ML20044B297

Monthly Operating Repts for June 1990 for South Texas Electric Generating Station Units 1 & 2.W/900713 Ltr

ML20044B297
Person / Time
Site:	South Texas
Issue date:	06/30/1990
From:	Kent A, Mcburnett M HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3507, NUDOCS 9007180313
Download: ML20044B297 (15)

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The Light c c o mp any South Texas Project Electric Generating P. O.Station Box 289 Wadsworth. Texas 77483, o  : Houston L.fghting & Power hi ,

-July-13, 1990 ST HL-AE-3507 File No.: 002 10CFR50.71 4; ,

'U.-S. Nuclear Regulatory Commission

/ Attention:- Document Control Desk

g. Washington, DC 20555

1. - South Texas Project Electric Generarisir, Station

/

Units 1 & 2

-Docket Nos. STN 50 498 & 50 499 y ;-

Monthlv Ooeratine Reports for June. 1990

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'q? Pursuant to 10CFR50.71(a) and South Texas Project Electric Generating

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. Station-(STPEGS)-Technical Spccification 6.9.1.5, attached are the Monthly Operating ~ Reports - for June , 1990.

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' 1f you should have any questions on .this matter, please contact

~l':', ;Mr.-C A.-.Ayalr, at (512) 972-8628.

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-M. A.- McBurnett 9, '

Manager, g.. Nuclear Licensing 9 '/

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s' -Attachments: 1) STPEGS Unit 1 Monthly Operating Report - -June 1990

2) STPECS Unit 2 Monthly Operating Report - June,1990

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c- ; h C' 9007180313'900630 4 PDR ADOCK 05000498 a- PDC 44 , - .

s , @ PA1/ .NL5' A Subsidiary of Ilouston Industries incorporated y s. . . . . .

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4 ST HL AE 3507

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Houston Lighting & Power Company File No.:G02 South Texas Project Electric Generating Station Page 2 cc:

. - Regional Adminit.ct .etor,' Region IV Rufus'S. Scott Nuclear, Regulatory = Commission Associate General Counsel 1611 Ryan Plazr drive, Suite 1000 Houston Lighting & Power Company Arlington, T?. 76011 P. O. Box 61867 Houston, TX- 77208

. Ceorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO i

Washington, DC 20555 Records Center 1100 circle 75 Parkway EJ. I. Tapia- Atlanta, CA 30339 3064 Senior Resident Inspector

.c/o U. S.-Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Bellpcrt Lane P. O. Box 910 . Be11 port, NY 11713 Bay City, TX 77414 D. K.. lacker 7 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 78704 -

D. E. Ward /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus.Christi, TX 78403 J. C. Lanier

- Director of Generation City of Austin Electric Ut'.11ty 3 721 Barton Springs Road

-Austin, TX. 78704 =!

R. J.'Costello/M. T. Hardt I City Public Service Board P. O.. Box 1771 San Antonio,'TX' 78296 .

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5 bi Revised 12/15/89

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7 ATTACHMENT 1 ST,Hl. AE-35o7 PAGE 1 0F 7-

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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION-s UNIT 1 1

MONTHLY OPERATING REPORT JUNE 1990 HOUSTON. LIGHTING AND POWER CO.

-NRC DOCKET NO. 50-498

, ~ LICENSE NO. NPF-76 Reviewe y; - /4[40~

Supervisor Date li ce ReviewedBygh 7 *[F 0 PlantEngineerngManager Date

,- Approved By: i \ 9-ID4D PlanYManagerjQ Date

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ATTACHMENT 1 M -'

ST-HL AE-350 7 4- PAGE A '0F ~7-Monthiv Su===ry STPEGS. Unit 1 began the reporting period shutdown for refueling and scheduled :

maintenance.

During the final synchronization of the generator to the grid a transformer ,

lockout occurred causing a loss of all reactor coolant pumps and subsequent turbine / reactor trip on 6/20/90 at 0410. The problem was traced to a f pole -

failure relay for the. main generator breaker. " relay was recalibrated and-the unit was returned to service on 6/21/90 at 190..

During power ascension the #1-main turbine governor valve experienced severe oscillations at-85% reactor power.- The oscillations caused the high pressure

-supply line of Throttle Valve #3 (TV-3) to rupture resulting-in a unit trip on 6/28/90 at 0554. Investigation re4ealed a loose primary coil wire on governor valve #1's linear variable differential transformer, and improper TV-3 tubing thickness.- Both problems were resotved and the unit was returned to service on 6/30/90 at'1312 with reactor power at approximately 14%.

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s. 2- ATTACHMENT 1 b ST.HL-AE- 350 7 7 L- , PAGE 3 0FL A

OPERATING DATA P.EPORT q DOCKET No. 50-498

. UNIT ~1 DATE Jul. 9. 1990 COMPLETED BY A . P . l<ent

.TELEP110NE - 512/972-7786; OPERATING STATUS ,

-1. REPORTING PERIOD: 06/01-06/30 GROSS-Il0URS IN REPGRTING PERIOD: 720 -

2. CURRENTLY AUT110RIZED POWER LEVEL (MWt): 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING (MWe-Net): -1250.6-

< 3. POWER LEVEL TO WilICl! RESTRICTED (IF ANY)(MWe Net): None

4. REASONS FOR RESTRICTION (IF ANY): N/A TilIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF 110URS REACTOR WAS CRITICAL, . . . . 359.7 2462.5 10709:81

6. REACTOR RESERVE SlIUTDOWN ll0URS........... 0 0' 0 'i

7. Il0URS GENFRATOR ON LINE.................. 183.5 2209.9 10142.2

8. UNIT RESERVE SilUTDOWN HOURS.,............ 0 0 __ 0-

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9. CROSS TilERMAL ENERGY GENERATED (MWt)..... 357271 8059489 36737922

10. CROSS ELECTRICAL ENERGY GENERATED (MWH).. 91670 2711080 12441670-

11. NET ELECTRICAL ENERGY GENERATED (MWH).... 63010 2548310 11672979 e 12. REACTOR SERVICE FACTOR................... 50.0% 56.7%- 66.1%

13. REACTOR' AVAIIABILITY FACTOR. . . . . . . . . . . . . . 50.0% 56.7%. 66.1%

14. UNIT SERVICE FACTOR...................... 25.5% 50.9% 62.6%

15. UNIT AVAILABILITY FACTOR................. 25.5% 50.91 62.6%

16. ' UNIT CAPACITY FACTOR'(Using MDC)......... 7.0% 46.9% -57.6%

'17. UNIT CAPACITY FACTOR (Using Design MWe).. 7.0% ,

46.9% 57.6% .;

18. UNIT F7RCED OUTAGE RATE.................. 34.8% e 21 8.91 19, SHUTDOWNS SCllEDULED OVER NEXT 6 MONTHS (TYPE, 'DATE, AND DURATION OF EACH):

4 N/A

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

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'- AVERAGE DAILY UNIT POWER LEVEL 4

, DOCKET.NO. 50-498 '

UNIT 1 DATE Jul. 9. 1990 -

COMPLETED BY : A.1= Kent-TELEPHONE 512/972-7786 .

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MONTH JUNE 4

-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe-Net). (MWe Net) 1 0 17 0 2.. 0 18 .

0  :

1 3 0 19 0

~4 0 20 0-

,', . 5: 0 21 0 "6; O 22 225 7 0'- 23' 230 ,

'0- 24: 363

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9 0 25 480 s ,

10 0 26 814 11 0 27 914 12 _,,

0 28 187

'13 -0 29 0

~14 0 30 101  ;

15 0 31 N/A i hi ". .

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' UNIT SHUTDOUNS AND POWER REDUCTIONS DOCKET NO. 50-498 .

UNIT 1 DATE Jul'. 9. 1990 '

COMPLETED BY{ A.P. Kent TELEPHONE 512/972-7786 REPORT MONTH JUNE Type Duration Reason Method of Licensee System Component Cause & Corrective Action to No. Date Prevent Recurrence Shutting' Event Code Code (Hours)

Down Report #

Reactor 433.1 C 4 N/A' N/A N/A Refueling and scheduled maintenance 90 03l900331 S outage.

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90-04 900619 F 3.5 A 9 N/A SB P The failure of the #11 turbine control 1 oil pump with the #12 pump being out for maintenance caused an electro-hydraulic control pressure decay which resulted in a turbine trip.

I N/A- N/A Turbine overspeed trip test.

90-05 900619 S 3.0 B 9 N/A 1-90-014 EA RLY Second turbine overspeed trip test.

90-06 900620 S 41.6 B 9.

Following the test during the final synch-ronization of.the generator to the grid, -

a turbine / reactor trip occurred at 0410. A transformer lockout occurred causing a loss of all reactor coolant pumps. The problem was traced to a pole failure relay for the main generator breaker. The relay was recalibrated. Recurrence measures l

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1:F Forced 2

Reason:

3 Method: IEEE 805-1983 IESE 803A-1983 g'g 1-Manual Ji m 2C S: Scheduled A-Equipment Failure (Explain) . [,s B-Maintenance or Test C-Refueling 2-Manual Scram 3-Automatic Scram y@

71 4 D-Regulatory Restriction 4-Cont. of Existing E-Operator Training & License Exam Outage d F-Administrative 5-Reduction G-Operational Error.(Explain) 9-Other H-Other (Explain) i.

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-U.VIT SHUTDOWNS'AND POWEK REDUCTIONS. ~~ ,

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50-498 " - . 7:

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DOCKET NO. ,

. UNIT- 1 '

DATE Jul. 9. 19901

~ COMPLETED BY A.P. Kent TELEPHCss 512/972-7786 REPORT MONTH JUNE  :

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 will be addressed in the LER.

90-07 900628  ? 55.3 A- 3 1-90-015 SB V-65 During power ascension the main turbine governor valve experienced severe oscilla-tions at 85% reactor power. The oscillations caused the high pressure supply line of throttle valve #3 (TV-3);

to rupture resulting in a unit trip.

Investigation revealed a loose primary coil wire on governor valve #1's linear variable differential transformer and' improper TV-3 tubing-thickness. Both problems were resolved and-the unit returned to service.

DE REF I 3 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 --

S: Scheduled A-Equipment Failure (Explain) 1-Manual 6rn B-Maintenance-or. Test- 2-Manual Scram to $

C-Refueling 3-Automatic Scram Q D-Regulatory Restriction 4-Cont. of Existing E-Operator Training & License Exam Outage q F-Administrative- . _

5-Reduction ,

j-G-Operational Error (Explain) 9-Other H-Other (Explain)

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,~- :ST HL AE 3Sa7 PAGE 1- 0F- 7 M. a. ,

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- PORVs'and Safety Valves Su==ary ...

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

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i SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION-UNIT 2 MONTHLY OPERATING REPORT JUNE 1990.

1' HOUSTON LIGHTING AND POWER CO.

l NRC DOCKET No. 50-499 LICENSE NO. NPF-80 4 ,

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Reviewe y: -

Supervisor. Date .

Reviewed By: d , - .7//o /P 2 -

T Plafit Ehf,ine ing Manager 'Date

'Approvisd By: h )~/0%

Planh-HanagerQ Date p

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. ATTACHMENT 2

,,- ST HL-AE 3507 Monthly Su-- ry -

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

Following the replacement of a Unit 1 Reactor Coolant System narrow range resistance temperature deto or (RTD) it was discovered that a required 0 ring was not installed in the associated Conax junction box. The 0 ring provides a sealed enclosure which is required to maintain the accuracy of the temperature measurements. Due to this event, Unit 2 was removed from service on 6/12/90 at 2235-for inspection of the 0 ring seals. A total of 6 seals were found to be missing in' Unit 2. These were replaced and the unit was returned to service on 6/13/90 at 1556. Further details will be provided on Unit 1 LER #1 90 012.

On 6/17/90 main ieedwater pump #21 tripped on electrical overspeed. This required;the unit to reduce reactor power to 98%. Troubleshooting revealed a failed tachometer assembly in the electro hydraulic contro11et A temporary modification has been prepared to install the new tachometer wit -ut affecting the operating pumps since they share a common control circuit cabinet.

<The unit concluded the reporting period at the plant maximum capability of 99.6% reactor power with one feedwater pump out of service.

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ATTACHMENT 3 ST-HL AE M07 C -PAGE 3 0F _ 4 OPERATING DATA REPOR'l DOCKET NO. 50 499 UNIT 2 DATE Jul. 9. 199U COMPLETED BY A.P. l(ent TELEPHONE 512/972-7786 j OPERATING STATUS 1, REPORTING PERIOD: 06/01 06/30 GROSS HOURS;IN REPORTING PERIOD: 720

2. CURRENTLY AUTil0RIZED POWER LEVEL (MWt): 3800 1250.6

. MAX. DEPEND. CAPACITY (MWe Net):

DESIGN ELECTRICAL RATING (MWe Net):: 1250.6

, 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe Net): Nono-

[ 4. . REASONS-FOR RESTRICTION (IF ANY); N/A-THIS MONTH YR TO DATE CUMULATIVE

5. . NUMBER OF ll0URS REACTOR WAS CRITICAL.....

720.0 3435.7 6412.6

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6. . REACTOR RESERVE SHUTDOWN-HOURS...,,...... 0' O O i

7. Il0URS GENERATOR ON LINE ...........,,, .. '702.7 3060.6 5907.2

8. UNIT RESERVE SHUTD0',,'N HOURS . . . . , , . . . . . . . 0 0 ,Q

9. GROSS TilERMAL ENERGY GENERATED (MWt).... 2644265 11293892. 20816269

.10; GROSS ELECTRICAL ENERGY GENERATED (MWH).. 894810 )_820070 7033100.

11 '. NET ELECTRICAL ENERGY GENERATED (MWH).... 851333 3608103 6629277

12. . REACTOR S ERVICE FACTOR. . . . . . . . . . . . . . . . . . , 100. 0 % 79 . l fs 70.9%

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, ? 13 ~. . REACTOR' AVAIIABILITY FACTOR. . . . . . . . . . . . . 100. 0% 79.1% 70.9% l i I

14. . UNIT SERVICE FACT 0R...................... 97.6% 70.5% 65.3% i 42

15. UNIT AVAILABILITY FACTOR................. 97.6% 70.5%- 65~3%

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16. UNIT' CAPACITY FACTOR (Uning MDC)........, 94.5% 66.4% 58.6%- .f l

17. UNIT CAPACITY FACTOR (Using Design MWe).. 94.5% 66.4% _

58.6%

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' 18 . UNIT FORCEL OUTAGE RATE........ ......... 2.4% 29 3 25.6%

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

Scheduled 55 day refueling outage to begin September 29, 1990. >

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

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PAGE t 0F 6 i AVERAGE DAILY UNIT POWER LEVEL' <

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, DOCKET NO. 50-499 UNIT 2

.DATE Jul. 9. 1990 s 4 COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 L."

4 MON'n! JUNE 1

k 4

DAY' AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (MWe-Net). (MWe-Net)~

.g , ;1 1213 17 1241 '

1- 2 1204 18 1236 3 '1205' 19 1234 ,

4' 1202 20 1221 S7 5 1235 21 1712 .

? , '6- 1236 22- 1237 s L

g ,  : ~ 1234 '23 1239:

Mi 8.

1234 24 1236- ,

'9 1236 1230 25 1230 26 1237 I Il0.- ._

11= _,_ 1233 ,

• 27 1239- 11

.'12 1049 28 1238i }

(; 13 78 29 1240

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16 1237 r

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h.'"D UNIT SHUTDOWNS AND POWER REDUCTIONS: _

DOCKET NO. 50-499' -t *

-- UNIT 2' DATE Jul.'9. 1990 m -

' COMPLETED BY ~

A.P. Kent ~

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TELEPHONE -512/972-7786' REPORT MONTH JUNE -

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 90-09 90J612 F 17.4 L 2 N/A AB SEAL The unit was removed from service to

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a. low inspection of O-ring seals on the Conax junction boxes associated with the  ;

Reactor Coolant System narrow range ._;

resistance temperature detectors. The missing 0-rings were replaced. (Refer-to Unit 1 LER #1-90-012) 90-10 900617 F 0.0 A 5 N/A SJ - P Main Feedwater Pump #21 tripped on electrical overspeed. This required the unit to reduce reactor power.to 98%.

Troubleshooting revealed a failed tacho-meter assembly in the electro-hydraulic controller. A temporary modification was prepared to install the new tachometer without affecting the operating pumps since they share a common control circuit cabinet.

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1 2 3 4 5 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983  ;^ CIO>

S: Scheduled A-Equipment Failure (Explain). 1-Mancal m .

B-Maintenance or Test 2-Manual Scram- .h

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3 C-Refueling D-Regulatory Restriction' 3-Automatic Scram 4-Cont. of Existing o .,3 p 3

'E-Operator: Training 6 License Exam Outage p F-Administrative 5-Reduction G-Operational Error (Explain) .9-Other-H-Other (Explain)

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,i PORVs and Safety Valves Sa===ry i

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