ST-HL-AE-3594, Monthly Operating Repts for Sept 1990 for South Texas Project Electric Generating Station Units 1 & 2

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Monthly Operating Repts for Sept 1990 for South Texas Project Electric Generating Station Units 1 & 2
ML20064B298
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 09/30/1990
From: Kent A, Mcburnett M
HOUSTON LIGHTING & POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3594, NUDOCS 9010160072
Download: ML20064B298 (14)


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Houston Lighting & Power October 9, 1990 ST-HL AE 3594 File No.: G02 10CFR50.71 U. S. Nuclear Regulatory Commission Attention: Document Control Desk-Washington, DC 20555 South Texas Project Electric Generating Station Units 1 & 2 Docket Nos. STN 50 498 & 50-499 j Monthly Operating Reoorts for Seutember. 1990-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 September, 1990.  ;

i If you should have any questions on this matter, please contact  ;

Mr. C. A. Ayala at (512) 972 8628.  ;

l hfkt M. A. McBurnett Manager, Nuclear Licensing-RAD / amp i Attachments: 1) STPEGS Unit 1 Monthly Operating Report - September, 1990

2) STPEGS Unit 2 Monthly Operating Report - September, 1990 hhb R

i At/m.m A Subsidiary of Houston Industries incorporated h

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. Houstrn Lighting & Power Company South Texas Project Electric Generating Station File No.:002 I Page 2 cc:

Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission- Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company l Arlingtor., TX 76011 P. O. Box 61867 1 Houston, TX 77208 George Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 circle 75 Parkway J. I. Tapia Atlanta, CA 30339-3064 Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 port Lane P. O. Box 910 Be11 port, NY 11713 Bay City, TX 77414 _

i D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Department of Health 1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756 3189 R. P. Verret/D. E. Ward Central Power & Light Company P. O, Box 2121 Corpus Christi, TX 78403 J. C. Lanier/M. B. Lee City of Austin Electric Utility Department P.O. Box 1088 j Austin, TX 78767 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 l

i Revised 10/08/90 L4/NRC/

- ATTACHMENT 1 ST-HL AE - 3 5P'

. ., ~'. PAGE I 0F b _

l SOUTH TEXAS PROJECT I ELECTRIC GENERATING STATION UNIT 1 i

MONTHLY OPERATING REPORT  !

SEPTEMBER 1990 HOUSTON LIGHTING AND POWER CO. j NRC DOCKET NO. 50-498 ,

LICENSE NO. NPF-76 i

l Reviewed M -

10[%do  ;

Supervisor Date .{

Revi y: bWS- -

/a/8

  • Plantin eeringfa' ager 'Date Approved By- ~~

n0lNQc Plant Man er. Date i

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. _. ATTACHMENT I ST-HL-AE- TOM PAGE 2- 0F G '

Monthly Su-- ry STPEGS Unit 1 began the reporting period slightly below 100% reactor power to allow a margin for possible transients due to speed spikes in the steam ,

generator feedwater pumps caused by a bad DC power supply in the 7300 cabinet, t

On 9/09/90 a loss of power to Class 1E distribution panel #2 was. experienced.

l The inverter for the power supply failed and could not be repaired during the '

Technical Specification allowable outage time. The unit was removed from service at 1330 on 9/10/90, the inverter was repaired and the unit returned to service on 9/13/90 at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />.

During the performance of a feedwater isolation valve .(WIV) surveillance test on 9/29/90 an I&C technician installed a jumper to the wrong terminal causing 1A WIV to go fully closed. The reactor was manually tripped at 0230 '

hours. The unit concluded the reporting period in mode 4 recovering from the trip.

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a ATTACHMENT I ST HL-AE- 336 PAGE- 3 0F 4 OPERATING DATA REPORT DOCKET NO. 50-498 UNIT 1 DATE Oct. 8. 1990-'

COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 OPERATING STATUS

1. REPORTING PERIOD: 09/01-09/30 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800  ;

MAX. DEPEND. CAPACITY (MWe Net): 1250.6 '

DESIGN ELECTRICAL RATING'(MWe Net): 1250.6

3. POWER LEVEL TO WIICil RESTRICTED (IP ANY)(MWe-Net); None
4. REASONS FOR RESTRICTION'(IF ANY):- N/A TilIS MONTH ' YR TO DATE CUMULATIVE
5. WUMBER' 0F 110URS REACTOR WAS CRITICAL. . . . . 617.2 4424.2 '12671.5 i
6. REACTOR RESERVE SHUTDOWN HOURS........... 0 0 0 .
7. Il0URS GENERATOR ON LINE.................. 603.7 4127.8 12066.9-
8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 . f.
9. GROSS THERMAL ENERGY GENERATED (MWt).... 2174774 14941173 43619607 i i
10. CROSS ELECT 111 CAL ENERGY GENERATED (MWH).. 716610 4984340: 147149}2.
11. NET ELECTRICAL ENERGY GENERATED (MWI).... 681516 4709671 13834340
12. REACTOR SERVICE FACTOR................... 85.7% -67.5% 68.8%
13. REACTOR AVAILABILITY FACTOR.............. 85.7% 67.5%- 68.8%
14. UNIT SERVICE FACT 0R...................... 83.8% 63.0% 65.5%
15. UNIT AVAILABILITY FACTOR................. 83.8% 63.0% 65.5%
16. UNIT CAPACITY FACTOR (Using MDC)......... 75.7% 57.5% 60.1%
17. UNIT CAPACITY FACTOR (Using Design MWe).. 75.7% 57.5% 60.1%
18. UNIT FORCED OUTACE RATE.................. 16.2% 10.6% 9.6%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Scheduled 70-day refueling outage to begin March 2, 1991.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 10/10/90

. .- " ATTACHMENT y4 6

ST-HL AE- 3 PAGE__ E 0F.__ L

" AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 498 UNIT 1 DATE Get. 8. 1990 .i l COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 j MONTH SEPTEMBER DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 '1212 .17- 1214 2 1214 18 1202 f

3 1209 19 1208 r

4 1209 20 '1213 5 1206 21 1214-6 1212 22 1212 7 1215 23- 1193 8 1213 24 '1153 ,

9 1212 25 1204 10 539 26 1197 11 0 27 1193 l

.12 0- 28 1195  !

13 80 29 91 l 14 416 30 0 i

15 898 31 N/A 16 1139

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-498 UNIT 1 -

DATE Oct. 8. 1990-COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 REPORT MONTH SEPTEMBER 1 2 3 4 5 No. Date Type Duration Reason Method of Licensee System Component Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent Recurrence Down Report #

Reactor 90-14 900910 F 70.8 A 1 1-90-021 EA INVT The unit was removed from service due to the failure of an inverter to the Class 1E electrical distribution panel that could not be repaired during the Technical Specification allowable outage time. The inverter was repaired and the unit was returned to service. Additional corrective actions are addressed in the LER.

90-15 900929 F 45.5 B 2 1-90-023 SJ ISV During the performance of a feedwater isolation valve (FWIV) surveillance an I&C technician installed a jumper to the wrong terminal causing the LA FWIV to go fully closed. The reactor was manually tripped in accordance with the procedure.

Recurrence measures will be addressed in the LER.

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F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explain) 1-Manual I"Ef!$f B-Maintenance or Test 2-Manual Scram  %;((

C-Refueling 3-Automatic Scram gp ' 00 D-Regulatory Restriction 4-Cont. of Existing @~4 E-Operator Training & License Exam Outage $3 [n -

F-Administrative 5-Reduction 4. _

G-Operational Error (Explain) 9-Other ('

H-Other (Explain)

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. . AT1 ACHMEin T ST-HL-AE 3594 ' G PAGE __L OF 20RVs and Safety Valves Stimmary r

There were no PORV or Safety Valve challenges during this reporting period, ,

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ATTACHMENT 2.  :

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PAGE .__L_0F I  ;

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i SOUTH TEXAS PROJECT

.' ELECTRIC GENERATING STATION. '[

UNIT 2 i

MONTHLY OPERATING REPORT SEPTEMBER 1990-HOUSTON LICHTING AND POWER.CO,  !

NRC DOCKET No. 50-499 ,

LICENSE NO. NPF-80 .

t:

Reviewed  :

10 /9!90 Supervisor Date '

Revi By: Iw /o/Mk

  • Plant'$n incering Manager Date-Approved By: u ,- [.. t /0 /A /fo PlantMa\Tager '

Date 4

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. ATTACHMENT ' 2.

ST HL-AE- ~ 3 53 PAGE- 2- .OF k Monthiv Sa===ry STPEGS began the reporting period at 100% reactor power..

On>9/17/90 at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> the . unit experienced a react'or trip. during the j' performance of a scheduled surveillance test on the ' reactor trip breakers. The l

trip occurred when a non licensed operator inadvertently manipulated the Train i

"R" reactor trip breaker test pushbutton instead of the Train "S" reactor trip breaker test pushbutton. The surveillance test was satisfactorily completed

) and the unit was returned to service on 9/18/90 at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br />.

The unit was removed from service on 9/29/90 at 0232 for refueling and-scheduled maintenance.

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- - ATTACHMENT39 W L.

- ST-HL-AE $_. OF h -

PAGE-OPERATING DATA REPORT DOCKET NO. 50 499 UNIT 2-DATE Oct. 8. 1990 COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 s OPERATING STATUS l  :

1. REPORTING PERIOD: 09/01-09/30 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING (MWe Net): 1250.6
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe Net): None 4 REASONS EVR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5.- NUMBER OF HOURS REACTOR WAS CRITICAL..... 650.7 __

5397.4- 8374'.3 t

6. REACTOR RESERVE SHUTDOWN HOURS........... 0 0 0
7. HOURS GENERATOR ON LINE.................. 632.5 4990.1 '7836.8
8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 ,

h i 9. GROSS THERMAL ENERGY GENERATED-(MWt).... 2361563 18573980 28096356 l 10. GROSS ELECTRICAL ENERGY GENERATED (MWH).. 794860 6274700 9487730 11, NET ELECTRICAL ENERGY GENERATED (HWH) . . . . 755618 5942413 8963587 (

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.12 . REACTOR SERVICE FACTOR................... 90.4% 82.4%' 74.43 ,

13. REACTOR AVAILABILITY FACTOR. . . . . . . . . . . . . . 90.4% 82.4% '74.4%
14. UNIT SERVICE FACTOR...................... 87.8% 76.2% 69.6%
15. UNIT AVAILABILITY FACTOR................. 87.8% 76.2% 69.6%
16. UNIT CAPACITY FACTOR (Using MDC)......... 83.9% 72.5% 63.7%' j
17. UNIT CAPACITY FACTOR (Using Design MWe).. 83.9% 72.5% 63.7%
18. UNIT FORCED OUTAGE RATE.................. 6.2% 22.7% '22.0%
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: 12/08/90

' ATTACHMENT 2. ,

..PAGE ST-HL-AE4 0F 35'If V AVERAGE DAILY UNIT, POWER LEVEL DOCKET NO. 50-499

' UNIT 2 ,

DATE Oct. 8. 1990 COMPLETED BY A.P. l'ent TELEPHONE ' 512/972-7786-MONTH SEPTEMBER DAY AVERACE DAILY POWER LEVEL DAY- AVERAGE DAILY POWER LEVEL' .i (MWe-Net) (MWe Net)'

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1231 17 138 2 1234 18 0 3 1236 19 896 4 1236 20 1228 5 1236 21 1227 6 1236 .22 1222 7 1238 23 1223 8 1237 24 1221-9 1238 25 1222 10 1238- 26 1214 l

l- 11 1227 27 1225' i

l 12 1232 28 996 13 1237 29 0 14 1238 30 0 l

15 1237 31 N/A 16 1235 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-499 UNIT 2 DATE Oct. 8. 1990' COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 REPORT MONTH SEPTEMBER 1 2 3 4 5 No. Date Type Duration Reason Method of Licensee System Component Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent' Recurrence Down Report #

Reactor 90-12 900917 F 42.0 G 3 2-90-013 JC BKR. A Reactor / Turbine trip occurred when a non-licensed operator inadvertently.

manipulated the Train "R" reactor trip test pushbutton instead of ~ the Train "S" reactor trip breaker test pushbutton.

during surveillance testing. The reactor trip breaker: surveillance was satisfac-torily completed and the unit was returned to service.

90-13 900929 S 45.5 -C 1 N/A N/A N/A Refueling and scheduled maintenance outage.

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$N F: Forced Reason: Methodi IEEE 805-1983 IEEE 803A-1983 "'kE!$

S: Scheduled A-Equipment Failure (Explain) 1-Manual- pgj{

B-Maintenance or Test 2-Manual Scram Ut

  • rn C-Refueling. 3-Automatic Scram gh S D-Regulatory Restriction 4-Cont. of Existing $$jg E-Operator Training & License Exam . Outage. 4f

.F-Administrative 5-Reduction P G-Operational Error (Explain) 9-Other H-Other (Explain)

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. ATTACHMENT- t- I-

, . ST-HL-AE-' >Gi f -

PAGE__(e_0F_k ~

'PORVs and Safety Valves Sn==ary There were no PORV or Safety Valves challenges during this reporting period.

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