Calvert Cliffs Nuclear Power Plant, Inc.; Independent Spent Fuel Storage Installation; Notice of Docketing of Materials License SNM-2505; Amendment Application, 36216 [E5-3227]
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36216
Federal Register / Vol. 70, No. 119 / Wednesday, June 22, 2005 / Notices
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–8]
Calvert Cliffs Nuclear Power Plant,
Inc.; Independent Spent Fuel Storage
Installation; Notice of Docketing of
Materials License SNM–2505;
Amendment Application
Nuclear Regulatory
Commission.
ACTION: License amendment.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
Joseph M. Sebrosky, Senior Project
Manager, Spent Fuel Project Office,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
Telephone: (301) 415–1132; fax number:
(301) 415–1179; e-mail: jms3@nrc.gov.
SUPPLEMENTARY INFORMATION: By letter
dated May 16, 2005, Calvert Cliffs
Nuclear Power Plant, Inc., (CCNPP or
licensee) submitted an application to
the U.S. Nuclear Regulatory
Commission (NRC or the Commission),
in accordance with Title 10 of the Code
of Federal Regulations (10 CFR) 72.56,
requesting the amendment of the
independent spent fuel storage
installation (ISFSI) license for the ISFSI
located in Calvert County, Maryland.
CCNPP proposes to incorporate changes
to the updated safety analysis report to
alter the design basis limit for the ISFSI
dry shielded canister internal pressure
from 50 psig to 100 psig.
This application was docketed under
10 CFR Part 72; the ISFSI Docket No. is
72–8 and will remain the same for this
action. Upon approval of the
Commission, the CCNPP ISFSI license,
SNM–2505, would be amended to allow
this action.
The Commission may issue either a
notice of hearing or a notice of proposed
action and opportunity for hearing in
accordance with 10 CFR 72.46(b)(1)
regarding the proposed amendment or,
if a determination is made that the
proposed amendment does not present
a genuine issue as to whether public
health and safety will be significantly
affected, take immediate action on the
proposed amendment in accordance
with 10 CFR 72.46(b)(2) and provide
notice of the action taken and an
opportunity for interested persons to
request a hearing on whether the action
should be rescinded or modified.
For further details with respect to this
amendment, see the application dated
May 16, 2005, which is publically
available in the records component of
NRC’s Agencywide Documents Access
and Management System (ADAMS). The
VerDate jul<14>2003
21:12 Jun 21, 2005
Jkt 205001
NRC maintains ADAMS, which
provides text and image files of NRC’s
public documents. These documents
may be accessed through the NRC’s
Public Electronic Reading Room on the
Internet at https://www.nrc.gov/readingrm/adams.html. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
Public Document Room (PDR) Reference
staff at 1–800–397–4209, 301–415–4737
or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 7th day
of June, 2005.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project
Office, Office of Nuclear Material Safety and
Safeguards.
[FR Doc. E5–3227 Filed 6–21–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–271; License No. DPR–28]
Entergy Nuclear Vermont Yankee, LLC
and Entergy Nuclear Operations, Inc.;
Receipt of Request for Action Under 10
CFR 2.206
Notice is hereby given that by petition
dated May 3, 2005, the New England
Coalition (NEC or the petitioner) has
requested that the Nuclear Regulatory
Commission (NRC or the Commission)
take action with regard to the Vermont
Yankee Nuclear Power Station (Vermont
Yankee). The NEC petition requested
that the NRC promptly restore
reasonable assurance of adequate
protection of public health and safety
with regard to the fire barriers in
electrical cable protection systems at
Vermont Yankee, or otherwise to order
a derate of Vermont Yankee until such
time as the operability of the fire
barriers can be assured. Specifically, the
petition requested that the Commission
take the following actions: (1) Require
Entergy Nuclear Vermont Yankee
(ENVY) to promptly conduct a review at
Vermont Yankee to determine the extent
of condition, including a full inventory
of the type, amount, application, and
placement of Hemyc, and an assessment
of the safety significance of each
application; (2) require ENVY to
promptly provide justification for
operation in nonconformance with 10
CFR Part 50, Appendix R; and (3) upon
finding that Vermont Yankee is
operating in an unanalyzed condition
and/or that assurance of public health
and safety is degraded, promptly order
a power reduction (derate) of Vermont
PO 00000
Frm 00108
Fmt 4703
Sfmt 4703
Yankee until such time as it can be
demonstrated that ENVY is operating in
conformance with 10 CFR Part 50,
Appendix R, and all other applicable
regulations.
The request is being treated pursuant
to Title 10 of the Code of Federal
Regulations (10 CFR), Section 2.206, of
the Commission’s regulations. The
request has been referred to the Director
of the Office of Nuclear Reactor
Regulation. As provided by 10 CFR
2.206, appropriate action will be taken
on this petition within a reasonable
time. Mr. Raymond Shadis, in his
capacity as the petitioner’s Staff
Technical Advisor, participated in a
telephone conference call with the
NRC’s Petition Review Board (PRB) on
May 17, 2005, to discuss the petition.
The results of that discussion were
considered in the PRB’s determination
regarding the petitioner’s request for
action and in establishing the schedule
for the review of the petition. During the
May 17, 2005, PRB conference call, the
petitioner requested that the licensee
review fire barriers beyond the Hemyc
electric raceway fire barrier system. This
request will not be accepted under the
2.206 process because the petitioner did
not provide adequate information to
justify expanding the scope of the
review.
A copy of the petition and the
transcript of the telephone conference
call are available for inspection at the
Commission’s Public Document Room
(PDR), located at One White Flint North,
Public File Area O1 F21, 11555
Rockville Pike (first floor), Rockville,
Maryland, and from the NRC’s
Agencywide Documents Access and
Management System (ADAMS), Public
Electronic Reading Room, on the
Internet at the NRC Web site, https://
www.nrc.gov/reading-rm/adams.html
(ADAMS Accession Nos. ML051370182
and ML051610042). 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 15th day
of June 2005.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Acting Director, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–3223 Filed 6–21–05; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\22JNN1.SGM
22JNN1
Agencies
[Federal Register Volume 70, Number 119 (Wednesday, June 22, 2005)]
[Notices]
[Page 36216]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-3227]
[[Page 36216]]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 72-8]
Calvert Cliffs Nuclear Power Plant, Inc.; Independent Spent Fuel
Storage Installation; Notice of Docketing of Materials License SNM-
2505; Amendment Application
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Joseph M. Sebrosky, Senior Project
Manager, Spent Fuel Project Office, Office of Nuclear Material Safety
and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC
20555. Telephone: (301) 415-1132; fax number: (301) 415-1179; e-mail:
jms3@nrc.gov.
SUPPLEMENTARY INFORMATION: By letter dated May 16, 2005, Calvert Cliffs
Nuclear Power Plant, Inc., (CCNPP or licensee) submitted an application
to the U.S. Nuclear Regulatory Commission (NRC or the Commission), in
accordance with Title 10 of the Code of Federal Regulations (10 CFR)
72.56, requesting the amendment of the independent spent fuel storage
installation (ISFSI) license for the ISFSI located in Calvert County,
Maryland. CCNPP proposes to incorporate changes to the updated safety
analysis report to alter the design basis limit for the ISFSI dry
shielded canister internal pressure from 50 psig to 100 psig.
This application was docketed under 10 CFR Part 72; the ISFSI
Docket No. is 72-8 and will remain the same for this action. Upon
approval of the Commission, the CCNPP ISFSI license, SNM-2505, would be
amended to allow this action.
The Commission may issue either a notice of hearing or a notice of
proposed action and opportunity for hearing in accordance with 10 CFR
72.46(b)(1) regarding the proposed amendment or, if a determination is
made that the proposed amendment does not present a genuine issue as to
whether public health and safety will be significantly affected, take
immediate action on the proposed amendment in accordance with 10 CFR
72.46(b)(2) and provide notice of the action taken and an opportunity
for interested persons to request a hearing on whether the action
should be rescinded or modified.
For further details with respect to this amendment, see the
application dated May 16, 2005, which is publically available in the
records component of NRC's Agencywide Documents Access and Management
System (ADAMS). The NRC maintains ADAMS, which provides text and image
files of NRC's public documents. These documents may be accessed
through the NRC's Public Electronic Reading Room on the Internet at
https://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 NRC Public Document Room (PDR) Reference staff at 1-
800-397-4209, 301-415-4737 or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 7th day of June, 2005.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project Office, Office of Nuclear
Material Safety and Safeguards.
[FR Doc. E5-3227 Filed 6-21-05; 8:45 am]
BILLING CODE 7590-01-P