[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 
H<INF>2 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 <SUP>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