Event Notification Report for February 26, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/23/2001 - 02/26/2001
** EVENT NUMBERS **
37773 37774 37775 37776 37777 37778 37779 37780
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37773 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. ARMY |NOTIFICATION DATE: 02/23/2001|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 13:16[EST]|
| CITY: REGION: |EVENT DATE: 12/15/2000|
| COUNTY: STATE: |EVENT TIME: 12:00[EST]|
|LICENSE#: 19-30653-01 AGREEMENT: N |LAST UPDATE DATE: 02/23/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GLENN MEYER R1 |
| |MARK RING R3 |
+------------------------------------------------+BRIAN SMITH NMSS |
| NRC NOTIFIED BY: JOYCE KUYKENDALL | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THREE CHEMICAL AGENT MONITORS FOUND MISSING DURING AN INVENTORY CHECK. |
| |
| During an inventory check on 12/15/2000 by the First Signal Brigade Unit |
| located in Yongsan, Korea, it was discovered that 3 chemical agent monitors |
| each containing 15mCi's of Nickel-63 were found missing. An investigation |
| into the loss of the three chemical agent monitors was initiated. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37774 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 02/23/2001|
| UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 14:50[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 02/20/2001|
+------------------------------------------------+EVENT TIME: 21:09[PST]|
| NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 02/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 SHIFT SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM FITNESS |
| FOR DUTY TEST. |
| |
| "On February 20, 2001, after reporting for a non-scheduled work shift at |
| about 1800 PST, the supervisor was informed he had been selected for a |
| random fitness for duty (FFD) test. As allowed by plant procedures, the |
| supervisor entered the protected area (PA) at about 1820 PST, but not any |
| vital areas, before reporting for FFD testing at about 2000 PST. At 2019, |
| breathalyzer test results were positive for alcohol. The supervisor |
| requested that a blood sample be used for confirmatory testing. Pending |
| blood sample testing results, the supervisor's PA access was immediately |
| terminated and he was placed on investigatory suspension. |
| |
| "On February 23, 2001, during an NRC inspection exit interview, NRC |
| inspectors commented that SCE should not wait on blood testing results to |
| determine reportability of this occurrence. Consequently, even though |
| evaluation of the blood sample test results by the Medical Review Officer |
| (MRO) have not been completed, SCE is reporting this occurrence . SCE will |
| implement appropriate disciplinary actions if completion of the blood sample |
| test result evaluation by the MRO confirms the initial test results." |
| |
| The NRC Resident Inspector will be notified of this event report. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37775 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 02/23/2001|
|LICENSEE: WAHLUKE PRODUCE, INC. |NOTIFICATION TIME: 18:14[EST]|
| CITY: MATTAWA REGION: 4 |EVENT DATE: 02/18/2001|
| COUNTY: STATE: WA |EVENT TIME: 00:00[PST]|
|LICENSE#: WN-I0332-1 AGREEMENT: Y |LAST UPDATE DATE: 02/23/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZEE | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A TROXLER MODEL 4302 GAUGE AND A CPN MODEL 503 GAUGE WERE REDUCED TO CHARRED |
| METAL IN A FIRE. NO EARLY INDICATION OF RADIOACTIVE LEAKAGE. |
| |
| In the early morning of Sunday, February 18, a fire destroyed the Wahluke |
| Produce, Inc., office and potato processing building. The building was |
| also used for storage of two portable gauges containing radioactive |
| material. A Troxler Model 4302 depth probe, serial number 116, containing |
| 11 millicuries (407 megabecquerels) of americium 241/beryllium and a CPN |
| Model 503 soil probe, serial number H36066789, containing 50 millicuries |
| (1850 megabecquerels) of americium 241/beryllium, were reduced to charred |
| metal and ash. The sealed sources were stored in their shields and |
| transport boxes at the time of the fire. All records of the business were |
| destroyed in the fire, including the radioactive materials license and |
| related information such as how to contact the department. The licensee was |
| able to reach the gauge consultant who in turn notified the department on |
| February 22, 2001. Department staff responded to the scene on February 23 |
| and dug the two gauges out of approximately two feet of ash and debris. The |
| gauges were surveyed and placed in 5 gallon buckets in a secure area to |
| await retrieval by the licensee's gauge consultant that evening. There was |
| no early indication of leakage based on the department's survey and a leak |
| test and shielding evaluation will be done by the consultant. The fire |
| remains under investigation although at this time it is not believed to have |
| been arson. |
| |
| What was the notification or reporting criteria involved? WAC 246-221-250 |
| |
| Washington State Report number WA-01-006 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37776 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 02/23/2001|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 20:11[EST]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 02/23/2001|
+------------------------------------------------+EVENT TIME: 16:05[EST]|
| NRC NOTIFIED BY: JEFF DEAL |LAST UPDATE DATE: 02/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE DATA ACQUISITION AND DISPLAY SYSTEM (ERDADS) FAILED. |
| |
| At 1605 ET ERDADS CPU module overheated and failed, causing a loss of the |
| ERDADS system. ERDADS system was returned to service at 1710 ET. |
| |
| The NRC Resident Inspector will be notified by the licensee of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37777 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/24/2001|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 00:53[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/23/2001|
+------------------------------------------------+EVENT TIME: 22:20[EST]|
| NRC NOTIFIED BY: BILL WOODBURY |LAST UPDATE DATE: 02/24/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 37 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DURING PLANT SHUTDOWN |
| |
| "On 02/23/01, at 22:20 during a planned Brunswick Unit 2 reactor shutdown |
| for refueling a manual reactor scram was inserted. The sequence of events |
| was as follows. At approximately 37% reactor power a turbine EHC |
| malfunction annunciator was received and turbine bypass valves were observed |
| opening. A turbine trip occurred on generator reverse power. A generator |
| primary lockout signal caused the site's four emergency diesels to start. |
| The emergency busses remained powered from offsite power, therefore the |
| diesels did not load. With the turbine control system malfunction, a |
| manual reactor scram was inserted. An expected reactor vessel level shrink |
| occurred where level lowered to approximately 150" (normal vessel level is |
| approximately 187"). This vessel level caused a group 2 and group 6 |
| isolation signal for the respective primary containment isolation valves. |
| These valves isolated properly." |
| |
| An investigation is in progress to understand the cause of the turbine |
| control system malfunction. Other plant systems functioned as designed. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37778 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/24/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 01:13[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/23/2001|
+------------------------------------------------+EVENT TIME: 21:19[EST]|
| NRC NOTIFIED BY: PETE ORPHANOS |LAST UPDATE DATE: 02/24/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GLENN MEYER R1 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 45 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP - SAFETY/RELIEF VALVE OPENED AT POWER |
| |
| Unit 2 was manually shutdown as required by plant procedures and Technical |
| Specifications for an actuation of a single reactor coolant system |
| safety/relief valve. A rapid plant shutdown from critical at 85% power was |
| performed. The shutdown required a manual actuation of the reactor |
| protection system. All rods inserted normally on the manual scram. All |
| plant systems operated as expected. Reactor level decreased below the low |
| level 3 reactor protection setpoint immediately following the scram as a |
| result of normal system response. |
| |
| Current plant conditions: The reactor is in HOT SHUTDOWN at 106 psig |
| progressing towards COLD SHUTDOWN. Reactor level is stable being controlled |
| by condensate injection. The safety/relief valve remains open. Suppression |
| Pool Cooling is in service with pool temperature 94 degrees Fahrenheit. |
| |
| The 2N SRV was the one that opened. The licensee had been in the process of |
| shutting down to make repairs to this valve when it fully opened. It is |
| believed to have a faulty pilot valve. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE AT 0859 ON 2/24/01 BY RICH RECEIVED BY WEAVER * * * |
| |
| The 2N reactor coolant safety/relief valve reseated at 130 psig reactor |
| coolant pressure. The MSIVs were reopened and plant cool down continued. |
| Unit 2 is currently in OPCON 4 with the "2B" Loop of Shutdown Cooling in |
| service. Reactor coolant temperature is less than 200 degrees F. The |
| licensee notified the NRC resident inspector. R1DO (Meyer) notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37779 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/24/2001|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 03:24[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/24/2001|
+------------------------------------------------+EVENT TIME: 03:06[EST]|
| NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 02/24/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GLENN MEYER R1 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFEGUARDS DEGRADATION RELATED TO AREA BOUNDARY |
| |
| IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. ADDITIONAL DETAILS MAY |
| BE OBTAINED FROM THE OPERATIONS CENTER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37780 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 02/24/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 18:04[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 02/24/2001|
+------------------------------------------------+EVENT TIME: 15:10[CST]|
| NRC NOTIFIED BY: J. TEMPLE |LAST UPDATE DATE: 02/24/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK RING R3 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |FRANK CONGEL IRO |
|*IND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) AND BOTH INJECTION PATHS OF LOW |
| PRESSURE COOLANT INJECTION (LPCI) DECLARED INOPERABLE. |
| |
| |
| HPCI and both injection paths of LPCI have been declared inoperable as a |
| result of not meeting inservice testing of injection check valves as |
| required by Technical Specification 4.15.B. Technical Specification |
| shutdown required by Technical Specification 3.5.A (4), be in a Hot Shutdown |
| condition within 24 hours (start time 1510 CT) . Plant shutdown commenced at |
| 1608 CT. |
| |
| Licensee was reviewing ASME Code Section XI requirements as a result of a |
| snubber problem encountered last week. While reviewing ASME Code Section XI |
| requirements it was determined that HPCI and LPCI injection test valves may |
| not meet ASME Code Section XI inservice testing requirements as specified |
| per their Technical Specification. The reactor has to be shutdown in order |
| to test the LPCI injection test valves since personnel have to enter the |
| drywell. A soft shutdown of the reactor will be performed (the reactor |
| will not be scrammed from power). All other Emergency Core Cooling Systems |
| and the Emergency Diesel Generators are fully operable if needed. Electrical |
| grid is stable. |
| |
| The NRC Resident Inspector will be notified by the licensee of this event. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021