Event Notification Report for May 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/18/1999 - 05/19/1999
** EVENT NUMBERS **
35604 35729 35730 35731 35732 35734 35735 35736
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35604 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/19/1999|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 15:07[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/19/1999|
+------------------------------------------------+EVENT TIME: 11:15[EDT]|
| NRC NOTIFIED BY: RICK LANGE |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION NOTIFIED OF 11 GALLON |
| OIL SPILL - |
| |
| AT 1115 ON 04/19/99, THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF |
| ENVIRONMENTAL CONSERVATION THAT APPROXIMATELY 11 GALLONS OF HYDRAULIC OIL |
| HAD SPILLED ON PAVED AND UNPAVED AREAS FROM A RUPTURED FORKLIFT HYDRAULIC |
| LINE. THE LICENSEE CLEANED UP THE OIL AND REMOVED THE AFFECTED SOIL. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE 1431EDT ON 5/18/99 FROM BRIAN WEAVER TO S.SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "At 1507 on 4/19/99, a 4-hr non-emergency phone notification was made to the |
| NRC by this facility regarding an 11 gallon hydraulic oil spill on paved and |
| unpaved areas from a rupture on a forklift hydraulic line under the category |
| of 10CFR 50.72(b)(2)(vi), Any event or situation, related to the health and |
| safety of the public or onsite personnel, or protection of the environment, |
| for which a news release is planned or notification to other government |
| agencies has been or will be made. |
| |
| "Subsequent review of the site reportability procedure and 10CFR |
| 50.72(b)(2)(vi) has determined that this event is not reportable under that |
| statute, specifically that the oil spill was not environmentally significant |
| in that the volume was actually only 2.5 gallons and that the spill was |
| immediately contained and cleaned up such that no oil reached ground or |
| surface water. No news release was made for the incident. |
| |
| "On this basis, this notification is being retracted." |
| |
| The licensee notified the NRC Resident Inspector. Notified R1DO(Trapp). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35729 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 02:07[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: 00:41[EDT]|
| NRC NOTIFIED BY: MIKE ECKHART |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RUDOLPH BERNHARD R2 |
|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 83 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP FROM 73% POWER DUE TO UNEXPECTED HIGH MAIN TURBINE |
| VIBRATION |
| |
| While the licensee was in the process of increasing load after exiting a |
| refueling outage, vibrations on the #1 and #2 bearings for the main turbine |
| were noted to be increasing unexpectedly. As a result, operators began to |
| decrease load at 0036 on 05/18/99 with the unit at approximately 83% reactor |
| power. Operators manually tripped the reactor from 73% power at 0041. At |
| that time of the manual reactor trip, vibrations on the #1 and #2 bearings |
| were at a level of about 10� mills and 12 mils, respectively. The limits on |
| vibration are either 10 mils for 15 minutes or when a vibration of 12 mils |
| is reached. |
| |
| All control rods fully inserted as a result of the manual reactor trip, and |
| all systems functioned as required. There were no engineered safety feature |
| actuations or emergency core cooling system injections, and none were |
| required. |
| |
| The unit is currently stable in Mode 3 (Hot Standby). The reactor coolant |
| pumps, normal charging and letdown, and pressurizer heaters and sprays are |
| being utilized for primary system transport, level, and pressure control. |
| All containment parameters are normal. Emergency feedwater was manually |
| initiated and is currently supplying water to the steam generators. |
| Secondary steam is being dumped to the condenser. Offsite power is |
| available, and the emergency diesel generators and emergency core cooling |
| systems are operable and available if needed. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35730 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 12:24[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: 09:07[EDT]|
| NRC NOTIFIED BY: ART BREADY |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |JIM TRAPP 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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Primary Containment Isolation Signal (PCIS) unexpectedly generated during |
| planned maintenance on the "B" channel Radiation Monitoring System. |
| |
| "While de-energizing the 'B' channel Radiation Monitoring System (RMS) to |
| replace a power supply, an unexpected 'B' channel actuation of the Primary |
| Containment Isolation System (PCIS, an ESF system) |
| occurred. The single channel actuation resulted in isolation of three |
| Containment Isolation Valves, electrical load shedding of two non-1E |
| ventilation fans, and automatic starts of the 'B' channel Filtration |
| Recirculation and Ventilation (FRVS) fans and Safety Auxiliaries Cooling |
| Pump (SACS). All isolations and actuations occurred as designed. The power |
| supply was re-energized and plant systems and components restored. The |
| impact on plant operation from this single channel PCIS actuation was |
| minimal. All plant safety systems remained capable of performing their |
| required functions, except for the 'B' Switchgear Room Cooler which had been |
| removed from service for scheduled maintenance. As a result of the change |
| in Reactor Building pressure, the Reactor Building to Turbine Building steam |
| tunnel blowout panel briefly indicated open, and is currently closed. A |
| visual inspection of the blowout panel is in progress. |
| |
| "The initial investigation has determined that de-energizing the 'B' channel |
| RMS power supply simulated high Reactor Building exhaust and Refueling Floor |
| exhaust radiation signals from the three RMS channels which input into the |
| 'B' PCIS channel. Investigation into the root cause of the single channel |
| actuation is in progress." |
| |
| The licensee informed the NRC Resident Inspector and will inform local |
| authorities (LAC Township). |
| |
| * * * UPDATE 1453 EDT ON 5/18/99 FROM BREADY TO S. SANDIN * * * |
| |
| The licensee has completed the visual inspection of the blowout panel with |
| no abnormalities noted. The licensee will inform the NRC Resident |
| Inspector. Notified R1DO(Eselgroth). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35731 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 12:47[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: JOSEPH A. WIDAY (FAX) |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: |VERN HODGE NRR |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DEFICIENT CONTROL RELAYS IDENTIFIED DURING PRE-INSTALLATION TESTING. |
| |
| ON 4/2/99, THE LICENSEE IDENTIFIED THAT CONTROL RELAYS (NBFD65NR) |
| MANUFACTURED BY EATON CORPORATION CONTAINED A MANUFACTURING DEFICIENCY, |
| I.E., "THE RELAY COIL HAD BEEN INCORRECTLY WIRED SUCH THAT THE INTERNAL |
| RELAY DESIGN, WHICH INCLUDES A PICK UP AND A HOLD COIL, WOULD OPPOSE EACH |
| OTHER AT LOWER VOLTAGES AND PROHIBIT HOLDING COIL ACTUATION WHICH RESULTED |
| IN EXCESSIVE RELAY CHATTER." THIS DEFECT WAS IDENTIFIED DURING |
| PRE-INSTALLATION TESTING PRIOR TO USE IN THE REACTOR TRIP LOGIC. NO |
| DEFICIENT RELAYS ARE INSTALLED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35732 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/18/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:06[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/17/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:40[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/18/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON R3 |
| DOCKET: 0707002 |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR REPORT DUE TO A "Q" SAFETY SYSTEM ACTUATION. |
| |
| "ON 5/17/99 AT 1540 HOURS THE #2 AUTOCLAVE EXPERIENCED A STEAM SHUT DOWN. |
| THE AUTOCLAVE WAS IN MODE II(HEATING) APPROXIMATELY TEN MINUTES WHEN THE |
| AUTOCLAVE EXPERIENCED A STEAM SHUTDOWN. OPERATIONS PERSONNEL ATTEMPTING TO |
| DETERMINE THE CAUSE RE-OPENED THE STEAM VALVE AND THEN RECEIVED A HIGH |
| CONDENSATE LEVEL SHUTDOWN ALARM. THE AUTOCLAVE WAS DECLARED INOPERABLE AT |
| 1710 HOURS AND INVESTIGATIONS ARE ON GOING. |
| |
| "THIS WAS AN AUTOMATIC ACTUATION OF A 'Q' SAFETY SYSTEM AND IS REPORTABLE TO |
| THE NRC BY USEC WITHIN 24 HOURS. THE SENIOR NRC RESIDENT HAS BEEN |
| NOTIFIED. |
| |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35734 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 15:52[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: RON STRICKLAND |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH R1 |
|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 85 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT |
| |
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO DETECTION/MONITORING/ALARM OF VITAL |
| AREA ACCESS DOORS. IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. CONTACT THE |
| HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35735 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 17:58[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: 17:08[EDT]|
| NRC NOTIFIED BY: MICHAEL CLOUTIER |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 97 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 MANUALLY SCRAMMED FOLLOWING TRIP OF THE "A" RECIRC PUMP. |
| |
| Unit 2 was manually scrammed following the unexpected trip of the "A" recirc |
| pump. At the time, electrical maintenance was in progress on the respective |
| motor-generator set. Following the recirc pump trip, operators initiated a |
| manual scram per procedure based on power-to-flow criteria. There was no |
| power peaking observed. All control rods fully inserted. Unit 2 is |
| currently in hot shutdown with steam bleed to the main condenser for decay |
| heat removal. All systems functioned as required. Both the traverse incore |
| probes and the recirc sump isolated during the transient as expected. |
| Offsite power is available and the emergency diesel generators are in |
| standby. The licensee informed the NRC Resident Inspector. |
| |
| * * * UPDATE 2108EDT ON 5/18/99 FROM JEFF GROFF TO S.SANDIN * * * |
| |
| The following information was provided as an update: |
| |
| "On 5/18/99 at 17:08, operators inserted a manual reactor scram due to |
| operation in the 'Scram Region' of the Power to Flow Map. All control rods |
| fully inserted into the core. Reactor water level is being maintained in |
| the normal operating band using the condensate system. |
| |
| "Preliminary investigation determined that while performing routine field |
| brush maintenance, a ground occurred tripping the 'A' Recirculation Pump. |
| The subsequent reactor power and flow decrease placed the reactor in the |
| 'Scram Region.' |
| |
| "Following the scram, water level dropped to approximately 130 inches, the |
| following 'Level 3' isolations occurred as expected: |
| |
| Group 4 - RHR Shutdown Cooling and Head Spray |
| Group 13 - Drywell Sumps |
| Group 15 - Traversing Incore Probe System |
| |
| "All valves in Group 4 and 15 were closed prior to the event, Group 13 |
| valves closed as designed. No ECCS systems initiated and no SRVs lifted. |
| All Emergency Diesel Generators are available." |
| |
| The licensee informed the NRC Resident Inspector of this update. Notified |
| R3DO(Clayton). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35736 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/18/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 19:13[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/18/1999|
+------------------------------------------------+EVENT TIME: 18:52[EDT]|
| NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 05/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |PETER ESELGROTH R1 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |CHARLES MILLER IRO |
| |SAM COLLINS NRR |
| |JOHN ZWOLINSKI NRR |
| |VICTOR DRICKS OPA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO REQUEST FOR OFFSITE FIRE FIGHTING ASSISTANCE |
| TO EXTINGUISH MAIN TRANSFORMER FIRE. |
| |
| THE UNIT IS CURRENTLY IN A REFUELING OUTAGE WITH FUEL IN THE VESSEL WITH NO |
| FUEL MOVEMENTS IN PROGRESS. DURING HI-POT TESTING OF THE MAIN TRANSFORMER |
| WHICH HAD BEEN DISCONNECTED FROM THE ELECTRICAL DISTRIBUTION SYSTEM, SMOKE |
| ERUPTED AT 1832EDT. THE FIRE BRIGADE RESPONDED AND A REQUEST FOR ASSISTANCE |
| TO THE PLYMOUTH FIRE DEPARTMENT WAS MADE. AT 1852EDT THE LICENSEE DECLARED |
| AN UNUSUAL EVENT BASED ON "ANY FIRE ONSITE FOR WHICH FIRE FIGHTING |
| ASSISTANCE IS REQUESTED." THERE WERE NO INJURIES OR UNACCOUNTED FOR |
| PERSONNEL. PLANT OPERATIONS IS NOT IMPACTED. THE FIRE BRIGADE IS ON SCENE |
| USING CARBON DIOXIDE FOR FIRE SUPPRESSION. LAYDOWN HOSES ARE POSITIONED |
| SHOULD THEY BECOME NECESSARY. THE LICENSEE DESCRIBED THE FIRE AS SMOLDERING |
| WITH NO VISIBLE FLAMES AND WAS NOT ABLE TO PROVIDE A DAMAGE ASSESSMENT AT |
| THIS TIME. |
| |
| THE LICENSEE CONTACTED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE 2143EDT ON 5/18/99 FROM MIKE ENGLAND TO S.SANDIN * * * |
| |
| THE UNUSUAL EVENT WAS TERMINATED AT 2125EDT AFTER VERIFYING THAT THE FIRE |
| WAS EXTINGUISHED. THE FIRE DEPARTMENT IS EXITING THE SITE. THE LICENSEE IS |
| PERFORMING A DAMAGE ASSESSMENT AT THIS TIME AND HAS INFORMED STATE/LOCAL |
| AGENCIES AND THE NRC RESIDENT INSPECTOR. NOTIFIED R1(ESELGROTH, ANDERSON), |
| NRR(RICHARDS) AND IRO(MILLER) AND FEMA (DEPUY). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021