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NPS_Watch Apr 16, 2019
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 7 EN(s) today, 3 associated with power stations.

[  ]

NRC Event Notices for April 16, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...416en.html

[  ]

--------------------------------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices
--------------------------------------------------------------------------------------------------------------------------

----------------------------------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for AL_Farley_1;2 ]

20190415 | AL_Farley_1;2 | OFFSITE NOTIFICATION - ON SITE FATAILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54002 |
RFOD_008; RX Mode: Defueled; Defueled


"At 2355 CDT on 4/15/19, life-saving activities by offsite medical personnel for a Farley employee were terminated.

The coroner declared the individual deceased at the plant site at 0130 CDT.

"The fatality is not believed to be work-related and the individual was inside of the Radiological Controlled Area.

"This is a four-hour notification, non-emergency for a notification of other government agency.
This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified."

The licensee will be notifying the Occupational Safety and Health Administration due to the on-site fatality.

The licensee will perform a radiological survey of the individual prior to transportation offsite.


----------- [ 2019 event history for AL_Farley ]


20190408 | AL_Farley_2 | Begin RFO ( 01 / 28 )


20190302 | AL_Farley_1 | 100 %

20190301 | AL_Farley_1;2 | NRC Names Senior Resident Inspector at Farley Nuclear Plant |
https://www.nrc.gov/reading-rm/doc-colle...005.ii.pdf

20190220 | AL_Farley_1 | [ shutdown, No EN, reason for shutdown unk. ]


20190130 | AL_Farley_1;2 | NRC Issues Confirmatory Order to Farley Nuclear Power Plant
to Address Issues Related to the Handling of Safeguards Information
https://www.nrc.gov/reading-rm/doc-colle...001.ii.pdf

20190115 | AL_Farley_1;2 | FITNESS-FOR-DUTY VIOLATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53827


----------------------------------------------------------------------------------------------------------------------------------------------------


--------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for MN_Monticello_1 ]

20190415 | MN_Monticello_1 | TRANSPORT OFFSITE TO MEDICAL FACILITY OF POTENTIALLY CONTAMINATED INDIVIDUAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54000 |
RFOD_003; RX Mode: Refueling; Refueling


"At 0511 CDT on 4/15/2019,
transport of a potentially radiologically contaminated person from the Monticello Nuclear Plant to a local hospital was performed
prior to conducting a radiological survey as a prudent measure to ensure timely medical support.

At 0658 CDT a radiological survey determined that the individual and their clothing were not contaminated.

"This is reportable under 10 CFR 50.72(b)(3)(xii). The NRC Resident Inspector has been notified."


----------- [ 2019 event history for MN_Monticello ]



20190413 | MN_Monticello_1 | Begin RFO ( 01 / 30 )


20190412 | MN_Monticello_1 | HIGH ENERGY LINE BREAK DOOR FOUND IN INCORRECT POSITION RESULTING IN LPCI AND CORE SPRAY BEING INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53997

20190322 | MN_Monticello_1 | Update PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846

20190124 | MN_Monticello_1 | PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846





----------------------------------------------------------------------------------------------------------------------------------------------------
----------------------------------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for

----------- [ 2019 event history for
[ no previous ENs for this site in 2019 ]
----------------------------------------------------------------------------------------------------------------------------------------------------

----------------------------------------------------------------------------------------------------------------------------------------------------
------------[ PART 21 ] - These ENs are for issues that involve multiple site/reactor units
----------------------------------------------------------------------------------------------------------------------------------------------------

20190416 | PART21 | PART-21 NOTIFICATION - SNUBBER HYDRAULIC FLUID BATCH CONTAINS PARTICULATES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54001

[
A snubber is  basically a shock absorber but unlike an automotive shock absorber, snubbers 'latch up' under certain loads
and become a structural component

]
http://basicpsa.com/products/psa-mechanical-snubber/

The following report was received via fax:

"Pacific Gas and Electric notified Curtiss Wright [CW] Enertech that they observed white particulate in SF-1154 fluid in three containers.

The white particulate was found settled at the bottom of the containers.

The fluid was dedicated and supplied by CW Enertech in November 2016.
The fluid was traced back to Momentive Batch 14ELVS145.

"The momentive batch 14ELVS145 was previously reported by Lake Engineering Company
(Ref NRC ML17212A628 and ML17128A465).

The white particulates/semisolid material was identified as phenyl cyclic precipitate.

The safety hazard that could be created by this defect is the blockage of snubber bleed port
as reported by Duane Arnold (Ref ML070300154).

This blockage could prevent the snubber from unlocking after a seismic event,
thus preventing the snubber to allow for system movement during normal operations.

"In addition, evaluation performed by Lake Engineering Company has found that all of the solids are dissolved
back into the fluid when heated to 110 [degrees] fahrenheit.

With all solids dissolved, there is no potential safety hazard with this fluid."
[ Will the fluid re-precipitate ? ]

Affected sites: Fermi, Shearon Harris, Beaver Valley, Diablo Canyon, Watts Bar, Perry, and Almaraz (Spain).


Curtiss-Wright point of contact: [ contact info on NRC site ]

See also EN 43071 dated 1/3/2007

--------------------------------------------


[ This was from an earlier PART21, ( I was posting on a different site at the time. ) ]

20160427 | PART21 | Update PART 21 - HYDRAULIC SNUBBER SEAL MATERIAL DEVIATION INTERIM REPORT |
http://www.nrc.gov/reading-rm/doc-collec...ml#en51788

Fifty-nine (59) total snubbers were shipped to NRC licensees
(Farley, Peach Bottom, Oconee, ANO, and Diablo Canyon);
Anvil will advise sites

March 15, 2016 at 8:02 pm     

Peach Bottom (PA) PART 21 – HYDRAULIC SNUBBER SEAL MATERIAL DEVIATION INTERIM REPORT |
http://www.nrc.gov/reading-rm/doc-collec...ml#en51788

" During the course of routine refueling outage activities in October 2015,
it was discovered that 9 of these 14 snubbers had no hydraulic fluid in the reservoir.

The cause of the hydraulic fluid loss was premature aging of the reservoir piston seal due to vibration
induced frictional heat. Subsequent laboratory testing of both replacement and degraded seal
material by Exelon Power Labs suggested that a material substitution had been made from the Anvil
approved Ethylene Propylene (EP) compound to a different grade of EP rubber."

[ Peach Bottom is the only plant named in the EN but others may be involved. ]

[ A snubber is basically a hydraulic shock absorber, they are used to limit movement of pipes during seismic events
and during normal operation to limit movement from vibration or thermal changes.
]

Pg 3 fig 3 of this document
http://digitalcommons.uri.edu/cgi/viewco...ext=theses
[ shows a snubber in use at Diablo Canyon ]

[ from the EN it appears the seal manufacturer made a change without proper testing, oops. ]

[ No problem unless there is an earthquake, but don't worry, before the next earthquake they will have found out how many units are affected and will have fixed them. ]

----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Other reactor info from daily power tracking
-----------------------------------------------------------------------------------------------------------------


Region 1
 
PA_Limerick_2 @ 0 % [ Begin RFO ( 02 / 20 ) 20190415 ]
[ Expect RPV OPEN Friday ]

CT_Millstone_3 @ 0 % [ RPV OPEN ( 05 / 33 ) RFO plan start 20190418 ]
[ unit may have entered RFO early ]

NY_Nine_Mile_Point_1 @ 21 % up from 5 %
[ Exit RFO ( 26 / 21 ) ] missed planned restart date

NJ_Salem_1 @ 0 % [ Begin RFO ( 04 / 28 ) ] started early
[ Expect RPV OPEN Wednesday ]

PA_Susquehanna_2 @ 0 % [ RPV OPEN ( 25 / 35 ) 20190323 ]


Region 2

AL_Browns_Ferry_2 @ 75 % unch from 75 % up from 66 % Sunday; 66 % Saturday
[ Exit RFO ( 39 / 25 ) ] missed planned restart date ]

NC_Brunswick_2 @ 82 % up from 50 % down from 52 % Sunday; 21 % Saturday
[ exit RFO ( 28 / 28 ) ] 1st restart failed
 [ recovering from ]
 MANUAL REACTOR SCRAM AND SPECIFIED SYSTEM ACTUATION |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en53966

AL_Farley_1 @ 96 % down from 97 % up from 96 % Sunday; 96 % Saturday
[ no EN, unk reason for power drop. ]

AL_Farley_2 @ 0 % [ RPV OPEN ( 09 / 28 ) 20190405 ]

NC_McGuire_1 @ 0 % [ RPV OPEN ( 24 / 31 ) 20190323 ]

VA_North_Anna_1 @ 98 % down from 100 % Monday
[ no EN, unk reason for power drop. ]

VA_NorthAnna_2 @ 99 % unch from 99 % unch from 99 % Sunday; 99 % Saturday
[ Exit RFO ( 37 / 36 ) ] missed planned restart date

TN_Sequoyah_1 @ 0 %
 AUTOMATIC REACTOR TRIP DUE TO MAIN FEEDWATER PUMP TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en53999

FL_Turkey_Point_4 @ 100 % up from 95 % up from 63 % Sunday; 48 % Saturday
[ Completed RFO ( 30 / 28 ) 20190311, missed planned restart date ]

TN_Watts_Bar_2 @ 0 % [ Begin RFO ( 04 / 26 ) 20190413 ]
[ Expect RPV OPEN Wednesday ]


Region 3

IL_Byron_2 @ 0 % [ RPV OPEN ( 09 / 18 ) 20190408 ]

IL_Clinton_1 @ 98 %
[ 98-99 % are this units normal thermal power range. ]

MI_DC_Cook_1 @ 0 % [ RPV OPEN ( 42 / 30 ) 20190306  ]
[ missed planned restart date ]

IA_Duane_Arnold_1 @ 97 % up from 96 % up from 62 % Sunday; 100 % Saturday
[ no EN, unk reason for power drop. ]

MN_Monticello_1 @ 0 %  [RPV OPEN ( 03 / 30 ) 20190413 ]

WI_Point_Beach_1 @ 0 % [ RPV OPEN ( 25 / 26 ) 20190322 ]



Region 4

MO_Callaway_1 @ 0 % [ RPV OPEN ( 15 / 42 ) 20190401; no coastdown 24hr SD

TX_ComanchePeak_1 @ 79 % [ coastdown to RFO 20190407 ] missed planned start date ]

MS_GrandGulf_1 @ 94 % unch from 94 % unch from 94 % Sunday; 94 % Saturday
[ no EN, unk reason for power drop. ]

AZ_PaloVerde_1 @ 0 % [ RPV OPEN ( 11 / 30 )

LA_RiverBend_1 @ 0 % [ RPV OPEN ( 18 / 34 ]


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[ There is/are currently 10 unit(s) with the RPV OPEN - ref the 2019 Spring Refueling Outage Schedule and Status ]

posted by Staup Knewkinus a Dane Gerous production. All human rights reserved.
 
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