Information Notice 2018-10, Thermal Sleeve Flange Wear Leads to Stuck Control Rod at Foreign Nuclear Plant: Difference between revisions

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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:ML18214A710
UNITED STATES


NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION
Line 22: Line 23:
OFFICE OF NEW REACTORS
OFFICE OF NEW REACTORS


WASHINGTON, DC 20555-0001 August 29, 2018 NRC INFORMATION NOTICE 2018-10:               THERMAL SLEEVE FLANGE WEAR LEADS TO
WASHINGTON, DC 20555-0001  
 
August 29, 2018  
 
NRC INFORMATION NOTICE 2018-10:  
THERMAL SLEEVE FLANGE WEAR LEADS TO


STUCK CONTROL ROD AT FOREIGN NUCLEAR
STUCK CONTROL ROD AT FOREIGN NUCLEAR
Line 44: Line 50:
steam supply system plants that have thermal sleeves in the control rod drive mechanism
steam supply system plants that have thermal sleeves in the control rod drive mechanism


(CRDM) penetration tubes. The available OE demonstrates the potential for these components
(CRDM) penetration tubes. The available OE demonstrates the potential for these components


to experience wear of the thermal sleeve flange from contact against the CRDM penetration
to experience wear of the thermal sleeve flange from contact against the CRDM penetration


tube. The resulting wear can have significant consequences which were not previously
tube. The resulting wear can have significant consequences which were not previously


considered for WEC designed pressurized water reactors (PWRs). The purpose of this IN is to
considered for WEC designed pressurized water reactors (PWRs). The purpose of this IN is to


raise industry awareness regarding this issue for similar designed PWRs. The NRC expects
raise industry awareness regarding this issue for similar designed PWRs. The NRC expects


that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN are not NRC
that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN are not NRC


requirements; therefore, no specific action or written response is required.
requirements; therefore, no specific action or written response is required.
Line 61: Line 67:
In December 2017, following a refueling outage at an Electricite de France (EDF) facility, the
In December 2017, following a refueling outage at an Electricite de France (EDF) facility, the


French plant identified one stuck control as part of the rod control rod drop and stepping tests, which precluded the plant from starting up. The plant returned to mode 6, removed the vessel
French plant identified one stuck control as part of the rod control rod drop and stepping tests, which precluded the plant from starting up. The plant returned to mode 6, removed the vessel


head and determined by visual inspection that the CRDM thermal sleeve flange in the
head and determined by visual inspection that the CRDM thermal sleeve flange in the


centermost location was completely worn through. This resulted in a loose part that lodged in
centermost location was completely worn through. This resulted in a loose part that lodged in


the path of the CRDM shaft, thereby precluding motion of the control rod. Within the same time
the path of the CRDM shaft, thereby precluding motion of the control rod. Within the same time


frame, another stuck control rod occurred at another French plant. Due to the common wear
frame, another stuck control rod occurred at another French plant. Due to the common wear


issue observed at these two plants, EDF notified the French Nuclear Safety Authority in
issue observed at these two plants, EDF notified the French Nuclear Safety Authority in
Line 77: Line 83:
Due to similarities in design it is reasonable to assume that over time US plants may also
Due to similarities in design it is reasonable to assume that over time US plants may also


experience similar wear. Additional information is available in WEC letter Nos. LTR-NRC-18-34 and LTR-NRC-18-53, dated May 23, 2018, and July 17, 2018, respectively. These documents
experience similar wear. Additional information is available in WEC letter Nos. LTR-NRC-18-34 and LTR-NRC-18-53, dated May 23, 2018, and July 17, 2018, respectively. These documents


can be found on the NRCs public Web site under Agencywide Documents Access and
can be found on the NRCs public Web site under Agencywide Documents Access and


Management System Accession Nos. ML18143B678 and ML18198A275.
Management System Accession Nos. ML18143B678 and ML18198A275.
ML18214A710


==BACKGROUND==
==BACKGROUND==
Line 93: Line 97:
The above operating experiences illustrate that unexpected wear could occur in certain thermal
The above operating experiences illustrate that unexpected wear could occur in certain thermal


sleeves during normal operating conditions. Therefore, facilities that have similarly designed
sleeves during normal operating conditions. Therefore, facilities that have similarly designed


thermal sleeves may consider monitoring for thermal sleeve flange wear and if needed consider
thermal sleeves may consider monitoring for thermal sleeve flange wear and if needed consider
Line 104: Line 108:
S
S


This information notice does not require any specific action or written response. Please direct
This information notice does not require any specific action or written response. Please direct


any questions about this matter to the technical contacts listed below.
any questions about this matter to the technical contacts listed below.


/RA/                                           /RA by Michael King for/
/RA/  
George A. Wilson, Director                       Christopher G. Miller, Director
 
/RA by Michael King for/  
 
George A. Wilson, Director
 
Christopher G. Miller, Director
 
Division of Materials and License Renewal
 
Division of Inspection and Regional Support


Division of Materials and License Renewal        Division of Inspection and Regional Support
Office of Nuclear Reactor Regulation


Office of Nuclear Reactor Regulation              Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


===Technical Contact:===
===Technical Contact:===
David Rudland, NRR
301-415-1896 E-mail:  David.Rudland@nrc.gov


===David Rudland, NRR===
ML18214A710
                      301-415-1896 E-mail: David.Rudland@nrc.gov


ML18214A710                                  *email concurrence
*email concurrence


NRR/DMLR/
OFFICE
  OFFICE


NRR/DMLR/
MPHB
MPHB


OIP/ICAB       RI*             RII*             RIII*       RIV*
OIP/ICAB
  NAME   RKalikian     SWittick       MFerdas*       SSandal*         AStone*     GGeorge*
 
  DATE   8/27 /18       8/28/18         8/09/18         8/03/18           8/13/18     8/04/18 NRR/DIRS/IRGB NRR/DIRS/IRGB/ NRR/DIRS/IRGB/L NRR/DIRS/IRGB/
RI*  
  OFFICE                                                                  NRR/DMLR/D   NRR/DIRS/D
RII*  
RIII*  
RIV*  
NAME
 
RKalikian
 
SWittick
 
MFerdas*  
SSandal*  
AStone*  
GGeorge*  
DATE
 
8/27 /18  
8/28/18  
8/09/18  
8/03/18  
8/13/18  
8/04/18 OFFICE
 
NRR/DIRS/IRGB
 
/PM
 
NRR/DIRS/IRGB/  
PM
 
NRR/DIRS/IRGB/L
 
A
 
NRR/DIRS/IRGB/
BC
 
NRR/DMLR/D
 
NRR/DIRS/D
 
NAME
 
GCroon
 
BBenney
 
ELee
 
BPham*
GWilson*
CMiller* 
/RA by MKing for/
DATE
 
8/27 /18
8/27 /18
08/21/18
8/27/18
8/29/18
8/29/18 OFFICE
 
NRO/DCIP/D
 
NAME


/PM            PM              A              BC
TMcGinty*


CMiller*
DATE
  NAME  GCroon        BBenney        ELee            BPham*            GWilson*
                                                                                      /RA by MKing for/
  DATE   8/27 /18      8/27 /18        08/21/18        8/27/18          8/29/18      8/29/18 OFFICE NRO/DCIP/D


NAME  TMcGinty*
08/29/18}}
  DATE  08/29/18}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 15:56, 5 January 2025

Thermal Sleeve Flange Wear Leads to Stuck Control Rod at Foreign Nuclear Plant
ML18214A710
Person / Time
Issue date: 08/29/2018
From: Chris Miller, George Wilson
Division of Inspection and Regional Support, Division of Materials and License Renewal
To:
Croon G
References
IN-18-010
Download: ML18214A710 (3)
v • d • e


ML18214A710

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001

August 29, 2018

NRC INFORMATION NOTICE 2018-10:

THERMAL SLEEVE FLANGE WEAR LEADS TO

STUCK CONTROL ROD AT FOREIGN NUCLEAR

PLANT

ADDRESSEES

All holders of an operating license or construction permit for a nuclear power reactor under

Title 10 of the Code of Federal Regulations Part 50, Domestic Licensing of Production and

Utilization Facilities, except those who have permanently ceased operations and have certified

that fuel has been permanently removed from the reactor vessel.

PURPOSE

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform

addressees about recent operating experience (OE) related to Westinghouse (WEC) nuclear

steam supply system plants that have thermal sleeves in the control rod drive mechanism

(CRDM) penetration tubes. The available OE demonstrates the potential for these components

to experience wear of the thermal sleeve flange from contact against the CRDM penetration

tube. The resulting wear can have significant consequences which were not previously

considered for WEC designed pressurized water reactors (PWRs). The purpose of this IN is to

raise industry awareness regarding this issue for similar designed PWRs. The NRC expects

that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN are not NRC

requirements; therefore, no specific action or written response is required.

DESCRIPTION OF CIRCUMSTANCES

In December 2017, following a refueling outage at an Electricite de France (EDF) facility, the

French plant identified one stuck control as part of the rod control rod drop and stepping tests, which precluded the plant from starting up. The plant returned to mode 6, removed the vessel

head and determined by visual inspection that the CRDM thermal sleeve flange in the

centermost location was completely worn through. This resulted in a loose part that lodged in

the path of the CRDM shaft, thereby precluding motion of the control rod. Within the same time

frame, another stuck control rod occurred at another French plant. Due to the common wear

issue observed at these two plants, EDF notified the French Nuclear Safety Authority in

February 2018 of the significant safety events.

Due to similarities in design it is reasonable to assume that over time US plants may also

experience similar wear. Additional information is available in WEC letter Nos. LTR-NRC-18-34 and LTR-NRC-18-53, dated May 23, 2018, and July 17, 2018, respectively. These documents

can be found on the NRCs public Web site under Agencywide Documents Access and

Management System Accession Nos. ML18143B678 and ML18198A275.

BACKGROUND

There have been no prior NRC Generic Communications related to the issue of CRDM thermal

sleeve flange wear.

DISCUSSION

The above operating experiences illustrate that unexpected wear could occur in certain thermal

sleeves during normal operating conditions. Therefore, facilities that have similarly designed

thermal sleeves may consider monitoring for thermal sleeve flange wear and if needed consider

taking corrective action(s) to mitigate any potential safety consequences that can result from the

noted wear.

CONTACT

S

This information notice does not require any specific action or written response. Please direct

any questions about this matter to the technical contacts listed below.

/RA/

/RA by Michael King for/

George A. Wilson, Director

Christopher G. Miller, Director

Division of Materials and License Renewal

Division of Inspection and Regional Support

Office of Nuclear Reactor Regulation

Office of Nuclear Reactor Regulation

Technical Contact:

David Rudland, NRR

301-415-1896 E-mail: David.Rudland@nrc.gov

ML18214A710

  • email concurrence

OFFICE

NRR/DMLR/

MPHB

OIP/ICAB

RI*

RII*

RIII*

RIV*

NAME

RKalikian

SWittick

MFerdas*

SSandal*

AStone*

GGeorge*

DATE

8/27 /18

8/28/18

8/09/18

8/03/18

8/13/18

8/04/18 OFFICE

NRR/DIRS/IRGB

/PM

NRR/DIRS/IRGB/

PM

NRR/DIRS/IRGB/L

A

NRR/DIRS/IRGB/

BC

NRR/DMLR/D

NRR/DIRS/D

NAME

GCroon

BBenney

ELee

BPham*

GWilson*

CMiller*

/RA by MKing for/

DATE

8/27 /18

8/27 /18

08/21/18

8/27/18

8/29/18

8/29/18 OFFICE

NRO/DCIP/D

NAME

TMcGinty*

DATE

08/29/18


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