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The following information was provided by the licensee: A Notification of Unusual Event, HU4.4 (see note below) was declared based a fire in the protected area requiring off site assistance to extinguish. The fire was in the main transformer yard. The fire was detected at 2328 CDT on March 21, 2024, and the fire was declared out at 0009 CDT on at March 22, 2024. An automatic reactor trip was initiated due to a loss of offsite power to the "B" train and a failure to automatically transfer from unit auxiliary transformer "B" to startup transformer "B. The licensee notified State and local authorities and the NRC Resident Inspector. The NRC remained in Normal. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email). NOTE: Due to a typographical error initiating condition HU4.1 was initially recorded for the event. The correct initiating condition is HU4.4 as now shown.

• * * UPDATE AT 0345 EDT ON 03/22/24 FROM LARRY GONSALES TO BILL GOTT * * *

The licensee terminated the Notification of Unusual Event at 0221 CDT on 3/22/24. The licensee notified the NRC Resident Inspector. Notified R4DO (Gepford), IR-MOC (Grant), NRR-EO (Felts), DHS-SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).

• * * UPDATE AT 0420EDT ON 03/22/24 FROM JOHN LEWIS TO BILL GOTT * * *

RPS ACTUATION The following information was provided by the licensee via email: On March 21, 2024, at 2328 CDT, Waterford 3 Steam Electric Station, Unit 3 was operating at 98 percent power when an automatic reactor trip was initiated due to a loss of offsite power to the B train and a failure to automatically transfer from unit auxiliary transformer B to startup transformer B. Emergency feedwater actuation signal 2 (EFAS), safety injection actuation signal (ECCS), containment isolation actuation signal and emergency diesel generators automatically actuated. The unit is currently stable in Mode 3. All control rods fully inserted and all other plant equipment functioned as expected. Forced circulation remains with one reactor coolant pump per loop running. Decay heat removal is via the main condenser. A train safety bus is being supplied by off-site power, and B train safety bus is being supplied by emergency diesel generator B. Following the loss of offsite power to the B train, it was reported that main transformer B and startup transformer B were both on fire. The Emergency Director declared an Unusual Event at time 2337 CDT. The fire was reported extinguished at 0009 CDT on March 22, 2024, and the Unusual Event was terminated at 0221 CDT on March 22, 2024. Offsite assistance was requested. The local fire department responded to the site but the fire was extinguished by the on-shift fire brigade. NRC Region IV management was contacted regarding the emergency plan entry at 0030 CDT on March 22, 2024. This event is being reported as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system (RPS) when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as valid actuation of the EFW system, ECCS, Containment Isolation and Emergency Diesel Generators. The NRC Resident Inspector has been notified. Notified R4DO (Gepford)

• * * RETRACTION OF NOTICE OF UNUSUAL EVENT FROM ON 03/26/24 AT 1721 FROM L. BROWN TO K. COTTON * * *

The initial notification in event notice #57042 by Waterford Steam Electric Station, Unit 3, reported a Notice Of Unusual Event (NOUE) emergency declaration due to a fire in the protected area requiring off site support to extinguish. The basis for retraction of the initial emergency notification is that this event did not meet the definition of a fire in the protected area that requires off site support to extinguish. Guidance provided in Nuclear Energy Institute (NEI) 99-01, Rev. 6 and implemented in Waterfords Emergency Plan procedure, initiating Condition HU4.4 states, The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish. (NOTE: The Initial Notification Form sent from the Control Room at 2341 CDT on March 21, 2024, requested by and provided to the NRC Headquarter Operations Center via e-mail at 0302 CDT on March 22, 2024, stated that the Emergency Classification had been made on Initiating Condition HU4.4 rather than HU4.1)" When the event occurred on March 21, 2024, the Emergency Director declared an Unusual Event at 2337 CDT and requested offsite support based on the information available at that time including the initial assessment by the fire brigade leader and expected need for offsite support to extinguish the fire. As reported in the 0420 EDT update on March 22, 2024, the fire was reported extinguished at 0009 CDT on March 22, 2024, by the Waterford Fire Brigade without the need of offsite support." Notified R4DO (Kellar).

• * * UPDATE AT 1209 EDT ON 03/27/24 FROM JOHN LEWIS TO KAREN COTTON * * *

The initial notification in EN 57042 by Waterford Steam Electric Station, Unit 3, reported an emergency declaration of an Unusual Event due to a fire in the protected area requiring off site support to extinguish. The basis for the update to the initial notification is that this event did not meet the definition of a Fire in the Protected Area that requires offsite support to extinguish. As provided in NEI 99-01, Rev. 6 and implemented in Waterfords emergency plan procedure, initiating condition HU4.4 states, The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish. Additionally, EAL 4.1 for a fire not extinguished within 15 minutes of detection in any Table H-1 fire area was not applicable because the fire did not occur in a Table H-1 fire area. When the event occurred on March 21, 2024, the Emergency Director declared an Unusual Event at 2337 CDT and requested offsite support based on the information available at that time including the initial assessment by the fire brigade leader and expected need for offsite support to extinguish the fire. As reported in the 0420 EDT update on March 22, 2024, the fire was reported extinguished at 0009 CDT on March 22, 2024, by the Waterford Fire Brigade without the need of offsite support. (NOTE: The Initial Notification Form sent from the Control Room at 2341 CDT on March 21, 2024, requested by and provided to the Headquarters Operation Center via e-mail at 0302 CDT on March 22, 2024, stated that the emergency classification had been made on initiating condition HU4.4 rather than HU4.1) In accordance with NRC Approved guidance in FAQ 21-02 (ML21117A104), Waterford 3 is retracting the initial event notification made at 0117 EDT on March 22, 2024. The remaining events that were reported in EN 57042 as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system (RPS) when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as valid actuation of the EFW (emergency feedwater) system, ECCS (emergency core cooling system), containment isolation and emergency diesel generators are still applicable and require no additional update at this time. The licensee also provided a site map. Notified R4DO (Kellar)

At 1728 EST on 11/15/2021, with Unit 1 in Mode 1 at 47 percent power, the reactor was manually tripped due to a main transformer fault. The trip was not complex, with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system through the main condenser. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, due to the valid actuation of the emergency feedwater system, this event is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified."

• * * UPDATE ON 11/16/21 AT 1649 EST FROM BRUCE BENNETT TO KERBY SCALES * * *

At approximately 0900 (EST) on 11/16/2021, it was identified that mineral oil from the faulted main transformer had surpassed the capability of the oil containment system and discharged into Lake Monticello. It is estimated that less than 50 gallons of mineral oil entered the Lake. The oil is contained with booms and cleanup is ongoing. The EPA National Response Center and the South Carolina Department of Health and Environmental Control have been notified. This is considered a news release or notification to other government agencies; therefore, this event is reportable under 10 CFR 50.72(b)(2)(xi). The NRC Senior Resident Inspector has been notified. Notified R2DO (Miller).

During a rain and lightning storm, plant operators observed arcing from the main transformer bus duct and notified the control room. The decision was made to trip the main generator which resulted in an automatic reactor trip. The plant entered EAL SU.1 as a result of the loss of offsite power for greater than fifteen minutes. Plant safety busses are being supplied by both emergency diesel generators while the licensee inspects the electrical system to determine any damage prior to bringing offsite power back into the facility. Offsite power is available to the facility. No offsite assistance was requested by the licensee. During the trip, all rods inserted into the core. Decay heat is being removed via the atmospheric dump valves with emergency feedwater supplying the steam generators. The main steam isolation valves were manually closed to protect the main condenser. There were no safeties or relief valves that actuated during the plant transient. There is no known primary-to-secondary leakage. Reactor cooling is via natural circulation. All safety equipment is available for the safe shutdown of the plant. The licensee has notified the NRC Resident Inspector, Louisiana Department of Environmental Quality and the local Parish emergency management agencies. Notified DHS SWO, FEMA, DHS NICC, FEMA National Watch Center (email) and Nuclear SSA (email).

• * * UPDATE ON 7/17/17 AT 2007 EDT FROM MARIA ZAMBER TO DONG PARK * * *

This notification is also made under 10 CFR 50.72(b)(3)(v)(D). This is a non-emergency notification from Waterford 3. On July 17, 2017 at 1606 CDT, the reactor automatically tripped due to a loss of Forced Circulation, which was the result of Loss of Offsite Power (LOOP) to the electrical (safety and non-safety) buses. Both 'A' and 'B' trains of Emergency Diesel Generators (EDGs) started as designed to reenergize the 'A' and 'B' safety buses. The LOOP caused a loss of feedwater pumps, resulting in an automatic actuation of the Emergency Feedwater (EFW) system. Prior to the reactor trip, at 1600 CDT, personnel noticed the isophase bus duct to main transformer 'B' glowing orange due to an unknown reason. Due to this, the main turbine was manually tripped at 1606 CDT. Following the turbine trip, the electrical (safety and non-safety) buses did not transfer to the startup transformers as expected due to an unknown reason. The plant entered the Emergency Operating Procedure for LOOP/Loss of Forced Circulation Recovery. At 1617 CDT, an Unusual Event was declared due to Initiating Condition (IC) SU1 - Loss of all offsite AC power to safety buses (greater than) 15 minutes. All safety systems responded as expected. The plant is currently in mode 3 and stable with the EDGs supplying both safety buses and with EFW feeding and maintaining both steam generators. Offsite power is in the process of being restored. The licensee has notified the NRC Resident Inspector, Louisiana Department of Environmental Quality and the local Parish emergency management agencies.

• * * UPDATE FROM ADAM TAMPLAIN TO HOWIE CROUCH AT 2203 EDT ON 7/17/17 * * *

The licensee terminated the Notification of Unusual Event at 2056 CDT. The basis for terminating was that offsite power was restored to the safety busses. The licensee has notified Louisiana Department of Environmental Quality, St. John and St. Charles Parishes, Louisiana Homeland Security Emergency Preparedness, and will be notifying the NRC Resident Inspector. Notified IRD (Stapleton), NRR (King), R4DO (Hipschman), DHS SWO, FEMA, DHS NICC, FEMA National Watch Center (email) and Nuclear SSA (email).

• * * UPDATE FROM SCOTT MEIKLEJOHN TO HOWIE CROUCH AT 1724 EDT ON 7/19/17 * * *

This update is being reported under 10 CFR 50.72(b)(3)(v)(B). During the event discussed in EN# 52863, at 1642 CDT (on July 17, 2017), Condensate Storage Pool (CSP) level lowered to less than 92% resulting in entry to Technical Specification (TS) 3.7.1.3. Level in the CSP was lowered due to feeding from both Steam Generators with EFW. Normal makeup to the CSP was temporarily unavailable due to the LOOP. Filling the CSP commenced at 1815 CDT (on July 17, 2017), and TS 3.7.1.3 was exited on July 18, 2017 at 0039 CDT. The licensee notified the NRC Resident Inspector. Notified R4DO (Hipschman).

• * * UPDATE FROM SCOTT MEIKLEJOHN TO HOWIE CROUCH AT 1233 EDT ON 9/14/17 * * *

Waterford 3 is retracting a follow up notification made on July 19, 2017 for EN# 52863, concerning the loss of safety function associated with the Condensate Storage Pool (CSP) per 10 CFR 50.72(b)(3)(v)(B). The Condensate Storage Pool was performing its required safety function by providing inventory to the Emergency Feed Water pumps when the required Tech Spec level (T.S. 3.7.1.3) dropped below 92%. The Technical Specification was entered at 1624 (CDT) on July 17, 2017 and exited after filling at 0039 on July 18, 2017. The total allowed outage time allowed by Tech Spec 3.7.1.3 is 10 hours to be in Hot Shutdown if not restored. The Condensate Storage Pool level was restored to greater than 92% prior to exceeding the allowed outage time. Based on level being restored and the Condensate Storage Pool performing its required safety function, 10 CFR 50.72(b)(3)(v)(B) does not apply. Prior to the automatic reactor trip, Condensate Storage Pool level was greater than 92%. The NRC Resident Inspector has been notified of the retraction. Notified R4DO (Groom).

At 1659 EST hours on January 6, 2014, Beaver Valley Power Station Unit 1 automatically tripped from 100% power. The cause of the reactor trip was a main transformer differential trip. All rods fully inserted into the core and the plant is stable in Mode 3. All three auxiliary feedwater pumps automatically started as expected. Normal and Emergency Busses are being powered by Offsite Power. The cause of the main transformer differential trip is being investigated. All other equipment functioned as expected. At 1757 EST hours the Emergency Operating Procedures were exited. Resident inspector has been notified. Decay heat is being removed via the turbine bypass valves to the condenser. No primary or secondary safety valves lifted. Unit 2 was unaffected.

Licensee notified the States of Pennsylvania, Ohio, and West Virginia and the Counties of Beaver, PA, Hancock, OH, and Columbiana, OH.

An unplanned, automatic reactor scram occurred at 0355 EST due to a Main Turbine trip signal. All safety systems operated and actuated as expected. Both the Main Transformer, T-1A and normal station services transformer T-4 activated their respective deluge systems. On-site fire brigade and offsite fire assistance have successfully extinguished the T-1A transformer fire. There is still an active fire in the T-1A bus ductwork. The plant will be taken to cold shutdown conditions. At 0545 EST the plant entered the emergency plan at the NUE level due to inability to successfully extinguish the fire. All control rods fully inserted following the reactor scram. MSIVs remain open with decay heat being removed via steam to the main condenser using the bypass valves. All electrical buses are powered from their normal offsite reserve source. The licensee notified the NRC Resident and appropriate State and local government agencies. Notified DHS SWO, FEMA, DHS NICC and NuclearSSA via email.

• * * UPDATE FROM JOHN WALKOWIAK TO DONALD NORWOOD AT 0642 EST ON 11/11/2012 * * *

As of 0639 EST the fire in the T-1A bus ductwork has been extinguished.

• * * UPDATE FROM MARK HAWES TO DONALD NORWOOD AT 0747 EST ON 11/11/2012 * * *

Local fire department is on-site. No radiological release and no protective actions required. Plant cooldown in progress.

• * * UPDATE FROM MARK HAWES TO DONALD NORWOOD AT 0810 EST ON 11/11/2012 * * *

The Unusual Event (HU 6.1) has been terminated at 0801 EST. Cooldown in progress to cold condition. Reactor level at 206 inches and pressure is at 530 pounds. The licensee notified the NRC Resident and appropriate State and local government agencies. Notified R1DO (Dentel), NRR EO (McGinty), IRD (Gott). Notified DHS SWO, FEMA, DHS NICC and NuclearSSA via email.

On June 18, 2010, at approximately 0807 MST, a manual turbine trip was initiated due to loss of cooling for Main Transformer X01C. The power supplies for the transformer cooling system was lost due to an inadvertent actuation of the transformer fire protection deluge system. The damage to the energized equipment met the definition for an Emergency Action Level HU 2.2. Based on HU 2.2 the Unit 1 Shift Manager declared a Notification of an Unusual Event (NOUE) at 0808 MST applicable to Palo Verde Unit 1 only. The manual trip of the turbine initiated a Reactor Power Cutback Large Load Rejection actuation which was successful. The reactor is stable at 25% with Heat Removal via main feedwater and steam bypass to main condenser. A down power to approximately 12% power is being planned. No anomalies were noted during the manual turbine trip. (There is) no release in progress and no safety systems actuations were required. Palo Verde Unit 1 is in a normal post-trip electrical lineup. State and local authorities have been notified as well as the NRC Resident Inspector.

• * * UPDATE FROM BRIAN FERGUSON TO DONG PARK @ 1333 EDT ON 6/18/10 * * *

The licensee terminated the Unusual Event at 1030 MST. The reactor remains stable at approximately 12% power, and heat removal is via main feedwater and steam bypass to the main condenser. Notified IRD (Gott), NRR EO (Cheok), R4DO (Jones), DHS (Inzer) and FEMA (Hollis).

At 2156 EST, a fire occurred on Main Transformer M1A. The loss of the main transformer resulted in a reactor scram from full power without complications. The transformer deluge system activated. The fire brigade responded and offsite assistance from the fire department was obtained to help extinguish the fire. The fire department has since departed the site. An Unusual Event was declared at 2211 EST based on the transformer fire lasting longer than 15 minutes. The fire was extinguished at 2227 EST. A fire reflash watch was established. There was no damage to any other equipment besides the main transformer. During the reactor scram transient, the isolation condenser actuated as expected and was subsequently secured. Four electro-magnetic relief valves actuated and reseated normally. The plant is currently in hot standby with reactor pressure at 927 psi and water level at 150 inches with all conditions stable and a normal electrical configuration. The licensee is assessing the criteria for exiting the UE at this time. The licensee has notified State and local government agencies and the NRC Resident Inspector.

• * * UPDATE FROM ZUCHOWSKI TO HUFFMAN AT 0001 EST ON 2/02/09 * * *

The licensee terminated the UE at 2337 EST due to stable plant conditions with all entry criteria for the UE exited and no concern of reflash. The licensee did note that there is an oil sheen on the water around the transformer and indication of a small amount of oil dripping from the transformer. The licensee is taking efforts to contain the spill with spill kits and barriers. The NRC Resident has been notified. Notified R1DO (Schmidt), R1 (Bellamy), NRR EO (Blount), and IRD (McMurtray). Informed DHS (Banner) and FEMA (Barden).

• * * UPDATE FROM FLESHER TO HUFFMAN AT 1907 EST ON 2/02/09 * * *

Upon review of the electromagnetic relief valve performance during the reactor scram at 2156 EST on 2/1/09, two electromagnetic relief valves opened - not four (as originally reported). Due to subsequent seat leakage of one electromagnetic relief valve, the valve was cycled and was able to be reseated. At 0444 EST on 2/2/09 downstream relief temperatures confirmed that the valve had reseated. The licensee has notified the NRC Resident Inspector. R1DO (Schmidt) notified.

At 0012 the licensee declared a Notice of Unusual Event due to a fire in Main Bank Transformer. The licensee is fighting the fire along with offsite assistance from CAL FIRE. The unit is shutdown and stable in mode 3. All control rods fully inserted on the trip. Decay heat is being removed via auxiliary feedwater to the steam generators steaming to the main condenser via the main condenser steam dumps. Emergency buses remain powered via offsite power with emergency diesel generators available if required. The licensee will notify the NRC Resident Inspector. Notified DHS (Barnes), FEMA (Blankenship).

* * * UPDATE FROM J. DILLIS TO J. KOZAL AT 0501 EDT ON 8/17/08 * * * 

The fire is out. Plant personnel are assessing the damage in the main transformer area. The plant is stable in mode 3. The licensee will notify the NRC Resident Inspector.

* * * UPDATE FROM J. DILLIS TO P. SNYDER AT 0542 EDT ON 8/17/08 * * * 

The licensee has terminated the Notice of Unusual Event at 0231 PDT due to the fact that the fire was out and no reflash occurred. The plant remains stable in mode 3. The licensee will notify the NRC Resident Inspector. Notified R4DO (Lantz), IRD (McMurtray), NRR EO (Wermiel), R4 (Collins), NRR (Grobe), DHS (Wallace), FEMA (Biscoe).

• * * UPDATE FROM M. KENNEDY TO J. KOZAL AT 1038 EDT ON 8/17/08 * * *

This is an update of the Notification of Unusual Event due to Fire in the 'C' phase of the main bank transformer, and Automatic Reactor Trip. This update is to report automatic actuation of the auxiliary feedwater system (AFW) and is being reported as an 8-hour non-emergency event in accordance with 10 CFR 50.72(b)(3)(iv)(A) 'System Actuation.' The unit is stable in mode 3 (Hot Standby) with offsite power being supplied to all buses via the 230 Kv startup circuit. All rods fully inserted on the reactor trip. All systems performed as designed. Operators are preparing to place the unit in Mode 5, while preparing to assess the damage to the 500 Kv transformer. All emergency diesel generators remain operable in standby. Unit 1 was unaffected by this event and remains at 100% power. This notification also constitutes a late 4 hour notification for the RPS actuation. To summarize, on August 16, 2008, at 2356 PDT, the 'C' phase 500 Kv transformer failed resulting in a fire and an automatic reactor trip, and automatic actuation of AFW. An unusual event was declared on August 17, 2008, at 0012 PDT due to the fire. Cal Fire was called to assist and support the on-site fire brigade. The fire was extinguished and the NUE was downgraded at 0231 PDT. The NRC Resident Inspector has been notified as well as State and local government agencies. The licensee intends to issue a press release. R4DO (Lantz) notified.

The Unusual Event was declared due to a fire lasting greater than 10 minutes (after discovery) within the protected area. The fire was located on the Isophase Bus Duct near the Main Transformer. A load reduction to 80% rated thermal power is in progress on Unit 1. The fire was extinguished at 0450 with dry chemicals extinguishers." The licensee believes the fire was on cabling in the Isophase bus duct due to overheating. The licensee has been monitoring hot spots on the duct cabling for several days. The fire did not apparently impact any other systems and observers are at the location monitoring for any change in conditions. No Tech Spec Limiting Conditions of Operations resulted from the fire and there is no impact on Unit 2 operations (which is currently at 100%). Termination criteria will be based on management judgment and safety assessment.

• * * UPDATE FROM P. UNDERWOOD TO M. RIPLEY 0727 EDT 05/01/06 * * *

Unusual Event terminated at 0655 (EDT). Fire extinguished. Reactor power reduction continuing. Management evaluating continued operation. The unit is currently at 77% power and plans are to reduce power to 60% pending their evaluation of continued operation. The licensee will notify the NRC Resident Inspector. Notified R2 DO (K. Landis), NRR EO (M.J. Ross-Lee), IRD Manager (P. Wilson), DHS (S. York), and FEMA ( M. Roland).

NUE declared on Hatch Unit 1 due to a fire on the main transformer lasting greater than 10 minutes. Unit 1 reactor scram on main turbine trip. Group 2 PCIV (Primary Containment Isolation Valves) isolation on low reactor water level (+3 inches). All group 2 valves closed as required. Fire extinguished at 1358 hours. Plant is stable. All control rods fully inserted on the reactor scram. The plant is in hot shutdown steaming through the turbine bypass valves to the main condenser. No safety systems are affected. Emergency electrical buses are on normal offsite power and emergency diesel generators are available if required. The onsite fire brigade responded to the fire and the fire suppression system for the main transformer functioned as expected. The licensee notified the NRC Resident Inspector.

• * * UPDATE FROM E. BURKETT TO W. GOTT AT 1950 ON 10/29/05 * * *

The licensee is still in a NUE. The fire is out. The fire reflashed at 1603 when the deluge system was secured to inspect the transformer. The deluge system was restarted immediately. Offsite fire support have responded. Cleanup efforts are in progress. The licensee notified the NRC Resident Inspector. Notified IRD (Blount), R2DO (Cahill), and NRR EO (J. Hannon).

• * * UPDATE FROM E. BURKETT TO P. SNYDER AT 2010 ON 10/29/05 * * *

The licensee is still in a NUE. This call is to add an offsite notification per 10 CFR 72.75 (b)(2) to another government agency. The site chemistry department notified the National Response Center (Coast Guard) at 1636 that the site had discharged an unknown quantity of oil into the Altamaha River and was implementing site spill control and countermeasures procedures. The licensee also notified the Georgia Environmental Protection Division. The licensee notified the NRC Resident Inspector. Notified IRD (Blount), NRR EO (J. Hannon), and R2DO(Cahill).

• * * UPDATE FROM E. BURKETT TO W. HUFFMAN AT 0021 EDT ON 10/30/05 * * *

The licensee reports that the fire is confirmed extinguished (i.e., no risk of reflash) based on long term monitoring of the transformer including thermography measurements. The Unit remains in an Unusual Event until assessment activities related to the transformer fire have been completed. The licensee notified the NRC Resident Inspector.

• * * UPDATE FROM E. BURKETT TO W. HUFFMAN AT 0105 EDT ON 10/30/05 * * *

Based on the results of assessment activities related to the transformer fire, the licensee has exited the Unusual Event at 0050. The licensee notified the NRC Resident Inspector. The R2DO (Cahill), EO (Hannon), IRD (Blount), DHS (Doyle), and FEMA (Bisco) have been notified.

UNUSUAL EVENT (EAL #16 - Fire) declared at 0327 on 6/27/05 due to uncontrolled fire in the Unit 4 Main Transformer lasting longer than 10 minutes. Unit 4 experienced an automatic reactor trip from 100% on a turbine trip due to a fire in the Main Transformer. The fire was extinguished after approximately 25 minutes. On-site fire brigade and Miami-Dade fire department responded. The cause of the fire is under investigation. The reactor is stable in Mode 3. No safety systems were affected. All rods fully inserted, no ECCS actuations, no relief valves lifted and no personnel injuries occurred. Offsite power is still available and no emergency diesels auto started, however, there was an auxiliary feedwater actuation. Hazardous Material response is being implemented due to discharge of transformer oil. There may be a possible press release on this event. The NRC Resident Inspector was notified along with State and local agencies.

• * * UPDATE ON 06/27/05 @ 05:13 BY SPEICHER TO GOULD * * *

The NOUE was terminated at 05:00 due to the fire being extinguished and the emergency no longer existing. The NRC Resident Inspector was notified. Notified RDO 3 (Evans), EDO (Case), IRO (Frant), FEMA (Bagwell), DHS (Reed)

• * * UPDATE 0915 EDT ON 6/27/05 BY S. SANDIN * * *

Received a call from a member of the Turkey Point Communications Group. The licensee does not plan on issuing a press release at this time. Notified R2DO (Evans).