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| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 51170 | 22 June 2015 18:06:00 | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Sodium Hydroxide Below Technical Specification Required Concentration | At 1406 (EDT) on 6/22/15, the chemistry sample results for the Salem Unit 1 Containment Spray Additive tank were below the minimum Technical Specification requirement for NaOH (Sodium Hydroxide) concentration. The Containment Spray Additive tank was declared inoperable at that time in accordance with Technical Specification 3.6.2.2.a. Based on the fact that there is no redundant equipment for the Containment Spray Additive tank, this condition could have prevented this Safety System from Controlling the Release of Radioactive Material and Mitigating the consequences of an accident. This event is being reported under the requirements of 10 CFR 50.72(b)(3)(v)(C) and (D) as 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of systems that are needed to Control the Release of Radioactive Material and Mitigate the Consequences of an Accident.' Actions are being taken to restore the NaOH concentration to within the Technical Specification limits. The Licensee has notified the NRC Resident. No one was injured as a result of the event. The licensee will notify the Lower Alloways Township. | Containment Spray | |
| ENS 47052 | 15 July 2011 00:53:00 | 10 CFR 50.72(a)(1)(i), Emergency Class Declaration 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Unusual Event Declared Based on Reactor Coolant Leak Greater than 10 Gpm | At 2053 on July 14, 2011 Salem unit 2 declared an Unusual Event due to reactor coolant system leakage greater than 10 gallons per minute. While performing a monthly Emergency Core Cooling System vent of the high head safety injection piping a motor operated valve was opened and a leak developed on the high head piping greater than 10 gallons per minute. The leak rate was approximately 11-15 gallon per minute. The leak was terminated when the motor operated valve was closed. The time of the leak was about 6 minutes. At this time the leak is believed to be from a crack on the Boron Injection Tank (BIT) relief valve line which is connected to the high head piping. A total of approximately 90 gallon of reactor coolant leaked into the BIT room. The licensee has declared the high head safety injection inoperable and is proceeding to shutdown under Tech Spec 3.0.3. The license has notified appropriate State and local authorities. The licensee will notify the NRC Resident Inspector.
Salem Unit 2 declared an Unusual Event due to Reactor Coolant System (RCS) leakage being greater than 10 gpm and pressurizer level decreasing. Leakage was estimated to be approximately 15 gpm. The leakage was determined to be from a weld on the high head charging injection relief valve connection. This leaking weld impacts both trains of high head charging/safety injection. Both trains of high head charging/safety injection were declared inoperable at 2038 (EDT) on July 14, 2011, entering TS 3.0.3. Salem Unit 2 began the Technical Specification shutdown in accordance with TS 3.0.3 at 2136 (EDT). The technical specification shutdown is being reported in accordance with 10CFR50.72(b)(2)(i) and RAL 11.1.1.a. In addition since the leakage from the weld on the high head charging/safety injection piping exceeded the analyzed limit for ESF leakage outside containment, this event is also being reported in accordance with 10CFR50.72(b)(3)(v) and RAL 11.2.2.b as a condition that prevents the ability to mitigate the consequences of an accident. Salem unit 2 is currently at 27% and reducing power. The licensee notified the states of New Jersey and Delaware, Lower Alloways Creek Township and the NRC Resident Inspector. Notified the R1DO (Dwyer), NRR-EO (Giiter) and IRD (Morris).
Salem Unit 2 has exited the Unusual Event as of 0339 EDT. The criteria for exit was the leakage rate was below the 10 gpm rate. The plant is in Mode 3 and is preparing to cooldown. The licensee will notify the NRC Resident Inspector. Notified the R1DO (Dwyer), NRR EO (Giitter), IRD (Morris), DHS(Hill), and FEMA (Blankenship). | Reactor Coolant System Emergency Core Cooling System | |
| ENS 42343 | 16 February 2006 04:45:00 | 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Potential Uncontrolled Radiological Release | This is an 8-hour notification being made to report exceeding the design basis for reactor coolant leakage outside of containment. The normal daily RCS leakrate was completed at 2345 on 2/15/06. This leakrate indicated a step change in unidentified leakrate to .8 gpm from .09 gpm. This leakage value is within the 1 gpm allowed by Technical Specifications. Investigation is on going, and the source of the leak has not been determined at this time, however preliminary conclusion is that the leakage is outside of containment and related to the centrifugal charging pumps. The design requirement ECCS leakage outside of containment is 3840 cc/hour ( .1 gpm) to support GDC-19 limits for control room habilitability. No safety system actuation occurred or were required. No injuries have occurred due to this event. The licensee has performed troubleshooting to identify the source of the leak and to narrow down the portion of the charging system where they believe the leak to be located. The licensee believes the leak is in a relief valve or hard pipe system to the waste tanks, and that the leak is not external to the system. The licensee notified the NRC Resident Inspector.
On February 16, 2006, PSEG made an 8-hour report (event number 42343) in accordance with 10CFR50.72(b)(3)(v) because of exceeding the design basis limits for ECCS leakage outside containment. The leakage was determined to be approximately 0.8 gpm with a limit of 3840 cc/hour. Further investigation into this event determined that the leakage was not in the ECCS recirculation flow path. The cause of the elevated RCS unidentified leakrate was the failure of the automatic three-way high level divert valve (2CV35), which prevents a high level from occurring in the Volume Control Tank (VCT). This valve failed to fully isolate flow to the Chemical Volume Control (CVC) Hold-Up Tanks (HUTs) after VCT level dropped below the divert setpoint of 77% . This conclusion is based on the VCT level being at the divert setpoint a number of times during the shift, the increased use of the valve to control level, and valve performance to fully isolate flow to the CVC HUT'S. Because this flow path is automatically isolated on a Safety Injection signal by other means (valves), the leakage through this valve is not considered part of the ECCS recirculation flow path and therefore is not included in the calculation for ECCS leakage outside containment. The event is being withdrawn. The licensee will notify the NRC Resident Inspector. R1DO(Finney) notified. | ||
| ENS 42114 | 3 November 2005 15:30:00 | 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Eccs Leakage Outside Containment | A 0.02 GPM leak was identified on the inlet valve (1CV89) to the 11 seal injection filter. This leak equates to 4500 cc/hour. The leakage is outside containment and quantified IAW Leakage Monitoring and reduction program procedure SC.RA-AP.ZZ-0051. This leakage exceeds the 3800cc/hour limit as stated in UFSAR section 6.3.2.11 and GDC-19 to ensure control room habitability. Therefore ECG section 11 section 11.2 specifically 11.2.2.b applies for being in a degraded or unanalyzed condition. The 1CV89 valve was recently replaced as a scheduled activity during the current 1R17 refueling outage. The 1CV89 packing has been adjusted and the leakage has stopped. The leakage was to the floor to the liquid waste system. There was no personnel contamination or injuries due to the leakage. Current Plant Conditions: RCS temperature is 340 degrees, RCS pressure is at 1400 PSIG and stable, plant heat-up and pressurization is in progress IAW integrated operating procedures. The leakage occurred from 10:30 to 12:30 EST. The valve has been tested and declared operable. Primary coolant activity is 0.828 microCuries per cc. There is no known steam generator tube leakage. The licensee will notify the NRC Resident Inspector.
On 11/03/05 at 1505, PSEG Nuclear made an 8 hour report in accordance with the 10CFR50.72(b)(3)(v) --(Event number 42114) - for ECCS leakage outside containment. Upon further investigation, it has been determined that the leak was within the guideline limits for the control room and off-site radiological exposure. Additionally, at the time of discovery, Salem Unit 1 was in Mode 4 coming out of its seventeenth refueling outage and 73 of the 193 fuel assemblies in the core were new fuel assemblies. Therefore, the actual core nuclide inventory would have been much less than the core nuclide inventory assumed in the design basis analysis. Therefore, the event of November 3, 2005 reported under 10CFR50.72(b)(3)(v) is being retracted. The licensee will notify the NRC Resident Inspector. R1DO (Doerflein) notified. | Steam Generator | |
| ENS 41245 | 5 December 2004 15:15:00 | 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Reactor Coolant Leakage Outside of Containmemt | This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10CFR50.72. On 12/05/04 at 1015 the control room was notified of leakage from a gasketed flange area on the 11 Residual Heat Removal Heat Exchanger. The leak rate has been conservatively quantified at 0.68 gpm, which is greater than the UFSAR limit of 2100 cc/hr (0.009 gpm) for ECCS leakage outside containment. With leakage greater than the UFSAR allowed limits, GDC-19 limits for control room habitability cannot be assured. Actions are in progress to torque the flange bolts to reduce the leakage. The licensee has notified the NRC Resident inspector of this event. Salem Unit One is in Mode 4 with the Residual Heat Removal system in service removing reactor decay heat. No ECCS system actuations occurred. No one was injured as a result of the leak. | Residual Heat Removal |