ML12080A217

Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages

ML12080A217
Person / Time
Site:	Harris
Issue date:	03/20/2012
From:	Burton C L Progress Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-12-040
Download: ML12080A217 (4)

Text

Christopher L. Burton.7~Vice President-airirk Nuclea; Planl'rogress Energy Carolinas.

Int.Serial: HNP-12-040 10 CFR 50.90 WAR 2 0 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63

Subject:

Application for Revisionto Technical Specification 5.3.1 and Core Operating Limits Report References for M5 T M Cladding Revised Technical Specification Pages

References:

1. Letter from C.L. Burton to the U.S. NRC, "Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5TM Cladding", Serial HNP-10-124 dated January 13, 2011, ADAMS Ascension No. ML 110250265 2. Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report (COLR)References for Realistic Large Break LOCA Analysis," Serial HNP-1 1-067 dated August 22, 2011, ADAMS Accession No. MLI 1238A077 Ladies and Gentlemen:

By letter dated January 13, 2011, Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., submitted a request: for an amendment to the Technical Specifications (TS) for Shearon Harris Nuclear Power Plaht, Unit No,, I (HNP). The license amendment request (LAR) proposed a change to theHNP TS 5.3.1 and to add the AREVA NP report BAW-l 0240(P)(A), "Incorporation of M5TM Properties in Framatome ANP Approved Methods," to the approved analytical methods in administrative TS 6.9.1.6.2.

The proposed amendment would modify the HNP TS to support the use of the AREVA fuel cladding alloy designated as M5TM.The mark-ups to the TS pages in the subject application were based upon other TS changes requested in reference 2 that were anticipated to be approved prior to this LAR. Reference 2 requested elimination of extraneous detail in TS 6.9.1.6 that cross references each method to the applicable TS Section 3.0 specifications and parameters.

We now anticipate that the subject ,10 Box 165 Ac) L New Hill, NC 27562!.5 919.362.2502 Do r., 919.362 2095 UI.S. Nuclear Regulatory Commission Page 2 lINP- 12-040 LAR will be approved prior to the LAR requested in reference 2, so the attached Technical Specification retyped pages have been revised accordingly.

This change is administrative in nature and does not affect the technical content of the I.AR.This document contains no new Regulatory Commitment.

Please direct any questions regarding this submittal to Dave Corlett at (919) 362-3137.Sincerely, CL.3/jrc Enclosed:

Revised Technical Specification Pages (2 pages)cc: Mr. J. D. Austin, NRC Sr. Resident Inspector.

HNP Mr. W. L. Cox, III, Section Chief N.C. DENR.Ms. A. T. l3illoch Colon. NRC Project Manager. [INP Mr. V. M. McCree., NRC Regional Administrator, Region II DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380 0 F.5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 or M5. Limited substitution of fuel rods by filler rods (consisting of Zircaloy-4 or M5 clad stainless steel or zirconium), or vacancies may be made in fuel assemblies if justified by a cycle specific evaluation.

Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling, a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.5 weight percent U 235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 52 shutdown and control rod assemblies.

The shutdown and control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80% silver, 15% indium, and 5%cadmium, or 95% hafnium with the remainder zirconium.

All control rods shall be clad with stainless steel tubing.5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is-designed and shall be maintained:

a. In accordance with the Coderequirements specified in Section 5.2 of the FSAR, with allowance for normpl degradation pursuant to the applicable Surveillance Requirements, .' : b. For a pressure of 2485 psig, and c. For a temperature of 650 0 F, except for the pressurizer which is 680°F.VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is approximately 10,300 cubic feet at a nominal Tavg of 588.8 0 F.SHEARON HARRIS -UNIT 1 5-6 Amendment No.J'.,,. ...:i,-

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-054(P)(A), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H.B. Robinson Unit 2," approved version as specified in the COLR.(Methodology for Specification 3.2.1 -Axial Flux Difference, and 3.2.2 -Heat Flux Hot Channel Factor).EMF-92-081(P)(A), "Statistical SetpointlTransient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.(Methodology for Specification 3.1.1.3 -Moderator Temperature Coefficient, 3.1.3.5 -Shutdown Bank Insertion Limits, 3.1.3.6 -Control Bank Insertion Limits, 3.2.1 -Axial Flux Difference, 3.2.2 -Heat Flux Hot Channel Factor, and 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor).j. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved version as specified in the COLR.(Methodology for Specification 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor).k. BAW-10240(P)(A), "Incorporation of M5 Properties in Framatome ANP Approved Methods." (Methodology for Specification 3.1.1.2 -SHUTDOWN MARGIN -MODES 3, 4 and 5, 3.1.1.3 -Moderator Temperature Coefficient, 3.1.3.5 -Shutdown Bank Insertion Limits, 3.1.3.6 -Control Bank Insertion Limits, 3.2.1 -Axial Flux Difference, 3.2.2 -Heat Flux Hot Channel Factor, 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor, and 3.9.1 -Boron Concentration).

EMF-96-029(P)(A), "Reactor Analysis Systems for PWRs," approved version as specified in the COLR.(Methodology for Specification 3.1.1.2 -SHUTDOWN MARGIN -MODES 3, 4 and 5, 3.1.1.3 -Moderator Temperature Coefficient, 3.1.3.5 -Shutdown Bank Insertion Limits, 3.1.3.6 -Control Bank Insertion Limits, 3.2.1 -Axial Flux Difference, 3.2.2 -Heat Flux Hot Channel Factor, 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor, and 3.9.1 -Boron Concentration).

m. EMF-2328(P)(A)

PWR Small Break LOCA Evaluation Model, S-RELAP5 Based, approved version as specified in the COLR.(Methodology for Specification 3.2.1 -Axial Flux Difference, 3.2.2 -Heat Flux Hot Channel Factor, and 3.2.3 -"Nuclear Irhthalpy Rise Hot Channel Factor).n. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors", approved version as specified in the COLR.SHEARON HARRIS -UNIT 1 6-24b Amendment No.