ML20213G967

Monthly Operating Rept for Apr 1987

ML20213G967
Person / Time
Site:	Harris
Issue date:	04/30/1987
From:	Watson R, Westmoreland J CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-872012-(O), NUDOCS 8705190066
Download: ML20213G967 (8)

Text

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OPERATING DATA REPORT DOCKET NO. 050-400 DATE 5/6/87 COMPLETED BY J. H. WESTMORELAND TELEPHONE (919) 362-2597 OPERATING STATUS

1. Unit Name: Shearon Harris Unit 1

2. Reporting Period: April 1987 Notes:

3. Licensed Thermal Power (MWt):

2775 Plant in Commercial

4. Nameplate Rating (Gross (MWe):

950 Operation Status on

5. Design Electrical Rating (Net-MWe):

900 May 2, 1987.

6. Maximum Dependable Capacity (Cross-MWe): 950

7. Maximum Dependable Capacity (Net-MWe):

860

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Cive Reasons: N/A

9. Power Level To Which Restricted, If Any (Net-MWe): None

10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative

11. Hours in Report Period 719 2425 2425

12. Number Of Hours Reactor Was Critical 629.74 1764.01 1764.01

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 602.55 1545.9 1545.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Cross Thermal Energy Generated (MWH) 1300085.28 2297819.88 2297819.88

17. Cross Electrical Energy Generated (MWH) 403326 645459 645459

18. Net Electrical Energy Generated (MWH) 364422 546440 546440

19. Unit Service Factor N/A N/A N/A

20. Unit Availability Factor N/A N/A N/A

21. Unit Capacity Factor (Using MDC Net)

N/A N/A N/A

22. Unit Capacity Factor (Using DER Net)

N/A N/A N/A

23. Unit Forced Outage Rate N/A N/A N/A

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

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

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

Forecast Achieved INITIAL CRITICALITY 12/30/86 1/3/87 INITIAL ELECTRICITY 1/11/87 1/19/87 COMMERCIAL OPERATION 4/25/87 5/2/87 8705190066 870430 PDR ADOCK 05000400 R

PDR L

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CP&L CO.

LANT PERFORMANCE DATA SYSTEM APPENDIX B - AVERAGE DAILY POWER LEVEL HARRIS UNIT 1 DOCKET No. 050-400 COMPLETED BY J. H. WESTMORELAND TELEPHONE (919) 362-2597 4

April 1987 DAY AVC. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 274 17 729 2

505 18 742 3

261 19 735 4

41 20 739 5

560 21 160 6

605 22 545 7

606 23

-39 8

609 24 236 9

590 25 795 10 587 26 781 11 587 27 493 12 265 28 819 13 460 29 824 14 411 30 820 15

-30 16 498

- MEM/DATAREPORT/2/OS2

UNIT SHUTDOWNS AM) POWER REDUCTION DOCKET NO.: 050-400 UNIT NAME: Harris DATE: 5/6/87 CO WLETED BY:

J. H. Westmoreland REPORT MONTH: April 1987

. TELEPHONE: (919) 362-2597 I

2 T

R Method No.

Date y

Duration e

of Licensee System Component Cause & Corrective p

(Hours!

a Shutting Event Code 4 Code 5 Action to e

s Down' Report i Prevent Recurrence 3

o Reactor n

87-013 4/3/87 F

30.35 B

2 87-018 i+1 INSTRU Manual reactor trip due to 4

loss of feedwater triggered by a loss of Condensate i

Booster Pump IB.

Test i

Engineers were monitoring plant process instrumenta-l tion with a personal computer and it induced an i

alarm signal followed by a l

Booster Pump Trip. The I

test connections were removed and the unit was returned to service.

I 2

3 4

F: Forced Reason:

Method:

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

B-Mainte.iance or Test 2-Manual Scram.

Entry Sheets for Licensee C-PF ueltag 3-Automatic Scrae.

Event Report (LER) File D-Regu'arory Restriction 4-Continued (NUREG-0161) a l

E-Operator Training & License Examination 5-Reduced Load F-Administrative 6-Other 5

j G-Operational Error (Explain)

Exhibit I-Same Source I

H-Other (Explain)

)

Corrective action to prevent recurrence as per the Licensee Event Report f

~

MEM/DATAREPORT/0$2

.m m,_

UNIT SMJTD00mS AND POWER REDUCTION DOCKET NO.: 050-400 UNIT NAE: Harris DATE: 5/6/87 j

.CorLETED BY:

J. H. Westmoreland REPORT MONTH: April 1987 TELEPHONE: (919) 362-2597 T

R Method I

2 No.

Date y

Duration e

of Licensee System Component Cause & Corrective j

p (Hours) a Shutting Event Code 4 Code 5 Action to j

e s

Down Report #

Prevent Recurrence 3

o Reactor i

n 87-014 4/12/87 F

10.68 8

2 87-019 let Pur Manual reactor trip due to j

loss of feedwater. Loss i

of feedwater transient initiated by trip of both

{

condensate pumps on high l

discharge temperature.

1 The reactor was manually tripped due to an impending 4

j loss of feedwater trip.

1 e

b 1

2 3

4 3

j 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) File D-Regulatory Restriction 4-Continued (NUREG-0161)

E-Orerator Training & License Examination 5-Reduced Load i

F-Administrative 6-Other 5

f G 4perational Error (Explain)

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

• Corrective action to prevent recurrence as per the Licensee Event Report

~

NEM/DATAREPORT/OS2

1 UNIT SHUTDOWNS ADD POWER REDUCTION DO(XET NO.: 050-400 UNIT NAME: Harris DATE: 5/6/87 COIW'LETED BY:

J. H. Westmoreland REPORT MONTH: April 1967 TELEPHQNE: (919) 362-2597 k'

I 2

T R

Method No.

Date y

Duration e

of Licensee System Component Cause & Corrective p

(Hours) a Shutting Event Code 4 Code 5 Action to e

s Down Report i Prevent Recurrence 3

o Reactor n

87-015 4/14/87 F

29.51 B

2 87-021 HF HTEXCH Nanual reactor trip due to an impending loss of feedwater, debris from the Cooling Tower entered the circulating water system through maintenance of the strainers. Debris blocked the cooling water inlet on the main condenser causing temperatures to increase and caused the Condensate Pumps to trip. The water box tube sheets were cleaned and unit was returned to service.

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 Tes?

2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File D-Pegulatory r.estriction 4-Continued (NUREG-0161)

E-Operator Training & License Examination 5-Reduced Load F-Administrative 6-Other 5

G-Operational Error (Explain)

Exhibit 1-Same Source H-Other (Explain)

Corrective action to prevent recurrence as per the Licensee Event Report MEM/DATAREPORT/OS2

.m.

.~_..

-... ~

~

.... ~ _

J i

UNIT SHUTDOWNS A W POWER REDUCTION DOCKET NO.: 050-400 UNIT NAME: Herris DATE: 5/6/87 COWLETED BY:

J. H. Westmoreland REPORT MONTH: April 1987 TELEPHONE: (919) 362-2597 I

I 2

T R

Method No.

Date y

Duration e

of Licensee System Component Cause & Corrective p

(Hours) a Shutting Event Code 4 Code 5 Action to e

s Down Report #

Prevent Recurrence 3

j o

Reactor n

j 87-016 4/21/87 F

11.0 A

2 87-024 Mi PW Manual reactor trip due to

]

loss of feedwater triggered by a Heater Drain Pump 1A trip, initial investigation revealed Pump 1A tripped due to low differential j

pres =ure followed by Pump 18. Feed Pump IA and j

i 1B then tripped on low suction pressure. Trio time delay for Main' Feed Pump adjusted and several Heater Drain Pump trips eliminated.

.I l

1 2

3 4

]

F: Forced Reason:

Method:

Exhibit G-Instructions f

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

B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee 1

C-Refueling 3-Automatic Scram.

Event Report (LER) File j

D-Regulatory Restriction 4-Continued (NUREG-Ol61)'

i E-Operator Training & License Examination 5-Reduced Load l

F-Administrative 6-Other 5

l G-Operational Error (Explain)

Exhibit 1-Same Source j

H-Other (Explain)

Corrective action to prevent recurrence as per the Licensee Event Report I ',

MEM/DATAREPORT/OS2 4

i t

UNIT SHUTDOWNS AIO POWER REDUCTION DOCKET NO.: 050-400' UNIT NADE: Herris DATE: 5/6/87 COWLETED BY:

J. H. Westmoreland REPORT MONTH: Aorli 1987 TELEPHONE: (919) 362-2597 I

2 T

R Method No.

Date y

Duration e

of Licensee System Component Cause & Corrective p.

(Hours) a Shutting Event Code 4 Code 5 Action to e

s Down Report #

Prevent Recurrence 3

I o

Reactor n

87-017 4/22/87 F

29.2 A

2 87-025 let Pur Menval reactor trip due to loss of feedwater triggered by the loss of Heater Drain Pump 1A.

Initial investiga-tion revealed Heater Drain Pump 1A tripped when its discharge valve failed shut.

Trip time delay for Main-Feed Pump adjusted and several Heater Drain Pump tripe eliminated.

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) File D-Regulatory Restriction 4-Continued.

(NUREG-0161)

E-Operator Training & License Examination 5-Reduced Load F-Administrative 6-Other 5

G-Operational Error (Explain)

Exhibit I-Same Source H-Other (Explain)

• Corrective action to prevent recurrence as per the Licensee Event Report MEM/DATAREPORT/0$2 O

a.

+

Cp&L Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. O. Box 165 New Hill, North Carolina 27562 MAY I4 1997 File Number:- SHF/10-15505 Letter Number: HO-872012 (0)

Document Control Desk United States Nuclear Regulatory Commission Washington, D.C.

20555 HARRIS NUCLEAR PROJECT DEPARTMENT UNIT NO. 1 DOCKET No. 50-400 LICENSE NO. NPF-63 MONTHLY OPERATIONS REPORT

Dear Sirs:

In accordance with Technical Speciticacions 6.9.1.5 for the Harris Nuclear Power Plant, Unit No. 1, Carolina Power & Light Company herewith submits the report of operation statistics and shutdown experience for the month of April 1987.

Yours very truly, fW R. A. Watson Vice President Harris Nuclear Project MWH:Imj Enclosure cc:

Dr. J. Nelson Crace (NRC)

Messrs.

J. M. Taylor (NRC)

G. F. Maxwell (NRC-SilNPP)

R. C. Oehl (DOE)

MEM/HO-8720120/ PACE 1/0S1 y di