ML20113D323
| ML20113D323 | |
| Person / Time | |
|---|---|
| Site: | Robinson, San Onofre, 05000262  |
| Issue date: | 06/26/1996 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20113D325 | List: |
| References | |
| NUDOCS 9607030106 | |
| Download: ML20113D323 (8) | |
Text
..
7590-01 UNITED STATES NUCLEAR REGULATORY COP 94ISSION SOUTHERN CALIFORNIA EDISON COMPANY DOCKET NOS. 50-361 AND 50-362 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO fAtiLITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERNINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License Nos. NPF-10 and NPF-15 issued to Southern California Edison Company (the licensee) for operation of the San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 located in San Diego County, California.
The proposed amendment would revise Technical Specifications 3.3.11
" Post Accident Monitoring Instrumentation (PAMI)," and 5.5.2.13, " Diesel Fuel Oil Testing Program." Specifically, the number of instruments required to measure reactor coolant inlet temperature (T,,to), and reactor coolant outlet temperature (Tw), will be revised froid two per loop to two (with one per steam generator). The proposed change would also revise criteria for diesel fuel oil testing.
The changes described above would reinstate provisions of the current San Onofre Nuclear Generating Station (SONGS), Unit Nos. 2 and 3 technical specifications that were revised as part of Amendment Nos.127 and 116. These amendments adopted the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants."
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.
9607030106 960626 PDR ADOCK 05000361 P
4
. 4
.I g
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 l
accordance with the proposed amendment would not (1) involve a significant 4
l increase in the probability or consequences of an accident previously i
evaluated; or (2) create the possibility of a new or different kind of i
i l
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), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Proposed Technical Specification Change Number NPF-10/15-466 (PCN-466), Supplement I addresses modifications to the Technical Specifications for San Onofre Nuclear Generating Station (SONGS)
Units 2 and 3 approved by NRC Amendment Nos. 127 and 116. NRC Amendment Nos. 127 and 116 approved changes to adopt the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants," requested through Proposed Technical Specification Change Number NPF-10/15-299 (PCN-299). The proposed changes were identified during drafting of the procedure changes required to implement NRC Amendment Nos. 127 and 116.
PCN-466 Supplement 1 is required to restore certain provisions of the current Technical Specifications that were not properly incorporated in Amendment Nos. 127 and 116. Changes are pioposed that would revise Technical Specification (TS) TS 3.3.11. " Post Accident Monitoring Instrumentation (PAMI)," and TS 5.5.2.13
" Diesel Fuel Oil Testing Program."
Specifically, the proposed change corrects the number of instruments required to measure T and T from two per loop to two (with one coldlegRDT[RTD]an{fwone hot 7eg RTD per steam generator) in TS 3.3.11.
Also, the proposed change revises diesel fuel oil testing requirements specified in TS 5.5.2.13.
In particular, the viscosity limit specified in the Administrative Controls is revised to the correct range per ASTM-D975-81, which is consistent with the Bases to SR 3.8.3.3.
Also, a typographical error in paragraph b is
i corrected. The ASTM standard for sampling fuel oil is restored to ASTM-D4057-81.
i i
These provisions are contained in the current Technical l
Specifications TS 3/4.3.3.6, " Accident Monitoring Instrumentation,"
and in SR 4.8.1.1.2.c of TS 3/4.8.1.1, "A.C. Sources."
4 j
Operation of the facility would remain unchanged as a result of the i
proposed changes. Therefore, the proposed change will not involve a i
significant increase in the probability or consequences of any
{
accident previously evalsated.
2.
The proposed change does not create the possibility of a new or l
different kind of accident from any accident previously evaluated.
4 Tia proposed change will restore provisions of the current Technical l
Specifications for SONGS Units 2 and 3.
The proposed change would correct the number of instruments required to be operable to measure T,deand T from two per loop to two (with one cold leg RDT [RTD]
i y
e one hol, leg RTD per steam generator), and revise diesel fuel oil an l
testing requirements.
Operation of the facility would remain unchanged as a result of the proposed change. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
i 3.
The proposed change does not involve a significant reduction in a margin of safety.
The proposed change will restore provisions of the current Technical Specifications for SONGS Units 2 and 3 and make certain changes for clarity. Operation of the facility would remain unchanged as a result of the proposed change. Therefore, the proposed change will not involve a significast reduction in a 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.
Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards censideration.
The Coanission is seeking pdlic comments on this proposed determination. Any comments received within 30 days after the date of
i i
i !.
publication of this notice will be considered in making any final 1
determination.
Normally, the Commission will not issue the amendment until the l
expiration of the 30-day notice period. However, should circumstances change j
during the notice period such that failure to act in a timely way would i
result, for example, in derating or shutdown of the facility, the Commission i
may issue the license amendment before the expiration of the 30-day notice 1
period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider j
all public and State comments received. Should the Commission take this action, it will publish in the FEDERA'. REGISTER a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects 1
il 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 cosanents may also be delivered to Room 6022, 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 August 1,1996, 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 document room located at the Main Library, University of California, P. O. Box 19557, Irvine, California 92713.
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.
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
i i
be entered in the proceeding on the petitioner's interest. The petition 1
j 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 abitted as a party may amend the petition without requesting leave of the Board up to 15 days 1
prior to the first prehearing conference scheduled in the proceeding, but such l
an amended petition must satisfy the specificity requirements described above.
I 4
l Not later than 15 days prior to the first prehearing conference j
i j
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 j
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 i
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 4
supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
O,
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 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.
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 William H. Bateman, Director, Project Directorate IV-2: 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 T. E. Oubre, Esquire, Southern California Edison Company, P. O. Box 800, Rosemead, California 91770, 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 ihe 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)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated June 3,1996, as superseded by application dated June 25, 1996, which is 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 room located at the Main Library, University of California, P. O. Box 19557, Irvine, California 92713.
Dated at Rockville, Naryland, this 26th day of June 1996.
FOR THE NUCLEAR REGULATORY COMISSION Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV office of Nuclear Reactor Regulation
....