[Federal Register Volume 59, Number 156 (Monday, August 15, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-19904]
[[Page Unknown]]
[Federal Register: August 15, 1994]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. STN 50-454, STN 50-455, STN 50-456, STN 50-457]
Commonwealth Edison Co.; 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 amendments to Facility Operating License No.
NPF-37, NPF-66, NPF-72, and NPF-77, issued to Commonwealth Edison
Company (the licensee), for operation of Byron Station, Units 1 and 2,
located in Ogle County, Illinois and Braidwood Station, Units 1 and 2,
located in Will County, Illinois.
The proposed amendments consist of two parts: Part one, would
revise ``Moderator Temperature Coefficient (MTC)'' Technical
Specifications (TSs) to allow the use of a slightly positive MTC for
the core design. The licensee has stated that a positive MTC will
reduce the burnable rod requirements and improve operational
flexibility. Because of using a positive MTC, the TSs would be revised
to permit a higher boron concentration in the refueling water storage
tank, the reactor coolant system (RCS) accumulators, and the refueling
cavity, in order to ensure adequate shutdown margin is maintained at
all times. Part two, would revise the TSs to reduce the required RCS
flow to offset any reduction in flow due to increased steam generator
tube plugging. Additionally, the associated Bases for the above TSs
would be revised to describe the basis for the TS requirements.
Because Byron, Unit 1, and Braidwood, Unit 2, will be in refueling
outage in the fall of 1994, the proposed TS changes will apply to them.
Byron, Unit 2 and Braidwood, Unit 1 will continue to operate in
accordance with the current TSs. the licensee's submittal identified
the appropriate unit applicability of the TSs pertaining to the
positive MTC and the required FCS flows.
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:
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:
A. The proposed changes do not involve a significant increase in
the probability or consequences of an accident previously evaluated.
(1) The reduced thermal design flow and positive moderator
temperature coefficient program includes corresponding increases to
the [refueling water storage tank] RWST and accumulator required
boron concentration. The analysis program and associated boron
concentration changes will not affect the operability and integrity
of plant systems and components. The analysis program also does not
result in a condition that would challenge the design, material, and
construction standards of the plant systems and components.
Additionally, the safety functions of the evaluated systems and
components remain unchanged. The safety analyses necessary to
support the reduced [thermal design flow] TDF and [positive
moderator temperature coefficient] PMTC program were performed (WCAP
13964) and found to be acceptable and consistent with the Byron and
Braidwood original safety analysis bases. All Departure from
Nucleate Boiling (DNB) Ratio (DNBR) design limits were determined
such that there was a 95 percent probability at a 95 percent
confidence level that a DNBR value of 1.25 for a typical and thimble
cell were verified to have been met. The present Technical
Specification limit for Nuclear Enthalpy Rise Hot Channel Factor,
FNH of less than 1.65 ensures that the
limiting DNB ratio during normal operations and operational
transients (Condition I and Condition II events) is greater than or
equal to the DNBR limit of the correlation being applied thus fuel
integrity will not be challenged.
The accidents which are found to be sensitive to PMTC were
analyzed as part of this effort and the results were found to be
acceptable. On a cycle-by-cycle basis, the impact of PMTC on
Anticipated Trip Without Scram (ATWS) risk will be addressed by
determining the Unfavorable Exposure Time (UET) per established
Westinghouse Owners Group methodology, with corrective actions to be
taken as appropriate to assure acceptable risk. The increase in the
RWST and accumulator boron concentration will have no adverse impact
on the previously evaluated accidents. The SGTP/TDF/PMTC program
does not affect the integrity of the safety related systems and
components such that their function to control radiological
consequences is affected and all fission barriers will remain intact
. The effects on offsite doses have been considered. The
incorporation of a PMTC, a reduction in TDF and increased tube
plugging levels will result in a small increase in offsite doses,
however, the total doses remain a small fraction of the 10 CFR 100
limits. As such, the accident analysis acceptance criteria continue
to be satisfied. Therefore, the probability or consequences of an
accident previously analyzed in the [Updated Final Safety Analysis
Report] UFSAR is not increased by the SGTP/TDF/PMTC program.
B. The proposed changes do not create the possibility of a new
or different type of accident from any accident previously
evaluated.
(2) The methodology and manner of plant operation as a result of
the proposed changes is unchanged. The increased SGTP, reduced TDF,
and PMTC program, which includes changes to the RWST and accumulator
boron concentration, does not impact the safe operation of the
reactor provided that the existing and proposed Limiting Conditions
for Operation (LCOs) and the associated action requirements are
satisfied.
The reactor response to normal temperature fluctuations will be
different due to PMTC, however, the normal reactor control systems,
as designed, will continue to maintain a stable primary system
temperature and reliable power production. The assumptions do not
create any new failure modes that could adversely impact safety
related equipment. The related Safety Limits and LCOs in the plant
Technical Specifications will be evaluated and satisfied for each
future reload core design via the 10 CFR 50.59 process. All DNBR
Limits have been satisfied. The typical and thimble fuel cells were
verified to maintain a DNBR value of 1.25 at a 95 percent
probability and 95 percent conference level. Other than the analysis
for tube plugging, the proposed changes do not involve any equipment
additions or modifications at the stations. Currently installed
equipment will not be operated in a manner different than previously
designed. Changes will be made to technical data within the existing
station procedures, however, the analytical methods used to
determine the data also remain unchanged. All aspects of the SGTP/
TDF/PMTC program have been evaluated, and no new or different
accidents or failure modes have been identified for any system or
component important to safety. No new credible limiting single
failure has been created.
Because the SGTP/TDF/PMTC program does not adversely affect the
integrity of the steam generator or any other equipment, it is
determined that the proposed changes do not create the possibility
of a new or different type of accident from any accident previously
evaluated.
C. The proposed changes do not involve a significant reduction
in a margin of safety.
(3) The performance and integrity of the evaluated safety-
related systems and components are not affected by the proposed
changes. The radiological consequences of all previously analyzed
accidents remain unchanged. The reduced TDF and PMTC program, which
includes changes to the RWST and accumulator boron concentration,
will have no effect on the availability, operability, or performance
of the evaluated safety-related systems or components. The reactor
response to normal temperature fluctuations will be different due to
PMTC, however, the normal reactor control systems, as designed, will
continue to maintain a stable primary system temperature and
reliable power production. The margin of safety associated with the
licensing basis safety analysis is not significantly reduced by the
proposed changes. All acceptance criteria for the specific UFSAR
Chapter 15 safety analyses (Non-LOCA and LOCA) have been
satisfactorily evaluated and verified using NRC approved
methodologies. Therefore, there is no significant reduction in the
margin of safety as defined in the bases of any affected Technical
Specification.
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 and provide for opportunity for a hearing
after 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, 11455 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 September 14, 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 rooms, which for Byron is located at the Byron Public
Library, 109 N. Franklin, Byron, Illinois 61010; and for Braidwood is
located at the Wilmington Township Public Library, 201 S. Kankakee
Street, Wilmington, Illinois 60481. 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 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 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, 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 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 Mr. Robert A. Capra: 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 Michael I. Miller, Esquire; Sidney and Austin, One First National
Plaza, Chicago, Illinois 60690, 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 11, 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 the local public document rooms, which
for Byron is located at the Byron Public Library, 109 N. Franklin, P.O.
Box 434, Byron, Illinois 61010; and for Braidwood is located at the
Wilmington Public Library, 201 S. Kankakee Street, Wilmington, Illinois
60481.
Dated At Rockville, Maryland, this 4th day of August 1994.
For the Nuclear Regulatory Commission.
George F. Dick, Jr.,
Project Manager, Project Directorate III-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 94-19904 Filed 8-12-94; 8:45 am]
BILLING CODE 7590-01-M