ML20132E715
| ML20132E715 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/17/1996 |
| From: | James Shea NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20132E719 | List: |
| References | |
| NUDOCS 9612230377 | |
| Download: ML20132E715 (8) | |
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7590-01-P UNITED STATES NUCLEAR REGULATORY C0ttilSSION PECO ENERGY COMPANY DOCKET NO. 50-353 NOTICE OF 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 Comission (the Comission) is considering issuance of an amendment to Facility Operating License No. NPF-85 issued to PECO Energy Company (the licensee) for operation of the Limerick Generating Station (LGS), Unit 2, located in Montgomery County, Pennsylvania.
The proposed amendment would revise technical specification (TS) Section i
2.1 and its associated TS basis to reflect the change in the Minimum Critical Power Ratio Safety Limit, due to the use of GE13 fuel product line and the cycle-specific analysis performed by the General Electric Company (GE), for LGS, Unit 2, Cycle 5.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the i
Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendment request involves 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 of accident from any accident previously evaluated; or (3) involve a significant MA22;ggg gagg;,
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i 5 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 proposed Technical Specifications (TS) change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The derivation of the revised Minimum Critical Power Ratio (MCPR)
Safety Limit for LGS Unit 2 Technical Specifications, and its use to determine cycle-specific thermal limits have been performed using i
NRC-accepted methodology described in " General Electric Standard Application for Reactor Fuel," NEDE-240ll-P-A-13, and U.S.
Supplement, NEDE-24011-P-A-13-US, August 1996 and the Technical Design Procedure ("GETAB Safety Limit", TDP-0049, Revision 0, July 1996). This change in the MCPR Safety Limit cannot increase the probability or severity of an accident.
The basis of the MCPR Safety Limit calculation is to ensure that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated. The new MCPR Safety Limit-preserves the existing margin to transition boiling and fuel damage in the event of a postulated accident. The fuel licensing acceptance criteria for the calculation of the MCPR Safety Limit apply to Limerick Generating Station (LGS), Unit 2, Cycle 5 in the same manner as they have applied previously. The probability of fuel damage is not increased.
Therefore, the proposed TS change does not involve an increase in l
the probability or consequences of an accident previously evaluated.
4 2.
The proposed TS change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The MCPR Safety Limit is a TS numerical value, designed to ensure i
that fuel damage from transition boiling does not occur as a result of the limiting postulated accident.
It cannot create the possibility of any new type of accident. The new Minimum Critical Power Ratio (MCPR) Safety Limit is calculated using NRC-accepted methodology described in " General Electric Standard Application for Reactor Fuel," NEDE-240ll-P-A-13, and U.S. Supplement, NEDE-240ll-P-A-13-US, August 1996 and the Technical Design Procedure ("GETAB Safety Limit", TDP-0049, Revision 0, July 1996).
9 Therefore, the proposed TS change does not create the possibility of a new or different kind of accident, from any accident previously evaluated.
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. 3.
The proposed TS change does not involve a significant reduction in a margin of safety.
The margin of safety as defined in the TS Bases will remain the same. The new Minimum Critical Power Ratio (MCPR) Safety Limit is calculated using NRC-accepted methodology described in " General Electric Standard Application for Reactor Fuel," NEDE-240ll-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, August 1996 and the Technical Design Procedure ("GETAB Safety Limit" TDP-0049, Revision 0, July 1996). The fuel licensing acceptance criteria for the calculation of the MCPR Safety Limit apply to LGS Unit 2 Cycle 5 in the same manner as they have applied previously.
The MCPR Safety Limit is set high enough to ensure that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity.
Therefore, the proposed TS change does not involve a reduction in a nargin 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.
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 coinnission take this
l action, it will publish in the FEDERAL REGISTER a notice of issuance and
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provide for opportunity for a hearing after issuance. The Commission expects i
that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rules Review and j
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
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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 January 22, 1997
, 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, and at the local public r
document room located at the Pottstown Public Library, 500 High Street,
. Pottstown, Pennsylvania 19464.
If a request for a hearing or petition for leave t'o 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 i
the Atomic Safety and Licensing Board Panel, will rule on the request and/or
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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 i
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 i
sought to be litigated in the matter.
Each contention must consist of a i
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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 i
l 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 j
proving the contention at the hearing. The petitioner must also provide l
references to those specific sources and documents of which the petitioner is l
aware and on which the petitioner intends to rely to establish those facts or j
expert opinion.
Petitioner must provide sufficient information to show that a i
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 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 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.
b 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: 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 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 John F. Stolz, Director, Project Directorate 1-2: petitioner's name and telephone number, date petition was uiled, 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 J. W. Durham, Sr., Esquire, Sr. V.P. and General Counsel, Philadelphia Electric Company, 2301 Market Street, Philadelphia, Pennsylvania 19101, attorney for the licensee.
Montimely 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
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- 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 amendment dated December 6, 1996, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, 4
NW., Washington, DC, and at the local public document room located at the Pottstown Public Library, 500 High Street, Pottstown, Pennsylvania 19464.
Dated at Rockville, Maryland, this 17th day of December 1996.
4 FOR NUCLEAR REGULAT RY COMMISSION i
n D Japeph W. Shea, Project Manager Prbject Directorate I-2 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
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