This section of the FEDERAL REGISTER

contains regulatory documents having general

applicability and legal effect, most of which

are keyed to and codified in the Code of

Federal Regulations, which is published under

50 titles pursuant to 44 U.S.C. 1510.

The Code of Federal Regulations is sold by

the Superintendent of Documents. Prices of

new books are listed in the first FEDERAL

REGISTER issue of each week.

Rules and Regulations Federal Register

9515 

Vol. 77, No. 33 

Friday, February 17, 2012 

NUCLEAR REGULATORY 

COMMISSION 

10 CFR Part 72 

[NRC–2011–0221] 

RIN 3150–AJ05 

List of Approved Spent Fuel Storage 

Casks: HI–STORM 100, Revision 8 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Direct final rule. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC or the Commission) 

is amending its spent fuel storage 

regulations by revising the Holtec 

International HI–STORM 100 dry cask 

storage system listing within the ‘‘List of 

Approved Spent Fuel Storage Casks’’ to 

include Amendment No. 8 to Certificate 

of Compliance (CoC) No. 1014. 

Amendment No. 8 adds a new 

multipurpose canister (MPC)–68M to 

the approved models currently included 

in CoC No. 1014 with two new boiling 

water reactor fuel assembly/array 

classes, and a new pressurized water 

reactor fuel assembly/class to CoC No. 

1014 for loading into the MPC–32. In 

addition, the amendment makes several 

other changes as described under the 

‘‘Discussion’’ heading in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

DATES: The final rule is effective May 2, 

2012, unless significant adverse 

comments are received by March 19, 

2012. A significant adverse comment is 

a comment where the commenter 

explains why the rule would be 

inappropriate, including challenges to 

the rule’s underlying premise or 

approach, or would be ineffective or 

unacceptable without a change. If the 

rule is withdrawn, timely notice will be 

published in the Federal Register. 

ADDRESSES: You can access publicly 

available documents related to this 

document using the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for documents filed under Docket ID 

NRC–2011–0221. Address questions 

about NRC dockets to Carol Gallagher, 

telephone: 301–492–3668; email: 

Carol.Gallagher@nrc.gov. 

• NRC’s Public Document Room 

(PDR): The public may examine and 

have copied, for a fee, publicly available 

documents at the NRC’s PDR, Room O– 

1F21, One White Flint North, 11555 

Rockville Pike, Rockville, Maryland 

20852. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): Publicly available documents 

created or received at the NRC are 

available online in the NRC Library at 

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

adams.html. From this page, the public 

can gain entry into ADAMS, which 

provides text and image files of NRC’s 

public documents. If you do not have 

access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC’s 

PDR Reference staff at 1–800–397–4209, 

301–415–4737, or by email to 

pdr.resource@nrc.gov. An electronic 

copy of the proposed CoC, Technical 

Specifications (TSs), and preliminary 

safety evaluation report (SER) can be 

found under ADAMS Package 

Accession Number ML112160574. 

FOR FURTHER INFORMATION CONTACT: 

Gregory Trussell, Office of Federal and 

State Materials and Environmental 

Management Programs, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone: 301–415– 

6445, email: Gregory.Trussell@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

Background 

Section 218(a) of the Nuclear Waste 

Policy Act (NWPA) of 1982, as 

amended, requires that ‘‘the Secretary 

[of the Department of Energy] shall 

establish a demonstration program, in 

cooperation with the private sector, for 

the dry storage of spent nuclear fuel at 

civilian nuclear power reactor sites, 

with the objective of establishing one or 

more technologies that the [U.S. Nuclear 

Regulatory] Commission may, by rule, 

approve for use at the sites of civilian 

nuclear power reactors without, to the 

maximum extent practicable, the need 

for additional site-specific approvals by 

the Commission.’’ Section 133 of the 

NWPA states, in part, that [the 

Commission] shall, by rule, establish 

procedures for the licensing of any 

technology approved by the 

Commission under Section 219(a) for 

use at the site of any civilian nuclear 

power reactor.’’ 

To implement this mandate, the 

Commission approved dry storage of 

spent nuclear fuel in NRC-approved 

casks under a general license by 

publishing a final rule in Title 10 of the 

Code of Federal Regulations (10 CFR) 

Part 72, which added a new Subpart K 

within 10 CFR Part 72, entitled ‘‘General 

License for Storage of Spent Fuel at 

Power Reactor Sites’’ (55 FR 29181; July 

18, 1990). This rule also established a 

new Subpart L within 10 CFR Part 72, 

entitled ‘‘Approval of Spent Fuel 

Storage Casks,’’ which contains 

procedures and criteria for obtaining 

NRC approval of spent fuel storage cask 

designs. The NRC subsequently issued a 

final rule on May 1, 2000 (65 FR 25241), 

that approved the Holtec International 

cask design and added it to the list of 

NRC-approved cask designs in 10 CFR 

72.214 as CoC No. 1014. 

Discussion 

On November 28, 2009, and as 

supplemented on November 4 and 

December 14, 2010, and February 25 

and July 8, 2011, Holtec International, 

the holder of CoC No. 1014, submitted 

a certificate amendment request to the 

NRC requesting an amendment to CoC 

No. 1014. Specifically, Holtec 

International requested changes to add a 

new MPC–68M to the approved models 

currently included in CoC No. 1014 

with two new boiling water reactor fuel 

assembly/array classes, and a new 

pressurized water reactor fuel assembly/ 

class to CoC No. 1014 for loading into 

the MPC–32. In addition, the 

amendment would change 1) Condition 

5 of CoC No. 1014 to add ‘‘if applicable’’ 

after the reference to Section 3.5 of 

Appendix B, ‘‘Cask Transfer Facility 

(CTF)’’ to clarify that the CTF is an 

optional facility; 2) Appendix A, TS 1.1, 

to modify the CTF definition to clarify 

that it could be used in lieu of 10 CFR 

Part 50 controlled structures for cask 

transfer evolutions; and 3) Table 3–1, 

MPC Cavity Drying Limits, to include 

the previously approved, but omitted 

table to eliminate inconsistencies 

mstockstill on DSK4VPTVN1PROD with RULES

9516 Federal Register / Vol. 77, No. 33 / Friday, February 17, 2012 / Rules and Regulations 

between Table 3–1 and TS 3.1.1, 

Limiting Condition for Operation. 

As documented in the SER, the NRC 

staff performed a detailed safety 

evaluation of the proposed CoC 

amendment request and found that an 

acceptable safety margin is maintained. 

In addition, the NRC staff has 

determined that there continues to be 

reasonable assurance that public health 

and safety will be adequately protected. 

This direct final rule revises the HI– 

STORM 100 listing in 10 CFR 72.214 by 

adding Amendment No. 8 to CoC No. 

1014. The amendment consists of the 

changes previously described, as set 

forth in the revised CoC and TSs. The 

revised TSs are identified in the SER. 

The amended HI–STORM 100 cask 

design, when used under the conditions 

specified in the CoC, the TSs, and the 

NRC’s regulations, will meet the 

requirements of 10 CFR Part 72; thus, 

adequate protection of public health and 

safety will continue to be ensured. 

When this direct final rule becomes 

effective, persons who hold a general 

license under 10 CFR 72.210 may load 

spent nuclear fuel into HI–STORM 100 

casks that meet the criteria of 

Amendment No. 8 to CoC No. 1014 

under 10 CFR 72.212. 

Discussion of Amendments by Section 

Section 72.214 List of approved spent 

fuel storage casks 

The CoC No. 1014 is revised by 

adding the effective date of Amendment 

Number 8. 

Procedural Background 

This rule is limited to the changes 

contained in Amendment No. 8 to CoC 

No. 1014 and does not include other 

aspects of the HI–STORM 100 dry 

storage cask system. The NRC is using 

the ‘‘direct final rule procedure’’ to 

issue this amendment because it 

represents a limited and routine change 

to an existing CoC that is expected to be 

noncontroversial. Adequate protection 

of public health and safety continues to 

be ensured. The amendment to the rule 

will become effective on May 2, 2012. 

However, if the NRC receives significant 

adverse comments on this direct final 

rule by March 19, 2012, then the NRC 

will publish a document that withdraws 

this action and will subsequently 

address the comments received in a 

final rule as a response to the 

companion proposed rule published 

elsewhere in this issue of the Federal 

Register. Absent significant 

modifications to the proposed revisions 

requiring republication, the NRC will 

not initiate a second comment period on 

this action. 

A significant adverse comment is a 

comment where the commenter 

explains why the rule would be 

inappropriate, including challenges to 

the rule’s underlying premise or 

approach, or would be ineffective or 

unacceptable without a change. A 

comment is adverse and significant if: 

(1) The comment opposes the rule and 

provides a reason sufficient to require a 

substantive response in a notice-andcomment process. For example, a 

substantive response is required when: 

(a) The comment causes the NRC staff 

to reevaluate (or reconsider) its position 

or conduct additional analysis; 

(b) The comment raises an issue 

serious enough to warrant a substantive 

response to clarify or complete the 

record; or 

(c) The comment raises a relevant 

issue that was not previously addressed 

or considered by the NRC staff. 

(2) The comment proposes a change 

or an addition to the rule, and it is 

apparent that the rule would be 

ineffective or unacceptable without 

incorporation of the change or addition. 

(3) The comment causes the NRC staff 

to make a change (other than editorial) 

to the rule, CoC, or TSs. 

For detailed instructions on filing 

comments, please see the companion 

proposed rule published elsewhere in 

this issue of the Federal Register. 

Voluntary Consensus Standards 

The National Technology Transfer 

and Advancement Act of 1995 (Pub. L. 

104–113) requires that Federal agencies 

use technical standards that are 

developed or adopted by voluntary 

consensus standards bodies unless the 

use of such a standard is inconsistent 

with applicable law or otherwise 

impractical. In this direct final rule, the 

NRC will revise the Holtec International 

HI–STORM 100 System cask design 

listed in § 72.214 (List of Approved 

Spent Fuel Storage Casks). This action 

does not constitute the establishment of 

a standard that contains generally 

applicable requirements. 

Agreement State Compatibility 

Under the ‘‘Policy Statement on 

Adequacy and Compatibility of 

Agreement State Programs’’ approved by 

the Commission on June 30, 1997, and 

published in the Federal Register on 

September 3, 1997 (62 FR 46517), this 

rule is classified as Compatibility 

Category ‘‘NRC.’’ Compatibility is not 

required for Category ‘‘NRC’’ 

regulations. The NRC program elements 

in this category are those that relate 

directly to areas of regulation reserved 

to the NRC by the Atomic Energy Act of 

1954, as amended, or the provisions of 

10 CFR. Although an Agreement State 

may not adopt program elements 

reserved to the NRC, it may wish to 

inform its licensees of certain 

requirements via a mechanism that is 

consistent with the particular State’s 

administrative procedure laws but does 

not confer regulatory authority on the 

State. 

Plain Writing 

The Plain Writing Act of 2010 (Pub. 

L. 111–274) requires Federal agencies to 

write documents in a clear, concise, 

well-organized manner that also follows 

other best practices appropriate to the 

subject or field and the intended 

audience. The NRC has attempted to use 

plain language in promulgating this rule 

consistent with the Federal Plain 

Writing Act guidelines. 

Finding of No Significant 

Environmental Impact: Availability 

Under the National Environmental 

Policy Act of 1969, as amended, and the 

NRC regulations in Subpart A of 10 CFR 

Part 51, the NRC has determined that 

this rule, if adopted, would not be a 

major Federal action significantly 

affecting the quality of the human 

environment and, therefore, an 

environmental impact statement is not 

required. The NRC has prepared an 

environmental assessment and, on the 

basis of this environmental assessment, 

has made a finding of no significant 

impact. This rule amends the CoC for 

the Holtec International HI–STORM 100 

System cask design within the list of 

approved spent fuel storage casks that 

power reactor licensees can use to store 

spent fuel at reactor sites under a 

general license. Amendment No. 8 adds 

a new multipurpose canister (MPC)— 

68M to the approved models currently 

included in CoC No. 1014 with two new 

boiling water reactor fuel assembly/ 

array classes, and a new pressurized 

water reactor fuel assembly/class to CoC 

No. 1014 for loading into the MPC–32. 

In addition, the amendment changes: (1) 

Condition 5 of CoC No. 1014 to add ‘‘if 

applicable’’ after the reference to 

Section 3.5 of Appendix B, ‘‘Cask 

Transfer Facility (CTF)’’ to clarify that 

the CTF is an optional facility; (2) 

Appendix A, TS 1.1, to modify the CTF 

definition to clarify that it could be used 

in lieu of 10 CFR part 50 controlled 

structures for cask transfer evolutions; 

and (3) Table 3–1, MPC Cavity Drying 

Limits, to include the previously 

approved, but omitted, table to 

eliminate inconsistencies between Table 

3–1 and TS 3.1.1, Limiting Condition for 

Operation. 

The environmental assessment and 

finding of no significant impact on 

mstockstill on DSK4VPTVN1PROD with RULES

Federal Register / Vol. 77, No. 33 / Friday, February 17, 2012 / Rules and Regulations 9517 

which this determination is based are 

available for inspection at the NRC PDR, 

Room O–1F21, One White Flint North, 

11555 Rockville Pike, Rockville, 

Maryland 20852. Single copies of the 

environmental assessment and finding 

of no significant impact are available 

from Gregory Trussell, Office of Federal 

and State Materials and Environmental 

Management Programs, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone: 301–415– 

6445, email: Gregory.Trussell@nrc.gov. 

Paperwork Reduction Act Statement 

This rule does not contain any 

information collection requirements 

and, therefore, is not subject to the 

Paperwork Reduction Act of 1995 (44 

U.S.C. 3501 et seq.). Existing 

requirements were approved by the 

Office of Management and Budget 

(OMB), Approval Number 3150–0132. 

Public Protection Notification 

The NRC may not conduct or sponsor, 

and a person is not required to respond 

to a request for information or an 

information collection requirement 

unless the requesting document 

displays a currently valid OMB control 

number. 

Regulatory Analysis 

On July 18, 1990 (55 FR 29181), the 

NRC issued an amendment to 10 CFR 

part 72 to provide for the storage of 

spent nuclear fuel under a general 

license in cask designs approved by the 

NRC. Any nuclear power reactor 

licensee can use NRC-approved cask 

designs to store spent nuclear fuel if it 

notifies the NRC in advance, the spent 

fuel is stored under the conditions 

specified in the cask’s CoC, and the 

conditions of the general license are 

met. A list of NRC-approved cask 

designs is contained in 10 CFR 72.214. 

On May 1, 2000 (65 FR 25241), the NRC 

issued an amendment to 10 CFR part 72 

that approved the HI–STORM 100 cask 

design by adding it to the list of NRCapproved cask designs in 10 CFR 

72.214. 

On November 28, 2009, and as 

supplemented on November 4 and 

December 14, 2010, and February 25 

and July 8, 2011, Holtec International, 

the holder of CoC No. 1014, submitted 

a certificate amendment request to the 

NRC requesting an amendment to CoC 

No. 1014. Specifically, Holtec 

International requested changes to add a 

new multipurpose canister (MPC)–68M 

to the approved models currently 

included in CoC No. 1014 with two new 

boiling water reactor fuel assembly/ 

array classes, and a new pressurized 

water reactor fuel assembly/class to CoC 

No. 1014 for loading into the MPC–32. 

In addition, the amendment would 

change: (1) Condition 5 of CoC No. 1014 

to add ‘‘if applicable’’ after the reference 

to Section 3.5 of Appendix B, ‘‘Cask 

Transfer Facility (CTF)’’ to clarify that 

the CTF is an optional facility; (2) 

Appendix A, TS 1.1, to modify the CTF 

definition to clarify that it could be used 

in lieu of 10 CFR part 50 controlled 

structures for cask transfer evolutions; 

and (3) Table 3–1, MPC Cavity Drying 

Limits, to include the previously 

approved, but omitted table to eliminate 

inconsistencies between Table 3–1 and 

TS 3.1.1, Limiting Condition for 

Operation. 

The alternative to this action is to 

withhold approval of Amendment No. 8 

and to require any 10 CFR part 72 

general licensee seeking to load spent 

nuclear fuel into HI–STORM 100 casks 

under the changes described in 

Amendment No. 8 to request an 

exemption from the requirements of 10 

CFR 72.212 and 72.214. Under this 

alternative, each interested 10 CFR part 

72 licensee would have to prepare, and 

the NRC would have to review, a 

separate exemption request, thereby 

increasing the administrative burden 

upon the NRC and the costs to each 

licensee. 

Approval of the direct final rule is 

consistent with previous NRC actions. 

Further, as documented in the SER and 

the environmental assessment, the 

direct final rule will have no adverse 

effect on public health and safety or the 

environment. This direct final rule has 

no significant identifiable impact or 

benefit on other Government agencies. 

Based on this regulatory analysis, the 

NRC concludes that the requirements of 

the direct final rule are commensurate 

with the NRC’s responsibilities for 

public health and safety and the 

common defense and security. No other 

available alternative is believed to be as 

satisfactory, and thus, this action is 

recommended. 

Regulatory Flexibility Certification 

Under the Regulatory Flexibility Act 

of 1980 (5 U.S.C. 605(b)), the NRC 

certifies that this rule will not, if issued, 

have a significant economic impact on 

a substantial number of small entities. 

This direct final rule affects only 

nuclear power plant licensees and 

Holtec International. These entities do 

not fall within the scope of the 

definition of ‘‘small entities’’ set forth in 

the Regulatory Flexibility Act or the size 

standards established by the NRC (10 

CFR 2.810). 

Backfit Analysis 

The NRC has determined that the 

backfit rule (10 CFR 72.62) does not 

apply to this direct final rule because 

this amendment does not involve any 

provisions that would impose backfits 

as defined in 10 CFR Chapter I. 

Therefore, a backfit analysis is not 

required. 

Congressional Review Act 

Under the Congressional Review Act 

of 1996, the NRC has determined that 

this action is not a major rule and has 

verified this determination with the 

Office of Information and Regulatory 

Affairs, OMB. 

List of Subjects in 10 CFR Part 72 

Administrative practice and 

procedure, Criminal penalties, 

Manpower training programs, Nuclear 

materials, Occupational safety and 

health, Penalties, Radiation protection, 

Reporting and recordkeeping 

requirements, Security measures, Spent 

fuel, Whistleblowing. 

For the reasons set out in the 

preamble and under the authority of the 

Atomic Energy Act of 1954, as amended; 

the Energy Reorganization Act of 1974, 

as amended; the Nuclear Waste Policy 

Act of 1982, as amended; and 5 U.S.C. 

552 and 553; the NRC is adopting the 

following amendments to 10 CFR part 

72. 

PART 72—LICENSING 

REQUIREMENTS FOR THE 

INDEPENDENT STORAGE OF SPENT 

NUCLEAR FUEL, HIGH-LEVEL 

RADIOACTIVE WASTE, AND 

REACTOR-RELATED GREATER THAN 

CLASS C WASTE 

■ 1. The authority citation for part 72 

continues to read as follows: 

Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 

81, 161, 182, 183, 184, 186, 187, 189, 68 Stat. 

929, 930, 932, 933, 934, 935, 948, 953, 954, 

955, as amended, sec. 234, 83 Stat. 444, as 

amended (42 U.S.C. 2071, 2073, 2077, 2092, 

2093, 2095, 2099, 2111, 2201, 2232, 2233, 

2234, 2236, 2237, 2238, 2282); sec. 274, Pub. 

L. 86–373, 73 Stat. 688, as amended (42 

U.S.C. 2021); sec. 201, as amended, 202, 206, 

88 Stat. 1242, as amended, 1244, 1246 (42 

U.S.C. 5841, 5842, 5846); Pub. L. 95–601, sec. 

10, 92 Stat. 2951 as amended by Pub. L. 102– 

486, sec. 7902, 106 Stat. 3123 (42 U.S.C. 

5851); sec. 102, Pub. L. 91–190, 83 Stat. 853 

(42 U.S.C. 4332); secs. 131, 132, 133, 135, 

137, 141, Pub. L. 97–425, 96 Stat. 2229, 2230, 

2232, 2241, sec. 148, Pub. L. 100–203, 101 

Stat. 1330–235 (42 U.S.C. 10151, 10152, 

10153, 10155, 10157, 10161, 10168); sec. 

1704, 112 Stat. 2750 (44 U.S.C. 3504 note); 

Energy Policy Act of 2005, Pub. L. No. 109– 

58, 119 Stat. 549 (2005). 

Section 72.44(g) also issued under secs. 

142(b) and 148(c), (d), Pub. L. 100–203, 101 

mstockstill on DSK4VPTVN1PROD with RULES

9518 Federal Register / Vol. 77, No. 33 / Friday, February 17, 2012 / Rules and Regulations 

Stat. 1330–232, 1330–236 (42 U.S.C. 

10162(b), 10168(c), (d)). Section 72.46 also 

issued under sec. 189, 68 Stat. 955 (42 U.S.C. 

2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230 

(42 U.S.C. 10154). Section 72.96(d) also 

issued under sec. 145(g), Pub. L. 100–203, 

101 Stat. 1330–235 (42 U.S.C. 10165(g)). 

Subpart J also issued under secs. 2(2), 2(15), 

2(19), 117(a), 141(h), Pub. L. 97–425, 96 Stat. 

2202, 2203, 2204, 2222, 2244 (42 U.S.C. 

10101, 10137(a), 10161(h)). Subparts K and L 

are also issued under sec. 133, 98 Stat. 2230 

(42 U.S.C. 10153) and sec. 218(a), 96 Stat. 

2252 (42 U.S.C. 10198). 

■ 2. In § 72.214, Certificate of 

Compliance 1014 is revised to read as 

follows: 

§ 72.214 List of approved spent fuel 

storage casks. 

* * * * * 

Certificate No.: 1014. 

Initial Certificate Effective Date: May 31, 

2000. 

Amendment Number 1 Effective Date: 

July 15, 2002. 

Amendment Number 2 Effective Date: 

June 7, 2005. 

Amendment Number 3 Effective Date: 

May 29, 2007. 

Amendment Number 4 Effective Date: 

January 8, 2008. 

Amendment Number 5 Effective Date: 

July 14, 2008. 

Amendment Number 6 Effective Date: 

August 17, 2009. 

Amendment Number 7 Effective Date: 

December 28, 2009. 

Amendment Number 8 Effective Date: 

May 2, 2012. 

SAR Submitted by: Holtec International. 

SAR Title: Final Safety Analysis Report 

for the HI–STORM 100 Cask System. 

Docket Number: 72–1014. 

Certificate Expiration Date: May 31, 

2020. 

Model Number: HI–STORM 100. 

* * * * * 

Dated at Rockville, Maryland, this 25th day 

of January, 2012. 

For the Nuclear Regulatory Commission. 

R.W. Borchardt, 

Executive Director for Operations. 

[FR Doc. 2012–3678 Filed 2–16–12; 8:45 am] 

BILLING CODE 7590–01–P 

DEPARTMENT OF TRANSPORTATION 

Federal Aviation Administration 

14 CFR Part 39 

[Docket No. FAA–2011–0725; Directorate 

Identifier 2011–NM–065–AD; Amendment 

39–16943; AD 2012–03–02] 

RIN 2120–AA64 

Airworthiness Directives; The Boeing 

Company Airplanes 

AGENCY: Federal Aviation 

Administration (FAA), DOT. 

ACTION: Final rule. 

SUMMARY: We are adopting a new 

airworthiness directive (AD) for certain 

The Boeing Company Model 767–200, 

–300, and –300F series airplanes. This 

AD was prompted by reports of loss of 

avionics cooling due to an unserviceable 

relay installed on a panel as part of the 

cabin air conditioning and temperature 

control system (CACTCS). This AD 

requires doing certain wiring changes, 

installing a new relay and necessary 

wiring in the CACTCS, and performing 

an operational test of the cooling pack 

system. We are issuing this AD to 

prevent loss of electrical equipment bay 

cooling and the overheating of flight 

deck instruments, which would result 

in the eventual loss of primary flight 

displays, an unusually high pilot 

workload, and depressurization of the 

cabin. 

DATES: This AD is effective March 23, 

2012. 

The Director of the Federal Register 

approved the incorporation by reference 

of certain publications listed in the AD 

as of March 23, 2012. 

ADDRESSES: For service information 

identified in this AD, contact Boeing 

Commercial Airplanes, Attention: Data 

& Services Management, P.O. Box 3707, 

MC 2H–65, Seattle, Washington 98124– 

2207; telephone 206–544–5000, 

extension 1; fax 206–766–5680; email: 

me.boecom@boeing.com; Internet 

https://www.myboeingfleet.com. You 

may review copies of the referenced 

service information at the FAA, 

Transport Airplane Directorate, 1601 

Lind Avenue SW., Renton, Washington. 

For information on the availability of 

this material at the FAA, call 425–227– 

1221. 

Examining the AD Docket 

You may examine the AD docket on 

the Internet at http:// 

www.regulations.gov; or in person at the 

Docket Management Facility between 

9 a.m. and 5 p.m., Monday through 

Friday, except Federal holidays. The AD 

docket contains this AD, the regulatory 

evaluation, any comments received, and 

other information. The address for the 

Docket Office (phone: 800–647–5527) is 

Document Management Facility, U.S. 

Department of Transportation, Docket 

Operations, M–30, West Building 

Ground Floor, Room W12–140, 1200 

New Jersey Avenue SE., Washington, 

DC 20590. 

FOR FURTHER INFORMATION CONTACT: Ana 

Martinez Hueto, Aerospace Engineer, 

Cabin Safety and Environmental 

Systems Branch, ANM–150S, FAA, 

Seattle Aircraft Certification Office, 

1601 Lind Avenue SW., Renton, WA 

98057–3356; phone: 425–917–6592; fax: 

425–917–6590; email: 

ana.m.hueto@faa.gov. 

SUPPLEMENTARY INFORMATION: 

Discussion 

We issued a notice of proposed 

rulemaking (NPRM) to amend 14 CFR 

part 39 to include an AD that would 

apply to the specified products. That 

NPRM published in the Federal 

Register on August 24, 2011 (76 FR 

52899). That NPRM proposed to require 

doing certain wiring changes, installing 

a new relay and necessary wiring in the 

CACTCS, and performing an operational 

test of the cooling pack system. 

Comments 

We gave the public the opportunity to 

participate in developing this AD. We 

have considered the comments received. 

Boeing supports the NPRM (76 FR 

52899, August 24, 2011). American 

Airlines stated that it is not affected by 

the NPRM. 

Conclusion 

We reviewed the relevant data, 

considered the comments received, and 

determined that air safety and the 

public interest require adopting the AD 

as proposed except for minor editorial 

changes. We have determined that these 

minor changes: 

• Are consistent with the intent that 

was proposed in the NPRM (76 FR 

52899, August 24, 2011) for correcting 

the unsafe condition; and 

• Do not add any additional burden 

upon the public than was already 

proposed in the NPRM (76 FR 52899, 

August 24, 2011). 

Costs of Compliance 

We estimate that this AD affects 35 

airplanes of U.S. registry. 

We estimate the following costs to 

comply with this AD: 

mstockstill on DSK4VPTVN1PROD with RULES