NL-17-2095, Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package

Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the Ast. TSTF-448 and TSTF-312 Amendment Package

ML17352B231
Person / Time
Site:	Farley
Issue date:	12/18/2017
From:	Wheat J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-2095
Download: ML17352B231 (3)

Text

~ Southern Nuclear Regulatory Affairs 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 5000 tel DEC 1 8 2017 205 992 7601 fax Docket Nos.: 50-348 NL-17-2095 50-364 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Supplement Submittal of Corrected Technical Specification Definition of Iodine 1-131 for the AST. TSTF- 448 and TSTF- 312 Amendment Package Ladies and Gentlemen:

By letter dated November 22, 2016, Southern Nuclear Operating Company (SNC) requested the Nuclear Regulatory Commission (NRC) review and approval of proposed revisions to the licensing basis of FNP that support a full scope application of an Alternative Source Term (AST) methodology. This letter submits the corrected Farley Nuclear Plant (FNP) Technical Specification (TS) definition of Dose Equivalent 1-131.

The definition in the current FNP TS is revised to match the industry standard definition.

Enclosure 1 contains the corrected Technical Specification page.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the

\$~day of December 2017.

~.-c~

Ju~Wheat Nuclear Licensing Manager JTW/NDJ/CG

Enclosure:

Corrected Technical Specification Page for the AST, TSTF-448 and TSTF-312 Amendment Package cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054

Joseph M. Farley Nuclear Plant Unit 1 and 2 Enclosure Supplemental Submittal of Corrected Technical Specification Page for the AST, TSTF-448 and TSTF-312 Amendment Package

Definitions 1.1 1.1 Definitions CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same committed effective dose equivalent (CEDE) as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The CEDE dose conversion factors used to determine the DOSE EQUIVALENT 1-131 shall be performed using Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

!::-AVERAGE 1:: shall be the average (weighted in proportion to the DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total non iodine activity in the coolant.

Farley Units 1 and 2 1.1-2 Amendment No. 216 (Unit 1)

Amendment No. 213 (Unit 2)