12576 Federal Register / Vol. 60, No. 44 / Tuesday, March 7, 1995 / Notices

nonradiological plant effluents and has

no other environmental impact.

Accordingly, the NRC staff concludes

that there are no significant

nonradiological environmental impacts

associated with the proposed action.

Alternatives to the Proposed Action

As an alternative to the proposed

action, the staff considered denial of the

proposed action. Denial of the

application would result in no changes

to current environmental impacts. The

environmental impacts of the proposed

action and the alternative action are

similar.

Alternate Use of Resources

This action does not involve the use

of any resources not previously

considered in the Final Environmental

Statement for the Perry Nuclear Power

Plant, Units 1 and 2, documented in

NUREG–0884.

Agencies and Persons Consulted

In accordance with its stated policy,

the staff consulted with the State of

Ohio regarding the environmental

impact of the proposed action. The state

of Ohio official had no comments.

Finding of No Significant Impact

Based upon the environmental

assessment, the Commission concludes

that the proposed action will not have

a significant effect on the quality of the

human environment. Accordingly, the

Commission has determined not to

prepare an environmental impact

statement for the proposed action.

For further details with respect to the

proposed action, see the licensee’s

letters dated September 27, 1993, and

December 16, 1994, which are available

for public inspection at the

Commission’s Public Document Room,

The Gelman Building, 2120 L Street,

NW, Washington, DC 20555, and at the

local public document room located at

the Perry Public Library, 3753 Main

Street, Perry, Ohio 44081.

Dated at Rockville, MD., this 28th day of

February 1995.

For the Nuclear Regulatory Commission.

Jon B. Hopkins, Sr.,

Project Manager, Project Directorate III–3,

Division of Reactor Project—III/IV, Office of

Nuclear Reactor Regulation.

[FR Doc. 95–5493 Filed 3–6–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Nuclear

Waste; Meeting

The Advisory Committee on Nuclear

Waste (ACNW) will hold its 72nd

meeting on March 15–16, 1995, in Room

T–2B1, 11545 Rockville Pike, Rockville,

Maryland. The meeting will be open to

public attendance, with the exception of

portions that may be closed to discuss

information and release of which would

constitute a clearly unwarranted

invasion of personal privacy pursuant to

5 U.S.C. 522b(c)(6).

The agenda for this meeting shall be

as follows: Wednesday and Thursday,

March 15 and 16, 1995—8:30 a.m. until

6 p.m.

During this meeting the Committee

plans to consider the following:

A. DOE’s Program Approach—The

Committee will hear presentations and

hold discussions with representatives of

the Department of Energy and the NRC

staff on DOE’s program approach for a

site suitability determination at the

Yucca Mountain site.

B. DOE’s Engineered Barrier System

Program—The Committee will hear

presentations and hold discussions with

representatives of the Department of

Energy and the NRC staff of DOE’s

efforts to design an engineered-barrier

system for the proposed high-level

radioactive waste repository.

C. Disposal of Baghouse Dirt—The

Committee will hear a presentation by

the NRC staff on the issues associated

with the management and disposal of

the mixed waste which is created when

scrap steel being recycled in an electric

arc furnace becomes inadvertently

contaminated by a cesium source. The

Florida Steel Corporation will also

address the Committee on this issue.

D. Branch Technical Position on LowLevel Radioactive Waste Performance

Assessment—The Committee will

review issues associated with the NRC

staff’s Branch Technical Position on

Low-Level Radioactive Waste

Performance Assessment as outlined in

a recent Commission paper.

E. Groundwater Travel Time—The

Committee will review the approach

proposed by the NRC staff for

compliance evaluation associated with

the groundwater travel time requirement

in 10 CFR part 60. Presentations will

also be made by ACNW consultants

regarding their views on this topic.

F. Meet with the Director, NRC’s

Division of Waste Management, Nuclear

Materials Safety & Safeguards—The

Director will provide information to the

Committee on current waste

management issues, which may include

the status of site characterization work

at the Yucca Mountain site, and preview

staff development of a technical

position on expert judgment.

G. Radiological Criteria for

Decommissioning (tentative)—The

Committee will hear presentations and

hold discussions with the NRC staff on

a proposed rule on radiological criteria

for decommissioning of NRC licensed

facilities. A comparison will be made of

this proposed rule and EPA’s proposed

Standards for Land Disposal of LowLevel Radioactive Waste.

H. Preparation of ACNW Reports—

The Committee will discuss proposed

reports on issues considered during this

meeting and, as time permits, safety

goals applicable to nuclear waste

disposal and generic issues involving

the direction of radioactive waste

research.

I. Committee Activities/Future

Agenda—The Committee will consider

topics proposed for future consideration

by the full Committee and working

groups. The Committee will also discuss

organizational and personnel matters

related to the selection of new ACNW

members and ACNW staff. A portion of

this session may be closed to public

attendance to discuss information the

release of which would constitute a

clearly unwarranted invasion of

personal privacy pursuant to 5 U.S.C.

552b(c)(6).

J. Miscellaneous—The Committee will

discuss miscellaneous matters related to

the conduct of Committee activities and

organizational activities and complete

discussion of matters and specific issues

that were not completed during

previous meetings, as time and

availability of information permit.

Procedures for the conduct of and

participation in ACNW meetings were

published in the Federal Register on

October 7, 1994 (59 FR 51219). In

accordance with these procedures, oral

or written statements may be presented

by members of the public, electronic

recordings will be permitted only

during those portions of the meeting

that are open to the public, and

questions may be asked only by

members of the Committee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the ACNW Executive Director, Dr. John

T. Larkins, as far in advance as

practicable so that appropriate

arrangements can be made to allow the

necessary time during the meeting for

such statements. Use of still, motion

picture, and television cameras during

this meeting may be limited to selected

portions of the meeting as determined

by the ACNW Chairman. Information

regarding the time to be set aside for this

purpose may be obtained by contacting

the ACNW Executive Director prior to

the meeting. In view of the possibility

that the schedule for ACNW meetings

maybe adjusted by the Chairman as

necessary to facilitate the conduct of the

meeting, persons planning to attend

should check with the ACNW Executive
Federal Register / Vol. 60, No. 44 / Tuesday, March 7, 1995 / Notices 12577

Director if such rescheduling would

result in major inconvenience.

Further information regarding topics

to be discussed, whether the meeting

has been cancelled or rescheduled, the

Chairman’s ruling on requests for the

opportunity to present oral statements

and the time allotted therefor can be

obtained by contacting the ACNW

Executive Director, Dr. John T. Larkins

(telephone 301/415–7360), between 7:30

a.m. and 4:15 p.m. EST.

Dated: February 28, 1995.

Andrew L. Bates,

Advisory Committee Management Officer.

[FR Doc. 95–5496 Filed 3–6–95; 8:45 am]

BILLING CODE 7590–01–M

Regulatory Information Conference

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of meeting.

SUMMARY: The objectives of the

conference are to give the licensees and

the public insights into our approach to

safety regulations and to provide a

forum for feedback from those in

attendance on their concerns about our

overall approach, as well as feedback on

differences that may exist on technical

issues. NRC staff will provide

information regarding on-going

programs and potential new initiatives

as a basis for discussion.

Discussions will proceed from general

(i.e., the plenary sessions) to specific

issues (i.e., the breakout sessions), with

emphasis on plant operations and the

NRC view of these operations based on

experience in carrying out its regulatory

mission. Three plenary sessions are

planned, two of which will be followed

by breakout sessions that will include

presentations by the NRC staff and

industry representatives.

DATES: Conference will be held May 9–

10, 1995.

ADDRESSES: The conference will be held

at the Crowne Plaza Hotel, 1750

Rockville Pike, Rockville, MD 20852.

Telephone: (301) 468–1100 FAX (301)

468–0163 (Refer to Group REG).

FOR REGISTRATION INFORMATION CONTACT:

ES Inc., by facsimile on (202) 835–0118

or by phone on (202) 835–1585.

PARTICIPATION: This conference is open

to the general public; however, advance

registration is required by April 24,

1995. The following is the preliminary

program for the conference:

Tuesday, May 9, 1995—(8:30 a.m.–5:15 p.m.)

1. Welcome and Introductory Remarks—

William T. Russell, Director Office of

Nuclear Reactor Regulation

2. Morning Plenary Session: Regulatory

Trends

3. Breakout Sessions:

1. On-Line Maintenance and Maintenance

Rule

2. Steam Generator Issues

3. Probabilistic Risk Assessment Policy and

Implementation Plan

4. 10 CFR Part 54—License Renewal

Rulemaking and 10 CFR Part 51—

Environmental Protection Rulemaking

for License Renewal

4. Post-Luncheon Speaker: Commissioner

Kenneth C. Rogers

5. Afternoon Plenary Session: Regional

Administrator Panel Issues:

1. Inspection Planning, Oversight, and

Followup

2. Cost Reduction and Safety

3. Feedback Report on Inspector

Professionalism

4. Systematic Assessment of Licensee

Performance Process

6. Breakout Sessions:

1. Outage Planning and Shutdown Risk

2. 10 CFR Part 52—Advanced Reactors/

Design Certification

3. Regulatory Process Improvements

(Commitment Management and Cost

Beneficial Licensing Actions)

4. Boiling Water Reactor Internals Cracking

7. Dinner Speaker: Commissioner E. Gail de

Planque

Wednesday, May 10, 1995—(8:00 a.m.–4:30

p.m.)

1. Breakout Sessions:

1. NRC/Licensee Interface and

Communications, Region I

2. NRC/Licensee Interface and

Communications, Region II

3. NRC/Licensee Interface and

Communications, Region III

4. NRC/Licensee Interface and

Communications, Region IV

2. Breakout Sessions:

1. Reactor Vessel Material Issues

2. Spent Fuel Issues/Dry Cask Storage/

Independent Spent Fuel Storage

Installations/Palisades and Davis Besse

Experience

3. New Source Term (Design Certification

Application and Future Applications to

Operating Licenses)

4. Security Issues

3. Post Luncheon Speaker: James M. Taylor,

Executive Director for Operations

4. Breakout Sessions:

1. New Approach to Assessing

Performance Through Inspection—the

Integrated Performance Assessment

Process (IPAP, formerly CIPP)

2. Self Assessment (Inspection Procedures

& Lessons Learned)

3. Standard Technical Specifications

4. Enforcement (Notice of Enforcement

Discretions) and Allegations

Closing Plenary Session: NRR Executive

Team and Regional Administrators

Note: There will be a question and answer

period after each session each day.

Next year’s conference is scheduled for

April 10–11, 1996, at the Capitol Hilton

Hotel, Washington, DC.

Dated in Rockville, Maryland this 2nd day

of March 1995.

For the Nuclear Regulatory Commission.

Gary G. Zech,

Chief, Planning, Program, and Management

Support Branch, Inspection and Support

Programs, Office of Nuclear Reactor

Regulation.

[FR Doc. 95–5551 Filed 3–6–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–245]

Northeast Utilities Millstone Nuclear

Power Station, Unit 1, License No.

DPR–21; Receipt of Petitions for

Director’s Decision Under 10 CFR

2.206

Notice is hereby given that Anthony

J. Ross (Petitioner) has filed four

Petitions with the Executive Director for

Operations requesting that escalated

enforcement action be taken with regard

to alleged violations at Millstone

Nuclear Power Station, Unit 1.

By Petition dated December 30, 1994,

the Petitioner requests that the Nuclear

Regulatory Commission (NRC)(1)

‘‘force’’ Northeast Utilities (NU) to

review all existing work orders for the

past 10 or 12 years, with NRC oversight,

to ensure that no quality assurance (QA)

motor and connection work has certain

deficiencies; (2) assess a Severity Level

I violation against NU and its managers

for apparent violations of 10 CFR 50.7

and a Severity Level III violation against

a gas turbine system engineer at

Millstone for his apparent violation of

10 CFR 50.7 and the company’s ‘‘Code

of Conduct and Ethics’’; and (3) institute

sanctions against the system engineer

and NU and its managers for engaging

in deliberate misconduct in violation of

10 CFR 50.5. As grounds for these

requests, the Petitioner asserts that (1)

work control and procedure compliance

are inadequate at Millstone, as

evidenced by the use of standard

commercial-grade lugs in a gas turbine

fuel forwarding pump and motor (QA

subsystems of the emergency gas turbine

generator) that had apparently been

crimped using diagonal pliers; improper

Raychem splices, cable bend radius, and

connections in the connection boxes of

major safety-related QA equipment; and

non-QA lugs crimped improperly and

installed in fire protection quality

assurance emergency lights; and (2) he

had been subjected to ridicule by the gas

turbine system engineer for raising

concerns regarding the lugs on the gas

turbine fuel forwarding pump and

motor.

By Petition dated January 2, 1995, the

Petitioner requests that the NRC: (1)

Assess a Severity Level II violation and

a Severity Level III violation against his

department manager and first line