| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/16/2015 - 03/17/2015 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 50351 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/07/2014
Notification Time: 20:00 [ET]
Event Date: 08/07/2014
Event Time: 17:07 [EDT]
Last Update Date: 03/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
REBECCA NEASE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 90 | Power Operation | 90 | Power Operation | Event Text UNANALYZED CONDITION DUE TO DISCOVERY OF DEGRADED FIRE BARRIER WALLS
"During a fire inspection activity involving inspection of fire walls that serve as Appendix R barriers, degradation of some fire walls was identified that was sufficient to prevent these walls from meeting Appendix R requirements as 3-hour fire barriers. In the event of a postulated fire in the affected areas, both safe shutdown paths on the affected unit could be compromised. Given this information, the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded penetrations in these same fire areas. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded conditions can be corrected.
"Condition Reports: 850802, 850819"
In addition to automatic fire protection features, the licensee has posted fire watches as a compensatory measure.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM STANLEY STONE TO DONALD NORWOOD AT 1814 EST ON 11/24/2014 * * *
"As part of the 'extent of condition' corrective action for the condition identified in EN 50351, an inspection activity is in progress to inspect the remaining fire walls for conditions similar to those reported on 8/7/2014. During this inspection, another condition was identified involving some degradation of the fire wall between Fire Area 1023 - RPS MG Set Room and Fire Area 1015 - Annunciator Room. In the event of a postulated fire in the affected areas both safe shutdown paths on Unit 1 could be compromised. Given this information, the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded penetrations in these same fire areas and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. The inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS update report and will be documented in a revised LER at the end of the inspection activity.
"Condition Report: 898908."
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Ehrhardt).
* * * UPDATE FROM KENNY HUNTER TO DANIEL MILLS AT 1758 EST ON 11/25/2014 * * *
"As part of the 'extent of condition' corrective action for the condition identified in EN 50351, an inspection activity is in progress to inspect the remaining fire walls for conditions similar to those reported on 8/7/2014. During this inspection, another condition was identified involving some degradation of the fire wall between Fire Area 1016 - 600 Volt Switchgear Room 1C and Fire Area 1017 - 600 Volt Switchgear Room 1D. In the event of a postulated fire in the affected areas, both safe shutdown paths on Unit 1 could be compromised. Given this information the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded penetrations in these same fire areas and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. The inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS update report and will be documented in a revised LER at the end of the inspection activity."
The licensee notified the NRC Resident Inspector.
Notified R2DO (Ernstes).
* * * UPDATE FROM SCOTT BRITT TO DONALD NORWOOD AT 1706 EST ON 12/4/2014 * * *
"As part of the 'extent of condition' corrective action for the condition identified in EN 50351, an inspection activity is in progress to inspect the remaining fire walls for conditions similar to those reported on 8/7/2014. During this inspection, additional conditions were identified involving multiple fire barriers in the control building that affected both safe shutdown paths on Unit 1 and Unit 2 based on the respective inspection results. In the event of a postulated fire in the affected areas both safe shutdown paths on Unit 1 and 2 could be compromised.
"Given this information the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B). Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded penetrations in these same fire areas and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. The inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS update report as required and will be documented in a revised LER at the end of the inspection activity."
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Freeman).
* * * UPDATE AT 1842 EST ON 12/12/2014 FROM G.S. GRIFFIS TO MARK ABRAMOVITZ * * *
"As part of the 'extent of condition' corrective action for the condition identified in EN# 50351, an inspection activity is in progress to inspect the remaining fire walls and associated penetrations for conditions similar to those reported on 08/07/2014. During this inspection, nonconformances of multiple fire barriers were identified that bring into question the functionality of the affected fire barriers that can compromise safe shutdown paths on Unit 1 and 2 based on the respective inspection results. Since additional time is required to further evaluate each nonconformance to conclusively determine if the nonconformance is sufficient to consider the barrier nonfunctional, interim conservative fire actions were taken by considering these fire barriers as nonfunctional. Based on this conservative conclusion, in the event of a postulated fire in the affected areas both safe shutdown paths on Unit 1 and 2 could be compromised. Given this information the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded penetrations and fire walls in most of these same fire areas and will remain in place until the barrier(s) are repaired. Additional fire actions were taken as required to address the additional fire areas identified. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. The inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS Update Report and will be documented in a revised LER at the end of the inspection activity.
"Unit 1 is entering a planned outage due to unrelated activities."
Condition Report: 10000607
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Desai).
* * * UPDATE FROM STANLEY STONE TO DONALD NORWOOD AT 2315 EST ON 1/15/2015 * * *
"As part of the 'extent of condition' corrective action for the conditions identified in EN# 50351, an inspection activity was performed of a fire wall for conditions similar to those reported on 12/12/2014. During this inspection, another condition was identified involving some degradation of the fire wall between Fire Area 1008 - Unit 1 AC Inverter Room and Fire Area 0001 to consider the barrier nonfunctional. In the event of a postulated fire in the affected areas both safe shutdown paths on Unit 1 could be compromised. Given this information the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded fire barriers in these same fire areas and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. The inspection activity is continuing and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS Update Report and will be documented in a revised LER at the end of the inspection activity."
Condition Report: 10013077
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Musser).
* * * UPDATE FROM JOHN MITCHELL TO JEFF HERRERA AT 2025 EST ON 1/21/2015 * * *
"During review and closeout of fire barrier and penetration seals work orders and surveillance procedures performed as part of the 'extent of condition' inspection activity initially described in Event # 50351, the following conditions were identified that in the event of a postulated fire in the respective fire areas listed both safe shutdown paths could be compromised.
"Unit 2 Control Bldg. el. 130', gap in the grout around conduit penetration between fire areas 2013 and 2015
"Unit 1 Reactor Bldg. el. 130', open conduit between fire areas 1203C and 1105
"Given this information the determination was made that this condition meets the reporting criteria of 10 CFR 50.72(b)(3)(ii)(B). Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded fire barriers in the Unit 2 fire area and will remain in place until the affected barrier areas are repaired. Compensatory measures were established for the Unit 1 areas and will remain in place until the affected barriers areas are repaired. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition is repaired. Subsequent similar condition(s) found when performing remaining inspections that meet the reporting requirements will be included in an ENS Update Report and will be documented in a revised LER at the end of the inspection activity.
"Condition Report 10015417
"Condition Report 10015437"
The licensee notified the NRC Resident Inspector.
Notified the R2DO (McCoy).
* * * UPDATE FROM G.S. GRIFFIS TO HOWIE CROUCH AT 1714 EST ON 2/4/15 * * *
"During the review of fire barrier surveillance procedures performed as part of the 'extent of condition' inspection activity for the event initially identified in EN# 50351, some degradation was observed on the east wall of fire area 2006. These nonconforming issues observed on the affected fire wall were identified as affecting both safe shutdown paths for Unit 2. Therefore, in the event of a postulated fire for the affected area, both safe shutdown paths on Unit 2 could be compromised. Given this information, the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded barriers in the same fire area and will remain in place until the wall is repaired. The presence of the compensatory measures, in addition to portable fire protection equipment located in adjacent areas, ensures the safe shutdown paths are preserved until the degraded conditions are repaired. The extent of condition inspection activity is continuing, and this, and any subsequent similar condition(s) that meets the reporting requirements, will be included in an ENS Update Report as required and will be documented in a revised LER at the end of the inspection activity."
CR 10021623
Notified R2DO (HAAG).
* * * UPDATE FROM JOHN MITCHELL TO DANIEL MILLS AT 1823 EST ON 2/18/15 * * *
"During performance of work package closeouts to support the 'extent of condition' inspection activity for the event initially identified in EN# 50351, the following fire barriers were identified as failing to meet the procedure acceptance criteria:
- Three penetrations separating Unit 1 Fire Areas 1013 and 0040
- A fire wall deficiency in the wall separating Unit 1 Fire Areas 1015 and 1013
"These nonconforming issues observed on the affected penetrations and fire wall were identified as affecting both safe shutdown paths for Unit 1. Therefore, in the event of a postulated fire for the affected area, both safe shutdown paths on Unit 1 could be compromised. Given this information, the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded barriers in the same fire area and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to portable fire protection equipment located in adjacent areas ensures the safe shutdown paths are preserved until the degraded conditions are repaired. The extent of condition inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS Update Report as required and will be documented in a revised LER at the end of the inspection activity.
"CR 10028364
"CR 10028366"
The NRC Resident Inspector has been notified. Notified R2DO (Rose).
* * * UPDATE AT 2035 EST ON 02/25/15 FROM SCOTT BRITT TO S. SANDIN * * *
"During the review and closeout of a work package performed as part of the 'extent of condition' for the inspection activity initially described in EN #50351, a fire penetration seal was identified as failing to meet the procedure acceptance criteria. This penetration seal is located in the 2C Diesel Generator (DG) room and passes between Fire Area 2407 and 2408.
"The nonconforming issue observed on the affected penetration was identified as affecting both safe shutdown paths for Unit 2. Compensatory measures were established for the Unit 2 Areas and will remain in place until the affected barriers areas are repaired. The presence of the compensatory measures in addition to portable fire protection equipment located in adjacent areas ensures the safe shutdown paths are preserved until the degraded conditions are repaired. The extent of condition inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS Update Report as required and will be documented in a revised LER at the end of the inspection activity.
"CR 10032202"
The licensee will inform the NRC Resident Inspector. Notified R2DO (Seymour).
* * * UPDATE FROM SCOTT BRITT TO HOWIE CROUCH AT 2000 EST ON 3/4/15 * * *
"During an expanded scope inspection, two deficiencies in the following areas were observed that caused the affected barriers to be considered nonfunctional:
- Small imperfections and a hole through Penetration 1Z43-H116C that passes between Fire Area 1101G (Unit 1 Reactor Building Closed Cooling Water (RBCCW) Room) and Fire Area 1006 (Unit 1 Water Analysis Room), and
- Gaps in a civil/architectural joint at the top of the south wall leading from Fire Area 1006 (Unit 1 Water Analysis Room) to Fire Area 0007A (East Corridor in the Control Bldg.).
"These nonconforming conditions observed for the affected penetration and fire barrier were identified as affecting both safe shutdown paths for Unit 1. Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded barriers in the same fire area and will remain in place until the wall is repaired. The presence of the compensatory measures in addition to portable fire protection equipment located in adjacent areas ensures the safe shutdown paths are preserved until the degraded conditions are repaired. The expanded scope inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS update report as required and will be documented in a revised LER at the end of the inspection activity.
"CR 10035730"
The licensee will be notifying the NRC Resident Inspector. Notified R2DO (Sykes).
* * * UPDATE FROM SCOTT BRITT TO DANIEL MILLS AT 2047 EDT ON 3/16/15 * * *
"During an expanded scope inspection, deficiencies in the following areas were observed that caused the affected barriers to be considered nonfunctional:
- Imperfections in three penetration seals (2Z43-H037C, 2Z43-H038C, and 2Z43-H177C) located in the 2A Battery Room separating Unit 2 Fire Areas 2004 and 2005
- Imperfections in fire penetration seal 2Z43-H644C located in the U2 Water Analysis Room separating Fire Area 2006 and 0007A
- Imperfections in the grout between two tiers of concrete masonry wall and at the intersection of the walls in the upper northeast corner of the U2 Water Analysis Room separating Fire Areas 2006 and 0007A
"The nonconforming conditions observed for the affected penetrations and fire barriers were identified as affecting both safe shutdown paths for Unit 2. Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions involving degraded barriers in the same fire areas and will remain in place until the fire barriers are repaired. The presence of the compensatory measures in addition to portable fire protection equipment located in adjacent areas ensures the safe shutdown paths are preserved until the degraded conditions are repaired. The expanded scope inspection activity is continuing, and this and any subsequent similar condition(s) that meets the reporting requirements will be included in an ENS Update Report as required and will be documented in a revised LER at the end of the inspection activity.
"CR 10041392, CR 10041394, and CR 10041397"
The NRC Resident Inspector will be notified. Notified R2DO (Shaeffer) |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50744 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: PIERCE C. MOORE
HQ OPS Officer: VINCE KLCO | Notification Date: 01/19/2015
Notification Time: 14:24 [ET]
Event Date: 01/19/2015
Event Time: 11:00 [CST]
Last Update Date: 03/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID PROULX (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MISSILE DOOR MISALIGNED RESULTS IN A REDUCTION IN ACCIDENT MITIGATION
"The missile door (door 33012) protecting Class 1E Engineered Safety Features (ESF) buses NB01/NB02 switchgear rooms was discovered misaligned on its hinge and stuck partially open and not capable of being closed. The missile door has since been repaired and closed. Technical Specification (TS) 3.8.9, 'Distribution Systems- Operating,' was declared not met and Condition F entered when the immediate operability determination identified that buses NB01 and NB02 were inoperable. Condition F of TS 3.8.9 requires immediate entry into Limiting Condition for Operation (LCO) 3.0.3. LCO 3.0.3 was entered at 1100 CST and subsequently exited when the missile door was repaired at 1118 CST. The unit was in and still is in MODE 1 at 100% power. No actions were initiated to commence a unit shut down. The NRC resident inspector was contacted regarding this event. All systems functioned as expected."
* * * RETRACTION FROM TRAVIS ROHLFING TO HOWIE CROUCH AT 1458 EDT ON 3/16/15 * * *
"The licensee is retracting this event based on the following:
"An engineering evaluation concluded that the weather conditions during the period of the event did not result in the threat of a tornado. Given that the weather during the event would not have presented a valid threat of a tornado, the stuck open missile door would not have prevented the ESF busses and the DGs [Diesel Generators] from performing their specified safety function. The ESF busses and the DGs were considered OPERABLE but degraded. This is analogous to Example 4 in RIS 2001-09, 'Control of Hazard Barriers', with the exception that this event did not occur as a result of planned maintenance or a plant modification. As such, this event has been determined to not be reportable per 10 CFR 50.72(b)(3)(v)(D)."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Gepford). |
| Fuel Cycle Facility | Event Number: 50776 | Facility: B&W NUCLEAR OPERATING GROUP, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: KENNY KIRBY
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 01/28/2015
Notification Time: 16:22 [ET]
Event Date: 01/09/2015
Event Time: 16:00 [EST]
Last Update Date: 03/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
ANTHONY MASTERS (R2DO)
JACK GUTTMANN (NMSS)
FUELS GROUP (OUO) (EMAI)
NMSS EVENTS NOTIFICA (EMAI)
| Event Text UNANALYZED CONDITION WHILE CLEANING THE CATCH TRAY
"I. EVENT DESCRIPTION
"Scrap material resulting from various operations at B&W NOG-L's facilities is processed in the Low Level Dissolver (LLD) to reclaim as much of the uranium as possible. Since the material is scrap (e.g., filters, vacuum cleaner bags, etc.), it contains only small amounts of uranium bearing materials. On occasion during processing a slight amount of material will spill over the edge of the dissolver trays, filter bowls, or when hand-transferring material between the trays and filter bowls. These small spills collect on a large catch tray in the bottom of the enclosure. Periodically the catch tray is cleaned to limit the amount of material buildup. By procedure the solid material is to be scraped up and collected in a [less than or equal to] 2.5 liter container. During the cleanout the LLD process is shutdown.
"On January 9, 2015, the LLD process was shutdown and the enclosure was undergoing a routine cleanout. However on this occasion the operators scraped the material on the tray into several piles for subsequent collection into containers. The volume of most of the piles exceeded the 2.5 liter limit. However, the spacing between the piles was greater than the 15 inch limit, and the net weight of any single pile was less than the 7 kg limit for a 2.5 liter volume containing an unknown amount of U-235 . NDA [Non-Destructive Assay] measurements later determined the U-235 content of the piles ranged from 6.5 to 20.8 grams. There was no risk of a criticality accident. The accident scenarios for [less than or equal to] 2.5 liter containers of an unknown amount of U-235 were reviewed to analyze the event. At that point in time it was concluded the performance requirements of 10 CFR 70.61 were maintained.
"At 0900 EST on January 28, 2015, during discussion with the NRC as part of a regularly scheduled NCS inspection the applicability of these scenarios to the event came into question. The scenarios assume the material is containerized rather than in piles. Some of the IROFS [item relied on for safety] were therefore considered not available in this particular situation.
"II. EVALUATION OF THE EVENT
"The cleanup process as analyzed assumed the material was scraped up and collected in [less than or equal to] 2.5 liter containers. The scraping of the material into piles for subsequent collection into containers is a different process than what had been analyzed. The scenarios for the handling of materials containing an unknown amount of U-235 assume the material is containerized rather than in piles. Some of the IROFS credited in these scenarios were therefore not available for the collection of the material in piles. Although the as-found condition presented no safety concern, the scenarios as documented in the ISA [Integrated Safety Analysis] did not demonstrate the performance requirements of 10 CFR 70.61 were maintained.
"There was no immediate risk of a criticality or threat to the safety of workers or the public as a result of this event.
"Ill. NOTIFICATION REQUIREMENTS
"B&W is making this 24 hour report in accordance with 10 CFR 70, Appendix A, (b)(1) - Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61.
"IV. STATUS OF CORRECTIVE ACTIONS
"An investigation of the root causes of this event is ongoing. Corrective actions will be determined as a result of the investigation."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM TONY ENGLAND TO JOHN SHOEMAKER AT 0908 EST ON 2/11/15 * * *
"I. EVENT DESCRIPTION
"On January 28, 2015 B&W NOG-L notified the NRC of an unanalyzed condition that occurred during the cleanup of residual solids from the Uranium Recovery Low Level Dissolver that failed to meet the performance requirements of 10 CFR 70.61. As part of the subsequent investigation of the event an Extent of Condition Review was performed. During the Extent of Condition Review of cleanup of residual solids from the High Level Dissolver, a similar potential condition was identified at 10:00 a.m. EST on February 10, 2015. A cleanup activity was not in process at the time of discovery.
"II. EVALUATION OF THE EVENT
"The Uranium Recovery High Level Dissolvers process scrap fuel materials. Undissolved residual solids collect in the Dissolvers' recirculation columns over time. These solids contain some amounts of U-235 that did not go into solution. The Dissolvers periodically undergo cleanup operations during inventory or contract changes. During this cleanout a small amount of solids are emptied from the horizontal recirculation columns onto drip pans and then transferred to a favorable volume less than or equal to 2.5 liter container. Although a cleanup was not in process at the time of the Extent of Condition Review, it could not be readily determined that the performance requirements of 10 CFR 70.61 would be met if a cleanup operation were to be performed. There was no immediate risk of a criticality or threat to the safety of workers or the public. No actual event occurred.
"Ill. NOTIFICATION REQUIREMENTS
"B&W is revising Event Report #50776 dated January 28, 2015. A potentially unanalyzed condition was identified that could not be demonstrated as meeting the performance requirements. B&W is making this 24 hr. report in accordance with 10 CFR 70, Appendix A, (b)(1) - Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61.
"IV. STATUS OF CORRECTIVE ACTIONS
"An investigation of the root causes of this event is ongoing. Corrective actions will be determined as a result of the investigation. No cleanouts of the High Level Dissolvers' recirculation columns will occur until it can be demonstrated the performance requirements of 10 CFR 70.61 are met for this maintenance task."
The licensee has notified the NRC Resident Inspector.
Notified R2DO (Nease), NMSS EO (Rahimi), Fuels Group, and NMSS Events Notification via email.
* * * UPDATE FROM TONY ENGLAND TO HOWIE CROUCH AT 1619 EDT ON 3/16/15 * * *
"On February 11, 2015 Babcock & Wilcox (B&W) revised Event Report #50776 dated January 28, 2015. An Extent of Condition Review identified an unanalyzed condition associated with the cleanout of a High Level Dissolver (HLD) recirculation column. Although a cleanup was not in process at the time, it could not be readily determined that the performance requirements of 10 CFR 70.61 would be met if a cleanup operation were to be performed. There was no immediate risk of a criticality or threat to the safety of workers or the public. B&W amended the initial Event Report in accordance with 10 CFR 70, Appendix A, (b)(1) - Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61.
"The HLDs process scrap fuel materials. Undissolved residual solids collect in the Dissolvers' recirculation columns over time. These solids contain some amount of U-235 that does not go into solution. The Dissolvers periodically undergo cleanup operations during inventory or contract changes. During this cleanout a small amount of solids are emptied from the horizontal recirculation columns onto drip pans and then transferred to a
favorable volume less than or equal to a 2.5 liter container. Further evaluation has determined that a criticality resulting from the cleanout of a recirculation column is not credible. This determination was made utilizing the guidance found in NUREG 15-20 which defines 'not credible' in part as: 'A process deviation that consists of a sequence of many unlikely human actions or errors in which there is no reason or motive... ' or 'Process deviations for which there is a convincing argument, given physical laws, that they are not possible, or any unquestionably extremely unlikely... '
"The inherent design and process intent of the trough dissolvers, the nature of the chemical reactions involved, and the number of unlikely human errors that would have to occur to accumulate a sufficient amount of fuel and have it collect with a low enough packing fraction and entrained water, combine to make a criticality on the drip pans not credible.
"Although the facility was in a state that was not analyzed, was improperly analyzed, or different from that analyzed in the Integrated Safety Analysis, a criticality was not credible. Therefore, B&W is correcting Event Notification #50776 in accordance with 10 CFR 70.74(a)(4) and withdrawing the 10 CFR 70, Appendix A, (b)(1) notification of February 11, 2015."
The licensee will notify the NRC Resident Inspector. Notified R2DO (Shaeffer), NMSS EO (Araguas) and FUELS OUO Group (email). |
| Power Reactor | Event Number: 50899 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DANA ANTON
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/17/2015
Notification Time: 02:57 [ET]
Event Date: 03/16/2015
Event Time: 18:20 [CDT]
Last Update Date: 03/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
KENNETH RIEMER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECT DECLARED INOPERABLE FOLLOWING SCHEDULED MAINTENANCE
"At 1820 on March 16th, 2015, the High Pressure Coolant Injection (HPCI) system steam lines were re-pressurized following scheduled maintenance. Upon restoration, an alarm was received that indicated condensate may exist in the steam line. The system responded as designed but the alarm did not clear as expected. Without assurance that the condensate has been removed from the HPCI steam line, HPCI remains inoperable for reasons other than the planned maintenance. As a result, this condition is being reported under 10CFR50.72(b)(3)(v)(D) as a condition that could have prevented fulfillment of the safety function at the time of discovery.
"The health and safety of the public was maintained as the plant was in a normal condition with no initiating event in progress.
"The NRC Resident Inspector has been notified."
The licensee will also notify the State of Minnesota. | |