ML20136D729
| ML20136D729 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/26/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20136D733 | List: |
| References | |
| NUDOCS 9703120474 | |
| Download: ML20136D729 (8) | |
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7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSlQB COMMONWEALTH EDISON COMPANY DOCKET NOS. 50-237 AND 50-249 i
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Comission (the Comission) is considariilg issuance of amendments to Facility Operating License Nos. DPR-19 and DPR-25, issued to Comonwealth Edison Company (Comed, the licensee) for operation of the Dresden Nuclear Power Station, Units 2 and 3, located in Grundy County, Illinois.
The proposed amendments would change the Technical Specifications (TS) by relocating the TS requirements associated with the 24/48 Vdc batteries, battery chargers and distribution systems to other licensee administrative 1y controlled documents.
Before issuance of the proposed license amendments, the Comission will have made findings requ,S M by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendments requested involve no significant hazards consideration. Under the Comission'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 nf 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),
9703120474 970226 fDR ADOCK 05000g37 PDR
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1 the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1 (1)
Involve a significant increase in the probability or consequences j
of an accident previously evaluated because of the following:
1 Removal of the 24/48 Vdc batteries, chargers, and distribution panels from the Technical Speci?ication requirements of 3/4.9.C.
3/4.9.D 3/4.9.E, and 3/4.9.F and the subsequent relocation of i
those requirements to licensee administrative control is an j
administrative change that will still ensure the availability of the 24/48 Vdc system and will not increase the probability of l
accidents previously evaluated.
Relocation of the 24/48 Vdc requirements to administrative controls will have no effect on the control instrumentation and cannot act as an initiator for any of the accidents evaluated in the UFSAR [ Updated Final Safety Analysis Report).
Similarly, relocation of the 24/48 Vdc system requirements to 1
licensee administrative control will have no effect on the availability of the loads which are supplied by the 24/48 Vdc batteries nor on any of the consequences of actidents previously evaluated in the UFSAR. Control of the 24/48 Vdc requirements by station administrative controls under 10 CFR 50.59 will not affect any of the protection or mitigation functions which may be provided by any of the loads supplied by the batteries.
Operation i
l under the proposed amendment will not significantly increase the l
probability or consequences of any accidents previously evaluated.
(
8ecause of the above evaluation, removal of the 24/48 Vdc system from the Technical Specifications will not involve a significant increase in the probability or the consequences of an accident previously evaluated.
(2)
Create the possibility of a new or different kind of accident from any accident previously evaluated because:
The 24/48 Vdc batteries, chargers, and other components will retain the separation, and redundancy under which they are presently installed. No new failure modes are introduced by this administrative relocation of requirements, for the 24/48 Vdc system, from the Technical Specifications to licensee administrative control. The possibility of a new or different accident from any accident previously evaluated is not increased or created by this administrative change.
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i (3)
Involve a significant reduction in the margin of safety because:
Relocation of the TS requirements for the 24/48 Vdc system does not affect the operating points or setpoints of any systems or components.
Plant operating points or parameters are not changed by this proposed relocation of requirements in this amendment request. The safer.y related equipment that is supported by the 24/48 Vdc system will continue to be required in the existing i
modes of applicability as determined by the individual equipment Technical Specifications. Thus operation under the proposed license amendment removes some redundancy and constraints during refueling but does not significantly reduce 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.
I Therefore, the NRC staff proposes to determine that the amendments requested involve no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of 4
i publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendments 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 amendments before the expiration of the 30-day notice period, provided that its final determination is that the amendments involve 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.
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Written comments may be submitted by mail to the Chief, Rules Review and i
Directives Branch, Division of Freedom of Information and Publications i
Services, Office of Administration, U.S. Neclear Regulatory Comission, 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 6D22, 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, 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 April 4, 1997
, the licensee may file a request for a hearing with respect to issuance of the amendments 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 Comission'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 Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public document room located at the Morris Area Public Library District, 604 Libarty Street, Morris, Illinois 60450.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic
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Safety and Licensing Board Panel, will rule on the request and/or petition; i
and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
3 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 ' actors:
(1) the nature of the petitioner's right under the Act to be made party to the proceeding; i
(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 i
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 k
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 require.ments 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 conteiition and a concise statement of the alleged facts or expert opinion
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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 amendments requested involve no significant hazards consideration, the Commission may issue the amendments and make them immediately effective, notwithstanding the request for a hearing.
Any hearing held would take place after issuance of the amendments.
If the final determination is that the amendments requested involve a significant hazards consideration, any hearing held would take place before the issuance of any amendments.
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. 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, Wsshington, 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 pecitioner 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 Robert A. Capra:
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 Michael I.
Miller, Esquire; Sidley and Austin, One First National Plaza, Chicago, Illinois 60603, 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)(1)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendments dated February 19, 1997, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street,
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I NW., Washington, DC, and at the local public document room located at the Morris Area Public Library District, 604 Liberty Street, Morris, Illinois 60450.
Dated at Rockville, Maryland, this 26thday of February 1997.
FOR THE NUCLEAR REGULATORY COMMISSION A
5 hn F. Stang, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV q
Office of Nuclear Reactor Regulation 4
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