SBK-L-04020, Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

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

ML042160295
Person / Time
Site:	Seabrook
Issue date:	07/27/2004
From:	Peschel J Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-04020
Download: ML042160295 (4)

Text

FPL Energy Seabrook Station FPL Energvy PO. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 JUL 2 7 2004 Docket No. 50-443 SBK-L-04020 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 (FPL Energy Seabrook) submits a tabulation of the current Small Break and Large Break LOCA PCT margin utilization tables applicable to Seabrook Station. The Small Break LOCA utilization table is consistent with the table provided in FPL Energy Seabrook's 2002 10 CFR 50.46 Report, NYN-03046, dated June 3, 2003. The Large Break LOCA PCT decreased 50'F to a new PCT value of 1901'F as the result of the removal of the 50'F Transition Core Penalty. Seabrook Station is now operating with a full core of fuel with Intermediate Flow Mixing grids.

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

Very truly yours, FPL Energy Seabrook, LLC

/ares M. Peschel egulatory Programs Manager cc: H. J. Miller, NRC Region I Administrator S. P. Wall, NRC Project Manager, Project Directorate 1-2 G.T. Dentel, NRC Senior Resident Inspector an FPL Group company

ENCLOSURE TO SBK-1-04020 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 FAH=1.65 SGTP=13% 3411 MWt Limiting Break: 4 inch Clad Temperature (OF)

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 Improved 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 SBLOCTA 13 Error Corrections

8. NOTRUMP Specific Enthalpy Error 20

9. SBLOCTA Fuel Rod Initialization Error 10

10. NOTRUMP Mixture Level Tracking / 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. 200210 CFR 50.46 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. +/-30F T-Avg Window 24

3. Increase of 20F to T-AvgWindow 16

4. AFWN Actuation on SI Signal Only 5 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT Total = 1301'F Page 1 of 2

I Large Break Peak Clad Temperature Margin Utilization ECCS EVALUATION MODEL REVISIONS/ERRORS 10 CFR 50.46 ANNUAL REPORT Evaluation Model: BASH Fuel: 17x17V5H FQ=2.5 F A H=1.65 SGTP=13% 3411 MWt Limiting Break Size: Cd = 0.6 Clad Temperature (FP)

ANALYSIS OF RECORD MARGIN ALLOCATIONS (Delta PCI) 1889 A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1. None 0 B. PLANNED PLANT CHANGE EVALUATIONS

1. None 0 C. 2002 10 CFR 50.46 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 5

2. +/-3 0F T-Avg Window 15

3. Increase of 2 0F to T-Avg Window 10

4. V5H AOR Limiting Case w/IFMs Reanalysis -51

5. RFA Fuel Evaluation 33 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT Total = 1901'F Page 2 of 2