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Event Notification Report for November 6, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/03/2000 - 11/06/2000

                              ** EVENT NUMBERS **

37485  37486  37487  37488  37489  37490  37491  37492  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37485       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 11/03/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:29[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/02/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:45[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/03/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WHITE                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN                                                       |
|                                                                              |
| At 1645 CST on 11-02-00, the Plant Shift Superintendent (PSS) was notified   |
| of a violation of NCSA GEN-15 Machining waste, defined in NCSE GPS-11 to be  |
| potentially fissile, was collected in a 55-gallon drum in the C-720 machine  |
| shop in violation of NCSA GEN-15.  GEN-15 limits the containers used for     |
| accumulating fissile/potentially fissile waste to approved 5.5-gallon        |
| container.  The purpose of this requirement is to ensure that fissile        |
| material will be accumulated in approved containers.                         |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS;                                               |
| The mass of fissile material contained in the waste drum is less than what   |
| is required to achieve criticality. Therefore, no possibility exists for an  |
| inadvertent criticality.  However, double contingency was not maintained.    |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR:                                                     |
| In order for a criticality to be possible, an additional violation would     |
| have to occur resulting in unsafe mass of fissile material accumulating in   |
| an unsafe geometry.                                                          |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC):      |
| Double contingency for this scenario is established by implementing one      |
| control on mass and one control on volume.                                   |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE CRITICAL MASS):                                       |
| A process limit of 22.3 kg. At 5.5 wt. % 235U would have to be exceeded for  |
| a criticality                                                                |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES;                                             |
| The two process conditions relied upon for double contingency for this       |
| scenario are mass and volume,                                                |
|                                                                              |
| The first leg of double contingency is based on limiting the mass of uranium |
| accumulated.  Analysis has shown that the machining waste from approximately |
| 1490 machining operations would have to be accumulated before exceeding an   |
| unsafe mass.  The waste would occupy more than eighteen 5.5-gallon           |
| containers, which exceeds the volume of the 55-gallon waste container (drum) |
| in the machine shop. This control was not violated.                          |
|                                                                              |
| The second leg of double contingency is based on the accumulation of fissile |
| waste only in approved containers, limited to 5.5 gallons. This is           |
| controlled by limiting the volume of the containers used for accumulating    |
| fissile waste.  Potentially fissile waste was placed In a container other    |
| than an approved 5.5 gallon container, violating this control.  The          |
| machining waste exceeded the allowed volume of 5.5 gallons and resulted in a |
| loss of the process condition.                                               |
|                                                                              |
| Since the volume process condition was lost, double contingency was not      |
| maintained.                                                                  |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
| Access to the area containing the 55 gallon drum has been controlled by      |
| ropes and signs. Remediation of violation will be made following development |
| of a Remediation Guide.                                                      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| The DOE Representative will be informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37486       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 11/03/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:27[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/02/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:30[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/03/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MIKE UNDERWOOD               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CRITICALITY ALARM HORNS AIR PRESSURE FOUND OUT OF SPECIFICATION DURING       |
| SURVEILLANCE                                                                 |
|                                                                              |
| "At 1330 on 11/2/00, the Plant Shift Superintendent was notified that the    |
| testing of the C-337 and C-337-A Criticality Accident Alarm System (CAAS)    |
| air horn regulators resulted in as found data which is outside of the        |
| optimum air pressure band allowed to insure desired horn sound quality.      |
| Twelve of the twenty-five CAAS horn regulators located in these two areas    |
| were discovered outside the desired pressure band. The effect of this as     |
| found condition is unknown at this time and is being evaluated by            |
| Engineering. This evaluation will require greater than the 24-hour reporting |
| time limit allowed by 10 CFR 76.120.c.2. Due to the uncertainties and the    |
| length of time required to complete the engineering evaluation the condition |
| is being conservatively reported.                                            |
|                                                                              |
| "Reasonable assurance of operability of CAAS horns in these and other        |
| buildings exists based on the successful completion of quarterly and annual  |
| TSR surveillances. In addition, all CAAS horn regulators found outside of    |
| established criteria during this and previous tests on other building CAAS   |
| systems were returned to acceptable values prior to returning the systems to |
| service.                                                                     |
|                                                                              |
| "This event is reportable under 10 CFR 76.120(c)(2) as an event in which     |
| equipment required by the TSR is disabled or fails to function as designed.  |
|                                                                              |
| "The NRC Senior Resident has been notified of this event."  The DOE          |
| representative will be notified.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37487       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 11/04/2000|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 08:27[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/04/2000|
+------------------------------------------------+EVENT TIME:        08:22[EST]|
| NRC NOTIFIED BY:  THOMAS VEITCH                |LAST UPDATE DATE:  11/04/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE EOF DUE TO PLANNED MAINTENANCE                          |
|                                                                              |
| "LOSS OF POWER TO THE EMERGENCY OPERATIONS FACILITY.  THIS IS A PREPLANNED   |
| MAINTENANCE ACTIVITY ON BREAKER H2110.  THE REMOVAL OF THIS BREAKER CAUSES   |
| THE FACILITY (EOF) TO LOSE POWER AND IS, THEREFORE, 'POTENTIALLY'            |
| UNAVAILABLE FOR GREATER THAN 90 MINUTES.  THE TOTAL ESTIMATED DURATION OF    |
| THE ACTIVITY IS 8 HOURS."                                                    |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37488       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 11/05/2000|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 04:21[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/05/2000|
+------------------------------------------------+EVENT TIME:        00:30[PST]|
| NRC NOTIFIED BY:  LAURA KENNEDY                |LAST UPDATE DATE:  11/05/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            IAT     |
|10 CFR SECTION:                                 |ROBERTA WARREN       IAT     |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 1-HR SECURITY REPORT                                                         |
|                                                                              |
| POTENTIAL BOMB THREAT.   IMMEDIATE COMPENSATORY MEASURE TAKEN UPON           |
| DISCOVERY.  LICENSEE HAS INFORMED STATE/LOCAL AGENCIES AND WILL INFORM THE   |
| NRC RESIDENT INSPECTOR.   CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR    |
| ADDITIONAL DETAILS.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37489       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 11/05/2000|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 04:39[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/05/2000|
+------------------------------------------------+EVENT TIME:        01:20[PST]|
| NRC NOTIFIED BY:  DAVID PIERCE                 |LAST UPDATE DATE:  11/05/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |PHIL HARRELL         R4      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|AAEC                                            |JOSEPH GIITTER       IRO     |
|                                                |KEN BROCKMAN         R4      |
|                                                |ELLIS MERSCHOFF      R4      |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO A POTENTIAL BOMB THREAT                        |
|                                                                              |
| THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO A POTENTIAL BOMB THREAT.  THE  |
| LICENSEE INFORMED STATE/LOCAL AUTHORITIES AND WILL INFORM THE NRC RESIDENT   |
| INSPECTOR.                                                                   |
|                                                                              |
| THE NRC WAS PLACED IN THE MONITORING PHASE OF THE NORMAL MODE OF OPERATION   |
| BY THE RIV RA ( MERSCHOFF) AT 0400CST FOLLOWING DISCUSSIONS WITH IRO         |
| (GIITTER) AND THE EO (RICHARDS) .  REGION IV INCIDENT RESPONSE CENTER WAS    |
| OPERATIONAL AT 0456CST.  NOTIFIED CHAIRMAN'S STAFF (TSCHILTZ) , EDO STAFF    |
| (SMITH), AND HEADQUARTERS PAO (GAGNER).                                      |
|                                                                              |
| * * * 0610EST ON 11/5/00 FROM DAVID PIERCE TO S. SANDIN * * *                |
|                                                                              |
| THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0237PST AFTER DETERMINING THAT  |
| THE BOMB THREAT WAS NOT CREDIBLE.  THE LICENSEE INFORMED STATE/LOCAL         |
| AGENCIES AND THE NRC RESIDENT INSPECTOR.  RIV IRC  AND FEMA (SULLIVAN)       |
| NOTIFIED.                                                                    |
|                                                                              |
| * * * 0700EST ON 11/5/00 * * *                                               |
|                                                                              |
| COMMISSIONER'S ASSISTANTS BRIEFING CONDUCTED.                                |
|                                                                              |
| * * * 1655 EST ON 11/4/00 * * *                                              |
|                                                                              |
| The NRC exited Monitoring Phase of the Normal Mode of Operation by NRC       |
| Region 4 Regional Administrator (Ellis Merschoff) following discussion with  |
| IRO (Joseph Giitter) and R4 DRP (Kenneth Brockman).  Notifications made      |
| include EDO's office (Garrett Smith), Chairman's office (Alan Levin), PAO    |
| (Sue Gagner).                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37490       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/05/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 16:38[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/05/2000|
+------------------------------------------------+EVENT TIME:        14:07[CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  11/05/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          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          Y       100      Power Operation  |100      Power Operation  |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED AUTOMATIC START OF THE G-03 EDG                                   |
|                                                                              |
| "During 2A06 Bus recovery work, from a scheduled bus maintenance outage,     |
| there was an automatic start of G-03 Emergency Diesel Generator (EDG). This  |
| was an inadvertent actuation and not part of the planned bus recovery work.  |
| G-03 EDG started and ran unloaded due to a 4160 Bus under voltage, that was  |
| caused by fuse replacement as part of the bus restoration procedure. The     |
| G-03 EDG output breaker 2A52-87 is currently out of service as part of the   |
| 2A06 bus outage, so the diesel could not have closed onto the dead bus. G-03 |
| EDG was and is still lined up for normal operation to the 1A06 bus. Further  |
| investigation is continuing into the root cause of this actuation.           |
|                                                                              |
| "All buses remained energized and there were no other abnormal indications.  |
| Currently Unit 2 is in a refueling outage and is defueled at this time. Unit |
| 1 is at 100% power normal operation."                                        |
|                                                                              |
| The sequence of actions taken were wrong in that the fuses were replaced     |
| when they should not have been.                                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37491       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 11/05/2000|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 20:44[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/05/2000|
+------------------------------------------------+EVENT TIME:        17:07[PST]|
| NRC NOTIFIED BY:  DAVE BAHNER                  |LAST UPDATE DATE:  11/05/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PHIL HARRELL         R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       0        Startup          |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP ON ROD CONTROL PROBLEM                                   |
|                                                                              |
| "Reactor startup was in progress. Power was stabilized at 10E-8 amps in the  |
| intermediate range to take critical data. A rod control urgent failure was   |
| received when the last rod step was taken to stabilize power. Maintenance    |
| was called to investigate. After troubleshooting, a card was replaced in the |
| logic cabinet. Rods were requested to be inserted 1 step after card          |
| replacement for post maintenance testing. Rods continued to move in with no  |
| demand. Rods inserted 2.5 steps until another urgent failure came in and     |
| stopped rod motion. The reactor trip breakers were opened at this time."     |
|                                                                              |
| All rods fully inserted and all other systems functioned as required.        |
| Troubleshooting will continue for the rod control system.                    |
|                                                                              |
| The licensee has notified the NRC Resident Inspector.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37492       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 11/06/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:29[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/06/2000|
+------------------------------------------------+EVENT TIME:        03:38[CST]|
| NRC NOTIFIED BY:  DOUG HITZEL                  |LAST UPDATE DATE:  11/06/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PHIL HARRELL         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       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT                                                       |
|                                                                              |
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO PERIMETER MONITORING.  IMMEDIATE    |
| COMPENSATORY MEASURES TAKEN UPON DISCOVERY.  THE LICENSEE WILL INFORM THE    |
| NRC RESIDENT INSPECTOR.  CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR     |
| ADDITIONAL DETAILS.                                                          |
+------------------------------------------------------------------------------+