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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39439       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39539       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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."                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39548       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+