ML20086J468
| ML20086J468 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/26/1991 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086J472 | List: |
| References | |
| NUDOCS 9112110270 | |
| Download: ML20086J468 (8) | |
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l'NITED STATES NUCLEAR REGULATORY COMMISS100 GEORGI A PQ.ER C0t3PANY ET AL'.
y0GTLEELECTRICCENERATlHGPLANT, UNITS 1-AND2 DOCKET NOS. 50-424 AND 50-425 NOTICE OF CONSIDEPATION OF iSSL'ANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED !!O SIGNIFICANT HA7ARDS CONSIDERATION DETEPHINATION, AND OPPORTUNITY FOR HEARING The.V.S. Nuclear Regulatory Commission (the Commissicn) is considering issuance of amendments to Facility Operating License No. NPF-68 and Facility
' Operating License No. NPF-81 issued to Georgia Power Company, et al. (licensee),
for operation of the Vogtle Electric Generating Plant, Units 1.and 2, loceted in Burke County, Georgia 3CF30.
The proposed amendments would change the Technical Specifications (TS) to revise the minimum required thermal design flow (TDF). Specifically, the footnote in TS Table 2.2.1, for " Loop Design Flow" would be changed to reduce the specified flow from 95,700 gpm to 93,600 gpm. Similarly, in TS 3.2.5.c, the "Feactor Coolant System (PCS) Flow" specified in the LCO (limiting condition for, operation) and associated TS Bases 3/4.2.5 would be revised from 393,136 grm to 384,509 gpm.
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) an'd the Commission's regulations.
'9112110270 911126 PDR ADOCK 05000424 P
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t The TDF is a design input parameter in the acudent analyses and reacter core thermal / hydraulic design calculations that demonstrate the necessary heet removhi'from the reactor core. The TDF value assumed in these analyses ar.d reflected in the plant TS prov1cc the licensing basis for the plant. The licensee indicates that the reduction in the TLF has been factored in the accident analyses including evaluation of component! and systems, and radiological consequences, as pert of its previously NRC approved analyses for VANTAGE-5 reload fuel, and relocation of steam generator narrow range level instrumentation taps. The licensee also indicates that additional transients and events, which were not considered in its VANTAGE-5 or level tap relocation analyses, have been reanalyzed. The structural and functional integrity of the plant systems are based on RCS flow assumptions that are more conservative than the currently proposed TDF values.
The Commission has provided standards for determining whether a signiftcant hazards consideration exists as stated in 10 CFR 50.92. Under the Cormission's regulations, this means that operation of the facility in acccrdance with the
-proposed amendment would not (1) involve a significant increoso in the probability or consequences of an accident previously evaluated; or (2) create the possib111ty of a new or different kind of accident f rom any accident previously evaluated; or (s) 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 reduction in TDF and the t.C0 value do not involve a significant increase in the probability or consequences of an accident previously evaluated.
An assumed lower TDF value for the accident analyses will not cause acceptance criterit. to be exceeded as determined by the component and systems evaluation. Structural and functional integrity of the plant sytems
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-is maintained since design crittria are based on conservative higher RCS flow assun ptions. The reduced LCO ficw value will similarly not affect any mechanical design issues.
The results of the accioent analyses have been shown to meet all acceptance criteria at the reduced TDF value. PCS flow rate is sn initial conoition assunption to the accident an61yses but it is not 'issif an initiator for any transient.
Therefore, the probability of oc:urrence is not affected.
The radiological consequences of operat1on at 3E65 ftWt with reduced TDI have been assessed as part of VANTAGF-5 fuel program.
It was concludec' that offsite dose predictiors remain within the acceptance criteria for each of the transients affected and this evaluation bounds the conditions of operation at 3411 NWt. Therefore, the constquences of an accident previously evaluated are not increased.
2.
The decrease in TOF and the LCO flow value does not create the possibility of a new or 'different kind of accic'ent from any accident previously evaluated.
No new operating configuration is imposed as a result of the assumed or measured flow reduction.
Hence, no new failure modes or failure scenarios are being created for any plant equipment.
System and component design bases continued to be based on conservatively higher RCS flow rates. The structural and functional integrity is not_ challenged as a result of a change in the flow ulue assurrtu in the accident analyses or by 6 reduced flow measurement requirement. Therefore, the types of eccidents defined in the FSAR-(Final Safety Analysis Report) continue to represent the credible spectrum of events to be analyzed which determine safe plant opcration.
3.
The proposed change does not involve a significant reduction in the margin of safety since the accioent analyses meet all acceptance criteria ar.d the plant systems onc equipment integrity have not been adversely affected.
The NRC staff has reviewed the 11censce's analysis and, based on this review, it appears that the three standarc's ut 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendment request involves no sigrificant hazards ccnsideration.
The Commission is seekirig public comments on this proposed determinatirn.
Any conanents received within thirty (30) days after the date of publication of this notice will be considered in making any #inc1 determination.
The Connission will not normally moke a final determination unless it receives a request for a hearing.
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Ur1tten comments may be submitted by mail to the Regulatory Publications Branch, Division of freedom _ of-Inf orriation and Publications Services, Office of Administration, U.S. fluclear Regulatory Consission, Washington, DC 205ES, and thould cite the publication date and page number of this FEDEPAL REGISTER notice. Written cor.ments may also be delivcrec to Room P.223, Phillips Building, 7920 Norfolk Avenue, Bethesda, !!aryland, from 7:30 a.m. to 4: 15 p.m.
Copies of 1,ritten comnents receivec may be examinea at the NRC Public Document Room, the felman Building, 2120 L Street, NV., Washington, DC 2C555. The filing of requests for hearing and petitions for leave to intervene is discussed below.
By 3anuary 2, 1992
, the licensee may file a reauest for a hearing with respect to issuance of the amercment to the subject facility operating literse and any person whose interest may be affected by this prcceeding and who wishes to participate as a party in the prcceeding must file a written request for a hearing and a petition _for leave to intervene. Requests for a hearing and a pet 1 tion for leave to intervene shall he filed in accordance with the Commission's " Pules of Practice for ?"e:estic. Licensing Proceedings" in 10 CFR Fart 2.
Interested persons should consult a current copy of 10 CFR 2.714 uh ch is avai ab e at-t e-omm ss on s Public Document Room, the Gelman Building, i
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i 2120 L Street, NW., Washington, DC 2055: and at the local public document room located at Burke County Public Library, al? Fourth Street, Waynesboro, Georgia 30030. 'If a request for a hearing or pctition for leave to intervene is filed by'the above date, the Commission or an Atomic S6fety 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.
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As required by 10 CFp. P.714, a petittcn for lehve to intervene sh.\\11 set forth with particularity the interest of the petitioner in the proceeding.
and how that interest may be affectrd by the results of the proceeding. The petition should specifichily explair the reasons why intervention should be permitted with particular referer.ce to the following facters:
(1) the nature of the petitioner's right under the Att 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 r.ay.be entered in the proceeding on the petitioner's interest.
The petition should also identity the specific espect(s) of the subject metter of the proceeding as to which petitioner wishes te-intervene. Any per. son who hos filed a petition-for leave to intervcne or who has been admitteo as a party may amend the petition without reouesting leave of the Board up to fifteen (15) days prior to the first prehearing conferer.ce scheduled in the proceeding, but such an amended petition must satisfy the specificity requirenents described above.
Not later thar fifteen (15) ca)s prior to the first prehearing conference schedeltu in the proceeding, a petitioner shall file e supplemcht to the petition to intervene which must include a list of the contentions which are scught to be litigated in the matter. Each tuntentinn must consist of a specific statement of the issue cf law or fact to be raised or controverted.
In addition, the petitioner shell provide a brief expl6 cation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and ca which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide
references to those specific sources and cocuments of which the petitioner is aware onn on which the petitioner intendt to rely to establish those facts or exper't opinion.- Petitioner must provide sufficient information to show that a genuine cispute exists with the anplicant on a material issue of law or f6ct.
Contentions shall be linited to matters within the scope of the amendment under consideration. The contentien must be one whi;h, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirauents with respect to at least one cor,tention 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 hearir.g is requested, the Commission will make a fital determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
If the final determinatien is that the amendment request involves no sigr.ificant hazards consideration, the Commission may issue the amendment and make'it intiediately effective, notwithstanding thr request for a hearing. Any hearing held would take place after issuance of tre amendment.
If the final determination is that the amendinent couest involves a significant hazards consideration, any hearing held would take place before the issuanca of any amendment.
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Is-l Normally,-the Comission will not issue the amendment until the expiraticn of the 30-day notice period.
However, should circumstances change during the notice perloo such that failure to act in a tiraely way would result, for example, in derating or shutdown of the facility, the Comission may issue the license ornendrient tofore the expiratior of the 30-day notice period, provided %at its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State coments received.
Should the Comission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance. The Comission expects that the need to take this action will occur very inf requently.
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 Comission, Kashington, DC 20555, Attention:
Docketing and Services Franch, or may be delivered to the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where petitions are filed
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during the last ten (10) days of the notice period, it is requested that the petitiorer promptly 50 inform the Comission by a toll-free telephont call to Western Union at 1-(800) 325-6000 (in Pissouri 1-(F00) 342-6700). The Western Union operator should be given Datagram identification Pumber 3737 and the-following rressage addressed to David B. Matthews: petitioner's name and telephone number, date petition was mailed, plant name, and publication date and page number of this FEDEPAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washington, DC 20E55,_and to MR. Arthur H. Domby, Troutman, Sanders, tockerman and Ashmore, Candler Building, Suite 1400, 127 Peachtree Street, NW., Atlanta, Georgia 30303-1P10 attorney for the licensee.
.. Nontirnely filings of petitions f or leuu to intervene, amended petitions, supplentental petitions and/or requests for hearing will not be entertained ob5Ent a deterr..ir.ation by the Commission, the prestoing officer or the Atomic f afety arid Licensing Ecatc that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and2.714(d).
For further details with respect to this action, see the application for airendment dated November 12, 1991, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washingtor., DC 20555 ar.d at the local public document room located at Budke County'Public Library. A12 Fourt'n Street, Waynesborc, Georgia 30830.
Dated at Rockville, Maryland, this 26th day of November 1991.
FOR THE HUCLEAR REGl'LATORY COMMISSION L
Darl S. Inod, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation