Event Notification Report for August 13, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/12/1999 - 08/13/1999
** EVENT NUMBERS **
36010 36022 36023 36024 36025 36026
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36010 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/10/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:49[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/09/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT) |
| |
| Operations personnel during a walkdown of the seal exhaust system discovered |
| that a nuclear criticality safety analysis (NCSA) requirement, maximum oil |
| volume, could not be verified when an oil level was observed in the pumps |
| separator's sight glass. The pumps in question were used for the highly |
| enriched uranium (HEU) program, and after it's suspension, prior to March |
| 1997, the pumps were placed out of service. Visible oil level in the sight |
| glass without supporting documentation for oil capacity of these pumps |
| constitutes a loss of one control (Volume) for double contingency. The |
| second control (Interaction) was maintained. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| The licensee notified the NRC resident inspector and DOE. |
| |
| *** UPDATE ON 8/12/99 @ 0130 BY SPAETH TO GOULD *** |
| |
| WALKDOWNS OF SEAL EXHAUST PUMPS IN THE X-326 BUILDING REVEALED THAT SEVERAL |
| OLD STYLE/OUT OF SERVICE PUMPS (KDH-80, DVD-8810) HAD INDICATION OF OIL IN |
| THE SEPARATOR SITE GLASS, ABOVE THE LEVEL OF THE OVERFLOW. THIS IS A LOSS |
| OF ONE CONTROL (VOLUME) OF THE DOUBLE CONTINGENCY PRINCIPLE. THE SECOND |
| CONTROL (INTERACTION) REMAINS IN PLACE. THIS UPDATE IS BEING SUBMITTED TO |
| IDENTIFY THE FACT THAT ADDITIONAL PUMPS WERE IDENTIFIED IN WHICH THE MAXIMUM |
| AMOUNT OF OIL COULD NOT BE VERIFIED. |
| |
| THE NRC RESIDENT INSPECTOR AND DOE WERE NOTIFIED BY PORTSMOUTH PERSONNEL. |
| |
| REG 3 RDO(BURGESS) AND NMSS EO(HICKEY) WERE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36022 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/12/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/11/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:35[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999|
| 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: SPAETH | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT) |
| |
| At 1235 on 08/11/99. the Plant Shift Superintendent (PSS) was notified that |
| a Nuclear Criticality Safety Approval (NCSA) requirement was not being |
| maintained in the X-333 process building. NCS Engineering, while performing |
| a pre-implementation walkdown of an NCSA, noticed a depression in the floor |
| around a building column (X-333 operating floor) that is greater than 1.5 |
| inches deep (~1.75 to 2 inches). A 12-position rack for storing small |
| diameter uranium bearing containers is located directly above the depression |
| (NCSA-PLANT025). |
| |
| Requirement #10 of NCSA-PLANT025.A01 states in part, "Storage areas shall |
| not be located over equipment or spaces that could confine a spill to a |
| depth of greater than 1.5 inches. In the event of a spill or a loss of |
| container integrity, the depression in the floor (a violation of requirement |
| #10) could result in an unfavorable geometry." |
| |
| At the direction of the PSS, the requirements for an NCS anomalous condition |
| were initiated, and the area was bounded off. |
| |
| Safety significance of the event is low, and the diked area would have to be |
| full of uranium at optimum moderated conditions for criticality to be |
| possible. Geometry was the controlled parameter that was lost. The mass of |
| material (uranium solution with a max allowed enrichment of 10%) is not |
| controlled; therefore, more than a safe mass could be in the containers. |
| |
| Corrective action was to remove all small containers from the storage area |
| and reestablish NCS compliance. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| The NRC Resident Inspector was notified, and the DOE Site Representative |
| will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36023 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/12/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 07:49[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/12/1999|
+------------------------------------------------+EVENT TIME: 04:05[EDT]|
| NRC NOTIFIED BY: ROKES |LAST UPDATE DATE: 08/12/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT HAD A REACTOR TRIP FROM 100% POWER DUE TO A LOW STEAM GENERATOR |
| LEVEL. |
| |
| AN AUTOMATIC REACTOR TRIP OCCURRED DURING A TRANSIENT ON THE 34 INSTRUMENT |
| BUS, WHICH DE-ENERGIZED FOR UNKNOWN REASONS. THIS RESULTED IN A TURBINE |
| RUNBACK AND LOSS OF AUTOMATIC CONTROL OF STEAM GENERATOR LEVEL. THE REACTOR |
| TRIP WAS GENERATED AS A RESULT OF A LOW LEVEL ON THE 33 STEAM GENERATOR. |
| AUXILIARY FEEDWATER AUTOMATICALLY STARTED AS A RESULT OF THE TRIP. ALL |
| RODS FULLY INSERTED, AND NO ECCS INJECTION OCCURRED. NO PRIMARY RELIEF |
| VALVES LIFTED, BUT ONE STEAM GENERATOR RELIEF VALVE LIFTED. (THEY HAVE NO |
| STEAM GENERATOR TUBE LEAKS.) THE PLANT IS STABLE IN HOT SHUTDOWN WITH THE |
| HEAT SINK BEING THE CONDENSER. THE CAUSE OF THE INSTRUMENT BUS TRANSIENT IS |
| UNDER INVESTIGATION. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36024 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 08/12/1999|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 16:00[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/12/1999|
+------------------------------------------------+EVENT TIME: 11:00[CDT]|
| NRC NOTIFIED BY: RICK NANCE |LAST UPDATE DATE: 08/12/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-hour report for violation of Operating License NPF-76 based on inoperable |
| control room makeup and cleanup filtration train (control room ventilation |
| system). |
| |
| In accordance with technical specification surveillance requirement |
| 4.7.7.c.2, carbon samples were removed from the Unit 1 train 'B' control |
| room makeup and cleanup filtration system on 07/19/99 and sent offsite for |
| laboratory analysis. On 08/02/99, the licensee was notified that the |
| as-found methyl iodide penetration for the makeup and cleanup filter unit |
| samples were 1.62% and 1.13%, respectively, which exceeded the required 1.0% |
| technical specification acceptance criteria. Although surveillance |
| requirement 4.7.7.c.2 allows up to 31 days to obtain charcoal sample |
| analysis results, the allowed outage time for the respective train per |
| Technical Specification 3.7.7 is 7 days. The charcoal samples were removed |
| on 07/19/99, and results were received on 08/02/99 (14 days later). Upon |
| receipt of the unsatisfactory laboratory analysis results, maintenance was |
| initiated to replace the charcoal and was completed on 08/05/99. Therefore, |
| the Unit 1 train 'B' control room makeup and cleanup filtration system was |
| in a condition prohibited by technical specifications for approximately 10 |
| days longer than the allowed outage time. |
| |
| Additionally, the Unit 1 train 'C' control room makeup and cleanup |
| filtration system was inoperable as part of a train 'C' extended allowed |
| outage time (EAOT) from 0300 CDT on 07/26/99 to 2227 CDT on 07/29/99 (based |
| on train 'C' essential chiller out-of service and return to operable status |
| times), and thus, both train 'B' and train 'C' control room makeup and |
| cleanup filtration systems were inoperable concurrently for a period of 91 |
| hours and 27 minutes. Therefore, Unit 1 had also unknowingly exceeded |
| Technical Specification 3.7.7 shutdown LCO requirements for two trains in an |
| inoperable condition by 13 hours and 27 minutes (based on a 72-hour LCO time |
| plus 6 hours to enter Mode 3). |
| |
| Furthermore, Technical Specification 3.8.1.1.d requires that with an |
| emergency diesel generator (EDG) inoperable, all required systems, |
| subsystems, trains, components, and devices that depend on the remaining two |
| operable EDGs are verified to be operable within 24 hours, or be in at least |
| Hot Standby within the next 6 hours, and in Cold Shutdown within the |
| following 30 hours. Since the train 'C' EDG was inoperable from 0300 CDT |
| on 07/26/99 until 0330 CDT on 07/29/99 (72 hours and 30 minutes) as part of |
| the train 'C' EAOT, Unit 1 had unknowingly exceeded Technical Specification |
| 3.8.1.1.d shutdown LCO requirements beginning at 0900 CDT on 07/27/99 (based |
| on a 24-hour LCO time plus 6 hours to enter Mode 3) for a total of 42 hours |
| and 30 minutes. |
| |
| Although the technical specification limit of 1.0% methyl iodide penetration |
| (or 99.0% filter efficiency) was exceeded, design basis accident analyses |
| assume a filter efficiency of 95%. Since the as-found efficiencies for both |
| the makeup and cleanup filter units were above 98%, the train 'B' control |
| room makeup and cleanup filtration system was at all times capable of |
| performing its required design function, and therefore, the overall safety |
| impact as a result of this event is believed to be minimal. |
| |
| This notification is being made pursuant to Operating License NPF-76, |
| Section 2.G, for an operation or condition prohibited by technical |
| specifications. |
| |
| This event had no impact on Unit 2. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36025 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: THERATRONICS INTERNATIONAL LIMITED |NOTIFICATION DATE: 08/12/1999|
|LICENSEE: SENTARA NORFOLK HOSPITAL |NOTIFICATION TIME: 17:11[EDT]|
| CITY: NORFOLK REGION: 2 |EVENT DATE: 08/06/1999|
| COUNTY: STATE: VA |EVENT TIME: 12:00[EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 08/12/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES OGLE R2 |
| |KEVIN RAMSEY (fax) NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DOUGLAS BEATTY, RSO | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PART 21 REPORT - DEFECT IN A GAMMAMED BRACHYTHERAPHY UNIT |
| |
| DOUGLAS BEATTY, RADIATION SAFETY OFFICER, THERATRONICS INTERNATIONAL LIMITED |
| IN KANATA, ONTARIO, CANADA, REPORTED THAT ON 08/06/99, AN Ir-192 SOURCE |
| CABLE ON A GAMMAMED BRACHYTHERAPY UNIT, MODEL #12i, SERIAL #709, LOCATED AT |
| SENTARA NORFOLK HOSPITAL IN NORFOLK, VA, FAILED TO RETRACT TO ITS SHIELDED |
| POSITION. THE SOURCE WAS MANUALLY RETURNED TO ITS SHIELDED POSITION BY A |
| THERATRONICS SERVICE TECHNICIAN ON 08/06/99. |
| |
| THE LICENSEE IS PERFORMING AN INVESTIGATION TO DETERMINE THE CAUSE OF THE |
| DEFECT AND PLANS TO SUBMIT A WRITTEN REPORT TO THE NRC. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36026 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/12/1999|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 20:40[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/12/1999|
+------------------------------------------------+EVENT TIME: 18:46[CDT]|
| NRC NOTIFIED BY: WARNER ANDREWS |LAST UPDATE DATE: 08/12/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - CONTROL ROOM CHILLER ROOM DOORS INOPERABLE DUE TO INCORRECT DOOR LATCH |
| PINS - |
| |
| AT 1846 CDT ON 08/12/99, THE LICENSEE IDENTIFIED PERSONNEL ENTRY DOORS #158 |
| AND #159 TO THE CONTROL ROOM CHILLER ROOMS #121 AND #123, RESPECTIVELY, AS |
| BEING INOPERABLE DUE TO MATERIAL PROPERTY CONCERNS OF THE LATCH PINS. AN |
| ANALYSIS SHOWED THAT THE EXISTING PINS WERE OF INADEQUATE STRENGTH TO |
| WITHSTAND HIGH ENERGY LINE BREAK FORCES. THE INOPERABILITY OF THE DOOR PINS |
| RESULTED IN THE INOPERABILITY OF BOTH TRAINS OF THE CONTROL ROOM SPECIAL |
| VENTILATION SYSTEM (TECH SPEC 3.13.A.1). |
| |
| AT 1938 CDT ON 08/12/99, THE PINS WERE REPLACED, AND THE DOORS AND CONTROL |
| ROOM VENTILATION SYSTEM WERE BOTH RETURNED TO OPERABLE STATUS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021