ML18302A256

Correction of Amendment No. 227 Adoption of TSTF-65-A, Revision 1

ML18302A256
Person / Time
Site:	Hatch
Issue date:	11/02/2018
From:	Hall J Plant Licensing Branch II
To:	Gayheart C Southern Nuclear Operating Co
Hall J
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ML18306A901	List: ML18302A256
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Download: ML18302A256 (4)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2018 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 - CORRECTION OF AMENDMENT NO. 227 RE: ADOPTION OF TSTF-65-A, REVISION 1

Dear Ms. Gayheart:

On January 13, 2017, the Nuclear Regulatory Commission (NRC) issued Amendment No. 227 (Agencywide Documents Access and Management System (ADAMS) Accession No.

ML16291A030) to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant (HNP) Unit No. 2. The amendment, among other things, made changes to the HNP Unit No. 2 Technical Specifications (TSs) to reflect the adoption of the Technical Specifications Task Force (TSTF) Traveler TSTF-65-A, Revision 1, "Use of Generic Titles for Utility Positions,"

(dated April 2, 1998, ADAMS Accession No. ML040080572).

By letter dated May 10, 2017 (ADAMS Accession No. ML17130A992), the Southern Nuclear Operating Company, Inc. (SNC) requested NRC approval of a correction of a typographical error in the HNP Unit No. 2 Technical Specifications. SNC stated that the error had been inadvertently introduced during the processing of Unit 2 License Amendment No. 227, and had removed a TS change approved in License Amendment No. 217 (dated January 6, 2015, ADAMS Accession No. ML14345A895). SNC further stated that this error was neither addressed in the notice to the public nor reviewed by the NRC, and thus falls within the scope of the guidance provided by SECY-96-238, "Proposed Guidance for Correction of Technical Specification Typographical Errors," dated December 17, 1996, ADAMS Accession No.

ML003754054).

The NRC staff has confirmed that Amendment No. 227 for HNP Unit No. 2 contained typographical errors on TS page 1.1-5 in the definition for "SHUTDOWN MARGIN (SOM),"

where the phrases "throughout the operating cycle" and "corresponding to the most reactive state," and the symbol "~" in front of the value "68°F" were removed. These changes had previously been explicitly approved by the NRC staff in Amendment No. 217. The NRC staff found that the errors originated from the licensee's application related to Amendment No. 227, (dated March 17, 2014, ADAMS Accession No. ML14076A141 ), and determined that these errors were inadvertently introduced and were not the subject of the amendment or the associated notice to the public. Therefore, consistent with NRC staff guidance dated January 16, 1997 (ADAMS Accession No. ML103260096), based on the NRC's policy established by SECY-96-238, these errors can be corrected by a letter to the licensee from the NRC staff.

C. A. Gayheart Enclosed please find the corrected HNP Unit No. 2 TS page 1.1-6 (please note that the definition for "SHUTDOWN MARGIN (SDM)" was moved to TS page 1.1-6 in subsequent Amendment No. 235, dated May 31, 2018, ADAMS Accession No. ML18123A368). This correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 227.

Sincerely, James R. Hall, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-366

Enclosure:

As stated cc: Listserv

Definitions 1.1 1.1 Definitions (continued)

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 14, Initial Tests and Operation, of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that provides the reactor vessel TEMPERATURE pressure and temperature limits, including heatup and cooldown rates, for LIMITS REPORT the current reactor vessel fluence period. These pressure and (PTLR) temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.

RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor POWER (RTP) coolant of 2804 Mwt.

REACTOR The RPS RESPONSE TIME shall be that time interval from when the PROTECTION monitored parameter exceeds its RPS trip setpoint at the channel SYSTEM (RPS) sensor until de-energization of the scram pilot valve solenoids. The RESPONSE TIME response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SHUTDOWN SDM shall be the amount of reactivity by which the reactor is subcritical MARGIN (SDM) or would be subcritical throughout the operating cycle assuming that:

a. The reactor is xenon free;

b. The moderator temperature is .i!: 68°F, corresponding to the most reactive state; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency , so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

(continued)

HATCH UNIT2 1.1-6 Amendment No. 235

ML18302A256 OFFICE NRR/D0RL/LPL2-1 /PM NRR/D0RL/LPL2-1/LA NRR/D0RL/LPL2-1/BC NRR/D0RL/LPL2-1/PM NAME RHall KGoldstein MMarkley RHall (MMarkley for)

DATE 10/30/18 10/30/18 11/02/18 11/02/18