33100 Federal Register / Vol. 63, No. 116 /Wednesday, June 17, 1998 / Notices

(second floor), 970 Broad Street (enter

on Walnut Street), Newark, New Jersey

07102. The hearing will continue, to the

extent necessary, on July 15–16, 1998, at

that same location, beginning at 9:00

a.m. each day. (The sessions are

expected to adjourn at approximately

5:00 p.m. daily.)

As provided by our May 1, 1998

Memorandum and Order, and consistent

with 10 CFR 2.743(b)(3), written direct

testimony of the parties need not be

utilized, but the parties must have in

our hands by Wednesday, July 8, 1998,

lists of witnesses and documents they

propose to use, together with statements

of the qualifications of those witnesses

(curriculum vitae). (If either of the

parties elects to use prefiled written

direct testimony, such testimony should

be filed so as to be in our hands by July

8, 1998.)

Notice is also hereby given that, in

accordance with 10 CFR 2.715(a), the

Licensing Board will hear oral limited

appearance statements on Tuesday, July

14, 1998, at the outset of the hearing and

in the aforementioned hearing room. A

person not a party to the proceeding

will be permitted to make such a

statement, setting forth his or her

position on the issues. The number of

persons making oral statements and the

time allotted for each statement may be

limited depending on the number of

persons present at the designated time.

(Normally, each oral statement may

extend for up to five (5) minutes.) These

statements do not constitute testimony

or evidence but may assist the Licensing

Board and parties in defining the scope

of the issues in the proceeding.

Requests to make oral statements may

be submitted to the Office of the

Secretary, Docketing and Service

Branch, U.S. Nuclear Regulatory

Commission, Washington, D.C. 20555. A

copy of each such request should also

be submitted to Judge Charles

Bechhoefer, Chairman of this Licensing

Board, U.S. Nuclear Regulatory

Commission, ASLBP, T–3 F23,

Washington, D.C. 20555.

Documents relating to this proceeding

are on file at the Commission’s Public

Document Room, the Gelman Building,

2120 L Street, N.W., Washington, D.C.

20555, and at the Commission’s Region

I office, 475 Allendale Road, King of

Prussia, Pennsylvania 19406–1415.

Rockville, Maryland, June 10, 1998.

For the Atomic Safety and Licensing

Board.

Charles Bechhoefer,

Chairman, Administrative Judge.

[FR Doc. 98–16013 Filed 6–16–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket Nos. 50–387/50–388]

Pennsylvania Power and Light

Company; Notice of Withdrawal of

Application for Amendment to Facility

Operating License

The U.S. Nuclear Regulatory

Commission (the Commission) has

granted the request of Pennsylvania

Power and Light Company (the licensee)

to withdraw its October 24, 1994,

application for proposed amendment to

Facility Operating License Nos. NPF–14

and NPF–22 for Susquehanna Steam

Electric Station, Units 1 and 2, located

in Luzerne County, Pennsylvania.

The proposed amendment would

have revised the Technical

Specifications pertaining to title/

organizational changes.

The Commission had previously

issued a Notice of Consideration of

Issuance of Amendment published in

the Federal Register on December 21,

1994 (59 FR 65820). However, by letter

dated June 3, 1998, the licensee

withdrew the proposed change.

For further details with respect to this

action, see the application for

amendment dated October 24, 1994, and

the licensee’s letter dated June 3, 1998,

which withdrew the application for

license amendment. The above

documents 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

located at the Osterhout Free Library,

Reference Department, 71 South

Franklin Street, Wilkes-Barre, PA 18701.

Dated at Rockville, Maryland, this 11th day

of June 1998.

For the Nuclear Regulatory Commission.

Victor Nerses,

Project Manager, Project Directorate I–2,

Division of Reactor Projects—I/II, Office of

Nuclear Reactor Regulation.

[FR Doc. 98–16109 Filed 6–16–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket Nos. 50–387/50–388]

Pennsylvania Power and Light

Company; Notice of Withdrawal of

Application for Amendment to Facility

Operating License

The U.S. Nuclear Regulatory

Commission (the Commission) has

granted the request of Pennsylvania

Power and Light Company (the licensee)

to withdraw its February 29, 1996,

application for proposed amendment to

Facility Operating License Nos. NPF–14

and NPF–22 for Susquehanna Steam

Electric Station, Units 1 and 2, located

in Luzerne County, Pennsylvania.

The proposed amendment would

have revised the Technical

Specifications to delete the Rod Block

Monitor.

The Commission had previously

issued a Notice of Consideration of

Issuance of Amendment published in

the Federal Register on April 10, 1996

(61 FR 15994). However, by letter dated

March 6, 1998, the licensee withdrew

the proposed change.

For further details with respect to this

action, see the application for

amendment dated February 29, 1996,

and the licensee’s letter dated March 6,

1998, which withdrew the application

for license amendment. The above

documents 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

located at the Osterhout Free Library,

Reference Department, 71 South

Franklin Street, Wilkes-Barre, PA 18701.

Dated at Rockville, Maryland, this 11th day

of June 1998.

For The Nuclear Regulatory Commission.

Victor Nerses,

Project Manager, Project Directorate I–2,

Division of Reactor Projects—I/II, Office of

Nuclear Reactor Regulation.

[FR Doc. 98–16134 Filed 6–16–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket 72–16]

Virginia Electric and Power Company,

Issuance of Environmental

Assessment and Finding of No

Significant Impact Regarding the

Proposed Exemptions From

Requirements of 10 CFR Part 72

By letter dated April 29, 1998,

Virginia Electric and Power Company,

(Virginia Power or applicant) requested

exemptions, pursuant to 10 CFR 72.7,

from the requirements of 10 CFR

72.44(d)(3) and 72.72(d). Virginia Power

is seeking a Nuclear Regulatory

Commission (NRC) license to construct

and operate an independent spent fuel

storage installation (ISFSI) at the site of

its North Anna Power Station (NAPS)

located in Louisa County, Virginia.
Federal Register / Vol. 63, No. 116 /Wednesday, June 17, 1998 / Notices 33101

Environmental Assessment (EA)

Identification of Proposed Action

By letter dated May 9, 1995, as

supplemented, and pursuant to 10 CFR

Part 72, Virginia Power submitted an

application for an NRC license for a

North Anna ISFSI. This application is

currently under consideration by the

NRC staff. By letter dated April 29,

1998, the applicant requested an

exemption from the requirements of 10

CFR 72.44(d)(3) and 77.72(d) for the

North Anna ISFSI.

The requirements of 10 CFR

72.44(d)(3) states in part that ‘‘An

annual report be submitted to the

appropriate regional office specified in

Appendix A of Part 73 of this chapter,

with a copy to the Director, Office of

Nuclear Material Safety and Safeguards,

U.S. Nuclear Regulatory Commission,

Washington DC, 20555, within 60 days

after January 1 of each year, specifying

the quantity of each of the principal

radionuclides released to the

environment in liquid and gaseous

effluents during the previous 12 months

of operation * * *’’ Specifically, the

applicant proposes to submit a single

NAPS Effluent Release Report

encompassing the North Anna power

reactors licensed under 10 CFR Part 50

and the proposed ISFSI which would be

licensed pursuant to 10 CFR Part 72.

The applicant also proposes to submit

that report by May 1 of each year rather

than within 60 days of January 1 as

prescribed in 10 CFR 72.44(d)(3).

The applicant also requested an

exemption from the requirements of 10

CFR 72.72(d), which states in part that

‘‘Records of spent fuel and high level

radioactive waste in storage must be

kept in duplicate. The duplicate set of

records must be kept at a separate

location sufficiently remote from the

original records that a single event

would not destroy both sets of records.’’

The applicant proposes to maintain a

single set of records of spent fuel in

storage at a records storage facility that

satisfies the standards set forth in ANSI

N45.2.9–1974.

Separately, the staff is considering

issuance of an exemption from the

requirements of 10 CFR 72.124(b) which

state that ‘‘When practicable the design

of an ISFSI or MRS [monitored

retrievable storage installation] must be

based on favorable geometry,

permanently fixed neutron absorbing

materials (poisons), or both. Where solid

neutron absorbing materials are used,

the design shall provide for positive

means to verify their continued

efficacy.’’ Specifically, the staff is

considering granting an exemption from

the requirement to verify continued

efficacy of neutron absorbing materials.

The proposed action before the

Commission is whether to grant these

exemptions pursuant to 10 CFR 72.7.

Need for the Proposed Action

The applicant is preparing to operate

the North Anna ISFSI described in the

May 9, 1995, application subject to

issuance of an NRC license pursuant to

10 CFR Part 72. The applicant is

implementing the necessary processes

and procedures to operate the ISFSI and

seeks to have those processes make

efficient use of resources. With regard to

annual effluent release reporting, the

applicant already prepares and submits

effluent release reports for the NAPS by

May 1 of each year pursuant to the

NAPS Technical Specifications. The

NAPS effluent release report provides

the same type of data and is generated

by the same licensee program as would

the annual effluent release report for the

ISFSI. The applicant states that

submittal of separate reports for the

NAPS and the ISFSI would entail

duplication of report preparation and

verification data.

With regard to duplicate record

storage for spent fuel records, the

applicant stated that, pursuant to 10

CFR 72.140(d), the Virginia Power

Operational Quality Assurance (QA)

Program Topical Report will be used to

satisfy the QA requirements for the

ISFSI. The QA Program Topical Report

states that QA records are maintained in

accordance with commitments to ANSI

N45.2.9–1974. ANSI N45.2.9–1974

allows for the storage of QA records in

a duplicate storage location sufficiently

remote from the original records or in a

records storage facility subject to certain

provisions designed to protect the

records from fire and other adverse

conditions. The applicant seeks to

streamline and standardize

recordkeeping procedures and processes

for the NAPS and the North Anna ISFSI

spent fuel records. The applicant states

that requiring a separate method of

record storage for ISFSI records diverts

resources unnecessarily.

ANSI N45.2.9–1974 provides

standards for the protection of nuclear

power plant quality assurance records

against degradation. It specifies design

standards for use in the construction of

record storage facilities when use of a

single storage facility is desired. It

includes specific standards for

protection against degradation

mechanisms such as fire, humidity and

condensation. The standards in ANSI

N45.2.9–1974 have been endorsed by

the NRC in Regulatory Guide 1.88,

‘‘Collection, Storage and Maintenance of

Nuclear Power Plant Quality Assurance

Records,’’ as adequate for satisfying the

record keeping requirements of 10 CFR

50, Appendix B. The standards of ANSI

N45.2.9–1974 also satisfy the

requirements of 10 CFR 72.72 by

providing for adequate maintenance of

records regarding the identity and

history of the spent fuel in storage. Such

records would be subject to, and need

to be protected from the same types of

degradation mechanisms, as nuclear

power plant quality assurance records.

With regard to verification of neutron

poison efficacy, the exemption is

necessary to ensure that the licensing

process for the North Anna ISFSI takes

into account previous staff conclusions

that fixed neutron poisons in the TN–32

storage cask will remain effective over

the 20-year period of the license.

Periodic verification of neutron poison

effectiveness is not possible for the TN–

32 cask and, consistent with the staff’s

conclusion described above, is not

necessary.

Environmental Impacts of the Proposed

Action

The Environmental Assessment (EA)

for the license application for the North

Anna ISFSI (62 FR 16202, April 4, 1997)

considered the potential environmental

impacts of construction and operation of

an ISFSI at the North Anna site. The

proposed actions now under

consideration would not change the

potential environmental effects assessed

in the April 4, 1997, EA. Specifically,

there are no environmental impacts

associated with the submittal date for

the annual effluent release report.

Notwithstanding the fact that the ISFSI

is not expected to generate any effluents

under normal or accident conditions,

the submittal date for the required

effluent release report does not change

the amount of effluent to be reported

and, thus, has no impact on the

environment.

With regard to record storage,

elimination of the requirement to store

ISFSI records at a duplicate facility has

no impact on the environment. Storage

of records does not change the methods

by which spent fuel will be handled and

stored at the NAPS and ISFSI and does

not change the amount of any effluents,

radiological or non-radiological,

associated with the ISFSI.

With regard to verification of neutron

absorber efficacy, the applicant has

proposed to use the TN–32 cask at the

North Anna ISFSI. The TN–32 cask

design includes fixed neutron absorbers

but does not provide for periodic

verification of neutron absorber efficacy.

The staff previously evaluated the

efficacy of the TN–32 cask fixed neutron
33102 Federal Register / Vol. 63, No. 116 /Wednesday, June 17, 1998 / Notices

absorbers. In NRC’s November 7, 1996,

safety evaluation of the TN–32 cask

Safety Analysis Report, the staff

concluded that fixed neutron poisons in

the TN–32 cask will remain effective for

the 20-year storage period. The

applicant evaluated the criticality and

radiological aspects of the North Anna

ISFSI based on use of the TN–32 cask,

as described in the North Anna ISFSI

Safety Analysis Report. Consistent with

the staff conclusions in the November 7,

1996, safety evaluation, the applicant

did not propose any verification of TN–

32 cask neutron absorber efficacy. The

staff evaluated the environmental effects

of the North Anna ISFSI and issued its

findings in the April 4, 1997, EA.

Granting an exemption from the

requirements of 10 CFR 72.124(b) will

have no environmental impact because

the staff has determined, through its

safety evaluation of the TN–32 cask, that

periodic verification of the neutron

absorber efficacy is not needed to assure

that the fixed neutron poisons in the

TN–32 cask will remain effective during

the storage period.

Alternative to the Proposed Action

Since there are no environmental

impacts associated with the proposed

actions, alternatives are not evaluated

other than the no action alternative. The

alternative to the proposed action would

be to deny approval of the exemption

and, therefore, not allow (1) submittal of

an annual effluent release report by May

1 rather than within 60 days of January

1, or (2) storage of ISFSI spent fuel

records at a single qualified record

storage facility, or (3) elimination of the

requirement to verify the efficacy of

neutron absorbing materials. These

alternatives would have the same, or

greater, environmental impacts.

Agencies and Persons Consulted

An official from the State of Virginia

Bureau of Radiological Health was

contacted about the EA for the proposed

action and had no concerns.

Finding of No Significant Impact

The environmental impacts of the

proposed action have been reviewed in

accordance with the requirements set

forth in 10 CFR Part 51. Based upon the

foregoing EA, the Commission finds that

the proposed action of (1) granting an

exemption from 10 CFR 72.44(d)(3) so

that Virginia Power may submit an

annual effluent release report by May 1

of each year, (2) granting an exemption

from 10 CFR 72.72(d) so that Virginia

Power may store records of spent fuel

stored at the ISFSI in a single record

storage facility which meets the

standards of ANSI N45.2.9–1974, and

(3) granting an exemption from 10 CFR

72.124(b) so that Virginia Power need

not verify the efficacy of the neutron

absorbing material in ISFSI storage

casks will not significantly impact the

quality of the human environment.

Accordingly, the Commission has

determined not to prepare an

environmental impact statement for the

proposed exemption.

This application was docketed under

10 CFR Part 72, Docket 72–16. For

further details with respect to this

action, see the application for an ISFSI

license dated May 9,1995, and the

request for exemption dated April 29,

1998, which is available for public

inspection at the Commission’s Public

Document Room, 2120 L Street, NW,

Washington, DC 20555, and the Local

Public Document Room at the

University of Virginia, Alderman

Library, Charlottesville, Virginia 22903.

Dated at Rockville, Maryland, this 10th day

of June 1998.

For the Nuclear Regulatory Commission.

William F. Kane,

Director, Spent Fuel Project Office, Office of

Nuclear Material Safety and Safeguards.

[FR Doc. 98–16018 Filed 6–16–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Advisory Committee on Reactor

Safeguards; Subcommittee Meeting on

Advanced Reactor Designs; Notice of

Meeting

The ACRS Subcommittee on

Advanced Reactor Designs will hold a

meeting on July 6–7, 1998, Room T–

2B3, 11545 Rockville Pike, Rockville,

Maryland.

A portion of the meeting may be

closed to public attendance to discuss

Westinghouse proprietary information

per 5 U.S.C. 552b(c)(4) and safeguards

information per 5 U.S.C. 552b(c)(3)

related to the AP600 design.

The agenda for the subject meeting

shall be as follows:

Monday, July 6, 1998—8:30 a.m. until

the conclusion of business

Tuesday, July 7, 1998—8:30 a.m. until

the conclusion of business

The Subcommittee will continue its

review of the Westinghouse AP600

design. Specifically, the Subcommittee

will review issues identified by ACRS

members at previous meetings related to

the AP600 design. 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

public, and questions may be asked only

by members of the Subcommittee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the cognizant ACRS staff engineer

named below five days prior to the

meeting, if possible, so that appropriate

arrangements can be made.

During the initial portion of the

meeting, the Subcommittee, along with

any of its consultants who may be

present, may exchange preliminary

views regarding matters to be

considered during the balance of the

meeting.

The Subcommittee will then hear

presentations by and hold discussions

with representatives of the NRC staff,

Westinghouse Electric Company, their

consultants, and other interested

persons regarding this review.

Further information regarding topics

to be discussed, the scheduling of

sessions open to the public, whether the

meeting has been cancelled or

rescheduled, and the Chairman’s ruling

on requests for the opportunity to

present oral statements and the time

allotted therefor, can be obtained by

contacting the cognizant ACRS staff

engineer, Mr. Noel F. Dudley (telephone

301/415–6888) between 7:30 a.m. and

4:15 p.m. (EDT). Persons planning to

attend this meeting are urged to contact

the above named individual one or two

working days prior to the meeting to be

advised of any potential changes to the

agenda, etc., that may have occurred.

Dated: June 11, 1998.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 98–16094 Filed 6–16–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Advisory Committee on Reactor

Safeguards Subcommittee Meeting on

Planning and Procedures; Notice of

Meeting

The ACRS Subcommittee on Planning

and Procedures will hold a meeting on

July 7, 1998, Room T–2B1, 11545

Rockville Pike, Rockville, Maryland.

The entire meeting will be open to

public attendance, with the exception of

a portion that may be closed pursuant

to 5 U.S.C. 552b(c) (2) and (6) to discuss