Event Notification Report for February 26, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/25/2002 - 02/26/2002
** EVENT NUMBERS **
38722 38723 38724 38725
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|Power Reactor |Event Number: 38722 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 02/25/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 04:25[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/25/2002|
+------------------------------------------------+EVENT TIME: 04:15[EST]|
| NRC NOTIFIED BY: STONE |LAST UPDATE DATE: 02/25/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 95 Power Operation |95 Power Operation |
| | |
| | |
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EVENT TEXT
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| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE |
| |
| The SPDS was removed from service for the purpose of implementing a |
| modification to replace the system. The primary means of monitoring the |
| critical parameters remains available to the operating crew and they will |
| continue to be able to perform the necessary actions regarding emergency |
| assessment. |
| |
| The NRC Resident Inspector will be notified. |
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|Power Reactor |Event Number: 38723 |
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| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 02/25/2002|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 15:00[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/25/2002|
+------------------------------------------------+EVENT TIME: 14:00[EST]|
| NRC NOTIFIED BY: ROBERT BOESCH |LAST UPDATE DATE: 02/25/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES LINVILLE R1 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 81 Power Operation |81 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| INABILITY TO MAINTAIN TEMPERATURES IN RELAY AND SWITCHGEAR ROOMS DUE
TO |
| CONTROL STRUCTURE HVAC SYSTEM INOPERABILITY |
| |
| The following is a portion of the facsimile from the Licensee: |
| |
| "During review of the station deficiency report the following reportable |
| condition was identified [at approximately 1400]. At 1855 on 2/22/02 while |
| placing the 'B' Control Structure Chiller handswitch from "auto" to "start", |
| the chiller tripped due to a trip of the Ventilation Supply Fan breaker. The |
| breaker was able to be reset and the Chiller was restored after 6 minutes. |
| The 'A' Control Structure Chiller was already inoperable with post |
| maintenance testing in progress. With the loss of Control Structure HVAC |
| System the ability to maintain temperatures in various spaces including |
| Relay rooms and Emergency Switchgear rooms was lost. The failure requires an |
| 8 hr ENS notification in accordance with 10CFR50.72(b)(3)(v)." |
| |
| The Resident Inspector was notified. |
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|Other Nuclear Material |Event Number: 38724 |
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| REP ORG: VA NATIONAL HP PROGRAM |NOTIFICATION DATE: 02/25/2002|
|LICENSEE: VETERANS ADMIN MEDICAL CTR |NOTIFICATION TIME: 16:10[EST]|
| CITY: BIRMINGHAM REGION: 2 |EVENT DATE: 02/25/2002|
| COUNTY: JEFFERSON STATE: AL |EVENT TIME: 14:15[CST]|
|LICENSE#: 01-00643-02 AGREEMENT: Y |LAST UPDATE DATE: 02/25/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LEONARD WERT R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+TIM MCGINTY IRO |
| NRC NOTIFIED BY: GARY WILLIAMS | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAA1 20.1906(d)(1) SURFACE CONTAM LEVELS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| RECEIPT OF A PACKAGE WITH A CONTAMINATED LABEL |
| |
| A thallium 201 transport container (metal "ammo" box) was found to be |
| contaminated with Technetium-99m upon arrival at the VA Medical Center in |
| Birmingham, AL from a vendor in Birmingham, AL. The removable contamination |
| was 969 DPM/cm� (limit =222 DPM/cm�) and identified as coming from a |
| magnetic sticker affixed to the box. The vendor, a commercial radiopharmacy, |
| was notified, and the licensee planned to notify the State of Alabama. The |
| licensee indicated that a similar event occurred at this hospital about 2 |
| years ago. |
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|Fuel Cycle Facility |Event Number: 38725 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/25/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:30[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/25/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/25/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |KENNETH RIEMER R3 |
| DOCKET: 0707001 |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM E. WHITE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NRC BULLETIN 91-01 RESPONSE (24-Hour Report) |
| |
| "At 1530 [CDT], on 02-25-32, the Plant Shift Superintendent (PSS) was |
| notified that the adjacent system post-removal NDA or visual inspection was |
| not performed as required by GEN-10 for the accumulator in C-310. The |
| post-removal NDA for the adjacent system is required to be performed within |
| 24 hours of the equipment being removed. The post-removal NDA measurement |
| is used to independently verify the mass of any potential adjacent system |
| deposit is less than an always-safe mass and can be characterized as |
| Uncomplicated Handling (UH), The pre-removal NDA indicated a UH deposit in |
| the adjacent system." |
| |
| "The post-removal NDA measurement was subsequently performed which confirmed |
| the adjacent system to be UH." |
| |
| "In summary, actions required by the NCSA were not completed within the time |
| frame specified." |
| |
| "The NRC Senior Resident Inspector has been notified of this event." |
| |
| "PGDP Assessment and Tracking Report No. ATR-02-1040; PGDP Event Report No. |
| PAD-2002-009, Event Worksheet [38725]." |
| |
| "Responsible Division: Operations" |
| |
| "SAFETY SIGNIFICANCE OF EVENTS:" |
| |
| "Double contingency was not maintained because the independent verification |
| of mass In the adjacent system was not performed within 24 hours of |
| equipment removal. The control relied upon for independent verification of |
| less than an always-safe mass was violated. However, a second independent |
| post-removal NDA result confirmed an always-safe mass." |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR:" |
| |
| "In order for a criticality to be possible, the pre-removal NDA would have |
| to be in error and a uranium deposit would have to exceed the always-safe |
| mass of approximately 30 pounds at 5.5 wt. %235 U. The deposit within the |
| adjacent system would then need to become moderated through wet air |
| in-leakage or introduction of moderator from a sprinkler activation, RCW |
| leak, etc." |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION,
ETC.:" |
| |
| "The controlled parameter is mass." |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE
PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS):" |
| |
| "The adjacent equipment post-removal NDA indicated <15 pounds of U with an |
| assay of 5.27% with <325 grams of U235." |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND
DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES:" |
| |
| "Double contingency for the adjacent system of the equipment removed relies |
| on the control of mass by two independent verifications. The mass process |
| condition is controlled by two independent verification of an always-safe |
| mass using NDA or visual inspections." |
| |
| "The first leg of double contingency is established by the requirement to |
| perform a pre-removal NDA measurement to ensure the adjacent system contains |
| lass than an always-safe mass prior to making the first cut. The |
| pre-removal NDA was performed and showed less than an always-safe mass. |
| This control was maintained." |
| |
| "The second leg of double contingency is established by the independent |
| verification of less than an always-safe mass by a post-removal NDA |
| measurement or visual inspection performed on the adjacent system within 24 |
| hours of equipment removal. The post-removal NDA or visual inspection was |
| not performed within the required time frame. Therefore, neither the |
| control nor the process condition was maintained." |
| |
| "The post-removal NDA measurement or visual inspection on the adjacent |
| system was not performed within the required 24-hour time limit. Therefore, |
| double contingency was not maintained." |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS
|
| IMPLEMENTED:" |
| |
| "Post-removal NDA has been completed with the results indicating the |
| adjacent piping is Uncomplicated Handling (UH)." |
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Page Last Reviewed/Updated Wednesday, March 24, 2021