ML20149J377

Monthly Operating Repts for Jan 1988

ML20149J377
Person / Time
Site:	Catawba
Issue date:	01/31/1988
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8802230022
Download: ML20149J377 (15)

Text

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0FERAi!hG DATA REFCRT DOCKET 50-413 DATE 2-15-88 OPERATINS STATUS CCRPLETED BY J. A. Reavis

=..

TELEPHCNE 704/373-7567

1. Unit Nase: CATAWBA 1

2. Reporting Feriod: JANUARY 1, 1988-JANUARY 31,1999

3. Licensed Theraal Foaer (MWt):

3411

4. Naseplate Rating (Gross MWe):

1305 i Notes eNaseplate Rating I

5. Design Electrical Rating (Net MWe):

1145 I (Gross MWe) calculated as I

6. Maxisus Dependable Capacity (Sross MWe):

I 1450.000MVA

.90 poser I

7. Maxieus Dependable Capacity (Net MW

!!!9 I factor per Page 111, I

8. If Changes Occur in Capacity Ratings (! tees Nusber 3 Through 7) Since Last i NUREB-0020.

I Report. 6iye Reasons:

l.............................,I

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

9. Poaer Leyel To Which Restricted, If Any (Net MWe)

10. Reasoa For Restrictions, If any:

This Month Yr.-to-Date Cusulative

11. Hours in Reporting Perisd 744.0 744.0 22,729.0

12. Nusber Of Hours Reactor Was Critical 559.1 559.1 15,672.8

13. Reactor Reserve Shutdown Hours

- --0--

--0--

14. Hours Generator On-Line 530.8 530.8 15,129.9

15. Unit Reserve Shutdown Hours

.-0--

- - 16. Gross Thersal Energy Benerated (MWH) 1,575,665 1,575,665 47,630,529

17. Gross Electrical Energy Generated (WH) 549,266 549,266 16,640,399

19. Net Electrical Energy Generated (MWH) 509,443 509,443 15,510,2BS

19. Unit Service Fsctor 71.3 71.3 66.6

20. Unit Availability Factor 71.3 71.3 66.6

21. Unit Capacity Factor (Us:ng MDC Net) 60.7 60.7 59.6

22. Unit Capacity Factor (Us:ng DER Net) 59.8 59.9 59.6

23. Unit Forced Outage Rate 29.6 29.6 19.7

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

..... M UR..................

25. If Shut Doun At End 0f Report Peried. Estisated Date of Stattup:..................................................,,,...

26. Units in Test Status (o ior to Coseercial Operation):

Forecast Achieved r

INITIAL CRii!CALITY INIt!A' ELECTRICITY CC'"ERCIAL OFERATICN 8802230022 880131 k

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PDR ADOCK 05000413

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-413 UNIT Catawba !

l DATE February 15,1988 i

COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH JANUARY,1988

=-

BAY AVERA6E DAILY POWER LEVEL DAY AVERA6E DAILY POWER LEVEL (MWE-Net)

(MWE-Net) 1 61 17 0

2 171 16 0

3 518 19 0

4 851 20 0

5 952 21 0

6 1078 22 0

7

!!!7 23 0

8

!!21 24 0

9 1126 25 762 11 1135 26

!!34 11

!!37 27 1130 12

!!37 29 1131 13 1153 29 1134 14 115e 30 1101 15 1152 31 1116 16 73 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

_59-913___________

UNIT NAME _CATAW@A_1________

DATE _Q2/15/BB_________

REPORT MONTH _____ January _1988_

COMPLETED BY _J._At_REAVIS_____

_ 2941-323-2562___

TELEPHONE

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Page 1 of 4 (1)

(2)

(3)

(4)

(5)

R MET-E HOD f

T A

OF LICENSE j

ft 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 I

BB-1-

1 S

O.50 B

1 HA TURBIN TURBINE GENERATOR TRIP FOR TURBINE OVERSPEED TRIP TEST lp 88-1-

1 F

B HB INSTRU HOLDING POWER FOR TROUBLESHOOTING LOW TEMP INDICATION ON A&C FEEDWATER LINES 2p 88-1-

1 F

A CH HTEXCH UNABLE TO ATTAIN 25% POWER LEVEL DUE TO UPPER NOZZLE RESTRICTION 2

88-1-

1 F

9.22 H

1 CH HTEXCH UNIT SHUTDOWN DUE TO INABLILITY TO ESTABLISH REVERSE PURGE PRIOR TO NOZZLE SWAP 3p 88-1-

2 S

B RC ZZZZZZ HOLDING POWER FOR CORE PHYSICS TESTING

(

6p 88-1-

3 S

B RC 222Z22 HOLDING POWER FOR CORE PHYSICS TESTING f

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

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61)

E-Operator Training & License Examination (5)

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

H-Other (Explain)

+ -

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

_50;t13___________

UNIT NAME

_GATGWBA_1________

DATE _02L15L8Q_________

REPORT MONTH _____ January _19@8_

COMPLETED BY _J._A._REAVIS_____

TELEPHONE (704)-373-7567 Page 2 of 4 (1)

(2)

(3)

(4) l (5)

R MET-E HOD T

A OF LICENSE N

Y S

SHUT E*JENT 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 l

SP 88-1-4 S

H RC 2222Z2 HOLDING POWER FOR CORE PHYSICS TESTING 6P 88-1-4 F

A HB HTEXCH POWER REDUCTION DUE TO SECOND STAGE REHEATER STEAM LEAK 7p L 88-1-4 S

lB l

RC ZZZZZZ HOLDING POWER FOR CORE PHYSICS l

l l

TESTING 8p

'l 88-1-

4 F

A HH HTEXCH POWER REDUCITON DUE TO LOSS OF CONDENSER VACUUM 9p 88-1-4 S

B RC 22222Z HOLDING POWER FOR CORE PHYSICS TESTING 10 p 88-1-5 S

8 CB ZZZZZZ HOLDING POWER FOR REACTOR COOLANT SYSTEM LEAKAGE CALCULATION l

1 (1)

(2)

(3)

(4) i 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 Licensee 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 - San,a Source j

H-Other (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

_50-413___________

UNIT NAME

_CATAW@A_1________

DATE _02/15/88_________

REPORT MONTH _____ January _19@@_

COMPLETED BY _J._A._REAVIS_____

TELEPHONE _1204)-323-2562___

Page 3 of 4

-(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 ll P 88-1-5 S

B IE INSTRU HOLDING POWER FOR NUCLEAR INSTRUMENTATION CALIBRATION 12 p 88-1-5 F

A HB HTEXCH MOISTURE SEPARATOR REHEATERS OUT OF SERVICE 13 P 88-1-6 F

B HB HTEXCH PREPARATION TO RETURN MOISTURE SEPARATOR REHEATERS INTO SERVICE 14-P 88-1-9 F

H ZZ ZZZZZZ SECONDARY SIDE THERMAL OUTPUT UNCERTAINTIES 3

88-1-16 F

7.55 A

1 IF INSTRU REACTOR COOLANT SYSTEM THERMOCOUPLE PROBLEM I

l 4

88-1-16 F

166.15 A

2 HF HTEXCH CONDENSER CIRCULATING WATER PIPE BREAK REPAIR 1!

1 (1)

(2)

(3)

(4)

F Forced R e a e.o n :

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NOo _5Q-413___________

UNIT NAME _ CATAWBA _1________

DATE _Q2L15L@@_________

REPORT MONTH _____ January _1298_

COMPLETED BY _J._A._REAVIS_____

TELEPHONE (704)-373-7567 Page 4 of 4 (1)

(2)

(3)

(4)

(5)

R

. MET-E HOD T

A CF 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 5

88-1-23 F

29.83 H

3 ZZ ZZZZZZ MAIN STEAM PRESSURE TOO LOW DURING START-UP ULTINATELY CAUSED REACTOR TRIP 15 p 88-1-25 F

F HG ZZZZZZ HOTWELL DISOLVED OXYGEN OUT OF SPEC 16 p 88-1-25 S

B HB VALVEX CONTROL VALVE MOVEMENT TEST 17 p 88-1-26 F

F CB 222222 REACTOR COOLANT FLOW OUT OF SPEC 18 p 88-1-30 F

A HJ VALVEX

'IC2' HEATER DRAIN PUMP DISCHARGE RELIEF VALVE FAILED CLOSED 19-p 88-1-30 F

F CB 222222 REACTOR COOLANT FLOW OUT OF SPEC (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-Ol61).

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

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain)

DOCKET NO:

50-413 UNIT:

Catavba 1 DATE:

02/15/88 NARRATIVE

SUMMARY

Month: January, 1988 Catawba Unit 1 began the month of January out of service due to a Turbine overspeed Trip Test. The unit returned to service at 0030 on 01/01, and held power at 22% to investigate low temperature indications on the "A" and "C" Feedwater lines. The unit was then held at 23% power due to a restriction in an upper steam generator nozzle. The unit was removed from service at 1749 on 01/01, due to an inability to establish reverse purge prior to steam generator nozzle swap. The unit returned to service at 0302 on 01/02, and following several startup related power holds, reached 100% full power at 2220 on 01/06.

On 01/09 at 1625, power was reduced to 98% due to secondary side thermal output uncertainties. The unit returned to 100% power at 2114 on 01/12. The unit was removed from service at 0457 on 01/16, due to a Reactor Coolant System thermocouple problem. While the unit was off line, a pipe break was found in the Condenser Circulating Water System, which kept the unit off line until 7

l 01/23. While returning the unit to service on 01/23, the Reactor tripped due to low main steam pressure during startup. The unit returned to service at 1629 on 1

(

01/24, and following several power holds, reached 98% power, limited in output by out of spec reactor coolant flow.

l l

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MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: December, 1988 3.

Scheduled restart following refueling: Feb rua ry, 1989 l

4.

Will refueling or resumption of operation thereafter require a technical l

specification change or other license amendment? No If yes, what will these be?

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

S.

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

Inportant licen.

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

l 7.

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

Present licensed fuel pool capacity: 1418 l

Size of requested or planned increase:

l 9.

Projected date of last refueling which can be accommodated by present licensed capacity: September, 2011 l

DUKE POWER COMPANY DATE: February 15, 1988 Name of

Contact:

J. A. Reavis Phone: 704-373-7567

4 OPEPATING DATA REPORT DOCKET 50-414 DATE 2-15-09 OFEFA11N5 STATUS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567

1. Unit Nase: CATAWBA 2

2. Reporting Period: JANUARY 1, 19BS-JANUARY 31,1998

3. Litensed Theraal Fener (Nt):

3411

6. Naseplate Pating (Gross Ne):

1305 i Noces *Naseplate Rating I

5. Design Electrical Rating (Net Ne):

1145 I (Gross He) calculated as 1

6. Maxieus Depend ele Ca;acity (Gross Ne):

1 1450.000 NA x 90 pcuer i

7. Maxisue Dependable Capacity (Net N 1129 I factor per Page lit, I

8. If Changes Occur in Capacity Ratings (! tees Nuster 3 Through 71 Since Last i NORES-0020.

I Re;ert. 6iye Reasois:....................................................

I I

9. Poaer Leye1 To Which Re5tricted, If Any (Net We1:

10. Reason For Re5trictiens, If any:......................................................................................

This Month Yr.-to-Date Cuaulative

11. Hours in Reporting Feriod 744.0 744.0 12,745.0

12. Nuoter Of Hours Reactor Was Critical 0.0 0.0 8,605.5

13. Reactor Reserve Shutdeun Heurs

--0--

--0--

- 14. Hours Secerator On-Line 0.0 0.0 8,344.6

15. Unit Reserve Shutdoun Hours

--0--

--0--

--0--

16. Gross Thersal Energy Generated (NH) 0 0

25,727,493

17. Stoss Electrical Energy Generated (NH) 0 0

9,077,029

18. Net Electrical Energy Generated (NH)

(4,336)

(4,336) 8,462,361

19. Unit Service Factor 0.0 0.0 65.5

20. Unit Availability Factor 0.0 0.0 65.5

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 59.0

22. Unit Capacity Fa. tor (Using DER Net) 0.0 0.0 58.0 23, Unit Forced Outage Rate 0.0 0.0 22.9

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

.....c.r.9 nth.E91.w.U.u............................................................................................

ar

25. If 55u t ce.n At End Of Report Period. Estinted Date of Star tup:,,f.e.t r,g,ry,,p,g,,1,9,8,8,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

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26. Units In Test Status (Prior to Coseercial Operation):

Forecast Achieved th!TIAL CRITICAllif INITIAL ELECTRICITY CCM."ERCIAL 0FERAi!04

AVERAGE DAILY UNIT F0WER LEVEL DOCKET NO 50-414 UNIT Catamba 2 DATE February 15,1988 CCMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH JANUARY,1988 FAY AVEFASE DAILY POWER LEVEL DAY AVERA6E DAILY POWER LEVEL (MWE-Net)

(MWE-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

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24 0

9 0

25 0

10 0

26 0

11 0

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29 0

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DOCKET NO:

50-414 UNIT:

Catawba 2 DATE:

02/15/88 NARRATIVE

SUMMARY

Month:

January, 1988 Catauba Unit 2 was out of service for the entire month of January due to its End of Cycle 1 Refueling Outage.

6 MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 2 2.

Scheduled next refueling shutdown: Currently Refueling 3.

Scheduled restart following refueling: February, 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, unreviewed design or performance analysis mothods, 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: February 15, 1988 Name of

Contact:

J. A. Reavis Phone: 704-373-7567

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.

Personnel Exposure For the month of December, no individuals exceeded 10 percent of their allowable annual radiation dose limit.

2.

The total station liquid release for December has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

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

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DUKE PowEn GOMPANY

~

P.O. box 33189 CHARLOTTE. N.C. 28949 HAL B. TUCKER reursson exu reseman (yo4) any4g3 3rttLEAe peopCCTION

+ _

February 15, 1988 U. S. Nuclear Regulatcry Commission Attention:

Document Control Der,k Washington, D. C.

20555 Ret Catawba Nuclear Statior, Docket No. 50-413 and 50-414

Dear Sir:

Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of January, 1988.

Very truly yours, O

Y g

I Hal B.

Pucker JAR /1392/sbn Attachment 7

xc:

Dr. J. Nelson Grace INPO Recorda Center l

Regional Administrator, Region I Suite 1500 U. S. Nuclear Regulatc.ry Commission 1100 Circle 75 Parkway 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30323 Mr. Richard G. Oehl, NE-44 Mr. Phil Ross U. S. Department of Energy 5

U. S. Nuclear Regulatory Commission 19901 Germantown Road I

MNBB-5715 Germantown, Maryland 20874 i

Washington, D. C.

20555 American Nuclear Insurers I

Dr. K. Jabbour, Project Manager c/o Dottie Sherman, ANI Library Office of Nuclecr 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

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