9/5/14 Power Reactor Event Number: 50427 Facility: QUAD CITIES Region: 3 State: IL Unit: [1] [2] CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INOPERABLE On September 04, 2014, at 1905 hours [CDT], the Control Room Emergency Ventilation (CREV) system was declared inoperable due to the Air Handling Unit (AHU) tripping upon restoration of Control Room Ventilation following testing of Reactor Building Ventilation instrumentation. Troubleshooting is in progress at this time. Technical Specification 3.7.4, Condition A, was entered which requires the CREV system to be restored to an operable status in seven (7) days. Additionally, Technical Specification 3.7.5, Condition A, was entered which requires CREV AC to be restored to an operable status in 30 days. This notification is being made in accordance with 10CFR50.72(b)(3)(v)(D), [any] event or condition that could have prevented fulfillment of a safety function, because the CREV system is a single train system required to mitigate the consequences of an accident. The licensee has notified the NRC Resident Inspector. Power Reactor Event Number: 50424 Facility: PRAIRIE ISLAND Region: 3 State: MN Unit: [1] 1R-50 SHIELD BUILDING HIGH RANGE VENT GAS RADIATION MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE At 0843 CDT on September 4th, 2014, 1R-50 High Range Shield Building Vent Gas Monitor was removed from service for planned maintenance. This monitor provides indication of release of gaseous radioactivity to the environment. There is not a compensatory measure that will allow timely classification of two Emergency Action Levels when out of service: General Emergency Event RG1.1 and Site Area Emergency Event RS1.1. This results in a loss of emergency assessment Capability while 1R-50 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii). Unit 1 Shield Building ventilation stack is also monitored by radiation monitor 1R-22 that is used for the same purpose in Alert or Unusual Event Emergency classifications. 1R-22 is being monitored and is indicating normal values. There are no radioactive leaks that will impact the Shield Building as evidenced by normal readings on 1R-50 prior to its removal from service. The maintenance is scheduled for ten hours or will continue until the monitor is returned to service. Maintenance will not result in the unplanned release of radioactivity to the environment and will not affect the safe operation of the plant or health and safety of the public. The licensee has notified the NRC Resident Inspector. !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! Non-Agreement State Event Number: 50420 Rep Org: NATIONAL INST OF STANDARDS & TECH Licensee: NATIONAL INST OF STANDARDS & TECH Region: 1 City: GAITHERSBURG State: MD UNPLANNED CONTAMINATION INCIDENT IN THE RESEARCH REACTOR FACILITY At approximately 1600 EDT on 08/29/14, a 60 nanocurie Pu-239 wafer source dropped from its holder during change out following neutron irradiation in building 235 (Research Reactor Test Facility). The wafer struck the floor and cleaved in half. Radiation surveys confirmed alpha contamination of approximately 200 counts per minute. The area was decontaminated, resurveyed and released. The licensee will notify their NMSS PM (Naquin) and the State of Maryland Department of Environment as a courtesy. * * * UPDATE AT 1840 EDT ON 08/30/14 FROM TOM OBRIEN TO STEVE SANDIN VIA EMAIL * * * Follow-up to the dropped source (Pu-239 RS# 87-0039(4) on 8/29/14)) at NG-6MAll personnel involved have been evaluated, with the exception of two nasal swipes, on two separate individuals not directly involved with the incident, but near the location, reporting about 0.17 dpm alpha each, all surveys find the personnel to be clear of contamination. It is believed the two 0.17 dpm nasal swipes are statistically not different than zero, follow-up measurements will be done to confirm this. Even if we assume them to be positive, the resulting estimated dose from these measurements would be on the order of 10 mrem. The NG-6M instrument area has been surveyed and cleared for normal use. All contamination swipe surveys of the floor, tools, furniture and equipment potentially involved in this incident have been found to be clean. With the exception of one alpha instrument survey, all surveys with alpha and beta/gamma survey instruments have found levels less than or equal to background. The one survey where positive indication was found was performed at the source drop location, directly underneath where the source fell. This survey was done after the source was retrieve. Initially measured about 200 cpm alpha contamination and very localized, the spot was carefully deconned and subsequent surveys found to be less than or equal to background. All swipes of this spot were also found to be clean. The source has been safely retrieved, secured and is locked in our safe in A134. No removable contamination was found on the source containers or during retrieval of the source. Gamma spectrum measurements of the retrieved source, detecting the Am-241 trace nuclide, and correlating this activity by know nuclide ratios find that the Pu-239 activity of the source is within good agreement of the original activity of the source (2190 Bq). While this confirmation has many errors incorporated into it, it is the best measurement we can make at this time, that along with the negative findings of any removable contamination to speak of, and visual inspections of the source, I conclude that to the best of my knowledge, the source material is intact on the broken source substrate pieces, inside the source container. Careful follow-up measurements would need to be performed to confirm this for certain, but based on the info I have at present this is my conclusion. Notified R1DO (Mangan), NMSS EO (Stablein) and NMSS PM (Naquin). * * *RETRACTION PROVIDED FROM TOM OBRIEN TO JEFF ROTTON AT 1425 EDT ON 09/04/2014 * * * Upon detailed review of the incident data NIST is requesting retraction of this notification on the basis that 70.50 (b)(1)(i) and (ii) are not applicable to this event and therefore no 24 hour (or other notification) was required. Access to the contaminated area was restricted for less than 24 hours. Additionally, at the time of initial reporting on 8/30/2014, the most conservative annual limit on intake (ALI) was used as the chemical composition was not yet known. As of today, 9/3/2014, we have confirmed that the radioactive material is in the form of PuO2. This additional information indicates that the involved quantity of radioactive material was less than five times the lowest ALI for Pu-239. Since the initial report of 8/30/2014, there has been no other contamination detected. The nasal-swab measurements were analyzed for a longer time period and have been determined to be less than the minimum detectable activity. NIST is evaluating the incident for lessons learned and extent of conditions and will advise [NRC] Region I and our [NRC] Project Manager of the outcome. Licensee also requested that the first sentence of the [original] Event Text be corrected as indicated below as the source was not subjected to neutron irradiation. At approximately 1600 EDT on 08/29/14, a 60 nanocurie Pu-239 wafer source (that was going to be used to calibrate an instrument detector) dropped from its holder during transfer in building 235 (Research Reactor Test Facility). Notified R1DO (Ferdas), NMSS EO (Smith) and NMSS PM (Naquin). and other reportable events... nrc.gov/reading-rm/doc-collections/event-status/event/en.html
Posted on: Fri, 05 Sep 2014 10:48:15 +0000
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