Event Notification Report for November 04, 2010

FOUR AVERAGE POWER RANGE MONITORS OUTSIDE ALLOWABLE RANGE

"Following a power reduction to 49 percent reactor thermal power at approximately 2312 [CDT] on November 4, 2010, 'B' high pressure feedwater heaters were isolated at approximately 2320 in preparation for repair of the 15B feedwater heater. Calculated core thermal power (CTP) rose by approximately 50 MWth. This resulted in all four average power range monitors (APRMs) failing to satisfy Technical Specification (TS) Surveillance Requirement SR 3.3.1.1.2 in that the absolute difference between the APRMs and the calculated power from the heat balance was greater than 2.0 percent rated thermal power (RTP). All four APRM channels were between approximately 3.5 and 4.0 percent lower than CTP. Since all four APRM channels were affected, the functions of the APRMs were inoperable and RPS trip capability had not been maintained. TS Conditions 3.3.1.1.A and 3.3.1.1.C were entered at 2325. All four APRM gains were adjusted and the TS Conditions were exited at 2349.

"This event is reportable under 10CFR50.72(b)(3)(v) as an event that could have prevented the fulfillment of the safety function of a system needed to: (A) shutdown the reactor and (D) mitigate the consequences of an accident.

"This event notification is being submitted outside the 8 hour reporting requirement."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM RANDY SCHULTZ TO HOWIE CROUCH AT 1652 EST ON 11/7/10 * * *

"The following is an update to Event Notification 46397 made on 5 November 2010 concerning Average Power Range Monitors (APRMs) inoperability due to >2% deviation from calculated Core Thermal Power (CTP).

"During review of inputs to the CTP calculation, Operations staff determined that indicated power levels were not consistent with the indicated electrical output of the turbine generator. Subsequent investigation revealed an erroneous feedwater flow input from the isolated 'B' feedwater heater string. Actual CTP was less than indicated CTP by approximately 50 MWth. This was validated and verified through manual calculation. 50 MWth constitutes approximately 3% of rated thermal power. With the adjustments made to APRM on 4 November 2010, this resulted in all four APRMs being outside of the acceptable tech spec value. Following Operations review, at 1108 on November 7, 2010, all four APRMs were declared inoperable and tech. spec. 3.3.1.1.A and 3.3.1.1.C actions were initiated.

"Values consistent with the actual plant configuration ('B' feedwater heater string isolated) were input to the CTP calculation with subsequent indicated CTP returning to actual CTP. All four APRM gains were adjusted and APRMs returned to operable status. Tech Spec 3,3.1.1.A and 3.3.1.1.C conditions were exited at 1207 on November 7, 2010."

The licensee has notified the NRC Resident Inspector. Notified R3DO (Giessner).

AGREEMENT STATE REPORT - LEAKING SEALED SOURCE

The following information was reported via e-mail by the State of California:

"On November 03, 2010, the RSO at UC Berkeley informed the [California] Radiologic Health Branch (RHB) that on 11/01/10 an Electron Capture Device (ECD), S/N F7737 containing 15 mCi of Ni-63, was determined to have leakage in excess of 0.005 microcurie criteria. The leaking source was installed in a Hewlett-Packard gas chromatography unit Mode 5890. Immediately after the leakage was found, the unit was taken out of service. Follow-up surveys performed did not show any area contamination. The maximum contamination found on the internal portion of the ECD outlet port was 0.007 microcuries. The extent of contamination was limited to the ECD and exhaust tubing. No personal contamination was expected since the leakage was limited to the internal parts of the gas chromatography unit and vent tubing.

"The unit was used for routine analysis of organic materials. The leakage may have been due to the routine use over many years (@ 16 years). The University will pursue disposal of this ECD."

California RHB 5010 - 110310.

CONTAINMENT AIR LOCK DOORS NOT OPERATED PROPERLY

"On November 4, 2010, at 11:28 AM both doors in airlock 124 from secondary containment to access control were simultaneously open for a period <5 seconds. The doors were immediately closed. This condition resulted in an unplanned entry into Technical Specification 3.6.4.1.A for secondary containment. The condition could have prevented the Standby Gas Treatment System from developing a negative pressure within secondary containment following a design basis accident. This negative pressure is required to prevent ground consequences following an accident. The Standby Gas Treatment System remained operable throughout the event."

The licensee was decreasing power at the time of the report for a condition unrelated to the report.

The licensee will notify the Minnesota Duty Officer.

The licensee notified the NRC Resident Inspector.

PORTAL RADIATION MONITOR ALARM ON A SCRAP SHIPMENT

"On November 4, 2010, at approximately 1504 PDT, San Onofre Nuclear Generating Station (SONGS) was notified that scrap circuit breakers salvaged from the SONGS warehouse had alarmed a portal radiation monitor at a metal recycling facility in Los Angeles County. The monitor indicated a reading approximately 40% above background levels. Naturally occurring isotopes in the circuit breakers are suspected to have alarmed the portal monitor. The metal recycling vendor (Alpert and Alpert) called the Los Angeles branch of the California Department of Health Services, Radiologic Health Branch to obtain a special permit authorizing the return shipment to SCE.

"SCE is reporting this event in accordance with 10CFR50.72(b)(2)(xi).

"At the time of this report, Unit 2 was operating at 100% power and Unit 3 is defueled."

The licensee notified the NRC Resident Inspector.


* * * UPDATE AT 0018 EDT ON 11/06/10 FROM SIMMON TO HUFFMAN * *

"On November 5, 2010, employees of the San Onofre staff disassembled the scrap circuit breakers that had been sent from the San Onofre Warehouse to the Alpert and Alpert salvage yard on November 4. These high voltage circuit breakers contain arc chutes consisting of large ceramic plates that contain naturally occurring radioactive material. All ceramic materials were removed. Health Physics technicians then re-surveyed the circuit breaker casings by direct and indirect survey and verified that they did not contain any detectable levels of radioactive material. Indirect survey of the ceramic material demonstrated that they had no detectable levels of removable radioactive material.

"The California Department of Health Services, Radiologic Health Branch will be notified of these results."

The licensee has notified the NRC Resident Inspector. R4DO (Howell) and FSME (Chang) notified.

CHARGING PUMP '23' DECLARED INOPERABLE DURING SURVEILLANCE TESTING

"On November 4, 2010 at 0123 [EDT], '23' Charging Pump was declared inoperable due to not meeting required test parameters during surveillance testing. '23' Charging Pump is required for remote shutdown per Technical Specification 3.3.4, Remote Shutdown, and is a single component system intended to perform the inventory control safety function. Since '23' Charging Pump has been declared inoperable, a loss of safely function has occurred and is reportable per 10CFR50.72 (b)(3)(v)(A).

"The cause of the inoperability is under investigation. Per Technical Specification 3.3.4, Remote Shutdown, '23' Charging Pump must be restored to operable status within 30 days."

The licensee will inform the NY State PSC (Public Service Commission) and the NRC Resident Inspector.

* * * RETRACTION FROM CHARLES ROKES TO DONG PARK AT 1028 EST ON 12/20/10 * * *

"Indian Point Unit 2 is withdrawing the 8-hour non-emergency notification made on November 4, 2010, at 0305 EST. The notification on November 4, 2010, reported a safety system functional failure (SSFF) as a result of declaring the 23 Charging Pump (CP) inoperable. The 23 CP failed to meet test parameters during testing. Because the 23 CP is credited in Technical Specification (TS) 3.3.4 for Remote Shutdown, the inoperable condition was determined to be a loss of safety function. The TS 3.3.4 Allowed Outage Time (AOT) for inoperable conditions is 30 days. The remote shutdown function is not credited in the accident analysis.

"Subsequent investigations determined that during a two year comprehensive test (IST) the 23 CP failed the flow test due to low pump discharge flow (79.3 gpm) at the prescribed test speed (85% of rated speed). Troubleshooting determined that the 23 CP recirculation line valves 1279 and 4902 had leak-by of approximately 6.7 gpm. The leak-by results in a reduction of available discharge flow from the 23 CP to the Reactor Coolant System (RCS) due to a small amount of the pump discharge being diverted through the recirculation line. Engineering determined that the CP capacity for emergency boration with the recirculation line valves leak-by was within the capability of the 23 CP to maintain overall system function. The 23 CP is also credited for RCS inventory maintenance per TS 3.3.4 and Station Administrative Order (SAO) 703 for fire protection. Engineering concluded that with a normal CP output of approximately 87-90 gpm and a nominal rated capacity of 98 gpm, the reduction by approximately 6.7 gpm due to leak-by did not significantly impact normal operation of the CP. Therefore, the 23 CP continues to meet the established IST requirement when the 6.7 gpm recirculation line valve leak-by is accounted for. The degraded output is associated with the system rather than the 23 CP therefore the IST requirement for the 23 CP is satisfied. Additionally, the 23 CP test was performed at approximately 85% of rated speed in accordance with the IST requirements. At 100% rated speed, the remaining available capability to the RCS would be approximately 92 gpm. Engineering concludes that although degraded the 23 CP and system can perform their intended function and no SSFF occurred."

The licensee will notify the NRC Resident Inspector. The R1DO (Perry) was notified.