Nuclear Management Company, LLC; Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing, 70889-70892 [E5-6451]
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Federal Register / Vol. 70, No. 225 / Wednesday, November 23, 2005 / Notices
For further details with respect to this
action, see the application for
amendment dated March 28, 2005, and
the licensee’s letter dated October 24,
2005, which withdrew the application
for license amendment. Documents may
be examined, and/or copied for a fee, at
the NRC’s Public Document Room
(PDR), located at One White Flint North,
Public File Area O1 F21, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible electronically from
the Agencywide Documents Access and
Management Systems (ADAMS) Public
Electronic Reading Room on the internet
at the NRC Web site, https://
www.nrc.gov/reading-rm/adams/html.
Persons who do not have access to
ADAMS or who encounter problems in
accessing the documents located in
ADAMS, should contact the NRC PDR
reference staff by telephone at 1–800–
397–4209, or 301–415–4737 or by e-mail
to pdr@nrc.gov.
Dated at Rockville, Maryland, this 9th day
of November, 2005.
For the Nuclear Regulatory Commission.
G. Edward Miller,
Project Manager, Plant Licensing Branch I–
2, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E5–6454 Filed 11–22–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–263]
Nuclear Management Company, LLC;
Notice of Consideration of Issuance of
Amendment to Facility Operating
License and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (NRC or the Commission)
is considering issuance of an
amendment to Facility Operating
License No. DPR–22 issued to the
Nuclear Management Company, LLC
(NMC or the licensee) for operation of
the Monticello Nuclear Generating Plant
(Monticello) located in Wright County,
Minnesota.
The proposed amendment, requested
by NMC in its application dated June
29, 2005, represents a full conversion
from the Current Technical
Specifications (CTS) to a set of
Improved Technical Specifications (ITS)
based on NUREG–1433, ‘‘Standard
Technical Specifications General
Electric Plants BWR/4,’’ Revision 3,
dated April 2001. NUREG–1433 has
been developed by the Commission’s
staff through working groups composed
of NRC staff and industry
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representatives, and has been endorsed
by the NRC staff as part of an industrywide initiative to standardize and
improve the Technical Specifications
(TSs) for nuclear power plants. As part
of this submittal, the licensee has
applied the criteria contained in the
Commission’s ‘‘Final Policy Statement
on Technical Specification
Improvements for Nuclear Power
Reactors (Final Policy Statement),’’
published in the Federal Register on
July 22,1993 (58 FR 39132), to the CTS
and using NUREG–1433 as a basis,
proposed ITS for Monticello. The
criteria in the Final Policy Statement
was subsequently added to Title 10 of
the Code of Federal Regulations (10
CFR), part 50.36, ‘‘Technical
Specifications,’’ in a rule change that
was published in the Federal Register
on July 19, 1995 (60 FR 36953) and
became effective on August 18, 1995.
This notice is based on the
application dated June 29, 2005, and
any information provided to the NRC
through the Monticello ITS Conversion
Web page. To expedite its application
review, the NRC staff will issue requests
for additional information (RAIs)
through the Monticello ITS Conversion
web page and the licensee will address
the RAIs by providing responses on the
Web page. Entry into the database is
protected so that only designated
licensee and NRC reviewers can enter
information; however, the public can
access the database to read the questions
asked and the responses provided. To be
in compliance with the regulations for
written communications for license
amendment requests and to have the
database on the Monticello docket
before the amendment would be issued,
the licensee will provide a copy of the
database in a submittal to the NRC after
there are no further RAIs and before the
amendment is to be issued.
The public can access the database
through the NRC Internet home page at
https://www.nrc.gov/reactors/operating/
licensing/techspecs.html. Click on the
link located near the bottom of the page
titled ‘‘Improved Technical
Specifications Data Base’’ to access the
Excel Services Corporation ITS
Licensing Databases. Click on
‘‘Monticello Nuclear Power Plant
Licensing Database’’ to view comments
and responses. The RAIs and responses
are organized by ITS sections 1.0, 2.0,
3.0, 3.1 through 3.9, 4.0, and 5.0, and
include beyond scope issues (BSIs)
which are discussed later in this notice.
For every ITS section or BSI, RAIs can
be read by clicking on the applicable
ITS Section. Licensee responses are
indicated by a solid blue triangle below
the ITS Number or, if accessing from the
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70889
ITS Section, at the bottom of the page.
To read a response, click on the triangle.
To page down through the ITS sections,
click on ‘‘Next’’ along the top or bottom
of the page. Click on ‘‘Previous’’ to
return to the previous page.
The licensee has categorized the
proposed changes to the CTS into five
general groupings within the
description of changes (DOC) section of
the application. These groupings are
characterized as administrative changes
(i.e., ITS x.x, DOC A.xx); more
restrictive changes (i.e., ITS x.x, DOC
M.xx); relocated specifications (i.e., ITS
x.x, DOC R.xx); removed detail changes
(i.e., ITS x.x, DOC LA.xx); and less
restrictive changes (i.e., ITS x.x, DOC
L.xx). The DOCs are numbered
sequentially within each letter
designator for each ITS Chapter,
Section, or Specification, and the
designations are A.xx for administrative
changes, M.xx for more restrictive
changes, R.xx for relocated
specifications, LA.xx for removed detail
changes, and L.xx for less restrictive
changes.
Administrative changes involve
restructuring, renumbering, rewording,
interpretation and complex rearranging
of requirements, and other changes not
affecting technical content or
substantially revising an operating
requirement. The reformatting,
renumbering and rewording process
reflects the attributes of NUREG–1433
and does not involve technical changes
to the CTS. The proposed changes
include: (a) Poviding the appropriate
numbers, etc., for NUREG–1433
bracketed information (information that
must be supplied on a plant-specific
basis, and which may change from plant
to plant), (b) identifying plant-specific
wording for system names, etc., and (c)
changing NUREG–1433 section wording
to conform to existing licensee
practices. Such changes are
administrative in nature and do not
impact initiators of analyzed events or
assumed mitigation of accident or
transient events.
More restrictive changes invoke more
stringent requirements compared to the
CTS for facility operation. These more
stringent requirements do not result in
operation that will alter assumptions
relative to the mitigation of an accident
or transient event. The more restrictive
requirements will not alter the operation
of process variables, structures, systems,
and components described in the safety
analyses. For each requirement in the
standard technical specification (STS)
that is more restrictive than the CTS
which the licensee proposes to adopt in
the ITS, the licensee has provided an
explanation as to why it concluded that
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Federal Register / Vol. 70, No. 225 / Wednesday, November 23, 2005 / Notices
adopting the more restrictive
requirement is desirable to ensure safe
operation of the facility because of
specific plant design features.
Relocated changes involve relocating
requirements and surveillances for
structures, systems, components, or
variables that do not meet the criteria
for inclusion in TSs. Relocated changes
are those CTS requirements that do not
satisfy or fall within any of the four
criteria specified in the 10 CFR 50.36(c)
and, therefore, may be relocated to
appropriate licensee-controlled
documents. The licensee’s application
of the screening criteria is described in
Enclosure 1 to the June 29, 2005,
application. The affected structures,
systems, components or variables are
not assumed to be initiators of analyzed
events and are not assumed to mitigate
accident or transient events. The
requirements and surveillances for these
affected structures, systems,
components, or variables will be
relocated from the TSs to
administratively-controlled documents
such as the quality assurance program,
the updated final safety analysis report
(UFSAR), the ITS Bases, the Technical
Requirements Manual that is
incorporated by reference in the
UFSAR, the core operating limits report,
the offsite dose calculation manual, the
inservice testing program, the inservice
inspection program, or other licenseecontrolled documents. Changes made to
these documents will be made pursuant
to 10 CFR 50.59 or other appropriate
control mechanisms, and may be made
without prior NRC review and approval.
In addition, the affected structures,
systems, components, or variables are
addressed in existing surveillance
procedures that are also subject to 10
CFR 50.59.
Removed detail changes to the CTSs
eliminate detail and relocate the detail
to a licensee-controlled document.
Typically, this involves details of
system design and function, or
procedural detail on methods of
conducting a surveillance requirement
(SR). These changes are supported, in
aggregate, by a single generic no
significant hazard consideration. The
generic type of removed detail change is
identified in italics at the beginning of
the DOC.
Less restrictive changes are those
where CTS requirements are relaxed or
eliminated, or new plant operational
flexibility is provided. The ‘‘more
significant’’ less restrictive requirements
are justified on a case-by-case basis.
When requirements have been shown to
provide little or no safety benefit, their
removal from the TSs may be
appropriate. Relaxations previously
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granted to individual plants on a plantspecific basis were, in most cases, the
result of (a) generic NRC actions, (b)
new NRC staff positions that evolved
from technological advancements and
operating experience, or (c) resolution of
the Owners Groups’ comments on the
Improved STSs. Generic relaxations
contained in NUREG–1433 were
reviewed by the NRC staff and found to
be acceptable because they are
consistent with current licensing
practices and NRC regulations. The
licensee’s design is being reviewed to
determine if the specific design-basis
and licensing basis are consistent with
the technical basis for the model
requirements in NUREG–1433, thus
providing a basis for the ITS, or if
relaxation of the requirements in the
CTS is warranted based on the
justification provided by the licensee.
These administrative, relocated, more
restrictive, and less restrictive changes
to the requirements of the CTS do not
result in operations that will alter
assumptions relative to mitigation of an
analyzed accident or transient event.
There are also changes proposed that
are different from the requirements in
both the CTSs and the STSs of NUREG–
1433. These are designated as BSIs and
are discussed below. The first 15 BSIs
were identified by the licensee and
described in Enclosure 2 of their
application. In some cases, a BSI may be
addressed as a justification for deviation
(JFD) from the STS, and identified as
ITS x.x, JFD x. The BSIs to the
conversion, listed in the order of the
applicable ITS specification or section,
are as follows:
1. CTS 3.1.A refers to the ‘‘Setpoints’’
of the Reactor Protection System (RPS)
Instrumentation Functions in CTS Table
3.1.1 and CTS Table 3.1.1, and specifies
the ‘‘Limiting Trip Settings’’ for the RPS
Instrumentation Functions. The
Limiting Trip Settings of CTS Table
3.1.1 Trip Functions 3.a, 4.a, and 4.c
have been modified to reflect new
‘‘Allowable Values’’ as indicated for ITS
Table 3.3.1.1–1 Functions 1.a and 2.a.
This changes the CTS by requiring RPS
Instrumentation to be set consistent
with the new Allowable Values. (ITS
3.3.1.1, DOC L.12)
2. CTS Table 4.1.1 requires a weekly
functional test of the Manual Scram
Function. ITS Table 3.3.1.1–1 Function
11 and ITS SR 3.3.1.1.5 require the
performance of the same test at a 31-day
frequency. This changes the CTS by
extending the Manual Scram functional
test frequency from 7 days to 31 days.
(ITS 3.3.1.1, DOC L.14)
3. CTS Table 3.2.5 specifies the ‘‘Trip
Setting’’ for the Anticipated Transient
Without Scram-Recirculation Pump
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Trip High Reactor Dome Pressure
Function. The Trip Setting of CTS Table
3.2.5 Function 1 has been modified to
reflect the new less restrictive
Allowable Value as indicated in ITS SR
3.3.4.1.5.b (ITS 3.3.4.1, DOC L.4)
4. CTS Table 3.2.2 specifies the ‘‘Trip
Setting’’ for Emergency Core Cooling
System (ECCS) Instrumentation
Functions. The Trip Setting of CTS 3.2.2
Function C.3 has been modified to
reflect new more restrictive Allowable
Values as indicated for ITS Table
3.3.5.1–1 Functions 4.c, 4.d, 5.c and 5.d.
(ITS 3.3.5.1, DOC M.8)
5. CTS Table 3.2.2 and Table 3.2.8
specify the ‘‘Trip Setting’’ for ECCS
Instrumentation Functions. The Trip
Settings of CTS Table 3.2.2 Functions
A.1.b.i and A.2, and Table 3.2.8
Function C.1 have been modified to
reflect new less restrictive Allowable
Values as indicated for ITS Table
3.3.5.1–1 Functions 1.c, 1.d, 2.c, 2.d,
and 3.d. In addition, the Allowable
Value for ITS Table 3.3.5.1–1 Function
3.d only specifies a single Allowable
value, which is applicable for both oneand two-tank operation. (ITS 3.3.5.1,
DOC L.5)
6. CTS Table 3.2.8 specifies the ‘‘Trip
Setting’’ for the Condensate Storage
Tank Level—Low for two tank and one
tank operation. The Trip Settings of CTS
Table 3.2.8 Function C.1 have been
modified to reflect a new less restrictive
Allowable Value as indicated for ITS
Table 3.3.5.2–1 Function 3. In addition,
the Allowable Value for this Function
only specifies a single Allowable Value,
which is applicable for both one- and
two-tank operation. (ITS 3.3.5.2, DOC
L.3)
7. CTS Table 3.2.1 specifies the ‘‘Trip
Settings’’ for the Primary Containment
Isolation Instrumentation. The Trip
Settings of CTS Table 3.2.1 Functions
3.d, 4.a, 4.b, 4.c, and 5.b have been
modified to reflect more restrictive
Allowable Values as indicated in ITS
Table 3.3.6.1–1 Function 3.a, 3.b, 3.c,
4.c, and 5.a. (ITS 3.3.6.1, DOC M.9)
8. CTS Table 3.2.1 specifies the ‘‘Trip
Settings’’ for the Primary Containment
Isolation Instrumentation. The Trip
Settings of CTS Table 3.2.1 Functions
1.b, 1.d, 5.a, 5.c, and 6.a have been
modified to reflect new less restrictive
Allowable Values as indicated in ITS
Table 3.3.6.1–1 Functions 1.b, 1.c, 4.a,
4.b, and 6.a. (ITS 3.3.6.1, DOC L.9)
9. CTS Table 3.2.6 specifies the ‘‘Trip
Settings’’ for the Loss of Power
Instrumentation. The Trip Setting of
CTS Table 3.2.6 Function 1 has been
modified to reflect new more restrictive
Allowable Values as indicated for ITS
Table 3.3.8.1–1 Functions 2.a and 2.b.
(ITS 3.3.8.1, DOC M.3)
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10. CTS 3.2.C.2.b states that the Rod
Block Monitor (RBM) bypass time delay
must be less than or equal to 2.0
seconds. ITS 3.3.2.1 does not require the
RBM bypass time delay to be
OPERABLE. This changes the CTS by
deleting the RBM bypass time delay
requirements. (ITS 3.3.2.1, DOC L.5)
11. CTS 4.14 does not provide a
delayed entry into associated
Conditions and Required Actions if a
Post-Accident Monitoring (PAM)
channel is inoperable solely for
performance of required surveillances.
ITS SR Note 2 has been added to allow
delayed entry into associated
Conditions and Required Actions for up
to 6 hours if a PAM channel is placed
in an inoperable status solely for
performance of required surveillances,
provided the associated function
remains capable. This changes the CTS
by providing a delay time to enter
Conditions and Required Actions for a
PAM channel placed in an inoperable
status solely for performance of required
surveillances. (ITS 3.3.3.1, DOC L.2)
12. CTS 4.1.C.2 requires an
instrument calibration of each RPS
power monitoring channel every
‘‘Operating Cycle.’’ ITS SR 3.3.8.2.2
requires the performance of a
CHANNEL CALIBRATION of the
overvoltage, undervoltage, and
underfrequency setpoints every 184
days. This changes the CTS by
increasing the frequency of performing
a CHANNEL CALIBRATION of the
overvoltage, undervoltage, and
underfrequency setpoints. (ITS 3.3.8.2,
DOC M.3)
13. CTS 4.5.F.1 provides a crossreference to the SRs in CTS 4.6.G.
However, these are jet pump
surveillances and reflect stability
monitoring issues. ITS SR 3.4.1.2
requires verification of operation in the
Normal Region of the power-to-flow
map every 24 hours or in the Stability
Buffer Region of the power-to-flow map,
with power distribution controls as
specified in the Core Operating Limits
Report, every 24 hours. This changes the
CTS by deleting the cross references to
the SRs in CTS 4.6.G and adds a new
SR. (ITS 3.4.1, DOC M.1)
14. CTS 6.8.B includes the Primary
Coolant Sources Outside Containment
program requirements. The Combustible
Gas Control System (CGCS) is included
in this program. ITS 5.5.2 includes the
same program requirements for the
Primary Coolant Sources Outside
Containment program, except the CGCS
will not be included. This changes the
CTS by deleting the program
requirement for the CGCS in the
Primary Coolant Sources Outside
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17:33 Nov 22, 2005
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Containment program. (ITS 5.5, DOC
L.4)
15. CTS 6.8.B.2 specifies that the
integrated leak test requirements for
each system outside containment that
could contain highly radioactive fluids
during a serious transient or accident
must be performed at a refueling cycle
or less. CTS 6.8.B also states that CTS
4.0.B (i.e. a 25 percent allowable grace
period) is applicable. ITS 5.5.2.b
specifies that the same test must be
performed at least once per 24 months
and that the provisions of ITS SR 3.0.2
(25 percent allowable grace period) are
applicable. This changes the CTS by
extending the frequency of the
surveillance from 18 months to 24
months, with a maximum of 30 months
accounting for the allowable grace
period. (ITS 5.5, DOC L.5)
Before issuance of the proposed
license amendment, the Commission
will have made findings required by the
Atomic Energy Act of 1954, as amended
(the Act) and the commission’s
regulations.
Within 60 days after the date of
publication of this notice, the licensee
may file a request for a hearing with
respect to issuance of the amendment to
the subject facility operating license and
any person whose interest may be
affected by this proceeding and who
wishes to participate as a party in the
proceeding must file a written request
for a hearing and a petition for leave to
intervene. Requests for a hearing and a
petition for leave to intervene shall be
filed in accordance with the
Commission’s ‘‘Rules of Practice for
Domestic Licensing Proceedings’’ in 10
CFR part 2. Interested persons should
consult a current copy of 10 CFR 2.309,
which is available at the Commission’s
Public Document Room (PDR), located
at One White Flint North, Public File
Area 01F21, 11555 Rockville Pike (first
floor), Rockville, Maryland. Publicly
available records will be accessible from
the Agencywide Documents Access and
Management System’s (ADAMS) Public
Electronic Reading Room on the Internet
at the NRC Web site, https://
www.nrc.gov/reading-rm/doccollections/cfr/. If a request for a hearing
or petition for leave to intervene is filed
by the above date, the Commission or a
presiding officer designated by the
Commission or by the Chief
Administrative Judge of the Atomic
Safety and Licensing Board Panel, will
rule on the request and/or petition; and
the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
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70891
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner/requestor in the
proceeding, and how that interest may
be affected by the results of the
proceeding. The petition should
specifically explain the reasons why
intervention should be permitted with
particular reference to the following
general requirements: (1) The name,
address and telephone number of the
requestor or petitioner; (2) the nature of
the requestor’s/petitioner’s right under
the Act to be made a party to the
proceeding; (3) the nature and extent of
the requestor’s/petitioner’s property,
financial, or other interest in the
proceeding; and (4) the possible effect of
any decision or order which may be
entered in the proceeding on the
requestor’s/petitioner’s interest. The
petition must also identify the specific
contentions which the petitioner/
requestor seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the petitioner/requestor shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the petitioner intends to
rely in proving the contention at the
hearing. The petitioner must also
provide references to those specific
sources and documents of which the
petitioner is aware and on which the
petitioner intends to rely to establish
those facts or expert opinion. The
petition must include sufficient
information to show that a genuine
dispute exists with the applicant on a
material issue of law or fact.
Contentions shall be limited to matters
within the scope of the amendment
under consideration. The contention
must be one which, if proven, would
entitle the petitioner/requestor to relief.
A petitioner/requestor who fails to
satisfy these requirements with respect
to at least one contention will not be
permitted to participate as a party.
Those permitted to intervene become
parties to the proceeding, subject to any
limitations in the order granting leave to
intervene, and have the opportunity to
participate fully in the conduct of the
hearing.
Non-timely requests and/or petitions
and contentions will not be entertained
absent a determination by the
Commission or the presiding officer of
the Atomic Safety and Licensing Board
that the petition, request and/or the
contentions should be granted based on
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Federal Register / Vol. 70, No. 225 / Wednesday, November 23, 2005 / Notices
a balancing of the factors specified in 10
CFR 2.309(a)(1)(i)–(viii).
A request for a hearing or a petition
for leave to intervene must be filed by:
(1) First class mail addressed to the
Office of the Secretary of the
Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
Adjudications Staff; (2) courier, express
mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland, 20852,
Attention: Rulemaking and
Adjudications Staff; (3) E-mail
addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission,
HEARINGDOCKET@NRC.GOV; or (4)
facsimile transmission addressed to the
Office of the Secretary, U.S. Nuclear
Regulatory Commission, Washington,
DC, Attention: Rulemakings and
Adjudications Staff at (301) 415–1101,
verification number is (301) 415–1966.
A copy of the request for hearing and
petition for leave to intervene should
also be sent to the Office of the General
Counsel, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, and it is requested that copies be
transmitted either by means of facsimile
transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. A copy
of the request for hearing and petition
for leave to intervene should also be
sent Jonathan Rogoff, Esq., 700 First
Street, Hudson, WI 54016, attorney for
the licensee.
For further details with respect to this
action, see the licensee’s application for
amendment dated June 29, 2005, and
the Monticello ITS Conversion Web
page (as discussed above). Documents
may be examined, and/or copied for a
fee at the Commission’s PDR, located at
One White Flint North, Public File Area
O1 F21, 11555 Rockville Pike (first
floor), Rockville, Maryland. Publicly
available records will be accessible
electronically from the Agencywide
Documents Access and Management
System’s (ADAMS) Public Electronic
Reading Room on the Internet at the
NRC Web site, https://www.nrc.gov/
reading-rm/adams.html. Persons who
do not have access to ADAMS or who
encounter problems in accessing the
documents located in ADAMS, should
contact the NRC PDR Reference staff by
telephone at 1–800–397–4209, 301–
415–4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 16th day
of November, 2005.
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17:33 Nov 22, 2005
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For the Nuclear Regulatory Commission.
John F. Stang,
Sr. Project Manager, Plant Licensing Branch
III–1, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E5–6451 Filed 11–22–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[EA–01–082 and EA–04–172]
In the Matter of: Williams Industrial
Services Group, LLC, 2076 West Park
Place, Stone Mountain, GA 30087;
Confirmatory Order (Effective
Immediately)
Williams Industrial Services Group,
LLC, (Williams) and its subsidiaries
(collectively known as Williams Group)
perform services for multiple reactor
facilities regulated by the U.S. Nuclear
Regulatory Commission (NRC or
Commission). Williams assumed the
contractual obligations of Williams
Service Group, LLC, formerly known as
Williams Power Corporation (WPC),
relating to services performed for NRC
licensees. Williams’ headquarters are
located in Stone Mountain, Georgia.
On May 22, 2000, the NRC’s Office of
Investigations (OI) began an
investigation into alleged employment
discrimination, during March 2000, by
WPC at FirstEnergy Nuclear Operating
Company’s (FENOC) Perry and DavisBesse Nuclear Power Plants. A
predecisional enforcement conference
(PEC) was held with FENOC and WPC
at the NRC Region III office on
September 26, 2001. Subsequent to the
PEC, a supplemental investigation was
conducted by OI Report No. 3–2000–
025S and an apparent violation
concerning the completeness and
accuracy of information was identified
during that investigation.
On February 24, 2005, the NRC staff
issued Notices of Violation (Notices) to
FENOC and to WPC. The NRC also
issued an order on February 25, 2005, to
the supervisor prohibiting involvement
in NRC-licensed activities for three
years for deliberately providing
materially inaccurate information to the
NRC in violation of 10 CFR 50.5(a)(2).
The Notice to WPC described violations
of 10 CFR 50.7, ‘‘Employee protection,’’
for discrimination and of 10 CFR
50.5(a)(2), ‘‘Deliberate misconduct,’’ for
deliberate inaccurate statements to the
NRC. The NRC also informed WPC that
FENOC had been offered an opportunity
to pursue resolution of the 10 CFR 50.7
violation with alternative dispute
resolution (ADR). In ADR, a neutral
mediator with no decision-making
PO 00000
Frm 00111
Fmt 4703
Sfmt 4703
authority facilitates discussions between
concerned parties to assist them in
reaching an agreement on resolving
concerns. If FENOC had elected to enter
into ADR, the NRC would have offered
WPC an opportunity to participate.
FENOC did not elect to enter into ADR,
and on March 28, 2005, FENOC
admitted to the 10 CFR 50.7 violation.
In a letter dated March 25, 2005,
Williams Service Group, LLC (WSG)
disputed the violations cited against
WPC. On April 15, 2005, WSG
requested an opportunity to enter into
ADR with the NRC in order to resolve
the violations cited in the Notice. The
NRC granted the request, and on July 26,
2005, the NRC and WSG met at NRC
Headquarters in Rockville, Maryland, at
which time a settlement was reached.
Based upon the corrective actions
taken as documented in the WSG letter
dated March 25, 2005, and the
commitments noted in Section IV
below, the NRC hereby withdraws the
10 CFR 50.5(a)(2) violation cited against
WPC on February 24, 2005. In addition,
the 10 CFR 50.7 violation, originally
issued as severity level III, is hereby recharacterized as a violation without
severity level specified.
By letter dated March 25, 2005, and
as further discussed during the July 26,
2005, ADR meeting, Williams stated that
it already had taken steps to enhance
awareness of and compliance with its
safety conscious work environment
(SCWE) program at NRC-license
facilities. These completed actions
include: (1) Enacting a new SCWE
policy approved by the Williams Board
of Directors in August 2002, (2) ensuring
that new employees receive site-specific
information on Williams’ SCWE policy
as well as ways to raise safety concerns
to Williams supervision, licensees and
the NRC, and (3) conducting moredetailed SCWE training sessions to
employees facilitated by Williams’
senior management. Furthermore, by
letter dated September 2, 2005,
Williams stated that, in addition to the
actions already taken to enhance
awareness of and compliance with its
SCWE program, Williams agrees to take
certain additional corrective measures
as noted in Section IV of this
Confirmatory Order.
On October 25, 2005, Williams
consented to the NRC issuing this
Confirmatory Order with the
commitments, as described in Section
IV below. Williams further agreed in its
October 28, 2005, letter that this Order
is to be effective upon issuance and that
it has waived its right to a hearing. The
NRC has concluded that its concerns
can be resolved through NRC’s
E:\FR\FM\23NON1.SGM
23NON1
]]>Agencies
[Federal Register Volume 70, Number 225 (Wednesday, November 23, 2005)]
[Notices]
[Pages 70889-70892]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-6451]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-263]
Nuclear Management Company, LLC; Notice of Consideration of
Issuance of Amendment to Facility Operating License and Opportunity for
a Hearing
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is
considering issuance of an amendment to Facility Operating License No.
DPR-22 issued to the Nuclear Management Company, LLC (NMC or the
licensee) for operation of the Monticello Nuclear Generating Plant
(Monticello) located in Wright County, Minnesota.
The proposed amendment, requested by NMC in its application dated
June 29, 2005, represents a full conversion from the Current Technical
Specifications (CTS) to a set of Improved Technical Specifications
(ITS) based on NUREG-1433, ``Standard Technical Specifications General
Electric Plants BWR/4,'' Revision 3, dated April 2001. NUREG-1433 has
been developed by the Commission's staff through working groups
composed of NRC staff and industry representatives, and has been
endorsed by the NRC staff as part of an industry-wide initiative to
standardize and improve the Technical Specifications (TSs) for nuclear
power plants. As part of this submittal, the licensee has applied the
criteria contained in the Commission's ``Final Policy Statement on
Technical Specification Improvements for Nuclear Power Reactors (Final
Policy Statement),'' published in the Federal Register on July 22,1993
(58 FR 39132), to the CTS and using NUREG-1433 as a basis, proposed ITS
for Monticello. The criteria in the Final Policy Statement was
subsequently added to Title 10 of the Code of Federal Regulations (10
CFR), part 50.36, ``Technical Specifications,'' in a rule change that
was published in the Federal Register on July 19, 1995 (60 FR 36953)
and became effective on August 18, 1995.
This notice is based on the application dated June 29, 2005, and
any information provided to the NRC through the Monticello ITS
Conversion Web page. To expedite its application review, the NRC staff
will issue requests for additional information (RAIs) through the
Monticello ITS Conversion web page and the licensee will address the
RAIs by providing responses on the Web page. Entry into the database is
protected so that only designated licensee and NRC reviewers can enter
information; however, the public can access the database to read the
questions asked and the responses provided. To be in compliance with
the regulations for written communications for license amendment
requests and to have the database on the Monticello docket before the
amendment would be issued, the licensee will provide a copy of the
database in a submittal to the NRC after there are no further RAIs and
before the amendment is to be issued.
The public can access the database through the NRC Internet home
page at https://www.nrc.gov/reactors/operating/licensing/techspecs.html.
Click on the link located near the bottom of the page titled ``Improved
Technical Specifications Data Base'' to access the Excel Services
Corporation ITS Licensing Databases. Click on ``Monticello Nuclear
Power Plant Licensing Database'' to view comments and responses. The
RAIs and responses are organized by ITS sections 1.0, 2.0, 3.0, 3.1
through 3.9, 4.0, and 5.0, and include beyond scope issues (BSIs) which
are discussed later in this notice. For every ITS section or BSI, RAIs
can be read by clicking on the applicable ITS Section. Licensee
responses are indicated by a solid blue triangle below the ITS Number
or, if accessing from the ITS Section, at the bottom of the page. To
read a response, click on the triangle. To page down through the ITS
sections, click on ``Next'' along the top or bottom of the page. Click
on ``Previous'' to return to the previous page.
The licensee has categorized the proposed changes to the CTS into
five general groupings within the description of changes (DOC) section
of the application. These groupings are characterized as administrative
changes (i.e., ITS x.x, DOC A.xx); more restrictive changes (i.e., ITS
x.x, DOC M.xx); relocated specifications (i.e., ITS x.x, DOC R.xx);
removed detail changes (i.e., ITS x.x, DOC LA.xx); and less restrictive
changes (i.e., ITS x.x, DOC L.xx). The DOCs are numbered sequentially
within each letter designator for each ITS Chapter, Section, or
Specification, and the designations are A.xx for administrative
changes, M.xx for more restrictive changes, R.xx for relocated
specifications, LA.xx for removed detail changes, and L.xx for less
restrictive changes.
Administrative changes involve restructuring, renumbering,
rewording, interpretation and complex rearranging of requirements, and
other changes not affecting technical content or substantially revising
an operating requirement. The reformatting, renumbering and rewording
process reflects the attributes of NUREG-1433 and does not involve
technical changes to the CTS. The proposed changes include: (a)
Poviding the appropriate numbers, etc., for NUREG-1433 bracketed
information (information that must be supplied on a plant-specific
basis, and which may change from plant to plant), (b) identifying
plant-specific wording for system names, etc., and (c) changing NUREG-
1433 section wording to conform to existing licensee practices. Such
changes are administrative in nature and do not impact initiators of
analyzed events or assumed mitigation of accident or transient events.
More restrictive changes invoke more stringent requirements
compared to the CTS for facility operation. These more stringent
requirements do not result in operation that will alter assumptions
relative to the mitigation of an accident or transient event. The more
restrictive requirements will not alter the operation of process
variables, structures, systems, and components described in the safety
analyses. For each requirement in the standard technical specification
(STS) that is more restrictive than the CTS which the licensee proposes
to adopt in the ITS, the licensee has provided an explanation as to why
it concluded that
[[Page 70890]]
adopting the more restrictive requirement is desirable to ensure safe
operation of the facility because of specific plant design features.
Relocated changes involve relocating requirements and surveillances
for structures, systems, components, or variables that do not meet the
criteria for inclusion in TSs. Relocated changes are those CTS
requirements that do not satisfy or fall within any of the four
criteria specified in the 10 CFR 50.36(c) and, therefore, may be
relocated to appropriate licensee-controlled documents. The licensee's
application of the screening criteria is described in Enclosure 1 to
the June 29, 2005, application. The affected structures, systems,
components or variables are not assumed to be initiators of analyzed
events and are not assumed to mitigate accident or transient events.
The requirements and surveillances for these affected structures,
systems, components, or variables will be relocated from the TSs to
administratively-controlled documents such as the quality assurance
program, the updated final safety analysis report (UFSAR), the ITS
Bases, the Technical Requirements Manual that is incorporated by
reference in the UFSAR, the core operating limits report, the offsite
dose calculation manual, the inservice testing program, the inservice
inspection program, or other licensee-controlled documents. Changes
made to these documents will be made pursuant to 10 CFR 50.59 or other
appropriate control mechanisms, and may be made without prior NRC
review and approval. In addition, the affected structures, systems,
components, or variables are addressed in existing surveillance
procedures that are also subject to 10 CFR 50.59.
Removed detail changes to the CTSs eliminate detail and relocate
the detail to a licensee-controlled document. Typically, this involves
details of system design and function, or procedural detail on methods
of conducting a surveillance requirement (SR). These changes are
supported, in aggregate, by a single generic no significant hazard
consideration. The generic type of removed detail change is identified
in italics at the beginning of the DOC.
Less restrictive changes are those where CTS requirements are
relaxed or eliminated, or new plant operational flexibility is
provided. The ``more significant'' less restrictive requirements are
justified on a case-by-case basis. When requirements have been shown to
provide little or no safety benefit, their removal from the TSs may be
appropriate. Relaxations previously granted to individual plants on a
plant-specific basis were, in most cases, the result of (a) generic NRC
actions, (b) new NRC staff positions that evolved from technological
advancements and operating experience, or (c) resolution of the Owners
Groups' comments on the Improved STSs. Generic relaxations contained in
NUREG-1433 were reviewed by the NRC staff and found to be acceptable
because they are consistent with current licensing practices and NRC
regulations. The licensee's design is being reviewed to determine if
the specific design-basis and licensing basis are consistent with the
technical basis for the model requirements in NUREG-1433, thus
providing a basis for the ITS, or if relaxation of the requirements in
the CTS is warranted based on the justification provided by the
licensee.
These administrative, relocated, more restrictive, and less
restrictive changes to the requirements of the CTS do not result in
operations that will alter assumptions relative to mitigation of an
analyzed accident or transient event.
There are also changes proposed that are different from the
requirements in both the CTSs and the STSs of NUREG-1433. These are
designated as BSIs and are discussed below. The first 15 BSIs were
identified by the licensee and described in Enclosure 2 of their
application. In some cases, a BSI may be addressed as a justification
for deviation (JFD) from the STS, and identified as ITS x.x, JFD x. The
BSIs to the conversion, listed in the order of the applicable ITS
specification or section, are as follows:
1. CTS 3.1.A refers to the ``Setpoints'' of the Reactor Protection
System (RPS) Instrumentation Functions in CTS Table 3.1.1 and CTS Table
3.1.1, and specifies the ``Limiting Trip Settings'' for the RPS
Instrumentation Functions. The Limiting Trip Settings of CTS Table
3.1.1 Trip Functions 3.a, 4.a, and 4.c have been modified to reflect
new ``Allowable Values'' as indicated for ITS Table 3.3.1.1-1 Functions
1.a and 2.a. This changes the CTS by requiring RPS Instrumentation to
be set consistent with the new Allowable Values. (ITS 3.3.1.1, DOC
L.12)
2. CTS Table 4.1.1 requires a weekly functional test of the Manual
Scram Function. ITS Table 3.3.1.1-1 Function 11 and ITS SR 3.3.1.1.5
require the performance of the same test at a 31-day frequency. This
changes the CTS by extending the Manual Scram functional test frequency
from 7 days to 31 days. (ITS 3.3.1.1, DOC L.14)
3. CTS Table 3.2.5 specifies the ``Trip Setting'' for the
Anticipated Transient Without Scram-Recirculation Pump Trip High
Reactor Dome Pressure Function. The Trip Setting of CTS Table 3.2.5
Function 1 has been modified to reflect the new less restrictive
Allowable Value as indicated in ITS SR 3.3.4.1.5.b (ITS 3.3.4.1, DOC
L.4)
4. CTS Table 3.2.2 specifies the ``Trip Setting'' for Emergency
Core Cooling System (ECCS) Instrumentation Functions. The Trip Setting
of CTS 3.2.2 Function C.3 has been modified to reflect new more
restrictive Allowable Values as indicated for ITS Table 3.3.5.1-1
Functions 4.c, 4.d, 5.c and 5.d. (ITS 3.3.5.1, DOC M.8)
5. CTS Table 3.2.2 and Table 3.2.8 specify the ``Trip Setting'' for
ECCS Instrumentation Functions. The Trip Settings of CTS Table 3.2.2
Functions A.1.b.i and A.2, and Table 3.2.8 Function C.1 have been
modified to reflect new less restrictive Allowable Values as indicated
for ITS Table 3.3.5.1-1 Functions 1.c, 1.d, 2.c, 2.d, and 3.d. In
addition, the Allowable Value for ITS Table 3.3.5.1-1 Function 3.d only
specifies a single Allowable value, which is applicable for both one-
and two-tank operation. (ITS 3.3.5.1, DOC L.5)
6. CTS Table 3.2.8 specifies the ``Trip Setting'' for the
Condensate Storage Tank Level--Low for two tank and one tank operation.
The Trip Settings of CTS Table 3.2.8 Function C.1 have been modified to
reflect a new less restrictive Allowable Value as indicated for ITS
Table 3.3.5.2-1 Function 3. In addition, the Allowable Value for this
Function only specifies a single Allowable Value, which is applicable
for both one- and two-tank operation. (ITS 3.3.5.2, DOC L.3)
7. CTS Table 3.2.1 specifies the ``Trip Settings'' for the Primary
Containment Isolation Instrumentation. The Trip Settings of CTS Table
3.2.1 Functions 3.d, 4.a, 4.b, 4.c, and 5.b have been modified to
reflect more restrictive Allowable Values as indicated in ITS Table
3.3.6.1-1 Function 3.a, 3.b, 3.c, 4.c, and 5.a. (ITS 3.3.6.1, DOC M.9)
8. CTS Table 3.2.1 specifies the ``Trip Settings'' for the Primary
Containment Isolation Instrumentation. The Trip Settings of CTS Table
3.2.1 Functions 1.b, 1.d, 5.a, 5.c, and 6.a have been modified to
reflect new less restrictive Allowable Values as indicated in ITS Table
3.3.6.1-1 Functions 1.b, 1.c, 4.a, 4.b, and 6.a. (ITS 3.3.6.1, DOC L.9)
9. CTS Table 3.2.6 specifies the ``Trip Settings'' for the Loss of
Power Instrumentation. The Trip Setting of CTS Table 3.2.6 Function 1
has been modified to reflect new more restrictive Allowable Values as
indicated for ITS Table 3.3.8.1-1 Functions 2.a and 2.b. (ITS 3.3.8.1,
DOC M.3)
[[Page 70891]]
10. CTS 3.2.C.2.b states that the Rod Block Monitor (RBM) bypass
time delay must be less than or equal to 2.0 seconds. ITS 3.3.2.1 does
not require the RBM bypass time delay to be OPERABLE. This changes the
CTS by deleting the RBM bypass time delay requirements. (ITS 3.3.2.1,
DOC L.5)
11. CTS 4.14 does not provide a delayed entry into associated
Conditions and Required Actions if a Post-Accident Monitoring (PAM)
channel is inoperable solely for performance of required surveillances.
ITS SR Note 2 has been added to allow delayed entry into associated
Conditions and Required Actions for up to 6 hours if a PAM channel is
placed in an inoperable status solely for performance of required
surveillances, provided the associated function remains capable. This
changes the CTS by providing a delay time to enter Conditions and
Required Actions for a PAM channel placed in an inoperable status
solely for performance of required surveillances. (ITS 3.3.3.1, DOC
L.2)
12. CTS 4.1.C.2 requires an instrument calibration of each RPS
power monitoring channel every ``Operating Cycle.'' ITS SR 3.3.8.2.2
requires the performance of a CHANNEL CALIBRATION of the overvoltage,
undervoltage, and underfrequency setpoints every 184 days. This changes
the CTS by increasing the frequency of performing a CHANNEL CALIBRATION
of the overvoltage, undervoltage, and underfrequency setpoints. (ITS
3.3.8.2, DOC M.3)
13. CTS 4.5.F.1 provides a cross-reference to the SRs in CTS 4.6.G.
However, these are jet pump surveillances and reflect stability
monitoring issues. ITS SR 3.4.1.2 requires verification of operation in
the Normal Region of the power-to-flow map every 24 hours or in the
Stability Buffer Region of the power-to-flow map, with power
distribution controls as specified in the Core Operating Limits Report,
every 24 hours. This changes the CTS by deleting the cross references
to the SRs in CTS 4.6.G and adds a new SR. (ITS 3.4.1, DOC M.1)
14. CTS 6.8.B includes the Primary Coolant Sources Outside
Containment program requirements. The Combustible Gas Control System
(CGCS) is included in this program. ITS 5.5.2 includes the same program
requirements for the Primary Coolant Sources Outside Containment
program, except the CGCS will not be included. This changes the CTS by
deleting the program requirement for the CGCS in the Primary Coolant
Sources Outside Containment program. (ITS 5.5, DOC L.4)
15. CTS 6.8.B.2 specifies that the integrated leak test
requirements for each system outside containment that could contain
highly radioactive fluids during a serious transient or accident must
be performed at a refueling cycle or less. CTS 6.8.B also states that
CTS 4.0.B (i.e. a 25 percent allowable grace period) is applicable. ITS
5.5.2.b specifies that the same test must be performed at least once
per 24 months and that the provisions of ITS SR 3.0.2 (25 percent
allowable grace period) are applicable. This changes the CTS by
extending the frequency of the surveillance from 18 months to 24
months, with a maximum of 30 months accounting for the allowable grace
period. (ITS 5.5, DOC L.5)
Before issuance of the proposed license amendment, the Commission
will have made findings required by the Atomic Energy Act of 1954, as
amended (the Act) and the commission's regulations.
Within 60 days after the date of publication of this notice, the
licensee may file a request for a hearing with respect to issuance of
the amendment to the subject facility operating license and any person
whose interest may be affected by this proceeding and who wishes to
participate as a party in the proceeding must file a written request
for a hearing and a petition for leave to intervene. Requests for a
hearing and a petition for leave to intervene shall be filed in
accordance with the Commission's ``Rules of Practice for Domestic
Licensing Proceedings'' in 10 CFR part 2. Interested persons should
consult a current copy of 10 CFR 2.309, which is available at the
Commission's Public Document Room (PDR), located at One White Flint
North, Public File Area 01F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible from
the Agencywide Documents Access and Management System's (ADAMS) Public
Electronic Reading Room on the Internet at the NRC Web site, https://
www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing
or petition for leave to intervene is filed by the above date, the
Commission or a presiding officer designated by the Commission or by
the Chief Administrative Judge of the Atomic Safety and Licensing Board
Panel, will rule on the request and/or petition; and the Secretary or
the Chief Administrative Judge of the Atomic Safety and Licensing Board
will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner/
requestor in the proceeding, and how that interest may be affected by
the results of the proceeding. The petition should specifically explain
the reasons why intervention should be permitted with particular
reference to the following general requirements: (1) The name, address
and telephone number of the requestor or petitioner; (2) the nature of
the requestor's/petitioner's right under the Act to be made a party to
the proceeding; (3) the nature and extent of the requestor's/
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the requestor's/petitioner's interest. The
petition must also identify the specific contentions which the
petitioner/requestor seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
petitioner/requestor shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to those specific sources and
documents of which the petitioner is aware and on which the petitioner
intends to rely to establish those facts or expert opinion. The
petition must include sufficient information to show that a genuine
dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the
amendment under consideration. The contention must be one which, if
proven, would entitle the petitioner/requestor to relief. A petitioner/
requestor who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
Non-timely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission or the presiding
officer of the Atomic Safety and Licensing Board that the petition,
request and/or the contentions should be granted based on
[[Page 70892]]
a balancing of the factors specified in 10 CFR 2.309(a)(1)(i)-(viii).
A request for a hearing or a petition for leave to intervene must
be filed by: (1) First class mail addressed to the Office of the
Secretary of the Commission, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attention: Rulemaking and Adjudications
Staff; (2) courier, express mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor, One White Flint North, 11555
Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and
Adjudications Staff; (3) E-mail addressed to the Office of the
Secretary, U.S. Nuclear Regulatory Commission, HEARINGDOCKET@NRC.GOV;
or (4) facsimile transmission addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission, Washington, DC, Attention:
Rulemakings and Adjudications Staff at (301) 415-1101, verification
number is (301) 415-1966. A copy of the request for hearing and
petition for leave to intervene should also be sent to the Office of
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, and it is requested that copies be transmitted either by
means of facsimile transmission to 301-415-3725 or by e-mail to
OGCMailCenter@nrc.gov. A copy of the request for hearing and petition
for leave to intervene should also be sent Jonathan Rogoff, Esq., 700
First Street, Hudson, WI 54016, attorney for the licensee.
For further details with respect to this action, see the licensee's
application for amendment dated June 29, 2005, and the Monticello ITS
Conversion Web page (as discussed above). Documents may be examined,
and/or copied for a fee at the Commission's PDR, located at One White
Flint North, Public File Area O1 F21, 11555 Rockville Pike (first
floor), Rockville, Maryland. Publicly available records will be
accessible electronically from the Agencywide Documents Access and
Management System's (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site, https://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who encounter problems in
accessing the documents located in ADAMS, should contact the NRC PDR
Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-
mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 16th day of November, 2005.
For the Nuclear Regulatory Commission.
John F. Stang,
Sr. Project Manager, Plant Licensing Branch III-1, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E5-6451 Filed 11-22-05; 8:45 am]
BILLING CODE 7590-01-P
