ML021270329

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10CFR50.46 Annual ECCS Report
ML021270329
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/26/2002
From: Mecredy R
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, NRC/NRR/DLPM/LPD1
References
Download: ML021270329 (5)


Text

R f A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION & 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001

  • 716 546-2700 www.rge.com ROBERT C. MECREDY Vice President Nuclear Operations April 26, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Robert Clark Project Directorate I Washington, D.C. 20555

Subject:

1 OCFR50.46 Annual ECCS Report R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.

(a)

Westinghouse Letter RGE-02-002,

Subject:

I 0CFR50.46 Annual Notification and Reporting for 2001, dated March 1, 2002.

Dear Mr. Clark In accordance with the requirements in 1 OCFR50.46 paragraph (a)(3)(ii), this annual ECCS report is hereby submitted.

Westinghouse, the provider of LOCA analysis for the R. E. Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna Station (Reference a).

The large break LOCA PCT has increased 13 aF from the value previously reported due to an oxidation thickness input error (+ 15 a F) and the removal of reconstituted fuel assemblies from Cycle 30 (-2°F). The new large break LOCA PCT is 2166°F and is summarized in Attachment 1 to this letter.

The small break LOCA PCT has not changed since the last report (Reference a). The small break LOCA PCT remains at 1346 °F and is summarized in Attachment 1 to this letter.

Very truly yours, Robert C. Mecredy

/000 CC

Attachment cc:

Mr. Robert Clark (Mail Stop O-8-C2)

Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector

ATTACHMENT I LOCA PCT

SUMMARY

APRIL 2002 UPDATE

ATTACHMENT I LOCA PT

SUMMARY

Large Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:

FQ = 2.4 5 A.

Analysis of Record (5/95) (effective 6/96)

B.

1995 10CFR50.46 Model Assessments

1. Fixed heat transfer node assignment Error/Accumulator water injection error C.

1996 10CFR50.46 Model Assessments

1. None D.

1997 10CFR50.46 Model Assessment

1. Accumulator Initial Water Volume Restart Data Transportation Error Plant Specific Analytical Reassessment of 1995 Model Assessments
2. Accumulator Initial Water Vol. = 1125 ft3
3.

1 -D Transition Boiling Heat Transfer Error

4. Vessel Channel DX Error
5.

Input Consistency E.

1998 10CFR50.46 Model Assessments

1. None F.

1999 10CFR50.46 Model Assessments

1. None G.

2000 10CFR50.46 Model Assessments

1. 100 psig IFBA RIP Modeling Error
2. Channel Splitting Error H.

2001 10CFR50.46 Model Assessments

1. Oxidation Thickness Input Error I.

Ginna Evaluations

1. Service Water Temp. >_30' (1997 evaluation; SEV-1090)

J.

Other Margin Allocations

1. None UPI SECY FAH = 1.75 Licensing Basis Fuel:

OFA SGTP = 15%

PCT = 2051 ° F APCT= 48°F APCT = 0°F APCT = 58°F APCT = -25°F APCT = -13'F APCT = 18'F APCT = -41°F APCT = 0°F APCT =0F APCT = 2°F APCT = 52 0 F APCT-15'F APCT= 1VF APCT = O°F PCT = 2166OF Revision Date: 4/2002

ATTACHMENT I LOCA PT

SUMMARY

Small Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model:

FQ = 2.50 NOTRUMP FAH = 1.75 A.

Analysis of Record (6/95) (effective 6/96)

B.

1995 10CFR50.46 Model Assessments

1. Notrump Specific Enthalpy Error
2. SALEIBRARY Double Precision Errors C.

1996 10CFR50.46 Model Assignments

1. SBLOCA Fuel Rod Initialization Error D.

1997 10CFR50.46 Model Assessment

1. None E.

1998 1 OCFR50.46 Model Assessments

1. None F.

1999 10CFR50.46 Model Assessments

1. None G.

2000 10CFR50.46 Model Assessments

1. NOTRUMP - Mixture Level Tracking/ Region Depletion Errors H.

2001 10CFR50.46 Model Assessments

1. None I.

Ginna Evaluations

1. Annular Axial Pellets (1997 evaluation; SEV-1108)

J.

Other Margin Allocations

1. None Licensing Basis Fuel:

OFA SGTP = 15%

A PCT= 1308'F A PCT = 20'F APCT= -15'F APCT = 10°F APCT = 0°F APCT = 00 F APCT = 0oF APCT = 13'F APCT = 0°F APCT = 10°F APCT = 0°F PCT = 1346 0F Revision Date: 4/2002