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On 9/26/2018 at 1530 EDT, it was discovered that the HPCI system was inoperable due to a blown fuse in the 10C617 Panel, E21-F15A. Therefore, this condition Is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The blown fuse also impacts 'A' channel Residual Heat Removal (RHR) subsystem and 'A' Core Spray (CS) subsystem. These Emergency Core Cooling subsystems have been declared inoperable. Remaining Emergency Core Cooling subsystems and the Reactor Core Isolation Cooling (RCIC) system remain OPERABLE.

There was no impact on the health and safety of the public or plant personnel." The licensee notified the NRC Resident Inspector and will notify the local authorities.

During the period of evaluation of tornado missile vulnerabilities and the potential impacts to technical specification (TS) plant equipment, it was determined that the power cables to a safety related motor control center (MCC) in the service water (SW) intake structure are not adequately protected from tornado generated missiles. During walk downs, it was identified that the installed SW pipe tunnel barrier is not adequate. A tornado could generate missiles capable of striking the power cables and rendering a SW MCC inoperable. These conditions are reportable per 10 CFR 50.72(b)(3)(ii)(B) and per 10 CFR 50.72(b)(3)(v)(D). This condition is being addressed in accordance with NRC enforcement guidance provided in Enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado- Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents. The NRC Resident Inspector has been notified. The licensee will be notifying the Lower Alloways Creek Township.

• * * UPDATE ON 6/18/2018 AT 1604 EDT FROM JUSTIN HARGRAVE TO RICHARD SMITH * * *

During subsequent walk downs, PSEG (Public Service Enterprise Group) identified that both the Unit 1 and Unit 2 turbine driven auxiliary feedwater pumps are also not adequately protected from tornado generated missiles. The steam exhaust pipe could be potentially impacted and cause crimping that could reduce steam exhaust flow and pump capacity. EN 53438 is updated to include both Salem units and these additional components. This condition is being addressed in accordance with NRC enforcement guidance provided in enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents." The NRC Resident Inspector has been notified. The licensee will be notifying the Lower Alloways Creek Township. Notified R1DO (Burritt).

An Unusual Event was declared at 1657 EST due to an earthquake detected onsite. The Unusual Event was declared under EAL HU1.1. There is no release in progress due to this event. There are no protective actions recommended at this time. The Licensee will notify the NRC Resident Inspector. Note: See also EN #53099 for Salem Unusual Event.

• * * UPDATE FROM JOSHUA MYERS TO DONALD NORWOOD AT 1742 EST ON 11/30/2017 * * *

An earthquake was felt onsite at time 1645 EST. Multiple phone calls were made to the Control Room confirming the earthquake. It was verified there was an earthquake felt in Delaware with a magnitude of 4.4. Neither seismic monitor at Salem Unit 1, Salem Unit 2, and Hope Creek actuated. There is no indication of any damage to any systems or plant structures. Plant walk-downs have been initiated in accordance with plant operating procedures for a seismic event. No injuries have been reported to the Control Room. The licensee will notify the NRC Resident Inspector and State and local government agencies. Notified R1DO (Gray), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), and DHS Nuclear SSA (email).

• * * UPDATE FROM THOMAS CLARK TO DAVID AIRD AT 2137 EST ON 11/30/2017 * * *

The licensee terminated the Unusual Event at 2125 EST on 11/30/2017 following plant walkdowns that revealed no damage to plant structures, systems, or components. The NRC Resident Inspector has been notified. Notified R1DO (Gray), IRD (Grant), and NRR EO (Miller), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), and DHS Nuclear SSA (email).

On February 28, 2017 at 0930 (EST), a containment visual inspection was performed to identify the source of elevated RCS (Reactor Coolant System) leakage. A leak was identified between 13RC6 and 13SS661, 13 RCS hot leg sample isolation valves at 1000 (EST). These valves are manual isolation valves in the reactor coolant hot leg sample line. Leak isolation could not be initially verified and is considered RCS pressure boundary leakage. Salem Unit 1 entered Technical Specification 3.4.6.2a, RCS operational leakage, for the existence of pressure boundary leakage. This event is being reported under the requirements of 10 CFR 50.72(b)(2)(i) for 'The initiation of a plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) or 'Any event of condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded.' The unit was placed in mode 3 at 1554 (EST) on 02/28/2017. This condition has no impact on public health and safety. Per Technical Specifications, the unit is proceeding to mode 5. The leak rate at the time of shutdown was 0.33 gpm. This event has no effect on Unit 2. The licensee has notified the NRC Resident Inspector. The licensee will be notifying the Lower Alloways Creek Township, the State of New Jersey and the State of Delaware.

• * * RETRACTION FROM MATT MOG TO HOWIE CROUCH AT 1144 EDT ON 4/14/17 * * *

The purpose of this notification is to retract event report number 52581 made on 2/28/2017 at 1624 (EST). Previously, PSEG notified the NRC that Salem Unit 1 initiated a shutdown required by Technical Specifications (TS) for Reactor Coolant System (RCS) Pressure Boundary Leakage. Subsequent to the initial report, PSEG has determined that the leak occurred in tubing downstream of the design specification break between Safety Related, Nuclear Class 1, Seismic Class1 and Non-Safety-Related, Nuclear Class 2, Seismic Class 2. Therefore, the observed leakage is not RCS pressure boundary leakage as defined in the Salem Unit 1 Technical Specifications and in the tubing design classification specification. At the time of the event, during initial entry into the containment, the volume of steam present and the height of the break above the floor made it difficult to ascertain the location of the steam source with certainty. The initial judgment of RCS Pressure Boundary Leakage was conservative under these circumstances. The plant was taken offline to minimize radiation exposure when personnel operated the isolation valves. Following the shutdown, the leak was isolated. Based on an observed reduction in RCS leak rate and visual verification of leakage isolation, the TS Limiting Condition for Operation (LCO) was exited and the unit remained in Mode 3, Hot Standby, to affect repairs. The condition did not meet the Technical Specification Pressure Boundary Leakage definition of leakage through a non-isolable fault in a RCS component body, pipe wall or vessel wall. The leakage did not impact the ability to shut down the unit and no TS limits were exceeded during this event. Therefore, the plant shutdown to investigate and correct leakage from flawed sample system tubing does not meet the reporting requirements of 10 CFR 50.72 and PSEG is retracting the notifications made under 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector was notified of this retraction by the licensee. Notified R1DO (Jackson).

This four and eight hour notification is being made to report that at 0541 (EDT) on 7/28/16, Salem Unit 1 initiated a shutdown to comply with Technical Specifications due to the inoperability of both source range nuclear instruments. During a reactor startup, with Unit 1 in Mode 2, both source range instruments were reading approximately one decade lower than expected compared to intermediate range and Gamma-Metric instruments and due to the proximity to the estimated critical condition. The condition could also have prevented the fulfilment of the source range instruments safety function to trip the reactor when required. Salem Unit 1 is currently stable in Mode 3. Reactor Coolant system pressure is 2235 psig and reactor coolant system temperature is 547 F with decay heat removal via the main steam dump and auxiliary feedwater systems. Unit 1 has one active shutdown tech spec action statement in effect due to the inoperability of the containment radiation monitor 1R11A. The inoperability of this radiation monitor had no effect on the event. All control rods were manually inserted to place Unit 1 in Hot Standby (Mode 3). No ECCS (emergency core cooling system) or ESF (emergency safety features) systems were required to function during this event. No major secondary equipment was tagged for maintenance prior to this event. No personnel were injured during this event. The reactor was manually shut down and a shutdown margin calculation verified sufficient margin. The licensee notified the NRC Resident Inspector and the local township.

• * * RETRACTION FROM MATT MOG TO VINCE KLCO ON 9/26/16 AT 1519 EDT * * *

The purpose of this notification is to retract event report number 52129 made on 7/28/2016 at 0925 (EDT). Previously PSEG reported that Salem Unit 1 initiated a shutdown to comply with Technical Specifications (TS) due to the inoperability of both source range nuclear instruments. Additionally PSEG reported that the condition could have prevented the fulfillment of the safety function needed to, 'Shut down the reactor and maintain it in a safe shutdown condition.' Subsequent review identified that the condition did not meet either reporting criteria. Maintenance and Engineering evaluation of the source range nuclear instruments determined that the instruments were fully operable at the time of the event. TS 3.3.1.1, Reactor Trip Instrumentation remained met, no TS shutdown was required and the instruments were capable of performing their required function. Therefore PSEG is retracting the notifications made under 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(A). The NRC Resident Inspector was notified of this retraction by the licensee. Notified the R1DO (Cook).

At 2148 EST on November 23, 2015, Salem Unit 2 declared an Unusual Event due to reactor coolant system leakage greater than 10 gallons per minute. While performing troubleshooting to determine the source of leakage from the Emergency Core Cooling System high head safety injection piping, a motor operated valve was opened and the high head piping relief valve lifted. Indications in the control room calculated the leak rate at 16 gallons per minute based on the change in Pressurizer level. The leak was terminated when the motor operated valve was closed and the relief valve reseated. The time (duration) of the leak was about one minute." The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA Ops Center, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

• * * UPDATE AT 0105 EST ON 11/24/15 FROM BILLY MOWER TO JEFF HERRERA * * *

The licensee terminated the Unusual Event at 0100 EST on 11/24/15. The licensee will be cooling down and depressurizing to mode 5 in order to replace the affected valve. The licensee will be notifying the NRC Resident Inspector as well as the New Jersey State police, Delaware State Police and local emergency dispatch. Notified the R1DO (Dwyer), NRR EO (Morris), IRD MOC (Stapleton), DHS SWO, FEMA Ops enter, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

• * * UPDATE FROM JOHN OSBORNE TO JOHN SHOEMAKER AT 0341 EST ON 11/24/15 * * *

This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D). 'Any event of condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident,' due to inoperability of both trains of the Emergency Core Cooling System high head safety injection systems. The unusual event was exited at 0100 (EST) on November 24th, 2015, when the Emergency Core Cooling System high head safety injection piping inlet valves were closed, ensuring isolation of the relief valve. The criteria for exit was leakage rate was below the 10 GPM rate. The plant is in mode 3 cooling down to mode 5. The licensee notified the states of New Jersey and Delaware, Lower Alloways Township, and the NRC Resident Inspector. Notified the R1DO (Dwyer).

At 1810 (EDT), the Salem unit 1 control room received an alarm that a CO2 discharge occurred in the Diesel Fuel Oil Transfer Pump Rooms on the 84 foot elevation in the Auxiliary Building. The control room referred to the OHA (Overhead Annunciator) response procedure S1.OP-AR.ZZ.0001 for OHA A-8, 'Fire Prot CO2/Halon Disch.' The ARP (Alarm Response Procedure) directed implementation of the S1.OP-AB.Fire-0001 procedure and control room ventilation was shifted to the 'fire outside' mode of operation. The on site fire protection team responded to the area and confirmed the CO2 discharge. The (on site) fire department determined that there was no fire and no smoke in the area of the discharge. The Fire Brigade Liaison inspected the equipment and determined that there was no adverse impact to any equipment located in the vicinity of the discharge and no operational impact on the plant. All systems responded as expected. There were no personnel injuries as a result of the discharge. Atmosphere in the area of the discharge has been verified normal and no restrictions to the area are in place. The cause of the discharge was determined to be a faulty detector. No off site response was requested and an hourly firewatch will be initiated until the detector is repaired. The licensee will notify the NRC Resident Inspector and has notified the states of Delaware and New Jersey. Notified DHS, FEMA Operations Center, and NICC and e-mailed Nuclear SSA and FEMA National Watch Center.

• * * UPDATE AT 2206 ON 7/11/15 FROM MARK FIOCCO TO MARK ABRAMOVITZ * * *

The Unusual Event was terminated at 2154 EDT. The licensee notified the NRC Resident Inspector and the states of Delaware and New Jersey. Notified IRD (Stapleton), R1DO (Cahill), NRR (Morris), DHS, FEMA Operations Center, and NICC and e-mailed Nuclear SSA and FEMA National Watch Center.