ML031610991

Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

ML031610991
Person / Time
Site:	Seabrook
Issue date:	06/03/2003
From:	Peschel J Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NYN-03046
Download: ML031610991 (4)

Text

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FPL Energy FPL Energy Seabrook Station Seabrook Station P.o. Box 300 Seabrook, NH 03874 (603) 773-7000 June 3, 2003 Docket No. 50-443 NYN-03046 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Annual Reporting of Changes to, or Errors In Emergency Core Cooling System Models or Applications In accordance with the requirements of 10 CFR 50.46(a)(3)(ii), FPL Energy Seabrook, LLC submits a tabulation of the current Small Break and Large Break LOCA PCT margin utilization tables applicable to Seabrook Station. The Small Break and Large Break LOCA utilization tables are consistent with the tables provided in North Atlantic's 2001 10 CFR 50.46 Report, NYN-02060, dated June 26, 2002.

Should you have any questions regarding this report, please contact Mr. Paul V. Gurney, Reactor Engineering Manager at (603) 773-7776.

Very truly yours, FPL Energy Seabrook, LLC

$n,s M. Peschel Wgulatory Programs Manager cc:

H. J. Miller, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G.T. Dentel, NRC Senior Resident Inspector A-1

ENCLOSURE TO NYN-03046

Small Break Peak Clad Temperature Margin Utilization ECCS EVALUATION MODEL REVISIONS/ERRORS 10 CFR 50.46 ANNUAL REPORT Evaluation Model: NOTRUMP Fuel: 17x17 V5H FQ=2.5 F A H=1.65 SGTP=13%

3411 MWt Limiting Break. 4 inch Clad Temperature (0F}

ANALYSIS OF RECORD MARGIN ALLOCATIONS (Delta PCT) 1082 A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1.

Effect of SI in Broken Loop 150

2.

Effect of Inproved COSI

-150

3.

Drift Flux Flow Regime Errors

-13

4.

LUCIFER Error Corrections

-16

5.

Boiling Heat Transfer Correlation Error

-6

6.

Steam Line Isolation Logic Error 30

7.

Axial Nodalization, RIP Model Revision and SBLOCrA 13 Error Corrections

8.

NOTRUMP Specific Enthalpy Error 20

9.

SBLOCTA Fuel Rod Initialization Error 10

10.

NOTRUMP Mixture Level Tracking t Region Depletion Errors 13 B. PLANNED PLANT CHANGE EVALUATIONS

1. Increased Safety Injection Pump Head Degradation Limiting Case 105 Evaluation

2.

Annular Blankets 10 C. 2002 10 CFR 50A6 MODEL ASSESSMENTS (Permanent Assessments of PCT Margin)

1. None 0

D. TEMPORARY ECCS MODEL ISSUES

1. None 0

E. OTHER

1. Increased T-Avg Uncertainty for RTD Bypass Elimination 8

2.

+-3F T-Avg Window 24

3.

Increase of 2F to T-AvgWindow 16

4. AFW Actuation on SI Signal Only 5

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT Total = 1301°F Page 1 of 2

Large Break Peak Clad Temperature Margin Utilization ECCS EVALUATION MODEL REVISIONSIERRORS 10 CER 50.46 ANNUAL REPORT Evaluation Model: BASH FAH=1.65 Limiting Break Size: Cd = 0.6 Fuel: 17x17 V5H SGTP=13%

Clad Temnerature (F°)

ANALYSIS OF RECORD MARGIN ALLOCATIONS (Delta PCI)

A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1. None B. PLANNED PLANT CHANGE EVALUATIONS

1. None C. 2002 10 CFR 50A6 MODEL ASSESSMENTS (Permanent Assessments of PCT Margin)

1. None D. TEMPORARY ECCS MODEL ISSUES

1. None E. OTEIER

1. Increased T-Avg Uncertainty for RTD Bypass Elimination

2.

+/-3°F T-Avg Window

3.

Increase of 2°F to T-Avg Window

4. V5H AOR Liaiting Case wlIFMs Reanalysis

5.

Transition Core Penalty

6.

RFA Fuel Evaluation LICENSING BASIS PCr + MARGIN ALLOCATIONS PCT Total = 1951°F Page 2 of 2 FQ=2.5 3411 MWt 1889 0

0 0

0 5

15 10

-51 50 33