ML20151G870

Monthly Operating Repts for Mar 1988

ML20151G870
Person / Time
Site:	Catawba
Issue date:	03/31/1988
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8804200168
Download: ML20151G870 (16)

Text

,

i' OFERATING DATA REPORT DOCVET 50-413 DATE 4-15-98 0FERATINS STATUS COMFLETEDBY J. A. Reavis

_=..

TELEPHONE 704/373-7567

1. Unit Nase: CATAWBA 1

2. Reportirg Pertod: MARCH 1, 1989-MARCH 31, !?88

3. Licensed Thersal Power (MWtli 3411

4. Naseplate Rating (Gress Ene):

1305 i Notes *Nueplate Rating I

5. Design Electrical Rating (Net MWe):

!!45 I (Gross MWel calculated as 1

6. Maxinus Deaendable Capacity (6tess MWe):

1 1450.000 MVA x.90 pcner 1

7. Maxi us Dependable Capacity (Net MWe):

!!29 1 fatter per Page lii, I

a. If Changes Occur in Capacity Ratings (Itess Number 3 Through 7) Since Last i NURE6-0020.

I Report. Give Reasons:

I

..,_,,,,,I 9-Foner Level To lihich Restricted, if Any (Net PWe):

10. R e a s o n Fo r R e s t r i c t i c ns, i f a n y :,,,,,,,,,,,,,,,,..,,,,,__,,_ __,,,...............,_ __,,... _ _ _ _ _ __ _ _ __,,,,,_ _,,,__,,,,

....................................=

_ _ =......... _ _... _

__=....__.............__........_____________..........

=..............__...............

This Month Yr.-to-Date Cumulative

!!. Hours In Reporting Period 744.0 2,194.0 24,169.0

12. Narber Of Hours Reactor Was Critical e67.1 1,897.7 17,0!!.4

13. Reactor Reserve Shutdown Hours

--0--

--0--

--0--

14. Heurs Generator On-Line 659.7 1,554.5 16,653.6

15. Unit Reserve Shutdown Hours

--0--

--0--

--0--

16. Gross Thersal Er.ergy Generated (MWH) 2,127,096 5,879,524 51,934,163

17. Eress Electrical Energy Cccerated (NWH) 758,660 2,065,070 18,176,192

10. Net Electrical Eurgy Generated (miH) 715,879 1,960,060 16,960,905

19. Unit Service Facter 28.5 84.9 69.1

20. Unit Availability Factor 88.5 64.9 69.1

21. Unit Capacity Factor (Using MDC Net) 85.2 79.5 61.4

22. Unit Capacity Factor (l' sing DER het) 84.0 78.4 61.3

23. Unit Forced Outage Rate 11.5 15.1 17.9

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

.........?.9')?........................................................_.............._....................................

25. If Shut Down At End Of Report Period. Estiented Date of Startup:___,............,_,.......,__.__,...,___.........___.

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

Forecast Achieved INITIAL CR!ilCAi.!TY INITIAL ELECTRICITY CO VERCIAL 0FERAi!0N 8804200168 880331 d

.O' PDR ADOCK 05000413 R

DCD l

)

r AVERAGE DAILY UMli POWER LEVEL DOCKET NO 50-413 UNIT Catanba 1 DATE April 15, 1988 COMPLETED J. A. Reavis TELEPfl0NE 704-373-7567 MONTH MARCH,1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWE-Netl

!125 17 1119 2

1127 18

!!21 3

1126 19 1124

=.......

4

!!23 20 1126 5

1127 21 1125 6

1130 22 1144 7

1127 23 1143 6

1124 24 1140 9

1111 25 1139 10 629 26 1141

.......=-

-===..........

11 0

27 1050 12 0

28 1146 13 0

29 1145 14 153 30 1141 15 982 31 1138 16

!!!9

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.-

50-413

~

I UNIT NAME [G5[hhBh((_(([_~((

DATE _Q4L15L@@_______;_

Page 1 of 2 REPORT MONTH _______ March _19@@_

COMPLETED BY _Jz_A._REAVIS______

TELEPHONE _iZQ4)-373-2562C__

(1)

(2)

(3)

(4)

(5)

R MET-E HOD T

A OF LICENSE N

Y S

EHUT EVENT SYS-CAUSE AND CORRECTIVE D

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE 22 p 88 1 F

A CB XXXXXX POWER REDUCTION DUE TO REACTOR COOLANT FLOW OUT OF SPEC 23 p 88 9 F

H CG XXXXXX POWER DECREASE DUE TO ACCIDENTAL BORON INJECTION 24 p 88-3-10 F

H WB XXXXXX POWER REDUCTION DUE TO LOSS OF ASSURED BACKUP COOLING WATER DUE TO ASIATIC CLAMS 7

88-3-10 F

85.28 H

1 WB XXXXXX UNIT SHUTDOWN DUE TO LOSS OF ASSURED BACKUP COOLING WATER DUE TO ASIATIC CLAMS 1

l 25 p 88-3-14 S

B IE INSTRU POWER INCREASE ON HOLD FOR NUCLEAR INSTRUMENTATION CALIBRATION I

26 p 88-3-14 S

8 IE INSTRU POWER INCREASE ON HOLD DUE TO NUCLEAR INSTRUMENTATION CALIBRATION (1)

(2)

(3)

(4)

F Forced Reason:

Method:

Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of' Data f B-Maintenance or test 2-Manual Scram Entry Sheets For Licensee C-Refueling 3-Automatic Suram Event Report (LER) l D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61)

E-Operator Training & License Examination (5)

F-Administrative Exhibit I - Same Sou ce G-Operator Error (Explain)

H-Other (Explain) o

~ ~

J UNI T SHUTDOWiVS ~ AND POWER REDUCTIONS DOCKET NO.

30-3o13 -

UNIT NAME _GATAW@A_1___,

_2_

Page 2 of 2 DATE _O4L15L@@_________.

REPORT MONTH _______ March _12@@_

COMPLETED BY _J._A._REAVIS___.__

TELEPHONE _1204 )-323--2562 *__

(1)

(2)

(3)

(4)

(5)

R MET-E HOD T

A OF LICENSE M

Y S

SHUT EVENT SYS-'

CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E I HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE 27-p 88-3-15 S

B IE INSTRU POWER INCREASE ON HOLD DUE TO NUCLEA3 INS'RUMENTATION CALIBRATION 28 p 88-3-15 S

B HB VALVEX POWER INCREASE ON HOLD FOR LONTROL VALVE MOVEMENT TEST 29-P 88-3-15 F I B

CB XXXXXX POWER INCREASE ON HOLD DUE TD-l REACTOR COOLANT-CLOW OUT OF SPEC 30-p 88-3-27 S

F ZZ ZZZZZZ POWER REDUCTION PER DISPAT'CHER REQUEST l

1 l

I l

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

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61) j E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)

Exhibit ~ I - Same Source I H-Other (Explain) 1 j

!Qj in hr' l-DOCKET NO:

50-413 UNIT:

Catawba 1 DATE: '

04/15/88

~

r, NARRATIVE

SUMMARY

Month: Macch, 1988 Catawba Unit 1 began the month of March operating at 98% power, limited in output by Reactor Coolant System Flow Technical Specification Limits. The unit operated at 98% power until 2s33~on 09/09, when power was reduced to 81% due to an accidental injection of boron into the Reactor Coolant System. The unit returne'd to 98%, power at 0026 on 03/10. At 1157 on 03/10, the unit began reducing power to go off-line due to a loss of assured backup cooling water.

The unit.was removed from service at 1636 on 03/10, and returned to service at 0553 on 03/14. The unit then returned to 98% power at 1721 on 03/15, following three power holds for Nuclear Instrumentation Calibration and one for Control Valve Movenent Testing. At 1800 on 03/21, power was increased to 100%,

following a Technical Specification revision. The unit then operated at 100%

power until 0025 on 03/27, when power was reduced to 89% to. help the Dispatcher meet minimum system load. The unit. returned to 100% power at 2300 on 03/27, where it operated for the remainder of the month.

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility names Catawba, Unit 1 2.

Scheduled next refueling sht.tdown: December, 1988 3.

Scheduled restart following refueling: February, 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, unroviewed 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 accormodated by present licensed capacity: September, 2011 DUKE POWER COMPANY DATE: April 15, 1988 Name of

Contact:

J. A. Reavis Phone:

704-373-7567

c

~.

s CPERATING DATA FEPORT DOCrET 50-414 DATE 4-15-88 0?ERATING STAillS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567

1. Unit Nase: CATAWBA 2

2. Reporting Period: MARCH 1, 1998-MARCH 31, 1983

3. Litersed 1hersal Power (MWt):

3411

't. Naseplate Rating (Gross MWel:

1305 i Notes INaseplate Rating i

9. Design Electrical Rating (Net FWe):

1145 i (6ross MWe) calculated as t

6. Maxista Dependable Capacity (Bross NWe):

1 1450.000 MVA x.90 poner I

7. Natisue Dependable Capacity (Net NWe):

1129 I factor per Fage lii, l

8. If Changes Occur in Capacity Ratings.(Itess Number 3 Through 7) Since Last i NUREG-0020.

I Report. Give Reasons:

i

..I 9' Power Level To Which Restricted, if Aoy (Net MWel:

10. Reason For Restrittlons, If any:......__

This Month Yr.-to-Date Cusulative

' !!. H urs in Reporting Peried 744.0 2,184.0 14,185.0

12. Nusber Of Hours Reactor Was Critical 377.7 377.7 0,983.2

13. Reactor Reserve Shutdown Hours

--0--

--0--

--0--

14. Hours Benerator On-Line 315.0 315.0 8,659.5

15. Unit Reserve Shutdown Hours

--0--

--0--

--0--

16. Gross Thereal Energy Generated (MWH) 840,085 240,065 26,567,578

17. Gross Electrical Energy Generated (MWH) 291,287 291,297 9,369,315

18. Net Electrical Energy Generated (MWH) 255,292 235,672 8,702,369

19. Unit Service Factor 42.3 14.4 61.1

20. Unit Availability Factor 42.3 14.4 61.1

21. Unit Capacity Factor (Using MDC Net) 30.4 9.6 53.7

22. Unit Capacity Factor (Using CER Net) 30.0 9.4 53.6

[

23. Unit Forced Outa;e Rate 57.6 59.5 30.0

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

........69.09........................................................-.......-...........................=--

^

=---....

..__.....................................................................................--.--......-..=-

l

25. If Shut Dow, At End Of Report Fer106. Estisated Date of Startup:.......................................................

26. Units in fest Status (Prior to Consercial Operation):

Forecast Achieved I

l L

l-INITIAL CRITICALITY INITIAL ELECTRICliY CO ME6CIAL OPERATIC't l

d-AVERAGE DAILY UNIT POWER LEVEL DOCKET ND 50-414

.=_=-- -

UNIT

.Catamba 2

.DATE April 15, 1988 COMPLETED J.A.Reavis TELEPHONE 704-373-7567 MONTH MARCH,1908

=.............

DAY AVERASE DAILY POWER LEVEL DAY AVERASE DAILY POWER LEVEL (MWE-Neti (MWE-Net) 1 0

17 0

2 0

18 0

-- =............

3 0

19 57 4

0 20 304 5

0 21 566 6

0 22 815 7

0 23 941 8

0 24

!!!9 9

0 25 1109 I

10 0

26

!!!9 i

27 1129 l

0 1

12 0

28

!!!6 13 0

29 1103 l

14 0

30 1091 15 0

31 876 I6 0

p UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

_J_O -- 4 B _ _ __ _ _ _ _ __ _

UNIT NAME

_CATAW@A_2____.___

DATE _O4/15L@@_________

REPORT MONTH _______ March _19@B_

COMPLETED BY._J._Az_REAVIS_____

Page 1 of 4 TELEPHONE _12041:323:2562;'__

(1)

(2)

(3)

(4)

(5)

~

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 4

88 1 F

197.17 A

HH PUMPXX OUTAGE OVERRUN DUE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP PROBLEMS 5

88 9 S

1.52 B

2 HA TURBIN TURBINE OVERSPEED TRIP TEST 6

88 9 F

18.07 A

3 HH VALVEX TURBINE / REACTOR TRIP WHEN S/G

'2B' FEEDWATER BYPASS CONTROL VALVE FAILED OPEN e

7 88-3-10 F

212.27 H

WB XXXXXX START-UP DELAY DUE TO LOSS OF ASSURED BACKUP COOLING WATER DUE TO ASIATIC CLAMS lP 88-3-19 S

B IE XXXXXX POWER INCREASE ON HOLD FOR FLUX MAPPING 2p 88-3-20 F

H IF XXXXXX POWER INCREASE DELAY DUE TO LOW REACTOR COOLANT SYSTEM' AVERAGE TEMPERATURE (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 Licensee 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)

UNIT SHUTDOW9fS AND POWER REDUCTIONS DOCKET NO. _50-914_______

UNIT NAME _GATAW@A_2____c___

DATE _O4f15L@@_________

Page 2 of 4 REPORT M O N T H _ _ _ _ _ _ _ tl a r c h _ 1 _9 9 @ _

COMPLETED BY._23_A._REAVIS_____

TELEPHONE _( 204 )-323--2562C__

(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

DOHN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE i

3-p 88-3-20 S

B h --

IE INSTRU POWER INCREASE ON HOLD DUE TO NUCLEAR INSTRUMENTATION CALIBRATION 4p 88-3-21 F

A XX XXXXXX POWER INCREASE ON HOLD-DUE TO OPERATOR AID COMPUTER PROBLEMS

'5 p 88-3-21 F

A CH INSTRU POWER INCREASE ON HOLD DUE TO S/G

'2D' LEVEL CONTROL PROBLEMS 6-p 88-3-21 F

H HA TURBIN TURBINE RUNBACK DUE TO DE-ENERGIZED RELAY THAT FEEDS RUNBACK CIRCUITRY 7-p 88-3-21 lF B

~~

HA XXXXXX POWER INCREASE DELAY TO REPAIR DE-ENERGIZED RELAY 8-p 88-3-22 F

H RC FUELXX POWER INCREASE ON HOLD DUE TO FUEL MANEUVERING LIMITS 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 L i c ensec:

C-Refueling 3-Automatic Scram

. Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

Fila (NUREG-Ol61)

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

G-Operator Error (Explain)

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

UNIT SHUTDOWNS AND. POWER REDUCTIONS DOCKET NO. _50-@l4___________

UNIT NAME _ CATAWBA _2____.;___

DATE _g4L15L8@_________

REPORT MONTH _______ March _19@@_

COMPLETED BY _2z_Az_REAVIS_____

Page 3 of 4 TELEPHONE _1294 )-323-2562 *__

I'~

(1)

(2)

(3)

(4)

(5)

R MET-i 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 9-P 88-3-22 S 1 bB IE INSTRU POWER INCREASE DELAY FOR NUCLEAR INSTRUMENTATION CALIBRATION 10 P 88-3-23 S

B HB VALVEX POWER INCREASE DELAY FOR CONTROL VALVE MOVEMENT TEST-11 P 88-3-24 S

B ZZ INSTRU POWER INCREASE ON HOLD FOR j

PRECISION CALORIMETRICS 12-P 88-3-25 F

B IF INSTRU POWER CECREASE DUE TO REACTOR COOLANT LOOP CALIBRATION 13 p 88-3-25 F

H CB XXXXXX POWER INCREASE DELAY DUE TO REACTOR-COOLANT FLOW OUT OF SPEC I4 P 88-3-28 S

A IE INSTRU POWER DECREASE DUE TO NUCLEAR INSTRUMENTATION & PRECISION CALORIMETRICS (1)

(2)

(3)

(4) 1 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 Licensec i

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

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61)

]

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

]

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain)

J i-

UNIT SHUTDOWNS AND POWER FiEDUCTIONS DOCKET NO.

50-414 UNIT NAME _CATAW@G_2____,;_,_

DATE _04L15L@@._________

REPORT MONTH ______f_1 arch _12@@_

COMPLETED BY _J._Az_REAVIS____,_.a Page 4 of 4 TELEPHONE _1204):373:2562r__

(1)

(2)

(3)

-l(4)

(5) 5 R

MET-E HOD T

A OF LICENSE M

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 15-p 88-3-30 F

A HH VALVEX POWER DECREASE DUE TO S/G

'2C' FEEDWATER CONTROL VALVE MALFUNCTION 16-p 88-3-31 F

A HH VALVEX POWER DECREASE DUE TO'S/G

'2C' FEEDWATER' CONTROL VALVE DRIFTING ERRATICALLY'-

17-p l 88-3-31 F

B HH VALVEX POWER DECREASE FOR REPAIR OF S/G l

'2C' FEEDWATER CONTROL VALVE (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 License; C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61)

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

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain)

y R

r DOCKET NO:

50-414 UNIT:

Catawba 2 DATE:

04/15/88-S NARRATIVE

SUMMARY

Month: March, 1988 Catawba Unit 2 began-the month of March off line due to Turbine Driven Auxiliary Feedwater Pump problems..The unit returned to service at 0510 on 03/09, and a

operated at 16% power until 1114 the same day, when the unit was removed from service to conduct a Turbine Overspeed Trip Test.

The unit then returned to service at 1245 on 03/09, and subsequently experienced a Turbine trip (1826 on 03/09)' on Hi-Hi S/G 1evel due to a failed Feedwater Bypass Control Valve.

The unit then remained out of service until 0846 on 03/19, due to a lack of assured backup cooling water.

Following several scheduled and several unscheduled power.

holds, the unit reached 98% at 2121 on 03/25, limited in power bf Reactor Coolant Flow Technical Specification Limits. On 03/28 at 1100, powe3. was reduced to 95% to conduct Nuclear Instrumentation Calibration and Precision Calorimetrics. Power was then reduced to 92% due to S/G Feed Regulator Valve problems, and then to 86% due to errat c drifting of the valve. The unit was i

then further reduced, finishing the month st 45% power, limited by S/G Feedwater Control Valve problems.

q-I

we-

='

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 2

2.

Scheduled next refueling shutdown:

Currently Refueling 3.

Scheduled restart following refueling: March, 1988 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, unteviewed 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 incraase:

9.

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

April 15, 1988 Name of

Contact:

J. A. Reavis Phones 704-373-7567

7 V.

1 t

I CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.

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

2.

The total station liquid release for February has been compared with the Technical Specifications maximum annual dose commitment and was 1ess than 10 percent cf this limit.

The total station gaseous release for February has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit, i

t l

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DUKE POWER GOMPAhT P.O. BOX 03180 CilANT OTTE. N.C. 28949 HAL B. TUCKER rzternown vms perm ommt (704) 3MF4NM wtes.us reoptresom April 15, 1988 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.

20555 Re: Catawba Nuclear Station Docket No. 50-413 and 50-414 1

Dear Sir:

Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the mor.th of Farch, 1988.

Very truly yours,

./

W Hal B. Tucker JAR /7015/sbn Attachment xc Dr. J. Nelson Grace INPO Records Center Regional Administrator, Region II Suite 1500 U. S. Nuclear Regulatory Commission 1100 circle 75 Parkway 101 Marietta Street, NW, Suite 2900 Atlants, Georgia 30323 Atlanta, Georgia 30323 Mr. Richard G. Oehl, NE-44 Mr. Phil Ross U. S. Department of Energy U. S. Nuclear Regulatory Commission 19901 Germantown Road MNBB-5715 Germantown, Maryland 20874 Washington, D. C.

20555 American Nuclear Insursrs Dr. K. Jabbour, Project Manager c/o Dottie Sherman, ANI Library Office of Nuclear 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 NRC Resident Inspector Catawba Nuclear Station

/

l