Event Notification Report for August 20, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/19/1999 - 08/20/1999 ** EVENT NUMBERS ** 36018 36041 36042 36043 36044 36045 36046 36047 36048 +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36018 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:46[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/10/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/19/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 | | DOCKET: 0707002 |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McCLEERY | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF 13 HIGH PRESSURE FIRE WATER SPRINKLER SYSTEMS TO MEET SYSTEM | | OPERABILITY REQUIREMENTS (24-Hour Report) | | | | The following text is a portion of a facsimile received from Portsmouth: | | | | "On 08/10/99 at approximately 1600 hours, the Plant Shift Superintendent | | (PSS) was notified that 13 sprinkler systems associated with the High | | Pressure Fire Water (HPFW) system were not capable of meeting system | | operability requirements. This condition was discovered as a result of an | | engineering review of individual sprinkler heads that had previously been | | identified as exhibiting corrosion around the valve seat. The engineering | | review was conducted following the discovery that similar corrosion problems | | experienced at the Paducah Gaseous Diffusion Plant resulted in sprinkler | | heads being unable to actuate at normal pressure. An initial screening of | | PORTS sprinkler heads known to exhibit corrosion was conducted, and systems | | where the potential for two or more adjacent heads to be corroded were | | inspected. This identified 11 systems in the X-333 and 2 systems in the | | X-326 that did not meet the sprinkler system operability requirement that no | | two adjacent sprinkler heads be inoperable." | | | | "The PSS declared the affected sprinkler systems inoperable, and TSR | | required actions were completed. Further inspections of sprinkler systems | | are planned. This report will be updated if additional sprinkler systems | | are determined to be inoperable." | | | | "There was no loss of hazardous/radioactive material or | | radioactive/radiological contamination exposure as a result of this | | event." | | | | Portsmouth personnel notified the NRC resident inspector as well as the | | onsite Department of Energy representative. | | | | *** UPDATE ON 8/19/99 AT 2327 FROM HALCOMB TO POERTNER *** | | | | During continuing walkdowns, HPFW system #398 was discovered with two or | | more (3) adjacent sprinkler heads with mineral deposits. This HPFW | | sprinkler was declared inoperable at 1038 hours and was repaired at 1407 | | hours. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36041 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/19/1999| | UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 02:48[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 08/19/1999| +------------------------------------------------+EVENT TIME: 01:00[EDT]| | NRC NOTIFIED BY: BOB MORGAN |LAST UPDATE DATE: 08/19/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF ONSITE CHEMICAL SPILL | | | | The licensee notified the Connecticut state Environmental Protection Agency | | regarding an onsite spill of sodium hypochlorite. Approximately 50 gallons | | of 50% sodium hypochlorite solution leaked from a barrel in the turbine | | building. The licensee reported that the leakage has stopped, and that the | | solution is flowing into floor drains which connect to an isolated sump (the | | licensee has disabled pumpout capability). A hazardous materials contractor | | has been retained to clean up the spill. The licensee plans to contact the | | National Response Center regarding this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36042 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/19/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:33[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/18/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:50[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/19/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON R3 | | DOCKET: 0707002 |JOSIE PICCONE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEITH WILLIAMSON | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | "On 8/18/99 at approximately 0980 hours, Operations personnel repackaging | | Dry Active Waste (DAW) in the X-326 Process Building discovered a plastic | | bag which contained between one (1) and two (2) quarts of water in the DAW | | drum. During handling, the plastic bag broke spilling its contents into the | | DAW drum. The amount of water present in the DAW drum exceeded the one quart | | of liquid allowed by Nuclear Criticality Safety Approval #NCSA-PLANT018.A02, | | which constitutes a violation of the double contingency principle (loss of | | one control). The second control (mass) was maintained throughout this | | event. The loss of one NCSA control is reportable to the NRC as a 24-hour | | Event Notification Report. | | | | "SAFETY SIGNIFICANCE OF EVENTS: The water when initially found was in a | | plastic bag. There was no visible uranium in the drum, thus there was no | | method for the water to dissolve fissile material. After the bag containing | | the water broke, it ran through the material in the drum and collected on | | the bottom of the drum. Since there was no visible uranium In the drum, the | | liquid could not adsorb sufficient tissue material to cause a noticeably nor | | could it form a shape favorable for criticality. Thus this event has a low | | safety significance. | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW | | CRITICALITY COULD OCCUR): items containing visible uranium could be placed | | into a DAW drum in violation of a NCSA control. Then free liquid could be | | placed into a DAW drum in violation of another NCSA control. The free liquid | | could dissolve the uranium. If the shape of the resulting solution is | | favorable there Is the possibility that a criticality could occur. | | | | "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | This NCSA controls the mass of uranium (no visible) and the amount of | | moderation present In a DAW drum. | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): Estimated Amount: No visible | | uranium in the DAW drum. Estimated Enrichment: Unknown, but probably less | | then 10% based on current plant operations. The NCSA assumed 100% enrichment | | for the analysis. Form: U02 F2, process limit is no visible. | | | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: Free liquid was placed in a DAW drum | | exceeding the amount allowed by NCSA-PLANT018.A02. The mass control (no | | visible uranium) from NCSA-PLANT018.A02 was maintained. | | | | "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | Nuclear Criticality Safety Engineer responded to the X326 Facility to assist | | in the assessment and safe resolution or the event. Compliance with | | NCSA-PLANT0I8.A02 was re-established at 1215 hours, 8/18/99". | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36043 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/19/1999| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:56[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/19/1999| +------------------------------------------------+EVENT TIME: 11:58[EDT]| | NRC NOTIFIED BY: CHARLIE KOCIS |LAST UPDATE DATE: 08/19/1999| | HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH MOTOR DRIVEN AUXILIARY BOILER FEEDWATER PUMPS AUTO STARTED DURING | | SURVEILLANCE ACTIVITIES. | | | | On August 19, 1999, at approximately 11:58 EDT, both motor driven auxiliary | | boiler feedwater pumps automatically started after exceeding their 28 second | | time delay during performance of the low-low steam generator water level | | section of procedure 3PT-M13B, "Reactor Protection Logic Channel Functional | | Test." The operators secured the pumps before discharge pressure exceeded | | steam generator pressure preventing them from feeding the steam generators. | | As a result, there was no positive reactivity addition. The operators | | anticipated these results because the test states in its precaution and | | limitations section that the pumps would start if the action required by the | | test is not completed within the 28 second time delay. | | | | The NRC resident inspector has been notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36044 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/19/1999| | UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 16:03[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/19/1999| +------------------------------------------------+EVENT TIME: 15:10[EDT]| | NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 08/19/1999| | HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS | | | | During the course of design documentation review, a potential condition was | | identified where in the event of a loss of offsite power and a unit trip | | with a single failure of one DC supply train, the Emergency Diesel Generator | | (EDG) load sequence would begin early. This could result in some equipment | | starting and loading earlier than the design specifies. | | | | Due to the probability of the failure, the existing operator procedurally | | driven responses, and initial review of the impact of potential loads on the | | EDG's, it is believed the EDG's are operable. | | | | This condition would have no impact on plant response to any safety | | injection signal/sequencing. | | | | A formal operability determination is underway and the plant plans to remain | | at full power. | | | | The NRC resident inspector has been notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36045 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION DATE: 08/19/1999| |LICENSEE: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION TIME: 16:24[EDT]| | CITY: IDAHO FALLS REGION: 4 |EVENT DATE: 08/19/1999| | COUNTY: STATE: ID |EVENT TIME: 13:34[MDT]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 08/19/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |LINDA HOWELL R4 | | |JOSIE PICCONE NMSS | +------------------------------------------------+JOSEPH GIITTER IRO | | NRC NOTIFIED BY: SCOTT SCHUM |WILLIAM BEECHER PAO | | HQ OPS OFFICER: WILLIAM POERTNER |YATES DOE | +------------------------------------------------+BLANCHARD EPA | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DOE ALERT DECLARED DUE TO A FIRE IN THE DESERT ON DOE CONTROLLED PROPERTY. | | | | This event was classified as an alert at 1334 MDT in accordance with | | Department of Energy (DOE) procedures. This is not a classification driven | | by the Three Mile Island Independent Spent Fuel Storage Facility (ISFSI) | | emergency plan. | | | | A range fire occurred on DOE controlled property. The Idaho Nuclear | | Engineering and Environmental Laboratory (INEEL) fire department and Bureau | | of Land Management (BLM) are fighting the fire. The fire is not threatening | | any site area. The fire is presently located 12 miles east of the ISFSI | | facility and is traveling north, away from the facility. Eight BLM rigs are | | in route to the fire. | | | | DOE made notifications per procedures to activate the Emergency Operations | | Center (EOC) and Emergency Control Center (ECC). DOE notified State and | | Local Authorities. | | | | NRC assistance was not requested. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36046 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/19/1999| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 16:50[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/19/1999| +------------------------------------------------+EVENT TIME: 12:15[EDT]| | NRC NOTIFIED BY: CHARLIE KOCSIS |LAST UPDATE DATE: 08/19/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY REPORT | | | | AT 1215 ON 08/19/99, THE LICENSEE WAS NOTIFIED OF A CONFIRMED POSITIVE DRUG | | TEST RESULT FROM A RANDOM FITNESS-FOR-DUTY TEST ON A NON-LICENSED PLANT | | EMPLOYEE. THE LICENSEE WITHDREW THE EMPLOYEE'S PLANT UNESCORTED ACCESS | | AUTHORIZATION AND REFERRED THE EMPLOYEE TO THE LICENSEE FITNESS-FOR-DUTY | | PROGRAM. THE LICENSEE IS REVIEWING THE EMPLOYEE'S WORK HISTORY BACK TO | | APRIL 1999, THE LAST TIME THE EMPLOYEE HAD SATISFACTORILY PASSED A RANDOM | | FITNESS-FOR-DUTY TEST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36047 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 08/19/1999| | UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 17:07[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/19/1999| +------------------------------------------------+EVENT TIME: 13:15[EDT]| | NRC NOTIFIED BY: LISA HILBERT-SEMMES |LAST UPDATE DATE: 08/19/1999| | HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KENNETH BARR R2 | |10 CFR SECTION: |LARRY CAMPER NMSS | |KBBF 70.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPENT FUEL STORAGE CASK SECONDARY SEAL LEAK AT THE SURRY INDEPENDENT SPENT | | FUEL STORAGE INSTALLATION | | | | At 1315 on 8/19/99, as a result of troubleshooting due to an intermittent | | low pressure alarm at the Surry Independent Spent Fuel Storage Installation | | (ISFSI) Facility, it was determined that a leak existed at the | | secondary seal on Cask #I-24. The leak rate was measured at 5.8E-2 | | mbar-liter/sec which exceeds the ISFSI Tech Spec limit of 1E-6 | | mbar-liter/sec. This is a GNSI Castor X/33 cask that was placed at the | | Surry ISFSI Facility, Pad #1 in 1994. It has been verified that there is | | still pressure between the primary and secondary lids and there is no | | evidence of a leak from the cask fuel cavity. Radiation levels at the cask | | are normal. Investigation is ongoing to determine the cause and required | | corrective actions for this issue. Both Unit 1 and Unit 2 are currently at | | 100% power. Pursuant to 10CFR72.75(b)(2) and (3), this event is being | | reported as a significant reduction in the effectiveness of a spent fuel | | storage confinement system during use. | | | | The licensee informed the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36048 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ALABAMA RADIATION CONTROL |NOTIFICATION DATE: 08/19/1999| |LICENSEE: HUNT REFINING COMPANY |NOTIFICATION TIME: 15:52[EDT]| | CITY: TUSCALOOSA REGION: 2 |EVENT DATE: 08/19/1999| | COUNTY: STATE: AL |EVENT TIME: 13:35[CDT]| |LICENSE#: AL-683 AGREEMENT: Y |LAST UPDATE DATE: 08/19/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |KENNETH BARR R2 | | |LARRY CAMPER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: J. McNESS | | | HQ OPS OFFICER: WILLIAM POERTNER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT OF A FIRE AT HUNT REFINING COMPANY, TUSCALOOSA, | | ALABAMA, (AL Incident #99-11) | | | | At 1335 on 08/18/99, Bobby Freeman, RSO at Hunt Refining Company, Alabama | | License No. 683, called the Alabama Radiation Control (ARC) and reported | | that there had been a fire at their plant around 1040 on 08/18/99 which | | lasted for about two hours. The fire had been in the vicinity of several | | Ohmart devices which contain Cs-137 radioactive sources. Mr. Freeman stated | | that none of the devices appeared to be melted or damaged when viewed from a | | few yards away. Mr. Freeman further informed ARC that a service technician | | from Ohmart was to arrive at approximately 1800 that evening to check out | | the gauges and that until that time the area within 12 to 15 feet of each | | device would be cordoned off. | | | | Hunt Refining Company does not possess radiation detection meters nor are | | they licensed to repair, relocate or service the radioactive devices. | | | | At approximately the same time as the notification from the licensee, ARC | | received a reciprocity notification from Ohmart, informing ARC that Ohmart | | was sending an employee to Hunt Refining Company to inspect and possibly | | repair or recover any damaged source holder(s) resulting from the fire. | | | | The State of Alabama decided it was not necessary to send a representative | | to the site. | | | | At the start of business on 08/19/99, ARC received reports from both the | | licensee and Ohmart, that on the evening of 08/18/99, the Ohmart | | representative inspected all radioactive devices in the area of the fire and | | found no structural damage or unusual radiation levels. One radiation | | detector located opposite the vessel from a radioactive source holder did | | sustain electrical wiring damage because of the fire and will be replaced. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Wednesday, March 24, 2021