ML20134M894
| ML20134M894 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/13/1997 |
| From: | Dick G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134M896 | List: |
| References | |
| NUDOCS 9702210077 | |
| Download: ML20134M894 (8) | |
Text
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i 7590-01-P i.
UNITED STATES NUCLEAR REGULATORY COMISSION COMONWEALTH EDISON COMPANY l
DOCKET NOS. STN 50-454. STN 50-455. STN 50-456 AND STN 50-457 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO j
FACILITY OPERATING LICENSES. PROPOSED NO SIGNIFICANT RAZARDS CONSIDERATION DETEWINATION. AND OPPORTUNITY FOR A HEARING i
The U.S. Nuclear Regulatory Commission (the Commission) is considering j
issuance of amendments to Facility Operating License Nos. NPF-37, NPF-66, j
NPF-72, and NPF-77 issued to Commonwealth Edison for operation of the Byron a
Station, Units 1 and 2, located in Ogle County, Illinois and Braidwood Station, Units 1 and 2, located in Will County, Illinois.
The proposed amendments would relocate certain cycle-specific parameter j
limits from the Technical Specifications to the Operating Limits Report (ORL).
Before issuance of the proposed license amendments, the Comission will have made findings as required by the Atomic Energy Act of 1954, as amended j
(the Act) and the Commission's regulations.
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The Commission has made a proposed determination that the amendments 1
l requested involve 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 amendments would not (1) involve a significant increase in the probability or consequences of an accident i
previously evaluated; or (2) create the possibility of a new or different kind d
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),
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the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
l 9702210077 970213 PDR ADOCK 05000454 p
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The proposed Technical Specification changes do not involve-a significant increase in the probability or consequences of an accident previously evaluated.
The relocation of the cycle-specific core operating limits from the Technical Specifications has no influence or impact on the probability or consequences of any accident previously evaluated. The Technical Specifications will continue to require operation within the analyzed core operating limits and the appropriate actions will be taken if the limits are exceeded.
The cycle specific limits within the OLR will be implemented and controlled by plant procedures. Any needed revisions of the limit values in the OLR will be performed based on NRC approved methodology as delineated in TS 6.9.1.9.
Each accident analysis addressed in the Byron and Braidwood Updated Final Safety Analysis Report (UFSAR) will be examined with respect to changes in cycle dependent parameters. These parameters are obtained from the application of NRC approved reload design methodologies, to ensure that the transient evaluation of new reloads are bounded by previously accepted analysis.
This examination, which will be performed under the requirements of 10 CFR 50.59 process, ensures that future reloads will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The relocation of the cycle specific variables has no influence or impact, nor does it contribute in any way to the probability or consequences of any new or different kind of accident. No safety related equipment, safety function or, plant operations will be altered as a result of this proposed change. The cycle specific variables are calculated using NRC approved methods and submitted to the NRC for their review to allow the Staff to continue to trend the values of these limits. The Technical Specifications will continue to require operation within the analyzed core operating limits and appropriate actions will be taken, I
when, or if, the limits are exceeded.
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Therefore, the proposed changes do not in any way create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The proposed change does not involve a significant reduction in a margin of safety for the following reasons:
The margin of safety is not affected by the relocation of cycle specific core operating limits from the Technical j
Specifications. The margin of safety presently provided by current Technical Specifications remains unchanged.
Appropriate measures exist to control the values of these cycle specific limits. The proposed amendment continues to require operation within the core limits as obtained from the NRC approved reload design and safety analysis methodologies. Appropriate actions are required to be i
taken, when, or if, these limits are exceeded.
The development of the limits for future reloads will continue to conform to those methods described in the NRC approved documentation.
In addition, each future reload will involve a 10 CFR 50.59 safety review to assure that operation of the Byron and Braidwood units within the cycle specific limits will not involve a reduction in the margin of safety as defined in the basis for any Technical Specification.
Therefore, the proposed changes do not impact operation of the )lant in a manner that involves a significant reduction in tie margin of safety.
i The NRC staff has reviewed the licensee's analysis and, based on this 1
review, it appears that the three standards of 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendments requested involve no significant hazards consideration.
The Commission is seeking public connents on this proposed determination. Any comments received within 30 days after the date of 2
publication of this notice will be considered in making any final detemination.
Normally, the Commission will not issue the amendments until the expiration of the 30-day notice period. However, should circumstances change
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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 detemination 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 Review and Directives Branch, Division of Freedom of Information and Publications 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 i
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 March 24, 1997
, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating licenses 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 l
request for a hearing and a peti +. ion for leave to intervene. Requests for a f
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:
for Byron, the Byron Public Library District,109 N. Franklin, P.O. Box 434, Byron, Illinois 61010; for Braidwood, the Wilmington Public Library, 201 S. Kankakee Street, Wilmington, Illinois 60481.
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 Chairaan 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
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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 amendments under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a
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supplement which satisfies these requirements with respect to at least one
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contention will not be permitted to participate as a party.
Those pemitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the i
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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 detemination on the issue of no significant hazards consideration. The final detemination will serve to decide when the hearing is held.
If the final determination is that the amendments requested involve no l
significant hazards consideration, the Commission may issue the amendments and l
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 l
j 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 l
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 i
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 l
of the petition should also be sent to the Office of the General Counsel, U.S.
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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 i
amendments dated December 21, 1995, as supplemented on October 24, 1996, which are 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 rooms located at:
for Byron, the Byron Public Library District,109 N. Franklin, P.O. Box 434, Byron, Illinois 61010; for Braidwood, the Wilmington Public Library, 201 S. Kankakee Street, Wilmington, Illinois 60481.
Dated at Rockville, Maryland, this 13th day of February 1997.
FOR THE NUCLEAR REGULATORY COMISSION Geo F. Dick, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation i
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