ML20141G284

Monthly Operating Repts for Apr 1997 for South Texas Project Electric Generating Station Units 1 & 2

ML20141G284
Person / Time
Site:	South Texas
Issue date:	04/30/1997
From:	Bergendahl D, Mallen F, Parkey G HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-005649, ST-HL-AE-5649, STI30379570, NUDOCS 9705220257
Download: ML20141G284 (14)

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Th6 Light company Houston Lighting & Power out exas reject ectr c nerating tation . O. Box 289 Mworth, Texas 7.983 ,

May 15,1997 ST-HL-AE-005649 File No. G02 l STI30279570 l 10CFR50.71 1 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555  :

I South Texas Project  ;

Units 1 and 2 l Docket Nos. STN 50-498, STN 50-499 l Monthly Operatina Reoorts for April 1997 Pursuant to 10CFR50.71(a) and South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.5, attached are the Monthly Operating Reports for April 1997.

If you should have any questions on this matter, please contact D. M. Bergendahl at (512) 972-7688.

Sincerely, F. H. Mallen Manager, Planning & Controls I I

RLH/sl l Attachments: 1) STPEGS Unit 1 Monthly Operating Report - April 1997 ,

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2) STPEGS Unit 2 Monthly Operating Report - April 1997 gl l

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9705220257 970430 l PDR ADOCK 05000498 i h R PDR 1

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llllllllllllll]EJllllllllll!!ll Project Manager on Behalf of the Participants in the South Texas Project

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I Houston Nghting & Power Company ST-HL-AE-5649 T th Texas Project Electric Generating Station File No.: G02 Page 2 t

Ellis W. Merschoff Rufus S. Scott Regional Administrator, Region IV Associate General Counsel U. S. Nuclear Regulatory Commission Houston Lighting & Power Company 611 Ryan Plaza Drive, Suite 400 P. O. Box 61%7 '

Arlington, TX 76011-8064 Houston, TX 77208 Thomas W.' Alexion Institute of Nuclear Power Project Manager, Mail Code 13H3 Operations - Records Center U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 Atlanta, GA 30339-5957 David P. Loveless Dr. Bertram Wolfe i

Sr. Resident Inspector 15453 Via Vaquero ,

! c/o U. S. Nuclear Regulatory Comm. Monte Sereno, CA 95030 i P. O. Box 910 Bay City, TX 77404-0910 Richard A. Ratliff i Bureau of Radiation Control ,

i J. R. Newman, Esquire Texas Department of Health i Morgan, Lewis & Bockius 1100 West 49th Street 1800 M Street, N.W. Austin, TX 78756-3189 l Washington, DC 20036-5869 l J. R. Egan, Esquire M. T. Hardt/W. C. Gunst . Egan & Associates, P.C.

City Public Service 2300 N Street, N.W.

P. O. Box 1771 Washington, D.C. 20037 San Antonio, TX 78296 l- J, C. Lanier/M. B. Lee U. S. Nuclear Regulatory Commission City of Austin Attention: Document Control Desk Electric Utility Depariment Washington, D.C. 20555-0001 i 721 Barton Springs Road Austin, TX 78704

' Central Power and Light Company ATTN: G. E. Vaughn/C. A. Johnson i P. O. Box 289, Mail Code: N5012 Wadsworth, TX 77483 a

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SOUTH TEXAS PROJECT l ELECTRIC GENERATING STATION l.

UNIT I MONTHLY OPERATING REPORT l

APRIL 1997 l

l HOUSTON LIGHTING AND POWER CO.

NRC DOCKET NO. 50-498 i

LICENSE NO. NPF-76 l

l Reviewed By:

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D.M. hER'G5HgHL 6 Datl Approved By: 2+t4/ , W. /!/3/17 G.L. PARREY f f D6tc #

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SUMMARY

STPEGS Unit I began the reporting period operating at full power, On April 5, at 0002 the unit was removed from service to allow Control Rod Drop Testing.

The unit was returned to senice on April 5, at 2330, achieved full power on April 6, at 2251 and

operated for the remainder of the reponing period with no other unit shutdowns or significant power l reductions.

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OPERATING DATA REPORT DOCKETNO. 50-498 ~

UNIT 1 DATE May 8. I997 COMPLETED BY R.L. Hill TELEPHONE 512 972-7667

. OPERATING STATUS -

1, REPORTING PERIOD: 4/1/97-4/30/97 GROSS HOURS IN REPORTING PERIOD: 212

- 2. CURRENTLY AUTHORIZED POWER LEVEL (Mwt): 3800 MAXIMUM DEPENDABLE CAPACITY (MWe-Net): 1250.6 DESIGN ELECTRICAL RATING (MWe-Net): 1250.6

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): Nktng s

' 4. ' REASONS FOR RESTRICTION (IF ANY): N/A s THIS MONTH YR TO DATE CUMULATIVE i

' 5. . NUMBER OF HOURS REACTOR CRITICAL 2013 2,823,8 52.703.2

6. REACTOR RESERVE SHUTDOWN HOURS 0 0 0 HOURS GENERATOR ON LINE 695.5 _2.805.8 51.359.2 h 7. -  :

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' 8. UNIT RESERVE SHUTDOWN HOURS 0 9

9. . GROSS THERMAL ENERGY GENERATED (MWH) 2491 02_6 10.606."i41 189.842.005

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 893,710 3.645.900 ' 64 m 707.610 1 L _ NET ELECTRICAL ENERGY GENERATED (MWH) 859.889 _1$05.979 6.L545,499 - *

12. REACTOR SERVICE FACTOR 22 8 % 8

.981% 69 1 %

. 13. ' REACTOR AVAILABILITY FACTOR _91.Y, 8 28J.% (L)%

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14. UNIT SERVICE FACTOR 96.7 % 22J% 62J%

15.I UNIT AVAILABILITY FACTOR 96,7Y, 27J% 62J%

16, UNIT CAPACITY FACTOR (Using MDC) 95 6 % 97.4 % 64 1 %

17. UNIT CAPACITY FACTOR (Using Design MWe) 95,6Y, 22 4 % 642%

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18. UNIT FORCED OUTAGE RATE 00%

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19f SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):  !

Scheduled 24-hour outage on June 28,1997 to allow control rod drop testing and a scheduled 35 day refueling outage to begin on September 13,1997.

4 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 1

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' AVERAGE DAILY UNIT POWER LEVEL DOCKETNO. 50-498 - l UNIT 1 l DATE 'May 8.1997 ;

COMPLETED BY R.L' Hill i

TELEPHONE 512 972-7667 )

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-DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER ,

LEVEL LEVEL- l (MWe-Net) (MWe-Net) .

1 1220 17 1261 2 1211 18 1261 3 1212 19 1260 .

4 -1165 20 1263 j 5 0 21 1269 6 , 604 22 'DB 7 126Q 23 126Q 8 DB 24 1264 9 J261 25 1258 1

10 1261 26. .1261 11- 126Q 27 1260 12 1261 28 1264 13 1261 29 1212 14 1261 30 1263 15 U.1_8 31 .tll/A  ;

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UNIT SHUTDOWNS AND POWER REDUCTIONS ." '

DOCKETNO. 50-498 UNIT 1 DATE May 8.1997 COMPLETED BY R.L. Hill TELEPHONE 512 972-7667 REPORTMONTli APRIL 1 2 3 4 5 No. Date Type Dumtion ' Reason Method of. Licensee System Component Cause & Correctim Action te Prevent Recurrence (Hours) Shutting Event Code Code Down Report #

Reactor 97-02 970405 S 23.5 B 1 N/A AA ROD The unit was removed from service to allow Control Rod Drop Testing.

I 2 3 4 5 F: Forced Reason: Method: IEEE 805-1983 IEEE 803-1983 S: Scheduled - A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Cont, of Existing E-Operator Training & License Exam Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other H-Other (Explain) l

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PORVS AND SAFETY VALVE

SUMMARY

There were no PORV or Safety Valves challenged during the reporting period.

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. SOUTH TEXAS PROJECT l \

ELECTRIC GENERATING STATION l I

UNIT 2 1 1

MONTHLY OPERATING REPORT APRIL 1997 -

HOUSTON LIGHTING AND POWER CO.

NRC DOCKET NO. 50-499 LICENSE NO. NPF-80

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1 Retiewed By: Of S" h fb ]

DTM. BE yENDAHL ' Date/ [

Approved By:

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MONTHLY

SUMMARY

i STPEGS Unit 2 began the reporting period operating at full power.

On April 30, at 2158 a manual trip was initiated following the loss of control of the feedwater to D .

l steam generator. A failed controller driver card resulted in loss of control to the' main feedwater regulating ,

l valve. The driver card vas 3 replaced and the unit returned to service on May 2, at 1736. Full power was l achieved on May 4, at 0342.

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I OPERATING DATA REPORT  !

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i ' DOCENT. 50-499 l ' UNIT 2 l' DATE - May 8.1997 ~i COMPLETED BY R.L. Hill I

TELEPHONE- 512 972-7667-h OPERATING STATUS

1. l REPORTING PERIOD: 4/1/97-4/30/97 GROSS HOURS IN REPORTING PERIOD: 212 2' CURRENTLY AUTHORIZED POWER LEVEL (Mwt): 3800.  ;

MAXIMUM DEPENDABLE CAPACITY (MWe-Net): 1250.6 - i DESIGN ELECTRICAL RATING (MWe-Net): 1250.6 i 3; POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): Eqng I

4. REASONS FOR RESTRICTION (IF ANY) N/A j I

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR CRITICAL- 717.0 2.416,5 48.970 9

6. REACTOR RESERVE SHUTDOWN HOURS 0 0 0

_l 7 HOURS GENERATOR ON LINE 2L7.0 21129 47.552.5

8. UNIT RESERVE SHUTDOWN HOURS Q Q Q

9. GROSS THERMAL ENERGY GENERATED (MWH) 2.734.865 8.753.969 175.570.579

-10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 939 548 2.998.581 59.747.862'

' 11. NE'n' ELECTRICAL ENERGY GENERATED (MWH) 198.772 2.869.668 56.976.944

12. REACTOR SERVICE FACTOR 221 % 112% .ILQ%

13. REACTOR AVAILABILITY FACTOR- 291 % 812% 71.0%

14 UNIT SERVICE FACTOR 992%

82.0 % 69.0 %

15. UNIT AVAILABILITY FACTOR 221% 32 Q% 69.0 %  ;

16. UNIT CAPACITY FACTOR (Using MDC) .100.0 % 221 % 66.1 %

17. UNIT CAPACITY FACTOR (Using Design MWe) 100.0 % 29 1 % MJ% .

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18. - UNIT FORCED OUTAGE RATE 0l%

_ L2% 2Li%  ;

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19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

N/A F 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A ,

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. . t e s AVERAGE DAILY UNIT POWER LEVEL DOCKETNO. 50-499 UNIT 2 DATE May 8.1997 COMPLETED BY R.L. Hill TELEPHONE ' 512 972-7667' MONTH APRIL DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER LEVEL- LEVEL-(MWe-Net) (MWe-Net) 1 1211 17 1212 l

-2 1212 18 1269 3 1232 19 1259 4 1211 20 1260 5 1211 21 1240  !

6 1239 22 124_8 i

7 12f2 23 1269 1 8 1259 24 12s69 ,

I 9 1258 25 1212 10 1211 26 6 J2_61 11 1252 27 1260 12 126_.1 28 12M 13 1261 29 12M i

-14' 6 12_61 30 1142 1

15 1261 31 N_/A 16 - 1213 d

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UNIT SHUTDOWNS'AND POWER REDUCTIONS t

DOCKETNO. 50-899 =*

UNIT 2 DATE May 8.1997- c COMPLETED BY ' R.L. Hill '

TELEPliONE 512 972-7667  !

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REPORTMONTH APRIL t

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No. Date Type Duration Reason Method of ~ Licensee System Component - Cause & Corrective Action to Prewnt Recurrence  !

(Hours) Shutting . ' Event Code' Code Down Report #

Reactor 97-05 970430 F 2.0 A 1 2-97-006 SJ ECBD A manual trip was initiated due to low water lesel on D 't 4

steam generator. A failed driver controller card resuld in loss ofcontrol to the main feedwater regulating vahe. t

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The driver controller card was replaced.

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F: Forced Reason: Method: IEEE 805-1983 IEEE 803-1983 i S: Scheduled A-Equipment Failure (Explain) 1-Manual ,

B-Maintenance or Test 2-Manual Scram C-Refueling . 3-Automatic Scram  !

, D-Regulatory Restriction - 4-Cont. of Existing ,

E-Operator Training & License Exam Outage l F-Administrative 5-Reduction [

G-Operational Errcr (Explain) 9-Other [

H-Other (Explain) . l I

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PORVS AND SAFETY VALVE

SUMMARY

There were no PORV or Safety Valves challenged during the reporting period.

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