Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 2 and 3, 63810-63811 [2016-22380]

Download as PDF mstockstill on DSK3G9T082PROD with NOTICES 63810 Federal Register / Vol. 81, No. 180 / Friday, September 16, 2016 / Notices collected will be kept strictly confidential and will be used only for research or statistical purposes. 2. Use of the Information: Results from the SED are used to assess characteristics of the doctorate population and trends in doctoral education and degrees by researchers, policy makers, universities, and government agencies. Data from the survey are published annually on the NCSES Web site in a publication series reporting on all fields of study, titled Doctorate Recipients from U.S. Universities. Information from the SED is also included in other series available online: Science and Engineering Degrees; Science and Engineering Degrees, by Race/Ethnicity of Recipients; Science and Engineering Indicators; and Women, Minorities, and Persons with Disabilities in Science and Engineering. In addition, access to tabular data from selected variables is available through WebCASPAR, an online table-generating tool on the NCSES Web site. 3. Expected Respondents: The SED is a census of all individuals receiving a research doctorate from an accredited U.S. academic institution in the academic year beginning 1 July and ending 30 June of the subsequent year. As such, the population for the 2018 SED consists of all individuals receiving a research doctorate in the 12-month period beginning 1 July 2017 and ending 30 June 2018. Likewise, the population for the 2019 SED consists of all individuals receiving a research doctorate in the 12-month period beginning 1 July 2018 and ending 30 June 2019. A research doctorate is a doctoral degree that (1) requires completion of an original intellectual contribution in the form of a dissertation or an equivalent culminating project (e.g., musical composition) and (2) is not primarily intended as a degree for the practice of a profession. The most common research doctorate degree is the Ph.D. Recipients of professional doctoral degrees only, such as MD, DDS, JD, DPharm, and PsyD, are not included in the SED. The 2018 and 2019 SED are expected to include about 580 separately reporting doctoral programs from among approximately 455 eligible research doctorate-granting institutions. 4. Estimate of Burden: A total response rate of 90% of the 55,006 persons who earned a research doctorate from a U.S. institution was obtained in academic year 2015. This level of response rate has been consistent for several years. Based on the historical trend, in 2018 approximately 58,000 individuals are expected to receive VerDate Sep<11>2014 17:55 Sep 15, 2016 Jkt 238001 research doctorates from U.S. institutions. Using the past response rate, the number of SED respondents in 2018 is estimated to be 52,200 (58,000 doctorate recipients × 0.90 response rate). Similarly, the number of individuals expected to earn research doctorates in 2019 is estimated to be about 59,000; hence, the number of respondents in 2019 is estimated to be 53,100 (59,000 × 0.90). Based on the average Web survey completion time for the 2017 SED (19 minutes) and the extension of a few questions to an additional subset of respondents, NSF estimates that, on average, 21 minutes per respondent will be required to complete the 2018 or 2019 SED questionnaire. The annual respondent burden for completing the SED is therefore estimated at 18,270 hours in 2018 (52,200 respondents × 21 minutes) and 18,585 hours in 2019 (based on 53,100 respondents). In addition to the actual questionnaire, the SED requires the collection of administrative data from participating academic institutions. The Institutional Coordinator at the institution helps distribute the Web survey link (and paper surveys when necessary), track survey completions, and submit information to the SED survey contractor. Based on focus groups conducted with Institutional Coordinators, it is estimated that the SED demands no more than 1% of the Institutional Coordinator’s time over the course of a year, which computes to 20 hours per year per Institutional Coordinator (40 hours per week × 50 weeks per year × .01). With about 580 programs expected to participate in the SED in 2018 and 2019, the estimated annual burden to Institutional Coordinators of administering the SED is 11,600 hours. Therefore, the total annual information burden for the SED is estimated to be 29,870 hours in 2018 (18,270 + 11,600) and 30,185 hours in 2019 (18,585 + 11,600). This is higher than the last annual estimate approved by OMB due to the increased number of respondents (doctorate recipients) and the increased number of survey questions being asked of each respondent. Authority: Section 3506(c)(2)(A) of the Paperwork Reduction Act of 1995 (Pub. L. 104–13) Dated: September 13, 2016. Suzanne H. Plimpton, Reports Clearance Officer, National Science Foundation. [FR Doc. 2016–22285 Filed 9–15–16; 8:45 am] BILLING CODE 7555–01–P PO 00000 Frm 00076 Fmt 4703 Sfmt 4703 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 Nuclear Regulatory Commission. ACTION: 10 CFR 2.206 request; receipt. AGENCY: 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 https://www.regulations.gov and search for Docket ID NRC–2016–0197. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://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 pdr.resource@nrc.gov. 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: SUMMARY: E:\FR\FM\16SEN1.SGM 16SEN1 mstockstill on DSK3G9T082PROD with NOTICES Federal Register / Vol. 81, No. 180 / Friday, September 16, 2016 / Notices 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 § 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 VerDate Sep<11>2014 17:55 Sep 15, 2016 Jkt 238001 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 OFFICE OF PERSONNEL MANAGEMENT Submission for Review: 3206–0208, Representative Payee Survey, RI 38– 115 U.S. Office of Personnel Management. ACTION: 60-Day Notice and request for comments. AGENCY: The Retirement Services, Office of Personnel Management (OPM) offers the general public and other Federal agencies the opportunity to comment on an extension, without change, of a currently approved information collection request (ICR) 3206–0208, Representative Payee Survey. As required by the Paperwork Reduction Act of 1995 (Pub. L. 104–13, 44 U.S.C. chapter 35) as amended by the Clinger-Cohen Act (Pub. L. 104–106), OPM is soliciting comments for this collection. SUMMARY: Comments are encouraged and will be accepted until November 15, 2016. This process is conducted in accordance with 5 CFR 1320.1. ADDRESSES: Interested persons are invited to submit written comments on the proposed information collection to the U.S. Office of Personnel Management, Retirement Services, 1900 E Street NW., Room 2347E, Washington, DC 20415, Attention: Alberta Butler, or sent by email to Alberta.Butler@ opm.gov. DATES: A copy of this ICR with applicable supporting documentation, may be obtained by contacting the Retirement Services Publications Team, Office of Personnel Management, 1900 E Street NW., Room 3316–L, Washington, DC 20415, Attention: Cyrus S. Benson, or sent by email to Cyrus.Benson@opm.gov or faxed to (202) 606–0910. SUPPLEMENTARY INFORMATION: The Representative Payee Survey is used to collect information about how the benefits paid to a representative payee have been used or conserved for the benefit of the incompetent annuitant. FOR FURTHER INFORMATION CONTACT: PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 63811 The Office of Management and Budget is particularly interested in comments that: 1. Evaluate whether the proposed collection of information is necessary for the proper performance of functions of OPM, including whether the information will have practical utility; 2. Evaluate the accuracy of OPM’s estimate of the burden of the proposed collection of information, including the validity of the methodology and assumptions used; 3. Enhance the quality, utility, and clarity of the information to be collected; and 4. Minimize the burden of the collection of information on those who are to respond, including through the use of appropriate automated, electronic, mechanical, or other technological collection techniques or other forms of information technology, e.g., permitting electronic submissions of responses. Analysis Agency: Retirement Operations, Retirement Services, Office of Personnel Management. Title: Representative Payee Survey. OMB Number: 3206–0208. Frequency: Annually. Affected Public: Individuals or Households. Number of Respondents: 11,000. Estimated Time per Respondent: 20 minutes. Total Burden Hours: 3,667. U.S. Office of Personnel Management. Beth F. Cobert, Acting Director. [FR Doc. 2016–22329 Filed 9–15–16; 8:45 am] BILLING CODE 6325–38–P SECURITIES AND EXCHANGE COMMISSION [Release No. 34–78817; File No. SR– NYSEMKT–2016–84] Self-Regulatory Organizations; NYSE MKT LLC; Notice of Filing and Immediate Effectiveness of Proposed Rule Change To Amend Rule 67— Equities To Modify Certain Data Collection Requirements of the Regulation NMS Plan To Implement a Tick Size Pilot Program September 12, 2016. Pursuant to Section 19(b)(1) 1 of the Securities Exchange Act of 1934 (the ‘‘Act’’) 2 and Rule 19b–4 thereunder,3 1 15 U.S.C. 78s(b)(1). U.S.C. 78a. 3 17 CFR 240.19b–4. 2 15 E:\FR\FM\16SEN1.SGM 16SEN1

Agencies

NUCLEAR REGULATORY COMMISSION

[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 https://www.regulations.gov and search for Docket ID NRC-2016-0197. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://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 pdr.resource@nrc.gov. 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

This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.