Washington Public Power Supply System; Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing

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

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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