[Federal Register Volume 59, Number 179 (Friday, September 16, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-22985]
[[Page Unknown]]
[Federal Register: September 16, 1994]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-325 and 50-324]
Carolina Power & Light Company; 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.
DPR-71 and DPR-62 issued to Carolina Power & Light Company (the
licensee) for operation of the Brunswick Steam Electric Plant, Units 1
and 2, located in Brunswick County, North Carolina.
The proposed amendment would revise the frequency for verifying the
position of the drywell-suppression chamber vacuum breakers when a
valve position indictor is inoperable from at least once every 72 hours
to at least once every 14 days. The proposed change is consistent with
the testing frequency for this equipment that is stipulated in the
Improved Boiling Water Reactor Standard Technical Specifications.
By letter dated September 9, 1994, the licensee requested exigent
handling of the proposed amendment request. The licensee stated that,
on September 3, 1994, the closed position indication was found
inoperable on one vacuum breaker, and they have been performing the
required testing to verify that the vacuum breaker is closed. Since the
plant is in operation and the primary containment suppression chamber
is inerted with nitrogen, the suppression chamber is not accessible to
repair the vacuum breaker position indication without an unscheduled
plant shutdown. To conduct the vacuum breaker test, the nitrogen
pressure is increased inside the drywell to establish the test
pressure. This test reduces the operational margin between the actual
drywell pressure and the high drywell pressure trip setpoint. If this
setpoint is reached or exceeded, a reactor scram and Group 1 isolation
will occur. Therefore, the changes to the test frequency will reduce
the potential for incurring an unnecessary plant transient.
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. The proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
The proposed change revises the surveillance requirements
associated with inoperable position indication for drywell-
suppression chamber vacuum breakers. No safety-related equipment,
safety function or plant operations will be altered as a result of
the proposed change. The change does not affect the design,
materials, or construction standards applicable to the vacuum
breakers or their position indication instrumentation.
Relaxation of the frequency for verifying the position of the
drywell-suppression chamber vacuum breakers from at least once every
72 hours to at least once every 14 days, as stated in the existing
Technical Specification 3.6.4.1, ACTION c, will not affect the
ability of the drywell-suppression chamber vacuum breakers to
perform their intended safety function. The extended frequency
provides adequate assurance that the vacuum breakers will perform
their intended safety function. Each drywell-suppression chamber
vacuum breaker will continue to be demonstrated OPERABLE and closed
at least once per 31 days and after any discharge of steam to the
suppression chamber in accordance with Technical Specification
4.6.1.a. In addition, the new surveillance requirement provided in
the proposed Technical Specification 4.6.4.1.a will require that
each vacuum breaker be verified to be closed at least once every 14
days. The new surveillance provides further assurance that the
vacuum breakers are capable of performing their design function
under accident conditions of allowing the venting of non-condensible
gases from the suppression chamber to the drywell while not allowing
bypass flow from the drywell to the suppression chamber.
Based on the above, the proposed change does not create a
significant increase in the probability or consequences of an
accident previously evaluated.
2. The proposed change would not create the possibility of a new
or different kind of accident from any accident previously
evaluated.
As stated above, no safety-related equipment, safety function or
plant operations will be altered as a result of the proposed change.
The change does not affect the design, materials, or construction
standards applicable to the vacuum breakers or their position
indication instrumentation.
Relaxation of the frequency for verifying the position of the
drywell-suppression chamber vacuum breakers of the existing
Technical Specification 3.6.4.1, ACTION c from at least once every
72 hours to at least once every 14 days will not affect the ability
of the drywell-suppression chamber vacuum breakers to perform their
intended safety function.
In addition, the new surveillance requirement provided in
proposed Technical Specification 4.6.4.1.a will require that each
vacuum breaker be verified to be closed at least once every 14 days.
The new surveillance will provide further assurance that the vacuum
breakers are capable of performing their design function under
accident conditions without altering plant operations in a manner
that would create a new or different kind of accident.
As such, the proposed license amendment cannot create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. The proposed amendment does not involve a significant
reduction in a margin of safety.
The proposed change does not involve any changes to the plant
design or operation. Therefore, no margins of safety, as defined by
the plant's accident analyses, are impacted. Relaxation of the
frequency for verifying the position of the drywell-suppression
chamber vacuum breakers of the existing Technical Specification
3.6.4.1, ACTION c from at least once every 72 hours to at least once
every 14 days will not affect the ability of the drywell-suppression
chamber vacuum breakers to perform their intended safety function.
The extended frequency provides adequate assurance that the vacuum
breakers will perform their intended safety function. Each drywell-
suppression chamber vacuum breaker will continue to be demonstrated
OPERABLE and closed at least once per 31 days and after any
discharge of steam to the suppression chamber in accordance with
Technical Specification 4.6.4.1.a.
In addition, performance of Technical Specification 4.6.4.1.b
requires pressurization of the drywell to approximately 1.0 psig and
then verifying that the differential drywell to suppression chamber
pressure is maintained greater than one-half the initial
differential pressure for one hour without nitrogen makeup. During
this evolution actual pressure will increase as high as 1.1 psig
before stablizing. The Drywell Pressure--High setpoint, which
initiates a reactor scram and a Group 1 isolation, is less than or
equal to 2.0 psig (the actual setpoint is 1.8 psig). As such,
performance of this evolution once per 72 hours unnecessarily risks
a plant transient without providing a significant increase in the
level of safety gained by performing the verification on a 14 day
frequency.
The new surveillance requirement provided in proposed Technical
Specification 4.6.4.1.a will require that each vacuum breaker be
verified to be closed at least once every 14 days. The new
surveillance provides further assurance that the vacuum breakers are
capable of performing their design function under accident
conditions of allowing the venting of non-condensible gases from the
suppression chamber to the drywell while not allowing bypass flow
from the drywell to the suppression chamber.
Based on the above reasoning, the proposed 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 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
20555.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
By October 3, 1994, 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 20555 and at the local
public document room located at the University of North Carolina at
Wilmington, William Madison Randall Library, 601 S. College Road,
Wilmington, North Carolina 28403-3297. 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.
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 20555, 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 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 September 9, 1994, which is available
for public inspection at the Commission's Public Document Room, the
Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the
local public document room, located at University of North Carolina at
Wilmington, William Madison Randall Library, 601 S. College Road,
Wilmington, North Carolina 28403-3297.
Dated at Rockville, Maryland, this 13th day of September 1994.
For the Nuclear Regulatory Commission.
Patrick D. Milano, Sr.
Project Manager Project Directorate II-1 Division of Reactor Projects--
I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 94-22985 Filed 9-15-94; 8:45 am]
BILLING CODE 7590-01-M
