[Federal Register Volume 61, Number 126 (Friday, June 28, 1996)]
[Notices]
[Pages 33777-33779]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-16555]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-397]
Washington Public Power Supply System; 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-21 issued to Washington Public Power Supply System (WPPSS, also the
licensee) for operation of the WPPSS Nuclear Project No. 2 located on
Hanford Reservation in Benton County, Washington.
The proposed amendment would add a reactor water cleanup (RWCU)
system high blowdown containment isolation trip function and associated
Limiting Condition for Operation (LCO) and surveillance requirements to
Technical Specification (TS) Tables 3.3.2-1, 3.3.2-2, and 4.3.2.1-1.
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 the change involve a significant increase in the
probability or consequences of an accident previously evaluated?
The proposed amendment incorporates design features being
implemented to reduce the detection and isolation time for a
postulated High Energy Line Break (HELB) at the piping connection to
the Reactor Water Cleanup (RWCU) system blowdown flow control valve.
These design features significantly improve the capability to detect
and mitigate the effects of the line break and are necessary to
resolve Reactor Building environmental concerns. Since the design
features are for accident detection and mitigation, they are not
considered an accident initiator in the analyses and will not
increase the probability of the accident. Moreover, the
instrumentation design ensures that no single failure would preclude
isolation of the HELB.
The proposed amendment does not remove or modify any existing
Technical Specification requirements, but imposes additional
requirements related to the new ``Blowdown Flow--High'' trip
function consistent with existing Limiting Condition for Operation
(LCO) and surveillance requirements, conservative analyses, and
instrumentation setpoint methodologies. These requirements will
maintain the Reactor Building environment consistent with the
current analyses for the postulated RWCU HELB and provide assurance
that the radiological effects of the line break are bounded by the
accident analysis for the design basis Main Steam line break (MSLB)
outside containment. The calculated offsite doses for the MSLB are
less than 10% of the 10 CFR 100 guideline values and meet the
acceptance criteria of Standard Review Plan (NUREG-0800) 15.6.4.
On the basis of the information presented above, it is concluded
that the change does not involve a significant increase in the
[[Page 33778]]
probability or consequences of an accident previously evaluated.
2. Does the change create the possibility of a new or different
kind of accident from any previously evaluated?
This proposed amendment incorporates design features to resolve
Reactor Building environmental concerns that resulted from a
postulated RWCU HELB that had previously not been fully analyzed.
The design features will significantly improve the capability to
detect and mitigate the effects of the HELB. The instrumentation
design meets the single failure criterion, and a flow switch failure
results in fulfillment of the accident safety function of RWCU
system isolation. The instrumentation being installed does not
represent a new or different kind than currently used in similar
safety-related applications in the plant. Furthermore, the flow
instrumentation, piping/tubing, and associated supports have been
evaluated to withstand the effects of the design basis earthquake
(DBE) and the postulated HELB. An environmental qualification
evaluation determined that the equipment required to mitigate the
HELB or assure safe shutdown can withstand the adverse effects of
the HELB.
The proposed amendment does not remove or modify any existing
Technical Specification requirements or change the method of plant
operation, but imposes additional requirements related to the new
``Blowdown Flow--High'' trip function consistent with existing LCO
and surveillance requirements, conservative analyses, and
instrumentation setpoint methodologies. These requirements will
maintain the Reactor Building environment consistent with the
assumptions used in current analyses for the postulated RWCU HELB
and provide assurance that the radiological effects of the line
break are bounded by the accident analysis of the design basis MSLB
outside containment.
On the basis of the information presented above, it is concluded
that the change does not create the possibility of a new or
different kind of accident from any accident previously evaluated.
3. Does the change involve a significant reduction in a margin
of safety?
This proposed amendment incorporates design features being
implemented to reduce the detection and isolation time for a
postulated RWCU HELB. The design change complies with applicable
codes and standards to meet the safety-related function objective.
The instrumentation design meets the single failure criterion, and
the flow instrumentation, piping/tubing, and associated supports
have been evaluated to withstand the effects of a DBE, and the
postulated HELB. Furthermore, an environmental qualification
evaluation determined that the equipment required to mitigate the
HELB or assure safe shutdown can withstand the adverse effects of
the HELB.
The proposed amendment does not remove or modify any existing
Technical Specification requirements, but imposes additional
requirements related to the new ``Blowdown Flow--High'' trip
function consistent with existing LCO and surveillance requirements,
conservative analyses, and instrument setpoint methodologies. These
requirements will maintain the Reactor Building environment
consistent with the new analyses for the postulated RWCU HELB and
provide assurance that the radiological effects of the line break
are bounded by the accident analysis for the design basis MSLB
outside containment. The calculated offsite doses for the MSLB are
less than 10% of the 10 CFR 100 guideline values and meet the
acceptance criteria of Standard Review Plan (NUREG-0800) 15.6.4.
On the basis of the information presented above, it is concluded
that the change 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 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 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 July 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 Richland Public Library, 955 Northgate
Street, Richland, Washington 99352. 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
[[Page 33779]]
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 20555-0001, 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 William H. Bateman, Director, Project
Directorate IV-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 M. H. Phillips Jr., Esq., Winston &
Strawn, 1400 L Street NW, Washington, DC 20005-3512, 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 April 25, 1995, 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 Richland Public Library, 955 Northgate
Street, Richland, Washington 99352.
Dated at Rockville, Maryland, this 21st day of June 1996.
For the Nuclear Regulatory Commission.
Timothy G. Colburn,
Senior Project Manager, Project Directorate IV-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 96-16555 Filed 6-27-96; 8:45 am]
BILLING CODE 7590-01-P
