Federal Register / Vol. 83, No. 243 / Wednesday, December 19, 2018 / Rules and Regulations 65077 

Reorganization Act of 1974, sec. 201 (42 

U.S.C. 5841); 44 U.S.C. 3504 note. 

Subpart A also issued under 31 U.S.C. 

9701. 

Subpart B also issued under 5 U.S.C. 552a. 

Subpart C also issued under 5 U.S.C. 552b. 

■ 2. In § 9.37, revise paragraphs (a) and 

(b) to read as follows: 

§ 9.37 Fees for search and review of 

agency records by NRC personnel. 

* * * * * 

(a) Clerical search and review at a 

salary rate that is equivalent to a GG–9/ 

step 7, plus 16 percent fringe benefits; 

(b) Professional/managerial search 

and review at a salary rate that is 

equivalent to a GG–14/step 7, plus 16 

percent fringe benefits; and 

* * * * * 

Dated at Rockville, Maryland, this 3rd day 

of December 2018. 

For the Nuclear Regulatory Commission. 

Margaret M. Doane, 

Executive Director for Operations. 

[FR Doc. 2018–27434 Filed 12–18–18; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

10 CFR Part 72 

[NRC–2018–0075] 

RIN 3150–AK12 

List of Approved Spent Fuel Storage 

Casks: NAC International NAC–UMS®

Universal Storage System, Certificate 

of Compliance No. 1015, Amendment 

No. 6 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Direct final rule; confirmation of 

effective date. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is confirming the 

effective date of January 7, 2019, for the 

direct final rule that was published in 

the Federal Register on October 22, 

2018. This direct final rule amends the 

NRC’s spent fuel storage regulations by 

revising the NAC International NAC– 

UMS® listing within the ‘‘List of 

approved spent fuel storage casks’’ to 

include Amendment No. 6 to Certificate 

of Compliance No. 1015. Amendment 

No. 6 revises the technical 

specifications of the certificate of 

compliance to: Remove a redundant 

requirement for inspection of the 

concrete cask and canister; revise a 

limiting condition of operation for heat 

removal to clarify that ‘‘LCO not met’’ 

means that the concrete heat removal 

system is inoperable; remove an 

inspection requirement that is already 

covered by limiting condition of 

operation surveillance requirements for 

off-normal, accident, or natural 

phenomenon events; and clarify that 

‘‘immediate’’ restoration of a concrete 

cask’s heat removal capabilities means 

‘‘within the design-basis time limit’’ in 

Section 11.2.13 of the final safety 

analysis report, ‘‘or within the time 

limit for a less than design-basis heat 

load case, as evaluated.’’ Amendment 

No. 6 also clarifies that a limiting 

condition of operation for loaded cask 

surface dose rates applies prior to 

storage conditions, when dose rates will 

be highest. 

DATES: Effective date: The effective date 

of January 7, 2019, for the direct final 

rule published October 22, 2018 (83 FR 

53159), is confirmed. 

ADDRESSES: Please refer to Docket ID 

NRC–2018–0075 when contacting the 

NRC about the availability of 

information for this action. You may 

obtain publicly-available information 

related to this action by any of the 

following methods: 

• Federal Rulemaking Website: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2018–0075. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individuals listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publiclyavailable documents online in the 

ADAMS Public Documents collection at 

http://www.nrc.gov/reading-rm/ 

adams.html. To begin the search, 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 proposed amendment to 

the certificate, the proposed Appendices 

A and B to the technical specifications, 

and preliminary safety evaluation report 

are available in ADAMS under 

Accession No. ML18088A169. The final 

amendment to the certificate, final 

appendices to the technical 

specifications, and final safety 

evaluation report can also be viewed in 

ADAMS under Accession No. 

ML18333A232. 

• 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: 

Bernard H. White, Office of Nuclear 

Material Safety and Safeguards; 

telephone: 301–415–6577; email: 

Bernard.White@nrc.gov or Robert D. 

MacDougall, Office of Nuclear Material 

Safety and Safeguards; telephone: 301– 

415–5175; email: Robert.MacDougall@

nrc.gov. Both are staff of the U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

SUPPLEMENTARY INFORMATION: On 

October 22, 2018 (83 FR 53159), the 

NRC published a direct final rule 

amending its regulations in part 72 of 

title 10 of the Code of Federal 

Regulations by revising the NAC 

International NAC–UMS® listing within 

the ‘‘List of approved spent fuel storage 

casks’’ to include Amendment No. 6 to 

Certificate of Compliance No. 1015. 

Amendment No. 6 revises the technical 

specifications of the certificate of 

compliance to: Remove a redundant 

requirement for inspection of the 

concrete cask and canister; revise a 

limiting condition of operation for heat 

removal to clarify that ‘‘LCO not met’’ 

means that the concrete heat removal 

system is inoperable; remove an 

inspection requirement that is already 

covered by limiting condition of 

operation surveillance requirements for 

off-normal, accident, or natural 

phenomenon events; and clarify that 

‘‘immediate’’ restoration of a concrete 

cask’s heat removal capabilities means 

‘‘within the design-basis time limit’’ in 

Section 11.2.13 of the final safety 

analysis report, ‘‘or within the time 

limit for a less than design-basis heat 

load case, as evaluated.’’ Amendment 

No. 6 also clarifies that a limiting 

condition of operation for loaded cask 

surface dose rates applies prior to 

storage conditions, when dose rates will 

be highest. In the direct final rule, the 

NRC stated that if no significant adverse 

comments were received, the direct 

final rule would become effective on 

January 7, 2019. The NRC did not 

receive any comments on the direct 

final rule. Therefore, this direct final 

rule will become effective as scheduled. 

Dated at Rockville, Maryland, this 13th day 

of December 2018. 

For the Nuclear Regulatory Commission. 

Cindy K. Bladey, 

Chief, Regulatory Analysis and Rulemaking 

Support Branch, Division of Rulemaking, 

Office of Nuclear Material Safety and 

Safeguards. 

[FR Doc. 2018–27436 Filed 12–18–18; 8:45 am] 

BILLING CODE 7590–01–P 


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