Federal Register / Vol. 62, No. 58 / Wednesday, March 26, 1997 / Notices 87

Amendment Nos.: 214 and 199

Facility Operating License Nos. DPR58 and DPR-74. Amendments revised

the Technical Specifications.

Date of initial notice in Federal

Register: July 19, 1995 (60 FR 37095)

The September 26, 1995, August 2,

1996, and February 6, 1997,

supplements provided clarifying

information that did not expand the

scope of the initial application or

change the staff’s proposed no

significant hazards determination. The

Commission’s related evaluation of the

amendments is contained in a Safety

Evaluation dated March 13, 1997. No

significant hazards consideration

comments received: No.

Local Public Document Room

location: Maud Preston Palenske

Memorial Library, 500 Market Street, St.

Joseph, Michigan 49085

North Atlantic Energy Service

Corporation, Docket No. 50-443,

Seabrook Station, Unit No. 1,

Rockingham County, New Hampshire

Date of amendment request: October

17, 1996

Description of amendment request:

The amendment revises the Appendix A

Technical Specifications relating to incore detector system, seismic

instrumentation, meteorological

instrumentation, and turbine overspeed

protection. The amendment deletes

Limiting Conditions for Operation and

Surveillance Requirements related to

these instruments. The deleted

requirements are to be incorporated into

the Seabrook Station Technical

Requirements Manual (SSTR). The

associated Bases Sections are also

deleted. In addition, Technical

Specification 5.5 is deleted but will not

be relocated to the SSTR. The

amendment also redesignates Paragraph

2.J of the Seabrook Operating License as

Paragraph 3, and has added new

Paragraph 2.J to document the North

Atlantic commitment to relocate the

above mentioned Technical

Specification requirements to the SSTR.

Date of issuance: March 12, 1997

Effective date: March 12, 1997

Amendment No.: 50

Facility Operating License No. NPF86. Amendment revised the Technical

Specifications and Operating License.

Date of initial notice in Federal

Register: December 18, 1996 (61 FR

66713). The Commission’s related

evaluation of the amendment is

contained in a Safety Evaluation dated

March 12, 1997. No significant hazards

consideration comments received: No.

Local Public Document Room

location: Exeter Public Library,

Founders Park, Exeter, NH 03833.

Northeast Nuclear Energy Company, et

al., Docket No. 50-423, Millstone

Nuclear Power Station, Unit No. 3, New

London County, Connecticut

Date of application for amendment:

May 23, 1996, as supplemented July 17

and December 4, 1996

Brief description of amendment: The

amendment modifies the description of

the time constants associated with the

Overtemperature Delta-T and

Overpower Delta-T calculations used to

establish the trip setpoints and the time

constant used in the rate-lag controller

for Steam Line Isolation, Steam Line

Pressure Negative Rate-High.

Date of issuance: March 11, 1997

Effective date: As of the date of

issuance, to be implemented within 60

days.

Amendment No.: 134

Facility Operating License No. NPF49: Amendment revised the Technical

Specifications.

Date of initial notice in Federal

Register: June 17, 1996 (61 FR 30639)

The July 17 and December 4, 1996,

letters provided additional, clarifying

information that did not change the

scope of the May 23, 1996, application

and the initial proposed no significant

hazards consideration determination.

The Commission’s related evaluation of

the amendment is contained in a Safety

Evaluation dated March 11, 1997. No

significant hazards consideration

comments received: No.

Local Public Document Room

location: Learning Resources Center,

Three Rivers Community-Technical

College, 574 New London Turnpike,

Norwich, Connecticut 06360, and the

Waterford Library, ATTN: Vince

Juliano, 49 Rope Ferry Road, Waterford,

Connecticut 06385

Southern California Edison Company,

et al., Docket No. 50-362, San Onofre

Nuclear Generating Station, Unit No. 3,

San Diego County, California

Date of application for amendment:

February 7, 1997

Brief description of amendment: The

amendment defers implementation of

Surveillance Requirement 3.1.5.4 of

Technical Specification 3.1.5, ‘‘Control

Element Assembly (CEA) Alignment,’’

until the next SONGS Unit 3 shutdown,

which will be no later than the

upcoming Cycle 9 refueling outage

(currently scheduled for April 12, 1997).

Date of issuance: March 5, 1997

Effective date: March 5, 1997

Amendment No.: 126

Facility Operating License No. NPF15: The amendments revised the

Technical Specifications. Public

comments requested as to proposed no

significant hazards consideration: Yes

(62 FR 7477 dated February 19, 1997).

The notice provided an opportunity to

submit comments on the Commission’s

proposed no significant hazards

consideration determination. No

comments have been received. The

notice also provided for an opportunity

to request a hearing by March 21, 1997,

but indicated that if the Commission

makes a final no significant hazards

consideration determination any such

hearing would take place after issuance

of the amendment. The Commission’s

related evaluation of the amendment is

contained in a Safety Evaluation dated

March 5, 1997.

Attorney for licensee: T. E. Oubre,

Esquire, Southern California Edison

Company, P. O. Box 800, Rosemead,

California 91770

Local Public Document Room

location: Main Library, University of

California, P. O. Box 19557, Irvine,

California 92713

Dated at Rockville, Maryland, this 19th day

of March 1997.

For the Nuclear Regulatory Commission

Elinor G. Adensam,

Acting Director, Division of Reactor Projects

III/IV, Office of Nuclear Reactor Regulation

[Doc. 97–7508 Filed 3–25–97; 8:45 am]

BILLING CODE 7590–01–F

[Docket No. 50–409]

Lacrosse Boiling Water Reactor; Intent

To Relocate Local Public Document

Room

Notice is hereby by given that the

Nuclear Regulatory Commission (NRC)

will be relocating the local public

document room (LPDR) for records

pertaining to Dairyland Power

Cooperative’s LaCrosse Boiling Water

Reactor located in Genoa, Wisconsin.

The LaCrosse LPDR is currently located

at the LaCrosse Public Library, 800 Main

Street, LaCrosse, Wisconsin. The

document collection is available in

microfiche form, with paper copy

indices. Library staff informed the NRC

that they are no longer able to maintain

the document collection and request

that it be moved. This notice invites

public comment on possible LPDR

locations in the Genoa, Wisconsin, area.

Among the factors the NRC will

consider in selecting a new location for

the LPDR are the following:

(1) Whether the institution is an

established document repository located

near the nuclear facility with a history

of impartially serving the public;

(2) The physical facilities available,

including shelf space, storage space,

patron workspace, copying equipment

and computer access;
88 Federal Register / Vol. 62, No. 58 / Wednesday, March 26, 1997 / Notices

(3) The willingness and ability of the

library staff to maintain the LPDR

collection and assist the public in

locating records;

(4) The nature and extent of related

research resources, such as government

documents;

(5) The public accessibility of the

library, including handicap

accessibility, parking, ground

transportation, and hours of operation,

particularly evening and weekend

hours;

(6) The proximity of the library to

existing user groups of the collection, if

known.

Comment period expires April 25,

1997. Comments received after this date

will be considered if it is practical to do

so, but assurance of consideration

cannot be given except as to comments

filed on or before this date.

Written comments may be submitted

to Mr. David Meyer, Chief, Regulatory

Publications Branch, Office of

Administration, U.S. Nuclear Regulatory

Commission, Washington, DC 20555.

Copies of comments received may be

examined at the NRC Public Document

Room, Gelman Building, 2120 L Street

NW, Washington, DC.

Questions concerning the NRC’s

LPDR Program should be addressed to

Ms. Jona L. Souder, LPDR Program

Manager, Freedom of Information/Local

Public Document Room Branch, Office

of Information Resources Management,

U.S. Nuclear Regulatory Commission,

Washington, DC 20555, telephone

number 301–415–7170, or toll-free 1–

800–638–8081.

Dated at Rockville, Md., this 20th day of

March, 1997.

For the Nuclear Regulatory Commission.

Russell A. Powell,

Chief, Freedom of Information/Local Public

Document Room Branch, Office of

Information Resources Management.

[FR Doc. 97–7640 Filed 3–25–97; 8:45 am]

BILLING CODE 7590–01–P

Regulatory Guide; Issuance,

Availability

The Nuclear Regulatory Commission

has issued a revision to a guide in its

Regulatory Guide Series. This series has

been developed to describe and make

available to the public such information

as methods acceptable to the NRC staff

for implementing specific parts of the

Commission’s regulations, techniques

used by the staff in evaluating specific

problems or postulated accidents, and

data needed by the staff in its review of

applications for permits and licenses.

Revision 2 of Regulatory Guide 1.160,

‘‘Monitoring the Effectiveness of

Maintenance at Nuclear Power Plants,’’

has been issued to endorse Revision 2

of NUMARC 93–01, ‘‘Industry Guideline

for Monitoring the Effectiveness of

Maintenance at Nuclear Power Plants’’

(April 1996), which has been updated

by the Nuclear Energy Institute. When

used in conjunction, these revisions to

Regulatory Guide 1.160 and NUMARC

93–01 provide methods acceptable to

the NRC staff for complying with the

NRC’s maintenance rule, 10 CFR 50.65.

Comments and suggestions in

connection with items for inclusion in

guides currently being developed or

improvements in all published guides

are encouraged at any time. Written

comments may be submitted to the

Publications Branch, Division of

Freedom of Information and

Publications Services, Office of

Administration, U.S. Nuclear Regulatory

Commission, Washington, DC 20555.

Regulatory guides are available for

inspection or copying for a fee at the

Commission’s Public Document Room,

2120 L Street NW., Washington, DC.

Single copies of regulatory guides, both

active and draft, may be obtained free of

charge by writing the Office of

Administration, Attn: Distribution and

Mail Services Section, USNRC,

Washington, DC 20555–0001, or by fax

at (301) 415–2260. Issued guides may

also be purchased from the National

Technical Information Service on a

standing order basis. Details on this

service may be obtained by writing

NTIS, 5285 Port Royal Road,

Springfield, VA 22161. Regulatory

guides are not copyrighted, and

Commission approval is not required to

reproduce them.

(5 U.S.C. 552(a))

Dated at Rockville, Maryland, this 13th day

of March 1997.

For the Nuclear Regulatory Commission.

David L. Morrison,

Director, Office of Nuclear Regulatory

Research.

[FR Doc. 97–7637 Filed 3–25–97; 8:45 am]

BILLING CODE 7590–01–P

[Docket No. 70–7002]

Amendment to Certificate of

Compliance for the U.S. Enrichment

Corporation Portsmouth Gaseous

Diffusion Plant, Portsmouth, OH

The Director, Office of Nuclear

Material Safety and Safeguards has

made a determination that the following

amendment request is not significant in

accordance with 10 CFR 76.45. In

making that determination the staff

concluded that (1) there is no change in

the types or significant increase in the

amounts of any effluents that may be

released offsite; (2) there is no

significant increase in individual or

cumulative occupational radiation

exposure; (3) there is no significant

construction impact; (4) there is no

significant increase in the potential for,

or radiological or chemical

consequences from, previous analyzed

accidents; (5) the proposed changes do

not result in the possibility of a new or

different kind of accident; (6) there is no

significant reduction in any margin of

safety; and (7) the proposed changes

will not result in an overall decrease in

the effectiveness of the plant’s safety,

safe guards or security programs. The

basis for this determination for the

amendment request is described below.

The NRC staff has reviewed the

certificate amendment application and

concluded that it provides reasonable

assurance of adequate safety, safeguards,

and security, and compliance with NRC

requirements. Therefore, the Director,

Office of Nuclear Material Safety and

Safeguards is prepared to issue an

amendment to the Certificate of

Compliance for the Portsmouth Gaseous

Diffusion Plant (PORTS). The staff has

prepared a Compliance Evaluation

Report which provides details of the

staff’s evaluation.

The NRC staff has determined that

this amendment satisfied the criteria for

a categorical exclusion in accordance

with 10 CFR 51.22. Therefore, pursuant

to 10 CFR 51.22(b), no environmental

impact statement or environmental

assessment need be prepared for this

amendment.

USEC or any person whose interest

may be affected may file a petition, not

exceeding 30 pages, requesting review

of the Director’s Decision. The petition

must be filed with the Commission not

later than 15 days after publication of

this Federal Register Notice. A petition

for review of the Director’s Decision

shall set forth with particularity the

interest of the petitioner and how that

interest may be affected by the results of

the decision. The petition should

specifically explain the reasons why

review of the Decision should be

permitted with particular reference to

the following factors: (1) The interest of

the petitioner; (2) how that interest may

be affected by the Decision, including

the reasons why the petitioner should

be permitted a review of the Decision;

and (3) the petitioner’s areas of concern

about the activity that is the subject

matter of the Decision. Any person

described in this paragraph (USEC or

any person who filed a petition) may

file a response to any petition for

review, not to exceed 30 pages, within

10 days after the filing of the petition.