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Event Notification Report for March 16, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/13/2015 - 03/16/2015

** EVENT NUMBERS **


50752 50867 50868 50882 50883 50884 50885 50887 50888 50889 50890 50891
50893 50894 50895 50896

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Power Reactor Event Number: 50752
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: JEFF HERRERA
Notification Date: 01/22/2015
Notification Time: 18:51 [ET]
Event Date: 01/22/2015
Event Time: 17:45 [EST]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

UNANALYZED HEAT EXCHANGER LINEUP COULD EXCEED DESIGN BASIS TEMPERATURES

"On 1/20/15, it was determined that a certain line up of component cooling heat exchangers and shutdown cooling heat exchangers could exceed the design basis temperatures for the component cooling water system following a design basis accident. Although not a safety concern at this time because of low ultimate heat sink temperatures (which cools component cooling water), in the past the ultimate heat sink temperatures have been high enough to create this condition. This particular heat exchanger line up was unanalyzed in that the ultimate heat sink temperature limits were not known until 1/22/15. This issue has been entered into the corrective action program.

"A review of Control Room logs for 2014 showed that in 1 instance for Unit 1 and 1 instance for Unit 2, the Units were in an unanalyzed lineup with ultimate heat sink temperature greater than the maximum now calculated. During these instances, both Units had an unanalyzed condition that had potential to significantly degrade plant safety and is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B).

"The NRC Resident Inspector has been notified."

* * * RETRACTED ON 03/03/15 AT 1410 EST FROM CHARLES MORGAN TO JEFF HERRERA * * *

"Further engineering analysis has refined the ultimate heat sink temperature that provides an acceptable safety system response with the component cooling water and shutdown cooling heat exchanger lineups in question. The revised information demonstrates that the system lineups that occurred in the last 12 months did not result in an unanalyzed condition that significantly degrades plant safety. This event notification is retracted."

The NRC Resident Inspector will be notified.

The R1DO (Burritt) was notified.

* * * UPDATE ON 03/12/15 AT 1303 EDT FROM ED SCHINNER TO DANIEL MILLS * * *

"The retraction statement provided on 3/3/15 incorrectly addressed system lineups limited to the last 12 months. The original withdrawal was prematurely submitted and therefore the original notification (Event report 50752) is not retracted and remains valid.

"The NRC Resident Inspector has been notified."

The R1DO (Cook) was notified.

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Agreement State Event Number: 50867
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: DESERT NDT
Region: 4
City: ELK CITY State: OK
County:
License #: OK-32101.01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/05/2015
Notification Time: 15:42 [ET]
Event Date: 03/05/2015
Event Time: [CST]
Last Update Date: 03/05/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO ASSISTANT RADIOGRAPHER

The following information was obtained from the State of Oklahoma via email:

"We [Oklahoma Department of Environmental Quality] have been notified by Desert NDT (OK-32104-01) located in Elk City, OK, that the dosimetry report for the February 2015 monitoring period showed a dose of 5780 mR for one of their assistant radiographers. They also report that the individual's daily pocket dosimetry readings for this period do not correlate with this result. The investigation is ongoing."

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Agreement State Event Number: 50868
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: LEGACY GOOD SAMARITAN MEDICAL CENTER
Region: 4
City: PORTLAND State: OR
County:
License #: ORE-91155
Agreement: Y
Docket:
NRC Notified By: DARYL LEON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/05/2015
Notification Time: 17:38 [ET]
Event Date: 03/04/2015
Event Time: [PST]
Last Update Date: 03/05/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - POTENTIAL MEDICAL EVENTS DUE TO A MISALIGNED GAMMA KNIFE

On March 4, 2015, the licensee notified the State of Oregon that they discovered that their Elekta Leksell Gamma Knife was off target by approximately 1.87mm. This was allegedly due to maintenance performed in early January 2015, that resulted in a misaligned couch. Since the misalignment, eight patients have undergone gamma knife surgery. The licensee Medical Physicist is currently evaluating each case to determine whether an underdose/overdose occurred to any of the patients.

The Elekta Leksell Gamma Knife is licensed for up to 6.6 kCi of Co-60.

The State of Oregon will update this report as more information becomes available.

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: 50882
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: AL MEURS
HQ OPS Officer: VINCE KLCO
Notification Date: 03/13/2015
Notification Time: 08:43 [ET]
Event Date: 03/13/2015
Event Time: 01:00 [CDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
STEVE ORTH (R3DO)

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

Event Text

FUEL ASSEMBLY MIS-ORIENTED RESULTING IN A UNANALYZED CONDITION

"On March 13, 2015 at 0100 [CDT], it was identified that fuel assembly QAD224 was mis-oriented 180 degrees at core location 51-40. The intended orientation was [southeast]. However the assembly was identified as being [northwest]. This issue was identified during the core verification process. In the current core configuration, there is not a bounding analysis that assures adequate Shutdown Margin.

"This event is reportable under 50.72(b)(3)(ii) as an unanalyzed condition that significantly degraded plant safety.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 50883
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: STEVEN CARTER
HQ OPS Officer: VINCE KLCO
Notification Date: 03/13/2015
Notification Time: 11:17 [ET]
Event Date: 03/12/2015
Event Time: 19:13 [CDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
NEIL OKEEFE (R4DO)

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

Event Text

POSITIVE RANDOM FITNESS FOR DUTY TEST

"A licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 50884
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/13/2015
Notification Time: 12:48 [ET]
Event Date: 03/13/2015
Event Time: 09:28 [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SCOTT SHAEFFER (R2DO)

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

Event Text

OFFSITE NOTIFICATION TO OSHA DUE TO ONSITE PLANT EMPLOYEE PASSING AWAY

"On March 13, 2015 at 0928 EDT, a notification to OSHA [Occupational Safety and Health Administration] was initiated due to an employee experiencing a non-work related medical event that resulted in the employee passing. When the issue was identified, the station first aid team responded to administer first aid. Subsequent to the employee passing, a report was made to OSHA in accordance with federal requirements. This event is reportable to the NRC per 10 CFR 50.72(b)(2)(xi) since another governmental agency was notified of this employer referral medical event."

The plant employee was in a building within the protected area and was not contaminated.

The licensee notified the NRC Resident Inspector and will notify the local government of the event.

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Power Reactor Event Number: 50885
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID DUTTRY
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/13/2015
Notification Time: 12:56 [ET]
Event Date: 03/13/2015
Event Time: 09:19 [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
WILLIAM COOK (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF SECONDARY CONTAINMENT DUE TO VENTILATION PLENUM DOOR OPEN

"On March 13, 2015 at 0919 [EDT], Secondary Containment became inoperable, requiring a Technical Specification 3.6.4.1 entry for failure to meet SR [Surveillance Requirement] 3.6.4.1.1 on Unit 1 and Unit 2.

"The inoperability was caused by Zone 2 differential pressure lowering to less than 0.25 inches WC [water column] when an air handling plenum door was opened for an extended period.

"The plenum door was closed and differential pressure restored to greater than 0.25 inches WC at 0930 on March 13, 2015.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev. 3 Section 3.2.7, as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50887
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HENRY TAYLOR
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/13/2015
Notification Time: 14:25 [ET]
Event Date: 03/13/2015
Event Time: 11:00 [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
SCOTT SHAEFFER (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

UNANALYZED CONDITION

"On March 13, 2015, Watts Bar determined that information received from Westinghouse represented an unanalyzed condition. The information challenged the current Unit 1 Fire Protection Report (FPR) analysis for 10 CFR 50 Appendix R. The current FPR analysis used a duration of 120 seconds before a low pressurizer pressure safety injection (SI) signal would be received due to a postulated failed open pressurizer power operated relief valve (PORV) from an Appendix R fire outside of the control building. During discussions with Westinghouse, Watts Bar determined that the 120 second value was non-conservative and not intended for this application. Recent information from Westinghouse indicates that a Sl signal would be received in approximately 34 seconds.

"This information places Watts Bar Unit 1 in an unanalyzed condition because the original analysis assumed that a Sl signal would not be received from fire-induced failures in the associated fire areas. While the existing Watts Bar Unit 1 Appendix R procedures direct operators to isolate the pressurizer PORV, the procedures did not have steps to mitigate and terminate the Sl. Without mitigating actions, the Sl would likely challenge the reactor coolant system boundary due to water relief through the remaining pressurizer PORV and/or safety valves.

"As a compensatory measure, Watts Bar has established administrative equipment controls to preclude the consequences of a spuriously opening pressurizer PORV. In addition, a compensatory measure in the form of fire watches has been established in areas where a fire could result in a spurious opening of a pressurizer PORV.

"This issue is being reported under 10 CFR 50.72(b)(3)(ii)(B), 'unanalyzed condition that significantly degrades plant safety.'

"The Watts Bar Resident Inspector has been notified."

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Part 21 Event Number: 50888
Rep Org: WEIR VALVES AND CONTROLS USA INC.
Licensee: WEIR VALVES AND CONTROLS USA INC.
Region: 1
City: IPSWITCH State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ARTHUR BUTTERS
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/13/2015
Notification Time: 15:48 [ET]
Event Date: 03/13/2015
Event Time: [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
STEVE ORTH (R3DO)
PART 21/50.55 REACT (EMAI)

Event Text

IMPROPER WELD USED ON GATE VALVE COVER

The following was received from the licensee via email:

"This notification is being submitted pursuant to the guidelines of 10 CFR Part 21 to report that, during the manufacturing of a replacement cover for a 24 inch gate valve on the reactor recirc line at Exelon LaSalle, Weir Valves and Controls used a weld that was not compliant to ASME Ill Subsection NB requirements.

"During review of the weld at site, the question was raised based on site procedures required a 2:1 profile in accordance to EPRI guidelines. During review of the documentation to determine if the 2:1 profile was required in this case, Weir Valves and Controls determined that improper weld call out was used on the design prints. The weld was corrected at site to meet the both ASME Ill Subsection NB requirements and EPRI guidelines.

"Weir Valves and Controls has performed an extent condition review and has concluded that no other undersized welds were made and delivered to any other operating sites.

"The root-cause of the issue was the improper call-out of the weld by design engineering.

"Weir Valves and Controls is performing corrective actions to ensure future re-occurrences cannot occur in design engineering."

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Power Reactor Event Number: 50889
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/13/2015
Notification Time: 17:08 [ET]
Event Date: 03/13/2015
Event Time: 10:34 [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
WILLIAM COOK (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

PLANT EMPLOYEE TESTED POSITIVE FOR BANNED SUBSTANCE

A non-licensed corporate employee tested positive for a banned substance. The individual's unescorted access has been revoked.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50890
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SUSAN HOLTH
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/13/2015
Notification Time: 17:12 [ET]
Event Date: 03/13/2015
Event Time: 11:08 [EDT]
Last Update Date: 03/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
SCOTT SHAEFFER (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
2 N N 0 Defueled 0 Defueled

Event Text

POSITIVE RANDOM FITNESS FOR DUTY TEST RESULT

A contract employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50891
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TERRY BRANDT
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/13/2015
Notification Time: 18:59 [ET]
Event Date: 03/13/2015
Event Time: 12:30 [CDT]
Last Update Date: 03/14/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ORTH (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

LOW PRESSURE COOLANT INJECTION DECLARED INOPERABLE

"This condition is reported in accordance with 10 CFR 50.72(b)(3)(v). On 3/12/15, during surveillance testing on LPCI [Low Pressure Coolant Injection] Loop Select Instrumentation, a degraded component was discovered. At 1230 CDT on 3/13/15, LPCI was declared INOPERABLE in accordance with Technical Specification requirements. All remaining ECCS systems remain available and operable.

"The NRC Resident Inspector has been informed."

* * * UPDATE AT 0210 EDT ON 03/14/15 FROM SCOTT AREBAUGH TO S. SANDIN * * *

"At 0105 CDT on 3/14/15, the subject component has been replaced and retested with satisfactory results. LPCI INOPERABLE condition was exited at 0105 CDT and the LPCI System is OPERABLE."

The licensee informed the NRC Resident Inspector. Notified R3DO (Orth).

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Power Reactor Event Number: 50893
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT FRECK
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/14/2015
Notification Time: 08:07 [ET]
Event Date: 03/14/2015
Event Time: 04:29 [EDT]
Last Update Date: 03/14/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
SCOTT SHAEFFER (R2DO)
MARY JANE ROSS-LEE (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP ON SYSTEM INJECTION ACTUATION SIGNAL

"Vogtle Unit 2 was operating in Mode 1 at 100% rated thermal power. At 0429 EDT a Unit 2 automatic Reactor Trip and Safety Injection / Steamline Isolation occurred. All systems operated as expected and all control rods fully inserted. The Safety Injection was terminated at 0447 EDT and the emergency operating procedures were exited at 0522 EDT. Unit 2 is stable in Mode 3 with decay heat removal via the Auxiliary Feedwater system and the atmospheric relief valves. A response team is investigating the cause of the event. Unit 1 was unaffected by the event.

"NRC Senior Resident Inspector was notified and is at plant site for investigation."

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Power Reactor Event Number: 50894
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN LOWE
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/14/2015
Notification Time: 19:19 [ET]
Event Date: 03/14/2015
Event Time: 12:07 [EDT]
Last Update Date: 03/14/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
SCOTT SHAEFFER (R2DO)

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

Event Text

UNPLANNED ACTUATION DURING SURVEILLANCE TEST

"On March 14, 2015 at 1207 EDT, operators were performing steps to disable an automatic actuation signal to the B-train Auxiliary Feedwater system (AFW), when a valid actuation signal was received on B-train only. Both motor driven Auxiliary Feedwater pumps were already running and feeding forward. The B-train discharge valves went from throttled to fully open. The AFW discharge valves were restored to their previous positions without any adverse impacts on the plant. Decay heat removal was still being removed through the Atmospheric Relief Valves."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50895
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MARK PHILLIPS
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/14/2015
Notification Time: 23:32 [ET]
Event Date: 03/14/2015
Event Time: 17:08 [EDT]
Last Update Date: 03/14/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WILLIAM COOK (R1DO)

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

DIGITAL RADIATION MONITORING SYSTEM FAILED

"At 1708 EDT on March 14, 2015, Beaver Valley Power Station (BVPS) Unit 2 determined that the Digital Radiation Monitoring System (DRMS) was not operating. This resulted in a loss of radiation monitor capability to alarm and indicate in the control room. BVPS Unit 2 DRMS was declared non-functional. Repair efforts were initiated and compensatory measures were initiated.

"The radiation monitoring computer system is a stand-alone system. No cyber interference is suspected.

"At 2056 EDT on March 14, 2015, following initial investigation and repairs, BVPS Unit 2 emergency assessment capability was restored in conjunction with DRMS restoration.

"Since the BVPS Unit 2 DRMS was non-functional, this event resulted in a loss of emergency assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii).

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 50896
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/15/2015
Notification Time: 13:29 [ET]
Event Date: 03/15/2015
Event Time: 12:27 [EDT]
Last Update Date: 03/15/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
WILLIAM COOK (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 60 Power Operation 55 Power Operation

Event Text

PLANT SHUTDOWN DUE TO FAILURE TO RESTORE CONTAINMENT FAN COOLER UNIT

"This 4 hour notification is being made pursuant to the requirements of 10 CFR 50.72(b)(2)(i), for 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications'.

"Salem Unit 1 has initiated a unit shutdown at 1227 [EDT] in accordance with Technical Specification Action Statement 3.6.2.3, Action A, for inoperability of the 14 Containment Fan Cooler Unit. Technical Specification 3.6.2.3, Action A requires that with one or two Containment Fan Cooler Units inoperable, operability must be restored within 7 days, or be in at least Hot Standby (Mode 3) within the next 6 hours and in Cold Shutdown (Mode 5) within the following 30 hours.

"The 14 Containment Fan Cooler Unit was declared inoperable on March 8, 2015, at 1158 EDT, following a trip of its low speed breaker on thermal overload during a scheduled surveillance test.

"13 Chiller is tagged for scheduled maintenance.

"The NRC Resident Inspector has been notified."

Unit 1 is proceeding to Mode 5. There is no effect on Unit 2.

The licensee will notify the Lower Alloways Creek Township, the State of New Jersey, and the State of Delaware.

Page Last Reviewed/Updated Monday, March 16, 2015
Monday, March 16, 2015