Event Notification Report for May 13, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/12/2003 - 05/13/2003 ** EVENT NUMBERS ** 39838 39840 39841 39842 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39838 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 05/12/2003| | UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 03:28[EDT]| | RXTYPE: [1] W-3-LP |EVENT DATE: 05/12/2003| +------------------------------------------------+EVENT TIME: 01:02[EDT]| | NRC NOTIFIED BY: EDDIE BYARS |LAST UPDATE DATE: 05/12/2003| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 100 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO MAIN GENERATOR OUTPUT BREAKER | | OPENING | | | | Main Generator output breaker opened after receiving Main Generator voltage | | regulator # 1 (core 1) & # 2 (core 2) alarms causing an automatic turbine | | trip followed by an automatic reactor trip (first out annunciator was over | | temperature differential temperature). All rods fully inserted into the | | core. Both motor driven auxiliary feedwater pumps were manually started to | | maintain reactor coolant temperature and proper steam generator water | | levels. Steam is being dumped to the main condenser. Emergency Operating | | procedure 1.0 entered and then Emergency Operating procedure 1.1, Reactor | | Recovery Procedure was entered. All emergency core cooling systems and the | | emergency diesel generators are fully operable if needed. The licensee | | believes that the main generator exciter breaker opened before the main | | generator output breaker opened. No work was going on in the area of the | | main generator when the output breaker opened. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 39840 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: STATE OF MISSOURI |NOTIFICATION DATE: 05/12/2003| |LICENSEE: MISSOURI DEPT. OF TRANSPORTATION |NOTIFICATION TIME: 14:57[EDT]| | CITY: JEFFERSON CITY REGION: 3 |EVENT DATE: 05/10/2003| | COUNTY: COLE STATE: MO |EVENT TIME: 18:00[CDT]| |LICENSE#: 24-20415-01 AGREEMENT: N |LAST UPDATE DATE: 05/12/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |SONIA BURGESS R3 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: BETH BROWN | | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST AND THEN RECOVERED TROXLER ASPHALT CONTENT GAUGE | | | | The following information was obtained from the licensee via facsimile: | | | | "On Saturday evening, May 10, 2003, at approximately 6:00 pm [CDT], a | | tornado wiped out a trailer at an asphalt plant that contained an asphalt | | nuclear gauge 3241 [Troxler]. The gauge was in its gray shipping container | | that was locked inside a metal case, which was bolted to the floor. The | | gauge was found about 100 feet from the trailer site out of the metal box, | | but the gray shipping case was still intact. It did not appear to be | | damaged. The contractor, Chester Bross Construction Company, found the gauge | | and stored it in their plant shack with their gauge. Their Safety Director, | | [DELETED], also came up on Sunday morning and took readings. Neither gauge | | appeared to be leaking." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 39841 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TRIPLER ARMY MEDICAL CENTER |NOTIFICATION DATE: 05/12/2003| |LICENSEE: TRIPLER ARMY MEDICAL CENTER |NOTIFICATION TIME: 17:32[EDT]| | CITY: HONOLULU REGION: 4 |EVENT DATE: 05/12/2003| | COUNTY: STATE: HI |EVENT TIME: 11:00[HST]| |LICENSE#: 53-00458-04 AGREEMENT: N |LAST UPDATE DATE: 05/12/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |LINDA SMITH R4 | | |SONIA BURGESS R3 | +------------------------------------------------+MELVYN LEACH NMSS | | NRC NOTIFIED BY: MAJ. ARTHUR MORTON, USA |MATT HAHN IAT | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR MATERIAL MISSING DURING SHIPMENT | | | | | | The following information was received from the licensee via facsimile: | | | | "An order for 150 milli-curies (mCi) of iodine-131 was placed with | | Mallinckrodt on May 9, 2003. The package was received by the Nuclear | | Pharmacist,[DELETED], on May 12, 2003 and indicated that the package had | | 154.10 mCi of iodine-131 but was measured to contain only 54.0 mCi of | | iodine-131. | | | | "At 11:00 [HST] the Nuclear Pharmacist paged me and I immediately went to | | the Nuclear Pharmacy laboratory. I verified that the dose calibrator was | | set on I-131and inquired about the package receipt procedures. The Nuclear | | Pharmacist indicated that the package was in excellent condition with no | | sign of physical damage. The package was received in a timely manner, | | metered and swiped without incident. The package contained two vials | | supposedly containing 140.00 mCi and 14.10 mCi of iodine-131 for a total of | | 154.10 mCi. The contents of the package appeared to be intact. The Nuclear | | Pharmacist combined the two vials and assayed the dose in the dose | | calibrator for an iodine ablation therapy but measured only 54.0 mCi of | | I-131. | | | | "At 11:20 I notified Mallinckrodt of the discrepancy, and then at 11:30 I | | notified the NRC Operations Center to report the missing licensed material | | in accordance with 10 CFR Part 20.2201(a)(1)(i). I will also contact the | | shipper, MMS Courier, and the Army Medical Command as well as any local or | | state notifications that are required." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 39842 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/12/2003| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:08[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/12/2003| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/12/2003| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |SONIA BURGESS R3 | | DOCKET: 0707001 |MELVYN LEACH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: THOMAS WHITE | | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF ONE OF TWO CONTROLS ON MODERATION | | | | NRC BULLETIN 91-01 24 HOUR NOTIFICATION | | | | The following information was received from the licensee via facsimile: | | | | "At 0900 on 5/12/03, the Plant Shift Superintendent (PSS) was notified that | | differential pressure transmitter inputs for three Freezer/Sublimers, | | U/2(Unit # 2) C/B (Cell B), U3 C/B and U/4 C/B located in C-337, were | | installed incorrectly. The transmitter (PDT-338) measures the differential | | pressure between the R-114 (freon) and the Recirculating Cooling Water | | (RCW). NCSA CAS-001 requires that the pressure differential between the | | R-114 and RCW pressures be such that the R-114 pressure is at least 2.0 psia | | above the RCW pressure. This would preclude the introduction of a moderator | | (RCW) into the process side of the system. The correct configuration of | | these inputs has the pressure tap on the inlet line to the | | condenser/reboiler. For Freezer/Sublimers U/2 C/B, U/3 C/B and U/4 C/B the | | pressure tap is located on the outlet line from the condenser/reboiler. As | | installed, the low differential pressure-alarm may not come in until after | | the R-114 pressure and RCW pressure at the inlet of the Condenser/Reboiler | | have exceeded the NCS limit. At 1040 on 5/12/03, the PSS was notified by | | Nuclear Criticality Safety that one of the two controls on moderation had | | been lost. | | | | The System Engineer identified four additional Freezer/Sublimers, two in | | C-331 and two in C-335, with the same problem. These Freezer/Sublimer units | | were out-of-service and the RCW had been drained prior to the walk-down. , | | | | | | SAFETY SIGNIFICANCS OF EVENTS: | | | | Although high side Condenser/Reboiler pressure readings could not be taken | | due to incorrect installation of an AQ-NCS pressure instrument, the | | integrity of the F/S tubes has been maintained. All of the | | Condenser/Reboilers had the RCW drained by 1345 hours on 5-12-03. thus | | re-establishing double contingency. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(s) OF HOW | | CRITICALITY COULD OCCUR) | | | | In order for a criticality to be possible, an unsafe mass of uranium would | | have to be present within the Freezer/Sublimer unit and a moderator would | | have to enter through the Freezer/Sublimer and Condenser/Reboiler tubes. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION,ETC.) | | | | Double contingency is maintained by implementing two controls on | | moderation. | | | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE CRITICAL MASS): | | | | For the 20 MW Freezer/Sublimers, less than a safe mass of uranium, at less | | than or equal to (LEU) U235. | | For the 10 MW Freezer/Sublimers, less than a safe mass of uranium, at less | | than or equal to (LEU) U235 | | | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIFNCIES | | | | The first leg of double contingency relies on Freezer/Sublimer and | | Condenser/Reboiler tube integrity. Since high UF6 pressure alarms or other | | operational indicators, caused by leaking R-114 into the Freezer/Sublimer, | | have not been received on the Freezer/Sublimer units, the integrity of the | | Freezer/Sublimer tubes has been maintained. Therefore, this leg of double | | contingency was maintained. | | | | The second leg of double contingency relies on the differential pressure | | between the R-114 and RCW, controlling the differential pressure such that | | the R-114 is maintained at least 2.0 psi above the RCW precludes the | | introduction of RCW to the process side of the unit. Monitoring the RCW | | pressure on the outlet to the Condenser/Reboiler, instead of the inlet, does | | not give correct differential pressure readings. Therefore. This leg of | | double contingency was not maintained. | | | | Even though the moderation parameter was maintained through integrity of the | | Freezer/Sublimer and Condenser/Reboiler tubes, double contingency Is based | | on two controls on moderation. Thus, double contingency was not maintained. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLFMENTED: | | | | 1. Drain Condenser/Reboiler RCW for the affected Freezer/Sublimer units. | | Completed at 1345 on 5-12-03. | | 2. Correct the installation of the pressure taps In accordance with the | | approved Engineering drawings. Complete prior to returning Freezer/Sublimors | | to service | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021