Event Notification Report for January 5, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/04/2001 - 01/05/2001 ** EVENT NUMBERS ** 37645 37646 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37645 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 01/04/2001| |LICENSEE: ANCORE (SAIC) |NOTIFICATION TIME: 12:01[EST]| | CITY: SAN DIEGO REGION: 4 |EVENT DATE: 12/15/2000| | COUNTY: STATE: CA |EVENT TIME: 12:00[PST]| |LICENSE#: 2484-43 AGREEMENT: Y |LAST UPDATE DATE: 01/04/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |WILLIAM JOHNSON R4 | | |BRIAN SMITH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ROB GREGER | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | ANCORE (previously SAIC) had requested to delete three nuclides from their | | CA RML. One of the items ANCORE asked to be deleted were fuel rods | | containing SNM. A letter for additional information concerning | | transfer/disposal of the fuel rods went out on May 25, 2000 but received no | | response. Tom Schell contacted the current RSO, David Mahood. Mr. Mahood | | stated that the fuel rods were sent to Combustion Engineering before he came | | to ANCORE. Mr. Mahood further added that his questions to the previous RSO | | failed to produce any new information or documents concerning the fuel rods. | | Tom Schell also contacted Brian Horn of the US NRC and the US Nuclear | | Tracking Database confirms the transfer of the three fuel rods to SAIC in | | San Diego, a different California license, in September 1989. A review of | | the Compliance and Licensing Folders SAIC's San Diego License (License | | Number 2290-37) was done but independent confirmation relating to the | | receipt of fuel rods containing SNM at SAIC in San Diego were not found. A | | Note: California regulations only require record keeping for three years, | | however 10 CFR 150.16 appears to have been violated. Personnel of | | California Radiologic Health Branch were informed. | | | | STATE OF CALIFORNIA REPORT NUMBER CA010003 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37646 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: HOLTEC INTERNATIONAL |NOTIFICATION DATE: 01/04/2001| |LICENSEE: HOLTEC INTERNATIONAL |NOTIFICATION TIME: 15:59[EST]| | CITY: MARLTON REGION: 1 |EVENT DATE: 10/18/2000| | COUNTY: STATE: NJ |EVENT TIME: 12:00[EST]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/04/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MELVYN LEACH R3 | | |VERN HODGE, FAX NRR | +------------------------------------------------+ | | NRC NOTIFIED BY: BRIAN GUTHERMAN | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION FOR DISCREPANT WEIGHT OF SPENT FUEL RACKS | | | | Spent fuel tacks removed from Byron Nuclear Power Plant were discovered to | | have as-found weights ranging from approximately 8,200 to 10,500 lbs more | | than the weights used in the analyses supporting the original design and | | licensing of these racks and in the design of the lifting equipment used to | | lift the racks. The analyses related to seismic loadings, bearing pad | | design, spent fuel pool liner fatigue, and possibly others used to design | | and license these racks may no longer be conservative when the additional | | weight is considered. The actual impact on these analyses has not, to our | | knowledge, been evaluated. The impact on the design of the lifting | | equipment is that the design safety factors for the lifting equipment, while | | still above 1.0, may not meet the minimum safety factors in NUREG-0612 and | | associated reference documents. | | | | Braidwood Nuclear Station has four similarly designed racks provided by the | | same supplier. | +------------------------------------------------------------------------------+
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