Semantic search

Jump to navigation Jump to search
 Entered dateEvent description
ENS 528928 August 2017 22:33:00On August 8th, 2017 at 2044 hrs. (EDT) a loss of secondary containment differential pressure (D/P) occurred due to an apparent equipment failure. This caused a reduction in Reactor Building Zone II (Unit 2) D/P to less than the required 0.25 inch WC (water column) per SR (Surveillance Requirement) 3.6.4.1.1. Reactor Building Zone II Exhaust Fans were manually swapped and Reactor Building Zone II D/P was restored to greater than 0.25 inch WC by 2112 hrs. Reactor Building Zone 1 (Unit 1) and Zone 3 (Units 1&2) ventilation remained in service and stable. This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system. The licensee notified the NRC Resident Inspector.
ENS 5282624 June 2017 15:42:00On June 24, 2017 at 1028 (EDT), a loss of secondary containment occurred due to trip of 2V217A Zone III Filtered Exhaust Fan causing a reduction in D/P (differential pressure) to less than the required 0.25 WC (water column). 2V217B Zone III Filtered Exhaust Fan started on low flow in AUTO as designed and secondary containment D/P was restored to greater than 0.25 WC by 1029 hours. This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022, Rev. 3, section 3.2.7 as a loss of a safety function. There is no redundant Susquehanna secondary containment system. The licensee notified the NRC Resident Inspector.
ENS 527979 June 2017 12:51:00On June 9, 2017 at 0509 (EDT), Secondary Containment Zone 3 (Unit 1 and 2 Reactor Building) differential pressure lowered to 0 (inches) WG (water gauge) during a routine restoration due to equipment failure. One of the two Unit 1 Zone 3 exhaust fan breakers experienced a failure that during procedural restoration caused Secondary Containment Zone 3 to experience a positive differential pressure. Required differential pressure per SR 3.6.4.1.1 could not be maintained. Zone 3 differential pressure was recovered to (greater than) 0.25 (inches) WG following restart of Unit 2 Zone 3 Secondary Containment fans. All other Zones of Secondary Containment were unaffected by this event. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System. The NRC Resident Inspector has been notified.
ENS 5183030 March 2016 02:13:00On March 29, 2016 at 2256 (EDT), Secondary Containment Zone 2 (Unit 2 Reactor Building) differential pressure lowered to 0.0 (inches) WG (water gauge) due to a failed closed discharge damper on the in service Zone 2 exhaust fan. Required differential pressure per SR 3.6.4.1.1 could not be maintained. Zone 2 ventilation was restored by starting the standby Zone 2 exhaust fan. Zone 2 differential pressure recovered to (greater than) 0.25 (inches) WG at 2321 hours. Zone 3 (Unit 1&2 Reactor Buildings) ventilation remained in service and stable. Zone 1(Unit 1 Reactor Building) ventilation remained in service however it is not required in this mode of Operation. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System. The licensee has notified the NRC Resident Inspector.
ENS 517778 March 2016 09:37:00On March 8, 2016 at 0232 hours (EST), Secondary Containment Zone 3 (Unit 1&2 Reactor Building) differential pressure lowered to 0.16 inches water gauge when securing Unit 1 Zone 3 HVAC for planned maintenance. Required differential pressure per SR 3.6.4.1.1 could not be maintained in the intended alignment. Zone 3 ventilation was restored to the original alignment and Zone 3 differential pressure recovered to greater than 0.25 inches water gauge at 0335 hours. Zone I (Unit 1 Reactor Building) and Zone II (Unit 2 Reactor Building) ventilation remained in service and stable. Station engineering and maintenance are investigating the Zone 3 HVAC system to determine the cause. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022, Rev. 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System. The NRC Resident Inspector has been notified.
ENS 517642 March 2016 17:20:00On March 2, 2016 at 1330 hrs. (EST), Secondary Containment became inoperable due to failure to meet a Surveillance Requirement (SR 3.6.4.1.3). The inoperability was caused when Unit 2 Reactor Building Airlock doors were inadvertently opened simultaneously. Secondary Containment was restored March 2, 2016 at 1331 hrs. when the doors were closed. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022, Rev. 3, section 3.2.7, as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system. The licensee has notified the NRC Resident Inspector.
ENS 5135527 August 2015 20:39:00

On 8/27/2015 at 1347 (EDT), a cart and personnel were being traversed through an airlock in the Unit 2 reactor building and both airlock doors were inadvertently opened at the same time for a brief period of time (approximately one minute). Secondary Containment differential pressure was maintained throughout the time period that the doors were opened. The doors serve as a Secondary Containment boundary and at least one in series is required to be closed at all times for Secondary Containment Operability. This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System. The licensee notified the NRC Resident Inspector.

  • * * RETRACTED ON 10/22/15 AT 1645 EDT FROM ALEX MCLELLAN TO DONG PARK * * *

NUREG-1022, Revision 3, Section 3.2.7, 'Event or Condition that Could Have Prevented Fulfillment of a Safety Function,' states, in part, that 'events covered in paragraph (b)(3)(v) of this section may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies.' The level of judgment for reporting an event or condition under this criterion is a reasonable expectation of preventing fulfillment of a safety function. A SSC (System, Structure, and/or Component) that has been declared inoperable is one in which the SSC capability has been degraded to the point where it cannot perform with reasonable expectation or reliability. For SSCs within the scope of this criterion, a report is required when: - There is a determination that the SSC is inoperable in a required mode or other specified condition in the TS (Technical Specification) applicability, -The inoperability is due to one of more personnel errors, including procedure violations; equipment failures; inadequate maintenance; or design, analysis, fabrication, equipment qualification, construction, or procedural deficiencies, and -No redundant equipment in the same system was operable. Subsequent to the reporting of this condition, Susquehanna Nuclear, LLC performed an investigation of the event. Below are the results. When the airlock doors were opened at the same time, they were being operated as designed. Each individual had a 'green' light, which allowed them to open each door. Based on the investigation, the doors were open at the same time for approximately one second. In summary, the inoperability of Secondary Containment was not due to personnel error or a procedure violation. At the time of the event, both airlock doors were operable. No equipment failures, inadequate maintenance, or design, analysis, fabrication, equipment qualification, construction, or procedural deficiencies were identified. In summary, based on the above, the identified condition is not reportable in accordance with 10 CFR 50.72(b)(3)(v), for an event or condition, that at the time of discovery, could have prevented the fulfillment of a safety function. As such, this 8-hour event notification is being retracted. The licensee has notified the NRC Resident Inspector. Notified R1DO (Gray).

ENS 5101426 April 2015 01:37:00At 2125 (EDT) on 4/25/15 the control room was notified of a medical emergency in the Radiologically Controlled Area (RCA). The individual was considered potentially contaminated since a complete frisk could not be performed prior to transport. An ambulance entered the Susquehanna Owner Controlled Area and the Protected Area at 2154 and exited at 2210 to transport the individual to the hospital. Radiological survey performed during transport by an SSES (Susquehanna Steam Electric Station) RP (Radiation Protection) Technician verified at 2255 the individual was not contaminated. The ambulance was verified not contaminated at 2303. This event is reportable under 10CFR50.72(b)(3)(xii). An Event of Potential Public Interest (EPPI) was made to the Pennsylvania Emergency Management Agency (PEMA) due to an emergency vehicle accessing company property. The licensee informed the NRC Resident Inspector.
ENS 5004017 April 2014 06:00:00On April 17, 2014 at 0335 EDT, Secondary Containment Zone 3 (Unit 1&2 Reactor Building) differential pressure went to 0.15 inches WG (negative) following securing Unit 1 Zone 3 HVAC in preparation for a LOCA/LOOP test. Zone 3 HVAC was restored at 0420 EDT. Zone I (Unit 1 Reactor Building) ventilation is isolated with secondary containment relaxed for refuel outage on Unit 1. Zone II (Unit 2 Reactor Building) ventilation remained in service and stable. Zone 3 differential pressure recovered to SR 3.6.4.1.1 requirements of 0.25 inches WG (negative) at 0420 EDT and was verified to be stable. LCO 3.6.4.1 was entered at 0335 EDT and exited at 0420 EDT. Tech Spec Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge (WG) for all three Reactor Building Ventilation Zones. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG-1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System. The licensee informed the NRC Resident Inspector.
ENS 4859514 December 2012 15:00:00

At 1350 on 12/14/2012, both Control Structure Chillers at Susquehanna were rendered inoperable. This event required entry into Tech Spec 3.0.3 for both Units. Per Susquehanna procedures, after 1 hour, a power reduction must be commenced. Tech Spec 3.0.3 requires that action be taken within one hour to place the Unit in Mode 3 within 13 hours and Mode 4 within 37 hours. Physical power reduction commenced at 1453 for Unit 1 and 1459 for Unit 2. The 'A' Control Structure Chiller was previously inoperable for routine maintenance. The system was in service for post maintenance testing and activities were underway to swap to the opposite train to allow removal of test instrumentation and fan belt tensioning for equipment associated with the 'A' Control Structure HVAC system. At 1350, the 'B' Control Structure loop circulating pump tripped, rendering the 'B' Control Structure Chiller inoperable. This condition requires immediate entry into Tech Spec 3.0.3. Both Control Structure Chillers are inoperable and this report is being made per 10CFR50.72(b)(2)(i) as a shutdown required by Tech Specs, and 10CFR 50.72(b)(3)(v)(D), Loss of a Safety Function required to mitigate the consequences of an accident. Efforts are underway to restore at least one system to operable status in parallel with Unit shutdown activities. The licensee has notified the NRC Resident Inspector, and will be notifying the State of Pennsylvania.

  • * * UPDATE FROM ALEX MCLELLAN TO JOHN KNOKE AT 2228 EST ON 12/14/12 * * *

On 12/14/12 at 1500 EST Susquehanna Steam Electric Station reported a shutdown had been commenced at 1453 EST for Unit 1 and 1459 EST for Unit 2 due to inoperability of both Control Structure Chillers. At 1750 EST the 'A' Control Structure Chiller was declared operable and LCO 3.0.3 was exited. Power reduction for both Units was halted at 1750 and preparations for power restoration initiated. On 12/14/12 Unit 1 power was restored to 98% at 1819 EST and Unit 2 power was restored to 98% at 1943 EST, the maximum power output possible based on grid conditions for Unit 1 and thermal limits for Unit 2. The licensee has notified the NRC Resident Inspector. R1DO (Holody) notified.

ENS 420343 October 2005 14:34:00At 12:48 PM EST, the Main Control Room was notified that an individual needed medical assistance at the South Building. The individual was experiencing chest pains. An ambulance was requested to the site, and arrived on site at 13:17 PM. The individual is not contaminated and was transported offsite to a local hospital at 13:35 PM. PEMA was notified of the incident. This requires a voluntary report due to the offsite notification on an emergency vehicle responding to the site. The NRC Resident Inspector was notified of this voluntary notification.
ENS 4097020 August 2004 17:48:00At 12:15 PM on 8/20/04, it was discovered that actions performed on 7/16/04 in support of Dry Fuel Storage activities to defeat the Railroad Access Area Radiation Monitor alarm horn had also defeated the actuation capability of the Railroad Access Process Radiation monitors. Per Technical Specifications, the process monitors are required to be operable "during movement of irradiated fuel assemblies within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open." Contrary to the Tech Spec requirement, two loaded Dry Fuel Storage Casks were lowered in the Railroad Shaft, one on 8/2/04 and the second on 8/16/04, with the radiation monitors inoperable. During this period the automatic isolation and re-alignment of Reactor Building Zone lll, automatic start of Reactor Building Recirculation Fans, and the automatic starts of SGTS and CREOASS would not have actuated from a HI-HI Radiation condition in the Railroad Access Shaft. Actual radiological conditions observed during the transfer of the casks in the railroad shaft would not have resulted in the need for system actuation. All other instruments in the Reactor Building ventilation system which actuate these systems were operable as required by Tech Specs. The jumpers which defeated the actuation capability were removed on 8/20/04 at 1400 (hrs.). This event is considered reportable under 50.72(b)(3)(v)(C) as a loss of safety function. The NRC Resident Inspector was notified.
ENS 406465 April 2004 18:19:00

At 1040 hrs during setup for Unit 1 Division 1 LOCA/LOOP Surveillance testing, the controlling procedure required making the Loss of Power instrumentation for the 1A and 1C ESS buses inoperable. The specification has a 1 hour time limit for restoration, or the associated Diesel Generators must be declared inoperable. Due to delays during the setup of equipment the time requirements were not met, and the 'E' (Substituting for 'A') and 'C' Diesel Generators were declared inoperable at 1140 hrs. The Loss of Power instruments were restored, and the Diesel Generators declared operable at 1206 hrs. Unit 1 is in Mode 5 requiring only 2 diesel generators operable, therefore not impacted by the Loss of Power instrumentation inoperability. Also during the surveillance, two pump start timers failed to meet the required acceptance criteria. The 'A' ESW Pump timer actuated at 47.86 seconds (criteria; 36 sec. to 44 sec) and the 'C' ESW Pump timer actuated at 50.38 seconds (criteria: 39.6 sec. to 48.4 sec). With failure of the timers, proper loading on the Diesel Generators is not assured, and they were declared inoperable until the associated pump control breakers were opened. The 'E' Diesel Generator was declared inoperable at 1448 hrs, when the data analysis identified that the 'A' ESW pump timer did not meet acceptance criteria. The 'E' Diesel Generator was returned to operable at 1453 hrs when the DC Knife switches for the 'A' ESW pump were open. The 'C' Diesel Generator was declared inoperable at 1524 hrs, when the data analysis identified that the 'C' ESW pump timer did not meet acceptance criteria. The 'C' Diesel Generator was restored to operable at 1706 hrs after supported systems were realigned to prevent further loss of safety function and the DC Knife switches for the 'C' ESW pump were open. The Susquehanna safety analysis requires three operable Diesel Generators to safely shutdown the plant. Therefore with only two operable Diesel Generators, the condition requires an 8 hr ENS notification in accordance with 10CFR50.72(b)(3)(v)and (vi). All times referenced above are EDT. The licensee informed the NRC Resident Inspector.

* * * RETRACTION FROM R. FRY TO M. RIPLEY 1419 ET ON 05/27/04 * * * *

The following is a retraction of ENS Notification #40642 AND #40646: On April 5, 2004, PPL Susquehanna, LLC reported three events to the NRC associated with Unit 1 Division 1 LOCA/LOOP surveillance testing. In each case, the safety function of two (out of 4) emergency diesel generators was brought into question during the testing. In two of these events, the E (substituting for A) and C diesel generators were administratively declared inoperable per Technical Specifications. This was necessary because Loss of Power instrumentation for the 1A and 1C buses, rendered inoperable in support of the test procedure, was not restored within 1 hour. In the third event, the E (for A) and C emergency diesel generators were, again, declared inoperable when two ESW pump start timers failed to meet acceptance criteria thus bringing the proper start sequencing of emergency loads into question. Because the Susquehanna Safety Analysis requires three diesel generators to safely shutdown an operating unit, the potential compromise of the diesel generator safety function was a concern for Unit 2 in each instance. (NOTE: Unit 1 was in Refueling Mode 5 and was, therefore, not impacted by these events.) Accordingly, Control Room personnel conservatively initiated ENS reporting under 10CFR50.72(b)(3)(v) in response to the apparent loss of safety function for Unit 2. Subsequent engineering analysis has concluded that, although the declaration of diesel generator inoperability was correct and in accordance with Technical Specifications, fulfillment of these administrative actions did not result in an actual loss of safety function during any of the above described events. Details of the analysis show that the diesel generators were available to supply emergency power to the ESS buses and/or that sufficient redundant equipment was available to fulfill the safety function needs of Unit 2. These analysis conclusions provide the basis for retraction of the ENS reports made on April 5, 2004." The licensee notified the NRC Resident Inspector. Notified R1DO (R. Conte)

ENS 4061628 March 2004 08:25:00On 3/28/04 at 0637, Plant Security was notified of a three car accident at the entrance to the site involving 1) an employee leaving the site, 2) a south bound vehicle on US Route 11, and 3) an employee entering the site. There were no reported injuries. Local law enforcement (LLEA) was contacted and investigated the incident. Because of the involvement of a LLEA and potential media or general public interest in the event, the Pennsylvania Emergency Management Agency (PEMA) was notified of the incident at 0812 hours. Based on the notification to a government agency and possible public interest, this event was determined to be reportable under 10CFR50.72(b)(2)(xi). The Licensee notified the NRC Resident Inspector.
ENS 4060221 March 2004 16:03:00On 3/21/04 at 12:32 hrs a bucket truck working at the Unit 1 Cooling Tower came in contact with a 230KV transmission line causing the loss of one off site power supply to the plant. The 500 KV offsite circuit remained energized during the event. A contract employee at the base of the truck was thrown due to the electrical short. A contract employee in the bucket of the truck was able to lower the bucket to the ground. A first aid crew was dispatched to the location and an Ambulance was requested. The Ambulance entered the site at 12:50 and at 13:02 the individuals were transported to the local hospital. Due to the electrical transient in the plant, a contract employee performing grinding activities lost control of the grinder and injured his middle finger. This individual received first aid and was transported to the local hospital by his supervisor. The individual injured in the plant was surveyed by Health Physics prior to leaving the site and no contamination was found. The Local Law Enforcement Agency was notified of the Emergency vehicle being dispatched to the site. The State Emergency Operations Center will be notified of the Emergency vehicle entering the site. The NRC Resident Inspector and local agencies were notified and the state will be notified.
ENS 405664 March 2004 10:51:00

Appendix J Local Leak Rate Testing (LLRT) of the RCIC Steam Supply failed the Combined Main Steam Isolation Valves leakage limit of 300 scfh. The Combined MSIV leakage limit includes MSIV'S, MSL Drains, HPCI Steam Supply and RCIC Steam Supply. The volume between RCIC Steam Supply valves could not be pressurized therefore, the Minimum Pathway leakage limit is considered to be exceeded. This is also considered a failure of the Primary Containment Air Leakage Minimum Pathway leakage limit of 1.0 La. The identified degraded condition is reportable as a condition of the nuclear power plant, including its principle safety barriers being seriously degraded per 10CFR50.72(b)(3)(ii) requiring an 8-hr ENS notification. The RCIC Steam Supply line was tested successfully approximately two years ago during the last refueling outage. The licensee will inform the NRC Resident Inspector.

            • RETRACTED ON 4/14/2004 AT 1610 EST FROM FRY TO HEISSERER*****

At the time the original 8-hour ENS notification was made, it was declared that the Appendix J Local Leak Rate Test of the RCIC Steam Supply had failed the combined Main Steam Isolation Valves Minimum Pathway leakage limit of 300 scfh. The combined MSIV leakage limit includes MSIVs, MSL Drains, HPCI Steam Supply and the RCIC Steam Supply. The volume between the inboard and outboard RCIC Steam Supply valves could not be pressurized, therefore the Minimum Pathway leakage limit was considered to be exceeded. Subsequent to this event, during performance of an additional Local Leak Rate Test of the RCIC Steam Supply Penetration, it was demonstrated that the as-found Appendix J and combined MSIV Minimum Pathway leakage and the Primary Containment Air Leakage Minimum Pathway of 1.0 La were not exceeded as previously reported. The original Local Leak Rate Test was performed between the combination of two parallel inboard valves and the outboard valve. The subsequent test determined that the outboard isolation valve did not exceed Minimum Pathway criteria. The majority of the leakage was from the smaller inboard RCIC warm-up line isolation valve of the three RCIC Steam Supply valves. The post-maintenance test of the penetration measured leakage that was within acceptable limits. As such, the condition of the nuclear power plant, including its principle barriers, was not significantly degraded. The NRC Resident Inspector has been notified. Notified R1DO (B. McDermott).

ENS 405643 March 2004 14:03:00At 12:45 PM EST, the Main Control Room was notified that an individual needed medical assistance at the South Building. The individual was light headed and nauseous. An ambulance was requested to the site, and arrived on site at 01:04 PM. The individual was not contaminated and was transported to a local hospital at 01:12 PM. Pennsylvania Emergency Management Agency (PEMA) was notified of the incident. This requires a voluntary report due to the offsite notification on an emergency vehicle responding to the site. The licensee notified the NRC Resident Inspector.