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On 5/01/2014 during the Beaver Valley Powe … On 5/01/2014 during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one of the 66 penetrations of the reactor vessel head would not meet the applicable acceptance criteria. This penetration will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to find potential flaws/indications well before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. Currently 52 of 66 penetrations have been examined, with 51 satisfactory. All of the penetrations will be examined during the current refueling outage.</br>The plant is currently shutdown and in a mode undefined (Defueled) and the reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.</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-729-1 to remain in-service without repair.</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
20:10:00, 1 May 2014 +
18:12:00, 1 May 2014 +
20:10:00, 1 May 2014 +
On 5/01/2014 during the Beaver Valley Powe … On 5/01/2014 during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one of the 66 penetrations of the reactor vessel head would not meet the applicable acceptance criteria. This penetration will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to find potential flaws/indications well before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. Currently 52 of 66 penetrations have been examined, with 51 satisfactory. All of the penetrations will be examined during the current refueling outage.</br>The plant is currently shutdown and in a mode undefined (Defueled) and the reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.</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-729-1 to remain in-service without repair.</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
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00:00:00, 1 May 2014 +
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