ML20011D494
| ML20011D494 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/14/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011D495 | List: |
| References | |
| NUDOCS 8912270323 | |
| Download: ML20011D494 (12) | |
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,j UNITED STATES 3
g NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D. C 20666 5
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i LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-38 1.
The huclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Louisiana Power'and Light Company (the licensee) dated July 1, 1988 as supplemented by letter dated' August 15, 1989, complies with_the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR-Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendraent can be conducted without endangering the health.
and safety of the public, and (ii) that. such activities will be l
conducted in compliance with the Commission's regulations; L
D.
The issuance of this amendn.ent will nct be inimical to the conron defense and security or to the health and safety? of the public; and L
E.
The issuance of this amendment is in accordance with 10 CFR' l
Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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LOUIS 1ANA p0WER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-38 1.
The kuclear Fegulatory Commission (the Comission) has found that:
A.
The application for amendment by Louisiana Power and Light Company (the licensee) dated July 1, 1988 as supplemented by letter dateo August 15, 1989, complies with the standards and requirementt of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, i
the provisions cf the Act, anc the rules and regulatier.s of the Commission;
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C.
There is reasonable assurance (1) that the activities authorized by this amencr.ent can be conducted without endangering the health and safety of the public, and (ii) that such activitics will be conducted in compliance with the Comission's regulations; D.
'be issuance of this pendnent will nct be inimical to the l
conron defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable i
requirements have been satisfied.
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8912270323 891214 PDR ADOCK 05000382 P
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2.
Accordingly, the literse is anenced by charges to the License Conditions as indicated in the attacho;ent to this license amendment.
3.
This license amendnent is effective as of its date of issuance. The license conditions are effective within 180 days of the date of issuence and upon the official transfer of respcnsibilities between the Louisiana Power & Light Company and Entergy Operations, Inc.
FOR THE NUCLEAR REGULATORY COMMISSION l
7).c. b!
^ ') fr.!b.~
l Frederick J. Hebden, Director Project Directorate IV Division of Reactor Projects. III,
!Y, V and Special Prcjects Office of Nucleer Reactor Regulation
Attachment:
Changes to ttt License Ccnditicns Date of Issuance: December 14, 1989
ATTACHMENT TO LICENSE AMEt<DMElli NO. 60 Tb FACILITY OPERATING LICENSE NO. NPF.38 DOCKET NO. 50-382 Peplace the following pages of the License with the attached pages. The revised pages contain vertical lines indicating the areas of change.
Remove Insf.rt Pages 1 thru 8 Pages 1 thru 8
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.,k UNITED STATES
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NUCLE AR REGULATORY COMMISSION J
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LOUISIANA POWER AND LIGHT COMPANY l
ENTERGY OPERATIONS. INC.
i DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION UNIT 3 FACILITY OPERATING LICENSE License No. NPF-38 Amendment No. 60 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
l A.
The application for license filed by the Louisiana Power and Light i
Company (LP&L) complies with the standards and requirements of the l
Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Waterford Steam Electric Station, Unit 3 l
(facility), has been substantially completed in conformity with Construction Permit No. CPPR-103 and the application as amended, the provisions of the Act, and re,;;1ations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Sections 1.I. and 2.D.below);
D.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forthin10CFRChapterI(exceptasexemptedfromcompliancein Sections 1.1 and 2.D below);
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2 E.
Entergy Operations Inc.(E01)# is technically qualified to engage in the activities authorized by thu operating license in accordance with the Comission's regulations set forth in 10 CFP, Chapter I; F.
LP&L has satisfied the applicable provisions of 10 CFR Part 140, l
" Financial Protection Requirements and Indemnity Agreements", of the Comission's regulations; G.
The issuance of this license will net be inimical to the comon defense and security or to the health and safety of the public; H.
After weighting the environmental, economic, technical, and other benefits of the facility against environmental and other costs, and after considering available alternatives, the issuance of the facility Operating License No. NPF-38, subject to the conditions for protectiot, of the environment set forth in the Environnental Protecticr. Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requiren,ents have been satisfied; and 1.
The receipt, possession, and use of source, byproduct, and special nuclear materiel as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40 and 70, except that an exemption to the provisions of 10 CFR 70.24 is granted as described in Supplement No. 8 to the Safety Evaluation Report. Thisexemptionisauthorizedunder10CFR70.24(d)andwill not endanger life or property or the comon defense and security and is otherwise in the public interest.
2.
Pursuant to approval by the Nuclear Regulatory Comission at a meeting on March 15, 1985, the license for fuel loading and icw power testing, License No. NPF-26, issued on December 18, 1984, is superseded by facility Operatirg License No. NPF-38 hereby issued to the Louisiana Power and Light Company and Entergy Operations, Inc., to read as follows:
A.
This license applies to the Waterford Steam Electric Station, Unit 3, a pressurized water reactor and associated equipnent (the facility),
owned by Louisiana Power and Light Company. The facility is located on LP&L's site in St. Charles Parish, Louisiana and is described in the Louisiana Power and Light Company Final Safety Analysis Report as amended, and the Environmental Report as amended.
3 B.
Subject to the conditions and requirer.ents incorporated herein, the Comission hereby licenses:
1.
LP&L, pursuant to Section 103 of the Act and 10 CFR Part 50, to l
possess but not operate the facility at the designated location in St. Charles Parish, Louisiana in accordance with the procedures ar.d limitations set forth in this license; 2.
E01, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in St. Charles Parish, Louisiana in accordance with the procedures anc limitations set forth in this license; 3.
E01, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time at the facility site and as designated solely for the facility, special nuclear material as reactor fuel, in accordance with the limitations for storagt and atounts required for reactor operation, as described in the Finel Safety Analysis Report, as supplemented and amended.
4.
E01, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to l
receive, possess, and use at any time any byproduct source and specialr.uclearmaterialassealedneutronsourcesforreactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibretion, and as fission detectors in amounts as required; 5.
E01, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to l
receive, possess and use in amounts as required any byproduct, sourceorspecialnuclearmaterialwithoutrestrictionto chernical or physical form, for sample analysis or instrument calibretion or associated with radioactive apparatus or components; and EDI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, lear l
6.
to possess, but not separate, such byproduct and special nuc materials as may be produced by the operation of the facility authorized herein.
7.
(a) LP&L, to transfer any portion of its 1001 undivided l
ownership interest (up to and inclusive of $515 million of aggregateappraisedvalue)inthefacilitytoequity investors, and at the same. time lease back from such equity investors, such intereste sold in the facility and receive from such equity investors, consistent with LP&L's leases, the right to use and enjoy the benefits of the undivided ownership interests sold in the facility. The terms of the leases are for approximately 271 years subject to right of renewal.
Such sale and leaseback transactions are subject to the condition that the equity investors and anyone else
' who tray acquire an interest under this transaction (s) are prchibited from exercising directly or indirectly any control over (1) the facility, (ii) power or energy produced by the facility, or (iii) the licensee of the facility.
i Further, any rights acquired under this euthorization n.ay i
be exercised only in compliance with and subject to the requirements and restrictions of this operating license, ForpurposesofthisconditIon,dtheNRC's the Atomic Energy Act of 1954, as amended an the limitations regulations.
of 10 CFR 50.81, as now in effect and as they may be i
subsequently amended, are fully appliceble to the equity investors and any successors in interest to the equity 1
investors, as long as the license for the facility remains i
in effect.
(b) LP&L, (or its designee) to notify the NRC in writing prior l-tc any change in (1) the terms or conditicos of any lease i
egreer.ents executed as part of the abcve authorized i
financial transactions, (ii) any facility operatirs agreer+nt involving a licensee that is in effect now or will be in effect in the future, or (iii) the existing i
property insurance coverages for the facility, that would materially titer the representations and ccnditions, set forth in the staff's Sefety Evaluation enclosed to the 110 letter dated September 18, 1589.
In addition, LP&L or its desigree is required to notify the NF.C of any action by tquity investors or successcrs in interest to LFI,L that r.ay have an effect on the operation of the facility.
C.
1his license shell be deemed to contain ard is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I end is subject tc all applicable provisions of the Act and to the rules, rtgulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
l I
1.
Maximum power Level
~
E01 is authorized to operate the facility at reactor core power l
levelsnotinexcessof3390-megaw6ttsthermal(100% power)in i
l accordance with the conditions specified herein and in Attachnent I to this license. The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby-l incorporated into this license.
o E.
Techni_ca,1_ Specifications _and Environmental Protection Plan t
l The Technical Specifications contained in Appendix A, as revised through Amendnent lio. 58, end the Environr ental Protection Flan a
ccntained in Appendix 6, are herEby incorporated in the license.
E01 shall operate the facility in accordance with the Technical
]
Specifications anc the Environrental Protection Flen.
5 3.
@titrustConditions a.
LP&L shall comply with the antitrust license conditions in Appendix C to this license.
b.
LP&L is responsible and accountable for the actions of its agents to the extent said agent's actions contravene the antitrust license conditions in Appendix C to this license.
4 Broad Rance Toxic Gas Detectors JSect_ ion 2.2.1 SSER 6*)
Prior to startup following the first refueling outage, the licensee +
shall propose technical specifications for the Broad Range Toxic Gas De'*ction System for inclusion in Appendix A to this license.
5.
InitialinserviceInspectionProprg,(Section6.6,$5ER5}
3 By June 1, 1985, the licensee must submit an initial inservice inspection program for staff review and approval.
6.
Environmenta1Jualification_jsection 3.11. SSER 8)
PriortoNovember30,lequIpmentaccordingtotheprovisionsof 1985 the licensee shall environmentally qualify all electrica 10 CFR 50.49.
7.
gialFue1J,rowth(Section12,SSER5}
PriortoenteringStartup(Mode 2)aftereachrefueling,the licensee shall either provide a report that demonstrates that the existing fuel element assemblies (FEA) have sufficient available thculder gap clearance for at least the next cycle of operation, or identify to the NRC and implement a modified FEA design that has adequate shoulder gap clearance for at least the next cycle of operation. This requirement will apply until the NRC concurs that the shoulder gap clearance provided is adequate for the design life of the fuel.
"The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
- The license originally authorized LP&L to possess, use and operate the facility.
Consequently, certain historical references applicable to LP&L as the Licensee" appear in these license conditions.
i>
. 0-
.Eymergep,cy,, Prepare,d,n,ess,,(Sec,t,1,on 13.3, SSER 8)
In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Energency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2)willapply.
9.
FireProtection(Section9.5.1.$$ER8)
E01shallimplementandniaintainineffectallprovisionsofthe l
approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment 36 and as approved in the SER through Supplerrent 9, subject to the following provision:
E01 may make changes to the approved fire protection prograh withcut prior approsal of the Commission enly if those changes veuld not adversely aff(ct the ability to achieve and n.aintain sefe shutdeun in the event of a fire.
10.
Fost-Fuel,,L,oad,ing, Initial Test Program 1Section 14,,, SSE.R )0)
Any char.ges to the Initici Test Progran. described in Section 14 of the FSAR made in accordance with the provisiors cf 10 CFR SC 59 thallbereportedinaccordancewith50.59(b)withinonemonthof such change.
11.
Eme rc e n_cy, Re sp_on s,e,,C apa b,i,1,1,t.i e s_,(S e c t i on 22,,,5,S,E,R, p)
E01 shall comply with the requirements of Supplement 1 to NUREG-0737 for the conduct of a Detailed Control Room Desian Review (DCRDR). Prior to May 1, 1985, the licensee shall submit for staff review and approval the DCRDR Sunnary Report, including a description of the process used in carrying out the function and task analysis performed as a part of both the DCRDR and the Procedures Generation Package efforts.
- 12. Reactor Coolant _ System (RCS),p.epressuri atio_n_ Cap,ab,1,1,1,ty,,(Se,c_tio_n A
5.4.3,SS11fF)
By June 18,1985, the licensee shall submit the results of confirmatory tests regarding the depressurization capability of the auxiliary pressurizer spray (APS) system.. This inferr..ation must demonstrate that the APS system con perform the necessary depressurization to meet the steam generattfr single-tube rupture accident acceptance criteria (SRP 15.6.3) with loop charging isoleticn valve feiled cpen. Should the test results fail to cotonstrate that the ecceptance criteria are tret, the licensee must provide fer staff review and approval, festification for interim cperation, and a schecule for corrective acticns.
I
l
! l t
Re,sppnse,,tpSalemATysEvent(Section7.2.9.SSER8) 13.
e The licensee shall subn.it responses and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in the licensee's letter of May 30, 1984 I
14 Fuel Moveu:nt in the Fuel Handling Building In the fuel handling building, during Modes 1-5, no more than one fuel assenbly shall be outside an approved shipping container, an a?provedstcragerack,thefueltransfertube(inc.udingupender),
tie fuel elevator, or the spent fuel handling machine.
I In addition to the above fuel assembly inspection / reconstitution n.ay take place outside of an approved storage rack, when required, provided that the inspection / reconstitution area is bc, rated to a itAc1 et or above 1720 ppm 1E. Oualification of Personr;ti(Section_13,1.3. SSER 8)
E01 shell have on each shift operators who meet the requirements l
described in Attac' ment 2.
Attachtnent 2 is htreby incorporated inte this lict:-nse.
l If. OperationalQAEnhancementProg,rE(,55,E.R,9) l The items listed below shc11 be completed on the scheduled indicated, a.
Prior to completion of Phase III of the Waterford 3 startup test progran., the licensee shall conduct a corprehensive audit of the Operational QA Progran that will itclude a sumary QA document of the Operational QA Program, the definition of responsibilitie3 and interfaces, and guidance on the location of information cn QA natters at all levels of concern, b.
Prior to completion of Phase III of the Waterford 3-startup test program, the licensee shall supplement its existing QA training program to incorporate specific discussion of QA problems experienced during construction and how this experience applies to operational activities.
c.
Prior to completion of Phase III of the Waterford 3 startup test program, the licensee shall address each of the reconriendationsintheTaskForceSupportGroup(TFSG) Limited Scope Audit Report of LP&L Operational Quality Assurance Procram, dated Decenber 4,1984.
8 d.
Prior to completion of Phase !!! of the Waterford 3 startup test program, the licensee shall complete corrective actions related to the 23 NRC issues as identified in the LP&L responses.
- 17. Basemat The licensee shall comply with its connitments to perforn a basemat cracking surveillance program and additional confirmatory analyses of basen;at structural strength as described in its letter of February 25,1985. Arty significant change to this prograrr shall be reviewed and approved by the NRC staff prior to its irnplementation.
D.
The facility requires an exer.ption from certain requirernents of A>rtndices E and J to 10 CFR Part 50.
These exemptions are described in t,e Office of Nucitar Reactor Regulation's safety Evaluation Report, Supplement No.10 (Section 6.1.2) and Supplement No. 8 (Section 6.2.6),
respectively.
These ex mptions are authorized by law and will not codanger life or property or the concon defense end security and are ctherwise in the public interest. These exmptions are, therefore, hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in confort.ity with the application, as amended, the previsiers of the Act, and the rules and regulations of the Corroission.
E.
E01 shall fully implement and maintain in effect all previsions of the l
ConTeission-approved physical security, cuard training and qualification, and safeguards contingency plans including anendments m6de pursuant to provisions o' the Miscellarcous At.endments and Search R(quiren.tnts revisiur.s to 10 CFR 73.55 (5) FP. 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFP 73.21, are entitled:
- Waterford Physical Security Plan," with raisient subnitted through March 21, 1988; "Waterford Security Training and Qualification Plan," with revisions sbbt.itted through December 16, 1983; and "Waterford Safeguards Centingency Plan " with revisions submitted through January 6,1987.
Changes tede in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
Except as otherwise provided in the Technical Specifications or the Environmental Protection Plan, E01 shall report any violations of the l
requirements contained in Section 2.0 of this license in the following manner.
Initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10CFR50.73(b),(c)and(e).
G.
LP&L shall have and maintain financial protecticn of such type ar.c' in l
such an. cunts as the Convuissicn shall require in accordance with Scction 170 of the Atomic Energy Act of 1954, as amended, to cover public liatility claims.
l
ATTACHMENT 2 Waterford Steam Electric Station Operating License NPT-38 Operatine Staff Experience Requirements er E01 shall have a licensed senior operator on each shift who has had at least l
six months of hot operating experience on a pressurized water reactor, including at least six weeks at power levels greater than 20% of full power, and who has had startup and shutdown experience.
For those shifts where such an individual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility.
Use of advisors who were licensed only at the R0 level will be evaluated on a case-by-case basis. Advisors shall be trained on plant procedures, technical specifications and plant systems, and shall be examined on these topics at a level sufficient to assure familiarity with the plant.
For each shift, the remainder of the shift crew shall be trained in the role of the advisors.
Advisors, or fully trained and qualified replacements, shall be retained until the experience levels identified in the first sentence above have been achieved. The names of any replacement advisors shall be certified by E01 l
prior to these individuals being placed on shift.
The NRC shall be notified at least 30 days prior to the date E01 proposes to release the advisors from l
further service.
.