RA-17-034, Transmittal of 10 CFR 50.46 Annual Report

Transmittal of 10 CFR 50.46 Annual Report

ML17143A301
Person / Time
Site:	Oyster Creek
Issue date:	05/23/2017
From:	David Helker Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-17-034
Download: ML17143A301 (6)

Text

Exelon Generation ~ 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp com 10 CFR 50.46 RA-17-034 May 23, 2017 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:

Letter from David P. Helker, Exelon Generation Company, LLC, to U.S.

Nuclear Regulatory Commission, "1 O CFR 50.46 Annual Report," dated May 26, 2016 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 submitted on May 26, 2016 (Reference), 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. In addition, subsequent to the last referenced annual report, all GE11 fuel has been unloaded from the core.

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 Loss of Coolant Accident (LOCA) analysis evaluations for OCNGS. Attachment 2, "Assessment Notes," contains a detailed description for each change or error reported.

There are no commitments contained in this letter.

If you have any questions, please contact Richard Gropp at 610-765-5557.

Respectfully, 9--# ~ ~

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

2) Assessment Notes cc: USNRC Administrator, Region I USNRC Senior Project Manager, OCNGS 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 23, 2017 Peak Cladding Temperature Rack-Up Sheet Oyster Creek Nuclear Generating Station

Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 1 of 2 PLANT NAME: Oyster Creek Nuclear Generation Station (OCNGS)

ECCS EVALUATION MODEL: SAFER/CORCUPRIME (GNF2)

REPORT REVISION DATE: 05/23/2017 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD CALCULATIONS Calculations:

1. Report 0000-0098-3503-R2, Revision 2, "Oyster Creek Generating Station GNF2 ECCS-LOCA Evaluation," GEH Nuclear Energy, dated November 201 O

2. Report 002N6964, Revision 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016 Fuel: GNF2 Limiting Fuel Type: GNF2 Limiting Single Failure: ADS Valve Limiting Break Size and Location: 4.66 tt2 Double-Ended Guillotine (DEG) in a Recirculation Discharge Pipe Reference Peak Cladding Temperature (PCT} for GNF2 Fuel: 2175°F

Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS None GNF2 t:lPCT =0°F NET PCT (GNF2) GNF2: 2175°F B. CURRENT LOCA MODEL ASSESSMENTS New Analysis for Cycle 26 (See Note 1) GNF2: LlPCT = 0°F Total PCT Chanqe from Current Assessments GNF2: LllPCT = 0°F Cumulative PCT Chanqe from Current Assessments GNF2: rlllPCTI = 0°F NET PCT GNF2: 2175°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 23, 2017 Assessment Notes Oyster Creek Nuclear Generating Station

Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2017 Attachment 2 Assessment Notes, OCNGS Page 1 of 1

1) Current LOCA Model Assessment A new LOCA/MAPLHGR analysis for fresh GNF2 fuel was performed for Cycle 26, and restated/confirmed the MAPLHGRs for the existing GNF2 fuel. This analysis maintained the licensing basis PCT at 2175°F and superseded all prior LOCA assessments. This analysis incorporated all ECCS/LOCA methodology errors and changes resolved at that time (as of August 2016). Since that time, no new vendor notifications of ECCS model error/changes have been reported.

[

Reference:

GNF Report 002N6964 Rev 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016.]