ML18338A204
| ML18338A204 | |
| Person / Time | |
|---|---|
| Site: | Framatome |
| Issue date: | 11/30/2018 |
| From: | Peters G Framatome |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| NRC:18:042 | |
| Download: ML18338A204 (7) | |
Text
framatome November 30, 2018 NRC:18:042 U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852 10 CFR 50.46 Annual Report for the U.S. EPR Design Certification Ref. 1: Letter, Sandra M. Sloan (AREVA NP Inc.) to Document Control Desk (NRC),
"Application for Standard Design Certification of the U.S. EPR (Project No. 733),"
NRC:07:070, December 11, 2007.
Ref. 2: Letter, Getachew Tesfaye (NRC) to Sandra M. Sloan (AREVA NP Inc.), "AREVA NP Inc. -Acceptance of the Application for Standard Design Certification of the U.S.
EPR," February 25, 2008.
- Ref. 3: Letter, Gary Peters (AREVA Inc.) to Document Control Desk (NRC), "10 CFR 50.46 Annual Report for the U.S. EPR Design Certification," NRC:17:051, November 17, 2017.
Framatome Inc. (Framatome, formerly AREVA Inc.) submitted the application for a Standard Design Certification of the U.S. EPR design in Reference 1. The NRC accepted the application for review in Reference 2. In accordance with 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Reactors," Framatome is submitting this annual report of the emergency core cooling system (ECCS) evaluation model changes and errors for the U.S. EPR Standard Design (Docket 52-020). The previous annual report was submitted in Reference 3.
This report addresses two evaluation models: one for the large break loss of coolant accident (LBLOCA), and one for the small break loss of coolant accident (SBLOCA). The summary of the changes and error corrections made between October 1, 2017 and September 30, 2018 for the LBLOCA evaluation model is provided in Attachment A The summary of the changes and error corrections made between October 1, 2017 and September 30, 2018 for the SBLOCA evaluation model is provided in Attachment B.
Framatome Inc.
3315 Old Fcirest* Rciad Lynchburg, VA 24501 Tel: (434) 832-3000 www.framatoirie.com
Document Control Desk NRC:18:042 November 30, 2018 Page2 If you have any questions related to this information, please contact Nathan Hottle, Product Licensing Manager by telephone at (432) 832-3864, or by e-mail at Nathan.Hottle@framatome.com.
Sincerely,
~?~
Gary Peters, Director Licensing & Regulatory Affairs Framatome Inc.
cc: Docket 52-020
Document Control Desk NRC:18:042 November 30, 2018 Page A-1 Attachment A:
Large Break Loss of Coolant Accident (LBLOCA) Evaluation Model There were no changes or errors reported in the LBLOCA evaluation model for the period of October 1, 2017 to September 30, 2018. The estimated effect on peak cladding temperature is summarized in Table A 1.
The LBLOCA evaluation model for the U.S. EPR design is described in the topical report ANP-10278PA. The primary computer code in the LBLOCA evaluation model is S-RELAP5.
Document Control Desk NRC:18:042 November 30, 2018 Page A-2 Table A1 LBLOCA Margin Summary Sheet - Annual Report Plant Name: U.S. EPR Standard Design Certification Evaluation Model: RLBLOCA (ANP-10278PA)
Initial Peak Cladding Temperature (PCT)= 1780°F Net PCT Absolute Effect PCT Effect A Prior 10 CFR 50.46 Changes or Error Corrections -
previous Years LlPCT = +0°F +0°F B. Current 10 CFR 50.46 Changes - This Report LlPCT = +0°F +0°F (no changes or errors)
Estimate of PCT (unchanged) = 1780°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200°F. .
Document Control Desk NRC:18:042 November 30, 2018 Page B-1 Attachment B Small Break Loss of Coolant Accident (SBLOCA) Evaluation Model A report of changes and errors in the SBLOCA evaluation model for the period of October 1, 2017 to September 30, 2018 is presented below. The estimated effect on peak cladding temperature is summarized in Table 81.
- 1. An error in the S-RELAP5 calculations of oxidation due to high temperature metal-water reaction was discovered. In a LOCA event, the cladding can swell (and potentially rupture) due to the difference in pressure between the fuel and the system which causes the clad to thin. The clad radius increases, while the thickness decreases. It was discovered that the S-RELAP5 oxidation calculations used cold cladding dimensions and therefore, did not fully account for the swelling phenomena. The error can lead to an under-prediction of the oxidation and heat from the metal-water reaction.
Only licensing bases supported by S-RELAP5 analyses which model clad swelling are impacted. The licensing basis analyses, inclusive of previous b.PCT estimates, were evaluated and ab.PCT estimate has been determined.
The U.S. EPR SBLOCA analysis b.PCT estimate is 0°F. The local oxidation and whole core hydrogen also remain well within the 10 CFR 50.46 acceptance criteria with the correction.
The SBLOCA evaluation model for the U.S. EPR design is described in the topical report ANP-10263PA and in the topical report EMF-2328PA.
- The primary computer code in the SBLOCA evaluation model is S-RELAP5.
Document Control Desk NRC:18:042 November 30, 2018 Page B-2 Table B1 SBLOCA Margin Summary Sheet - Annual Report Plant Name: U.S. EPR Standard Design Certification Evaluation Model: SBLOCA (ANP-10263PA and EMF-2328PA)
Initial Peak Cladding Temperature (PCT) = 1638°F NetPCT Absolute Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections - ~PCT= +2°F +266°F previous Years
- 8. Current 10 CFR 50.46 Changes - This Report Error in the S-RELAP5 oxidation calculations ~PCT= +0°F +0°F Sum of 10 CFR 50.46 Changes for this Reporting ~PCT= +0°F +0°F Period Estimate of PCT (unchanged) = 1640°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200°F.
0418-01-F06 (Rev. 002, 01/16/2017)
A NRC CORRESPONDENCE CONCURRENCE SHEET AREVA (Note: Licensing Manager must fill in Regulatory Considerations)
Due Date: November 30, 2018 Author: Nathan Hottle Letter No.: NRC:18:042
Subject:
10 CFR 50.46 Annual Report for the U.S. EPR Design Certification REGULATORY CONSIDERATIONS Affidavit DYes IX] No Posting Requirements DYes IXI No For NOVs and Orders Licensing Verification OYes IX] No New Commitments DYes IXI No Legal Consultation DYes IXI No If yes, Date: If yes, Licensing Added to Comm List: Manager should D Yes D No discuss with legal.
LIC-109 Review OYes IX] No Engineering Technical Review IXI Yes ONo LIC-500 Review D Yes IX] No If yes, the Manager has read requirements.
CONCURRENCE A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with AREVA Policy, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.
Name Role Signature/E-sign Date WILLS Tiffany Tiffany Wills Technical Editor 2018.11.28 14:36:54 -06'00' Id rt, Digitally signed y HOLM Jerald Jerry Holm Peer Reviewer HOLM Jera ;/
DN: o=AREVA GI OUP.
12.5~\45=T197A3 Cl 272DA352C27C49, cn=HOLM Jerald Date:2018.11.29 07:39:26 -07"00" Jeff Seals Engineering technical review (if required) qfiV~
ll/ot>{w18 Nathan Hottle Letter Author/Licensing Manager
~-1/dlt I/ /?a /J1Jl8 Spell Checked: IX] Yes. D No Attachment(s) Enclosed: IX] Yes D No Correspondence File update by: _ _ _ _ _ _ _ _ __
Documentum T-point update b y : - - - - - - - - - -