[Federal Register Volume 62, Number 57 (Tuesday, March 25, 1997)]
[Notices]
[Pages 14167-14169]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-7507]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-388]
Pennsylvania Power & Light 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 (the Commission) is
considering issuance of an amendment to Facility Operating License No.
NPF-22, issued to Pennsylvania Power & Light Company (PP&L), (the
licensee), for operation of the Susquehanna Steam Electric Station
(SSES), Unit 2, located in Luzerne County, PA.
The proposed amendment would modify the Design Features Section
5.3.1 of the Technical Specifications to reflect the Atrium-10 design
and would include a Siemens Power Corporation (SPC) topical report
reference in Section 6.9.3.2 to reflect mechanical design criteria for
this fuel. This change would allow this fuel to be loaded and
maintained in the core only under Condition 5, (refueling).
PP&L has indicated that exigent circumstances exist which are a
result of the following. PP&L submitted its proposal for amendment for
the staff to approve the use of SPC Atrium-10 fuel in SSES, Unit 2 on
December 18, 1996 and as supplemented on March 12, 1997. The staff
approval has been predicated on the completion of an audit at SPC.
Issues raised during the SPC audit have caused an unanticipated delay
in completing the staff's review. In its letter, the licensee stated
that this delay causes a threat to PP&L's ability to complete the Unit
2 8th refueling and inspection outage as planned and the return to Unit
2 operation. This outage has already begun. During the original Unit 2
outage scoping process PP&L stated that it did not anticipate the need
for a specific NRC inspection of SPC to support the NRC review and
approval of the December 18, 1996 amendment. Further, PP&L reasonably
expected that all audit results would be satisfactory and would not
impact the current Unit 2 outage schedule. The resultant consequences
required the supplemental submittal on March 12, 1997, and requires
additional unavoidable NRC staff review which is ongoing. The March 17,
1997 application is only to approve those changes that are applicable
to allow fuel to be loaded and maintained in the reactor core only
during Operational Condition 5 on an interim basis during the outage
and prior to the NRC's approval of the December 18, 1996 and March 12,
1997, requested TS changes, to minimize the delay in startup based on
the NRC review of the two submittals discussed above. The staff agrees
that exigent conditions exist that were not anticipated by the
licensee.
This notice is related to the amendment requested by the December
18, 1996 and March 12, 1997 submittals by Pennsylvania Power and Light
Company, but does not affect the previous notice dated March 12, 1997,
which was published in the Federal Register on March 18, 1997 (62 FR
12859).
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 change does not involve a significant increase
in the probability or consequences of an accident previously
evaluated.
The description of a fuel assembly (Section 5.3.1) is revised to
reflect the fact that ATRIUMTM-10 contains a central water
channel. Since the active fuel length of ATRIUMTM-10 is
different from that of 9 x 9-2, reference to an active fuel length
of 150 inches is no longer appropriate and was deleted. There is no
safety significance to these changes.
Due to the limitation of this proposed change to Operational
Condition 5, only a subset of the accident events analyzed in the
FSAR [Final Safety Analysis Report] needed to be addressed. All
other events were considered and the addition of ATRIUMTM-10
fuel to the reactor core in Operational Condition 5 did not increase
the probability or consequences of an accident previously evaluated.
The events considered are described below.
The maximum allowed enrichment (Section 5.3.1) is increased from
4.0 to 4.5 weight percent U235. Criticality calculations were
performed with a KENO Monte Carlo code to ensure that ATRIUMTM-
10 fuel with a lattice average enrichment of 4.5 weight percent U235
can be safely stored in both the new fuel vault and the spent fuel
storage pool at Susquehanna. These calculations demonstrated,
consistent with current Technical Specifications, that the maximum
k-effective of both the new fuel vault and spent fuel storage pool
will not exceed 0.95 under the worst credible storage array or
accident conditions.
The ATRIUMTM-10 fuel assembly is unirradiated and its
weight is nearly identical to the current SPC 9 x 9-2 fuel assembly
weight as well as being less than the fuel assembly weight used in
the 9 x 9-2 analyses (680 lbs.). The dose consequences of the
current 9 x 9-2 licensing analyses of the Fuel and Equipment
Handling Accidents bound the dose consequences of a Fuel Handling
Accident involving ATRIUMTM-10 fuel.
The grappling of the ATRIUMTM-10 fuel is similar to the
9 x 9-2, due to the similar bail handle dimensions and assembly
weights. Therefore, ATRIUMTM-10 fuel is completely compatible
with the refueling platform main grapple. Because the assembly
weights of the ATRIUMTM-10 fuel and the 9 x 9-2 fuel are
essentially the same, the capacity of the refueling platform main
hoist will be sufficient to handle the ATRIUMTM-10 fuel. Also,
the ATRIUMTM-10 fuel uses the identical fuel channel design as
the 9 x 9-2 fuel and the lower tie plate has very similar outside
dimensions. Therefore, the ATRIUMTM-10 fuel is compatible with,
and can be safely inserted/placed into the reactor core.
Storage of channelled ATRIUMTM-10 fuel in the Reactor Core
was evaluated. Core shutdown margin calculations were performed
using NRC approved methodology for the beginning of cycle core
configuration. Validation of the shutdown margin methodology as it
applies to ATRIUMTM-10 was done through comparisons to Siemens'
Power Corporation analyses and higher-order Monte Carlo
calculations. Calculated core shutdown margin for the beginning of
cycle core loading is greater than 1.00%[delta]k/k which far exceeds
the Technical Specification value of 0.38%[delta]k/k. Therefore,
ATRIUMTM-10 fuel can be placed into the U2C9 final core
configuration with assurance that the core will remain subcritical
with the strongest worth rod withdrawn. A positive core shutdown
margin assures protection against the control rod removal error
during refueling (FSAR Section 15.4.1.1) because subcriticality is
maintained.
[[Page 14168]]
In addition, the ATRIUMTM-10 fuel assembly dimensions
critical to interface with the Spent Fuel Storage Pool and Reactor
Vessel are essentially the same as the 9 x 9-2 design. Therefore,
the ATRIUMTM-10 can be properly stored.
Included in the revised Technical Specifications via reference
(Section 6.9.3.2) is one NRC approved topical report containing the
criteria for the design of Siemens Power Corporation fuel. SPC
analyses have demonstrated that ATRIUMTM-10 fuel complies with
the NRC approved criteria thus assuring the structural integrity of
the fuel. Compliance with the criteria applicable to Operational
Condition 5 assures that ATRIUMTM-10 fuel can be safely stored
in the spent fuel pool and loaded in the Unit 2 reactor core during
Operational Condition 5.
Based on the foregoing, the proposed action does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. The proposed change does not create the possibility of a new
or different kind of accident from any accident previously
evaluated.
The changes to the Unit 2 Technical Specifications (Design
Features and inclusion of the methodology reference) to allow
Operational Condition 5 loading of ATRIUM-10 fuel do not require any
physical plant modifications (other than loading of the
ATRIUMTM-10 assemblies), physically affect any plant
components, or entail changes in plant operation. ATRIUMTM-10
fuel assemblies have approximately the same weight, outer
dimensions, and the same basic bail handle design as 9 x 9-2 fuel
assemblies and are handled in the same manner as 9 x 9-2 fuel
assemblies. Thus, the proposed change does not create the
possibility of a previously unevaluated operator error.
The topical report reference added to Section 6.9.3.2 contains
NRC approved acceptance criteria. SPC analyses have been performed
according to their Quality Assurance Program which demonstrate
compliance with these NRC approved fuel design criteria. Thus, the
ATRIUMTM-10 fuel will maintain its structural integrity during
core loading.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. The proposed change does not involve a significant reduction
in a margin of safety.
The changes to the Unit 2 Technical Specifications discussed in
Item 1 above (Design Features and inclusion of the mechanical design
methodology reference) will allow loading of ATRIUM-10 fuel in
Operational Condition 5. The proposed change does not require any
physical plant modifications (other than the loading of the
ATRIUMTM-10 fuel), physically affect any plant components, or
entail changes in plant operation. Therefore, the proposed change
will not jeopardize or degrade the function or operation of any
plant system or component governed by Technical Specifications. The
analyses performed provide assurance that the ATRIUMTM-10 fuel
will remain subcritical during storage and core loading and meets
the requirements of Technical Specification 5.6 and, thus, an
equivalent margin of safety is maintained.
ATRIUMTM-10 fuel assemblies have approximately the same
weight, outer dimensions, and the same basic bail handle design as
9 x 9-2 fuel assemblies and are handled in the same manner as 9 x 9-
2 fuel assemblies. The dose consequences of the Fuel and Equipment
Handling Accidents are not increased and, thus, an equivalent margin
of safety is maintained.
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
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, 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 April 24, 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 Osterhout Free Library, Reference
Department, 71 South Franklin Street, Wilkes-Barre, PA 18701. 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.
[[Page 14169]]
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 20555-0001, 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 John F. Stolz, Director, Project
Directorate I-2: 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 20555-0001, and to Jay Silberg, Esquire, Shaw, Pittman,
Potts and Trowbridge, 2300 N Street NW., Washington, DC 20037, 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 17, 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 Osterhout Free Library, Reference
Department, 71 South Franklin Street, Wilkes-Barre, PA 18701.
Dated at Rockville, Maryland, this 19th day of March 1997.
For the Nuclear Regulatory Commission.
Chester Poslusny,
Project Manager, Project Directorate I-2, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 97-7507 Filed 3-24-97; 8:45 am]
BILLING CODE 7590-01-P