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
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|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
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| 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
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| 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. |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021