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While investigating operating experience f … While investigating operating experience from another station it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. The operating experience involved setpoint drift of safety related pressure switches beyond what had been accounted for in the station's safety analyses. </br>Following investigation and evaluation, it was determined that pressure switches that provide safety related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated, and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may not occur until slightly higher than the required pressure. Other systems are currently being evaluated to see if this same condition applies.</br>The station is in MODE 5, refueling shutdown condition, and there is no immediate safety concern.</br>The pressure instruments are located in the penetration area which is subject to elevated temperatures.</br>The licensee notified the NRC Resident Inspector.</br>* * * RETRACTION AT 1616 EDT ON 10/19/2012 FROM LUKE JENSEN TO MARK ABRAMOVITZ * * *</br>The condition was initially determined to be reportable under 10CFR50.72(b)(3)(ii)(B), plant in unanalyzed condition, based on a conservative assumption that the error introduced violated not only the Technical Specification limit (5.0 psig) but also the safety analysis limit of 5.4 psig, USAR Table 14.1-1. Subsequent evaluation of actual data concluded that the safety analysis limit was not exceeded and therefore not reportable under 10 CFR 50.72(b)(3)(ii)(B).</br>LER 2012-004-1 reported this condition under 10CFR50.73(a)(2)(i)(B), 10CFR50.73(a)(2)(ix)(A), and 10CFR50.73(a)(2)(v)(A,B,C,D). Revision 2 of the LER will correct the reporting criteria.</br>The NRC Resident Inspector was notified by the licensee.</br>Notified the R4DO (Pick).by the licensee.
Notified the R4DO (Pick).
16:55:00, 2 May 2012 +
19:02:00, 2 May 2012 +
16:55:00, 2 May 2012 +
While investigating operating experience f … While investigating operating experience from another station it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. The operating experience involved setpoint drift of safety related pressure switches beyond what had been accounted for in the station's safety analyses. </br>Following investigation and evaluation, it was determined that pressure switches that provide safety related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated, and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may not occur until slightly higher than the required pressure. Other systems are currently being evaluated to see if this same condition applies.</br>The station is in MODE 5, refueling shutdown condition, and there is no immediate safety concern.</br>The pressure instruments are located in the penetration area which is subject to elevated temperatures.</br>The licensee notified the NRC Resident Inspector.</br>* * * RETRACTION AT 1616 EDT ON 10/19/2012 FROM LUKE JENSEN TO MARK ABRAMOVITZ * * *</br>The condition was initially determined to be reportable under 10CFR50.72(b)(3)(ii)(B), plant in unanalyzed condition, based on a conservative assumption that the error introduced violated not only the Technical Specification limit (5.0 psig) but also the safety analysis limit of 5.4 psig, USAR Table 14.1-1. Subsequent evaluation of actual data concluded that the safety analysis limit was not exceeded and therefore not reportable under 10 CFR 50.72(b)(3)(ii)(B).</br>LER 2012-004-1 reported this condition under 10CFR50.73(a)(2)(i)(B), 10CFR50.73(a)(2)(ix)(A), and 10CFR50.73(a)(2)(v)(A,B,C,D). Revision 2 of the LER will correct the reporting criteria.</br>The NRC Resident Inspector was notified by the licensee.</br>Notified the R4DO (Pick).by the licensee.
Notified the R4DO (Pick).
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00:00:00, 19 October 2012 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
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