U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/24/2003 - 04/25/2003
** EVENT NUMBERS **
39777 39780 39789 39790 39791 39792 39793 39794
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39777 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 04/21/2003|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 12:35[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/21/2003|
+------------------------------------------------+EVENT TIME: 11:40[EDT]|
| NRC NOTIFIED BY: A. HALLIDAY |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF SAFEGUARDS INFORMATION. |
| |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| CONTACT THE HOO FOR FURTHER DETAILS. |
| |
| |
| * * * * UPDATE ON 04/24/03 AT 1410 BY HALLIDAY TO GOULD * * * * |
| RETRACTION |
| |
| The Security Manager, with personnel from Security and Regulatory Compliance |
| reviewed the incident using the guidance in USNRC Regulatory guide 5.62, |
| Reporting of Safeguards Events, and USNRC Generic Letter 91-03, Reporting of |
| Safeguards events. It was determined that although the document contained |
| some low level safeguards information, the document could not have |
| significantly aided an adversary in defeating a security barrier or in |
| carrying out an act of radiological sabotage as the key piece of safeguards |
| information, an encryption table, was not filled out. Based on that |
| determination JAF is withdrawing the one-hour telephone notification |
| (EN-39777). The event remains a loggable event per 10 CFR 95.57(b). It was |
| entered into the Security Log at the time of notification. The event has |
| also been entered into the licensee's corrective action program for apparent |
| cause determination. |
| |
| The NRC Resident inspector was notified and the state will be notified. |
| |
| Notified the Reg 1 RDO(Gray) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39780 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MARYLAND DEPT OF THE ENVIRONMENT |NOTIFICATION DATE: 04/22/2003|
|LICENSEE: ENGINEERING CONSULTANT SERVICES |NOTIFICATION TIME: 11:05[EDT]|
| CITY: FREDERICK REGION: 1 |EVENT DATE: 04/22/2003|
| COUNTY: FREDERICK STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: MD2103701 AGREEMENT: Y |LAST UPDATE DATE: 04/22/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |HAROLD GRAY R1 |
| |TOM ESSIG NMSS |
+------------------------------------------------+MATT HAHN IAT |
| NRC NOTIFIED BY: ALAN JACOBSON | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN MOISTURE DENSITY GAUGE |
| |
| The licensee reported that upon arriving at their work site in Bethesda, MD |
| early in the morning of 04/22/03 they discovered that their construction |
| trailer was broken into and a moisture density gauge stolen. The gauge is a |
| CPN Model # MC1DR, S/N MD00305503 containing 10 millicuries Cs-137 and 50 |
| millicuries Am-241:Be. The licensee notified the Montgomery County Police |
| (Case # B03089862). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39789 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 01:25[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/23/2003|
+------------------------------------------------+EVENT TIME: 19:23[CDT]|
| NRC NOTIFIED BY: MARK OKOPNY |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|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 67 Power Operation |67 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ACCIDENT MITIGATION |
| |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or |
| Condition that could have prevented fulfillment of a Safety Function needed |
| to Mitigate the Consequences of an Accident. On 04/23/03, at 18:15 CDST, the |
| 1A Diesel Generator was made inoperable for a scheduled surveillance. |
| Concurrent with this inoperability, the 0 Diesel Generator received a |
| spurious CO2 actuation signal. This spurious CO2 partial logic actuation did |
| not result in an actual CO2 injection into the 0 Diesel Generator Room. The |
| CO2 system partial actuation however resulted in several ventilation dampers |
| failing closed as designed. With these dampers closed, the ventilation |
| support system for the 0 Diesel Generator became inoperable, the 0 Diesel |
| Generator was declared inoperable at 1923 hours 04/23/03. This condition |
| resulted in both the 1A and 0 Diesel Generators concurrently being |
| inoperable. Actions were taken to terminate the 1A Diesel surveillance and |
| restore the 1A Diesel Generator to an operable status. This was accomplished |
| at 1952 hours 04/23/03. The 1A and 0 Diesel Generators were simultaneously |
| inoperable for 29 minutes. Due to the concurrent Diesel Generator |
| inoperabilities which affect redundant trains required to mitigate the |
| consequences of an accident, it has been determined that this event is |
| reportable as an 8 hour ENS notification. |
| |
| "Corrective actions have been initiated to address the 0 Diesel Generator |
| CO2 system and restore the ventilation dampers to an operable status. The |
| spurious actuation of the 0 Diesel Generator CO2 system was determined to be |
| due to a Non-Licensed Operator opening the fire detection panel for |
| inspection." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39790 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 04:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 03:48[EDT]|
| NRC NOTIFIED BY: STUART SCHUETTPELZ |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALERT |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JAMES LYONS NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MICHELE EVANS IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|CHUCK CAIN R4 |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT|CHARLIE BAGWELL FEMA |
| |JOHN FLACH NRC |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALERT DECLARED |
| |
| At 0348 EDT on 4/24/03, the plant experienced an influx of fish on the |
| intake screens for the circwater and essential service water (ESW) systems. |
| This resulted in a loss of vacuum to Units 1 and 2 main turbines, which led |
| operators to manually trip both reactors. Following the trip, operators |
| noted that ESW flow to all 4 emergency diesel generators (EDGs) was severely |
| degraded. This resulted in the licensee declaring all 4 EDG's inoperable. |
| An alert was declared at 0348 EDT, and the NRC entered Monitoring Mode at |
| 0506 EDT. |
| |
| * * * UPDATE AT 0600 ON 4/24/03 FROM LICENSEE TO H. CROUCH * * * |
| |
| All EDG's have adequate flow to be used in an emergency, but remain |
| inoperable. |
| |
| The licensee is assessing damage to intake screens and strainers in the ESW |
| system, and manually backwashing ESW screens. |
| |
| * * * UPDATE AT 0718 ON 4/24/03 FROM DEAN BRUCK TO E. THOMAS * * * |
| |
| The licensee made a 4-hour ENS notification under 10 CFR 50.72(b)(2)(iv)(B) |
| to inform the NRC of the manual reactor trips inserted on Units 1 and 2 at |
| 0328 and 0329 on 4/24/03 for the reasons listed above. Post-trip response |
| of the plant was normal. Main Steam Isolation Valves were manually closed |
| on both units due to lowering Reactor Coolant System temperature and |
| lowering vacuum. Both units remain in Mode 3. |
| |
| * * * UPDATE AT 1020 ON 4/24/03 FROM TODD CASPER TO E. THOMAS * * * |
| |
| The licensee made an 8-hour ENS notification under 10 CFR 50.72(b)(3)(iv)(A) |
| to inform the NRC of the Auxiliary Feedwater System (AFW) actuations in |
| Units 1 and 2 following the reactor trips. The heat removal path for both |
| units is via AFW to the steam generator pressure operated relief valves. |
| |
| * * * UPDATE AT 0532 ON 4/25/03 FROM R3 IRC TO E. THOMAS * * * |
| |
| The licensee terminated the Alert at 0521 EDT. The Alert was terminated |
| based on having one train of ESW and one EDG declared OPERABLE for each |
| Unit. The NRC exited the Monitoring Mode of normal operations at 0532 EDT. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39791 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/24/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:42[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/24/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: [CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/24/2003|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS R3 |
| DOCKET: 0707001 |DANIEL GILLEN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM WHITE | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY CONTROL 24-HOUR REPORT (RESPONSE BULLETIN 91-01) |
| |
| The following information was obtained from the regulatee via facsimile: |
| |
| "At 1320 [CDT] on 4/23/03, the Plant Shift Superintendent (PSS) was notified |
| that the trap media replacement activities for C-337 #4 Seal Exhaust (SX) |
| trap were performed on 4/6/03 through 4/8/03 and the trap media and the |
| bottom screen were replaced. Contrary to the requirements of NCSA CAS-007, |
| 'independent verification of no trap media below the bottom screen' was not |
| performed prior to the bottom flange being removed. This requirement |
| ensures that an unanalyzed volume of media does not spill from the trap. |
| |
| "The NRC Resident Inspector has been notified of the event. |
| |
| "PDGP Assessment and Tracking Report No. ATR 03-1199 PGDP Event Report No. |
| PAD-2003-008 NRC Event Worksheet [39791]. |
| |
| "Responsible Division: Maintenance |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "Although the trap was not independently verified to be essentially empty of |
| accumulated trap mix, prior to in-place maintenance, no media was found when |
| the bottom flange was removed. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(s) OF HOW |
| CRITICALITY COULD OCCUR): |
| |
| "In order for a criticality to be possible, a critical volume of trap mix |
| would have to be accumulated in an unsafe geometry. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION. ETC): |
| |
| "Double contingency is maintained by implementing two controls on volume. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): |
| |
| "There was no media found when the bottom flange was removed. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL (S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| |
| "The first leg of double contingency relies on controlling the volume of |
| trap mix available to be spilled from the, trap after removal of media above |
| the bottom screen. NCSA CAS-007 requires the trap to be verified emptied of |
| trap media prior to in-place maintenance, thus ensuring that the trap does |
| not contain any accumulated trap mix in excess of a 5.5-gal drum. |
| Verification of the trap mix accumulated in the trap was not done, thus, |
| this control was violated. |
| |
| "The second leg of double contingency relies on controlling the volume of |
| trap mix available to be spilled from the trap after removal of media above |
| the bottom screen. NCSA CAS-007 requires the trap to be independently |
| verified emptied of trap media prior to in-place maintenance. Independent |
| verification of the trap mix accumulated in the trap was not performed, |
| therefore, this control was violated. Neither of the controls (verification |
| and independent verification) of the single parameter (volume) were |
| performed and double contingency was not maintained. |
| |
| "No trap media was spilled from the trap, thus maintaining the volume |
| parameter. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| |
| |
| "None." |
| |
| Operations notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39792 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 12:07[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 11:00[EDT]|
| NRC NOTIFIED BY: JOHN SHIPMAN |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALERT |MONTE PHILLIPS R3 |
|10 CFR SECTION: |MICHELE EVANS IRO |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |TERRY REIS NRR |
| |JIM CALDWELL R3 |
| |DENVER |
| |JANIE EVERETTE DOE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALERT AT PERRY DUE TO EVENT IN FUEL HANDLING BUILDING |
| |
| "At 11:00 the control room received a High alarm on the FHB Gas and Alert on |
| FHB Iodine. ONI ZZZ-7 was entered along with ONI J11-2 and ONI D17. Fuel |
| movement was stopped after all fuel was placed in a safe condition. The FHB, |
| Drywell, and Containment were evacuated and the Containment and FHB closure |
| plans were carried out. At 11:30 the control room received a report that the |
| fuel bundle being inspected in the FHB had a bubble float to the top of the |
| pool. At 11:27 the alarms in the FHB reset. The entry into an Alert was |
| recognized at 11:50 and initial notifications were completed. The Technical |
| Support center has been staffed to develop a recovery plan." |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39793 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 15:33[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 09:47[CDT]|
| NRC NOTIFIED BY: ROBERT BRINKMAN |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHUCK CAIN R4 |
|10 CFR SECTION: |MICHELE EVANS IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|TERRY REIS NRR |
|ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GRAND GULF AUTOMATIC SCRAM AND ECCS INJECTION DUE TO PARTIAL LOOP |
| |
| "At 09:47 (CDT), Grand Gulf Nuclear Station (GGNS) auto scrammed due to |
| complications following a partial loss of offsite power. At the time of the |
| scram there was a severe thunderstorm in the vicinity of GGNS. It is |
| believed that high winds caused damage in the GGNS switchyard which in turn |
| led to the partial LOOP. The following items actuated/initiated during this |
| event: |
| |
| "1. RPS automatic actuation, exact cause unknown. |
| "2. HPCS and RCIC initiated on reactor water level 2 and injected into the |
| vessel to restore water level. |
| "3. Division 2 and 3 EDGs started on a loss of power to the 16 and 17 buses. |
| Division 2 and 3 EDG energized the 16 and 17 buses respectively. |
| "4. Some time after the initial event the 15 bus lost power and was |
| re-energized by the Division 1 EDG. |
| "5. All MSIVs isolated on loss of power. |
| "6. Containment isolation occurred on power loss and on reactor water level |
| 2. |
| |
| "At present reactor water level is being maintained with RCIC and reactor |
| pressure is being maintained with SRVs. A review of plant data is underway |
| to confirm proper response of plant equipment." |
| |
| The NRC Resident Inspector was notified by the licensee. |
| |
| *****UPDATE ON 4/24/03 AT 19:20 FROM BRINMAN TO LAURA***** |
| |
| "It should be noted that offsite power was always available to the GGNS from |
| the ESF transformer #12 during/following the scram at 09:47 hours (CDT) on |
| 4/24/03. Also, there was no structural damage to the GGNS switchyard. There |
| was only minor damage to a locking collar on a disconnect in the GGNS |
| switchyard. The wind blew the disconnect closed breaking it's locking collar |
| and grounding the switchyard through a grounding strap. The grounding strap |
| disintegrated and a lockout occurred on service transformer #21 and the west |
| bus of the GGNS switchyard. Power has been restored to all busses and all |
| diesel generators have been secured." |
| |
| Notified R4DO (C. Cain) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39794 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 15:01[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 14:06[EDT]|
| NRC NOTIFIED BY: REID |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO HYDRAULIC OIL SPILL |
| |
| The licensee notified the state that they had approximately one tablespoon |
| of hydraulic oil spill from a manlift to the soil in the south RCA yard near |
| the rad waste reduction facility. |
| |
| The NRC RDO(Gray) was notified. |
+------------------------------------------------------------------------------+
