The NRC staff requested that GE-Hitachi Nuclear Energy (GEH) evaluate the potential non-conservatism in the GE Thermal-Mechanical Methodology, GESTR-M, identified in the ESBWR design certification review in accordance with the provisions of 10CFR Part 21. The staff was concerned that qualification of GESTR-M against high exposure fuel data could indicate that GESTR-M under-predicts fuel centerline temperature. GEH completed an extensive evaluation and concluded that GESTR-M and its associated statistical methodology, in conjunction with the exposure dependent Linear Heat Generate Rate (LHGR) limit, was adequate for fuel licensing and design calculations within its qualification domain and therefore did not constitute a reportable condition ...
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Eval...
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
the use of historical fuel thermal conductivity models in the safety analyses of operating reactor p...
NRC review and approval. NEDC-33408P and its supplement address the Plant Based Load Evaluation (PBL...
water Reactors, " GE Hitachi Nuclear Energy (GEH) is submitting this report to document any eme...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
The purpose of this letter is to provide a status of the NRC staffs review of the hydrodynamic load ...
Additional Information. Twenty-six questions, associated with the NRC Staff's review of GE Nucl...
Subject: Revised Responses to MELLLA+ RAIs (IAC No MB6157) In References 1 and 2, GE responded to NR...
Design Investigations: The effects on the power distribuestablished. A mathematical model was develo...
The GE Hitachi Nuclear Energy (GEH) nuclear criticality safety (NCS) function remains actively engag...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
We have completed our review of the subject topical report dated July 1988 together with responses t...
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Eval...
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
the use of historical fuel thermal conductivity models in the safety analyses of operating reactor p...
NRC review and approval. NEDC-33408P and its supplement address the Plant Based Load Evaluation (PBL...
water Reactors, " GE Hitachi Nuclear Energy (GEH) is submitting this report to document any eme...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
The purpose of this letter is to provide a status of the NRC staffs review of the hydrodynamic load ...
Additional Information. Twenty-six questions, associated with the NRC Staff's review of GE Nucl...
Subject: Revised Responses to MELLLA+ RAIs (IAC No MB6157) In References 1 and 2, GE responded to NR...
Design Investigations: The effects on the power distribuestablished. A mathematical model was develo...
The GE Hitachi Nuclear Energy (GEH) nuclear criticality safety (NCS) function remains actively engag...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
We have completed our review of the subject topical report dated July 1988 together with responses t...
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Eval...
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...