[Federal Register Volume 79, Number 94 (Thursday, May 15, 2014)]
[Notices]
[Pages 27939-27940]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-11231]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-302; License No. DPR-72; NRC-2010-0096]
Duke Energy Florida, Inc.; Crystal River Nuclear Generating
Plant, Unit 3
AGENCY: Nuclear Regulatory Commission.
ACTION: Director's decision; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is giving notice
that the Director of the Office of Nuclear Reactor Regulation (NRR) has
issued a director's decision with regard to a petition dated December
9, 2009, as supplemented on January 7 and August 6, 2010, filed by
Thomas Saporitio (the petitioner).
ADDRESSES: Please refer to Docket ID NRC-2010-0096 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2010-0096. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by
[[Page 27940]]
email to [email protected]. The ADAMS accession number for each
document referenced in this document (if that document is available in
ADAMS) is provided the first time that a document is referenced.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Christopher Gratton, Office of Nuclear
Reactor Regulation; U.S. Nuclear Regulatory Commission, Washington DC
20555-0001; telephone: 301-415-1055; email:
[email protected].
SUPPLEMENTARY INFORMATION: Notice is hereby given that the Director, of
NRR, has issued a director's decision with regard to a petition dated
December 5, 2009, filed by Thomas Saporito (ADAMS Accession No.
ML093430702). The petition was supplemented on January 7, 2010 (ADAMS
Accession No. ML100200966) and consolidated with an additional August
6, 2010, petition (ADAMS Accession No. ML102220032). The petition
concerns the operation of the Crystal River Nuclear Generating Plant,
Unit 3 (CR-3).
In the December 5, 2009, petition, the petitioner raised concerns
about the delamination (i.e., the separation of the different layers)
of the CR-3 containment that occurred during the fall 2009 refueling
outage. The petitioner considers this condition to be potentially
unsafe and to be in violation of Federal regulations. In the petition,
a number of references to the condition of the CR-3 containment were
cited that the petitioner believes prohibit operation of the facility.
The petition requested that CR-3 perform the following actions, as
summarized below:
1. Physically remove the outer 25 centimeters (10 inches) of
concrete surrounding the CR-3 containment building.
2. Test samples of the concrete removed from the CR-3 containment
building for composition and compare the test results to a sample of
concrete from a similarly designed facility.
3. Keep the CR-3 in cold shutdown mode until such time as the
licensee can demonstrate full compliance with its NRC operating license
for CR-3 within the safety margins delineated in the licensee's final
safety analysis report (FSAR) and within the CR-3 site-specific
technical specifications.
4. Provide the public with an opportunity to intervene at a public
hearing before the NRC's Atomic Safety and Licensing Board to challenge
any certification made by the licensee to the NRC that it has
reestablished full regulatory compliance.
The petition of December 5, 2009, provided the following basis for
CR-3 remaining in cold shutdown, as summarized below:
1. The licensee has not determined the root cause of the
separation.
2. No method of non-destructive or destructive testing is
sufficient to satisfy the FSAR requirements.
3. The removal of the top 10 inches of concrete of the entire
containment outer wall would allow for proper visual inspection.
4. The removal of the top 10 inches of concrete of the entire
containment outer wall would ensure the best adhesion of the new
concrete pour to the existing inner wall.
5. The licensee's FSAR requires that the CR-3 containment building
be comprised of a monolithic concrete perimeter wall. The only way the
licensee can fully achieve compliance with its FSAR is to remove 10
inches of concrete from the entire outer wall for proper visual inspect
and repair activities.
On January 7, 2010, the petitioner participated in a teleconference
with the staff's petition review board. The meeting gave the petitioner
an opportunity to provide additional information and to clarify issues
raised in the petition. The information provided during this
teleconference was considered a supplement to the December 9, 2009,
petition.
On August 6, 2010, the petitioner sent in an additional petition
related to the original December 5, 2009, petition; however, it was not
accepted for review under Section 2.206 of Title 10 of the Code of
Federal Regulations (10 CFR) process. By letter dated September 3, 2010
(ADAMS Accession No. ML102290577), the NRC informed the petitioner that
the August 6, 2010, petition would be considered a supplement to the
December 5, 2009, petition.
The NRC sent a copy of the proposed director's decision to the
petitioner and to Duke Energy Florida, Inc., for comment on January 24,
2014. The staff did not receive any comments on the proposed director's
decision.
The Director of NRR has determined that the request, to require CR-
3 to remain in cold shutdown mode, is moot and no action will be taken.
The reasons for this decision are explained in the director's decision
14-03, pursuant to 10 CFR 2.206, the complete text of which is
available in ADAMS under Accession No. ML14097A185.
The NRC will take no action on the request to require CR-3 to
remain in cold shutdown because on February 20, 2013 (ADAMS Accession
No. ML13056A005), the licensee provided the certification required by
10 CFR 50.82(a)(1)(i) and (ii) to the NRC staff that CR-3 had
permanently ceased power operations and that all fuel had been
permanently removed from the reactor vessel. Upon docketing of these
two certifications, the licensee's 10 CFR Part 50 license no longer
authorized operation of the CR-3 reactor or emplacement or retention of
fuel into the reactor vessel. Accordingly, the licensee is prohibited
by regulation from restarting CR-3 or loading fuel into the reactor
vessel. Because the licensee is no longer authorized to operate the
reactor, CR-3 may not enter a mode of operation that requires the
containment to be in an operable condition.
A copy of the director's decision will be filed with the Secretary
of the Commission for the Commission's review in accordance with 10 CFR
2.206 of the Commission's regulations. As provided for by this
regulation, the director's decision will constitute the final action of
the Commission 25 days after the date of the decision, unless the
Commission, on its own motion, institutes a review of the director's
decision in that time.
Dated at Rockville, Maryland, this 6th day of May 2014.
For the Nuclear Regulatory Commission.
Jennifer L. Uhle,
Deputy Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2014-11231 Filed 5-14-14; 8:45 am]
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