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On March 31, 2018, during the Indian Point … On March 31, 2018, during the Indian Point Unit 2 refueling outage, with the reactor defueled and the head removed and located on the head stand, and all fuel from the reactor vessel removed and located in the spent fuel pool, while performing planned examinations on the 97 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per the requirements of 10CFR50.55a for the reactor coolant system pressure boundary. The examinations are being performed to the meet the requirements of 10CFR50.55a(g)(6)(ii)(D), and ASME Code Case N-729-4, to find potential flaws/indications well before they increase to a degree that could potentially challenge the reactor vessel head pressure boundary. All other reactor vessel head penetrations have had a bare metal visual inspection completed with no other indications identified. The station is currently performing the remaining non-destructive examinations required by Code Case N-729-4.</br>Repairs are currently being planned, and will be completed prior to entering Mode 5 from the current refueling outage.</br>This is reportable, pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-4 to remain in-service without repair.</br>The NRC Resident Inspector has been informed. </br>The licensee has also notified the NY Public Service Commission.notified the NY Public Service Commission. +
04:00:00, 31 March 2018 +
53,305 +
19:33:00, 31 March 2018 +
04:00:00, 31 March 2018 +
On March 31, 2018, during the Indian Point … On March 31, 2018, during the Indian Point Unit 2 refueling outage, with the reactor defueled and the head removed and located on the head stand, and all fuel from the reactor vessel removed and located in the spent fuel pool, while performing planned examinations on the 97 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per the requirements of 10CFR50.55a for the reactor coolant system pressure boundary. The examinations are being performed to the meet the requirements of 10CFR50.55a(g)(6)(ii)(D), and ASME Code Case N-729-4, to find potential flaws/indications well before they increase to a degree that could potentially challenge the reactor vessel head pressure boundary. All other reactor vessel head penetrations have had a bare metal visual inspection completed with no other indications identified. The station is currently performing the remaining non-destructive examinations required by Code Case N-729-4.</br>Repairs are currently being planned, and will be completed prior to entering Mode 5 from the current refueling outage.</br>This is reportable, pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-4 to remain in-service without repair.</br>The NRC Resident Inspector has been informed. </br>The licensee has also notified the NY Public Service Commission.notified the NY Public Service Commission. +
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00:00:00, 31 March 2018 +
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>.
11:30:52, 2 April 2018 +
19:33:00, 31 March 2018 +
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0.648 d (15.55 hours, 0.0926 weeks, 0.0213 months) +
04:00:00, 31 March 2018 +
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