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Event Notification Report for August 13, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/12/2015 - 08/13/2015

** EVENT NUMBERS **


51274 51286 51287 51288 51313

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 51274
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARIAZ DAVIS
HQ OPS Officer: JEFF ROTTON
Notification Date: 07/28/2015
Notification Time: 18:55 [ET]
Event Date: 07/28/2015
Event Time: 13:58 [EDT]
Last Update Date: 08/12/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RAY MCKINLEY (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

DISCOVERED ONE INCH DIAMETER HOLE BETWEEN REACTOR BUILDING AND AUXILIARY BUILDING

"At 1358 [EDT] on July 28, 2015, a 1 inch diameter hole was discovered in the secondary containment wall, between the Reactor Building and the Auxiliary Building, causing the Secondary Containment to become inoperable under Technical Specification 3.6.5.1. Reactor Building pressure was maintained at a negative pressure as required by Technical Specification 3.6.5.1 with the Reactor Building ventilation system in service before and after discovery of the hole. In addition, the Filtration, Recirculation and Ventilation system remained fully operable and remained in standby. The hole was sealed at 1600 and technical specification 3.6.5.1 was exited. Plant operation was not impacted by the event and was operating at 100% power. No personnel injuries resulted from this event."

The hole was discovered by plant personnel that were walking past the wall. Due to the discovery of the hole, the plant is performing an extent of condition inspection.

The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Dispatch.

* * * * RETRACTION FROM MARIAZ DAVIS TO STEVEN VITTO AT 1232 EDT ON 08/ 12/15 * * * *

"This event is being retracted.

"Hope Creek Generating Station Unit 1, is retracting the 8-hour non-emergency notification (EN# 51274) made on July 28, 2015, at 1855 EDT. The notification on July 28, 2015, reported that secondary containment was declared inoperable when a 1 inch hole was discovered in the secondary containment wall, between the Reactor Building and the Auxiliary Building. Secondary containment was declared inoperable based on the initial interpretation of the definition of secondary containment. The hole did not impact the ability to maintain the Tech Spec required negative pressure. Subsequent evaluation determined that secondary containment was always operable. Based on the engineering evaluation, the condition reported in EN# 51274 did not result in an inoperability of the secondary containment. Therefore, there is no reportable condition and this event report is being retracted.

"The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction."

The licensee also notified the Lower Alloways Creek Dispatch.

Notified R1DO (Powell).

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Agreement State Event Number: 51286
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: SUTTER SURGICAL - FAIRFIELD
Region: 4
City: FAIRFIELD State: CA
County:
License #: 7602
Agreement: Y
Docket:
NRC Notified By: GENE FORRER
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/04/2015
Notification Time: 14:06 [ET]
Event Date: 07/20/2013
Event Time: [PDT]
Last Update Date: 08/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

CALIFORNIA AGREEMENT STATE REPORT - HISTORICAL MEDICAL EVENTS DISCOVERED DURING STATE INVESTIGATION

The following information was provided by the State of California via email:

"RHB [ California Radiation Heath Branch] personnel noted irregularities in the way brachytherapy was being performed by an authorized user and investigated all facilities where he is authorized to perform brachytherapy.

"On August 3, 2015, after reviewing files and consulting with the RSO of the facility, it was determined that there had been two medical events that had gone unreported. Both events were prostate Pd-103 implants performed in 2013 and 2014. One treatment resulted in a dose of only 37.6 percent of the target dose to the prostate (139.5 mCi Pd-103) and the second resulted in a dose of 66.9 percent of the target dose to the prostate (189.1 mCi Pd-103). The licensee will submit a follow up report within 15 days."

CA 5010 (Date Notified): 072015

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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Non-Agreement State Event Number: 51287
Rep Org: SANFORD HEALTH
Licensee: SANFORD HEALTH
Region: 4
City: SIOUX FALLS State: SD
County:
License #: 40-12378-01
Agreement: N
Docket:
NRC Notified By: STEVEN MOECKLY
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/04/2015
Notification Time: 18:09 [ET]
Event Date: 07/30/2015
Event Time: 12:00 [CDT]
Last Update Date: 08/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

MEDICAL EVENT RESULTING FROM ACTUAL TREATMENT DOSE 30 PERCENT GREATER THAN PRESCRIBED

On 7/31/2015, a patient was undergoing a single treatment for liver cancer using Y-90 microspheres (SIR-Spheres) with a prescribed dose from the physicians written directive of 29.43 milliCi. On 8/4/2015, it was discovered that the patient actually received 38.2 milliCi dose due a calculation error based on the physician's initial written directive when the physician had decided on a final dose reduction prior to treatment. The physician has been notified and believes that there will be no adverse effects to the patient. The patient will be notified on 8/5/2015.

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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Non-Agreement State Event Number: 51288
Rep Org: ADVANCE TESTING COMPANY, INC
Licensee: ADVANCE TESTING COMPANY INC
Region: 1
City: CAMPBELL HALL State: NY
County:
License #: 31-31284-01
Agreement: Y
Docket:
NRC Notified By: MARK CLARK
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/05/2015
Notification Time: 10:02 [ET]
Event Date: 08/05/2015
Event Time: [EDT]
Last Update Date: 08/07/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
ART BURRITT (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

DAMAGED PORTABLE MOISTURE DENSITY GAUGE

The licensee reported that a portable moisture density gauge was damaged, by a dump truck, during a road paving project in Glastonbury, CT. The gauge case and keypad were damaged however, the sources are in the stored/safe position. There is no indication of leakage and no radiation exposures have occurred. The licensee has stored the gauge in their secure location pending further evaluation. The gauge is an Instrotek Model 3500 gauge containing 11mCi Cs-137 and 44 mCi Am/Be sources.

* * * UPDATE PROVIDED BY MARK CLARK TO JEFF ROTTON AT 1258 EDT ON 08/07/2015 * * *

Licensee called to correct initial report. The damaged gauge was actually a Troxler 3440, Serial number 18428 and not an Instrotek model 3500. Reported activity of sources remains the same.

Notified R1DO (Burritt) and NMSS Events Notification Group via email.

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Power Reactor Event Number: 51313
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: BRETT JEBBIA
HQ OPS Officer: STEVEN VITTO
Notification Date: 08/12/2015
Notification Time: 13:31 [ET]
Event Date: 08/12/2015
Event Time: 10:07 [EDT]
Last Update Date: 08/12/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

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

SECONDARY CONTAINMENT TECHNICAL SPECIFICATIONS NOT MET

"At 1007 [EDT] on August 12, 2015, while restoring Reactor Building (RB) HVAC (RBHVAC) after surveillance testing, an equipment malfunction resulted in improper damper alignment resulting in Secondary Containment Technical Specifications (TS) to not be met.

"The plant TS require Secondary Containment pressure be maintained greater than or equal to -0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1). This specification was not maintained for five seconds and the highest pressure observed was -0.095 inches of vacuum water gauge. This value was observed on only one of two installed recorders, of the Secondary Containment pressure recorders. The highest observed pressure on the other recorder was -0.14 inches of vacuum water gauge. Secondary Containment was restored by the Standby Gas Treatment System (SGTS) already in operation and shutting down the affected train of RBHVAC.

"The technical specification requirement is to maintain secondary containment at -0.125 inches of vacuum water gauge for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR50.72(b)(3)(v)(c) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, August 13, 2015
Thursday, August 13, 2015