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Event Notification Report for January 22, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/18/2013 - 01/22/2013

** EVENT NUMBERS **


48671 48681 48684 48685 48686 48687

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Agreement State Event Number: 48671
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: THOMAS JEFFERSON UNIVERSITY HOSPITALS, INC.
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0130
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 01/14/2013
Notification Time: 14:53 [ET]
Event Date: 01/11/2013
Event Time: [EST]
Last Update Date: 01/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING PROSTATE BRACHYTHERAPY IMPLANT

The following information was obtained from the Commonwealth of Pennsylvania Department of Environmental Protection via e-mail:

"On January 11, 2013 the licensee informed the Department's Southeastern Regional Office of the Medical Event. The event is reportable within 24 hours per 10CFR 35.3045(a)(1)(i). Both the patient and referring physician were notified.

"On December 4, 2012 the patient received an iodine-125 prostate seed implant. The patient returned for the 30 day post-treatment follow-up CT scan on January 9, 2013. Upon review of the CT results on January 10, 2013, it was discovered that the prostate received approximately 60% of the intended dose. The D90 was determined to be 56 Gy out of a prescribed dose of 110 Gy.

"The potential cause of the event was noted as possible organ shift or incorrect depth placement of needles.

"The licensee plans to compensate for the undertreated area with follow-up external beam therapy. They will provide the Department a written report in 15 days. The Southeastern Regional Office plans to follow up with a reactive inspection."

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.

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Power Reactor Event Number: 48681
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. EARSLEY
HQ OPS Officer: PETE SNYDER
Notification Date: 01/18/2013
Notification Time: 15:37 [ET]
Event Date: 01/18/2013
Event Time: 12:40 [CST]
Last Update Date: 01/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
TAMARA BLOOMER (R3DO)

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

Event Text

PANS SYSTEM FALSE ACTIVATION OF 58 SIRENS

There was a false activation signal applied for 3 seconds to site emergency sirens. The licensee notified the State of Minnesota and local government agencies.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 48684
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/20/2013
Notification Time: 20:50 [ET]
Event Date: 01/20/2013
Event Time: 16:41 [EST]
Last Update Date: 01/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT FREEMAN (R2DO)

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

Event Text

TECHNICAL SUPPORT CENTER VENTILATION DISABLED

"At 1641 on January 20, 2013, the Technical Support Center (TSC) became non-functional when the ventilation system was secured and disabled by a fire alarm. Investigation of the alarm condition determined the fire alarm was not valid and would not reset. At 1830, Technical Support Center ventilation was restored by disabling the deficient fire alarm by using guidance in alarm response procedure APP-FP-KBLDG. The Technical Support Center was restored to functional status at 1830 on January 20, 2013.

"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this condition affected an emergency response facility for greater than facility activation time (one hour).

"The NRC Resident Inspector has been informed"

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Power Reactor Event Number: 48685
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: PAUL GALLANT
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/20/2013
Notification Time: 23:30 [ET]
Event Date: 01/20/2013
Event Time: 20:50 [EST]
Last Update Date: 01/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JOHN ROGGE (R1DO)

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

Event Text

TECHNICAL SPECIFICATION (TS) REQUIRED SHUTDOWN - SAFETY RELIEF VALVE DECLARED INOPERABLE

"On Sunday, January 20, 2013, at 2050 hours, with the reactor at 100% core thermal power, the station entered a 24-hour action statement to initiate a controlled shutdown and be less than 104 psig reactor pressure due to suspected leakage across the first stage pilot of safety relief valve (SRV) RV-203-3B and subsequent declaration of the SRV inoperable due to criteria specified in Pilgrim plant procedure 2.2.23.

"As background, the pressure relief system includes four (4) SRVs and two (2) spring safety valves (SSVs). The SRVs discharge through their individual discharge piping, terminating below the minimum suppression pool (torus) water level. The four SRVs are installed on the main steam piping in containment between the reactor pressure vessel and the flow restrictors.

"While at full power, indication of a steam leak across the first stage pilot of RV-203-3B was determined in accordance with criteria specified in procedure 2.2.23. Specifically, the SRV is inoperable if the pilot stage thermocouple temperature is 35 degrees F below its baseline temperature (with a lower decrease at the 2nd stage thermocouple) and cannot be explained by a corresponding downpower. The safety relief valve was subsequently declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.6.D was entered. Due to the valve being declared inoperable the station is required to be shutdown and reactor coolant pressure below 104 psig within 24 hours per TS 3.6.D.2.

"Currently a reactor shutdown is in progress to initiate safety relief valve repairs.

"This event has no impact on the health and/or safety of the public.

"The USNRC Senior Resident Inspector has been notified."

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Power Reactor Event Number: 48686
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: RYAN MACNAIL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/21/2013
Notification Time: 11:32 [ET]
Event Date: 01/21/2013
Event Time: 13:00 [EST]
Last Update Date: 01/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT FREEMAN (R2DO)

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

Event Text

LOSS OF RESPONSE CAPABILITY - TECHNICAL SUPPORT CENTER AH-17 SUPPLY FAN NON-FUNCTIONAL FOR PREPLANNED MAINTENANCE

"This is a non-emergency notification. At approximately 1300 [EST] on January 21, 2013 preplanned maintenance will be performed which will remove AH-17, one of three Technical Support Center (TSC) Supply Fans from service. The scope of the maintenance is to replace and align the fan's sheave with a contingency to replace its drive belt. This maintenance is expected to be performed and completed within approximately 7 hours. If an emergency condition should occur, the ventilation system will be restored, but potentially not within the time required for activation of the TSC. In addition, the ventilation system will be restored, but potentially not within the time required for activation of the TSC. In addition, the Harris Nuclear Plant (HNP) emergency plan has procedural guidance for use of an alternate location in the event the TSC is not habitable. The on-call TSC Site Emergency Coordinator and Emergency Response Manager have been notified."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48687
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JOE WILLIAMS
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/21/2013
Notification Time: 19:55 [ET]
Event Date: 01/21/2013
Event Time: 15:51 [CST]
Last Update Date: 01/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MICHAEL VASQUEZ (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 84 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL

"At 15:51 CST, Waterford 3 experienced an uncomplicated automatic reactor trip from 84.5% reactor power. The actuations of the Reactor Protection System (RPS) and the Emergency Feedwater Actuation System (EFAS) resulted from Steam Generator #1 Low Level, which is at a nominal 27.4% narrow range setpoint. Safety systems responded as expected.

"All three (3) Emergency Feedwater Pumps started and injected into Steam Generator #1. Auxiliary Feedwater pump has been started, feeding both Steam Generators (#1 and #2) at levels above the EFAS low level setpoint. All control rods inserted by the automatic RPS actuation. Electrical power is being supplied from normal off-site power and condenser vacuum is available for Steam Generator heat removal via the Steam Dump Bypass Control system. There are no safety systems out of service or inoperable, nor any safety system TS [Technical Specification] LCO [Limiting Condition for Operation] actions entered.

"The cause of the Steam Generator #1 Low Level condition, and associated Reactor Trip, is under investigation. This event occurred during the initial power escalation from refuel outage RF18, after attempting to place C Heater Drain Pump (HDP), the first of three, into service. After starting, C HDP tripped for a reason not yet verified. Subsequently, based on initial Control Room operator observations, the Steam Generator #1 Main Feedwater control valve position was observed to be at 10-20% open, but with an open position demand signal of 100%. Main Feedwater response to the reactor trip (Rector Trip Override) was as expected."

The NRC Resident Inspector has been informed.

Page Last Reviewed/Updated Tuesday, January 22, 2013
Tuesday, January 22, 2013