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Event Notification Report for February 24, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/23/2000 - 02/24/2000

                              ** EVENT NUMBERS **

36713  36719  36720  36721  36722  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36713       |
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| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 02/21/2000|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 16:16[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/21/2000|
+------------------------------------------------+EVENT TIME:        08:40[CST]|
| NRC NOTIFIED BY:  GREG JANAK                   |LAST UPDATE DATE:  02/23/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| - 24 hour Report, Violation of Operating License, condition existing longer  |
| than permitted by Plant Tech Specs -                                         |
|                                                                              |
| Carbon samples obtained from Fuel Handling Building Exhaust Filtration Unit  |
| Train A failed laboratory tests.  The Plant Technical Specification          |
| 4.7.8.a.2 limit of less than 1% methyl iodide penetration was exceeded.  The |
| as-found methyl iodide penetration results were 1.07%.  This resulted in the |
| Train A Fuel Handling Exhaust Filtration Unit being inoperable since the     |
| time that the carbon samples were obtained at 0900 CST on 02/17/00.  This    |
| results in the system being inoperable for longer than 7 days which is a     |
| violation of Technical Specification 3.7.8. Action a.  The sample results    |
| were obtained at 0840 CST on 02/21/00.                                       |
|                                                                              |
| This notification is being made pursuant to Operating License NPF-76,        |
| Section 2.G for operation or condition prohibited by Plant Technical         |
| Specifications.                                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1604 ON 02/23/00 BY GREG JANAK TO JOLLIFFE * * *             |
|                                                                              |
| Plant Technical Specification Surveillance Requirement 4.7.8 (b) requires    |
| that periodic samples be taken from charcoal beds and analyzed within 31     |
| days after removal.  These requirements were met and action to declare that  |
| train inoperable was taken upon notification of unsatisfactory results.      |
| Based on previous practice, a 24-hour report for a violation of the          |
| operating license was made to the NRC as a result of this failure.           |
|                                                                              |
| While onsite for an inspection of the Effluents Program, an NRC inspector    |
| questioned the reportability of this event.  After further investigation     |
| into the issue, and input from both Region IV and NRR on this issue, the     |
| licensee has determined that this event is not reportable to the NRC as long |
| as the charcoal in question is replaced within the allowed outage time, as   |
| specified in the Plant Technical Specifications.  Based on the above, the    |
| licensee retracted this event.                                               |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.  The NRC Operations |
| Officer notified the R4DO Charles Marschall.                                 |
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|Fuel Cycle Facility                              |Event Number:   36719       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/22/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:29[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/21/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:45[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/23/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH DISCHARGE ALARM FOR THE W-2 COMPRESSOR.  LEAK TESTING OF THE W-2        |
| COMPRESSOR INDICATE A SEAL FAILURE WITH POTENTIAL FOR URANIUM HEXAFLUORIDE   |
| OUT GASSING.                                                                 |
|                                                                              |
| At approximately 2347 hours, 02/21/00, operations personnel received a       |
| Cascade Automatic Data Processing (CADP) smoke head alarm for Extended Range |
| Product (ERP) W-2 withdrawal station compressor.  Operations personnel had   |
| responded to a High Discharge Alarm for the W-2 compressor and upon arrival  |
| discovered the compressor shutdown and the CADP smoke head in alarm.  No     |
| smoke was discovered during the investigation of the alarm, however the      |
| smoke head is located inside a heated housing not readily accessible to      |
| operations personnel.  Leak testing of the W-2 compressor indicated a seal   |
| failure with potential for uranium hexafluoride outgassing.                  |
|                                                                              |
| Operations and engineering personnel are continuing to investigate the cause |
| of the smoke head alarm, but have not provided evidence at this time to      |
| invalidate the alarm.  PORTS is reporting this alarm as a valid actuation to |
| a "Q" Safety System.                                                         |
|                                                                              |
| There was no loss of hazardous/radioactive material or                       |
| radioactive/radiological contamination exposure as a result  of this event.  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36720       |
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/23/2000|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 18:00[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/23/2000|
+------------------------------------------------+EVENT TIME:        14:00[CST]|
| NRC NOTIFIED BY:  ELLIS PFEFFER                |LAST UPDATE DATE:  02/23/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Discovery of unfiltered leak path from Secondary Containment to outside    |
| atmosphere via the SBGT System -                                             |
|                                                                              |
| During Standby Gas Treatment (SBGT) System testing, the pressure in the room |
| containing the SBGT System was found to be at a lower pressure than          |
| Secondary Containment (SC).  The SBGT System draws a negative pressure on    |
| the SC during accident scenarios.  The SBGT System room is located outside   |
| SC.  With the SBGT System room being at a lower pressure than SC, a possible |
| leakage path is created from SC into the SBGT System room, into the SBGT     |
| System (downstream of the filters) and out the plant stack.  This path       |
| bypasses the SBGT System filtering assumed in the offsite dose analysis.     |
| This leakage path is small, but is not currently assumed in the accident     |
| analysis.                                                                    |
|                                                                              |
| The licensee is determining corrective actions and plans to resolve this     |
| issue prior to restarting the plant.                                         |
|                                                                              |
| The licensee notified state and local officials and the NRC Resident         |
| Inspector.                                                                   |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36721       |
+------------------------------------------------------------------------------+
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/23/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 19:11[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/23/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:35[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/23/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |WILLIAM BRACH        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Emergency response procedures implemented due to a smoke head alarm and    |
| high pressure vent actuation -                                               |
|                                                                              |
| At approximately 0835 on 02/23/00, Portsmouth operations personnel received  |
| a smoke head alarm for extended range product (ERP) compressor W-3 in Area   |
| Control Room (ACR)-4.  At the same time, another operator in ACR-4 looked at |
| the TV monitor for the ERP compressors and saw a "puff" of smoke around      |
| compressor W-3.  The plant's "SEE & FLEE" emergency procedures were          |
| immediately implemented.  The ERP stations' high pressure vent actuated      |
| taking the station below atmospheric pressure.  Results of all surveys       |
| performed during the emergency response were less than minimum detectable    |
| activity.  At 0949, the emergency response was cancelled.  The ERP station   |
| was made inoperable to allow for testing of the system by operations and     |
| engineering personnel.  Portsmouth is reporting this alarm as a valid        |
| actuation of a "Q" Safety System.                                            |
|                                                                              |
| This event is reportable to the NRC as a valid actuation of a "Q" Safety     |
| System in accordance with Safety Analysis Report, Section 6.9 (24-HOUR       |
| REPORT).                                                                     |
|                                                                              |
| There was no loss of hazardous or radioactive material nor radioactive or    |
| radiological contamination exposure as result of this event.                 |
|                                                                              |
| The NRC Resident Inspector and DOE site representative were notified of this |
| event.                                                                       |
|                                                                              |
| PTS-2000-020   PR-PTS-00-01079                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36722       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 02/24/2000|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 02:48[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        02/24/2000|
+------------------------------------------------+EVENT TIME:        02:10[EST]|
| NRC NOTIFIED BY:  NEWTON                       |LAST UPDATE DATE:  02/24/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES OGLE         R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE DATA ACQUISITION AND DISPLAY SYSTEM (ERDADS) INOPERABLE   |
| GREATER THAN 30 MINUTES.                                                     |
|                                                                              |
|                                                                              |
| ERDADS LOCKED UP FOR GREATER THAN 30 MINUTES. PERSONNEL HAVE BEEN CALLED OUT |
| TO REPAIR ERDADS.  ALL OTHER SYSTEMS OPERATING PROPERLY.                     |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
|                                                                              |
| * * * UPDATE ON 02/24/00 AT 0515 ET BY MR. MORRIS TAKEN BY MACKINNON * * *   |
|                                                                              |
| ERDADS RETURNED TO SERVICE AT 0400 ET.                                       |
| R2DO (CHARLES OGLE) NOTIFIED.                                                |
|                                                                              |
| THE NRC RESIDENT INSPECOTR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT    |
| UPDATE.                                                                      |
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