[Federal Register Volume 62, Number 155 (Tuesday, August 12, 1997)]
[Notices]
[Pages 43187-43189]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-21245]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-325 and 50-324]


Carolina Power & Light Company; Notice of Consideration of 
Issuance of Amendment to Facility Operating License, 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-71 and DPR-62 issued to the Carolina Power & Light Company (the 
licensee) for operation of the Brunswick Steam Electric Plant, Units 1 
and 2 (BSEP) located in Southport, North Carolina.

[[Page 43188]]

    NRC Generic Letter (GL) 88-01 outlines the NRC staff's positions on 
intergranular stress corrosion cracking (IGSCC) in boiling water 
reactor (BWR) austenitic stainless steel piping. Technical 
Specification (TS) 4.0.5.f requires that the BSEP Inservice Inspection 
(ISI) program be performed in accordance with the positions identified 
in GL 88-01. The proposed amendments would modify TS 4.0.5.f in a 
manner that would allow exceptions to these positions where specific 
written relief has been granted by the NRC.
    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 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 amendments 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 amendments do not involve a significant increase 
in the probability or consequences of an accident previously 
evaluated.
    Technical Specification 4.0.5.f provides inservice inspection 
requirements (e.g., schedule, methods, personnel, and sampling) for 
piping covered by the scope of NRC Generic Letter 88-01, ``NRC Staff 
Position on IGSCC in BWR Austenitic Stainless Steel Piping'' dated 
January 25, 1988. The proposed revision to Technical Specification 
4.0.5.f provides a clarification for this piping regarding the use 
of alternatives on schedule, methods, personnel, and sampling that 
have been reviewed and accepted by the NRC staff. The proposed 
change to Technical Specification 4.0.5.f is an administrative 
change that clarifies that alternate requirements regarding 
inspection schedules, methods, personnel, and sample expansion are 
acceptable provided these alternatives have been reviewed and 
approved by the NRC staff. The proposed license amendments do not 
alter the function of existing equipment and will ensure that the 
consequences of any previously evaluated accident do not increase. 
As such, the proposed license amendments do not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.
    2. The proposed amendments would not create the possibility of a 
new or different kind of accident from any accident previously 
evaluated.
    The proposed revision to Technical Specification 4.0.5.f is an 
administrative change [that] provides a clarification that alternate 
requirements for inspection schedules, methods, personnel, and 
sample expansion for piping susceptible to intergranular stress 
corrosion cracking (IGSCC) are acceptable for use. Inclusion of this 
clarification in Technical Specification 4.0.5.f is an 
administrative change which will not introduce new equipment nor 
require any existing equipment or systems to perform a different 
type of function than they are presently designed to perform.
    3. The proposed amendments do not involve a significant 
reduction in a margin of safety.
    As previously stated, the proposed revision to Technical 
Specification 4.0.5.f provides a clarification allowing inspection 
of austenitic stainless steel piping using alternatives on schedule, 
methods, personnel, and sampling that have been reviewed and 
accepted by the NRC staff. The proposed license amendments do not 
introduce any new equipment nor do they require any existing 
equipment or systems to perform a different type of function than 
they are presently designed to perform. As such, the proposed change 
to Technical Specification 4.0.5.f is administrative in nature. 
Therefore, the proposed license amendments do not involve a 
significant reduction in a 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 
amendment request involves 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 amendment 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 amendment 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 Rules Review and 
Directives Branch, Division of Freedom of Information and Publications 
Services, Office of Administration, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, and should cite the publication date and 
page number of this Federal Register notice. Written comments may also 
be delivered to Room 6D22, Two White Flint North, 11545 Rockville Pike, 
Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. 
Copies of written comments received may be examined at the NRC Public 
Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC.
    The filing of requests for hearing and petitions for leave to 
intervene is discussed below.
    By September 11, 1997, the licensee may file a request for a 
hearing with respect to issuance of the amendment to the subject 
facility operating license and any person whose interest may be 
affected by this proceeding and who wishes to participate as a party in 
the proceeding must file a written request for a hearing and a petition 
for leave to intervene. Requests for a hearing and a petition for leave 
to intervene shall be filed in accordance with the Commission's ``Rules 
of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2. 
Interested persons should consult a current copy of 10 CFR 2.714 which 
is available 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 University of North Carolina at 
Wilmington, William Madison Randall Library, 601 S. College Road, 
Wilmington, North Carolina 28403-3297. If a request for a hearing or 
petition for leave to intervene is filed by the above date, the 
Commission or an Atomic Safety and Licensing Board, designated by the 
Commission or by the Chairman of the Atomic Safety and Licensing Board 
Panel, will rule on the request and/or petition; and the Secretary or 
the designated Atomic Safety and Licensing Board will issue a notice of 
hearing or an appropriate order.
    As required by 10 CFR 2.714, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner in 
the proceeding, and how that interest may be affected by the results of 
the proceeding. The petition should specifically explain the reasons 
why intervention should be permitted

[[Page 43189]]

with particular reference to the following factors: (1) the nature of 
the petitioner's right under the Act to be made party to the 
proceeding; (2) the nature and extent of the petitioner's property, 
financial, or other interest in the proceeding; and (3) the possible 
effect of any order which may be entered in the proceeding on the 
petitioner's interest. The petition should also identify the specific 
aspect(s) of the subject matter of the proceeding as to which 
petitioner wishes to intervene. Any person who has filed a petition for 
leave to intervene or who has been admitted as a party may amend the 
petition without requesting leave of the Board up to 15 days prior to 
the first prehearing conference scheduled in the proceeding, but such 
an amended petition must satisfy the specificity requirements described 
above.
    Not later than 15 days prior to the first prehearing conference 
scheduled in the proceeding, a petitioner shall file a supplement to 
the petition to intervene which must include a list of the contentions 
which are sought to be litigated in the matter. Each contention must 
consist of a specific statement of the issue of law or fact to be 
raised or controverted. In addition, the petitioner shall provide a 
brief explanation of the bases of the contention and a concise 
statement of the alleged facts or expert opinion which support the 
contention and on which the petitioner intends to rely in proving the 
contention at the hearing. The petitioner must also provide references 
to those specific sources and documents of which the petitioner is 
aware and on which the petitioner intends to rely to establish those 
facts or expert opinion. Petitioner must provide sufficient information 
to show that a genuine dispute exists with the applicant on a material 
issue of law or fact. Contentions shall be limited to matters within 
the scope of the amendment under consideration. The contention must be 
one which, if proven, would entitle the petitioner to relief. A 
petitioner who fails to file such a supplement which satisfies these 
requirements with respect to at least one contention will not be 
permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing, including the opportunity to present evidence and cross-
examine witnesses.
    If a hearing is requested, the Commission will make a final 
determination on the issue of no significant hazards consideration. The 
final determination will serve to decide when the hearing is held.
    If the final determination is that the amendment request involves 
no significant hazards consideration, the Commission may issue the 
amendment and make it immediately effective, notwithstanding the 
request for a hearing. Any hearing held would take place after issuance 
of the amendment.
    If the final determination is that the amendment request involves a 
significant hazards consideration, any hearing held would take place 
before the issuance of any amendment.
    A request for a hearing or a petition for leave to intervene must 
be filed with the Secretary of the Commission, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attention: Rulemakings and 
Adjudications Staff, or may be delivered to the Commission's Public 
Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, 
by the above date. A copy of the petition should also be sent to the 
Office of the General Counsel, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, and to General Counsel, Carolina Power & 
Light Company, P.O. Box 1551, Raleigh, North Carolina 27602, attorney 
for the licensee.
    Nontimely filings of petitions for leave to intervene, amended 
petitions, supplemental petitions and/or requests for hearing will not 
be entertained absent a determination by the Commission, the presiding 
officer or the presiding Atomic Safety and Licensing Board that the 
petition and/or request should be granted based upon a balancing of the 
factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
    For further details with respect to this action, see the 
application for amendments dated July 25, 1997, which is 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 University of North Carolina at 
Wilmington, William Madison Randall Library, 601 S. College Road, 
Wilmington, North Carolina 28403-3297.

    Dated at Rockville, Maryland, this 6th day of August 1997.

    For the Nuclear Regulatory Commission.
David C. Trimble,
Project Manager, Project Directorate II-1, Division of Reactor 
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 97-21245 Filed 8-11-97; 8:45 am]
BILLING CODE 7590-01-P