Event Notification Report for February 06, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/05/2015 - 02/06/2015
EVENT NUMBERS
50791507925079350794
Part 21
Event Number: 50791
Rep Org: THERMO GAMMA-METRICS LLC
Licensee: THERMO GAMMA-METRICS LLC
Region: 4
City: SAN DIEGO State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CLARK ARTAUD
HQ OPS Officer: DANIEL MILLS
Licensee: THERMO GAMMA-METRICS LLC
Region: 4
City: SAN DIEGO State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CLARK ARTAUD
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/06/2015
Notification Time: 13:17 [ET]
Event Date: 02/06/2015
Event Time: 00:00 [PST]
Last Update Date: 02/06/2015
Notification Time: 13:17 [ET]
Event Date: 02/06/2015
Event Time: 00:00 [PST]
Last Update Date: 02/06/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
ROBERT HAAG (R2DO)
LAURA KOZAK (R3DO)
GEOFFREY MILLER (R4DO)
PART 21/50.55 REACT (EMAI)
ANNE DeFRANCISCO (R1DO)
ROBERT HAAG (R2DO)
LAURA KOZAK (R3DO)
GEOFFREY MILLER (R4DO)
PART 21/50.55 REACT (EMAI)
PART 21 REPORT - SHUTDOWN MARGIN MONITOR ENVIRONMENTAL QUALIFICATION NONCOMPLIANCE
The following is an excerpt of a report received from the vendor via email:
"A deviation has been identified in the SDMM supplied by Thermo Gamma-Metrics LLC. The SDMM will fail during conditions of simultaneous high temperature and high humidity less than the values reported in Qualification Test Report (QTR) 010. Testing has indicated the SDMM would not properly operate above a certain value of moisture content corresponding to a dew point of around 128øF. QTR 010 listed qualified temperature and humidity conditions corresponding to a dew point of around 136øF."
The vendor has issued a revised qualification test report which documents the revised qualified conditions for the affected SDMMs.
The following plants are potentially affected: ANO U2; Millstone U3; Prairie Island U1 & U2; Seabrook U1 & U2; South Texas U1 & U2; St. Lucie U1; Catawba U1 & U2; McGuire U1 & U2; Salem U1 & U2; Calvert Cliffs U1 & U2; Almaraz U1 & U2; Sequoyah U1 & U2; Watts Bar U1 & U2; Vogtle U1 & U2; Byron U1 & U2; Ringhals U2, U3 & U4.
The following is an excerpt of a report received from the vendor via email:
"A deviation has been identified in the SDMM supplied by Thermo Gamma-Metrics LLC. The SDMM will fail during conditions of simultaneous high temperature and high humidity less than the values reported in Qualification Test Report (QTR) 010. Testing has indicated the SDMM would not properly operate above a certain value of moisture content corresponding to a dew point of around 128øF. QTR 010 listed qualified temperature and humidity conditions corresponding to a dew point of around 136øF."
The vendor has issued a revised qualification test report which documents the revised qualified conditions for the affected SDMMs.
The following plants are potentially affected: ANO U2; Millstone U3; Prairie Island U1 & U2; Seabrook U1 & U2; South Texas U1 & U2; St. Lucie U1; Catawba U1 & U2; McGuire U1 & U2; Salem U1 & U2; Calvert Cliffs U1 & U2; Almaraz U1 & U2; Sequoyah U1 & U2; Watts Bar U1 & U2; Vogtle U1 & U2; Byron U1 & U2; Ringhals U2, U3 & U4.
Power Reactor
Event Number: 50792
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RYAN SEARS
HQ OPS Officer: DANIEL MILLS
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RYAN SEARS
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/06/2015
Notification Time: 16:53 [ET]
Event Date: 02/06/2015
Event Time: 12:27 [CST]
Last Update Date: 02/06/2015
Notification Time: 16:53 [ET]
Event Date: 02/06/2015
Event Time: 12:27 [CST]
Last Update Date: 02/06/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO LOSS OF FEEDWATER
"At 1227 CST on 06 Feb 2015, Dresden Unit 2 automatically scrammed due to a Reactor Water Level transient. Set up activities for weekend maintenance were being performed on the feedwater system at the time of the event.
"All rods inserted to their full-in positions.
"Systems operated as expected.
"Reactor vessel inventory and pressure are being maintained in normal control bands. The ultimate heat sink was maintained.
"The source of the transient was a loss of Feedwater Level Control and the reactor automatically scrammed on low reactor water level. Cause of the failure is under investigation. All three feed pumps tripped as a result of the transient. The 2B reactor feed pump was restored following the transient in accordance with station operating procedures. Level is being maintained with normal feedwater.
"High Pressure Coolant Injection initiated on a valid low-low reactor water level. Manual operator action was taken to prevent unneeded injection into the reactor coolant system.
"Group 2 Primary Containment and Group 3 Shutdown Cooling and Reactor Water Clean-up system isolations occurred as expected.
"Unit 2 and 2/3 [swing diesel] EDGs started as expected, but did not load onto their associated busses as offsite power was maintained."
The licensee has notified the NRC Resident Inspector.
"At 1227 CST on 06 Feb 2015, Dresden Unit 2 automatically scrammed due to a Reactor Water Level transient. Set up activities for weekend maintenance were being performed on the feedwater system at the time of the event.
"All rods inserted to their full-in positions.
"Systems operated as expected.
"Reactor vessel inventory and pressure are being maintained in normal control bands. The ultimate heat sink was maintained.
"The source of the transient was a loss of Feedwater Level Control and the reactor automatically scrammed on low reactor water level. Cause of the failure is under investigation. All three feed pumps tripped as a result of the transient. The 2B reactor feed pump was restored following the transient in accordance with station operating procedures. Level is being maintained with normal feedwater.
"High Pressure Coolant Injection initiated on a valid low-low reactor water level. Manual operator action was taken to prevent unneeded injection into the reactor coolant system.
"Group 2 Primary Containment and Group 3 Shutdown Cooling and Reactor Water Clean-up system isolations occurred as expected.
"Unit 2 and 2/3 [swing diesel] EDGs started as expected, but did not load onto their associated busses as offsite power was maintained."
The licensee has notified the NRC Resident Inspector.
Non-Agreement State
Event Number: 50793
Rep Org: MCLAREN MEDICAL CENTER - BAY REGION
Licensee: MCLAREN MEDICAL CENTER - BAY REGION
Region: 3
City: BAY CITY State: MI
County:
License #: 21-18585-01
Agreement: N
Docket:
NRC Notified By: MATT BUCZEK
HQ OPS Officer: DANIEL MILLS
Licensee: MCLAREN MEDICAL CENTER - BAY REGION
Region: 3
City: BAY CITY State: MI
County:
License #: 21-18585-01
Agreement: N
Docket:
NRC Notified By: MATT BUCZEK
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/06/2015
Notification Time: 18:39 [ET]
Event Date: 02/06/2015
Event Time: 08:00 [EST]
Last Update Date: 02/06/2015
Notification Time: 18:39 [ET]
Event Date: 02/06/2015
Event Time: 08:00 [EST]
Last Update Date: 02/06/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
LAURA KOZAK (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
JAMES RUBENSTONE (NMSS)
LAURA KOZAK (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
JAMES RUBENSTONE (NMSS)
MEDICAL MISADMINISTRATION DURING BRACHYTHERAPY
A patient underwent brachytherapy utilizing a vaginal cylinder. The prescribed dose was 5.5 Gray (550 rem) to the target volume, but due to mispositioning of the source, the target volume received only a negligible dose. The source was positioned such that the skin received a dose of up to 2.5 Gray (250 rem). The patient and prescribing physician have been notified. The patient is unlikely to suffer any permanent effects, but could experience mild erythema. The patient has been scheduled for an additional treatment. The hospital will take steps to prevent a future recurrence before the next patient is treated.
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.
A patient underwent brachytherapy utilizing a vaginal cylinder. The prescribed dose was 5.5 Gray (550 rem) to the target volume, but due to mispositioning of the source, the target volume received only a negligible dose. The source was positioned such that the skin received a dose of up to 2.5 Gray (250 rem). The patient and prescribing physician have been notified. The patient is unlikely to suffer any permanent effects, but could experience mild erythema. The patient has been scheduled for an additional treatment. The hospital will take steps to prevent a future recurrence before the next patient is treated.
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: 50794
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: RICHARD CHAMPLEY
HQ OPS Officer: VINCE KLCO
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: RICHARD CHAMPLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 02/07/2015
Notification Time: 07:37 [ET]
Event Date: 02/06/2015
Event Time: 23:55 [CST]
Last Update Date: 02/07/2015
Notification Time: 07:37 [ET]
Event Date: 02/06/2015
Event Time: 23:55 [CST]
Last Update Date: 02/07/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
LEAKAGE DETECTION SYSTEM INOPERABLE
"On 2/6/15 at 2300 (CST) the Division 1 Reactor Water Cleanup (RT) system differential flow instrument was declared inoperable due to erratic indication. The Division 1 RT differential flow instrument was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1. At time 2355 Division 2 RT differential flow instrument failed downscale and was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1 and also Technical Specification 3.3.6.1 Action E.1 (entered due to Division 1 RT differential flow already inoperable). Since this condition renders the Leakage Detection System incapable of performing its safety function, it is reportable under 10CFR50.72(b)(3)(v)(C). Division 1 RT differential flow was declared Operable at time 0036 on 2/7/15. Division 2 RT differential flow was restored to Operable at time 0225 on 2/07/2015.
"The NRC Resident [Inspector] has been notified."
"On 2/6/15 at 2300 (CST) the Division 1 Reactor Water Cleanup (RT) system differential flow instrument was declared inoperable due to erratic indication. The Division 1 RT differential flow instrument was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1. At time 2355 Division 2 RT differential flow instrument failed downscale and was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1 and also Technical Specification 3.3.6.1 Action E.1 (entered due to Division 1 RT differential flow already inoperable). Since this condition renders the Leakage Detection System incapable of performing its safety function, it is reportable under 10CFR50.72(b)(3)(v)(C). Division 1 RT differential flow was declared Operable at time 0036 on 2/7/15. Division 2 RT differential flow was restored to Operable at time 0225 on 2/07/2015.
"The NRC Resident [Inspector] has been notified."