53932 Federal Register / Vol. 62, No. 201 / Friday, October 17, 1997 / Rules and Regulations

and weight range and the number of

days grazing occurred, and the amount

and type of feed fed such grazing

animals during any grazing period

within the crop year.

(f) Animal Unit Day adjustments, as

determined by CCC, may be calculated

when a producer of forage

predominantly grazed, provides

adequate evidence, as determined by

CCC, that unit forage management and

maintenance practices provide different

carrying capacity than practices

generally provided forage acreage used

to calculate the approved county

expected carrying capacity.

8. Amend § 1437.9 to revise paragraph

(b)(2) to read as follows:

§ 1437.9 Loss Requirements.

* * * * *

(b) * * *

(2) The failure of the producer to

reseed or replant to the same crop in the

county where it is practicable to reseed

or replant;

* * * * *

9. Amend § 1437.11 to revise the

introductory text and add paragraph (c)

to read as follows:

§ 1437.11 Payments for reduced yields and

prevented planting.

In the event that the area loss

requirement has been satisfied for the

crop and:

* * * * *

(c) The producer has sustained a loss

of forage determined by CCC to be

predominantly grazed in accordance

with § 1437.7(l), in excess of 50 percent

of the producer’s expected Animal Unit

Day established for the unit, the NAP

payment will be determined by:

(1) Dividing the unit acreage for each

species or type or variety identified on

the unit by the approved carrying

capacity and multiplying the result by

the corresponding grazing days used as

the basis for determination of the

carrying capacity, totaling the result for

each species or types and varieties.

(2) Multiplying the result of paragraph

(c)(1) of this section by 50 percent.

(3) Multiplying the number of animals

grazed by the daily allowance of corn

according to type and weight range and

divide the result by pounds of corn CCC

determines is necessary to provide the

daily energy requirement for one animal

unit.

(4) Multiplying the result of paragraph

(c)(3) of this section by the number of

days grazing occurred to determine

gross actual AUD.

(5) Adding AUD for ineligible causes

of loss and incidental mechanically

harvested Category 1 forage to the result

of paragraph (c)(4) of this section.

(6) Subtracting AUD or equivalent

value of supplemental feed fed to the

grazing livestock during the crop year

from the result of paragraph (c)(5) of this

section.

(7) Subtracting the result of paragraph

(c)(6) of this section from the result of

paragraph (c)(2) of this section. If a zero

or negative number results, payment

cannot be calculated.

(8) Multiplying the positive result of

paragraph (c)(7) of this section by:

(i) For the 1997 through 1998 crop

years, 60 percent of the average market

price, as determined by CCC, or any

comparable coverage, as determined by

CCC; or

(ii) For the 1999 and subsequent

years, 55 percent of the average market

price, as determined by CCC, or any

comparable coverage, as determined by

CCC.

Signed at Washington, DC, on October 8,

1997.

Keith Kelly,

Executive Vice President, Commodity Credit

Corporation.

[FR Doc. 97–27432 Filed 10–16–97; 8:45 am]

BILLING CODE 3410–01–P

NUCLEAR REGULATORY

COMMISSION

10 CFR Part 50

RIN 3150–AF73

Codes and Standards; IEEE National

Consensus Standard

AGENCY: Nuclear Regulatory

Commission.

ACTION: Direct final rule.

SUMMARY: The Nuclear Regulatory

Commission is amending its regulations

to incorporate by reference IEEE Std.

603–1991, a national consensus

standard for power, instrumentation,

and control portions of safety systems in

nuclear power plants. This action is

necessary to endorse the latest version

of this national consensus standard in

NRC’s regulations, and replace an IEEE

standard currently endorsed in the

NRC’s regulations which has been

withdrawn by the IEEE.

EFFECTIVE DATE: The final rule is

effective on January 1, 1998, unless

significant adverse comments are

received by December 1, 1997. If the

effective date is delayed, timely notice

will be published in the Federal

Register. The incorporation by reference

of IEEE Std. 603–1991 is approved by

the Director of the Federal Register as of

January 1, 1998.

ADDRESSES: Mail comments to:

Secretary, U.S. Nuclear Regulatory

Commission, Washington, DC 20555–

0001; Attention: Rulemakings and

Adjudications Staff. Hand deliver

comments to 11555 Rockville Pike,

Rockville, Maryland, between 7:30 a.m.

and 4:15 p.m. on Federal workdays.

FOR FURTHER INFORMATION CONTACT:

Satish K. Aggarwal, Senior Program

Manager, Office of Nuclear Regulatory

Research, U.S. Nuclear Regulatory

Commission, Washington, DC 20555,

Telephone (301) 415–6005, Fax (301)

415–5074 (e-mail: SKA@NRC.GOV).

SUPPLEMENTARY INFORMATION: NRC

considers this rulemaking, which

endorses IEEE Std. 603–1991, to be

noncontroversial because, as noted in

the background discussion, there was no

adverse public comment on the

regulatory guide endorsing this

standard. Accordingly, the Commission

finds that public notice and opportunity

for comment are unnecessary pursuant

to 5 U.S.C. 553(b)(B). Thus, the

Commission is publishing this rule in

final form without seeking public

comments on the amendment in a

proposed rule. This action will become

effective on January 1, 1998. However,

if the NRC receives significant adverse

comments by December 1, 1997, then

the NRC will publish a document that

withdraws this action, and will address

the comments received in response to

an identical proposed rule which is

being concurrently published in the

proposed rules section of this Federal

Register. Any significant adverse

comments will be addressed in a

subsequent final rule. The NRC will not

initiate a second comment period on

this action in the event the direct final

rule is withdrawn.

Background

In 10 CFR part 50, ‘‘Domestic

Licensing of Production and Utilization

Facilities,’’ § 50.55a requires that the

protection systems in nuclear power

plants meet the requirements set forth in

IEEE Std. 279, ‘‘Criteria for Protection

Systems for Nuclear Power Generating

Stations,’’ in effect on the formal docket

date of the application. However, IEEE

Std. 279 is obsolete, has been

withdrawn by IEEE and has now been

superseded by IEEE Std. 603–1991,

‘‘Criteria for Safety Systems for Nuclear

Power Generating Stations.’’

In November 1995, the NRC staff

issued for public comment a draft

regulatory guide, DG–1042, which was

proposed Revision 1 to Regulatory

Guide 1.153, ‘‘Criteria for Safety

Systems.’’ This draft regulatory guide

proposed to endorse IEEE Std. 603–1991
Federal Register / Vol. 62, No. 201 / Friday, October 17, 1997 / Rules and Regulations 53933

(including the correction sheet dated

January 30, 1995). Because there were

no adverse public comments to Revision

1 to Regulatory Guide 1.153, the

Commission believes that there is

general public consensus that IEEE Std.

603–1991 provides acceptable criteria

for safety systems in nuclear power

plants.

Discussion

The direct final rule incorporates a

national consensus standard, IEEE Std.

603–1991, for establishing minimal

functional and design requirements for

power, instrumentation, and control

portions of safety systems for nuclear

power plants into NRC regulations. This

action is consistent with the provisions

of the National Technology Transfer and

Advancement Act of 1995, Pub. L. 104–

113, which encourages Federal

regulatory agencies to consider adopting

industry consensus standards as an

alternative to de novo agency

development of standards affecting an

industry. This action is also consistent

with the NRC policy of evaluating the

latest versions of national consensus

standards in terms of their suitability for

endorsement by regulations or

regulatory guides.

Currently, 10 CFR 50.55 a(h) specifies

that ‘‘protection systems’’ for plants

with construction permits issued after

January 1, 1971, must meet the

requirements in IEEE Std. 279 in effect

on the formal docket date of the

application for a construction permit.

IEEE Std. 279 states that a ‘‘protection

system’’ encompasses all electric and

mechanical devices and circuitry (from

sensors to actuation device input

terminals) involved in generating those

signals associated with the protective

function. These signals include those

that actuate reactor trip and that, in the

event of a serious reactor accident,

actuate engineered safeguards such as

containment isolation, core spray, safety

injection, pressure reduction, and air

cleaning. ‘‘Protective Function’’ is

defined by IEEE Std. 279, as ‘‘the

sensing of one or more variables

associated with a particular generating

station condition, signal processing, and

the initiation and completion of the

protective action at values of the

variables established in the design

bases.’’

IEEE Std. 603–1991 uses the term

‘‘safety systems’’ rather than ‘‘protection

systems.’’ A ‘‘safety system’’ is defined

by IEEE Std. 603–1991 as ‘‘a system that

is relied upon to remain functional

during and following design basis

events to ensure: (i) The integrity of the

reactor coolant pressure boundary, (ii)

the capability to shut down the reactor

and maintain it in a safe shut down

condition, or (iii) the capability to

prevent or mitigate the consequences of

accidents that could result in potential

off-site exposures comparable to the 10

CFR part 100 guidelines.’’ A ‘‘safety

function’’ is defined by IEEE Std. 603–

1991 as ‘‘one of the processes or

conditions (for example, emergency

negative reactivity insertion, postaccident heat removal, emergency core

cooling, post-accident radioactivity

removal, and containment isolation)

essential to maintain plant parameters

within acceptable limits established for

a design basis event.’’

The Commission considers that the

systems covered by IEEE Std. 603–1991

and IEEE Std. 279–1971 are the same.

Therefore, for purposes of paragraph (h)

of 10 CFR 50.55a, ‘‘protection systems,’’

and ‘‘safety systems’’ are synonymous.

The Commission notes that these two

terms are also synonymous with the

term ‘‘safety-related systems,’’ used

elsewhere in the Commission’s

regulations. Therefore, licensees are

expected to apply IEEE Std. 279–1971

and IEEE Std. 603–1991, as appropriate,

to ‘‘safety-related systems.’’

This rule mandates the use of IEEE

Std. 603–1991 (including the correction

sheet dated January 30, 1995) for future

nuclear power plants, including final

design approvals, design certifications

and combined licenses under 10 CFR

part 52. Current licensees may continue

to meet the requirements set forth in the

edition or revision of IEEE Std. 279 in

effect on the formal date of their

application for a construction permit or

may, at their option, use IEEE Std. 603–

1991, provided they comply with all

applicable requirements for making

changes to their licensing basis.

However, changes to protection systems

in operating nuclear power plants

initiated on or after January 1, 1998

must meet the requirements in IEEE Std.

603–1991. For purposes of this rule,

‘‘changes’’ to protection systems include

(i) modifications, augmentation or

replacement of protection systems

permitted by license amendments, (ii)

changes made by the licensees pursuant

to procedures in 10 CFR 50.59, and (iii)

plant-specific departures from a design

certification rule under 10 CFR part 52.

In-kind (like-for-like) replacement of

protection system components are not

considered changes to the protection

systems.

Section 3 of IEEE Std. 603–1991

references several industry codes and

standards. If the referenced standard has

been endorsed in a regulatory guide, the

standard constitutes a method

acceptable to the Commission of

meeting a regulatory requirement as

described in the regulatory guide. If a

referenced standard has not been

endorsed in a regulatory guide, the

licensees and applicants may consider

and use the information in the

referenced standard consistent with

current regulatory practices.

Electronic Access

You may also provide comments via

the NRC’s interactive rulemaking

website through the NRC home page

(http://www.nrc.gov). This site provides

the availability to upload comments as

files (any format), if your web browser

supports that function. For information

about the interactive rulemaking

website, contact Ms. Carol Gallagher,

(301) 415–5905 (e-mail: CAG@nrc.gov).

Finding of No Environmental Impact:

Availability of Environmental

Assessment

The Commission has determined

under the National Environmental

Policy Act of 1969, as amended, and the

Commission’s regulations in subpart A

of 10 CFR part 51, that this rule would

not be a major Federal action

significantly affecting the quality of the

human environment and, therefore, an

environment impact statement is not

required. The Commission has prepared

an Environmental Assessment

supporting this finding of no significant

environmental impact.

The NRC has sent a copy of the

environmental assessment and a copy of

the Federal Register Notice to every

State liaison officer and requested their

comments on the environmental

assessment. The environmental

assessment is available for inspection at

the NRC Public Document Room, 2120

L Street NW., Washington, DC. Also, the

NRC has committed itself to complying

in all its actions with the Presidential

Executive Order #12898—Federal

Actions to Address Environmental

Justice in Minority Populations and

Low-Income Populations, dated

February 11, 1994. Therefore, the NRC

also has determined that there are no

disproportionate, high, and adverse

impacts on minority and low-income

populations. The NRC uses the

following working definition of

environmental justice: environmental

justice means the fair treatment and

meaningful involvement of all people,

regardless of race, ethnicity, culture,

income, or educational level with

respect to the development,

implementation, and enforcement of

environmental laws, regulations and

policies.
53934 Federal Register / Vol. 62, No. 201 / Friday, October 17, 1997 / Rules and Regulations

Paperwork Reduction Act Statement

This final rule does not contain a new

or amended information collection

requirement 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, approval No. 3150–0011.

Public Protection Notification

If a document used to impose an

information collection does not display

a currently valid OMB control number,

the NRC may not conduct or sponsor,

and a person is not required to respond

to, an information collection.

Regulatory Analysis

The Commission has prepared a

regulatory analysis which shows that

the proposed amendment does not

impose any new requirements or costs

on current licensees who do not make

changes to safety systems. However,

licensees planning or proposing changes

to power and instrumentation & control

systems will be impacted because they

will be required to meet the

requirements of IEEE Std. 603–1991 for

the changes even though the remainder

of the plant power and I&C systems are

only required to meet their current

licensing basis. The draft regulatory

analysis is available for inspection in

the NRC Public Document Room, 2120

L Street, NW., Washington, DC.

Regulatory Flexibility Certification

As required by the Regulatory

Flexibility Act of 1980 (5 U.S.C. 605(b)),

the Commission certifies that this rule

will not have a significant economic

impact on small entities. This rule

affects only the operation of nuclear

power plants. The companies that own

these plants do not fall within the scope

of the definition of ‘‘small entities’’ set

forth in the Regulatory Flexibility Act or

the small business size standards

adopted by the NRC (10 CFR 2.810).

Since these companies are dominant in

their service areas, this rule does not fall

within the purview of the Act.

Backfit Analysis

The rule requires applicants and

holders of new construction permits,

new operating licenses, new final design

approvals, new design certifications and

combined licenses to comply with IEEE

Std. 603–1991 (including the correction

sheet dated January 30, 1995). Changes

to protection systems in existing

operating plants initiated on or after

January 1, 1998 must meet the

requirements of IEEE Std. 603–1991.

IEEE Std. 279 will continue to apply to

existing nuclear power plants that do

not make any changes to their

protection systems, but the rule permits

the licensee the option of meeting IEEE

Std. 603–1991.

The backfit rule was not intended to

apply to regulatory actions which

change expectations of prospective

applicants, and therefore the backfit rule

does not apply to the portion of the rule

applicable to new construction permits,

new operating licenses, new final design

approvals, new design certifications and

combined licenses. This rule does not

change the licensing basis (i.e., IEEE

Std. 279) for plants that do not intend

to make any changes to their power and

instrumentation and control systems.

However, the rule would require future

changes to existing power and

instrumentation and control portions of

protection systems to comply with the

new standard. This would not be

considered a backfit, since the changes

are voluntarily initiated by the licensee,

or separately imposed by the NRC after

a separate backfit analysis. This is

consistent with past NRC practice and

the discussions on backfitting in

‘‘Value-Impact Statement’’ prepared for

Revision 1 to Regulatory Guide 1.153. A

copy of the Value-Impact Statement is

available for inspection or copying for a

fee in the Commission’s Public

Document Room at 2120 L Street NW.,

Washington, DC, under Task DG–1042.

In summary, the NRC has determined

that the backfit rule, 10 CFR 50.109,

does not apply to this direct final rule

because it does not impose any backfits

as defined in 10 CFR 50.109(a)(1) and,

therefore, a backfit analysis has not been

prepared for this direct final rule.

Small Business Regulatory Enforcement

Fairness Act

In accordance with the Small

Business Regulatory Enforcement

Fairness 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 of

OMB.

List of Subjects in 10 CFR Part 50

Antitrust, Classified information,

Criminal penalties, Fire protection,

Incorporation by reference,

Intergovernmental relations, Nuclear

power plants and reactors, Radiation

protection, Reactor siting criteria, and

Reporting and recordkeeping

requirements.

For the reasons set out in the

preamble and under the authority of the

Atomic Energy Act of 1954, as amended,

the Energy Reorganizations Act of 1974,

as amended, and 5 U.S.C. 552 and 553,

the NRC is adopting the following

amendment to 10 CFR part 50.

PART 50—DOMESTIC LICENSING OF

PRODUCTION AND UTILIZATION

FACILITIES

1. The authority citation for part 50

continues to read as follows:

Authority: Secs. 102, 103, 104, 105, 161,

182, 183, 186, 189, 68 Stat. 936, 937, 938,

948, 953, 954, 955, 956, as amended, sec.

234, 83 Stat. 1244, as amended (42 U.S.C.

2132, 2133, 2134, 2135, 2201, 2232, 2233,

2236, 2239, 2282); secs. 201, as amended,

202, 206, 88 Stat. 1242, as amended, 1244,

1246 (42 U.S.C. 5841, 5842, 5846).

Section 50.7 also issued under Pub. L. 95–

601, sec, 10, 92 Stat. 2951 (42 U.S.C. 5851).

Section 50.10 also issued under secs. 101,

185, 68 Stat. 955 as amended (42 U.S.C. 2131,

2235), sec. 102, Pub. L. 91–190, 83 Stat. 853

(42 U.S.C. 4332). Sections 50.13, and 50.54

(dd), and 50.103 also issued under sec. 108,

68 Stat. 939, as amended (42 U.S.C. 2138),

Sections 50.23, 50.35, 50.55, and 50.56 also

issued under sec. 185, 68 Stat. 955 (42 U.S.C.

2235), Sections 50.33a, 50.55a and Appendix

Q also issued under sec. 102, Pub. L. 91–190,

83 Stat. 853 (42 U.S.C. 4332). Sections 50.34

and 50.54 also issued under sec. 204, 88 Stat.

1245 (42 U.S.C. 5844). Sections 50.58, 50.91,

and 50.92 also issued under Pub. L. 97–415,

96 Stat. 2073 (42 U.S.C. 2239). Section 50.78

also issued under sec. 122, 68 Stat. 939 (42

U.S.C. 2152). Sections 50.80–50.81 also

issued under sec. 184, 68 Stat. 954, as

amended (42 U.S.C. 2234). Appendix F also

issued under sec. 187, 68 Stat. 955 (42 U.S.C.

2237).

12. In § 50.55a, paragraph (h) is

revised to read as follows:

§ 50.55a Codes and standards.

* * * * *

(h) Protection and Safety Systems. (1)

IEEE Std. 603–1991 and the correction

sheet dated January 30, 1995, which are

referenced in paragraph (h)(3) and

(h)(4), are approved for incorporation by

reference by the Director of the Federal

Register in accordance with 5 U.S.C.

552(a) and 1 CFR part 51. A notice of

any changes made to the material

incorporated by reference will be

published in the Federal Register.

Copies of IEEE Std. 603–1991 may be

purchased from the Institute of

Electrical and Electronics Engineers

Service Center, 445 Hoes Lane,

Piscataway, NJ 08855. It is also available

for inspection at the NRC Library, 11545

Rockville Pike, Rockville, MD 20852–

2738, and at the Office of the Federal

Register, 800 North Capital Street, NW,

Suite 700, Washington, DC. IEEE Std.

279, which is referenced in paragraph

(h)(2) of this section was approved for

incorporation by reference by the

Director of the Federal Register in

accordance with 5 U.S.C. 552(a) and 1

CFR part 51. Copies of this standard are

also available as indicated for IEEE Std.

603–1991.
Federal Register / Vol. 62, No. 201 / Friday, October 17, 1997 / Rules and Regulations 53935

(2) Definitions.

(I) For purposes of this paragraph the

terms ‘‘protection systems,’’ ‘‘safety

systems,’’ and ‘‘safety-related systems’’

are synonymous.

(ii) Changes to protection systems

include modification, augmentation or

replacement of protection systems

permitted by license amendments,

changes to protection systems made by

licensees pursuant to 10 CFR 50.59, and

plant specific departures from a design

certification rule under 10 CFR part 52.

(3) Protection systems. For nuclear

power plants with construction permits

issued after January 1, 1971, but prior to

January 1, 1998, protection systems

must meet the requirements set forth

either in the Institute of Electrical and

Electronics Engineers (IEEE) Std. 279,

‘‘Criteria for Protection Systems for

Nuclear Power Generating Stations,’’ or

in IEEE Std. 603–1991, ‘‘Criteria for

Safety Systems for Nuclear Power

Generating Stations,’’ and the correction

sheet dated January 30, 1995. However,

changes to protection systems initiated

on or after January 1, 1998 must meet

the requirements set forth in IEEE Std.

603–1991, and the correction sheet

dated January 30, 1995.

(4) Safety systems. For construction

permits, operating licenses, final design

approvals, design certifications and

combined licenses issued on or after

January 1, 1998, safety systems must

meet the requirements set forth in IEEE

Std. 603–1991, and the correction sheet,

dated January 30, 1995.

Dated at Rockville, this 9th day of October,

1997.

For the Nuclear Regulatory Commission.

John C. Hoyle,

Secretary of the Commission.

[FR Doc. 97–27421 Filed 10–16–97; 8:45 am]

BILLING CODE 7590–01–P

DEPARTMENT OF TRANSPORTATION

Federal Aviation Administration

14 CFR Part 39

[Docket No. 97–ANE–38–AD; Amendment

39–10160; AD 97–21–07]

RIN 2120–AA64

Airworthiness Directives; AlliedSignal

Inc. (Formerly Textron Lycoming)

Model T5313B, T5317A, and T53

(Military) Turboshaft Engines

AGENCY: Federal Aviation

Administration, DOT.

ACTION: Final rule; request for

comments.

SUMMARY: This amendment adopts a

new airworthiness directive (AD) that is

applicable to AlliedSignal Inc. (formerly

Textron Lycoming) Model T5313B,

T5317A, and T53 series military

turboshaft engines approved for

installation on aircraft certified in

accordance with Section 21.25 of the

Federal Aviation Regulations (FAR).

This action requires a one-time visual

inspection of accessory drive carrier

assemblies for affected serial numbers

(S/Ns) designating a defective assembly,

and if the S/N is applicable,

replacement with a serviceable

assembly. This amendment is prompted

by a report of an N2 overspeed

condition due to a defective accessory

drive carrier assembly. The actions

specified in this AD are intended to

prevent accessory drive carrier assembly

failure, which could result in an N2

overspeed and an uncontained engine

failure.

DATES: Effective November 3, 1997.

The incorporation by reference of

certain publications listed in the

regulations is approved by the Director

of the Federal Register as of November

3, 1997.

Comments for inclusion in the Rules

Docket must be received on or before

December 16, 1997.

ADDRESSES: Submit comments in

triplicate to the Federal Aviation

Administration (FAA), New England

Region, Office of the Assistant Chief

Counsel, Attention: Rules Docket No.

97–ANE–38–AD, 12 New England

Executive Park, Burlington, MA 01803–

5299. Comments may also be sent via

the Internet using the following address:

‘‘9-ad-engineprop@faa.dot.gov’’.

Comments sent via the Internet must

contain the docket number in the

subject line.

The service information referenced in

this AD may be obtained from

AlliedSignal Aerospace, Attn: Data

Distribution, M/S 64–3/2101–201, P.O.

Box 29003, Phoenix, AZ 85038–9003;

telephone (602) 365–2493, fax (602)

365–5577. This information may be

examined at the FAA, New England

Region, Office of the Assistant Chief

Counsel, 12 New England Executive

Park, Burlington, MA; or at the Office of

the Federal Register, 800 North Capitol

Street, NW., suite 700, Washington, DC.

FOR FURTHER INFORMATION CONTACT: Ray

Vakili, Aerospace Engineer, Los Angeles

Aircraft Certification Office, FAA,

Transport Airplane Directorate, 3960

Paramount Blvd., Lakewood, CA 90712–

4137; telephone (562) 627–5262, fax

(562) 627–5210.

SUPPLEMENTARY INFORMATION: The

Federal Aviation Administration has

received a report of an N2 overspeed

condition on an AlliedSignal Inc.

(formerly Textron Lycoming) Model

T5317A–1 turboshaft engine. The

investigation revealed that the N2

overspeed condition was caused when

the N2 overspeed governor bevel gear,

which is part of the accessory drive

carrier and cap assembly, shifted out of

position. This gear shifting out of

position was determined to be due to

improper manufacturing of the

accessory drive carrier and cap

assembly, Part Number (P/N) 1–070–

210–01, which is installed on the higher

level assembly, accessory drive carrier

assembly, P/N 1–070–220–03, 1–070–

220–12, or 1–070–220–13. All accessory

drive carrier assemblies, P/Ns 1–070–

220–03, 1–070–220–12, and 1-070–220–

13, installed after November 1, 1985,

and have been identified by serial

number (S/N) are subject to this

inspection. This condition, if not

corrected, could result in accessory

drive carrier assembly failure, which

could result in an N2 overspeed and an

uncontained engine failure.

The FAA has reviewed and approved

the technical contents of AlliedSignal

Inc. Alert Service Bulletin (ASB) No.

T5313B/17A–A0092, Revision 1, dated

July 1, 1997; ASB No. T53–L–13B–

A0092, dated June 4, 1997; and ASB No.

T53–L–703–A0092, dated June 4, 1997.

These ASBs describe procedures for

performing a one-time visual inspection

of accessory drive carrier assemblies for

affected S/Ns designating a defective

assembly, and if the S/N is applicable,

replacement with a serviceable

assembly.

Since an unsafe condition has been

identified that is likely to exist or

develop on other engines of the same

type design, this AD is being issued to

prevent accessory drive carrier assembly

failure. This AD requires a one-time

visual inspection of accessory drive

carrier assemblies for affected S/Ns

designating a potentially defective

assembly, and if the S/N is applicable,

replacement with a serviceable

assembly. The actions are required to be

accomplished in accordance with the

ASBs described previously.

Since a situation exists that requires

the immediate adoption of this

regulation, it is found that notice and

opportunity for prior public comment

hereon are impracticable, and that good

cause exists for making this amendment

effective in less than 30 days.

Comments Invited

Although this action is in the form of

a final rule that involves requirements

affecting flight safety and, thus, was not

preceded by notice and an opportunity