76404 Federal Register / Vol. 79, No. 245 / Monday, December 22, 2014 / Notices 

effort; and whether financially 

supported by NSF. 

AUTHORITY FOR MAINTENANCE OF THE SYSTEM: 

42 U.S.C. 1870 and 44 U.S.C. 3101. 

PURPOSE(S) OF THE SYSTEM: 

Supplements other information 

gathered via project reporting on 

projects funded by NSF. The primary 

purpose is to enable NSF to identify 

outcomes of projects funded under NSF 

awards for management, evaluation, and 

for reporting. Information on 

participants will normally be 

aggregated, usually statistically, to 

identify outcomes of NSF programs. On 

occasion non-sensitive information 

might be used to identify persons who 

have achieved distinction in science, 

engineering, education, or the like (for 

example, by award of a prize) as 

beneficiaries of NSF support. 

The information in the system may 

also be used secondarily for compatible 

purposes including to: 

(1) Identify scientists, engineers, or 

educators who may be interested in 

applying for support, in attending a 

scientific or similar meeting, in 

applying for a position, or in taking 

advantage of some similar opportunity; 

(2) Identify possible candidates to 

serve as reviewers in the peer review 

system or for inclusion on a panel or 

advisory committee (information from 

this system may be entered in the NSF’s 

reviewer databases, NSF–51 and NSF– 

54, for this purpose). 

ROUTINE USES OF RECORDS MAINTAINED IN THE

SYSTEM, INCLUDING CATEGORIES OF USERS AND

THE PURPOSES OF SUCH USES: 

NSF standard routine uses apply. In 

addition, information may be disclosed 

to: 

(1) A government agency so that it can 

identify and contact persons who might 

be interested in a scientific, technical, or 

educational program, meeting, vacancy, 

or similar opportunity. 

(2) Other government agencies or 

other entities as part of a joint 

application review process, or in order 

to coordinate programs or policy. 

(3) Other entities when merging 

records with other computer files to 

carry out statistical studies for or 

otherwise assist NSF with program 

management, evaluation, or reporting. 

Disclosure may be made for this 

purpose to NSF contractors and 

collaborating researchers, and other 

government agencies and qualified 

research institutions and their staffs. 

Disclosures are made only after scrutiny 

of research protocols and with 

appropriate controls. The results of such 

studies are statistical in nature and do 

not identify individuals. 

(4) Contractors, grantees, volunteers, 

experts, consultants, advisors, and other 

individuals who perform a service to or 

work on or under a contract, grant, 

cooperative agreement, advisory 

committee, committee of visitors, or 

other arrangement with or for the 

Federal government, as necessary to 

carry out their duties in pursuit of the 

purposes described above. The 

contractors are subject to the provisions 

of the Privacy Act. 

POLICIES AND PRACTICES FOR STORING, 

RETRIEVING, ACCESSING, RETAINING, AND

DISPOSING OF RECORDS IN THE SYSTEM: 

STORAGE: 

Records are stored on electronic 

digital media. 

RETRIEVABILITY: 

Records are retrieved by a 

participant’s name. 

SAFEGUARDS: 

Records are protected by 

administrative, technical, and physical 

safeguards administered by NSF. 

RETENTION AND DISPOSAL: 

Records are maintained and disposed 

of in accordance with NARA approved 

record schedules. Participant records 

follow the records retention schedule 

for awarded proposals. See SORN NSF– 

50. 

SYSTEM MANAGER(S) AND ADDRESS: 

Director/Head or designee of the 

particular Division or Office 

maintaining such records at NSF 

headquarters, Virginia. 

NOTIFICATION PROCEDURE: 

Follow the Requesting Access to 

Records procedures found at 45 CFR 

part 613. 

RECORD ACCESS PROCEDURES: 

Follow the Requesting Access to 

Records procedures found at 45 CFR 

part 613. 

CONTESTING RECORD PROCEDURES: 

Follow the procedures found at 45 

CFR part 613. 

RECORD SOURCE CATEGORIES: 

An individual participant’s name, the 

identity of any project on which the 

participant worked, and information on 

the nature and extent of the individual’s 

involvement, level of effort, and NSF 

support is provided by the PI/grantee 

through project reporting. Demographic 

data is supplied by the individual 

participant on a voluntary basis. The 

individual participant may report ‘‘Do 

not wish to Provide.’’ 

EXEMPTIONS CLAIMED FOR THE SYSTEM: 

None. 

[FR Doc. 2014–29760 Filed 12–19–14; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–295, 50–304, and 72–1037; 

NRC–2014–0199] 

ZionSolutions, LLC.; Zion Nuclear 

Power Station, Units 1 and 2; 

Independent Spent Fuel Storage 

Installation 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemption; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing an 

exemption in response to a request 

submitted by ZionSolutions on June 25, 

2014, for its general license to operate 

an independent spent fuel storage 

installation (ISFSI) at the Zion Nuclear 

Power Station (ZNPS). The exemption 

would permit ZionSolutions to load 

NAC International, Inc. (NAC), Modular 

Advanced Generation Nuclear Allpurpose Storage (MAGNASTOR®) casks 

(Certificate of Compliance (CoC) No. 

1031) in a manner different than 

permitted by any amendment to the 

MAGNASTOR® CoC. ZionSolutions is 

currently loading MAGNASTOR®

storage casks and maintains that relief 

from requirements provides flexibility 

in operations, minimizes equipment 

runtime and repair, and minimizes 

personnel dose. 

DATES: Notice of issuance of exemption 

given on December 22, 2014. 

ADDRESSES: Please refer to Docket ID 

NRC–2014–0199 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–2014–0199. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–287–3422; 

email: Carol.Gallagher@nrc.gov. 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 publiclyavailable documents online in the 

ADAMS Public Documents collection at 

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

adams.html. To begin the search, select 


tkelley on DSK3SPTVN1PROD with NOTICES
Federal Register / Vol. 79, No. 245 / Monday, December 22, 2014 / Notices 76405 

‘‘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. For the 

convenience of the reader, the ADAMS 

accession numbers are provided in a 

table in the ‘‘Availability of Documents’’ 

section of this document. Some 

documents referenced are located in the 

NRC’s ADAMS Legacy Library. To 

obtain these documents, contact the 

NRC’s PDR for assistance. 

• 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 White, Office of Nuclear 

Material Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington DC 20555–0001; telephone: 

301–287–0810; email: Bernard.White@

nrc.gov. 

I. Background 

In February 1998, ZNPS, Units 1 and 

2, were permanently shut down. On 

February 13, 1998, Commonwealth 

Edison Company, the ZNPS licensee at 

that time, submitted a letter certifying 

the permanent cessation of operations at 

ZNPS, Units 1 and 2. On March 9, 1998, 

Commonwealth Edison Company 

submitted a letter certifying the 

permanent removal of fuel from the 

reactor vessels at ZNPS. On May 4, 

2009, the NRC issued the order to 

transfer the ownership of the 

permanently shut down ZNPS facility, 

and responsibility for its 

decommissioning to ZionSolutions. This 

transfer was effectuated on September 1, 

2010. ZionSolutions was established 

solely for the purpose of acquiring and 

decommissioning the ZNPS facility for 

release for unrestricted use, while 

transferring the spent nuclear fuel and 

Greater-Than-Class C radioactive waste 

to the ZNPS ISFSI. ZionSolutions holds 

Facility Operating License Nos. DPR–39 

and DPR–48, which authorize 

possession of spent fuel from the 

operation of ZNPS, Units 1 and 2, in 

Zion, Illinois, pursuant to Part 50 of 

Title 10 of the Code of Federal 

Regulations (10 CFR). The licenses 

provide, among other things, that the 

facility must comply with all applicable 

NRC requirements. 

Consistent with 10 CFR part 72, 

subpart K, a general license is issued for 

the storage of spent fuel in an ISFSI at 

power reactor sites to persons 

authorized to possess or operate nuclear 

power reactors under 10 CFR part 50. 

ZionSolutions is currently authorized to 

store spent fuel at the ZNPS ISFSI under 

the 10 CFR part 72 general license 

provisions. 

The conditions of the 10 CFR part 72 

general license, specifically 10 CFR 

72.212(a)(2), 72.212(b)(3), 

72.212(b)(5)(i), and 72.212(b)(11), 

require a general licensee to store spent 

fuel in an approved spent fuel storage 

cask listed in 10 CFR 72.214, and to 

comply with the conditions specified in 

the cask’s CoC. The ZNPS ISFSI is 

currently loading and storing spent fuel 

in MAGNASTOR® storage casks, 

approved by the NRC under CoC No. 

1031, Amendment No. 3. 

The MAGNASTOR® system provides 

for the vertical dry storage of spent fuel 

assemblies in a welded transportable 

storage canister (TSC). The storage 

system components for MAGNASTOR®

consist of a vertical concrete cask (VCC), 

a TSC with an internal basket assembly 

that holds the spent fuel assemblies, and 

a transfer cask, which contains the TSC 

during loading, transfer, and unloading 

operations. The VCC is constructed of 

reinforced concrete designed to 

withstand all normal condition loads, as 

well as abnormal condition loads 

created by natural phenomena such as 

earthquakes and tornados. The storage 

system is also designed to withstand 

design-basis accident conditions. 

II. Request/Action 

By letter dated June 25, 2014, 

ZionSolutions submitted a request for 

exemptions from specific portions of the 

requirements of 10 CFR 72.212, 

‘‘Conditions of general license issued 

under § 72.210,’’ specifically 10 CFR 

72.212(a)(2), 72.212(b)(3), 

72.212(b)(5)(i), 72.212(b)(11), and 10 

CFR 72.214, ‘‘List of approved spent 

fuel storage casks.’’ Specifically, 

ZionSolutions has requested an 

exemption from the requirements of 

limiting condition of operation (LCO) 

3.1.1, Section 1, Table A, of the 

technical specification (TS), regarding 

allowed transfer time from loading of a 

TSC inside the MAGNASTOR® transfer 

cask to placement into the VCC 

following the completion of helium 

backfill. ZionSolutions must connect the 

TSC to the annulus cooling water 

system (ACWS) for a certain minimum 

period prior to attempting the transfer. 

The length of time the TSC is connected 

to the ACWS prior to the transfer 

determines the maximum time 

ZionSolutions has to successfully 

complete the transfer to the VCC. 

Currently, ZionSolutions connects the 

TSC to the ACWS for 8 hours, which 

then affords a maximum of 8 hours to 

complete the transfer. ZionSolutions 

could increase the maximum transfer 

time to 48 hours by TSC connected to 

the ACWS for an additional 24 hours. 

However, the proposed exemption 

would modify the allowable transfer 

time for pressurized-water reactor 

(PWR) spent fuel after helium backfill 

from a maximum of 8 hours to 600 

hours for the movement of a TSC, with 

heat load ≤20 kW, from the 

decontamination pit into the VCC. In its 

request, ZionSolutions explained that 

this exemption will reduce maintenance 

and delays, and potentially reduce the 

dose received by workers during the 

transfer. If granted, ZionSolutions 

intends to use this exemption for the 

remainder of a loading campaign that 

began in January 2014. 

The NRC has the authority to grant 

specific exemptions from these 

requirements under 10 CFR 72.7 if the 

exemption is authorized by law and will 

not endanger life or property or the 

common defense and security and the 

exemption is otherwise in the public 

interest. For the reasons described 

below, the NRC is granting an 

exemption to ZionSolutions. This 

exemption is valid until March 31, 

2015. 

III. Discussion 

Pursuant to 10 CFR 72.7, the 

Commission may, upon application by 

any interested person or upon its own 

initiative, grant exemptions from the 

requirements of 10 CFR part 72 when 

the exemptions are authorized by law, 

will not endanger life or property or the 

common defense and security, and is 

otherwise in the public interest. 

A. Authorized by Law 

The Commission issued 10 CFR 72.7 

under the authority granted to it under 

Section 133 of the Nuclear Waste Policy 

Act of 1982, as amended, 42 U.S.C. 

10153. Section 72.7 allows the NRC to 

grant exemptions from the requirements 

of 10 CFR part 72 if the exemption is 

authorized by law, will not endanger 

life or property or the common defense 

and security, and is otherwise in the 

public interest. As explained below, the 

proposed exemption will not endanger 

life or property, or the common defense 

and security, and is otherwise in the 

public interest. The ISFSI regulations 

cited in this exemption request are 10 

CFR 72.212(a)(2), 72.212(b)(3), 

72.212(b)(5)(i), 72.212(b)(11), and 10 

CFR 72.214. The Commission has the 

legal authority to issue exemptions from 

the requirements of Part 72 as provided 

in 10 CFR 72.7. Issuance of this 

exemption is consistent with the Atomic 

Energy Act of 1954, as amended, and 

not otherwise inconsistent with NRC 


tkelley on DSK3SPTVN1PROD with NOTICES
76406 Federal Register / Vol. 79, No. 245 / Monday, December 22, 2014 / Notices 

1While the Amendment No. 4 application 

includes the addition of increased transfer time, the 

application also includes other changes not at issue 

in this exemption. 

regulations or other applicable laws. 

Therefore, issuance of the exemption is 

authorized by law. 

B. The Exemption Will Not Endanger 

Life or Property or the Common Defense 

and Security 

In its exemption request, 

ZionSolutions referred to analyses 

performed by the cask vendor, NAC, in 

support of ZionSolutions’ request.1

Approval of this exemption request 

will allow ZionSolutions to utilize a 

longer transfer time to place the canister 

in a VCC, may reduce operational dose 

associated with a shorter transfer time, 

in the event the licensee is unable to 

complete the transfer in the maximum 

8-hour period allowed under the terms 

of the MAGNASTOR CoC. If the 

exemption is not granted and 

ZionSolutions is unable to conclude the 

transfer within the 8 hours, it would 

have to reconnect the TSC to ACWS 

within the 8 hour transfer time. 

Alternately, ZionSolutions can connect 

the TSC to the ACWS for an additional 

24 hours prior to transfer to be allowed 

more time for the transfer. The 

additional cooling time extends the 

permitted maximum time for the 

transfer from 8 hours to 48 hours, per 

Table B of LCO 3.1.1. Granting 

ZionSolutions’ exemption to use the 

longer transfer time may reduce dose to 

the operators, which conforms to the 

NRC’s as low as reasonably achievable 

(ALARA) requirements. 

As discussed below, the NRC staff 

finds that ZionSolutions’ proposal to 

increase its transfer time after helium 

backfill from 8 to 600 hours for heat 

loads ≤20 kW is acceptable for PWR 

spent fuel and will not endanger life or 

property or common defense and 

security. The thermal evaluation for the 

increased transfer time was evaluated 

using guidance in NUREG–1536, 

‘‘Standard Review Plan for Spent Fuel 

Dry Storage Systems at a General 

License Facility, Rev. 1.’’ 

Safety Evaluation: ZionSolutions 

proposed to increase the maximum 

transfer time for the TSC specified in 

LCO 3.1.1, Section 1, Table A, of the TS 

from 8 to 600 hours for decay heat loads 

less than 20 kW. 

The cask vendor, NAC, performed a 

steady state analysis for the TSC located 

in the transfer cask, which had no 

additional cooling, and calculated a 

peak cladding temperature of 653 °F for 

the ≤20 kW PWR heat load condition. 

The analysis by NAC shows that the 

peak cladding temperature during the 

extended transfer times proposed by 

ZionSolutions is below the limit of 

752 °F by a significant margin (∼100 °F). 

As discussed below, because the peak 

cladding temperature during the 

extended transfer times proposed by 

ZionSolutions will remain below the 

limit of 752 °F, the NRC staff concludes 

that the additional cooling is not 

required for loading heat loads ≤20 kW 

at ZNPS. 

As part of its review of ZionSolutions’ 

exemption request, the NRC staff 

referred to NAC’s modeling methods, 

initial conditions, and boundary 

conditions and determined the analyses 

show that the extended transfer times 

requested by ZionSolutions are 

acceptable. First, the NRC staff 

determined that the mesh discretization 

used in the model is acceptable to 

support this exemption because it does 

not significantly change the results from 

the prior model for laminar flows inside 

the canister and in the annulus between 

the canister and transfer cask inner 

shell. Second, the NRC staff determined 

that the flow resistance factor, used to 

model fluid flow through the 14x14 

PWR fuel assembly as a porous media, 

is acceptable because it conforms to 

known thermal-hydraulic measurements 

on a PWR fuel assembly. The analysis 

is also acceptable to support this 

exemption because the methodology 

used is the same as the methodology 

used in the thermal evaluation for the 

initial issuance of CoC No. 1031, which 

the NRC staff had previously found to 

be acceptable. Finally, the NRC staff has 

determined that the analysis is 

acceptable to support this exemption 

because the results of the calculation 

show that the fuel temperatures will 

remain below the fuel temperature limit 

of 752 °F, as specified in NUREG–1536, 

Rev. 1, ‘‘Standard Review Plan for Dry 

Cask Storage Systems,’’ and Interim 

Staff Guidance No. 11, Rev. 3, 

‘‘Cladding Considerations for the 

Transportation and Storage of Spent 

Fuel.’’ Therefore, the NRC staff 

concludes that ZionSolutions will meet 

the requirements of Part 72 while 

operating with this exemption. 

Security Evaluation: Modification of 

the transfer time when a canister’s 

thermal output is ≤20 kW for PWR spent 

fuel does not affect the ISFSI security 

plans. Accordingly, the ZNPS ISFSI will 

continue to be physically protected 

under ZionSolutions’ ISFSI Physical 

Security Plan to the same level of 

security. Additionally, the changes do 

not affect the confinement barriers of 

the canisters or affect the integrity of the 

spent nuclear fuel. Therefore, 

confinement of the spent fuel stored at 

the ISFSI facility is not affected. 

As discussed above, the safety and 

security requirements associated with 

transferring the loaded TSC in a transfer 

cask to a VCC at the ZNPS ISFSI will 

continue to be met if the exemption is 

granted. Therefore, issuance of the 

exemption will not endanger life or 

property or the common defense and 

security. 

C. The Exemption Is Otherwise in the 

Public Interest 

ZionSolutions stated that adoption of 

the revised transfer times as proposed 

will maintain doses ALARA by ensuring 

that the time needed to prepare the 

canister for storage is minimized. Based 

on its review of ZionSolutions’ request, 

the NRC staff concludes that allowing 

the use of the extended maximum 

transfer time reduces time constraints 

during transfer operations on operators 

and thereby reduces dose to ZNPS 

operators for the following reasons. 

If the operator is unable to conclude 

the activity within 8 hours due to 

operational delays or complications, 

ZionSolutions stated that it reconnects 

the MAGNASTOR transfer cask to 

annulus cooling water system (ACWS) 

within the 8 hour transfer time. 

ZionSolutions’ exemption request 

indicated that operators include a 2- 

hour buffer in the transfer time to 

account for the possibility that the 

transfer cask will need to be 

reconnected to the ACWS. As a result, 

the transfer time available to the 

operator is limited to approximately 6 

hours. Performing the ACWS 

reconnection increases dose to the 

operators and, as discussed above, the 

NRC staff has concluded that 

successfully completing the transfer 

within 600 hours is sufficient to provide 

adequate protection of the public health 

and safety. 

To avoid the 8 hour transfer time 

limitation, ZionSolutions could use an 

alternative procedure that allows a 48 

hour limit (LCO 3.1.1, Table B ‘‘PWR 

with Maximum TSC Backfill’’). That 

alternate procedure requires the TSC to 

remain connected to the ACWS for an 

additional 24 hours prior to attempting 

the transfer. This alternate procedure is 

likely to be used to avoid needing to 

make multiple transfer attempts to 

account for operational delays or 

complications. However, that alternate 

procedure results in an additional 17 

hours of operating time, per individual 

cask loading, and would include 

additional dose to personnel, increase 

equipment wear, and increase the risk of 

equipment failure during extended 

operation. The resulting system’s lack of 


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Federal Register / Vol. 79, No. 245 / Monday, December 22, 2014 / Notices 76407 

availability would also impact 

operations. The additional operational 

period is specifically a concern for the 

ZionSolutions fuel loading campaign, 

which involves 61 casks, because up to 

43 days will be added to the transfer 

duration if the alternate procedure is 

adopted for all 61 casks. Based on the 

NRC staff’s evaluation of the extended 

transfer times proposed by 

ZionSolutions, the NRC staff determines 

that those procedures are not necessary 

to meet the requirements of Part 72 

because even without the alternate 

procedures the fuel temperature will 

remain below the temperature limit in 

NUREG–1536 and ISG–11 which limits 

fuel degradation and ensures ready 

retrievability as required in 10 CFR 

72.122(h) and (l). 

Given the potential avoidance of 

additional radiological exposure to 

workers during the cask loading 

campaign, issuance of the exemption is 

in the public interest. 

D. Environmental Considerations 

The NRC staff also considered 

whether there would be any significant 

environmental impacts associated with 

the exemption. For this proposed action, 

the NRC staff performed an 

environmental assessment pursuant to 

10 CFR 51.30. The environmental 

assessment concluded that the proposed 

action would not significantly impact 

the quality of the human environment. 

The NRC staff concluded that the 

proposed action will not result in any 

changes in the types or amounts of any 

radiological or non-radiological 

effluents that may be released offsite, 

and there is no significant increase in 

occupational or public radiation 

exposure because of the proposed 

action. The Environmental Assessment 

and the Finding of No Significant 

Impact was published on October 16, 

2014 (79 FR 62211). 

IV. Conclusions 

Accordingly, the NRC has determined 

that, pursuant to 10 CFR 72.7, this 

exemption is authorized by law, will not 

endanger life or property or the common 

defense and security, and is otherwise 

in the public interest. Therefore, the 

Commission hereby grants 

ZionSolutions an exemption from 10 

CFR part 72.212(a)(2), 72.212(b)(3), 

72.212(b)(5)(i), 72.212(b)(11) and 

72.214, which states that the licensee 

shall comply with the terms, conditions, 

and specifications of the CoC only with 

regard to LCO 3.1.1, Section 1, Table A, 

of TS to MAGNASTOR® CoC No. 1031, 

Amendment No. 3, to change the time 

allowed after helium backfill from 8 

hours to 600 hours for transferring a 

canister containing ≤20 kW of decay 

heat load from decontamination pit to a 

VCC. This exemption approval is only 

valid for authorizing a longer transfer 

time up to 600 hours for canisters with 

a decay heat load ≤20 kW at the 

ZionSolutions Nuclear Station ISFSI 

until March 31, 2015. 

V. Availability of Documents 

The documents identified in the 

following table are available to 

interested persons in ADAMS. For 

information on accessing ADAMS see 

the ADDRESSES section of this document. 

Document ADAMS Accession No. 

Commonwealth Edison Company letter certifying the permanent cessation of operations at ZNPS, Units 1 

and 2.

9802200407 (Legacy Library). 

Commonwealth Edison Company letter certifying the permanent removal of fuel from the reactor vessels at 

ZNPS.

9803110251 (Legacy Library). 

NRC order and conforming amendments transferring ownership of ZNPS facility ........................................... ML090930037. 

Letter issuing conforming amendments relating to transfer of licenses for ZNPS ............................................ ML102290437. 

Zion exemption request ..................................................................................................................................... ML14182A474. 

NAC amendment request No. 4 to change LCO 3.1.1, Section 1, Table A ..................................................... ML13171A031. 

NAC MAGANSTOR Amendment 4 response to NRC request for supplemental information .......................... ML13261A278. 

NAC MAGANSTOR final safety analysis report, Revision 13C ........................................................................ ML13268A050. 

NAC supplement to correct TS error associated with additional cooling times for fuel assemblies containing 

control elements.

ML14170A070. 

NAC supplement to correct typographical error in boron density in TS ........................................................... ML14170A022. 

NAC request to have Amendment 3 to CoC 1031 be the basis for Amendment 4 instead of Amendment 2 ML14199A501. 

NUREG–1536, Rev. 1, ‘‘Standard Review Plan for Dry Cask Storage Systems,’’ dated July 2010 ................ ML101040620. 

Interim Staff Guidance No. 11, Rev. 3, ‘‘Cladding Considerations for the Transportation and Storage of 

Spent Fuel’’.

ML033230244. 

Initial issuance of Certificate of Compliance No. 1031 ...................................................................................... ML090350509. 

The exemption is effective upon 

issuance. 

Dated at Rockville, Maryland, this 11th day 

of December, 2014. 

For the Nuclear Regulatory Commission. 

Anthony H. Hsia, 

Deputy Director, Division of Spent Fuel 

Management, Office of Nuclear Material 

Safety and Safeguards. 

[FR Doc. 2014–29889 Filed 12–19–14; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2014–0001] 

Sunshine Act Meeting Notice 

DATE: December 15, 22, 29, 2014; 

January 5, 12, 19, 26 2015. 

PLACE: Commissioners’ Conference 

Room, 11555 Rockville Pike, Rockville, 

Maryland. 

STATUS: Public. 

Week of December 15, 2014 

Friday, December 19, 2014 

10:55 a.m. Affirmation Session (Public 

Meeting) (Tentative) 

Florida Power & Light Co. (St. Lucie 

Plant, Unit 2) (Tentative) 

* * * * * 

Week of December 22, 2014 

There are no meetings scheduled for 

the week of December 22, 2014. 

Week of December 29, 2014—Tentative 

There are no meetings scheduled for 

the week of December 29, 2014. 

Week of January 5, 2015—Tentative 

There are no meetings scheduled for 

the week of January 5, 2015. 

Week of January 12, 2015—Tentative 

There are no meetings scheduled for 

the week of January 12, 2015. 


tkelley on DSK3SPTVN1PROD with NOTICES