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Event Notification Report for August 12, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/11/2016 - 08/12/2016

** EVENT NUMBERS **


52151 52169 52172 52174

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Agreement State Event Number: 52151
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: UKNOWKN
Region: 3
City: CLEVELAND State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/04/2016
Notification Time: 14:28 [ET]
Event Date: 08/02/2016
Event Time: 09:40 [EDT]
Last Update Date: 08/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSC (CANADA) (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE WITH SEALED RADIOACTIVE SOURCE RECOVERED AT A SCRAPYARD

The following information was received from the Ohio Department of Health (ODH) via email:

"A load of scrap metal set off the radiation detectors at a scrapyard in Cleveland, Ohio at approximately 0940 EDT on 8/2/16. A Department of Transportation exemption was issued and the scrap was returned to the supplier, Cleveland Wire, also located in Cleveland. The load was sorted by Cleveland Wire staff and a 'C-arm' fixed gauge was discovered.

"ODH investigators arrived at the Cleveland Wire site on 8/3/16 and surveyed the gauge. Highest readings were determined to be 4 mR/hour on contact at the point where the source would be located inside the device, indicating that a source was present and the shutter was closed. Smear wipes taken indicated no removable contamination present. Further investigation showed that a tag was still affixed to the device, indicating the isotope (Sr-90), activity (70 mCi) and assay date (June, 1976). The radiation readings and identifying information are in keeping with what would be expected upon review of the Sealed Source & Device (SS&D) registration for the device. The device is currently in secure storage on site at Cleveland Wire, awaiting plans for transfer or disposal.

"The ODH investigators at Cleveland Wire also learned that the device had been received from an industrial equipment reseller, HDR Industrial Surplus, located in Euclid, Ohio. Another ODH inspector was dispatched to that location on 8/3/16 to survey the facility, check for additional items that might contain radioactive materials, and to determine if the original owner/consignor could be located. No radiation levels were detected above background at the Euclid location, and no other items containing radioactive materials appeared to be present.

"Research and investigation is ongoing to attempt to determine the owner of the device.

"Source/Radioactive Material: SEALED SOURCE GAUGE
Manufacturer: AMERSHAM
Model Number: S-18
Serial Number: S-1078-7
Radionuclide: SR-90, 0.070 Ci
IAEA Category: 5

"Device/Associated Equipment:
Device Name: FIXED GAUGE
Manufacturer: SANGAMO-WESTON-SCHLUMBERGER
Model Number: M-3."

Ohio Item Number: OH160008"

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

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Power Reactor Event Number: 52169
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BARRETT NICHOLS
HQ OPS Officer: DANIEL MILLS
Notification Date: 08/11/2016
Notification Time: 11:09 [ET]
Event Date: 08/11/2016
Event Time: 09:59 [EDT]
Last Update Date: 08/11/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ART BURRITT (R1DO)

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

Event Text

MANUAL REACTOR TRIP DUE TO LOSS OF TWO CIRCULATING WATER PUMPS

Reactor operators manually tripped the reactor due to the loss of two out of four circulating water pumps which caused a drop in condenser vacuum. The trip was uncomplicated. The reactor is shutdown and stable with decay heat removal via steam dumps to the condenser. The cause of the circulating water pump trips is currently unknown, but initial indications are that the pumps tripped due to a lightning strike that caused an electrical perturbation. The reactor will remain shutdown while the licensee investigates the cause. Unit 3 was not affected.

The licensee notified the NRC Resident Inspector and the State and Local governments.

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Power Reactor Event Number: 52172
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIMOTHY M. WOOD
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/11/2016
Notification Time: 16:35 [ET]
Event Date: 08/11/2016
Event Time: 10:15 [EDT]
Last Update Date: 08/11/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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 Y 100 Power Operation 100 Power Operation

Event Text

CONTROL ROOM EMERGENCY VENTILATION SYSTEM DECLARED INOPERABLE

"At 1015 [EDT] on August 11, 2016, it was discovered that a Fire Protection damper associated with the Control Room Emergency Ventilation System had closed unexpectedly due to component failure. The closure rendered both trains of the Control Room Emergency Ventilation System (CREVS) inoperable requiring both Unit 1 and 2 to enter Technical Specification Limiting Condition of Operation (LCO) 3.7.10 Condition G. Condition G requires immediate entry into LCO 3.0.3. At 1159 on August 11, 2016, actions were taken to block the deficient damper in the open position restoring both trains of CREVS to a fully operable condition and allowing exit of LCO 3.0.3 and 3.7.10 Condition G.

"The purpose of CREVS is to provide a protected environment from which occupants can control the [respective] unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. In the event of a design basis accident, emergency ventilation components realign to supply filtered air and to pressurize the Control Room Envelop (CRE). While the damper was closed both trains of CREVS were incapable of supplying the Relay Room as well as the Technical Support Center and its associated support spaces. These locations constitute part of the CRE, therefore both trains of CREVS were inoperable.

"Both trains of CREVS being inoperable affected the habitability of the TSC where the assessment capability of the facility for all emergencies was adversely effected.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 52174
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: NICK ROH
HQ OPS Officer: JEFF HERRERA
Notification Date: 08/11/2016
Notification Time: 18:41 [ET]
Event Date: 08/11/2016
Event Time: 15:05 [EDT]
Last Update Date: 08/11/2016
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

ROBINSON DAM TAINTER GATES UNANALYZED CONDITION

"During testing it was discovered that the H. B. Robinson Steam Electric Plant, Unit 2 (RNP) Lake Robinson Dam Tainter Gates A and B were in degraded condition. The Tainter Gates are non-technical specification features of design that control Lake Robinson water level. RNP was not able to achieve full opening of the Tainter Gates. Subsequent analysis has concluded that the degraded condition of the Tainter Gates adversely impacts their UFSAR credited safety function. On 8/11/2016, at 1505 EDT, it was determined this places RNP in an unanalyzed condition that significantly degrades plant safety [per] 10 CFR 50.72 (b)(3)(ii)(B). The Tainter Gates have been repaired, tested and rendered complaint with their original licensing basis function. The current plant status does not pose undue risk to the health and safety of the public.

"The NRC Senior Resident Inspector has been notified of this condition."

Page Last Reviewed/Updated Friday, August 12, 2016
Friday, August 12, 2016