ML20206P372

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Monthly Operating Repts for Mar 1987
ML20206P372
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 03/31/1987
From: Reavis J, Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8704210166
Download: ML20206P372 (15)
v • d • e


Text

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OPERATIN6 DATA REFDRT DOCKET 50-413 DATE 4-15-87 COMPLETED BY J. A. Reavis 0:ERATIN3 STATUS

~~~~-~~

TELEPH04E 704/373-7567

1. Unit Nase: CATAWBA 1
2. Repertirg Period: MARCH 1, 1987-MARCH 31, 1987
3. Licensed Thereal Power (MWt):

3411

4. Naseplate Rating (Gress MWe):

1305 i Notes *Maseplate Ratirg I

5. Design Electrical Rating (het MWe):

!!45 I (Gross MWel calculated as 1 i 1450.000 MVA :.90 power i

6. Maxteue Dependable Capacity (Gross MWelt
7. Maxiste Dependable Capacity (Net MWe):

1145 i factor per Page lii, I

8. If Cnanges Cccur in Capacity Ratirgs (Itees Nueber 3 Through 7) Since Last i NUREG-0020.

I I

I Report. Eive' Reasons: ___ _

.. ~...... -.

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'U$erlNii"ToEIN~Resiribed,IfAnh'I5ei~i5eiI((~~~

._ ",[~[~,___..[.[~[~[~[~[~((",.[~~"~~~

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10. Reason For Restritttors, If any:.,.. _,..,..,,. _....,,___

This Menth Yr.-to-Date Cueulative

!!. Fours in Reportirg Period 744,0 2,160.0 15,385.0

12. %ece-Of do;rs Reactor Was Critical 515.0 1,816.0 10,853.4
13. Reacter Reserve Shuttown Hours

--0--

--0--

--0--

14. lours Benerator On-Line 476.8 1,764.1 10,434.8
15. Unit Reserve Ehutdown Ecurs -

--0--

--0--

16. Stoss The* sal Energy Se'erated (MWH) 1,491,547 5,696,504 32,268,726
17. Eross Electrical Energy Generated (MWH) 529,395 2,0!0,420

!!,291 152

18. het Electrical Energy Generated (MWH) 490,310 1,BE7,150 10,510,156
19. Unit Service Factor 64.1 81.7 67.8
20. Unit Availability Factor 64.1 81.7 67.8
21. Unit Capacity Fatter (Usinq MCC Net) 57.6 76.3 59.7
22. Unit Capacity Factor (Using DER Net) 57.6 76.3 59.7 E3. Unit Fciced Datage Rate 35.9 18.3 19.6
24. Shutdowns Echeduled Over Next 6 Montns (Type, Date, and Duration cf Eachl:

...... N.o.n..e......... -

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

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

- =...........____

E5. If Shut Down At End Of Report Fertod. Estteated Date of Startus:....................... _

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

Forecast Achieved th!TIAL CRITICALIT)

IhlilAL ELECTRICITY CCV ERCIAL OPERAT Dh

% b G704210166 870331

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PDR ADOCK 05000413 R

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AVERABE DAILY UNIT PDWER LEVEL DOCKET NO 50-413 UNIT Catawba 1 DATE April 15, 1987 COMPLETED

3. A. Reavis TELEPHONE 704-373-7567 MONTH MARCH,1987 DAY AVERASE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWE-Net)

I 1127 17 88 2

1143 18 718 3

1140 19 1119 4

1141 20 1142 5

674 21

!!43 6

0 22 1143 7

0 23 1142 8

0 24 1140 9

0 25 953 10 0

26

!!35 11 0

27

!!35 12 0

28 1136 13 0

29 1137 14 0

30 1134

=-

15 105 31 1142

=__-

16 0

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Pyga 1 of 3 UNIT SHUTDOWNS 9.ND POWER REDUCTIONS.

DOCKET-NO.

50-413-.

1 UNIT NAME _CATAW@A_1________

DATE _04415L@Z_________

REPORT MONTH _______ Match _1282_

COMPLETED BY _ GERALD _REAVIS____

j TELEPHONE

__(7_ 0_ 4 _) _ 3_ 7_ 3_ _- 7_ 5_ 6_

MET-l R

HOD E.

OF T

A SHU-LICENSE 4

f N

Y l S.

TING EVENT SYS-CAUSE AND CORRECTIVE 1

0 P

DURATION O

DOWNl REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X l NO.

CODE CODE PREVENT RECURRENCE l}-p 87 1 S

B HB VALVEX CONTROL VALVE MOVEMENT TEST' I

4 87 5 F

236.37 lA 1

'EE GENERA SHUTDOWN DUE TO DIESEL GENERATOR

'1B' l

l BEARING REPAIR j

14-p 87-3-15 F

H HH PUMPXX SECURED POWER INCREASE TO PLACE l

l SECOND FEEDWATER PUMP ON LINE.

l t

5 87-3-16 F

20.50 A

3 HH VALVEX REACTOR. TRIP DUE TO STEAM GENERATOR' l

'1A' FEEDWATER CONTROL VALVE FAILURE l

A l --

HH VALVEX

, POWER INCREASE DELAY DUE TO STEAM

-l 15-p 87-3-16 F

}

l l

GENERATOR

l VALVE REPAIR 16-p l 87-3-17 F

B IE INSTRU POWER INCREASE ON HOLD DUE TO CALIBRATION OF NUCLEAR INSTRUMENTATION i

1 2

3 4

I F Forced Reason:

Method:

Exhibit G - Instructions l

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

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

G-Operator Error (Explain)

Exhibit'I.- Same Source.

i H-Other (Explain) 1

UNIT SHUTDOWNS AND POWER.HEDUCTIONS DOCKET NO.

50-413 Pign 2 of 3 UNIT NAME _ CATAWBA _1________

DATE _Q4f15LB2_________

REPORT MONTH _______ Match _1282_

COMPLETED BY _GERALQ_REAVIS____

TELEPHONE _17Q41-323-7562___

MET-l R

HOD l

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 17-p 87-3-17 S I B

HB VALVEX CONTROL VALVE MOVEMENT TEST 18-p 87-3-17 F

A HA INSTRU TURBINE RUNBACK CAUSED BY LOSS OF EMERGENCY TRIP SYSTEM PRESSURE 6

87-3-17 F

10.33 A

4 HB VALVEX TURBINE MANUALLY TRIPPED, TURBINE CIV REALIGNMENT FAILURE (RX CRITICAL) 19-p 87-3-17 F

H HH VALVEX HOLDING POWER TO SWAP MAIN STEAM l

GENERATOR FEED REG VALVES 20-p 87-3-18 F

B IE INSTRU POWER INCREASE ON HOLD DUE TO RECALI-BRATAION OF NUCLEAR INSTRUMENTATION I

21-p 87-3-18 F

B IE INSTRU POWER INCREASE ON HOLD DUE TO RECALI-BRATION OF NUCLEAR INSTRUMENTATION 22-p 87-3-18 F

A HH VALVEX POWER INCREASE DELAY DUE TO FEEDWATER HEATER RELIEF VALVE REPAIR 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 SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-413 P ga 3 of 3 UNIT-NAME _COTAWHA_1________

DATE _Qh(15Lg2_________

REPORT MONTH _______ March _12@2_

COMPLETED BY _ GERALD _REAVIS____

TELEPHONE _12941-323:2562___

MET-l R

HOD l

E OF T

A SHU-l 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 23-p 87-3-25 S

B HB VALVEX CONTROL VALVE MOVEMENT TEST l

1 1

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)

DOCKET NO:

50-413 UNIT:

Catawba 1 DATE:

4/15/87

' NARRATIVE

SUMMARY

Month: -March, 1987 Catawba Unit i began the month at 100%, but was forced off line on 03/05 because of an inoperable emergency diesel generator. The unit returned to service on

' 03/15, but was manually tripped on 03/16 to prevent an automatic trip caused by

~

a malfunctioning feedwater regulating valve. The unit returned to service on 03/16. On 03/17 during power escalation a turbine runback occurred and the turbine was manually tripped. An intercept valve had developed hydraulic problems and the turbine was tripped to perform an investigation and make repairs. The unit returned to service on 03/17.

Power escalation was delayed on 03/18 for nuclear instrument recalibration and to repair a relief valve on a feedwater heater. The unit was back to 100% on 03/19 and remained at that level for the rest of the month.

i l

I I

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MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: October, 1987 3.

Scheduled restart following refueling: December, 1987 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: 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: August, 2008 DUKE POWER COMPANY DATE: April 15, 1987 Name of

Contact:

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

r-CFERATING DATA REPORT I

DDCKET 50-414 DATE 4-15-87 GFERATING STATUS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567

1. Unit Name: CATAWBA 2
2. Reportir.g Period: MARCH 1, 1987-MARCH 31, 1987 3.' Licersed Thersal Fower (MWt):

3411

4. Naseplate Rating (Gross MWe):

1305 i flotes *Naseplate Rating 1

5. Design Electrical Rating (Net MWe):

!!45 I (6ross MWe) calculated as 1

6. Marisue Dependable Capacity (6ress MWe):

1 1450.000 MVA :.90 power i

7. Maxisus Dependable Capacity (Net MWel:

!!45 I factor per Page lii, I

B. If Changes Occur in Capacity Ratings (! tees Naeber 3 Through 7) Since Last i NURE6-0020.

I Eeport. 6:ye Reasons:

l

_l I'EinerLevil~io'EIEh Restricted, If Any (Net MWe):

~~~~

~

~

~~

10. Reason For Restrictions, If any: _

This Month Yr.-tc-Date Cuaulative

!! Hours In Reporting Period' 744.0 2,160.0 5,401.0

12. Nusser Of Hours Reacter Was Critical 543.9 1,835.4 3.228.3 13.ReactorReserveSh
19. Hcurs eenerator Onuttonn Hours

--0--

--0--

--0--

L:ne 543.4 1,784.6 3,110.3

15. Unit Reserve Shatdenn Hours

--0--

--0--

--0--

16. Gross Thereal Energy Generated (MWH) 1,009,132 5,733,994 9,778,608
17. Gross Electrical Energy Generated (PWH) 636,669 2,002,219 3,425,361
15. Net Electrical Energy Generated (MWH) 596,771 1,879,684 3,176,886
19. Ur.it Service Factar 73.0 82.6 57.6
20. I' nit Availability factor 73.0 82.6 57.6
21. Unit Capacity Factor (Using MDC Net) 70.1 76.0 51.4
22. Unit Capacity Factor (Using DER Net) 70.1 76.0 51.4 E3. Unit Forced Outage Rate 27.0 14.6 41.7
24. Shutdowr.s Etteduled Over Next 6 Morths (Type,-Date, and Duration of Each):

Nana._-

3 "l?T$t'UEEW$nTUf Report Eirisi!Tsiliiiirbate of starten:....Aptti 1.4....tgaz 5

2e. Units !n Test Status (Frier to Coseercial Operation):

__ Forecast _

_R6....l.

eve INIT!AL CRITICALITY INIT!AL ELECTRICITY

[.~.'[."[.'

COMMERCIAL OPERAT101

4 AVERASE DAILY UNIT POWER LEVEL DOCKET N3 50-414 UNIT Catawba 2 DATE April 15, 1987 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH MARCH,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERABE DAILY POWER LEVEL (MWE-Nett (MWE-Net) i 1006 17 1116 2

1100 18 1117 3

1092 19

!!!6 4

1118 20 1115 5

1121 21 1119 6

1124 22 1059 7

1129 23 698 B

1121 24 0

9 1120 25 0

10 1123 26 0

11 1126 27 0

12 1123 28 0

13 1119 29 0

14 1121 30 0

15 1118 31 0

16 1114

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO, 50-414

~ ~~

P:ge 1 of 2 UNIT NAME [Gd5hd55[2_[___I(([

DATE _Q4415L@2___

REPORT MONTH _______ March _12@7_

COMPLETED BY _ GERALD _REAVIS____

TELEPHONE _17941-373-2567___

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 I

DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE 31-p 87 1 S

F ZZ 222222 STOPPED POWER INCREASE PER DISPATCHER REQUEST 32-p 87 1 S

B HB VALVEX CONTROL VALVE MOVEMENT TEST 33-p 87 1 S

F ZZ ZZZZZZ STOPPED POWER INCREASE PER DISPATCHER REQUEST 34-p 87 2 F

A HJ MOTORX REDUCTION TO SECURE '2C1' -HEATER DRAIN PUMP DUE TO HI MOTOR BEARING TEMPERATURE & SEAL REPAIR 35-p 87 3 F

A HJ PUMPXX HEATER DRAIN PUMP '2C1' SHAFT REPAIR (REACTOR AT 100%)

f l

l 36-p 87-3-22 S

F ZZ Z22222 POWER DECREASE PER DISPATCHER REQUEST L_

j 1

2 3

4 i

F Forced Reason:

Method:

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

.for Preparation of Data l

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

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-Ol61) l E-Operator Training & License Examination l

F-Administrative 5

l G-Operator Error (Explain)

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

9 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

_QOd414___________

Pign 2 of 2 UNIT NAME

_GATAWHA_2_________

DATE _Q4(1QLQ2__________

' REPORT MONTH _______ March _19@2_

COMPLETED BY _ GERALD _REAVIS____.

TELEPHONE _12941-323-2g62___

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 37-p 87-3-23 F

A HJ PUMPXX HEATER DRAIN PUMP '2C1' SHAFT REPAIR (REACTOR AT 100%)

S 87-3-23 F

200.65 A

3 CS VALVEX REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE OUT OF SPEC (PRESSURIZER ISOLATION VALVE LEAK) l r

1 E

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:

50-414 UNIT:

Catawba 2 DATE:

4/15/87 NARRATIVE

SUMMARY

Month: March, 1987 Catawba Unit 2 began the month in a power increase and returning from an outage.

Several holds in power increase were required due to system load and testing.

On 03/03 the efficiency of the unit was decreased after a heater drain pump was removed from service. The unit continued to operate at 100% power until 03/23 when it was forced off line by unidentified reactor' coolant system leakage. The unit remained off line for the rest of the month.

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ve-

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e,-y,-,

MONTHLY REFUELING INFORMATION REQUEST

1. -Facility name: Catawba, Unit 2 2.

Scheduled next refueling shutdown: De cember, 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 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: 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: August, 2008 DUKE POWER COMPANY DATE: April 15, 1987 Name of

Contact:

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

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... ~.

e CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT l

1. ' Personnel Exposure For the month of February, no individual 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 less than 10 percent of 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.

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o DUKE POWER GOMPANY P.O. BOX 33189 CHAmLOFFE, N.O. 28242 HAL B. TUCKER TELENOM i

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(704) 373-4aat woos.saa e

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April 15, 1987 U. S. Nuclear Regulatory Commission Attention: Document Control Desk l

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 March, 1987.

Very truly yours, NJ B. tag

.Hal B. Tucker i-JAR /18/sbn' Attachment

-xc:

Dr. J. Nelson Grace, Regional Administrator INPO Records Center U. S. Nuclear Regulatory Commission 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 Commiission 19901 Germantown Road 4

MNBB-5715 Germantown, Maryland 20874 i-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 Commission 270 Farmington Avenue Washington, D. C.

20555 Farmington, CT 06032 I-Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Ih 9

-.

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