ML20141E700

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Monthly Operating Rept for Mar 1986
ML20141E700
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 03/31/1986
From: Reavis J, Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8604220354
Download: ML20141E700 (8)


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OPERATING DATA REPORT DQCKET NO.

50-413 DATE 04/15/86 COhlPLETED BY J. A. Reavis TELEPilONE 704/373-7567 OPERATING STATdS

1. Unit Name.

Catawba 1 Notes

  • Nameplate Rating -

i (Gross MWe) calculated as

2. Reporting Period: March 1. 1986-March 31. 1986 1450.000_MVA x.90 power
3. Licensed Thermal Power (MWt):

3411 factor per Page 111,

4. Nameplate Rating (Gross MWe):

1205 NUREG-0020.

1145

5. Design Electrical Rating (Net MWe):
6. Maximum Dependable Capacity (Gross MWe):
7. Maximum Dependable Capacity (Net MWe):

1145

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

None

9. Power Level To Which Restricted,1f Any (Net MWe):

None

10. Reasons For Restrictions,if Any:

This Month Yr..to Date Cumulative

11. Hours in Reporting Period 744.0 2 160.0 6 625.0
12. Number Of Hours Reactor Was Critical 682.2 2 030.8 5 643.I
13. Reactor Reserve Shutdown Hours
14. Hours Generator On Line 663.7 1 994.9 5 510.6
15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (MWH) 2 079 297 6 326 200 17 016 380

.17. Gross Electrical Energy Generated (MWH) 716 970 2 215 560 5 899 829

18. Net Electrical Energy Generated (MWH) 671 533 2 086 249 5 526 763
19. Unit Service Factor 89.2 92.4 83.2
20. Unit Availability Factor 89.2 92.4 83.2
21. Unit Capacity Factor (Using MDC Net).

78.8 84.4 72.9

22. ' Unit Capacity Factor (Using DER Net) 78.8 84.4 72.9
23. Unit Forced Outage Rate 10.8 7.6 16.8 4
24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

Refueling - August 19, 1986 - 10 weeks

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

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

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY l

COMMERCIAL OPERATION

\\g 8604220354 03 PDR ADOCK O 0041 (9/77)

R PDR 4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-413

' UNIT Catawba 1

.DATE 04/15/86 COMPi.ETED BY.

J. A. Reavis TELEPHONE 704/373-7567 MONTH March. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1 145 17 964 2-1 145 18 506 3

1 141 19 1 036 4

1 137 20

-1 116 5

1 140-21 932 6

1 139 22 162 7

1 132 23 674 8

1 139 24 1 140 9

678 25 1 141 10 26 1 140 11 27 1 142 12 28 1 143 13 -

401 29 1 142 14 1 103 30 1 142 15 1 140 31 1 142 16 1 143 lNSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

9

~

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-413 UNIT NAME Catawba 1 DATE 4/15/86 REPORT MONTH March, 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s.o o eny License g

Cause & Corrective e32 "c

o3E y

y3 Event

,Be, gm, Action to No.

Date

%b o

5:E E

%5b EB BB Prevent Recurrence H

o~

a:

E m o Report #

mo oo 37-p 86-03-07 S

B CC VALVEX Control Valve Movement Test 3

86-03-09 F

46.33 A

1 HA FILTER Decreased Generator Cooling Water Flow 4

86-03-11 F

34.00 A

1 SH FILTER Auxiliary Building Ventilation Carbon Filter Loading and Retest 38-p 86-03-13 F

B RC ZZZZZZ Reactor Coolant System Leakage Calculation Varification 39-p 86-03-13 S

B HA VALVEX Weekly Turbine Testing 40-p 86-03-13 F

B WG HTEXCH Component Cooling System Heat Exchanger Capacity Testing 41-p 86-03-17 F

B XX PENETR Containment Penetration Bellows Structural Integrity Testing 42-p 86-03-17 F

F RC FUELXX Axial Flux Difference Deviation Out of Spec 43-p 86-03-21 F

A CH VALVEX Feedwater Isolation Valve Repair (Hydraulic Actuaror) 44-p 86-03-23 F

A RB INSTRU Faulty Rod Position Indication Due to Bad Displav Card 1

2 3

4 Reason:

Method:

Exhibit G - Instructions S

e led 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 4 License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(O /7 71

e.

o DOCKET NO: 50-413 UNIT: Catawba 1 DATE: 4/15/86 NARRATIVE SIRefARY Month: March. 1986 The unit began March at 100% but was forced to shutdown on March 9, 1986 when cooling water to the Generator was sharply reduced by a clogged strainer. Work was also required on Feedwater System valves and an Auxiliary Building Carbon Filter which is required operable prior to startup. The unit returned to service on March 13.

On March 17 the unit was forced to reduce power because of Mechanical penetrations which were not tested within the specified surveillence period. The unit tested the penetrations and began to increase power at a reduced rate due to Core power distribution limits. The unit was back at 100% on March 19.

On March 21 the unit was forced to reduce power to 25% to repair a Feedwater Isolation valve, but was back at 100% on March 23, where it remained for the balance of the month.

7 MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: August, 1986 3.

Scheduled restart following refueling: October, 1986 4.

Will refueling or resumption of operation thereafter equire 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, 1986_

Name of

Contact:

J. A. Reavis Phone:

704-373-7567

CATAWBA NUCLEAR STATION Monthly Operating Status Report i

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 comitment and was less than 10 percent of this limit.

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

l

DUKE PowEn GOMPANY P.O. Box 33100 CitAHLOTrE, N.C. 28242 IIALB. TUCKER retzpuoxe 9M's PSRSWENT (704) 373-4531 stra. man reonarrion April 15, 1986 Director l

Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Re: Catawba Nuclear Station Docket No. 50-413

Dear Sir:

Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of i

March, 1986.

l l

Very truly yours, Hal B. Tucker l

JAR: sib Attachment xc:

Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Phil Ross U. S. Nuclear Regulatory Commission MNBB-5715 Washington, D. C.

205f5 Dr. K. Jabbour, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission j

Washington, D. C.

20555 i

Director April 15, 1986 Page Two xc: American Nuclear Insurer c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30323 NkC Resident Inspector Catawba Nuclear Station Mr. Richard G. Oehl, NE-44 U. S. Department of Energy 19901 Germantown Road Germantown, Maryland 20874 l

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