[Federal Register Volume 81, Number 180 (Friday, September 16, 2016)]
[Notices]
[Pages 63810-63811]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-22380]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-247 and 50-286; NRC-2016-0197]
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating
Unit Nos. 2 and 3
AGENCY: Nuclear Regulatory Commission.
ACTION: 10 CFR 2.206 request; receipt.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is giving notice
that by petition dated June 30, 2016, Mr. David A. Lochbaum of the
Union of Concerned Scientists (the petitioner) requested that the NRC
take action with regard to Indian Point Nuclear Generating Unit Nos. 2
and 3. The petitioner's requests are included in the SUPPLEMENTARY
INFORMATION section of this document.
ADDRESSES: Please refer to Docket ID NRC-2016-0197 when contacting the
NRC about the availability of information regarding this document. You
may obtain 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-2016-0197. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected].
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 email to [email protected]. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document.
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.
SUPPLEMENTARY INFORMATION: On June 30, 2016, the petitioner requested
that the NRC take action with regard to Indian Point Nuclear Generating
Unit Nos. 2 and 3 (ADAMS Accession No. ML16187A186). The petitioner
requested that the NRC take the following enforcement actions:
[[Page 63811]]
1. Issue an Order requiring the Indian Point licensee to inspect
the reactor vessel baffle-former bolts and to install the downflow to
upflow modification on Unit 2 during its next refueling outage;
2. Issue a Demand for Information requiring the Indian Point
licensee to submit an operability determination to the agency regarding
continued operation of Unit 3 until its reactor vessel baffle-former
bolts can be inspected per Material Reliability Project-227-A; and
3. Issue a Demand for Information requiring the Indian Point
licensee to submit an evaluation of the performance, role and operating
experience of the metal impact monitoring system in detecting and
responding to indications of loose parts (such as broken baffle bolts)
within the reactor coolant system.
As the basis for this request, the petitioner cited Licensee Event
Report 2016-004-00 ``Unanalyzed Condition due to Degraded Reactor
Baffle-Former Bolts,'' submitted by the licensee on May 31, 2016 (ADAMS
Accession No. ML16159A219) that describes an event where there was an
unanalyzed condition due to degraded reactor vessel baffle-former bolts
at Indian Point Unit 2, which is reportable under Sec.
50.73(a)(2)(ii)(B) of title 10 of the Code of Federal Regulations (10
CFR). Furthermore, the petitioner states that (1) an order is the
proper means for ensuring that the bolts are inspected and that the
downflow to upflow modification is installed during the next refueling
outage at Indian Point Unit 2; (2) Indian Point Unit 3 is potentially
operating with degraded baffle-former bolts and an operability
determination is the mechanism established by the NRC to properly
evaluate situations such as this; and (3) the metal impact monitoring
system as described in the Updated Final Safety Analysis Report, has
the potential to act as an alternate monitoring system to identify
degraded baffle-former bolts, yet neither the NRC nor the licensee have
referred to this system in publicly available documents relating to
this issue.
The request is being treated pursuant to Section 2.206 of Title 10
of the Code of Federal Regulations (10 CFR) 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. The petitioner met with the Petition Review Board on July 28,
2016, to discuss the petition; the transcript of that meeting is an
additional supplement to the petition (ADAMS Accession No.
ML16215A391).
Dated at Rockville, Maryland, this 7th day of September 2016.
For the Nuclear Regulatory Commission.
William M. Dean,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2016-22380 Filed 9-15-16; 8:45 am]
BILLING CODE 7590-01-P