Event Notification Report for January 31, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/30/2003 - 01/31/2003
** EVENT NUMBERS **
39439 39539 39546 39547 39548
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39439 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/12/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 00:20[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 12/11/2002|
+------------------------------------------------+EVENT TIME: 18:13[EST]|
| NRC NOTIFIED BY: JIM CASE |LAST UPDATE DATE: 01/30/2003|
| HQ OPS OFFICER: JASON FLEMMING +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
|AIND 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 |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| RHR B MINIMUM CONTROL FLOW VALVE INOPERABLE |
| |
| "Scheduled maintenance activities were being performed on RHR B minimum flow |
| valve 1E12-F064B which is a containment isolation valve. When the E12-F064 B |
| power supply was energized the Control Room indication for the valve |
| indicated intermediate. Local indication for the valve indicated the valve |
| was closed. When the valve control switch was taken to closed the valve was |
| observed to move 1/16 of an inch and the control room indication changed to |
| full close. The valve was closed and verified down powered on 12/09/02 to |
| comply with Tech Spec 3.6.1.3 Primary Containment Isolation Valves. |
| Maintenance test equipment was installed however no maintenance had been |
| performed." |
| |
| Licensee informed NRC resident inspector. |
| |
| *** RETRACTION ON 01/30/03 AT 1016 ET BY MR. RUSSELL TAKEN BY MACKINNON *** |
| |
| "Subsequently, an engineering evaluation that utilized the valve as-found |
| test data concluded that the valve stem loading was reduced. This resulted |
| in the intermediate valve position when the valve breaker was re-energized. |
| It was also determined that although the valve stem load was reduced, the |
| valve disc remained tightly seated in the closed position. |
| |
| "The valve provides isolation for a containment penetration that interfaces |
| with a closed system outside containment. Since the valve was determined to |
| have remained closed, and the closed system outside containment had not been |
| breached, there was no loss of the containment accident mitigation function |
| and no loss in the control of radiation release function. Since neither of |
| these two functions was lost, there was no reportable condition, and this |
| Event Notification (EN# 39439) is retracted." R3DO (Mark Ring) notified. |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
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|General Information or Other |Event Number: 39539 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 01/27/2003|
|LICENSEE: ISOTOPE PRODUCTS LABORATORIES |NOTIFICATION TIME: 15:16[EST]|
| CITY: BURBANK REGION: 4 |EVENT DATE: 01/23/2003|
| COUNTY: LOS ANGELES STATE: CA |EVENT TIME: 16:30[PST]|
|LICENSE#: CA-1509 AGREEMENT: Y |LAST UPDATE DATE: 01/27/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JONES R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+TIM MCGINTY IRO |
| NRC NOTIFIED BY: ROBERT GREGER |CREWS NRC |
| HQ OPS OFFICER: GERRY WAIG |JOHN HICKEY NMSS |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - CONTAMINATED PACKAGE |
| |
| The following is taken from a facsimile from the State of California: |
| |
| "On 1/24/03 the RSO [Radiation Safety Officer] @ IPL [Isotope Products |
| Laboratories] reported their receipt of a contaminated package. The package |
| had been picked up from LAX & delivered to IPL on 1/23 @ 2:25 pm by Kamino |
| Int'l Transport, 2580 Santa Fe, Redondo Beach, contact person [DELETED]. The |
| package was wiped upon receipt, and received the results approximately 4:30 |
| pm. The RSO was notified the next morning. The contamination appears to be |
| H-3, although the licensee needs to perform an energy calibration on their |
| liquid scintillation counter to verify both this and their quantification of |
| the package wipes. It appears that all sides of the package were |
| contaminated, at up to approximately 100,000 dpm/wipe. The latest wipes |
| measured up to approximately 40,000 dpm/wipe. |
| |
| "The package came from a company in Switzerland called RC Tritec AG, who is |
| a distributor for a Russian company (unknown name at this time). IPL |
| believes that the box was trans-shipped, & was never actually at Tritec, but |
| they're still trying to get Lufthansa's paperwork. IPL is also trying to get |
| info on the Russian company. |
| |
| "IPL had the delivery truck return to IPL, & they found a small area of |
| contamination, about 12 X 10 inches, on the carpet, where the package was |
| located, of about 800 dpm/wipe. After vacuuming, they got nothing. About 11 |
| other wipes in the truck were negative. They checked the driver's gloves- |
| there's no removable contamination. All wipes @ IPL's Shipping Dept were |
| negative. They think there was at least one other package on the truck that |
| was destined for an electronics company, but they're still trying to get |
| info on that. There was at least one other package for IPL on the truck that |
| was not contaminated (they're checking to see if it had come from the same |
| Russian company). |
| |
| "Note: Assuming that the contamination is H-3, the dose consequences of |
| 100,000 dpm/wipe are approximately equivalent to the dose consequences of |
| 2.5 dpm/wipe of Cs-137." |
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|Power Reactor |Event Number: 39546 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 01/29/2003|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 20:57[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/29/2003|
+------------------------------------------------+EVENT TIME: 20:32[EST]|
| NRC NOTIFIED BY: VAL MANCE |LAST UPDATE DATE: 01/30/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |J. BRADLEY FEWELL R1 |
|10 CFR SECTION: |WILLIAM RULAND NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO |
| |DORA HEYMAN FEMA |
| |P.O. BAUMGARTNER EPA |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| NOUE DECLARED AT SUSQUEHANNA DUE TO NON-ROUTINE RADIOACTIVE GAS RELEASE |
| |
| "At 8:32 pm EST PPL Susquehanna , LLC, declared an Unusual Event for an |
| Airborne Release. The EAL entered was 15.1.a A.2, I-131 > 2.08E+2 |
| microcuries/minute. Chemistry sample did not indicate any Iodine in the |
| release steam, however Cs-138 was detected in the sample which may have |
| affected the vent stack monitor. Investigation continues. The release is |
| being monitored by the plant Vent Stack monitoring system. The source of the |
| release is unknown at this time. Plant procedures are being implemented to |
| determine and isolate the source. Offsite monitors have been activated to |
| monitor offsite dose rates. Activation of the Emergency plan and Offsite |
| releases are reportable under 10CFR50.72(a)(1) and 10CFR50.73(a)(2)(viii)." |
| |
| The licensee has notified state and local officials and will notify the NRC |
| Resident Inspector. A media/press release is planned. |
| |
| *** UPDATE at 0132 ET on 01/30/03 by Dave Flyte/ Phil Brady taken by |
| MacKinnon **** |
| |
| Unusual Event was terminated at 0125 ET on 01/30/03. Investigation found |
| that the release was from the off gas system via a drain trap which entered |
| the ventilation system which then exited out the vent stack. According to |
| licensee's records, the release was greater than 2 times their Technical |
| Specification limit (208 microcuries per minute) from 1940 hours until 2111 |
| hours. Max level detected was 600 microcuries per minute. No iodine was |
| released just noble gases. NRC R1DO (Brad Fewell), FEMA (Nora Heyman), |
| NRC/DOT (Petty Officer Baumgartner), Office of Homeland Security (Damon |
| Edwards), and NRR EO (Bill Ruland) notified. |
| |
| The NRC Resident Inspector was notified by the licensee. |
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|Power Reactor |Event Number: 39547 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 01/30/2003|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 14:23[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 01/30/2003|
+------------------------------------------------+EVENT TIME: 11:30[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 01/30/2003|
| HQ OPS OFFICER: YAMIR DIAZ +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JONES R4 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
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| INFORMATION CALL CONCERNING PRESS RELEASE ON SAFEGUARDS EVENT |
| |
| Press release regarding a safeguards event involving a flyover at Palo |
| Verde. The press release was made by a local radio station, KTAR. |
| |
| The NRC resident inspector was notified. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 39548 |
+------------------------------------------------------------------------------+
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| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 01/30/2003|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 14:42[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/30/2003|
+------------------------------------------------+EVENT TIME: 10:54[CST]|
| NRC NOTIFIED BY: BEARD |LAST UPDATE DATE: 01/30/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JONES R4 |
|10 CFR SECTION: | |
|ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MANUAL REACTOR SCRAM ON DECREASING REACTOR VESSEL LEVEL |
| |
| "At 10:54 CDT Grand Gulf Nuclear Station inserted a manual scram on |
| decreasing vessel level as a result of the loss of all 3 condensate booster |
| pumps. Loss of the booster pumps resulted in loss of normal feedwater to the |
| vessel. Vessel level decreased to the auto initiation set point for High |
| Pressure Core Spray (HPCS), Reactor Isolation Cooling System (RCIC), and |
| Containment Isolation System. HPCS and RCIC started and injected to the |
| vessel and the containment isolated. The HPCS initiation also included an |
| auto start of the HPCS Diesel as expected. Reactor level was restored by |
| injection of HPCS and RCIC. Vessel pressure was maintained by the turbine |
| bypass valves. At present vessel level has been restored to normal. Systems |
| affected by the containment isolation have been restored as needed. The |
| cause of the condensate booster trips is under investigation. A review of |
| plant data is underway to confirm proper response by equipment." |
| |
| There was an ECCS injection for 5 - 10 minutes. All control rods inserted |
| and no relief valves lifted. |
| |
| The NRC Resident Inspector was notified. |
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