Federal Register / Vol. 80, No. 40 / Monday, March 2, 2015 / Notices 11233 

2. Department of Defense, National 

Reconnaissance Office; Department of 

Defense, National GeospatialIntelligence Agency; Department of 

Defense, National Security Agency (N1– 

525–13–2, 4 items, 4 temporary items). 

Routine human resources records 

associated with a multi-mission ground 

station. 

3. Department of Defense, National 

Reconnaissance Office; Department of 

Defense, National GeospatialIntelligence Agency; Department of 

Defense, National Security Agency (N1– 

525–14–2, 3 items, 3 temporary items). 

Project files and routine information 

technology records associated with a 

multi-mission ground station. 

4. Department of Defense, National 

Reconnaissance Office; Department of 

Defense, National GeospatialIntelligence Agency; Department of 

Defense, National Security Agency (N1– 

525–14–3, 11 items, 11 temporary 

items). Routine environmental safety, 

health and wellness, facilities, and 

logistics records associated with a 

multi-mission ground station. 

5. Department of Defense, National 

Reconnaissance Office; Department of 

Defense, National GeospatialIntelligence Agency; Department of 

Defense, National Security Agency (N1– 

525–14–4, 7 items, 7 temporary items). 

Routine physical security records and 

information security records associated 

with a multi-mission ground station. 

6. Department of Homeland Security, 

Transportation Security Administration 

(DAA–0560–2013–0001, 1 item, 1 

temporary item). Master files of an 

electronic information system used to 

track the collection and disposal of 

hazardous materials collected at 

screening checkpoints. 

7. Department of Homeland Security, 

Transportation Security Administration 

(DAA–0560–2013–0004, 1 item, 1 

temporary item). Master files of an 

electronic information system used to 

track occupational health information. 

8. Department of Homeland Security, 

Transportation Security Administration 

(DAA–0560–2013–0009, 2 items, 2 

temporary items). Records related to 

performance audits at screening 

locations. 

9. Department of Justice, Bureau of 

Alcohol, Tobacco, Firearms, and 

Explosives (DAA–0436–2012–0005, 2 

items, 2 temporary items). Master files 

and outputs of an electronic information 

system used to process background 

checks for firearms purchases. 

10. Department of Justice, Bureau of 

Alcohol, Tobacco, Firearms, and 

Explosives (DAA–0436–2012–0009, 2 

items, 2 temporary items). Records 

related to the importation of firearms 

and ammunition. 

11. Department of Justice, Bureau of 

Alcohol, Tobacco, Firearms, and 

Explosives (DAA–0436–2012–0010, 9 

items, 9 temporary items). Records 

related to firearms registration and 

taxation. Records also include master 

files and outputs of electronic 

information systems used in the 

administration of a firearms registration 

program. 

12. Department of Justice, Bureau of 

Alcohol, Tobacco, Firearms, and 

Explosives (DAA–0436–2012–0011, 2 

items, 2 temporary items). Master files 

and outputs of an electronic information 

system used to manage investigative 

case files. 

13. Department of State, Bureau of 

Diplomatic Security (N1–59–11–13, 7 

items, 7 temporary items). Records of 

the Office of Investigations and 

Counterintelligence including 

assessments, reports, administrative 

files, and investigative case files. 

14. Department of Transportation, 

Federal Highway Administration (DAA– 

0406–2013–0001, 2 items, 2 temporary 

items). Experimental project files and 

test and evaluation project files. 

15. Department of Transportation, 

Federal Highway Administration (DAA– 

0406–2014–0001, 3 items, 3 temporary 

items). Content records of agency social 

networking Web sites. 

16. Department of Transportation, 

Federal Highway Administration (DAA– 

0406–2014–0002, 3 items, 3 temporary 

items). Loan and grant files. 

17. Department of Transportation, 

Federal Motor Carrier Safety 

Administration (DAA–0557–2013–0003, 

1 item, 1 temporary item). Master files 

of an electronic information system 

used to track safety performance and 

compliance histories. 

18. Export-Import Bank of the United 

States, Agency-wide (DAA–0275–2015– 

0001, 1 item, 1 temporary item). 

Compliance documents, final 

agreements, and other transaction 

records. 

19. Federal Communications 

Commission, Office of Media Relations 

(DAA–0173–2015–0001, 1 item, 1 

temporary item). Content records of 

agency social networking Web sites. 

20. James Madison Memorial 

Fellowship Foundation, Agency-wide 

(N1–508–15–1, 17 items, 8 temporary 

items). Routine and uncaptioned 

photographs, compliance reports, 

fellowship applications, administrative 

files, recipient financial records, and 

Web site records. Proposed for 

permanent retention are records of 

executive leadership, publications, 

news releases, video recordings, and 

event photographs. 

21. National Archives and Records 

Administration, Government-wide 

(DAA–GRS–2014–0002, 20 items, 20 

temporary items). General Records 

Schedule for employee acquisition 

records including classification 

standards, position descriptions, 

classification appeals, job vacancy case 

files and application packages, 

interview records, political appointment 

records, special hiring authority 

program records, and pre-appointment 

records. 

22. National Archives and Records 

Administration, Government-wide 

(DAA–GRS–2015–0002, 3 items, 3 

temporary items). General Records 

Schedule for classified information 

nondisclosure agreements and files 

relating to the inadvertent release of 

privileged information to unauthorized 

parties. 

23. Office of the Federal Coordinator 

for Alaska Natural Gas Transportation 

Projects, Agency-wide (N1–596–15–1, 9 

items, 4 temporary items). Records 

include correspondence, policy 

memorandums, and pilot project files. 

Proposed for permanent retention are 

records of the executive leadership, 

white papers, speeches, publications, 

and public presentations. 

Dated: February 23, 2015. 

Paul M. Wester Jr., 

Chief Records Officer for the U.S. 

Government. 

[FR Doc. 2015–04235 Filed 2–27–15; 8:45 am] 

BILLING CODE 7515–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–302; NRC–2015–0042] 

Duke Energy Florida, Inc.; Crystal 

River Unit 3 Nuclear Generating Plant 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Environmental assessment and 

finding of no significant impact; 

issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of exemptions in response to a 

request from Duke Energy Florida, Inc. 

(DEF, the licensee) that would permit 

the licensee to reduce its emergency 

planning (EP) activities at the Crystal 

River Unit 3 Nuclear Generating Plant 

(CR–3). CR–3 has been shut down since 

September 26, 2009, and the final 

removal of fuel from the reactor vessel 

was completed on May 28, 2011. By 

letter dated February 20, 2013, DEF 


asabaliauskas on DSK5VPTVN1PROD with NOTICES
11234 Federal Register / Vol. 80, No. 40 / Monday, March 2, 2015 / Notices 

submitted a certification to the NRC of 

permanent cessation of power 

operations and the removal of fuel from 

the reactor vessel. The licensee is 

seeking exemptions that would 

eliminate the requirements to maintain 

offsite radiological emergency plans and 

reduce some of the onsite EP activities 

based on the reduced risks at the 

permanently shutdown and defueled 

reactor. Offsite EP provisions would still 

exist using a comprehensive emergency 

management plan process. The NRC 

staff is issuing a final environmental 

assessment (EA) and final finding of no 

significant impact (FONSI) associated 

with the proposed exemptions. 

DATES: The EA and FONSI referenced in 

this document are available on March 2, 

2015. 

ADDRESSES: Please refer to Docket ID 

NRC–2015–0042 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–2015–0042. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

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 

‘‘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 in this document 

(if that document is available in 

ADAMS) is provided the first time that 

a document is referenced. 

• 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: 

Michael D. Orenak, Office of Nuclear 

Reactor Regulation, U.S. Nuclear 

Regulatory Commission, Washington DC 

20555–0001; telephone: 301–415–3229; 

email: Michael.Orenak@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

Crystal River Unit 3 Nuclear 

Generating Plant (CR–3) is a 

permanently shutdown and defueled 

power reactor in the process of 

decommissioning. CR–3 is located in 

Citrus County, Florida, 80 miles north of 

Tampa, FL. Duke Energy Florida, Inc. 

(DEF, the licensee) is the holder of 

Facility Operating License No. DPR–72 

for CR–3. CR–3 has been shut down 

since September 26, 2009, and the final 

removal of fuel from the reactor vessel 

was completed on May 28, 2011. By 

letter dated February 20, 2013, DEF 

submitted a certification to the NRC of 

permanent cessation of power 

operations and the removal of fuel from 

the reactor vessel. As a permanently 

shutdown and defueled facility, and 

pursuant to section 50.82(a)(2) of Title 

10 of the Code of Federal Regulations 

(10 CFR), CR–3 is no longer authorized 

to be operated or to have fuel placed 

into its reactor vessel, but the licensee 

is still authorized to possess and store 

irradiated nuclear fuel. Irradiated fuel is 

currently stored onsite at CR–3 in a 

spent fuel pool (SFP). The licensee has 

requested exemptions from certain 

emergency planning (EP) requirements 

in 10 CFR part 50, ‘‘Domestic Licensing 

of Production and Utilization 

Facilities,’’ for CR–3. The NRC 

regulations concerning EP do not 

recognize the reduced risks after a 

reactor is permanently shut down and 

defueled. A permanently shutdown 

reactor, such as CR–3, must continue to 

maintain the same EP requirements as 

an operating power reactor under the 

existing regulatory requirements. To 

establish a level of EP commensurate 

with the reduced risks of a permanently 

shutdown and defueled reactor, DEF 

requires exemptions from certain EP 

regulatory requirements before it can 

change its emergency plans. 

The NRC is considering issuance of 

exemptions to DEF from portions of 10 

CFR 50.47, ‘‘Emergency plans,’’ and 10 

CFR part 50, appendix E, ‘‘Emergency 

Planning and Preparedness for 

Production and Utilization Facilities,’’ 

which would permit DEF to modify its 

emergency plan to eliminate the 

requirements to maintain offsite 

radiological emergency plans and 

reduce some of the onsite EP activities 

based on the reduced risks at CR–3, due 

to its permanently shutdown and 

defueled status. Consistent with 10 CFR 

51.21, the NRC has reviewed the 

requirements in 10 CFR 51.20(b) and 10 

CFR 51.22(c) and determined that an 

environmental assessment (EA) is the 

appropriate form of environmental 

review for the requested action. Based 

on the results of the EA, which is 

provided in Section II of this document, 

the NRC has determined not to prepare 

an environmental impact statement for 

the proposed action, and is issuing a 

finding of no significant impact. 

II. Environmental Assessment 

Identification of the Proposed Action 

The proposed action would exempt 

DEF from meeting certain requirements 

set forth in 10 CFR 50.47 and appendix 

E to 10 CFR part 50. More specifically, 

DEF requested exemptions from (1) 

certain requirements in 10 CFR 50.47(b) 

regarding onsite and offsite emergency 

response plans for nuclear power 

reactors, (2) certain requirements in 10 

CFR 50.47(c)(2) to establish plume 

exposure and ingestion pathway EP 

zones for nuclear power reactors, and 

(3) certain requirements in 10 CFR part 

50, appendix E, section IV, which 

establishes the elements that make up 

the content of emergency plans. The 

proposed action of granting these 

exemptions would result in the 

elimination of the requirements for the 

licensee to maintain offsite radiological 

emergency plans and reduce some of the 

onsite EP activities at CR–3, based on 

the reduced risks at the permanently 

shutdown and defueled reactor. 

However, requirements for certain 

onsite capabilities to communicate and 

coordinate with offsite response 

authorities will be retained. If necessary, 

offsite protective actions could still be 

implemented using a comprehensive 

emergency management plan (CEMP) 

process. A CEMP in this context, also 

referred to as an emergency operations 

plan (EOP), is addressed in the Federal 

Emergency Management Agency’s 

Comprehensive Preparedness Guide 

(CPG) 101, ‘‘Developing and 

Maintaining Emergency Operations 

Plans.’’ The CPG 101 is the foundation 

for State, territorial, tribal, and local EP 

in the United States. It promotes a 

common understanding of the 

fundamentals of risk-informed planning 

and decisionmaking, and helps planners 

at all levels of government in their 

efforts to develop and maintain viable, 

all-hazards, all-threats emergency plans. 

An EOP is flexible enough for use in all 

emergencies. It describes how people 

and property will be protected; details 

regarding who is responsible for 

carrying out specific actions; identifies 

the personnel, equipment, facilities, 

supplies, and other resources available; 

and outlines how all actions will be 

coordinated. A CEMP is often referred to 

as a synonym for ‘‘all hazards 

planning.’’ 


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Federal Register / Vol. 80, No. 40 / Monday, March 2, 2015 / Notices 11235 

The proposed action is in accordance 

with the licensee’s application dated 

September 26, 2013, ‘‘Permanently 

Defueled Emergency Plan and 

Emergency Action Level Scheme, and 

Request for Exemption to Certain 

Radiological Emergency Response Plan 

Requirements Defined by 10 CFR [Part] 

50’’ (ADAMS Accession No. 

ML13274A584), as supplemented by 

letters dated March 28, 2014, and 

August 28, 2014. In its letter dated 

March 28, 2014 (ADAMS Accession No. 

ML14098A072), DEF provided 

responses to the NRC staff’s request for 

additional information concerning the 

proposed exemptions. In its letter dated 

August 28, 2014 (ADAMS Accession 

No. ML14251A237), DEF provided a 

supplement, which amended its request 

to align with the exemptions approved 

in Staff Requirements Memorandum to 

SECY–14–0066 (ADAMS Accession No. 

ML14219A366). 

Need for the Proposed Action 

The proposed action is needed for 

DEF to revise the CR–3 emergency plan 

to reflect the permanently shutdown 

and defueled status of the facility. The 

EP requirements currently applicable to 

CR–3 are for an operating power reactor. 

There are no explicit regulatory 

provisions distinguishing EP 

requirements for a power reactor that 

has been permanently shutdown from 

those for an operating power reactor. 

Therefore, since the 10 CFR part 50 

license for CR–3 no longer authorizes 

operation of the reactor or emplacement 

or retention of fuel into the reactor 

vessel as specified in 10 CFR 

50.82(a)(2), the occurrence of postulated 

accidents associated with reactor 

operation is no longer credible. 

In its exemption request, the licensee 

identified six possible radiological 

accidents at CR–3 in its permanently 

shut down and defueled condition. 

These are (1) a fuel handling accident, 

(2) a radioactive waste handling 

accident, (3) a loss of SFP normal 

cooling (boil off), (4) a loss of SFP 

inventory with air-cooling, (5) an 

adiabatic heatup of the hottest fuel 

assembly, and (6) a loss of SFP 

inventory radiation dose. The NRC staff 

evaluated these possible radiological 

accidents in the Commission Paper 

(SECY) 14–0118, ‘‘Request by Duke 

Energy Florida, Inc., for Exemptions 

from Certain Emergency Planning 

Requirements,’’ dated October 29, 2014 

(ADAMS Accession No. ML14219A444). 

In SECY–14–0118, the staff verified that 

DEF’s analyses and calculations provide 

reasonable assurance that if the 

requested exemptions were granted, 

then (1) for a design-basis accident 

(DBA), an offsite radiological release 

will not exceed the Environmental 

Protection Agency’s (EPA) Protective 

Action Guides (PAGs) at the exclusion 

area boundary, as detailed in the EPA 

‘‘PAG Manual, Protective Action Guides 

and Planning Guidance for Radiological 

Incidents,’’ dated March 2013, which 

was issued as Draft for Interim Use and 

Public Comment; and, (2) in the 

unlikely event of a beyond DBA 

resulting in a loss of all SFP cooling, 

there is sufficient time to initiate 

appropriate mitigating actions, and in 

the unlikely event that a release is 

projected to occur, there is sufficient 

time for offsite agencies to take 

protective actions using a CEMP to 

protect the health and safety of the 

public. The Commission approved the 

NRC staff’s recommendation to grant the 

exemptions in the Staff Requirements 

Memorandum to SECY–14–0118, dated 

December 30, 2014 (ADAMS Accession 

No. ML14364A111). 

Based on these analyses, the licensee 

states that complete application of the 

EP rule, in its particular circumstances 

as a permanently shutdown and 

defueled reactor with sufficiently cooled 

spent fuel in its spent fuel pool, would 

not serve the underlying purpose of the 

rule or is not necessary to achieve the 

underlying purpose of the rule. DEF also 

states that it would incur undue costs in 

the application of operating plant EP 

requirements for the maintenance of an 

emergency response organization in 

excess of that actually needed to 

respond to the diminished scope of 

credible accidents for a permanently 

shutdown and defueled reactor, with 

sufficiently cooled spent fuel in its 

spent fuel pool. 

Environmental Impacts of the Proposed 

Action 

The NRC staff concluded that the 

exemptions, if granted, will not 

significantly increase the probability or 

consequences of accidents at CR–3 in its 

permanently shutdown and defueled 

condition. There will be no significant 

change in the types of any effluents that 

may be released offsite. There will be no 

significant increase in the amounts of 

any effluents that may be released 

offsite. There will be no significant 

increase in individual or cumulative 

occupational or public radiation 

exposure. Therefore, there are no 

significant radiological environmental 

impacts associated with the proposed 

action. 

With regards to potential nonradiological impacts, the proposed 

action does not have any foreseeable 

impacts to land, air, or water resources, 

including impacts to biota. In addition, 

there are also no known socioeconomic 

or environmental justice impacts 

associated with the proposed action. 

Therefore, there are no significant nonradiological environmental impacts 

associated with the proposed action. 

Accordingly, the NRC concludes that 

there are no significant environmental 

impacts associated with the proposed 

action. 

Environmental Impacts of the 

Alternatives to the Proposed Action 

As an alternative to the proposed 

action, the staff considered denial of the 

proposed action (i.e., the ‘‘no-action’’ 

alternative). Denial of the application 

would result in no change in current 

environmental impacts. Therefore, the 

environmental impacts of the proposed 

action and the alternative action are 

similar. 

Alternative Use of Resources 

The proposed action does not involve 

the use of any different resources than 

those previously considered in the Final 

Environmental Statement for CR–3, 

dated May 1973 (ADAMS Accession No. 

ML091520178). 

Agencies or Persons Consulted 

The NRC staff did not enter into 

consultation with any other Federal 

agency or with the State of Florida 

regarding the environmental impact of 

the proposed action. On January 20, 

2015, the Florida state representative 

was notified of this EA and FONSI and 

did not provide any comments. 

III. Finding of No Significant Impact 

The licensee has proposed 

exemptions from (1) certain 

requirements in 10 CFR 50.47(b) 

regarding onsite and offsite emergency 

response plans for nuclear power 

reactors; (2) certain requirements in 10 

CFR 50.47(c)(2) to establish plume 

exposure and ingestion pathway EP 

zones for nuclear power reactors; and 

(3) certain requirements in 10 CFR part 

50, appendix E, section IV, which 

establishes the elements that make up 

the content of emergency plans. The 

proposed action of granting these 

exemptions would result in the 

elimination of the requirements for the 

licensee to maintain offsite radiological 

emergency plans and reduce some of the 

onsite EP activities at CR–3, based on 

the reduced risks at the permanently 

shutdown and defueled reactor. 

However, requirements for certain 

onsite capabilities to communicate and 

coordinate with offsite response 

authorities will be retained. 

Consistent with 10 CFR 51.21, the 

NRC conducted the EA for the proposed 


asabaliauskas on DSK5VPTVN1PROD with NOTICES
11236 Federal Register / Vol. 80, No. 40 / Monday, March 2, 2015 / Notices 

action included in Section II of this 

document and incorporated by reference 

in this finding. On the basis of this EA, 

the NRC concludes that the proposed 

action will not have a significant effect 

on the quality of the human 

environment. Accordingly, the NRC has 

decided not to prepare an 

environmental impact statement for the 

proposed action. 

This EA and FONSI is based on the 

licensee’s letter dated September 26, 

2013, as supplemented by letters dated 

March 28, 2014, and August 28, 2014. 

Otherwise, there are no other 

environmental documents associated 

with this review. These documents are 

available for public inspection as 

indicated above. 

Dated at Rockville, Maryland, this 23rd day 

of February, 2015. 

For the Nuclear Regulatory Commission. 

Meena K. Khanna, 

Chief, Plant Licensing IV–2 and 

Decommissioning Transition Branch, 

Division of Operating Reactor Licensing, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2015–04288 Filed 2–27–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–247; NRC–2015–0038] 

Entergy Nuclear Operations, Inc., 

Indian Point Nuclear Generating, Unit 2 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: License amendment application; 

opportunity to comment, request a 

hearing, and petition for leave to 

intervene. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of an amendment to Facility 

Operating License No. DPR–26, issued 

to Entergy Nuclear Operations, Inc., for 

operation of the Indian Point Nuclear 

Generating, Unit 2. The proposed 

amendment would allow a revision to 

the acceptance criteria for the 

Surveillance Requirement 3.1.4.2 for 

Control Rod G–3. During the last two 

performances of this Surveillance on 

September 18, 2014, and December 11, 

2014, Control Rod G–3 misalignment 

occurred with Shutdown Bank B group 

movement as displayed by the 

Individual Rod Position Indication and 

Plant Instrument Computer System. The 

proposed change is to defer subsequent 

testing of the Control Rod G–3 until 

repaired during the next refuel outage 

(March 2016) or forced outage long 

enough to repair the Control Rod. 

DATES: Submit comments by April 1, 

2015. Requests for a hearing or petition 

for leave to intervene must be filed by 

May 1, 2015. 

ADDRESSES: You may submit comments 

by any of the following methods (unless 

this document describes a different 

method for submitting comments on a 

specific subject): 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2015–0038. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individual listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Mail comments to: Cindy Bladey, 

Office of Administration, Mail Stop: 

OWFN–12–H08, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

For additional direction on obtaining 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Douglas V. Pickett, Office of Nuclear 

Reactor Regulation, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; telephone: 301–415– 

1364, email: Douglas.Pickett@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2015– 

0038 when contacting the NRC about 

the availability of information for this 

action. You may obtain publiclyavailable information related to this 

action by any of the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2015–0038. 

• 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 

‘‘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 

Proposed License Amendment 

Regarding a Change to Technical 

Specification 3.1.4, ‘‘Reactivity Control 

Systems’’, is available in ADAMS under 

Accession No. ML15044A471. 

• 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. 

B. Submitting Comments 

Please include Docket ID NRC–2015– 

0038 in the subject line of your 

comment submission, in order to ensure 

that the NRC is able to make your 

comment submission available to the 

public in this docket. 

The NRC cautions you not to include 

identifying or contact information that 

you do not want to be publicly 

disclosed in your comment submission. 

The NRC posts all comment 

submissions at http://

www.regulations.gov as well as entering 

the comment submissions into ADAMS. 

The NRC does not routinely edit 

comment submissions to remove 

identifying or contact information. 

If you are requesting or aggregating 

comments from other persons for 

submission to the NRC, then you should 

inform those persons not to include 

identifying or contact information that 

they do not want to be publicly 

disclosed in their comment submission. 

Your request should state that the NRC 

does not routinely edit comment 

submissions to remove such information 

before making the comment 

submissions available to the public or 

entering the comment submissions into 

ADAMS. 

I. Introduction 

The NRC is considering issuance of an 

amendment to Facility Operating 

License No. DPR–26, issued to Entergy 

Nuclear Operations, Inc., for operation 

of the Indian Point Nuclear Generating, 

Unit 2, located in Westchester County, 

New York. 

The proposed amendment would 

allow a revision to the acceptance 

criteria for Surveillance Requirement 

3.1.4.2 for Control Rod G–3. During the 

last two performances of this 

Surveillance on September 18, 2014, 

and December 11, 2014, Control Rod G– 

3 misalignment occurred with 

Shutdown Bank B group movement as 

displayed by the Individual Rod 

Position Indication and Plant 

Instrument Computer System. The 

proposed change is to defer subsequent 

testing of the Control Rod G–3 until 

repaired during the next refuel outage 

(March 2016) or forced outage long 

enough to repair the Control Rod. 

Before any issuance of the proposed 

license amendment, the NRC will need 

to make the findings required by the 


asabaliauskas on DSK5VPTVN1PROD with NOTICES