ML20247E626
| ML20247E626 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/27/1989 |
| From: | Boyle M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E610 | List: |
| References | |
| NUDOCS 8904030187 | |
| Download: ML20247E626 (6) | |
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7590-01 A
UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 q
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-21, issued to Northeast Nuclear Energy Company (NNECO), for operation of the Millstone Nuclear Power Station, Unit 1, located in Waterford, Connecticut.
By letter dated January 24, 1989, NNEC0 proposed an amendment to the license for Millstone Unit 1.
The proposed amendment will change Technical Specification (TS) 3.5.F.7(e) to clarify emergency core cooling system (EECS) availability and power requirements.
This clarification was requested because of maintenance activities on 4160 volt busses to be conducted during the next refueling outage, which is scheduled to start April 1, 1989.
In addition, editorial changes are being made to delete references to TS 3.5.F.8, 3.7.C.1.c and 3.7.C.1.d since these specifications were deleted in Amendment No. I to the Millstone Unit 1 license.
During the 1989 refueling outage, 4160 volt busses 14C and 14D are scheduled to be removed from service for extended periods of time (not concurrently) to conduct maintenance and inspections.
The net effect of the licensee's proposed change is that additional breaker manipulation by the l
operator will be required to permit injection from a second ECCS subsystem with a separate power supply.
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8904030187 890322 PDR ADOCK 05000245 P
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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 prob-ability 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.
The licensee provided the following evaluation of the above three criteria in their application.
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The clarification of power requirements during refueling will not impact the consequences of the reactor vessel draining event since the means tc ensure that adequate water level (> 12 inches) is maintained above the irradiated fuel in the vessel draining event due to the additional operator actions which would be needed to align separate power to ECCS equipment, is not significant.
The other proposed changes are administrative.
2.
Create the possibility of a new or different kind of accident from any previously analyzed.
The proposed changes to Specification 3.5.F.7.(e) do not impact plant response to any event to the point where it should be considered a new accident.
No new failure modes are associated with this change.
Assurance that the fuel will remain covered will be maintained, even though additional breaker manipulation will be required to provide separate power.
3.
Involve a significant reduction in a margin of safety.
The basis for the ECCS system requirements specified in Technical Specification 3.5.F is to ensure that water to the vessel is available to maintain water level above the fuel during refueling operations.
As specified in Technical Specifications 2.1.1.D, at least 12 inches of water must remain above the top of active fuel with fuel in the vessel during refueling.
This change will not decrease the margin of safety as defined in the basis of any Technical Specification.
The staff reviewed and agrees with the licensee's analysis provided above.
Accordingly, the Commission proposes to determine that this change does not involve significant hazards considerations.
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l 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.
The Commission will not normally make a final determination unless it receives a request for a hearing.
Written comments may be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publications Services. Office of Administration and Resources Management, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of the FEDERAL REGISTER notice. Written comments may also be delivered to Room P-216, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC. The filing of requests for hearing and petitions for leave to intervene is discussed below.
By
':tay 1, 1989
, 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 te affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene.
Requests for a hearing and petitions 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.
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.
4 As required by 10 CFR S2.714, 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 fifteen (15) days prior to the first pre-hearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (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, and the bases for each contention set forth with reason-able specificity.
Contentions shall be limited to matters within the scope of the amendment under consideration.
A petitioner who fails to file such a supple-ment which sathfies 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 l
any limitations in the order granting leave to intervene, and have the oppor-tunity to participate fully in the conduct of the hearing, including the oppor-tunity to present evidence and cross-examine witnesses.
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-5 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 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 b'efore the issuance of any amendment.
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 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.
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A request for a hearing or a petition for leave to intervene must be filed j
i with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, i
Washington, D.C.
20555, Attention:
Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W. Washington, D.C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that
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the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to John F. Stolz:
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, D.C. 20555, and to Gerald Garfield, Esquire, Day, Berry & Howard, Counselors at Law, City Place, Hartford, Connecticut 06103-3494, 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 Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a ' ate petition and/or request.
That determination will be 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 January 24, 1989, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, D.C.
20555, and at the Local Public Document Room, Waterford Public Library, 49 Rope Ferry Road, Waterford, Connecticut 06385.
Dated at Rockville, Maryland, this 27th day of Mareb. 1789.
FOR THE NUCLEAR REGULATORY COMMISSION Michael L. Boyle, Project Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation