ST-HL-AE-3195, Monthly Operating Repts for Jul 1989 for South Texas Project Electric Station Units 1 & 2
| ML20246B507 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/31/1989 |
| From: | Kent A, Mcburnett M HOUSTON LIGHTING & POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ST-HL-AE-3195, NUDOCS 8908230377 | |
| Download: ML20246B507 (15) | |
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.l The Light u company 2 P.O. Box 1700 Houston, Texas 77001 (713) 228 9211 Ilouston Lighting 8e Power _,. , ..., _ . ~ . . . ~ - - . - . _ . - . ~ . _ , . - - - . - - . ~ . , . -
August 14, 1989 ST-HL-AE-3195 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 Monthlv Operatinn Reports for July. 1989 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 July,1989.
If you should have any questions on this matter, please contact Mr. C. A. Ayala at (512) 972-8628.
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M. A. McBurnett Manager Support Licensing MAM/BEM/km Attachments: 1) STPEGS Unit 1 Monthly Operating Report - July, 1989
- 2) STPEGS Unit 2 Monthly Operating Report - July, 1989 i
8908230377 890731 PLR R ADOCK 05000498 1 PDC l
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Al/023.NL5 A Subsidiary of Houston Industries Incorporated l 7 ;
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llouston Ligt ting & Power (anupany .;
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Regional Administrator, Region IV Rufus S. Scott Nucicar Regulatory Commission Associate General Counsel ;
611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company j
Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 Ceorge Dick, Project Manager ,
U. S. Nuclear Regulatory Commission INPO Washington,lDC 20555 Records Center 1100 circle 75 Parkway Jack E. Bess Atlanta, GA 30339-3064 Senior Resident Inspector Unit 1 c/o U. S. Nuclear Regulatory Commission Dr. Joseph M. Hendrie P. O. Box.910 50 Bellport Lane Bay City, TX 77414 Bellport, NY 11713 l J. 1. Tapia D. R. Lacker l Senior Resident Inspector - Unit 2 Bureau of Radiation Control l c/o U. S. Nuclear Regulatory Commission Texas Department of Health l P. O. Box 910 1100 West 89th Street l
Bay City, TX 77414 Austin, TX 78756-3189 J. R. Newman, Esquire Newman & Holtzinger, P. C.
1615 L Street, N. W.
Washington, DC 20036
.R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 Copies)
Chief bperating Officer City ' Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P, O. Box 1771 San Antonio, TX 78296 Revised 06/16/89 A1/NL.DISR4
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SOUTH TEXAS PROJECT ELECTRIC GENERATING. STATION UNIT 1 HONTHLY OPERATING REPORT
. JULY 1989 HOUSTON LIGHTING.AND POWER CO.
NRC DOCKET NO. 50-498' LICENSE NO. NPF-76 Reviewed By .
9!3/9'l General Supervisor Date Reviewed By: '
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' OPERATING DATA REPORT DOCKET NO. 50-498-UNIT 1 DATE Aug. 3, 1989 COMPLETED BY A.P. Kent TELEPHONE 512-972-7786 OPERATING STATUS
- 1. . REPORTING PERIOD: 07/01-07/31 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 HONTH YR TO DATE CUNULATIVE
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL...... 685.0 3996.5' 6493.4
- 6. REACTOR RESERVE SHUTDOWN HOURS............. 0 0 0
- 7. HOURS' GENERATOR ON LINE................... 676.4 3925.2 6331.2
- 8. UNIT RESERVE SHUTDOWN HOURS................ 0 0 0
- 9. GROSS THERMAL ENERGY GENERATED (MWt)...... 2372372 14276649. 23091170
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWH).... 802480- 4857010 7849240
- 11. NET ELECTRICAL ENFRGY GENERATED (MWH)..... 755521 4585183 7376675
- 12. REACTOR' SERVICE FACTOR.................... 92.1% 78.6% 79.3%
- 13. REACTOR AVAILABILITY FACTOR............... 92.1% 78.6% 79.3%
- 14. UNIT SERVICE FACT 0R....................... 90.9% 77.2% 77.4%
- 15. UNIT AVAILABILITY FACTOR.................. 90.9% 77.2% 77.4%
- 16. UNIT CAPACITY FACTOR (Using MDC).......... 81.2% 72.1% 72.1%
- 17. UNIT CAPACITY FACTOR (Using Design MWe)... 81.2% 72.1% 72.1%
- 18. UNIT FORCED OUTAGE RATE................... 9.1% 5.3% 7.7%
19 .' SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
SCHEDULED 55 DAY OUTAGE TO BEGIN AUGUST 4, 1989 FOR REFUELING.
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A i
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AVERAGE DAILY UNIT POWER LEVEL l'
DOCKET NO. 50-498 UNIT 1 DATE Aug. 3, 1989 COMPLETED BY' A.P. Kent L TELEPHONE < 512-972-7786 MONTH July DAY. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
I 1213 17 1207 2 1240 18 1205
.3 1242 19- 1224 4- 985 20 1231 5 0- 21 839-6 0 22 967 7 24 23 994-8- 929 24 993 9 1225 25 999 10 1231 26 1213 11 1231 27 1236 12 1231 28 1229 13 1229 29 933 14 1217 30 944 15 1216 31 949 16 1215 I
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h PAGE ( OF ' 7 Monthly Summary-STPEGS Unit I began the reporting period at 90%. reactor power.
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-completing turbine valve stroke testing. The throttle valve position linkage had been replaced. The valve was stroked following ~
maintenance. - The unit returned to 100% reactor power on 7/1/89 at 0600.
On.7/4/89 at 1915 a reactor / turbine trip occurred on over temperature delta temperature. The wrong size relay had been installed in the main generator output breaker circuitry. Failure in the relay resulted in the output breaker opening and subsequent reactor trip. 'The correct size relay was replaced in the breaker circuitry and the unit was returned to service on 7/7/89 at 1449.
On 7/21/89 at 0120 the unit reduced reactor power to ~48% to reduce the bearing temperature of a steam driven feedwater pump. A motor driven feedwater pump was started but was forced to shutdown due to high motor bearing vibrations. With the motor driven pump'out of service the unit was limited to the capacity of' the remaining two feedwater pumps. Reactor power was returned to 83% on 7/22/89 at 1300. On 7/26/89 repairs to the motor driven pump were completed and the unit returned to 100% reactor power at 1100.
On 7/29/89 at 0300 the inboard seal on the motor driven feedwater pump failed. Reactor power was reduced to ~80% to allow for-securing the pump. The unit completed the report period at ~80%
reactor power with maintenance ongoing on the feedwater pump, i
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l PORVs and Safety Valves Summary On JulyL4, 1989"at'1915 the Unit i generator output circuit-
' breaker opened.~ The cause of the breaker opening was due to the failure'of a' relay in'the Main Generator Breaker Protection and Control Circuit. Following the opening of the breaker an actuation of the Overspeed Protection Control caused the four governor valves to' close. This' rapid termination of steam flow caused steam pressure,
.T-ave and pressurizer pressure to immediately. increase. As a result P of the pressurizer increase, Pressurizer Power Operated. Relief Valve-(PORV)-656A opened and remained open for approximately.3 seconds. The steam generator PORV's also began to open as'a response to the.
increased steam pressure. The reduction in steam flow from the steam l . generators. caused Reactor Coolant System Delta-T to decrease. The rapid increase:in T-ave caused the OT Delta-T setpoint to decrease.
faster than the rate'of Delta-T. decrease. This resulted in a 2 of 4 u OT Delta-T reactor trip shortly after the governor valves closed. The l: reactor trip then resulted in a turbine trip.
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' SOUTH. TEXAS PROJECTI
- p ELECTRIC GENERATING STATION
- UNIT 2' MONTHLY OPERATING REPORT.
JULY 1989 HOUSTON LIGHTING AND POWER CO.
NRC DOCKET NO. 50-499 LICENSE NO. NPF-80
-. Reviewed By: . . N3 2%'
General Supervisor Date
- Reviewed By: 87 k 7~ Pl[/ Engineering Manager /Dalte Approved By: hh k E #d g Plant Manager Q,,,) bate
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. ST.HL AE. 3 /6 PAGEo7 OF (p OPERATING DATA REPORT, E DOCKET NO. '50-499; UNIT- 2
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DATE Aug. 3, 1989 COMPLETED BY- A.P. Kent' TELEPHONE ~- 512-972-7786 OPERATING STATUS-
'1. REPORTING PERIOD: 07/01-07/31 GROSS HOURS IN REPORTING PERIOD: 744'
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800 MAX. DEFEND. CAPACITY (MWe-Net): 1250.6 l DESIGN ELECTRICAL RATING (MWe-Net):1250.6 1 ~'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...... 625.3 913.3 913.3-
'6. REACTOR RESERVE SHUTDOWN HOURS.............. 0 0 0
- 7. HOURS GENERATOR ON LINE.................... 609.4- 897.4 897.4 l
- 8. UNIT RESERVE SHUTDOWN HOURS................._ 0 0 0
- 9. GROSS THERMAL ENERGY GENERATED (MWt)...... 1902515 2997505 2997505'
- 10. GROSS ELECTRICAL' ENERGY GENERATED (MWH).... 640490 1015700 1015700
- 11. . NET ELECTRICAL ENERGY GENERATED-(MWH)..... 604787 963652 963652.
- 12. REACTOR SERVICE FACTOR.................... 84.0% 88.5% 88.5%
- 13. REACTOR AVAILABILITY FACTOR................ 84.0% 88.5% '88.5% ,
- 14. UNIT SERVICE FACT 0R....................-... 81.9% 87.0% 87.0%
- 15. UNIT AVAILABILITY' FACTOR... .............. 81.9% _37.0% 87.0%
- 16. UNIT CAPACITY FACTOR (Using-MDC).......... 65.0% 74.7% 74.7%
- 17. UNIT CAPACITY FACTOR (Using Design MWe)... 65.0% 74.7% 74.7%
'18. UNIT FORCED OUTAGE RATE.................... 18.1% 13.0% 13.0%
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Scheduled 14 day outage to begin November 4, 1989 for Bottom Mounted Instrumentation Inspection.
- 20. -IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l-l i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-499 UNIT' 2 _.
'DATE Aug. 3, 1989-
-COMPLETED BY 'A.P. Kent TELEPHONE' 512-972-7786 0
-MONTH' " July' i.
-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t') (MWe-Net)
, 'l '12581 17 0 +
2 -1256 18- 0 3 1252 19 193 41 1242 20 733 5 1228 21- 697 6 1224 22 732 7- ~1237 23 776- ,
8 1239 24 781 9 1239 25 781 10 1243 26 781 11 1238 27 779 12 1228 28 781 13 1031 29 782 14 0 30 -784 15 0 31 766 16 0
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Monthly Summary STPEGS Unit 2 began the reporting period at 100% reactor power.
On 7/13/89 at 2002 with reactor power at ~98% Unit 2 l' experienced a turbine trip followed by a' reactor trip when Main Transformer 2A faulted internally causing severe' damage to the transformer. The area where the fault occurred'is known, but the l root cause of the event is unknown at thin time.
l After determining that Main Transformer 2B was capable of being energized, Unit 2 went critical on 7/18/89 at 0444. The Unit entered Mode 3 at 1156 to repair Feedwater Isolation Bypass Valves. On 7/19/89 the repair work was completed and the unit went back on line at 1040 and commenced power ascension to ~65%.
The unit concluded the report period at ~65% power.
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PORV's and Safety Valves Summarv ll On July 16, 1989, Unit 2 was in Mode 3 at normal operating pressure u -and temperature. Reactor Coolant Pump 2A was in service with the associated spray valve in manual and full open.. The Pressurizer heaters were off and the l'
. Master Controller:was in Automatic. Heat Removal from the Reactor Coolant System was being accomplished by feeding the steam generators with auxiliary feedwater- At approximately 0031 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> on July -16, .1989, Lauxiliary feedwater
. flow was throttled back to maintain steam generator level between 50 and 70 percent. -This resulted in the heat addition rate to the RCS being greater than the heat removal rate and subsequently RCS pressure began to rise.
At approximately 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> Presr.urizer Pressure Deviation High Alarm annunciated with pressure at approximately 2260 psig and stable. 'This deviation continued to exist until 0109 hours0.00126 days <br />0.0303 hours <br />1.802249e-4 weeks <br />4.14745e-5 months <br />,'which resulted in the output.
I, from the' Master Controller increasing such that PORV 655A operated.
- Pressurizer pressure was automatically reduced to 2230 psig. Plant Operations.
perscnnel took remedial actions to stabilize pressure at 2235 psig.
South Texas Project has 2 Pressurizer Power Operated Relief Valves (PORVs). one which operates based upon a fixed setpoint of 2335 psig. The second PORV receives its input from the Master Controller which is a proportional bank controller and varies the setpoint of PORV 655A. The Mastre Controller also sends an output signal to the Pressurizer heaters, spray valves (if in automatic) and Pressure Deviation High Alarm. This Master Controller has an integration function where the control signal is increased s
-ba~ed on'the time period that a deviation exists.
Based on procedures and training the operators did not recognize that the integration function of the Master Controller would open PORV 655A at a pressure less than 2335 psig. Procedures are being revised and training'is being provided to ensure that operators understand and correctly respond to pressure transients of this nature prior to PORV actuation.
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