| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/24/2014 - 02/25/2014 ** EVENT NUMBERS ** |
 | 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: 02/24/2014 | 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
* * * UPDATE AT 1110 EST ON 02/24/14 FROM CHRISTIAN RHEAULT TO S. SANDIN VIA FAX * * *
The following updated information was received from C&D Technologies:
"Subject: Updated Interim Report - Inability to Complete 10CFR Part 21 Evaluation regarding cracking in KCR-13 Standby Battery Jars
"As previously stated, 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 until a final report Is issued by Lucius Pitkin. Although several requests to both Indian Point and Lucius Pitkin have been made, a receipt date for the analysis results is still indeterminate."
If you have any questions or wish to discuss this matter or this report, please contact:
Robert Malley
VP Quality and Process Engineering
Office Phone 215-619-7830
Email bmalley@cdtechno.com
Notified R1 (DeFrancisco), R3DO (Kunowski) and Part 21 Group (via email). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49828 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: NICK BUEHLER
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/14/2014
Notification Time: 11:14 [ET]
Event Date: 02/14/2014
Event Time: 03:25 [EST]
Last Update Date: 02/24/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Defueled | 0 | Defueled | Event Text SHIELD BUILDING CONSTRUCTION OPENING
"On 02/14/2014, an unfilled area was discovered in the concrete along the top of the shield building construction opening on the annulus side. The condition was discovered during the current steam generator replacement outage, and is likely due to not completely repouring the shield building wall opening in 2011. Analysis shows this condition is bounded by previous calculations that demonstrate the containment function is maintained such that the protection of the health and safety of the public was not in question. Further analysis is planned to reconfirm previous calculations.
"The NRC Resident Inspector has been notified."
* * * RETRACTION FROM ROBERT OESTERLE TO VINCE KLCO ON 2/24/14 AT 1650 EST * * *
"The FirstEnergy Nuclear Operating Company is retracting the 8-hour non-emergency notification made on 02/14/2014 (EN# 49828).
"Engineering evaluation of the unfilled concrete area along the top of the shield building construction opening determined the condition did not prevent the shield building from performing all design functions as described in the Updated Safety Analysis Report. Therefore, this issue did not represent a condition that significantly degraded plant safety, and the notification made per 10CFR 50.72(b)(3)(ii)(B) is being retracted.
"The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction."
Notified the R3DO (Kunowski). |
| Fuel Cycle Facility | Event Number: 49848 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: VINCE KLCO | Notification Date: 02/21/2014
Notification Time: 15:45 [ET]
Event Date: 02/21/2014
Event Time: 08:39 [EST]
Last Update Date: 02/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
MICHELE SAMPSON (NMSS)
FUELS GROUP by email ()
| Event Text AUDIBILITY OF ALARM SYSTEM
"A report was made to the facility Corrective Action Program (PIRCS) at 0839 [EST] on 2/21/2014 regarding difficulty hearing plant announcements and alarms in the recently renovated Building 110B restroom. Testing of the Public Address (PA) system confirmed that the PA system was difficult to hear. The speakers associated with the PA system are also used for annunciating the site criticality accident alarm evacuation warning. Subsequent testing of the criticality evacuation alarm indicated the alarm was difficult to hear as well. Safety management personnel were notified of the problem and the restroom was locked and posted with signs indicating the area was not to be occupied, pending resolution of the audibility issue.
"The licensee notified the NRC Resident Inspector." | |