[Federal Register Volume 73, Number 68 (Tuesday, April 8, 2008)]
[Notices]
[Pages 19106-19117]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E8-6904]
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NUCLEAR REGULATORY COMMISSION
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses Involving No Significant Hazards Considerations
I. Background
Pursuant to section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (the
Commission or NRC staff) is publishing this regular biweekly notice.
The Act requires the Commission publish notice of any amendments
issued, or proposed to be issued and grants the Commission the
authority to issue and make immediately effective any amendment to an
operating license upon a determination by the Commission that such
amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued from March 13, 2008 to March 26, 2008. The last
biweekly notice was published on March 25, 2008 (73 FR 15780).
Notice of Consideration of Issuance of Amendments to Facility Operating
Licenses, Proposed No Significant Hazards Consideration Determination,
and Opportunity for a Hearing
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in 10 CFR 50.92, this means that operation
of the facility in accordance with the proposed amendment would not (1)
Involve a significant increase in the probability or consequences of an
accident previously evaluated; or (2) create the possibility of a new
or different kind of accident from any accident previously evaluated;
or (3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking,
Directives and Editing Branch, Division of Administrative Services,
Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, and should cite the publication date and
page number of this Federal Register notice. Written comments may also
be delivered to Room 6D22, Two White Flint North, 11545 Rockville Pike,
Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays.
Copies of written comments received may be examined 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. The filing of requests for a hearing and petitions for leave
to intervene is discussed below.
Within 60 days after the date of publication of this notice,
person(s) may file a request for a hearing with respect
[[Page 19107]]
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 via electronic submission through the NRC E-Filing
system 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 person(s) should
consult a current copy of 10 CFR 2.309, which is available at the
Commission's 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, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition
for leave to intervene is filed within 60 days, 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 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 set forth 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/
requestor intends to rely in proving the contention at the hearing. The
petitioner/requestor must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
petitioner/requestor 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.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to decide when the hearing is held. If the final determination is that
the amendment request involves no significant hazards consideration,
the Commission may issue the amendment and make it immediately
effective, notwithstanding the request for a hearing. Any hearing held
would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, any hearing held would take place before the
issuance of any amendment.
A request for hearing or a petition for leave to intervene must be
filed in accordance with the NRC E-Filing rule, which the NRC
promulgated in August 28, 2007 (72 FR 49139). The E-Filing process
requires participants to submit and serve documents over the internet
or in some cases to mail copies on electronic storage media.
Participants may not submit paper copies of their filings unless they
seek a waiver in accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least
five (5) days prior to the filing deadline, the petitioner/requestor
must contact the Office of the Secretary by e-mail at
[email protected], or by calling (301) 415-1677, to request (1) a
digital ID certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and/or (2)
creation of an electronic docket for the proceeding (even in instances
in which the petitioner/requestor (or its counsel or representative)
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms ViewerTM
to access the Electronic Information Exchange (EIE), a component of the
E-Filing system. The Workplace Forms Viewer\TM\ is free and is
available at http://www.nrc.gov/site-help/e-submittals/install-viewer.html. Information about applying for a digital ID certificate is
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
Once a petitioner/requestor has obtained a digital ID certificate,
had a docket created, and downloaded the EIE viewer, it can then submit
a request for hearing or petition for leave to intervene. Submissions
should be in Portable Document Format (PDF) in accordance with NRC
guidance available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the
time the filer submits its documents through EIE. To be timely, an
electronic filing must be submitted to the EIE system no later than
11:59 p.m. Eastern Time on the due date. Upon receipt of a
transmission, the E-Filing system time-stamps the document and sends
the submitter an e-mail notice confirming receipt of the document. The
EIE system also distributes an e-mail notice that provides access to
the document to the NRC Office of the General Counsel and any others
who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically may seek assistance through the
``Contact Us'' link located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC
[[Page 19108]]
technical help line, which is available between 8:30 a.m. and 4:15
p.m., Eastern Time, Monday through Friday. The help line number is
(800) 397-4209 or locally, (301) 415-4737.
Participants who believe that they have a good cause for not
submitting documents electronically must file a motion, in accordance
with 10 CFR 2.302(g), with their initial paper filing requesting
authorization to continue to submit documents in paper format. Such
filings must be submitted 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; or (2) courier, express mail, or expedited
delivery service to the Office of the Secretary, Sixteenth Floor, One
White Flint North, 11555 Rockville, Pike, Rockville, Maryland, 20852,
Attention: Rulemaking and Adjudications Staff. Participants filing a
document in this manner are responsible for serving the document on all
other participants. Filing is considered complete by first-class mail
as of the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service.
Non-timely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission, the presiding
officer, or the Atomic Safety and Licensing Board that the petition
and/or request should be granted and/or the contentions should be
admitted, based on a balancing of the factors specified in 10 CFR
2.309(c)(1)(i)-(viii). To be timely, filings must be submitted no later
than 11:59 p.m. Eastern Time on the due date.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant
to an order of the Commission, an Atomic Safety and Licensing Board, or
a Presiding Officer. Participants are requested not to include personal
privacy information, such as social security numbers, home addresses,
or home phone numbers in their filings. With respect to copyrighted
works, except for limited excerpts that serve the purpose of the
adjudicatory filings and would constitute a Fair Use application,
participants are requested not to include copyrighted materials in
their submission.
For further details with respect to this amendment action, see the
application for amendment which is available for public inspection at
the Commission's 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 ADAMS Public
Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. 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 [email protected].
AmerGen Energy Company, LLC, et al., Docket No. 50-219, Oyster Creek
Nuclear Generating Station (Oyster Creek), Ocean County, New Jersey
Date of amendment request: November 13, 2007.
Description of amendment request: The proposed amendment would
delete the Oyster Creek Technical Specification (TS) 6.5, ``Review and
Audit.'' Specifically, the proposed change would delete TS 6.5.1,
``Technical Review and Control,'' TS 6.5.2, ``Independent Safety Review
Function,'' and TS 6.5.3, ``Audits'' which are currently being
implemented by the Exelon/AmerGen Quality Assurance Topical Report.
Additionally, the proposed amendment would correct typographical errors
in Table 3.1.1, ``Protective Instrumentation Requirements'' and Table
4.1.1, ``Minimum Check, Calibration and Test Frequency for Protective
Instrumentation'' and would delete the Condenser Vacuum Pump Isolation
Surveillance from Table 4.1.2, ``Minimum Test Frequencies for Trip
Systems.'' The TS required operability associated with the Surveillance
Requirement (SR) was removed from the Oyster Creek TSs via Amendment
No. 169 and removal of the SR was inadvertently omitted. This request
for approval of a license amendment was submitted concurrently with a
similar request for Three Mile Island Nuclear Station, Unit No. 1
(TMI). Due to some differences in the requested changes, the TMI
amendment request will be noticed separately.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
No physical changes to the facilities, OCNGS [Oyster Creek] and
TMI, will occur as a result of this proposed amendment. The proposed
changes will not alter the physical design or operational procedures
associated with any plant structure, system, or component.
The proposed changes involve the deletion of several
administrative requirements from the Technical Specifications (TS)
that are now controlled under the Exelon/AmerGen Quality Assurance
Topical Report (QATR) and several administrative procedures, AS-AA-
102, [Station Qualified Review Program], HU-AA-1212 (Independent
Third Party Reviews), LS-AA-101 (License/TS changes), LS-AA-106
(PORC), NO-AA-200-002 (Audits) and SY-AA-101-104 (Security Plan
changes), and are, therefore, administrative in nature. The TS
requirements involve Technical Review and Control and Audits. In
accordance with the guidance provided in NRC Administrative Letter
95-06, ``Relocation of Technical Specification Administrative
Controls related to Quality Assurance,'' the proposed changes are an
acceptable method for removing technical specification quality
assurance requirements.
The Independent Safety Review Function is being deleted because
it is a redundant independent safety review to the existing
independent review process being performed under the AmerGen/Exelon
PORC.
The remaining proposed changes are administrative in nature and
have no affect on plant operation. The changes do not reduce the
duties and responsibilities of the organizations performing the
technical review, independent safety review and audit functions
essential to ensuring the safe operation of the plant.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes are administrative in nature. The proposed
changes do not alter the physical design, safety limits, or safety
analysis assumptions associated with the operation of the plant.
Accordingly, the changes do not introduce any new accident
initiators, nor do they reduce or adversely affect the capabilities
of any plant structure, system, or component to perform their safety
function.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes conform to NRC regulatory guidance
regarding the content of plant Technical Specifications. The
guidance is presented in Administrative Letter 95-06, NUREG-1430[,
``Standard Technical Specifications--Babcock and Wilcox Plants,'']
and NUREG-1433[, ``Standard Technical Specifications--General
Electric Plants, BWR/4.''] The relocation of these
[[Page 19109]]
administrative requirements and the deletion of a redundant
independent safety review function will not reduce the
[effectiveness of the] quality assurance commitments as accepted by
the [Nuclear Regulatory Commission (NRC)], nor reduce administrative
controls essential to the safe operation of the plant. Future
changes to these administrative requirements will be performed in
accordance with NRC regulation 10 CFR 50.54(a), consistent with the
guidance identified above. Accordingly, the replacement of TS
requirements by existing QATR requirements results in an
[acceptable] level of regulatory control.
Therefore, the proposed changes do not involve a significant
reduction in any margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, and with the changes noted above, it appears that the
three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC
staff proposes to determine that the amendment request involves no
significant hazards consideration.
Attorney for licensee: Thomas S. O'Neill, Associate General
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road,
Warrenville, IL 60555.
NRC Branch Chief: Richard B. Ennis (Acting).
AmerGen Energy Company, LLC, et al., Docket No. 50-289, Three Mile
Island Nuclear Station, Unit 1 (TMI), Dauphin County, Pennsylvania
Date of amendment request: November 13, 2007.
Description of amendment request: The proposed amendment would
delete the TMI Technical Specification (TS) 6.5, ``Review and Audit.''
Specifically, the proposed change would delete TS 6.5.1, ``Technical
Review and Control,'' TS 6.5.2, ``Independent Safety Review Function,''
and TS 6.5.3, ``Audits'' which are currently being implemented by the
Exelon/AmerGen Quality Assurance Topical Report. Additionally, the
proposed amendment would correct typographical errors in the TMI
Facility Operating License, the TS Table of Contents, and Figure 5-3
while providing more legible versions of Figure 3.1-2a, Figure 3.5-1,
Figure 3.5-2, and Figure 3.5-3. Further, the proposed amendment would
update the description of the installed spent fuel pool storage
locations. This request for approval of a license amendment was
submitted concurrently with a similar request for the Oyster Creek
Nuclear Generating Station (Oyster Creek). Due to some differences in
the requested changes, the Oyster Creek amendment request will be
noticed separately.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
No physical changes to the facilities, OCNGS [Oyster Creek] and
TMI, will occur as a result of this proposed amendment. The proposed
changes will not alter the physical design or operational procedures
associated with any plant structure, system, or component.
The proposed changes involve the deletion of several
administrative requirements from the Technical Specifications (TS)
that are now controlled under the Exelon/AmerGen Quality Assurance
Topical Report (QATR) and several administrative procedures, AS-AA-
102, [Station Qualified Review Program], HU-AA-1212 (Independent
Third Party Reviews), LS-AA-101 (License/TS changes), LS-AA-106
(PORC), NO-AA-200-002 (Audits) and SY-AA-101-104 (Security Plan
changes), and are, therefore, administrative in nature. The TS
requirements involve Technical Review and Control and Audits. In
accordance with the guidance provided in NRC Administrative Letter
95-06, ``Relocation of Technical Specification Administrative
Controls related to Quality Assurance,'' the proposed changes are an
acceptable method for removing technical specification quality
assurance requirements.
The Independent Safety Review Function is being deleted because
it is a redundant independent safety review to the existing
independent review process being performed under the AmerGen/Exelon
PORC.
The remaining proposed changes are administrative in nature and
have no affect on plant operation. The changes do not reduce the
duties and responsibilities of the organizations performing the
technical review, independent safety review and audit functions
essential to ensuring the safe operation of the plant.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes are administrative in nature. The proposed
changes do not alter the physical design, safety limits, or safety
analysis assumptions associated with the operation of the plant.
Accordingly, the changes do not introduce any new accident
initiators, nor do they reduce or adversely affect the capabilities
of any plant structure, system, or component to perform their safety
function.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes conform to NRC regulatory guidance
regarding the content of plant Technical Specifications. The
guidance is presented in Administrative Letter 95-06, NUREG-1430[,
``Standard Technical Specifications--Babcock and Wilcox Plants,'']
and NUREG-1433[, ``Standard Technical Specifications--General
Electric Plants, BWR/4.''] The relocation of these administrative
requirements and the deletion of a redundant independent safety
review function will not reduce the [effectiveness of the] quality
assurance commitments as accepted by the [Nuclear Regulatory
Commission (NRC)], nor reduce administrative controls essential to
the safe operation of the plant. Future changes to these
administrative requirements will be performed in accordance with NRC
regulation 10 CFR 50.54(a), consistent with the guidance identified
above. Accordingly, the replacement of TS requirements by existing
QATR requirements results in an [acceptable] level of regulatory
control.
Therefore, the proposed changes do not involve a significant
reduction in any margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, and with the changes noted above, it appears that the
three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC
staff proposes to determine that the amendment request involves no
significant hazards consideration.
Attorney for licensee: Mr. Bradley Fewell, Associate General
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road,
Warrenville, IL 60555.
NRC Branch Chief: Richard B. Ennis (Acting).
Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point
Nuclear Generating Unit No. 3 (IP3), Westchester County, New York
Date of amendment request: February 28, 2008.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) requirements related to the
containment buffering agent used for pH control under post loss-of-
coolant accident (LOCA) conditions. Specifically, the proposal would
approve the use of sodium tetraborate (STB) as the buffering agent
instead of the currently approved compound, sodium hydroxide (NaOH).
The reason for this change in buffering agents is to minimize the
potential for an adverse chemical interaction between the NaOH and
certain insulation materials in the containment that could degrade flow
through the sump screens following certain design-basis accident
scenarios such as a LOCA.
Basis for proposed no significant hazards consideration
determination:
[[Page 19110]]
As required by 10 CFR 50.91(a), the licensee has provided its analysis
of the issue of no significant hazards consideration, which is
presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment does not involve a significant increase
in the probability of an accident previously evaluated because the
containment buffering agent is not an initiator of any analyzed
accident. The proposed change does not impact any failure modes that
could lead to an accident.
The proposed amendment does not involve a significant increase
in the consequences of an accident previously evaluated. The
buffering agent in containment is designed to buffer the acids
expected to be produced after a LOCA and is credited in the
radiological analysis for iodine retention. Utilizing STB as a
buffering agent ensures the post-LOCA containment sump mixture will
have a pH >= 7.0. The proposed change of replacing sodium hydroxide
with STB results in the radiological consequences remaining within
the limits of 10 CFR 50.67. There is no dose change with the pH
above 7.0.
Therefore, operation of the facility in accordance with the
proposed amendment would not involve a significant increase in the
probability or consequences of an accident previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment does not create the possibility of a new
or different kind of accident from any accident previously
evaluated. STB is a passive component that is proposed to be used at
IP3 as a buffering agent to increase the pH of the initially acidic
post-LOCA containment water to a more neutral pH. Changing the
proposed buffering agent from sodium hydroxide to STB does not
constitute an accident initiator or create a new or different kind
of accident previously analyzed. The operation of the Containment
Spray System remains the same with the isolation of the sodium
hydroxide to the eductors because the flow path of the spray remains
constant through the eductors. The proposed amendment does not
involve operation of any required systems, structures or components
in a manner or configuration different from those previously
recognized or evaluated. No new failure mechanisms will be
introduced by the changes being requested.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed amendment does not involve a significant reduction
in a margin of safety. The proposed amendment of changing the
buffering agent from sodium hydroxide to STB results in equivalent
control of maintaining sump pH at 7.0 or greater, thereby
controlling containment atmosphere iodine and ensuring the
radiological consequences of a LOCA are within regulatory limits.
The change of buffering agent from NaOH to STB also reduces the
amount of sodium aluminum silicate precipitate thereby reducing the
overall amount of precipitate that may be formed in a postulated
LOCA. The buffer change would minimize the potential chemical
effects and should enhance the ability of the emergency core cooling
system to perform the post-accident mitigating functions.
Therefore, the proposed amendment does not involve a significant
reduction in [a] margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. William C. Dennis, Assistant General
Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White
Plains, NY 10601.
NRC Branch Chief: Mark G. Kowal.
Nine Mile Point Nuclear Station, LLC, (NMPNS) Docket No. 50-220, Nine
Mile Point Nuclear Station Unit No. 1 (NMP1), Oswego County, New York
Date of amendment request: February 25, 2008.
Description of amendment request: The proposed amendment would
revise NMP1 Technical Specification (TS) 3/4.4.4, ``Emergency
Ventilation System,'' to remove the operability and surveillance
requirements for the 10,000 watt heater located in the common supply
inlet air duct for the Reactor Building Emergency Ventilation System
(RBEVS). The proposed amendment would also revise TS 3/4.4.5, ``Control
Room Air Treatment System,'' to reduce the 10-hour duration monthly
system operational surveillance test requirement to a 15-minute run
surveillance test requirement.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The RBEVS and the CRAT [Control Room Air Treatment] System do
not involve any initiators or precursors to an accident previously
evaluated as the systems perform a mitigative function in response
to an accident. Failure of the systems would result in the inability
to perform their mitigative function but would not increase the
probability of an accident previously evaluated. The RBEVS is
designed to limit the release of radioactive gases to the
environment such that resulting doses will be less than the
guideline values of 10 CFR 50.67, ``Accident Source Term.'' The CRAT
System is designed to minimize the amount of radioactivity or other
gases from entering the control room in the event of an accident.
Both the RBEVS and the CRAT System charcoal filter materials are
tested in accordance with American Society for Testing and Materials
(ASTM) D3803-1989, ``Standard Test Method for Nuclear-Grade
Activated Carbon'' at a test temperature of 30[deg] C [degrees
Celsius] (86[deg]F [degrees Fahrenheit]) while maintaining a
relative humidity (RH) value of 95%. The testing method assures the
ability of the charcoal filters to perform their intended function
with or without the humidity control function provided by the 10 kW
[kilowatt] heater. The filter efficiency values required by the TS
test criteria provide a safety factor of 2, consistent with the
recommendations of GL [Generic Letter] 99-02.
The previous NMP1 adoption of the more stringent ASTM D3803-1989
charcoal testing parameters resulted in the elimination for humidity
control of inlet air in both the RBEVS and the CRAT system.
Therefore, the need for a 10 hour duration monthly system
operational surveillance test is no longer necessary to demonstrate
reliability and proper function of the systems.
Therefore, these proposed changes do not alter the results of
the accident dose consequence analyses and do not involve a
significant increase in probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed amendment of removing the RBEVS 10 kW common supply
air inlet heater requirements and reducing the duration of the
monthly system operational surveillance requirements from 10 hours
to 15 minutes for both the RBEVS and the CRAT System will not
involve placing the system in a new configuration or operating the
system in a different manner that could result in a new or different
kind of accident. Testing of the charcoal filter materials in
accordance with ASTM D3803-1989 standard at a test temperature of
30[deg] C (86[deg] F) while maintaining a relative humidity 95% will
continue to assure the ability of the system's charcoal filters to
perform its intended function under potential higher inlet air RH
values.
The previous NMP1 adoption of the more stringent ASTM D3803-1989
charcoal testing parameters resulted in the elimination of the need
for humidity control of inlet air in both the RBEVS and the CRAT
system. Therefore, a 10 hour duration monthly system operational
surveillance test is no longer necessary to demonstrate reliability
and proper function of the systems.
[[Page 19111]]
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any [accident] previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment will not adversely affect the performance
characteristics of either the RBEVS or the CRAT System, and will not
affect the ability of either system to perform its intended
function.
Testing of the charcoal filter materials in accordance with ASTM
D3803-1989 and the test parameters required by the TS assures the
ability of the charcoal filters to perform their intended function
with or without the humidity control. The filter efficiency values
required by the TS test criteria provide a safety factor of 2,
consistent with the recommendations of GL 99-02.
The previous NMP1 adoption of the more stringent ASTM D3803-1989
charcoal testing parameters resulted in the elimination of the need
for humidity control of inlet air in both the RBEVS and the CRAT
system. Therefore, a 10 hour duration monthly system operational
surveillance test is no longer necessary to demonstrate reliability
and proper function of the systems.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mark J. Wetterhahn, Esquire, Winston &
Strawn, 1700 K Street, NW., Washington, DC 20006.
NRC Branch Chief: Mark G. Kowal.
R.E. Ginna Nuclear Power Plant, LLC, Docket No. 50-244, R.E. Ginna
Nuclear Power Plant, Wayne County, New York
Date of amendment request: February 8, 2008.
Description of amendment request: The proposed amendment would
revise Technical Specification 5.6.6, ``Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR),'' to update the method
used to develop the RCS heatup and cooldown and Low Temperature Over
Pressure (LTOP) limits utilizing current NRC approved methodology.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
Integrity of the reactor vessel is integral to plant safety. It
provides containment and continuity for the reactor core, and as
part of the reactor coolant system acts as one of the three fission
product barriers to the environment. The purpose of the heatup and
cooldown limit curves and LTOP setpoints is to ensure vessel
integrity through the spectrum of operating modes. Operating within
those limits ensures that brittle failure of the vessel material
does not occur due to the thermal and pressure stresses the vessel
is subjected to during operation. During power operation, the
effects of neutron radiation tend to change the characteristics of
the vessel material making it more brittle. To compensate for this
the operating limits must be periodically adjusted. The methodology
being proposed in this submittal is designed to ensure vessel
integrity, is analytically sound, and has been reviewed and approved
by the NRC. Therefore, the proposed change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
Due to its thickness and material properties, the reactor vessel
is the limiting component for brittle fracture in the reactor
coolant system. The proposed methodology appropriately limits the
operating parameters to preclude the possibility of vessel failure.
No new failure mechanisms or accident precursors are introduced as a
result of this proposed change. Therefore, this change does not
create the possibility of a new or different [kind] of accident from
any accident previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed methodology in WCAP-14040-A, Methodology Used to
Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup
and Cooldown Limit Curves, Revision 4, contains appropriate margin
and has been reviewed and approved by the NRC. Since the new
methodology for developing heatup and cooldown curves will produce
less restrictive curves, use of the existing methodology for LTOP
setpoints will continue to provide adequate margin to the [Title 10
of the Code of Federal Regulations, Part 50] Appendix G limits.
Therefore, this proposed change does not involve a significant
reduction in [a] margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Carey Fleming, Sr. Counsel--Nuclear
Generation, Constellation Generation Group, LLC, 750 East Pratt Street,
17th floor, Baltimore, MD 21202.
NRC Branch Chief: Mark G. Kowal.
Previously Published Notices of Consideration of Issuance of Amendments
to Facility Operating Licenses, Proposed No Significant Hazards
Consideration Determination, and Opportunity for a Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois
Date of amendment request: February 25, 2008.
Brief description of amendment request: The proposed amendment
would revise Technical Specification (TS) 5.5.9, ``Steam Generator (SG)
Program,'' and TS 5.6.9, ``Steam Generator Tube Inspection Report.''
For TS 5.5.9, the amendment would replace the existing alternate repair
criteria in the provisions for SG tube repair criteria during Braidwood
Station (Braidwood), Unit 2, refueling outage 13 and the subsequent
operating cycle. For TS 5.6.9, three new reporting requirements are
proposed to be added to the existing seven requirements. The proposed
changes only affect Braidwood, Unit 2; however, this is docketed for
Braidwood, Units 1 and 2, because the TS are common to both units.
Date of publication of individual notice in Federal Register: March
11, 2008.
Expiration date of individual notice: April 11, 2008 (public
comment); May 11, 2008 (hearing requests).
FPL Energy Seabrook LLC, Docket No. 50-443, Seabrook Station, Unit No.
1, Rockingham County, New Hampshire
Date of amendment request: March 7, 2008.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) Table 4.3-1, ``Reactor Trip System
Instrumentation
[[Page 19112]]
Surveillance Requirements,'' to require the initial plateau curves to
be measured within 24 hours after attaining 100 percent steady-state
power. Currently, initial plateau curves are required to be taken
within 24 hours of entry into Mode 2.
Date of publication of individual notice in Federal Register: March
19, 2008 (FR 72 14850).
Expiration date of individual notice: April 18, 2008 (Public
comment) and May 19, 2008 (Hearing requests).
Notice of Issuance of Amendments To Facility Operating Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
Notice of Consideration of Issuance of Amendment to Facility
Operating License, Proposed No Significant Hazards Consideration
Determination, and Opportunity for A Hearing in connection with these
actions was published in the Federal Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) The
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection 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 Systems (ADAMS) Public
Electronic Reading Room on the Internet at the NRC web site, http://www.nrc.gov/reading-rm/adams.html. 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 [email protected].
Calvert Cliffs Nuclear Power Plant, Inc., Docket Nos. 50-317 and 50-
318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert
County, Maryland
Date of application for amendments: October 17, 2007, as
supplemented by letter dated December 13, 2007.
Brief description of amendments: These amendments modify Technical
Specification requirements for inoperable snubbers by adding Limiting
Condition for Operation (LCO) 3.0.8. This operating license improvement
was made available by the Nuclear Regulatory Commission on May 4, 2005
(70 FR 23252) as part of the consolidated line item improvement
process. In addition, the amendments correct an omission to Amendment
No. 282 and 259, issued on September 27, 2007, that adopted Technical
Specification Task Force Traveler 427 by including a reference to LCO
3.0.9 in LCO 3.0.1.
Date of issuance: March 24, 2008.
Effective date: As of the date of issuance to be implemented within
60 days.
Amendment Nos.: Unit 1--285, Unit 2--262.
Renewed Facility Operating License Nos. DPR-53 and DPR-69:
Amendments revised the License and Technical Specifications.
Date of initial notice in Federal Register: November 20, 2007 (72
FR 65362) The letter dated December 13, 2007, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the staff's
original proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of these amendments is
contained in a Safety Evaluation dated March 24, 2008.
No significant hazards consideration comments received: No.
Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of application for amendment: March 19, 2007, as supplemented
by letter dated August 16, 2007.
Brief description of amendment: The amendment revised the Technical
Specification 3.8.1 entitled ``AC [Alternating Current] Sources-
Operating'' to change the minimum Emergency Diesel Generator output
voltage acceptance criterion from 3740 to 3873 volts. Specifically, the
proposed change revised the Surveillance Requirements 3.8.1.2, 3.8.1.7,
3.8.1.10, 3.8.1.11, 3.8.1.14, and 3.8.1.17.
Date of issuance: March 17, 2008.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment No.: 178.
Facility Operating License No. NPF-43: Amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: April 24, 2007 (72 FR
20379).
The supplemental letter contained clarifying information and did
not change the initial no significant hazards consideration
determination, and did not expand the scope of the original Federal
Register notice.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 17, 2008.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden
Nuclear Power Station, Units 2 and 3, Grundy County, Illinois, Docket
Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and
2, Rock Island County, Illinois
Date of application for amendments: April 12, 2007.
Brief description of amendments: The amendments revise technical
specification requirements related to control room envelope
habitability in accordance with Technical Specification Task Force
Traveler TSTF-448, Revision 3, ``Control Room Habitability.''
Date of issuance: March 20, 2008.
Effective date: As of the date of issuance and shall be implemented
within 180 days of the date of issuance.
Amendment Nos.: 226/218 and 238/233.
Renewed Facility Operating License Nos. DPR-19, DPR-25, DPR-29 and
DPR-30: The amendments revised the Technical Specifications and
License.
Date of initial notice in Federal Register: June 5, 2007 (72 FR
31100) The Commission's related evaluation of the amendments is
contained in a Safety Evaluation dated March 20, 2008.
No significant hazards consideration comments received: No.
[[Page 19113]]
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad
Cities Nuclear Power Station, Units 1 and 2, Rock Island County,
Illinois
Date of application for amendments: November 20, 2007.
Brief description of amendments: The amendments revised the values
of the safety limit minimum critical power ratio (SLMCPR) in Technical
Specification (TS) Section 2.1.1, ``Reactor Core SLs.'' Specifically,
the amendments deleted the Quad Cities Nuclear Power Station (QCNPS),
Unit 2 fuel-specific SLMCPR requirements for Global Nuclear Fuel GE14
fuel and consolidated QCNPS SLMCPR requirements into a bounding dual-
unit requirement.
Date of issuance: February 28, 2008.
Effective date: As of the date of issuance and shall be implemented
prior to startup from the next refueling outage for QCNPS, Unit 2
(Q2R19), which is scheduled to start in March 2008.
Amendment Nos.: 237/232.
Renewed Facility Operating License Nos. DPR-29 and DPR-30: The
amendments revised the Technical Specifications and License.
Date of initial notice in Federal Register: December 18, 2007 (72
FR 71712) The Commission's related evaluation of the amendments is
contained in a Safety Evaluation dated February 28, 2008.
No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, et al., Docket No. 50-412,
Beaver Valley Power, Station, Unit No. 2, Beaver County, Pennsylvania
Date of application for amendment: February 9, 2007, as
supplemented by letters dated August 8, August 23, September 13, 2007,
and January 25, 2008.
Brief description of amendment: The amendment will address Generic
Safety Issue 191 ``Assessment of Debris Accumulation on PWR Sump
Performance,'' by implementing Technical Specification (TS) changes
that reflect the use of a new recirculation spray system pump start
signal due to a modification to the containment sump screens and
replace the use of LOCTIC with the Modular Accident Analysis Program-
Design Basis Accident calculation methodology to calculate containment
pressure, temperature, and condensation rates for input to the SWNAUA
code, which ultimately changes the aerosol removal coefficients used in
dose consequence analysis.
Date of issuance: March 11, 2008.
Effective date: As of the date of issuance, and shall be
implemented prior to the first entry into Mode 4 coming out of 2R13,
which begins April 2008.
Amendment No: 164.
Facility Operating License No. NPF-73: The amendment revised the
License and TS.
Date of initial notice in Federal Register: April 24, 2007 (72 FR
20383). The supplements dated August 8, August 23, September 13, 2007,
and January 25, 2008, provided additional information that clarified
the application, did not expand the scope of the application as
originally noticed, and did not change the staff's original proposed no
significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 11, 2008.
No significant hazards consideration comments received: No.
FPL Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold Energy
Center, Linn County, Iowa
Date of application for amendment: September 14, 2007.
Brief description of amendment: This amendment consists of changes
to the Technical Specifications in response to your application dated
September 14, 2007, which requested revision to TS 3.3.2.1, ``Control
Rod Block Instrumentation,'' Table 3.3.2.1-1, ``Control Rod Block
Instrumentation,'' to modify a footnote such that a new Banked Position
Withdrawal Sequence (BPWS) shutdown sequence could be utilized.
Date of issuance: March 20, 2008.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment No.: 268.
Facility Operating License No. DPR-49: The amendment revised the
Technical Specifications and Facility Operating License.
Date of initial notice in Federal Register: December 4, 2007 (72 FR
68216).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 20, 2008.
No significant hazards consideration comments received: No.
Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo
Canyon Nuclear Power Plant, Unit Nos. 1 and 2, San Luis Obispo County,
California
Date of application for amendments: October 2, 2007, as
supplemented by letters dated February 8, and March 11, 2008.
Brief description of amendments: The amendments revised Technical
Specification 3.5.4, ``Refueling Water Storage Tank (RWST),'' and
Surveillance Requirement 3.5.4.2, to increase the minimum required
borated water volume from ``>= 400,000 gallons (81.5% indicated
level)'' to ``>= 455,300 gallons.''
Date of issuance: March 26, 2008.
Effective date: As of its date of issuance and shall be implemented
prior to Mode 4 entry following refueling outage 2R14.
Amendment Nos.: Unit 1--199; Unit 2--200.
Facility Operating License Nos. DPR-80 and DPR-82: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: December 31, 2007 (72
FR 74361). The supplemental letters dated February 8, and March 11,
2008, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register. The
Commission's related evaluation of the amendments is contained in a
Safety Evaluation dated March 26, 2008.
No significant hazards consideration comments received: No.
R.E. Ginna Nuclear Power Plant, LLC, Docket No. 50-244, R.E. Ginna
Nuclear Power Plant, Wayne County, New York
Date of application for amendment: October 17, 2007, as
supplemented by letter dated December 13, 2007.
Brief description of amendment: The amendment revises Technical
Specifications requirements for inoperable snubbers by adding Limiting
Condition for Operation 3.0.8. This operating license improvement was
made available by the Nuclear Regulatory Commission on May 4, 2005 (70
FR 23252) as part of the consolidated line item improvement process.
Date of issuance: March 19, 2008.
Effective date: As of the date of issuance to be implemented within
60 days.
Amendment No.: 104.
Renewed Facility Operating License No. DPR-18: Amendment revised
the License and Technical Specifications.
Date of initial notice in Federal Register: November 20, 2007 (72
FR 65371) The letter dated December 13, 2007, provided additional
information that clarified the application, did not
[[Page 19114]]
expand the scope of the application as originally noticed, and did not
change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 19, 2008.
No significant hazards consideration comments received: No.
Southern California Edison Company, et al., Docket Nos. 50-361 and 50-
362, San Onofre Nuclear Generating Station, Units 2 and 3, San Diego
County, California
Date of application for amendments: February 8, 2007, as
supplemented by letters dated July 24 and November 15, 2007, and
February 19, 2008.
Brief description of amendments: The amendments incorporate changes
which (1) revised Technical Specifications (TS) Surveillance
Requirement (SR) 3.3.7.3.a to lower the allowable value for dropout and
raise the allowable value for pickup of the degraded voltage function,
and (2) revised TS SR 3.8.1 to lower the diesel generator minimum
output voltage due to lower settings for the degraded voltage function.
Date of issuance: March 18, 2008.
Effective date: as of its date of issuance, to be implemented
within 60 days of issuance.
Amendment Nos.: Unit 2--216; Unit 3--208.
Facility Operating License Nos. NPF-10 and NPF-15: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: March 27, 2007 (72 FR
14307). The supplemental letters dated July 24 and November 15, 2007,
and February 19, 2008, provided additional information that clarified
the application, did not expand the scope of the application as
originally noticed, and did not change the staff's original proposed no
significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 18, 2008.
No significant hazards consideration comments received: No.
Southern California Edison Company, et al., Docket Nos. 50-361 and 50-
362, San Onofre Nuclear Generating Station, Units 2 and 3, San Diego
County, California
Date of application for amendments: March 30, 2007, as supplemented
by letters dated November 5, 2007, and January 15 and February 19,
2008.
Brief description of amendments: The amendments revised Technical
Specifications Surveillance Requirement 3.3.7.3.b, ``Loss of Voltage
Function,'' to a narrower voltage band and lower operating time for
channel calibration testing, by replacing the undervoltage relays with
the reset time significantly lower.
Date of issuance: March 25, 2008.
Effective date: As of the date of its issuance and shall be
implemented in the next refueling outage or unit outage of sufficient
duration, whichever occurs first.
Amendment Nos.: Unit 2--217; Unit 3--209.
Facility Operating License Nos. NPF-10 and NPF-15: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: April 24, 2007 (72 FR
20385). The supplemental letters dated November 5, 2007, and January 15
and February 19, 2008, provided additional information that clarified
the application, did not expand the scope of the application as
originally noticed, and did not change the staff's original proposed no
significant hazards consideration determination as published in the
Federal Register. The Commission's related evaluation of the amendments
is contained in a Safety Evaluation dated March 25, 2008.
No significant hazards consideration comments received: No.
STP Nuclear Operating Company, Docket Nos. 50-498 and 50-499, South
Texas Project, Units 1 and 2, Matagorda County, Texas
Date of amendment request: May 21, 2007, as supplemented by letter
dated November 26, 2007.
Brief description of amendments: The amendments revised the
Technical Specifications Surveillance Requirement 4.5.2.d for the
Emergency Core Cooling System sumps for consistency with the new sump
design and configuration.
Date of issuance: March 25, 2008.
Effective date: As of its date of issuance and shall be implemented
after completion of the corrective actions and modifications for
resolution of Generic Safety Issue 191, ``Assessment of Debris
Accumulation on PWR Sump Pump Performance.''
Amendment Nos.: Unit 1--183; Unit 2--170.
Facility Operating License Nos. NPF-76 and NPF-80: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: July 31, 2007 (72 FR
41789). The supplemental letter dated November 26, 2007, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register. The Commission's
related evaluation of the amendments is contained in a Safety
Evaluation dated March 25, 2008.
No significant hazards consideration comments received: No.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek
Generating Station, Coffey County, Kansas
Date of amendment request: March 14, 2007, as supplemented by
letters dated September 12, October 16, and December 14 (two letters),
2007, and January 18, 2008.
Brief description of amendment: The amendment authorizes (1) the
replacement of the main steam isolation valves (MSIVs) and main
feedwater isolation valves (MFIVs) and (2) the use of Figures B 3.7.2-1
(MSIVs) and 3.7.3-1 (MFIVs) as the limiting closure times for these
valves to demonstrate that these valves meet the limiting conditions
for operation with respect to the valve closure time. The remaining
amendment requests in the application that have not yet been addressed
by the NRC are the proposed (1) addition of main feedwater regulating
valves and bypass valves to TS 3.7.3, ``Main Feedwater Isolation
Valves,'' and (2) modification of the main steam and feedwater
isolation system (MSFIS) controls. These requests will be addressed in
future letters to the licensee.
Date of issuance: March 21, 2008.
Effective date: As of its date of issuance and shall be implemented
before entry into Mode 3 in the restart from Refueling Outage 16, which
is to be conducted in the spring of 2008.
Amendment No.: 176.
Facility Operating License No. NPF-42. The amendment revises the
license.
Date of initial notice in Federal Register: June 19, 2007 (72 FR
33785).
The supplemental letters dated September 12, October 16, and
December 14 (two letters), 2007, and January 18, 2008, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
[[Page 19115]]
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 21, 2008.
No significant hazards consideration comments received: No.
Notice of Issuance of Amendments to Facility Operating Licenses and
Final Determination of No Significant Hazards Consideration and
Opportunity for a Hearing (Exigent Public Announcement or Emergency
Circumstances)
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application for the
amendment complies with the standards and requirements of the Atomic
Energy Act of 1954, as amended (the Act), and the Commission's rules
and regulations. The Commission has made appropriate findings as
required by the Act and the Commission's rules and regulations in 10
CFR Chapter I, which are set forth in the license amendment.
Because of exigent or emergency circumstances associated with the
date the amendment was needed, there was not time for the Commission to
publish, for public comment before issuance, its usual Notice of
Consideration of Issuance of Amendment, Proposed No Significant Hazards
Consideration Determination, and Opportunity for a Hearing.
For exigent circumstances, the Commission has either issued a
Federal Register notice providing opportunity for public comment or has
used local media to provide notice to the public in the area
surrounding a licensee's facility of the licensee's application and of
the Commission's proposed determination of no significant hazards
consideration. The Commission has provided a reasonable opportunity for
the public to comment, using its best efforts to make available to the
public means of communication for the public to respond quickly, and in
the case of telephone comments, the comments have been recorded or
transcribed as appropriate and the licensee has been informed of the
public comments.
In circumstances where failure to act in a timely way would have
resulted, for example, in derating or shutdown of a nuclear power plant
or in prevention of either resumption of operation or of increase in
power output up to the plant's licensed power level, the Commission may
not have had an opportunity to provide for public comment on its no
significant hazards consideration determination. In such case, the
license amendment has been issued without opportunity for comment. If
there has been some time for public comment but less than 30 days, the
Commission may provide an opportunity for public comment. If comments
have been requested, it is so stated. In either event, the State has
been consulted by telephone whenever possible.
Under its regulations, the Commission may issue and make an
amendment immediately effective, notwithstanding the pendency before it
of a request for a hearing from any person, in advance of the holding
and completion of any required hearing, where it has determined that no
significant hazards consideration is involved.
The Commission has applied the standards of 10 CFR 50.92 and has
made a final determination that the amendment involves no significant
hazards consideration. The basis for this determination is contained in
the documents related to this action. Accordingly, the amendments have
been issued and made effective as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.12(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) The
application for amendment, (2) the amendment to Facility Operating
License, and (3) the Commission's related letter, Safety Evaluation
and/or Environmental Assessment, as indicated. All of these items are
available for public inspection 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, http://www.nrc.gov/reading-rm/adams.html. 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 [email protected].
The Commission is also offering an opportunity for a hearing with
respect to the issuance of the amendment. Within 60 days after the date
of publication of this notice, person(s) 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 via electronic submission
through the NRC E-Filing system 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 person(s) should consult a current copy of 10 CFR 2.309,
which is available at the Commission's PDR, located at One White Flint
North, Public File Area 01F21, 11555 Rockville Pike (first floor),
Rockville, Maryland, and electronically on the Internet at the NRC Web
site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are
problems in accessing the document, contact the PDR Reference staff at
1 (800) 397-4209, (301) 415-4737, or by e-mail to [email protected]. 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 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/
[[Page 19116]]
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.\1\ 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 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.
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\1\ To the extent that the applications contain attachments and
supporting documents that are not publicly available because they
are asserted to contain safeguards or proprietary information,
petitioners desiring access to this information should contact the
applicant or applicant's counsel and discuss the need for a
protective order.
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Each contention shall be given a separate numeric or alpha
designation within one of the following groups:
1. Technical--primarily concerns/issues relating to technical and/
or health and safety matters discussed or referenced in the
applications.
2. Environmental--primarily concerns/issues relating to matters
discussed or referenced in the environmental analysis for the
applications.
3. Miscellaneous--does not fall into one of the categories outlined
above.
As specified in 10 CFR 2.309, if two or more petitioners/requestors
seek to co-sponsor a contention, the petitioners/requestors shall
jointly designate a representative who shall have the authority to act
for the petitioners/requestors with respect to that contention. If a
petitioner/requestor seeks to adopt the contention of another
sponsoring petitioner/requestor, the petitioner/requestor who seeks to
adopt the contention must either agree that the sponsoring petitioner/
requestor shall act as the representative with respect to that
contention, or jointly designate with the sponsoring petitioner/
requestor a representative who shall have the authority to act for the
petitioners/requestors with respect to that contention.
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. Since the Commission has made a final determination that the
amendment involves no significant hazards consideration, if a hearing
is requested, it will not stay the effectiveness of the amendment. Any
hearing held would take place while the amendment is in effect.
A request for hearing or a petition for leave to intervene must be
filed in accordance with the NRC E-Filing rule, which the NRC
promulgated in August 28, 2007 (72 FR 49139). The E-Filing process
requires participants to submit and serve documents over the Internet
or in some cases to mail copies on electronic storage media.
Participants may not submit paper copies of their filings unless they
seek a waiver in accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least
five (5) days prior to the filing deadline, the petitioner/ requestor
must contact the Office of the Secretary by e-mail at
[email protected], or by calling (301) 415-1677, to request (1) a
digital ID certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and/or (2)
creation of an electronic docket for the proceeding (even in instances
in which the petitioner/requestor (or its counsel or representative)
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms ViewerTM
to access the Electronic Information Exchange (EIE), a component of the
E-Filing system. The Workplace Forms ViewerTM is free and is
available at http://www.nrc.gov/site-help/e-submittals/install-viewer.html. Information about applying for a digital ID certificate is
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
Once a petitioner/requestor has obtained a digital ID certificate,
had a docket created, and downloaded the EIE viewer, it can then submit
a request for hearing or petition for leave to intervene. Submissions
should be in Portable Document Format (PDF) in accordance with NRC
guidance available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the
time the filer submits its documents through EIE. To be timely, an
electronic filing must be submitted to the EIE system no later than
11:59 p.m. Eastern Time on the due date. Upon receipt of a
transmission, the E-Filing system time-stamps the document and sends
the submitter an e-mail notice confirming receipt of the document. The
EIE system also distributes an e-mail notice that provides access to
the document to the NRC Office of the General Counsel and any others
who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically may seek assistance through the
``Contact Us'' link located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC technical help line,
which is available between 8:30 a.m. and 4:15 p.m., Eastern Time,
Monday through Friday. The help line number is (800) 397-4209 or
locally, (301) 415-4737.
Participants who believe that they have a good cause for not
submitting documents electronically must file a motion, in accordance
with 10 CFR 2.302(g), with their initial paper filing requesting
authorization to continue to submit documents in paper format. Such
filings must be submitted 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; or (2) courier, express mail, or expedited
delivery service to the Office of the Secretary, Sixteenth Floor, One
White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852,
Attention: Rulemaking and Adjudications Staff. Participants filing a
document in this manner are responsible for serving the document on all
other participants. Filing is considered complete by first-class mail
as of the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service.
Non-timely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission, the presiding
officer, or
[[Page 19117]]
the Atomic Safety and Licensing Board that the petition and/or request
should be granted and/or the contentions should be admitted, based on a
balancing of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii). To
be timely, filings must be submitted no later than 11:59 p.m. Eastern
Time on the due date.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant
to an order of the Commission, an Atomic Safety and Licensing Board, or
a Presiding Officer. Participants are requested not to include personal
privacy information, such as social security numbers, home addresses,
or home phone numbers in their filings. With respect to copyrighted
works, except for limited excerpts that serve the purpose of the
adjudicatory filings and would constitute a Fair Use application,
participants are requested not to include copyrighted materials in
their submission.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear
Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey
Date of amendment request: March 5, 2008.
Description of amendment request: The amendments revise the
surveillance requirements for Technical Specification (TS) 3/4.9.4,
``Containment Building Penetrations.''
Date of issuance: March 13, 2008.
Effective date: As of the date of issuance, to be implemented
within 1 day.
Amendment Nos.: 288 and 272.
Facility Operating License Nos. DPR-70 and DPR-75: The amendments
revise the TSs and the licenses.
Public comments requested as to proposed no significant hazards
consideration (NSHC): Yes. Public notice of the proposed amendments was
published in the Today's Sunbeam newspaper, located in Salem, New
Jersey on March 11, 2008. The notice provided an opportunity to submit
comments on the Commission's proposed NSHC determination. No comments
have been received.
The Commission's related evaluation of the amendment, finding of
exigent circumstances, state consultation, and final NSHC determination
are contained in a safety evaluation dated March 13, 2008.
Attorney for licensee: Jeffrie J. Keenan, Esquire, Nuclear Business
Unit--N21, P.O. Box 236, Hancocks Bridge, NJ 08038.
NRC Branch Chief: Harold K. Chernoff.
Dated at Rockville, Maryland, this 28th day of March, 2008.
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E8-6904 Filed 4-7-08; 8:45 am]
BILLING CODE 7590-01-P