ST-HL-AE-3744, Monthly Operating Repts for Mar 1991 for South Texas Project Electric Generating Station Units 1 & 2

Monthly Operating Repts for Mar 1991 for South Texas Project Electric Generating Station Units 1 & 2

ML20072V573
Person / Time
Site:	South Texas
Issue date:	03/31/1991
From:	Jump W, Kent A HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3744, NUDOCS 9104220301
Download: ML20072V573 (15)

Text

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The Light c o mp a nyS uth Tesas Pn> jut Deoric C,mratig llouston Lighting & Power P.O.BoStation 289 Wadsworth, Texas 77483 April 15, 1991 ST.HL AE-3744 File No.: CO2 10CFR50.71 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Vashington, DC 20555 South Texas Project Electric Generating Station Units 1 6 2 Docket Nos. STN 50-498 6 50 499 Monthly Operatinc Reports for March. 101 Pursuant to 10CFR50.71(a) and South Texas Project Electric Genetating Station (STPEGS) Technical Specification 6.9.1,5, attached are the Monthly Operating Reports for March 1991.

If you should have any questions on this matter, please contact Mr. C. A. Ayala at (512) 972-8628.

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t ,. m Villiam J. Jump Manager Nuclear Licensing HKJ/kmd Attachments: 1) STPEGS Unit 1 Monthly Operating Report - March, 1991

2) STPEGS Unit 2 Monthly Operating Report - March, 1991 I

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[,y A Subsidiary of Houston ladustries incorporated ./ l j L

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Houston Lighting & Power Company ST-HL AE 3744 I

.- South Texas Project Electric Generating Station No.: Oc p

l Cc' Regional Administrator, Region IV Rutus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 Houston, TX 77208 l George Dick, Project Manager i

U.S. Nuclear Regulatory Commission INPO l Washington, DC 20555 Records conter 1100 Circle 75 Parkway J. I Tapia Atlanta, CA 30339 3064 Senior Resident Inspector l c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie ,

Cocmission 50 Bellport Lane l P, O. Box 910 Bellport, NY 11713 Bay City, TX 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman 6 Holtzinger, P.C. Texas Department of Health

-1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756 3189-l D. E. Ward /T. M, Puckett l Central Power and Lig!,t Company L .P. O. Box 2121 L Corpus Christi, TX 78403 l

l J. C. Lanier/M. B. Lee d l City of Austin '

l Electric Utility Department 1 L P.O. Box 1088 l Austin, TX 78767 ]

R. J . Costello/M. T. Hardt i City Public Service Board y P. O. Box 1771 l San Antonio, TX 78296-I l

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l l-l Revised 01/29/91 L4/NRC/

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l ST HL-AE 374'l PAGE i 0F l.

SOUTH TEXA5 PROJECT ELECTRIC GENERATING STAT UN UNIT 1 MONTHLY OPERATING REPORT MARCH 1991 HOUSTON LIGHTING AND POWER CO.

NRC DOCKET NO, 50-498 LICENSE NO. NPF-76 Reviewed i N'9-9I Supervisor Date Reviewed By: _U_ . -

A 130 M9/

J1 ant ' %eringMap,er Date Approved By: k M. / Yf /

PlantM.dger ( bate

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AIIACHMErd n SNlL AE 37't9 Monthly Summary PAGE OF L STPEGS Unit I remained shutdown during the reporting period for refueling and scheduled maintenance.

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.__ l ATTACHMEM i ST HL AE 3794

' FAGE._'> 0F L OPERATING DATA RFPORT DOCKET NO. 50-498 UNIT 1 DATE Apr. 4 1991 l COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 OPERATING STATUS

1. REPORTING PERIOD: 03/01-03/31 GROSS HOURS IN REPORTING PERIOD: 744 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800 l MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING (MWe Net): 1250.6

3. POWER LEVEL TO VHICH RESTRICTED (IF ANY)(MWe Net): None 4

REASONS FOR RESTRICTION (IF ANY): N/A l

1 THIS MONTH YR TO DATE CUPULATIVE

! 5. NUMBER CF HOURS REACTOR WAS CRITICAL..... 8.6 8.6 13789.7

6. REACTOR RESERVE SHUTDOVN HOURS. , ..... . 0 0 0 i

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HOURS GENERATOR ON LINE.. , .... .. .

Q 0 13141.5 H

8. UNIT RESERVE SHUTDOWN HOURS., . . ... . 0 0 0 l 9. GROSS THERMAL ENERGY GENERATED (MWt). 0 0

... 47678208

10. CROSS ELECTRICAL ENERGY GENERATED (MWH)., 0 0 16097440

! 11. NET. ELECTRICAL ENERGY CENERATED (MWH)... -18P77 -35893 15088590

12. REACTOR SERVICE FACTOR. . . . . . ..... . ,, 1.2% 0.4% 60.5%

13. REACTOR AVAILABILITY FACTOR. . . . . 1.2% 60.5$

0.41

14. UNIT SERVICE FACTOR., ... ........... 0.0% 0.0% 57.7%

15. UNIT AVAILABILITY FACTOR........ ...... 0.0% 0.0% 57.7%

16. UNIT CAPACITY FACTOR (Using MDC) . . .... -2.04 -1.3% 53.0%

17. UNIT CAPACITY FACT 0k (Using Desigr. MWe),. -2.0% -1.3% 53.0%

18. UNIT FORCED OUTAGE RATE.... ......... . 0% 100.0% 17.3%

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

N/A

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 04/07/91 l

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ATTACHMENT I ST- HL- AE- 3M 4 AVERAGE DAILY UNIT POWER LEVEL PAGE '4 0F 6 DOCKET NO. 50-498 UNIT. 1-DATE Apr. 4. 1991 '

COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 MONTH MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MVe-Net) (MVe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 J

4 C 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 _., 0 16 0

UNIT SHUTDOWNS ANu POWER REDUCTIONS DOCKET NO. 50-498 '

UNIT 1 DATE Apr. 4 1991 COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 REPORT MONTH MARCH 1 2 Licensee System4 Component 5 No. Date Type 3 Duration Reason Method of Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent Recurrence Down Report #

Reactor t

91-01 910115 S 744.0 C 4 N/A N/A N/A Refueling and scheduled maintenance outage.

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1 2 If9b; F: Forced Reason: 3 4 5 I Method: IEEE 805-1983 IEEE803A-198I 'k p rn ?hC S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram l HEE C-Refueling c)j-4 3-Automatic Scram 71 z. --

D-Regulatory Restriction 4-Cent. of Existing-E-Operator Training 6 License Exam g-Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other II-Other (Explain)

ATTACFME;4T

• Si HL-AE 37" PORVs and Safety Va_1ves Summary FAGE._L. OF . L i There were no POR\' or Safety Valves challenged during the reporting period.

ATTACHMENT 2 ST HL AE 37'4 4 PAGE \ OF 1 l

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l SOUTH TEXAS PROJECT I l

ELECTRIC GENERATING STATION UNIT 2 l MONTHLY OPERATING REPORT MARCH 1991 HOUSTON LIGHTING AND POWER CO.

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

( f Reviewed By: w_I -

/7 N'80-9' Supervisoy Date Reviewed By:_D b- r blld Y /

Plant E ic ring kan er Date Approved By: Y 10 9I Plant Manag h \ Date

1 ATT/.CHMENT 2 l ST HL AE 37" ,1 PAGE _R 0F - - -

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Monthly Summary STPEGS Unit 2 began the reporting period at 1004 reactor power.

On 3/14/91 at 1816 the unit tripped from 1006 reactor power due to a Main Generator lockout. The lockout was associated with the actuation of a high speed differential relay circuit across the Main Generator Isophase Bus and Main Generator breaker. Troubleshooting efforts indicated no faults on the Main Generator or Isophase Bus, The differential relay was replaced and no problems which could have caused the trip were identified on other protective relay circuitry. The unit was returned to service on 3/10/91 at 0917.

On 3/30/91 at 1932 the unit tripped on actuation of the Generator Lockout relay via the Main Generator Isophase Bus differential relay, A turbine and reactor trip followed. The sequence of events was similar to those that preceded the unit trip on 3/14/91. The actuation of the Main Generator Isophase Bus relay and a.ubsequent Main Generator Lockout was caused by a difference in the saturation rates of the Current Transformers associated with the Isophase Bus, The unit concluded the reporting period with analysis efforts ongoing.

ATTACHMENT 7-ST HL AE 3794 PAGE 3 0F 7 OPERATING DATA REPORT DOCKET NO. 50-499 UNIT 2 DATE Aor. 10. 1991 COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 OPERATING STATUS )

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2. REPORTING PERIOD: Q1ZQ1-03/31 GROSS HOURS IN REPORTING PERIOD: 744 j CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING (MWe-Net): _1250.6 3.

4. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe Net): None REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS DIACTOR VAS CRITICAL. . . . . 682.3 2065.5 11046.8

6. REACTOR RESERVE SHUTDOWN HOURS. . . . . . 0

.... 0 0

7. HOURS GENERATOR ON LINE.. 628.5 2002.2 10348.5

8. UNIT RESERVE SHUTDOWN HOURS. 0 0

. .. .... 0

9. GROSS THERMAL ENERGY CENERATED (MWt) . . . 2372189 7406782 37112049

10. GROSS ELECTRICAL ENERGY GENERATED (MWH).. 803590 2517310

, 12539780

11. NET ELECTRICAL ENERCY GENERATED (MWH), 764028 2403929 11852607

12. REACTOR SERVICE FACTOR.. 91.7%

95.6% 70.7%

13. REACTOR AVAILABILITY FACTOR. . 91.7% 95.6%

70.7%

14 UNIT SERVICE FACTOR.., .... ........... 84.5% 92.7% 66.21

15. UNIT AVAILABILITY FACTOR. . . . . . . . . . . 84.5% 92.7%

. ... 66.2%

16. UNIT CAPACITY FACTOR (Using MDC).. 82.1% 89.0%

. .... 60.7%

17. UNIT CAPACITY FACTOR (Using Design MWe).. 82.1% 89.Gt 60.7%

18. UNIT FORCED OUTAGE RATE., 15.5%

... . . .... 7.3% it 21

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

Refueling and scheduled maintenance outage to begin September 28, 1991.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 04/02/91

ATTACHMENT 2.

ST HL AE 37"

• PAGE 9 0F 7 AVERAGE DAILY UNIT POVER LEVEL DOCKET NO. 50-499 UNIT 2 DATE Apr . 10. 1991 COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 J

l MONTH MARCH DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe Net) (MWe-Net) 1 1241 17 0 2 1242 18 290 3 1243 19 1139 4 1241 20 1243 5 1242 21 1250 6 1243 22 1251 7 1243 23 1249 8 1744 24 1251 9 1245 25 1247 10 1245 26 1243 11 1246 27 1234 12 1244 28 1231 13 1246 29 1245 14 936 30 998 15 0 31 0 16 0

UNYT SHUTDOWNS ANu POWER REDUCTIONS' DOCKET NO. 50-499 UNIT 2 DATE Apr. 10. 1991 COMPLETED BY A.P. Kent ,

TELEPHONE 512/072-7786 -

REPORT *10 NTH MARCH 2

Method of 3 Licensee System 4 Component 5

'l No. Date. Type Duration Reason Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent Recurrence Down Report n i Reactor '

91-04 910314 F 87.0 A 3 2-91-003 EL RLY-86 Reactor / Turbine trip from 100% reactor power due to a Main Generator Lockout. -

The lockout was associated with the actuation of a high speed differential relay circuit across the Main Generator Isophase Bus and Generator Breaker.

Troubleshooting efforts indicated no faults on the Main Generator er Isophase Bus. The differential relay was replaced and no problems which could have caused the trip were identified on other protec-tive relay circuitry. Causes and corrective actions are addressed in event 91-05. '

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F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 h$.'j S: Scheduled A-Equipment Failure (Explain) 1-Manual "'0E ds B-Maintenance or Test 2-Manual Scram i> EE C-Refueling 3-Automatic Scram G" $$

D-Regulatory Restriction 4-Cont. of Existing d33 E-Operator. Training & License Exam Outage 5@ j g F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other H-Other (Explain)

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UNIT SilUTDOWNS Ahu POWER REDUCTIONS DOCKET NO. 50-490 UNIT 2 DATE Apr. 10. 1991 COMPLETED BY A.P. Kent TELEPl!ONE M /972-7786 REPORT MONTil MARCll No. Date Type Duration Reason Method of Licensee System Component Cause & Correct've Action to (flours) Shutting Event Code Code Prevent Recurrence Down Report #

Reactor 91-05 910330 F 28.5 A 3 2-91-004 EL R LY . 6 Reactor / Turbine trip due to Main Generator Lockout. The lockout occurred at the same time Unit 1 closed switchyard breaker YS10. The actuation of the Main Generator Isophase Bus relay and subsequent Main Generator Lockout was caused by a difference in the saturation rates of the Current Transformers associated with the Isophase Bus Relay.

The evaluation of the test data collected for the Main Generator Isophase Bus relay and the associated Current Transformers continues. Corrective actions associated with the Current Trans-former are being addressed in the LER.

i m cn 2-F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 d57d :1 S: Scheduled A-Equipment Failure (Explain) 1-Manual kE [$

B-Maintenance or Test 2-Manual Scram 1* ES C-Refueling 3-Automatic Scram C' 'N$

D-Regulatory Restriction 4-Cont. of Existing $35 E-Operator Training 6 License Exam Outage 5@ p p F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other li-Other (Explain)

ATTACHMENT 2.

ST HL AE '579 4 PAGE 'l 0F 'l PORVs and Safety Valves Summary There were no PORV or Safety Valves challenged durinS the reporting period.

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