The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for December 19, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/18/2001 - 12/19/2001

                              ** EVENT NUMBERS **

38424  38580  38581  
.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38424       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/24/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 19:09[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/24/2001|
+------------------------------------------------+EVENT TIME:        16:25[CDT]|
| NRC NOTIFIED BY:  RODE                         |LAST UPDATE DATE:  12/18/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       63       Power Operation  |63       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PROCEDURE USED FOR INSTALLATION OF TEMPORARY FIRE SEALS WAS NOT IN         
 |
| COMPLIANCE WITH THE CALCULATION QUALIFYING THE TEMPORARY FIRE SEALS       
  |
|                                                                              |
| During an internal review of the fire protection program at Point Beach      |
| Nuclear Power Plant, it was determined that the procedure used for the       |
| installation of temporary fire seals was not in compliance with the          |
| calculation qualifying the temporary fire seals. The procedure called for 4  |
| inches of Kaowool while the calculation demonstrated the 5 inches would      |
| ensure adequate fire protection.                                             |
|                                                                              |
| Out of the 9 barriers that were identified, 4 of them are required to        |
| provide train separation for safe shut down equipment. Due to the identified |
| condition, these penetrations may not have adequately provided such          |
| separation as required by our safe shutdown analysis.                        |
|                                                                              |
| Immediate actions taken included:  1) Affected penetrations were identified  |
| and declared out of service. 2) Appropriate fire rounds were commenced. 3)   |
| Installed the required 5 inches of Kaowool in the identified barriers and    |
| returned the barriers back to service.                                       |
|                                                                              |
| Pending corrective actions:  Although the calculation determined 5 inches of |
| Kaowool provides an adequate fire barrier, engineering will perform an       |
| additional evaluation to determine if 4 inches of Kaowool would suffice.     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * UPDATE 1409EST ON 12/18/2001 FROM RYAN RODE TO S. SANDIN * * *         |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "Subsequent to this notification our Engineering Staff has prepared and      |
| approved, a Fire Protection Engineering Evaluation (FPEE 2001-003) of the    |
| as-found condition for these temporary fire seals following the guidelines   |
| of Generic Letter 86-10.  This analysis demonstrates that a 4 inch temporary |
| penetration seal constructed of 8 pounds per cubic feet ceramic fiber        |
| material satisfies the time function of a 3 hour rated seal by preventing    |
| fire propagation across the barrier.  Accordingly, we have concluded that    |
| the presence of temporary fire seals with 4 inches of seal material did not  |
| significantly compromise plant safety with respect to separation of the safe |
| shutdown equipment and this event notification should be retracted.          |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R3DO(Phillips).  |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38580       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HONEYWELL INTERNATIONAL, INC.        |NOTIFICATION DATE: 12/18/2001|
|   RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION      |NOTIFICATION TIME:
09:13[EST]|
| COMMENTS: UF6 CONVERSION (DRY PROCESS)         |EVENT DATE:        12/17/2001|
|                                                |EVENT TIME:        12:05[CST]|
|                                                |LAST UPDATE DATE:  12/18/2001|
|    CITY:  METROPOLIS               REGION:  3  +-----------------------------+
|  COUNTY:  MASSAC                    STATE:  IL |PERSON          ORGANIZATION |
|LICENSE#:  SUB-526               AGREEMENT:  Y  |MONTE PHILLIPS       R3      |
|  DOCKET:  04003392                             |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HUGH ROBERTS                 |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|JBBE 40.60(b)(2)         SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF THE STANDBY GENERATOR TO START ON AUTOMATIC DUE TO A
PARTIAL      |
| POWER OUTAGE AND RELAY FAILURE                                               |
|                                                                              |
| Moisture in a substation resulted in a partial power outage, and a faulty    |
| relay resulted in a failure to switch over to an automatic start on the      |
| standby generator.  The failure of the standby generator to start on         |
| automatic occurred at 1205 CST on 12/17/01.  The facility was shut down      |
| until the generator was restored and the relay was fixed.  The system was    |
| restored to service at approximately 1930 CST on 12/17/01.                   |
|                                                                              |
| The licensee reported that there was no loss of source material related to   |
| this event.  In addition, there were no personnel radiation exposures or     |
| contaminations.                                                              |
|                                                                              |
| The licensee reported this event in accordance with 10CFR40.60(b)(2)(iii)    |
| because there was no redundant equipment available to operate and perform    |
| the required safety function.                                                |
|                                                                              |
| The licensee notified the NRC resident inspector (Bruce Bartlett) for        |
| Paducah and plans to submit a written report.                                |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38581       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 12/19/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 04:47[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        12/19/2001|
+------------------------------------------------+EVENT TIME:        02:50[CST]|
| NRC NOTIFIED BY:  CHRISTENSEN                  |LAST UPDATE DATE:  12/19/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SANBORN         R4      |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOCAL FIRE DEPARTMENT NOTIFIED OF A FIRE ONSITE                              |
|                                                                              |
| A fire alarm was received @ 0248 CST on 12/19/01 for room-22 safety          |
| injection pump room.    An inspection showed heavy smoke at entrance to      |
| room.   The plant fire brigade was manned and personnel entered the room.    |
| The fire source was an extension cord, connected to some heaters, which      |
| started some anti-contamination clothing on fire.  The fire was identified @ |
| 0306 CST and declared out @ 0308 CST.   The Blair Fire Department was        |
| notified @ 0250 CST and responded to the site.  No entry was made to the     |
| Protected Area, as the fire was out upon their arrival.  The licensee is     |
| still investigating the cause.                                               |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+
.

Page Last Reviewed/Updated Thursday, March 25, 2021