Federal Register / Vol. 62, No. 43 / Wednesday, March 5, 1997 / Notices 10087

SUMMARY: The NRC has recently

submitted to OMB for review the

following proposal for collection of

information under the provisions of the

Paperwork Reduction Act of 1995 (44

U.S.C. Chapter 35).

1. Type of submission, new, revision,

or extension: Revision.

2. The title of the information

collection: 10 CFR Part 34, ‘‘Licenses for

Radiography and Radiation Safety

Requirements for Radiographic

Operations,’’ 10 CFR Part 71,

‘‘Packaging and Transportation of

Radioactive Material,’’ and NRC Form

313, Application for Material License.

3. The form number if applicable:

NRC Form 313.

4. How often is the collection

required: On occasion, such as upon

submittal of an application for a

materials license or renewal, or upon

discovery of a leaking source.

5. Who will be required or asked to

report: Licensees and applicants

requesting approvals in accordance with

10 CFR Part 34.

6. An estimate of the number of

responses: Part 34—696, Part 71—

(–)450, NRC Form 313—450.

7. The estimated number of annual

respondents: 450.

8. An estimate of the number of hours

needed annually to complete the

requirement or request: Part 34—1,440

hours for reporting (approximately 3.2

hours per response) plus an additional

41,406 hours for recordkeeping

(approximately 92 hours per licensee);

Part 71—(–)1,440 hours for reporting

and recordkeeping (approximately

(–)3.2 hours per response); NRC Form

313—5,850 hours for 450 licensees

(approximately 13 hours per response).

9. An indication of whether Section

3507(d), Pub. L. 104–13 applies:

Applicable.

10. Abstract: The NRC regulation, 10

CFR Part 34, specifies the information

and data to be provided by applicants

and licensees using byproduct material

for industrial radiography. 10 CFR Part

34 has been revised in its entirety. The

revision adds to or modifies the

requirements to include additional

training of radiographers’ assistants,

leak tests of ‘‘S’’ tubes, and specifies

records to be kept at various locations.

The revision deletes the requirement for

radiography licensees to submit a

Quality Assurance program under 10

CFR Part 71. The revision requires the

following additional information to be

reported on NRC Form 313, Application

for Materials License: locations and

descriptions of all field stations and

permanent radiographic installations,

designation of a Radiation Safety

Officer, and additional information on

training and testing. This information is

reviewed by NRC to ensure that the

safety of radiographers and the public is

protected.

Submit by April 4, 1997, comments

that address the following question:

1. Is the proposed collection of

information necessary for the NRC to

properly perform its functions? Does the

information have practical utility?

2. Is the burden estimate accurate?

3. Is there a way to enhance the

quality, utility, and clarity of the

information to be collected?

4. How can the burden of the

information collection be minimized,

including the use of automated

collection techniques or other forms of

information technology?

A copy of the submittal may be

viewed free of charge at the NRC Public

Document Room, 2120 L Street, NW

(Lower Level), Washington, DC 20555–

0001. Members of the public who are in

the Washington, DC, area can access this

document via modem on the Public

Document Room Bulletin Board (NRC’s

Advanced Copy Document Library),

NRC subsystem at FedWorld, 703–321–

3339. Members of the public who are

located outside of the Washington, DC,

area can dial FedWorld, 1–800–303–

9672), or use the FedWorld Internet

address: fedworld.gov (Telnet). The

document will be available on the

bulletin board for 30 days after the

signature date of this notice. If

assistance is needed in accessing the

document, please contact the FedWorld

help desk at 703–487–4608. Additional

assistance in locating the document is

available from the NRC Public

Document Room, nationally at 1–800–

397–4209, or within the Washington,

DC, area at 202–634–3273.

Comments and questions should be

directed to the OMB reviewer by April

4, 1997: Edward Michlovich, Office of

Information and Regulatory Affairs,

(3150–0007 and 3150–0120), NEOB–

10202, Office of Management and

Budget, Washington, DC 20503.

Comments can also be submitted by

telephone at (202) 395–3084.

The NRC Clearance Officer is Brenda

Jo Shelton, (301) 415–7233.

Dated at Rockville, Maryland, this 26th day

of February, 1997.

For the Nuclear Regulatory Commission.

Gerald F. Cranford,

Designated Senior Official for Information

Resources Management.

[FR Doc. 97–5384 Filed 3–4–97; 8:45 am]

BILLING CODE 7590–01–P

Agency Information Collection

Activities: Submission for OMB

Review; Comment Request

AGENCY: U.S. Nuclear Regulatory

Commission (NRC).

ACTION: Notice of the OMB review of

information collection and solicitation

of public comment.

SUMMARY: The NRC has recently

submitted to OMB for review the

following proposal for the collection of

information under the provisions of the

Paperwork Reduction Act of 1995 (44

U.S.C. Chapter 35). The NRC hereby

informs potential respondents that an

agency may not conduct or sponsor, and

that a person is not required to respond

to, a collection of information unless it

displays a currently valid OMB control

number.

1. Type of submission, new, revision,

or extension: Revision.

2. The title of the information

collection: Reactor Operator and Senior

Reactor Operator Licensing Training

and Requalification Programs.

3. The form number if applicable: Not

applicable.

4. How often the collection is

required: As needed per facility;

generally once or less per year.

5. Who will be required or asked to

report: All reactor licensees and

applicants for an operating license at

power and non-power reactors.

6. An estimate of the number of

responses: One each for 72 power

reactors and 30 non-power reactors

annually.

7. The estimated number of annual

respondents: 75 for power reactors and

30 for non-power reactors.

8. An estimate of the total number of

hours needed annually to complete the

requirement or request: 27,882 hours

annually (24,882 hours for reporting and

3000 hours for recordkeeping for power

reactor licensees (387 hours per

response) and 124 reporting hours

annually for non-power reactor

licensees (4 hours per response).

9. An indication of whether section

3507(d), Public Law. 104–13 applies:

Not applicable.

10. Abstract: The NRC requests copies

of initial and requalification training

material and examinations from reactor

licensees/applicants. The training

material is used by the NRC staff to

develop operator and senior operator

licensing and requalification

examinations. The initial examinations

are reviewed, modified, and approved

by the NRC staff for use in licensing

operators and senior operators; the

requalification examinations are

inspected to verify regulatory

compliance.
10088 Federal Register / Vol. 62, No. 43 / Wednesday, March 5, 1997 / Notices

A copy of the submittal may be

viewed free of charge at the NRC Public

Document Room, 2120 L Street, NW.

(Lower Level), Washington, DC.

Members of the public who are in the

Washington, DC, area can access the

submittal via modem on the Public

Document Room Bulletin Board (NRC’s

Advanced Copy Document Library) NRC

subsystem at FedWorld, 703–321–3339.

Members of the public who are located

outside of the Washington, DC, area can

dial FedWorld, 1–800–303–9672, or use

the FedWorld Internet address:

fedworld.gov (Telnet). The document

will be available on the bulletin board

for 30 days after the signature date of

this notice. If assistance is needed in

accessing the document, please contact

the FedWorld help desk at 703–487–

4608. Additional assistance in locating

the document is available from the NRC

Public Document Room, nationally at 1–

800–397–4209, or within the

Washington, DC, area at 202–634–3273.

Comments and questions should be

directed to the OMB reviewer by April

4, 1997: Edward Michlovich, Office of

Information and Regulatory Affairs

(3150–0101) NEOB–10202, Office of

Management and Budget, Washington,

DC 20503. Comments can also be

submitted by telephone at (202) 395–

3084.

The NRC Clearance Officer is Brenda

Jo. Shelton, (301) 415–7233.

Dated at Rockville, Maryland, this 28th day

of February, 1997.

For the Nuclear Regulatory Commission.

Gerald F. Cranford,

Designated Senior Official, Information

Resources Management.

[FR Doc. 97–5506 Filed 3–4–97; 8:45 am]

BILLING CODE 7590–01–P

[Docket Nos. 50–237 and 50–249]

Commonwealth Edison Company;

Notice of Consideration of Issuance of

Amendments to Facility Operating

Licenses, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of amendments to

Facility Operating License Nos. DPR–19

and DPR–25, issued to Commonwealth

Edison Company (ComEd, the licensee)

for operation of the Dresden Nuclear

Power Station, Units 2 and 3, located in

Grundy County, Illinois.

The proposed amendments would

change the Technical Specifications

(TS) by relocating the TS requirements

associated with the 24/48 Vdc batteries,

battery chargers and distribution

systems to other licensee

administratively controlled documents.

Before issuance of the proposed

license amendments, 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

amendments requested involve 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) Involve a significant increase in the

probability or consequences of an accident

previously evaluated because of the

following:

Removal of the 24/48 Vdc batteries,

chargers, and distribution panels from the

Technical Specification requirements of 3/

4.9.C, 3/4.9.D, 3/4.9.E, and 3/4.9.F and the

subsequent relocation of those requirements

to licensee administrative control is an

administrative change that will still ensure

the availability of the 24/48 Vdc system and

will not increase the probability of accidents

previously evaluated. Relocation of the 24/48

Vdc requirements to administrative controls

will have no effect on the control

instrumentation and cannot act as an initiator

for any of the accidents evaluated in the

UFSAR [Updated Final Safety Analysis

Report].

Similarly, relocation of the 24/48 Vdc

system requirements to licensee

administrative control will have no effect on

the availability of the loads which are

supplied by the 24/48 Vdc batteries nor on

any of the consequences of accidents

previously evaluated in the UFSAR. Control

of the 24/48 Vdc requirements by station

administrative controls under 10 CFR 50.59

will not affect any of the protection or

mitigation functions which may be provided

by any of the loads supplied by the batteries.

Operation under the proposed amendment

will not significantly increase the probability

or consequences of any accidents previously

evaluated.

Because of the above evaluation, removal

of the 24/48 Vdc system from the Technical

Specifications will not involve a significant

increase in the probability or the

consequences of an accident previously

evaluated.

(2) Create the possibility of a new or

different kind of accident from any accident

previously evaluated because:

The 24/48 Vdc batteries, chargers, and

other components will retain the separation,

and redundancy under which they are

presently installed. No new failure modes are

introduced by this administrative relocation

of requirements, for the 24/48 Vdc system,

from the Technical Specifications to licensee

administrative control. The possibility of a

new or different accident from any accident

previously evaluated is not increased or

created by this administrative change.

(3) Involve a significant reduction in the

margin of safety because:

Relocation of the TS requirements for the

24/48 Vdc system does not affect the

operating points or setpoints of any systems

or components. Plant operating points or

parameters are not changed by this proposed

relocation of requirements in this

amendment request. The safety related

equipment that is supported by the 24/48

Vdc system will continue to be required in

the existing modes of applicability as

determined by the individual equipment

Technical Specifications. Thus operation

under the proposed license amendment

removes some redundancy and constraints

during refueling but does not significantly

reduce the margin of safety.

The NRC staff has reviewed the

licensee’s analysis and, based on this

review, it appears that the three

standards of 10 CFR 50.92(c) are

satisfied. Therefore, the NRC staff

proposes to determine that the

amendments requested involve no

significant hazards consideration.

The Commission is seeking public

comments on this proposed

determination. Any comments received

within 30 days after the date of

publication of this notice will be

considered in making any final

determination.

Normally, the Commission will not

issue the amendments until the

expiration of the 30-day notice period.

However, should circumstances change

during the notice period such that

failure to act in a timely way would

result, for example, in derating or

shutdown of the facility, the

Commission may issue the license

amendments before the expiration of the

30-day notice period, provided that its

final determination is that the

amendments involve no significant

hazards consideration. The final

determination will consider all public

and State comments received. Should

the Commission take this action, it will

publish in the Federal Register a notice

of issuance and provide for opportunity

for a hearing after issuance. The

Commission expects that the need to

take this action will occur very

infrequently.

Written comments may be submitted

by mail to the Chief, Rules Review and

Directives Branch, Division of Freedom

of Information and Publications