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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.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 March 19, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/16/2001 - 03/19/2001

                              ** EVENT NUMBERS **

37844  37845  37846  37847  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37844       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/17/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 10:55[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/16/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/17/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |GEOFFREY WRIGHT      R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SPAETH                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN - GEOMETRY VIOLATION                                  |
|                                                                              |
| At 1100 on 3/16/01, a seal test buggy was found without signs or tags as     |
| required by NCSA-PLANT_031 (Potable Sampling/Test Buggies and Carts).  Upon  |
| investigation of the test buggy, the chemical trap was found to have a       |
| nominal diameter of four inches and a length of twenty two inches.  The four |
| inch diameter violates the passive design control 2(b) which requires a      |
| three inch nominal diameter and a thirty three inch length.  Nuclear         |
| Criticality personnel have determined the maximum loading of the effected    |
| trap to be 76 gram U-235 at 3% assay.  76 grams is lower than the 350 gram   |
| safe mass limit.  The NCSE contingency analysis considers credible, a        |
| maximum five inch nominal diameter to remain subcritical.                    |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| Safety significance is considered very low. The NCSA requirement is three,   |
| three inch nominal diameter chemical traps.  However, the NCSE allows for    |
| three, five inch nominal diameter chemical traps and remain subcritical,     |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW            |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| Based on the bounding calculations for five inch diameter chemical traps,    |
| there no critical pathways involved                                          |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
|                                                                              |
| Geometry is the controlled parameter that was violated                       |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| The amount of uranium is unknown, however, it is not expected to be above    |
| 350 grams U-235 due to the operation performed with this buggy and the fact  |
| that the maximum loading of a 4" X 22" chemical trap is only 76 grams U-235  |
| at 3% assay.                                                                 |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| The control violated was the geometry control of the chemical trap.  The     |
| chemical trap was required to be three inch schedule 40 pipe, but it was     |
| found to be a nominal four inch diameter pipe.                               |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED;   |
|                                                                              |
| The test buggy was posted with temporary signs as required by                |
| NCSA-PLANT_031.  The buggy will remain in the anomalous condition boundary   |
| until NDA results are obtained.  Disposition of the buggy will be determined |
| based on the NDA results.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.  The DOE Representative will be     |
| informed.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37845       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 03/18/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 00:03[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/17/2001|
+------------------------------------------------+EVENT TIME:        21:13[EST]|
| NRC NOTIFIED BY:  TURNER                       |LAST UPDATE DATE:  03/18/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP FROM 100% POWER DUE TO DECREASING STEAM GENERATOR WATER LEVELS  |
|                                                                              |
| During 100% power operation of Unit 2, the Reactor Protection System (RPS)   |
| properly initiated an automatic Reactor Scram signal in response to          |
| decreasing Steam Generator (S/G) water levels.  Steam Generator              |
| water levels were decreasing due to an 'A' Main Feedwater Pump trip, which   |
| in turn had been caused by an 'A'                                            |
| Condensate Pump trip.   All rods fully inserted into the core, and all       |
| Safety Systems operated as designed.   The                                   |
| cause of the Condensate Pump trip is not currently known, and investigation  |
| is continuing.  No Radiological Releases, RCS leaks, or S/G leaks occurred   |
| during this event.                                                           |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37846       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 03/18/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 04:12[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/18/2001|
+------------------------------------------------+EVENT TIME:        02:12[CST]|
| NRC NOTIFIED BY:  BARTON                       |LAST UPDATE DATE:  03/18/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|*COM 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     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE EOF IS CONSIDERED UNAVAILABLE DUE TO PARTIAL LOSS OF POWER.              |
|                                                                              |
| A partial loss of electrical power to the Emergency Operations Facility      |
| (EOF) occurred at 0212 CST.  The partial loss of power resulted from opening |
| a circuit breaker that appeared to be tripped.  The failed circuit feeds     |
| lighting in the EOF as well as various other support loads.  Based on the    |
| partial loss of electrical power, the EOF is being considered unavailable.   |
| Callout of electrical support is in progress for troubleshooting and         |
| repair.                                                                      |
|                                                                              |
| The NRC Resident Inspector will be informed.                                 |
|                                                                              |
| ***** UPDATE AT 1216 EST ON 03/18/01 FROM SCOTT MAGLIO TO LEIGH TROCINE      |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This is a followup notification to the initial call made at 0312 [CST] on   |
| 03/18/01.  Restored electrical power to the Emergency Operations Facility at |
| 1010 [CST].  The partial loss of power to the facility was caused by a fault |
| on one of the parking lot lighting circuits.  This circuit has been          |
| isolated.  Facility and equipment checks have been initiated."               |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R4DO (Johnson).                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37847       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 03/18/2001|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 05:07[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/18/2001|
+------------------------------------------------+EVENT TIME:        01:00[PST]|
| NRC NOTIFIED BY:  BROWN                        |LAST UPDATE DATE:  03/18/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| Unaccounted for security weapon.  Compensatory measures were put into place  |
| immediately following discovery.  Contact HOO for additional information.    |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 25, 2021