[Federal Register Volume 61, Number 61 (Thursday, March 28, 1996)]
[Notices]
[Pages 13888-13890]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-7674]
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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 (the Commission) is
considering issuance of an amendment to Facility Operating License No.
DPR-72, issued to Florida Power Corporation, et al. (the licensee), for
operation of the Crystal River Nuclear Generating Plant, Unit No. 3
(CR3 or the facility) located in Citrus County, Florida.
Currently, the technical specifications (TS) for CR3 relating to
the Once Through Steam Generator's (OTSG's) tube inspection acceptance
criteria, specify repair limit for removing steam generator tubes from
service. This repair limit is based on a structural evaluation of a
simplified model of tubes with uniform through wall (T/W) thinning. A
recent tube-pull examination at CR3 identified a number of low signal-
to-noise (S/N) tube eddy current indications. The licensee indicated
that these S/N indications are a substantially different morphology
from the model used to develop the current TS inspection and acceptance
limit. As a result of the small signal amplitude associated with these
S/N indications, they could not be accurately sized by conventional
bobbin coil phase angle.
By letter dated May 31, 1995, proposed TS changes which involved a
broad and long-term criteria addressing both wear and Inter-Granular-
Attack (IGA) degradation mechanisms. The licensee's May 31, 1995
request was noticed in the Federal Register on July 5, 1995 (60 FR
35071). By letter dated March 21, 1996, the licensee superseded its May
31, 1995 request and proposed a more focused TS change which would be
applicable for one cycle duration, and only to Inter-Granular-Attack
(IGA) degradation mechanisms in a limited region of the OTSG.
Accordingly, this supersedes that notice in its entirety.
Specifically, the licensee proposed to:
A. Revise TS 3.4.12 item d, to read: ``150 gpd primary to secondary
LEAKAGE through any one steam generator (OTSG).''
B. Revise TS 5.6.2.10.2, page 5.0-14, ``The results of each sample
inspection shall be classified into one of the following three
categories:'' to read: ``The results of each bobbin coil sample
inspection shall be classified into one of the following three
categories:''
C. Revise the Note in TS 5.6.2.10.2, page 5.0-14, ``In all
inspections, previously degraded tubes whose degradation has not been
spanned by a sleeve must exhibit a significant increase in the
applicable imperfection size measurement (>+0.3V bobbin coil amplitude
increase for first span IGA indications or >10% further wall
penetration for all other imperfections) to be included in the below
percentage calculations.''
D. Revise the second sentence in TS 5.6.2.10.4.a.2, page 5.0-16,
``Eddy-current * * * as imperfections'' to read: ``Any indication below
all degraded tube criteria specified in item below may be considered as
imperfections.''
E. Revise TS 5.6.2.10.4.a.4, page 5.0-16, to read: ``Degraded Tube
means a tube containing a first span IGA indication with a bobbin coil
amplitude [greater than or equal to] 0.65V, an axial extent of [greater
than or equal to] 0.13 inch, or a circumferential extent of [greater
than or equal to] 0.3 inch or other imperfections [greater than or
equal to] 20% of the nominal wall thickness caused by degradation
except where all such degradation has been spanned by the installation
of a sleeve.''
F. Add TS 5.6.2.10.4.a.7 ``First span Inter-Granular-Attack (IGA)
indication means a bobbin coil indication located between the lower
tubesheet secondary face and the first tube support plate confirmed by
MRPC to have a volumetric morphology characteristic of IGA.''
G. As a result of adding the new TS 5.6.2.10.4.a.7 above, revise
applicable TS to reflect the new ``first span IGA definition'' term.
Renumber 5.6.2.10.4.a.8 and 9 to 5.6.2.10.4.a.9 and 10.
H. Renumber TS 5.6.2.10.4.a.7 to TS 5.6.2.10.4.a.8, and revise to
read: ``Plugging/Sleeving Limit means the extent of degradation beyond
which the tube shall be restored to serviceability by the installation
of a sleeve or removed from service because it may become unserviceable
prior to the next inspection. The limit for first span IGA indications
is a bobbin coil amplitude of 1.25V, an axial extent of 0.25 inch, or a
circumferential extent of 0.6 inch. The limit for indications other
than first span IGA is equal to 40% of the nominal tube or sleeve wall
thickness. No more than five thousand sleeves may be installed in each
OTSG.''
I. Revise TS 5.7.2.c.2, page 5.0-29, to read: ``Following each
inservice inspection of steam generator (OTSG) tubes, the NRC shall be
notified of the following prior to plant ascension into Mode 4.
1. Number of tubes plugged and sleeved
2. Crack like indications in the first span
3. An assessment of growth in the first span indications, and
4. Results of in-situ pressure testing, if performed.
The complete results of the OTSG tube inservice inspection shall be
submitted to the NRC within 90 days following the completion of the
inspection. The report shall include:
1. Number and extent of tubes inspected,
2. Location and percent of wall-thickness penetration for each
indication of an imperfection,
3. Location, bobbin coil amplitude, and axial and circumferential
extent (if determined) for each first span IGA indication, and
4. Identification of tubes plugged and tubes sleeved.''
The licensee requested that the above proposed license amendment be
processed as an emergency or exigent amendment to prevent delay of the
restart of the facility which is currently in an refueling outage. The
licensee described the circumstances involving the request and stated
that its request meets the requirements of 10 CFR 50.91a (5) and (6).
The licensee stated that the complexity of the issues involved,
differences between the licensee's and the industry's approach, and
evolving industry/NRC interactions on the steam generator integrity
issues resulted in a longer than anticipated NRC staff review time of
the licensee's previous submittal (May 31, 1995). As a result, staff
review of the licensee's May 31, 1995 submittal has not been completed.
Therefore, the licensee proposed this more limited license amendment as
described herein. 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
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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. The proposed change will not significantly increase the
probability or consequences of an accident previously evaluated. The
relevant accidents are excessive leakage or steam generator tube
rupture (as a consequence of MSLB [Main steam Line Break] or
otherwise).
RG [Regulatory Guide] 1.121 establishes a standard method for
demonstrating structural integrity under worse-than-DBE [design
basis Event] conditions. The existing TS is based on this RG. The
first span, IGA disposition strategy continues to rely on this
guidance. Current TW [through wall] sizing techniques would allow
defects greater than the current TS limit of 40% to remain in
service since these techniques do not accurately measure percent
wall penetration for small volume indications. The proposed
disposition strategy is based on measurable eddy current parameters
of voltage, axial extent, and circumferential extent has been shown
to provide a higher confidence that unacceptable flaws are removed
from service. Therefore, the probability of a Steam Generator Tube
Rupture (SGTR) is not increased and may well be decreased by
implementation of this S/N disposition strategy.
The probability of OTSG tube leakage during normal operation or
accident conditions is not adversely affected by the proposed S/N
disposition strategy. Operating history indicates essentially no
primary to secondary leakage through the OTSG tubes at CR-3. Growth
rate studies imply this trend could be expected to continue.
However, for conservatism the OTSG leakage limit has been reduced
from 1 gallon per minute through all OTSGs to 150 gallons per day
through any one OTSG. This change is consistent with the guidance
provided in Generic Letter 95-05. Small volume indications which
might leak during worse-case FWLB [Feedwater Line Break] conditions
are addressed in the RG 1.121 evaluation. The disposition strategy
ensure these indications are removed from service as part of the
inservice inspection. Once detected, the proposed criteria is at
least as effective in determining those indications which should be
removed from service as are the existing TS limits.
The first span IGA disposition strategy is an integral part of
an overall effort to better address these and similar phenomena in
OTSGs.
2. The proposed change will not create the possibility of a new
or different kind of accident from any accident previously
evaluated.
The key `new or different' accidents addressed in this and
similar proposals is the potential for MSLB-induced multiple SGTR or
excessive primary-to-secondary leakage during such events. While
these events are addressed in CR-3 Emergency Operating Procedures
(EOPs), they are beyond those licensed for the facility.
However, as noted above, the probability of MSLB induced
multiple SGTR is reduced by more effective screening and plugging/
sleeving criteria. The probability of detection and identification
of tubes which should be removed from service is maintained or
improved by the S/N disposition strategy. The likelihood of adverse
effects from plugging sound tubes is reduced. The operation of the
OTSG or related structures, systems or components is otherwise
unaffected.
3. The proposed change will not involve a significant reduction
to any margin of safety.
The margins of safety defined in RG 1.121, including the
required pressure used in the structural analysis, are retained. The
probability of detecting degradation is unchanged since bobbin coil
methods will continue to be the primary means of initial detection.
The probability of leakage remains acceptably small. The proposed S/
N disposition strategy is an enhancement to the inservice inspection
of OTSG tubing that will provide a higher level of confidence that
tubes exceeding the allowable limits are repaired while sound tubes
are left in service. Based upon results of the various growth rate
studies, the probability of an accident at the end of cycle is
essentially the same as the beginning.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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 15 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 15-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 15-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 Rules Review and
Directives Branch, Division of Freedom of Information and Publications
Services, Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555, 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 April 29, 1996, 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 32629. 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
[[Page 13890]]
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 the amendment is issued before the expiration of the 30-day
hearing period, the Commission will make a final determination on the
issue of no significant hazards consideration. If a hearing is
requested, 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, Attention: Docketing and Services
Branch, or may be delivered to the Commission's Public Document Room,
the Gelman Building, 2120 L Street, NW., Washington, DC, by the above
date. Where petitions are filed during the last 10 days of the notice
period, it is requested that the petitioner promptly so inform the
Commission by a toll-free telephone call to Western Union at 1-(800)
248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator
should be given Datagram Identification Number N1023 and the following
message addressed to Eugene V. Imbro: petitioner's name and telephone
number, date petition was mailed, plant name, and publication date and
page number of this Federal Register notice. A copy of the petition
should also be sent to the Office of the General Counsel, U.S. Nuclear
Regulatory Commission, Washington, DC 20555, and to A. H. Stephens,
General Counsel, Florida Power Corporation, MAC--A5D, P. O. Box 14042,
St. Petersburg, Florida 33733, 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 March 21, 1996, 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 32629.
Dated at Rockville, Maryland, this 25th day of March 1996.
For the Nuclear Regulatory Commission.
Bart C. Buckley,
Acting Director, Project Directorate II-1, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 96-7674 Filed 3-27-96; 8:45 am]
BILLING CODE 7590-01-P
