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

From kanterella
Jump to navigation Jump to search
Created page by program invented by StriderTol
Created page by program invented by StriderTol
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
{{#Wiki_filter:Code of Federal Regulations}}
{{#Wiki_filter: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.
 
ML18214A710
 
==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
 
NRR/DMLR/
  OFFICE
 
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 NRR/DIRS/IRGB  NRR/DIRS/IRGB/  NRR/DIRS/IRGB/L NRR/DIRS/IRGB/
  OFFICE                                                                  NRR/DMLR/D  NRR/DIRS/D
 
/PM            PM              A              BC
 
CMiller*
  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*
  DATE  08/29/18}}


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

Revision as of 19:15, 20 October 2019

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)


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.

ML18214A710

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

NRR/DMLR/

OFFICE

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 NRR/DIRS/IRGB NRR/DIRS/IRGB/ NRR/DIRS/IRGB/L NRR/DIRS/IRGB/

OFFICE NRR/DMLR/D NRR/DIRS/D

/PM PM A BC

CMiller*

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*

DATE 08/29/18