RA-13-056, CFR 50.46 Annual Report

CFR 50.46 Annual Report

ML13151A450
Person / Time
Site:	Oyster Creek
Issue date:	05/31/2013
From:	David Helker Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-13-056
Download: ML13151A450 (7)

Text

10 CFR 50.46 RA-13-056 May31,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

10 CFR 50.46 Annual Report

Reference:

1) Letter from Michael D. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report,"

dated June 1, 2012 The purpose of this letter is to transmit the annual 10 CFR 50.46 reporting information for Oyster Creek Nuclear Generating Station (OCNGS). The previous annual 50.46 report for OCNGS (Reference 1) provided the cumulative Peak Cladding Temperature (PCT) errors for the most recent fuel designs.

Since the referenced annual report was issued, no vendor notifications of Emergency Core Cooling System (ECCS) model errors/changes that are applicable to OCNGS have been issued. Also, no ECCS-related changes or modifications have occurred at OCNGS that affect the assumptions of the ECCS analyses.

As noted in Attachment 2, new Loss of Coolant Accident (LOCA)/Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) analyses were performed for both GE11 and GNF2 fuel in support of operating Cycle 24. These analyses supersede all prior LOCA assessments. These reanalyses incorporate all ECCS/LOCA methodology errors and changes known/resolved at that time (as of October 2012). Accordingly, Attachment 2 reflects this reanalysis by stating that all errors and changes have been incorporated into the reanalysis.

Two attachments are included with this letter that provide the current OCNGS 10 CFR 50.46 status. Attachment 1, "Peak Cladding Temperature Rack-Up Sheet," provides information regarding the PCT for the limiting large break LOCA analysis evaluations for OCNGS. , "Assessment Notes," contains a detailed description for each change or error reported.

10 CFR 50.46 Annual Report May 31,2013 Page 2 There are no commitments contained in this letter. If you have any questions, please contact Tom Loomis at 610~765-5510.

Respectfully, David P. Helker Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Peak Cladding Temperature Rack-Up Sheet

2) Assessment Notes cc: W. Dean, USNRC Administrator, Region I J. Lamb, USNRC Senior Project Manager, OCNGS J. A. Kulp, USNRC Senior Resident Inspector, OCNGS

ATTACHMENT 1 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 31, 2013 Peak Cladding Temperature Rack-Up Sheet Oyster Creek Nuclear Generating Station

Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 31, 2013 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 1 of 2 PLANT NAME: Oyster Creek ECCS EVALUATION MODEL: SAFER/CORCUGESTR-LOCA REPORT REVISION DATE: 5/31113 CURRENT OPERATING CYCLE: 24 ANALYSIS OF RECORD Evaluation Model:

1. NEDC-23785-1-PA Rev. 1, "The GESTR*LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume II, SAFER - Long Term Inventory Model tor BWR Loss-Ot-Coolant Analysis," October 1984.

2. NEDC-30996P-A, "SAFER Model for Evaluation of Loss-ot-Coolant Accidents for Jet Pump and Non-jet Pump Plants, Volume I, SAFER - Long Term Inventory Model for BWR Loss-of-Coolant Analysis," October 1987.

3. NEDC-30996P-A, "SAFER Model for Evaluation of Loss-of-Coolant Accidents for Jet Pump and Non-jet Pump Plants, Volume II, SAFER Application Methodology for Non-jet Pump Plants," October 1987 (Non-jet Pump Plant - SAFER/CORCL).

4. NEDC-32950P, "Compilation of Improvements to GENE's SAFER ECCS-LOCA Evaluation Model," January 2000.

Calculations:

1. GE-NE-0000-0001-7486-01 P, "Oyster Creek Generating Station Loss-of-Coolant Accident Evaluation for GE11 ," GE Nuclear Energy, dated July 2002.

2. Report 0000-0098-3503-R2, "Oyster Creek Generating Station GNF2 ECCS-LOCA Evaluation," GEH Nuclear Energy, dated November 2010.

3. Report 0000-0138-9259-SRLR, "Supplemental Reload Licensing Report for Oyster Creek Reload 24 Cycle 24," dated October 2012.

Fuel: GE11/GNF2 Limiting Fuel Type: GE11/GNF2 Limiting Single Failure: ADS Valve Limiting Break Size and Location: 4.66 tf Double-Ended Guillotine (DEG) in a Recirculation Discharge Pipe Reference Peak Cladding Temperature (PCT) PCT = 2150°F

Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 31, 2013 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS B. CURRENT LOCA MODEL ASSESSMENTS New Analysis for Cycle 24 (See Note 1) ~PCT = OaF Total PCT Change from Current Assessments I~PCT = OaF Cumulative peT Change from Current Assessments I I~PCT I= OaF NET PCT (GE11/GNF2) 2150°F

ATTACHMENT 2 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 31, 2013 Assessment Notes Oyster Creek Nuclear Generating Station

Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 31, 2013 Attachment 2 Assessment Notes, OCNGS Page 1 of 1

1. New Analyses for Cycle 24 (Current LOCA Model Assessment)

Updated LOCAIMAPLHGR analyses were performed for both GE11 and GNF2 fuel in support of operating Cycle 24. These analyses maintained the calculated PCT at 2150°F and superseded all prior LOCA assessments. These analyses incorporated all ECCS/LOCA methodology errors and changes known/resolved at that time (as of October 2012).

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Reference:

GNF Report 0000-0138-9259-SRLR, "Supplemental Reload Licensing Report for Oyster Creek Reload 24 Cycle 24," dated October 2012)