ML20080K977
| ML20080K977 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/04/1983 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080K979 | List: |
| References | |
| NUDOCS 8309290575 | |
| Download: ML20080K977 (8) | |
Text
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-e (7590-01)
UNITED STATES NUCLEAR REGULATORY COMMISSION MISSISSIPPI POWER & LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT dAZARDS C?1 SIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Faciitty Opera,, ting License No. NPF-13, issued to Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association (the licensees), for operation of the Grand Gulf Nuclear Station, Unit 1, located in Claiborne County, Mississippi.
The amendment would provide changes to the Technical Specifications in accordance with the licensees' applications for' amendment dated April 25, June 9, June 23, and July 11, 1983.
These changes to the Technical Specificatio'ns involve the following sections:
(a) 4.7.6.1.3:
Revises surveillance procedure for fire pump diesel bitteries (April 25, 1983).
(b) 3.9.6: Change in refueling platform hoist interlock function (June 9,1983).
(c) 4.8.2.1:
Increase in. the load profile for Division 2125 volt DC batteries (June 23, 1983).
(d) Tables 3.3.2-1 and 4.3.2.1-1:
Deletes automatic removal of low condenser vacuum bypass (June 23, 1983).
(e) 3.4.2.1: _ Revises low-low set function for relief valves (July 11, 1983).
0309290575 030913 PDR ADDCK 05000416 P
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- (7590-01)
Before issuance of the proposed license amendment, the Comissfor, will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The proposed changes to the Technical Specifications were proposed to achieve consistency with BWR Standard Technical Specifications, with the as-built condition of the plant or with design changes currently being implemented at the plant. The proposed changes for battery surveillance (a) maintains a seven day surveillance for pilot cells only and requires each cell to be tested once per 92 days.
This surveillance revision has been determined to provide equivalent assurance of battery performance as compared to the surveillance currently used and has been approved in the GE BWR Standard Technical Specifications.
Thus, this change does not result in the significant reduction,of a safety margin, involve a significant increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes for refueling operations (b) expand the Technical Specifications to include an auxiliary platfonn in the primary containment and a fuel handling platform in the Auxiliary Building.
The changes also include additional separate and redundant interlock circuits while eliminating other refueling interlocks.
The interlocks that have been removed are not associated with equier.ent used for handling irradiated fuel assemblies. Thus, there is no reduction in the overall safety function.
The additional coverage discussed above results in a more stringent condition than that currently in the Technical Specificatiois.
The proposed changes to the Division 2 DC load profile (c) results from anti-cipated additional loads on.the system. The proposed load test is more severe
~ (7590-01) than the current one, thus is a more stringent condition than that presently in the Technical Specifications.
The proposed changes for the low condenser 4
vacuum bypass (d) will change this function from automatic to manual initiation. '
For the Grand Gulf accident analysis, automatic removal of this bypass function was not considered. Thus, this change does not result in the significant reduction of a safety margin, involve a significant increase in the propbility or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated.
The changes to the low-low set relief logic (e) revise the arming function so as to prevent simultaneous opening of ganged SRV's under certain transient conditions. Ganged opening of these SRV's was not considered in the containment design analysis. The change in arming logic does not change the setpoint for l
any SRY.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
"w the Cortnission's r,egulations 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 of different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The Commission has provided guidance concerning the application of its standards set forth in 10 CFR 50.92 for no significant hazards considerations, by proviJing certain examples, published in the Fedcral Register an April 6, 1983 (48 FR 14864). One of the examples of an amendment which will likely be found to
. (7590-01) involve no significant hazards considerations involves a change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications, for example, a more stringent surveillance requirem,ent.
Proposed ch,anges (b) (c) and (e) impose additional limitations, restrictions or controls not presently included in the license and fall within the Commission's example (ii), of action not likely to involve significant hazards consideration.
Proposed change (a) is a change in surveillance to meet GE BWR Standard Technical Specifications and provides equivalent assurance of battery performance as compared to current surveillance requirements. Proposed chahge (d) will correct an identified difference in the-as-%uilt plant and has no impact on safety as it was not considered to be associated with any operational or accident analysis. Due to the nature of proposed changes (a) and,(d) as discussed above, we have determined that these changes 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 Commission is seeking public comments on this proposed determination.
Any coments received within 30 days af ter the date of publication of this notice will be considered in naking any final determination.
The Cc m ission will not normally nake a final determination unless it receives a recuest for a hearing.
Comments should be addressed to the Secretary of the Commission, U. S.
'Juclear Regulatory Commission, tlashington, D. C. 20555, ATTN:
Docketing and Service Branch.
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By September g,1983, the licensees 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 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 Licerising 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 52.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that inte.est may be affected by the results of the proceeding. The i
petition should specifically explain the reasons why intervention should bb' 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, cr other interest in the proceeding; and (3) the possible effect of any order vehich 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 l
proceeding as to which petitioner wishes to intervene. Any persen who has filed a petition for leave to intervene or who has been admitted as a party
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' (7590-01) 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 sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to mat'ters within the scope of the amendment under consideration 7 A petitioner who fails to file such a supplement which satisfies ti ese requirements with respect to at least l
one contention will not be permitted to participate as a party.
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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 witnesse:.
If a hearing is requested, the Commission will make a final determination on the 1ssue of no significant hazards consideration. The final determination' f
will serve to decide when the hearing is held.
If the final determination is that the amendment requests involve no significant hazards consideration, the Commission may issue the amendnent and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
. (7590-01)
If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expiraticn 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 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 'p'ublic 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 Conmission expects that the need to take this action will occur very infrequently.
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 Conaission, Washington, D. C. 20555, ATTN:
Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H Street, N. W. Uashington, 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 prcTptly so inform the Commission by a toll-free telephone call to Uestern Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Hunber 3737 and the following message addressed to A. Schwencer:
petitioner's name and telephone number; date petition was i
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(7590-01) mailed; plant name; and publication date and page number of this FEDER'AL 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 Troy B. Conner, Jr., Esquire, Conner and Wetterhahn,1747 Pennsylvania Avenue, N. W., Washington, D. C. 20006, attorney for the licensees.
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 Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substant.f al' showing of gdod cause for the granting of a late petition and/or request. That determination will be based upon a balancing of the factors specifled in 10 CFi< 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the applications for amendment which are available for public inspection at the Commission's Public Docunent room,1717 H Street, N. W., Washington, D. C., and at the Hinds Jr. College, George M. ficLendon Library, Ravmond, 'tississippi 39154.
Dated at Bethesda, ttaryland, this 4th day of August 1983.
FOR THE NUCLEAR REGULATORY. C0!"11SSION
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A. Schwencer, Chief Licensing Branch t'o. 2 Division of Licensing