HNP-10-073, Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code S-RELAP5 for Non-LOCA Accident Transients

Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code S-RELAP5 for Non-LOCA Accident Transients

ML102160371
Person / Time
Site:	Harris
Issue date:	07/28/2010
From:	Warner J Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-10-073
Download: ML102160371 (3)

Text

L)Progress .Energ Serial: HNP-10-073 JUL 2"8 20M 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL INFORMATION REGARDING AMENDMENT TO ALLOW THE USE OF THERMAL-HYDRAULIC ANALYSIS CODE S-RELAP5 FOR NON-LOCA ACCIDENT TRANSIENTS

References:

, 1. Letter from C. L. Burton to-the Nuclear Regulatory Commission (Serial:,

HNP-09-05 5), "Application for Revision to Technical Specification Core Operating Limits Report (COLR) References," dated July 21, 2009 (ML092150053)

2. Letter from C. L. Burton to the Nuclear Regulatory Commission (Serial:

HNP-10-028), "Response to Request for Additional Information Regarding*

Amendment to Allow the Use of Thermal-Hydraulic Analysis Code S-RELAP5 for Non-LOCA Accident Transients," dated March 03, 2010 (ML100700076)

Ladies and Gentlemen:

On July 21, 2009, the Harris Nuclear Plant (HNP) submitted a License Amendment Request (LAR) to'modify Technical Specification (TS) 6.9.1.6 to allow the use of thermal-hydraulic analysis code S-RELAP5 for Chapter 15 non loss-of-coolant accident (LOCA) transients in the HNP safety analysis (Reference 1). Additionally, HNP submitted its response to the NRC's Request for Additional Information on March 03, 2010 (Reference 2).

During a June 02,'20 10, telephone discussion with the NRC Staff, HNP agreed to provide a Regulatory Commitment to clarify the response provided in Reference 2.

The Enclosure to this submittal contains this Regulatory Commitment.

In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this response.

Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137.

Progress Energy Carolinas, Inc.

Harris Nuclear Plant PN0H New Box Hill, 165 NC27562 4"c.

• ,.((

Serial: HNP-10-073 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on JUL 2 8 2010 Sincerely,

/ John C. Warner Manager - Support Services Harris Nuclear Plant JCW/kms,

Enclosure:

Regulatory Commitment cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N. C. DENR Mr. L. A. Reyes, NRC Regional Administrator, Region II Ms. M. G. Vaaler, NRC Project Manager, HNP

Enclosure to SERIAL: HNP-10-073 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL INFORMATION REGARDING AMENDMENT TO ALLOW THE USE -OF THERMAL-HYDRAULIC ANALYSIS CODE S-RELAP5 FOR NON-LOCA ACCIDENT TRANSIENTS REGULATORY COMMITMENT The action in this document committed to by Harris Nuclear Plant (HNP) regarding the July 21, 2009, 10 CFR 50.90 License Amendment Request (LAR), "Application for Revision to Technical Specification Core Operating Limits Report (COLR) References," is identified in the following table. Statements in this submittal, with the exception of that in the table below, are provided for information purposes and are not considered commitments. Please direct any questions regarding this document or any associated regulatory commitments to the Supervisor, Licensing/Regulatory Programs.

Ifeh~ Conunitment~~ Completion Da.tc 7 i 1 After implementation of the HNP TS Amendment approving Upon implementation of use of the thermal-hydraulic analysis methodology EMF-2310 approved TS Amendment (S-RELAP5) for Chapter 15 non loss-of-coolant accident (60-days implementation period (LOCA) transients, EMF-23 10 will be used for new requested). This commitment replacement safety analysis currently performed using will remain in effect until all ANF-89-151 methodology. ANF-89-151 analyses are replaced with EMF-23 10 If it becomes necessary to correct an error in the current ANF- analyses.89-151 analyses, ANF-89-151 methodology will be used for the error correction.

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