05000482/FIN-2014502-01: Difference between revisions

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| identified by = Licensee
| identified by = Licensee
| Inspection procedure = IP 71114.05
| Inspection procedure = IP 71114.05
| Inspector = G Guerra, M Haireg, Guerra M, Haire N, Okonkwo P, Elkmann R, Strobl
| Inspector = G Guerra, M Haireg, Guerram Haire, N Okonkwo, P Elkmann, R Stroble
| CCA = P.2
| CCA = P.2
| INPO aspect = PI.2
| INPO aspect = PI.2
| description = An apparent violation of 10 CFR 50.54(q)(2) was identified involving the failure to maintain adequate methods for assessing the actual or potential consequences of a radiological emergency between September 2012 and November 2013, in accordance with the requirements of 10 CFR 50.47(b)(9). During an exercise conducted on November 13, 2012, the licensee identified that the Electronic Dose Calculation Program did not accurately calculate the consequences of a radiological release through the main vent stack with the effluent monitor in accident mode. The inaccurate calculation was corrected on February 25, 2014. The inspectors determined the failure to maintain a dose assessment process capable of providing a technically adequate estimate of offsite dose was a performance deficiency within the licensees control. This finding is more than minor because it was associated with the emergency response organization performance and the Facilities and Equipment cornerstone attributes. This finding was evaluated using the Emergency Preparedness Significance Determination Process and was preliminarily determined to be of low to moderate safety significance (White) because it was a degraded risk significant planning standard function. The planning standard function was degraded because between September 13, 2012, and November 8, 2013, some calculations used to assess the offsite consequences of a radiological release were inaccurate. This issue has been entered into the licensees corrective action system as Condition Report 2013-0076247.
| description = An apparent violation of 10 CFR 50.54(q)(2) was identified involving the failure to maintain adequate methods for assessing the actual or potential consequences of a radiological emergency between September 2012 and November 2013, in accordance with the requirements of 10 CFR 50.47(b)(9). During an exercise conducted on November 13, 2012, the licensee identified that the Electronic Dose Calculation Program did not accurately calculate the consequences of a radiological release through the main vent stack with the effluent monitor in accident mode. The inaccurate calculation was corrected on February 25, 2014. The inspectors determined the failure to maintain a dose assessment process capable of providing a technically adequate estimate of offsite dose was a performance deficiency within the licensees control. This finding is more than minor because it was associated with the emergency response organization performance and the Facilities and Equipment cornerstone attributes. This finding was evaluated using the Emergency Preparedness Significance Determination Process and was preliminarily determined to be of low to moderate safety significance (White) because it was a degraded risk significant planning standard function. The planning standard function was degraded because between September 13, 2012, and November 8, 2013, some calculations used to assess the offsite consequences of a radiological release were inaccurate. This issue has been entered into the licensees corrective action system as Condition Report 2013-0076247.
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Latest revision as of 19:52, 20 February 2018

01
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Report IR 05000482/2014502 Section 1EP5
Date counted Mar 31, 2014 (2014Q1)
Type: Violation: White
cornerstone Emergency Prep
Identified by: Licensee-identified
Inspection Procedure: IP 71114.05
Inspectors (proximate) G Guerra
M Haireg
Guerram Haire
N Okonkwo
P Elkmann
R Stroble
Violation of: 10 CFR 50.47(b)(9)

10 CFR 50.47

10 CFR 50.54(q)

10 CFR 50.54
CCA P.2, Evaluation
INPO aspect PI.2
'