60192 Federal Register / Vol. 69, No. 194 / Thursday, October 7, 2004 / Notices 

Docket Office for information about 

materials not available through the 

OSHA Web page and for assistance 

using the Web page to locate docket 

submissions. 

Electronic copies of this Federal 

Register notice as well as other relevant 

documents are available on OSHA’s 

Web page. 

II. Background 

The Department of Labor, as part of its 

continuing effort to reduce paperwork 

and respondent (i.e., employer) burden, 

conducts a preclearance consultation 

program to provide the public with an 

opportunity to comment on proposed 

and continuing information collection 

requirements in accordance with the 

Paperwork Reduction Act of 1995 

(PRA–95) (44 U.S.C. 3506(c)(2)(A)). 

This program ensures that 

information is in the desired format, 

reporting burden (time and costs) is 

minimal, collection instruments are 

clearly understood, and OSHA’s 

estimate of the information collection 

burden is accurate. The Occupational 

Safety and Health Act of 1970 (the Act) 

(29 U.S.C. 651 et seq.) authorizes 

information collection by employers as 

necessary or appropriate for 

enforcement of the Act or for developing 

information regarding the causes and 

prevention of occupational injuries, 

illnesses, and accidents (29 U.S.C. 657). 

Paragraph (g)(4)(ii)(I) of the Cranes 

and Derricks Standard for Construction 

(Sec. 1926.550) requires employers to 

post conspicuously with a plate or other 

permanent marking the weight and 

rated load capacity or maximum 

intended loads of each platform used to 

raise and lower employees to a worksite 

using a crane or derrick. This 

requirement helps employers to avoid 

exceeding the lifting capacity of such 

platforms and the cranes or derrick 

being used to lift the platforms. 

Therefore, this requirement can prevent 

the platform, crane, or derrick from 

collapsing and causing serious injury to 

death to employees on or below the 

platform. 

III. Special Issues for Comment 

OSHA has a particular interest in 

comments on the following issues:

• Whether the proposed information 

collection requirements are necessary 

for the proper performance of the 

Agency’s functions, including whether 

the information is useful; 

• The accuracy of OSHA’s estimate of 

the burden (time and costs) of the 

information collection requirements, 

including the validity of the 

methodology and assumptions used; 

• The quality, utility, and clarity of 

the information collected; and 

• Ways to minimize the burden on 

employers who must comply; for 

example, by using automated or other 

technological information collection 

and transmission techniques. 

IV. Proposed Actions 

OSHA is proposing to extend the 

information collection requirement 

specified by paragraph (g)(4)(ii)(I) of 

Sec. 1926.550. The Agency will 

summarize the comments submitted in 

response to this notice and will include 

this summary in its request to OMB to 

extend the approval of this information 

collection requirements contained in the 

Standard. 

Type of Review: Extension of 

currently approved information 

collection requirements. 

Title: Cranes and Derricks Standard 

for Construction; Posting Weight and 

Load Capacity of Personnel Platforms 

(29 CFR 1926.550). 

OMB Number: 1218–0151. 

Affected Public: Business or other forprofit; not-for-profit institutions; Federal 

government; State, local, or Tribal 

governments. 

Number of Respondents: 2,750 

(platforms). 

Frequency of Response: On occasion. 

Total Responses: 2,750. 

Average Time per Response: Five 

minutes to post or mark a platform. 

Estimated Total Burden Hours: 229. 

Estimated Cost. (Operation and 

Maintenance): $0. 

V. Authority and Signature 

John L. Henshaw, Assistant Secretary 

of Labor for Occupational Safety and 

Health, directed the preparation of this 

notice. The authority for this notice is 

the Paperwork Reduction Act of 1995 

(44 U.S.C. 3506 et seq.), and Secretary 

of Labor’s Order No. 5–2002 (67 FR 

65008).

Signed at Washington, DC, on October 4, 

2004. 

John L. Henshaw, 

Assistant Secretary of Labor.

[FR Doc. 04–22600 Filed 10–6–04; 8:45 am] 

BILLING CODE 4510–26–M

NUCLEAR REGULATORY 

COMMISSION 

Draft Regulatory Guide; Issuance, 

Availability 

The U.S. Nuclear Regulatory 

Commission (NRC) has issued for public 

comment a draft of a new guide in the 

agency’s Regulatory Guide Series. This 

series has been developed to describe 

and make available to the public such 

information as methods that are 

acceptable to the NRC staff for 

implementing specific parts of the 

NRC’s regulations, techniques that the 

staff uses in evaluating specific 

problems or postulated accidents, and 

data that the staff needs in its review of 

applications for permits and licenses. 

The new draft regulatory guide, 

entitled ‘‘Risk-Informed, PerformanceBased Fire Protection for Existing LightWater Nuclear Power Plants,’’ is 

temporarily identified by its task 

number, DG–1139, which should be 

mentioned in all related 

correspondence. The draft regulatory 

guide contains the staff’s regulatory 

position on ‘‘Guidance for 

Implementing a Risk-Informed, 

Performance-Based Fire Protection 

Program Under 10 CFR 50.48(c),’’ which 

the Nuclear Energy Institute (NEI) has 

promulgated as document #NEI 04–02. 

It is the staff’s intent to endorse a 

version of NEI 04–02, as appropriate, in 

the final regulatory guide, consistent 

with the new risk-informed, 

performance-based fire protection rule, 

specified in Title 10, Section 50.48(c), of 

the Code of Federal Regulations [10 CFR 

50.48(c)], which the NRC has issued for 

existing light-water nuclear power 

plants. This new regulation provides a 

voluntary alternative to the 

requirements of Appendix R to 10 CFR 

part 50, ‘‘Fire Protection Program for 

Nuclear Power Facilities Operating Prior 

to January 1, 1979.’’ As such, the new 

rule endorses a national consensus 

standard (NEI 04–02), sets performance 

goals and criteria, and takes advantage 

of experience and enhanced 

methodologies. 

The NRC staff is soliciting comments 

on draft regulatory guide DG–1139, and 

comments may be accompanied by 

relevant information or supporting data. 

Please mention DG–1139 [50.48(c) RG] 

in the subject line of your comments. 

Comments on this draft regulatory guide 

submitted in writing or in electronic 

form will be made available to the 

public in their entirety on the NRC’s 

rulemaking Web site. Personal 

information will not be removed from 

your comments. You may submit 

comments by any of the following 

methods. 

Mail comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555–

0001. 

Email comments to: 

NRCREP@nrc.gov. You may also submit 

comments via the NRC’s rulemaking 

Web site at http://ruleforum.llnl.gov. 

Address questions about our rulemaking 

Federal Register / Vol. 69, No. 194 / Thursday, October 7, 2004 / Notices 60193

Web site to Carol A. Gallagher (301) 

415–5905; email CAG@nrc.gov. 

Hand-deliver comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, 11555 Rockville Pike, 

Rockville, Maryland 20852, between 

7:30 a.m. and 4:15 p.m. on Federal 

workdays. 

Fax comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission at (301) 415–5144. 

Request for information about draft 

regulatory guide DG–1139 may be 

directed to Paul W. Lain at (301) 415–

2346 or via email to PWL@nrc.gov. 

Comments would be most helpful if 

received by December 15, 2004. 

Comments received after this date will 

be considered if it is practical to do so, 

but the NRC is able to ensure 

consideration only for comments 

received on or before this date. 

Although a time limit is given, 

comments and suggestions in 

connection with items for inclusion in 

guides currently being developed or 

improvements in all published guides 

are encouraged at any time. 

Electronic copies of the draft 

regulatory guide are available through 

the NRC’s public Web site under Draft 

Regulatory Guides in the Regulatory 

Guides document collection of the 

NRC’s Electronic Reading Room at

http://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also 

available in the NRC’s Agencywide 

Documents Access and Management 

System (ADAMS) at http://

www.nrc.gov/reading-rm/adams.html, 

under Accession No. ML042740308. In 

addition, regulatory guides are available 

for inspection at the NRC’s Public 

Document Room (PDR), which is 

located at 11555 Rockville Pike, 

Rockville, Maryland; the PDR’s mailing 

address is USNRC PDR, Washington, DC 

20555–0001. The PDR can also be 

reached by telephone at (301) 415–4737 

or (800) 397–4205, by fax at (301) 415–

3548; and by email to PDR@nrc.gov. 

Requests for single copies of draft or 

final guides (which may be reproduced) 

or for placement on an automatic 

distribution list for single copies of 

future draft guides in specific divisions 

should be made in writing to the U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, Attention: 

Reproduction and Distribution Services 

Section; by email to 

DISTRIBUTION@nrc.gov; or by fax to 

(301) 415–2289. Telephone requests 

cannot be accommodated. Regulatory 

guides are not copyrighted, and 

Commission approval is not required to 

reproduce them. (U.S.C. 552(a))

Dated at Rockville, Maryland, this 30th day 

of September , 2004. 

For the U.S. Nuclear Regulatory 

Commission. 

Sharon D. Stewart, 

Acting Director, Program Management, Policy 

Development and Analysis Staff, Office of 

Nuclear Regulatory Research.

[FR Doc. 04–22545 Filed 10–6–04; 8:45 am] 

BILLING CODE 7590–01–P

NUCLEAR REGULATORY 

COMMISSION 

Proposed Generic Communication; 

Steam Generator Tube Integrity and 

Associated Technical Specifications

AGENCY: Nuclear Regulatory 

Commission.

ACTION: Notice of opportunity for public 

comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is proposing to issue 

a generic letter (GL) to request that 

addressees submit a description of their 

program for ensuring steam generator 

(SG) tube integrity for the interval 

between inspections and description of 

the methodology used to assess the 

effects of non-pressure-related loads 

such as bending on SG tube integrity. 

Addressees should also provide a safety 

assessment demonstrating that the SG 

tubes will have adequate structural and 

leakage integrity (with appropriate 

regulatory margins) at the time of their 

next SG tube inspection, taking into 

account the effects of non-pressurerelated loads. 

This Federal Register notice is 

available through the NRC’s 

Agencywide Documents Access and 

Management System (ADAMS) under 

accession number ML042710075.

DATES: Comment period expires 

December 6, 2004. Comments submitted 

after this date will be considered if it is 

practical to do so, but assurance of 

consideration cannot be given except for 

comments received on or before this 

date.

ADDRESSEES: Submit written comments 

to the Chief, Rules and Directives 

Branch, Division of Administrative 

Services, Office of Administration, U.S. 

Nuclear Regulatory Commission, Mail 

Stop T6-D59, Washington, DC 20555–

0001, and cite the publication date and 

page number of this Federal Register

notice. Written comments may also be 

delivered to NRC Headquarters, 11545 

Rockville Pike (Room T–6D59), 

Rockville, Maryland, between 7:30 am 

and 4:15 pm on Federal workdays.

FOR FURTHER INFORMATION CONTACT:

Kenneth Karwoski, NRR at 301–415–

2752 or by e-mail at kjk1@nrc.gov or 

Maitri Banerjee, NRR at 301–415–2277 

or by e-mail at mxb@nrc.gov.

SUPPLEMENTARY INFORMATION: 

Draft NRC Generic Letter 2004–XX: 

Steam Generator Tube Integrity and 

Associated Technical Specifications 

Addressees 

All holders of operating licenses for 

pressurized-water reactors (PWRs), 

except those who have permanently 

ceased operations and have certified 

that fuel has been permanently removed 

from the reactor vessel and {the 

following plants that have already 

modified their technical specifications 

to be consistent with those in the 

Attachment}. 

Purpose 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing this 

generic letter (GL) to: 

(1) Request that addressees submit a 

description of their program for 

ensuring steam generator (SG) tube 

integrity for the interval between 

inspections; and 

(2) Request that addressees submit a 

description of the methodology used to 

assess the effects of non-pressure-related 

loads such as bending on SG tube 

integrity. Addressees should also 

provide a safety assessment 

demonstrating that the SG tubes will 

have adequate structural and leakage 

integrity (with appropriate regulatory 

margins) at the time of their next SG 

tube inspection, taking into account the 

effects of non-pressure-related loads. 

Discussion 

Steam generator tubes function as an 

integral part of the reactor coolant 

pressure boundary (RCPB) and also 

serve to isolate radiological fission 

products in the primary coolant from 

the secondary coolant and the 

environment. For the purposes of this 

generic letter, tube integrity means that 

the tubes are capable of performing 

these functions in accordance with the 

plant design and licensing basis, 

including applicable regulatory 

requirements. 

During operation, licensees are 

required to monitor and maintain the 

condition of the SG tubing with the 

objective of ensuring its continued 

integrity. Specifically, licensees are 

required by 10 CFR 50.55a(b)(2)(iii), 10 

CFR 50.55a(g), or by the plant technical 

specifications to perform periodic 

inservice inspections and to repair (e.g., 

sleeve) or remove from service (by 

installing plugs in the tube ends) all 

tubes found to contain flaws exceeding