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Event Notification Report for December 23, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/20/2013 - 12/23/2013

** EVENT NUMBERS **


49563 49645 49661 49666 49667 49671

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Power Reactor Event Number: 49563
Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KELLY BAKER
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/20/2013
Notification Time: 17:04 [ET]
Event Date: 11/20/2013
Event Time: 20:00 [EST]
Last Update Date: 12/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID HILLS (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

LOSS OF EMERGENCY PREPAREDNESS CAPABILITIES DUE TO UNIT 2 PLANT PROCESS COMPUTER REPLACEMENT

"The Unit 2 DC Cook Nuclear Plant (CNP) Plant Process Computer (PPC) will be removed from service on Wednesday, November 20, 2013 at 2000 [EST] to support planned replacement. The Unit 2 PPC, including the Emergency Response Data System (ERDS), will be unavailable to the NRC Operations Center. Planned replacement also affects the Safety Parameter Display System (SPDS), the Real Time Data Repository (RDR), and PPC data to emergency response facilities at CNP. Safety system annunciators and indications in the control room remain available.

"The scheduled replacement, returning of equipment to service and post maintenance testing is expected to be completed by 1400 on Sunday, December 22, 2013.

"Compensatory measures exist within the DC Cook emergency response procedures to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.

"The licensee has notified the NRC Resident Inspector.

"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)."


* * * UPDATE FROM DAN KURTH TO DONALD NORWOOD AT 1535 EST ON 12/21/2013 * * *

"The Unit 2 DC Cook Nuclear Plant (CNP) Plant Process Computer (PPC) has been restored to service as of Saturday, December 21, 2013 at 1046 EST. The Unit 2 PPC, including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Real Time Data Repository (RDR), and PPC data to the Emergency Response Facilities at CNP have been restored to normal operation. No further compensatory actions required.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Riemer).

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Power Reactor Event Number: 49645
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JASON LOVEGREN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/17/2013
Notification Time: 15:25 [ET]
Event Date: 12/17/2013
Event Time: 11:33 [PST]
Last Update Date: 12/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (R4DO)

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

REACTOR BUILDING STACK RADIATION MONITOR INOPERABLE DUE TO SCHEDULED MAINTENANCE ON SUPPORTING EQUIPMENT

"At 1133 PST on December 17, 2013, the Reactor Building Stack Radiation Monitor - Intermediate Range detector was declared non-functional due to scheduled maintenance on supporting equipment. Preplanned compensatory actions have been initiated.

"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). A follow up notification will be made when the equipment has been returned to service.

"The licensee has notified the NRC Resident Inspector."

* * * UPDATE FROM RUSSELL LONG TO DONG PARK AT 1912 EST ON 12/21/13 * * *

"At 1457 [PST] on December 21, 2013, the Reactor Building Stack Radiation Monitor - Intermediate Range detector was declared functional following scheduled maintenance on supporting equipment. Emergency assessment capability has been restored. Preplanned compensatory actions have been secured.

"The licensee has notified the NRC Resident Inspector."

Notified the R4DO (Werner).

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Power Reactor Event Number: 49661
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: GREG KNUDSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/19/2013
Notification Time: 12:58 [ET]
Event Date: 12/19/2013
Event Time: 08:38 [PST]
Last Update Date: 12/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (R4DO)

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

BOTH DIVISIONS OF PRIMARY CONTAINMENT OXYGEN AND HYDROGEN ATMOSPHERIC MONITORS INOPERABLE FOR MAINTENANCE

"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0838 PST on 12/19/2013, the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was removed from service for planned maintenance activities. The Division 1 sample rack is expected to be out of service for 14 hours. The redundant Division 2 sample rack was previously removed from service for maintenance and remains out of service for repairs. Compensatory measures to monitor primary containment for hydrogen and oxygen are available via grab samples using chemistry procedures.

"The NRC Resident Inspector has been notified."

* * * UPDATE FROM QUOC VO TO VINCE KLCO AT 0130 EST ON 12/20/13 * * *

"Following completion of surveillance activities, the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was returned to operable status at 2114 PST on 12/19/2013, restoring its required emergency assessment capability.

"The NRC Resident Inspector has been notified."

Notified the R4DO (Lantz).

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Power Reactor Event Number: 49666
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT J. LANE
HQ OPS Officer: VINCE KLCO
Notification Date: 12/20/2013
Notification Time: 11:23 [ET]
Event Date: 12/19/2013
Event Time: 22:33 [CST]
Last Update Date: 12/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RYAN LANTZ (R4DO)

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

VALID ACTUATION OF MAIN STEAM ISOLATION VALVES THAT WAS NOT PART OF A PREPLANNED SEQUENCE

"While in Mode 3 in preparing the Unit 2 secondary plant for startup, conditions occurred where it became necessary to break vacuum on the main condenser. Procedures directed closing of the main steam isolation valves. Instead of shutting each main steam isolation valve individually, a manual main steam isolation actuation was initiated through the solid state protection system (SSPS) to close the valves. This actuation of SSPS was a valid signal. The actuation was not part of a preplanned sequence.

"This notification is supported by the guidance of NUREG-1022, Revision 3, 'Event Reporting Guidelines 10CFR50.72 and 50.73.' In part, the guidance states: 'The Commission is interested in both events in which a system was needed to mitigate the consequences of an event (whether or not the equipment performed properly) and events in which a system actuated unnecessarily.'

"The manual actuation was not initiated to mitigate the consequences of an actual event. However, the method of closing the main steam valves for this condition did not specifically require that the valves should be closed by initiating a main steam isolation signal and therefore, the safety system was unnecessarily actuated.

"Therefore, this notification is being made pursuant to 10 CFR 50.72(b)(3)(iv)(A) as an event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) that was not part of preplanned sequence during testing or reactor operation. The system listed in paragraph (b)(3)(iv)(B) is (2) main steam isolation valves."

The licensee notified the NRC Resident Inspector.

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Part 21 Event Number: 49667
Rep Org: C&D TECHNOLOGIES, INC.
Licensee: C&D TECHNOLOGIES, INC.
Region: 1
City: BLUE BELL State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CHRISTIAN RHEAULT
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/20/2013
Notification Time: 11:45 [ET]
Event Date: 10/22/2013
Event Time: [EST]
Last Update Date: 12/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
KENNETH RIEMER (R3DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 REPORT - CRACKING IN KCR-13 STANDBY BATTERY JARS

The following was received via facsimile:

"The purpose of this letter is to provide the NRC a report in general conformity to the requirements of 10CFR Part 21.21 (a)(2). On October 22, 2013, C&D Technologies, Inc. (C&D) was informed by Entergy Nuclear Northeast that a KCR-13 battery installed at the Indian Point Nuclear Energy Center had developed a small crack in the polycarbonate jar material. The jar is a safety related component with the primary function of containing electrolyte. C&D does not believe that significant quantity of electrolyte was lost through this crack, because there was a normal level of electrolyte in the battery. This unit has been replaced, and the unit was sent by Entergy to an outside lab, Lucius Pitkin (LPI) of New York, NY, for analysis. As C&D did not have access to the components of the allegedly defective battery, and a report has not yet been issued by Lucius Pitkin, C&D cannot perform a root cause technical evaluation and affirm whether there is any defect in the component or manufacturing process, or whether the reported condition may have been due to user abuse of product, improper maintenance or other negligence or error. No formal report from Entergy or LPI Is expected before the expiration of the 60 day limit from the date C&D was notified of the issue. Thus, C&D is submitting this interim report to the NRC and notifying C&D's customers that use C&D KCR-13 batteries of this interim report. [C&D is also] initiating an action plan to evaluate the reported potential defect and determine whether it could pose a substantial safety hazard for any U.S. licensee using such batteries.

"Concurrent actions underway to complete the evaluation: a) On receipt of the final report by LPI/Indian Point by C&D, C&D shall evaluate the findings and the causes for failure. Maximum time 14 days from receipt of the report. b) In conjunction with the licensees identified in section vi, C&D will recommend maintenance assessment of all KCR-13 batteries at these locations to determine their status, and specifically the presence of any evidence of potential defects via visual examination. For any cells exhibiting the presence of potential defect, C&D shall further recommend that they be returned for analysis. Estimated completion date of analysis is thirty (30) days from the receipt of the returned batteries."

KCR-13 batteries are used in Indian Point and Monticello Nuclear Plants.

For further information contact:
Robert Malley
VP Quality and Process Engineering
Office Phone 215-619-7830
Email bmalley@cdtechno.com

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Power Reactor Event Number: 49671
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/20/2013
Notification Time: 20:10 [ET]
Event Date: 12/20/2013
Event Time: 13:03 [EST]
Last Update Date: 12/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANTHONY DIMITRIADIS (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

BOTH CONTROL ROOM AIR CONDITIONING SUBSYSTEMS INOPERABLE

"While the B control room chiller was out of service for planned maintenance, the A control room chiller was manually secured due to excessive fluctuations in load and running current. TS 3.7.2.2 Action a.2 was entered at 1303 [EST] for both control room air conditioning subsystems inoperable. Control room temperature is being maintained below the TS limit of 90 degrees F.

"The required TS Action is to restore one control room AC subsystem to operable status within 72 hours."

The licensee will notify the NRC Resident Inspector and the Lower Alloways Creek township.

* * * UPDATE ON 12/20/13 AT 2234 EST FROM JOHN PANAGOTOPULOS TO DONG PARK * * *

The B control room chiller was returned to service at 2120 EST. The A control room chiller remains out of service resulting in a 30-day TS LCO.

Notified R1DO (Dimitriadis).

Page Last Reviewed/Updated Monday, December 23, 2013
Monday, December 23, 2013