combined page for the following sub criteria.
3.2.4 Degraded or Unanalyzed Condition
§ 50.72(b)(3)(ii)
"Any event or condition that results in:
- (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded; or
- (B) The nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."
§ 50.73(a)(2)(ii)
"(a)(2)(ii) Any event or condition that resulted in:
- (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;
- (B) The nuclear power plant being in an unanalyzed condition that significantly degraded plant safety." In a condition that is outside the design basis of the plant; or In a condition not covered by the plant’s operating and emergency procedures." In a condition that was outside the design basis of the plant; or In a condition not covered by the plant's operating and emergency procedures.
An LER is required for a seriously degraded principal safety barrier or an unanalyzed condition that significantly degrades plant safety. If not reported under § 50.72(a), (b)(1), or (b)(2) an ENS notification is required under § 50.72(b)(3) [an 8-hour report].
Discussion
(A) Nuclear Power Plant, Including Its Principal Safety Barriers, Being Seriously Degraded
This criterion applies to material (e.g., metallurgical or chemical) problems that cause abnormal degradation of or stress upon the principal safety barriers (i.e., the fuel cladding, reactor coolant system (RCS) pressure boundary, or the containment). Abnormal degradation of a barrier may be indicated by the necessity of taking corrective action to restore the barrier’s capability, as is the case in some of the examples discussed below. Abnormal stress upon a barrier may result from an unplanned transient, as is the case in one of the examples discussed below. The following are examples of reportable events and conditions:
- (1) Fuel cladding failures in the reactor, or in the storage pool, that exceed expected values, or that are unique or widespread, or that are caused by unexpected factors.
- (2) Welding or material defects in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600, “Analytical Evaluation of Flaws,” or ASME Section XI, Table IWB-3410-1, “Acceptance Standards.”
- (3) Serious steam generator tube degradation. A licensee’s plant-specific TS contain performance criteria for steam generator tube integrity, which includes structural integrity, accident induced leakage, and operational leakage. Steam generator tube degradation is considered serious only if either the steam generator structural integrity or accident-induced leakage performance criteria are not met.
- In addition, one or more steam generator tubes satisfying the tube repair criteria and not plugged or repaired in accordance with the steam generator program is not considered to be serious steam generator tube degradation and therefore is not reportable as a “Degraded or Unanalyzed Condition,” as long as the structural integrity and accident-induced leakage performance criteria are both met.
- (4) Low temperature over pressure transients in which the pressure-temperature relationship violates pressure-temperature limits derived from Appendix G, “Fracture Toughness Requirements,” to 10 CFR Part 50 (e.g., TS pressure-temperature curves).
- (5) Loss of containment function or integrity, including containment leak rate tests in which the total containment as-found, minimum-pathway leak rate exceeds limits in the facility’s TS.<ref>The LCO typically employs La, which is defined in Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,” to 10 CFR Part 50 as the maximum allowable containment leak rate at pressure Pa, the calculated peak containment internal pressure related to the design-basis accident. “Minimum pathway leak rate” means the minimum leak rate that can be attributed to a penetration leakage path; for example, the smaller of either the inboard or outboard valve’s individual leak rates.</ref>
(B) Unanalyzed Condition that Significantly Affects Plant Safety
The 1983 Statements of Consideration for 10 CFR 50.72 and 50.73 indicated the following with regard to an unanalyzed condition that significantly compromises plant safety:
The Commission recognizes that the licensee may use engineering judgment and experience to determine whether an unanalyzed condition existed. It is not intended that this paragraph apply to minor variations in individual parameters, or to problems concerning single pieces of equipment. For example, at any time, one or more safety-related components may be out of service due to testing, maintenance, or a fault that has not yet been repaired. Any trivial single failure or minor error in performing surveillance tests could produce a situation in which two or more often unrelated, safety-grade components are out-of-service.
Technically, this is an unanalyzed condition. However, these events should be reported only if they involve functionally related components or if they significantly compromise plant safety.<ref>48 FR 39042, August 29, 1983, and 48 FR 33856, July 26, 1983.</ref>
When licensees are applying engineering judgment, and there is a doubt regarding whether or not to report, the Commission’s policy is that licensees should make the report.<ref>48 FR 39042, August 29, 1983.</ref>
For example, small voids in systems designed to remove heat from the reactor core that have been previously shown through analysis not to be safety significant need not be reported.
However, the accumulation of voids that could inhibit the ability to adequately remove heat from the reactor core, particularly under natural circulation conditions, would constitute an unanalyzed condition and would be reportable.<ref>48 FR 39042, August 29, 1983, and 48 FR 33856, July 26, 1983.</ref>
In addition, voiding in instrument lines that results in an erroneous indication causing the operator to misunderstand the true condition of the plant is also an unanalyzed condition and should be reported.<ref>48 FR 39042, August 29, 1983, and 48 FR 33856, July 26, 1983.</ref>
The level of significance of these cases generally corresponds to the inability to perform a required safety function. For instance, accumulation of voids that could inhibit the ability to adequately remove heat from the reactor core, particularly under natural circulation conditions, has an effect similar to a condition that could prevent the fulfillment of the safety function of the AFW system.
Beyond the examples given in 1983, an example of an event reportable as an unanalyzed condition that significantly degraded plant safety would be the discovery that a system required to meet the single failure criterion does not do so.
In another example, if fire barriers are found to be missing, such that the required degree of separation for redundant safe shutdown trains is lacking, the event would be reportable as an unanalyzed condition that significantly degraded plant safety. On the other hand, if a fire wrap, to which the licensee has committed, is missing from a safe shutdown train but another safe shutdown train is available in a different fire area, protected such that the required separation for safe shutdown trains is still provided, the event would not be reportable.
Examples
(1) Failures of Reactor Fuel Rod Cladding Identified during Testing of Fuel Assemblies Radiochemistry data for a particular PWR indicated that a number of fuel rods had failed during the first few months of operation. Projections ranged from 6 to 12 failed rods.
The end-of-cycle RCS iodine-131 activity averaged 0.025 microcuries per milliliter.
Following the end-of-cycle shutdown, iodine-131 spiked to 11.45 microcuries per milliliter. The cause was a significant number of failed fuel rods. Inspections revealed that 136 of the total 157 fuel assemblies contained failed fuel (approximately 300 fuel rods had through-wall penetrations), far exceeding the anticipated number of failures.
The defects were generally pinhole sized. The fuel cladding failures were caused by long-term fretting from debris that became lodged between the lower fuel assembly nozzle and the first spacer grid, resulting in penetration of the stainless-steel fuel cladding. The source of the debris was apparently a machining byproduct from the thermal shield support system repairs during the previous refueling outage.
The event is reportable because the cladding failures exceed expected values and are unique or widespread.
(2) Reactor Coolant System Pressure Boundary Degradation Due to Corrosion of a Control Rod Drive Mechanism Flange While the plant was in hot shutdown, a total of six control rod drive mechanism (CRDM) reactor vessel nozzle flanges were identified as leaking. Subsequently, one of the flanges was found to be eroded and pitted. While removing the nut ring from beneath the flange, it was discovered that approximately 50 percent of one of the nut ring halves had corroded away and that two of the four bolt holes in the corroded nut ring half were degraded to the point that there was no bolt–thread engagement.
An inspection of the flanges and spiral wound gaskets, which were removed from between the flanges, revealed that the cause of the leaks was the gradual deterioration of the gaskets from age. A replacement CRDM was installed and the gaskets on all six CRDMs were replaced with new-design graphite-type gaskets.
The event is reportable because there is a material defect in the primary coolant system that cannot be found acceptable under ASME Section XI.
(3) Degradation of Reactor Fuel Rod Cladding Identified during Fuel Sipping Operations With the plant in cold shutdown, fuel sipping operations appeared to indicate that a significant portion of cycle 2 fuel, type “LYP,” had failed; i.e., 4 confirmed and 12 potential fuel leakers. The potential fuel leakers had only been sipped once before the ENS notification was made. The licensee contacted the fuel vendor for assistance onsite in evaluating this problem.
An ENS notification was made because the fuel cladding degradation was thought to be widespread. However, additional sipping operations and a subsequent evaluation by the licensee’s reactor engineering department with vendor assistance concluded that no additional fuel failures had occurred; i.e., the abnormal readings associated with the potential fuel leakers was attributed to fission products trapped in the crud layer. Based on the results of the evaluation, the licensee concluded that the fuel cladding was not seriously degraded and that the event was not reportable. Consequently, after discussion with the regional office, the licensee appropriately retracted this event.
References
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WEEKMONTHYEARENS 569742024-02-17T13:37:000Start date: 17 February 2024 13:37:00 Site: Brunswick Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 569592024-02-11T15:11:000Start date: 11 February 2024 15:11:00 Site: Hatch Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 569572024-02-09T18:22:000Start date: 9 February 2024 18:22:00 Site: Peach Bottom Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 569282024-01-18T20:04:000Start date: 18 January 2024 20:04:00 Site: Columbia Reporting criterion: 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 569122024-01-03T17:57:000Start date: 3 January 2024 17:57:00 Site: Saint Lucie Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 569102023-12-28T16:29:000Start date: 28 December 2023 16:29:00 Site: Watts Bar Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 568932023-12-16T01:45:000Start date: 16 December 2023 01:45:00 Site: Saint Lucie Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 568492023-11-10T21:45:000Start date: 10 November 2023 21:45:00 Site: Waterford Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 568342023-11-05T16:33:000Start date: 5 November 2023 16:33:00 Site: Waterford Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 567852023-10-09T22:07:000Start date: 9 October 2023 22:07:00 Site: Palo Verde Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 567742023-10-03T15:54:000Start date: 3 October 2023 15:54:00 Site: North Anna Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 566852023-08-20T20:00:000Start date: 20 August 2023 20:00:00 Site: Fermi Reporting criterion: 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 534562023-07-15T10:39:000Start date: 15 July 2023 10:39:00 Site: Arkansas Nuclear Reporting criterion: 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 566102023-07-06T16:32:000Start date: 6 July 2023 16:32:00 Site: Millstone Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 565692023-06-11T05:30:000Start date: 11 June 2023 05:30:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 565412023-05-25T17:45:000Start date: 25 May 2023 17:45:00 Site: Watts Bar Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 564942023-04-30T05:00:000Start date: 30 April 2023 05:00:00 Site: Hope Creek Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 564852023-04-22T23:42:000Start date: 22 April 2023 23:42:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 564742023-04-15T15:12:000Start date: 15 April 2023 15:12:00 Site: Turkey Point Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 564552023-04-06T20:46:000Start date: 6 April 2023 20:46:00 Site: Perry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 564342023-03-26T20:03:000Start date: 26 March 2023 20:03:00 Site: Susquehanna Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 564212023-03-18T18:10:000Start date: 18 March 2023 18:10:00 Site: Nine Mile Point Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 564112023-03-15T03:57:000Start date: 15 March 2023 03:57:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 563712023-02-18T10:39:000Start date: 18 February 2023 10:39:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 563502023-02-12T13:00:000Start date: 12 February 2023 13:00:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 563422023-02-07T22:38:000Start date: 7 February 2023 22:38:00 Site: Hatch Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 562572022-12-03T16:00:000Start date: 3 December 2022 16:00:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 562212022-11-14T11:30:000Start date: 14 November 2022 11:30:00 Site: Oconee Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 561972022-11-01T18:33:000Start date: 1 November 2022 18:33:00 Site: Oconee Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 561762022-10-23T15:30:000Start date: 23 October 2022 15:30:00 Site: Diablo Canyon Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 561652022-10-15T15:59:000Start date: 15 October 2022 15:59:00 Site: Catawba Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 561532022-10-07T06:19:000Start date: 7 October 2022 06:19:00 Site: Braidwood Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 558962022-05-13T16:11:000Start date: 13 May 2022 16:11:00 Site: Monticello Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 558572022-04-23T13:54:000Start date: 23 April 2022 13:54:00 Site: Byron Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 557062022-01-16T05:20:000Start date: 16 January 2022 05:20:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 555762021-11-14T16:50:000Start date: 14 November 2021 16:50:00 Site: Millstone Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 555742021-11-12T21:05:000Start date: 12 November 2021 21:05:00 Site: Turkey Point Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 555652021-11-06T15:00:000Start date: 6 November 2021 15:00:00 Site: Millstone Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 555602021-11-03T19:31:000Start date: 3 November 2021 19:31:00 Site: Columbia Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 555402021-10-22T05:04:000Start date: 22 October 2021 05:04:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 555062021-10-04T19:33:000Start date: 4 October 2021 19:33:00 Site: Arkansas Nuclear Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 554592021-09-13T22:22:000Start date: 13 September 2021 22:22:00 Site: Surry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 554572021-09-12T21:28:000Start date: 12 September 2021 21:28:00 Site: North Anna Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 554272021-08-24T18:06:000Start date: 24 August 2021 18:06:00 Site: FitzPatrick Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 553752021-07-22T21:51:000Start date: 22 July 2021 21:51:00 Site: North Anna Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 553212021-06-22T16:08:000Start date: 22 June 2021 16:08:00 Site: Davis Besse Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 552752021-05-25T21:51:000Start date: 25 May 2021 21:51:00 Site: Catawba Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 552312021-05-03T13:30:000Start date: 3 May 2021 13:30:00 Site: Fermi Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 552012021-04-21T02:30:000Start date: 21 April 2021 02:30:00 Site: Catawba Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 551222021-03-04T08:23:000Start date: 4 March 2021 08:23:00 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 549942020-11-11T18:11:000Start date: 11 November 2020 18:11:00 Site: Watts Bar Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 549712020-10-29T14:30:000Start date: 29 October 2020 14:30:00 Site: Peach Bottom Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 549302020-10-03T14:13:000Start date: 3 October 2020 14:13:00 Site: Point Beach Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 548972020-09-11T23:30:000Start date: 11 September 2020 23:30:00 Site: Palisades Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 548062020-07-30T13:15:000Start date: 30 July 2020 13:15:00 Site: Callaway Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 547072020-05-13T02:20:000Start date: 13 May 2020 02:20:00 Site: Catawba Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 546802020-04-24T05:30:000Start date: 24 April 2020 05:30:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 546142020-03-26T07:00:000Start date: 26 March 2020 07:00:00 Site: McGuire Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 545332020-02-20T17:40:000Start date: 20 February 2020 17:40:00 Site: FitzPatrick Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 544872020-01-22T03:18:000Start date: 22 January 2020 03:18:00 Site: Sequoyah Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 544632020-01-04T16:09:000Start date: 4 January 2020 16:09:00 Site: Hatch Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 544372019-12-11T18:56:000Start date: 11 December 2019 18:56:00 Site: Surry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 544252019-12-05T14:10:000Start date: 5 December 2019 14:10:00 Site: Cooper Reporting criterion: 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 544172019-11-30T19:00:000Start date: 30 November 2019 19:00:00 Site: Diablo Canyon Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 543662019-11-02T19:15:000Start date: 2 November 2019 19:15:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 543372019-10-17T23:51:000Start date: 17 October 2019 23:51:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 542662019-09-11T00:34:000Start date: 11 September 2019 00:34:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 542572019-09-06T02:15:000Start date: 6 September 2019 02:15:00 Site: South Texas Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material ENS 541302019-06-24T22:15:000Start date: 24 June 2019 22:15:00 Site: FitzPatrick Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 541112019-06-11T16:32:000Start date: 11 June 2019 16:32:00 Site: Monticello Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material ENS 540312019-04-26T16:47:000Start date: 26 April 2019 16:47:00 Site: River Bend Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 539972019-04-12T23:15:000Start date: 12 April 2019 23:15:00 Site: Monticello Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 539682019-04-01T03:06:000Start date: 1 April 2019 03:06:00 Site: Palo Verde Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material ENS 539592019-03-26T15:30:000Start date: 26 March 2019 15:30:00 Site: Browns Ferry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 538372019-01-18T19:33:000Start date: 18 January 2019 19:33:00 Site: Waterford Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 538342019-01-17T06:00:000Start date: 17 January 2019 06:00:00 Site: Waterford Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 538012018-12-20T05:00:000Start date: 20 December 2018 05:00:00 Site: Watts Bar Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 537492018-11-21T05:00:000Start date: 21 November 2018 05:00:00 Site: Palisades Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 537342018-11-11T04:00:000Start date: 11 November 2018 04:00:00 Site: Palisades Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 537332018-11-10T05:00:000Start date: 10 November 2018 05:00:00 Site: Palisades Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 537112018-11-01T04:00:000Start date: 1 November 2018 04:00:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 537122018-11-01T04:00:000Start date: 1 November 2018 04:00:00 Site: Fermi Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536742018-10-19T04:00:000Start date: 19 October 2018 04:00:00 Site: Fermi Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536752018-10-19T04:00:000Start date: 19 October 2018 04:00:00 Site: Perry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536632018-10-11T04:00:000Start date: 11 October 2018 04:00:00 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536522018-10-08T05:00:000Start date: 8 October 2018 05:00:00 Site: Braidwood Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 536462018-10-05T05:00:000Start date: 5 October 2018 05:00:00 Site: Cooper Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 536442018-10-04T04:00:000Start date: 4 October 2018 04:00:00 Site: Perry Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536222018-09-25T05:00:000Start date: 25 September 2018 05:00:00 Site: River Bend Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 536172018-09-21T04:00:000Start date: 21 September 2018 04:00:00 Site: Peach Bottom Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 535972018-09-11T05:00:000Start date: 11 September 2018 05:00:00 Site: Monticello Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material ENS 535982018-09-11T04:00:000Start date: 11 September 2018 04:00:00 Site: Saint Lucie Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 535892018-09-07T04:00:000Start date: 7 September 2018 04:00:00 Site: Indian Point Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 535482018-08-12T04:00:000Start date: 12 August 2018 04:00:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown ENS 534852018-07-03T05:00:000Start date: 3 July 2018 05:00:00 Site: Callaway Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 534382018-06-01T04:00:000Start date: 1 June 2018 04:00:00 Site: Salem Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 534192018-05-22T04:00:000Start date: 22 May 2018 04:00:00 Site: Beaver Valley Reporting criterion: 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown ENS 534012018-05-14T17:05:000Start date: 14 May 2018 17:05:00 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition ENS 533932018-05-08T06:39:000Start date: 8 May 2018 06:39:00 Site: Farley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 533922018-05-08T04:00:000Start date: 8 May 2018 04:00:00 Site: Farley Reporting criterion: 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
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