ML13316A820
| ML13316A820 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/25/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A819 | List: |
| References | |
| NUDOCS 8505010409 | |
| Download: ML13316A820 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTHERN CALI FORNIA EDISON COMPANY DOCKET NO.
50-206 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO PROVISIONAL OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOP HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Provisional Operating License No. DPR-13, issued to Southern California Edison Company (the licensee), for operation of the San Onofre Nuclear Generating Station, Unit No. 1 located in San Diego County, California.
By letter dated April 9, 1985, the licensee requested an amendment which would modify license condition 3.E, Steam Generator InsDections. The amendment would modify the schedule for performing an inspection of the steam generators from within six equivalent months of operation from the outage that ended on November 27, 1984 (estimated mid to late June 1985) to during the refueling outage scheduled to begin no later than November 30, 1985. The requirements to submit the inspection program 45 days prior to the shutdown and to obtain Commission approval before resuming power operation after the, inspection are unchanced.
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.
8505010409 850425 PDR ADOCK 05000206 PDR_
-2 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.
The basis For the proposed determination is discussed in the following paragraphs.
The present license condition 3.E.became effective upon issuance of Amendment No. 80 to the license on September 4, 1984. The basis for this license condition was discussed in the safety evaluation supportina Amendment No. 80 and in the staff's safety evaluation dated February 7, 1984 regarding the results of the previous steam generator inspection. The staff concluded in the February 7, 1984 safety evaluation that a steam generator inspection would be required within six Effective Full Power Months (EFPM) from the previous inspection based on the licensee's inability, at that time, to demonstrate a degradation rate less than 15% per year, but that the staff would evaluate any additional justification that the licensee may provide for extending this inspection interval.
The licensee's April 9, 1985 amendment request references a report entitled "1985 Reevaluation of Steam Generator Inspection Interval, March 1985" that was submitted for NRC staff review by letter dated March 19, 1985.
The purpose of this report is to document the reevaluation of the basis for the current steam generator inspection interval and to provide sufficient
-3 information to justify a longer inspection interval.
The licensee has reevaluated the intergranular attack degradation rate of the nonsleeved steam cenerator tubes using the methodology in the March 1985 report. The licensee concludes that the reevaluated intergranular attack rate (10% growth per 15 EFPM) justifies the resumption of a refueling cycle interval (15 EFPM)
For steam generator inspections.
The staff's preliminary evaluation of the March 1985 report indicates that the information presented justifies the licensee's amendment request to extend the schedule for performing the next steam generator inspection until the refueling outage scheduled to begin no later than November 30, 1985 after approximately 10.5 EFPM of operation, assuming optimum _peration, since the last inspection. The licensee's analysis shows that the degradation rate is less than 15% per year.
The Commission has provided guidance concerning the application of the standards for determinina whether a significant-hazards consideration exists by providing certain examples (48 FR 14870, April 6, 1983).
One of the examples (iv) of actions not likely to involve a significant hazards consideration relates to a relief granted upon demonstration of acceptable operation from an operating restriction that was imposed because acceptable operation was not yet demonstrated. This assumes that the operating restriction and the criteria to be applied to a request for relief have been established in a prior review and that it is justified in a satisfactory way that the criteria have been met. The proposed license amendment is encompassed by this example.
The Commission is seeking public comments on this proposed determination.
Any commerts 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 hearina.
Comments should be addressed to the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attn: Docketing and Service Branch.
By May 31, 1985
, 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 petition for leave to intervene. Request 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 reouest 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 desionated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As reouired by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceed ing, 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
5.
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 aspects(s) of the subject matter o 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 prehearing 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 souaht to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. 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 particiapte fully in the cnnduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
-6 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 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 involves a sionificant hazards consideration, any hearing held would take place before 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.
7 A request for a hearing or a petition for leave to intervene must be filed with the Secretarv of the Commission, U.S. Nuclear Requlatorv Commission, Washington, D.C.
20555, Attn:
Docketing and Service Pranch, or may be delivered to the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C., by the above date. Where petitions are filed during the last ten (10) day's of the notice period, it is requested that the petitioner promotly 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 J. A. Zwolinski:
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 Executive Legal Director, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, and to Charles R.
Kocher, AssistantGeneral Counsel, James Beoletto, Esquire, Southern California Edison Company, Post Office Box 800, Rosemead, California 91770, 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 presidino 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 late petition and/or request. That determina tion will be based upon a balancing of the factors specified in 10 CFR
?.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the licensee's apolication for amendment dated April 9, 1985, the steam generator inspection interval.report submitted March 19, 1985, and the NRC staff's safety evaluation dated February 7, 1984 which are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C.,
and at the San Clemente Public Library, 242 Avenida Del Mar, San Clemente, California 92672.
Dated at Bethesda, Maryland this 25th day of April 1985.
FOR P NUCLEAR REGU ATO COMMISSION John A. Zwolinski, Chief Opera ing Reactors Branch #5 Division of Licensing