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| | issue date = 01/05/2018 | | | issue date = 01/05/2018 |
| | title = Verification Letter for the Approved Version of NEDC-33840P (Prime) | | | title = Verification Letter for the Approved Version of NEDC-33840P (Prime) |
| | author name = Morey D C | | | author name = Morey D |
| | author affiliation = NRC/NRR/DLP/PLPB | | | author affiliation = NRC/NRR/DLP/PLPB |
| | addressee name = Head J G | | | addressee name = Head J |
| | addressee affiliation = GE-Hitachi Nuclear Energy Americas, LLC | | | addressee affiliation = GE-Hitachi Nuclear Energy Americas, LLC |
| | docket = 99902024, PROJ0710 | | | docket = 99902024, PROJ0710 |
| | license number = | | | license number = |
| | contact person = Golla J A | | | contact person = Golla J |
| | case reference number = EPID L-2016-TOP-0003 | | | case reference number = EPID L-2016-TOP-0003 |
| | document type = Letter | | | document type = Letter |
Revision as of 11:55, 18 June 2019
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Category:Letter
MONTHYEARML23283A0892023-10-10010 October 2023 ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023 ML23277A1692023-10-0404 October 2023 GE-Hitachi Nuclear Energy Americas, LLC, ABWR Design Certification Annual 10 CFR 50.46 Report for 2023 ML23277A1702023-10-0404 October 2023 GE-Hitachi Nuclear Energy Americas, LLC, ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023 ML22347A2842022-12-0808 December 2022 GE-Hitachi Nuclear Energy Americas, LLC, Accepted Version of NEDO-11209-A Revision 17, GE Hitachi Nuclear Energy Quality Assurance Program Description ML21320A1902021-11-16016 November 2021 Pre-Application Presentation Slides for Amendment to NEDO-11209-A, Rev. 16, GE Hitachi Nuclear Energy Quality Assurance Program Description ML20197A2692020-07-15015 July 2020 Pre-application Presentation Slides for Amendment to NEDO-11209-A Revision 15, GE Hitachi Nuclear Energy Quality Assurance Program Description ML20184A1582020-07-14014 July 2020 Verification of Accepted Version of NEDO-11209 Revision 15, GE Hitachi Nuclear Energy Quality Assurance Program Description ML20093B4532020-04-0202 April 2020 GE-Hitachi Nuclear Energy Americas, LLC - Revision of the GE Model No. 2000 (Docket No. 71-9228) to Clarify Irradiated Hardware Content and Update the Quality Assurance Program References ML19242D0982019-09-19019 September 2019 General Electric Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure ML19242D6962019-09-19019 September 2019 Verification of NEDC-33173P Supplement 6 Revision 1, Licensing Topical Report Applicability of GE Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Ratio (SLMCPR) Penalty ML19199A1822019-08-0808 August 2019 Final Safety Evaluation for NEDC-33173P Supplement 6 - Applicability of GE Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Raito (SLMCPR) Penalty ML19094A0582019-04-25025 April 2019 Verification of GE Hitachi Topical Report NEDC-33173 Supplement 5p-A, Revision 1, Applicability of General Electric Methods to Expanded Operating Domains - Supplement for GNF3 Fuel ML19094A9182019-04-25025 April 2019 General Electric Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure ML19071A1012019-03-26026 March 2019 Draft Safety Evaluation for NEDC-33173p Supplement 6 - Applicability of General Electric Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Ratio Penalty ML19074A0542019-03-21021 March 2019 Imltr Supplement 5 Final SE Non-Proprietary ML19017A0432019-03-0505 March 2019 GE Hitachi Nuclear Energy Americas, Llc, Request for Withholding Information from Public Disclosure ML19016A4072019-03-0505 March 2019 GE Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure ML19002A3762019-02-0505 February 2019 Draft Safety Evaluation for NEDC-33173p Supplement 5 and Applicability of GE Methods to Expanded Operating Domains and Supplement for GNF3 Fuel ML18155A2102018-06-22022 June 2018 Verification of GE Hitachi Topical Report NEDE-33005P-A, Revision 2 Tracg Application for Emergency Core Cooling Systems/Loss-of Coolant Accident Analysis for BWR/2-6 ML18129A0242018-05-11011 May 2018 Final Safety Evaluation for Licensing Topical Report Nede 33005P-A / NEDO-33005-A, Tracg Application for Emergency Core Cooling Systems / Loss-Of-Coolant-Accident Analysis for BWR/2-6 Satisfaction of Limitation 10.7 ML18117A3112018-04-27027 April 2018 Draft Safety Evaluation for Licensing Topical Report NEDE-33005P-A / NEDO-33005-A, Tracg Application for Emergency Core Cooling Systems / Loss-of-Coolant-Accident Analysis for BWR/2-6 Satisfaction of Limitation 10.7 ML18078A5872018-04-10010 April 2018 Satisfaction of TRACG-LOCA Limitation 10.7 Draft SE Cover Letter ML18046A6392018-03-0606 March 2018 Proprietary Determination Letter for TRACG-LOCA Satisfaction of Limitation 10.7 RAI Response ML18002A4322018-01-10010 January 2018 Final SE for Amendment to NEDO-11209 Revision 13 GE QAPD ML17347B1992018-01-0909 January 2018 GNF2 Compliance Report Proprietary Determination Letter ML17342A1012018-01-0909 January 2018 Proprietary Determination Letter for Nsf Annual Experience Summary Report ML17332A6012018-01-0909 January 2018 Proprietary Determination Letter for NEDC-33840P-A, Prime Model for Transient Analysis ML17341A9432018-01-0505 January 2018 Verification Letter for the Approved Version of NEDC-33840P (Prime) ML17332A2962018-01-0505 January 2018 Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 44 to NEDE-24011-P-A-24 ML14062A0442014-03-0303 March 2014 Additional Utility Support for NEDE-33766P, GEH Simplified Stability Solution (GS3) ML1032704642010-12-28028 December 2010 Letter Transmitting Final Safety Evaluation of GE Hitachi Nuclear Energy (GEH) Topical Report NEDC-33173P, Supplement 3, Applicability of GE Methods to Expanded Operating Domains - Supplement for GNF2 Fuel ML0717106152007-07-18018 July 2007 Potential Adverse Flow Effects in Nuclear Power Plants ML0610803382006-04-14014 April 2006 Withholding Letter to G Strambach, GE, GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point Nuclear Station 2 and Perry Nuclear Power Plant (Mfn 06-089) ML0608804422006-03-24024 March 2006 GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point, Unit 2 and Perry Nuclear Power Plant ML0500600862004-11-12012 November 2004 Content of VY Steam Dryer Audit Report, Non-Proprietary ML0416204602004-05-0707 May 2004 Supporting Lattice Information - Mellla+ RAI AOO 6 2023-10-04
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Text
January 5, 2018
Mr. Jerald G. Head Senior Vice President, Regulatory Affairs
GE-Hitachi Nuclear Energy Americas, LLC P.O. Box 780, M/C A-18 Wilmington, NC 28401-0780
SUBJECT:
VERIFICATION OF THE APPROVAL VERSION OF GLOBAL NUCLEAR FUEL - AMERICAS TOPICAL REPORT NEDC-33840P, REVISION 0, "THE PRIME MODEL FOR TRANSIENT ANALYSIS OF FUEL ROD THERMAL - MECHANICAL PERFORMANCE" (EPID NO. L-2016-TOP-0003)
Dear Mr. Head:
By letter dated August 18, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17230A010), Global Nuclear Fuel - Americas (GNF) submitted an approval ("-A") version of Topical Report (TR) NEDC-33840P, Revision 0, "The PRIME Model for Transient Analysis of Fuel Rod Thermal - Mechanical Performance," to the U.S. Nuclear
Regulatory Commission (NRC) staff. GNF has done so in accordance with our request to publish an approved version of this TR, as detail ed in the transmittal letter of the NRC staff's final safety evaluation (SE) (ADAMS Accession No. ML17159A806) of the original TR. It is understood that the approval version of NEDC-33840P, Revision 0, is designated as NEDC-33840P-A, Revision 1.
The NRC staff has completed its review of the approval version of the TR. The NRC staff verified that Global Nuclear Fuel has met the requirements and determined that the submitted -A version is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the approval version of the TR.
TR NEDC-33840P-A, Revision 1, "The PRIME Model for Transient Analysis of Fuel Rod Thermal - Mechanical Performance," is now approved for use in future licensing actions as specified in the final SE.
Please contact Joseph A. Golla at (301) 415-1002, if you have any questions on this subject.
Sincerely, /RA/ Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
Docket No. 99902024 GE-Hitachi Nuclear Energy Americas Project No. 710
cc: Mr. James F. Harrison
GE-Hitachi Nuclear Energy Americas LLC Vice President - Fuel Licensing P.O. Box 780, M/C A-55
Wilmington, NC 28401-0780 james.harrison@ge.com Ms. Patricia L. Campbell Vice President, Washington Regulatory Affairs
GE-Hitachi Nuclear Energy Americas LLC 1299 Pennsylvania Avenue, NW, 9 th Floor Washington, DC 20004 patriciaL.campbell@ge.com
Mr. Brian R. Moore General Manager, Core & Fuel Engineering Global Nuclear Fuel-Americas, LLC P.O. Box 780, M/C A-75
Wilmington, NC 28401-0780 Brian.Moore@gnf.com
ML17341A943; *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DSS/SNPB NRR/DLP/PLPB/BC NAME JGolla DHarrison RLukes DMorey DATE 1/3/2018 12/19/2017 1/3/2018 1/5/2018