ML20246C170
| ML20246C170 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/20/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246C175 | List: |
| References | |
| NUDOCS 8905090278 | |
| Download: ML20246C170 (8) | |
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7590-01 l
UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of an amendment to Facility Operating License No. NPF-12, issued to South Carolina Electric & Gas Company and South Carolina Public Service Authority (the licensees) for operation of the Virgil C. Summer Nuclear Station, Unit 1, located in Fairfield County, South Carolina.
The proposed amendment to the Virgil C. Summer Nuclear Station Technical Specifications (TS) would reduce the number and severity of starts of the emergency diesel generators, thereby decreasing engine wear and increasing reliability. This proposed change was originally noticed as a proposed no significant hazards consideration on July 17, 1985 at 50 FR 29016 and renoticed on June 4, 1986 at 50 FR 20373, and August 24, 1988 at 53 FR 32295.
By letter dated November 9,1987, the NRC requested additional information on the proposed changes. The licensee responded with a submittal dated May 16, 1988 that was modified in a July 14, 1988 submittal.
These two submittals were referenced in the August 24, 1988 proposed no significant hazards consideration.
8905090278 890503 PDR ADOCK 05000395 P
2 The November 18, 1988 submittal modified the note to Table 4.8-1 to indicate that loading the diesel generator was part of the ten tests identified in the note. Therefore, Surveillance Requirement 4.8.1.1.2.a.4 was added to the note.
l Surveillance Requirement 4.8.1.2 was also modified to indicate that loading the diesel generator (4.8.1.1.2.a.4) was unnecessary in the demonstration of the operability of the A. C. electrical power sources. Finally, Surveillance Requirement 4.8.1.1.3 was modified to indicate that a Special Report is required to be filed with the Nuclear Regulatory Comission for all failures of the diesel generators, valid or non-valid.
The April 5, 1989 submittal modified Surveillance Requirement 4.8.1.2 to delete the term "or verification" from it.
In addition, the note to TS 3.8.1.2.b was modified to indicate that the ESF Load-Sequencer may be deenergized in Modes 5 and 6 provided that the loss of voltage and the degraded voltage relays are disabled.
8efore issuance of the proposed license amendment, the Comission will have made findings required 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 amendment request involves no significant hazards consideration. Under the Comission's
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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 aceldent 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 shfety. The basis for this proposed determination is provided below.
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j The licensee has determined the proposed amendment involves no significant hazards consideration as follows:
(1) The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because a reduction in frequency and severity of diesel generator test starts will result in less wear and stress on engine parts. This will decrease the probability of an accident due to failure of engine parts, and the consequences of an accident will not change.
The present Technical Specifications do not require the various sequencer actuation signals to be operable in Modes 5 and 6.
The defeat of the loss of voltage and degraded voltage relays in conjunction with the sequencer being inoperable will prevent a potential inadvertent overload of the unit and require the operdtor to manually control loading of the unit. A conservative engineering evaluation has shown that there is adequate time for manual operator action;. This change will decrease probability of a diesel failure and enhance the operators' capability to respond to a loss of power in Modes 5 and 6.
(2) The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated because the design and function of the diesel generator will not change. Starting and loading of the diesel generator will be manually controlled to reduce the possibility of overloading the unit.
l (3) The proposed amendment does not involve a significant reduction in the margin of safety because there will be no change in response times or emergency loads assumed in the accident analysis for Modes 5 and 6.
The NRC staff has made a preliminary review of the licensee's no significant hazards consideration determination and agrees with the licensee's analysis. Accordingly, the Commission proposes to determine that the requested amendment does not involve a significant hazards consideration.
l The Commission is seeking public comments on this proposed determination.
Any comments received within 30 days after the date of publication of this l
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i 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 hearing.
l Written comments may be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publications Services, Office of Administration and Resources Management, U. S. Nuclear Regulatory Commission, Washington, DC 20555 and should cite the publication date and page number of the FEDERAL REGISTER notice. Written comments nay also be delivered to 7920 Norfolk Avenue, Room P-216, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m.
Copies of written comments received may be examined at the Nuclear Regulatory Commission Public Document Room, 2120 L Street N.W., Washington, D. C.
The filing of requests for hearing and petitions for leave to intervene l
1s discussed below.
By May 26,1989
. 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. Requests 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 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 I
an appropriate order.
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l As required by 10 CFR 92.714, 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 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 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 fifteen (15)' days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition niust 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 i
petition to intervene which must include a list of the contentions which dre sought 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 petitior.er 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.
6 Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the oppor-tunity 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 Comission 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 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 pla'ce before the issuance of any amendment.
Normally, the Comission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the I
notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Comission 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 v;111 publish a notice of issuance and provide fnr opportunity for a hearfr.g after issuance. The Comission expects tnat the need to take this action will occur 4
very inf requently.
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A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Commission.
Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room, 2120 L Street N.W.
Washington, D.C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner promptly so inform _ the Comission by a toll-free telephone call to Western Union at 1 (800) 325-6000 (in Missouri I (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Elinor G. Adensam:
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 Of fice of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and to Randolph R. Mahan, South Carolina Electric & Gas Company, P. O. Box 764, Columbia, South Carolina 29218, 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 tta Comission, the presiding 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 determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
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For further details with respect to this action, see the application for l
amendment dated June 10, 1985, as supplemented December 6, 1985 and May 16, July 14, July 28, and November 18, 1988 and April 5, 1989, which is available for public inspection at the Commission's Public Document Room, 2120 L Street N.W., Washington, D.C.
20555, and at the Fairfield County Library, Garden and Washington Streets, Winnsboro, South Carolina 29180.
Dated at Rockville, Maryland, this 20th day of April 1989.
FOR THE NUCLEAR REGULATORY COMt11SSION Original Signed By:
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation l
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