Event Notification Report for July 10, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/07/2000 - 07/10/2000
** EVENT NUMBERS **
37148 37149 37150 37151 37152 37153
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|Power Reactor |Event Number: 37148 |
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| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/07/2000|
| UNIT: [] [2] [3] STATE: IL |NOTIFICATION TIME: 05:18[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/07/2000|
+------------------------------------------------+EVENT TIME: 02:05[CDT]|
| NRC NOTIFIED BY: DAVID THRONE |LAST UPDATE DATE: 07/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| MAIN CONTROL ROOM HVAC EMERGENCY VENTILATION DECLARED INOPERABLE |
| |
| "During performance of scheduled monthly surveillance testing, it was |
| determined that overall differential pressure on the Main Control Room HVAC |
| Emergency Ventilation Train Air Filtration Unit (AFU) was out of |
| specification high. The AFU is a single train system required to provide |
| habitable conditions for control room personnel during design basis accident |
| conditions. This condition is reportable under the requirements of SAF 1.17 |
| 'Could alone have prevented safety function.' and 10CFR50.72(b). This |
| condition places both Units in a 7 day shutdown LCO." |
| |
| The licensee will inform the NRC Resident Inspector. |
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|General Information or Other |Event Number: 37149 |
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| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 07/07/2000|
|LICENSEE: GOOD SAMARITAN HOSPITAL |NOTIFICATION TIME: 13:29[EDT]|
| CITY: PUYALLUP REGION: 4 |EVENT DATE: 07/06/2000|
| COUNTY: STATE: WA |EVENT TIME: [PDT]|
|LICENSE#: WN-M0137-1 AGREEMENT: Y |LAST UPDATE DATE: 07/07/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID GRAVES R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZEE (VIA EMAIL) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| "The licensee reported that a radioiodine therapy patient had |
| self-discharged the previous evening at 8 PM. The patient, a 45 year old |
| male, had been administered 200 millicuries of sodium iodide at |
| approximately 11 AM on Wednesday, July 5. Retained activity was determined |
| to be 60 millicuries at 9 AM and 47 millicuries at 5 PM on Thursday, July 6. |
| The patient was counseled by the authorized user as late as 5 PM on July 6 |
| as to the radiological hazard that he would present to others and he was |
| informed that hospitalization was a regulatory requirement. Nevertheless, |
| the patient had his wife pick him up from the hospital at 8 PM on July 6. |
| The estimated activity at the time of departure was 40 millicuries. The |
| licensee will determine the patient's subsequent activities and whether |
| there were any children in the home. The licensee estimated that the |
| patient would have been released at noon July 7. |
| |
| "Activity and isotope(s) involved: 40 millicuries I-131." |
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|Power Reactor |Event Number: 37150 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/07/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 15:03[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 07/07/2000|
+------------------------------------------------+EVENT TIME: 13:47[CDT]|
| NRC NOTIFIED BY: BARTON CROW |LAST UPDATE DATE: 07/07/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |88 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "This report is being made in order to comply with the requirements of |
| 10CFR50.72(b)(1)(i)A due to the initiation of a Technical Specification |
| Required Plant Shutdown. |
| |
| "At 0831 CDT while operating at 100% power Reactor Equipment Cooling (REC) |
| Pump 'C' unexpectedly tripped. This condition required entering Technical |
| Specification LCO 3.7.3 Condition B due to both REC subsystems being |
| Inoperable. REC pump 'C' is in Division 2 of REC. Division 1 of REC had been |
| declared Inoperable on 7-5-2000 at 2134 when REC pump 'A' tripped. |
| |
| "The Required Actions of LCO 3.7.3 Condition B require the Plant to be in |
| Mode 3 in 12 hours and Mode 4 in 36 hours. The first power drop occurred at |
| 1347 CDT. |
| |
| "The electrical grid is stable at this time. The cause of the REC pump 'C' |
| trip is currently under investigation. It is suspected the thermal overloads |
| on REC Pump 'A' are the cause of that pump trip and they are being replaced |
| at this time." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE 1848 7/7/00 FROM CROW TAKEN BY STRANSKY * * * |
| |
| "At 1545, both REC subsystems were declared Operable. This was based on an |
| operability determination requiring the operation of all four REC pumps, |
| which will add margin to where the pumps are operating compared to the |
| thermal overload setpoints. The Technical Specification shutdown was exited |
| at that time. Power had been lowered to approximately 80% prior to both REC |
| subsystems being declared Operable. The return to 100% power is in |
| progress." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| Notified R4DO (Graves). |
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|Other Nuclear Material |Event Number: 37151 |
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| REP ORG: U.S. ARMY |NOTIFICATION DATE: 07/07/2000|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 15:22[EDT]|
| CITY: FORT CAMPBELL REGION: 2 |EVENT DATE: 05/27/2000|
| COUNTY: STATE: KY |EVENT TIME: [CDT]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 07/07/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL JORDAN R3 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF HAVENER | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MISSING M43A1 CHEMICAL AGENT DETECTOR |
| |
| The licensee reported that one M43A1 chemical agent detector, containing 250 |
| �Ci of Am-241, had been lost during a field training exercise at Fort |
| Campbell, KY. A field artillery unit had deployed the detector in accordance |
| with the field manual, but was later unable to locate the detector. Another |
| unit may have taken the detector. |
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|Power Reactor |Event Number: 37152 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/08/2000|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 08:33[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/08/2000|
+------------------------------------------------+EVENT TIME: 04:40[EDT]|
| NRC NOTIFIED BY: GREG SOSSON |LAST UPDATE DATE: 07/08/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEVEN DENNIS R1 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |52 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNANALYZED CONDITION |
| |
| At 04:40 the Unit 2 #4 Main Turbine control valve closed. No testing or |
| maintenance was in progress at the time of the valve closure. Plant |
| Operating procedures specify that the MCPR thermal limit is not analyzed for |
| this condition. The appropriate technical specification action is being |
| entered to reduce power to below 25% power within 6 hours. Reactor power is |
| currently 52% and being reduced. |
| |
| At 07:47 it was determined that an unanalyzed condition exists on Unit 2 |
| that has the potential to compromise plant safety based on the above |
| condition. |
| |
| The cause of the control valve failure is not determined at this time. At |
| the time of the control valve closure, reactor power and pressure remained |
| stable with one main turbine bypass valve opening approximately 40%. Power |
| was immediately reduced to 95% in accordance with plant procedures. The |
| bypass valve closed. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 37153 |
+------------------------------------------------------------------------------+
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| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/08/2000|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 22:19[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/08/2000|
+------------------------------------------------+EVENT TIME: 21:07[EDT]|
| NRC NOTIFIED BY: JOHN CLAIRE |LAST UPDATE DATE: 07/08/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEVEN DENNIS 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
+------------------------------------------------------------------------------+
| UNIT OUTSIDE OF DESIGN BASIS FOLLOWING CIRCULATING WATER SYSTEM |
| BACKFLUSHING |
| |
| The licensee reported that the service water system inlet temperature |
| exceeded the design basis temperature of 75� F for approximately 9 minutes |
| following the completion of a condenser backwashing operation. Actual system |
| temperatures increased from an initial temperature of 66� F to a high of |
| 90.6� F before returning to normal. |
| |
| The licensee stated that a new procedure for cleaning the circulating water |
| system was being used; instead of elevating and holding system temperature |
| ("mussel cooking"), a high flow rate "velocity flush" was performed. The |
| flushing was performed for approximately four minutes, during which time |
| service water inlet temperatures remained normal. However, after the |
| flushing was completed, service water system inlet temperatures, as measured |
| at various system headers, increased unexpectedly. The licensee has |
| cancelled additional flushing operations that had been planned for the |
| weekend. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021