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###### Nuclear Regulatory Commission

          - [Docket No. 50-271] 

The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-28 issued to Vermont Yankee Nuclear Power Corporation (the licensee) for operation of the Vermont Yankee Nuclear Power Station (Vermont Yankee) located in Vernon, Vermont. 

The proposed amendment would clarify the valve isolation signal information in the Technical Specification (TS) Table 4.7.2 and make an administrative change to the Table main steam isolation valves component identification. TS Table 4.7.2 lists containment isolation valves and the Primary Containment Isolation System (PCIS) groups to which the valves are assigned. Note 1 to Table 4.7.2 defines the isolation signals that are associated with the designated groups. The isolation signal description for Group 2 states that the valves are closed upon either low reactor water level or high drywell pressure. Residual heat removal (RHR) containment cooling valves V10-39A/B, V10-34A/B, V10-26A/B, V10-31A/B, and V10-38A/B are designated as Group 2 in Table 4.7.2 and isolate upon either (1) low-low reactor water level and low reactor pressure, or (2) high drywell pressure. Table 4.7.2 and associated Note 1 are being revised to clarify Group 2 isolation signals. Additionally, main steam isolation valve component identifications are revised by this proposed change to more clearly reflect all four inboard and outboard valves. 

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. The operation of the Vermont Yankee Nuclear Power Station in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. 

No changes are being made to plant design, method of operation or method of testing. This change will not alter the basic operation of process variables, systems, or components as described in the safety analysis. No new equipment is introduced. 

The proposed change does not affect the ability of the primary containment isolation system or ECCS systems to perform their required safety functions. The essential safety functions of providing primary containment integrity and providing water to cool the core in the event of an accident are maintained. There is no physical or operational change being made which would alter the sequence of events, plant response, or conclusions of existing safety analyses. This proposed change results in no impact on analyzed accident event precursors or effects. 

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 

2. The operation of Vermont Yankee Nuclear Power Station in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated. 

The proposed change does not involve any physical alteration of plant equipment and does not change the method by which any safety-related system performs its function. As such, no new or different types of equipment will be installed, and the basic operation of installed equipment is unchanged. There is no change in plant operation that involves failure modes other than those previously evaluated. The methods governing plant operation and testing remain consistent with current safety analysis assumptions. 

Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated. 

3. The operation of Vermont Yankee Nuclear Power Station in accordance with the proposed amendment will not involve a significant reduction in a margin of safety. 

No changes are being made to plant design, method of operation or method of testing. This change will not alter the basic operation of process variables, systems, or components as described in the safety analysis. No new equipment is introduced. 

The proposed change does not affect the ability of the primary containment isolation system or ECCS systems to perform their required safety functions. The essential safety functions of providing primary containment integrity and providing water to cool the core in the event of an accident are maintained. There is no physical or operational change being made which would alter the sequence of events, plant response, or conclusions of existing safety analyses. This proposed change results in no impact on analyzed accident event precursors or effects. 

This proposed change does not alter the physical design of the plant, methods or modes of operation, testing or analyses, thereby resulting in no impact on safety functions. Since the proposed change does not alter the means by which primary containment isolation is maintained and containment cooling valves are isolated in support of RHR LPCI actuation, there is no 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.                          ( print page 58112)    

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 and Directives Branch, Division of Administrative 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 6D59, 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, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland.                 

The filing of requests for hearing and petitions for leave to intervene is discussed below. 

By October 27, 2000, 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, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, and accessible electronically through the ADAMS Public Electronic Reading Room link at the NRC Web site (http://www.nrc.gov). 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 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: Rulemakings and Adjudications Staff, or may be delivered to the Commission's Public Document Room, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, by the above date. 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 David R. Lewis, Esq., Shaw, Pittman, Potts, and Trowbridge, 2300 N Street, NW., Washington, DC, 20037-1128, 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                           ( print page 58113)                        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 September 14, 2000, which is available for public inspection at the Commission's Public Document Room, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, and accessible electronically through the ADAMS Public Electronic Reading Room link at the NRC Web site (http://www.nrc.gov). 

Dated at Rockville, Maryland, this 21st day of September, 2000. 

For the Nuclear Regulatory Commission.

Richard P. Croteau,

Sr. Project Manager, Section 2, Project Directorate I, Division of Licensing Project Management, Office of Nuclear Reactor Regulation.

[FR Doc. 00-24831 Filed 9-26-00; 8:45 am] 

BILLING CODE 7590-01-P