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| issue date = 03/13/2007
| issue date = 03/13/2007
| title = Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection (CDBI) - NRC Inspection Report 05000327-07-006 and 05000328-07-006 and Information Request for CDBI
| title = Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection (CDBI) - NRC Inspection Report 05000327-07-006 and 05000328-07-006 and Information Request for CDBI
| author name = Cain L M
| author name = Cain L
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Singer K W
| addressee name = Singer K
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000327, 05000328
| docket = 05000327, 05000328
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
See also: [[followed by::IR 05000327/2007006]]
See also: [[see also::IR 05000327/2007006]]


=Text=
=Text=
{{#Wiki_filter:March 13, 2007Tennessee Valley AuthorityATTN:Mr. Karl W. SingerChief Nuclear Officer and
{{#Wiki_filter:March 13, 2007
Executive Vice President6A Lookout Place
Tennessee Valley Authority
ATTN:
Mr. Karl W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
1101 Market Street
Chattanooga, TN  37402-2801SUBJECT:NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGNBASES INSPECTION - NRC INSPECTION REPORT 05000327/2007006 AND
Chattanooga, TN  37402-2801
05000328/2007006Dear Mr. Singer:
SUBJECT:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region II staff will conduct a component design bases inspection at your Sequoyah Nuclear
NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000327/2007006 AND
05000328/2007006
Dear Mr. Singer:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your Sequoyah Nuclear
Plant during the weeks of June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007.  The
Plant during the weeks of June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007.  The
inspection team will be led by Mr. Ryan Taylor, a Senior Reactor Inspector from the NRC's
inspection team will be led by Mr. Ryan Taylor, a Senior Reactor Inspector from the NRC's
Region II Office.  This inspection will be conducted in accordance with the baseline inspection
Region II Office.  This inspection will be conducted in accordance with the baseline inspection
procedure, Procedure 71111.21, Component Design Bases Inspection, issued June 22, 2006.The inspection will evaluate the capability of risk significant / low margin components to functionas designed and support proper system operation.  The inspection will also include a review of
procedure, Procedure 71111.21, Component Design Bases Inspection, issued June 22, 2006.
selected operator actions, operating experience, and modifications. During a telephone conversation on March 13, 2007, Mr. R. Moore confirmed with Mr. R. Proffitt of your staff, arrangements for an information gathering site visit and the three-
The inspection will evaluate the capability of risk significant / low margin components to function
week onsite inspection.  The schedule is as follows: *Information gathering visit:  Week of May 14-18, 2007*Onsite weeks:  June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007. The purpose of the information gathering visit is to meet with members of your staff to identifyrisk-significant components and operator actions.  Information and documentation needed to
as designed and support proper system operation.  The inspection will also include a review of
selected operator actions, operating experience, and modifications.  
During a telephone conversation on March 13, 2007, Mr. R. Moore confirmed with  
Mr. R. Proffitt of your staff, arrangements for an information gathering site visit and the three-
week onsite inspection.  The schedule is as follows:  
*
Information gathering visit:  Week of May 14-18, 2007
*
Onsite weeks:  June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007.  
The purpose of the information gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions.  Information and documentation needed to
support the inspection will also be identified.  Mr. Rudy Bernhard, a Region II Senior Reactor
support the inspection will also be identified.  Mr. Rudy Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Taylor during the information gathering visit to review probabilistic
Analyst, may accompany Mr. Taylor during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
risk assessment data and identify risk significant components which will be examined during the
inspection.The enclosure lists documents that will be needed prior to the information gathering visit.  Pleasecontact Mr. Taylor prior to preparing copies of the materials listed in the enclosure and provide
inspection.
this information to the Region II office by April 30, 2007.  
The enclosure lists documents that will be needed prior to the information gathering visit.  Please
TVA 2The inspectors will try to minimize your administrative burden by specifically identifying onlythose documents required for the inspection preparation.  During the information gathering visit, the team leader will also discuss the following inspectionsupport administrative details: office space, supplemental documents requested to be made
contact Mr. Taylor prior to preparing copies of the materials listed in the enclosure and provide
this information to the Region II office by April 30, 2007.
 
TVA
2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.   
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
available to the team in the Region II office prior to the inspection preparation week of
May 28 - June 1, 2007; arrangements for site access; and the availability of knowledgeable
May 28 - June 1, 2007; arrangements for site access; and the availability of knowledgeable
plant engineering and licensing personnel to serve as points of contact during the inspection.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system
plant engineering and licensing personnel to serve as points of contact during the inspection.
(ADAMS).  ADAMS is accessible from the NRC Web  
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Thank you for your cooperation in this matter.  If you have any questions regarding theinformation requested or the inspection, please contact Mr. Taylor at (404) 562-4568 or me at
enclosure will be available electronically for public inspection in the NRC Public Document
(404) 562-4876.Sincerely,/RA/L.M. Cain, Acting Branch ChiefEngineering Branch 1
Room or from the Publicly Available Records (PARS) component of NRC's document system
Division of Reactor SafetyDocket Nos.:50-327, 50-328License Nos.:DPR-77, DPR-79Enclosure: Information Request for Sequoyah Nuclear Plant                       Component Design Bases Inspection
(ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
cc w/encl:  
rm/adams.html (the Public Electronic Reading Room).
TVA 3Ashok S. BhatnagarSenior Vice President
Thank you for your cooperation in this matter.  If you have any questions regarding the
information requested or the inspection, please contact Mr. Taylor at (404) 562-4568 or me at
(404) 562-4876.
Sincerely,
/RA/
L.M. Cain, Acting Branch Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.:50-327, 50-328
License Nos.:DPR-77, DPR-79
Enclosure: Information Request for Sequoyah Nuclear Plant
                      Component Design Bases Inspection
cc w/encl:
 
TVA
3
Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Nuclear Operations
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionPreston D. SwaffordSenior Vice President
Electronic Mail Distribution
Preston D. Swafford
Senior Vice President
Nuclear Support
Nuclear Support
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionLarry S. Bryant, Vice PresidentNuclear Engineering &
Electronic Mail Distribution
Larry S. Bryant, Vice President
Nuclear Engineering &
Technical Services
Technical Services
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionRandy DouetSite Vice President
Electronic Mail Distribution
Randy Douet
Site Vice President
Sequoyah Nuclear Plant
Sequoyah Nuclear Plant
Electronic Mail DistributionGeneral CounselTennessee Valley Authority
Electronic Mail Distribution
Electronic Mail DistributionJohn C. Fornicola, General ManagerNuclear Assurance
General Counsel
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionGlenn W. Morris, ManagerLicensing and Industry Affairs
Electronic Mail Distribution
John C. Fornicola, General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
Glenn W. Morris, Manager
Licensing and Industry Affairs
Sequoyah Nuclear Plant
Sequoyah Nuclear Plant
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionBeth A. Wetzel, ManagerCorporate Nuclear Licensing and
Electronic Mail Distribution
Beth A. Wetzel, Manager
Corporate Nuclear Licensing and
   Industry Affairs
   Industry Affairs
Tennessee Valley Authority
Tennessee Valley Authority
4X Blue Ridge
4X Blue Ridge
1101 Market Street
1101 Market Street
Chattanooga, TN 37402-2801Robert H. Bryan, Jr., General  ManagerLicensing and Industry Affairs
Chattanooga, TN 37402-2801
Robert H. Bryan, Jr., General  Manager
Licensing and Industry Affairs
Sequoyah Nuclear Plant
Sequoyah Nuclear Plant
Tennessee Valley Authority
Tennessee Valley Authority
4X Blue Ridge
4X Blue Ridge
1101 Market Street
1101 Market Street
Chattanooga, TN 37402-2801David A. Kulisek, Plant ManagerSequoyah Nuclear Plant
Chattanooga, TN 37402-2801
David A. Kulisek, Plant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail DistributionLawrence E. Nanney, DirectorTN Dept. of Environment & Conservation
Electronic Mail Distribution
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Division of Radiological Health
Electronic Mail DistributionCounty MayorHamilton County Courthouse
Electronic Mail Distribution
Chattanooga, TN  37402-2801Ann Harris341 Swing Loop
County Mayor
Hamilton County Courthouse
Chattanooga, TN  37402-2801
Ann Harris
341 Swing Loop
Rockwood, TN  37854
Rockwood, TN  37854
James H. Bassham, DirectorTennessee Emergency Management
James H. Bassham, Director
Tennessee Emergency Management
Agency
Agency
Electronic Mail Distribution  
Electronic Mail Distribution
 
 
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
/RA/
/RA/
NAME
RBernhard
RMoore
MWidmann
RTaylor
DATE
3/13/2007
3/13/2007
3/13/2007
3/13/2007
E-MAIL COPY?
    YES
NO      YES
NO      YES
NO      YES
NO      YES
NO      YES
NO      YES
NO   


_________________________OFFICERII:DRSRII:DRSRII:DRPRII:DRSSIGNATURE/RA//RA//RA//RA/NAMERBernhardRMooreMWidmannRTaylorDATE3/13/20073/13/20073/13/20073/13/2007
Enclosure
E-MAIL COPY?    YESNO      YESNO      YESNO      YESNO      YESNO      YESNO      YESNO   
Please provide the information electronically in .pdf files, Excel, or other searchable format on
EnclosurePlease provide the information electronically in ".pdf" files, Excel, or other searchable format onCDROM.  The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
CDROM.  The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
should contain enough information to be easily understood to someone who has a knowledge
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
of pressurized water reactor technology.
1.From your most-recent probabilistic safety analysis (PSA) excluding external events andfires:
1.
a.Two risk rankings of components from your site-specific probabilistic safety analysis(PSA):  one sorted by Risk Achievement Worth (RAW), and the other sorted by
From your most-recent probabilistic safety analysis (PSA) excluding external events and
Birnbaum Importance.b.A list of the top 500 cutsets.2.From your most-recent probabilistic safety analysis (PSA) including external events andfires:
fires:
a.Two risk rankings of components from your site-specific probabilistic safety analysis(PSA):  one sorted by Risk Achievement Worth (RAW), and the other sorted by
a.
Birnbaum Importance.b.A list of the top 500 cutsets..  3.Risk ranking of operator actions from your site specific PSA sorted by RAW.  Providecopies of your human reliability worksheets for these items..4.Any pre-existing evaluation or list of components and calculations with low design margins(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design
Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA):  one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b.
A list of the top 500 cutsets.
2.
From your most-recent probabilistic safety analysis (PSA) including external events and
fires:
a.
Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA):  one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b.
A list of the top 500 cutsets..   
3.
Risk ranking of operator actions from your site specific PSA sorted by RAW.  Provide
copies of your human reliability worksheets for these items..
4.
Any pre-existing evaluation or list of components and calculations with low design margins
(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design
required output, heat exchangers close to rated design heat removal, MOV risk-margin
required output, heat exchangers close to rated design heat removal, MOV risk-margin
rankings, etc.).5.A list of station applicability evaluations/reviews performed and documented in the stationcorrective action program in the past two years for industry events, critical equipment
rankings, etc.).
5.
A list of station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
communications, industry communications, 10 CFR part 21 notifications, etc.] 6.A list of safety related SSC design modifications implemented within the last two years,sorted by affected system.7.This item deleted.  Corrective action lists will be requested after the component sample isdetermined
communications, industry communications, 10 CFR part 21 notifications, etc.]  
.8.A list of common-cause failure of components that have occurred at Sequoyah and havebeen identified within the last five years.  9.A list of operability evaluations completed within the last two years, sorted by associatedcomponent or system.10.Contact information for a person to discuss PRA information prior to the informationgathering trip: name, title, phone number, and e-mail address11.List of equipment currently on the site's Station Equipment Reliability Issues List, includinga description of the reason(s) why each component is on that list and summaries (if
6.
available) of your plans to address those reasons.12.List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
A list of safety related SSC design modifications implemented within the last two years,
13.List of equipment currently in MR (a)(1) status.
sorted by affected system.
7.
This item deleted.  Corrective action lists will be requested after the component sample is
determined.
8.
A list of common-cause failure of components that have occurred at Sequoyah and have
been identified within the last five years.   
9.
A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address
11. List of equipment currently on the sites Station Equipment Reliability Issues List, including
a description of the reason(s) why each component is on that list and summaries (if
available) of your plans to address those reasons.
12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.
}}
}}

Latest revision as of 02:43, 15 January 2025

Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection (CDBI) - NRC Inspection Report 05000327-07-006 and 05000328-07-006 and Information Request for CDBI
ML070730078
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 03/13/2007
From: Cain L
NRC/RGN-II/DRS/EB1
To: Singer K
Tennessee Valley Authority
References
IR-07-006
Download: ML070730078 (5)
v • d • e


See also: IR 05000327/2007006

Text

March 13, 2007

Tennessee Valley Authority

ATTN:

Mr. Karl W. Singer

Chief Nuclear Officer and

Executive Vice President

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

SUBJECT:

NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN

BASES INSPECTION - NRC INSPECTION REPORT 05000327/2007006 AND

05000328/2007006

Dear Mr. Singer:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a component design bases inspection at your Sequoyah Nuclear

Plant during the weeks of June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007. The

inspection team will be led by Mr. Ryan Taylor, a Senior Reactor Inspector from the NRC's

Region II Office. This inspection will be conducted in accordance with the baseline inspection

procedure, Procedure 71111.21, Component Design Bases Inspection, issued June 22, 2006.

The inspection will evaluate the capability of risk significant / low margin components to function

as designed and support proper system operation. The inspection will also include a review of

selected operator actions, operating experience, and modifications.

During a telephone conversation on March 13, 2007, Mr. R. Moore confirmed with

Mr. R. Proffitt of your staff, arrangements for an information gathering site visit and the three-

week onsite inspection. The schedule is as follows:

Information gathering visit: Week of May 14-18, 2007

Onsite weeks: June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007.

The purpose of the information gathering visit is to meet with members of your staff to identify

risk-significant components and operator actions. Information and documentation needed to

support the inspection will also be identified. Mr. Rudy Bernhard, a Region II Senior Reactor

Analyst, may accompany Mr. Taylor during the information gathering visit to review probabilistic

risk assessment data and identify risk significant components which will be examined during the

inspection.

The enclosure lists documents that will be needed prior to the information gathering visit. Please

contact Mr. Taylor prior to preparing copies of the materials listed in the enclosure and provide

this information to the Region II office by April 30, 2007.

TVA

2

The inspectors will try to minimize your administrative burden by specifically identifying only

those documents required for the inspection preparation.

During the information gathering visit, the team leader will also discuss the following inspection

support administrative details: office space, supplemental documents requested to be made

available to the team in the Region II office prior to the inspection preparation week of

May 28 - June 1, 2007; arrangements for site access; and the availability of knowledgeable

plant engineering and licensing personnel to serve as points of contact during the inspection.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRC's document system

(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact Mr. Taylor at (404) 562-4568 or me at

(404) 562-4876.

Sincerely,

/RA/

L.M. Cain, Acting Branch Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.:50-327, 50-328

License Nos.:DPR-77, DPR-79

Enclosure: Information Request for Sequoyah Nuclear Plant

Component Design Bases Inspection

cc w/encl:

TVA

3

Ashok S. Bhatnagar

Senior Vice President

Nuclear Operations

Tennessee Valley Authority

Electronic Mail Distribution

Preston D. Swafford

Senior Vice President

Nuclear Support

Tennessee Valley Authority

Electronic Mail Distribution

Larry S. Bryant, Vice President

Nuclear Engineering &

Technical Services

Tennessee Valley Authority

Electronic Mail Distribution

Randy Douet

Site Vice President

Sequoyah Nuclear Plant

Electronic Mail Distribution

General Counsel

Tennessee Valley Authority

Electronic Mail Distribution

John C. Fornicola, General Manager

Nuclear Assurance

Tennessee Valley Authority

Electronic Mail Distribution

Glenn W. Morris, Manager

Licensing and Industry Affairs

Sequoyah Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Beth A. Wetzel, Manager

Corporate Nuclear Licensing and

Industry Affairs

Tennessee Valley Authority

4X Blue Ridge

1101 Market Street

Chattanooga, TN 37402-2801

Robert H. Bryan, Jr., General Manager

Licensing and Industry Affairs

Sequoyah Nuclear Plant

Tennessee Valley Authority

4X Blue Ridge

1101 Market Street

Chattanooga, TN 37402-2801

David A. Kulisek, Plant Manager

Sequoyah Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Lawrence E. Nanney, Director

TN Dept. of Environment & Conservation

Division of Radiological Health

Electronic Mail Distribution

County Mayor

Hamilton County Courthouse

Chattanooga, TN 37402-2801

Ann Harris

341 Swing Loop

Rockwood, TN 37854

James H. Bassham, Director

Tennessee Emergency Management

Agency

Electronic Mail Distribution

_________________________

OFFICE

RII:DRS

RII:DRS

RII:DRP

RII:DRS

SIGNATURE

/RA/

/RA/

/RA/

/RA/

NAME

RBernhard

RMoore

MWidmann

RTaylor

DATE

3/13/2007

3/13/2007

3/13/2007

3/13/2007

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO

Enclosure

Please provide the information electronically in .pdf files, Excel, or other searchable format on

CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists

should contain enough information to be easily understood to someone who has a knowledge

of pressurized water reactor technology.

1.

From your most-recent probabilistic safety analysis (PSA) excluding external events and

fires:

a.

Two risk rankings of components from your site-specific probabilistic safety analysis

(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by

Birnbaum Importance.

b.

A list of the top 500 cutsets.

2.

From your most-recent probabilistic safety analysis (PSA) including external events and

fires:

a.

Two risk rankings of components from your site-specific probabilistic safety analysis

(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by

Birnbaum Importance.

b.

A list of the top 500 cutsets..

3.

Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide

copies of your human reliability worksheets for these items..

4.

Any pre-existing evaluation or list of components and calculations with low design margins

(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design

required output, heat exchangers close to rated design heat removal, MOV risk-margin

rankings, etc.).

5.

A list of station applicability evaluations/reviews performed and documented in the station

corrective action program in the past two years for industry events, critical equipment

failures, and safety related equipment vulnerabilities [as communicated by NRC generic

communications, industry communications, 10 CFR part 21 notifications, etc.]

6.

A list of safety related SSC design modifications implemented within the last two years,

sorted by affected system.

7.

This item deleted. Corrective action lists will be requested after the component sample is

determined.

8.

A list of common-cause failure of components that have occurred at Sequoyah and have

been identified within the last five years.

9.

A list of operability evaluations completed within the last two years, sorted by associated

component or system.

10. Contact information for a person to discuss PRA information prior to the information

gathering trip: name, title, phone number, and e-mail address

11. List of equipment currently on the sites Station Equipment Reliability Issues List, including

a description of the reason(s) why each component is on that list and summaries (if

available) of your plans to address those reasons.

12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.

13. List of equipment currently in MR (a)(1) status.

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