81 FR 63810 - Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 2 and 3

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 81, Issue 180 (September 16, 2016)

Page Range		63810-63811
FR Document		2016-22380

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.

Federal Register, Volume 81 Issue 180 (Friday, September 16, 2016)

[Federal Register Volume 81, Number 180 (Friday, September 16, 2016)]
[Notices]
[Pages 63810-63811]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2016-22380]


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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.

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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

Federal Register / Vol. 81, No. 180 / Friday, September 16, 2016 / Notices 63811

1. Issue an Order requiring the Indian additional supplement to the petition The Office of Management and Budget
Point licensee to inspect the reactor (ADAMS Accession No. ML16215A391). is particularly interested in comments
vessel baffle-former bolts and to install Dated at Rockville, Maryland, this 7th day that:
the downflow to upflow modification of September 2016. 1. Evaluate whether the proposed
on Unit 2 during its next refueling For the Nuclear Regulatory Commission. collection of information is necessary
outage; William M. Dean,
for the proper performance of functions
2. Issue a Demand for Information of OPM, including whether the
Director, Office of Nuclear Reactor
requiring the Indian Point licensee to Regulation.
information will have practical utility;
submit an operability determination to 2. Evaluate the accuracy of OPM’s
[FR Doc. 2016–22380 Filed 9–15–16; 8:45 am]
the agency regarding continued estimate of the burden of the proposed
BILLING CODE 7590–01–P
operation of Unit 3 until its reactor collection of information, including the
vessel baffle-former bolts can be validity of the methodology and
inspected per Material Reliability assumptions used;
Project–227–A; and OFFICE OF PERSONNEL 3. Enhance the quality, utility, and
3. Issue a Demand for Information MANAGEMENT clarity of the information to be
requiring the Indian Point licensee to collected; and
Submission for Review: 3206–0208,
submit an evaluation of the 4. Minimize the burden of the
Representative Payee Survey, RI 38–
performance, role and operating collection of information on those who
115
experience of the metal impact are to respond, including through the
monitoring system in detecting and AGENCY: U.S. Office of Personnel use of appropriate automated,
responding to indications of loose parts Management. electronic, mechanical, or other
(such as broken baffle bolts) within the ACTION: 60-Day Notice and request for technological collection techniques or
reactor coolant system. comments. other forms of information technology,
As the basis for this request, the e.g., permitting electronic submissions
petitioner cited Licensee Event Report SUMMARY: The Retirement Services, of responses.
2016–004–00 ‘‘Unanalyzed Condition Office of Personnel Management (OPM)
Analysis
due to Degraded Reactor Baffle-Former offers the general public and other
Bolts,’’ submitted by the licensee on Federal agencies the opportunity to Agency: Retirement Operations,
May 31, 2016 (ADAMS Accession No. comment on an extension, without Retirement Services, Office of Personnel
ML16159A219) that describes an event change, of a currently approved Management.
where there was an unanalyzed information collection request (ICR) Title: Representative Payee Survey.
condition due to degraded reactor vessel 3206–0208, Representative Payee OMB Number: 3206–0208.
baffle-former bolts at Indian Point Unit Survey. As required by the Paperwork Frequency: Annually.
2, which is reportable under Reduction Act of 1995 (Pub. L. 104–13, Affected Public: Individuals or
§ 50.73(a)(2)(ii)(B) of title 10 of the Code 44 U.S.C. chapter 35) as amended by the Households.
of Federal Regulations (10 CFR). Clinger-Cohen Act (Pub. L. 104–106), Number of Respondents: 11,000.
Furthermore, the petitioner states that OPM is soliciting comments for this Estimated Time per Respondent: 20
(1) an order is the proper means for collection. minutes.
ensuring that the bolts are inspected and Total Burden Hours: 3,667.
DATES: Comments are encouraged and
that the downflow to upflow will be accepted until November 15, U.S. Office of Personnel Management.
modification is installed during the next 2016. This process is conducted in Beth F. Cobert,
refueling outage at Indian Point Unit 2; accordance with 5 CFR 1320.1. Acting Director.
(2) Indian Point Unit 3 is potentially [FR Doc. 2016–22329 Filed 9–15–16; 8:45 am]
ADDRESSES: Interested persons are
operating with degraded baffle-former
invited to submit written comments on BILLING CODE 6325–38–P
bolts and an operability determination
the proposed information collection to
is the mechanism established by the
the U.S. Office of Personnel
NRC to properly evaluate situations
Management, Retirement Services, 1900 SECURITIES AND EXCHANGE
such as this; and (3) the metal impact
E Street NW., Room 2347E, Washington, COMMISSION
monitoring system as described in the
DC 20415, Attention: Alberta Butler, or
Updated Final Safety Analysis Report, [Release No. 34–78817; File No. SR–
sent by email to Alberta.Butler@ NYSEMKT–2016–84]
has the potential to act as an alternate
opm.gov.
monitoring system to identify degraded
baffle-former bolts, yet neither the NRC FOR FURTHER INFORMATION CONTACT: A Self-Regulatory Organizations; NYSE
nor the licensee have referred to this copy of this ICR with applicable MKT LLC; Notice of Filing and
system in publicly available documents supporting documentation, may be Immediate Effectiveness of Proposed
relating to this issue. obtained by contacting the Retirement Rule Change To Amend Rule 67—
The request is being treated pursuant Services Publications Team, Office of Equities To Modify Certain Data
to Section 2.206 of Title 10 of the Code Personnel Management, 1900 E Street Collection Requirements of the
of Federal Regulations (10 CFR) of the NW., Room 3316–L, Washington, DC Regulation NMS Plan To Implement a
Commission’s regulations. The request 20415, Attention: Cyrus S. Benson, or Tick Size Pilot Program
has been referred to the Director of the sent by email to Cyrus.Benson@opm.gov
mstockstill on DSK3G9T082PROD with NOTICES

September 12, 2016.
Office of Nuclear Reactor Regulation. As or faxed to (202) 606–0910.
Pursuant to Section 19(b)(1) 1 of the
provided by 10 CFR 2.206, appropriate SUPPLEMENTARY INFORMATION: The Securities Exchange Act of 1934 (the
action will be taken on this petition Representative Payee Survey is used to ‘‘Act’’) 2 and Rule 19b–4 thereunder,3
within a reasonable time. The petitioner collect information about how the
met with the Petition Review Board on benefits paid to a representative payee 1 15 U.S.C. 78s(b)(1).
July 28, 2016, to discuss the petition; have been used or conserved for the 2 15 U.S.C. 78a.
the transcript of that meeting is an benefit of the incompetent annuitant. 3 17 CFR 240.19b–4.

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Document Created: 2016-09-16 00:25:00
Document Modified: 2016-09-16 00:25:00

Category		Regulatory Information
Collection		Federal Register
sudoc Class		AE 2.7: GS 4.107: AE 2.106:
Publisher		Office of the Federal Register, National Archives and Records Administration
Section		Notices
Action		10 CFR 2.206 request; receipt.
FR Citation		81 FR 63810