[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
