ML16027A177

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Correction of Technical Specification Typographical Error Incurred During License Amendment No. 327
ML16027A177
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/11/2016
From: Dietrich A
Plant Licensing Branch III
To: Gebbie J
Indiana Michigan Power Co, Nuclear Generation Group
Allison Dietrich
References
CAC MF7279, TAC MF7279
Download: ML16027A177 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 11, 2016 Mr. Joel P. Gebbie Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNIT 1 - CORRECTION OF TECHNICAL SPECIFICATION TYPOGRAPHICAL ERROR INCURRED DURING LICENSE AMENDMENT NO. 327 (CAC NO. MF7279)

Dear Mr. Gebbie:

By letter dated April 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15076A226), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 327 and 310 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 specification (TS) requirements for unavailable barriers by adding limiting condition for operation (LCO) 3.0.8, consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-427.

By letter dated January 15, 2016 (ADAMS Accession No. ML16020A451), from Michael Scarpello, Regulatory Affairs Manager, the NRC was notified that errors had been identified on TS pages 3.0-2 and 3.0-3 for CNP Unit 1. Specifically, the headers on both pages read "SR

[Surveillance Requirement] Applicability 3.0." The headers should read "LCO Applicability 3.0."

The NRC staff has reviewed the relevant documents and confirmed that the errors can be specifically traced to the issuance of Amendment No. 327 for CNP Unit 1.

The NRC staff has determined that these were typographical errors inadvertently introduced when the NRC issued Amendment No. 327, and are entirely editorial in nature. The errors were not addressed or contained in the notice to the public and were not reviewed by the staff. The proposed corrections do not change any of the conclusions in the safety evaluation associated with Amendment No. 327 for CNP Unit 1, and do not affect the associated notice to the public.

Please find enclosed the replacement pages.

J. Gebbie If you have any questions regarding this matter, please contact me at (301) 415-2846.

s7(v/)JU Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315

Enclosure:

Corrected Pages to License Amendment No. 327 cc w/encl: Distribution via ListServ

ENCLOSURE DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-315 CORRECTED PAGES TO LICENSE AMENDMENT NO. 327 TECHNICAL SPECIFICATIONS PAGES 3.0-2 AND 3.0-3

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8, "PHYSIC TESTS Exceptions - MODE 2,"

allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support Cook Nuclear Plant Unit 1 3.0-2 Amendment No.~. 327

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.8 (continued) function(s), and risk is assessed and managed. This specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.

If the required OPERABLE train or subsystem becomes inoperable while this specification is in use, it must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the provisions of this specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s).

At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.

Cook Nuclear Plant Unit 1 3.0-3 Amendment No. ~. 327

ML16027A177 OFFICE DORL/LPL3-1/PM DORL/LPL3-1/LA OGC NAME ADietrich MHenderson SF owler DATE 01 /28/16 01/26/16 02/4/16 OFFICE DORL/LPL3-1/BC DORL/LPL3-1/PM NAME DWrona ADietrich DATE 02/10/16 02/11/16