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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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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."                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37150       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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).                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37151       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING M43A1 CHEMICAL AGENT DETECTOR                                        |
|                                                                              |
| The licensee reported that one M43A1 chemical agent detector, containing 250 |
| ÁCi 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.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37152       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37153       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.  |
+------------------------------------------------------------------------------+