Federal Register / Vol. 60, No. 45 / Wednesday, March 8, 1995 / Notices 12789

30 and Gable Road, St. Helens, Oregon.

The meeting will begin at 7:30 pm and

will last approximately two hours. The

purpose of the meeting is to provide the

NRC and the ODOE an opportunity to

explain their respective

decommissioning review processes and

to provide interested members of the

public an opportunity to ask questions

and provide comments on the

decommissioning of the Trojan plant.

Copies of the Decommissioning Plan

and Environmental Report are available

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 on the fifth floor of the Branford

Price Millar Library, Portland State

University, 934 S.W. Harrison Street,

P.O. Box 1151, Portland, Oregon 97207.

Dated at Rockville, Maryland, this 28th day

of February 1995.

For the Nuclear Regulatory Commission.

Seymour H. Weiss,

Director, Non-Power Reactors and

Decommissioning Project Directorate,

Division of Project Support, Office of Nuclear

Reactor Regulation.

[FR Doc. 95–5613 Filed 3–7–95; 8:45 am]

BILLING CODE 7590–01–M

Regulatory Guide; Issuance,

Availability

The Nuclear Regulatory Commission

has issued a new 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.

Regulatory Guide 6.9, ‘‘Establishing

Quality Assurance Programs for the

Manufacture and Distribution of Sealed

Sources and Devices Containing

Byproduct Material,’’ provides guidance

acceptable to the NRC staff on the

essential elements needed to develop,

establish, and maintain a quality

assurance program for the manufacture

and distribution of sealed sources and

devices.

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

Rules Review and Directives 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 at the Commission’s Public

Document Room, 2120 L Street NW.,

Washington, DC. Copies of issued

guides may be purchased from the

Government Printing Office at the

current GPO price. Information on

current GPO prices may be obtained by

contacting the Superintendent of

Documents, U.S. Government Printing

Office, Post Office Box 37082,

Washington, DC 20013–7082, telephone

(202) 512–2249. 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.

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

Dated at Rockville, Maryland, this 13th day

of February 1995.

For the Nuclear Regulatory Commission.

Eric S. Beckjord,

Director, Office of Nuclear Regulatory

Research.

[FR Doc. 95–5609 Filed 3–7–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–318]

Baltimore Gas and Electric Co.;

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–

69 issued to Baltimore Gas and Electric

Company (the licensee) for operation of

the Calvert Cliffs Nuclear Power Plant,

Unit No. 2, located in Calvert County,

Maryland.

The proposed amendment would

revise the Calvert Cliffs, Unit No. 2,

Technical Specifications (TSs).

Specifically, TS 4.G.1.2 would reference

10 CFR part 50, Appendix J directly,

and any approved exemptions to the

Type A testing frequently requirements,

rather than paraphrase the regulation.

The proposed wording is consistent

with that used in NUREG–1432,

‘‘Standard Technical Specifications—

Combustion Engineering Plants,’’ dated

September 1992.

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.

The proposed change revises Technical

Specification 4.6.1.2.a to reference the testing

frequency requirements of 10 CFR part 50,

Appendix J, and to state that NRC-approved

exemptions to the applicable regulatory

requirements are permitted. The current

Technical Specification 4.6.1.2.a paraphrases

the requirements of Appendix J, paragraph

III.D.1.(a) and necessitates a change to the

Technical Specifications should the

Appendix J language change or an exemption

be granted. The proposed administrative

revision simply deletes the paraphrased

language and directly references Appendix J

and any approved exemptions. No new

requirements are added, nor are any existing

requirements deleted. Any specific

exemptions from the requirements of

Appendix J, paragraph III.D.1.(a) will

continue to require a submittal from

Baltimore Gas and Electric Company under

10 CFR 50.12 and subsequent review and

approval by the NRC prior to

implementation.

The proposed change will provide a onetime exemption from the 10 CFR part 50,

Appendix J, paragraph III.D.1.(a) leak rate test

schedule requirement. This change will

allow for a one-time interval between

subsequent Type A test of approximately 72

months. It will also extend the second tenyear Type A testing service period to 12 years

to coincide with the inservice inspection

interval.

No physical or operational changes to the

structure, plant systems or components

would be made as a result of the proposed

change. Furthermore, leak rate testing is not

an initiating event in any accident, therefore

this proposed change does not involve a

significant increase in the probability of any

accident previously evaluated.

Type A tests are capable of detecting

containment leaks through containment

penetrations and through the containment

liner. The history at Calvert Cliffs Unit 2

demonstrates that Type B and C Local Leak

Rate Tests (LLRTs) have consistently

detected leakage through penetrations. With

the exception of the first periodic Unit 2

Type A test in 1979, which failed and was

promptly corrected, Type A tests have not