ML17227A502

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Monthly Operating Repts for June 1992 for St Lucie Units 1 & 2.W/920709 Ltr
ML17227A502
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/30/1992
From: Breen J, Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-202, NUDOCS 9207160165
Download: ML17227A502 (17)


Text

ACCELERATED DISTMBUTION DEMONSATION SYSTEM ACCESSION NBR:9207160165 DOC.DATE: ~~

REGUDAT(0 INFORMATION DISTRIBUTION SYSTEN (RIDE)

FACIE:50-335 St. Lucie Plant, Unit 1, Florida Power 50-389 St. Lucie Plant, Unit 2, Florida Power NOTARIZED: NO 6

Light Light Co.

Co.

DOCKET 05000335 05000389

¹ AUTH. NAME AUTHOR AFFILIATION BREEN,J.J. Florida Power S Light Co.

SAGER,D.A. Florida Power a Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthl ating repts for June 1992 for St. Lucie Units 1

2. 920709 tr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Specs NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD 1 1 NORRIS,J 1 1 INTERNAL: ACRS 10 10 AEOD/DOA 1 1 AEOD/DSP/TPAB NRR/DOEA/OEAB RGN2 11EGF 1

1 1

1 NRR DLPQ/LPEB10 01 1

1 1

1 EXTERNAL 'GGG BRYCE F J ~ H 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM 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 July 9, 1992 II=IPII L-92-202 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 eratin Re ort Attached are the June 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 truly yours, D. A. ger Vice, sident St. Lucie Plant DAS:JJB:kw

. cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC Attachments DAS/PSL N734-92 9207160165 920630 F!DR,; ADOCK 05000335

'R FDR an FPL Group company

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-335 DATE COMPLETED BY J.J. Breen MONTH JUNE f992 DAY AVERAGE DAILY POWER LEVEL

(:-%'~-Net) 6/ 1/92 849 6/ 2/92 849 6/ 3/92 848 6/ 4/92 851 6/ 5/92 828 6/ 6/92 663 6/ 7/92 645 6/ 8/92 702 6/ 9/92 857 6/10/92 861 6/11/92 862 6/12/92 "

857 6/13/92 854 6/14/92 786 6/15/92 659 6/16/92 668 6/17/92 703 6/18/92 854 6/19/92 852 6/20/92 853 6/21/92 851 6/22/92 850 6/23/92 847 6/24/92 851 6/25/92 855 6/26/92 860 6/27/92 861 6/28/92 859 6/29/92 861 6/30/92 857

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e OPERATING DATA REPORT DOCKET NO 50 335 DATE COMPLETED'BY Ji Ji BREEN TELEPHONE 487/468/4248 OPERATING STATUS 1 o UNIT NAME o ST o LUCIE UNIT 1 2+ REPORTXNG PERIOD: JUNE 1992 3+ LXCENSED THERMAL POWER (MWT)o 2700 4o NAMEPLATE RATING (GROSS MWE) i 850 5i DESIGN ELECTRICAL RATING (NET MWE) o 830 6o MAXXMUM DEPENDABLE CAPACXTY (GROSS MWE)o 872 7i MAXIMUM DEPENDABLE CAPACITY <NET MWE) o 839 8 XF CHANGES OCCUR IN CAPACITY RATINGS (XTEMS NUMBER 3 THROUGH 7)

SINCE LAST REPORT~ GIVE REASONS'+

POWER LEVEL TO WHICH RESTRICTED'F ANY (NET MWE) 10, REASONS FOR RESTRICTIONS'F ANY:

MONTHLY - YTD- CUMULATIVE ii,o HOURS IN REPORT PERIOD: 720 4367 136103+0 12 o NUMBER OF HOURS REACTOR WAS CRITXCAL 720eO 4367 ' 104476o6 13+ REACTOR RESERVE SHUTDOWN HOURS oie OoO 205o3 14 o HOURS GENERATOR ON-LINE 720eO 4367oO 103562o9 15'NIT RESERVE SHUTDOWN HOURS OiO OoO 39i3 267404459 16'ROSS THERMAL ENERGY GENERATED (MWH) 1866658 11677207 17m GROSS ELECTRXCAL ENERGY GENERATED (MWH) 618780 3920130 88252950 18'ET ELECTRICAL ENERGY GENERATED <MWH) 586786 3725908 83409604 76ii 19 o UNIT SERVICE FACTOR 100oO 180+0 20 o UNIT AVAILABILITYFACTOR 10eoe 100ee 76oi 21 o CAPACXTY FACTOR (USXNG MDC NET ) 97+1 101+7 75o7 22+ CAPACITY FACTOR (USXNG DER NET) 98+2 102+8 74o8 23'NIT FORCED OUTAGE RATE OiO OoO 4+0 24+ SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS 25 o IF SHUT DOWN AT END OF REPORT PERIOD ~ ESTIMATED DATE OF STARTUP o

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UNIT SHUTDOWNS AtG) POWER REDUCTIONS DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 4 Q 4 REPORT MONTH No. Date Type'uration (Hours)

Reasons Method of Reactor'ystem Shutting Licensee Event Report Code'ode'ause Component & Corrective Action to Down Prevent Recurrence 920605 0.0 B N/A HF Unit 1 reduced power for cleaning of the 1B1 and 1A2 waterboxes.

920614 0.0 B N/A HF XXXXXX Unit 1 reduced power for cleaning of the 1A1 and 1B2 watetboxes.

4 F Forced Reason Method Exhibit G - Instructions for S Schcdulcd 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) Filo (NUREG4161)

D - Regulatory restriction 4 - Continued E - Opcratoi Training dt License Examination S - Load Reduction F - Administrative 9 - Other (Explain) Exhibit 1 - Samo Source G - Operational Error (Expalin)

H - Other (Explain)

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SUMMARY

OP OPERATING EXPERIENCE DOCKET NO. 50-335 DATE COMPLETED BY J.J. Breen REPORT MONTH JUNE 1992 Unit 1 operated at reduced power from June 5, 1992, until 'June 8, 1992, and from June 14, 1992, until June 17, 1992, due to waterbox cleaning. Unit 1's average daily power level was at 1004 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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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO ~ 50-389 I~

DATE COMPLETED BY J.J. Breen MONTH JUNE 1992 DAY AVERAGE DAILY POSER LEVEL (Mve-Net) 6/ 1/92 -3 6/ 2/92 -3 6/ 3/92 -3 6/ 4/92 -3 6/ 5/92 -3 6/ 6/92 4 6/ 7/92 -3 6/ 8/92 -3 6/ 9/92 6/10/92 4 6/il/92 6/12/92 -6 6/13/92 -4 6/14/92 -4 6/15/92 6/16/92 5 6/17/92 -4 6/18/92 -6 6/19/92 -7 6/20/92 -10 6/21/92 -20 6/22/92 -38 6/23/92 -31 6/24/92 -31 6/25/92 -34 6/26/92 33 6/27/92 104 6/28/92 410 6/29/92 628 6/30/92 730

OPERATING DATA REPORT DOCVET NO 50 389 DATE COMPLETED BY Ji Ji BREEN TELEPHONE 407/468/4248 OPERATING STATUS 1 t UNIT NAME ~ ST ~ LUCIE UNIT 2 2 o REPORTXNG PERIOD+ JUNE 1992 3i LICENSED THERMAL POWER (MWT): 2700 NAMEPLATE RATING (GROSS MWE)f 850 5i DESIGN ELECTRICAL RATING (NET MWE) o 830 6i MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) i 882 7i MAXXMUM DEPENDABLE CAPACITY (NET MWE) f 839 so IF CHANGES OCCUR XN CAPACXTY RATINGS (ITEMS NUMBER 3 THROUGH 7)

SINCE LAST REPORTS GIVE REASONS'OWER LEVEL, TO WHXCH RESTRICTED'F ANY (NET MWE) 10m REASONS FOR RESTRICTIONS~ IF ANYo MONTHLY -.-YTD- CUMULATIVE ili HOURS IN REPORT PERIOD'2+.

NUMBER OF HOURS REACTOR WAS CRXTXCAL 720 4367 78000.0 166i2 283io9 66452il 13'EACTOR RESERVE SHUTDOWN HOURS eoO 0+0 OoO 14 'OURS GENERATOR ON-LXNE 108+3 2766oO 65370o3 15+ UNIT RESERVE SHUTDOWN HOURS OoO OiO OiO 16+ GROSS THERMAL ENERGY GENERATED (MWH) 159590 .71S1S3e 171294436 17'ROSS ELECTRICAL ENERGY GENERATED (MWH) 50520 2411070 57136890 iso NET ELECTRICAL ENERGY GENERATED (MWH) 40892 2274732 54037579 19'NIT SERVICE FACTOR 13+ 9 63o3 83os 20, UNIT AVAILABILITYFACTOR 13+9 63o3 83os 2ii CAPACITY FACTOR (USING MDC NET) 6+6 62+1 83' 22'APACITY FACTOR (USING DER NET) 6+7 62is 84 F 1 23 o UNIT FORCED OUTAGE RATE 0+0 OiO 4o9 24m SHUTDOWNS SCHEDULED, OVER NEXT 6 MONTHS 25+ XF SHUT DOWN AT END OF REPORT PERIOD ~ ESTIMATED DATE OF STARTUP i

f UNIT SHUTDOWNS AM) POWER REDUCTIONS DOCKET NO.

UNIT NAME DATE COMPLETED BY .

TELEPHONE 4 4 REPORT MONTH No. Date Type Duration (Hours)

Reasons Method of Shutting Licensee Event Report Code'omponent'ode'ause System 8e Corrective Action to Down Prevent Recurrence Reactor 920421 613.5 N/A RC FUELEX Unit 2 taken offline for refueling.

10 920626 0.0 B N/A ZZZZZZ Unit 2 held at approximately 25% power for physics testing.

10 920627 6.2 N/A HA FUELEX Unit 2 reduced power for the turbine overspeed trip test.

920627 0.0 N/A ZZ ZZZZZZ Unit 2 held at 30% power due to a Chemistry hold.

F Forced Reason Method Exhibit G - Instructions for S Schcdulcd A - Equipment failure (explain) 1 - Manual preparation of Data Entry B - Maintenance or Test 2- Manual Scram Shccts Licensee Event Report C - Rcfucling 3 - Automatic Scram (LER) Filo (NVREG4161)

D - Regulatory restriction 4 - Continued E - Operator Training dt License Examination 5 - Load Reduction F - Administrative 9 - Other (Explain) Exhtbtt 1 Same Source G - Operational Error (Expalin)

H - Other (Explain)

UNIT SHUTDOWNS 826) POWER REDUCTIONS DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE REPORT MONTH No. Date Type'uration (Hours)

Reason Method of Shutting Licensee Event Report System Code" Code'ause Component 8c Corrective Action to Down Prevent Recurrence Reactor 12 920628 0.0 B N/A zzzzzz Unit 2 held at approximately 50% power for physics testing.

13 920629 0.0 B N/A zzzzzz Unit 2 held at approximately 80% power for physics testing.

2 F Forced Reason Method Exhibit G Instructions for S Sehcdulcd h - Equipmcnt failure (explain) 1 - Manual Preparation of Data Entry B - Maintenance or Test 2 - Manual Scram Sheets Licensee Event Rcport C - Refueling 3 - hutomatic Scram (LER) File (NUREG4161)

D - Regulatory restriction 4 - Continued E - Operator Training ds License Examination S - Load Reduction F - hdministrative 9 - Other (Explain) Exhibit I - Same Source G - Operational Error (Expa! in)

H - Other (Explain)

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SUMMARY

OP OPERATING EXPERIENCE DOCKET NO. 50-389 i~

DATE COMPLETED BY J.J. Breen TELEPHONE 407 468-4248 REPORT MONTH JUNE 1992 Unit 2 was in a refueling outage for most of the month of June.

The refueling outage ended on June 26, 1992. On June 27, 1992, the unit vas held at approximately 25~ power for physics testing and then reduced pover for the turbine overspeed trip test. Upon completion of the turbine overspeed trip test, pover was increased and held at approximately 30% due to a chemistry hold. On June 28, 1992, power was increased and held at approximately 504 for physics testing. On June 29, 1992, power was increased and held at approximately 804 for physics testing. As of June 30, 1992, the unit was at approximately 85% power.,

In accordance vith 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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