ML20206G008
| ML20206G008 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/16/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G013 | List: |
| References | |
| NUDOCS 8811210456 | |
| Download: ML20206G008 (10) | |
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7590-01 RNJ,TEp,)LAH}_REGULATpRJY_ COMMISSION HOUSTON LIGHTING 8 POWER COMPANY DOCKET,NO. 50_-498 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATipH_DEHRylNATION_ ANp_0PPpRTU11Ty,FpR,pEARj NG TheU.S.ituelearRegulatoryCotwission(theCoceission)isconsidering issuance of an an ndrent to facility Operating License i;o. NPF-76, issued to Houston Lighting A Power Company (the licensee), for operation of the South Texas Project, Unit 1, located in t4atagorda County, TeFas.
The proposed amendment wou N revise the Unit 1 Technical Specifications l
2 (TS) to the Conbined Technical Specifications for Units 1 and 2, add placing the positive displacement purp in a lock-out condition during cold overpressur-ization, add a reactor coolant punp seal isolation charging header pressurt interlock and modify the ada:inistrative section of the Technical Specifications.
Each of these are addressed separately below.
Before issuance of the proposed licen;e amendoent, the Comission will i
t have made findings required by the Atomic Energy Act of 1954, as ariended (the Act) and the Cornission's regulations.
The Cornission has e6ade a proposed determination that the request for amendrent involves no significant hazards t.onsideration. Under the Comission's i
regulations in 10 CFR 50.9?, this means that operation of the facility in l
accordance with the proposed amendment would not (1) involve a significant i
l increase in the probability or consequences of an accident previously evaluated.
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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 6 mrgin of safety.
TheSouthTexasProjectElectricGeneratingStation(STPEGS) Unit 1 I
operating license includes the Technical specifications for the optration of Unit 1.
At the time Unit 2 receives an operating license, Houston Lighting &
f PowerCompany(CP)willreceiveTechnicalSpecificationsthatareapplicable for tcth units.,1.e., Combined Technical Specifications. To implement the l
Corbined Technical Specificationt cr Unit 1, the Unit 1 license requires 4
administrative change 3.
2 The Centnission has provided guidance for the application of criteria fcr l
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io significant hazards consideration deternination by providing examples of acendeents that are considered not likely to involve significant hozards j
censiderations ($1 FR 775,). These exarples include exanple (1), A purtly administrative change tr technical specifications:
for exar.ple, a change to i
achieve consistency thecughcut the technical specifications, correction of an error or a change 1. nerenclature.
The changes asscciated with the section of the proposed agendrent for the Combined Technical Specifications are administrative in nature and, therefore, are within the scope of the exarple. Since this section of the amendrent involves changes that are encorpassed by an example for which no significant hazards consideration exists, the staff has m de a proposed determination that this section of the amndrent involves no significant hazards consideration.
The section of the proposed anendnent regarding the positive displacer.ent pump (PDP) adds to the Technical Specifications the placenent of the positive
displacement punp in a lock-out coridition before reaching a cold overpressure mitigation system activation condition. The proposed change would irplen!ent the lock-out as a sarveillance in the overpressure protection systen.
The Houston Lighting & Power Company reviewed the proposed change and determined, and the staff agrees that:
1)
This section of the proposed amenament does not involve a significant increase in the probability or conser,uences of an accident previously evaluated.
No hardware changes or rethods of operation are altered as a result of the acendment. The actual PCP lock-out provisicrs are already addressed in plant operatir,g precedures.
This change elevates the PCP lock-out to the sate status as the other affected purps (i.e., charging and high head safety injection).
7)
This section of the proposed arendrent does sat create the possibility cf a new or different kind of accident frem any accident previously evaluated.
This charge fornalizes, in the Technical Specifications, operational requirerents already in:pler ented by the plant.
In addition, no hardware changes are involved with this change.
3)
This sect'on of the proposed scendr.ent does not involve a significant reduction in the nargin of safety.
No changes to the plant from a hardware or operational standpoint are made as a result of this change. The proposed I
technical specification requirement (the locking-out of the PDP) is already included in plant operating procedures. Since the proposed specifications add additional surveillance requirerents to verify that the PDP is locked-out, ell a.argins of safety are maintained.
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f The section of the prcposed ainendment regarding the reactor coolant purp seal isolation proposes to incorporate the reactor coolant purp seal isolation charging header pressure interlock into the Technical Specifications by specifically addressing operability and surveillance requiresients for the ch,rging header pressure interlock #**cuit.
The interlock circuit provides a tr.ip signal if 9e charging header pressure is low. The proposed change incorporates the' survr:111ance requirements in the appropriate tables.
The Houston Lighting & Power Ccrpany reviewed the prcposed change and i
determitied, and the staff agrees that:
l 1)
This section of the proposed arendcent does not involve a significant l
increase in the probability or consequences of an accident previously i
evaluated, tlo hardware chcoges are required es a result cf this change.
The proposed arendrnent will provide the contair.cer.t isolation function associated with this inter 1cck with the same technical specification status 'as other containinent isolatten functions.
2)
This section of the preposed arendoent does not create the possibility of a new or different kind of accident frora any ac':ident previously evaluated.
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!!o hardware changes are rade which would create any new failure or accident I
J sequences. Conditions could exist wherein the plant was in the proposed t
action staterent and a sporious er actus1 Phase T isolation could occur.
The STPEG5 Er.ergency Operating Procedures (EOP's) address this scenario adequately f
in that continued operation of the reactor coolant purps is not allowed if seal l
injection flow is lost and Component Cooling Water flow is not available to the l
RCP therr.a1 barrier. The E0P's also provide guidance to the operators to i
atterpt to restore seal injection as soon as possible.
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. 3)
This section of the proposed arendenent does not involve a significant redu: tion in the siargin of safety. The proposed changes include the Seal Injection Isolation Yalve Interlock function in the Technical Specificatiens to clarify plant response to a failure of this circuit. There is no change in the margin of safety. The proposed action statenent maintains plant conditions which satisfy safety analysis assurptions and allows for an orderly response to an inoperable circuit.
The Houston Lighting & Power Conpany proposed four changes to the adtninis-trative sectior, of the Technical Specifications. The first change involves the corposition cf the Plant Operations Feview Comittee. The change requires that if the Technical Services t'anager dets not. neet the qualifications of a Fadiation Protectior. Fanager, the comittee will be augrented by a mer.ber who reets the qualifications. The second change further defines the quorum, requirements for the Nuclear Safety Review Ecard by indicating that a majority of the board rerbers rest te present for a quorum to exist. The third change specifies the*
r.inirun, approval authority for plant procedures. For procedures other than station adatinistrative procedures, the Plant l'anager, Plant Superintendeat or other responsible departcent head will approve procedures prior to implecentation.
The fourth change specifies that procedures will be reviewed periodically.
The Comissicn has provided guidance for the application of criteria for no significant hazards consideration deters:ination by providing examples of amendments that are considered not likely to involve significant hazards considerations (51 FR 7751), these exarples include exar.ple (1), A purely adriinistrative change to technical specifications:
a change to achieve consistency throughcut the technical specifications, correction of an errer, or e change in norenclature.
The changes associated with this section of the amendrent are administratSt in nature and, therefore ore 'ithin the scope of the example. Since the application for this section of the atendment involves changes that are er.com-passed by an example for which no significent hazards consideration exists, the staff has r4de a proposed determination that this section of the arendrent involves no significant hazards consideratior..
The staff has reviewed the proposed arendrent and the licensee's no significant hazards consideration determination. Based on the review of the proposed areas of change and the above discussions, the staff proposes to i
I determine that the proposed arendment does not involve a significant hazards t
consideration.
The Comission is seeking public coments on this proposed determination.
Any corrents received within 30 dsys after the date of publication of this notice will be considered in making any final determination. The Comission
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will not normally make a final determination unless it rectives a request for a hearing.
Corrents should be addressed to the Rules and Procedures Eranch, Divisien of Rules and Records, Office of Ada.inistration U.S. Nuclear Regulatory r
Comission Washington, D.C.
20555, and should cite the publication date and i
page number of this FEDERAL REGISTER notice.
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By December 22, 1988 the licensee r.ay file a request ft,r a hearing
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with respect to issuance of the ar.endrent to the subject facil$ty operating i
license, and any person whose interest may be affected by thi proceeding and i
who wishes to participate as a party in the proceeding must file a written j
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petition for leave to intervene. Request for a hearing and petitions for l
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s leave to intervene must be filed in accordance with the Corsnission'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 Con.ission or an Atomic Safety and Licensing Board Panel will rule on the request and/or petitiori, and the Sveretery or the designated Atocic 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 must set forth with particularity the interest of the petiticr.er in the proceeding, or:d j
how that interest may be affected by the results cf the proceeding. The petition should specifically expiair the reasons why intervention should be permitted with particular reference to the following factors:
(1)thenature of the petitioner's right under the Act to be rnade a party to the proceedirig; l
l (2) the nature and extent of the petitioner's property, finarcial, or other interest in the proceeding; and (3) the possible effect of any order which ray be er,ttred in the proceediq cn the petitiorier's interest. The petittor.
shculd also identify the spe:cific aspect (s) of the subject matter of the proceeding as to which the petitiorer wishes to intervene. Any person who has I
filed a petition for leave to intervene or who has been adef',ted as a party l
ray ar<nd the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearir,g conference scheduled in the proceeding, but such an arended petition s.ust satisfy the specificity requirements described
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above.
Not later than fif teen (15) days prior to the fir;t prehearing conference I
scheduled in the proceeding, the petitioner shall file a supplecent to the
8-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 matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfies these requirerents with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene becoce parties to the proceeding, subject to any limitations.in the order granting leave to intervene, and have the opportunity tc participate fully in the conduct of the hearing, including the opportunity te present evidesite and cross-examine witnesses.
If a hearing is requested, the Corr.iissien will s.ake a final deterrination on the issue cf no significant hazards consideration. The final daterednation will serve to decide when the iearing is held.
If the final deterednation is that the request for acendcent inycives no l
significant hazards censideration, the Cordssicn ray issue the atendr4nt ar.d sake it effective, netwithstanding the request for a hearing. Any hearing held wculd take place after is.suance of the arendrent.
!!orrally, the Corvrissicn will r,ct issue the amendment until the espiration of the 30 day notice period. However, should circumstances change during the notice such that failure to act in a tirely wsy world result, for exerple, in derating or shutdown of the facility, the Coreission r.4y issue the license acendrent before the expiration of the 30-day notice period, provided that its final determination is that the amendrent involves no significant hazards consideration. The final determination will consider all public and state corrents received. Should the Consiissicn take this action, it will
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-9 publish a notice of issuance and provide for opportunity for a hearing after issuance. The Comission expects that the rieed to tale this action will occur vtry infrequently.
A request for a hearing or a petition for leave to intervene r,ust be filed with the Secretary of the Concission, U.S. i;uclear Regulatory Comission, Washington, D.C.
20555, Attentior : Docketing and Service Eranch, or r.ay be delivered to the Co6.ssion's Foblic Docur>ent Roor.,1717 H Street.
fl.W., Pash ugton D.C., by the above date. Where petitions ere filed during the last ten (10) deys of the r.otice pericd, it is requested that the petitioner prorptly so infort. the Comission by a toll-free telephone call to Western L'nion at (800) 325-6000 (in l'issouri (P00) 342-6700). The Westerr Unicn operator shculd be given Datagram Identification Nunber 3737 ar.e the follcwing ressage addressed to Jose A. Calvo: petitiermr's nace ar.d telephone r.urber; date petition was cailed; plant nare; and publicatier, date and page nunter of this FEDERAL FEGISTER notice. A copy of the petition shculd also be 1
sent to the Office of the General Counsel-Rockvillt U.S. Nuclear Fegulatory Comission, Washington, D.C.
20555, ar4 to Jack R. i;ewran, Esq., Newean &
Poltzinger, P.C., 1615 L Street,fi.W., Washington, D.C.
20036, atturney for the licensee, i: entirely filings of petitions for leave to intervene, arended petitions, supplerental petitions and/or requests for hearing will not be entertained absent a determination by the Comission, the presiding officer or the presiding Atcric Safety and Licensing Board, that the request should be granted based upon a balancing of the factors specified in 10 CFR 2.714 (a)'t)(1)-(v)and2.714(d).
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For further details with respect to this action, see the application for amendment which is available for public inspection at the Cossiission's Public Document Room, 2120 L Street N.W., Washington, D.C. 20555, and at the Wharton
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Junior College Library, J. M. Hodges Learning Center, 911 Boling Highway, Wharton, Texas 77488 and Austin Public Library, 810 Guadalupe Street, Austin, Texas 78701.
Dated at Rockville, Faryland, this 16th day of Ncvember,1988.
FOR THE NUCLEAR REGULATORY COPr15$10h t
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Uose A. Calvo, Director i
Project Directorate - IV Civisien of Peactor Projects - !!!,
1Y, V and Special Projects Office of Nuclear Reactor Regulation l
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