ML20211E276

Monthly Operating Repts for Jan 1987

ML20211E276
Person / Time
Site:	Catawba
Issue date:	01/31/1987
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8702240278
Download: ML20211E276 (15)

Text

..

t OPERATING DATA REPORT DOCKET No. 50-413 DATE 0_2-_16 _87 COhlPLETED BY J..

A. Reavis TELEPil0NE 7na/373-7567 OPERAllNG SI AIUS I* Unit Name:

catawha 1 Notes *Naineplate Rating (Gross HWe) calculated as

2. Reporting Period: Januarv 1-1987 Tanunrv 31. 1987 1450.000 MVA x.90 power

3. Licensed Thennal Power (blWI):

3411 factor per Page 111, 1305

4. Nameplate Nating (Gross MWe):

NUREG-0020.

5. Design Electrical Rating (Net MWe): 1145

6. Maximum Dependable Capacity (Gross MWe):

1145

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report Give Reasons:

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

10. Reasons For Restrictions.lf Any:

This Month Yr. to Date Cumulatise

11. Ilours in Reporting Period 744.0 744.0 13 969.0 l

12. Number of Ilours Reactor was Critical 638.7 638.7 9 676.0 l

13. Reactor Resene Shutdown Hours

14. Ilours Generator On Line 677.4 627.4 9 298.1

15. Unit Resene Shutdown Hours

16. Gross Thermal Energy Generated IMWH) 1 985 676 1 985 676 28 557 898

17. Gross Electrical Energy Generated (MWil) 699 610 699 610 9 980 342

18. Net Electrical Energy Generated (MWH) 656 878 656 878 9 279 884

19. Unit Senice Factor 84.3 84.3 66.6

20. Unit Availability Factor 84.3 84.3 66.6

21. Unit Capacity Factor (Using MDC Net) 77.1 77.1 58.0

22. Unit Capacity Factor IUsing DER Net) 77.1 77.1 58.0

23. Unit Forced Outage Rate 15.7 15.7 19.6

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

Nnno

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

26. Units in Test StJtus (Prior to Commercial Operation):

Eocecast Achie%Cd INiil \\ L CRITICA LITY INIIIA L ELECT RICIf Y COMMERCl 4L OPER A Il0N m=";*3 %$W on R

AVERAGE DA!LY UNii POWER LEVEL DOCKET NO.

50-413 UNIT Catawba 1 DATE

. 0 2...1.6..8. 7....

COMPLETED BY J. A. Reavis TELEPHCNE 704-373-7567 MONTH JANUARY,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Neti IMWE-Net) 1 731 17

!!32 2

905 18 1144 3

!!46 19 1146 4

!!46 20 1148 5

!!42 21 1146 6

!!45 22

!!44 7

!!45 23

!!41 8

!!49 24

!!40 9

!!49 25

!!40 10 1145 26 1132 11 153 27 1141 12 0

28

!!42 l

13 0

29

!!41 14 0

30 926 15 139 31 0

!6 593 i

P:gs 1 of 2 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-413 UNIT NAME CATAWBA 1 DATE 02-16-87 REPORT MONTH Januarv,1987 COMPLETED BY Jerel Reavis_

TELEPHONE (704)-373-7567 l

MET-l l

R HOD E

OF T

A SHU-LICENSE N

lY S

TING EVENT lSYS-l

'CAUSE AND CORRECTIVE O

lP DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE lE HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE i

1-p l 87-1-

1 iF

.A

-- l HH TURBIN POWER INCREASE HOLD'AT 65'/. TO REPAIR l

l l

FEEDWATER PUMP TURBINE

'1B' l

2-p 87-1-2 F

B IE INSTRU NUCLEAR INSTRUMENTATION RECALIBRATION

~

3-p 87-1-2 F

B IE INSTRU NUCLEAR INSTRUMENTATION RECALIBRATION l

l 1

87-1-11 F

91.13 A

1 IF l XXXXXX REACTOR COOLANT SYSTEM LEAKAGE-(LOOP l

l l

'1C' RTD BYPASS) l 4-p 87-1-15 F

F HG 222222 CONDENSATE DISSOLVED OXYGEN OUT OF SPEC.

l l

222222 l CONDENSATE DISSOLVED OXYGEN OUT OF l

5-p 87-1-15 lF F

l HG l

l l SPEC.

l l

l I

3

/

4 O'

h 1

2 F Forced Reason:

['

Method: l Exhibit G - Instruc'tIo'ns C'

S Scheduled A-Equipment Fa'ilure (Explain) 1-Manual for Preparatic~n of Data B-Maintenance or test 2-Manual! Scram Entry Sheets For Licensee C-Refueling 3-Automatic Scrard

_3 Event" Report (LER) 4 Other ;(Explain)- ?

-File'(NUREGh0161),

L D-Regulatory Restriction E

E-Operator Training & License. Examination.,

l ' y #

^}

j F-Administrative 5'

M T-y,

~

G-Operator Error (Explain)

'*5Exh ib li; I - Same Source.

~

T H-Other (Explain) e 9

^

_, _ _ N?

=

=.

~

ut w-1, f

Prg 2 of 2 7_

l-UNIT SHUTDOWNS AND POWER REDUCTIGNS DOCKET NO.

50-413_,7 UNIT NAME CATAWBA 1-DATE 02-16-87~

REPORT MONTH Januarv. 1987 COMFLETED BY Jerel Reavis TELEPHONE (704)-373-7567 MET-R HOD E

OF T l

.A SHU-LICENSE 1

N Y

S TING EVENT SYS-CAUSE AND CORRECTIVE l

0 P

DURATICN O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE I

6-p l 87-1-16 F

B IE INSTRU NUCLEAR INSTRUMENTATION RECALIBRATION l

TO CORRECT POWER MISMATCH i

7-P 87-1-26 S

B HB VALVEX CONTROL VALVE MOVEMENT TEST 8-P 87-1-29 F

A HH PUMPXX HIGH VIBRATIONS ON FEEDWATER PUMP

'A' 1

i 2

87-1-30 F

19.60 H

1 SB BLOWER CONTAINMENT AIR RETURN FAN DEFICIENCY MAKING BOTH TRAINS INOPERABLE 3

97-1-31 F

5.92 H

3 IE XXXXXX REACTOR TRIP DUE TO HIGH FLUX LOW l

POWER RANGE SETPOINT l

l l

l1 2

3 4

l 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 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:

Catawba 1 DATE: 02-16-8,7 NARRATIVE

SUMMARY

Month:

January 1987 Catawba Unit 1 began the month at 65% power, while repairing the "B" Feedwater pump. On 1/02, the unit increased power to 100% and operated at that level until it was-forced off line on 1/11 by a Reactor Coolant system leak. The unit returned to service on 1/15, but was forced to hold at 30% power until 1/16 by Secondary chemistry restrictions. The unit was back at 100% on 1/17.

On 1/30, the unit was forced off line due to a deficiency in both trains of the Containment Air Return Fans. The deficiency was corrected, and the unit returned to service on 1/13.- During the increase, a power surge occurred which caused the Reactor to trip. The unit remained off line for the remainder of the month.

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: October, 1987 3.

Scheduled restart following refueling: January, 1988 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be? Technical Specification Revision 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: 6j{

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: A_ gust, 2008 l

l l

f DUKE POWER COMPANY DATE: February 16, 1987 l

Name of

Contact:

J. A. Reavis Phone:

704-373-7567 l

I

OPERATING DATA REPORT DOCKET NO.

50-414 _

DATE 02-16-87 COh!PLETED BY J. A. Reavis TELEPilONE 704/171-7567 OPERAllNG STAlUS

1. Unit Name:

catawba 2 Notes

• Nameplate Rating (Gross MWe) calculated as

2. Reporting Period: January 1. 1987.innunryJ 1_

lor 7 1450.000 MVA x.90 power

3. Licensed 1hennal Power I.hlWt):

3411 factor per Page 111,

4. Nameplate Rating (Gross blWe):

1305 NUREG-0020.

5. Design Electrical Rating (Net blWe): 1145

6. Staximum Dependable Capacity (Gross hlWe):

7. blasimum Dependable Capacity (Net blWe):

1145

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Lesel To Which Restricted. If Any (Net SIWE):

10. Reasons For Restrictions. lf Any:

This 51onth Yr. to Date Cumulative

11. Ilours in Reporting Period 744.0 744.0 3 985.0

12. Number Of Houn Reactor Was Critical 683.2 683.'2 2 076.0

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 666.4 666.4 1 992.1

15. Unit Resene Shutdown Hours

16. Gross Thermal Energy Generated (SIWH) 2 177 867 2 177 867 6 222 481

17. Gross Electrical Energy Generated (5tWH) 762 600 762 600 2 1Rs 742

18. Net Electrical Energy Generated (alWH) 718 092 718 092 2 015 294

19. Unit Service Factor 89.6 89.6 50.0

20. Unit Availability Factor 89.6 89.6 50.0

21. Unit Capacity Factor (Using 51DC Net) 84.3 84.3 44.2

22. Unit Capacity Factor IUsing DER Net) 84.3 84.3 44.2

23. Unit Forced Outage Rate 5.4 5.4 49.5

24. Shutdowns Scheduled Over Next 6 Slonths (Type. Date,and Duration of Eacht:

None

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

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

Forecast Achiesed INITI A L CRIllCA LITY INITIAL ELECTRICITY CO\\lalERCIA L OPER A TION (9/ M i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-414 UNIT Catauba 2 DATE 02-16-87 COMPLETED BY J. A. Feavis TELEPHONE 704-373-7567 MONTH JANUARY,1987 DAY AVERAGE DAILY F0WER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWE-Net)

(MWE-Net) 1 1149 17 1124 2

1146 18 1136 3

1141 19 1117 4

1146 20 1125 5

1149 21 1125 6

1102 22 1125 7

999 23 1125 8

987 24 1121 9

1025 25 1124 10 764-26

!!24 11 838 27 1120 12 1117 28 709 13 1143 29 0

14 1142 30 0

15 1051 31 0

16 1066

i I

'Pagc~1 of 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414 UNIT NAME-CATAWBA 2 DATE 02-16 '

REPORT MONTH January, 1987 COMPLETED'BY Jerel Reavis

. TELEPHONE (704)-373-7567'.

MET-R HOD E

OF T

A SHU-LICENSE N

Y S

TING 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 l-p 87-1-6 F

A HJ PUMPXX POWER DECREASE TO REMOVE '2C2' HEATER l

DRAIN PUMP FOR REPAIRS l

2-p 87-1-9 F

A HH PUMPXX.

POWER INCREASE DELAY DUE TO HIGH FEEDWATER PUMP. BEARING TEMPERATURE 3-p 87-1-10 F

A RB CONROD CONTROL ROD POSITION INDICATION l

REFAIR i

4-p 87-1-11 F

F RC XXXXXX POWER INCREASE DELAY DUE TO QUADRANT POWER TILT RATIO TECH SPEC-5-P 87-1-12 F

F IA INSTRU REACTOR POWER HOLDING AT 90% TO SET 4

POWER RANGE HI FLUX TRIP SETPOINT l

i 6-p 87-1-15 F

A HJ PUMPXX-

"2C1" HEATER DRAIN PUMP HIGH BEARING j

TEMPERATURE i

i l

i i1 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 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) t i

I

.c

Page-2 of 3 UNIT SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO. _50-414 UNIT.NAME CATAWBA 2 DATE _q2-16 -

REPORT MONTH.

January. 1987 COMPLETED BY _Jere_L Reavis.

TELEPHONE (704)-373-7567

.l MET-R HOD E

OF T

A SHU-LICENSE N

Y S

TING 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 7-p 87-1-16 F

A HJ PUMPXX "2C1" HEATER DRAIN PUMP HIGH BEARING TEMPERATURE I

HA VALVEX AIR IN LINES DUE TO REPLACING VENT 8-p 87-1-19 F

A VALVE ON "2A" TURBINE HYDRAULIC OIL PUMP l

l 9-p 87-1-19 F

A HH PUMPXX "2C1" HOTWELL PUMP SEAL RUPTURE 10-p 87-1-28 F

A HB HTEXCH HIGH FEEDWATER HEATER'"2B2" LEVEL CAUSING LOW FEEDWATER PUMP SUCTION PRESSURE 1

87-1-28 F

30.83 G

3 ZZ ZZZZZZ STEAM GENERATOR "2D" FEEDWATER CONTROL VALVE FAILED CLOSED l

2 87-1-30 F

6.80 A

4 HB HTEXCH TURBINE TRIP DUE TO MOISTURE SEPARATOR REHEATER HI LEVEL 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)

_~

Page.3 of 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-414 1

UNIT NAME CATAWBA 2 DATE 02-16 '!

REPORT MONTH January. 1987 COMPLETED BY Jerel,Reavis,

TELEPHONE (704)-373-7567 a

MET-R HOD E

OF T

A SHU-LICENSE N

Y S

TING 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 3

87-1-30 S

40.00 A

4 CB HTEXCH REACTOR COOLANT DRAIN TANK HEAT EXCHANGER LEAK REPAIR i

j 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) 1 E-Operator Training & License Examination F-Administrative 5

G-Operator Error (Explain)

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

~

DOCKET NO: 50-414 UNIT: Catawba 2 DATE: 02-16-87 NARRATIVE

SUMMARY

Month: January, 1987 Catawba Unit 2 began the month at 100% power, but on 1/06 power was reduced to 88% to remove a Heater Drain pump from service.

Flux mapping was also performed which required the unit to maintain 88% power until 1/09. On 1/10, the unit reduced power from 100% to 17% to repair a Steam Generator Feedwater regulating valve. The valve repairs were completed the same day and the unit began to increase power. A hold was necessary at 82% power due to Power Tilt limits in the core. The unit was back at 100% on 1/12. The unit reduced power to 85% on 1/15 to remove a Heater Drain pump from service, but was able to return to 100% on 1/16 at reduced megawatt output due to the loss of the Heater Drain pump. On-1/28, the unit tripped after a Steam Generator Feedwater regulating valve failed closed. The unit returned to service on 1/29, but tripped on 1/30 due to high Moisture Separator Reheater levels. The unit remained off line for the remainder of the month.

- -. =_.

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 2 2.

Scheduled next refueling shutdown: December, 1987 3.

Scheduled restart following refueling: March, 1988 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A -

s 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.. Important licensing considerations (new or different design or a

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: 8.

Present licensed fuel pool capacity:

1418 Size of requested or planned increase: -

9.

)l Projected date of last refueling which can be accommodated by present licensed capacity: August, 2008 I

4 I

DUKE POWER COMPANY DATE: February 16, 1987 Name of

Contact:

J. A. Reavis Phone:

704-373-7567 j

4 I

- -,.. _. _. _.., ~.,,,. _ _ _ _. -,, _. _ _ _... _.

_,-.,._--,_,...,_,..,,_,m

CATAWBA NUCLEAR STATION

. MONTHLY OPERATING STATUS REPORT 1.

Personnel Exposure For the month of December, no individual 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 conmitment 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.

I i

f.

.. -.... -. ~ _

.. sA.

1 9

DUKE PowEn GOMPAhT P.O. HOK 33189 CHARLOTTE, N.C. 28242 HAL B.1L'CKER TELEPHONE vuos reessesse (Fo4) 373-4531 woon.sas enoncorean

' February 16, 1987 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C.

20555 Re: Catawba Nuclear Station 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,1987.

Very truly yours, bf Hal B. Tucker JAR /02/sbn Attachment xc:

Dr. J. Nelson Grace, Regional Administrator INPO Records Center U. S. Nuclear Regulatory Comission Suite 1500 Region II 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 U. S. Nuclear Regulatory Comission 19901 Germantown Road 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 Nuclear Reactor Regulation The Exchange, Suite 245 U. S. Nuclear Regulatory Comission 270 Farmington Avenue Washington, D. C.

20555 Farmington, CT 06032 l

NRC Resident Inspector Catawba Nuclear Station i

-