L-94-073, Provides 10CFR50.46, Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors Annual Rept for Turkey Point Units 3 & 4 Since Last Rept & Returns Turkey Point to Annual Cycle Consistent W/Other Westinghouse Units

Provides 10CFR50.46, Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors Annual Rept for Turkey Point Units 3 & 4 Since Last Rept & Returns Turkey Point to Annual Cycle Consistent W/Other Westinghouse Units

ML17352A534
Person / Time
Site:	Turkey Point
Issue date:	04/11/1994
From:	Plunkett T FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-94-073, L-94-73, NUDOCS 9404190154
Download: ML17352A534 (7)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9404190154 DOC. DATE: 94/04/11 NOTARIZED: NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION PLUNKETT,T.F.

Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET g

05000250 05000251

SUBJECT:

Provides 10CFR50.46, "Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors" annual rept for Turkey Point Units 3

& 4 since last rept dtd 931029 6 returns Turkey Point to annual cycle consistent w/other Westinghouse units.

DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

General Distribution NOTES:

D RECIPIENT ID CODE/NAME PD2-2 LA CROTEAU,R INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

1 2

2 1

1 1

1 1

1 1

1 1

0 1

1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DORS/OTS B NRR/DRPW NRR/DS SA/SRXB L

C LE 01 NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

0 1

1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

D D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LIS1$ FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16 ENCL 14

i=PI APR 11 'l99$

L-94-073 10 CFR 50.46 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555 Gentlemen:

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 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 since the last report dated October 29,

1993, and returns Turkey Point to an annual cycle consistent, with other Westinghouse units.

Should there be any questions, please contact us.

Very truly yours, cNW T. F. Plunkett Vice President Turkey Point Plant Attachment TFP/RJT/rjt cc:

S.

DE Ebneter, Regional Administrator, Region II, USNRC T.

P.

Johnson, Sr. Resident Inspector, USNRC, Turkey Point Plant

~ cw~pgy 9404190154 940411 PDR ADGCK 05000250 R

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L-94-073 Attachment Page 1 of 4

ATTACHMENT Re:

Turkey Point Units 3 and 4

Docket Nos.

50-250 and 50-251 10 CFR 50,46, "Acceptance Criteria for Emergency Coze Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Lar e Break LOCA LBLOCA By letter L-93-267 dated October 29, 1993, Florida Power and Light Company (FPL) reported a peak clad temperatuze (PCT) of 2104'F in the event of a worst case large break loss of coolant accident (LBLOCA) transient.

This value included a calculated peak temperature of 2082'F plus 22'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, steam generator tube collapse during an earthquake, revised grid loss coefficients resulting in an increased core pressure drop and corrections to the WREFLOOD-INTERIM Structural Metal Heat Model in the BART Computer code.

Recent corrections to the VESCAL subroutine of the LUCIFER computer model have resulted in a decrease in the peak clad temperature for the worst case LBLOCA of 6'F for a total PCT of 2098'F.

This O'F benefit is a result of a correction to the mass and geometry calculations of the reactor pressure vessel and steam generator.

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

Small Break LOCA SBLOCA By letter L-93-267, Florida Power and Light Company reported a

peak clad temperature of 1703'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.

This value included a calculated peak clad temperature of 1749'F less a 46'F benefit due to the presence of stainless steel rods in fuel assemblies, corrections to the NOTRUMP Bessel

function, corrections due to the effects of safety injection on the broken loop and an improved condensation

model, and errors in the drift flux flow regime.

L-94-073 Attachment Page 2 of 4

Small Break LOCA SBLOCA (Continued)

Recent corrections to the VESCAL subroutine of the LUCIFER computer model have resulted in a decrease in the peak clad temperature for the worst case SBLOCA of 16'F for a total PCT of 1687'F.

This 16'F benefit is a result of a correction to the mass and geometry calculations of the reactor pressure vessel and steam generator.

~Summa r The revised peak clad temperatures of 2098'F for the worst case LBLOCA and 1687'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-94-0/3 Attachment Page 3 of 4

TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Evaluations s ecified in FPL letter L-93-267 2082'F Effect of Containment Purging Pressurizer Pressure Uncertainty Implementation of Debris Resistant FA Transition Core Penalty Stainless Steel Rods in Fuel Assemblies Steam Generator Tube Collapse During an Earthquake Revised Grid Loss Coefficients WREFLOOD Structural Metal Heat Modeling Total LBLOCA PCT specified in FPL Letter L-93-267 9'

SoF 3 F 10'F 2'F 1 SoF

-3'F 25oF 2104 F Evaluations since issuance of FPL letter L-93-267 Vessel and Steam Generator calculational errors in the LUCIFER model Total Estimated LBLOCA PCT

-6 F 2098 F

r

L-94-073 Attachment Page 4 of 4

TABLE 2 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Evaluations s ecified in FPL letter L-93-267 Stainless Steel Rods in Fuel Assemblies NOTRUMP Bessel Function Correction Effect of Safety Injection in Broken Loop Effect of Improved Condensation Model Drift Flux Flow Regime Errors 2 F

-35 F 150 F

-150 F

-13'F 1749 F Total SBLOCA PCT specified in FPL Letter L-93-267 1703 F Evaluations since issuance of FPL letter L-93-267 Vessel and Steam Generator calculational errors in LUCIFER model

'16'F Total Estimated SBLOCA PCT 1687 F