ST-HL-AE-5002, Monthly Operating Repts for Jan 1995 for South Texas Project Units 1 & 2

Monthly Operating Repts for Jan 1995 for South Texas Project Units 1 & 2

ML20078Q499
Person / Time
Site:	South Texas
Issue date:	01/31/1995
From:	Hill R, Masse R, Myers L HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-5002, NUDOCS 9502210281
Download: ML20078Q499 (14)

Text

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e The Light c o m p a n y South Texas Project Electric Generating P. O. Station Box 289 Weworth, Texas 77483 llouston Lighting & Power February 14, 1995 ST-HL-AE-5002 File No.: G02 10CFR50.71 U. S. Nuclear Regulatory :.'onm en Attention: Document Contra! Den:

Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50499 Monthly Operatina Reports for January 1995 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 January 1995.

If you should have any questions on this matter, please contact Mr. S. M. Head at (512) 972-7136.

/ fm A L. W. Myers R. E. Masse Plant Manager, Plant Manager, Unit 1 Unit 2 MKJ/lf Attachments: 1) STPEGS Unit 1 Monthly Operating Report - January 1995

, , , _ 2) STPEGS Unit 2 Monthly Operating Report - January 1995 d, .;t U (,.))

9502210281 950131 PDR ADOCK 05000498 R PDR Project Manager on Behalf of the Participants in the South Texas Project py a Mtsc 95\9Mus ooi

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Houston Lighting & Power Company ST-HL-AE-5002 South Texas Project Electric Generating Station File No.: G02 Page 2 c:

Leonard J. Callan 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 61067 Arlington, TX 76011-8084 Houston, TX 77208 Thomas W. Alexion Institute of Nuclear Power Project Manager Operations - Records Center U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 13H15 Atlanta, GA 30339-5957 David P. Loveless Dr. Joseph M. Hendrie Sr. Resident inspector 50 Bellport Lane c/o U. S. Nuclear Regulatoiy Comm. Bellport, NY l1713 P. O. Box 910 Bay City, TX 77404-0910 Richard A. Ratliff Bureau of Radiation Control J. R. Newman, Esquire Texas Department of Health Morgan, Lewis & Bockius 1100 West 49th Street 1800 M Street, N.W. Austin, TX 78756-3189 Washington, DC 20036-5869 U. S. Nuclear Regulatory Comm.

K. J. Fiedler/M. T. Hard! Attn: Document Control Desk City Public Service Washington, D. C. 20555-0001 P. O. Box 1771 San Antonio, TX 78296 J. C. Lanier/M. B. Lee J. R. Egan, Esquire City of Austin Egan & Associates, P.C.

Electric Utility Department 2300 N Street, N.W.

721 Barton Springs Road Washington, D.C. 20037 Austin, TX 78704 G. E. Vaughn/C. A. Johnson Central Power and Light Company P. O. Box 2121 Corpus Christi, TX 78403 l

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i SOUTH TEXA5 PROJECT ELECTRIC GENERATING STATION UNIT 1 NONTELY OPERATING REPORT JANL'ARY 1995 BOUSTON LIGHTI'JG AND PONER CO.

NRC DOCKET NO. 50-498 LICENSE NO. NPF-76  !

Reviewed By: _ l(> '([ [_

D. M/ BER JDAHM Dptel Reviewed By: DN F. H. MALLEN V 7[Tfif Date Approved By: M Q h t_ n L. W. MYERS N

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e ATT/4HL':ENT I ST-HL-AE 500 2, Monthly 8 - ary PAGE 1 0F le STPEGS Unit 1 began the reporting period operating at 100% reactor power.

On 1/8/95 reactor power was reduced to approximately 34% to allow for repair of a 0.2 gallon per minute leak at a compression fitting on a Reactor Coolant System flow transmitter instrument line. Repairs were completed with the unit achieving full power on 1/10/95 at 0058.

On 1/24/95 at 1528 the unit experienced a reactor trip on low steam generator level due to the loss of a steam generator feedwater pump in conjunction with the startup feedwater pump being out of service for scheduled maintenance. Corrective maintenance was performed and the unit was returned to service on 1/27/95 at 0245.

On 1/28/95 reactor power ascension was stabilized at approximately 87% to allow feedwater heater tube leak repairs. Reactor power was further reduced to approximately 72% on 1/30/95 at 0225 to repair an electro-hydraulic oil leak on a steam generator feedwater pump (SGFP) governor valve actuator. Following SGFP repairs the unit was returned to 87% reactor power at 1339 to complete feedwater heater maintenance.

Corrective maintenance was completed and the unit continued reactor power ascension on 1/31/95 concluding the reporting period at approximately 99.4% with ascension to full power in progress.

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1 ATTACHMENT I ST-HL-AE- 500 2. I OPERATING DATA REPORT PAGE 3 0F lo DOCKET NO. 50-498 UNIT 1 DATE Feb. 8, 1995 COMPLETED BY R.L. Hill TELEPHONE 512/972-7667 OPERATING STATUS

1. REPORTING PERIOD: 01/01/95-01/31/95 GROSS HOURS IN REPORTING PERIOD: 744

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 FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL..... 710.6 710.6 34663.5

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

7. HOURS GENERATOR ON LINE............. .... 684.7 684.7 33451.8

8. UNIT RESERVE SHUTDOWN HOURS......... .. 0 0 0

9. GROSS THERMAL ENERGY GENERATED (MWt)... .2476989 2476989 122298969

10. GROSS ELECTRICAL ENERGY GENERATED (MWH).. 850850 850850 41505810

11. NET ELECTRICAL ENERGY GENERATED (MWH).... 814056 814056 39325008

12. REACTOR SERVICE FACTOR.................. 95.5% 95.5% 61.4%

13. REACTOR AVAILABILITY FACTOR.............. 95.5% 95.5% 61.4%

14. UNIT SERVICE FACTOR., .. ... . ...... 92.0% 92.0% 59.3%

15. UNIT AVAILABILITY FACTOR....... ... ..... 92.0% 92.0% 59.3%

16. UNIT CAPACITY FACTOR (Using MDC)......... 87.5% B7.5% 55.7%

17 UNIT CAPACITY FACTOR (Using Design MWe).. 87.5% 87.5% 55.7

18. UNIT FORCED OUTAGE RATE............ .. . 8.0% 8.0% 30.0%

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

Scheduled 45 day refueling outage to begin on March 4, 1995.

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

-_ .= - _= _ - ._ - _ - . . _ . .. . - - . . - - . - . . .. -.

. . i NrrACHMENT I -

AvEmAGE DAILY UNIT POWER LEVEL ST-HL A 9 Soo1 i _ PAGE *- 0F L,  !

DOCKET NO. 50-498 UNIT 1 DATE Feb. 8, 1995 COMPLETED BY R.L. Hill TELEPHONE 512/972-7667 MONTH JANUARY DAY AVERAGE DAILY POWER LEVEL DhY AVERAGE DAILY POWER LEVEL '

(MWe-Net) (MWe-Net) 1 1266 17 1265 I

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2 1266 18 1266 3 1266 19 1265 4 1265 20 1266 5 1265 21 1268 )

6 1265 22 1268 7 1265 23 1268 8 101? 24 802 '

9 778 25 0

• l 10 1265 26 0 11 1264 27 466 12 1264 28 1077  ;

13 1265 29 1093 l

14 1265 30 973 l

15 1265 31 1142 l 16 1264

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-498 UNIT 1 DATE Feb. 8, 1995 COMPLETED BY R.L. Hill TELEPHC+NE 512/972-7667 REPORT MONTH JANUARY l!  ! 2 3 I 4 5!

i No.  ; Date (Type ! Duration l Reason Method of Licensee System i

Component Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent Recurrence l j l 1 Down Report #

!y j l Reactor

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l F 0.0 A 5 l N/A AB CON Reactor power was reduced to l95-01950108l l f approximately 34% to allow for repair of a j i

. i i 0.2 gallon per minute leak at a I '  !

compression fitting on a Reactor Coolant j System flow transmitter instrument line.

l95-02!950124j F  ! 59.3 A 3 1-95-001 JB CBL The unit experienced a reactor trip on low-low steam generator level in Steam i l ,

l Generator 1C. The event was initiated l  ; I when Steam Generator Feedwater Pump 13

tripped as a result of a defective cable i .f i

on the turbine thrust bearing wear l detector. The thrust bearing wear i ,

detector cable failed causing intermittent

! l l signal spiking resulting in the generation j i .

of a trip signal to the feedwater pump l' l control system. The loss of the steam generator feedwater pump in conjunction l with the startup feedwater pump being out i

l of service for scheduled maintenance

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1 2 3 4 5 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram g 7, C-Refueling 3-Automatic Scram t -:

D-Regulatory Restriction 4-Cont. of Existing G7

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E-Operator Training & License Exam Outage f" r7 47 F-Administrative 5-Reduction 7" G-Operational Error (Explain) 9-Other J 9' d; $;

H-Other (Explain) w"T1 b' 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-498 LHIT 1 DATE Feb. 8, 1995 COMPLETED BY R.L. Hill TELEPHONE 512/972-7667 REPORT MONTH JANUARY l ,  : lj i 21 3 4l 5

No. ! Date jType jDurationl Reason Method of Licensee System jComponent Cause & Corrective Action to

(Hours) Shutting Event Code Code Prevent Recurrence

, i g Down Report #

j l l Reactor l l l resulted in low water level in the steam i

!  ! generator and the subsequent reactor trip.

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The thrust bearing wear detector and the cable was replaced.

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95-031950128 F , 0.0 A 5 N/A SJ TBG Reactor power ascension was stabilized l l at approximately 87% to allow tube leak i

! repair on Feedwater Heater 15A.

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95-04 950130 F l 0.0 A 5 N/A SJ V With the unit at approximately 87%

{ reactor power while maintenance was being

} l performed on Feedwater Heater 15A, reactor

! l power was further reduced to approximately

.  ! 72% to allow repair of an electro-l hydraulic oil leak on the low pressure

! governor actuator valve of Steam Generator l l Feedwater Pump 11.

1 2 3 4 5 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram [_OM D-Regulatory Reetriction 4-Cont. of Existing Q L -4 E-Operator Training & License Exam Outage ry h F-Administrative 5-Reduction , >Z G-Operational Error (Explain) 9-Other SIP rrF OZ O --i OO Tip -

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. ATTACHMENT I ST HL-AE- 500 L PORVs and Safety Valves Sitamary PAGE - Le OF 6 I

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

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• ATTACHt.1ENT A ST-HL-AE L PhGE _ 1_ 0F- "Jooz (o SOUTE TEEAS PROJECT ELECTRIC GENERATING STATION UNIT 2 NONTHLY OPERATING REPORT JANUARY 1995 HOUSTON LIGHTING AND POWER CO.

NRC DOCKET NO. 50-499 LICENSE NO. NPF-80 Reviewed By: OA D/W _C D. M. D$RGENMHL D6te d Reviewed By: T V 21 F EN Ddte Approved By: \6 . W- // i I Rf E. MASSE Date i

ATTACHMENT 1 ST- H L-AE- soo 2 Monthly Snummary PAGE ,2 0F b STPEGS Unit 2 operated during the reporting period with no shutdowns or significant power reductions.

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. ST-HL-AE- 500 2 PAGE__3_._0F__.lo  !

, OPERATING DATA REPORT i

DOCKET NO. 50-499 UNIT 2 DATE Feb. 7, 1995  ;

COMPLETED BY R.L. Hill i TELEPHONE 512/972-7667 OPERATING STATUS

1. REPORTING PERIOD: 01/01/95-01/31/95 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800 {

3 MAX . DEPEND. CAPACITY (MWe-Net) : 1250.6 i DESIGN ELECTRICAL RATING (MWe-Net): 1250.6 l

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) : None  !

4. REASONS FOR RESTRICTION (IF ANY): N/A '

THIS MONTH YR TO DATE CUMULATIVE l t

5. NUMBER OF HOURS REACTOR WAS CRITICAL..... 744.0 744.0 30780.7

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

7 HOURS GENERATOR ON LINE.................. 744.0 744.0 29576.7 .

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8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 [

9. GROSS THERMAL ENERGY GENERATED (MWt).... 2833527 2833527 107614024  ;

10. GROSS ELECTRICAL ENERGY GENERATED (MWH).. 980770 980770 36438640 i

11. NET ELECTRICAL ENERGY GENERATED (MWH).... 941587 941587 34667842

12. REACTOR SERVICE FACTOR.... .............. 100.0% 100.0% 62.5%

13. REACTOR AVAILABILITY FACTOR ............. 100.0% 100.0% 62.5% i i

14. UNIT SERVICE FACTOR...................... 100.0% 100.0% 60.0%

15. UNIT AVAILABILITY FACTOR................. 100.0% 100.0% 60.0% .

16. UNIT CAPACITY FACTOR (Using MDC)......... 101.2% 101.2% 56.3% l

17. UNIT CAPACITY FACTOR (Using Design MWe). 101.2% 101.2% 56.3% i i

18. UNIT FORCED OUTAGE RATE.................. 0.0% 0.0% 30.1% l

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

N/A f i

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l f

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ATTACHMENT 5 ST-HL-AE- S o o 2, PAGE 4 0F_ b AVERAGE DAILY UNIT POWER LEVEL '

DOCKET NO. 50-499 UNIT 2 DATE Feb. 7, 1995 i COMPLETED BY R.L. Hill- i TELEPHONE 512/972-7667 MONTH JANUARY

• i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1271 17 1269 2 1267 18 1269 3 1271 19 1270 4 1270 20 1268 5 1271 21 1271  !

6 1270 22 1271 i 7 1271 23 1263 i 8 1270 24 1268 9 1270 25 1259 10 1270 26 1243 l 11 1268 27 1265 12 1269 28 1109 13 1266 29 1272 14 1269 30 1274 15 1269 31 1274 16 1268 L

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i UNIT SHUTDONES AMD POWER REDUCTIONS i

DOCKET NO. 50-499 ,

l UNIT 2 ,

j DATE Feb. 7. 1995 COMPLETED BY R.L. Hill REPORT MONTH JANCARY i

1 2 3 4 5 lNo. Date Type Duration Reason Method of Licensee System Componeet Cause & Corrective Action to l (Hours) Shutting Event Code Code Prevent Recurrence i

Down Report #

Reactor i

THERE WERE NO UNIT SHUTDOWNS OR SIGNIFICANT POWER REDUCTIONS DURING THE REPORTING PERIOD 1 2 3 4 5 F: Forced Reasont Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram 3 .-4 D-Regulatory Restriction E-Operator Training & License Exam 4-Cont. of Existing Outage Ob5 m6 r F-Administrative 5-Reduction D> Sm 1 G-Operational Error (Explain) 9-Other H-Other (Explain) Z OO TYN e

. _ _ . _ _ .. . . . - . . . -,y. , - - , - - -, 4,,-. - , . - ,w.,-w-m~v- . . . . - - - , ,w, , . 2-... c.. r.-+-_,~r - - . . . - - - . _ . ,-~- .-> -.- - - % - , , - - - ..

e ATTACHMENT 2 ,

PORVs and Safety Valves Summary ST-HL-AE- 6 oo d l PAGE. to 0F G  !

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

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