ML12137A298

ANP-2970Q2(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis

ML12137A298
Person / Time
Site:	Sequoyah
Issue date:	05/15/2012
From:	AREVA, AREVA NP
To:	Office of Nuclear Reactor Regulation
References
TAC ME6538, TAC ME6539, TS-SQN-2011-07 ANP-2970Q2(NP), Rev 0
Download: ML12137A298 (17)

Text

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS I AND 2 ANP-2970Q2(NP), Revision 000, Sequoyah Units I and 2 HTP Fuel Realistic Large Break LOCA Analysis, May 2012 (Non-Proprietary Version)

ANP-2970Q2(NP)

Revision 000 Sequoyah Units 1 and 2 HTP Fuel Realistic Large Break LOCA Analysis May 2012 AREVA HP Onc. AR EVA

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Larqe Break LOCA Analysis Page II Copyright © 2012 AREVA NP Inc.

All Rights Reserved AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page III Nature of Changes Item Page Description and Justification

1. All This is a new document.

AREVA NP Inc.

A A REVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page IV Table of Contents Page NAT UR E O F C HA NG E S ......................................................................................................................... III LIS T O F T A B LE S ................................................................................................................................... IV 1 .0 INT R O DUCT IO N ........................................................................................................................... 5 2.0 NRC REVIEW COMMENTS AND AREVA NP'S RESPONSES .............................................. 6 2 .1 NR C Q uestion 1 (a - e) ............................................................................................................ .. 6 3 .0 R E F E R E NC E S ............................................................................................................................ 12 List of Tables Page Table 2-1: Original and SRR Cases PCT .......................................................................................... 7 Table 2-2: Sampled Parameters 92nd and 93rd Ranked Case ........................................................... 9 Table 2-3: 93rd Case Event Timing ................................................................................................... 10 This document contains a total of 12 pages.

AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 5

1.0 INTRODUCTION

AREVA NP Inc. produced an application of the NRC-approved Realistic Large Break Loss-of-Coolant Accident (RLBLOCA) analysis for the Sequoyah Nuclear (SQN) Plant, Units 1 and 2.

SQN is a Westinghouse (W) 4-loop design with a rated thermal power of 3455 Mega Watt Thermal (MWt). The plant containment building is comprised of lower and upper compartments separated by an ice-condenser. Implementation of a full core of AREVA NP 17x17 HTP fuel design at SQN is simulated in the analysis.

SQN operation at a safety analysis power level of 3479 MWt (rated thermal power plus uncertainty), a steam generator tube plugging level of up to 15 percent (%) in all steam generators, a total peaking factor (FQ) of up to 2.65 (including uncertainty) and a nuclear enthalpy rise factor (FAH) of 1.7056 (including uncertainty) with no axial or burnup dependent power peaking limit is supported by the analysis. The analysis demonstrates compliance with regulatory requirements for evaluation of a large break LOCA via application of an NRC-approved evaluation methodology (EM) (Ref. 1), predicting acceptable peak cladding temperature, oxidation thickness, and hydrogen generation (Summary Report (Ref. 2)).

Tennessee Valley Authority submitted the RLBLOCA Summary Report to the NRC for review.

Section 2.0 of this report contains AREVA NP Inc.'s responses to NRC questions regarding the RLBLOCA Summary Report and the swelling, rupture, and relocation (SRR) analysis (ANP-2970Q1P) submitted to the NRC in Reference 3.

AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 6 2.0 NRC REVIEW COMMENTS AND AREVA NP'S RESPONSES 2.1 NRC Question 1 (a - e)

ANP-2970Q1(NP) discusses the number of cases that were analyzed to evaluate clad swelling, rupture and relocation (ADAMS Accession No. ML12118A166). In ANP-2970(NP),

on Page 2-1, Footnote 3 states, "AREVA decided to run 93 cases (reporting the 9 2 nd case) for the Sequoyah analysis for three main reasons: 1) current AOR Sequoyah RLBLOCA results,

2) high peaking values analyzed, and 3) the greater pressure drop in the 17x17 HTP fuel w/

integral flow mixers. The allowance to execute more cases is discussed in EMF-2103(P)(A),

Section 5.2.1 ." Please provide the following additional information:

a. Was the decision to execute 93 cases made prior to or after completing an analysis using the standard number of cases?

b. For both the original and swelling, rupture, and relocation cases, please provide the highest PCT value obtained from the 93 cases.

c. Please confirm that the same approach (i.e., eliminating the highest value case as beyond the required upper tolerance limit) was used for the swelling, rupture, and relocation study.

d. Please provide the modeling guidelines that are used to assist the analyst in deciding to execute additional cases.

e. Please provide additional detail concerning the reasons given above for executing additional cases. What about the current AOR results leads one to decide to execute additional cases? Did the eliminated case have a peaking factor value that was an outlier from the rest of the population? How does the pressure drop cause the population of results to de-stabilize?

Response

AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 7 1.b. Table 2-1 below provides the top 5 highest Peak Cladding Temperatures (PCTs) in degrees Fahrenheit (OF) obtained from the 93 cases run in the original analysis and the SRR analysis for thIe offsite power available scenario 2 .

Table 2-1: Original and SRR Cases PCT 2 Section 2.0 and Figure 3-24 in ANP-2970P disclosed that the offsite power available scenario produced the most limiting PCT, therefore, the sensitivity for SRR was executed for this configuration.

3 The elevation of the PCT node was 11.3 feet.

4 The elevation of the PCT node was 10.0 feet.

AREVA NP Inc.

A ARE VA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 8 Part 2: The sampled parameters for the 92nd and 9 3 rd cases were reviewed and are presented in Table 2-2. The timing of the event for the 9 3 rd case is presented in Table 2-3.

AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 9 Table 2-2: Sampled Parameters 92nd and 93rd Ranked Case AREVA NP Inc.

A ARE VA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 10 Table 2-3: 93rd Case Event Timing AREVA NP Inc.

A AR EVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 11 AREVA NP Inc.

A AREVA ANP-2970Q2(NP)

Sequoyah Units 1 and 2 HTP Fuel Revision 000 Realistic Large Break LOCA Analysis Page 12

3.0 REFERENCES

1. EMF-2103(P)(A) Revision 0, "Realistic Large Break LOCA Methodology," Framatome ANP, Inc., April 2003.

2. ANP-2970(P) Revision 0, "Sequoyah Units 1 and 2 HTP Fuel Realistic Large Break LOCA Analysis," April 2011.

3. "Response to NRC Third Request for Additional Information Regarding Application to Modifiy Technical Specifications for the Use of AREVA Advanced W1 7 HTP Fuel (TS-SQN-2011-07) (TAC Nos. ME6538 and ME6539)," April 26, 2012.

4. ANP-2655(P) Revision 1, "Sequoyah Nuclear Plant Unit 2 Realistic Large Break LOCA Analysis," February 2008.

5-. ANP-2695(P) Revision 0, "Sequoyah Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis," February 2008.

6. EMF-2103(P) Revision 2, "Realistic Large Break LOCA Methodology," AREVA, Inc.,

November 2010.

AREVA NP Inc.

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS I AND 2 AREVA NP Affidavit Attached is the affidavit supporting the request to withhold the proprietary information included in Enclosure 1 from public disclosure in accordance with 10 CFR 2.390, "Public inspections, exemptions, requests for withholding," paragraph (a)(4).

AFFIDAVIT COMMONWEALTH OF VIRGINIA )

) ss.

CITY OF LYNCHBURG )

1. My name is Gayle F. Elliott. I am Manager, Product Licensing, for AREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.

3. I am familiar with the AREVA NP information contained ANP-2970Q2(P)

Revision 000 entitled "Sequoyah Units 1 and 2 HTP Fuel Realistic Large Break LOCA Analysis,"

dated May 2012 and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is

requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information":

6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:

(a) The information reveals details of AREVA NP's research and development plans and programs or their results.

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.

(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.

The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b) and 6(c) above.

7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

SUBSCRIBED before me this day of 2012.

Kathleen Ann Bennett NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 8/31/15 Reg. # 110864 I KATmLEEN ANN BENNETT No"y Publ commoffi n of viI0, h&- A.mhamda Emafra. LAnaA 9fi1G i -IWU IURUgJ~WIYv weep**ii -r ** w -

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