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Event Notification Report for April 27, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/26/2000 - 04/27/2000

                              ** EVENT NUMBERS **

36911  36930  36931  36932  36933  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36911       |
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| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 04/20/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 20:29[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/20/2000|
+------------------------------------------------+EVENT TIME:        19:30[EDT]|
| NRC NOTIFIED BY:  DOUG AMTHFIELD               |LAST UPDATE DATE:  04/26/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| - LICENSEE NOTIFIED NATIONAL RESPONSE CENTER AND STATE DEP OF A CHEMICAL     |
| SPILL ONSITE -                                                               |
|                                                                              |
| The licensee notified the National Response Center and the State Department  |
| of Environmental Protection (DEP) that approximately 5 gallons of a mixture  |
| of sulfuric acid and sodium hydroxide spilled from a tank truck onto the     |
| ground after a chemical reaction took place.  The spill was contained within |
| a portable dike area onsite and is being cleaned up.                         |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| * * * UPDATE AT 0948 EDT ON 04/26/00 FROM ROY HARDING TO S. SANDIN * * *     |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "This is a retraction of the notification made on 04/20/00 at 2029 hours     |
| (Event 36911).  This event was reported as a notification of another         |
| government agency [National Response Center and Pennsylvania Department of   |
| Environmental Protection (PADEP)] pursuant to 10CFR50.72(2)(b)(vi).          |
|                                                                              |
| "On April 20, 2000 at 1930 hours while Limerick Unit 1 was shutdown for      |
| refueling, 5 to 10 gallons of a dilute and partially neutralized acid        |
| (Sulfuric Acid-pH 3) was expelled from a temporary trailer tank onto asphalt |
| and stone surface in an adjacent area outside a temporary dike.  In          |
| addition, approximately 30 gallons of the acid/sludge mixture spilled into   |
| the temporary dike.  The spill never threatened navigable waterways, and     |
| subsequently was cleaned up within a 24 hour period.  The initial            |
| notification was conservatively reported based on information known at the   |
| time of the event.                                                           |
|                                                                              |
| "A minor spill of this nature is not reportable to the PADEP in accordance   |
| with 40CFR112 and the Preparedness Prevention Plan for Limerick Generating   |
| Station.  This spill from a temporary tank had no impact on navigable        |
| waterways and was less than the Reportable Quantity (69 gallons)."           |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.  The NRC Operations     |
| Officer notified the R1DO (Noggle).                                          |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36930       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/26/2000|
|    UNIT:  [] [] [3]                 STATE:  AL |NOTIFICATION TIME: 03:23[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/25/2000|
+------------------------------------------------+EVENT TIME:        23:42[CDT]|
| NRC NOTIFIED BY:  RODNEY NACOSTE               |LAST UPDATE DATE:  04/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VARIOUS ESF ACTUATIONS DUE TO RPS BUS 3B DEENERGIZING AS A RESULT OF A       |
| FAILED RELAY                                                                 |
|                                                                              |
| "At 2342 CDT on 04/25/00, the RPS bus 3B deenergized causing PCIS Group 2    |
| and Group 6 isolation valves to automatically close.  A burnt relay was the  |
| initiating condition. Group 2 outboard drywell equipment drain valve and     |
| drywell floor drain valve closed. Group 6 drywell radiation monitor          |
| isolation valves closed.  All other expected group isolations occurred along |
| with the automatic starts of SBGT and CREV Systems.                          |
|                                                                              |
| "Unit 3 is in Mode 5 with primary containment integrity not required.        |
|                                                                              |
| "This event is reportable under criteria 10CFR50.72.b.2.ii :  Any event or   |
| condition that results in manual or automatic actuation of any engineered    |
| safety feature (ESF), including the reactor protection system (RPS)."        |
|                                                                              |
| RPS bus 3B was reenergized from its alternate power supply.  Electricians    |
| are currently troubleshooting the cause of the failed relay.  There was no   |
| electrical maintenance or testing ongoing at the time of the relay failure.  |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36931       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  DRESSER EQUIPMENT GROUP              |NOTIFICATION DATE: 04/26/2000|
|LICENSEE:  DRESSER VALVE DIVISION               |NOTIFICATION TIME: 14:40[EDT]|
|    CITY:  BURLINGTON               REGION:     |EVENT DATE:        04/25/2000|
|  COUNTY:                            STATE:     |EVENT TIME:        14:00[EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  04/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PAUL FREDRICKSON     R2      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  L. H. WINDFIELD              |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DRESSER VALVES  NAME PLATE AND CODE PLATE HAVE INCORRECT SET PRESSURE        |
| INFORMATION AT HATCH.                                                        |
|                                                                              |
| PART 21 FROM DRESSER EQUIPMENT GROUP, DRESSER VALVE DIVISION, BURLINGTON,    |
| ONTARIO, CANADA.                                                             |
|                                                                              |
|                                                                              |
| The following noncompliance has been determined to be reportable within the  |
| requirements of 10CFR Part 21. The noncompliance involves seven safety       |
| relief valves that were purchased for the Hatch Electric Generating Plant by |
| the Georgia Power Company through its agent, Southern Nuclear Operating      |
| Company, Inc.  The valves are for use in a safely related service.           |
|                                                                              |
| The valves were purchased on Southern Nuclear Operating Company purchase     |
| order #6040304 and produced on Dresser Valve Division sales order #119588N   |
| and are further described as follows:                                        |
|                                                                              |
| Contract Item 002 Quantity 7                 Part Number                     |
| 3990C-1-S4-MS-33-SC-SC-GS produced  ASME Section                             |
| III  Class 2 valves with the following serial numbers and                    |
| required set pressures:                                                      |
|                                                                              |
| SERIAL NO.     SET PRESSURE REQD                                             |
| B119588-2-1     250  psig                                                    |
| B119588-2-2     250  psig                                                    |
| B119588-2-3     250  psig                                                    |
| B119588-2-4     250  psig                                                    |
| B119588-2-5     250  psig                                                    |
|                                                                              |
| B119588-3-1    170  psig                                                     |
| B119588-3-2    170  psig                                                     |
|                                                                              |
| NONCOMPLIANCE SITUATION AND BRIEF HISTORY                                    |
|                                                                              |
| On Tuesday April 25, 2000, the customer was performing receiving inspection  |
| and noticed that the set pressure information on the Code Plates and the     |
| Name Plates do not conform to the specification requirements or the history  |
| docket testing information. The customer called the Quality Assurance        |
| Department of Dresser Valve Division to discuss the finding.  It appears     |
| that the set pressure information on the plates has been interchanged.       |
|                                                                              |
| A summary of the information is as follows:                                  |
|                                                                              |
| SERIAL NO          SET PRESSURE REQD                               CODE      |
| PLATE                         NAME PLATE                                     |
| B119588-2-1                      250 psig                                    |
| 170 psig                                    170 psig                         |
| B119588-2-2                      250 psig                                    |
| 170 psig                                    170 psig                         |
| B119588-2-3                      250 psig                                    |
| 170 psig                                    170 psig                         |
| B119588-2-4                      250 psig                                    |
| 170 psig                                    170 psig                         |
| B119588-2-5                      250 psig                                    |
| 170 psig                                    170 psig                         |
|                                                                              |
| B119588-3-1                      170 psig                                    |
| 250 psig                                    250 psig                         |
| B119588-3-2                      170 psig                                    |
| 250 psig                                    250 psig                         |
|                                                                              |
| Our investigation has begun and we have conducted a full review of our       |
| records to confirm that the valves are set correctly to the contract         |
| requirements.  A notice has been given to the customer to return the         |
| affected valves to Dresser Valve Division for confirmation of the plate      |
| information and correction if required.  The ANI will be involved in the     |
| investigation and corrective actions as required.                            |
|                                                                              |
| We have conducted a full review of our records and confirmed that these are  |
| the only valves involved.  A full review of our procedures regarding plate   |
| preparation, inspection and installation will be completed.  Corrective      |
| actions will be initiated to address the internal issues, if warranted, and  |
| details will be provided in our closure reports at the completion of our     |
| investigation into the cause of this situation.                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36932       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 04/26/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 16:01[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        04/26/2000|
+------------------------------------------------+EVENT TIME:        13:42[CDT]|
| NRC NOTIFIED BY:  DAVID LOHMAN                 |LAST UPDATE DATE:  04/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY BUILDING SPECIAL VENTILATION AND CONTROL ROOM POST ACCIDENT        |
| RECIRCULATION ACTUATED DUE TO A STEAM EXCLUSION SIGNAL.                      |
|                                                                              |
| At 1342 CDT on 04/26/00, the Auxiliary Building Special Ventilation and      |
| Control Room Post Accident Recirculation Systems actuated due to a steam     |
| exclusion signal.   Auxiliary Building Special Ventilation and Control Room  |
| Post Accident Recirculation are Engineered Safety Features Systems.  The     |
| steam exclusion signal was due to the rupture disk on Boric Acid Recovery    |
| System rupturing.  Steam to the Boric Acid Recovery System was isolated.  At |
| 1425 CDT, steam exclusion was reset and the Auxiliary Building Special       |
| Ventilation and Control Room Post Accident Recirculation Systems were        |
| shutdown.  All equipment operated as designed.  There was no radiological    |
| release.  The licensee is currently investigating why the rupture disc       |
| ruptured.  Nobody was injured.                                               |
|                                                                              |
| The NRC Resident Inspector was notified of this event  by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36933       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OFFICE OF EMERGENCY PREPAREDNESS     |NOTIFICATION DATE: 04/26/2000|
|LICENSEE:  U.S. PUBLIC HEALTH SERVICE           |NOTIFICATION TIME: 16:16[EDT]|
|    CITY:  WINSTON-SALEM            REGION:  2  |EVENT DATE:        04/06/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:        12:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PAUL FREDRICKSON     R2      |
|                                                |JAMES NOGGLE         R1      |
+------------------------------------------------+JOE HOLONICH         NMSS    |
| NRC NOTIFIED BY:  ROBERT CORNISH               |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TWO CHEMICAL AGENT MONITORS EACH CONTAINING 15 MILLICURIES OF NICKEL-63      |
| MISSING DURING SHIPMENT FROM WINSTON-SALEM, NC TO BALTIMORE, MD VIA FEDEX    |
|                                                                              |
| On March 29, 2000, two Chemical Agent Monitors, APD-2000, each containing 15 |
| mCi of Nickel-63 were shipped by FEDEX from Winston-Salem, North Carolina    |
| to Environmental Technology Group, Baltimore, Maryland to be wiped tested.   |
| On April 06, 2000, U.S. Public Health Service was notified that the two      |
| Chemical Agent Monitors were missing.  The U.S. Public Health Service and    |
| FEDEX are unable to located the missing monitors using the FEDEX tracking    |
| number.  FEDEX is still trying to locate the missing monitors.               |
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