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| Entered date | Event description | |
|---|---|---|
| ENS 54680 | 24 April 2020 07:00:00 | At 0130 (EDT) on April 24, 2020, during the Beaver Valley Power Station, Unit 2 refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 37 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 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| ENS 51453 | 5 October 2015 15:01:00 | On 10/5/2015, during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, while performing planned ultrasonic examinations (UT) on the 66 reactor vessel head penetrations, it was determined, that two penetrations could not be dispositioned as acceptable per ASME (American Society of Mechanical Engineers) Code Section XI in a Reactor Coolant System pressure boundary. The indications of a degraded condition, on these two penetrations, are not through wall, as no leak path was identified. The examinations are being performed to meet the requirements of 10 CFR 50.55a(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. All 66 reactor vessel head penetrations are scheduled to be examined during the current refueling outage. The plant is currently shutdown and in Mode 6. The reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup. This is reportable, pursuant to 10 CFR 50.72(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. The NRC Resident Inspector has been notified.
The Beaver Valley Power Station Unit 2, FirstEnergy Nuclear Operating Company (FENOC) is retracting the 8-hour non-emergency notification made on 10/05/2015 (EN 51453). This retraction is based on additional examinations and subsequent engineering assessments completed that concluded the penetrations meet the requirements of ASME Code Case N-729-1 as amended by 10CFR50.55a(g)(6)(ii)(D) and no repairs are required. The two reactor head penetration indications, are therefore not reportable, pursuant to 10CFR50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified. R1DO(Gray) has been notified. |