Federal Register / Vol. 60, No. 98 / Monday, May 22, 1995 / Notices 27143

is being performed as required by the

technical specifications.

Requested Actions

The NRC staff requests that all holders

of operating licenses for nuclear power

reactors take the following actions:

(1) Compare electrical schematic

drawings and logic diagrams for the

reactor protection system, EDG load

shedding and sequencing and actuation

logic for the engineered safety features

systems against technical specification

surveillance test procedures to ensure

that all portions of the logic circuitry,

including the parallel logic, interlocks,

bypasses and inhibit circuits, are

adequately covered in the surveillance

procedures. This review should also

include relay contacts, control switches,

and other relevant electrical

components within these systems,

utilized in the logic circuits.

(2) Modify the surveillance

procedures as necessary for complete

testing to comply with the technical

specifications. Additionally, the

licensee may request an amendment to

the technical specifications if relief from

certain testing requirements can be

justified.

It is requested the completion of these

actions not go beyond the first refueling

outage commencing 90 days after the

issuance of this generic letter.

Note: Some licensees may have already

performed the requested reviews and taken

appropriate corrective actions. These

licensees do not need to perform any

additional review unless modifications have

been made to the logic circuits for these

systems. In these cases the modifications

should be reviewed.

Required Response

All addressees, including those who

have already completed the requested

actions, are required to submit a written

response to this generic letter as follows:

(1) Within 60 days of the date of this

generic letter, a written response

indicating whether or not the addressee

will implement the actions requested

above. If the addressee intends to

implement the requested actions,

submit a schedule for completing

implementation. If an addressee chooses

not to take the requested actions, submit

a description of any proposed

alternative course of action, the

schedule for completing the alternative

course of action (if applicable), and the

safety basis for determining the

acceptability of the planned alternative

course of action.

(2) Within 30 days of completion of

the requested actions, a response

confirming completion.

Backfit Discussion

The actions requested in this generic

letter are considered backfits in

accordance with NRC procedures.

Because established regulatory

requirements exist but were not

satisfied, these backfits are necessary to

bring the addressees into compliance

with existing requirements. Therefore,

on the basis of 10 CFR 50.109(a)(4)(i), a

full backfit analysis was not performed.

An evaluation was performed in

accordance with NRC procedures,

including a statement of the objectives

of and reasons for the requested actions

and the basis for invoking the

compliance exception. Response to

question ix in the CRGR review package

contains this evaluation.

Dated at Rockville, Maryland, this 15th day

of May, 1995.

For the Nuclear Regulatory Commission.

Brian K. Grimes,

Director, Division of Project Support, Office

of Nuclear Reactor Regulation.

[FR Doc. 95–12468 Filed 5–19–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Reactor

Safeguards; Meeting Agenda

In accordance with the purposes of

Sections 29 and 182b. of the Atomic

Energy Act (42 U.S.C. 2039, 2232b), the

Advisory Committee on Reactor

Safeguards will hold a meeting on June

8–10, 1995, in Conference Room T2B3,

11545 Rockville Pike, Rockville,

Maryland. The date of this meeting was

previously published in the Federal

Register on Wednesday, December 28,

1994 (59 FR 66977).

Thursday, June 8, 1995

8:30 a.m.–8:45 a.m.: Opening

Remarks by the ACRS Chairman

(Open)—The ACRS Chairman will make

opening remarks regarding conduct of

the meeting and comment briefly

regarding items of current interest.

During this session, the Committee will

discuss priorities for preparation of

ACRS reports.

8:45 a.m.–9:15 a.m.: Preparation for

Meeting with the Commissioners

(Open)—The Committee will discuss

topics scheduled for the meeting with

the Commissioners.

9:30 a.m.–11:00 a.m.: Meeting with

the Commissioners (Open)—The

Committee will meet with the

Commissioners, in the Commissioner’s

Conference Room, One White Flint

North, to discuss items of mutual

interest.

11:15 a.m.–12:00 noon: Ethics

Training (Open)—The Committee will

hear presentations by and hold

discussions with representatives of the

NRC Office of the General Counsel

regarding the provisions of the Ethics

regulations which apply to Special

Government Employees.

1:00 p.m.–3:00 p.m.: Proposed Final

PRA Policy Statement (Open)—The

Committee will hear presentations by

and hold discussions with

representatives of the NRC staff

regarding the proposed Final PRA

Policy Statement. Also representatives

of the Nuclear Energy Institute (NEI)

will brief the Committee regarding the

NEI/EPRI Probabilistic Safety

Assessment (PSA) Application Guide.

3:15 p.m.–4:45 p.m.: Proposed Final

Rule on Reactor Vessel Annealing

(Open)—The Committee will hear

presentations by and hold discussions

with representatives of the NRC staff

regarding the proposed final rule on

reactor vessel annealing.

Representatives of the industry will

participate, as appropriate.

5:00 p.m.–6:30 p.m.: Preparation of

ACRS Reports (Open)—The Committee

will discuss proposed ACRS reports on

matters considered during this meeting.

Friday, June 9, 1995

8:30 a.m.–8:35 a.m.: Opening

Remarks by the ACRS Chairman

(Open)—The ACRS Chairman will make

opening remarks regarding conduct of

the meeting.

8:35 a.m.–9:45 a.m.: Status of Issues

Associated with the AP600 Design

Certification Review (Open)—The

Committee will hear presentations by

and hold discussions with

representatives of the NRC staff

regarding the status of issues associated

with the AP600 design certification

review.

Representatives of the industry will

participate, as appropriate.

9:45 a.m.–10:45 a.m.: Policy and

Technical Issues for Passive Plant

Designs (Open)—The Committee will

hear presentations by and hold

discussions with representatives of the

NRC staff regarding policy and technical

issues for passive plant designs.

Representatives of the industry will

participate, as appropriate.

11:00 a.m.–12:30 p.m.: Prioritization

of Generic Safety Issues (GSIs) (Open)—

The Committee will hold discussions

with representatives of the NRC staff

regarding the comments from cognizant

subcommittee chairman on the priority

rankings proposed by the Staff for a

group of GSIs, and also the schedule for

prioritizing the remaining GSIs.

1:30 p.m.–2:30 p.m.: Fire-Protection

Related Issues (Open/Closed)—The

Committee will hear presentations by
27144 Federal Register / Vol. 60, No. 98 / Monday, May 22, 1995 / Notices

and hold discussions with

representatives of the NRC staff and the

Nuclear Energy Institute (NEI) regarding

several fire-protection related issues,

including the NEI petition for

rulemaking to amend portions of 10 CFR

50.48, ‘‘Fire Protection’’, status of the

staff’s Fire Protection Action Plan,

adequacy of fire barrier penetration

seals, and the fire event at the Narora

nuclear plant in India.

A portion of this session may be

closed to discuss information provided

in confidence by a foreign source.

2:30 p.m.–3:15 p.m.: Report of the

Planning and Procedures Subcommittee

(Open/Closed)—The Committee will

hear a report of the Planning and

Procedures Subcommittee on matters

related to the conduct of ACRS business

and internal organizational and

personnel matters relating to the ACRS

staff members.

A portion of this session may be

closed to discuss matters that relate

solely to internal personnel rules and

practices of this Advisory Committee,

and matters the release of which would

constitute a clearly unwarranted

invasion of personal privacy.

3:15 p.m.–3:30 p.m.: Reconciliation of

ACRS Comments and

Recommendations (Open)—The

Committee will discuss responses

expected from the NRC Executive

Director for Operations to ACRS

comments and recommendations

included in recent ACRS reports.

3:45 p.m.–4:30 p.m.: Future ACRS

Activities (Open)—The Committee will

select topics for consideration during

future ACRS meetings.

4:30 p.m.–6:30 p.m.: Preparation of

ACRS Reports (Open)—The Committee

will continue its discussion of proposed

ACRS reports on matters considered

during this meeting.

Saturday, June 10, 1995

8:30 a.m.–11:30 a.m.: Preparation of

ACRS Reports (Open)—The Committee

will continue its discussion of proposed

ACRS reports on matters considered

during this meeting.

11:30 a.m.–12:30 p.m.: Strategic

Planning (Open)—The Committee will

discuss items that are of importance to

the NRC which should receive

additional emphasis in its future

deliberations.

12:30 p.m.–12:45 p.m.: New Research

Needs (Open)—The Committee will

discuss new research needs, if any,

identified during this meeting.

12:45 p.m.–1:00 p.m.: Miscellaneous

(Open)—The Committee will discuss

miscellaneous matters related to the

conduct of Committee activities.

Procedures for the conduct of and

participation in ACRS meetings were

published in the Federal Register on

October 5, 1994 (59 FR 50780). In

accordance with these procedures, oral

or written statements may be presented

by members of the public, electronic

recordings will be permitted only

during the open portions of the meeting,

and questions may be asked only by

members of the Committee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the ACRS Executive Director, Dr. John

T. Larkins, at least five days before the

meeting if possible, 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 Chairman. Information regarding

the time to be set aside for this purpose

may be obtained by contacting the

ACRS Executive Director prior to the

meeting. In view of the possibility that

the schedule for ACRS Meetings may be

adjusted by the Chairman as necessary

to facilitate the conduct of the meeting,

persons planning to attend should check

with the ACRS Executive Director if

such rescheduling would result in major

inconvenience.

In accordance with Subsection 10(d)

Public Law 92–463, I have determined

that it is necessary to close portions of

this meeting noted above to discuss

information that involves the internal

personnel rules and practices of this

Advisory Committee per 5 U.S.C.

552b(c)(2); to discuss information the

release of which would constitute a

clearly unwarranted invasion of

personal privacy per 5 U.S.C. 552(c)(6);

and to discuss information provided in

confidence by a foreign source per 5

U.S.C. 552b(c)(4).

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 ACRS

Executive Director, Dr. John T. Larkins

(telephone 301–415–7361), between

7:30 a.m. and 4:15 p.m. edt.

Dated: May 18, 1995.

John C. Hoyle,

Acting Advisory Committee Management

Officer.

[FR Doc. 95–12467 Filed 5–19–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–313]

Arkansas Nuclear One, Unit 1; 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. 50–

313, issued to Entergy Operations Inc.

(the licensee), for operation of Arkansas

Nuclear One, Unit 1 (ANO–1) located in

Pope County Arkansas.

The proposed amendment would

modify the operability requirements

related to the reactor building

(containment) emergency cooling

system. Following failure of one of four

reactor building cooling fans, the

licensee reconfigured the reactor

building cooling air and water flows to

ensure that the system could cool the

reactor building after a design basis loss

of coolant accident. The licensee

requested an exigent Technical

Specification (TS) change to include the

reconfigured reactor building cooling

system in the TS as an authorized

configuration. NRC granted enforcement

discretion on May 12, 1995 to allow the

facility to continue operation while this

exigent TS is processed.

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.

Pursuant to 10 CFR 50.91(a)(6) for

amendments to be granted under

exigent circumstances, the NRC staff

must determine 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:

Criterion 1: Involves a significant increase

in the probability or consequences of an

accident previously evaluated.

The Reactor Building Emergency Cooling

system is not an initiator of any accident

described in the ANO–1 Safety Analysis

Report. The engineering evaluation discussed