48320 Federal Register / Vol. 62, No. 178 / Monday, September 15, 1997 / Notices

of 440 psig is not exceeded; (3) pigtail

isolation system to limit the UF6 release

to less than 127 pounds in case of a

pigtail failure; (4) assay monitoring to

ensure that the TSR specified maximum

assays for the accumulators and

cylinders are not exceeded; (5) cylinder

cart movement restrictions to ensure

that a cylinder is not moved while it is

connected to the withdrawal manifold;

(6) liquid UF6 cylinder movement

methods and restrictions to minimize

the risk of a liquid UF6 cylinder drop

and rupture; (7) UF6 cylinder weight

monitoring to ensure that the TSR

specified fill weights are not exceeded;

and (8) restrictions on heating solidified

UF6 plugs to prevent pipe rupture that

could be caused by local liquefaction

and expansion.

m. There are specific general design

feature requirements and associated SRs

related to (1) design, construction,

testing and maintenance to ensure that

the intended functions of UF6 cylinders

and pigtails are met so that they do not

fail during normal operations; (2)

cylinder lifting cranes and fixtures to

ensure that a cylinder is not dropped

and ruptured; and (3) Raschig rings in

scale pits to enhance criticality safety.

Consequently, there will be no

significant increase in a risk of a

criticality accident which could

significantly increase individual or

cumulative occupational radiation

exposures.

3. The proposed amendment will not

result in a significant construction

impact.

The proposed amendment does not

involve any construction, therefore,

there will be no construction impacts.

4. The proposed amendment will not

result in a significant increase in the

potential for, or radiological or chemical

consequences from, previously analyzed

accidents.

For similar reasons (adequacy of

contingencies, reliability of controls,

and unlikelihood of common-mode

failures) provided in the assessment of

criterion 2, the proposed amendment

will not significantly increase the risk of

a criticality accident. Therefore, the

proposed amendment will not

significantly increase the potential for,

or radiological or chemical

consequences from, previously analyzed

accidents.

5. The proposed amendment will not

result in the possibility of a new or

different kind of accident.

Based on the adequacy of

contingencies, reliability of controls,

and unlikelihood of common-mode

failures provided in the assessment of

criterion 2, the NRC staff has

determined that the proposed

amendment will not result in the

possibility of a new or different kind of

accident.

6. The proposed amendment will not

result in a significant reduction in any

margin of safety.

For similar reasons (adequacy of

contingencies, reliability of controls,

and unlikelihood of common-mode

failures) provided in the assessment of

criterion 2, the proposed amendment

will not significantly increase the risk of

a criticality accident. In addition, the

amendment is required to ensure proper

operability of the ERP 1A scale, which

performs the safety function of

measuring the weight of the cylinder as

it is being filled. Properly and safely

weighing the cylinder is necessary to

ensure safety of the facility. Therefore,

the proposed amendment will not result

in a significant reduction in any margin

of safety.

7. The proposed amendment will not

result in an overall decrease in the

effectiveness of the plant’s safety,

safeguards or security programs.

For similar reasons (adequacy of

contingencies, reliability of controls,

unlikelihood of common-mode failures,

and operability of ERP 1A scale)

provided in the assessment of criteria 2

and 6, the proposed amendment will

not significantly increase the risk of a

criticality or UF6 release accident.

Therefore, the proposed amendment

will not result in a decrease in the

plant’s overall safety program.

The staff has not identified any

safeguards or security related

implications from the proposed

amendment. Therefore, the proposed

amendment will not result in an overall

decrease in the effectiveness of the

plants safeguards or security programs.

Effective date: The amendment to

GDP–2 will become effective 30 days

after issuance by NRC.

Certificate of Compliance No. GDP–2:

Amendment will incorporate a revised

requirement of a General Design Feature

contained in the Technical Safety

Requirements.

Local Public Document Room

location: Portsmouth Public Library,

1220 Gallia Street, Portsmouth, Ohio

45662.

Dated at Rockville, Maryland, this 2nd day

of September 1997.

For the Nuclear Regulatory Commission.

William F. Kane,

Acting Deputy Director, Office of Nuclear

Material Safety and Safeguards.

[FR Doc. 97–24380 Filed 9–12–97; 8:45 am]

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[Docket 70–7001]

Notice of Amendment to Certificate of

Compliance GDP–1 for the U.S.

Enrichment Corporation Paducah

Gaseous Diffusion Plant Paducah, KY

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, previously 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,

safeguards or security programs. The

basis for this determination for the

amendment request is shown 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 Paducah Gaseous

Diffusion Plant. The staff has prepared

a Compliance Evaluation Report which

provides details of the staff’s evaluation.

The NRC staff has determined that

this amendment satisfies 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
Federal Register / Vol. 62, No. 178 / Monday, September 15, 1997 / Notices 48321

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 filing of the petition. If no

petition is received within the

designated 15-day period, the Director

will issue the final amendment to the

Certificate of Compliance without

further delay. If a petition for review is

received, the decision on the

amendment application will become

final in 60 days, unless the Commission

grants the petition for review or

otherwise acts within 60 days after

publication of this Federal Register

notice.

A petition for review must be filed

with the Secretary, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555–0001, Attention: Rulemakings

and Adjudications Staff, or may be

delivered to the Commission’s Public

Document Room, the Gelman Building,

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

the above date.

For further details with respect to the

action see (1) the application for

amendment and (2) the Commission’s

Compliance Evaluation Report. These

items are 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.

Date of amendment request: June 16,

1997.

Brief description of amendment: The

amendment proposes to revise the

Technical Safety Requirement (TSR) for

the Nuclear Criticality Safety Program

by adding a new program element.

Basis for Finding of No Significance

1. The proposed amendment will not

result in a change in the types or

significant increase in the amounts of

any effluents that may be released

offsite.

The proposed change involves

revision of the Nuclear Criticality Safety

Program TSR to add a new program

element on identification of safety

structures, systems and components

(SSCs) required to meet the double

contingency. Because there are no

effluent release associated with this

change, the proposed changes will not

affect the effluent.

2. The proposed amendment will not

result in a significant increase in

individual or cumulative occupational

radiation exposure.

The proposed changes do not relate to

controls used to minimize occupational

radiation exposures, therefore, the

changes will not increase exposure.

3. The proposed amendment will not

result in a significant construction

impact.

The proposed changes will not result

in any construction, therefore, there will

be no construction impacts.

4. The proposed amendment will not

result in a significant increase in the

potential for, or radiological or chemical

consequences from, previously analyzed

accidents.

The proposed changes will not

increase the probability of occurrence or

consequence of any postulated accident

currently identified in the safety

analysis report. Therefore, there is no

significant increase in the potential for

or radiological or chemical

consequences from previously evaluated

accidents.

5. The proposed amendment will not

result in the possibility of a new or

different kind of accident.

Changing the TSR to add a new

program element will not create a new

or different type of accident. The

proposed changes would not create new

operating conditions or new plant

configuration that could lead to a new

or different type of accident.

6. The proposed amendment will not

result in a significant reduction in any

margin of safety.

There are no increases in the

probability or consequences of a

criticality and no new accident

initiators were identified. These changes

do not increase the margins of safety. In

fact safety may be enhanced by putting

more emphasis on the clear

identification of SSCs necessary to meet

the double contingency principle.

7. The proposed amendment will not

result in an overall decrease in the

effectiveness of the plant’s safety,

safeguards or security programs.

Implementation of the proposed

changes do not change the safety,

safeguards, or security programs.

Although the program element is being

added to the TSR, there was already a

commitment to identify the SSCs. The

effectiveness of the safety, safeguards,

and security programs is not decreased.

Effective date: The amendment to

Certificate of Compliance GDP–1

becomes effective 30 days after being

signed by the Director, Office of Nuclear

Material Safety and Safeguards.

Certificate of Compliance No. GDP–1:

Amendment will revise Technical

Safety Requirement for the nuclear

criticality safety program by adding a

new program element.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003.

Dated at Rockville, Maryland, this 2nd day

of September 1997.

For the Nuclear Regulatory Commission.

William F. Kane,

Acting Deputy Director, Office of Nuclear

Material Safety and Safeguards.

[FR Doc. 97–24384 Filed 9–12–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

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Advisory Committee on Reactor

Safeguards, Subcommittee Meeting on

Thermal-Hydraulic and SevereAccident Phenomena; Notice of

Meeting

The ACRS Subcommittee on ThermalHydraulic and Severe-Accident

Phenomena will hold a meeting on

September 29–30, 1997, Room T–2B3,

11545 Rockville Pike, Rockville,

Maryland.

Most of the meeting will be closed to

public attendance to discuss

Westinghouse Electric Corporation

proprietary information pursuant to 5

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

The agenda for the subject meeting

shall be as follows:

Monday, September 29, 1997—8:30

a.m. until the conclusion of business

Tuesday, September 30, 1997—8:30

a.m. until the conclusion of business

The Subcommittee will continue its

review of the results of the

Westinghouse Test and Analysis

Program being conducted in support of

the AP600 design certification and the

associated NRC staff’s Supplemental

Draft Safety Evaluation Report.

Specifically, the Subcommittee will

review key elements of the passive

containment cooling system test and

analysis program. The purpose of this

meeting is to gather information,

analyze relevant issues and facts, and to

formulate proposed positions and

actions, as appropriate, for deliberation

by the full Committee.

Oral statements may be presented by

members of the public with the

concurrence of the Subcommittee

Chairman; written statements will be

accepted and made available to the

Committee. Electronic recordings will

be permitted only during those portions

of the meeting that are open to the