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Event Notification Report for May 04, 2011

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
05/03/2011 - 05/04/2011

EVENT NUMBERS
46820468214695648011

Power Reactor
Event Number: 46820
Facility: OYSTER CREEK
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: PETE SNYDER
Notification Date: 05/04/2011
Notification Time: 17:57 [ET]
Event Date: 05/04/2011
Event Time: 16:13 [EDT]
Last Update Date: 05/04/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
HAROLD GRAY (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
Event Text
CHANGES IN FUEL VENDOR CALCULATION METHODOLOGY TO COMPLY WITH THE ECCS PERFORMANCE REQUIREMENTS OF 10 CFR 50.46(b).

"Oyster Creek has been informed of a change in its vendor's calculation of Peak Cladding Temperature (PCT) and the Maximum Local Oxidation (MLO) that is based on corrections to errors in the previous calculation of record the vendor has identified. Based on 10 CFR 50.46 Appendix K inputs and assumptions, the correction of errors resulted in an increase of 115 degrees F in the PCT for GE11 fuel and 145 degrees F for the GNF2 fuel. The impact on the MLO due to these errors resulted in an increase of 16.0% for GE11 fuel and 33.0% for the GNF2 fuel.

"To ensure compliance with the 10 CFR 50.46 requirements, administrative Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit adjustments have been applied to bring the PCT and MLO limits below the 10 CFR 50.46 criteria of 2200 degrees F and 17% acceptance criteria. The current LOCA analysis of record remains applicable with the applied MAPLHGR limit adjustments.

"This notification is being made as a result of the 10 CFR 50.46(a)(3)(ii) requirement to report this issue in accordance with 10 CFR50.72 and 10 CFR50.73.

"Based on current core thermal power level and existing margin to limits on power operation there is sufficient margin for analyzed accident scenarios requiring ECCS operation including appropriate MAPLHGR compensation to restore the PCT and the MLO within 10 CFR 50.46 acceptance criteria and therefore there is no impact on safe operation. As a result of the MAPLHGR limit adjustment the current LOCA analysis of record remains applicable and therefore, the offsite dose is still bounded by our current safety analysis. Therefore this event is not significant with respect to the health and safety of the public.

"Corrective Action(s):
"(1) Administrative adjustments to allowable MAPLHGR limits have been imposed to restore the applicability of the current LOCA analysis of record.
"(2) Revised MAPLHGR limits have been provided by the fuel vendor and will be implemented into the plant monitoring system, followed by removal of the administrative adjustments to the MAPLGHR.
"(3) A 10 CFR 50.46 report will be submitted within 30-days."

The licensee will notify the NRC Resident Inspector.


Part 21
Event Number: 46821
Rep Org: SOR INC PROCESS INSTRUMENTATION
Licensee: SOR INC PROCESS INSTRUMENTATION
Region: 4
City: LENEXA   State: KS
County:
License #:
Agreement: Y
Docket:
NRC Notified By: COLBERT TURNEY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/04/2011
Notification Time: 12:14 [ET]
Event Date: 05/04/2011
Event Time: 00:00 [CDT]
Last Update Date: 05/04/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
DAVID PROULX (R4DO)
PART 21 GROUP
MARK RING (R3DO)
Event Text
PRESSURE SWITCH WITH POSSIBLE SUB-STANDARD ELECTRICAL LEAD TERMINATIONS

SOR Process Instruments has determined that certain model pressure switches it has manufactured may have leads attached to the terminal blocks that are not in conformance with good manufacturing practice. The pressure switches in question may have lead wire attached to the terminal block in which the connection between the stripped, stranded wire and a crimped terminal may not be flush with the terminal end. SOR states that there have been no known field problems associated with this issue.

This condition applies to SOR model switches with terminal block "X" options 9013-737, 9013-747, 9013-7674. SOR has provided this information to those customers that purchased these switches. The U.S. plants that received these switches are Braidwood and Duane Arnold.


Agreement State
Event Number: 46956
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: SENTARA HOSPITAL
Region: 1
City: NORFOLK   State: VA
County:
License #: 710-189-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/13/2011
Notification Time: 16:39 [ET]
Event Date: 05/04/2011
Event Time: 00:00 [EDT]
Last Update Date: 06/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JUDY JOUSTRA (R1DO)
ANDREW PERSINKO (FSME)
Event Text
AGREEMENT STATE REPORT - MEDICAL EVENT DURING LIVER RADIATION THERAPY

The following report was received via fax:

"On May 4, 2011 a patient underwent a Y-90 therapy procedure. Two doses were to be administered to the right lobe of the patient's liver. The first dose was terminated when stasis was achieved. The second dose was terminated because of patient pain after 48% of the dose had been delivered. The pain during the second dose was considered most likely due to embolization. The licensee notified VDH (Virginia Department of Health) and requested guidance on whether the circumstances could be due to patient intervention. It was determined by VDH to be a medical event and not excepted because of patient intervention. A conference call was held with the licensee on June 10th and a written report submitted to VDH. The licensee indicated written directives, patient preparation, and pain control methods would be reviewed."

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.


Power Reactor
Event Number: 48011
Facility: ROBINSON
Region: 2     State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: RICH ROGALSKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/11/2012
Notification Time: 10:03 [ET]
Event Date: 05/04/2011
Event Time: 13:25 [EDT]
Last Update Date: 06/11/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MALCOLM WIDMANN (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
REFUELING WATER STORAGE TANK CONNECTED TO NON-SEISMICALLY QUALIFIED SYSTEM

"On May 4, 2011, at approximately 1325 Eastern Daylight Time (EDT), with H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, in Mode 1 at 100% power, it was determined that over the last 40 years, HBRSEP, Unit No. 2 periodically performed cleanup of the Refueling Water Storage Tank (RWST) by aligning the non-seismically qualified refueling water purification system to the safety related and seismically qualified RWST without recognizing that the action rendered the RWST inoperable. As a result, on multiple occasions, the RWST was inoperable for a period longer than allowed by Technical Specification (TS) Limiting Condition for Operation 3.5.4, Emergency Core Cooling Systems Refueling Water Storage Tank.

'The cause of this event was that regulatory requirements for the separation of seismically qualified and non-qualified systems, structures, and components were not adequately incorporated into the Design Basis Document (DBD) and Updated Final Safety Analysis Report (UFSAR).

"A clearance order has been placed in effect to ensure restrictions for piping that could affect the operability of the RWST remain in place.

"This event was described in Licensee Event Report 2011-001-00 and was initially reported in accordance with 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications. However, further reviews determined at 0800 on June 11, 2012, that the event is also reportable under 10 CFR 50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a safety function.

"During the three year period prior to May 4, 2011, it is estimated that the purification loop was in service aligned to the RWST while on-line nine times, totaling 297 days."

The licensee has notified the NRC Resident Inspector.