ML18094A399
| ML18094A399 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/02/1989 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | Tosch K NEW JERSEY, STATE OF |
| References | |
| TAC-71836, TAC-71837, NUDOCS 8905050170 | |
| Download: ML18094A399 (2) | |
Text
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- Dqcket Nos. 50-272/311 May 2, 19-DISTRIBUTION Docket File Local PDR SVarga WButler Kent Tosch, Chief Bureau of Nuclear Engineering State of New Jersey Department of Environmental Protection Division of Environmental Quality CN 415 Trenton, New Jersey 08625-0415
Dear Mr. Tosch:
SUBJECT:
HYDROGEN GENERATION FROM VANTAGE 5 HYBRID FUEL (TAC NOS. 71836/71837)
NRC PDR PDI-2 Rdg.
BBoger MO'Brien MThadani EJordan WHodges Your letter of March 6, 1989, raised a concern with Vantage 5 Hybrid Fuel (V5H) in that V5H has grids of zircalloy-4 instead of Inconel.
Your specific concern was that the significant hazards consideration provided in the Public Service Electric and Gas Company's amendment request dated December 30, 1988, did not evaluate the potential for hydrogen generation as a result of metal-water reaction involving the grids under a postulated Loss-of-Coolant-Accident (LOCA).
Because the melting temperature of zircalloy (3362°F) is much higher than Inconel (2346°F), the fuel bundles will be maintained in a coolable geometry for a longer period of time, thus, delaying the development of conditions necessary for the metal-water reaction to proceed. Also, the weight of zircalloy in the grids is a small fraction of the total zircalloy in the core which further reduces the affect of the metal-water reaction 1nvolving the grids on the overall hydrogen generation.
The regulatory requirements of 10 CFR 50.44 require that only the fuel cladding must be considered in the hydrogen generation analysis, not structural components.
The use of zircalloy for core structural components has been previously approved in earlier core designs.
The V5H fuel design has been reviewed and appro'ved by the NRC on a generic basis, without conditions pertaining to the use of zircalloy in core structural components.
Accordingly, we believe it is appropriate to conclude that the use of zircalloy in lieu of Inconel for the fuel element spacers would involve no significant hazards consideration.
cc: Steven E. Miltenberger Previously concurred*
PDI-2/PM*
JStone:tr 05/01/89
-~------ --~---
PDI-2/D*
WButler 05/02/89
~
8905050170 890502 PDR ADOCK 050~)272 p
PDC I
I Sincerely, Isl James C. Stone, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation NRR/SRXB*
WHodges 05/01/89
[TOSCH LETTER]
e e
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Kent Tosch, Chief Bureau of Nuclear Engineering State of New Jersey Department of Environmental Protection Division of Environmental Quality CN 415 Trenton; New Jersey 08625-0415
Dear Mr. Tosch:
May 2, 1989
SUBJECT:
HYDROGEN GENERATION FROM VANTAGE 5 HYBRID FUEL (TAC NOS. 71836/71837)
Your letter of March 6, 1989, raised a concern with Vantage 5 Hybrid Fuel (VSH) in that V5H has grids of zircalloy-4 instead of Inconel.
Your specific concern was that the significant hazards consideration provided in the Public Service Electric and Gas Company's amendment request dated December 30, 1988, did not evaluate the potential for hydrogen generation as a result of metal-water reaction involving the grids under a postulated Loss-of-Coolant-Accident (LOCA).
s Because the melting temperature of zircalloy (3362°F) is much higher than Inconel (2346°F), the fuel bundles will be maintained in a coolable geometry for a longer period of time, thus, delaying the development of conditions necessary for the metal-water reaction to proceed. Also, the weight of zircalloy in the grids is a small fraction of the total zircalloy in the core which further reduces the affect of the metal-water reaction involving the grids on the overall hydrogen generation.
The regulatory requirements of 10 CFR 50.44 require that only the fuel cladding must be considered in the hydrogen generation analysis, not structural components.
The use of zircalloy for core structural components has been previous_ly approved in earlier core designs. The V5H fuel design has been reviewed and approved by the NRC on a generic basis, without conditions pertaining to the use of zircalloy in core structural components.
Accordingly, we believe it is appropriate to conclude that the use of zjrcalloy in lieu of Inconel for the fuel element spacers would involve no significant hazards consideration.
cc: Steven E. Miltenberger Sincerely, 2:::S~e!=
Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation