40320 Federal Register / Vol. 63, No. 144 /Tuesday, July 28, 1998 / Notices

be provided in the desired format,

reporting burden (time and financial

resources) is minimized, collection

instruments are clearly understood, and

impact of collection requirements on

respondents can be properly assessed.

Currently, the Occupational Safety and

Health Administration (OSHA) is

soliciting comments concerning the

proposed extension of the information

collection requirements contained in the

standard on Accident Prevention Tags

(29 CFR 1910.145). The Agency is

particularly interested in comments

that:

• Evaluate whether the proposed

collection of information is necessary

for the proper performance of the

functions of the Agency, including

whether the information will have

practical utility;

• Evaluate the accuracy of the

Agency’s estimate of the burden of the

proposed collection of information,

including the validity of the

methodology and assumptions used;

• Enhance the quality, utility and

clarity of the information to be

collected; and

• Minimize the burden of the

collection of information on those who

are to respond, including through the

use of appropriate automated,

electronic, mechanical, or other

technological collection techniques or

other forms of information technology,

e.g., permitting electronic submissions

of responses.

DATES: Written comments must be

submitted on or before September 28,

1998.

ADDRESSES: Comments are to be

submitted to the Docket Office, Docket

No. ICR–98–33, Occupational Safety

and Health Administration, U.S.

Department of Labor, Room N–2625,

200 Constitution Avenue, NW.,

Washington, DC 20210. Telephone:

(202) 219–7894. Written comments

limited to 10 pages or less in length may

also be transmitted by facsimile to (202)

219–5046.

FOR FURTHER INFORMATION CONTACT:

Theda Kenney, Directorate of Safety

Standards Programs, Occupational

Safety and Health Administration, U.S.

Department of Labor, Room N–3605,

200 Constitution Avenue, NW.,

Washington, DC 20210, telephone: (202)

219–8061. A copy of the referenced

information collection request is

available for inspection and copying in

the Docket Office and will be mailed to

persons who request copies by

telephoning Theda Kenney at (202) 219–

8061, extension 100, or Barbara Bielaski

at (202) 219–8076, extension 142. For

electronic copies of the Information

Collection Request on Accident

Prevention Tags, contact OSHA’s

WebPage on the Internet at http://

www.osha.gov and click on

‘‘Regulations and Compliance.’’

SUPPLEMENTARY INFORMATION:

I. Background

The Occupational Safety and Health

Act of 1970 (the Act) authorizes the

promulgation of such health and safety

standards as are necessary or

appropriate to provide safe or healthful

employment and places of employment.

The statute specifically authorizes

information collection by employers as

necessary or appropriate for the

enforcement of the Act or for developing

information regarding the causes and

prevention of occupational injuries,

illnesses, and accidents.

In the standard on Accident

Prevention Tags, information

concerning the degree of hazard

associated with a workplace condition

is used by the employer to select the

type of accident prevention tag (sign) to

be used on a workplace hazard. The tag

(sign) selected will identify the

workplace hazard and convey the

severity of hazard and any accident

prevention instruction to the employee.

II. Current Actions

This notice requests public comment

on OSHA’s burden hour estimates prior

to OSHA seeking Office of Management

and Budget (OMB) approval of the

information collection requirements

contained in the standard on Accident

Prevention Tags (29 CFR 1910.145).

Type of Review: Extension of a

Currently Approved Collection.

Agency: U.S. Department of Labor,

Occupational Safety and Health

Administration.

Title: Accident Prevention Tags (29

CFR 1910.145).

OMB Number: 1218–0132.

Agency Number: Docket Number ICR–

98–33.

Affected Public: Business or other forprofit; Not for profit institutions;

Federal Government; State, local or

tribal Government.

Number of Respondents: 112,000.

Frequency: On Occasion.

Average Time Per Response: 3

minutes (.05 hr.).

Estimated Total Burden Hours: 5,600.

Total Annualized Capital/Startup

Costs: $0.

Comments submitted in response to

this notice will be summarized and

included in the request for Office of

Management and Budget (OMB)

approval of the information collection

request. The comments will become a

matter of public record.

Signed at Washington, DC, this 21st day of

July 1998.

Charles N. Jeffress,

Assistant Secretary of Labor.

[FR Doc. 98–20137 Filed 7–27–98; 8:45 am]

BILLING CODE 4510–26–M

NATIONAL CREDIT UNION

ADMINISTRATION

Sunshine Act Meeting

TIME AND DATE: 10:00 a.m., Thursday,

July 30, 1998.

PLACE: Board Room, 7th Floor, Room

7047, 1775 Duke Street, Alexandria, VA

22314–3428.

STATUS: Open.

MATTERS TO BE CONSIDERED:

1. Requests from Two (2) Federal

Credit Unions to Convert to Community

Charters.

2. Request from a Federal Credit

Union to Convert to a State Chartered,

Non-federally Insured Credit Union.

3. Request from a Credit Union to

Convert Insurance.

4. NCUA’s FY–98 Mid-Session Budget

Review.

5. Proposed Amendment: Section

701.21(g), NCUA’s Rules and

Regulations, Real Estate Lending.

6. Proposed Amendment: Section

701.23(b), NCUA’s Rules and

Regulations, Purchase of Eligible

Obligations.

RECESS: 11:15 a.m.

TIME AND DATE: 11:30 a.m, Thursday,

July 30, 1998.

PLACE: Board Room, 7th Floor, Room,

7047, 1775 Duke Street, Alexandria, VA

22314–3428.

STATUS: Closed.

MATTERS TO BE CONSIDERED:

1. Administrative Action under

Sections 205 and 206 of the Federal

Credit Union Act and Part 708 of

NCUA’s Rules & Regulations. Closed

pursuant to exemption (8).

2. Administrative Action under

Section 206 of the Federal Credit Union

Act. Closed pursuant to exemptions (4),

(7), (8), (9)(A)(ii) and (9)(B).

3. Administrative Action under

Section 206 of the FCU Act. Closed

pursuant to exemptions (2) and (8).

4. Administrative Action under Part

704 of NCUA’s Rules and Regulations.

Closed pursuant to exemption (8).

5. Corporate Examiner Review Task

Force Recommendations. Closed

pursuant to exemption (2).

6. Appeal from a Federal Credit Union

of the Regional Director’s Denial of a

Community Charter. Closed pursuant to

exemption (8).
Federal Register / Vol. 63, No. 144 /Tuesday, July 28, 1998 / Notices 40321

7. Three (3) Administrative Actions

under Part 745 of NCUA’s Rules and

Regulations. Closed pursuant to

exemption (6).

8. Seven (7) Personnel Actions.

Closed pursuant to exemptions (2) and

(6).

FOR FURTHER INFORMATION CONTACT:

Becky Baker, Secretary of the Board,

Telephone (703) 518–6304.

Becky Baker,

Secretary of the Board.

[FR Doc. 98–20208 Filed 7–23–98; 4:47 pm]

BILLING CODE 7535–01–M

NUCLEAR REGULATORY

COMMISSION

Northern States Power Company;

Notice of Issuance of Amendment to

Facility Operating License No. DPR–22

Proposed No Significant Hazards

Consideration Determination, and

Opportunity for a Hearing

[Docket No. 50–263]

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. DPR–

22 issued to Northern States Power

Company (the licensee) for operation of

the Monticello Nuclear Generating Plant

located in Wright County, Minnesota.

The proposed amendment would

revise Section 3.6.C, Coolant Chemistry,

and 3/4.17.B, Control Room Emergency

Filtration System, of the Technical

Specifications (TS), Appendix A of the

Operating License for the Monticello

Nuclear Generating Plant. The changes

were proposed to establish TS

requirements consistent with modified

analysis inputs used for the evaluation

of the radiological consequences of the

main steam line break accident. This

amendment request was originally

noticed in the Federal Register on May

6, 1998 (63 FR 25115). On June 19,

1998, supplemented July 1, 1998, the

licensee submitted an application that

superseded in its entirety the licensee’s

previous submittal dated April 11, 1997.

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. The proposed amendment will not

involve a significant increase in the

probability or consequences of an accident

previously evaluated.

A limit is established in the plant

Technical Specifications for steady state

radioiodine concentration in the reactor

coolant to ensure that in the event of a

release of radioactive material to the

environment due to a postulated high energy

line break up to and including a design basis

Main Steam Line Break Accident, radiation

doses are maintained well within the

regulatory guidelines. The steady state

radioiodine concentration in the reactor

coolant is an input for analysis of the

radiological consequences of an accident due

to a Main Steam Line Break outside of

containment and postulated high energy line

breaks. In addition, requirements are

established in the Technical Specifications

for control room habitability. During an

accident, the control room emergency

filtration system provides filtered air to

pressurize the Control Room to minimize the

activity, and therefore the radiological dose,

inside the control room.

A change is proposed for the steady state

radioiodine concentration. This value is

conservative with respect to the value used

in the Main Steam Line Break dose

consequences analysis and is consistent with

the dose consequences evaluation of a

postulated Reactor Water Cleanup (RWCU)

line break. Changes are proposed to the

limiting conditions for operation and

surveillance requirements for the Control

Room Emergency Filtration Train iodine

removal efficiency. These changes are

consistent with the inputs used in the

analysis of the radiological consequences of

the postulated RWCU line break and the

Main Steam Line Break Accident. Changes to

testing requirements are more restrictive and

in accordance with the applicable regulatory

guidance. These proposed requirements

maintain operating restrictions for analytical

inputs used in the analysis of the Main Steam

Line Break Accident. Evaluation of these

events has demonstrated that the postulated

radiological consequences will also remain

within the licensing basis established in the

AEC [Atomic Energy Commission]

Provisional Operating License Safety

Evaluation Report, dated March 18, 1970,

thus the proposed changes do not result in

an increase in the consequences of

previously evaluated accidents.

The analysis of the Main Steam Line Break

Accident performed using a reactor coolant

radioiodine concentration of 2 [micro]Ci/gm

dose equivalent Iodine-131 and a control

room ventilation filter efficiency consistent

with the proposed Technical Specifications

changes demonstrated that radiological

consequences of the Main Steam Line Break

are not changed significantly. The

radiological consequences of the Main Steam

Line Break Accident remain within the

exposure guidelines of 10 CFR 100 and 10

CFR 50 Appendix A, General Design

Criterion 19. The offsite dose consequences

remain bounded by the original licensing

basis provided in the AEC Provisional

Operating License Safety Evaluation Report,

dated March 18, 1970. The control room

doses calculated for the hot standby Main

Steam Line Break Accident using the TID–

14844 dose conversion factors remain

bounded by the dose consequences of the

comparable design basis loss of coolant

accident.

The evaluation of the postulated RWCU

line break, performed using a reactor coolant

radioiodine concentration of 0.25 [micro]Ci/

gm dose equivalent Iodine-131 and a control

room ventilation filter efficiency consistent

with the proposed Technical Specifications

changes, demonstrated that the radiological

consequences of this event remain within the

exposure guidelines of 10 CFR 100 and 10

CFR 50 Appendix A, General Design

Criterion 19. The offsite dose consequences

remain bounded by the Main Steam Line

Break as established in the licensing basis

provided in the AEC Provisional Operating

License Safety Evaluation Report, dated

March 18, 1970.

The proposed Technical Specification

changes do not introduce new equipment

operating modes, nor do the proposed

changes alter existing system relationships.

The proposed changes do not introduce new

failure modes. The system improvements to

reduce bypass leakage during postulated

accidents do not have an adverse effect on

control room habitability. Therefore, this

amendment will not cause a significant

increase in the probability of an accident

previously evaluated for the Monticello

plant.

2. The proposed amendment will not

create the possibility of a new or different

kind of accident from any accident

previously analyzed.

The proposed Technical Specification

changes do not introduce new equipment

operating modes, nor do the proposed

changes alter existing system relationships.

Operator action to mitigate the consequences

of the postulated RWCU line break is

conservative based on the simple action

required by the operator to close the

containment isolation valves within 10

minutes. Isolation at 10 minutes is very

conservative since a safety related RWCU

containment isolation system that was

installed during the 1998 refueling outage

would effect an automatic isolation within

one minute of the RWCU break.

The proposed change to the specification

for reactor coolant dose equivalent

radioiodine is conservative with respect to

the re-evaluation of the Main Steam Line

Break Accident for the more conservative hot

standby initial condition for the postulated

accident. The proposed change to the

specification for reactor coolant dose

equivalent radioiodine is consistent with the

postulated high energy line break of a Reactor