Event Notification Report for December 21, 2012

UNIT 1 AUTOMATIC REACTOR TRIP ON TURBINE TRIP

"Salem Unit 1 has experienced an automatic reactor trip at 0528 [EST] on 12/21/12. The unit tripped due to turbine trip above P-9 [Greater than 49% power]. All shutdown and control rods fully inserted on the reactor trip. Prior to the trip, the unit was operating at 100% when the crew received the OHA [Overhead Alarm] for main power transformer over excitation which actuated generator protection, which initiated the turbine trip. The auxiliary feed water (AFW) system auto started on low steam generator levels as expected on a reactor trip. Numbers 11, 12 & 13 AFW pumps all automatically started to provide feed to the steam generators. The [Operating Crew] entered EOP-Trip-1, then transitioned to EOP-Trip-2 and stabilized the plant.

"The unit is currently in mode 3. The OCC [Outage Control Center] is manned and the cause of the main power transformer over excitation is under investigation at this time. RCS temperature is 547 degrees F, RCS pressure is 2235 psig. The 11-14 RCP's are in service. There is one shut down technical specification action statement in effect. Unit 1 containment APD [Containment Radiation Monitor] is inoperable for DCP [Design Change Package] work. This is a 30 day shutdown LCO that expires on 1/16/2013 at 0830. All ECCS and ESF systems are available. Decay heat removal is being provided by 11 and 12 AFW pumps and the main steam dump system. The 13 AFW pump operation is not required and has been removed from service. The plant is aligned with a normal electrical line-up from offsite power sources. There were no personnel injuries associated with this event

"This event is reportable per 10CFR50.72(b)(2)(iv)(b) due to the automatic reactor trip.

"This event is reportable per 10CFR50.72(b)(3)(iv)(a) due the AFW actuation on low steam generator levels."

There was no lifting of PORVs or primary to secondary leakage. There was no impact on Unit 2.

The licensee notified the NRC Resident Inspector.

LOSS OF EMERGENCY RESPONSE DATA SYSTEM (ERDS)

"At approximately 0730 CST, Xcel Energy Monticello Nuclear Generating Plant was informed of a loss of internet and data services due to equipment problems with the Wide Area Network (WAN). The loss of data services resulted in the loss of ERDS communication capabilities with the NRC. Compensatory actions were established to communicate plant parameters verbally via the Emergency Notification System, which was verified functional at 0836 CST.

"The WAN and ERDS were restored at 0921 CST and ERDS was verified functional at 0948 CST.

"This issue is being reported as a loss of communications capability non-emergency event notification under 10CFR50.72(b)(3)(xiii) as defined in NUREG 1022, Rev. 2.

"The licensee has notified the NRC Resident Inspector."

BOTH UNIT TWO AUXILIARY FEEDWATER PUMPS DECLARED INOPERABLE

"21 Motor Driven and 22 Turbine Driven Auxiliary Feedwater Pumps (AFWP) were declared inoperable at 0900 CST on 12/21/2012 due to the Condensate Storage Tank (CST) temperature exceeding 92 degrees F.

"In accordance with procedure C28.6, 'Condensate Storage Tank Freeze Protection System', the maximum CST temperature shall not exceed 92 degrees F. This is to ensure the maximum AFWP discharge temperature is less than 100 degrees F when an AFWP is at design flow per USAR Table 11.9-2, 'Summary of Assumptions,' used in the AFW system design verification analyses.

"LCO 3.7.5 Condition D was entered for two AFW trains inoperable in Modes 1, 2 or 3. The AFWP's could start and run if required at the time of entry.

"Immediate action was taken to reduce the CST temperature. At 1315 CST temperature were lowered below 92 degrees F and LCO 3.7.5 condition D was exited.

"This condition is reportable per 10 CFR 50.72(b) (3) (v) (D) as an event or condition that could have prevented the fulfillment of a safety function."

The licensee has notified the NRC Resident Inspector.


* * * RETRACTION FROM LOOSBROCK TO TEAL ON 1/17/13 AT 1412 EST * * *

"This notification is being made to retract Event Notification (EN) #48619, which reported 21 Motor Driven and 22 Turbine Driven Auxiliary Feedwater Pumps (AFWP) were declared inoperable due to the Condensate Storage Tank (CST) temperature exceeding 92 degrees F. Based on engineering analysis the 92 degree F was a margin value with no formal basis or evaluation. This value was added to the C28.6 procedure in the early 1990's as a precaution to provide Operations with additional operating information.

"After the 22 CST tank was found above the 92 degrees F temperature on 12/21/12, a formal engineering evaluation (EC 21354) was performed to determine CST heat values and provide an accurate number for temperature margin. The purpose of the CST tank temperature being at a specific value is to ensure that the AFWP discharge temperature stays at or under 100 degrees F to ensure the AF system can provide adequate decay heat removal if called upon during an accident. Engineering evaluation EC 21354 determined that the average CST tank temperatures could reach 96.5 degrees F before the AFWP discharge temperature could have reached 100 degrees F. Therefore, there was no loss of safety function or past operability concerns."

"The NRC Resident Inspector has been informed."

Notified R3DO (Bloomer).

LOSS OF EMERGENCY RESPONSE DATA SYSTEM (ERDS)

"At approximately 0730 CST, Xcel Energy Prairie Island Nuclear Generating Plant was informed of a loss of internet and data services due to equipment problems with the Wide Area Network (WAN). The loss of data services resulted in the loss of ERDS communication capabilities with the NRC.

"The WAN and ERDS were restored at 0921 CST."

The licensee has notified the NRC Resident Inspector.