HNP-10-028, Response to Request for Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code-RELAPS 5 for Non-LOCA Accident Transients

Response to Request for Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code-RELAPS 5 for Non-LOCA Accident Transients

ML100700076
Person / Time
Site:	Harris
Issue date:	03/03/2010
From:	Burton C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-10-028
Download: ML100700076 (3)

Text

Progress Energy Christopher L.Burton Vice Prlaident Harris Nuclear Plant Progress Energy Carolinas, Inc.

Serial: HNP-10-028 3 20]10 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 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO ALLOW THE USE OF THERMAL-HYDRAULIC ANALYSIS CODE S-RELAP5 FOR NON-LOCA ACCIDENT TRANSIENTS

References:

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

HNP-09-055), "Application for Revision to Technical Specification Core Operating Limits Report (COLR) References," dated July 21, 2009 (ML092150053)

2. Letter from M. Vaaler, Nuclear Regulatory Commission, to C. L. Burton, "Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code S-RELAP5 for Non-Loss-Of-Coolant Accident Transients (TAC NO. ME1735)," dated February 2, 2010 (ML100321334)

Ladies and Gentlemen:

On February 2, 2010, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference 2) for additional information needed to facilitate the review of the License Amendment Request to revise Technical Specification (TS) Section 6.9.1.6 to add the NRC approved topical report (TR) EMF-23 I0(P)(A), "SRP Chapter 15 Non-LOCA [Loss-of-Coolant Accident] Methodology for Pressurized Water Reactors," to its Core Operating Limits Report methodologies list. This original request was submitted as Serial: HNP-09-055 (Reference 1).

The Enclosure to this submittal contains HNP's response to this request for additional information.

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

This document contains no regulatory commitments.

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

P.. Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095

Serial: HNP-10-028 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on MAR 3 2010 Sincerely, CLB/kms

Enclosure:

Response to Request for Additional Information 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-10-028 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Summary By letter dated July 21, 2009, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc. (PEC), submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment would revise Technical Specification (TS) Section 6.9.1.6 to add the U.S. Nuclear Regulatory Commission (NRC) approved topical report (TR) EMF-23 10(P)(A), "SRP Chapter 15 Non-LOCA [Loss-of-Coolant Accident] Methodology for Pressurized Water Reactors," to the Core Operating Limits Report methodologies list.

This change will allow the use of thermal-hydraulic analysis code S-RELAP5 for Final Safety Analysis Report (FSAR) Chapter 15 non-LOCA transients in the HNP safety analyses. TR EMF-23 10(P)(A), Revision 0, was approved by the NRC on May 11, 2001, for the application of the S-RELAP5 thermal-hydraulic analysis computer code to FSAR Chapter 15 non-LOCA transients. EMF-23 10(P)(A), Revision 1, approved by the NRC on May 19, 2004, updated Section 5.6 of the TR.

The NRC staff has determined the following information is required to complete the evaluation of the subject amendment request:

The NRC staff understands that S-RELAP5 is an updated version of the ANF-RELAP code. Please confirm whether or not the ANF-RELAP model will still be retained in the Technical Specification Core Operating Limits Report (COLR) references after the proposed addition of the S-RELAP5 code to the list of COLR references.

If so, please discuss any circumstances when the older version (i.e., the ANF-RELAP model) of the code may be applied for use in licensing calculations instead of the S-RELAP5 model, and why this choice would be appropriate.

Response: Since ANF-89-151 (P)(A) (ANF-RELAP model) must be retained until all analyses based on ANF-89-151 (P)(A) are replaced with the newer EMF-23 10 analyses, the LAR does not delete the older model ANF-89-151 (P)(A) from HNP's TS 6.9.1.6.2 COLR reference list. If errors are discovered in the existing ANF-RELAP analyses in the future, ANF-RELAP will be used for the corrections since the inputs to the analysis would remain unchanged. While approval of the S-RELAP5 methodology for HNP will allow future new non-LOCA FSAR Chapter 15 safety analysis to be performed using EMF-23 10, there is no plan to replace all the current FSAR system transient analyses with EMF-23 10 analyses.

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