49710 Federal Register / Vol. 62, No. 184 / Tuesday, September 23, 1997 / Notices

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: April 14,

1997, as revised June 13, June 23, and

August 18, 1997.

Brief description of amendment: The

amendment proposes to revise the

Technical Safety Requirement (TSR) on

the cell trip function to provide

clarification of battery cell parameters,

to provide for alternate means of

verifying functionality of the cascade

cell trip circuit, and to provide a

definition of planned and unplanned

cell shutdown.

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 changes will provide an

alternative surveillance test to verify the

functionality of the cascade cell trip

circuit and will provide clarification for

battery cell parameters. There are no

effluent releases 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 provide for the

clarification of battery parameters and

ability to test cell trip function by a

second method. This surveillance

method can be performed on cells that

are shutdown, providing a means to

meet the surveillance requirements and

restart the shutdown cell. The test is

functionally equivalent to the

surveillance currently specified in the

TSR. The proposed changes do not

represent an 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.

The proposed changes to the TSR do

not result in any situation whereby

components are not capable of

performing the required safety

functions. 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.

Although the timing of the

surveillance for testing cell trip function

is modified by addition of the

alternative test, system operability is

still ensured before the cell is restarted.

The other changes to the TSR do not

result in any situation whereby the

components are not capable of

performing the required safety function.

These changes do not decrease the

margins 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.

Implementation of the proposed

changes do not change the safety,

safeguards, or security programs.

Therefore, the effectiveness of the

safety, safeguards, and security

programs is not decreased.

Effective date: The amendment to

Certificate of Compliance GDP–1

becomes effective 15 days after being

signed by the Director, Office of Nuclear

Material Safety and Safeguards.

Certificate of Compliance No. GDP–1:

Amendment will revise the Technical

Safety Requirement for the cell trip

function.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003.

Dated at Rockville, Maryland, this 15th day

of September 1997.

For the Nuclear Regulatory Commission.

Carl J. Paperiello,

Director, Office of Nuclear Material Safety

and Safeguards.

[FR Doc. 97–25212 Filed 9–22–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket 70–7001]

Notice of Amendment to Certificate of

Compliance GDP–1 for the U.S.

Enrichment Corporation Paducah

Gaseous Diffusion Plant, Paducah,

Kentucky

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

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
Federal Register / Vol. 62, No. 184 / Tuesday, September 23, 1997 / Notices 49711

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: August

11, 1997.

Brief description of amendment: The

amendment proposes to revise

Compliance Plan Issue 3, Action 7

which provides for the modification of

the C–360 autoclave controls to add a

low instrument air pressure switch to

initiate containment upon loss of

instrument air. Instead of adding a low

instrument air pressure switch, USEC

proposes to provide a second channel

for high pressure containment that does

not rely on instrument air. USEC also

proposes to extend the due date from

August 31, 1997 to October 31, 1997.

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 the

High Pressure Isolation and Steam

Pressure Control Systems. The change

will not affect the function of the

system. Because there are no effluent

releases associated with this change, the

proposed change will not affect

effluents.

2. The proposed amendment will not

result in a significant increase in

individual or cumulative occupational

radiation exposure.

The proposed changes will not

significantly increase any exposure to

radiation. Therefore, the changes will

not result in a significant increase in

individual or cumulative radiation

exposure.

3. The proposed amendment will not

result in a significant construction

impact.

The proposed changes will not result

in any building construction, only

equipment modification, 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. The proposed change

will reduce the failure modes of the

High Pressure Isolation and Steam

Pressure Control Systems. The

extension of the completion date will

not significantly increase the probability

of an accident. The existing Justification

for Continued Operation will remain in

effect during the two-month extension.

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.

The function of the High Pressure

Isolation and Steam Pressure Control

systems will not be changed by the

modifications. The proposed changes

will not create any new or different type

of accident.

6. The proposed amendment will not

result in a significant reduction in any

margin of safety.

The safety limit associated with the

modifications remains unchanged. The

proposed change will provide for two

safety channels for initiating autoclave

containment that do not rely on

instrument air. These changes do not

decrease the margins 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.

Implementation of the proposed

changes do not change the safety,

safeguards, or security programs.

Therefore, the effectiveness of the

safety, safeguards, and security

programs is not decreased.

Effective date: The amendment to

Certificate of Compliance GDP–1

becomes effective immediately after

being signed by the Director, Office of

Nuclear Material Safety and Safeguards.

Certificate of Compliance No. GDP–1:

Amendment will revise the Compliance

Plan Issue 3, Action 7 on the autoclave

upgrades to extend the due date by two

months and to allow for mechanicalelectrical pressure switches instead of

pneumatic switches.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003.

Dated at Rockville, Maryland, this 15th day

of September 1997.

For the Nuclear Regulatory Commission.

Carl J. Paperiello,

Director, Office of Nuclear Material Safety

and Safeguards.

[FR Doc. 97–25213 Filed 9–22–97; 8:45 am]

BILLING CODE 7590–01–P

SECURITIES AND EXCHANGE

COMMISSION

[Rel. No. IC–22823; File No. 812–10692]

Variable Annuity Portfolios, et al.;

Notice of Application

September 17, 1997.

AGENCY: Securities and Exchange

Commission (the ‘‘SEC’’ or the

‘‘Commission’’).

ACTION: Notice of Application for an

order under Section 6(c) of the

Investment Company Act of 1940 (the

‘‘1940 Act’’) granting relief from the

provisions of Sections 9(a), 13(a), 15(a)

and 15(b) of the 1940 Act and Rules 6e–

2(b)(15) and 6e–3(T)(b)(15) thereunder.

SUMMARY OF APPLICATION: Applicants

seek exemptive relief to the extent

necessary to permit shares of the

Variable Annuity Portfolio (the ‘‘Trust’’)

to be sold to and held by: (1) separate

accounts (‘‘Separate Accounts’’) funding

variable annuity and variable life

insurance contracts issued by both

affiliated and unaffiliated life insurance

companies (‘‘Participating Insurance

Companies’’); (2) qualified pension and

retirement plans; and (3) subadvisers to

certain series of the Trust.

APPLICANTS: Variable Annuity Portfolios

and Citibank, N.A. (‘‘Citibank’’).

FILING DATE: The application was filed

on June 5, 1997, and an amendment was

filed on September 5, 1997.

HEARING OR NOTIFICATION OF HEARING: An

order granting the application will be

issued unless the Commission orders a

hearing. Interested persons may request

a hearing on this application by writing

to the Secretary of the Secretary of the

SEC and serving Applicants with a copy

of the request, in person or by mail.