U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/28/2003 - 03/31/2003
** EVENT NUMBERS **
39709 39711 39712 39713 39714
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|Power Reactor |Event Number: 39709 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 03/28/2003|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 02:28[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/28/2003|
+------------------------------------------------+EVENT TIME: 00:45[EST]|
| NRC NOTIFIED BY: JIM GROOM |LAST UPDATE DATE: 03/28/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Refueling |0 Refueling |
| | |
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EVENT TEXT
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| POTENTIAL MEDIA INTEREST DUE TO STATE POLICE SEARCH OF THE OWNER CONTROLLED |
| AREA |
| |
| The Calvert Control Center in Prince Frederick County received an anonymous |
| call through the 911 operator which prompted the Maryland State Police to |
| furnish additional officers to the site for a search of the woodline area of |
| the owner controlled property. The licensee will inform their media group |
| due to the potential media interest and has informed both state/local |
| agencies and the NRC resident inspector. |
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|General Information or Other |Event Number: 39711 |
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| REP ORG: FOX CHASE CANCER CENTER |NOTIFICATION DATE: 03/28/2003|
|LICENSEE: FOX CHASE CANCER CENTER |NOTIFICATION TIME: 14:30[EST]|
| CITY: PHILADELPHIA REGION: 1 |EVENT DATE: 04/16/2000|
| COUNTY: STATE: PA |EVENT TIME: [EST]|
|LICENSE#: 37-02766-01 AGREEMENT: N |LAST UPDATE DATE: 03/28/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PAMELA HENDERSON R1 |
| |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KAREN SHEEHAN | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NRC LICENSEE TRANSFERRED RADIOACTIVE MATERIAL TO UNLICENSED ENTITY |
| |
| On April 16, 2000, the licensee transferred a Varian 6/100 linear |
| accelerator, with a 41 millicurie depleted uranium source, to Centura X-Ray, |
| Cleveland, Ohio, an unlicensed entity. The transfer was part of an equipment |
| upgrade made between the licensee and Siemens Medical Systems Inc. |
| |
| Siemens sold the Varian 6/100 to Linac Systems, Lakewood, New Jersey who in |
| turn sold the equipment to eRad Therapy, Inc. of Bothell, Washington. eRad |
| Therapy transported the device to the therapy division of Centura X-ray. |
| |
| The depleted uranium is currently in the possession of a licensed low level |
| waste storage facility awaiting burial at an appropriate waste disposal |
| facility. |
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|Power Reactor |Event Number: 39712 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/29/2003|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 04:44[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/29/2003|
+------------------------------------------------+EVENT TIME: 02:55[EST]|
| NRC NOTIFIED BY: EDWEN URQUHART |LAST UPDATE DATE: 03/29/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 1 Startup |1 Startup |
| | |
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EVENT TEXT
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| HPCI TURBINE FAILS TO COME TO SPEED DURING SURVEILLANCE TEST |
| |
| "While starting up Unit Two reactor from a planned refueling/maintenance |
| outage, the HPCI system would not pass the required tech spec surveillance |
| when tested at 160 psig reactor pressure. The HPCI turbine failed to come |
| up to speed due to its turbine steam control valve did not open after the |
| turbine stop valve was opened per system operability surveillance. The |
| system engineer and maintenance are investigating the speed control circuit |
| at this time." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39713 |
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| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/29/2003|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 07:15[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/29/2003|
+------------------------------------------------+EVENT TIME: 04:42[EST]|
| NRC NOTIFIED BY: JOHN GARECHT |LAST UPDATE DATE: 03/29/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAMELA HENDERSON R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 80 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO LOSS OF SECONDARY CIRCULATING WATER PUMPS |
| |
| "Salem Unit 2 was manually tripped in response to loss of circulating water |
| pumps. Loss of circulators was caused by heavy grass intrusion from the |
| Delaware River. At time of trip, a load reduction was in progress and power |
| level was approximately 80%. All safety systems operated as designed during |
| and after the reactor trip. Unit 2 is currently stable in Mode 3 at normal |
| operating temperature and pressure. All reactor cooling pumps are in |
| service and core cooling is being supported by auxiliary feedwater pumps and |
| main steam dumps to the condenser. No safety systems or equipment was out |
| of service at the time of the trip. Salem Unit 1 was also affected by the |
| heavy river grass conditions and is currently in Mode 1 and stable at 55% |
| reactor power." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39714 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/29/2003|
| UNIT: [] [] [3] STATE: AZ |NOTIFICATION TIME: 13:41[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/29/2003|
+------------------------------------------------+EVENT TIME: 04:00[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 03/29/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Hot Shutdown |0 Hot Shutdown |
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EVENT TEXT
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| DEGRADED CONDITION DUE TO LEAKAGE AT SMALL BORE INCONEL 600 PENETRATIONS |
| |
| The following information was received from the licensee via facsimile: |
| |
| "The following event description is based on information currently |
| available. If through subsequent reviews of this event, additional |
| information is identified that is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 10CFR50.73. |
| |
| "On March 29, 2003, at approximately 04:00 Mountain Standard Time (MST) |
| engineering personnel performing preplanned visual examinations of reactor |
| coolant System (RCS) piping in accordance with procedure requirements |
| discovered boric acid residue on three RCS small bore Inconel 600 |
| penetrations. One location was the RCS hot leg in-service thermowell |
| 3JRCBTW0112HB. The visual observation was characterized as a small white |
| trail of boron residue running down the hot leg approximately 2 inches. |
| There were no signs of dripping, spraying, puddles of liquid, or liquid |
| running down the nozzle or hot leg. The residue appeared dry. The other two |
| were on pressurizer heater sleeves (nozzles) A-4 and A-18. The visual |
| observation at these two locations was characterized as a small white |
| buildup of boron residue around the heater sleeve as the sleeve enters the |
| pressurizer bottom head. There does not appear to be residue running down |
| the outside of the sleeves. There were no signs of dripping, spraying, |
| puddles of liquid, or liquid running down the nozzle or [pressurizer]. The |
| residue appeared dry. |
| |
| "Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.14 |
| permits no reactor coolant system (RCS) pressure boundary leakage and |
| therefore, the discovery of leakage (presumed boric acid residue) from the |
| hot leg thermowell and the pressurizer heater sleeves was a degradation of a |
| principal safety barrier. Therefore, the ENS notification of this event is |
| in accordance with 10CFR50.72(b)(3)(ii). The control room personnel entered |
| LCO 3.4.14 Condition B and are continuing to place the plant in Mode 5. The |
| RCS was being cooled down in preparation for Unit 3's tenth refueling |
| outage. At the time of discovery, the RCS was at approximately 520 degrees F |
| and 2218 psia. |
| |
| "An investigation of this event will be conducted in accordance with the |
| PVNGS [Palo Verde Nuclear Generating Station] corrective action program. The |
| cracking of Alloy 600 components both at Palo Verde and industry-wide has |
| been attributed to axially oriented, primary water stress corrosion cracking |
| (PWSCC). PWSCC is not considered a significant threat to the structural |
| integrity of the RCS boundary, thermowell, or heater sleeves as this type of |
| cracking typically results only in small leaks. |
| |
| "The bases for this conclusion is that if PWSCC occurred at Palo Verde, the |
| cracks would be predominately axial in orientation. As in this case, the |
| cracks would result in visibly detectable leakage that would be apparent |
| during visual examinations, performed as part of walkdown inspections, |
| before significant damage to the reactor coolant boundary occurred. |
| |
| "Palo Verde has a program for replacing the Alloy 600 hot leg thermowells. |
| This thermowell was scheduled for replacement during this refueling outage. |
| The plans to replace the thermowell remain unchanged. |
| |
| "A mechanical nozzle sleeve assembly (MNSA) will be installed on each of the |
| pressurizer heater sleeves. |
| |
| "No ESF actuations occurred and none were required. There were no |
| structures, systems, or components that were inoperable at the time of |
| discovery that contributed to this condition. There were no failures that |
| rendered a train of a safety system inoperable and no failures of components |
| with multiple functions were involved. The event did not result in the |
| release of radioactivity to the environment and did not adversely affect the |
| safe operation of the plant or health and safety of the public." |
| |
| The licensee has informed the NRC Resident Inspector. |
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