L-2012-072, ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3
| ML12061A250 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/29/2012 |
| From: | AREVA NP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-2012-072 ANP-2903Q2(NP), Rev 0 | |
| Download: ML12061A250 (32) | |
Text
L-2012-072 ATTACHMENT 3 EXTENDED POWER UPRATE -
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION IDENTIFIED DURING AUDIT OF THE SAFETY ANALYSES CALCULATIONS NON-PROPRIETARY VERSION ANP-2903Q2(NP)
Revision 0 St. Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding (Cover pageplus 27 pages)
.ortrollie Doc;ument ANP-2903Q2(NP)
Revision 0 St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding February 2012 A
AREVA AREVA NP Inc.
Controlled Documient A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page ii Copyright © 2012 AREVA NP Inc.
All Rights Reserved AREVA NP Inc.
C ontrolled Docum~.ent A
AREVA St Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page iii Nature of Changes Description and Justification Item Page
- 1.
All This is a new document.
AREVA NP Inc.
C'ontrolled Document A
AREVA ANP-2903Q2(NP)
St Lucie Nuclear Plant Unit 1 EPU Cycle Revision 0 Realistic Large Break LOCA Summary Report Page iv with Zr-4 Fuel Cladding Table of Contents Page NATURE OF CHANGES.........................................................................................................................
III LIST O F TABLES....................................................................................................................................
V LIST O F FIG URES.................................................................................................................................
VI 1.0 INTRO DUCTIO N...........................................................................................................................
1 2.0 NRC REVIEW COMMENTS AND AREVA NP'S RESPONSES...............................................
2 2.1 NRC Audit Q1...................................................................................................................................
2 2.2 NRC Audit Q2...................................................................................................................................
4 2.3 NRC Audit Q3...................................................................................................................................
9 2.4 NRC Audit Q4.................................................................................................................................
18
3.0 REFERENCES
21 This document contains a total of 27 pages.
AREVA NP Inc.
Cntrolled Docurnni t
A AREVA St Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page v List of Tables Page Table 2-1: Limiting PCT Case Void Fractions and Heat Transfer Coefficients, 0-50 seconds.......
18 AREVA NP Inc.
C.ontrolled Document A
AREVA ANP-2903Q2(NP)
St Lucie Nuclear Plant Unit 1 EPU Cycle Revision 0 Realistic Large Break LOCA Summary Report Page vi with Zr-4 Fuel Cladding List of Figures Page Figure 2-1: [
]....................
3 Figure 2-2: Example of Power History................................................................................................
6 Figure 2-3: Decay Heat Curve, Burnup = 1 GWd/MTU......................................................................
8 Figure 2-4 : C ase 32 P C T T race.............................................................................................................
10 Figure 2-5: Case 32 Upper Plenum Pressure....................................................................................
11 Figure 2-6: Case 32 Core Inlet Mass Flux........................................................................................
12 Figure 2-7: Case 32 Core Outlet Mass Flux.....................................................................................
13 Figure 2-8: C ase 46 PC T T race.............................................................................................................
14 Figure 2-9: Case 46 Upper Plenum Pressure....................................................................................
15 Figure 2-10: Case 46 Core Inlet Mass Flux.....................................................................................
16 Figure 2-11: Case 46 Core Outlet Mass Flux..................................................................................
17 AREVA NP Inc.
Controlled Document A
AREVA ANP-2903Q2(NP)
St Lucie Nuclear Plant Unit I EPU Cycle Revision 0 Realistic Large Break LOCA Summary Report Page 1 with Zr-4 Fuel Cladding
1.0 INTRODUCTION
AREVA NP Inc. performed an RLBLOCA analysis for the St Lucie Nuclear Plant (SLA) Unit 1 Extended Power Uprate (EPU). The analysis supports operation for EPU Cycle and beyond with AREVA NP's HTP 14X14 fuel design using standard U0 2 fuel with 2%, 4%, 6% and 8% Gd 20 3 and Zircaloy-4 cladding. The analysis was performed in compliance with the U.S. Nuclear Regulatory Commission (NRC) approved RLBLOCA Evaluation Model (EM) (Ref. [1]). Analysis results confirm the 10CFR50.46 (b) acceptance criteria presented in Section 3.0 are met and serve as the basis for operation of the St Lucie Nuclear Plant Unit 1 with AREVA NP fuel (Summary Report, Ref. [2]).
Florida Power and Light submitted the RLBLOCA Summary Report to the NRC for review. Section 2.0 contains AREVA NP Inc.'s responses to NRC questions posed during the audit held in Lynchburg, VA on January 30-31, 2012.
AREVA NP Inc.
C1ontrolled Documven t A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 2 2.0 NRC REVIEW COMMENTS AND AREVA NP'S RESPONSES 2.1 NRC Audit QI Provide the estimated PCT impact for the Sleicher-Rouse correction for SBLOCA and RLBLOCA. Decribe how the estimates were developed.
Response
Te
]
The impact of the update of the heat transfer correlation is evaluated for the St Lucie Plant.
AREVA NP Inc.
Controlle Idocip A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 3 Figure 2-1: [
I AREVA NP Inc.
,ritrollec,(
Docurn ýn A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page 4 2.2 NRC Audit Q2 Issue the decay heat response that that was provided to the auditors during their visit.
Response
AREVA NP Inc.
Controlled Docu:ment A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddinq ANP-2903Q2(NP)
Revision 0 Page 5 AREVA NP Inc.
Controlled Document A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page 6 P"4 P. 1 PM I
U-t Ii t2 POs a-'F 4 3-*T4T t
l t
Time Figure 2-2: Example of Power History AREVA NP Inc.
2~ontrjIed Doe r, erA A
AR EVA St Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 7 AREVA NP Inc.
2.on trolled DocG1;-"
ite A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 8 Figure 2-3: Decay Heat Curve, Burnup = I GWd/MTU AREVA NP Inc.
Contrlle'OLm n
A AREVA ANP-2903Q2(NP)
St Lucie Nuclear Plant Unit 1 EPU Cycle Revision 0 Realistic Large Break LOCA Summary Report Page 9 with Zr-4 Fuel Cladding 2.3 NRC Audit Q3 Provide a set of plots for the first 50-seconds of the limiting PCT case and the very late PCT case including:
- a. PCT
- b. Core inlet mass flux
- c. Core exit mass flux
- d. System pressure
Response
The limiting case is Case 32 with a PCT of 16670F occurring at 9.6 seconds. Figure 2-4 displays the PCT in the fresh U0 2 rod for Case 32. Figure 2-5, Figure 2-6, and Figure 2-7 show the system pressure (upper plenum pressure), the core inlet mass flux, and the core outlet mass flux, respectively, for Case
- 32. [
] Figure 2-8 displays the PCT in the fresh U0 2 rod for Case 46. Figure 2-9, Figure 2-10, and Figure 2-11 show the system pressure, the core inlet mass flux, and the core outlet mass flux, respectively, for Case 46.
AREVA NP Inc.
iOontrolled Documnte A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 10 PCT Trace for Case #32 PCT = 1666.3 0F, at Time = 9.63 s, on Hot U02 Rod 2000 1500 LL 0
a-0 E
(D 0~
C,,
1000 500 0 0 10 20 30 40 Time (s)
Figure 2-4: Case 32 PCT Trace 50 AREVA NP Inc.
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AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 11 3000 2000 ci, 0~
I-Co (0'p I-0~
1000 0 0 10 20 30 40 50 Time (s)
Figure 2-5: Case 32 Upper Plenum Pressure AREVA NP Inc.
r-ýControlled DOCLIment A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 12 1000 750 E
.0 x3 u-500 250 0
-250
-500 L 0
10 20 30 40 50 Time (s)
Figure 2-6: Case 32 Core Inlet Mass Flux AREVA NP Inc.
Controlled Document A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 13 1000 750 E
x L) 0)
500 250 0
-250
-500 0 10 20 30 40 Time (s) 50 Figure 2-7: Case 32 Core Outlet Mass Flux AREVA NP Inc.
Controlled Document A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page 14 Figure 2-8: Case 46 PCT Trace AREVA NP Inc
C ontrolled DOL) Ime 1 nt A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 15 Figure 2-9: Case 46 Upper Plenum Pressure AREVA NP Inc.
oItrc lied Documnent A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 16 Figure 2-10: Case 46 Core Inlet Mass Flux AREVA NP Inc.
Controlledi DOCLIrent A
AR EVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddina ANP-2903Q2(NP)
Revision 0 Page 17 Figure 2-11: Case 46 Core Outlet Mass Flux AREVA NP Inc.
,oritrolled DOCUmnie A
AREVA St Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Claddinq ANP-2903Q2(NP)
Revision 0 Page 18 2.4 NRC Audit Q4 For the limiting case, provide a tabulated of the individual heat transfer coefficients at the PCT node, void fractions and the heat transfer coefficient multipliers used (0.1 second for the first second, 1 second after that, up to 50 seconds).
Response
The void fraction and wall-to-liquid radiation, wall-to-vapor radiation, convection to vapor, and film boiling heat transfer coefficients are provided in Table 2-1 for the first 50 seconds of the limiting PCT transient.
The heat transfer coefficients presented in the table are based on the saturation temperature. In addition, the summation of the four heat transfer coefficients is provided.
Table 2-1: Limiting PCT Case Void Fractions and Heat Transfer Coefficients, 0-50 seconds AREVA NP Inc.
ontrolled Document A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 19 AREVA NP Inc.
ontrolled Docurment A
AREVA St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding ANP-2903Q2(NP)
Revision 0 Page 20 AREVA NP Inc.
Controlled Document A
AR EVA ANP-2903Q2(NP)
St Lucie Nuclear Plant Unit 1 EPU Cycle Revision 0 Realistic Large Break LOCA Summary Report Page 21 with Zr-4 Fuel Cladding
3.0 REFERENCES
- 1.
EMF-2103(P)(A )Revision 0, "Realistic Large Break LOCA Methodology," Framatome ANP, Inc.
- 2.
ANP-2903(P) Revision 1, "St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding."
3 ANP-3000(P) Revision 0, "St. Lucie Unit I EPU - Information to Support License Amendment Request."
- 4.
ANSI/ANS-5.1-1979 American National Standard for Decay Heat Power in Light Water Reactors, American National Standards Institute, Inc., August 29, 1979.
- 5.
Regulatory Guide 1.157, "Best Estimate Calculations of Emergency Core Cooling System Performance", May 1989.
AREVA NP Inc.
L-2012-072 ATTACHMENT 5 EXTENDED POWER UPRATE -
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION IDENTIFIED DURING AUDIT OF THE SAFETY ANALYSES CALCULATIONS Affidavit to Withhold from Public Disclosure Proprietary Information Under 10 CFR 2.390 ANP-2903Q2(P)
Revision 0 St. Lucie Nuclear Plant Unit I EPU Cycle Realistic Large Break-LOCA Summary Report with Zr-4 Fuel Cladding (Cover page -plus 3 pages)
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 in the report ANP-2903Q2(P), Revision 0, entitled "St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding," dated February 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 secret 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 %t7Zl:Ze,2012.
Kathleen Ann Bennett NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 8/31/15 Reg. # 110864 WATHLEN ANN SENNETY Cmmgg~gg of WOWm~