ML16154A207: Difference between revisions
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FAX (301) 816.. 5151 Docwnent Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 From: | FAX (301) 816.. 5151 Docwnent Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 From: | ||
Les Taggart Quality Assurance Program Mgr. | Les Taggart Quality Assurance Program Mgr. | ||
AZZINLI Nuclear Logistics 7410 Pebble Drive Fort Worth, Texas 76118 UPDATE - Report of potential | AZZINLI Nuclear Logistics 7410 Pebble Drive Fort Worth, Texas 76118 UPDATE - Report of potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC Report No: P21-04_302015, Rev. 2 Previous NRC Event number 51030 Previous Accession No: ML15134A016 Total pages including this page: 1 NUCLEAR LOGISTICS INC:. www.au.com 741 o Pebble Drive | ||
* Fort Worth, *Texas 761 *IS | * Fort Worth, *Texas 761 *IS | ||
* 800.448.4124 Pho11e | * 800.448.4124 Pho11e | ||
Line 52: | Line 52: | ||
==Subject:== | ==Subject:== | ||
Update- Report ofpotential | Update- Report ofpotential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC - NRC Event Number 51030, Accession Number MLl S134AO 16 Revision 2, corrections: | ||
: 1. Page 5 (vii), znd paragraph: changed EPRI TR-102323 Rev. 3 to Rev. 4. | : 1. Page 5 (vii), znd paragraph: changed EPRI TR-102323 Rev. 3 to Rev. 4. | ||
: 2. Page 5 (vii), 3rd paragraph: changed 'timing~ contacts to 'instantaneous' contacts. | : 2. Page 5 (vii), 3rd paragraph: changed 'timing~ contacts to 'instantaneous' contacts. | ||
Pursuant to | Pursuant to 10CFR 21.21 (d) (3) (ii), AZZINLI is providing written notification of the identification of a potential failure to comply. | ||
On the basis of our evaluation. it is determined that AZZINLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications. | On the basis of our evaluation. it is determined that AZZINLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications. | ||
The following information is required per | The following information is required per 10CFR 21.21 (d) (4). | ||
(i) Name and address of the individual or individuals informing the Commission. | (i) Name and address of the individual or individuals informing the Commission. | ||
Tracy Bolt, Director of Quality Assurance Nuclear Logistics, Inc 7410 Pebble Drive Ft. Worth, TX 76118 (ii) Identification of the facility, activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. | Tracy Bolt, Director of Quality Assurance Nuclear Logistics, Inc 7410 Pebble Drive Ft. Worth, TX 76118 (ii) Identification of the facility, activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. | ||
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FAX (301) 816.. 5151 Docwnent Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 From: | FAX (301) 816.. 5151 Docwnent Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 From: | ||
Les Taggart Quality Assurance Program Mgr. | Les Taggart Quality Assurance Program Mgr. | ||
AZZINLI Nuclear Logistics 7410 Pebble Drive Fort Worth, Texas 76118 UPDATE - Report of potential | AZZINLI Nuclear Logistics 7410 Pebble Drive Fort Worth, Texas 76118 UPDATE - Report of potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC Report No: P21-04_302015, Rev. 2 Previous NRC Event number 51030 Previous Accession No: ML15134A016 Total pages including this page: 1 NUCLEAR LOGISTICS INC:. www.au.com 741 o Pebble Drive | ||
* Fort Worth, *Texas 761 *IS | * Fort Worth, *Texas 761 *IS | ||
* 800.448.4124 Pho11e | * 800.448.4124 Pho11e | ||
Line 139: | Line 139: | ||
==Subject:== | ==Subject:== | ||
Update- Report ofpotential | Update- Report ofpotential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC - NRC Event Number 51030, Accession Number MLl S134AO 16 Revision 2, corrections: | ||
: 1. Page 5 (vii), znd paragraph: changed EPRI TR-102323 Rev. 3 to Rev. 4. | : 1. Page 5 (vii), znd paragraph: changed EPRI TR-102323 Rev. 3 to Rev. 4. | ||
: 2. Page 5 (vii), 3rd paragraph: changed 'timing~ contacts to 'instantaneous' contacts. | : 2. Page 5 (vii), 3rd paragraph: changed 'timing~ contacts to 'instantaneous' contacts. | ||
Pursuant to | Pursuant to 10CFR 21.21 (d) (3) (ii), AZZINLI is providing written notification of the identification of a potential failure to comply. | ||
On the basis of our evaluation. it is determined that AZZINLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications. | On the basis of our evaluation. it is determined that AZZINLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications. | ||
The following information is required per | The following information is required per 10CFR 21.21 (d) (4). | ||
(i) Name and address of the individual or individuals informing the Commission. | (i) Name and address of the individual or individuals informing the Commission. | ||
Tracy Bolt, Director of Quality Assurance Nuclear Logistics, Inc 7410 Pebble Drive Ft. Worth, TX 76118 (ii) Identification of the facility, activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. | Tracy Bolt, Director of Quality Assurance Nuclear Logistics, Inc 7410 Pebble Drive Ft. Worth, TX 76118 (ii) Identification of the facility, activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. |
Revision as of 17:51, 10 November 2019
ML16154A207 | |
Person / Time | |
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Site: | Millstone, Browns Ferry, Nine Mile Point, Perry, Saint Lucie, North Anna, River Bend, Ginna, South Texas, Fort Calhoun |
Issue date: | 05/26/2016 |
From: | Bolt T AZZ Nuclear Logistics |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML16154A207 (9) | |
Text
0512612016 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel Part 21 (PAR) Event# 51030 Rep Org: AZZ/NLI NUCLEAR LOGISTICS, INC Notification Date I Time: 05/01/2015 13:32 (EDT)
Supplier: ALLEN BRADLEY Event Date I Time: 04/30/2015 (CDT)
Last Modification: 04/08/2016 Region: 4 Docket#:
City: FORT WORTH Agreement State: Yes County: License #:
State: TX NRC Notified by: TRACY BOLT Notifications: MEL GRAY R1DO HQ Ops Officer: DANIEL MILLS FRANK EHRHARDT R2DO Emergency Class: NON EMERGENCY ROBERT ORLIKOWSKI R3DO 10 CFR Section: GEOFFREY MILLER R4DO 21.21(d)(3)(i) DEFECTS AND NONCOMPLIANCE PART 21/50.55 REACTORS EMAIL POTENTIALLY UNQUALIFIED COMPONENT IN CERTAIN ALLEN BRADLEY TIMING RELAYS The following is an excerpt from a document received from the licensee via email:
"Report of potential 10 CFR Part 21, Allen Bradley Timing Relay Model 700RTC "Pursuant to 10 CFR 21.21 (d)(3)(ii}, AZZ/N LI is providing written notification of the identification of a potential failure to comply.
"On the basis of our evaluation, it is determined that AZZ/NLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications.
"The specific part which fails to comply or contains a defect:
"As of 2009-2010, Allen Bradley relays base model 700RTC, contain an unevaluated CPLD (Complex Programmable Logic Device). This was an unpublished design change that was implemented to replace an obsolete integrated circuit chip. The undocumented design change did not result in a part number change from Allen-Bradley. There was no change to the appearance of the relay that would identify any design changes were made to the relay configuration. Therefore, NLI qualification/dedication of the relays after 2009 have not included additional testing for the new CPLD component.
"The timing relay model 700RTC has been dedicated/qualified for multiple applications for various plants.
"Between 2009-2010 Allen Bradley made a design change without changing the part number of the commercial
0512612016 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 2 relay or providing any documented evidence of a design change. The manufacturer specification data sheets maintain the classification that the relays are 'solid state', which would imply that there are no digital devices installed in the relay. However, after inspection of the internals of the timing relay (Figure 2), it has been identified that the unit does contain a CPLD which meets the definition of a digital device under the guidance of NEI 01-01."
Potentially affected plants include Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project, and St. Lucie.
- UPDATE FROM TRACY BOLT TO JOHN SHOEMAKER AT 1744 EDT ON 4/8/16 * *
- AZZ/NLI Nuclear Logistics provided additional information regarding Part 21 Report No: P21-04302015, Rev. 1.
Notified R1DO (Rogge), R2DO (Nease), R3DO(Skokowski), R4DO (Kellar), and PART 21/50.55 REACTORS via email.
- UPDATE FROM LES TAGGART TO BETHANY CECERE AT 0951 EDT ON 5/26/16 * *
- AZZ/NLI Nuclear Logistics provided Revision 2 to Part 21 Report No: P21-04302015 to correct the referenced EPRI TR-102323 Rev. 3 to Rev. 4 and change 'timing' contacts to 'instantaneous' contacts as shown below:
"(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
"The relays that are currently in stock at NLI have been. placed on hold until after the units have been determined to be qualified for the specific application. NU has completed the EMC qualification testing per the requirements of EPRI TR-102323 Rev. 4 for the following tests, as applicable: CE101, CE102, RE101, RE102, RS101, RS103, CS101, CS114, CS115 and CS116.
"The results were satisfactory with exception of the following condition: During Conducted Susceptibility CS114 onto the power lines, with the timing circuit in operation, the instantaneous contacts exhibited chatter in the range of 2.6 MHz to 20.3 MHz. The unit requires a ferrite to be installed onto the input power lines of the relay with 3 turns through the ferrite core. In this modified configuration, the relay was not susceptible to Conducted Susceptibility and successfully passed the required test per CS114."
Notified R1 DO (Lilliendahl), R2DO (Guthrie), R3DO(Kunowski), R4DO (Werner), and PART 21/50.55 REACTORS via email.