| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/12/2017 - 05/15/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52735 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: S-2 ENGINEERING, INC.
Region: 4
City: RANCHO CUCAMONGA State: CA
County:
License #: 7192-36
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: STEVE SANDIN | Notification Date: 05/05/2017
Notification Time: 16:02 [ET]
Event Date: 05/01/2017
Event Time: [PDT]
Last Update Date: 05/05/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
GREGORY AHERN (ILTA)
CNSNS (MEXICO) (FAX)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - THEFT OF TROXLER MOISTURE DENSITY GAUGE
The following information was provided by the State of California:
"S-2 Engineering reported the loss of a Troxler 3411-B # [S/N] 12398 moisture density gauge that had been in storage at a job site in Barstow, CA. This device contains 0.296 GBq (8 mCi) of Cs-137 and 1.48 GBq (40 mCi) of Am-241.
"The licensee was conducting a physical inventory of their devices containing radioactive material and found this one to be missing from the locked storage box.
"The licensee checked with all of their authorized gauge users to determine if the device was in use but not checked out properly before reporting it as lost. The last documented use of the density gauge was Sept. 22, 2016.
"This investigation is ongoing."
The licensee notified their Local Law Enforcement Agency (LLEA) of the theft.
CA 5010 Number: 050417
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 52750 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT RUSH
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/12/2017
Notification Time: 08:20 [ET]
Event Date: 05/12/2017
Event Time: 00:45 [CDT]
Last Update Date: 05/12/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
DAVID HILLS (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 MAIN STEAM ISOLATION VALVES EXCEEDED PRIMARY CONTAINMENT LOCAL LEAK RATE ACCEPTANCE CRITERIA
"At 0045 [CDT] on May 12, 2017, it was discovered that a Primary Containment local leak rate test performed on Main Steam Isolation Valves (MSIV) exceeded its acceptance criteria.
"During Modes 1, 2, and 3, Technical Specification Surveillance Requirement 3.6.1.3.9 requires MSIV leakage for a single MSIV line to be less than or equal to 100 standard cubic feet per hour (scfh) (47,195 sccm) and requires the combined leakage rate for all MSIV leakage paths to be less than or equal to 200 scfh (94,390 sccm) when tested at 9 psig.
"As-found for the 'D' MSIV line leakage is 53,921.61 standard cubic centimeter per minute (sccm) for the 'D' Inboard MSIV 1B21F022D and 59,698.8 sccm for the 'D' Outboard MSIV 1B21F028D. As-found combined MSIV min-path leakage is 102,463 sccm.
"This event is being reported as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10 CFR 50.72(b)(3)(ii)(A) since the Primary Containment Isolation Valves leakage limits for MSIVs were exceeded.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 52751 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL McCARTHY
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/14/2017
Notification Time: 15:32 [ET]
Event Date: 05/14/2017
Event Time: 09:30 [EDT]
Last Update Date: 05/14/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DON JACKSON (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text SINGLE FLOW BARRIER ACCESS POINT FOUND UNBOLTED
"On May 14, 2017, with the Unit in Mode 4, it was identified that a single flow barrier access point (Gate C) to the 46 ft. elevation of Containment was unbolted for access to the inner crane wall to perform surveillance testing. This single flow barrier access point is required to be bolted closed to ensure the Emergency Core Cooling System (ECCS) operability basis which requires the sump barrier system to be operable in Modes 1- 4. The sump barrier system is required to prevent the transport of debris to the recirculation and containment sumps. This event is a safety system functional failure as the condition could have prevented adequate post-accident core cooling due to Design Basis Accident debris blockage of the recirculation and/or the containment sump and is reportable under 10 CFR 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector and the New York Public Service Commission. |
| Power Reactor | Event Number: 52752 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MARK MAYER
HQ OPS Officer: VINCE KLCO | Notification Date: 05/14/2017
Notification Time: 16:09 [ET]
Event Date: 05/14/2017
Event Time: 07:30 [CDT]
Last Update Date: 05/14/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DAVID HILLS (R3DO)
FFD GROUP (EMAI)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text FITNESS FOR DUTY
"At 0730 [CDT] on 5/14/2017, a visitor was working in the Protected Area (PA) on the turbine building roof and discovered a blue 12 ounce can of beer in their cooler. This was discovered when the visitor was removing items from their cooler into a larger community cooler. The visitor immediately notified their escort of the prohibited item. The escort then notified Security of the event. Security took possession of the item and the individual was escorted offsite. The individual stated when they packed their cooler at home they thought they had picked up a blue can of soda and did not notice it was a blue can of beer. This event is being reported per 10CFR26.719(b)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 52753 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: SCOTT MEIKLEJHON
HQ OPS Officer: VINCE KLCO | Notification Date: 05/14/2017
Notification Time: 21:27 [ET]
Event Date: 05/14/2017
Event Time: 18:23 [CDT]
Last Update Date: 05/14/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JOHN KRAMER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling | 0 | Refueling | Event Text FIRE IN ADMINISTRATIVE BUILDING RESULT IN LOCAL FIRE DEPARTMENT NOTIFICATION
"On May 14, 2017 at time 1823 [CDT], Waterford 3 Steam Electric Station notified St. Charles Parish Emergency Services via 911 of a fire in the Generation Support Building (GSB), the Hahnville, Luling and Killona Fire Departments were dispatched. The GSB is an Administrative and Engineering Building outside the Protected Area and on the Owner Controlled Area. The fire was reported out at 1841. No personnel were injured due to the fire. The fire appeared to be from an external building exhaust fan. There was no internal or structural damage to the building. There was no radiological release. No Safety Related Systems were required to function."
The licensee notified the NRC Resident Inspector. | |