[Federal Register Volume 73, Number 75 (Thursday, April 17, 2008)]
[Notices]
[Pages 20961-20963]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E8-8271]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-529]


Arizona Public Service 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 (NRC, the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
STN 50-529 to Arizona Public Service Company (APS or the licensee) for 
operation of the Palo Verde Nuclear Generating Station (Palo Verde), 
Unit 2, located in Maricopa County, Arizona.
    The proposed amendment in the licensee's application dated April 
10, 2008, would revise Technical Specification (TS) 3.5.5, Refueling 
Water Tank (RWT), to increase the minimum required RWT level 
indications and the corresponding borated water volumes in TS Figure 
3.5.5-1, ``Minimum Required RWT Volume,'' by 3 percent. This change 
will ensure that there is adequate water volume available in the RWT to 
ensure that the engineered safety feature (ESF) pumps and the new 
containment recirculation sump strainers will meet their design 
functions during loss-of-coolant accidents (LOCAs).
    This condition is exigent for Unit 2, as it entered into a 
refueling outage on March 29, 2008, and during that outage the new 
containment sump strainers will be installed as part of the licensee's 
commitments related to NRC Generic Letter 2004-02, ``Potential Impact 
of Debris Blockage on Emergency Recirculation during Design Basis 
Accidents at Pressurized-Water Reactors.'' Without this amendment, the 
necessary modifications cannot be completed before startup from the 
refueling outage. Palo Verde is scheduled to restart on or about May 
11, 2008.
    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. 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 amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change would raise the RWT minimum level by 3% to 
ensure that there is adequate water volume available at the 
containment recirculation sumps for the limiting small break LOCA 
scenario for submergence of the new strainer designs that are being 
installed in Unit 2 in the spring 2008 outage. The new strainers are 
designed and tested to operate submerged at the start of 
recirculation actuation post-LOCA. This change ensures that the 
level of water at the strainers supports this assumption of the 
design.
    The RWT water volume is not an initiator of any accident 
previously evaluated. As a result, the probability of an accident 
previously evaluated is not affected. The proposed change does not 
alter or prevent the ability of structures, systems, and components 
from performing their intended function to mitigate the consequences 
of an initiating event within the assumed acceptance limits.
    The effect on containment flood level, equipment qualification, 
and containment sump pH [potential of hydrogen] remains within the 
limits assumed in the design and accident analyses. The calculated 
maximum containment flood level is based on the RWT water level 
associated with the bottom of the RWT overflow nozzle. This change 
does not revise the location of the RWT overflow nozzle and there is 
no change in the calculated maximum flood level. As a result, the 
proposed change has no impact on the qualification of equipment 
above the maximum containment flood level. For the same reason the 
impact of the proposed change on post-LOCA sump pH is bounded by the 
current analysis for post-LOCA sump pH. In that analysis, the 
calculated minimum post-LOCA sump pH is based on the maximum RWT 
water level associated with the bottom of the RWT overflow nozzle. 
The maximum flood level is not affected by this change. In addition, 
the change is conservative with respect to the calculated maximum 
post-LOCA sump pH since it is increasing the minimum required RWT 
volume.
    The proposed change does not affect the source term, containment 
isolation, or radiological release assumptions used in evaluating 
the radiological consequences of an accident previously evaluated. 
Further, the proposed change does not increase the types or amounts 
of radioactive effluent that may be released offsite, nor 
significantly increase individual or cumulative occupational/public 
radiation exposures. The proposed change is consistent with the 
safety analysis assumptions and resultant consequences.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The change does not involve a physical alteration of the plant 
(i.e., no new or different components or physical changes are 
involved with this change) or a change in the methods governing 
normal plant operation. The change does not alter any assumptions 
made in the safety analysis.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed change to raise the required RWT minimum water 
volume does not alter the manner in which safety limits, limiting 
safety system settings or limiting conditions for operation are 
determined. The safety analysis acceptance criteria are not affected 
by this change. The proposed change will not result in plant 
operation in a configuration outside of the design basis.
    Therefore, the proposed change does 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 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

[[Page 20962]]

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, Rulemaking, 
Directives and Editing 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, located at One White Flint North, Public File Area O1 
F21, 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, a 
person(s) may file a request for a hearing with respect to issuance of 
the amendment to the subject facility operating license and any 
person(s) whose interest may be affected by this proceeding and who 
wishes to participate as a party in the proceeding must file a written 
request via electronic submission through the NRC E-filing system 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 person(s) 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 O1F21, 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.
    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.
    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 hearing or a petition for leave to intervene must be 
filed in accordance with the NRC E-Filing rule, which the NRC 
promulgated on August 28, 2007 (72 FR 49139). The E-Filing process 
requires participants to submit and serve documents over the Internet 
or in some cases to mail copies on electronic storage media. 
Participants may not submit paper copies of their filings unless they 
seek a waiver in accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 
five (5) days prior to the filing deadline, the petitioner/requestor 
must contact the Office of the Secretary by e-mail at 
[email protected], or by calling (301) 415-1677, to request (1) a 
digital ID certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and/or (2) 
creation of an electronic docket for the proceeding (even in instances 
in which the petitioner/requestor (or its counsel or representative) 
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms Viewer\TM\ to 
access the Electronic Information Exchange (EIE), a component of the E-
Filing system. The Workplace Forms Viewer\TM\ is free and is available 
at http://www.nrc.gov/site-help/e-submittals/install-viewer.html. 
Information about applying for a digital ID certificate is available on 
NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. Once a petitioner/requestor has obtained a 
digital ID certificate, had a docket created, and downloaded the EIE 
viewer, it can then submit a request for hearing or petition for leave 
to intervene. Submissions should be in Portable Document Format (PDF) 
in accordance with NRC guidance available on the NRC public Web site at 
http://www.nrc.gov/site-help/e-submittals.html. A filing is considered 
complete at the time the filer submits its documents through EIE. To be 
timely, an electronic filing must be submitted to the EIE system no 
later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a 
transmission, the E-Filing system time-stamps the document and sends 
the submitter an e-mail notice confirming receipt of the document. The 
EIE system also distributes an e-mail notice that provides access to 
the document to the NRC Office of the General Counsel and any others 
who have advised the Office of the Secretary

[[Page 20963]]

that they wish to participate in the proceeding, so that the filer need 
not serve the documents on those participants separately. Therefore, 
applicants and other participants (or their counsel or representative) 
must apply for and receive a digital ID certificate before a hearing 
request/petition to intervene is filed so that they can obtain access 
to the document via the E-Filing system.
    A person filing electronically may seek assistance through the 
``Contact Us'' link located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC technical help line, 
which is available between 8:30 a.m. and 4:15 p.m., Eastern Time, 
Monday through Friday. The help line number is (800) 397-4209 or 
locally, (301) 415-4737. Participants who believe that they have a good 
cause for not submitting documents electronically must file a motion, 
in accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted 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; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 
20852, Attention: Rulemaking and Adjudications Staff. Participants 
filing a document in this manner are responsible for serving the 
document on all other participants. Filing is considered complete by 
first-class mail as of the time of deposit in the mail, or by courier, 
express mail, or expedited delivery service upon depositing the 
document with the provider of the service.
    Documents submitted in adjudicatory proceedings will appear in 
NRC's electronic hearing docket which is available to the public at 
http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant 
to an order of the Commission, an Atomic Safety and Licensing Board, or 
a Presiding Officer. Participants are requested not to include personal 
privacy information, such as social security numbers, home addresses, 
or home phone numbers in their filings. With respect to copyrighted 
works, except for limited excerpts that serve the purpose of the 
adjudicatory filings and would constitute a Fair Use application, 
Participants are requested not to include copyrighted materials in 
their submissions.
    Non-timely requests and/or petitions and contentions will not be 
entertained absent a determination by the Commission, the presiding 
officer, or the Atomic Safety and Licensing Board that the petition 
and/or request should be granted and/or the contentions should be 
admitted, based on a balancing of the factors specified in 10 CFR 
2.309(c)(1)(i)-(viii). To be timely, filings must be submitted no later 
than 11:59 p.m. Eastern Time on the due date.
    For further details with respect to this exigent license 
application, see the application for amendment dated April 10, 2008, 
from Arizona Public Service Company which is available for public 
inspection at the Commission's Public Document Room (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 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.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, or 301-415-4737, or by 
e-mail to [email protected].

    Dated at Rockville, Maryland, this 11th day of April, 2008.

    For the Nuclear Regulatory Commission.
Michael T. Markley,
Senior Project Manager, Plant Licensing Branch LPL4, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
 [FR Doc. E8-8271 Filed 4-16-08; 8:45 am]
BILLING CODE 7590-01-P