57366 Federal Register / Vol. 69, No. 185 / Friday, September 24, 2004 / Notices 

SUMMARY: ACCSH will meet October 19–

20, 2004, in Washington, DC. This 

meeting is open to the public.

TIME AND DATE: ACCSH will meet from 

8:30 a.m. to 4:30 p.m., Tuesday, October 

19, 2004, and 8:30 a.m. to noon, 

Wednesday, October 20, 2004.

PLACE: ACCSH will meet at the U.S. 

Department of Labor, Frances Perkins 

Building, Room N3437A/B/C, 200 

Constitution Avenue, NW., Washington, 

DC.

FOR FURTHER INFORMATION CONTACT: For 

general information about ACCSH and 

ACCSH meetings: Michael Buchet, 

OSHA, Directorate of Construction, 

Room N–3468, U.S. Department of 

Labor, 200 Constitution Avenue, NW., 

Washington, DC 20210; telephone 202–

693–2020. For information about 

submission of comments, requests to 

speak, and the need for special 

accommodations for the meeting: 

Veneta Chatmon, OSHA, Office of 

Public Affairs, Room N–3647, U.S. 

Department of Labor, 200 Constitution 

Avenue, NW., Washington, DC 20210; 

telephone 292–693–1999. Individuals 

needing special accommodations should 

contact Ms. Chatmon no later than 

October 4, 2004. Electronic copies of 

this Federal Register notice, as well as 

information about ACCSH workgroups 

and other relevant documents, are 

available at OSHA’s Webpage on the 

Internet at http://www.osha.gov.

SUPPLEMENTARY INFORMATION: ACCSH 

will meet October 19–20, 2004, in 

Washington, DC. The agenda for this 

meeting includes: 

• Remarks—Office of the Assistant 

Secretary—OSHA. 

• Welcome to new members. 

• Hispanic Summit Report. 

• Standards Update. 

• Work Group Assignments/Reports. 

• Partnership and Alliance Update. 

• Public Comment (During this 

period, any member of the public is 

welcome to address ACCSH about 

construction-related safety and health 

issues. See information below to request 

time to speak at the meeting.) 

All ACCSH meetings are open to the 

public. An official record of the meeting 

will be available for public inspection at 

the OSHA Docket Office, Room N–2625, 

at the address above, telephone (202) 

693–2350. Electronic copies of this 

Federal Register notice, as well as 

information about ACCSH workgroups 

and other relevant documents, are 

available at OSHA’s Web page on the 

Internet at http://www.osha.gov. 

Interested parties may submit written 

data, views or comments, preferably 

with 20 copies, to Ms. Chatmon, at the 

address above. OSHA will provide 

submissions received prior to the 

meeting to ACCSH members and will 

include each submission in the record 

of the meeting. Attendees may also 

request to make an oral presentation by 

notifying Veneta Chatmon before the 

meeting at the address above. The 

request must state the amount of time 

desired, the interest represented by the 

presenter (e.g., the name of the business 

or organization), if any, and a brief 

outline of the presentation. The Chair of 

ACCSH may grant the request at his 

discretion and as time permits. 

ACCSH Work Groups 

The ACCSH Excavation work group 

will meet from 8:30 a.m.–4:30 p.m. 

Tuesday, September 28, 2004 in Room 

N3437A/B/C of the Frances Perkins 

Building at the address above. 

The ACCSH Tower Erection work 

group will meet from 1 p.m.–4:30 p.m., 

Monday, October 18, 2004, in Room 

N3437A/B of the Frances Perkins 

Building at the address above. Work 

group meetings are open to the public. 

For further information on ACCSH work 

group meetings or on participating on 

ACCSH work groups, please contact 

Michael Buchet at the address above or 

look on the ACCSH page on OSHA’s 

Web page at http://www.osha.gov.

Authority: John L. Henshaw, Assistant 

Secretary of Labor for Occupational Safety 

and Health, directed the preparation of this 

notice under the authority granted by section 

7 of the Occupational Safety and Health Act 

of 1970 (29 U.S.C. 656), section 107 of the 

Contract Work Hours and Safety Standards 

Act (Construction Safety Act) (40 U.S.C. 333), 

and Secretary of Labor’s Order No. 5–2002 

(67 FR 65008).

Signed at Washington, DC this 15th day of 

September, 2004. 

John L. Henshaw, 

Assistant Secretary of Labor.

[FR Doc. 04–21449 Filed 9–23–04; 8:45 am] 

BILLING CODE 4510–26–P

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–315 and 50–316] 

Indiana Michigan Power Company 

Donald C. Cook Nuclear Plant; Notice 

of Availability of the Draft Supplement 

20 to the Generic Environmental 

Impact Statement and Public Meeting 

for the License Renewal of Donald C. 

Cook Nuclear Plant, Units 1 and 2 

Notice is hereby given that the U.S. 

Nuclear Regulatory Commission (the 

Commission) has published a draft 

plant-specific supplement to the 

Generic Environmental Impact 

Statement (GEIS), NUREG–1437, 

regarding the renewal of operating 

licenses DPR–58 and DPR–74 for an 

additional 20 years of operation at 

Donald C. Cook Nuclear Plant, Units 1 

and 2 (CNP). CNP is located in Berrien 

County, Michigan, about 55 miles east 

of Chicago, Illinois. Possible alternatives 

to the proposed action (license renewal) 

include no action and reasonable 

alternative energy sources. 

The draft Supplement to the GEIS is 

available for public inspection in the 

NRC Public Document Room (PDR) 

located at One White Flint North, 11555 

Rockville Pike (first floor), Rockville, 

Maryland, 20852 or from the Publicly 

Available Records (PARS) component of 

NRC’s Agencywide Documents Access 

and Management System (ADAMS). 

ADAMS is accessible from the NRC Web 

site at http://www.nrc.gov/reading-rm/

adams.html (the Public Electronic 

Reading Room). Persons who do not 

have access to ADAMS, or who 

encounter problems in accessing the 

documents located in ADAMS, should 

contact the PDR reference staff at 1–

800–397–4209, 301–415–4737, or by email to pdr@nrc.gov. In addition, the 

Bridgman Public Library, 4460 Lake 

Street, Bridgman, Michigan and the 

Maud Preston Palenske Memorial 

Library, 500 Market Street, St. Joseph, 

Michigan have agreed to make the draft 

plant-specific supplement to the GEIS 

available for public inspection. 

Any interested party may submit 

comments on the draft supplement to 

the GEIS for consideration by the NRC 

staff. To be certain of consideration, 

comments on the draft supplement to 

the GEIS and the proposed action must 

be received by December 8, 2004. 

Comments received after the due date 

will be considered if it is practical to do 

so, but the NRC staff is able to assure 

consideration only for comments 

received on or before this date. Written 

comments on the draft supplement to 

the GEIS should be sent to: Chief, Rules 

and Directives Branch, Division of 

Administrative Services, Office of 

Administration, Mailstop T–6D59, U.S. 

Nuclear Regulatory Commission, 

Washington, DC, 20555–0001. 

Comments may be hand-delivered to 

the NRC at 11545 Rockville Pike, Room 

T–6D59, Rockville, Maryland, between 

7:45 a.m. and 4:15 p.m. on Federal 

workdays. Electronic comments may be 

submitted to the NRC by e-mail at 

CookEIS@nrc.gov. All comments 

received by the Commission, including 

those made by Federal, State, and local 

agencies, Native American Tribes, or 

other interested persons, will be made 

available electronically at the 

Commission’s PDR in Rockville, 

Federal Register / Vol. 69, No. 185 / Friday, September 24, 2004 / Notices 57367

Maryland, and from the PARS 

component of ADAMS. 

The NRC staff will hold two public 

meetings to present an overview of the 

draft plant-specific supplement to the 

GEIS and to accept public comments on 

the document. The public meetings will 

be held on November 9, 2004, at the 

Lake Charter Township Hall, 3220 

Shawnee Road, Bridgman, Michigan. 

The first session will convene at 1:30 

p.m. and will continue until 4:30 p.m., 

as necessary. The second session will 

convene at 7 p.m. with a repeat of the 

overview portions of the meeting and 

will continue until 10 p.m., as 

necessary. Both meetings will be 

transcribed and will include: (1) A 

presentation of the contents of the draft 

plant-specific supplement to the GEIS, 

and (2) the opportunity for interested 

government agencies, organizations, and 

individuals to provide comments on the 

draft report. Additionally, the NRC staff 

will host informal discussions one hour 

before the start of each meeting at the 

Lake Charter Township Hall. No 

comments on the draft supplement to 

the GEIS will be accepted during the 

informal discussions. To be considered, 

comments must be provided either at 

the transcribed public meetings or in 

writing, as discussed below. Persons 

may register to attend or present oral 

comments at the meetings by contacting 

Mr. Robert Schaaf, by telephone at 1–

800–368–5642, extension 1312, or by email at CookEIS@nrc.gov no later than 

November 3, 2004. Members of the 

public may also register to speak at the 

meeting within 15 minutes of the start 

of each session. Individual oral 

comments may be limited by the time 

available, depending on the number of 

persons who register. Members of the 

public who have not registered may also 

have an opportunity to speak, if time 

permits. If special equipment or 

accommodations are needed to attend or 

present information at the public 

meeting, Mr. Schaaf will need to be 

contacted no later than November 1, 

2004, so that the NRC staff can 

determine whether the request can be 

accommodated.

FOR FURTHER INFORMATION, CONTACT: Mr. 

Robert Schaaf, License Renewal and 

Environmental Impacts Program, 

Division of Regulatory Improvement 

Programs, U.S. Nuclear Regulatory 

Commission, Washington, DC, 20555–

0001. Mr. Schaaf may be contacted at 

the aforementioned telephone number 

or e-mail address.

Dated at Rockville, Maryland, this 8th day 

of September, 2004.

For the Nuclear Regulatory Commission. 

Pao-Tsin Kuo, 

Program Director, License Renewal and 

Environmental Impacts Program, Division of 

Regulatory Improvement Programs, Office of 

Nuclear Reactor Regulation.

[FR Doc. 04–21342 Filed 9–23–04; 8:45 am] 

BILLING CODE 7590–01–P

NUCLEAR REGULATORY 

COMMISSION 

Notice of Clarification to Steam 

Generator Tube Integrity Event 

Reporting Guideline in NUREG–1022, 

‘‘Event Reporting Guidelines 10 CFR 

50.72 and 50.73’’

AGENCY: Nuclear Regulatory 

Commission.

ACTION: Notice of clarification in 

reporting guideline for steam generator 

tube integrity event. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission has made a clarification in 

the reporting guideline for serious steam 

generator tube degradation contained 

within Revision 2 to NUREG–1022, 

‘‘Event Reporting Guidelines 10 CFR 

50.72 and 50.73.’’ The NRC will issue an 

errata to NUREG–1022, Revision 2. The 

purpose of this clarification is to ensure 

that the NRC receives timely 

notification of serious steam generator 

tube degradation.

SUPPLEMENTARY INFORMATION: On 

February 18, 2004, the NRC staff issued 

a Federal Register notice (69 FR 7661) 

that requested comments on the staff’s 

intent to issue errata to Revision 2 of 

NUREG–1022, ‘‘Event Reporting 

Guidelines 10 CFR 50.72 and 50.73.’’

The errata would indicate that steam 

generator tube degradation is considered 

serious if either of the two criteria 

specified in Section 3.2.4(A)(3) of 

NUREG–1022, Revision 2, is not 

satisfied. 

Steam generator tube degradation is 

currently characterized in Section 

3.2.4(A)(3) of NUREG–1022 as being 

seriously degraded if the tubing fails to 

meet the following two performance 

criteria: 

(A) Steam generator tubing shall 

retain structural integrity over the full 

range of normal operating conditions 

(including startup, operation in the 

power range, hot standby, and 

cooldown and all anticipated transients 

included in the design specification) 

and design basis accidents. This 

includes retaining a margin of 3.0 

against burst under normal steady state 

full power operation and a margin of 1.4 

against burst under the limiting design 

basis accident concurrent with a safe 

shutdown earthquake. 

(B) The primary to secondary accident 

induced leakage rate for the limiting 

design basis accident, other than a 

steam generator tube rupture, shall not 

exceed the leakage rate assumed in the 

accident analysis in terms of total 

leakage rate for all steam generators and 

leakage rate for an individual steam 

generator. The licensing basis accident 

analyses typically assume a 1 gallon per 

minute primary to secondary leak rate 

per steam generator, except for specific 

types of degradation at specific 

locations where the tubes are confined, 

as approved by the NRC and 

enumerated in conjunction with the list 

of approved repair criteria in the 

licensee’s design basis documents. 

The first performance criterion is 

commonly referred to as the structural 

integrity performance criterion and the 

second criterion is commonly referred 

to as the accident induced leakage 

performance criterion. As written, 

NUREG–1022 could be read to indicate 

that the principal safety barrier (i.e., the 

steam generator tubes in this case) 

would only be considered seriously 

degraded if it had neither structural nor 

leakage integrity. Accordingly, if the 

steam generator tubes lacked only one of 

structural or leakage integrity, they 

would not be considered seriously 

degraded. This is contradictory to 

existing NRC regulations which require, 

in part, that the reactor coolant pressure 

boundary (which includes the steam 

generator tubes) be designed to permit 

periodic inspection and testing of 

important areas and features to assess 

both their structural and leaktight 

integrity (refer to General Design 

Criterion 32 of Appendix A to 10 CFR 

part 50) and be designed and tested so 

as to have an extremely low probability 

of abnormal leakage, of rapidly 

propagating failure, and of gross rupture 

(refer to General Design Criterion 14 of 

Appendix A to 10 CFR part 50). The 

regulations, therefore, indicate that both 

structural and leakage integrity criteria 

must be satisfied, and not meeting either 

one of the two performance criteria 

should constitute serious degradation of 

the principal safety barrier. 

In response to the Federal Register

notice, one public comment was 

received from Progress Energy 

(ML040850494). The comment was that 

the notice did not indicate whether the 

new criteria would require the reevaluation of the reportability of 

existing steam generator tube 

degradation that was previously 

evaluated based on the criteria that were 

in effect before issuance of the errata. 

The commenter also indicated that