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Event Notification Report for March 29, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/28/2000 - 03/29/2000

                              ** EVENT NUMBERS **

36834  36839  36840  36841  36842  36843  

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|General Information or Other                     |Event Number:   36834       |
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 03/24/2000|
|LICENSEE:  HTS, INC CONSULTANTS                 |NOTIFICATION TIME: 17:25[EST]|
|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        02/08/2000|
|  COUNTY:                            STATE:  TX |EVENT TIME:        12:00[CST]|
|LICENSE#:  TX-L-02757            AGREEMENT:  Y  |LAST UPDATE DATE:  03/28/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE YANDELL     R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAMES OGDEN                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT - STOLEN / RECOVERED CPN NUCLEAR GAUGE IN HOUSTON,    |
| TX                                                                           |
|                                                                              |
| The following text is from the facsimile received from the Texas Department  |
| of Health:                                                                   |
|                                                                              |
| "Theft/Recovery of a nuclear gauge - licensee notified the agency [Texas     |
| Department of Health] Feb 8, 2000.  Reports lost in mail.  Faxed information |
| today at request of Incident Investigation.  Gauge recovered intact Feb 14,  |
| 2000.  Leak tested Feb 15, 2000 was fully satisfactory."                     |
|                                                                              |
| * * * UPDATE AT 1255 ON 03/28/00 BY JAMES OGDEN TO JOLLIFFE * * *            |
|                                                                              |
| The following is a more detailed version of the above Agreement State        |
| Report:                                                                      |
|                                                                              |
| Texas Licensee #TX-L-02757, HTS, Inc. Consultants, Houston, Texas, reported  |
| to Texas Department of Health, Bureau of Radiation Control, the theft of a   |
| nuclear gauge in it's transport box from the bed of a company pickup truck   |
| on February 8, 2000.  Gauge Manufacturer: CPN, Model: MC-3. Serial Number:   |
| M35116369.  Two sealed sources: 1) Cs-137, maximum activity 10 millicuries   |
| and 2) Am-241/Be, maximum activity 50 millicuries.  The gauge was stolen     |
| between 5:45 a.m. and 1:45 p.m. from a jobsite.  Incident Report Number      |
| 16656300-H was filed with the Houston Police Department on February 8, 2000. |
| Ten local pawn shops were notified by the licensee.  The stolen gauge was    |
| discovered in a lot adjacent to Hemmi Autoworks, Houston, TX  by the         |
| facility owner, Richard "Butch" Hemmi and reported to the City of Houston,   |
| Bureau of Occupational Health and Radiation Control.  This organization      |
| recovered all components of the gauge intact on February 14, 2000 (Gauge,    |
| Transport box, Calibration Block, Guide Pin, Guide Plate, and paperwork of   |
| the last leak test.)   The gauge was satisfactorily leak tested on February  |
| 15, 2000.  The gauge was returned to storage and to service with the Texas   |
| licensee.                                                                    |
|                                                                              |
| The NRC Operations Officer notified the R4DO Kriss Kennedy and NMSS EO Brian |
| Smith.                                                                       |
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|General Information or Other                     |Event Number:   36839       |
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 03/28/2000|
|LICENSEE:  FUGRO-McCLELLAND, INC                |NOTIFICATION TIME: 12:27[EST]|
|    CITY:  FORT WORTH               REGION:  4  |EVENT DATE:        03/28/2000|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|
|LICENSE#:  TX-L-05082            AGREEMENT:  Y  |LAST UPDATE DATE:  03/28/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAMES OGDEN                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT - STOLEN / RECOVERED TROXLER NUCLEAR GAUGE IN         |
| ARLINGTON, TX                                                                |
|                                                                              |
| Texas Licensee #TX-L-05082, Fugro-McClelland (Southwest), Inc., Fort Worth,  |
| Texas, reported to Texas Department of Health, Bureau of Radiation Control,  |
| the theft of a nuclear gauge from it's unsecured transport box sitting near  |
| a work site at the General Motors Plant in Arlington, Texas. The gauge was   |
| unsecured and the source rod was not locked, as the operator was going to    |
| use the gauge after a short discussion approximately 100 feet from the       |
| transport box.  Gauge Manufacturer: Troxler, Model: 3411-B, Serial Number:   |
| 10390.  Two sealed sources: 1) Cs-137 with nominal activity of 10            |
| millicuries and 2) Am-241/Be, nominal activity 40 millicuries.  The stolen   |
| gauge was discovered along a local street several blocks from the GM Plant   |
| and in a damaged condition - the source rod was extended and broken.  The    |
| gauge was recovered by a passerby who thought the damaged gauge may be of    |
| value and took it to a local equipment rental facility to ascertain the      |
| value.  He was warned of the radiation hazard but reportedly departed the    |
| facility with the broken gauge.  He evidently changed his mind and notified  |
| the City of Arlington, who arrived and recovered the gauge.  The gauge was   |
| turned over to the Troxler Service Facility in Arlington where a leak test   |
| was performed and indicated that the sealed sources were still intact.       |
| However, the gauge would require repair before being placed back into        |
| service.  The Texas Licensee was notified of the recovery.  The gauge is     |
| being maintained by the Troxler facility until release by this agency for    |
| repairs.                                                                     |
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|Power Reactor                                    |Event Number:   36840       |
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| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 03/28/2000|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 15:21[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/28/2000|
+------------------------------------------------+EVENT TIME:        12:41[EST]|
| NRC NOTIFIED BY:  MATTHEW ARSENAULT            |LAST UPDATE DATE:  03/28/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| PRIMARY COMPONENT COOLING WATER SYSTEM INOPERABLE DUE TO THE AREA            |
| VENTILATION SYSTEM INCAPABLE OF PERFORMING ITS SAFETY FUNCTION               |
|                                                                              |
| "On 03/26/00 Seabrook Station entered Tech Spec (TS) 3.0.3 due to both       |
| trains of the Primary Component Cooling Water (PCCW) system being declared   |
| inoperable. Both trains of PCCW were declared inoperable because the PCCW    |
| Area Ventilation System was determined to be incapable of performing its     |
| intended function.                                                           |
|                                                                              |
| "The PCCW system is a two train closed loop cooling system used to remove    |
| heat from plant components during plant operation, plant cooldown and during |
| various phases of an accident. The PCCW pumps are located within the Primary |
| Auxiliary Building (PAB). The operation of the PCCW pumps is supported by    |
| the PCCW Area Ventilation system. This ventilation system has redundant,     |
| automatically controlled auxiliary supply fans and associated dampers to     |
| ensure that the temperature in this area does not exceed design limits       |
| should the normal PAB ventilation system fail.                               |
|                                                                              |
| "During surveillance testing of the PCCW Area Ventilation system, an exhaust |
| damper (PAH-DP-357) failed to open as required. During a subsequent local    |
| investigation by the Shift Manager and Unit Supervisor it was determined     |
| that recent painting activities may have affected both PAB Exhaust Dampers   |
| (PAH-DP-357 and PAH-DP-358).  A subsequent test of PAH-DP-358 indicated that |
| it also failed to open as required. TS 3.0.3 was entered on 03/26/00 at      |
| 0346. TS 3.0.3 was subsequently exited at 0425 on 03/26/00 after plant       |
| personnel reestablished operability for PAH-DP-358. The subject dampers      |
| automatically open to provide an exhaust flow path for the PCCW Pump Area    |
| ventilation system which supports operation of the PCCW pumps. An initial    |
| review of this condition concluded that a report pursuant to the             |
| requirements of 10CFR50.72 was not required.  A subsequent review of this    |
| event determined that it is reportable pursuant to the requirements of       |
| 10CFR50.72(b)(2)(iii) as a condition that alone could have prevented the     |
| fulfillment of a safety function."                                           |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| HOO Note:  The event time was the time the licensee determined this          |
| condition to be reportable to the NRC.                                       |
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|Fuel Cycle Facility                              |Event Number:   36841       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/28/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:54[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/28/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:30[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/28/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |RONALD GARDNER       R3      |
|  DOCKET:  0707002                              |JOHN GREEVES         NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01, 4 HOUR REPORT -                                          |
|                                                                              |
| At 1030 on 03/28/00, a box containing uranium oxide standard vials was       |
| discovered under a workbench in building X-710 room 117,  The applicable     |
| Nuclear Criticality Safety Approval/Evaluation (NCSA/E-0710-011) does not    |
| analyze storing uranium oxide vials in this area of the X-710 building.  The |
| uranium oxide vials were transported to an area designated for storage of    |
| such materials under applicable approved NCSAs.  The material was            |
| non-destructive assay (NDA) tested.  The combined mass of all of the uranium |
| oxides in all the standard vials was 18 +/- 9 grams U-235 with an average    |
| enrichment of 18 wt% U-235,                                                  |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
| The uranium oxide vials were stored at least two feet edge-to-edge from any  |
| other fissile material.  The combined mass of all of the uranium oxides in   |
| all the standard vials was determined by NDA to be 18 +/- 9 grams U-235 with |
| an average enrichment of 18 wt% U-235.  Due to the low mass and absence of   |
| moderation, the safety significance is low.                                  |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR]:                                                    |
| Additional mass and a spacing violation would have been required before a    |
| criticality would be possible. Without moderation, much more than the safe   |
| mass of 350 grams of U-235 would have to be present before a criticality     |
| could be possible.                                                           |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
| This was an unanalyzed condition.  Although not specifically controlled, the |
| combined mass of all the uranium oxides in all the standard vials was less   |
| than a safe mass, moderation was not present, and the uranium oxide vials    |
| were spaced at least two feet from any other fissile material.               |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDING PROCESS   |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
| NDA shows the combined mass of all of the uranium oxides in all the standard |
| vials to be 18 +/- 9 grams of U-235 with an enrichment of 18 wt% U-235.  The |
| material is in the form of dry oxides.  For a spherical system at optimum    |
| moderation, full water reflection, and 100 wt% enrichment, the safe mass is  |
| 350 grams U-235.                                                             |
|                                                                              |
| NUCLEAR CRITICALITY SAFEEY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
| The request failed to identify the presence of uranium oxide vials in the    |
| room resulting in an unanalyzed condition.  The uranium oxides are less than |
| a safe mass and other uranium bearing material was spaced at least two feet  |
| edge-to-edge from the uranium oxides.                                        |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:   |
| The uranium oxide vials were removed from the X-710 room 117 under           |
| applicable plant approved NCSAs. Total mass of material in X-710 room 117 is |
| currently less than 15 grams U-235.                                          |
|                                                                              |
| The NRC Resident Inspector and the site DOE Representative were notified.    |
|                                                                              |
| PTS-2000-038;  PR-PTS-00-01697.                                              |
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|Power Reactor                                    |Event Number:   36842       |
+------------------------------------------------------------------------------+
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| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/28/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 22:33[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/27/2000|
+------------------------------------------------+EVENT TIME:        15:30[EST]|
| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  03/28/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|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                                   
+------------------------------------------------------------------------------+
| - ESF ACTUATION OF REACTOR WATER CLEANUP SYSTEM DURING DRAINING EVOLUTIONS   |
| -                                                                            |
|                                                                              |
| During the Unit 1 Refueling and Inspection Outage, the licensee determined   |
| that the Reactor Water Cleanup System received an ESF Actuation signal       |
| during draining evolutions. The potential for an ESF Actuation is identified |
| in the draining procedure, however after review, the licensee determined     |
| that the actuation signal was not part of the planned evolution due to the   |
| system not being properly removed from service.  An actual isolation did not |
| occur due to the isolation valves being bypassed per the draining procedure. |
|                                                                              |
|                                                                              |
| This event has no effect on Unit 2 which is at 100% power.                   |
|                                                                              |
| The licensee is investigating this event and determining corrective          |
| actions.                                                                     |
|                                                                              |
| At 2030 on 03/28/00, while reviewing this event, the licensee determined     |
| that this event is reportable to the NRC.  This failure requires a four hour |
| ENS notification under 10CFR50.72(b)(2)(ii).                                 |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36843       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/29/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 02:38[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/29/2000|
+------------------------------------------------+EVENT TIME:        02:00[EST]|
| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  03/29/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EXCESSIVE LEAKAGE THROUGH CONTROL ROD DRIVE CHECK VALVES                     |
|                                                                              |
| "During the Unit 1 Refuel and Inspection Outage, it has been determined that |
| the CRD check valves (CRD Seismic Island) exceeded the as-found minimum path |
| leakage limit of 508 ml/hr. This failure is a degraded condition found while |
| the plant is shutdown, and requires a 4 hour ENS notification under          |
| 10CFR50.72(b)(2)(i)."                                                        |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
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