Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components: Difference between revisions

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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:ML111800524 UNITED STATES


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


WASHINGTON, DC 20555-0001 September 26, 2011 NRC INFORMATION NOTICE 2011-19:                         LICENSEE EVENT REPORTS CONTAINING
WASHINGTON, DC 20555-0001  
 
September 26, 2011  
 
NRC INFORMATION NOTICE 2011-19:  
LICENSEE EVENT REPORTS CONTAINING


INFORMATION PERTAINING TO DEFECTS IN
INFORMATION PERTAINING TO DEFECTS IN
Line 52: Line 57:
[LER] System, that discussed defects1 to basic components2 and the new NRC practice of
[LER] System, that discussed defects1 to basic components2 and the new NRC practice of


posting such LERs to the 10 CFR Part 21 report page of the NRC public website. Although
posting such LERs to the 10 CFR Part 21 report page of the NRC public website. Although


there is no explicit NRC requirement for licensees to do so, the NRC encourages licensees
there is no explicit NRC requirement for licensees to do so, the NRC encourages licensees
Line 58: Line 63:
reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note 10 CFR Part 21 applicability on
reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note 10 CFR Part 21 applicability on


the LER form (NRC Form 366) and within the text of the LER. The NRC expects that recipients
the LER form (NRC Form 366) and within the text of the LER. 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;
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.
therefore, no specific action or written response is required.


Line 75: Line 80:
maintain it in a safe-shutdown condition, or the capability to prevent or mitigate the consequences of
maintain it in a safe-shutdown condition, or the capability to prevent or mitigate the consequences of


accidents. In all cases, a basic component includes safety-related design, analysis, inspection, testing, fabrication, replacement of parts, or consulting services that are associated with the component hardware, design certification, design approval, or information in support of an early site permit application under
accidents. In all cases, a basic component includes safety-related design, analysis, inspection, testing, fabrication, replacement of parts, or consulting services that are associated with the component hardware, design certification, design approval, or information in support of an early site permit application under


10 CFR Part 52, whether these services are performed by the component supplier or others.
10 CFR Part 52, whether these services are performed by the component supplier or others.
Line 82: Line 87:
The regulations in 10 CFR Part 21 establish procedures and requirements for the
The regulations in 10 CFR Part 21 establish procedures and requirements for the


implementation of Section 206 of the Energy Reorganization Act of 1974. Section 206 requires
implementation of Section 206 of the Energy Reorganization Act of 1974. Section 206 requires


any individual director or responsible officer of a firm constructing, owning, operating, or
any individual director or responsible officer of a firm constructing, owning, operating, or
Line 117: Line 122:


==DESCRIPTION OF CIRCUMSTANCES==
==DESCRIPTION OF CIRCUMSTANCES==
The NRC reviews all LERs for safety significance and generic applicability. The NRC
The NRC reviews all LERs for safety significance and generic applicability. The NRC


occasionally identifies LERs containing information related to defects in basic components
occasionally identifies LERs containing information related to defects in basic components
Line 123: Line 128:
(which satisfies the reporting obligation to report defects under 10 CFR Part 21) where the LER
(which satisfies the reporting obligation to report defects under 10 CFR Part 21) where the LER


does not specifically mention 10 CFR Part 21. The following LER provides a specific example
does not specifically mention 10 CFR Part 21. The following LER provides a specific example


of this situation.
of this situation.


===H.B. Robinson Steam Electric Plant, Unit 2===
H.B. Robinson Steam Electric Plant, Unit 2  
 
On February 22, 2010, the licensee at H.B. Robinson Unit 2 removed the B emergency diesel
On February 22, 2010, the licensee at H.B. Robinson Unit 2 removed the B emergency diesel


generator (EDG) from service for planned maintenance. During post-maintenance testing, the
generator (EDG) from service for planned maintenance. During post-maintenance testing, the


output breaker for the B EDG failed to close. The breakers failure to close was unrelated to
output breaker for the B EDG failed to close. The breakers failure to close was unrelated to


the maintenance activity. The licensees analysis determined that the cause of the EDG output
the maintenance activity. The licensees analysis determined that the cause of the EDG output


breaker failure was a vendor workmanship error related to a defective shunt trip attachment
breaker failure was a vendor workmanship error related to a defective shunt trip attachment


movable core in the breaker control circuit. The licensee determined that the B EDG had been
movable core in the breaker control circuit. The licensee determined that the B EDG had been


inoperable for a period of 27 days and reported the condition under 10 CFR 50.73(a)(2)(i)(B) as
inoperable for a period of 27 days and reported the condition under 10 CFR 50.73(a)(2)(i)(B) as


any operation or condition that was prohibited by the plants technical specifications. Additional
any operation or condition that was prohibited by the plants technical specifications. Additional


3 NRC regulations in 10 CFR 21.3 state that a substantial safety hazard means a loss of safety function to the
3 NRC regulations in 10 CFR 21.3 state that a substantial safety hazard means a loss of safety function to the
Line 159: Line 165:
Regulation 10 CFR 21.2 specifies that a nuclear power plant licensees evaluation of potential
Regulation 10 CFR 21.2 specifies that a nuclear power plant licensees evaluation of potential


defects and appropriate reporting of defects under 10 CFR 50.73 satisfies the evaluation, notification, and obligation to report defects under 10 CFR Part 21. Because of the potential
defects and appropriate reporting of defects under 10 CFR 50.73 satisfies the evaluation, notification, and obligation to report defects under 10 CFR Part 21. Because of the potential


generic nature of defects to basic components reported in some LERs, the NRC staff will now
generic nature of defects to basic components reported in some LERs, the NRC staff will now


post all LERs containing information pertaining to defects to basic components to the Part 21 Reports page on the NRC public website. The intent of this effort is to raise licensee awareness
post all LERs containing information pertaining to defects to basic components to the Part 21 Reports page on the NRC public website. The intent of this effort is to raise licensee awareness


of defects to basic components by rapidly disseminating this information to the industry via the
of defects to basic components by rapidly disseminating this information to the industry via the


NRC public website. Although there is no explicit NRC requirement for licensees to do so, the
NRC public website. Although there is no explicit NRC requirement for licensees to do so, the


NRC encourages licensees reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note
NRC encourages licensees reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note
Line 174: Line 180:


==CONTACT==
==CONTACT==
This IN requires no specific action or written response. Please direct any questions about this
This IN requires no specific action or written response. Please direct any questions about this


matter to the technical contacts listed below or the appropriate Office of Nuclear Reactor
matter to the technical contacts listed below or the appropriate Office of Nuclear Reactor
Line 180: Line 186:
Regulation (NRR) project manager.
Regulation (NRR) project manager.


/RA/                                           /RA/
/RA/  
Laura A. Dudes, Director                       Timothy J. McGinty, Director
 
/RA/  
 
Laura A. Dudes, Director
 
Timothy J. McGinty, Director
 
Division of Construction Inspection
 
Division of Policy and Rulemaking
 
and Operational Programs
 
Office of Nuclear Reactor Regulation
 
Office of New Reactors


Division of Construction Inspection            Division of Policy and Rulemaking
Technical Contacts: Stephen J. Pannier, NRR


and Operational Programs                    Office of Nuclear Reactor Regulation
Paul Prescott, NRR


===Office of New Reactors===
301-415-4083
Technical Contacts:     Stephen J. Pannier, NRR                Paul Prescott, NRR
301-415-3026 E-mail: stephen.pannier@nrc.gov


301-415-4083                          301-415-3026 E-mail: stephen.pannier@nrc.gov        E-mail: paul.prescott@nrc.gov
E-mail: paul.prescott@nrc.gov


Omid Tabatabai, NRO
Omid Tabatabai, NRO


301-415-6616 E-mail: omid.tabatabai@nrc.gov
301-415-6616 E-mail: omid.tabatabai@nrc.gov
 
Note:  NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library.
 
ML111800524 TAC ME5927 OFFICE
 
IOEB/DIRS
 
Tech Editor
 
BC:IOEB/DIRS
 
BC:EQVB/DE
 
NAME
 
SPannier
 
KAzariah-Kribbs
 
JThorp
 
MMurphy
 
DATE
 
8/16/11
7/29/11 e-mail
 
8/16/11 e-mail
 
8/31/11 OFFICE
 
BC:CQVB/DCIP
 
BC:IRIB/DIRS
 
D:DIRS
 
LA:PGCB/NRR
 
NAME
 
RRasmussen
 
TKobetz
 
FBrown JAnderson for
 
CHawes
 
DATE
 
8/1/11 e-mail
 
9/14/11
9/19/11
9/21/11 OFFICE
 
PM:PGCB/NRR
 
BC:PGCB/NRR


Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library.
D:DCIP:NRO


ML111800524                                                        TAC ME5927 OFFICE  IOEB/DIRS              Tech Editor              BC:IOEB/DIRS          BC:EQVB/DE
D:DPR:NRR


NAME     SPannier                KAzariah-Kribbs          JThorp                MMurphy
NAME


DATE    8/16/11                7/29/11 e-mail          8/16/11 e-mail        8/31/11 OFFICE  BC:CQVB/DCIP            BC:IRIB/DIRS            D:DIRS                LA:PGCB/NRR
DBeaulieu


NAME    RRasmussen              TKobetz                  FBrown JAnderson for CHawes
SRosenberg TAlexion for LDudes


DATE    8/1/11 e-mail          9/14/11                  9/19/11              9/21/11 OFFICE  PM:PGCB/NRR            BC:PGCB/NRR              D:DCIP:NRO            D:DPR:NRR
TMcGinty


NAME    DBeaulieu              SRosenberg TAlexion for  LDudes                TMcGinty
OFFICE


OFFICE  9/20/11                 9/21/11                 9/23/11               9/26/11}}
9/20/11  
9/21/11  
9/23/11  
9/26/11}}


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

Latest revision as of 05:39, 13 January 2025

Licensee Event Reports Containing Information Pertaining to Defects to Basic Components
ML111800524
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 09/26/2011
From: Laura Dudes, Mcginty T
Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking
To:
Beaulieu, D P, NRR/DPR, 415-3243
References
IN-11-019
Download: ML111800524 (4)
v • d • e


ML111800524 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001

September 26, 2011

NRC INFORMATION NOTICE 2011-19:

LICENSEE EVENT REPORTS CONTAINING

INFORMATION PERTAINING TO DEFECTS IN

BASIC COMPONENTS

ADDRESSEES

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

Title 10 of the Code of Federal Regulations (10 CFR) 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.

All holders of or applicants for an early site permit, standard design certification, standard

design approval, manufacturing license, or combined license under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.

All individuals, corporations, partnerships, or other entities for which the regulations of

10 CFR Part 21, Reporting of Defects and Noncompliance, apply (see 10 CFR 21.2, Scope).

PURPOSE

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

addressees of recent events that were reported under 10 CFR 50.73, Licensee Event Report

[LER] System, that discussed defects1 to basic components2 and the new NRC practice of

posting such LERs to the 10 CFR Part 21 report page of the NRC public website. Although

there is no explicit NRC requirement for licensees to do so, the NRC encourages licensees

reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note 10 CFR Part 21 applicability on

the LER form (NRC Form 366) and within the text of the LER. 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.

1 NRC regulations in 10 CFR 21.3, Definitions, state that a defect is a deviation in a basic component

delivered to a purchaser for use in a facility or an activity subject to the regulations in 10 CFR Part 21 if, on

the basis of an evaluation, the deviation could create a substantial safety hazard.

2 NRC regulations in 10 CFR 21.3 state that a basic component is a structure, system, or component that

ensures the integrity of the reactor coolant pressure boundary, the capability to shut down the reactor and

maintain it in a safe-shutdown condition, or the capability to prevent or mitigate the consequences of

accidents. In all cases, a basic component includes safety-related design, analysis, inspection, testing, fabrication, replacement of parts, or consulting services that are associated with the component hardware, design certification, design approval, or information in support of an early site permit application under

10 CFR Part 52, whether these services are performed by the component supplier or others.

BACKGROUND

The regulations in 10 CFR Part 21 establish procedures and requirements for the

implementation of Section 206 of the Energy Reorganization Act of 1974. Section 206 requires

any individual director or responsible officer of a firm constructing, owning, operating, or

supplying the components of any facility or activity that is licensed or otherwise regulated

pursuant to the Atomic Energy Act of 1954, as amended, or the Energy Reorganization Act of

1974, who obtains information reasonably indicating (1) that the facility, activity, or basic

component supplied to such facility or activity fails to comply with the Atomic Energy Act of

1954, as amended, or any applicable rule, regulation, order, or license of the Commission

relating to substantial safety hazards3, or (2) that the facility, activity, or basic component

supplied to such facility or activity contains defects that could create a substantial safety hazard, to immediately notify the Commission of such failure to comply or such defect, unless he has

actual knowledge that the Commission has been adequately informed of such defect or failure

to comply.

Regulation 10 CFR 21.2 states that for persons licensed to operate a nuclear power plant under

10 CFR Part 50 or 10 CFR Part 52, evaluation of potential defects and appropriate reporting of

defects under 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear

Power Reactors, 10 CFR 50.73, or 10 CFR 73.71, Reporting of Safeguards Events, satisfy

each persons evaluation, notification, and reporting obligation to report defects under

10 CFR Part 21.

DESCRIPTION OF CIRCUMSTANCES

The NRC reviews all LERs for safety significance and generic applicability. The NRC

occasionally identifies LERs containing information related to defects in basic components

(which satisfies the reporting obligation to report defects under 10 CFR Part 21) where the LER

does not specifically mention 10 CFR Part 21. The following LER provides a specific example

of this situation.

H.B. Robinson Steam Electric Plant, Unit 2

On February 22, 2010, the licensee at H.B. Robinson Unit 2 removed the B emergency diesel

generator (EDG) from service for planned maintenance. During post-maintenance testing, the

output breaker for the B EDG failed to close. The breakers failure to close was unrelated to

the maintenance activity. The licensees analysis determined that the cause of the EDG output

breaker failure was a vendor workmanship error related to a defective shunt trip attachment

movable core in the breaker control circuit. The licensee determined that the B EDG had been

inoperable for a period of 27 days and reported the condition under 10 CFR 50.73(a)(2)(i)(B) as

any operation or condition that was prohibited by the plants technical specifications. Additional

3 NRC regulations in 10 CFR 21.3 state that a substantial safety hazard means a loss of safety function to the

extent that there is a major reduction in the degree of protection provided to public health and safety for any

facility or activity licensed or otherwise approved or regulated by the NRC, other than for export, under

10 CFR Part 30, 40, 50, 52, 60, 61, 63, 70, 71, or 72. information appears in H.B. Robinson Steam Electric Plant, Unit 2, LER 05000261/2010-001-01, Emergency Diesel Generator Inoperable in Excess of Technical Specifications Completion

Time due to Output Breaker Failure, dated June 1, 2010, on the NRCs public Web site in the

Agencywide Documents Access and Management System, Accession No. ML101590222.

DISCUSSION

Regulation 10 CFR 21.2 specifies that a nuclear power plant licensees evaluation of potential

defects and appropriate reporting of defects under 10 CFR 50.73 satisfies the evaluation, notification, and obligation to report defects under 10 CFR Part 21. Because of the potential

generic nature of defects to basic components reported in some LERs, the NRC staff will now

post all LERs containing information pertaining to defects to basic components to the Part 21 Reports page on the NRC public website. The intent of this effort is to raise licensee awareness

of defects to basic components by rapidly disseminating this information to the industry via the

NRC public website. Although there is no explicit NRC requirement for licensees to do so, the

NRC encourages licensees reporting 10 CFR Part 21 defects under 10 CFR 50.73 to note

10 CFR Part 21 applicability on the LER form (NRC Form 366) and within the text of the LER.

CONTACT

This IN requires no specific action or written response. Please direct any questions about this

matter to the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

/RA/

/RA/

Laura A. Dudes, Director

Timothy J. McGinty, Director

Division of Construction Inspection

Division of Policy and Rulemaking

and Operational Programs

Office of Nuclear Reactor Regulation

Office of New Reactors

Technical Contacts: Stephen J. Pannier, NRR

Paul Prescott, NRR

301-415-4083

301-415-3026 E-mail: stephen.pannier@nrc.gov

E-mail: paul.prescott@nrc.gov

Omid Tabatabai, NRO

301-415-6616 E-mail: omid.tabatabai@nrc.gov

Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library.

ML111800524 TAC ME5927 OFFICE

IOEB/DIRS

Tech Editor

BC:IOEB/DIRS

BC:EQVB/DE

NAME

SPannier

KAzariah-Kribbs

JThorp

MMurphy

DATE

8/16/11

7/29/11 e-mail

8/16/11 e-mail

8/31/11 OFFICE

BC:CQVB/DCIP

BC:IRIB/DIRS

D:DIRS

LA:PGCB/NRR

NAME

RRasmussen

TKobetz

FBrown JAnderson for

CHawes

DATE

8/1/11 e-mail

9/14/11

9/19/11

9/21/11 OFFICE

PM:PGCB/NRR

BC:PGCB/NRR

D:DCIP:NRO

D:DPR:NRR

NAME

DBeaulieu

SRosenberg TAlexion for LDudes

TMcGinty

OFFICE

9/20/11

9/21/11

9/23/11

9/26/11


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