ML15041A723

Donald C. Cook Nuclear Plant, Unit 2, Correction of Technical Specification Typographical Error Incurred During License Amendment No. 304

ML15041A723
Person / Time
Site:	Cook
Issue date:	02/19/2015
From:	Chawla M L Plant Licensing Branch III
To:	Weber L J Indiana Michigan Power Co
Chawla M L
References
TAC MF5673
Download: ML15041A723 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 February 19, 2015

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNIT 2 -CORRECTION OF TECHNICAL SPECIFICATION TYPOGRAPHICAL ERROR INCURRED DURING LICENSE AMENDMENT NO. 304 (TAC NO. MF5673)

Dear Mr. Weber:

By letter dated March 22, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13046A114), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 320 and 304 to Renewed Facility Operating License Nos. DPR-58 and DPR-74 for Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. The amendments modified the technical specifications (TSs) to adopt Technical Specifications Task Force (TSTF) Change Traveler TSTF-510.

On February 2, 2015, the NRC was notified by letter from Michael Scarpello, Regulatory Affairs Manager (ADAMS Accession No. ML 15035A065), that errors had been identified page 5.6-4 of the TSs for CNP Unit 2. Specifically, an extraneous reference was listed under section 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued).

Also, in Section 5.6.6 Post Accident Monitoring Report, "Condition B or G of LCO 3.3.3" was incorrectly written as "Condition B or H of LCO 3.3.3." Condition H of LCO 3.3.3 does not exist in the CNP Unit 2 TSs. Both errors were introduced during the issuance of License Amendment No. 304. The NRC staff has determined that these were inadvertent typographical errors and are entirely editorial in nature. The proposed corrections do not change any of the conclusions in the safety evaluation associated with Amendment No. 304 for CNP Unit 2, and do not affect the associated notice to the public. Please find enclosed the replacement page.

L. Weber If you have any questions regarding this matter, please contact me at (301) 415-8371.

Docket No. 50-316

Enclosure:

Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Corrected Pages to License Amendment No. 304 cc w/encl: Distribution via ListServ ENCLOSURE DONALD C. COOK NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-316 CORRECTED PAGES TO LICENSE AMENDMENT NO. 304 TECHNICAL SPECIFICATIONS PAGE 5.6-4

5.6 Reporting

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

Reporting Requirements 5.6 7. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," (Westinghouse Proprietary);

and 8. WCAP-12610-P-A

& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOŽ," July 2006 (Westinghouse Proprietary)

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 SDM, 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 Post Accident Monitoring Report When a report is required by Condition B or G of 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 inoperabi!ity, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status. 5.6.7 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.7, Steam Generator (SG) Program. The report shall include: a. The scope of inspections perlormed on each SG, b. Degradation mechanisms found, c. Nondestructive examination techniques utilized for each degradation mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, e. Number of tubes plugged during the inspection outage for each degradation, f. The number and percentages of tubes plugged to date, and the effective plugging percentage in each generator, and Cook Nuclear Plant Unit 2 5.6-4 Amendment No. 2-99, :rnJ, 2+9, .200, Corrected by letter of 2119/15 L. Weber If you have any questions regarding this matter, please contact me at (301) 415-8371.

Docket No. 50-316

Enclosure:

Sincerely, IRA/ Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Corrected Pages to License Amendment No. 304 cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-1 r/f RidsNrrDorllpl3-1 Resource RidsNrrPMDCCook Resource RidsNrrLAMHendersonResource RidsAcrsAcnw_MailCTRResource RidsRg n3MailCenterResou rce RecordsAmend Resource ADAMS Accession No.: ML 15041A723 OFFICE LPL3-1/PMiT LPL3-1/PM LPL3-1/LA DSS/STSB/BC NAME ADietrich MChawla MHenderson RElliott DATE 2/10/2015 02/11/2015 02/12/2015 2/19/2015 OFFICIAL RECORD COPY LPL3-1/BC LPL3-1/PM DPelton MChawla 02/19/2015 02/19/2015