PNO-IV-87-037, on 870814,licensee Measured Breakthrough of Mo-99 During First Elution of New England Nuclear Tc-99m Generator.No Contaminated Radiopharm Dispensed.Generator Returned to Mfg for Further Analysis
| ML20237G268 | |
| Person / Time | |
|---|---|
| Site: | 03020964 |
| Issue date: | 08/14/1987 |
| From: | Spitzberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| References | |
| PNO-IV-87-037, PNO-IV-87-37, NUDOCS 8708240026 | |
| Download: ML20237G268 (1) | |
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August 14, 1987 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-IV-87-37 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region IV staff on this date.
FACILITY: Syncor Corporation Licensee Emergency Classification:
Oklahoma City, Oklahoma Notification of Unusual Event Alert Site Area Emergency General Emergency X Not Applicable (
SUBJECT:
REPORT OF M0LYBDENUM-99 BREAKTHROUGH ON TECHNETIUM-99m GENERATOR The licensee reported that on the morning of August 14, 1987, they measured a breakthrough of Mo-99 during the first elution of a technetium-99m generator.
The measured Mo-99 activity was a 24 mci fraction of the estimated 3000-3200 mci elution. None of the contaminated radiopharmaceutical was dispensed. The 2.7 Ci generator was manufactured by New England Nuclear, lot 8732-2F-37, expiration 8/26/87. The generator is being returned at the manufacturer's request for further analysis.
Neither the licensee nor the NRC plans to issue a press release.
The state of Oklahoma will be informed.
Region IV received notification of this occurrence by telephone from the licensee at 11:00 a.m., 8/14/87. Region IV has informed NMSS.
This information has been confirmed with a licensee representative.
CONTACT: D. Blair Spitzberg, FTS 728-8191 DISTRIBUTION:
MAIL:
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PDR NRR RRI DCS NRC OC LICENSE T Regional Offices (Reactor Licensee)
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hB2g268'0814 PNO-IV-87-037 PDR