ML20082H984

Monthly Operating Repts for Mar 1995 for Catawba Nuclear Station

ML20082H984
Person / Time
Site:	Catawba
Issue date:	03/31/1995
From:	Robert Williams DUKE POWER CO.
To:
Shared Package
ML20082H982	List: ML20082H979 ML20082H984 ML20082H986
References
NUDOCS 9504180012
Download: ML20082H984 (11)

Text

i OPERATING DATA REPORT j

DOCKET NO 50-413 DATE Acril 14.1995 OPERATING STATUS COMPLETED BY R.A. Willines TELEPHONE 704-382-5346

1. Unit Names Catawba 1

2. Reporting Period: March 1, 1995-March 31, 1995 30 Licensed Thersal Power (Mti 3411

4. Naseplate Rating (Gross MWel:

13056 Notes (Xaaeplate Rating 50 Design Electrical Rating (Net Me):

1145 (6ross MWe) calculated as

6. Marisus Dependable Capacity (Gross MWe):

1192 1450.000 MVA

.90 power

7. Maxieus Dependable Capacity (Net MWe):

1129 factor per Page lit,

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

Report. Give Reasons:

9. Power Level To Which Restricted, if Any (Net MWe):

10. Reason For Restrictions, If any:

This Month Yr.-to44te Cumulative

11. Hours in Reporting Period 744.0 2160.0 85513.0

12. Number Of Hours Reactor Was Critical 198.8 1208.3 65719.9

13. Reactor Reserve Shutdown Hours

--0--

--0--

--0--

14. Hours Generator On-Line 147.1 1130.4 64505.9 13.UnitReserveShutdownHours

--0-- -

- 16. Gross Thereal Energy Generated (MWH) 418111 3686468 209829899

17. Gross Electrical Energy Generated (MWH) 144498 1324047 74007797

18. Net Electrical Energy Generated (MWH) 125129 1241503 69564965

19. Unit Service Factor 19.8 52.3 75.4

20. Unit Availability Factor 19.8 52.3 75.4

21. Unit Capacity Factor (Using MDC Net) 14.9 50.9 71.8

22. Unit Capacity Factor (Using DER Net) 14.7 50.2 71.1

23. Unit Forced Outage Rate 14.5 2.2 8.9

24. Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Eachl None

25. If Shut Down At End Of Report Pericd. Estisated Date of Startup:

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

Forecast Achieved l

l INITIAL CRITICAllTY l

INITIAL ELECTRICITY COMMERCIAL OPERATION l

l 9504180012 950414

~

PDR ADOCK 05000413 R

PDR

~.

s OPERATING DATA REPORT DOCKETNo 50-413 UNIT Catauba 1-DATE Asril 14. 1995 -

~

COMPLETED BY ' R. A. Williams TELEPH8ME 7M-382-5346 MONTH March. 1995 MY AVERAliE DAILY POWER LEVEL M1 AYERABE DAILY PONETt LEVEL' Ulue-Net)

(MWe-Ilet) 1 0

17 0

2 0

18 0-3 0

19 0

4 0

20 0

5 0

21 0

6 0

N 0

7 0

5 0

1 8

0 24 0

9 0

25 0

10 0

26 305 11 0

27 817 1

12 0

28 1091 13 0

29 1118 14 0

30 1157 13 0

31 1160-16 0

i.

t E

T y+p.-

u-

-(+-

r

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-413 UNIT NAME mranna 1 DATE ve/14/wp__.

REPORT MONTH March 1995 COMPLETED BY x.

a.

w1111ams PAGE 1 OF 2 TELEPHONE tivej-Juz-sJen (1) 2)

3 (4)

(5)

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 RC FUELXX END-OF-CYCLE 8 REFUELING OUTAGE 1

95 1 S

565.95 C

HA

'TURBIN MAIN TURBINE OVERSPEED TEST SOAK 1-P 95-3-24 S

B 2-P 95-3-24 S

B HA TURBIN MAIN TURBINE OVERSPEED TEST SOAK HA TURBIN MAIN TURBINE OVERSPEED TRIP TEST 2

95-3-24 S

6.07 B

3 95-3-25 F

24.85 A

1 CH HTEXCH STEAM GENERATOR MANWAY LEAK RC FUELXX CORE FLUX MAPPING 3-P 95-3-26 S

A B

HB VALVEX MAIN TURBINE CONTROL VALVE MOVEMENT A-P 95-3-26 S

TESTING 5-P 95-3-27 S

A RC FUELXX CORE FLUX MAPPING (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 Sneets For Licensee C-Refueling 3-Automatic Scram Event ~ Report (LER (N N EG-0161))

D-Regulatory Restriction 4-Other (Explain)

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

G-Operator Error Exhibit I - Same' Source H-Other (Explain) (Explain)

---

---a.

l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET-NO.

50-413 UNIT NAME. vaianna 1 DATE ve / 2 4f a _.

REPORT MONTH March 1995 COMPLETED BY x.

r.. w1111ams PAGE 2 OF 2 TELEPHONE tivej-Jue-maso (1) 2)

3 (4)

(5)

E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRSCTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE-E HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE RC INSTRU REACTOR COOLANT LOOP DELTA T's 6-P 95-3-27 S

A (1)

(2)

(3)

(4)

F Forced-Reason

• Method:

Exhibit G - Instructions A-Equipment FailureB-Maintenance or test (Explain) 1-Manual for Preparation of Data

-S Scheduled 2-Manual Scram Entry Sneets For Licensee Event Report (LER (NNEG-0161) ) -

C-Refueling 3-Automatic Scram D-Regulatory R9striction 4-Other (Explain)

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

G-Operator Error (Explain) nhibit I - Same Source H-Other (Explain)

DOCKET: 50-413-UNIT:

Catawba 1 Date:

04/14/95 NARRATIVE

SUMMARY

MONTH: March 1995 Catawba Unit 1 began the month of March in end-of-cycle 08 refueling outage. The refueling outage spanned 41.61 days. The unit was placed on-line 03/24/95 at 1357 During power escalation, the unit held at 14% power on 03/24/95 from 1440 to 1740 and also at 8% power from 1751 to 1756 due to turbine overspeed test soak. On 03/24/95 at 1756 the unit was removed from service for a turbine overspeed trip test. On 03/25 at 0000 the reactor was shutdown to repair a steam generator manway leak. The unit returned to service on 03/26/95 at 0051. During power escalation, the unit held at various power levels due to core flux mapping and main turbine control valve movement testing. The unit held at 80% power on 03/27/95 from 1430 to 2055 due to reactor coolant loop delta T's. The unit returned to 100% full power on 03/29/95 at 1205. The unit operated at or near 100% the remainder of the month.

Prepared by: R. A. Williams Telephone (704)-382-5346 L

{

- ~

j I

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility names Catawba.

Unit 1 2.

Scheduled next refueling shutdown: June 1996 3.

Scheduled restart following refueling: Sootember 1996 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S.

CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.

4.

Will refueling or resumption of operation thereafter require a i

i technical specification change or other licence amendment?

If yes, what will these be7 i

If no, has reload design and core configuration been reviewed by l

Safety Review Committee regarding unreviewed safety questions?

5.

Scheduled date(s) for submitting proposed licensing action and i

supporting information.

j i

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 122

-(b) in the spent fuel pools liq f

8. Present licensed fuel pool capacity: lill size of requested or planned increases ---

9. Projected date of last refueling which can be accommodated by present licensed capacity: Sootember 2029 i

DUKE POWER COMPANY DATE: April 14, 1995 Name of

Contact:

R.

A. Williams Phone:

(7041-382-5346 P

)

OPERATING DATA REPORT DOCKET NO 50-414 DATE toril 14. 1995 OPERATIN6 STATUS COMPLETED BY R.A. Williaes

' TELEPHONE 704-382-5346

1. Unit Names Catasha 2

2. Reporting Period: March 1, 1995-Narch 31, 1995 j

3. Licensed Thersal Poser (Mtli 3411 1

4. Naseplate Rating (Gross pel:

1305+

Notes oMaseplate Rating.

l

5. Design Electrical Rating (Net Me):

!!45 (6ress Me) calculated as j

6 Marious Dependable Capacity (6ross Me):

1192-1450.000 IWA

.90 poser

7. Maxieue Dependable Capacity (Net Mels 1129 factor per Page 111,'

8. If Changes Occur in Capacity Ratings'(Itses llueber 3 Through 7) Since Last NURE6-0020.

Report. Give Reasons:

9. Power Level Te Nhich Restricted, if Any (Net Mel.

10. Reason For Restrictions, if any:

1 This Month Yr.-to-Date Cueulative

]

11. Hours in Reporting Period 744.0 2160.0 75529.0 I

12. Nueber Of Hours Reactor Was Critical 696.5 1942.6 58951.9

13. Reactor Reserve Shutdown Hours

--0--

- --0--

14. Hours Senerator On-Line 678.4 1924.3 57985.7

15. Unit Reserve Shutdown Hours

--0--

--0--

- --0--

16. Gross Thereal Energy Generated (! Mil 2266128 6511016 186209999

17. Gross Electrical Energy Generated ( MH) 800629 2314014 66013394.

18. Net Electrical Energy Generated (MH) 756666 2188277 62153830

19. Unit Service Factor 91.2 89.1 76.8

20. Unit Availability Factor 91.2 89.1 76.8

21. Unit Capacity Factor (Using MDC Net!

90.1 89.7 72.7

22. Unit Capacity Factor (Using DER Net) 88.8 88.5 71.9

23. Unit Forced Outage Rate 8.8 10.9 8.9

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

None

25. If Shut Down At End Of Report Period. Estinated Date of Startup:

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMERCIAL OPERATION

4 i

OPERATING DATA REPORT I

' DOCKET NO 50-414 istT Catasha 2

[

BATE Anril 14. 1995 l

CONPLETE8 BY R. A. Ililliams -

t TELEPHONE 704-382-5346 i

MONTH March.'1995

-v M1 AVERA6E DAILY Poller LEVEL M1 AVERAGE DAILY Poller LEVEL (llle-Ilet1 (Inle-Ileti 1

0 17 1145 2

0 18 1149 3

0 19 1153 4

619 to 1155 5

1137 21 1149 6

1147 22 1145 7

1143 23

-1142

)

8 1144 M

-1148

)

9 1152 25 1157 10 1152 26 1157 11 1151 27 '

1152 12 1149 28

-1153 13 1146 29 1155 j

10 1130 30 1154 13 1138 31 1156 16 1147

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414 UNIT NAME uranna e DATE ueIlof w:p _ _,

REPORT MONTH

-March 1995 COMPLETED BY x.

a.

williams TELEPHONE tivej-auz-oJee (1)

{2) 3 (4)

(5)

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 HB VALVEX CLOSURE OF STEAM GENERATOR

'B' MAIN 3

95 1 F

65.62 A

STEAM ISOLATION VALVE IA INSTRU NUCLEAR INSTRUMENTATION CALIBRATION 1-P 95 4 F

B 2-P 95 4 S

B HB VALVEX MAIN TURBINE CONTROL VA.VE MOVEMENT L

TESTING (1

(2 (3

(4 Forced eason*

ethod:

xhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram EntW Sneets For Licensee t

C-Refueling 3-Automatic Scram Event Report (LER (N W EG-0161))

D-Regulatory R9striction 4-Other (Explain)

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

G-Operator Error (Explain)

Exhibit I - Same Source H-Other (Explain)

. m sm.

a

. m 1

m m. v'e e e-

4 DOCKET: 50-414 UNIT: Catawba 2 Date:

04/14/95 NARRATIVE

SUMMARY

4 MONTH: March 1995 Catawba Unit 2 began the month of March in an outage due to closure of steam' generator

'B' main steam isolation valve. The. unit was placed on-line 03/03/95 at 1737. During power escalation, the unit held at 45% power on 03/04/95 from.0225 to 4

0452 due to nuclear instrumentation calibration. The unit held at 77% power from 1620 to 1705 due to main turbine control-valve movement testing. The unit resumed power escalation, and returned to 100% full power.on 03/05/95 at 0818. The unit operated at or near 100% full power the remainder of the month.

t t

Prepared by: R. A. Williams Telephones.(704)-382-5346

4.

)

,' h '.

,g s

MONTHLY REFUELING INFORMATION REQUEST

l..' Facility names Catawba.

Unit 2

~

~

'2..~ Scheduled next refueling. shutdown: ' October 1995

13. l Scheduled restart following refueling: November 1995 THE PROJECT MANAGER HAS'BEEN' ADVISED'BY SEPARATE COMMUNICATION'OF-ANY T.S.

CHANGE OR LICENSE AMENDMENT.-THEREFOR'J, QUESTIONS -4 THROUGH 6 WILL NO LONGER BE MAINTAINED'IN THIS FAPORT.

.4.

Will-refueling or resumption of operation thereafter. require a technical specification change or other licence amendment?

l

[

~l If.yes, what will these be?

If no,Lhas reload design and; core configuration been-reviewed by.

-Safety Review Committee regarding unreviewed safety questions?

5.

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

.a

-i l

. 6., ~ Important licensing considerations (new or difforent design or-i supplier, unreviewed design or performance analysis methods,-

significant changes in design or new operating procedures).

]

d

7. : Number of Fuel assemblies (a) in the core: 121 (b) in the spent' fuel' pools.411

}

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: sentember 2011 l

i DUKE POWER COMPANY DATE: Aoril 14. 1995 a

Name of

Contact:

R.

A. Williams Phones ~ (7041-382-5346 l

'l

)

a..

.