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Event Notification Report for February 24, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/23/2004 - 02/24/2004

** EVENT NUMBERS **

40539

40541

Power Reactor	Event Number: 40539
Facility: HOPE CREEK Region: 1 State: NJ Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: MARK SHAFFER HQ OPS Officer: MIKE RIPLEY	Notification Date: 02/23/2004 Notification Time: 07:32 [ET] Event Date: 02/23/2004 Event Time: 01:52 [EST] Last Update Date: 02/23/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): PAMELA HENDERSON (R1)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	Y	100	Power Operation	94	Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN STARTED DUE TO GRASS INTRUSION

"At 0152 on February 23rd the station service water system at Hope Creek experienced elevated differential pressure due to grass intrusion. At the time of the grass intrusion the `C' Service Water Traveling Screen was removed from service for an inspection. The grass intrusion resulted in the `A' Service Water strainer breaker tripping open de-energizing the strainer. Differential pressure on this strainer was pegged high and flow was reduced to 1900 gallons per minute [17,000 normal; 15,500 minimum]. The combination of these conditions resulted in inadequate cooling water flow to the `A' Station Auxiliaries Cooling Water system, and consequently inadequate cooling for the `A' Control Room Emergency Filtration [CREF] unit. With the `B' CREF fan already inoperable for a scheduled maintenance window, this resulted in entry into Technical Specification 3.0.3.

"This report is to document starting a unit shutdown to comply with Technical Specifications 3.0.3. Power reduction for Unit shutdown was commenced at 0407 [ET]. Unit shutdown was terminated at 0424 when `C' Service water pump was returned to service restoring cooling water to `A' SACS loop, restoring it to an OPERABLE status. This event is reportable under 10CFR50.72(b)(2)(i) as a four hour report.

"The Control Room Ventilation System provides heating, cooling, ventilation, and environmental control for the control room and adjacent areas. Under accident conditions, the Control Room Emergency Filtration Unit (CREF) ensures that the control room will remain habitable during and following all design basis accidents. Because the CREF system is required to automatically respond in the event of a design basis accident, having both trains of CREF inoperable at the same time impacted the ability to mitigate the consequences of an accident. Therefore, this event is also being reported in accordance with 10CFR50.72(b)(3)(v)(D) to comply with the requirements of an 8 hour report.

"At the time of the event the following Tech Spec related equipment was inoperable. `C' Service Water for screen inspection and `B' CREF for chiller maintenance work. Currently all safety related equipment is operable with the exception of the `A' Service Water Loop."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 40541
Facility: BRUNSWICK Region: 2 State: NC Unit: [1] [ ] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: CHARLES ELBERFELD HQ OPS Officer: ERIC THOMAS	Notification Date: 02/23/2004 Notification Time: 15:36 [ET] Event Date: 01/11/2004 Event Time: 06:37 [EST] Last Update Date: 02/23/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION	Person (Organization): BRIAN BONSER (R2)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	Y	93	Power Operation	93	Power Operation

Event Text

INVALID SPECIFIED SYSTEM ACTUATION

"This report is being made in accordance with 10CFR50.73 (a)(1), which states, in part, "in the case of an invalid actuation reported under 10 CFR50.73(a)(2)(iv), other than actuation of the reactor protection system (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER." These invalid actuations are being reported under 10CFR50.73(a)(2)(iv)(A). NUREG-1022, Rev. 2, states that the report should provide the following information:

-The specific train(s) and system(s) that were actuated
-Whether each train actuation was complete or partial
-Whether or not the system started and functioned successfully.

"On January 11, 2004, at 0637 hours, the Reactor Building Exhaust Radiation Monitor (i.e., 1-D12-RM-K609B) signal input spiked resulting in the invalid actuation of the logic associated with the instrument channel. The actuations included the Primary Containment Isolation System (PCIS) Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems) valves, the Reactor Building Ventilation System isolation (i.e., Secondary Containment isolation) and the automatic start of both Standby Gas Treatment (SGT) System trains A and B. The actuations of PCIS Group 6 valves and Reactor Building Ventilation System isolation were complete and the affected equipment responded as designed to the invalid signal (i.e., the valves and dampers that were open, at the time of the event, closed). Additionally, SGT System trains A and B started and functioned successfully. After verification of the expected equipment responses, 1-D12-RM-K609B was reset, the actuation logic was reset, and the equipment/systems were returned to the status required by plant conditions. A radiological survey of the monitored area was completed with no abnormal conditions noted.

"Discussion of the causes and corrective actions associated with this event are documented in the corrective action program in action request (i.e., AR) 115087. The resident inspector has been notified."