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Event Notification Report for June 24, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/21/2002 - 06/24/2002

                              ** EVENT NUMBERS **

39002  39008  39009  39010  39011  39012  

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|General Information or Other                     |Event Number:   39002       |
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| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 06/18/2002|
|LICENSEE:  JOSLIN DIABETES CENTER               |NOTIFICATION TIME: 15:58[EDT]|
|    CITY:  BOSTON                   REGION:  1  |EVENT DATE:        06/18/2002|
|  COUNTY:                            STATE:  MA |EVENT TIME:             [EDT]|
|LICENSE#:  15-2661               AGREEMENT:  Y  |LAST UPDATE DATE:  06/18/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES TRAPP          R1      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KENATH TRAEGDE               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST RADIOACTIVE MATERIAL SHIPMENT                  |
|                                                                              |
| The Massachusetts Radiation Control Program was contacted by the Joslin      |
| Diabetes Center about a missing shipment of  500 microcuries of P32.  The    |
| shipment was shipped from Perkin-Elmer on 6/10/02 and received on 6/11/02 at |
| the center.  The package was discovered missing on 6/14/02 and notification  |
| to the state was on 6/18/02.  The center has been searched and further       |
| searches are ongoing.                                                        |
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|Power Reactor                                    |Event Number:   39008       |
+------------------------------------------------------------------------------+
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 06/21/2002|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 13:30[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/21/2002|
+------------------------------------------------+EVENT TIME:        13:12[EDT]|
| NRC NOTIFIED BY:  JOHN KONOVALCHICK            |LAST UPDATE DATE:  06/21/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VOLUNTARY INFORMATION REPORT ON PLANNED SPDS OUTAGE AT SALEM                
|
|                                                                              |
| "The safety parameter display system (SPDS) is being removed from service to |
| perform planned upgrades to the system. The removal of SPDS from service for |
| Salem Units 1 & 2 also affects the transmission of data from the emergency   |
| response data system (ERDS). Appropriate compensatory measures are in place  |
| while the SPDS system is out of service. SPDS is expected to return to       |
| service by end of August. This is considered a condition warranting          |
| voluntary/courtesy NRC notification"                                         |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39009       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  BUREAU OF INDIAN AFFAIRS             |NOTIFICATION DATE: 06/22/2002|
|LICENSEE:  BUREAU OF INDIAN AFFAIRS             |NOTIFICATION TIME: 13:00[EDT]|
|    CITY:  FAIRFAX                  REGION:  4  |EVENT DATE:        06/21/2002|
|  COUNTY:  OSAGE                     STATE:  OK |EVENT TIME:        09:00[CDT]|
|LICENSE#:  35-15239-02           AGREEMENT:  Y  |LAST UPDATE DATE:  06/22/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BOB FAVORS                   |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN TROXLER MOISTURE DENSITY GAUGE                                        |
|                                                                              |
| On 9:00 a.m. CDT on 6/22/02, the licensee discovered that their storage shed |
| had been broken into and a Troxler moisture density gauge was stolen.  The   |
| model number is 3440, which contains 8 millicuries of CS-137 and 40          |
| millicuries of Am-Be 241, and serial numbers 18746 and 18745.  The licensee  |
| contacted the local police, Fairfax City Police and Osage County Sheriffs    |
| office.  The storage shed is located 2 miles east of Highway 20 and Highway  |
| 18 in Osage County, Oklahoma.                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39010       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 06/22/2002|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 18:27[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/22/2002|
+------------------------------------------------+EVENT TIME:        14:16[EDT]|
| NRC NOTIFIED BY:  CHRISTOPHER SERATA           |LAST UPDATE DATE:  06/22/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC SCRAM AT HOPE CREEK DUE TO TURBINE TRIP                            |
|                                                                              |
| "Immediately following the RPS actuation, the success of the SCRAM was       |
| evaluated. Initially, the Rod Worth Minimizer indicated that some control    |
| rods were not fully inserted and control rod 22-31 indicated full out on the |
| Full Core Display. Alternate Rod Insertion (ARI) was initiated as per        |
| established operating procedures. The STA observed all Control Rods except   |
| 22-31 to be fully inserted on the Core Monitoring System before ARI was      |
| initiated, indicating the reactor was shutdown without ARI. The indicated    |
| position of CR 22-31 did not change immediately following the SCRAM, but     |
| changed over time consistent with a known problem with its                   |
| position-indicating probe.                                                   |
|                                                                              |
| "Both Reactor Recirculation Pumps tripped as expected from the turbine trip  |
| above 30% power (End-of-Cycle Recirculation Pump Trip function), and remain  |
| out of service. The Reactor is presently shutdown. Reactor pressure is 700   |
| psig and slowly lowering and reactor level is 32 and stable (normal band     |
| 30-39). Efforts are underway to stabilize and normalize reactor coolant and  |
| metal temperatures to allow the restarting of a Reactor Recirculation        |
| Pump."                                                                       |
|                                                                              |
| The NRC resident inspector was notified by the licensee.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39011       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 06/22/2002|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 17:02[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        06/21/2002|
+------------------------------------------------+EVENT TIME:        01:00[CDT]|
| NRC NOTIFIED BY:  TRACY ALDRICH                |LAST UPDATE DATE:  06/22/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SHIFT SECURITY STAFFING BELOW SECURITY PLAN LEVEL                            |
|                                                                              |
| A security guard failed a random drug test and was immediately removed from  |
| duties.  This placed the site below the minimum security level for           |
| approximately 1 hour. Contact the HOO for more details.                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39012       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 06/23/2002|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 02:38[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        06/22/2002|
+------------------------------------------------+EVENT TIME:        22:17[CDT]|
| NRC NOTIFIED BY:  ROBERT BRINKMAN              |LAST UPDATE DATE:  06/23/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM FOLLOWING SERVICE TRANSFORMER LOCKOUT FOR
REASONS    |
| UNKNOWN                                                                      |
|                                                                              |
| "At  2217 CDT on 6/22/02, GGNS scrammed from 100% CTP.  The scram was the    |
| results of a lockout trip on service transformer 21 (ST21).  Exact cause of  |
| [the] scram has not been determined yet..  [The] Plant is stable and all     |
| parameters are being controlled.  [The] scram is suspected to be due to loss |
| of feedwater (i.e., Rx Low Level) when ST21 tripped.  Div 2 and 3 buses did  |
| deenergize and [their] respective Diesel Generators started and carried      |
| [the] buses."                                                                |
|                                                                              |
| All control rods fully inserted.  RWCU is currently in-service removing      |
| decay heat.  ST21 remains out-of-service.  Electrical loads have been        |
| shifted to ST11 (500KV feed) and the ESF transformer (115KV feed).  The unit |
| is not in any TS A/S for offsite power since 2 of the 3 sources are          |
| available.  The licensee notified the NRC Resident Inspector.                |
|                                                                              |
| * * * UPDATE 0404 EDT ON 6/23/02 FROM ROBERT BRINKMAN TO S. SANDIN * * *     |
|                                                                              |
| "This is an update to Event Notification #39012.  This call in is to report  |
| the 8 hr non-emergency call in under 10CFR50.72(b)(3)(iv)(A).  As reported   |
| earlier, Division 2 and 3 electrical buses deenergized when service          |
| transformer 21 tripped.  Division 2 and 3 Diesel Generators started and      |
| energized these buses.  The actuation of Division 2 and 3 Diesel Generators  |
| is the 'Specified System Actuation' reported by this notification.  Also,    |
| Div. 2 Control Room A/C failed to automatically restart following Div. 2 bus |
| being re-energized.  [The] breaker was closed manually and Control Room A/C  |
| (Div. 2) restarted."                                                         |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified                  |
| R4DO(Marschall).                                                             |
|                                                                              |
| * * * UPDATE 0555 EDT ON 6/23/02 FROM ROBERT BRINKMAN TO S. SANDIN * * *     |
|                                                                              |
| "This notification is to report an 8 hr non-emergency call in under          |
| 10CFR50.72(b)(3)(xiii).  At 0425 CDT, on 6/23/02, the GGNS Control Room was  |
| notified that the EOF had no electrical power.  The site power loop was      |
| deenergized when service transformer 21 tripped, which caused the EOF to     |
| become de-energized (see EN #39012).  The EOF backup generator did not start |
| as required, therefore the EOF (Emergency Operations Facility) did not have  |
| any electrical power.  Normal electrical power was restored to [the] EOF at  |
| 0415 hrs CDT on 6/23/02.  [The] backup EOF was available at all times."      |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R4DO(Marschall). |
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