ML20155K702

Correction to Amendment No. 265 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-564 Revision 2, Safety Limit MCPR

ML20155K702
Person / Time
Site:	Cooper
Issue date:	06/10/2020
From:	Thomas Wengert Plant Licensing Branch IV
To:	Dent J Nebraska Public Power District (NPPD)
Wengert T, NRR/DORL/LPLIV, 415-4037
References
EPID L-2019-LLA-0127
Download: ML20155K702 (5)

Text

June 10, 2020 Mr. John Dent, Jr.

Vice President and Chief Nuclear Officer Nebraska Public Power District 72676 648A Avenue P.O. Box 98 Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - CORRECTION TO AMENDMENT NO. 265 RE: ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE (TSTF)

TRAVELER TSTF-564 REVISION 2, SAFETY LIMIT MCPR (EPID L-2019-LLA-0127)

Dear Mr. Dent:

On May 12, 2020 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML19329B151), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 265 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment was issued in response to Nebraska Public Power Districts (the licensees) application dated May 23, 2019 (ADAMS Accession No. ML19171A266).

The amendment revised the CNS Technical Specifications (TSs) based on Technical Specifications Task Force (TSTF) Traveler TSTF-564, Revision 2, Safety Limit MCPR

[Minimum Critical Power Ratio], dated October 24, 2018 (ADAMS Accession No. ML18297A361). The amendment revised the CNS TS Safety Limit 2.1.1.2 and TS 5.6.5, Core Operating Limits Report (COLR).

During the licensees review of the issued amendment, it identified an administrative formatting error on TS page 5.0-21, which was issued with the amendment. Specifically, the break line at the bottom of the page and the (continued) designation were inadvertently removed from the TS page.

The NRC staff agrees that break line and designation should not have been removed from TS page 5.0-21. The enclosure to this letter contains revised TS page 5.0-21. The proposed revision does not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public. Please replace TS page 5.0-21 to Amendment No. 265 with the enclosed page.

J. Dent, Jr. The NRC staff regrets any inconvenience this may have caused. If you have any questions, please contact me at 301-415-4037 or via e-mail at Thomas.Wengert@nrc.gov.

Sincerely,

/RA/

Thomas J. Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298

Enclosure:

Corrected TS page 5.0-21 cc: Listserv

ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 5.0-21 TO AMENDMENT NO. 265 NEBRASKA PUBLIC POWER DISTRICT RENEWED FACILITY OPERATING LICENSE DPR-46 COOPER NUCLEAR STATION DOCKET NO. 50-298

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODAM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 (Deleted) 5.6.5 Core Operating Limits Report (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rates for Specifications 3.2.1 and 3.7.7.

2. The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7, and MCPR99.9% for Specification 3.2.2.

3. The Linear Heat Generation Rates for Specifications 3.2.3 and 3.7.7.

4. The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1.

5. The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (Revision specified in the COLR).

______________________________________________________________ (continued)

Cooper 5.0-21 Amendment No. 265

ML20155K702 *by e-mail OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*

NAME TWengert PBlechman JDixon-Herrity TWengert DATE 6/8/2020 6/4/2020 6/9/2020 6/10/2020