHER' 53-p 88-6-10 S

REQUEST 54-p 88-6-13 S

F ZZ ZZZZZZ HOLDING POWER PER' DISPATCHER' l

REQUEST 55-p 88-6-13 S

B IS INSTRU HOLDING POWER FOR NUCLEAR l

INSTRUMENTATION CALIBRATION HJ PUMPXX POWER REDUCTION DUE TO '2C1' HEATER-l 56-p 88-6-13 F

A DRAIN TANK PUMP DISCHARGE CONTROL...

l REPAIR t

j (1)

(2)

(3)

(4) l F Forced Reason:

Method:

Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual ~

for Preparation of Data.

B-Maintenanceaor test 2-Manual Scram-Entry Sheets For LicenseG C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)'

G-Operator Error (Explain)

Exhibit.I - Same Source H-Other (Explain) 1 I

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414' UNIT NAME CATAWBA 2

' DATE' 07/15/88 REPORT MONTH June 1988 COMPLETED BY

-J.

A.

REAVIS TELEPHONE (704)-373 -7567 (1)

(2)

(3)

(4)

(5)

R MET-E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRECTIVE C

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CCDE PREVENT RECURRENCE 57-p 88-6-17 S

F ZZ ZZZZZZ POWER REDUCTION PER DISPATCHER REQUEST 58-pl 88-6-20 S

B IE INSTRU POWER HOLD FOR NUCLEAR INSTRUMENTATION CALIBRATION g

14 88-6-20 F

20.15 A

2 HH CKTBKR MANUAL REACTOR TRIP DUE TO LOSS GF l

'A' FEEDWATER TURBINE LUBE OIL PUMP (FAULIT SWITCH) 59-p 88-6-21 S

B IE INSTRU POWER HOLD FOR NUCLEAR INSTRUMENTATION, CALIBRATION I

IE INSTRU POWER HOLD FOR NUCLEAR

~60-p 88-6-22 lS B

INSTRUMENTATION CALIBRATION l

l HJ HTEXCH POWER REDUCTION TO REPAIR A l

61-p 88-6-22 F

A.

MOISTURE SEPARATOR REHEATER DRAIN / LEVEL TRANSMITTER (1)

(2)

(3)

(4)

F Forced Reason:

Method:

Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual

.for Preparation of Data l

B-Maintenance or test 2-Manual' Scram Entry Sheets For-LicenseG 4

C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training & License Examination l

F-Administrative (5)

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain)

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1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414 i

UNIT NAME CATAWBA 2 DATE 07/15/88 REPORT MONTH June 1988 COMPLETED BY J.

A.

REAVIS TELEPHONE. (704)-373-7567-i (1)

(2)

(3)

(4)

(5)

R MET-E HOD i

T A

OF LICENSE i

N Y

S SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REP _ ORT TEM COMPONENT ACTION TO

^

DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE HJ PUMPXX POWER REDUCTION DUE.TO '2C1' HEATER 62-p 88-6-23 F

B

' DRAIN PUMP LOOP CALIBRATION' 15 88-6-26 F

17.05 A

3 ZZ HTEXCH REACTOR TRIP DUE TO INADVERTANT CLOSING OF STEAM GENIRATOR

'2D' MAIN STEAM ISOLATION l

HE TURBIN.

HOLDING POWER DUE TO STEAM' LEAK ON A

63-p 88-6-28 F

THE INLET LINE TO THE HIGH PRESSURE i

TURBINE A

HE TURBIN POWER REDUCTION TO' REPAIR A. STEAM l

64-p 88-6-28 F

i LEAK ON THE INLET LINE TO THE.HIGH PRESSURE TURBINE HE TURBIN HOLDING POWER TO REPAIR A'STSAM 65-p 88-6-28 F

A l

LEAK.ON THE INLET LINE TO THE HIGH PRESSURE TURBINE i

'(1)

(2)

(3)

(4)-

F Forced Reason:

Method:

Exhibit G - Instructions i

S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data ;

B-Maintenance or test 2-Manual Scram Entry Sheets For License @

C-Refueling 3-Automatic Scram Event Report (LER) i D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)

Exhibit I - Same Source, J

H-Other (Explain) i

UNIT SHUTDOWNS AND POWER REDUCTIONS

-DOCKET MO.

50-414 UNIT NAME CATAWBA 2 DATE- 07/15/88 REPORT MONTH June 1988 COMPLETED BY J.

A.

REAVIS TELEPHONE (704)-373-7567 (1)

(2)

(3)

(4)

(5)

R MET-E HOD

.T A

OF LICENSE i

N Y

S SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE B

IE INSTRU-POWER HOLD FOR NUCLEAR 66-p 88-6-29 S

INSTRUMENTATION CALIBRATION r

4 (1)

(2)

(3)

(4)

F Forced P.eason:

Method:

Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual ~

for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For License @

(

C-Refueling 3-Automatic: Scram.

Event' Report (LER) l D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161) l E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)

Exhibit I -'Same Sc>.rae H-Other (Explain)

' DOCKET NO:

50-414 UNIT:

Catawba 2 DATE:

07/15/88 NARRATIVE

SUMMARY

Month: June, 1988 4

Catawba Unit 2 began the month of June holding at 49% power for a Main Turbine piping steam leak investigation. The unit returned to 100% full power at 1745 on 6/01 following a hold at 95% for Nuclear Instrumentation Calibration.. The unit reduced power to 90% to perform Control Valve Movement tests. While.there, the unit reduced power further to 66% to repair a Main Steam Piping steam leak.

At this power level,-the unit was manually tripped due to a loss of steam pressure to the "2B" Feedwater Pump Turbine. The unit returned to service at 2055 on 6/04. The unit reached 60% power following several holds when the Reactor tripped on 6/06 at 1338 due to_a blown fuse on a Rod Control Stationary Coil. The unit returned to service at 0715 on 6/07 and reached 15% power before a hydraulic oil leak at the Turbine Control Valves forced the Turbine Generator to be taken off line. The unit returned to service at 1800 the same day and reached 100% full power on 6/08 at 1706 following several startup related holds.

The unit reduced power to 98%.due to a Heater Drain Tank Pump Discharge Control Valve Packing leak later the same day. On 6/10 the unit reduced load to 60% and then further to 40% to help the Dispatcher meet minimum system load.= On-6/13, the unit again reduced power to 75% per Dispatcher request. The unit returned to 100% power at 1320 on 6/13. The unit reduced to 60% power on 6/17 again per

~

dispatcher request. The unit held at 90% power on 6/20 following the dispatch reduction, for Nuclear Instrumentation Calibration.

The unit was manually i

tripped-from 98% power due to a loss of'the "A".Feedwater Turbine Lube Oil Pump on 6/20 at 1010. The unit returned to service at 0619 on 6/21 and reached 100%

power following two holds for Nuc1 car Instrumentation Calibration. Following power reductions for Moisture Separator Reheater problems and Heater Drain Pump Loop Calibration, the unit experienced a Reactor Trip on 6/26 at 2303 due to an inadvertant closing of a Steam Generator Main Steam Isolation Valve. The unit returned to service on 6/27 at 1606 and reached 100% power following several startup related power holds, where it operated for the remainder of the month.

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 2 2.

Scheduled next refueling shutdown: March, 1989 3.

Scheduled restart following refueling:

May, 1989 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

193 (b) in the spent fuel pool: 64 8.

Present licensed fuel pool capacity:

1418 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity: January, 2013 DUKE POWER COMPANY DATE:

July 15, 1988 Name of

Contact:

J. A. Reavis Phone 704-373-7567

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CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.

Personnel Exposure i

For the month of May, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.

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2.

The total station liquid release for May has been compared with l

the Technical Specifications maximum annual dose comitment and was l

less than 10 percent of this limit.

The total station gaseous release for May has been compared with l

the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

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t DuxE POWER COMPANY P.O. BOX 03180 oHARLOT17, N,0. 98949 HALH.TUC JR tmLarnown vice cessionar (704) 373-4tKH wtuna recouction July 15, 1988 U. S. Nuclear Regulatory Gomission Attention: Document Control Desk Wsshington, D. C.

20555 Re Catawba Nuclear Station Docket No. 50-413 and 50-414

Dear Sir:

Please find attached inforu.ation concerning the performance and operating status of the Catawba Nuclear Station for the month of June, 1983.

t Very truly yours, M /f A Hal B. Tucker-r l

JAR /15/sbn Attachment xc Dr. J. Nelson Grace INPO Records Center Regional Administrator, Region II Suite 1500 U. S. Nuclear Regulatory Comission 1100 Circle 75 Parkway 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-Atlanta, Georgia 30323 Mr. Richard G. Oehl, NL 44 Mr. Phil Rosa U.~ S. Department of Energy U. S. Nuclear Regulatory Commission 19901 Germantown Road I

MNBB-5715 Germantown, Maryland 20874 Washington, D. C.

20555 American Nuclear Insurers Dr. K. Jabbour, Project Manager c/o Dottie Sherman, ANI Library.

Office of tiuclear Reactor Regulation The Exchange, Suite 245 U. S. Nuclear Regulatory Commission 270 Farmington Avenue Washington, D. C.

20555 Farmington, CT 06032 Mr. P. K. Van Doorn l

NRC Resident Inspector Catawba Nuclear Station 6 i l

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