ML060940297

R. E. Ginna - 10CFR50.46 30 Day and Annual ECCS Report

ML060940297
Person / Time
Site:	Ginna
Issue date:	03/28/2006
From:	Korsnick M Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
1001531
Download: ML060940297 (5)

Text

Maria Korsnick R.E. Ginna Nuclear Power Plant. LLC Site Vice President 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maia.korsnick@costellation.com Constellation Energy Generation Group March 28, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 10CFR50.46 30 Dav and Annual ECCS Report

References:

(a)

Westinghouse Letter LTR-LIS-06-117,

Subject:

10CFR50.46 Annual Notification and Reporting for 2005, dated March 6, 2006.

(b)

Letter from Mary G. Korsnick (Ginna LLC) to Donna M. Skay (NRC), "License Amendment Request Regarding Revised Loss of Coolant Accident (LOCA)

Analyses - Changes to Accumulator, Refueling Water Storage (RWST), and Administrative Control Technical Specifications", dated April 29, 2005.

In accordance with the requirements in 10CFR50.46 paragraph (a)(3)(ii), this 30 day and annual Emergency Core Cooling System (ECCS) report is hereby submitted by R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC).

Westinghouse, the provider of loss of coolant accident (LOCA) analysis services for the R.E. Ginna Nuclear Power Plant, has provided an update to the peak cladding temperature (PCT) margin in Reference (a). A summary of the cumulative PCT changes can be found in Attachment 1 to this letter.

The large-break LOCA PCT has increased by 130F since the last annual report. The large-break LOCA PCT is currently at 21000F.

The small-break LOCA PCT has not changed since the last annual report. The small-break LOCA PCT remains at 1381 0F. Because the cumulative sum of the absolute magnitudes of the effects on the small-break LOCA PCT remain greater than 50'F, the changes conservatively qualify as being significant as defined in 10CFR50.46(a)(3)(i). Consequently, the cumulative changes are being reported in this 30 day report.

The small-break LOCA PCT value determined in the analysis of record, when combined with all PCT margin allocations, remains over 800'F below the 10CFR50.46 acceptance criteria of 2200'F. As such, no reanalysis is currently planned to address the specific issues raised in Attachment 1. Ginna LLC has previously submitted (Reference (b)) new large-break LOCA and small-break LOCA analyses in support of the planned power uprate of the facility.

O/53/

If you should have any questions regarding this submittal, please contact Robert Randall at (585) 771-3734.

Very truly you s, Mary G. Korsnick

Attachment:

LOCA PCT Summary, 2006 Update cc:

S. J. Collins, NRC P. D. Milano, NRC Resident Inspector, NRC

ATTACHMENT (1)

LOCA PCT

SUMMARY

2006 UPDATE

ATTACHMENT 1 LOCA PCT

SUMMARY

Large-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model:

FQ = 2.45 UPI SECY FA H= 1.75 Fuel:

OFA SGTP = 15%

A.

Analysis of Record (3/03) (effective 6/03)

B.

2004 10CFR50.46 Model Assessments

1. None PCT = 20870F APCT = 00F C.

2005 10CFR50.46 Model Assessments

1. SECY Cold Leg Nozzle Expansion D.

Other Margin Allocations

1. None APCT = 13'F APCT = 00F Licensing Basis PCT = 2100°F

A.

B.

C.

D.

E.

F.

G.

H.

I.

J.

K.

L.

M.

N.

ATTACHMENT 1 LOCA PCT

SUMMARY

Small-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model:

NOTRUMP FQ = 2.50 F, H,= 1.75 Analysis of Record (6/95) (effective 6/96) 1995 10CFR50.46 Model Assessments

1. NOTRUMP Specific Enthalpy Error

2. SALIBRARY Double Precision Errors 1996 10CFR50.46 Model Assignments

1. SBLOCA Fuel Rod Initialization Error 1997 10CFR50.46 Model Assessment

1. None 1998 10CFR50.46 Model Assessments

1. None 1999 10CFR50.46 Model Assessments

1. None 2000 10CFR50.46 Model Assessments

1. NOTRUMP - Mixture Level Tracking /

Region Depletion Errors 2001 10CFR50.46 Model Assessments

1. None 2002 10CFR50.46 Model Assessments

1. None 2003 10CFR50.46 Model Assessments

1. NOTRUMP - Bubble Rise /

Drift Flux Model Inconsistencies 2004 10CFR50.46 Model Assessments

1. None 2005 10CFR50.46 Model Assessments

1. None Ginna Evaluations

1. AnnularAxial Pellets (1997 evaluation, SEV-1108)

Other Margin Allocations

1. None Fuel:

OFA SGTP= 15%

APCT = 1308WF APCT = 20'F APCT = -15 0F APCT= 10F APCT = 0°F APCT = 0°F APCT = 0°F APCT= 13°F APCT = 0°F APCT = 0°F APCT = 35°F APCT = OF APCT = 0°F APCT = 10°F APCT = 0°F PCT = 1381°F Licensing Basis