ML17349A560

Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors, Annual Rept for CY92

ML17349A560
Person / Time
Site:	Turkey Point
Issue date:	12/18/1992
From:	Plunkett T FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-338, NUDOCS 9212280161
Download: ML17349A560 (8)

Text

ACCEI ERAT DOCUMENT DISTR UTION SYSTEM REGULATO INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9212280161 DOC.DATE: 92/12/18 NOTARIZED: NO DOCKET FACIE:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power & Light Co. R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

Criteria for in Light Water Nuclear Power i

SUBJECT:

"Acceptance ECCS Reactors," annual rept for CY92. D DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution i ENCL SIZE: 5 NOTES NRR RAGHAVANP L 05000250 /

NRR RAGHAVAN,L 05000251 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 1 PD2-2 PD 1 . 1 AULUCKiR 2 2 D INTERNAL: NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC LFMB 1 0 OGC/HDS3 1 0

- ~EM Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTES: 1 1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15

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P.O. Box 029100, Miami, FL, 33102-9100 OIS 18 '(992 L-92-338 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Gentlemen:

10 CFR 50.46 (a)(3)(ii) requires that licensees report to the Commission at least annually the nature of changes to, or errors discovered in, the emergency core cooling system (ECCS) evaluation models, or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis. This letter provides Florida Power and Light Company's report for Turkey Point Units 3 and 4 for calendar year 1992.

Should there be any questions, please contact us.

Very truly yours, Wr. 7/~EH 8 T. F. Plunkett Vice President.

Turkey Point Nuclear Attachment TFP/RJT/rjt cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant r;~OO'zs 9212280ibi 9212i8 PDR ADQCK 05000250 R PDR g0 an FPL Group company

c'-92-338 Attachment Page 1 ATTACHMENT Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Lar e Break IOCA LBLOCA By letter L-91-165 dated June 7, 1991'lorida Power and Light Company (FPL) reported a peak clad temperature of 2132'F in the event of a worst case large break loss of coolant accident (LBLOCA) transients This value included a calculated peak temperature of 2082'F plus 50 F increment due to containment purge coincident with a LBLOCA, increased steady-state pressurizer pressure uncertainty band, transition fuel core penalty, implementation of debris resistant fuel assemblies and stainless steel rods in fuel assemblies, and steam generator tube collapse during an earthquake.

Recent corrections to LBLOCA modelling have resulted in a decrease in the peak clad temperature for the worst case LBLOCA of 3'F for a total of 2129'F. This 3 F benefit is a result of a revision in the grid loss coefficients for the Optimized Fuel Assemblies (OFA) .

The LBLOCA analysis as de'scribed in the Updated Final Safety Analysis Report (UFSAR) was performed by Westinghouse in 1991 using the BART computer model with fuel assembly spacer grids.

Small Break LOCA SBLOCA By letter L-91-165, Florida Power and Light Company reported a peak clad temperature of 1749'F in the event of a worst case small break loss of coolant accident (SBLOCA) transient. This value was based upon a new Turkey Point SBLOCA analysis performed by Westinghouse in 1991 using the NOTRUMP digital computer code.

Recent plant changes and corrections in SBLOCA coding have resulted in a decrease in the peak clad temperature for the worst case SBLOCA of 33'F for a total of 1716'F. This value includes a 2'F increase due to the presence of stainless steel rods in fuel assemblies, and a 35'F benefit due to a NOTRUMP Bessel function correction.

C L-92-338 Attachment Page 2

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The revised peak clad temperatures of 2129'F for the worst case LBLOCA and 1716'F for the worst case SBLOCA, correcting for the effects discussed herein and summarized in the enclosed Tables 1 and 2, are below the 10 CFR 50.46 acceptance limit of 2200'F.

L-92-338 Attachment Page 3 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record 2082'F Evaluations s ecified in FPL letter L-91-165 Effect of Containment Purging 9 F Pressurizer Pressure Uncertainty 8oF Implementation of Debris Resistant FA 3 F Transition Core Penalty 10 F Stainless Steel Rods in Fuel Assemblies 2 F Steam Generator Tube Collapse During an Earthquake 18oF Total LBLOCA PCT specified in FPL Letter L-91-165 2132'F Evaluations since issuance of FPL letter L-91-165 Increase Core Pressure Drop 3 F Total Estimated LBLOCA PCT 2129'F

L-92-338 Attachment Page 4 TABLE 2 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record 1749 F Evaluations since issuance of L-91-165 Stainless Steel Rods Cycle 12 Fuel 2'F NOTRUMP Bessel Function Correction -35'F Tota1 Estimated SBLOCA PCT 1716 F

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