Safety Culture Policy Statement Development: Public Meeting and Request for Public Comments, 6433-6436 [E9-2621]
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Federal Register / Vol. 74, No. 25 / Monday, February 9, 2009 / Notices
NUCLEAR REGULATORY
COMMISSION
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS) Subcommittee
Meeting on Thermal-Hydraulic
Phenomena; Notice of Meeting
[NRC–2009–0013]
The ACRS Subcommittee on ThermalHydraulic Phenomena will hold a
meeting on February 27, 2009, in Room
T–2B3, Two White Flint North, 11545
Rockville Pike, Rockville, Maryland.
A portion of the meeting may be
closed to discuss and protect
information that is proprietary to
General Electric—Hitachi, and its
contractors pursuant to 5 U.S.C
552b(c)(4).
The agenda for the subject meeting
shall be as follows:
AGENCY: U.S. Nuclear Regulatory
Commission (NRC).
ACTION: Notice of Public Meeting and
request for comments.
Safety Culture Policy Statement
Development: Public Meeting and
Request for Public Comments
Friday, February 27, 2009—8:30 a.m.
Until the Conclusion of Business
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The Subcommittee will discuss the
applicability of the TRACE code to the
ESBWR design. The Subcommittee will
hear presentations by and hold
discussions with representatives of the
NRC staff, consultants to the staff, and
other interested persons regarding this
matter. The Subcommittee will gather
information, analyze relevant issues and
facts, and formulate proposed positions
and actions, as appropriate, for
deliberation by the full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Officer, Mr. David Bessette at
301–415–8065, five days prior to the
meeting, if possible, so that appropriate
arrangements can be made. Electronic
recordings will be permitted only
during those portions of the meeting
that are open to the public. Detailed
procedures for the conduct of and
participation in ACRS meetings were
published in the Federal Register on
October 6, 2008, (73 FR 58268–58269).
Further information regarding this
meeting can be obtained by contacting
the Designated Federal Officer between
7:45 a.m. and 4:30 p.m. (ET). Persons
planning to attend this meeting are
urged to contact the above named
individual at least two working days
prior to the meeting to be advised of any
potential changes to the agenda.
Dated: February 3, 2009.
Antonio Dias,
Chief, Reactor Safety Branch B, Advisory
Committee on Reactor Safeguards.
[FR Doc. E9–2625 Filed 2–6–09; 8:45 am]
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SUMMARY: The NRC is developing an
update to its policy statement on safety
culture to include the unique aspects of
security and to ensure that the policy
applies to all licensees and certificate
holders. The NRC is conducting a public
meeting to solicit public input on topics
relating to the development of the
policy statement. In addition to
announcing the public meeting, the
NRC is using this notice to request
comments on the topics discussed in
this notice. These topics can be found
in section D (Topics for Discussion) of
the SUPPLEMENTARY INFORMATION.
DATES:
Public Meeting Dates: The NRC will
take public comments at the public
meeting on February 3, 2009.
Comment Dates: Comments are
requested by February 11, 2009.
Comments received after this date will
be considered if it is practical to do so,
but the NRC is able to assure
consideration only for comments
received on or before this date. The NRC
will also take public comments on the
questions raised in this notice at a
public meeting on February 3, 2009.
Please refer to the SUPPLEMENTARY
INFORMATION section for additional
information, including the topics and
associated questions to which NRC is
requesting input.
ADDRESSES: The public meeting will be
held on February 3, 2009, in the
Commissioners’ Hearing Room of the
NRC Headquarters building at 11555
Rockville Pike, Rockville, MD 20852,
which is across the street from the
White Flint Metro stop. The most
convenient transportation to the
meeting venue is via Metro since there
is extremely limited on-street parking.
Please take Metro to the White Flint
Metro stop on the Red Line. Please
allow time to register with building
security and to check with the entry
guard station for signs for the Safety
Culture Policy Statement Public
Meeting room as you enter the building.
Users unable to travel to the NRC
Headquarters may participate by
Webinar or teleconference. Please see
the meeting notice, which is posted on
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the NRC public meeting schedule Web
site: https://www.nrc.gov/public-involve/
public-meetings/index.cfm?fuseaction=
Search.Detail&MC=20080837&NS=
0&CFID=264654&CFTOKEN=94010205,
for instructions on how to register for
the workshop.
After the conduct of the public
meeting, members of the public are
invited and encouraged to submit
comments by February 11, 2009, by mail
to June Cai, Concerns Resolution
Branch, Office of Enforcement, Mail
Stop O–4 A15A, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, or by e-mail to
june.cai@nrc.gov.
To ensure efficient consideration of
your comments, please identify the
related topic and specific question
numbers with your comments when
applicable. When commenting, please
exercise caution with regard to sitespecific security-related information.
Comments will be made available to the
public in their entirety. Personal
information, such as your name,
address, telephone number, e-mail
address, etc. will not be removed from
your submission.
You can access publicly available
documents related to this notice using
the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee, publicly available
documents at the NRC’s PDR, Public
File Area O–1 F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC after November 1,
1999, are available electronically at the
NRC’s Electronic Reading Room at
https://www.nrc.gov/reading-rm/
adams.html. From this site, the public
can gain entry into ADAMS, which
provides text and image files of NRC’s
public documents. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the PDR
Reference staff at 1–800–397–4209,
(301) 415–4737 or by e-mail to
pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT: June
Cai, (301) 415–5192, june.cai@nrc.gov of
the Office of Enforcement, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001. Public meeting
attendees are requested to register with
one of the meeting contacts by January
30, 2009. Please let the meeting contacts
know if special services, such as for the
hearing impaired, are necessary.
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Federal Register / Vol. 74, No. 25 / Monday, February 9, 2009 / Notices
A.
Purpose of the Public Meeting: The
purpose of this meeting is to solicit the
views of interested stakeholders on
topics related to safety culture that were
provided in the Commission’s Staff
Requirements Memoranda (SRM)–
COMGBJ–08–0001 (ML080560476), ‘‘A
Commission Policy Statement on Safety
Culture,’’ dated February 25, 2008,
which are presented in Section D,
below. The NRC will consider the input
received during the meeting in the
development of the draft policy
statement(s) addressing safety culture
and security culture.
B. Public Meeting Agenda: A meeting
notice and detailed agenda is available
on the NRC public meeting schedule
Web site: https://www.nrc.gov/publicinvolve/public-meetings/index.cfm
?fuseaction=Search.Detail&
MC=20080837&NS=0&CFID=264654
&CFTOKEN=94010205. The meeting
notice has information on how to
participate via Webinar or
teleconference. Concurrent with the
meeting, there will be an open house
poster session throughout the day to
provide additional opportunities for
attendees to provide input. The
information presented at the open house
will also be made available at the Web
site listed above, to allow those unable
to attend the meeting or attending
through the Webinar or teleconference
to view the information and have an
opportunity to provide their input on
the topics addressed at the open house.
C. Background: The NRC recognizes
the importance of licensees to establish
and maintain a strong safety culture—a
work environment where management
and employees are dedicated to putting
safety first. The Commission previously
addressed this topic on January 24, 1989
(54 FR 3424) in ‘‘Policy Statement on
the Conduct of Nuclear Power Plant
Operations’’ (https://www.nrc.gov/aboutnrc/regulatory/enforcement/
54fr3424.pdf)—the Commission’s policy
statement on safety culture—where it
described expectations for such a safety
culture and how it supports the agency’s
mission to protect public health and
safety. Although the policy statement
was issued to make clear the
Commission’s expectation of utility
management and licensed operators
with respect to the conduct of nuclear
power plant operations, the Commission
intended for the policy statement to
help foster the development and
maintenance of a safety culture at every
facility licensed by the NRC. In the
Policy Statement, safety culture is
described as ‘‘the necessary full
attention to safety matters,’’ and the
‘‘personal dedication and accountability
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SUPPLEMENTARY INFORMATION:
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of all individuals engaged in any
activity which has a bearing on the
safety of nuclear power plants. A strong
safety culture is one that has a strong
safety-first focus.’’
The Commission has referenced the
International Nuclear Safety Advisory
Group’s (INSAG) definition of safety
culture as follows: ‘‘Safety Culture is
that assembly of characteristics and
attitudes in organizations and
individuals which establishes that, as an
overriding priority, nuclear safety issues
receive the attention warranted by their
significance.’’
On May 14, 1996, the Commission
published its policy, ‘‘Freedom of
Employees in the Nuclear Industry to
Raise Safety Concerns without Fear of
Retaliation’’ (61 FR 24336) (https://www.
nrc.gov/about-nrc/regulatory/
allegations/scwe-frn-5-14-96.pdf), which
expressed the Commissions expectation
that licensees and other employers
subject to NRC authority will establish
and maintain a safety conscious
environment in which employees feel
free to raise safety concerns, both to
their management and to the NRC,
without fear of retaliation. A safety
conscious work environment is one
facet of a strong safety culture. On
August 25, 2005, the NRC issued
Regulatory Issue Summary 2005–018
(ML052220239), ‘‘Guidance for
Establishing and Maintaining a Safety
Conscious Work Environment,’’ to
provide guidance on maintaining a
safety conscious work environment.
In SRM–COMGBJ–08–0001
(ML080560476), ‘‘A Commission Policy
Statement on Safety Culture,’’ dated
February 25, 2008, the Commission
directed staff to ‘‘expand the
Commission’s policy of safety culture to
address the unique aspects of security
and to ensure the resulting policy is
applicable to all licensees and certificate
holders,’’ and to conduct a ‘‘broad
review of issues related to safety culture
as part of the effort for developing the
oversight process and for revising or
developing additional Commission
Policy Statement(s).’’
The Commission directed the staff to
complete its evaluation, provide a
recommendation to the Commission on
how best to update the Commission
policy, and provide draft policy
statement(s) on safety culture to the
Commission for its consideration. In its
review, the staff should, at a minimum,
evaluate the following key areas:
(1) Whether safety culture as applied
to reactors needs to be strengthened.
(2) How to increase attention to safety
culture in the materials area.
(3) How stakeholder involvement can
most effectively be used to address
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safety culture for all NRC and
Agreement State licensees and
certificate holders, including any
unique aspects of security. The staff
should, as part of its public stakeholder
outreach, reach out to all types of
licensees and certificate holders,
including power reactors (including
new reactors), research and test reactors,
fuel facilities, spent fuel shipping and
storage cask vendors, and the materials
community, including industrial,
academic, and medical users. The
assessment should also involve outreach
activities to Members of Congress, the
Agreement States, and other
stakeholders.
(4) Whether publishing NRC’s
expectations for safety culture and for
security culture is best accomplished in
one safety/security culture statement or
in two separate statements, one each for
safety and security, while still
considering the safety and security
interfaces.
A Safety Culture Policy Statement
Task Group and Steering Committee
have been established to address this
direction. The Task Group has been
conducting review and analysis of
various information and data sources in
order to inform and provide the basis for
the draft policy statement(s) and
recommendations development.
Examples of these sources are
information from existing agency
activities in the safety culture and
security culture area and information
and insights from relevant industry
activities, international activities and
organizations, and the organizational
research literature.
The Task Group has also been
conducting outreach activities with
stakeholders to raise awareness of safety
culture and to provide information
about this activity. The Task Group is
holding the public meeting on February
3, 2009, to provide opportunity for
stakeholders to offer input on the draft
policy statement(s) development and on
key topics related to the Commission
direction.
D. Topics for Discussion: The NRC is
seeking input on key topics related to
the direction from the Commission on
the Safety Culture Policy Statement
development. Specifically, the NRC is
seeking input on the following topics:
1. Should NRC combine its
expectations in the policy statement for
safety culture and security culture or
should NRC keep its expectations
separate?
2. How should NRC increase attention
by NRC, licensees, and certificate
holders to safety culture in the materials
area?
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3. Does safety culture as applied to
reactors needs to be strengthened?
Obtaining public input on these
topics will be the focus of the February
3, 2009, public meeting. The NRC has
developed a series of questions relating
to each of these topics to foster
discussion and to solicit specific
information relating to the Commission
direction.
The following format is used in the
presentation of the topics below. Each
topic is assigned a number and a short
title, and a list of questions for
consideration then follows. Each
question, or set of questions, is also
assigned a number. When providing
written comments, please list the
relevant topic and question numbers
when appropriate.
Topic 1: Should NRC combine its
expectations in the policy statement for
safety culture and security culture or
should NRC keep its expectations
separate?
Q1.1. Within organizations, one can
think about safety and security in
different ways. For example, safety may
take precedence over security, security
may take precedence over safety, or both
may be treated equally. Different types
of licensees, certificate holders and
organizations have a variety of
experiences and perspectives. How do
you generally view the relationship or
hierarchy between safety and security
functions and decision making?
Q1.2. While efforts to maintain safety
and security have the same common
goal of protecting public health and
safety, there can be distinct differences
in the approach used to achieve that
goal and that may have competing
outcomes. One example is how
information is shared to mitigate risks,
where increased sharing of information
may contribute to maintaining safety,
but presents increased security risks.
Are there other examples where efforts
to maintain safety and security require
different approaches or result in
competing outcomes that need to be
addressed to achieve the desired
outcome or goal?
Q1.3. When resolving differences or
conflicts while seeking to maintain
safety and security—such as when
managing risk, sharing information,
planning work, correcting problems,
etc.—and where changes or actions that
are taken to address either a safety issue
or a security issue could have an
adverse effect on the other (i.e., security
or safety, respectively); what challenges
does your organization face?
Q1.4. What challenges or complexities
arise when licensees and certificate
holders work with contractors and
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vendors where the organizations either
take different approaches to resolving
conflicting outcomes when they seek to
maintain safety and security or the
organizations may balance the
conflicting outcomes of efforts to
maintain safety and security differently?
Q1.5. What practices have been used
to effectively address the conflicts to
achieve the desired outcomes or goals?
Q1.6. Given that there are several
ways to think about safety culture and
security culture within organizations,
the NRC wishes to express a policy in
a way that best furthers its goals of
protecting the public and environment
and ensuring the secure use and
management of radioactive materials.
If the above issues are viewed in
terms of safety culture and security
culture implementation, what benefits
or challenges would licensees,
certificate holders, Agreement States, or
others foresee with a single policy
statement? Two separate policy
statements?
Q1.7. How can the NRC best express
a policy that gives appropriate weight to
safety culture and security culture
across the range of licensees and
certificate holders?
Q1.8. Given the diversity among the
licensees and certificate holders
regulated by the NRC and the
Agreement States, how should the
policy statement address any differences
in emphasis on safety and security at
the different types of licensees and
certificate holders?
Topic 2: How should NRC increase
attention by licensees and certificate
holders to safety culture in the materials
area?
Q2.1. What is the NRC doing that is
working well to help materials licensees
and certificate holders to maintain their
safety culture and security culture?
Q2.2. What might the NRC do
differently, or that it is not currently
doing, to increase NRC, licensee, or
certificate holder attention to safety
culture at materials licensees and
certificate holders?
Q2.3. How could the NRC better
interact with materials licensees and
certificate holders to help them to pay
greater attention to maintaining their
safety culture and/or security culture?
Q2.4. If the NRC expresses a policy for
materials licensees and certificate
holders to maintain safety culture and
security culture, or made its references
to safety culture and security culture
more explicit in its interactions with
these licensees and certificate holders,
how would their performance change?
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Q2.5. What should the NRC consider
when developing policy statement(s) on
safety culture and security culture?
Q2.5.1. What is the current level of
understanding of materials licensees
and certificate holders of the NRC’s
expectations that they maintain a safety
culture that is cognizant of issues
relating to security? How does this level
of understanding change with the type
of licensee or certificate holder?
Q2.5.2. How should the NRC consider
the different activities (e.g., risk, type of
material, quantities of materials, how
the material is used, location, etc.)
conducted at materials licensees and
certificate holders when evaluating
whether, or how, to express its policy?
Q2.5.3. How should NRC consider
differences in the materials licensees
and certificate holders (e.g., size of
workforce, relationship to activities not
regulated by the NRC, etc.) when
evaluating whether, or how, to express
its policy? What differences should the
NRC consider?
Q2.5.4. What are the unique aspects of
security at materials licensees and
certificate holders that the NRC should
consider when expressing its policy?
Q2.5.5. What topics should be
addressed in the policy statement(s) that
would be of value to materials licensees
and certificate holders?
Q2.5.6. How could the policy
statement(s) effectively address issues
that involve both safety and security (at
the safety/security interface) at materials
licensees and certificate holders?
Q2.5.7. How can the NRC best express
a policy that gives appropriate weight to
safety culture and security culture
across the range of licensees and
certificate holders?
Q2.5.8. Given the diversity among the
licensees and certificate holders
regulated by the NRC and the
Agreement States, how should the
policy statement address any differences
in emphasis on safety and security at
the different types of licensees and
certificate holders?
Q2.6. How should the NRC work with
the Agreement States to encourage
increased attention being focused on
safety culture, including the unique
aspects of security, at Agreement State
licensees?
Q2.6.1. What is the level of
understanding at Agreement State
licensees regarding the value in
maintaining safety culture and security
culture?
Q2.6.2. What is the level of
understanding of safety culture and
security culture within the Agreement
States?
Q2.6.3. How do the Agreement States
view the NRC’s goal of increasing the
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attention paid to safety culture and
security culture at materials licensees
and certificate holders?
Q2.6.4. What topics do the Agreement
States believe should be addressed in
the policy statement(s)?
Q2.6.5. How could the NRC help the
Agreement States to increase attention
to safety culture and security culture at
their licensees?
Q2.6.6. How should the NRC address
safety culture and security culture at
Agreement State licensees that engage in
activities within NRC jurisdiction under
reciprocity?
Q2.6.7. How might NRC use
stakeholder involvement to increase the
attention that materials licensees and
certificate holders give to maintaining a
safety culture, including the unique
aspects of security?
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Topic 3: Does safety culture as applied
to reactors need to be strengthened?
A number of enhancements were
made to the ROP in 2006 to address
safety culture (for example: safety
culture cross-cutting aspect assignment
to findings; identifying substantive
cross-cutting issues; performing an
independent NRC safety culture
assessment for licensees in Column 4 of
the ROP Action Matrix).
Q3.1. What are the strengths and
weaknesses of the current approach for
evaluating licensee safety culture in the
ROP?
Q3.2. How has the use of safety
culture cross-cutting aspects that are
assigned to inspection findings helped
to identify potential safety culture
issues? Suggest any alternative
approaches that licensees could use to
identify potential safety culture issues.
Q3.3. What may be better or more
effective methods or tools that the NRC
could use to help identify precursors to
future plant performance deficiencies?
Q.3.4. In the following situations the
NRC may/or will request a licensee to
perform a safety culture assessment
(licensee self-assessment, independent
assessment, or a third-party assessment):
(a) The same substantive cross-cutting
issue had been identified in three
consecutive assessment letters
(generated from assessments conducted
at 6 month intervals); (b) a 95002
inspection (Inspection for One Degraded
Cornerstone or Any Three White Inputs
in a Strategic Performance Area) that
confirmed the licensee had not
identified a safety culture component
that either caused or significantly
contributed to the risk-significant
performance issue that resulted in the
supplemental inspection; and (c) a plant
enters Column 4 of the Action Matrix.
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Under what other situations should
the NRC consider requesting that a
licensee perform a safety culture
assessment?
Another ROP enhancement was for
the NRC to perform an independent
safety culture assessment for plants that
enter the multiple repetitive/degraded
cornerstone column (column 4).
Q3.5. In what other circumstances
might the NRC consider performing an
independent safety culture assessment?
Q3.6. What other entity, other than
the NRC, could perform an independent
safety culture assessment or simply
verify the results of the licensee’s
assessments and corrective actions?
Q3.7. What additional safety culture
related ROP changes could help the
NRC to improve the focus of NRC and
licensee attention on site safety culture
issues?
The NRC has held public meetings
where draft changes to several ROP
guidance documents resulting from a
lessons learned evaluation of the initial
implementation period of the ROP
safety culture enhancements have been
made available for public comment.
Q3.8. What areas beyond the draft
changes (for example, a provision in
Inspection Procedure 95003 for the NRC
to be able to conduct a graded safety
culture assessment) presented by the
NRC have the potential to further
enhance how the ROP addresses safety
culture?
Q3.8.1. How would these potential
changes enhance or improve how the
NRC addresses safety culture through
the ROP?
Q3.9. In what ways does the current
process lead to consistency/
predictability of implementation by the
NRC? Provide examples to support your
view.
Q3.9.1. In what ways does it lead to
inconsistency or unpredictability?
Q3.10. How effective is the ROP in
addressing security culture issues?
Q3.10.1. What ROP changes could
help the NRC to improve the focus of
NRC and licensee attention on site
security culture issues?
In previous public meetings, the NRC
has discussed using the ROP safety
culture components and modified
aspects as a tool to understand the
challenges to safety culture during new
reactor construction.
Q3.11. How can challenges to safety
culture in new reactor construction be
identified and addressed in regulatory
oversight?
Dated at Rockville, Maryland, this 27th day
of January, 2009.
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For the Nuclear Regulatory Commission.
Stewart L. Magruder,
Deputy Director, Office of Enforcement.
[FR Doc. E9–2621 Filed 2–6–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 040–08502; NRC–2009–0036]
Notice of Request To Renew Source
Materials License SUA–1341, COGEMA
Mining, Inc., Christensen and Irigaray
Ranch Facilities, Johnson and
Campbell Counties, WY, and
Opportunity To Request a Hearing
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of license renewal
request and opportunity to request a
hearing.
DATES: A request for a hearing must be
filed by April 10, 2009.
FOR FURTHER INFORMATION CONTACT: Ron
C. Linton, Project Manager, Uranium
Recovery Licensing Branch, Division of
Waste Management and Environmental
Protection, Office of Federal and State
Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555. Telephone: (301) 415–7777;
fax number: (301) 415–5369; e-mail:
ron.linton@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
By letter dated May 30, 2008,
COGEMA Mining, Inc. (COGEMA),
submitted a License Renewal
Application to the U.S. Nuclear
Regulatory Commission (NRC) to renew
Source Materials License SUA–1341 for
the Christensen and Irigaray Ranch
Facilities in Johnson and Campbell
Counties, Wyoming (ADAMS Accession
Package No. ML081850689). COGEMA
has requested that the license be
renewed as a performance-based
license, which is its current form.
COGEMA also requested that the
renewal be for ten (10) years, consistent
with the last renewal. The renewal, if
granted, would allow for continued
uranium production operations and the
recovery of uranium by in situ recovery
(ISR) extraction techniques as
previously licensed by the NRC. An
NRC administrative review,
documented in a letter to COGEMA
dated December 29, 2008 (ADAMS
Accession No. ML082760265), found
the amendment request acceptable to
begin a technical review. Before
approving the license amendment, the
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Agencies
[Federal Register Volume 74, Number 25 (Monday, February 9, 2009)]
[Notices]
[Pages 6433-6436]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-2621]
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NUCLEAR REGULATORY COMMISSION
[NRC-2009-0013]
Safety Culture Policy Statement Development: Public Meeting and
Request for Public Comments
AGENCY: U.S. Nuclear Regulatory Commission (NRC).
ACTION: Notice of Public Meeting and request for comments.
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SUMMARY: The NRC is developing an update to its policy statement on
safety culture to include the unique aspects of security and to ensure
that the policy applies to all licensees and certificate holders. The
NRC is conducting a public meeting to solicit public input on topics
relating to the development of the policy statement. In addition to
announcing the public meeting, the NRC is using this notice to request
comments on the topics discussed in this notice. These topics can be
found in section D (Topics for Discussion) of the SUPPLEMENTARY
INFORMATION.
DATES:
Public Meeting Dates: The NRC will take public comments at the
public meeting on February 3, 2009.
Comment Dates: Comments are requested by February 11, 2009.
Comments received after this date will be considered if it is practical
to do so, but the NRC is able to assure consideration only for comments
received on or before this date. The NRC will also take public comments
on the questions raised in this notice at a public meeting on February
3, 2009. Please refer to the SUPPLEMENTARY INFORMATION section for
additional information, including the topics and associated questions
to which NRC is requesting input.
ADDRESSES: The public meeting will be held on February 3, 2009, in the
Commissioners' Hearing Room of the NRC Headquarters building at 11555
Rockville Pike, Rockville, MD 20852, which is across the street from
the White Flint Metro stop. The most convenient transportation to the
meeting venue is via Metro since there is extremely limited on-street
parking. Please take Metro to the White Flint Metro stop on the Red
Line. Please allow time to register with building security and to check
with the entry guard station for signs for the Safety Culture Policy
Statement Public Meeting room as you enter the building. Users unable
to travel to the NRC Headquarters may participate by Webinar or
teleconference. Please see the meeting notice, which is posted on the
NRC public meeting schedule Web site: https://www.nrc.gov/public-
involve/public-meetings/
index.cfm?fuseaction=Search.Detail&MC=20080837&NS=0&CFID=264654&CFTOKEN=
94010205, for instructions on how to register for the workshop.
After the conduct of the public meeting, members of the public are
invited and encouraged to submit comments by February 11, 2009, by mail
to June Cai, Concerns Resolution Branch, Office of Enforcement, Mail
Stop O-4 A15A, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, or by e-mail to june.cai@nrc.gov.
To ensure efficient consideration of your comments, please identify
the related topic and specific question numbers with your comments when
applicable. When commenting, please exercise caution with regard to
site-specific security-related information. Comments will be made
available to the public in their entirety. Personal information, such
as your name, address, telephone number, e-mail address, etc. will not
be removed from your submission.
You can access publicly available documents related to this notice
using the following methods:
NRC's Public Document Room (PDR): The public may examine and have
copied for a fee, publicly available documents at the NRC's PDR, Public
File Area O-1 F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC after
November 1, 1999, are available electronically at the NRC's Electronic
Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this
site, the public can gain entry into ADAMS, which provides text and
image files of NRC's public documents. If you do not have access to
ADAMS or if there are problems in accessing the documents located in
ADAMS, contact the PDR Reference staff at 1-800-397-4209, (301) 415-
4737 or by e-mail to pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT: June Cai, (301) 415-5192,
june.cai@nrc.gov of the Office of Enforcement, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001. Public meeting attendees are
requested to register with one of the meeting contacts by January 30,
2009. Please let the meeting contacts know if special services, such as
for the hearing impaired, are necessary.
[[Page 6434]]
SUPPLEMENTARY INFORMATION: A. Purpose of the Public Meeting: The
purpose of this meeting is to solicit the views of interested
stakeholders on topics related to safety culture that were provided in
the Commission's Staff Requirements Memoranda (SRM)-COMGBJ-08-0001
(ML080560476), ``A Commission Policy Statement on Safety Culture,''
dated February 25, 2008, which are presented in Section D, below. The
NRC will consider the input received during the meeting in the
development of the draft policy statement(s) addressing safety culture
and security culture.
B. Public Meeting Agenda: A meeting notice and detailed agenda is
available on the NRC public meeting schedule Web site: https://
www.nrc.gov/public-involve/public-meetings/
index.cfm?fuseaction=Search.Detail&MC=20080837&NS=0&CFID=264654&CFTOKEN=
94010205. The meeting notice has information on how to participate via
Webinar or teleconference. Concurrent with the meeting, there will be
an open house poster session throughout the day to provide additional
opportunities for attendees to provide input. The information presented
at the open house will also be made available at the Web site listed
above, to allow those unable to attend the meeting or attending through
the Webinar or teleconference to view the information and have an
opportunity to provide their input on the topics addressed at the open
house.
C. Background: The NRC recognizes the importance of licensees to
establish and maintain a strong safety culture--a work environment
where management and employees are dedicated to putting safety first.
The Commission previously addressed this topic on January 24, 1989 (54
FR 3424) in ``Policy Statement on the Conduct of Nuclear Power Plant
Operations'' (https://www.nrc.gov/about-nrc/regulatory/enforcement/
54fr3424.pdf)--the Commission's policy statement on safety culture--
where it described expectations for such a safety culture and how it
supports the agency's mission to protect public health and safety.
Although the policy statement was issued to make clear the Commission's
expectation of utility management and licensed operators with respect
to the conduct of nuclear power plant operations, the Commission
intended for the policy statement to help foster the development and
maintenance of a safety culture at every facility licensed by the NRC.
In the Policy Statement, safety culture is described as ``the necessary
full attention to safety matters,'' and the ``personal dedication and
accountability of all individuals engaged in any activity which has a
bearing on the safety of nuclear power plants. A strong safety culture
is one that has a strong safety-first focus.''
The Commission has referenced the International Nuclear Safety
Advisory Group's (INSAG) definition of safety culture as follows:
``Safety Culture is that assembly of characteristics and attitudes in
organizations and individuals which establishes that, as an overriding
priority, nuclear safety issues receive the attention warranted by
their significance.''
On May 14, 1996, the Commission published its policy, ``Freedom of
Employees in the Nuclear Industry to Raise Safety Concerns without Fear
of Retaliation'' (61 FR 24336) (https://www.nrc.gov/about-nrc/
regulatory/allegations/scwe-frn-5-14-96.pdf), which expressed the
Commissions expectation that licensees and other employers subject to
NRC authority will establish and maintain a safety conscious
environment in which employees feel free to raise safety concerns, both
to their management and to the NRC, without fear of retaliation. A
safety conscious work environment is one facet of a strong safety
culture. On August 25, 2005, the NRC issued Regulatory Issue Summary
2005-018 (ML052220239), ``Guidance for Establishing and Maintaining a
Safety Conscious Work Environment,'' to provide guidance on maintaining
a safety conscious work environment.
In SRM-COMGBJ-08-0001 (ML080560476), ``A Commission Policy
Statement on Safety Culture,'' dated February 25, 2008, the Commission
directed staff to ``expand the Commission's policy of safety culture to
address the unique aspects of security and to ensure the resulting
policy is applicable to all licensees and certificate holders,'' and to
conduct a ``broad review of issues related to safety culture as part of
the effort for developing the oversight process and for revising or
developing additional Commission Policy Statement(s).''
The Commission directed the staff to complete its evaluation,
provide a recommendation to the Commission on how best to update the
Commission policy, and provide draft policy statement(s) on safety
culture to the Commission for its consideration. In its review, the
staff should, at a minimum, evaluate the following key areas:
(1) Whether safety culture as applied to reactors needs to be
strengthened.
(2) How to increase attention to safety culture in the materials
area.
(3) How stakeholder involvement can most effectively be used to
address safety culture for all NRC and Agreement State licensees and
certificate holders, including any unique aspects of security. The
staff should, as part of its public stakeholder outreach, reach out to
all types of licensees and certificate holders, including power
reactors (including new reactors), research and test reactors, fuel
facilities, spent fuel shipping and storage cask vendors, and the
materials community, including industrial, academic, and medical users.
The assessment should also involve outreach activities to Members of
Congress, the Agreement States, and other stakeholders.
(4) Whether publishing NRC's expectations for safety culture and
for security culture is best accomplished in one safety/security
culture statement or in two separate statements, one each for safety
and security, while still considering the safety and security
interfaces.
A Safety Culture Policy Statement Task Group and Steering Committee
have been established to address this direction. The Task Group has
been conducting review and analysis of various information and data
sources in order to inform and provide the basis for the draft policy
statement(s) and recommendations development. Examples of these sources
are information from existing agency activities in the safety culture
and security culture area and information and insights from relevant
industry activities, international activities and organizations, and
the organizational research literature.
The Task Group has also been conducting outreach activities with
stakeholders to raise awareness of safety culture and to provide
information about this activity. The Task Group is holding the public
meeting on February 3, 2009, to provide opportunity for stakeholders to
offer input on the draft policy statement(s) development and on key
topics related to the Commission direction.
D. Topics for Discussion: The NRC is seeking input on key topics
related to the direction from the Commission on the Safety Culture
Policy Statement development. Specifically, the NRC is seeking input on
the following topics:
1. Should NRC combine its expectations in the policy statement for
safety culture and security culture or should NRC keep its expectations
separate?
2. How should NRC increase attention by NRC, licensees, and
certificate holders to safety culture in the materials area?
[[Page 6435]]
3. Does safety culture as applied to reactors needs to be
strengthened?
Obtaining public input on these topics will be the focus of the
February 3, 2009, public meeting. The NRC has developed a series of
questions relating to each of these topics to foster discussion and to
solicit specific information relating to the Commission direction.
The following format is used in the presentation of the topics
below. Each topic is assigned a number and a short title, and a list of
questions for consideration then follows. Each question, or set of
questions, is also assigned a number. When providing written comments,
please list the relevant topic and question numbers when appropriate.
Topic 1: Should NRC combine its expectations in the policy statement
for safety culture and security culture or should NRC keep its
expectations separate?
Q1.1. Within organizations, one can think about safety and security
in different ways. For example, safety may take precedence over
security, security may take precedence over safety, or both may be
treated equally. Different types of licensees, certificate holders and
organizations have a variety of experiences and perspectives. How do
you generally view the relationship or hierarchy between safety and
security functions and decision making?
Q1.2. While efforts to maintain safety and security have the same
common goal of protecting public health and safety, there can be
distinct differences in the approach used to achieve that goal and that
may have competing outcomes. One example is how information is shared
to mitigate risks, where increased sharing of information may
contribute to maintaining safety, but presents increased security
risks. Are there other examples where efforts to maintain safety and
security require different approaches or result in competing outcomes
that need to be addressed to achieve the desired outcome or goal?
Q1.3. When resolving differences or conflicts while seeking to
maintain safety and security--such as when managing risk, sharing
information, planning work, correcting problems, etc.--and where
changes or actions that are taken to address either a safety issue or a
security issue could have an adverse effect on the other (i.e.,
security or safety, respectively); what challenges does your
organization face?
Q1.4. What challenges or complexities arise when licensees and
certificate holders work with contractors and vendors where the
organizations either take different approaches to resolving conflicting
outcomes when they seek to maintain safety and security or the
organizations may balance the conflicting outcomes of efforts to
maintain safety and security differently?
Q1.5. What practices have been used to effectively address the
conflicts to achieve the desired outcomes or goals?
Q1.6. Given that there are several ways to think about safety
culture and security culture within organizations, the NRC wishes to
express a policy in a way that best furthers its goals of protecting
the public and environment and ensuring the secure use and management
of radioactive materials.
If the above issues are viewed in terms of safety culture and
security culture implementation, what benefits or challenges would
licensees, certificate holders, Agreement States, or others foresee
with a single policy statement? Two separate policy statements?
Q1.7. How can the NRC best express a policy that gives appropriate
weight to safety culture and security culture across the range of
licensees and certificate holders?
Q1.8. Given the diversity among the licensees and certificate
holders regulated by the NRC and the Agreement States, how should the
policy statement address any differences in emphasis on safety and
security at the different types of licensees and certificate holders?
Topic 2: How should NRC increase attention by licensees and certificate
holders to safety culture in the materials area?
Q2.1. What is the NRC doing that is working well to help materials
licensees and certificate holders to maintain their safety culture and
security culture?
Q2.2. What might the NRC do differently, or that it is not
currently doing, to increase NRC, licensee, or certificate holder
attention to safety culture at materials licensees and certificate
holders?
Q2.3. How could the NRC better interact with materials licensees
and certificate holders to help them to pay greater attention to
maintaining their safety culture and/or security culture?
Q2.4. If the NRC expresses a policy for materials licensees and
certificate holders to maintain safety culture and security culture, or
made its references to safety culture and security culture more
explicit in its interactions with these licensees and certificate
holders, how would their performance change?
Q2.5. What should the NRC consider when developing policy
statement(s) on safety culture and security culture?
Q2.5.1. What is the current level of understanding of materials
licensees and certificate holders of the NRC's expectations that they
maintain a safety culture that is cognizant of issues relating to
security? How does this level of understanding change with the type of
licensee or certificate holder?
Q2.5.2. How should the NRC consider the different activities (e.g.,
risk, type of material, quantities of materials, how the material is
used, location, etc.) conducted at materials licensees and certificate
holders when evaluating whether, or how, to express its policy?
Q2.5.3. How should NRC consider differences in the materials
licensees and certificate holders (e.g., size of workforce,
relationship to activities not regulated by the NRC, etc.) when
evaluating whether, or how, to express its policy? What differences
should the NRC consider?
Q2.5.4. What are the unique aspects of security at materials
licensees and certificate holders that the NRC should consider when
expressing its policy?
Q2.5.5. What topics should be addressed in the policy statement(s)
that would be of value to materials licensees and certificate holders?
Q2.5.6. How could the policy statement(s) effectively address
issues that involve both safety and security (at the safety/security
interface) at materials licensees and certificate holders?
Q2.5.7. How can the NRC best express a policy that gives
appropriate weight to safety culture and security culture across the
range of licensees and certificate holders?
Q2.5.8. Given the diversity among the licensees and certificate
holders regulated by the NRC and the Agreement States, how should the
policy statement address any differences in emphasis on safety and
security at the different types of licensees and certificate holders?
Q2.6. How should the NRC work with the Agreement States to
encourage increased attention being focused on safety culture,
including the unique aspects of security, at Agreement State licensees?
Q2.6.1. What is the level of understanding at Agreement State
licensees regarding the value in maintaining safety culture and
security culture?
Q2.6.2. What is the level of understanding of safety culture and
security culture within the Agreement States?
Q2.6.3. How do the Agreement States view the NRC's goal of
increasing the
[[Page 6436]]
attention paid to safety culture and security culture at materials
licensees and certificate holders?
Q2.6.4. What topics do the Agreement States believe should be
addressed in the policy statement(s)?
Q2.6.5. How could the NRC help the Agreement States to increase
attention to safety culture and security culture at their licensees?
Q2.6.6. How should the NRC address safety culture and security
culture at Agreement State licensees that engage in activities within
NRC jurisdiction under reciprocity?
Q2.6.7. How might NRC use stakeholder involvement to increase the
attention that materials licensees and certificate holders give to
maintaining a safety culture, including the unique aspects of security?
Topic 3: Does safety culture as applied to reactors need to be
strengthened?
A number of enhancements were made to the ROP in 2006 to address
safety culture (for example: safety culture cross-cutting aspect
assignment to findings; identifying substantive cross-cutting issues;
performing an independent NRC safety culture assessment for licensees
in Column 4 of the ROP Action Matrix).
Q3.1. What are the strengths and weaknesses of the current approach
for evaluating licensee safety culture in the ROP?
Q3.2. How has the use of safety culture cross-cutting aspects that
are assigned to inspection findings helped to identify potential safety
culture issues? Suggest any alternative approaches that licensees could
use to identify potential safety culture issues.
Q3.3. What may be better or more effective methods or tools that
the NRC could use to help identify precursors to future plant
performance deficiencies?
Q.3.4. In the following situations the NRC may/or will request a
licensee to perform a safety culture assessment (licensee self-
assessment, independent assessment, or a third-party assessment): (a)
The same substantive cross-cutting issue had been identified in three
consecutive assessment letters (generated from assessments conducted at
6 month intervals); (b) a 95002 inspection (Inspection for One Degraded
Cornerstone or Any Three White Inputs in a Strategic Performance Area)
that confirmed the licensee had not identified a safety culture
component that either caused or significantly contributed to the risk-
significant performance issue that resulted in the supplemental
inspection; and (c) a plant enters Column 4 of the Action Matrix.
Under what other situations should the NRC consider requesting that
a licensee perform a safety culture assessment?
Another ROP enhancement was for the NRC to perform an independent
safety culture assessment for plants that enter the multiple
repetitive/degraded cornerstone column (column 4).
Q3.5. In what other circumstances might the NRC consider performing
an independent safety culture assessment?
Q3.6. What other entity, other than the NRC, could perform an
independent safety culture assessment or simply verify the results of
the licensee's assessments and corrective actions?
Q3.7. What additional safety culture related ROP changes could help
the NRC to improve the focus of NRC and licensee attention on site
safety culture issues?
The NRC has held public meetings where draft changes to several ROP
guidance documents resulting from a lessons learned evaluation of the
initial implementation period of the ROP safety culture enhancements
have been made available for public comment.
Q3.8. What areas beyond the draft changes (for example, a provision
in Inspection Procedure 95003 for the NRC to be able to conduct a
graded safety culture assessment) presented by the NRC have the
potential to further enhance how the ROP addresses safety culture?
Q3.8.1. How would these potential changes enhance or improve how
the NRC addresses safety culture through the ROP?
Q3.9. In what ways does the current process lead to consistency/
predictability of implementation by the NRC? Provide examples to
support your view.
Q3.9.1. In what ways does it lead to inconsistency or
unpredictability?
Q3.10. How effective is the ROP in addressing security culture
issues?
Q3.10.1. What ROP changes could help the NRC to improve the focus
of NRC and licensee attention on site security culture issues?
In previous public meetings, the NRC has discussed using the ROP
safety culture components and modified aspects as a tool to understand
the challenges to safety culture during new reactor construction.
Q3.11. How can challenges to safety culture in new reactor
construction be identified and addressed in regulatory oversight?
Dated at Rockville, Maryland, this 27th day of January, 2009.
For the Nuclear Regulatory Commission.
Stewart L. Magruder,
Deputy Director, Office of Enforcement.
[FR Doc. E9-2621 Filed 2-6-09; 8:45 am]
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