NLS2020001, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2019

Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2019

ML20036C961
Person / Time
Site:	Cooper
Issue date:	01/20/2020
From:	Dewhirst L Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2020001
Download: ML20036C961 (4)

Text

H Nebraska Public Power District Always there when you need us NLS2020001 50.46(a)(3 )(ii)

January 20, 2020 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2019 Cooper Nuclear Station, Docket No. 50-298, DPR-46

Reference:

Letter from Jim Shaw, Nebraska Public Power District, to U.S. Nuclear Regulatory Commission, dated January 11, 2019, "Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2018"

Dear Sir or Madam:

The purpose of this letter is to submit the 2019 annual report of changes and errors in the Emergency Core Cooling System (ECCS) evaluation models pursuant to 10 CFR 50.46(a)(3)(ii) for Cooper Nuclear Station (CNS).

Per the reference letter, Nebraska Public Power District previously reported errors/changes in the ECCS evaluation models for GE14 and GNF2 fuel. For GNF2 fuel these errors continued to apply to the ECCS evaluation methodologies for 2019. The last GE14 fuel was discharged from the reactor at the end of Cycle 30 (September 2018), therefore no data for the GE14 fuel type is included in this letter. There was one zero-degree error for the GNF2 fuel type reported in 2019 applicable to the licensing basis peak clad temperature (PCT). CNS continues to comply with the PCT limit of 2200°F specified in 10 CFR 50.46(b)(1 ).

Attachment 1 to this letter itemizes the changes/errors in the ECCS evaluation models that remained applicable in 2019 and Attachment 2 provides data that demonstrates compliance with the ECCS performance requirements of 10 CFR 50.46.

This letter makes no regulatory commitments.

If you have any questions regarding this report, please contact Stephen Luther, Engineer, at (402) 825-5267.

~i-...-,rr1a D hirst Regulatory Affairs & Compliance Manager COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

NLS2020001 Page 2 of2

/tf Attachments: 1) Changes/Errors in Emergency Core Cooling System Evaluation Models Applicable in 2019

2) 10 CFR 50.46 Criteria in Emergency Core Cooling System Evaluation Models for 2019 cc: Regional Administrator w/attachments USNRC - Region IV Cooper Project Manager w/attachments USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/attachments USNRC-CNS NPG Distribution w/attachments CNS Records w/attachments

NLS2020001 Page 1 of 1 Changes/Errors in Emergency Core Cooling System Evaluation Models Applicable in 2019 GNF2 Fuel GE Hitachi Date Subject PCT Impact 10 CFR 50.46 Notification Letter 2017-01 6/12/17 GNF2 Lower Tie -20°F Plate Leakage 2017-02 8/2/17 Fuel Rod Plenum ooF Temperature Update 2019-05 11/1/19 SAFER Lower Limit oop on Differential Pressure for Bypass Leakage Total = -20°F

NLS2020001 Page 1 of 1 10 CFR 50.46 Criteria in Emergency Core Cooling System Evaluation Models for 2019 Fuel Type Licensing Basis PCT Local Oxidation Core-Wide Metal-Water Reaction GNF2 2130°F <6.00% <0.10%