Federal Register / Vol. 60, No. 52 / Friday, March 17, 1995 / Notices 14467

[NAFTA–00319]

Woodward Governor Co., Stevens

Point, WI.; Amended Certification

Regarding Eligibility to Apply for

NAFTA Transitional Adjustment

Assistance

In accordance with Section 250(a),

Subchapter D, Chapter 2, Title II, of the

Trade Act of 1974, as amended (19

U.S.C. 2273), the Department of Labor

issued a Certification for NAFTA

Transitional Adjustment Assistance on

February 3, 1995, applicable to all

workers of the Aircraft Controls Group

of the subject firm in Stevens Point,

Wisconsin. The notice was published in

the Federal Register on February 14,

1995 (60 FR 8416).

At the request of the State Agency and

the company, the Department reviewed

the certification for workers of the

subject firm. New findings show that

some production was in hydromatic

controls. The workers were not entirely

separately identifiable by product line

and the plant will close in 1995.

Accordingly, the Department is

amending the certification to include all

workers at Woodward Governor

Company in Stevens Point, Wisconsin.

The intent of the Department’s

certification is to include all workers

who were adversely affected at

Woodward Governor Company in

Stevens Point, Wisconsin by increased

imports.

The amended notice applicable to

NAFTA—00319 is hereby issued as

follows:

All workers of the Woodward Governor

Company, Stevens Point, Wisconsin who

became totally or partially separated from

employment on or after December 27, 1993

are eligible to apply for NAFTA–TAA under

Section 250 of the Trade Act of 1974.

Signed at Washington, D.C., this 3rd day of

March 1995.

Victor J. Trunzo,

Program Manager, Policy and Reemployment

Services, Office of Trade Adjustment

Assistance.

[FR Doc. 95–6655 Filed 3–16–95; 8:45 am]

BILLING CODE 4510–30–M

NATIONAL SCIENCE FOUNDATION

Advisory Committee for Biological

Sciences (BIO); Notice of Meeting

In accordance with the Federal

Advisory Committee Act (Pub. L. 92–

463, as amended), the National Science

Foundation announces the following

meeting:

Name: Advisory Committee for Biological

Sciences (BIO) (1110).

Date and Time: April 3, 1995; 8:45 a.m.–

6 p.m.; April 4, 1995; 8:45 a.m.–12 Noon.

Place: National Science Foundation, 4201

Wilson Blvd., Arlington, VA 22230, Room

1235.

Type of Meeting: Open.

Contact Person: Dr. Mary E. Clutter,

Assistance Director, Biological Sciences,

Room 605, National Science Foundation,

4201 Wilson Blvd., Arlington, VA 22230, Tel

No.: (703) 306–1400.

Minutes: May be obtained from the contact

person listed above.

Purpose of Meeting: The Advisory

Committee for BIO provides advice,

recommendations, and oversight concerning

major program emphases, directions, and

goals for the research-related activities of the

divisions that make up BIO.

Agenda: NSF and BIO strategic planning;

integration of research and education.

Dated: March 14, 1995.

M. Rebecca Winkler,

Committee Management Officer.

[FR Doc. 95–6679 Filed 3–16–95; 8:45 am]

BILLING CODE 7555–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 30–16055–ML–Ren, ASLBP No.

95–707–02–ML–Ren, (Source Material

License No. 34–19089–01)]

Atomic Safety and Licensing Board

Panel; Notice of Hearing

March 13, 1995.

In the Matter of Advanced Medical

Systems, Inc. Cleveland, Ohio.

Notice is hereby given that, by

Memorandum and Order dated March

10, 1995, the Presiding Officer in this

proceeding has granted the hearing

requests of the Northeast Ohio Regional

Sewer District (dated December 29,

1994) and the City of Cleveland, Ohio

(dated January 13, 1995), and has

conditionally granted the participation

of the Cuyahoga County Local

Emergency Planning Committee in a

hearing regarding the license renewal

application of Advanced Medical

Systems, Inc. for its facility located at

1020 London Road in Cleveland, Ohio.

Advanced Medical Systems, Inc. seeks

continued permission from the Nuclear

Regulatory Commission to possess

various quantities of radioactive

materials for use in its manufacture of

medically related devices. The hearing

will involve the sufficiency of the

renewal application.

This proceeding will be conducted

under the Commission’s Informal

Hearing Procedures for Adjudications in

Materials and Operator Licensing

Proceedings, set forth in 10 CFR part 2,

subpart L. Further details appear in

Statement of Considerations, Informal

Hearing Procedures for Materials

Licensing Adjudications, 54 Fed. Reg.

8269 (February 28, 1989) and the March

10, 1995 Memorandum and Order

referenced above. Documents relating to

this proceeding are available for public

inspection and copying at the

Commission’s Public Document Room,

Gelman Building, 2120 L St. NW.,

Washington, DC.

Advanced Medical Systems, Inc., the

Northeast Ohio Regional Sewer District,

the City of Cleveland, and the NRC Staff

are parties to this proceeding. The

Cuyahoga County Local Emergency

Planning Committee may participate in

this proceeding under the provisions of

10 CFR 2.1211(b) upon submission to

the Presiding Officer (and service on the

parties) of an affidavit of a Cuyahoga

County official attesting that the Local

Emergency Planning Committee is

representing the County’s interest in

this matter. If admitted as a

representative of an interested county,

the Local Emergency Planning

Committee’s participation shall be

limited to the extent allowed by 10 CFR

2.1211(b).

In accordance with 10 CFR

2.1205(l)(4), any person whose interest

may be affected by this proceeding may,

within 30 days of publication of this

Notice, file a petition for leave to

intervene. Such petition must identify

(1) the interest of the petitioner in the

proceeding, (2) how that interest may be

affected by the results of the proceeding,

with particular reference to the factors

set out in 10 CFR 2.1205(g), (3) the

petitioner’s areas of concern about the

licensing activity which must be

germane to the subject matter of the

proceeding, and (4) the circumstances

establishing that the petition is timely

and that the petitioner has the requisite

standing to intervene in the hearing.

Each petition must be submitted to

the Secretary of the Commission, ATTN:

Chief, Docketing and Services Branch,

U.S. Nuclear Regulatory Commission,

Washington, DC 20555. Copies should

be served upon the Presiding Officer;

the Special Assistant; the Assistant

General Counsel for Hearings and

Enforcement; the Senior Attorney,

Atomic Safety and Licensing Board

Panel; and the Executive Director for

Operations, U.S. Nuclear Regulatory

Commission, Washington, DC 20555.

Copies should also be served on the

Licensee, through its attorney, Henry E.

Billingsley, II, Arter and Hadden, 1100

Huntington Building, 925 Euclid

Avenue, Cleveland, Ohio 44115; and the

other parties through Thomas E.

Lenhart, Assistant General Counsel,

Northeast Ohio Regional Sewer District,

3826 Euclid Avenue, Cleveland, Ohio
14468 Federal Register / Vol. 60, No. 52 / Friday, March 17, 1995 / Notices

44115; and Martha R. McCorkle,

Assistant Director of Law, City of

Cleveland Department of Law, Room

106, City Hall, 601 Lakeside Avenue,

Cleveland, Ohio 44114. Pursuant to 10

CFR 2.1205(j)(2), any party may file an

answer to a petition to intervene within

10 days of service of such petition (15

days in the case of the NRC Staff).

Pursuant to 10 CFR 2.1211(a), any

member of the public who is not a party

to this proceeding may make a written

statement in order to express his or her

views of the issues involved in this

license renewal proceeding. These

statements are not evidence and do not

become part of the decisional record

under 10 CFR 2.1251(c). Written

statements should be submitted to the

Secretary of the Commission, ATTN:

Chief, Docketing and Services Branch,

U.S. Nuclear Regulatory Commission,

Washington, DC 20555.

Dated: March 13, 1995.

Marshall E. Miller,

Presiding Officer, Administrative Judge.

[FR Doc. 95–6617 Filed 3–16–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket Nos. 50–373 50–374

Exemption

In the Matter of Commonwealth Edison

Co., LaSalle County Station, Units 1 and 2.

I

Commonwealth Edison Company

(ComEd, the licensee) is the holder of

Facility Operating License Nos. NPF–11

and NPF–18, which authorize operation

of the LaSalle County Station, Units 1

and 2 (the facility), at a steady state

power level not in excess of 3323

megawatts thermal. The facility consists

of two boiling water reactors at the

licensee’s site located in LaSalle

County, Illinois. The licenses provide,

among other things, that they are subject

to all rules, regulations, and orders of

the U.S. Nuclear Regulatory

Commission (the Commission) now or

hereafter in effect.

II

Section III.A.6(b) of Appendix J to 10

CFR Part 50 states the following in

regard to performing Overall Integrated

Containment Leakage Rate (Type A)

Tests (ILRT):

If two consecutive periodic Type A tests

fail to meet the applicable acceptance criteria

in III.A.5(b), notwithstanding the periodic

retest schedule of III.D., a Type A test shall

be performed at each plant shutdown for

refueling or approximately every 18 months,

whichever occurs first, until two consecutive

Type A tests meet the acceptance criteria in

III.A.5(b), after which time the retest

schedule specified in III.D. may be resumed.

The Type A tests performed during

the first, third and fourth refueling

outages for LaSalle County Station, Unit

2, were considered to be failures in the

‘‘as-found’’ condition due to penalties

incurred as a result of leakage measured

in Type B and C local leak rate tests

(LLRT). Pursuant to Section III.A.6(b) of

Appendix J, Type A testing was

performed during the fifth refueling

outage for LaSalle County Station, Unit

2, in December 1993. That Type A test

satisfied the ‘‘as-found’’ acceptance

criteria. Section III.A.6(b) of Appendix J

requires an additional Type A test

during the sixth refueling outage,

currently scheduled for February 1995,

in order to fulfill the condition of two

consecutive successful tests prior to

resuming the Type A test interval of

Section III.D.

As an alternative to performing the

required Type A test, the licensee has

submitted a Corrective Action Plan to

address excessive local leakage in

accordance with the guidance provided

in NRC Information Notice 85–71,

‘‘Containment Integrated Leak Rate

Tests,’’ dated August 22, 1985. The

Corrective Action Plan is in lieu of the

increased test frequency required by

Section III.A.6(b) and, therefore, an

exemption from this requirement is

needed.

Section III.D.1(a) of Appendix J

requires ‘‘* * * a set of three Type A

tests shall be performed, at

approximately equal intervals during

each 10-year service period. The third

test of each set shall be conducted when

the plant is shutdown for the 10-year

plant inservice inspections.’’ The last

refueling outage for Unit 2 during the

first 10-year inservice inspection period

is the sixth refueling outage scheduled

for February 1995. Therefore, in

addition to the requirements for

additional testing specified in Section

III.A.6(b), a Type A test is required

during the upcoming Unit 2 refueling

outage as a result of the periodic retest

schedule contained in Section III.D.1(a).

To address the short-term desire not to

perform a Type A test during the sixth

refueling outage for Unit 2 and avoid

potential future problems, the licensee

has requested an exemption from this

requirement such that future Type A

test would not need to coincide with the

end of 10-year inservice inspection

periods.

The NRC may grant exemptions from

the requirements of the regulations,

pursuant to 10 CFR 50.12, that (1) are

authorized by law, will not present an

undue risk to the public health and

safety, and are consistent with the

common defense and security; and (2)

present special circumstances. Section

50.12(a)(2) of 10 CFR Part 50 describes

special circumstances as including cases

that would not serve the underlying

purpose of the rule or are not necessary

to achieve the underlying purpose of the

rule.

III

The underlying purpose of the

requirements in Appendix J is to ensure

that containment leakage remains below

criteria established to limit the release

of radioactive materials in the event of

a design basis accident. The Type A test

is defined in 10 CFR Part 50, Appendix

J, Section II.F, as a ‘‘test intended to

measure the primary reactor

containment overall integrated leakage

rate (1) after the containment has been

completed and is ready for operation,

and (2) at periodic intervals thereafter.’’

Containment leakage is measured

during the periodic testing required by

Section III.D.1(a) and the additional

testing requirements of Section III.A.6 if

the measured leakage exceeds the

established limits. The testing and other

requirements contained in Appendix J

ensure that leakage from the

containment structure and penetrations

remain below the acceptance criteria.

The licensee conducted four ILRTs

during the first 10-year service period

for Unit 1. For Unit 2, ILRTs were

performed during the first, third, fourth,

and fifth refueling outages. The Type A

test history for Unit 2 is that the

measured leakage rates for Type B and

C penetrations, when added to the

measured results from the Type A test,

resulted in an ‘‘as-found’’ integrated

leakage rate above the acceptance

criteria. These test failures were the

direct result of leakage penalties from

Type B and C LLRTs.

Leakage from specific containment

penetrations that have been major

contributors to the failure of the

integrated leakage rate acceptance

criteria for Unit 2 have been identified.

These leakage paths include isolation

valves associated with the drywell

equipment and floor drain sumps,

reactor water cleanup suction,

transversing incore probe air purge

supply, residual heat removal shutdown

cooling return, hydrogen recombiners,

and primary containment chilled water

supply. The leakage associated with the

reactor water cleanup suction

penetration provided the overwhelming

contribution of local leakage penalty

that resulted in the unsuccessful test

during the fourth refueling outage.

Leakage through the various isolation

valves has been attributed to causes