| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/09/2014 - 05/12/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49658 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: DOMTAR A.W., LLC
Region: 4
City: ASHTOWN State: AR
County:
License #: ARK-0354-0312
Agreement: Y
Docket:
NRC Notified By: KAYLA AVERY
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/18/2013
Notification Time: 17:06 [ET]
Event Date: 12/18/2013
Event Time: [CST]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MULTIPLE STUCK SHUTTERS AT A PAPER MILL PLANT
The following report was received via email:
"The following are the preliminary findings of the Arkansas Department of Health, Radioactive Materials Program, involving multiple stuck shutters at a paper mill plant.
"An onsite inspection of this licensee was conducted on December 17, 2013. During this inspection, it was discovered that since 2008, multiple shutters were found to have been stuck open and were not able to be locked out. Based on the records reviewed at the time of inspection, it appears that there were a total of 17 gauges with stuck shutters since May 2010. It appears at this time that all but nine (9) of these gauges have been repaired, dismounted and/or disposed. Currently, these nine gauges (9) are still in use with the shutters stuck in the open position. In accordance with RH-1502.f.2. (equivalent 10 CFR 30.50(b)(2)), each stuck shutter event should have been reported to the State of Arkansas within 24 hours. The licensee failed to notify the State of Arkansas of all of these events.
"The information concerning the 17 gauges is as follows:
Radionuclide Manufacturer Model # Activity
Cesium-137 Berthold LB 7440 50 mCi
Cesium-137 Berthold LB7440 100 mCi
Cesium-137 Berthold LB 7440 30 mCi
Cesium-137 Berthold LB 7440 250 mCi
Cobalt-60 Berthold LB 300L 0.2 mCi
Cobalt-60 Berthold LB 300L 0.5 mCi
Cobalt -60 Berthold LB 300L 0.19 mCi
Cobalt-60 Berthold LB 300L 0.7 mCi
Cobalt-60 Berthold LB 300L 4.14 mCi
Cobalt-60 Berthold LB 300L 0.46 mCi
Cobalt-60 Berthold LB 300L 1.8 mCi
Cobalt-60 Berthold LB 300L 1.51 mCi
Cesium-137 Berthold LB 330 24 mCi
Cobalt-60 Berthold LB 300L 1.8 mCi
Cobalt-60 Berthold LB 300L 0.46 mCi
Cobalt-60 Berthold LB 300L 1.51 mCi
Cobalt-60 Berthold LB 300L 0.22 mCi
"The licensee is in the process of submitting additional records. Information related to the gauge serial numbers and event date will be provided in another update. The Department is continuing to investigate and will provide updates as information is received."
* * * UPDATE FROM KAYLA AVERY TO HOWIE CROUCH VIA EMAIL ON 1/24/14 AT 1629 EST * * *
"The Arkansas Department of Health, Radioactive Materials Program, received an incident report from Domtar A.W., LLC on January 17, 2014. All stuck shutters were discovered in May of 2010, when a new consultant was hired who properly performed the shutter checks. Since that time, there were a total of 22 stuck shutters. Some of these shutters were stuck open from seven months to two years before being replaced or repaired. The licensee has confirmed that no Domtar workers, contractors or members of the public received any radiation exposure from these gauges. The following devices had stuck shutters:
Radionuclide Manufacturer Model Activity Date of Repair
Cs-137 Berthold LB7440 50 mCi 12/14/10
Cs-137 Berthold LB7440 50 mCi 12/15/10
Cs-137 Berthold LB7440 50 mCi 12/14/10
Cs-137 Berthold LB7440 50 mCi 12/15/10
Cs-137 Berthold LB7440 250 mCi 08/10/11
Cs-137 Berthold LB7440 100 mCi 12/16/10
Cs-137 Berthold LB7440 30 mCi 08/09/11
Cs-137 Berthold LB7440 100 mCi 06/28/11
Cs-137 Berthold LB7440 50 mCi 06/30/11
Cs-137 Berthold LB7440 30 mCi 06/29/11
Cs-137 Berthold LB7440 100 mCi 08/11/11
Cs-137 Berthold LB7440 30 mCi Disposed on 05/24/12
Cs-137 Berthold LB7440 100 mCi 08/12/11
Co-60 Berthold LB300L 2.5 mCi total 12/17/13 for 1 shutter **
Co-60 Berthold LB300L 5.03 mCi total 12/17/13 for 2 shutters**
Co-60 Berthold LB300L 2.19 mCi total 12/17/13 for 2 shutters**
"** These gauges contain three (3) sources with three (3) shutters, which had been all stuck open. Currently, one of these gauges still has two (2) shutters stuck open, and two of the gauges still each have one (1) shutter stuck open. Therefore, a total of four (4) shutters are currently stuck open. The licensee has committed to the Department that these gauges will be replaced on 01/23/14, 02/20/14 and 04/17/14 during mill outages. The licensee is required to notify the Department when the replacements are complete. The Department will provide another update when this information is received."
Notified R4DO (Spitzberg) and FSME Events Resource (email).
* * * UPDATE AT 1612 EDT ON 05/09/14 FROM KAYLA AVERY TO S. SANDIN VIA EMAIL * * *
This update provided device serial numbers and closed out this incident.
Radionuclide Manufacturer Model Serial Number Activity Date of Repair
Cs-137 Berthold LB7440 37624-12097 50 mCi 12/14/10
Cs-137 Berthold LB7440 37624-11867 50 mCi 12/15/10
Cs-137 Berthold LB7440 700799-2813 50 mCi 12/14/10
Cs-137 Berthold LB7440 37624-12090 50 mCi 12/15/10
Cs-137 Berthold LB7440 37624-12273 250 mCi 08/10/11
Cs-137 Berthold LB7440 37624-12098 100 mCi 12/16/10
Cs-137 Berthold LB7440 37624-12271 30 mCi 08/09/11
Cs-137 Berthold LB7440 37624-12281 100 mCi 06/28/11
Cs-137 Berthold LB7440 *** 50 mCi 06/30/11
Cs-137 Berthold LB7440 37624-12279 30 mCi 06/29/11
Cs-137 Berthold LB7440 37624-12278 100 mCi 08/11/11
Cs-137 Berthold LB7440 *** 30 mCi Disposed on 05/24/12
Cs-137 Berthold LB7440 37624-12272 100 mCi 08/12/11
Co-60 Berthold LB300L 7687 2.5 mCi total 12/17/13 for 1 shutter **
Co-60 Berthold LB300L 8654 5.03 mCi total 12/17/13 for 2 shutters**
Co-60 Berthold LB300L 9507 2.19 mCi total 12/17/13 for 2 shutters**
"** These gauges contain three (3) sources with three (3) shutters, which had been all stuck open. Currently, one of these gauges still has two (2) shutters stuck open, and two of the gauges still each have one (1) shutter stuck open. Therefore, a total of four (4) shutters are currently stuck open. The licensee has committed to the Department that these gauges will be replaced on 01/23/14, 02/20/14 and 04/17/14 during mill outages. The licensee is required to notify the Department when the replacements are complete. The Department will provide another update when this information is received."
Notified R4DO (Whitten) and FSME_Events Resource via email. |
| 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: 05/09/2014 | 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).
* * * UPDATE AT 0927 EDT ON 5/9/2014 FROM ROBERT MALLEY TO MARK ABRAMOVITZ * * *
The following report was received via fax:
"C&D has recently received and is evaluating the report from Lucius Pitkin and will 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. The planned final evaluation should be completed by May 31, 2014 at which time it is anticipated that a final report will be issued."
Notified the R1DO (Lilliendahl), R3DO (Riemer), and Part 21 Group (via e-mail). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50004 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/07/2014
Notification Time: 13:17 [ET]
Event Date: 04/07/2014
Event Time: 06:00 [CDT]
Last Update Date: 05/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
PATTY PELKE (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 CONTROL ROOM SPECIAL VENT BOUNDARY INOPERABLE
"At approximately 0600 CDT on April 7, 2014, Units 1 and 2 Control Room Special Vent System (CRSVS) Boundary was declared inoperable when a Control Room door handle fell off. Air could be felt flowing through the hole, causing an opening in the Control Room Envelope (CRE) Boundary. An opening reduces the protection of the Control Room Envelope provided to the operators in the event of a Design Basis Accident. The CRSVS Boundary was declared Inoperable, which required entry into Technical Specifications (TS) LCO 3.7.10. Condition B, one or more CRSVS trains inoperable, in MODES 1, 2, 3, or 4. Actions were immediately initiated to implement mitigating actions. A Work Request (WR) was initiated to repair the door, and work is in progress to restore the Control Room Boundary to an operable condition.
"This condition is reportable under 10CFR50.72(b)(3)(v)(C), Event or Condition that Could Have Prevented Fulfillment of a Safety Function.
"The plant remains safe, and this condition does not pose any additional risk to the public. Additionally, our defense in depth strategies are relied upon to take actions to protect the health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
* * * RETRACTION ON 5/10/14 AT 2032 EDT FROM STEVE INGALLS TO DONG PARK * * *
"Engineering evaluation has determined that the door would still fulfill its safety function of maintaining the integrity of the Control Room Envelope while the door handle was broken. The Control Room Special Vent System Boundary remained operable with the door handle off, therefore, there was no loss of safety function.
"The licensee has notified the NRC Resident Inspector."
Notified R3DO (Riemer). |
| Part 21 | Event Number: 50015 | Rep Org: QUALTECH NP
Licensee: QUALTECH NP
Region: 1
City: HUNTSVILLE State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MATTHEW THELEN
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/09/2014
Notification Time: 15:21 [ET]
Event Date: 04/09/2014
Event Time: [CDT]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
JAMES DRAKE (R4DO)
NRR PART 21 GROUP (EMAI)
| Event Text PART 21 - POTENTIAL DEFECT IN GENERAL ELECTRIC TYPE CR120AD CONTROL RELAYS
The following information was received via fax:
"This letter is being issued by QualTech NP, Huntsville, AL, to provide an initial notification to the Nuclear Regulatory Commission and Nebraska Public Power District [NPPD] Cooper Nuclear Station concerning a potential defect in General Electric Type CR120AD control relays. A failure analysis revealed that the most likely initiator of the failure was a flaw or defect in the start wrap of the magnet wire. The flaw created an arc that involved windings directly beneath the start wrap which resulted in an open circuit on the coil windings. This failure is classified as infant mortality, which is similar to the failure mode identified in the 10 CFR part 21 30 day report (accession number 9706190261) dated June 12, 1997 submitted by GPU Nuclear.
"Investigation of documents dating back to 1997 revealed that the manufacturer issued an informal recommendation to detect infant mortality in these relays by performing burn-in testing and mechanical cycle aging of the relay. QualTech NP, in conjunction with NPPD, determined that the risk of infant mortality can be mitigated by subjecting these relays to a 100 hour burn-in and performance of 100 mechanical cycles prior to installation.
"It has been confirmed that only two orders, with two units each, for this particular relay are affected. Both orders have been shipped to Nebraska Public Power District as requested by purchase orders 4500149953 and 4500142705. All subject relays shall be subjected to a 100 hour bum-in and exposed to 100 mechanical cycles or returned to QualTech NP for replacement.
"Additional details will be provided in the formal written report. Please contact Matthew Thelen at 256-924-7441 (office) or mthelen@curtisswright.com for additional information.
"Matthew Thelen
Project Manager
QualTech NP Huntsville Operations
a business unit of Curtiss-Wright Flow Control Company
http://qualtechnp.cwfc.com"
* * * UPDATE AT 1707 EDT ON 05/09/14 FROM MATTHEW THELEN TO S. SANDIN VIA FAX * * *
"(File No.: QTHuntsville 10CFR21-2014-01)
"To whom it may concern:
"This letter is being issued by QuaiTech NP, Huntsville Operations to provide a final notification to the Nuclear Regulatory Commission and Nebraska Public Power District (NPPD) Cooper Nuclear Station concerning a potential defect in General Electric Type CR120AD control relays.
"Replacement relays have been provided to NPPD. All required dedication procedures at QualTech NP have been revised to include a 100 hour burn-in and 100 mechanical cycles in an effort to detect infant mortality. No further actions are required at this time.
"This 10CFR part 21 file is closed."
Notified R2DO (Bonser), R4DO (Whitten) and NRR Part 21 Group via email. |
| Agreement State | Event Number: 50074 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: SENTARA NORFOLK GENERAL HOSPITAL
Region: 1
City: NORFOLK State: VA
County:
License #: 710-189-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/30/2014
Notification Time: 15:26 [ET]
Event Date: 04/24/2014
Event Time: [EDT]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1DO)
FSME EVENT RESOURCES (EMAI)
| Event Text AGREEMENT STATE REPORT - SECOND SCHEDULED MEDICAL DOSE NOT DELIVERED DUE TO EQUIPMENT FAILURE
The following information was provided by the State of Virginia via facsimile:
"On April 24, 2014, the licensee performed a two part therapy procedure using yttrium-90 microspheres (Sirtex SirSpheres). The procedure was to treat the same lobe of the liver via two different arterial pathways. There were no problems with the first injection, but the second injection failed and none of the yttrium-90 was delivered to the patient. The licensee determined that the failure occurred because of a faulty Surefire Medical catheter. The authorized user decided not to repeat the administration of the second dose but will treat the region with an alternate method. The licensee indicated that the prescribed dosage for the first injection was 11.7 millicuries and that 12.7 millicuries (27,500 rem to the target region of the loft lobe) was delivered. The prescribed dosage for the second injection was 8.3 millicuries (to give a dose of 26,200 rem to the targeted region) but no activity was delivered. This resulted in a medical event for the second injection (or fraction) as well as for the entire procedure."
VA Event Report ID No.: VA-2014-003
* * * UPDATE ON 5/9/14 AT 1420 EDT FROM CHARLES COLEMAN TO DONG PARK * * *
The following information was provided by the Commonwealth of Virginia via facsimile:
"The licensee submitted a written report on May 9, 2014, which contained additional information from its review of the event. The licensee's review concluded that the failure of the catheter (Surefire Medical, Model SHF-38120-mT) during the second procedure was attributable a kink or fold in a basket on the catheter which resulted in a catheter occlusion. The licensee concluded that the short arterial segment used for the arterial pathway and the acute angle at the arterial origin, along with possible manipulation or patient movement, resulted in a kink or fold as the basket entered the acute angle of the artery. The catheter will be returned after decay of the radioactivity to the manufacturer for examination. The licensee submitted corrective actions for the procedure which include retraining of personnel to use extra care in ensuring the catheter is firmly set and to flush the catheter prior to administration of the microspheres to ensure there is no occlusion. The agency will review implementation of the corrective actions
during a future inspection."
Notified R1DO (Lilliendahl) and FSME Events Resource via email.
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. |
| Agreement State | Event Number: 50082 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: DUNN CONSTRUCTION
Region: 1
City: BIRMINGHAM State: AL
County:
License #: 812
Agreement: Y
Docket:
NRC Notified By: MYRON RILEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/02/2014
Notification Time: 16:30 [ET]
Event Date: 05/02/2014
Event Time: 05:30 [CDT]
Last Update Date: 05/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following was provided by the State of Alabama via facsimile:
"On the morning of May 2, 2014 at approximately 0530 CDT, a CPN model MC-3 moisture density gauge, serial number M30129990, containing 10 millicuries of Cs-137 and 50 millicuries of Am-241:Be was damaged while in use at a temporary job site in Birmingham, Alabama when it was run over by a motorist. The licensee, Dunn Construction, notified the Alabama Office of Radiation Control at 0803 CDT. Dunn Construction is authorized to possess and use radioactive material under their Alabama Radioactive Material License No. 812. The licensee representative stated that the source rod became unattached, but was returned to the shielded position. Radiation levels around the gauge were found to be within the normal range. The gauge was placed back in the transport container and returned to the licensee's facility. The licensee was advised to perform a leak test of the gauge."
Alabama Incident 14-14 |
| Power Reactor | Event Number: 50090 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: PETE SNYDER | Notification Date: 05/06/2014
Notification Time: 13:27 [ET]
Event Date: 05/06/2014
Event Time: 08:30 [CDT]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN BONSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL DURING INSTRUMENT TESTING
"At 0830 [CDT] on 05/06/2014, the Unit 3 reactor automatically scrammed due to low reactor water level as a result of a trip of both recirculation pumps. Main Steam Isolation Valves remained open with main turbine bypass valves controlling reactor pressure. Reactor feedwater pumps are in service to control reactor water level.
"Primary Containment Isolation System Groups 2, 3, 6, and 8 containment isolation and initiation signals were received. Upon receipt of these signals all required components actuated as required. The Reactor Feedwater System controlled and maintained water level above the level 2 initiation setpoint.
"Prior to the Scram, the reactor was operating at 100% power. A Core and Containment Cooling Systems Analog Trip Unit Functional Test was in progress. The cause of the recirculation pump trip is under investigation.
"This event is reportable within 4 hours per 10CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' It is also reportable within 8 hours per 10CFR 50.72(b)(3)(iv)(A) and requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A).
"The NRC Resident Inspector has been notified."
U1 and U2 remained at 100% power and were unaffected.
* * * UPDATE AT 1302 EDT ON 05/09/14 FROM TODD BOHANAN TO DONG PARK * * *
"Investigation revealed that a failed power supply caused an Anticipated Transient Without Scram/Alternate Rod Insertion (ATWS/ARI) signal to be generated when a level 2 Reactor Water Level was simulated on one instrument. All systems responded to the ATWS/ARI signal as designed. This signal opened the Recirc Pump Trip breakers for both Recirculation Pumps and opened the ARI valves to bleed air from the Reactor Protection System (RPS) scram air header. The resulting transient caused reactor water level to dip below the RPS trip setpoint (level 3 Reactor Water Level), a normal plant response, and the automatic scram signal occurred. At the time of the RPS scram signal, all rods were inserting and reactor power was approximately 2-3% and lowering.
"The NRC Resident Inspector has been notified."
Notified R2DO (Bonser). |
| Power Reactor | Event Number: 50102 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: WILLIAM BULLOCK
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/09/2014
Notification Time: 12:37 [ET]
Event Date: 05/08/2014
Event Time: 18:15 [EDT]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
BRIAN BONSER (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 NON-LICENSED CONTRACT SUPERVISOR IN VIOLATION OF FITNESS FOR DUTY POLICY
"A non-licensed contract supervisor has been found in violation of the Fitness for Duty Policy. The individual's access to the plant has been terminated.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 50104 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID CALLEN
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/09/2014
Notification Time: 16:46 [ET]
Event Date: 05/09/2014
Event Time: 15:26 [EDT]
Last Update Date: 05/09/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JOHNATHAN LILLIENDAH (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 NON-LICENSED EMPLOYEE SUPERVISOR IN VIOLATION OF FITNESS FOR DUTY POLICY
"A non-licensed employee supervisor had a confirmed positive drug test during a random fitness-for-duty test. The employee's access to the plant has been revoked."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 50105 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES DEDIC
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/11/2014
Notification Time: 16:00 [ET]
Event Date: 05/11/2014
Event Time: 08:02 [CDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JACK WHITTEN (R4DO)
|
| 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 LOSS OF THE METEOROLOGICAL TOWER COMPUTER SYSTEM
"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0802 (CDT), on 05/11/2014, the meteorological tower computer system failed which resulted in a loss of meteorological data to the plant. Information Technology personnel have reported to the plant for investigation. Proceduralized compensatory measures for dose assessment include use of National Weather Service followed by historically determined default values.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50106 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD STRINGFELLOW
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/12/2014
Notification Time: 11:13 [ET]
Event Date: 05/12/2014
Event Time: 07:31 [EDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DON JACKSON (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | | 0 | | Event Text | UNIT 2 STACK HIGH RANGE RADIATION MONITOR REMOVED FROM SERVICE FOR PRE-PLANNED MAINTENANCE | |