ML20042E318

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Monthly Operating Repts for Mar 1990 for South Texas Project Electric Generating Station Units 1 & 2.W/900416 Ltr
ML20042E318
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 03/31/1990
From: Kent A, Mcburnett M
HOUSTON LIGHTING & POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3434, NUDOCS 9004200608
Download: ML20042E318 (14)


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The Light 1 c o nap a nySouth Temu Project Electric Generating Station P. O. Boa 289 Wadeworth, Temas 77483 -- Houston Lighting & Power , April 16,-1990 1 ST-llL AE-3434 ' File No.: G02 10CFR50.71

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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 Monthly Oocratine-Recorts for March. 1990 Pursuant to 10CFR50.71(a) and- South Texas Project Electric' Generating Station (STPEGS) Technical Specification 6.9.1.5, attached are the Monthly. i Operating Reports for March, 1990. If you should have any questions on this matter, please contact Mr. C. A. Aycla at (512) 972-8628.

                                                                                                                                .i fffs&n/)
                                                                                .~Mc urnett l

Manager,-Nuclear  !

                                                                        . Licensing

!' i l l l BEM/n1 .j Attachments: 1) STPEGS Unit 1 Monthly Operating Report - March,1990

2) STPEGS Unit 2~ Monthly' Operating Report March, 1990-i i
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9004200608'900331 PDR A  ! R ADOCK 05000498 rg PDC , j r A1/023.NL5 A Subsidiary of Houston Industries incorporated  !

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ST-HL- AE- 3434 Houston Lighting & Power Company South Texas Project Electric Generating Station File No. : 002 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 Arlington, 1DC 76011 P. O. Box 61867 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                                                                     _!

D. K. Lacker i J. R. Newman, Esquire Bureau of Radiation Control l Newman & Holtzinger, P.C. Texas Department of Health  ! 1615 L Street, N.W. 1100 West 49th Street i Weshington, 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 I Director of Generation City of 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 i Revised 12/15/89 L4/NRC/

l l SOUTH TEXAS PROJECT-ELECTRIC CENERATING STATION l.' l UNIT 1 '? MONTHLY OPERATING REPORT-r MARCH. 1990 . HOUSTON LIGHTING AND POWER CO. NRC DOCKET NO. 50-498 l LICENSE NO. NPF-76 l.- l 1

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STPEGS Unit.,1; began the reporting _ period'acL100% reactor power.
                   >                     10n3/29/90:at1447areactor/tbrbineltripoccurred'du'etoLowLowLevel?                                             ,

on' "1C" Steam . Generator;' Thel event -occurred 4. followin6 ;the; trip. of a feedwater, , bo'oster pump.... The redundant _ booster pump failed to s'upply' sufficient' suction head-to.the-main feedwater: pump causing it to. trip.

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                                       ~-The refueling outage wasLre schedule'd-to begin'on 3/31/90 ~atl.1600..
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4 OPERATING DATA REPORT ~ j DOCKET NO. 150 498  ; UNIT: 1 [ DATE 'Aor. 5. 1990 COMPLETED BY A.PJ Kent TELEPHONE. 512/972-7786 OPERATING STATUS-  ; 1 1.- REPORTING PERIOD: 03/01-03/311 GROSS Il0URS.IN REPORTING PERIOD: 744'  :!

                  '2.                                                                                                                                --i CURRENTLY AUTi!0RIZED. POWER LEVEL (MWt):- ~3800
MAX. DEPEND. CAPACITY L(MWe Net): 1250.6 _ .

DESIGN ELECTRICAL RATING (MWe-Net): 1250:6 _ 3e ' POWER LEVEL TO WilICil RESTRICTED (IF ANY)(MWe-Net): 'None

                -4.       REASONS FOR RESTRICTION,(IF ANY): N/Al                                                                                     ;;

a THIS MONTil. . YR TO DATE ~CUMUI.ATIVE

                                                                                                                              .                       a
5. NUMBER OF 110URS REACTOR WAS: CRITICAL. . . . . 686.8 2102.8 10350.2 . l
6. REACTOR RESERVE SHUTDOWN 110URS. . . . . . . . . . O' -0 0 't
7. Il0URS GENERATOR 10N'LINE.......... .....:.. 686.8 2026.4~ 9958.7
8. 1 UNIT RESERVE SIIUTDOWN HOURS,.......,,..., O. 0 0 -

9, . GROSS' TilERMAL- ENERGYJGENERATED (MWt) . . . . 2614217 7702217: ^36380651 l

10. GROSS EELECTRICAL ENERGY . GENERATED (MWH) . . 8929201 2619410' 12350000 l

11, NET ELECTRICAL-ENERGY-GENERATED-(MW11).... 853211l 2504104 11628773 1

12. REACTOR S ERVICE - FACTOR . . . . . . . . . . . . . . . . . . . 92.3% 9714% -73.8%1 <
13. REACTOR AVAILABILITY FACTOR. . . . . . . . . . . . . . 92.3%L = 9 7 '. 4 % - 73:8%
14. ' UNIT SERVICE. FACTOR........,............. 9 2 . 3'% ' 9 3 '. 8 % - '71.d%
15. UNIT AVAILABILITY' FACTOR................. 92.3%- 93.8%~ 71.0%
16. UNIT CAPACITY FACTOR (Using MDC)......... 91.71 92.7%-- 66.3% i
17. UNIT CAPACITY FACTOR (Using Design MWe)., 91.7% 92,7%~ 66.3%
18. UNIT FORCED OUTAGE RATE.................. 6.7% 5.8%1 8:5%- d.
19. SHUTDOWNS SCllEDULED 0VER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

N/A a

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: -6/2/90 .

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AVERAGE DAILY. UNIT POWER-LEVEL-DOCKET NO.- 50-498 UNIT 1 DATE Apr. 5. 1990 COMPLETED BY A.P; Kent ~ TELEPil0NE 512/972-7786 MONTil MARCil DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) -(MWe-Net)

                 '1              1254                              17              1250 2             1252                              18               1250-3              1250                              19               1251 4              1251                              20              1250 b              1252                              21              1247 6    ,

1252 22 '1249' 7 1250 23 1240 8 1248 24 _ 1178 9 1248 25 1251

               -10               1248                              26              ~1250 11               1252                              27              1235 12               1249                              28              1246 13               1250                              29                747 14               1254                              30                  0 15               1251-                             31                  0-16              -1249

UNIT SHUTDOWNS AND POWER REDUCTIONS 7- . DOCKET NO. 50-498 UNIT 'l ", DATE Anr. 5. 1990 COMPLETED BY 'A.P. Kent TELEPHONE 512/972-7786 REPORT MONTH MARCH No. Date Type Duration Reason Method of Licensee System Component Cause & Corrective Action to

                         -(Hours)                               Shutting       Event    Code       Code                           Prevent Recurrence Down         Report #

Reactor

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90-02 900329 F 49.2' A 3 1-90-005 AB P Reactor / Turbine trip occurred due to Ima-Low Invel on *1C" Steam Generator. The event occurred following the trip of. a feedwater booster pump. The redundant-booster pump failed to supply sufficient suction head to the main feedwater pump causing-it to trip. The problem is being investigated. 90-03 900331 S 8.0 C- 9 N/A N/A N/A Refueling and scheduled maintenance outage. i I 0 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 D-Regulatory Restriction 4-Cont.1of Existing 4 E-Operator Training & License Exam . Outage F-Administrative 5-Reduction C-Operational Error ~(Explain) 9-Other. H-Other (Explain)

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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 2 MONTHLY OPERATING REPORT MARCH 1990 HOUSTON LIGHTING AND POWER CO. NRC DOCKET NO. 50 499 LICENSE NO NPF-80 l-i Reviewed y: . . 4 [6 /90 Supervisor Date Revie /By: M '/ ~!# 3 Plan VEngineering Manager ~Date Approved By: bU i -- 4\io\90 Plant Manager D dath

4* 6 g Monthly Summary STPEGS Unit 2 began the' reporting period at 100% reactor power. Reactor power was -- reduced to 75% on 3/16/90 at 1130 due to #22 Main

                       . Feedwater Pump outage and rapid degrading condition of the w24 Motor Driven Main Feedwater Pump,. The pump seals were degrading.due to high vibration of the purop. The #22 Feedwater Pump was returned to service and #24 Motor Driven Pump removed from service for repairs. Reactor power was returned'to 100%

on 3/17/90.. On 3/26/90 at 0723<a reactor trip was initiated by Low Level in the "20" Steam Generator due to a separation of the Feedwater Regulator Valve disc,from the stem. At the conclusion of the reporting period the unit was shutdown with repairs to the valve =in progress; y . nl

ff's e ic OPERATING DATA REPORT i DOCKET NO. 50-499 UNIT 2 DATE Aor. 6. 1990-COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 OPERATING STATUS

1. REPORTING PERIOD: 03/01 03/31 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 WHICil RESTRICTED ~(IF ANY)(MWe. Net): None
              '4    REASONS FOR RESTRICTION (IF ANY): N/A-THIS MONTil . YR TO DATE CUMULATIVE
5. NUMBER OF 110URS REACTOR WAS CRITICAL. . . . . 607.4 1613.9 4590.8
6. REACTOR RES ERVE SilUTDOWN 110URS . . . . . . . . . . . 0 3 0-
7. Il0URS GENERATOR ON LINE. . . . . . . . . . . . . . . . . . 607.4 1539.1 4385.7-
8. UNIT RESERVE SHUTDOWN 110URS . . . . . . . . . . ... . . 0 0 0-
9. CROSS TilERMAL ENERGY GENERATED-(MWt).... 2297162' 5741715 15264091
10. CROSS ELECTRICAL ENERGY GENERATED (MWH).. 788290' 1948360 5161390
11. NET ELECTRICAL ENERGY GENERATED (MWH) . . . . 751608 1846595 4867769
12. REACTOR SERVICE FACTOR................... 81.6%- 74.7%  ! 66.9%
13. REACTOR AVAILABILITY FACTOR. . . . . . . . . . . . . , 81 '. 6 % 74 7t
                                                                                                      .              66.96 14    UNIT SERVICE FACTOR.......................-                  81.6%             71.3%             63.9%
15. UNIT AVAI LABILITY FACTOR. . . . . . . . . . . . . . . . . . 81.6% -71.3% 63.9%-
16. UNIT CAPACITY FACTOR (Using MDC)......... 80.8% 68.4t' 56.74
17. UNIT CAPACITY FACTOR (Using Design MWe).,- 80.8% 68.46- 56.74 18', UNIT FORCED OUTAGE RATE.................. 18.4% '28.8%- 23.84 19.. SHUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACil):

Scheduled 55 day refueling outage to begin September 29 1990.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 4/7/90-
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AVERACE DAILY UNIT' POWER LEVEL i DOCKET NO, 50 499 s UNIT 2 DATE -Aor. 5. 1990 COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 MONTil MARCH DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net)- 1 1258 17 1176 2 1253 18 1254 3 1236 19 1257 4 1260 20 1250 i 5 1248 21 1257 6 1246 22 1257 7 1256 23 1258 8 1256 24 1259 9 1257 25 1258 10 1254 26 360 11 1258 27 0 12 1256 28 0 13 1256 29 0 14 1256 30 0 15 1255 31 0 16 1089 _

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UNIT SHUTDOUNS AND POWER REDJCTIONS ..f ' DOCKET NO. 50-499 UNIT 2 DATE Aor. 5. 1990 COMPLETED BY A.P. Kent TELEPHONE 512/972-7786-REPORT MONTH MARCH No. Date Type Duration Reason Method of Licensee System Component Cause & Corrective Action to (Hours) Shutting Event Code Code Prevent Recurrence Down Report

  • Reactor 90-03 900316 F O.0 A 5 N/A SJ P- Reactor power was reduced to 75% due to
                                                                                                          #22 Main Feedwater Pump outage and rapid degrading condition of the #24 Motor Driven Main Feedwater Pump. The #24 pump seals were degradin8 due to high vibration of the pump. 'The #22 Feedwater Pump was returned to. service and 100% reactor power restored.. The #24 Motor Driven Pump is out of service for repair.

90-04 900326 F 136.6 A 3 2-90-004 AB V Reactor trip initiated by Low level in the "2C" Steam Generator due to a separation of the Feedwater Regulator valve disc from the stem. . Repairs to the valve are in progress. 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. D-Regulatory Restriction: 4-Cont. of Existing E-Operator Training & License Exam Outage F-Administrative 5-Reduction

                              'G-Operational Error (Explain)'                              9-Other H-Other (Explain) 1
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No PORVs'or. Safety Valves were challenged during thisl reporting period.

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