L-16-096, Transmittal of 2015 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models and Commitment Change Related to Revised Peak Cladding Temperature Analysis

Transmittal of 2015 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models and Commitment Change Related to Revised Peak Cladding Temperature Analysis

ML16162A205
Person / Time
Site:	Beaver Valley
Issue date:	06/09/2016
From:	Richey M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-16-096
Download: ML16162A205 (5)

Text

FENOC' Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Marty L. Richey 724-682-5234 Site Vice President Fax: 724-643-8069 June 9, 2016 L-16-096 10 CFR 50.46(a)(3)(ii)

ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 2015 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models and Commitment Change Related to Revised Peak Cladding Temperature Analysis In accordance with Title 10 of the Code of Federal Regulations, Part 50, Section 50.46(a)(3)(ii), FirstEnergy Nuclear Operating Company (FENOC) provides the attached report as the 2015 annual notification of changes or errors in emergency core cooling system evaluation models or the application of the models for the Beaver Valley Power Station, Unit Nos. 1 (BVPS-1) and 2 (BVPS-2). Current information for both large and small break loss-of-coolant accident (LOCA) transients is provided to satisfy 10 CFR 50.46 reporting requirements.

Attachments 1 and 2 provide a summary list and description of each change or error in the acceptable evaluation models or the application of the models that affects the peak fuel cladding temperature (PCT) calculation for various LOCA transients, as well as the estimated PCT effects of the change or error.

The changes or errors communicated to FENOC since the previous annual report are listed in the attachments and result in PCTs for the large and small break LOCA transients as follows:

BVPS-1 large break LOCA- 1840°F BVPS-1 small break LOCA- 1895°F BVPS-2 large break LOCA- 1839°F BVPS-2 small break LOCA- 191?°F By letter dated March 16, 2012, FENOC established a regulatory commitment to submit to the Nuclear Regulatory Commission (NRC) for review and approval large break LOCA (LBLOCA) analyses that apply NRG-approved methods that include the effects of fuel pellet thermal conductivity degradation (TCD) on or before December 15, 2016.

FENOC is revising this commitment to change the specific calendar due date to one

Beaver Valley Power Station, Unit Nos. 1 and 2 L-16-096 Page 2 based on NRC approval of the related evaluation methodologies that have been previously submitted to the NRC for review and approval. Specifically, WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)" and WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to Full Spectrum of Break Sizes (Full Spectrum LOCA Methodology)," are currently with the NRC for review. The commitment due date is being revised to reflect an event based due date as shown in Attachment 3. The revised due date is to be within one year after NRC approval of the fuel performance analysis (PAD5) and LBLOCA evaluation model (full spectrum LOCA) methodologies.

There are no new regulatory commitments contained in this submittal, although the due date of one regulatory commitment has been revised. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.

Sincerely, 10- t,p Marty L. Riche Attachments:

1 Summary of Peak Fuel Cladding Temperature (PCT) Effects for Beaver Valley Power Station (BVPS) Loss-of-Coolant Accident (LOCA) Transients 2 Descriptions of Emergency Core Cooling System (ECCS) Evaluation Model Changes or Errors 3 Regulatory Commitment List cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Attachment 1 L-16-096 Summary of Peak Fuel Cladding Temperature (PCT) Effects for Beaver Valley Power Station (BVPS) Loss-of-Coolant Accident (LOCA) Transients Page 1 of 1 Beaver Valle Power Station Unit No. 1 BVPS-1 Lar e Break LOCA Description PCT Effect Attachment 2 Description None- Not A licable NA NA NA BVPS-1 Small Break LOCA Description PCT Effect Attachment 2 (OF) Description General Computer Code Maintenance 0 Paqe 1 Beaver Valley Power Station Unit No. 2 (BVPS-2) Large Break LOCA Description PCT Effect Attachment 2 (oF) Description None- NA NA NA BVPS-2 Small Break LOCA Description PCT Effect Attachment 2 (OF) Description General Computer Code Maintenance 0 Paqe 1

Attachment 2 L-16-096 Descriptions of Emergency Core Cooling System (ECCS) Evaluation Model Changes or Errors Page 1 of 1 GENERAL COMPUTER CODE MAINTENANCE

Background

Various changes have been made to enhance the usability of computer codes and to streamline future analyses. Examples of these changes include: modifying input variable definitions, units, and defaults; improving the input diagnostic checks; enhancing the computer code output; optimizing active coding; and eliminating inactive coding. These changes represent discretionary changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451, "Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting," October 1992.

Affected Evaluation Models 1985 Westinghouse Small Break Loss of Coolant Accident (LOCA) Evaluation Model with NOTRUMP (a nodal transient small break and general network computer code)

(Applicable to BVPS-1 and BVPS-2)

Estimated Effect The nature of these changes leads to an estimated peak fuel cladding temperature (PCT) impact of 0°F for both BVPS-1 and BVPS-2.

Attachment 3 L-16-096 Regulatory Commitment List Page 1 of 1 The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for the Beaver Valley Power Station, Unit Nos. 1 and 2 in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not Regulatory Commitments. Please notify Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810 of any questions regarding this document or associated Regulatory Commitments.

Reaulatorv Commitment (no chanae) Due Date <revised)

1. Submit to the NRG for review and Within one year after NRG approval of approval LBLOCA analyses that apply the fuel performance analysis (PAD5)

NRG-approved methods that include the and LBLOCA evaluation model (full effects of fuel pellet TCD. spectrum LOCA) methodologies.