Washington Public Power Supply System; Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing

NUCLEAR REGULATORY COMMISSION

[Docket No. 50-397]

Washington Public Power Supply System; 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 issuing an amendment to Facility Operating License No. NFP-

21 issued to Washington Public Power Supply System (the licensee) for

operation of the Nuclear Project No. 2 (WNP-2) plant, located in Benton

County, Washington.

The proposed amendment would (1) revise TS 3/4.4.2 and 3/4.5.1 to

require main stream system and automatic depressurization system

safety/relief valve (SRV) surveillance testing within 12 hours after

steam pressure and flow are adequate to do the testing; and (2) revise

TS Table 4.3.7.5-1 to require SRV position indicator surveillance

testing within 12 hours after steam pressure and flow are adequate to

do the testing.

The intent of the change is to clarify when the 12-hour time period

begins. The licensee is also making a change to the TS SRV basis to

clarify that testing SRVs at low power means testing them when there is

adequate steam pressure and flow.

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:

The Supply System has evaluated the proposed changes against the

above standards as required by 10 CFR 50.91(a) and concluded that

the change does not:

(1) Involve a significant increase in the probability or

consequences of any accident previously evaluated.

The potential delay in confirming safety relief valve (SRV), SRV

position indication (acoustic monitor, valve stem position

indicators, and tailpipe temperature instruments), and ADS

operability during plant startup should not result in any change to

the expected satisfactory completion of the required surveillance

tests. Surveillance testing that is conducted during the plant

shutdown sequence, and during shutdown, provides reasonable

assurance that the SRVs will function when required. Under the

proposed change, plant test conditions would not be different than

in the past since testing was not begun until adequate pressure for

the duration of the test was achieved.

Therefore, this change does not involve a significant increase

in the probability or consequences of any accident previously

evaluated.

(2) Create the possibility of a new or different kind of

accident from any accident previously evaluated.

The proposed changes do not involve a design change nor do they

involve changes outside the scope of the existing test requirements.

No new failure modes are introduced as a result of the proposed

changes. The acoustic monitors merely provide indication that an SRV

is open. They do not provide an actuation signal. Alternate

mechanisms of SRV position indication exist, i.e., reactor water

level changes, reactor pressure changes, main turbine bypass valve

position, SRV tail pipe temperature, suppression pool level, and

suppression pool temperature. The time delay prior to operability

verification will not affect Technical Specification requirements.

Therefore, the proposed changes do not create the possibility of

a new or different kind of accident from any accident previously

evaluated.

(3) Involve a significant reduction in a margin of safety.

The proposed changes have no impact on the operability or

performance requirements of the SRVs, including the ADS function, as

they do not change the lift setpoints or minimum number of valves

required to be operable. The effect of delaying the starting point

of the time clock is not expected to affect completion of the

required tests. ADS/SRV position indication availability will not be

significantly affected by the proposed change since the additional

48 hours per refueling cycle of not verifying SRV, SRV position

indication, and ADS SRV operability occurs at low power with the

High Pressure Core Spray and Reactor Core Isolation Cooling systems

available. Additionally, there is a high probability that the SRVs

would perform their intended function if required even though they

have not been declared operable.

Therefore, the proposed changes do not involve a significant

reduction in a margin of safety.

The NRC staff 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 30-day notice period expires. 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 a notice of

issuance in the Federal Register 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, 11555 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 June 13, 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 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 particularly 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 Theodore R. Quay, Director, Project Directorate

IV-3: 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 M. H. Phillips, Jr., Esq., Winston &

Strawn, 1400 L Street NW., Washington, DC 20005-3502, the licensee's

attorney.

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 May 5, 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 Richland Public Library, 955

Northgate Street, Richland, Washington 99352.

Dated at Rockville, Maryland, this 10th day of May 1994.

For the Nuclear Regulatory Commission.

L. Mark Padovan,

Acting Project Manager, Project Directorate IV-3, Division of Reactor

Projects--III/IV, Office of Nuclear Reactor Regulation.

[FR Doc. 94-11786 Filed 5-12-94; 8:45 am]

BILLING CODE 7590-01-M