ML17227A556

Monthly Operating Repts for Jul 1992 for St Lucie Units 1 & 2.W/920814 Ltr

ML17227A556
Person / Time
Site:	Saint Lucie
Issue date:	07/31/1992
From:	Breen J, Sager D FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-228, NUDOCS 9208190214
Download: ML17227A556 (19)

Text

ACCELERATED TRIBUTION DEMOIVRATION SYSTEM 2 REQULAl RY INFORMATION DISTRIBUTION SYSTEM (R IDS)

ACCESSION NBR: 9208190214 DQC. DATE: OTAR IZED: NO DOCVET e FACIL: 50-335 St. Lucie Plant> Unit li Florida Power Sc- Light Co. 05000335 50-389 St. Lucie Plant> Unit 2i Florida Power 5 Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION BREENi J. J. Florida Power 8c Light Co.

SAGER'. A. Florida Power 5 Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

Month I ating repts for Jul 1'F92 for St Lucie units 8c 2 /920814 DISTRIBUTION CODE:

TITLE: Monthly Operating IEE4D COPIEE RECEIVED: LTR J Repov t (per Tech Specs)

ENCL f BIIE: (g ~ D NOTES:

RECIPXENT COPIES RECIPIENT CQPXES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD 1 1 NORRIS' 1 1 INTERNAL: ACRS 10 10 AEOD/DQA AEOD/DSP/TPAB 1 NRR/DLPG/LPEB 10 1 1 NRR/DOEA/OEAB 1 REG F 01 1 1 RQN2 "1 1 EXTERNAL: EGScG BRYCEi J. H 1 NRC PDR 1 1 NSXC 1 1 R

D NOTE TO ALL "RIDS RECIPIENTS:

PLEASE HELP US TO RFDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOhk P 1-37 (E>'T. 504-2065) TO ELIMINATEYOUR NAME FROhf DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24

P.O. Box 128, Ft. Pierce, FL 34954-0128 August 14, 1992 L-92-228 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Monthl 0 erat'.in Re ort Attached are the July 1992 Operating Status and Summary of Operating Experience Reports for St. Lucie Units 1 and 2.

Should there be any questions on this information, please contact us ~

Very tru y yours, D. A Sager Vic resident St. cie Plant DAS:JJB:kw cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC Attachments DAS/PSL 8715-92 9208190214 920731 PDR ADOCK 05000335 R PDR an FPL Group company zaoooz

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO ~ 50-335 UNIT St. Lucie 1 DATE 4 COMPLETED BY J.J. Breen TELEPHONE 407 46B-424B MONTH JULY 1992 DAY -AVERAGE DAILY POWER LEVEL (MWe<<Net) 7/ 1/92 858 7/ 2/92 ~ 856 7/ 3/92 851 7/ 4/92 847 7/ 5/92 844 7/ 6/92 848 7/ 7/92 852 7/ 8/92 848 7/ 9/92 848 7/10/92 846 7/11/92 846 7/12/92 846 7/13/92 848 7/14/92 851 7/15/92 847 7/16/92 848 7/17/92 852 7/18/92 853 7/19/92 848 7/20/92 845 7/21/92 845 7/22/92 846 7/23/92 849 7/24/92 854 7/25/92 854 7/26/92 851 7/27/92 850 7'/28/92 850 7/29/92 848 7/30/92 849 7/31/92 847

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OPERATING DATA REPORT DOCKET NO >0 335 DATE AUu g 4 gyp COMPLETED BY J. J. BREEN TELEPHONE 487/468/4248 OPERATING STATUS

1. UNIT NAME+ STi LUCXE UNIT 1 2+ REPORTING PERIOD: JULY r 1992

3. LICENSED THERMAL POWER ( MWT ): ~700 4+ NAMEPLATE RATING (GROSS MWE) i 858 5+ DESIGN ELECTRICAL RATING (NET MWE) i 830 hi MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) t 872 7, MAXIMUM DEPENDABLE CAPACITY <NET MWE): 839 8 i IF CHANGES OCCUR IN CAPACITY RATINGS < XTEMS NUMBER 3 THROUGH 7)

SINCE LAST REPORT ~ GIVE REASONS:

9 ~ POWER LEVEL TO WHXCH RESTRICTED'F ANY <NET MWE) 10, REASONS FOR RESTRICTIONS ~ IF ANY:

MONTHLY - YTD- CUMULATIVE iii HOURS IN REPORT PERIOD'2+

NUMBER OF HOURS REACTOR WAS CRXTICAL 744 744iO 5111 5iiiie 136847.0 105220ih 13'EACTOR RESERVE SHUTDOWN HOURS 0+0 0+0 205i3 14 o HOURS GENERATOR ON-LINE 744ee 5111+0 104306i9 15'NIT RESERVE SHUTDOWM HOURS 0+0 0+0 39o3 ihi GROSS THERMAL ENERGY GENERATED (MWH) 2009035 13686242 269413494 17+ GROSS ELECTRICAL ENERGY GENERATED (MWH) 665200 4585330 88918150 iso NET El ECTRXCAL ENERGY GENERATED (MWH) 631780 4357688 84041384 19 i UNIT SERVICE FACTOR 100+0 100iO rhi2 20, UNIT AVAILABILITYFACTOR 108 i 0 100+0 rhi3 Zl i CAPACITY FACTOR (USING MDC NET) 10ie2 101oh 75.8 22'APACITY FACTOR (USING DER NET) 102i3 102 i 7 74i9 23'NIT FORCEl)'~CUTAGE RATE 0+0 OiO 3o9 24'HUTDOWNS SQKDLRED OVER NEXT 6 MONTHS 25'F SHUT DOWN AT END OF REPORT PERIOD~ ESTIMATED DATE OF STARTUPt

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-335 UNIT NAME TL IE I DATE AUG S C QR COMPLETED BY BREEN TELEPHONE 4 4 -424 REPORT MONTH LY I 2 No. Date Type'uration Reason~ Method of Licensee System Code'omponent Cause 8c Corrective (Hours) Shutting Event Report Code Action to Down Prevent Recurrence Reactor For the month of July, 1992, the average daily power level for Unit 1 was 100%.

F Foteed Reason Method Exhibit G - Insuuctions for S Scheduled A - Equipmcnt failure (explain) I - Manual Preparation of Data Entry B - Maintenance or Test 2 - Manual Scram Sheets Liccnscc Event Report C - Refueling 3 - Automatic Scram (LER) Fdc (NUREG4t6l)

D - Regulatory reariction 4 - Continued E - Operator Training 4 License Examination 5 - Load Reduction F - Adnunistrative 9 - Other (Explain) Exhibit l - Same Source G - Operational Error (Expalin)

H - Other (Explain)

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO ~ 50-335 COMPLETED BY J.J. Breen TELEPHONE 407 468-4248 REPORT MONTH JULY 1992 For the month of July, 1992, the average daily power level for Unit 1 was 100%.

In accordance with the requirements of Technical Specification 6.9.1.6, there were no challenges to the PORVs or safety valves during the report period.

~ ~14/5 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO ~ 50-389 UNIT St. Lucie 2 DATE COMPLETED BY J.J. Breen TELEPHONE 407 468-4248 MONTH JULY 1992 DAY AVERAGE DAILY POWER LEVEL (Mwe<<Net) 7/ 1/92 727 7/ 2/92 801 7/ 3/92 849 7/ 4/92 848 7/ 5/92 846 7/ 6/92 846 7/ 7/92 848 7/ 8/92 392 7/ 9/92 390 7/10/92 406 7/11/92 845 7/12/92 853 7/13/92 855 7/14/92 858 7/15/92 856 7/16/92 857 7/17/92 859 7/18/92 645 7/19/92 -30 7/20/92 -31 7/21/92 686 7/22/92 858 7/23/92 860 7/24/9Z 759 7/25/92 697 7/26/92 663 7/27/92 649 7/Z8/92 646 7/29/92 623 7/30/92 848 7/31/92 860

OPERATING DATA REPORT DOCKET NO 50 389 DATE . NG i.e,i%2 COMPLETED BY J. J. BREEN TELEPHONE 407/468/4248 OPERATING STATUS

'30 io UNIT NAME; ST. LUCXE UNIT 2 Zi'EPORTING PERIODS JULY~ 1992 3+ LICENSED THERMAL POHER (MAT) i. 2708 NAMEPLATE RATING (GROSS MHE)$ 850 5 DESIGN ELECTRICAL RATING (NET MHE) hi M*XXMUM DEPENDABLE CAPACITY (GROSS MHE) 5 882

7. MAXXMUM DEPENDABLE CAPACITY (NET MHE): 839

8. IF CHANGES OCCUR XN CAPACITY RATINGS (XTEMS NUMBER 3 THROUGH 7)

SINCE LAST REPORT r GIVE REASONS i 9i POHER LEVEL TO WHICH RESTRICTED~ XF ANY (NET MHE) 10, REASONS FOR RESTRICTIONS~ XF ANY:

MONTHLY - YTD- CUMULATIVE i1 + HOURS XN REPORT PERIODS 744 5111 78744iO 12 o NUMBER OF HOURS REACTOR HAS CRXTICAL 675i9 3507+7 67128.0 13+ REACTOR RESERVE SHUTDOWN HOURS OiO OiO OoO 14'OURS GENERATOR ON-LXNE hhio7 3427o7 66032iO 15'NXT RESERVE SHUTDOWN HOURS OiO 0+0 0.8 16 GROSS THERMAL ENERGY GENERATED (MHH) 1664865 8845895 172958501 17'ROSS ELECTRICAL ENERGY GENERATED (MHH) 552700 2963770 57689590 18'ET ELECTRICAL ENERGY GENERATED (MHH) 519969 2794781 54557548 19, UNXT SERVICE FACTOR 88+9 67ii 83i9 20 i UNIT AVAILABILXTYFACTOR 88+ 67ii 83+9 21 i CAPACXTY FACTOR (USXNG MDC NET) 3 9'3+

65+2 83'

22. CAPACXTY FACTOR (USING DER NET) 84i2 65' 84.1

23. UNIT FORCED 0~AGE RATE 11+1 213 5+0 24, SHUTDONNS SCHEQN ED OVER NEXT 6 MONTHS 25, XF SHUT DOWN AT END OF REPORT PERIOD~ ESTIMATED DATE OF STARTUP:

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-389 UNIT NAME TL IE NIT 2 DATE COMPLETED BY 'REEN TELEPHONE 4 468-4248 REPORT MONTH J LY I 2 No. Date Type Duration (Hours)

Reason'ethod of Shutting Licensee Event Report System Code'omponent Code'ause 8c Corrective Action to Down ¹ Prevent Recurrence Reactor 14 920708 17.62 LER 92~ HH lNSTRU Unit 2 was manually tripped due to low (A) Steam Generator water level caused by by a failed circuit in the 2A feedwater regulating valve control system.

15 920710 F 9.92 B LER 92-05 HA TURBIN Unit 2 tripped automatically on loss of load during performance of the turbine 20/ET test.

16 920718 0.0 N/A CB PUMPXX Unit 2 was downpowered due to a cracked oil line in the 2B1 Reactor Coolant Pump (RCP).

16 920718 F 54.70 B N/A CB PUMPXX Unit 2 was manually tripped for repairwork of the 2BI RCP cracked oil line.

F Fore<<d Reason Method Exhibit G - Instructions for S Scheduled A - Equipment failure (explain) I - Manual Preparation of Data Entry B - Maintenance or Test 2 - Manual Scram Sheets Licensee Event Report C - Refueling 3 - Automatic Scram (LER) File (NUREGW161)

D - Regulatory restriction 4 - Continued E - Operator Training dt License Examination 5 - Load Reduction F - Adnunistrative 9 - Other (Explain) Exhibit I - Same Source G - Operational Error (Expalin)

H - Other (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-389 UNIT NAME TL IE NIT 2 DATE ~G1 4 COMPLETED BY J BREEN THLEPHONB L4444248 REPORT MONTH Y I 2 Date Type Duration Reason~ Method of System Component Cause Sc Corrective No. (Hours) Shutting Event Report Codes Codes Action to Reactor'icensee Down ¹ Prevent Recurrence 17 920724 0.0 B N/A HF PUMPXX Unit 2 was manually downpowered to repair the traveling screen for the 2B2 Circulating Water Pump (CWP).

17 920729 0.0 B N/A HF PUMPXX Unit 2 was downpowered further because of seaweed on traveling screen and to decrease backpressure to the 2A2 CWP.

18 920729 0.0 N/A HF PUMPXX Unit 2 was held at approximately 81% power for repair of the 282 CWP traveling screen.

F Forced Reason Method Exhibit G - Insttuctions for S Scheduled A - Equipment failure (explain) 1 - Manual Preparation of Data Entry B - Maintenance or Test 2 - Manual Scram Sheets Licensee Event Report C - Refueling 3 - Automatic Scram (LER) File (NUREGW161)

D - Regulatory restriction 4 - Continued E - Operator Training dc License Examination 5 - Load Reduction F - Adnutdstrative 9 - Other (Explain) Exhibit t - Sane Source G - Operational Error (Expalin)

H - Other (Explain)

SUMMARY

OP OPERATING EXPERIENCE DOCKET Noi 50-389 AOA~

COMPLETED BY J.J. Breen TELEPHONE 407 468-4248 REPORT MONTH JULY 1992 On July 8, 1992, Unit 2 had a manual reactor trip due to low (A)

Steam Generator water level caused by a failed circuit in the 2A feedwater regulating valve control system; this event was reported to the NRC in License Event Report 92-04, for Unit 2. Unit 2 was returned to 1004 power on July 9, 1992. On July 10, 1992, the reactor tripped from 1004 power on loss of load caused by a design inadequacy in the on-line testing modification of the turbine trip control system; this event was reported to the NRC in License Event Report 92-05, for Unit 2. On July 11, 1992, the unit was at 100%

power and remained there until July 18, 1992, when the unit was downpowered due to a cracked oil line in the 2B1 Reactor Coolant Pump (RCP); Unit 2 was then manually tripped for repairwork and was returned to 1004 power on July 22, 1992. From July 24, 1992, to July 30, 1992, Unit 2 was operated at reduced power to repair the traveling screens to the 2A2 and 2B2 Circulating Water Pumps(CWP). On July 30, 1992, the unit was at 100% power and remained there for the rest of the month.

In accordance with the requirements of Technical Specification 6.9.1.6, there were no challenges to the PORVs or safety valves during the report period.

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