[Federal Register Volume 62, Number 219 (Thursday, November 13, 1997)]
[Notices]
[Pages 60921-60923]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-29889]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-302]


Florida Power Corporation; 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 or the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
DPR 72, issued to the Florida Power Corporation, (FPC or the licensee), 
for operation of the Crystal River Nuclear Generating Unit 3 (CR3) 
located in Citrus County, Florida.
    The proposed amendment involves modifications to the electrical 
controls of the Reactor Building (RB) Recirculation System Fan/Cooler, 
AHF-1C. FPC has determined that the modification involves an Unreviewed 
Safety Question, in that modification will install additional 
components that could increase the probability of occurrence of a 
malfunction of equipment important to safety previously evaluated in 
the Final Safety Analysis Report (FSAR). Therefore, this action 
requires NRC approval. The proposed modification to the fan logic will 
enable utilization of AHF-1C, in place of either AHF-1A or AHF-1B (the 
normally running RB Recirculation System fans), by providing engineered 
safeguards (ES) auto-start permissive interlocks from its MCC-3AB 
transfer switch. This modification will automatically prevent 
inadvertent loading of two RB Recirculation System fans on a single 
emergency diesel generator when the ES-MCC-3AB source is transferred. 
The AHF-1C Engineered Safeguards ``A'' train auto start signal will be 
enabled only when AHF-1C is ES-selected as the ``A'' train fan with ES-
MCC-3AB supplied from the ``A'' train source. Conversely, the AHF-1C ES 
``B'' train auto-start signal will be enabled only when AHF-1C is ES-
selected as the ``B'' train fan with ES-MCC-3AB supplied from the ``B'' 
train source.
    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. 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 not involve a significant increase in the probability or 
consequences of an accident previously evaluated.
    This license amendment involves the addition of electrical 
circuits to preclude the loading of two Reactor Building 
Recirculation System fans onto the same Emergency Diesel Generator 
when AHF-1C is in service. This equipment will enable use of Reactor 
Building Recirculation System fan/cooler unit AHF-1C in place of 
either AHF-1A or AHF-1B by providing ES auto-start permissive 
interlocks from the source transfer switch for Motor Control Center 
ES-MCC-3AB. The AHF-1C ES-select control circuitry and ES-MCC-3AB do 
not initiate any accidents previously evaluated. Accident mitigation 
strategies assume that one train of the Reactor Building 
Recirculation System is available. This license amendment does not 
restrict the availability of one train. One Reactor Building 
Recirculation System fan/cooler unit will always be in operation 
even if AHF-1C is not available because of a malfunction in this 
control circuitry.
    A failure to open or close a manual Nuclear Services Closed 
Cycle Cooling (SW) System valve at a Reactor Building Recirculation 
System cooling coil is a remote possibility. Adequate procedural 
controls are in place to ensure that proper steps are taken when a 
fan/cooler unit is being placed in service or removed from service. 
These procedures are not required during an accident, but are part 
of the normal operation of CR-3. However, should a failure occur, 
the other aligned Reactor Building Recirculation fan/cooler unit is 
available. In addition, both trains of the Reactor Building Spray 
System will be available to perform the post accident containment 
heat removal function.
    Failure to properly ES-select a fan/cooler unit could result in 
a failure of the ES start function. However, an alignment error in 
the ES-selection of AHF-1C is annunciated and printed out by the 
events recorder to minimize the effect of this type of failure. Also 
procedural controls are in place to align the ES-selection for the 
fan/cooler unit being placed in service. The other train of the 
Reactor Building Recirculation System would be available, as well 
as, both trains of the Reactor Building Spray System. Therefore, 
this license amendment does not involve a significant increase in 
the probability of an accident previously evaluated.
    Because of CR-3 single failure design bases considerations, a 
failure of one-half of the Reactor Building Recirculation System 
during accident mitigation would mean that both trains of the 
Reactor Building Spray System are available for mitigating any 
accident previously evaluated. Accident analyses for CR-3 assume 
only one train of the Reactor Building Recirculation System. Either 
train of the Reactor Building Spray System has the capability to 
maintain the accident dose consequences well below the requirements 
of 10 CFR 100 (25 rem whole body, 300 rem thyroid) and General 
Design Criteria 19 (5 rem whole body, or its equivalent to any part 
of the body). Installation of the ES auto-start permissive 
interlocks from the transfer switch for Motor Control Center ES-MCC-
3AB will not alter any assumptions made in evaluating the 
radiological consequences of any accident described in the FSAR nor 
will it affect any fission product barriers since the post-accident 
containment heat removal functions will still meet design 
requirements. Therefore installation of ES auto-start permissive 
interlocks from Motor Control Center ES-MCC-3AB transfer switch does 
not involve a significant increase in the consequences of an 
accident previously evaluated.
    2. Does not create the possibility of a new or different kind of 
accident from any accident previously evaluated.
    The accident mitigation strategies for CR-3 assume two different 
types of post-accident

[[Page 60922]]

containment heat removal functions--Reactor Building Recirculation 
System and Reactor Building Spray System. This license amendment 
will allow the use of Reactor Building Recirculation System fan/
cooler unit AHF-1C, which is presently administratively out of 
service, to control the Reactor Building temperature during normal 
operations and to mitigate any postulated accidents. The use of AHF-
1C in place of either AHF-1A or AHF-1B does not alter the success 
path for post-accident mitigation. The addition of the ES auto-start 
permissive interlocks from the ES-MCC-3AB transfer switch will not 
introduce failure modes and effects that create the possibility of a 
new or different kind of accident from any accident previously 
evaluated.
    3. Does not involve a significant reduction in the margin of 
safety.
    This license amendment will allow the use of Reactor Building 
Recirculation System fan/cooler unit AHF-1C that is presently 
administratively out of service. AHF-1C is identical in design 
function to the other two fan/cooler units that are presently in 
service. During normal operation, two operating Reactor Building 
Recirculation System fan/cooler units maintain the Reactor Building 
temperature below the Improved Technical Specification limit of 
130 deg.F. Installation of this modification will allow the use of 
AHF-1C in place of either AHF-1A or AHF-1B, and maintain the 
licensing and design bases that assume two trains are operable for 
accident mitigation. The use of AHF-1C in place of the other fan/
cooler units will preserve the margin of safety, pre-accident and 
post-accident, because the assumptions used in FSAR analyses remain 
valid. Peak Reactor Building pressures and temperatures will not be 
exceeded and the margin provided by this fission product barrier 
will not be reduced. Therefore, this license amendment does not 
involve a significant reduction in the 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 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 
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 December 15, 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 Coastal Region Library, 8619 W. Crystal 
Street, Crystal River, Florida.
    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 with particular reference to the 
following factors: (1) the nature of the petitioner's right under the 
Act to be made a 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.

[[Page 60923]]

    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 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 R. Alexander Glenn, General Counsel, 
Florida Power Corporation, MAC-A5A, P.O. Box 14042, St. Petersburg, 
Florida 33733-4042, 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 amendment dated October 4, 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 Coastal Region Library, 8619 W. Crystal 
Street, Crystal River, Florida.

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

    For the Nuclear Regulatory Commission.
L. Raghavan,
Sr. Project Manager, Project Directorate II-3, Division of Reactor 
Projects--I/II Office of Nuclear Reactor Regulation.
[FR Doc. 97-29889 Filed 11-12-97; 8:45 am]
BILLING CODE 7590-01-P