ML20235M158
| ML20235M158 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1987 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Thompson H NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-39, REF-PROJ-M-41 NUDOCS 8710060081 | |
| Download: ML20235M158 (3) | |
Text
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SEP 3 01987 i
MEMORANDUM FOR: Hugh L. Thompson, Jr., Director Office of Nuclear Material Safety and Safeguards 1
THRU:
Richard E. Cunningham, Director Division of Industrial and Medical Nuclear Safety FROM:
Leland C. Rouse, Chief Fuel Cycle Safety Branch
SUBJECT:
ITEMS OF INTEREST UF6 CYLINDER VALVES As recommended by the Department of Energy (DOE), the NRC Order issued on August 19, 1987, prohibiting the use of 1-inch valves used in 30- and 48-inch UF cylinders manufactured by Superior Valve Company in lots 16-22 has been g
modified. The modification issued on September 25, 1987, permitted NRC licensees to use valves in lot 16. All other lots of these valves, lots 17-22, i
remain restricted for use. The DOE has made similar recommendations to its customers.
The valves in lots 17-22 remain restricted from use because of cracks observed in the threads of some valves in these lots. Preliminary investigation by the DOE indicates that the casting of the alloy of these lots may have been improperly performed. Casting of lot 16 was performed in an earlier time frame than the affected lots.
Release of lot 16 for use permits the industry to use approximately 550 valves now in service.
DRY SPENT FUEL STORAGE APPLICATION By letter dated Septembe'r 14, 1987, Duke Power Company with NUTECH Engineers, Inc., has stated its intent to apply by April 1,1988, for a license under 10 CFR Part 72 for dry storage of spent fuel on its Oconee Nuclear Station site.
To facilitate this application NUTECH will submit by January 4, 1988, an amendment to its currently approved topical report for its NUHOMS concrete module dry storage system design. The modified NUHOMS design will be incorporated in the Duke application.
Duke seeks to have dry storage available by January 1,1990 to meet its spent fuel storage needs.
FUEL CYCLE SAFETY MEETING On September 22 and 23, 1987, the NRC representative attended the biannual meeting of the Fuel Cycle Safety Working Group of the Committee for Safety of Nuclear Installation, Nuclear Energy Agency, in Paris. Topics covered by representatives of member nations included (1) the future of the Fuel Cycle Safety Working Group in light of NEA budgetary constraints; (2) commencement 8710060001 870930 "
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SEP 3 01987 Hugh L. Thompson, Jr.
2 of a needed updating of the Report on the Fuel Cycle (CSNI S0AR No, 3) in light of significant technical and quantitative developments in the fuel cycle, particularly with respect to reprocessing and enrichment; and (3) plans for a specialists' meeting on Fire Protection and Firefighting in Nuclear Fuel Cycle Facilities in January 1989. The tentative meeting place for the 1989 meeting is the BNFL: reprocessing facility at Sellafield in the United Kingdom.
DRY SPENT FUEL STORAGE CASK APPROVAL On September 30, 1987, a letter of approval with a related safety evaluation report was issued for the topical report submitted by Westinghouse for its q
Model MC-10 dry spent fuel storage cask design. The Westinghouse MC-10 Cask is i
a forged steel cylinder approximately 16 feet in length with a diameter of j
about 8 feet, a steel wall thickness of 10 inches and a solid neutron shield of 3 inches. Loaded cask weight is about 113 tons with a cask capacity of 24 PWR assemblies. Spent fuel must have a burnup less than or equal to 35,000 MWD /MTU q
and must have decayed at least 10 years to be stored in the MC-10 cask.
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Another metal dry storage cask design previously approved by the NRC, the GNSI CASTOR V, which is fabricated of nodular cast iron and has a capacity of 21 PWR assemblies, is now being used for spent fuel storage at the Virginia Power i
Surry Station.
Originni Signed BY:
Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and I
Medical Nuclear Safety
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