ML16175A320

Cooper - Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications

ML16175A320
Person / Time
Site:	Cooper
Issue date:	06/13/2016
From:	Limpias O A Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2016038
Download: ML16175A320 (6)

Text

NLS2016038 June 13, 2016 Nebraska Public Power District Always there when you need us U.S. Nuclear Regulatory Commission Attention: Document Control Desk

• Washington, D.C. 20555-0001

Subject:

Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications Cooper Nuclear Station, Docket No. 50-298, DPR-46 50.90

Reference:

Letter from Oscar A. Limpias, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated September 8, 2015, "License Amendment Request to Replace Figure with Text in Technical Specifications"

Dear Sir or Madam:

The purpose of this letter is for the Nebraska Public Power District to correct a typographical error identified during the review of the referenced submittal. The proposed licensed amendment request contains a typographical error in Technical Specifications (TS) Section 1.1, Definitions. Specifically, DOSE EQUIVALENT 1-131 should be DOSE EQUIVALENT I-131. Attachment 1 provides the marked up TS page. Attachment 2 provides the final typed format TS page to be issued with the amendment. The editorial change submitted in this letter does not affect the technical or regulatory analysis included in .the referenced submittal. This letter contains no regulatory commitments. Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

• I declare under penalty of perjury that the foregoing is true and correct. Executed on: O((:J 3 / I (,p r 1 (Date) COOPER NUCLEAR STATION P.O .. Box 98 /Brownville, NE 68321-0098 Telephone: (402) 825-3811 /Fax: (402) 825-5211 www.nppd.com NLS2016038 Page 2 of2 /jo Attachments: 1. Proposed Technical Specifications Revision (Markup) 2. Proposed Technical Specifications Revision (Final Typed Format) cc: Regional Administrator w/ attachments USNRC -Region IV Cooper Project Manager w/ attachments USNRC -NRR Project Directorate IV-1 Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments CNS Records w/ attachments NLS2016038 Attachment 1 Page 1 of2 Attachment 1 Proposed Technical Specifications Revision (Markup) Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3

1. 1 Definitions rl-131, Definitions 1.1 DOSE EQUIVALENT-4-4-a+ {continued) LEAKAGE LINEAR HEAT GENERATION. 1-133, I* 134, and 1-135 actually present. The DOSE EQUIVALENT 1-131 concentration is calculated as follows: DOSE EQUIVALENT 1-131 = (1-131) + 0.0060 (1-132) + 0.17 (1-133) + 0.0010 (1-134) + 0.029 {1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall. or vessel wall. The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, {continued). Cooper 1.1-3 Amendment No. 251-NLS2016038 Attachment 2 Page 1 of2 Attachment 2 Proposed Technical Specifications Revision (Final Typed Format) Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3 1.1 Definitions DOSE EQUIVALENT 1-131 (continued) LEAKAGE LINEAR HEAT GENERATION RATE (LHGR) Definitions 1.1 1-133, 1-134, and 1-135 actually present. The DOSE EQUIVALENT 1-131 concentration is calculated as follows: DOSE EQUIVALENT 1-131=(1-131)+0.0060 (1-132) + 0.17 (l-133) + 0.0010 (1-134) + 0.029 (1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE into the drywall, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or 2. LEAKAGE into the drywall atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; b. Unidentified LEAKAGE All LEAKAGE into the drywall that is not identified LEAKAGE; c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall. The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, (continued) Cooper 1.1-3 Amendment No.