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While the B control room chiller was out of service for planned maintenance, the A control room chiller was manually secured due to excessive fluctuations in load and running current. TS 3.7.2.2 Action a.2 was entered at 1303 (EST) for both control room air conditioning subsystems inoperable. Control room temperature is being maintained below the TS limit of 90 degrees F. The required TS Action is to restore one control room AC subsystem to operable status within 72 hours. The licensee will notify the NRC Resident Inspector and the Lower Alloways Creek township.

• * * UPDATE ON 12/20/13 AT 2234 EST FROM JOHN PANAGOTOPULOS TO DONG PARK * * *

The B control room chiller was returned to service at 2120 EST. The A control room chiller remains out of service resulting in a 30-day TS LCO. Notified R1DO (Dimitriadis).

On January 11, 2012 at 22:15 (EST), the High Pressure Coolant Injection System (HPCI) was declared inoperable due to a failure of the turbine governor valve to respond to demanded position. When demanded to travel to the full closed position, the governor valve remained full open rendering the speed and flow control system for the turbine inoperable. The failure was discovered as part of a planned maintenance evolution. All other Emergency Core Cooling Systems and the Reactor Core Isolation Cooling (RCIC) system remain operable. The unit remains at 100% power. The station has initiated an Event Response Team to identify and correct the cause of the failure. No personnel injuries resulted from the event. The NRC Resident Inspector (has been notified) and Lower Alloway Creek Township will be notified. The unit is in a 14-day LCO for HPCI inoperability.

• * * RETRACTION FROM JAMES PRIEST TO VINCE KLCO ON 1/13/12 AT 1644 EST * * *

The following is a retraction of ENS Notification #47585: On January 11, 2012, Hope Creek Generating Station reported to the NRC that High Pressure Coolant Injection System (HPCI) was declared inoperable due to a failure of the turbine governor valve to respond to demanded position. This condition was discovered when obtaining an oil sample from the HPCI system. According to the procedure, the HPCI flow controller automatic setpoint was lowered to zero. The procedure set the manual controller setpoint by having the operator lower the demand for a time period rather than verifying the setpoint at zero. The HPCI Auxiliary Oil Pump is then started. The governor valve was expected to start to open (intermediate position) and then close. Instead the valve went to the full open position and did not respond to attempts to close the valve from the flow controller. 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 1. Subsequent technical evaluation concluded that the performance and response of the HPCI turbine governor control valve was as expected based on the manual controller demand being at 35% when the HPCI Auxiliary Oil Pump was started to collect a HPCI oil sample. The Engineering review concluded that there are no problems with the HPCI turbine governor control valve response to controller demand. Operating procedures have been revised to provide guidance on verifying manual controller demand at 0% before placing the HPCI Auxiliary Oil Pump in service under standby conditions for oil sampling or similar evolutions. Since January 11th, 2012, HPCI has remained available to perform its required safety functions and only became inoperable during planned evolutions to either obtain oil samples or to investigate HPCI turbine governor control valve performance. On this basis, the HPCI system was capable of performing its function to mitigate the consequences of an accident and the issue described in Event #47585 is not reportable under 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector and Lower Alloway Creek Township will be notified of this retraction. Notified R1DO (Trapp).

On 6/04/08 at 0257, the High Pressure Coolant Injection (HPCI) system was declared inoperable. The HPCI pump was placed in service to evaluate HPCI pump start performance. The HPCI pump tripped on low suction pressure when started. An Event Response Team is assembled to investigate the cause of the low suction trip of HPCI. Loss of the HPCI system is reportable under 10 CFR 50.72(b)(3)(v) as loss of a single train safety system required to mitigate the consequences of an accident. No additional Emergency Core Cooling Systems or Safety Related equipment was inoperable during this time period. The licensee is in a 14 day LCO due to TS 3.5.1. The licensee notified the NRC Resident Inspector.

• * * RETRACTION ON 6/6/08 AT 1933 EST FROM LITKETT TO HUFFMAN * * *

The purpose of this notification is to retract a previous report made on 6/04/08 at 0758 (EN# 44263). The High Pressure Coolant Injection (HPCI) system was declared inoperable. The HPCI pump was placed in service to evaluate HPCI pump start performance. The HPCI pump received a momentary low suction pressure trip signal in the test configuration alignment. Since the initial report, failure mode cause technical evaluation has determined that the HPCI was always able to satisfy its design safety function. Additional instrumentation was added and data collected from seven HPCI test runs was analyzed. As evidenced by the successful completion of its IST test and the detailed review of multiple HPCI runs, the HPCI system was always able to perform its design function because: --- HPCI restarted on its own with no operator action. --- HPCI would meet its injection time requirements. --- Required flows and required pressures were reached on all HPCI runs . Therefore HPCI was never inoperable. The NRC resident has been informed of the retraction. R1DO (Henderson) notified.

On 11/11/07 at 1639, the High Pressure Coolant Injection (HPCI) system was declared inoperable. The quarterly HPCI System Valve In-Service Surveillance was in progress. During the performance of the surveillance, the Suppression Chamber supply check valve was unable to be cycled open in accordance with the surveillance procedure. Loss of the HPCI system is reportable under 10CFR50.72(b)(3)(v) as loss of a single train safety system required to mitigate the consequences of an accident. The plant is stable in Operational Condition 2, no other Emergency Core Cooling or Safety Related systems are inoperable and plant start-up activities are in progress. The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township.

• * * RETRACTION AT 1532 ON 12/4/2007 FROM MICHAEL REED TO MARK ABRAMOVITZ * * *

Further investigation revealed that the existing steps of the controlling surveillance procedure did not consistently equalize pressure across the HPCI suction check valve and therefore did not establish adequate test conditions. The surveillance procedure was revised to ensure adequate test conditions were established and the valve was successfully stroked. Evaluation of the initial assessment of operability determined that the suction check valve was not inoperable. Therefore the HPCI system was also not inoperable as initially declared and continued to be able to perform its safety function. Based on this additional information, the associated non-emergency 8-hour notification made on November 11, 2007, is retracted. The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township. Notified the R1DO (Barkley).

On 03/14/06 at 1655 hours, the 'A' Control Room Emergency Filtration (CREF) system was removed from service to address a high oil level and subsequent high bearing drain oil temperatures. The 'A' CREF train was declared inoperable and a 7-day LCO was entered. While placing the 'B' CREF train in-service the chiller did not respond as expected. The chiller failed to properly load and supply cooling. At 1659 hours the 'B' CREF train was declared inoperable. This resulted in both 'A' and 'B' trains of CREF (being) unable to perform their design safety function and thus unable to mitigate the consequences of an accident. This failure placed the Hope Creek Station in a Technical Specification 3.0.3 condition requiring a unit shutdown. Oil level was restored to normal band for the 'A' CREF train at 1732 hours and the 3.0.3 condition was exited prior to any actions being initiated to start reducing reactor power to achieve a Hot Shutdown condition. A 8 hour report is being made under ECG Section 11.2.2.b, an Event/Condition could have prevented certain safety functions IAW 10.CFR50.72(b)(3)(v). At the time of event all safety systems were operable. The license has notified the NRC resident inspector.

• * * UPDATE FROM ZAKARIAN TO HUFFMAN AT 1359 EDT ON 4/22/06 * * *

This is a retraction of the event notification made on 3/14/06 at 20:21 (ET) hours. This event (#42422) was initially reported as a condition that at the time of discovery could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident per 10CFR50.72(b)(3)(v)(D). The safety function of the system is to ensure that the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system. Further review has determined that the Control Room Emergency Filtration (CREF) chiller system maintained its capability to complete its specified safety function. During the event, the chilled water and affected room temperatures increased only minimally and remained well below the maximum allowable temperatures. The proceduralized in-progress activity to address the 'A' chiller high oil level condition promptly re-established full system cooling prior to approaching any required temperature limits. The procedure was completed in a timely manner with no complications. Therefore, the temperature limits of the Control Room and equipment rooms would not have been challenged had an event occurred during the time 'A' chiller oil level was being adjusted and the safety function of maintaining room ambient air temperature within limits would have been accomplished. The licensee has notified the NRC resident inspector. R1DO(Holody) notified.

At 09:24 am on 08/27/03, a Control Room access door latch was determined to be not fully engaging. The door and latch provide the following functions: maintain the integrity of the Control Room boundary which is a design feature to maintain Control Room habitability following a design bases accident, and provide a security barrier to restrict access into the Control Rom complex to only those personnel with preapproved security clearance. With the latch not engaged, the door was not capable of performing these functions. The appropriate security contingencies were implemented, requiring posting of a Security Force Member at the door controlling access to the Control Room Complex. Technical Specification (TS) 3.0.3 was entered due to the inability of either Control Room ventilation system to maintain Control Room habitability, as required by TS 3.7.2. At 10:20, the door latch was replaced to re-establish the integrity of the Control Room habitability boundary and TS 3.0.3 was exited. The ability of the latch to properly operate for access and egress was not established; access through the affected door remained restricted until repairs can be completed (there are additional doors to the Control Room that remain fully functional). At 14:00, the door was again impaired for repair of the door latch. Full functionality of the door was restored at 14:41. The NRC Resident Inspector was notified of this event by the licensee.

• * * RETRACTION AT 1143 EDT ON 10/22/03 FROM A. BRAEDY TO E. THOMAS * * *

At the time of the original notification the ability to maintain Control Room habitability, as required by TS 3.7.2 was not assured. Subsequent evaluation has determined that if a postulated accident had occurred during the time that the door latch was impaired, control room dose would be less than the acceptance criteria specified in 10CFR50.67 and Regulatory Guide 1.183 and bounded by our current analysis. The site boundary doses were never affected. The dose impact of the condition as it existed would be bounded by the current analysis. Thus, the safety function would have been fulfilled. Notified R1DO (L. Doerflein)