Federal Register / Vol. 62, No. 53 / Wednesday, March 19, 1997 / Notices 13171

collection is the only national level data

collection, furnishing information on

sentencing, time served in State prisons,

and time served on parol. The NCRP

also contains other individual level of

data on prisoners, including offense,

admission/release type, and

demographics. The Bureau of Justice

Statistics, the Congress, researchers,

practioners, and others in the criminal

justice community use these data to

enumerate and describe annual

movements of adult offenders

throughout state correctional systems.

(5) An estimate of the total number of

respondents and the amount of time

estimated for an average respondent to

respond: 41 respondents at an average 2

hours per response.

(6) An estimate of the total public

burden (in hours) associated with the

collection: 1,643 burden hours.

If additional information is required

contact: Mr. Robert B. Briggs,

Department Clearance Officer,

Information Management and Security

Staff, Justice Management Division,

United States Department of Justice,

Suite 850, Washington Center, 1001 G

Street, NW, Washington, DC 20530.

Dated: March 14, 1997.

Robert B. Briggs,

Department Clearance Officer, United States

Department of Justice.

[FR Doc. 97–6874 Filed 3–18–97; 8:45 am]

BILLING CODE 4410–18–M

DEPARTMENT OF LABOR

Pension and Welfare Benefits

Administration

Working Group Studying Soft Dollar

Arrangements and Commission

Recapture Advisory Council on

Employee Welfare and Pension

Benefits Plans; Notice of Meeting

Pursuant to the authority contained in

Section 512 of the Employee Retirement

Income Security Act of 1974 (ERISA), 29

U.S.C. 1142, a public meeting will be

held April 8 of the Advisory Council on

Employee Welfare and Pension Benefit

Plans’ new Working Group being

formed to Study Soft Dollar

Arrangements and Commission

Recapture.

The session will take place in Room

N–5437 A&B, U.S. Department of Labor

Building, Second and Constitution

Avenue, NW, Washington, D.C. 20210.

The purpose of the open meeting, which

will run from 1:00 p.m. to

approximately 3:30 p.m., is for Working

Group members to begin organizing its

study for the year and, it is hoped, to

begin taking testimony on the topic.

Members of the public are encouraged

to file a written statement pertaining to

any topic concerning ERISA by

submitting 20 copies on or before April

1, 1997, to Sharon Morrissey, Executive

Secretary, ERISA Advisory Council,

U.S. Department of Labor, Room N–

5677, 200 Constitution Avenue, NW,

Washington, D.C. 20210. Individuals or

representatives of organizations wishing

to address the Working Group on Soft

Dollar Arrangements and Commission

Recapture should forward their request

to the Executive Secretary or telephone

(202) 219–8753. Oral presentations will

be limited to 10 minutes, but an

extended statement may be submitted

for the record. Individuals with

disabilities, who need special

accommodations, should contact Sharon

Morrissey by April 1, at the address

indicated in this notice.

Organizations or individuals may also

submit statements for the record

without testifying. Twenty (20) copies of

such statements should be sent to the

Executive Secretary of the Advisory

Council at the above address. Papers

will be accepted and included in the

record of the meeting if received on or

before April 1.

Signed at Washington, D.C. this 12 day of

March, 1997.

Olena Berg,

Assistant Secretary, Pension and Welfare

Benefits Administration.

[FR Doc. 97–6896 Filed 3–18–97; 8:45 am]

BILLING CODE 4510–29–M

NATIONAL AERONAUTICS AND

SPACE ADMINISTRATION

[Notice 97–029]

NASA Advisory Council (NAC), Space

Science Advisory Committee (SScAC),

Sun-Earth Connection Advisory

Subcommittee; Meeting

AGENCY: National Aeronautics and

Space Administration.

ACTION: Notice of meeting.

SUMMARY: In accordance with the

Federal Advisory Committee Act, Pub.

L. 92–463, as amended, the National

Aeronautics and Space Administration

announces a meeting of the NASA

Advisory Council, Space Science

Advisory Committee, Sun-Earth

Connection Advisory Subcommittee.

DATES: Monday, March 24, 1997, 8:30

a.m. to 5:00 p.m.; Tuesday, March 25,

1997, 8:30 a.m. 5:00 p.m.

ADDRESSES: Southwest Research

Institution, Building 189, Conference

Room, San Antonio, TX.

FOR FURTHER INFORMATION CONTACT:

George L. Withbroe, Code SA, National

Aeronautics and Space Administration,

Washington, DC 20546, (202) 358–2150.

SUPPLEMENTARY INFORMATION: The

meeting will be open to the public up

to the capacity of the room. The agenda

for the meeting is as follows:

—Review of Charge from Space Science

Advisory Committee —Review of Sun-Earth Connection

Roadmap —Solar Terrestrial Probe line goals

—Presentation of Solar B

—Presentation of Geospace Multisats

—Formulation of Prioritization Process

—Develop Consensus on Mission

Priorities.

It is imperative that the meeting be

held on these dates to accommodate the

scheduling priories of the key

participants, and in order for the

Subcommittee to complete its report in

May.

Dated: March 14, 1997.

Leslie M. Nolan,

Advisory Committee Management Officer,

National Aeronautics and Space

Administration.

[FR Doc. 97–6946 Filed 3–18–97; 8:45 am]

BILLING CODE 7510–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–318]

Baltimore Gas and Electric Company;

Notice of Consideration of Issuance to

Amendment to Facility Operating

License, Proposed no Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. DPR–

69 isssued to Baltimore Gas and Electric

Company (BGE), for operation of the

Calvert Cliffs Nuclear Power Plant, Unit

No. 2, located in Calvert County,

Maryland. The proposed amendment would

allow a modification to the Unit 2

Service Water System (SWS) which

constitutes an unreviewed safety

question as described in 10 CFR 50.59.

BGE proposes to add a nitrogen system

to the SWS head tanks to increase the

pressure in the SWS by approximately

15 psi. This proposed modification is in

response to the water hammer concerns

expressed in Generic Letter (GL) 96–06.

The concern of the GL was that a lossof-offsite power would disable the SWS

pumps and stop flow in the SWS for a

short time. If this situation should occur

concurrent with a loss-of-coolant
13172 Federal Register / Vol. 62, No. 53 / Wednesday, March 19, 1997 / Notices

accident or main steam line break, the

water in the containment air coolers

(CACs) could boil as a result of the

energy released to containment by the

accident. The boiling would form steam

voids in the CACs. The voids would

collapse when SWS flow was reestablished and the collapse, combined

with the returning flow, would cause a

water hammer, challenging the CAC(s)

and/or the related SWS piping. As

discussed in a letter from Mr. C. H.

Cruse dated January 28, 1997, the CACs

and associated equipment were shown

to be operable under these conditions.

After considering several options, it

was determined that the best method for

resolving this concern is to increase the

pressure in the SWS above the fluid

saturation point, thus providing a means

to prevent boiling in the CACs until the

SWS pumps automatically restart.

Before issuance of the proposed

license amendment, the Commission

will have made findings required by the

Atomic Energy Act of 1954, as amended

(the Act) and the Commission’s

regulations.

The Commission has made a

proposed determination that the

amendment request involves no

significant hazards consideration. Under

the Commission’s regulations in 10 CFR

50.92, this means that operation of the

facility in accordance with the proposed

amendment would not (1) involve a

significant increase in the probability or

consequences of an accident previously

evaluated; or (2) create the possibility of

a new or different kind of accident from

any accident previously evaluated; or

(3) involve a significant reduction in a

margin of safety. As required by 10 CFR

50.91 (a), the licensee has provided its

analysis of the issue of no significant

hazards consideration, which is

presented below:

1. Would not involve a significant increase

in the probability or consequences of an

accident previously evaluated.

Neither the [SWS] nor any [SWS]

component is an initiator to an accident. The

[SWS] provides cooling to safety-related

equipment following an accident. It supports

accident mitigation functions. Therefore, this

proposed modification does not significantly

increase the probability of an accident

previously evaluated.

The [SWS] provides cooling water to the

containment air coolers to mitigate the

consequences of a loss-of-accident or main

steam line break. A loss of nitrogen pressure

to the [SWS] due to a single active failure has

been evaluated. Since the nitrogen

pressurization system is redundant, a single

active failure in the nitrogen system would

not prevent the [SWS] from performing its

safety function. Therefore this proposed

modification does not involve a significant

increase in the consequences of an accident.

Therefore, this proposed modification does

not involve a significant increase in the

probability or consequences of an accident

previously evaluated.

2. Would not create the possibility of a new

or different type of accident from any

accident previously evaluated.

The [SWS] provides cooling water to the

containment air coolers and emergency

diesel generators. The purpose of the

components which are affected by this

proposed modification is to mitigate

accidents. This proposed modification does

not change equipment function, or

significantly alter the method of operating

equipment to be modified. The system will

continue to operate in essentially the same

manner as before the proposed modification

was done.

Therefore, the proposed changes does not

create the possibility of a new or different

type of accident from any accident

previously evaluated.

3. Would not involve a significant

reduction in a margin of safety.

The margin of safety in this case is the

degree to which a single failure of the

nitrogen system can affect the [SWS], since

it connects to both [SWS] head tanks. To

determine if there would be an adverse effect

on plant safety resulting from this proposed

modification, an evaluation of malfunctions

of the nitrogen pressurization system was

conducted. The only credible malfunctions

are those related to failure of the pressure

regulator. Even if a regulator were to fail

open or closed, the [SWS] can perform its

safety function. The proposed modification

includes design features which ensure that

pressure is maintained in each subsystem,

even if this single failure occurs. Therefore,

this proposed modification maintains the

ability of the [SWS] to properly respond to

an accident.

Therefore, this proposed modification does

not significantly reduce the margin of safety.

The NRC staff has reviewed the

licensee’s analysis and, based on this

review, it appears that the three

standards of 10 CFR 50.92(c) are

satisfied. Therefore, the NRC staff

proposes to determine that the

amendment request involves no

significant hazards consideration.

The Commission is seeking public

comments on this proposed

determination. Any comments received

within 30 days after the date of

publication of this notice will be

considered in making any final

determination.

Normally, the Commission will not

issue the amendment until the

expiration of the 30-day notice period.

However, should circumstances change

during the notice period such that

failure to act in a timely way would

result, for example, in derating or

shutdown of the facility, the

Commission may issue the license

amendment before the expiration of the

30-day notice period, provided that its

final determination is that the

amendment involves no significant

hazards consideration. The final

determination will consider all public

and State comments received. Should

the Commission take this action, it will

publish in the Federal Register a notice

of issuance and provide for opportunity

for a hearing after issuance. The

Commission expects that the need to

take this action will occur very

infrequently.

Written comments may be submitted

by mail to the Chief, Rules Review and

Directives Branch, Division of Freedom

of Information and Publications

Services, Office of Administration, U.S.

Nuclear Regulatory Commission,

Washington, DC 20555–0001, and

should cite the publication date and

page number of this Federal Register

notice. Written comments may also be

delivered to Room 6D22, Two White

Flint North, 11545 Rockville Pike,

Rockville, Maryland, from 7:30 a.m. to

4:15 p.m. Federal workdays. Copies of

written comments received may be

examined at the NRC Public Document

Room, the Gelman Building, 2120 L

Street, NW., Washington, DC.

The filing of requests for hearing and

petitions for leave to intervene is

discussed below.

By April 18, 1997, the licensee may

file a request for a hearing with respect

to issuance of the amendment to the

subject facility operating license any

person whose interest may be affected

by this proceeding and who wishes to

participate as a party in the proceeding

must file a written request for a hearing

and a petition for leave to intervene.

Requests for a hearing and a petition for

leave to intervene. Requests for a

hearing and a petition for leave to

intervene shall be filed in accordance

with the Commission’s ‘‘Rules of

Practice for Domestic Licensing

Proceedings’’ in 10 CFR part 2.

Interested persons should consult a

current copy of 10 CFR 2.714 which is

available at the Commission’s Public

Document Room, the Gelman Building,

2120 L Street, NW., Washington, DC,

and at the local public document room

located at the Calvert County Library,

Prince Frederick, Maryland 20678. If a

request for a hearing or petition for

leave to intervene is filed by the above

date, the Commission or an Atomic

Safety and Licensing Board, designated

by the Commission or by the Chairman

of the Atomic Safety and Licensing

Board Panel, will rule on the request

and/or petition; and the Secretary or the

designated Atomic Safety and Licensing

Board will issue a notice of hearing or

an appropriate order.

As required by 10 CFR 2.714, a

petition for leave to intervene shall set
Federal Register / Vol. 62, No. 53 / Wednesday, March 19, 1997 / Notices 13173

forth with particularity the interest of

the petitioner in the proceeding, and

how that interest may be affected by the

results of the proceeding. The petition

should specifically explain the reasons

why intervention should be permitted

with particular reference to the

following factors: (1) The nature of the

petitioner’s right under the Act to be

made party to the proceeding; (2) the

nature and extent of the petitioner’s

property, financial, or other interest in

the proceeding; and (3) the possible

effect of any order which may be

entered in the proceeding on the

petitioner’s interest. The petition should

also identify the specific aspect(s) of the

subject matter of the proceeding as to

which petitioner wishes to intervene.

Any person who has filed a petition for

leave to intervene or who has been

admitted as a party may amend the

petition without requesting leave of the

Board up to 15 days prior to the first

prehearing conference scheduled in the

proceeding, but such an amended

petition must satisfy the specificity

requirements described above.

Not later than 15 days prior to the first

prehearing conference scheduled in the

proceeding, a petitioner shall file a

supplement to the petition to intervene

which must include a list of the

contentions which are sought to be

litigated in the matter. Each contention

must consist of a specific statement of

the issue of law or fact or be raised or

controverted. In addition, the petitioner

shall provide a brief explanation of the

bases of the contention and a concise

statement of the alleged facts or expert

opinion which support the contention

and on which the petitioner intends to

rely in proving the contention at the

hearing. The petitioner must also

provide references to those specific

sources and documents of which the

petitioner is aware and on which the

petitioner intends to rely to establish

those facts or expert opinion. Petitioner

must provide sufficient information to

show that a genuine dispute exists with

the applicant on a material issue of law

or fact. Contentions shall be limited to

matters within the scope of the

amendment under consideration. The

contention must be one which, if

proven, would entitle the petitioner to

relief. A petitioner who fails to file such

a supplement which satisfies these

requirements with respect to be least

one contention will not be permitted to

participate as a party.

Those permitted to intervene become

parties to the proceeding, subject to any

limitations in the order granting leave to

intervene, and have the opportunity to

participate fully in the conduct of the

hearing, including the opportunity to

present evidence and cross-examine

witnesses.

If a hearing is requested, the

Commission will make a final

determination on the issue of no

significant hazards consideration. The

final determination will serve to decide

when the hearing is held.

If the final determination is that the

amendment request involves no

significant hazards consideration, the

Commission may issue the amendment

and make it immediately effective,

notwithstanding the request for a

hearing. Any hearing held would take

place after issuance of the amendment.

If the final determination is that the

amendment request involves a

significant hazards consideration, any

hearing held would take place before

the issuance of any amendment.

A request for a hearing or a petition

for leave to intervene must be filed with

the Secretary of the Commission, U.S.

Nuclear Regulatory Commission,

Washington, DC 20555–0001, Attention:

Docketing and Services Branch, or may

be delivered to the Commission’s Public

Document Room, the Gelman Building,

2120 L Street, NW., Washington, DC, by

the above date. Where petitions are filed

during the last 10 days of the notice

period, it is requested that the petitioner

promptly so inform the Commission by

a toll-free telephone call to Western

Union at 1–(800) 248–5100 (in Missouri

1–(800) 342–6700). The Western Union

operator should be given Datagram

Identification Number N1023 and the

following message addressed to S. Singh

Bajwa: petitioner’s name and telephone

number, date petition was mailed, plant

name, and publication date and page

number of this Federal Register notice.

A copy of the petition should also be

sent to the Office of the General

Counsel, U.S. Nuclear Regulatory

Commission, Washington, DC 20555–

0001, and to Jay E. Silbert, Esquire,

Shaw, Pittman, Potts and Trowbridge,

2300 N Street, NW., Washington, DC,

attorney for the licensee.

Nontimely filings of petitions for

leave to intervene, amended petitions,

supplemental petitions and/or requests

for hearing will not be entertained

absent a determination by the

Commission, the presiding officer or the

presiding Atomic Safety and Licensing

Board that the petition and/or request

should be granted based upon a

balancing of the factors specified in 10

CFR 2.714(a)(1)(i)-(v) and 2.714(d).

For further details with respect to this

action, see the application for

amendment dated March 6, 1997, which

is available for public inspection at the

Commission’s Public Document Room,

the Gelman Building, 2120 L Street,

NW., Washington, DC, and at the local

public document room located at the

Calvert County Library, Prince

Frederick, Maryland 20678.

Dated at Rockville, Maryland, this 12th day

of March 1997.

For the Nuclear Regulatory Commission.

Alexander W. Dromerick,

Senior Project Manager, Project Directorate

I–1, Division of Reactor Projects—I/II, Office

of Nuclear Reactor Regulation.

[FR Doc. 97–6881 Filed 3–18– 97; 8:45 am]

BILLING CODE 7590–01–P

[Docket No. 50–286]

Power Authority of the State of New

York; Notice of Consideration of

Issuance of Amendment to Facility

Operating License, Proposed no

Significant Hazards Consideration

Determination, and Opportunity for a

Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. DPR–

64 issued to New York Power Authority

(NYPA) for operation of the Indian Point

Nuclear Generating Unit No. 3 (IP3)

located in Westchester County, New

York.

The proposed amendment would add

several containment isolation valves to

the list of containment isolation valves

in the technical specifications and

amends the technical specifications to

allow the use of performance-based

methods described in 10 CFR Part 50,

Appendix J, Option B for containment

leakage rate testing.

Before issuance of the proposed

license amendment, the Commission

will have made findings required by the

Atomic Energy Act of 1954, as amended

(the Act) and the Commission’s

regulations.

The Commission has made a

proposed determination that the

amendment request involves no

significant hazards consideration. The

proposed amendment changes the TS to

implement 10 CFR Part 50, Appendix J,

Option B, by referencing Regulatory

Guide 1.163, ‘‘Performance-Based

Containment Leakage-Test Program.’’

Under the Commission’s regulations in

10 CFR 50.92, this means that operation

of the facility in accordance with the

proposed amendment would not (1)

involve a significant increase in the

probability or consequences of an

accident previously evaluated; or (2)

create the possibility of a new or

different kind of accident from any

accident previously evaluated; or (3)

involve a significant reduction in a