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Event Notification Report for November 19, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/18/2014 - 11/19/2014

** EVENT NUMBERS **


50475 50523 50603 50622 50623 50624 50625

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Power Reactor Event Number: 50475
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/19/2014
Notification Time: 17:54 [ET]
Event Date: 09/19/2014
Event Time: 13:53 [CDT]
Last Update Date: 11/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BILLY DICKSON (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

UNANALYZED CONDITION DUE TO MISSING FIRE BARRIERS

"As part of an extent of condition review related to ENS report 50362 (Unanalyzed Condition Due to Lack of Appropriate Fuse Protection), it was identified that, within the past three years, three additional examples existed of missing fire barriers that could have impacted separation of redundant safe shutdown trains. For the affected areas associated with each of the three missing barriers, compensatory measures (hourly fire watches) had been in place for three years prior to the discovery of the condition. However, it was determined the missing barriers met the reporting criteria for 10 CFR 50.72(b)(3)(ii)(B) as unanalyzed conditions that significantly degraded plant safety.

"The first condition was the use of rodofoam material in Auxiliary Building seismic joint seals. Rodofoam is a combustible foam material and does not provide a fire rating equivalent to the barriers in which it was used. This issue was corrected in a plant modification.

"The second condition is the lack of required fire dampers in ventilation supply ducts to the Aux. Feedwater (AFW) Pump Rooms (Fire areas 31 and 32). An engineering change package has been approved to implement a plant modification to install the required dampers as part of the NFPA-805 transition.

"The third condition is a gap where the ventilation duct passes through the wall from the Bus 150/160 room into the AFW pump room. An engineering change package has been approved to implement a plant modification to correct this condition as part of the NFPA-805 transition.

"The protection of the health and safety of the public was not affected by this issue. In all cases, compensatory measures existed to ensure the protection of safe shutdown equipment.

"The licensee has notified the NRC Senior Resident Inspector."

* * * UPDATE FROM DOUG LARSON TO DANIEL MILLS AT 2122 EST ON 11/18/14 * * *

"Northern States Power Company (NSPM) has determined that the missing fire damper and the wall gap (the second and third identified conditions) are not separating redundant equipment and no longer meet the regulatory definition of an unanalyzed condition. This was identified when it was determined that the redundant pressurizer heater cables credited for safe shutdown were routed through the same fire area. This was reported under EN 50531 (Unanalyzed Condition Due To Missing Fire Barrier). Since the missing fire barrier does not separate redundant equipment, the condition does not degrade plant safety, and is no longer reportable.

"The protection of the health and safety of the public was not affected by this issue.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Peterson).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 50523
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/11/2014
Notification Time: 00:03 [ET]
Event Date: 10/10/2014
Event Time: 17:17 [CDT]
Last Update Date: 11/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
2 N Y 100 Power Operation 100 Power Operation

Event Text

MISSING FIRE BARRIER

"During a Fire Penetration walkdown, an opening less than 1 [inch] tall under a duct was identified between the Train B Aux Feedwater Pump (AFWP) Room (Unit 1 side) and the Bus150/160 room. This constitutes a missing fire barrier between Fire Area (FA) 32 and FA 37 such that the required degree of separation for redundant safe shutdown trains is lacking.

"A firewatch has been established on the Unit 1 side of the AFWP Room and Bus 150/160 room. The compensatory fire watch will remain in place per F5 Appendix K until the fire barrier is returned to full functional status.

"The discovery of this non-compliance is being reported as an unanalyzed condition as defined by 10CFR50.72(b)(3)(ii)(B).

"The protection of the health and safety of the public was not affected by this issue.

"The licensee has notified the NRC Resident Inspector of this event."

* * * RETRACTION FROM DOUG LARSON TO DANIEL MILLS AT 2118 EST ON 11/18/2014 * * *

"Northern States Power Company (NSPM) has determined that the opening under the duct is not separating redundant equipment and no longer meets the regulatory definition of an unanalyzed condition. This was identified when it was determined that the redundant pressurizer heater cables credited for safe shutdown were routed through the same fire area. This was reported under EN 50531 (Unanalyzed Condition Due To Missing Fire Barrier). Since the missing fire barrier does not separate redundant equipment, the condition does not degrade plant safety, and is no longer reportable.

"The protection of the health and safety of the public was not affected by this issue.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Peterson).

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Non-Agreement State Event Number: 50603
Rep Org: PARKVIEW HEALTH
Licensee: PARKVIEW HEALTH
Region: 3
City: FORT WAYNE State: IN
County:
License #: 13-01284-02
Agreement: N
Docket:
NRC Notified By: YUENIAN ZHANG
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/11/2014
Notification Time: 16:25 [ET]
Event Date: 11/11/2014
Event Time: [EST]
Last Update Date: 11/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
Person (Organization):
DAVID HILLS (R3DO)
FSME EVENTS RESOURCE (EMAI)
NMSS EVENTS RESOURCE (EMAI)

Event Text

GYNECOLOGICAL BRACHYTHERAPY TREATMENT TO LARGER AREA THAN PRESCRIBED AREA

A patient was prescribed four 550 cGy gynecologic brachytherapy treatments totaling 2200 cGy. The third treatment prescribed a treatment area of 5 cm instead of the actual treated area of 7 cm. The patient was released after the outpatient treatment. The hospital in attempting to notify the physician of the incident.

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: 50622
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DEREK DROCKELMAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/18/2014
Notification Time: 13:29 [ET]
Event Date: 11/18/2014
Event Time: 09:00 [CST]
Last Update Date: 11/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
HIRONORI PETERSON (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT INTERLOCK DOORS OPEN SIMULTANEOUSLY

"On November 18, 2014, at 0900 [CST], the Shift Manager was notified that two Secondary Containment interlock doors were open simultaneously. The doors were immediately closed and Secondary Containment pressure remained negative throughout the event.

"This condition represents a failure to meet Surveillance Requirement 3.6.4.1.2 given two doors in a single access opening were open. As a result entry into Technical Specification 3.6.4.1, Condition A, was made momentarily due to Secondary Containment being inoperable.

"This event is reportable under 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

The State of Illinois has been notified.

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Part 21 Event Number: 50623
Rep Org: TECHNOLOGY FOR ENERGY CORP.
Licensee: TECHNOLOGY FOR ENERGY CORP.
Region: 1
City: KNOXVILLE State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DONNA MULLALY
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/18/2014
Notification Time: 15:09 [ET]
Event Date: 11/18/2014
Event Time: [EST]
Last Update Date: 11/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
TODD JACKSON (R1DO)
FRANK EHRHARDT (R2DO)
HIRONORI PETERSON (R3DO)
BOB HAGAR (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 - LACK OF PROPER POWER SUPPLY INDICATION

The following information was summarized from the report obtained from the vendor via facsimile:

Technology for Energy Corporation [TEC] has determined that the Model 1414 Valve Flow Monitoring Systems power supply may not provide proper output voltage contrary to power supply status indicators on the rack. This may result in the power supply not providing necessary power to its associated input sensor. A subsequent loss of the sensor output would result in the inability of the system to indicate any valve flow. Depending on the specific configuration, signals from more than one sensor could be lost on a single failure.

This Model 1414 system design dates back to 1979. TEC has not been made aware of any instances of the described failure mode in the 35 year history of the product design, suggesting that the robustness of power supply design and the users periodic maintenance of the system has provided for acceptable continued operation.

The potentially affected plants include Clinton Unit 1; Comanche Peak Units 1 & 2; Nine Mile Point Unit 2; Palo Verde Units 1, 2, & 3; River Bend Unit 1; Susquehanna Units 1 & 2; Watts Bar Units 1 & 2.

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Power Reactor Event Number: 50624
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JAY VANHULZEN
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/18/2014
Notification Time: 19:25 [ET]
Event Date: 11/17/2014
Event Time: 06:08 [EST]
Last Update Date: 11/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
FRANK EHRHARDT (R2DO)

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

Event Text

EMERGENCY SIREN MALFUNCTION

"On November 17, 2014, Miami Dade County notified the site of an alarming single Emergency Plan siren. Following this notification from the County, a courtesy ENS Notification was made to the NRC Operations Center and the State of Florida State Warning Point. The siren has been repaired and returned to service. At no time was there an emergency requiring the siren activation. FPL [Florida Power and Light] did not issue a news release.

"This notification is made in accordance with 10 CFR 50.72(b)(2)(xi) for notification to 'other government agencies.'

"The NRC Senior Resident has been notified."

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Power Reactor Event Number: 50625
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/19/2014
Notification Time: 03:39 [ET]
Event Date: 11/18/2014
Event Time: 19:00 [CST]
Last Update Date: 11/19/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BOB HAGAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby

Event Text

UNANALYZED CONDITION DUE TO ALL FOUR SAFETY INJECTION ACCUMULATORS INOPERABLE

"Following shift turnover from days to nights on 11/18/2014, it was discovered that all (4) of the Safety Injection (SI) Accumulator Outlet Isolation Valve breakers were unlocked and closed. At the time of discovery, 3 of the safety injection accumulator valves were open and 1 was closed for testing. At that time the plant was in MODE 3 at normal operating pressure and temperature. The plant had been performing RCS pressure isolation valve testing prior to shift turnover. The condition was discovered during testing of valves associated with the 'C' safety injection accumulator.

"After discovery of the condition, Operations directed that the 'A', 'B', and 'D' SI Accumulator Outlet Isolation Valve breakers be opened and locked. This action was completed by approximately 1930 [CST] on 11/18/2014.

"The NRC Resident Inspector was notified."

The plant entered T.S. 3.0.3 for approximately 30 minutes while restoring the 'A', 'B' and 'C' accumulators to operable (breakers opened and locked with their associated outlet valves open).

Page Last Reviewed/Updated Wednesday, November 19, 2014
Wednesday, November 19, 2014