Source: http://caferadlab.com/thread-3588.html
Timestamp: 2020-08-13 03:09:53
Document Index: 106424807

Matched Legal Cases: ['ART 21', 'art\n20190513', 'ART21', 'ART 21', 'ART21', 'ART 21', 'art 21', 'art 20190515']

NPS_Watch Jun 03, 2019
Cafe RadLab > Directory > American Continent NPPs > The Daily Dose > NPS_Watch Jun 03, 2019 >
There is 9 EN(s) today, 4 associated with power stations.
NRC Event Notices for June 03, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...603en.html
----------- [ Current event for TX_SouthTx_1 ]
20190601 | TX_SouthTx_1 | OFFSITE NOTIFICATION DUE TO GASOLINE LEAKAGE TO SITE DRAINAGE SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54097
"On June 1,2019, at 1618 [CDT], a notification under 10 CFR 50.72(b)(2) is being made due to notification to offsite agencies as a result of gasoline leakage to the site drainage system in the owner controlled area at South Texas Project.
[ Where does the drainage system drain to? ]
"During a routine tour, the facilities department notified the site environmental group about a gasoline leak on fuel tank sight glass at the fuel island on site.
The site environmental [group] has determined the leak amount requires notification
to the Texas Commission of Environmental Quality and the Environmental Protection Agency National Response Center.
"The Texas Commission of Environmental Quality was notified at 1618 on June 1, 2019,
and the Environmental Protection Agency National Response Center at 1626 on June 1, 2019.
The licensee stated that approximately 1,384 gallons of gasoline leaked over a period of time.
The spill is located at an equipment warehouse area at a distance from the plant.
The leak has been isolated and the cleanup is expected to be completed by tomorrow.
----------- [ 2019 event history for TX_SouthTx ]
20190423 | TX_SouthTX_1;2 | FITNESS FOR DUTY REPORT - ALGORITHM USED FOR RANDOM TESTING EXCLUDED A POPULATION OF INDIVIDUALS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54024
20190306 | TX_SouthTX_1;2 | PART 21 REPORT - TARGET ROCK SOLENOID VALVE 810000-X POSITIONER CIRCUIT FAILURE MAY CAUSE UNDESIRED POSITION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53912
20190601 | LA_RiverBend_1 | MANUAL REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL |
"At 2345 CDT at River Bend Station (RBS) Unit 1,
a manual Reactor scram was inserted in anticipation of receiving an automatic Reactor Water Level 3 (9.7") scram
due to the isolation of the 'B' Heater String with the 'A' Heater String already isolated.
The 'B' heater string isolation caused loss of suction and subsequent trip of the running Feed Water Pumps 'A' and 'C'.
All control rods fully inserted with no issues.
Subsequently Reactor level was controlled by the Reactor Core Isolation Cooling (RCIC) system.
Feed Water Pump 'C' was restored 4 minutes after the initial trip and the RCIC system secured.
Currently RBS-1 is stable and is being cooled down using Turbine Bypass Valves.
----------- [ 2019 event history for LA_RiverBend ]
20190514 | LA_RiverBend_1 | restart
20190513 | LA_RiverBend_1 | shutdown
20190511 | LA_RiverBend_1 | Exit RFO ( 42 / 34 )
20190426 | LA_RiverBend_1 | THROUGH WALL LEAK ON STANDBY LIQUID CONTROL SYSTEM PIPING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54031 |
RFOD_028; RX Mode: Refueling; Refueling
20190330 | LA_RiverBend_1 | Begin RFO ( 01 / 34 )
20190531 | PART21 | PART 21 NOTIFICATION - INTROL POSITIONERS POTENTIAL LATENT DEFECT |
"Introl Positioners used by stations in G32 Terry Turbine control applicators have the potential to contain a latent defect.
The defect is the result of internal corrosion which has been identified in Tl Operational Amplifiers Part No.TL084CN
on the SL3EX Controller Boards of the turbine throttle valve positioner.
It is believed the likely cause is associated with the ingress of solder flux into the IC Chip package on the controller board
due to delamination caused by the soldering process during fabrication.
The corrosion over time can result in intermittent open circuiting and high resistance in the aluminum metallization.
Chlorine ionic contamination can also result in high leakage currents within the component circuitry.
Failures may be manifested by a reduced valve position signal disproportional to the expected demand condition,
no actuation signal (i.e. throttle valve remaining full open), or other anomalous unexpected behavior.
There are three TL084CN chips on each SL3EX Controller Board within the positioner assembly.
There have been two documented failures to date occurring in 2015 and 2019 in installed systems.
"Affected sites:
Farley, SONGS, Cooper, Almaraz Trillo Nuclear Power Plant (Spain), Clinton, Harris, Wolf Creek, Point Beach, Hatch, Watts Bar, Sequoyah.
20190531 | PART21 | Update PART 21 NOTIFICATION - NAMCO LIMIT SWITCH FAILED TEST DUE TO INSUFFICIENT LUBRICATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53653
* * * UPDATE AT 1106 EDT ON 5/31/19 FROM MARGIE HOVER TO JEFF HERRERA * * *
"ln reference to the Curtiss-Wright Interim Notification Report dated 10/8/2018 (Event No. ML18289A457lLoC No. 2018-24-00) for an EA700-90954 limit switch failure, the following updates are provided.
"Curtiss-Wright was notified on August 7th, 2018 by Exelon's Quad Cities Plant that a Curtiss-Wright Supplied Namco Limit Switch, PIN: EA 700-90954 had failed during a planned maintenance test.
"CW Conclusion:
"Based upon similar wear patterns, the presence of 'significant grease' does not resolve wear pattern issue caused in a shorter period of time, thus the lack of grease can be considered to 'not be a significant credible failure mechanism' (same or no grease between shuttle and housing). Based upon the NAMCO report, the presence or lack of grease has no impact on wear or operability and thus does not affect the safety function.
"In addition, the CQ14100801 S/N 03 installed for 9 months, the O-Ring measured an 81 durometer hardness (showing aging) but not brittle. The other 3 installed for 6 years were brittle but did not affect operability. Thus the hardness of the O-Rings can be considered to 'not be a significant credible failure mechanism'.
"All four switches in Report QDC-62770 had paint scrapings caused by wear which was present and operated properly after being in service for an extended period of time. Thus the presence of paint residue due to wear can be considered to 'not be a significant credible failure mechanism'.
"There have been no other reported failures of this type. The root cause failure mechanism has not been identified, thus this switch failure does not appear to represent a common mode failure."
Notified the R3DO (Daley) and Part 21/50.55 Reactors group (via email).
NJ_Hope_Creek_1 @ 100 % unch from 100 % Sunday; 81 % Saturday
[ no EN, unk reason for powr drop. ]
PA_Limerick_1 @ 100 % up from 80 % Sunday; 60 % Saturday
PA_Peach_Bottom_2 @ 100 % unch from 100 % Sunday; 55 % Saturday
NJ_Salem_1 @ 0 % [ RPV OPEN ( 52 / 28 ) ] RFO started early
PA_Susquehanna_1 @ 91 % down from 100 % Sunday; 77 % Saturday
AL_Browns_Ferry_2 @ 94 % unch from 94 % Sunday; 94 % Saturday
NC_Brunswick_2 @ 100 % unch from 100 % Sunday; 90 % Saturday
GA_Vogtle_1 @ 82 % up from 37 % Sunday; 100 % Saturday
Region 3 [ notice how many units dropped power Sunday ]
IL_Braidwood_1 @ 100 % up from 95 % Sunday; 100 % Saturday
IL_Clinton_1 @ 98 % unch from 98 % Sunday; 98 % Saturday
OH_Davis-Besse_1 @ 100 % up from 98 % Sunday; 100 % Satyrday
IL_Dresden_3 @ 100 % up from 78 % Sunday; 100 % Satyrday
IL_La_Salle_2 @ 100 % up from 79 % Sunday; 100 % Satyrday
OH_Perry_1 @ 70 % up from 22 % Sunday; 25 % Saturday
IL_Quad_Cities_2 @ 100 % up from 80 % Sunday; 100 % Satyrday
AR_Arkansas_2 @ 0 % unch from 0 % since 20190527; 100 % Sunday; 100 % Saturday
WA_Columbia_2 @ 0 % [ RPV OPEN ( 21 / 31 ) ] plnd start 20190515 ] started early
MS_GrandGulf_1 @ 100 % unch from 100 % Sunday; 89 % Saturday
LA_RiverBend_1 @ 0 % since 20190601