ML19112A311

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Correction Letter to License Amendment Nos. 313 and 292 Removal of Heaters from Ventilation System Technical Specifications
ML19112A311
Person / Time
Site: Mcguire, McGuire  Duke energy icon.png
Issue date: 04/24/2019
From: Michael Mahoney
Plant Licensing Branch II
To: Capps S
Duke Energy Carolinas
Mahoney M, NRR/DORL/LPL2-1, 415-3867
References
EPID L-2018-LLA-0134
Download: ML19112A311 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 24, 2019 Mr. Steven Capps Senior Vice President - Nuclear Operation Duke Energy Carolinas, LLC.

526 South Church Street, EC-07H Charlotte, NC 28202

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - CORRECTION LETTER TO LICENSE AMENDMENT NOS. 313 AND 292 RE: REMOVAL OF HEATERS FROM VENTILATION SYSTEM TECHNICAL SPECIFICATIONS (EPID NO. L-2018-LLA-0134)

Dear Mr. Capps:

By letter dated April 18, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19050A297), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 313 and 292 to Renewed Facility Operating License Nos. NPF-9 and NPF-17 for the McGuire Nuclear Station (McGuire), Units 1 and 2, respectively. The amendments changed the Technical Specifications (TS) in response to Duke Energy Carolinas application dated May 10, 2018.

The amendments removed ventilation heaters from TSs for McGuire, Units 1 and 2. The amendments issued on April 18, 2019 also revised the TSs for Catawba Nuclear Station, Units 1 and 2; Shearon Harris Nuclear Power Plant, Unit No. 1; and H. B. Robinson Steam Electric Plant, Unit No. 2.

Subsequent to the issuance of the amendments, the NRC staff discovered a typographical error on one of the TS pages for McGuire. McGuire TS page numbered as 5.6-5 should have been 5.6-4 (information on the page is correct). This error is administrative in nature and correcting it does not affect the safety evaluation for Amendment Nos. 313 and 292 or the no significant hazards consideration published in the Federal Register.

Enclosed is the revised TS page 5.6-4. Please replace the corresponding page (page 5.6-5) issued by Amendment Nos 313 and 292 for McGuire, Units 1 and 2.

S. Capps If you have any questions regarding this matter, I may be reached at (301) 415-3867 or via e-mail at michael.mahoney@nrc.gov.

Si~

Michael Mahoney, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosure:

Revised Technical Specification Page cc: Listserv

ENCLOSURE DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 REPLACEMENT TS PAGE FOR AMENDMENT NOS. 313 AND 292 DOCKET NOS. 50-369 AND 50-370

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

14. DPC-NE-2009-P-A, 'Westinghouse Fuel Transition Report," (DPC Proprietary).
15. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (Yj_ Proprietary).
16. DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASM0-4/SIMULATE-3 MOX," (DPC Proprietary).
17. DPC-NE-1007-PA, "Conditional Exemption of the EOC MTC Measurement Methodology" (Duke and Westinghouse Proprietary).
18. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995. (Westinghouse Proprietary).
19. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO' ," July 2006. (Westinghouse Proprietary).

The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Not Used.

5.6.7 PAM Report When a report is required by LCO 3.3.3, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

McGuire Units 1 and 2 5.6-4 Amendment Nos. 313/292

ML19112A311 OFFICE NRR/DORULPL2-1 /PM NRR/DORL/LPL2-1 /LA NRR/DORULPL2-1 /BC NRR/DORULPL2-1 /PM NAME MMahoney KGoldstein MMarkley MMahoney DATE 4/24/19 04/23/19 4/24/19 4/24/19