Semantic search

The following information was provided by the licensee via email:

• • • 8 Hour Notification was due at 1520 CST *** Follow up discussion of conditions after recovery determined that a report is required. This report restores reporting compliance.

On March 5, 2024, at 0720 CST, the X-02 118V uninterruptible power supply air conditioning (UPS A/C) unit tripped with the associated emergency fan coil units (EFCUs) shut down for planned maintenance in the area. The X-01 UPS A/C unit was declared inoperable upon discovery due to a scheduled outage of support systems (Unit 1 station service water) via the safety function determination process. This placed the site in technical specification 3.7.20 condition A, B, and C to restore the UPS A/C system within one hour. The EFCUs were restarted at 0729 which satisfied condition B and C, and X-01 UPS A/C unit was aligned to Unit 2 cooling water at 0801, exiting condition A. The condition that could have prevented the fulfillment of the safety function lasted for approximately nine minutes. Area temperatures had no notable change based on field observations during the condition. The UPS HVAC system provides temperature control for the safety related UPS and distribution rooms during all normal and accident conditions. The UPS HVAC system consists of (a) a dedicated UPS room EFCU in each safety-related UPS and distribution room, and (b) two electrically independent and redundant A/C trains either of which can support all four safety related UPS and distribution rooms; each train consists of an air conditioning unit, ductwork, dampers, and instrumentation. The NRC Resident Inspector has been notified.

The following information was provided by the licensee via email: At 2108 EDT on August 17, 2022 the Division 2 Mechanical Draft Cooling Tower (MDCT) fans were declared inoperable due to failure of the over speed fan brake inverter. The brakes prevent fan over speed from a design basis tornado. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The Division 2 EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) room cooler and Division 2 Control Center HVAC (CCHVAC) chiller. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. At the time of the event, Division I CCHVAC was inoperable for maintenance (but was running for a maintenance run) and the event caused an inoperability of Division 2 CCHVAC. This resulted in an inoperability of both divisions of CCHVAC. Failure of the Division 2 MDCT Fan brake inverter occurred due to a trip of the DC input breaker. The breaker was reset at 2128 EDT restoring Division 2 UHS Operability. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfilment of the safety function of structures or systems that are needed to mitigate the consequences of an accident based on a loss of a single train safety system and loss of both divisions of a safety system. The Senior NRC Resident Inspector has been notified

• * * RETRACTION ON 09/08/2022 AT 0856 EDT FROM JEFF MYERS TO MIKE STAFFORD * * *

The following information was provided by the licensee via email: On 8/17/22 at 2108 EDT the Division 2 (Div. 2) mechanical draft cooling tower (MDCT) brake inverter input breaker tripped for an unknown cause. The result of the loss of power was the inoperability of the MDCT fan brakes which impacts the ultimate heat sink (UHS) (TS 3.7.2). The UHS cascades to the EECW (emergency equipment cooling water) (TS 3.7.2) which is a support system for Div. 2 CCHVAC (Control Cell) Chiller A/C system (TS 3.7.4). This resulted in the inoperability of the Div. 2 CCHVAC Chiller. The cause for the breaker to trip is an intermittent electrical transient. Immediate corrective action was to reset the breaker, and the long-term action is to implement a modification to mitigate susceptibility to voltage variations. Div. 1 has implemented this long-term mod and no unexpected trips have occurred to date. Div. 1 CCHVAC Chiller was previously inoperable from equipment issues which was repaired, and the unit was in service for a 24-hour confidence run. Although licensed personnel had not completed the administrative actions for documenting operability during the 24-hour confidence run to monitor parameters, the (post maintenance test) PMT related to the maintenance was already completed, which included a 4-hour run in accordance with surveillance 24.413.01, Div. 1 and Div. 2 Chilled Water Pump and Valve, to verify normal operation and motor current. These PMT's were completed prior to the identified inoperability of the Div. 2 UHS due to the tripped breaker on the brake power supply. At the time of the MDCT brake inverter trip, the Operations' Senior License and the Night Shift Manager were aligned that, although still operating as part of the 24-hour confidence run, the unit was in service and capable of performing its safety function, but the administrative tasks were not completed, the Limited Condition of Operation (LCO) sheet had not been cleared, and no log entries were made. Since the Div. 1 Chiller was, in fact, operable at the time of the trip of the breaker on the inverter, this would allow the use of Technical Specification (TS) 3.0.9 'Barriers'. Per Operations Department Expectation (ODE)-12 `LCOs' (standard guidance and expectations for preparing and implementing an LCO), Operations determined that the MDCT brakes are barriers to a tornado event and TS 3.0.9 could be utilized. By invoking TS 3.0.9, as long as all other supported systems in the other division are operable, Div. 2 supported systems relying upon the UHS can remain operable and the Automatic Depressurization System (ADS) and Reactor Core Isolation Cooling (RCIC) system can be used as backup to the High Pressure Coolant Injection (HPCI) system. Based on this information, there was no loss of safety function with CCHVAC A/C system or HPCI. Therefore, the NRC non-emergency 10CFR50.72(b)(3)(v)(D) report was not required and the NRC report 56054 can be retracted. The NRC Resident Inspector has been notified. Notified R3DO (Orlikowski)

EN Revision Imported Date : 10/12/2020 LOSS OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM DUE TO PLANNED MAINTENANCE: This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the planned maintenance affects the functionality of an emergency response facility. Planned maintenance activities are being performed on 09/28/20 to the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) HVAC. The work includes replacement of supply fan and roof-top unit. Work is scheduled to complete on 10/11/20. If an emergency is declared requiring PBAPS TSC activation during this period, the PBAPS TSC will be staffed and activated using existing Emergency Preparedness (EP) procedures. If the PBAPS TS becomes uninhabitable due to radiological, or other conditions, the TSC Station Emergency Director will relocate the TSC staff to an alternate location in accordance with EP procedures. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency. The NRC Resident Inspector will be notified by the licensee.

• * * UPDATE ON 10/9/20 AT 1234 EDT FROM BRIAN BAILEY TO ANDREW WAUGH * * *

An eight-hour, non-emergency notification for a loss of Emergency Assessment Capability was made on 9/28/20 under Event Notification 54917 for planned maintenance activities to the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) ventilation system. This event was reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the planned maintenance affected the functionality of an emergency response facility. This update to EN 54917 is to notify applicable stakeholders that, following satisfactory completion of the planned supply fan and roof-top unit replacement work, the PBAPS TSC ventilation system has been returned to service with no remaining work or outstanding deficiencies related to this work. The licensee has notified the NRC Resident Inspector. Notified R1DO (Lally).

On 5/22/2019, the 'A' Control Structure Chiller (Div I) tripped due to a loss of (motor control center) MCC 0B136. The 'B' Control Structure Chiller was already inoperable due to Div II (Emergency Service Water) ESW being out of service for planned maintenance. With the loss of Control Structure HVAC System the ability to maintain temperatures in various spaces including relay rooms, Control Room Floor Cooling and Emergency Switchgear rooms was lost. The 'B' Control Structure Chiller was restarted at 0251 EDT and cooling was reestablished to the required areas, however the 'B' chiller is not considered operable at this time. Units 1 and 2 entered (Technical Specification) TS 3.0.3 at 0256 EDT and a controlled shutdown of both units commenced, Unit 2 at 0340 EDT and Unit 1 0350 EDT. This constitutes a TS required shutdown and requires a 4 hour (Emergency Notification System) ENS notification in accordance with 10 CFR 50.72(b)(2)(i). The failure also requires an 8 hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v) due to the loss of a safety function. The licensee needs to restore the 'B' loop of ESW to exit the Limiting Condition of Operation (LCO). The licensee is currently performing a flow surveillance, once complete and assuming the data is acceptable, the licensee will be able to exit the LCO. The units are in a normal electrical lineup. The licensee will be notifying the state of Pennsylvania FEMA Operations Center. The licensee has notified the NRC Resident Inspector.

• * * UPDATE ON 05/22/2019 AT 1302 FROM SCOTT MYRTHEL TO THOMAS KENDZIA * * *

On 5/22/2019 at 0601 EDT Susquehanna Steam Electric Station reported a shutdown had been commenced at 0340 EDT for Unit 2 and 0350 EDT for Unit 1 due to inoperability of both control structure chillers. Power has been restored to MCC 0B136, and at 0901 EDT the 'A' control structure chiller was declared operable and LCO 3.0.3 was exited. Power reduction for both units was halted at 0901 EDT and preparations for power restoration initiated. As of 1255 EDT on 5/22/2019, Unit 1 power is 94% and Unit 2 power is 92%. Notified the R1DO (Arner).

At 0400 (CST) on 1/23/2018 the Braidwood Technical Support Center (TSC) HVAC (Heating, Ventilation and Air Conditioning) Emergency Makeup Air Filter train was taken out of service to perform a planned Makeup Air Filter charcoal replacement. The TSC HVAC Makeup Air Filter train will be rendered nonfunctional during the charcoal replacement. Subsequent charcoal and HEPA filter testing will restore functionality of the TSC HVAC Makeup Air Filter train. The expected duration of the charcoal replacement and subsequent testing is 30 hours. If an emergency is declared requiring TSC activation during the time TSC HVAC is non-functional, the TSC will be staffed and activated using existing emergency planning procedure unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures. This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to a major loss of emergency preparedness capability. An update will be provided once the TSC HVAC Emergency Makeup Air Filter train functionality has been restored. The licensee has notified the NRC Resident Inspector.

• * * UPDATE AT 1645 EST ON 01/26/2018 FROM PAUL ARTUSA TO JEFF HERRERA * * *

On 1/26/18 at time 1539 EST, the TSC HVAC Emergency Makeup Air Filter train was returned to service following the planned Makeup Alr Filter charcoal replacement. Functionality was verified by charcoal and HEPA filter post maintenance testing. The licensee has notified the NRC Resident Inspector. Notified the R3DO (Cameron).

On October 4, 2017, at 0250 hours (EDT), the Perry Nuclear Power Plant commenced a Technical Specification (TS) shutdown by lowering reactor power from 100 percent rated thermal power to 98 percent to comply with TS LCO 3.0.3. Reactor power was further reduced to 82 percent rated thermal power at 0430 hours (EDT). The plant had entered TS 3.0.3 at 0155 hours (EDT) upon loss of MCC (Motor Control Center), Switchgear, and Miscellaneous Electrical Equipment Areas HVAC System train A while train B was removed from service for maintenance. MCC switchgear ventilation train A was declared inoperable based on excessive belt noise and a dropped belt on MCC switchgear supply fan A. This also constitutes a loss of safety function. This event is being reported in accordance with 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector was notified.

• * * UPDATE ON 10/04/17 AT 0926 EDT FROM DAN HARTIGAN TO STEVEN VITTO * * *

Due to the loss of both trains of MCC, Switchgear, and Miscellaneous Electrical Equipment Areas HVAC, actions were taken in LCO 3.8.7 for AC and DC Distribution Systems, LCO 3.8.4 for DC Sources, LCO 3.8.1 for AC Sources, and the associated support systems, the High Pressure Core Spray system was also declared inoperable, which is a single train safety system and therefore, an additional loss of safety function. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(B), 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72 (b)(3)(v)(D). At 0620 hours (EDT) the A train of MCC, Switchgear, and Miscellaneous Electrical Equipment Areas HVAC and High Pressure Core Spray was declared operable and LCO 3.0.3 was exited. The plant was restored to 100% (percent) power at 0804 (EDT). The NRC Resident Inspector was notified. Notified R3DO(Hills).

On December 14, 2016, starting at 2345 EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met numerous times. The duration of time that the secondary containment Technical Specification was not met was approximately one second for each instance. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. At 0300 EST on December 15, 2016, high wind conditions had subsided and secondary containment vacuum was greater than the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) and steady, and the LCO was exited. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.

• * * RETRACTION AT 1922 EDT ON 3/17/2017 FROM DEREK ETUE TO BETHANY CECERE * * *

In this event notification, DTE Electric Company (DTE) reported conditions whereby the Fermi 2 secondary containment was believed to have exceeded Technical Specification Surveillance Requirements due to high winds. DTE hereby retracts this event notification as the Fermi 2 secondary containment has been determined to have been operable during this event as described below. The Fermi 2 secondary containment pressure is maintained at a pressure less than the external pressure to contain, dilute, hold up, and reduce the activity level of fission products prior to release to the environment, and to isolate and contain fission products that are released during a Design Basis Accident or certain operations. Secondary containment pressure is monitored by a number of differential pressure (dP) sensors. High wind gusts have resulted in momentary negative pressure on the leeward side of the building, causing a more positive pressure indication from one or more dP sensors. The secondary containment building pressure remains relatively constant during these 'wind events.' In December 2016, DTE implemented a software design change to display a 120-second rolling average for secondary containment dP indication. A 120-second rolling average recorded every second provides the operator a more accurate report of actual secondary containment conditions, while mitigating the signal noise and wind gust effects. The conditions associated with the subject event notification were re-reviewed in light of the improved secondary containment dP indication and it was determined that the Fermi 2 secondary containment was operable during this event. Specifically, the secondary containment pressure did not exceed Technical Specification Surveillance Requirements during this event. In summary, the above event notification is retracted because the Fermi 2 secondary containment was determined to have been fully operable during the conditions identified in the subject report. The licensee notified the NRC Resident Inspector. Notified R3DO (Stoedter)

On November 28, 2016, starting at 2105 hrs. EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met numerous times. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each instance. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. At 0055 EST on November 29, 2016, high wind conditions had subsided and secondary containment vacuum was greater than the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) and steady, and the LCO was exited. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.

• * * UPDATE FROM CHRIS MCALLISTER TO HOWIE CROUCH AT 1027 EST ON 11/29/16 * * *

On November 29, 2016, at 0242 EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met numerous times following the initial event notification. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each instance. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure to within TS limits. High wind conditions are expected to decrease throughout the day. If additional instances are identified that require entry into the Technical Specifications (TS) for secondary containment pressure boundary not being met, another follow up notification will be performed. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector. Notified R3DO (Stoedter).

• * * RETRACTION AT 1922 EDT ON 3/17/2017 FROM DEREK ETUE TO BETHANY CECERE * * *

In this event notification, DTE Electric Company (DTE) reported conditions whereby the Fermi 2 secondary containment was believed to have exceeded Technical Specification Surveillance Requirements due to high winds. DTE hereby retracts this event notification as the Fermi 2 secondary containment has been determined to have been operable during this event as described below. The Fermi 2 secondary containment pressure is maintained at a pressure less than the external pressure to contain, dilute, hold up, and reduce the activity level of fission products prior to release to the environment, and to isolate and contain fission products that are released during a Design Basis Accident or certain operations. Secondary containment pressure is monitored by a number of differential pressure (dP) sensors. High wind gusts have resulted in momentary negative pressure on the leeward side of the building, causing a more positive pressure indication from one or more dP sensors. The secondary containment building pressure remains relatively constant during these 'wind events.' In December 2016, DTE implemented a software design change to display a 120-second rolling average for secondary containment dP indication. A 120-second rolling average recorded every second provides the operator a more accurate report of actual secondary containment conditions, while mitigating the signal noise and wind gust effects. The conditions associated with the subject event notification were re-reviewed in light of the improved secondary containment dP indication and it was determined that the Fermi 2 secondary containment was operable during this event. Specifically, the secondary containment pressure did not exceed Technical Specification Surveillance Requirements during this event. In summary, the above event notification is retracted because the Fermi 2 secondary containment was determined to have been fully operable during the conditions identified in the subject report. The licensee notified the NRC Resident Inspector. Notified R3DO (Stoedter).

On November 19, 2016, starting at 2150 EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met numerous times. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each instance. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. At 0430 EST, high wind conditions have subsided and secondary containment vacuum was greater than the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) and steady, and the LCO was exited. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.

• * * UPDATE ON 11/20/16 AT 1416 EST FROM BRETT JEBBIA TO BETHANY CECERE * * *

On November 20, 2016, starting at 0654 EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met on multiple different occasions as of event notification update time. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each instance. Fermi 2 continues to remain in a gale force wind advisory for the local area of Lake Erie. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector. The R3DO (Jeffers) has been notified.

• * * UPDATE ON 11/20/16 AT 2104 FROM GREG MILLER TO BETHANY CECERE * * *

On November 20, 2016, at 1426 EST, high wind conditions encountered on site resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second. The Fermi 2 local area of Lake Erie is no longer in a gale force wind advisory and the high wind conditions have subsided. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector. The R3DO (Jeffers) has been notified.

• * * RETRACTION AT 1922 EDT ON 3/17/2017 FROM DEREK ETUE TO BETHANY CECERE * * *

In this event notification, DTE Electric Company (DTE) reported conditions whereby the Fermi 2 secondary containment was believed to have exceeded Technical Specification Surveillance Requirements due to high winds. DTE hereby retracts this event notification as the Fermi 2 secondary containment has been determined to have been operable during this event as described below. The Fermi 2 secondary containment pressure is maintained at a pressure less than the external pressure to contain, dilute, hold up, and reduce the activity level of fission products prior to release to the environment, and to isolate and contain fission products that are released during a Design Basis Accident or certain operations. Secondary containment pressure is monitored by a number of differential pressure (dP) sensors. High wind gusts have resulted in momentary negative pressure on the leeward side of the building, causing a more positive pressure indication from one or more dP sensors. The secondary containment building pressure remains relatively constant during these 'wind events.' In December 2016, DTE implemented a software design change to display a 120-second rolling average for secondary containment dP indication. A 120-second rolling average recorded every second provides the operator a more accurate report of actual secondary containment conditions, while mitigating the signal noise and wind gust effects. The conditions associated with the subject event notification were re-reviewed in light of the improved secondary containment dP indication and it was determined that the Fermi 2 secondary containment was operable during this event. Specifically, the secondary containment pressure did not exceed Technical Specification Surveillance Requirements during this event. In summary, the above event notification is retracted because the Fermi 2 secondary containment was determined to have been fully operable during the conditions identified in the subject report. The licensee notified the NRC Resident Inspector. Notified R3DO (Stoedter)

On July 13, 2016, at 19:50 EDT a severe thunderstorm warning was issued for Monroe County. This severe thunderstorm warning included the Fermi 2 site. Due to high winds encountered during the thunderstorm, the Technical Specification (TS) for secondary containment pressure boundary was not met numerous times. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each event. All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. At 20:40 EDT secondary containment vacuum was greater than the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) and steady, and the LCO was exited. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.

• * * RETRACTION AT 1922 EDT ON 3/17/2017 FROM DEREK ETUE TO BETHANY CECERE * * *

In this event notification, DTE Electric Company (DTE) reported conditions whereby the Fermi 2 secondary containment was believed to have exceeded Technical Specification Surveillance Requirements due to high winds. DTE hereby retracts this event notification as the Fermi 2 secondary containment has been determined to have been operable during this event as described below. The Fermi 2 secondary containment pressure is maintained at a pressure less than the external pressure to contain, dilute, hold up, and reduce the activity level of fission products prior to release to the environment, and to isolate and contain fission products that are released during a Design Basis Accident or certain operations. Secondary containment pressure is monitored by a number of differential pressure (dP) sensors. High wind gusts have resulted in momentary negative pressure on the leeward side of the building, causing a more positive pressure indication from one or more dP sensors. The secondary containment building pressure remains relatively constant during these 'wind events.' In December 2016, DTE implemented a software design change to display a 120-second rolling average for secondary containment dP indication. A 120-second rolling average recorded every second provides the operator a more accurate report of actual secondary containment conditions, while mitigating the signal noise and wind gust effects. The conditions associated with the subject event notification were re-reviewed in light of the improved secondary containment dP indication and it was determined that the Fermi 2 secondary containment was operable during this event. Specifically, the secondary containment pressure did not exceed Technical Specification Surveillance Requirements during this event. In summary, the above event notification is retracted because the Fermi 2 secondary containment was determined to have been fully operable during the conditions identified in the subject report. The licensee notified the NRC Resident Inspector. Notified R3DO (Stoedter)

At 1200 (CDT) May 13, 2016, while the plant was operating at 100% power, it was brought to the attention of the River Bend Station Main Control Room staff that an existing design inadequacy could prevent both trains of the Standby Gas Treatment System (GTS) from performing its design function. Under certain specific conditions, the installed Masterpact breakers may not close to allow energization of the filter train exhaust fans. A start signal (reactor level 2, drywell pressure 1.68 psid, annulus high radiation, annulus low flow) combined with a trip signal within a certain time differential, could result in a failure of the breakers to close. As a result of this condition, both Standby Gas Trains were declared inoperable, which required entry into LCO 3.6.4.3 Condition C (requires entering Mode 3 in 12 hours). Declaring both trains of Standby Gas Treatment System inoperable resulted in loss of the safety function since a system that has been declared inoperable is one in which the capability has degraded to the point where it cannot perform with reasonable expectation or reliability. The Standby Gas Treatment System (GTS) limits release to the environment of radioisotopes, which may leak from the primary containment, ECCS systems, and other potential radioactive sources to the secondary containment under accident conditions. At 1240 (CDT) May 13, 2016, one division of GTS, GTS 'A', was manually started from the Main Control Room. This action prevents the breaker failure mode, restored the operability of one train and restored the safety function of the GTS system. LCO 3.6.4.3 Condition A (restore Operability in 7 days) is currently entered for Standby Gas Train 'B'. During the 40 minutes of inoperability, both trains of Standby Gas remained available. At no time was the health or safety of the public impacted. This condition is being reported in accordance with 10CFR50.72(b)(3)(v)(C) as an event that could have caused a loss of safety function to control the release of radioactive material. The Senior NRC Resident was notified.

• * * UPDATED AT 1341 EDT ON 05/17/16 FROM DAN PIPKIN TO RICHARD SMITH * * *

Further review has determined that the design inadequacy discussed in EN #51928 could adversely effect the ability of the main control building heating, ventilation, and air conditioning (HVAC) system to perform its design safety function, based upon a particular sequence of events occurring within a short window of time (approximately 75 milliseconds). River Bend has implemented compensatory actions to ensure operability of the main control building HVAC system. The Resident Inspector has been notified by the licensee. Notified the R4DO (Miller).

At 1007 (EDT) on August 12, 2015, while restoring Reactor Building (RB) HVAC (RBHVAC) after surveillance testing, an equipment malfunction resulted in improper damper alignment resulting in Secondary Containment Technical Specifications (TS) to not be met. The plant TS require Secondary Containment pressure be maintained greater than or equal to -0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1). This specification was not maintained for five seconds and the highest pressure observed was -0.095 inches of vacuum water gauge. This value was observed on only one of two installed recorders, of the Secondary Containment pressure recorders. The highest observed pressure on the other recorder was -0.14 inches of vacuum water gauge. Secondary Containment was restored by the Standby Gas Treatment System (SGTS) already in operation and shutting down the affected train of RBHVAC. The technical specification requirement is to maintain secondary containment at -0.125 inches of vacuum water gauge for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR50.72(b)(3)(v)(c) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee notified the NRC Resident Inspector.

• * * UPDATE AT 1159 EDT ON 08/13/15 FROM BRETT JEBBIA TO S. SANDIN * * *

The licensee is updating this report to delete the minus sign for all references to inches of vacuum water gauge. FOLLOW UP - CORRECTED INFORMATION: At 1007 (EDT) on August 12, 2015, while restoring Reactor Building (RB) HVAC (RBHVAC) after surveillance testing, an equipment malfunction resulted in improper damper alignment resulting in Secondary Containment Technical Specifications (TS) to not be met. The plant TS require Secondary Containment pressure be maintained greater than or equal to .125 inches of vacuum water gauge (TS SR 3.6.4.1.1). This specification was not maintained for five seconds and the highest pressure observed was .095 inches of vacuum water gauge. This value was observed on only one, of two installed recorders, of the Secondary Containment pressure recorders. The highest observed pressure on the other recorder was .14 inches of vacuum water gauge. Secondary Containment was restored by the Standby Gas Treatment System (SGTS) already in operation and shutting down the affected train of RBHV AC. The technical specification requirement is to maintain secondary containment greater than or equal to .125 inches of vacuum water gauge for secondary containment operability. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)c as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. the licensee informed the NRC Resident Inspector. Notified R1DO (Powell).

On 7/7/2015 at approximately 1435 EDT, the Technical Specification for Secondary Containment Pressure Boundary was not met when vacuum could not be maintained greater than or equal to -0.125 inches of water gauge for approximately 41 seconds. As part of post-maintenance testing for the non-safety related Reactor Building HVAC Center Exhaust Fan, the fan was started while the safety-related Standby Gas Treatment system was also in operation. Shortly after the fan was started, operators observed degrading vacuum in secondary containment and subsequently secured the center exhaust and supply fans. Vacuum continued to degrade momentarily after the fans were secured, and then returned to a Technical Specification allowable value. Subsequent inspections discovered that the affected fan was operating in the reverse direction. This is believed to have caused Secondary Containment pressure to increase. Since vacuum could not be maintained with the safety-related Standby Gas Treatment system operating, the plant operated in an unanalyzed condition. The cause of the reverse rotation is under investigation. There were no radiological releases associated with this event. The NRC Senior Resident Inspector has been notified.

• * * UPDATE FROM CHRIS ROBINSON TO VINCE KLCO ON 7/7/2015 AT 2153 EDT* * *

Based on plant configuration at the time of the event and further review of the Fermi 2 UFSAR, the plant did not operate in an unanalyzed condition. The Reactor Building HVAC fans would have tripped, as designed, upon receipt of a safety-related Standby Gas Treatment actuation signal during the time of the event. Therefore, the fans' pressurizing effect on secondary containment would have ceased within the time limits assumed in the existing accident analysis. The reporting criteria of 10CFR50.72(b)(3)(v)(C) remains valid. The licensee notified the NRC Resident Inspector. Notified the R3DO (Stone).

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Unit 1 and Unit 2 Reactor Buildings. This updated analysis has identified circuit configurations in four Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. In the Unit 1 Safe Shutdown Analysis, RCIC (1E51C001) (Path 1) components are impacted by a fire in Fire Area 1203. The postulated failure described above impacts HPCI (1E41C001) (Path 2) operation. Therefore, in the updated analysis there is no safe shutdown method for high pressure injection that remains free of fire damage for an Appendix R postulated fire in Fire Area 1203. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1203. In the Unit 1 Safe Shutdown Analysis, Path 2 components are impacted by a fire in Fire Area 1205. The postulated failure described above impacts the 1E 4160 Kv (1R22S005) emergency bus power to Path 1 components. Therefore, in the updated analysis there is no safe shutdown method that remains available for an Appendix R postulated fire in Fire Area 1205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1205. In the Unit 2 Safe Shutdown Analysis, Path 2 components are impacted by a fire in Fire Area 2205. The postulated failure described above impacts the 2E 4160 Kv (2R22S005) emergency bus power to Path 1 components. Therefore, in the updated analysis there is no safe shutdown method that remains available for an Appendix R postulated fire in Fire Area 2205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 2205. In the updated post-fire safe shutdown model, both safe shutdown paths include the same three options for Torus Water Temperature indication (1T48R072, 1T47R611 or 1T47R612). Only one of these three components is required to succeed, however, all are impacted by the postulated fire. Thus, there is no Unit 1 Torus Water Temperature Indication available for a fire in Fire Area 1205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1205. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. CR 10079009, 10079019, 10079022, 10079025 The licensee has notified the NRC Resident Inspector.

• * * UPDATE FROM STANLEY STONE TO DONALD NORWOOD AT 1634 EDT ON 6/17/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Unit 1 and Unit 2 Turbine Building. This updated analysis has identified circuit configurations in two Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. 1) In the Unit 1 Safe Shutdown Analysis, Path 1 RCIC components are impacted by a fire in Fire Area 1105. The postulated failure would impact Path 2 (HPCI) operation. Therefore, in the current analysis for the credited safe shutdown method for high pressure injection may be affected for an Appendix R postulated fire in Fire Area 1105. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1105. 2) In the updated post-fire safe shutdown model, both safe shutdown paths include the same two options for Torus Water Level Indication: 2T48-R622A and 2T48-R622B. Only one of these two components is required to succeed, however both would be impacted by a postulated fire in Fire Area 2104. Consequently, both credited paths of Unit 2 Torus Water Level Indication could potentially be affected due to a fire in Fire Area 2104. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2104. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10084753, CR 10084757. The licensee notified the NRC Resident Inspector. Notified R2DO (HAAG).

• * * UPDATE FROM SCOTT BRITT TO VINCE KLCO ON 6/24/15 AT 2114 EDT * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Diesel Generator Building. This updated analysis has identified circuit configurations in five Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. 1) An Appendix R postulated fire in Fire Area 1404 is assessed to impact a cable required for RHR Inboard Injection Valve A, 1E11-F015A, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop A in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1404. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1404. RHR Loop B is not available in this fire area due to fire impacts. 2) An Appendix R postulated fire in Fire Area 1408 is assessed to impact cables required for RHR Inboard Injection Valve B, 1E11-F015B, to open. These cables were not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1408. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1408. RHR Loop A is not available in this fire area due to fire impacts. 3) An Appendix R postulated fire in Fire Area 1412 is assessed to impact a cable required for RHR Inboard Injection Valve B, 1E11-F015B, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1412. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1412. RHR Loop A is not available in this fire area due to fire impacts. 4) An Appendix R postulated fire in Fire Area 2404 is assessed to impact a cable required for RHR Inboard Injection Valve B, 2E11-F015B, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 2 in support of Inventory Control to the RPV for a fire in Fire Area 2404. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2404. RHR Loop A is not available in this fire area due to fire impacts. 5) An Appendix R postulated fire in Fire Area 2408 is assessed to impact cables required for RHR Inboard Injection Valve B, 2E11-F015B, to open. These cables were not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 2 in support of Inventory Control to the RPV for a fire in Fire Area 2408. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2408. RHR Loop A is not available in this fire area due to fire impacts. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10088142 The licensee will notify the NRC Resident Inspector. Notified the R2DO (O'Donohue).

• * * UPDATE AT 1739 EDT ON 08/13/15 FROM PAUL UNDERWOOD TO JEFF HERRERA * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Control Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 0014 is assessed to impact a cable that is required for Diesel Building MCC 1C, 1R24-S027, to remain energized. Further analysis has shown that an inter-cable hot short between two conductors could cause the feeder breaker to this MCC to trip. This MCC is required to support the operation of Diesel Generator 1C, which is a credited power source in the Safe Shutdown analysis for both Unit 1 and Unit 2 in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. CR 10108999. The licensee notified the NRC Resident Inspector. Notified the R2DO (Nease).

• * * UPDATE AT 1331 EDT ON 08/25/15 FROM JOHN MITCHELL TO JEFF HERRERA * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48c (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Diesel Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1408 is assessed to impact a cable that is required for Station Battery Chargers 1D, 1E, and 1F to remain energized. These chargers support 125V DC Switchgear 1B which is the credited DC Switchgear for Unit 1 Path 2 Safe Shutdown in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1408. 2) An Appendix R postulated fire in Fire Area 2408 is assessed to impact a cable that is required for Station Battery Chargers 2D, 2E, and 2F to remain energized. These chargers support 125V DC Switchgear 2B which is the credited DC Switchgear for Unit 2 Path 2 Safe Shutdown in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2408. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report.

CR 10113740, CR 10113745 The Licensee notified the NRC Resident Inspector. Notified the R2DO (Rose).

• * * UPDATE FROM KENNY HUNTER TO DONALD NORWOOD AT 1717 EDT ON 8/28/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Turbine Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown (SSD) conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1105 is assessed to impact cables which are required for HPCI Steam Supply Isolation MOV, 1E41-F002, to remain open. This valve is required open in support of HPCI (SSD Path 2), which is the credited form of high pressure injection in this fire area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1105. 2) An Appendix R postulated fire in Fire Area 1104 is assessed to impact a cable required for the RCIC Vacuum Breaker Isolation MOV, 1E51-F105, to remain open. This valve is required open to ensure operability of the RCIC turbine if RCIC is required to stop and restart. Failure of this valve to remain open could cause a siphon that would impact the operability of RCIC, and thus disable Safe Shutdown Path 1 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1104. In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Reactor Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1203 is assessed to impact a cable required for HPCI Steam Supply Isolation MOV, 1E41-F002, to remain open. This valve is required open to ensure steam flow to the HPCI turbine. Failure of this valve to remain open would isolate steam to the HPCI turbine, which would disable HPCI, and thus disable Safe Shutdown Path 2 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1203. 2) An Appendix R postulated fire in Fire Area 2203 is assessed to impact cables required for RHR Outboard Injection Valve B, 2E11-F017B, to remain open. This valve is required open to support RHR Loop B in LPCI mode, which is the credited lineup for Path 2 Safe Shutdown Decay Heat Removal. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2203. 3) An Appendix R postulated fire in Fire Area 2203 is assessed to impact cables required for HPCI Vacuum Breaker Isolation Valve, 2E41-F104, to remain open. This valve is required open in support of Safe Shutdown Path 2 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2203. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10115432, CR10115473, CR10115436, CR10115446, CR10115444 The licensee will notify the NRC Resident Inspector. Notified R2DO (Rose).

• * * UPDATE PROVIDED BY GUY GRIFFIS TO JEFF ROTTON AT 1815 EDT ON 09/04/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10CFR50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Control Building and Reactor Building. This updated analysis has identified circuit configurations in Fire Area's where an Appendix R postulated fire could impact the ability to achieve safe shutdown (SSD) conditions. These are Category 1 barrier impairments. 1) An Appendix R postulated fire in Fire Area 0024 is assessed to impact a cable that is required for Torus Suction Valve, 1E11-F065B to remain open. This valve is required to remain open in support of LPCI train B which is credited for Unit 1 Safe Shutdown in the event that the RPV has spuriously depressurized and low pressure inventory control is performed from the remote shutdown panel. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0024. 2) An Appendix R postulated fire in Fire Area 0024 is assessed to impact a cable required for Torus Suction Valve, 2E11-F065B to remain open. This valve is required to remain open in support of LPCI train B which is credited for Unit 2 Safe Shutdown in the event that the RPV has spuriously depressurized and low pressure inventory control is performed from the remote shutdown panel. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0024. 3) An Appendix R postulated fire in Fire Area 0014 is assessed to impact all three Air Handling Units; 1Z41-B003A, 1Z41-B003B, and 1Z41-B003C. The fire impacts a cable required for MCC 1C, 1R23-S003 to remain energized. This MCC supports the operation of Air Handling Unit B, 1Z41-B003B which is required in support of Main Control Room HVAC. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. 4) An Appendix R postulated fire in Fire Area 0031 is assessed to impact all three Air Handling Units; 1Z41-B003A, 1Z41-B003B, and 1Z41-B003C. These AHUs are required in support of MCR HVAC. MCR HVAC was not required in the current Safe Shutdown Analysis Report, and thus these failures were not evaluated in this fire area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0031. 5) An Appendix R postulated fire in Fire Area 2014 is assessed to impact a cable required for Station Battery Chargers 2A (2R42-S026) 2B (2R42-S027) and 2C (2R42-S028) to remain energized. These chargers support 125 VDC Switchgear 2A (2R22-S016), which is the credited DC Switchgear for Path 1 Safe Shutdown. Path 2 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2014. 6) An Appendix R postulated fire in Fire Area 2014 is assessed to impact a cable required for 125 VDC Switchgear 2A (2R22-S016) to remain energized. This is the credited DC Switchgear for Path 1 Safe Shutdown. Path 2 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2014. 7) An Appendix R postulated fire in Fire Area 0014 is assessed to impact cables required for Station Battery Chargers 1D (1R42-S029), 1E (1R42-S030), and 1F (1R42-S031) to remain energized. These chargers support 125VDC Switchgear 1B (1R22-S017) which is the credited DC Switchgear for Path 2 Safe Shutdown. Path 1 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10118312, CR 10118328, CR10118333, CR10118338, CR10118345 The licensee will notify the NRC Resident Inspector. Notified R2DO (Seymour)