THE PHRASE "NON-EMERGENCY" SEEMS TO BE THE FAVORITE BY ALL WHO REPORT "EVENTS" TO THE NUCLEAR REGULATORY COMMISSION (NRC), BUT HOW MANY ARE "NON-EMERGENCIES" IN FACT?
THE FOLLOWING ARE JUST SOME OF THE EVENTS FROM THIS MONTH, SO FAR.
THE LAST "REPORT" LISTED BELOW IS PERHAPS THE WORST BECAUSE OF THE WIDE AREA INVOLVED..
SOME ACCIDENTS, SOME KNOWN LEAKS, ALL TROUBLING TO ONE DEGREE OR ANOTHER FOR THOSE OF US WHO KNOW THE REAL HAZARDS OF ANY/ALL RADIATION, A "LITTLE BIT" OR "A LOT".
WHILE THESE "EVENTS" APPEAR IN THE MARCH REPORT, SEVERAL HAPPENED NEAR THE END OF FEBRUARY AND EVEN AS FAR BACK AS JANUARY...JUST A LITTLE LATE BEING "REPORTED".
1~ Event Number: 51753
PENNSYLVANIA BUREAU OF RADIATION PROTECTION
(WHICH IS PROTECTING WHOM? THE NUCLEAR INDUSTRY, AS DOES THE NRC?)
Licensee: UNKNOWN
(That's right, UNKNOWN, because they don't know where this came from, supposedly)
Region: 1
City: BEAVER FALLS
State: PA
Notification Date: 02/24/2016
Notification Time: 15:10 [ET]
Event Date: 02/22/2016
Event Time: [EST]
Last Update Date: 02/24/2016
AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION AT METAL RECYCLING FACILITY
The following information was provided by the Commonwealth of Pennsylvania via fax:
"Notifications:
The non-licensee discovered the event on February 23, 2016 and notified the Ohio Department of Health, who then notified our Department [PA Bureau of Radiation Protection] after normal business hours on the same evening.
It is reportable per 10 CFR 30.50(b)(1)(i) and 20.2201(a)(i).
"Event Description:
On Monday, February 22, 2016, a large orphan radium-226 (Ra-226) source of unknown total activity or origin was shredded at the PSC Metals facility in Beaver Falls, PA. The recycled material was then shipped to two different Ohio facilities where it was discovered during an inbound radiation scan on February 23, 2016.
"Cause of the Event:
The Pennsylvania facility was [apparently] not performing outbound gamma radiation surveys on recycled materials.
[HOW MANY OTHER TIMES DID THEY FAIL TO PERFORM THESE SURVEYS?
WE MAY NEVER KNOW.]
"Actions: The contaminated shredder, with gamma radiation levels of over 400 mrem/hr, has been isolated.
The locker room, clothes, vehicles and workers have been surveyed and no contamination has been found.
The gloves of two workers were found to have contamination.
A reactive inspection occurred the evening of the 23rd to survey the entrance/gate area of the Beaver Falls facility, and a full emergency response occurred the morning of February 24, 2016.
PA and OH Radiation Control Programs are onsite in their respective states and communicating findings.
Surveys of employees, vehicles and equipment are ongoing.
The response will continue until isolation and containment of Ra-226 is ensured.
A local health physics service provider has also been contracted by PSC to assist with the decontamination operation. More information will be provided upon receipt.
"Media Attention: None at this time, but OH may issue a Press Release.
AND, MIRACLE OF MIRACLES, A LOCAL NEWS ITEM DID APPEAR!
Scrap contaminated with radioactive material shipped from ... www.wpxi.com › News › Local
WPXI, Feb 25, 2016
WPXI, Feb 25, 2016
RIGHT, NO WORRIES, THEY JUST CLOSED THE SCRAPYARD AND HAVEN'T RELEASED TEST RESULTS ON WORKERS AT THE 3 FACILITIES INVOLVED...MOVE ALONG, ALL IS WELL...OR NOT.
2~ FERMI NUCLEAR GENERATING STATION IN MICHIGAN HAS TWO 'EVENTS' POSTED FOR MARCH, BUT, WELL, THEY SORT OF DID NOT REPORT THESE WHEN THEY WERE "REPORTABLE", SO WE GET ONE OF THESE ALMOST 2 MONTHS LATE, WHICH IS FINE, JUST FINE, WITH NRC.
2a- Event Number: 51756 Power Reactor
Facility: FERMI, UNIT 2
Region: 3
State: MI
Notification Date: 02/25/2016
Event Date: 02/21/2015
Last Update Date: 03/02/2016
POWER REDUCTION DUE TO AUTOMATIC OPENING OF A TURBINE BYPASS VALVE
"On February 21, 2015, at approximately 0030 EST, with Fermi 2 in Mode 1 operating at 100 percent reactor thermal power, the West Turbine Bypass Valve (TBV) automatically opened in response to the number two High Pressure Turbine Stop Valve (TSV) cycling from full open to closed and then to 22 percent open. Reactor power was subsequently lowered to 91.5 percent reactor thermal power and the bypass valve closed.
"Per Technical Specification Bases 3.3.1.1, TBVs must remain shut while reactor thermal power is at or above 29.5 percent to consider the TSV closure and Turbine Control Valve (TCV) fast closure Reactor Protection System (RPS) functions operable.
The condition was recognized at the time of the event and the RPS functions were declared inoperable.
The Limiting Condition for Operation was exited at 0031 EST following TBV closure.
"Since the RPS functions were verified to remain enabled, Fermi 2 did not report this event within 8 hours of occurrence. However, this event was subsequently determined to meet the reporting criterion and is being reported pursuant to 10 CFR 50.72(b)(3)(v)(A).
"The licensee informed the NRC Resident Inspector."
The cause of the High Pressure Turbine Stop Valve cycling was due to a communication card failure that has since been corrected.
This event was determined to be reportable at 1200 EST on 02/24/16. See EN #51755 for a similar event that occurred on 01/06/16.
"UPDATE:Although this event was determined to be reportable at 1200 EST on 02/24/16, it met the reporting requirement on the date of the event (02/21/2015). "
OOPS!
NO HARM DONE, RIGHT?
IT ISN'T LIKE THE NRC GIVES A RIP, IS IT?
2b- Event Number: 51755 FERMI
Notification Date: 02/25/2016Event Date: 01/06/2016
Last Update Date: 03/02/2016
POWER REDUCTION DUE TO AUTOMATIC OPENING OF THE TURBINE BYPASS VALVES.
"On January 6, 2016, at approximately 1514 EST, with Fermi 2 in Mode 1 operating at 100 percent reactor thermal power, the East and West Turbine Bypass Valves (TBVs) automatically opened for 3 minutes and 32 seconds in response to the number one High Pressure Turbine Stop Valve (TSV) drifting from full open to 25 percent open. Reactor power was subsequently lowered to 91.0 percent reactor thermal power and the bypass valves closed.
"Per Technical Specification Bases 3.3.1.1, TBVs must remain shut while reactor thermal power is at or above 29.5 percent to consider the TSV closure and Turbine Control Valve (TCV) fast closure Reactor Protection System (RPS) functions operable. The condition was recognized at the time of the event and the RPS functions were not declared inoperable since the functions were verified to remain enabled.
"Since the RPS functions were not declared inoperable, Fermi 2 did not report this event within 8 hours of occurrence. However, after further evaluation, it was determined that this event met the reporting criterion. Accordingly, this event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(A).
"The licensee informed the NRC Resident Inspector."
The cause of the High Pressure Turbine Stop Valve drifting was due to an actuator malfunction that has since been corrected.
UPDATE: "Although this event was determined to be reportable at 1200 EST on 02/24/16, it met the reporting requirement on the date of the event (01/06/2016)."
DON'T WORRY, BABY, IT'S NOT A "THREE STRIKES AND YOU'RE OUT", EVER.
THE NRC WILL JUST MAKE IT ALL GO AWAY....LIKE IT NEVER EVEN HAPPENED.
NEXT, ANOTHER MYSTERY, AND THERE ARE MANY "UNKNOWN CAUSES"...AS IN, "SHEESH, WE REALLY WON'T SAY HOW WE SCREWED UP LIKE THIS."
3~SEABROOK NUKE SITE ALSO HAD 2 'EVENTS' LISTED THIS MONTH.
3a- Event Number: 51762
Facility: SEABROOK, UNIT 1
Region: 1
State: NH
Notification Date: 03/02/2016
Event Date: 03/02/2016
Last Update Date: 03/02/2016
TURBINE TRIP CAUSING A REACTOR TRIP
"The turbine tripped for an unknown cause followed by a reactor trip.
All systems are functioning as designed.
Operators have transitioned out of the EOP [Emergency Operating Procedure] network into normal operating procedures. The plant is stable in mode 3."
All control rods fully inserted during the trip and no safety or relief valves lifted.
The plant is in its normal shutdown electrical lineup.
Emergency Feedwater actuation occurred to restore steam generator levels.
The plant expects to make a press release.
NO, NO PRESS RELEASE...SEABROOK DECIDED NOT TO CAUSE A STIR...AGAIN.
UPDATE: The licensee will not issue a press release for this event.
SURE, WHY BOTHER FOLKS WITH ANOTHER "ACCIDENT OF UNKNOWN CAUSE", RISK SHOWING HOW OFTEN AND QUICKLY THESE THINGS HAPPEN?
WELL, THE WASHINGTON TIMES FOUND OUT SOMEHOW...
Spokesman: Seabrook station nuclear plant reactor down ...
THE LAST PRESS RELEASE FOR A REACTOR TRIP AT SEABROOK WAS IN 2014:
Unexpected reactor shutdown at Seabrook nuclear plant ...
AND BACK IN 2012... Facility: SEABROOK; AUTOMATIC REACTOR TRIP ...
3b- Event Number: 51765
UNIT 1 AT SEABROOK, YET AGAIN...
Notification Date: 03/02/2016
Event Date: 03/02/2016
VALID ACTUATION OF EMERGENCY FEEDWATER
"On 3/2/2016, [at] 1312 hours EST, while in the process of a plant cooldown, a valid actuation of the emergency feedwater system (EFW) occurred when B steam generator levels were reduced to 20 [percent].
The lowering level was a result of the unanticipated tripping of the start up feed pump on low condensate storage level while it was the feed source to the steam generators. The start up feed pump was restarted and feed flow had been restored when the actuation took place.
The EFW flow was secured per procedure and the start up feed pump remains the feed source to the steam generators.
POOR LITTLE SEABROOK, SO PLAGUED BY FAILURE SINCE IT CAME ONLINE.
SUCH A "HARD-LUCK" STORY OVER THE YEARS...NO WONDER THE NRC DOESN'T BOTHER IT WITH HEAVY FINES OR CLOSE IT, OR...
4~ Event Number: 51764
POWER REACTOR
FACILITY: SUSQUEHANNA, UNIT 1
Region: 1
State: PA
Notification Date: 03/02/2016
Event Date: 03/02/2016
Last Update Date: 03/02/2016
SECONDARY CONTAINMENT INOPERABLE
"On March 2, 2016 at 1330 hrs. [EST], Secondary Containment became inoperable due to failure to meet a Surveillance Requirement (SR 3.6.4.1.3).
"The inoperability was caused when Unit 2 Reactor Building Airlock doors were inadvertently opened simultaneously.
"Secondary Containment was restored March 2, 2016 at 1331 hrs. when the doors were closed.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022, Rev. 3, section 3.2.7, as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."
AS MY GRAMMY WOULD SAY, 'BLESS THEIR HEARTS, DON'T HAVE SENSE ENOUGH TO SHUT THE DOOR."
SUSQUEHANNA HAD ANOTHER ALMOST IDENTICAL "EVENT" ON MARCH 8, 2016.
HAD A SIMILAR PROBLEM BACK IN DECEMBER, 2015
IN JUNE OF 2015, THE NRC ACTUALLY REQUIRED "RETRAINING" BECAUSE THINGS WERE SO BAD...
"The preliminary finding relates to one specific accident type – a primary coolant system leak outside primary containment, and inside the secondary containment," NRC records say. "The performance deficiency was not noted in any other accident scenario."
Susquehanna Nuclear had been interpreting the rule to start that 15-minute clock "when operator actions were, or expected to be, unsuccessful in isolating" the leak, records say."
Unit 1 as of June 2010 was the nation's largest boiling water reactor in terms of thermal power and generating capacity.
SEE?
WE'RE IN GOOD HANDS AT THESE PLACES...AREN'T WE?
BIGGEST OF ITS KIND AND COOLING PROBLEMS AGAIN AND AGAIN.... NICE.
SOMETHING ON THAT PAGE AND EVERY PAGE STRUCK ME AS A BIT ODD...EACH PAGE IS SORTED BY DATE, YET FOR MARCH 3, 2016, THE "EVENTS" ARE NUMBERED....
| 51752 |
| 51753 |
| 51755 |
| 51756 |
| 51762 |
| 51764 |
| 51765 |
WHERE IS EVENT 51754, OR 51757 THROUGH 51763?
MAYBE THEY'LL TURN UP ELSEWHERE?
INDIAN POINT, LIMERICK, BYRON, BRAIDWOOD NUKE FACILITIES/PLANTS EACH HAD AN EVENT REPORTED BY THE NRC ON MARCH 8.
5~ WATTS BAR IN TENNESSEE, UNIT 2, ON MARCH 9, 2016, HAD AN "Emergency Class: UNUSUAL EVENT".
"Watts Bar Unit 2 declared an Unusual Event at 0342 EST based on a fire greater than 15 minutes in the turbine building - 2B Hotwell pump motor.
The fire was extinguished by 0401 EST, at the time of notification. Unit 2 is currently shutdown in Mode 5 making preparations for startup. No offsite assistance was requested. All personnel are accounted for and there are no personnel injuries reported.
The licensee terminated the Unusual Event at 0508 EST based on verification that the
fire was out and that the fire response team had been secured. "
TVA: Watts Bar Dam generating unit caught on fire | WJHL
SURELY WE WERE NEVER IN DANGER FROM A FIRE AT A NUKE PLANT, WERE WE?
THOSE PLACES ARE 1001% ABSOLUTELY SAFE!
6~ THE LOUISIANA POWER REACTOR, UNIT 1, AT RIVER BEND HAD AN "INVALID ACTUATION OF THE PRIMARY CONTAINMENT ISOLATION LOGIC"...WAY BACK IN JANUARY THIS YEAR, REPORTED ON MARCH 9.
"This event resulted from the failure to maintain corrective actions in place that were develop after a similar event in 1994. Additionally, the operators were not using the type of jumpers required by the procedure, which likely contributed to the blown fuse.
"The RHR system operating procedure has been revised to require that the potentially affected valves in the shutdown cooling loop will be de-energized during jumper installation to eliminate the possibility of inadvertent isolation.
"This is being reported in accordance with 10 CFR 50.73(a)(1) as an invalid actuation of the primary containment isolation logic."
During this event, the RCS temperature increased from approximately 130 to 190 degree F. "
LAISSEZ LES BONS TEMPS ROULER, BOYS!
PARTY ON!
THE NRC LOVES YOU!
6~ AN EXAMPLE OF AN EVENT BEING REPORTED AND THEN RETRACTED, MADE TO DISAPPEAR, CAN BE SEEN IN EVENT 51663, WHICH HAPPENED AND THEN DID NOT "REALLY" HAPPEN AT OLD RICKETY SALEM'S #2 REACTOR IN NEW JERSEY ON 01/19/2016, UPDATED AT LAST ON 03/10/2016.
HERE IS THEIR REASONING ON CALLING THE WHOLE THING OFF...
""This event is being retracted. An engineering review determined that while the auxiliary feedwater flow loop response time test results did not meet the procedural acceptance criteria, the accident analysis assumptions remained valid.
The ATWS [Anticipated Transient Without Scram] was the limiting accident, and the loop response time results were still bounded by the existing analyses.
The failed loop response time DID result in a condition prohibited by TS which will be reported in a Licensee Event Report (LER). This condition has been documented in the licensee's Corrective Action Program."
ATTABOY, SALEM, YOU TELL THEM!
SHAME ON THE NRC FOR NOT AWARDING YOU THE BIG PRIZE FOR "BEST USE OF DOUBLESPEAK BY A MAJOR LEAKER"!
7~ ON MARCH 10, ARKANSAS NUCLEAR POWER REACTORS #1 AND #2, EVENT
51785...
"SEISMIC ALARM FUNCTION NOT AVAILABLE DURING SEMI-ANNUAL SEISMIC SYSTEM FUNCTIONAL TEST ".
THAT FACILITY BEING CLOSE TO THE NEW MADRID FAULT, SHOULD THIS CONCERN US?
SURELY NOT!
8~ BLOWING IN THE WIND...THIS ONE IS A REAL DOOSIE...CONTAMINATED MATERIAL GOES ON A LONG ROAD TRIP, RELEASING ALPHA RADIATION ALL ALONG THE WAY...
EVENT #51767
THIS STARTED ABOUT MARCH 3 OR 4.Facility: NUCLEAR FUEL SERVICES INC.HEU CONVERSION & SCRAP RECOVERYNAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
CONTAMINATED RADIOACTIVE MATERIAL SHIPMENT
"On March 3, 2016, at approximately 1745 [EST], a radioactive material shipment was received at NFS from the Westinghouse Electric Company in Hopkins, South Carolina.
Receipt contamination and radiation surveys were completed at approximately 1905. Results indicated removable surface contamination on two of the nine radioactive material packages that exceeded the criteria of the cited regulations.
BUT THEY SHIPPED THEM ON TO TENNESSEE ANYWAY!!!
"The radioactive material shipment left the Westinghouse Electric Company facility at 1300 [EST] on March 3, 2016. It was received at the NFS receiving facility (IN ERWIN, TN) at approximately 1745 on March 3, 2016.
Surface contamination and radiation surveys were initiated immediately upon receipt. Removable surface contamination in excess of 10 CFR 20.1906(d) limits was verified to be present on the external surface of two of the nine shipping containers in the shipment at 1905.
Contamination was controlled at the receiving facility and successfully decontaminated below criteria of 10 CFR 20.1906(d) by approximately 2030 on March 3, 2016."
This was an exclusive shipment.
The alpha contamination measured 4278 dpm/100 sq. cm. and 6345 dpm/100 sq. cm., respectively.
The licensee informed Westinghouse who is conducting an investigation into this incident. "
ISN'T THAT LIKE ASKING THE FOX TO REPORT ON WHAT HAPPENED TO ALL THE CHICKENS IN THE HEN-HOUSE HE WAS CAUGHT IN?
BUT THAT 'REPORT' DOESN'T QUITE TELL THE WHOLE TALE.
MICHAEL COLLINS OVER AT MINING AWARENESS PLUS FILLS US IN A BIT MORE:
[EMPHASIS ADDED BY THE TEA ROOM]
"Westinghouse is now a Toshiba (Japan) subsidiary.
It is 87% Toshiba owned; 10% Kazatomprom (Kazakhstan State owned), and 3% IHI (Japan) owned.
The first US NRC “event” apparently has to do with down-blending of HEU (highly enriched uranium) and LEU (low enriched uranium) recovery.
Some of the containers for the radioactive material shipped from South Carolina to Tennessee had high levels of alpha radiation on the outside.
The highest was 106 Bq (disintegrations, shots, per second) per 100 sq cm (i.e. 10 x 10 cm or 4 x 4 inches). Nuclear is lethal through its entire fuel chain.
Any one of these shots can cause genetic damage, which may or may not be properly repaired, and which can thus lead to cancer or other diseases, which may sometimes even be inherited.
Alpha emitters are particularly damaging and thus difficult to repair.
How much, if any, of this radioactive dust blew through the air?
How much, if any, fell upon crops?
In short, who may have been exposed, or may be exposed, along the route?
Alpha radiation is extremely dangerous upon ingestion, also upon inhalation.
NOT THE FIRST TIME FOR THIS FACILITY
“Fuel Cycle Facility
Event Number: 51425
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
Notification Date: 09/25/2015
Event Date: 09/25/2015
Last Update Date: 09/25/2015
OFFSITE NOTIFICATION DUE TO EMPLOYEES INJURED BY NON-RADIOACTIVE HIGH TEMPERATURE WATER AND STEAM
“On September 25, 2015 at roughly 0430 EDT, four employees were in the work area when high temperature water and steam released from a wash operation in the Final Assembly Area.
The cause of the water/steam release is unknown at this time, and a comprehensive investigation is underway.
[TEA ROOM NOTE: UNKNOWN BECAUSE, TO ADMIT THEY DO KNOW, COULD MEAN THEY GET THEIR ENTIRE BEHINDS SUED COMPLETELY OFF!]
The area is in a safe, shutdown state, and is roped off to preserve the scene.
[ROPED OFF AND "HOT"?]
The event did not involve any special nuclear material or contamination and is classified as an industrial safety incident.
“Three of the four employees were affected by the high temperature water/steam and were transported by ambulance to the hospital for treatment.
“This concurrent report is being made under Paragraph c of 10 CFR 70, Appendix A because in-patient hospitalization requires a 24 hour report to the South Carolina Department of Labor.”
AND IT IS ONLY MARCH 15 NOW...BEWARE THE IDES OF MARCH?
GO HAVE A READ AT THE NRC'S READING ROOM ON EVENT NOTIFICATIONS SOMETIMES... IT'S AN EYE-OPENER.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/
THE NRC LIKES TO LET US THINK WE HAVE A SAY IN SOME AREAS OF THEIR "NUCLEAR REGULATIONS", BUT THAT REALLY IS NOT THE CASE AS HISTORY AUS.
PUBLIC COMMENT MAY BE 'INVITED' BUT THE NRC GOES RIGHT AHEAD AND DOES AS IT PLEASES, OR AS THE NUKE INDUSTRY PLEASES...
STILL, THEY DO PUBLISH 'PUBLIC COMMENTS', USUALLY AFTER MONTHS HAVE PASSED, SO ANYONE INTERESTED IN LEAVING THEM A COMMENT ON CURRENT "DOCUMENTS", GO TO http://www.nrc.gov/public-involve/doc-comment.html
Rulemaking-Related Documents
The NRC began managing rulemaking-related actions on the Government-wide Regulations.gov Web site in January 2008. The public can submit comments on NRC rulemaking actions through that site; see Navigating Rulemaking-Related Documents.
| Docket ID | Title | Comment Period Close Date |
|---|
| NRC-2015-0070 |
| Regulatory Improvements for Power Reactors Transitioning to Decommissioning |
| 03/18/2016 |
| NRC-2015-0213 |
| Determining Which Structures, Systems, Components and Functions are Important to Safety |
| 03/21/2016 |
| NRC-2015-0270 |
| List of Approved Spent Fuel Storage Casks – Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 10 |
| 04/13/2016 |
| NRC-2015-0109 |
| Physical Protection of Category 1 and Category 2 Quantities of Radioactive Materials |
| 05/13/2016 |
| NRC-2012-0059 |
| Incorporation by Reference of Revisions of ASME Regulatory Guides |
| 05/16/2016 |
_____________________
A POSTSCRIPT:
MIXED IN WITH THE NUCLEAR MOMENTS REPORTED ON THE NRC READING ROOM ARE LOST RADIOACTIVE EQUIPMENT AND LOST OR STOLEN BITS AND PIECES LIKE THE ONES DESCRIBED BELOW:
"(i) Lost device ECD, Serial# B794, Model# 03-917440-00, isotope Ni-63, activity 15 mCi, was manufactured by Varian Associates, Inc.
(ii) Lost device ECD, Serial# A10856, Model# 02-0001972-00, isotope Ni-63, activity 15 mCi, was manufactured by Varian Associates, Inc.
(iii) Both ECDs were not located in a recent inventory check.
(iv) Both ECDs were more than likely returned to Varian for disposal before 2008.
(v) No KNOWN exposures have been reported from this ECD at this time.
(vi) [EEA] performed a thorough search of the facility and in-house records.
In addition, [EEA] attempted to contact Varian. In 2010 Varian was sold off to Agilent and Buker Corp. Buker Corp then sold off their portion of Varian Gas Chromatography equipment to Scion in 2014. All three companies were contacted in order to determine who currently holds the Varian ECD records.
None of the companies contacted claimed to hold the records.
(vii) [EEA] NOW [NOW, NOT THEN?] maintains a list of ECDs showing each ECD location. The list is maintained by the laboratory and monitored by the RSO."
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIA.
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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