[Federal Register Volume 61, Number 124 (Wednesday, June 26, 1996)]
[Notices]
[Pages 33144-33146]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-16267]
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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 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 (the licensee),
for operation of the Washington Nuclear Project No. 2 (WNP-2), located
in Benton County, Washington.
The proposed amendment, requested by the licensee by letter of
December 8, 1995, would represent a full conversion from the current
Technical Specifications (TS) to a set of TS based on NUREG-1434,
``Improved BWR/6 Technical Specifications,'' Revision 1, April 1995.
NUREG-1434 has been developed through working groups composed of both
NRC staff members and the BWR/6 owners and has been endorsed by the
staff as part of an industry-wide initiative to standardize and improve
TS. As part of this submittal, the licensee has applied the criteria
contained in the Final NRC Policy Statement on Technical Specification
Improvements to the current WNP-2 Technical Specifications utilizing
BWR Owners' Group (BWROG) report NEDO-31466, ``Technical Specification
Screening Criteria Application and Risk Assessment,'' (and Supplement
1) as incorporated in NUREG-1434.
The licensee has categorized the proposed changes into four general
groupings. These groups are characterized as administrative changes,
relocated changes, more restrictive changes, and less restrictive
changes.
Administrative changes are those that involve reformatting,
renumbering and rewording of the existing TS. The reformatting,
renumbering and rewording process reflects the attributes of NUREG-1434
and do not involve technical changes to the existing TS. Such changes
are administrative in nature and do not impact initiators of analyzed
events or assumed mitigation of accidents or transient events.
Relocated changes are those involving relocation of requirements
and surveillances for structures, systems, components or variables that
do not meet the criteria of inclusion in TS as identified in the
Application of Selection Criteria to the WNP-2 TS. The affected
structures, systems, components or variables are not assumed to be
initiators of analyzed events and are not assumed to mitigate accident
or transient events. The requirements and surveillances for these
affected structures, systems, components or variables will be relocated
from the TS to administratively controlled documents. Changes to these
documents will be made pursuant to 10 CFR 50.59. In addition, the
affected structures, systems, components or variables are addressed in
existing surveillance procedures which are subject to 10 CFR 50.59 and
subject to the change control
[[Page 33145]]
provision in the Administrative Controls Section of the TS. These
proposed changes will not impose or eliminate any requirements.
More restrictive changes are those involving more stringent
requirements for operation of the facility. These more stringent
requirements do not result in operation that will alter assumptions
relative to mitigation of an accident or transient event. The more
restrictive requirements continue to ensure process variables,
structures, systems and components are maintained consistent with the
safety analyses and licensing basis.
Changes characterized as less restrictive have been subdivided into
four additional subcategories. They include:
a. Relocating details to TS Bases, the Updated Safety Analysis
Report (USAR), or procedures. The requirements to be transposed from
the TS to the Bases, USAR or procedures are the same as those currently
included in the existing TS. The TS Bases, USAR and procedures
containing the relocated information are subject to 10 CFR 50.59 and
are subject to the change control provisions in the Administrative
Controls section of the TS.
b. Extension of instrumentation surveillance test intervals (STIs)
and allowed outage times (AOTs). The proposed changes affect only the
STIs and AOTs and will not impact the function of monitoring system
variables over the anticipated ranges for normal operation, anticipated
operational occurrences, or accident conditions. However, the changes
are expected to reduce the test related plant scrams and test induced
wear on the equipment. General Electric Topical Reports GENE-770-06-1
and GENE-770-06-2 showed that the effects of these extensions of STIs
and AOTs, which produced negligible impact, are bounded by previous
analyses. Further, the NRC has reviewed these reports and approved the
conclusions on a generic basis.
c. Relocation of instrumentation only requirements (which provide
no post-accident function). These requirements are part of the routine
operational monitoring and are not considered in the safety analysis.
Changes made to the Bases, USAR, and procedures containing the
relocated information will be made in accordance with 10 CFR 50.59 and
are subject to the change control provisions in the Administrative
Controls section of the TS. These proposed changes will not impose or
eliminate any requirements.
d. Other less restrictive changes. Additional changes that result
in less restrictions in the TS are discussed individually in the
licensee's submittal. In addition to the changes solely involving the
conversion, changes are proposed to the current Technical
Specifications or as deviations from the Improved BWR/6 Technical
Specifications (NUREG-1434) as follows:
1. Surveillance frequency changed from 18 months to 24 months for
all surveillances normally performed at refueling outages.
2. LCO 3.1.4 and SR 3.1.4--change to average scram time of 2x2
array of control rods with allowance for ``slow'' rods.
3. LCO 3.3.6.1--delete isolation function of RHR shutdown cooling
suction flow rate high.
4. LCO 3.3.7.1--change proposed ACTION for inoperable control room
emergency filtration system (CREFS) radiation monitors.
5. LCO 3.3.8.1--reduce number of required loss of voltage channels.
6. LCO 3.3.1.1--revise Standard Technical Specification (STS)
ACTION for loss of one manual trip function to increase allowable
outage time (AOT) from 1 hour to 12 hours.
7. SR 3.3.1.2.5--note added which provides SR 3.0.1 exception for
signal-noise ratio.
8. LCO 3.3.3.1--post accident monitoring (PAM) function
surveillance requirement (SR) frequencies. Application of NEDO-30851-P-
A to adopt a 6 hour AOT for required surveillances.
9. LCO 3.3.3.2--delay entry into TS ACTION for up to 6 hours to
perform surveillance.
10. LCO 3.3.6.1--delete ** Modes for reactor building exhaust
radiation-high isolation signal for primary containment.
11. LCO 3.3.6.1--delete certain containment isolation functions.
12. LCO 3.3.6.2--delete fuel handling sweep radiation monitor.
13. LCO 3.7.1--increase SW system AOT.
14. LCO 3.3.6.1--delete Mode 2 for shutdown cooling (SDC) isolation
on pump room high temperature and area ventilation delta T.
15. LCO 3.3.7.1--delete requirement to isolate remote air intake if
one of two radiation monitors is inoperable.
16. LCO 3.3.7.1--restore inoperable air intake radiation monitor in
30 days vice CTS AOT of 7 days.
17. LCO 3.3.8.1--changes to current technical specifications (CTS)
allowable values.
18. LCO 3.3.8.2--changes to CTS allowable values and new condition
and applicability statements.
19. SR 3.4.8--note added to Table to allow a channel to be
inoperable for 6 hours solely for performance of required SRs.
20. LCO 3.5.1--extended AOTs for one low pressure emergency core
cooling system (ECCS) subsystem, two low pressure ECCS subsystems, high
pressure core spray (HPCS) concurrent with one low pressure coolant
injection (LPCI) subsystem, and one automatic depressurization system
(ADS) valve concurrent with one low pressure ECCS subsystem out of
service.
21. SR 3.6.1.2.2--decrease airlock interlock verification from 6
months to 24 months.
22. Current TS 3/4.6.1.6--deletion of entire specification for
drywell and suppression chamber pressure.
23. Current TS 4.6.2.2.b--remove surveillance test of residual heat
removal (RHR) pump recirculation flow through RHR HX and suppression
pool sparger to plant controlled document.
24. LCO 3.6.2.3--add allowance of 8 hours to restore one RHR
suppression pool cooling subsystem to OPERABLE with both inoperable.
25. SR 3.6.2.3.2--reduce required flow from 7450 gpm to 7100 gpm.
26. LCO 3.8.1--increase AOTs for diesel generators (DGs).
27. SR 3.8.1--increase start and load times for DGs from 10 to 15
seconds.
28. LCO 3.8.2--increase in restoration completion time for DG-3
from 72 hours to 7 days.
29. SR 3.8.3.5--decrease frequency of water check in diesel oil
from 31 days to 92 days.
30. SR 3.8.4.2 and 5--move resistance limits on connections to
battery terminals to BASES.
31. SR 3.8.4.6--reduce length of battery charger load test from 4
to 1.5 hours.
32. SR 3.8.4.1--reduce battery terminal voltage from 258 to 252
volts and from 129 to 126 volts.
33. LCO 3.3.2.1--adds ``and with no peripheral control rod
selected'' to RBM operability.
34. LCO 3.3.3.1--delete note to Condition C and Condition D for
H2 monitors.
35. LCO 3.3.4.2--reduce frequency of reactor vessel pressure high
ATWS-RPT function channel calibration from quarterly to 18 months.
36. LCO 3.4.7--change reactor coolant system (RCS) pressure
isolation valve (PIV) test pressure from 935 plus-minus 10 psig to
1035 psig.
37. LCO 3.4.1--move power-to-flow map from LCO to the Core
Operating Limits Report (COLR).
38. LCO 3.5.1--change in pressure for ADS operability from 128 psig
to 150 psig.
[[Page 33146]]
39. LCO 3.5.2--change in suppression pool level requirement in
Modes 4 and 5 from 30 ft. 9\3/4\ in. to 18 ft. 6 in.
40. 4.0--change in water level requirement for spent fuel pool from
605 ft. 7 in. to 583 ft. 1\1/4\ in.
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.
By July 26, 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 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.
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. Philips, Jr., Esq., Winston &
Strawn, 1400 L Street, N.W., Washington, D.C. 20005-3502, 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).
If a request for a hearing is received, the Commission's staff may
issue the amendment after it completes its technical review and prior
to the completion of any required hearing if it publishes a further
notice for public comment of its proposed finding of no significant
hazards consideration in accordance with 10 CFR 50.91 and 50.92.
For further details with respect to this action, see the
application for amendment dated December 8, 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 20th 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. 96-16267 Filed 6-25-96; 8:45 am]
BILLING CODE 7590-01-P
