[Federal Register Volume 70, Number 113 (Tuesday, June 14, 2005)]
[Notices]
[Pages 34506-34508]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E5-3065]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-361 and 50-362]
Southern California Edison 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 an amendment to Facility Operating License Nos.
NPF-10 and NPF-15, issued to Southern California Edison Company (SCE or
the licensee), for operation of the San Onofre Nuclear Generating
Station (SONGS), Units 2 and 3 located in San Diego County, California.
The proposed amendment would lower the allowable values for dropout
and pickup of the degraded voltage function. The amendment request was
submitted on May 27, 2005, on an exigent basis because the need for a
license amendment to change the degraded voltage function was not
recognized by the licensee or the NRC staff until recently, and the
licensee requests approval of the proposed amendment by July 1, 2005,
to allow implementation of the amendment before the expected high
summer load period.
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.
Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under
exigent circumstances, the NRC staff must determine 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. Does the proposed change involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
This proposed change revises the Technical Specification (TS)
Surveillance Requirement (SR) 3.3.7.a allowable values of the Degraded
Voltage Function. This proposed change will allow Southern California
Edison (SCE) to re-establish 218 kV as the minimum voltage on the
offsite transmission grid necessary to support operability of the
immediate access offsite power source (also referred to as the normal
preferred power source[)]. This will be accomplished by lowering the
dropout and pickup settings, including allowable values for dropout and
pickup of the degraded voltage protection relays. Following approval of
this proposed change, the 4.16 kV Class 1E buses would be capable of
remaining on the normal preferred power source at or above a grid
voltage of 218 kV while protecting all Class 1E equipment from degraded
grid conditions.
The degraded voltage protection circuits are designed to protect
electrical equipment against the effects of degraded voltage on the
offsite transmission networks. Therefore, these circuits are generally
not considered to be accident initiators. However, spurious actuation
of the degraded voltage protection relays could result in the loss of
the preferred power source (offsite source of alternating current (AC)
power). The proposed change lowers the allowable values for both
dropout and pickup for the degraded voltage protection relays. This
results in an increase in operating margin and a lower probability of
spurious actuation of these degraded voltage signals. Therefore, there
is no increase in the probability of a Loss of Offsite Power (preferred
power source) as a result of this proposed change.
The safety function of the degraded voltage protection circuits is
to ensure the operability of Class 1E equipment. SCE has performed
calculations that demonstrate that operation in accordance with this
proposed change will not result in operation of plant equipment at
degraded voltages.
[[Page 34507]]
Therefore, there is no increase in the consequences of any accident
previously evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of any accident previously
evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed allowable values of the degraded voltage relays will
provide an acceptable level of protection for plant equipment.
This proposed change affects only the voltage settings of the
degraded voltage protection relays. There is no other change to the
degraded voltage function. There are no physical modifications
necessary to the degraded voltage protection relays. There are no
changes to the actions performed by the relays following actuation.
Therefore, there are no new failure modes or effects introduced by this
proposed change.
Therefore, this proposed change does not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed degraded voltage protection schemes are designed to
ensure that plant equipment will not operate at a degraded voltage. The
proposed degraded voltage allowable values will not affect the existing
protection criterion for plant equipment. This maintains the existing
margin of safety for plant equipment.
Therefore, there is no significant reduction in the margin of
safety as a result of the proposed amendment.
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 14 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 14-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 14-day notice period, provided that its final determination is that
the amendment involves 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. 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 and
Directives Branch, Division of Administrative 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 6D59, Two White Flint North, 11545 Rockville Pike, Rockville,
Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Documents may
be examined, and/or copied for a fee, at the NRC's Public Document Room
(PDR), located at One White Flint North, 11555 Rockville Pike (first
floor), Rockville, Maryland.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
Within 60 days after the date of publication of this notice, 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 and Issuance of Orders'' in 10 CFR part 2.
Interested persons should consult a current copy of 10 CFR 2.309, which
is available at the Commission's PDR, located at One White Flint North,
Public File Area 01F21, 11555 Rockville Pike (first floor), Rockville,
Maryland. Publicly available records will be accessible from the
Agencywide Documents Access and Management System's (ADAMS) Public
Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing
or petition for leave to intervene is filed by the above date, the
Commission or a presiding officer designated by the Commission or by
the Chief Administrative Judge of the Atomic Safety and Licensing Board
Panel, will rule on the request and/or petition; and the Secretary or
the Chief Administrative Judge of the Atomic Safety and Licensing Board
will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, 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 with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the petitioner/requestor
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
petitioner/requestor shall provide a brief explanation of the bases for
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/requestor must also provide references to those specific
sources and documents of which the petitioner/requestor is aware and on
which the petitioner/requestor intends to rely to establish those facts
or expert opinion. The petitioner/requestor 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/
requestor to relief. A petitioner/requestor who fails to satisfy 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.
[[Page 34508]]
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.
Nontimely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission or the presiding
officer of the Atomic Safety and Licensing Board that the petition,
request and/or the contentions should be granted based on a balancing
of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).
A request for a hearing or a petition for leave to intervene must
be filed by: (1) First class mail addressed to the Office of the
Secretary of the Commission, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attention: Rulemaking and Adjudications
Staff; (2) courier, express mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor, One White Flint North, 11555
Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and
Adjudications Staff; (3) E-mail addressed to the Office of the
Secretary, U.S. Nuclear Regulatory Commission, [email protected];
or (4) facsimile transmission addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission, Washington, DC, Attention:
Rulemakings and Adjudications Staff at (301) 415-1101, verification
number is (301) 415-1966. A copy of the request for hearing and
petition for leave to intervene should also be sent to the Office of
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, and it is requested that copies be transmitted either by
means of facsimile transmission to 301-415-3725 or by e-mail to
[email protected]. A copy of the request for hearing and petition
for leave to intervene should also be sent to Nicolas S. Reynolds,
Esquire, Winston and Strawn, 1400 L Street, NW., Washington, DC 2005-
3502, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated May 27, 2005, which is available for
public inspection at the Commission's PDR, located at One White Flint
North, Public File Area O1 F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible
electronically from the ADAMS Public Electronic Reading Room on the
Internet at the NRC Web site http://www.nrc.gov/reading-rm.html.
Persons who do not have access to ADAMS or who encounter problems in
accessing the documents located in ADAMS, should contact the NRC PDR
Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-
mail to [email protected].
Dated at Rockville, Maryland, this 7th day of June 2005.
For the Nuclear Regulatory Commission.
Mel B. Fields,
Senior Project Manager, Section 2, Project Directorate IV, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-3065 Filed 6-13-05; 8:45 am]
BILLING CODE 7590-01-P