ST-HL-AE-3973, Monthly Operating Repts for Dec 1991 for South Texas Project Electric Generating Station,Units 1 & 2

Monthly Operating Repts for Dec 1991 for South Texas Project Electric Generating Station,Units 1 & 2

ML20091K146
Person / Time
Site:	South Texas
Issue date:	12/31/1991
From:	Jump W, Kent A HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3973, NUDOCS 9201220237
Download: ML20091K146 (15)

Text

t-t The Light cllouston o mLighting p a n& Power y S uth

_ Texas Project Dettgegnerating P. O. Box 289 Statjon

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'anuary 14, 1992 ST-HL-AE-3973 File No.: CO2 10CFR50.71 U. S Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Electric Cenerating Station Units 1 6 2 Docket Nos. STN 50 498 6 50 499 Monthly Operatine Reoorts ihr December. 1991 Pursuant to 10CFR50.71(a) and Scu:h Texas Project Electric Cenerating Station (STPEGS) Techni al Specification 6.9.1.5, attached are the Monthly Operating Reports for December, 1991. ,

if you should have any questions on this matter, please contact i Mr. C. A, Ayala at (512) 972-8628.

WA William J. Jump

(

Manager Nuclear Licensing

-MKJ/lf Attachments: 1) STPEGS Unit 1 Monthly Operating Report - December, 1991

2) STPECS Unit 2 Monthly Operating Report - December, 1991 RREPiB2008002.1&2 A Subsidiary of Ilouston Industries incorporated 9201220237-911231

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ST-ilL AE 3973

, HoLdon Lighting & Power Company File No.:002-

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• South Texas Project Electric Generating Station Page 2 cc:

-Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory-Commission' Associate General Counsel 611 Ryan Plara Drive, Suite 400 Houston Lighting & Power Company.

' Arlington, TX -76011 P. O. Box 61867 Houston, TX 77208 Ceorge Dick, Project Manager U.S. Nuclear Regutatory 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. Elendrie Commission 50 Bellport Lane

, P.-0. Box 910- Bellport, NY 11713

' Bay. City,'TX 77414 D. K. L cker

-J. R. Newman,- Esquire .

Bureau of Radiation Control Newman & iloltzinger,_P.C. Texas Department of Health 1615 L Street,EN.W. 1100 West'49th Street

-Washington, DC 20036 Austin, TX 78756 3189 D. E. Ward /T.-M. Puckett Central Power .and Light Company P.- 0.-Box 2121

Corpus Christi TX~~78403

.J. C. Lanier/M.-B. Lee City.of Austin Electric Utility Department ,

P.O. Box.1088 .

Austin, TX 78767:

c R.-J. Fiedler/M.-T. Hardt--

City'Public Service Board P. 0.. Box 1771 San' Antonio,-TX 78296-

'I Revised 10/11/91 i 14/NRC/

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/JT Arn4 MEN ~I I ra p, AE-3973 JL1=-JL.g -

SOUTil TEXAS PROJECT ELECTRIC CENERATING STATION i

UNIT 1 HONTitLY OPERATING REPORT DECEMBER 1991 Il0USTON LICHTING AND POWER CO.

NRC v0CKET NO. 50 498 LICEUSP NO. NPF-76 Reviewe y; - <,_- 4 I-G 't ?-

Supervirer ) Data Reviewed By(A  !.

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' Plant EngT 4eriU[, Manager Date Acproved By: LA k L\S hV PlantMany,er Date

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• ATTACHMENT /

' ST HL AE-39 7 3

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s l STPEGS Unit 1 began the reporting period at 100% reactor power.

l On 1?/7/91 reactor power was reduced to allow repair of the Main reedwater i Pump Speed Control Circuit.

The unit returned to 2004 reactor power on 17/8/91 and operated for the l

! remainder of the reporting period with no shutdowns or significant power 3

reductions.

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$1.HL4AD.vi? 3 OPERATING DATA REPORT PAGE ,,1 .Of:__b_. ,

DOCRET NO. 50 498 UNIT 1 DATE Jan. 3. 1992 COMPLETED fly L.E Ment TELEPil0NE 312/972 778k i

OPERATING STATUS  ;

1. REPORTING PERIOD: _12/01 12/31 CROSS ll0URS IN REPORTING PERIOD: 744

2. CURRENTLY AUTil0RIZED POWER LEVEL (MWt): 3800 MAX DEPEND.CAPAC.'TY (HWe Net): 1250.6 DESIGN ELECTRICAL RATING (MWe Not): ,,.12 5 0. 6 -

3. POWER LEVEL TO WillCll RESTRICTED (IF ANY)(MWe Net): __None

4. RFASONS FOR RESTRICTION (IF ANY): '4/A Tills MONTil YR TO DATE CUMU!ATIVE

5. NUMBER OF 110VRS REACTOR WAS CRITICAL. . . . , 744.0 __ 6238.9 - _ 20019.9

6. REACTOR RESERVE Sil0TDOWN 110URS. . . . . . . . . . . 0 ,, 0 0

7. Il0URS CENERATOR ON LINE.................. 744.0 6070.8 19212.3

8. UNIT RESERVE SliUTDOWN 110URS.............. 0 0 0 9.. _ CROSS TilERMAL ENERCY CENERATED (MWt). . . . 2762897 ,,___22476114 70154322

10. CROSS ELECTRICAL ENERGY GENERATED (MVil) . . 941970 7610510 23703QQQ ,

11. NE7 ELECTRICAL ENERGY CENERATED (MWil), . . . _ 90]49.A 7203886 22328369 P

12. ItEACTOR SERVICE FACTOR . . . . . . . . . . . . . . . . . . . 100. 0 6 71.2% 68.14

13. REACTOR _ AVAIIABILITY FACTOR. , . . . . . . . . . . . 100. 01 71.24 68.1%

14. UNIT SERVICE FACT 0R..................... 100.0% 69 21 65.4%

15i UNIT AVAIIA151 LITY FACTOR . . . . . . , . . . . . . . . . . _100. 0 g 69.3% 65.4%

16. -UNIT CAPACITY FACTOR (Using MDC)........._ 96.9% 65.8% 60.8%

17. UNIT CAPACITY FACTOR (Using Design MWo). 96.9% 65.8% 60.8%

18. UNIT FORCED OUTACE PATE. . . . . . . . . . . . . . . . . -. 0.0% 11.4% - 14.3%

19. SilUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACll):

N/A

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

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. ATTACHMENT I ST ill AE 3173 AVERAGE DAILY UNIT POWER LEVEL PAGE_1/ 20F 6 ,_

DOCKET NO, 30 498 UNIT 1 DATE Jan. 6. 1992 COMPl.ETED liY A.P. Kent TELEPil0NE $12/972 7786 HONTil ,,,,,,MQfdEE

l DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe. Net) (MWo Net) 1 1223 17 1254 2 1247 18 1246 3 L.8 19 1245 4 1245 ,

20 1244 5 1238 ,,, 21 1243 6 1244 22 1240 7 S97 23 1242 8 1025 24 1247 9 1246 25 12/22 10 1244 26 1248 11 1238 27 1254 12 1232 28 1257 13 1239 29 1260

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

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i ATTACHMENT 2 ST HL AE Yt?3 PAGE_.1 0F 7- _ . _ .

SOUTil TEXAS PROJECT ELECTRIC CENERATING STATION UNIT 2 MONTill.Y Ol'ERATING KEPORT DECEMBER 1991 Il00STON LICitTING AND POWER Co.

NRC DOCKET NO. $0 499 LICENSE NO. NPF-80 Review y: v . ** C ' 9 ~4 Supervisor l Date Reviewed liyg -

.h . sM'D f- 74 P ant'I1 ',i ne *ffidManapr Date Approved lay: A 1 b* '

I Date nant Hangr

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STpEGS Unit 2 began the reporting period shutdown for refueling and scheduled maint enance, Due to corrective maintenance work on equipment a cquired for start up, the ref uelitig out age was ext ended beyond the original scheduled start up date of December 5, 1991. December 6, 1991 inat ked the begituting of forced shutdown time accrued to the unit.

The generator was synchrontred to the grid on 12/16/91 at 0129 and the Turbine Overspeed Trip Tat was performed successfully. The unit remained oft line when probleros were e.pm lenced with the Main Generator Seal 011 System not ce trolling pr essure prcpe.ly. The unit was taken to Mode 2 to t ropicment r vective action. It was discovered that some relief valves were incorrectly nd that an air side filter was installed backward causing high backpressure to develop and a relief valve to lif t. The lit ting of the relief valvo n* event ed adequate pressure from being developed in the seals and a subsequent loss of hydrogen pressure in the generator. The illter was reversed.

The unit was returned to service for normal operat ion on 12/18/91 at 1852, On 12/22/91 reactor power was reduced to 12% to correct icedwater flow oscillations occurring on the 2b Steam Generator loop. The oscillations were caused by a bad positioner on a feedvater regulatin6 Valve.

On 12/24/91 with the unit at 306 reactor power and ramping up, a reactor trip and safety inj ection occurred due to low pressurteer pressure. The pressurizer spray valve on the ?A Reactor Coolant loop failed, The positioner arm from the spray valve had fallen of f because of a loose support bolt / nut arrangement. The positiones arm was replaced, With the unit in Mode 2, while attempting to transfer to governor valve control, the Electro llydraulic Control System ret.ponded incorrectly causing a turbine trip on 12/26/91. Investigations revealed tio significant problems, Throttle and governor valve testing was performed with satisfactory results on 12/27/91.

The unit achieved Mode 1 on 12/27/91 at 0641 and was synchrontred to the grid on 12/28/91 at 0129. The unit concluded the reporting period at 100%

reactor power.

l Mb i ENT 2

.. si.HL AEG17 3 OPERATING DATA REPORT PA E J = _0 L L DOCEET No. $0 499 UNIT 2 DATE J a n . 4. 1922 COMPLETED BY A.P. Eent TELEPil0NE $12/972 7786 OPERATING STATUS j l

1. REPORTING PERIOD: 12d' 12/31 GROSS ll0URS IN REPORTING PERIOD: .744 .

l I

2. CURRENTLY AUTil0RIZED POWER LEVEL (MWL): 3800-MAX. DEPEND. CAPACITY (MWa Net): 1250.6 DESIGN ELECTRICAL RATING (MVe Net): 1250.6 -

3. PWER LEVEL TO WillCil RESTRICTED (IP ANY)(MWe Net): None. l

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

Tills MONTil YR TO DATE CUMULATIVE j

5. NUMBER OF 110URS REACTOR WAS CRITICAL. . . . . 449.3 6441.3 15422.6 i 6.- . REACTOR RESERVE SIRITDOWN ll0VRS . . . , . . . . . . D 0 0 l 7,. Il0URS CENERATOR ON LINE.................. 247.1 6136.6 ,

14482.2

8. UNIT RESERVE SilVTDOWN 1100RS. . . . . . . . . . . . . , 0 0 0 f

9. CROSS'TI{ERMAL ENERGY GENERATED (MWt)..... 553038 2268800,1 52393271

10. . CROSS ELECTRICAL ENERGY GENERATED (MWit). . 154310 7644890- 17667360 11 '. NET ELECTRICAL ENERGY GENERATED (MWil) . . . .. 120528 7255235 16704001 1

12. REACTOR SERVICE FACTOR................... 60.4% 73.$t 69.4%

13. REACTOR AVAILABILITY FACTOR. . . . . . . . . . . . . . 60.4% 73.54 69.4%

14. UNIT SERVICE FACT 0R...................... 33.21 70. h 65.2%

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15. UNI T AVAIL AB I LI TY FACTOR . . . . . . . . . . . . . . . . . . 33.21 70.11. ,,

65.2%

- 16. ; UNIT CAPACITY FACTOR (Using MDC)......... 13.0% 66.2% 60.1%

'17. . . UNIT CAPACITY FACTOR (Using Design MWo)., _ 13.0% 66.2% 60.1%

18. UNIT FORCED OUTAGE RATE.................., 60.4% 9.3% 16.4%

'19.

. SHUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE. DATE AND DURATION OF EACil): .4

.N/A 2 0.. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A i

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, p ATTACHMENT 2 STHL AE 3773 -'i AVERACE DAILY UNIT POWER LEVEL L

DOCKET NO. 50 499 UNIT 2 DATE J.O.tL6 . 1992 COMPLETED BY A.P. Kent TELEPil0NE 512/972 7786 MONTil _DECEMIWR i DAY AVERACE DM LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MVe Net) 1 0 17 0 2 0 18 0  !

3 0 19 171 4 0 20 528 5 0 21 .

876 6 __ O' 22 439 7 0 23 51 8 0 24 44-9 9 25 0 10 0 26 9

'll 0 27 0 12 0 28 372 13 0 29 1005 14 0 30 1159 l--

'In 0 31 1209 16 10' -

UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET ECO. 50-449 UNIT 2 DATE 1=n. 6. 1992 -

COMPLETED BY A.P.J ent -

TETIPHONE 512/972 7766 REPORT MONTH DECEMBER l 1 2 3 4 5 1 - No. Date Type Duration Reason Method of Licensee. System Component Cause & Corrective Action to j (Hours) Shutting Event Code Code Prevent Recurrence j Down Report

• l Reactor i

91-07 910914 S 120.0. C 4 N/A N/A N/A Refueling and scheduled maintenance

, outage.

91-08 911206 F 241.5' B 9 N/A N/A N/A Corrective maintenance work on equipment required for start-up.

l j 91-09 911216 F 54.7 B 5 N/A TB FLT The Main Generator Seal Oil System was 3 not controlling pressure properly during t'

Main Turbine testing _ It was discovered that some pressure relief valves were

incorrectly set and that an air side

filter was installed backwards causing

) high backpressure to develop and a relief j valve to lift. The lifting of the relief j valve prevented adequate pressure from i being developed at the seals and a subse-i quent loss of hydrogen pressure in the j generator. The filter was reversed.

) 7 1

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F: Forced' Reason: ' Me iod: IEEE 805-1983 IEEE 803A-1983 7 52

) S: Scheduled A-Equipment Failure (Explain)

B-Maintenance or Test 1-Manual 2-Manual Scram }

hM&

C-Refueling D-Regulatory Restriction 3-Automatic Scram 4-Cont. of Existing

[ t},. myh lOW %

E-Operator Training & License Exam Outage i l

F-Administrat?ve 5-Reduction N l

G-Operational Error (Explain) 9-Other 8

~

H-Other (Explain)

UNIT SHUTDO*=*NS AND PO'=T.R REDUCTIONS DOCKET NO. 50-4?9 .

UNIT 2 DATE Jan. 6. 1992 ,

COMPLt.ita BY A.P. Fest TELEPHONE 512/972-7786 REPORT MONTH DECE?ER 2 3 4' 5 1

Duration Reason Method of Licensee System Component Cause & Corrective Action to No. Date Type Prevent Recurrence Shutting Event Code Code (Hours)

Down Report

• Reactor A 3 2-91-010 AB SPT Reactor trip and safety injection 91-10 911224 F 80.7 occurred due to low pressurizer pressure. l The pressurizer spray valve off of the 2A ,

Reactor Coolant loop failed due to a l positioner arm from the spray valve l falling off because of a loose support bolt / nut arran6enent. The positioner arm was replaced and its support supplemented by using a lock washer and a series of nuts. Corrective action to prevent recurrence will be discussed in the LER.

With the unit in Mode 2, while attempting to transfer to governor valve control the Electro-Hydraulic Control System responded incorrectly causin5 8 turbine trip.

Investigation revealed no significant problems. Throttle and governor valve testing was performed with satisfactory  ;:  ;

results. { te

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1 2 3 Method:

4 IEEE S05-1983 5 j!

IEEE S03A-1983 jf'rn>:rt E

F: Forced Reason:

1-Manual d ve[Ejl 5: Scheduled A-Equipment Failure (Explain) j y3 7]

B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram l 71 La }]j 4-Cont. of Existing }l  ;

f D-Regulatory Restriction Q '*, l E-Operator Training & License Exam Outage j

F-Administrative 5-Reduction I G-Operational Error (Explain) 9-Other H-Other (Explain) f

1 4- {~}c31.Hl.AETl?3- ;ii AC l

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{ PAGE d_OF _7 --

PORVs aDLSafety Valves S"==ary There were no PORV or Safety Valves challenged during the reporting period, t

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