ML19250D617
| ML19250D617 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/06/1981 |
| From: | Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Bradford P, Gilinsky V, Hendrie J NRC COMMISSION (OCM) |
| Shared Package | |
| ML19250D618 | List: |
| References | |
| REF-10CFR9.7 NUDOCS 8103170693 | |
| Download: ML19250D617 (22) | |
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Lillier J. Dirci 3, Executive f.irecter f or Operatiens fl'I J E CT :
C0!:SII EEATIO!! ( F Fl!LL KFER f f E0ATIt:0 LICEl'SE FCF FAFLEY L:f:IT ?
The staff has corpleted its review of the Jesoph I. Ferley t.uclear Flent l' nit ? for isseence of a full Freer license. Ti r rirnt is evned by the Alat ara f ewer Corrany end is located near Pott en (Frusten Courty), /lettre.
TFe rirnt is the second of r tuc-Unit facility censistinc of two FLP rients designed t'y restinctouse fer croretier et 26E2 t';(1) and FTP t't!(e). 1 nit 1 krs licensed for creration en June Pf,1977. Unit P was licensed for r rercrnt rcoer en Octcher 23, 1900.
Our review cf l' nit 2 is docurerted in tFe crclosed FE0 Surrierent r and the draf t license end Tectnical Specifications.
Le will to Prcrared to reet with the Ecrrissier en tFe creratinr license for Farley Unit 2 on l' arch 11,19f1.
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rercort retor er (>cteFrr 23, lorr, for review cf Unit 2 is recurerter in tre crcler.rd TEF !nprir-trt r and tFe cref t licente end Tectricel Sr+cf fiertiers.
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,g UNITED STATES
[,j, r, j NUCLE AR REGULATORY COMMISSION M
C W ASHINGTON, D. C. 20555 t
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MEMORANDUM FCiR: Chairman Hendrie Commissioner Gilinsky Commissioner Bradford Commissioner Ahearne FROM:
William J. Dircks, Executive Director for Operations
SUBJECT:
CONSIDERATION OF FULL POWER OPERATING LICENSE FOR FARLEY UNIT 2 The staff has completed its review of the Joseph M. Farley W clear Plant Unit 2 for issuance of a full power license. The plant is owned by the Alabama Power Company and is located nea,- Dothan (Houston County), Alabama.
The plant is the second of a two-unit facility consisting of two PWR plants designed by Westinghouse for operation at 2652 MW(t) and 829 MW(e). Unit I was licensed for operation on June 25, 1977. Unit 2 was licensed for 5 percent power on October 23, 1980.
Our review of Unit 2 is documented in the enclosed SER Supplement 5 and the draf t license and Technical Specifications.
We will be prcpared to meet with the Commission on the operating license for Farley Unit 2 en March 11, 1981.
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a William J. Dircks Executive Director for Operations
Enclosures:
As Stated cc: SECY OGC OPE
- g. a t:y~'e UNITED STATES i
NUCLEAR REGULATORY COMMISSION O g)\\ " j' c
i W ASHINGTON, D. C. 20555 e
c Docket No. 50-363 t'r. F. L Cl ayten, Jr.
Senior Vice President Alabara Power Corpany Post Office Ecx 2641 Birmingham, Alabara 35291
Dear Mr. Clayton:
SUBJECT:
JOSEPH M. FARLEY NUCLEAP PLANT, UNIT 2 - ISSUANCE OF FACILITY CPEPATING LICENSE The Nuclear Regulatory Ccnrission has issued the enciesed Facility Operating License No. NPF-9 to the Alabama Perer Company for the Joseph M. Farief Nuclear "iant, Unit 2, located in Houston County, Alabara. Facility Operating License NPF-8 authorizes operation of the Joseph M. Farley Nuclear Plant, Unit 2, at 100 percent power (2652 regawatts therral) upcn cocpletien of certain related construction items.
Also enclosed is a copy of the staff's safety evaluation rescrt sacporting this actien, NUF,EG-Cll7, and a copy of the notice which has been ferwarded to the Office of the Federal Pepister fcr publication.
Sincerely, D. G. Eisenhr.t, Director Civision of.icensinc Office of Nsclear Reactor Regulatien
Enclosures:
1.
Facility Crerating License No. NPF-8 2.
NUREG-0117, Safety Evaluation Pecert Supplerent No. 5 3.
Feceral Pegister notice cc w/ enclosures:
See rext page
ja arc f,
UNITED STATES E ' g #, y
^n NUCLEAR RFGULATORY COMMISSION W ASHINGTON. D. C. 20555 s,
ALABAMA PCFER C0hPALY D0C.'ET NO. 50-364 JOSEPH ft. FARLEY NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for licenses filed by the Alabama Power Corpany cc' plies with the standards and requirerents of the Atoric Energy Act of 1954, as amended (the Act), and the Corrission's ref;ulations set forth in 10 CFR Chapter I, and all reouired notifications ta other agencies or bodies have been duly r de; B.
Construction of the Jose'h M. Farley Nu-lear Plant, Unit 2 (the Facility), has been substantially completed in conforrity with Construction Permit No. CPPR-86 and the application, as amended, the provisions of the Act and the regulations of the Corr'ission; C.
The faci sity will operate in conformity with the application, as anended, the provisions of the Act, and the regulations of the Corr,i ssion; D.
There is reasonable assurance: (i) that the activities authorized by this license can be conducted without endangering the health and safety ct the public, and (ii) that such activities will be conducted in corpliance with the Commission's regulations set forth in 10 CFR Chapter I; E.
'The Alabara Power Company is technically and financially qualified to engage in the activities authorized by this license in accordance with the Cor:nission's regulations set forth in 10 CFR Chapter I; F.
The Alabama Power Company has satisified the applicable provisions of 10 CFR Part 140, Financial Protection Requirements and Indemnity Agreerents", of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, econcric, technical, and other benefits of the f acility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-8, subject to the conditions for pe-tection of the environment set forth in the Environrental Protection Plan which is Appendix B to this license, is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirerents have been satisfied; and I.
The receipt, possession, and use of scurce, byproduct and seecial nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, a0 and 70.
2.
Pursuant to approval by the Nuclear Regulatory Cornission at a meeting en
, the License for Fuel Leading and Lcw Power Testing, NPF-8, issued on October 23,19E0, as arended, is superseded by Facility Operating License NFF-8 which is hereby issued to the Alabara PJwer Ccrpany (the licensee) to read as follows:
A.
This license applies to the Jcseph P. F'eley Nuclear Plant, Unit 2, a pressurized water nuclear reactor and associated ecuipment (the facility),
own.td by the Alabama Pcwer Corpany. The facility is located in Hcuston County, Alabera, and is described in the licensee's " Final Safety Analysis Report," as supolerented and arended, and in the licensee's Envirenrental Report, as supplemented and arended.
B.
Subject to the ccnditicns and recuirements incorperated herein, the Conrission hereby licenses the Alabara Pcwer Ccrpany:
(1) Pursuant to Secticn 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Houston County, Alabara, in accordance with the limitatiens set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, cessess and use at eny tire special nuclear material as reactor ? vel, in accordance with thc 'iritaticns for stcrage and amounts recuired for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, pcssess, and use at any tire any byproduct, source and special nuclear material as sealed neutron sources for reactor startue, sealed sources for reactor instrurentation and radiation monitcring equiprent calibration, and as fission detectors in amounts as recuired.
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or arsociated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Comm4 scion's regulations set forth in 10 CFR Chapter I and is subject to all cpplicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximun Power Level Alabama Power Company is authorized to operate the facility at reactor core power levels not in excess of 265? megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B attached hereto are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Initial Test Program The licensee shall conduct the initial test progran (set forth in Section 14 of the licensee's Final Safety Analysis Report as amended) without making any modifications to this program unless such modifications are in accordance with the provisions of 10 CFR Section 50.59.
In addition, the licensee shall not make any major modifications to this program unless the modifications have been identified and have received prior NRC approval. Major modifications are defined as:
a.
Elimination of any test identified as essential in Section la of the licensee's Final Safety Analysis Report, as arended; b.
Modification of test objectives, methods or acceptance criteria for any test identified as essential in Section 14 of the licensee's Final Safety Analysis Report, as amended;
c.
cerforrance of any test at a pcmer level cifferent from tre level in the described prograr; and d.
Failure to corplete any tests included in tre cescribed prograr (planned or scheduled for pcwer levels up to the autrerized sewer level.
(4) The licensee shall not use the spent fuel cask crane for tre purpcse of roving spent fuel casks prier to a;preval by the N;C of the lifting devices which attach the scent fuel cask t0 the crane.
(5) The interval for testing purps and valves in acccrdance =ith 10 CFR 50.55 a(g)(2) is 120 renths conrencing with the start of cenrercial operaticr. The licensee shall previde additicnal inforration reeded by the NEC to crrplete its detailed review of the licensee's inservice testir; regrar fer pu ps and valves no later than 6 rer:ths prior to the end cf :te first 120 ecrth interval.
(6) Fire Protecticn Fregrar Tne licensee shall raintain in effect and fully ir:lerent all previsicns of the approved fire protection plan. The a;;reved fire protecticn plan censists of the docu ent entitled "Farley Nuclear Plant Fire Prctecticn Prograr Reevaluation" which incluces:
Initial Issue, subritted with letter dated Septercer 15, 1977; Arendrent 1, subritted with letter dated February 23, 1975; Amendrent 2, subeitted with letter dated July la,1979; Arencrent 3, subritted with letter cated Cctcber 27, 1975; Ar.encrent 4, subritted with letter cated January 3,1979, and arended by letter dated Cct ber 21, 1950.
The licensee is recuired te corplete and raintain the rodificatiens identified in Tables 1, 2, and 3 of the NEC's Jeserb w. Fa rley Safety Evaluation Eepert, Fire Frctecticn Review Unit Ncs.1 and 2 transmitted to the licensee April 13,1979 (Fire Protecticn SER).
The fc110 wing three additienal issues identified in Aprer:f x R to 10 CFR Fart 50 shall be irclerented in acccrdance with the recuire-rents cf 550.4? cf 10 CFR 50.
Section III.G, Fire Protection of Safe Shutdown Capability Secticn III.J Emergency Lighting Secticn III.0, Cil Collection System for Reactor Coolant Purp.
The licensee shall perform a program of ouality decurent review as described in the letter dated October 23, 1980 and, where necessary, perform fire protection system installation inspections.
The review and installation verification inspections shall be corpleted prior to initial criticality. Discrepancies, if found, shall be resolved to the satisfaction of the NRC's Office of Inspection and Enforcement.
Administrative control changes and procedure revisions shall be irplerented and maintained in effect as described in NRC's Fire Protection SER.
(7) The licensee shall maintain in effect an emergency plan that meets:
(1) Regulatory recuiremen?e of 10 CFR 50.47(b) and Appendix E, and (ii) The operator planning standards cf NUREG-C654, "c ri te ri a fer Preparaticn and Evaluation of Radiological Prepared-ness in Support of Nuclear Power Plants," t'ovember 1980.
This plan snall provide an emergency operations facility as a base for coordinating onsite activities and an interface with State, local and Federal agencies.
No later than 90 days from the date of issuance of this license, the licensee shall report to the NRC the status of any items related to eme :ency preparedness identified by FEMA or the NRC as recuiring f_
er action.
The licensee shall coeplete its plans for prorrt notification, staffing for emergencies upgrading the meterological progran and upgrading emergency support facilit:$s on the NRC approved schedule identified in the following sections of SER Supplement 5:
Secticn 22.5, Dated Recuirements:
Item III.A.l.2 Upgrade Emergency Support Facilities Item III.A.2 Long Term Emergency Preparedness Appendix B Emergency Preparedness Evaluation Report:
Section B Ons'te Emergency Organization Section E Notification Methods and Procedures (8)
Prior to initial criticalicy the licensee shall complete to the satisfaction of the NRC's Office of Inspection and Enforcement the preoperational testing on the following systems:
liquid radiological waste, gaseous radiological waste, containment purge, auxiliary building ventilation, and the radiation monitoring systems associated with above systems.
(9) Prior to March 31, 1981, the licensee shall provide a schedule acceptable to the NRC for bringing the facility into compliance with Revision 2 of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident", dated December 1980.
(10) (a) Prior to exceeding 5 percent power, the licensee shall obtain NRC approval of the results of the following seven augmented low power tests:
natural c1rculation natural circulation with simulated loss of offsite power natural circulation with loss of pressurized heaters effect of steam generator secondary side isolation on natural circulation natural circulation at reduced pressure cooldown capability of the charging and let down system simulated loss of all onsite and offsite ac power (b) Within 60 days af ter fuel burnup is sufficient to produce meaningful results for the test of natural circulation cooldown with boron mixing, the test results shall be sub-mitted to the NRC for approval.
(11) Prior to exceeding 5 percent power, the licensee shall make fully operational the post-accident sampling system.
(12) Prior to exceeding 5 percent power, the licensee shall complete the training for mitigating core damage.
(13) The licensee shall modify procedures and, if necessary, equipment used for natural circulation cooldown as follows:
(a) Prior to exceeding 5 percent power, the licensee shall perform tests to demonstrate manual operation of an atmospheric steam dump valve.
(b) Prior to startup following the first refueling, the licensee shall upgrade the valve operators on all safety-related pcmer-
cperated relief valves (PCRYs) to meet seismic Category I concitions, based on results frc: relief valve tests teing performed by Electric Power Research Institute (EPRI).
(c) Prior to startup follo.ing tne first refueling, the licensee shall oDtain NRC approval of natural circulation coolocan procedures, based on reactor natural circulation cc01c *n test results applicatie to Farley Unit 2.
(14) Prior to exceeding 5 percent power, the licensae stall (a) modify and test reset circuits for tne c ntainment air mixing fans, containment purge isolation valves, and auxiliary fee: water purp cisenarge valves to oeet the repairements of IE Eulletin 50-06
" Engineered Safety Feature Reset Controls", and (b) revise procedures to be censistent witn tne Scdified designs required by (a).
(15) Price to May 1,1951, the licensee shall cocplete modificati ns to tne sub coling monitor system.
(16) The f acility shift canning shall be as sho.'n in Table 5.2-1 Of tne Technical Specifications. Inis table shall te in effect until tne licensee has additional licensed cperat:rs to fully meet the new recairements described in the NRC letter of July 31, 1980, but no later tnan 'iay 1,1931 without prior approval Oy the NRC.
(17) The licensee shall re-evaluate and modify, as ne:essary, safety-related masonry walls in a:: rdance ith IE Eulletin 80-11
' Masonry Wall Oesign". During tne re-evaluation if the operability of any safety-related system is judged to be in jeopardy, that system snall be declared to be inc;eraole and acticns taken as required by Technical Specifications for that inoperaDie system.
Prior to May 17, 1951, tne licensee shall provide its res; nse to IE Eulletin 50-11, including its re-evaluaticn re:crt. Prior to startup follo.ing tne first refueling, tne licensee shall ettain NRC appr: val of the structural integrity cf safety-related masonry all s.
(18) Prior to C: toter 1,1951, the licensee shall submit for NRC approval the design of a modified containment vent and purge system to substantially reduce the use of the IS-inch purge valves during po.er operation. Prior to startup follo.ing the first refueling, the licensee shall install the ARC-approved modi fied system.
(19) The licensee shall take the following reredial actions, Or alternative actions, acceptacle to t're NRC, with regard to the environmental cualification re;uiremente for Class IE etui; rent:
-e-(a) Ccaplete and auditable recercs must be available and rain-tained at a central locatien wnich describe the enviren ental quali 'icatien rethod used for all safety-related electrical ecuiprent in sufficient detail to docurent the degree Of corpliance with AUREG-0EE8, "Interir itaff Pesitien en Envirenrental Oualification cf Safety ? elated Electrical Ecuiprent," dated Decerter 1979. Such recercs shall te updated and raintained current as ecuipment is replacec, further tested, or otherwise further cualified te cccurent corplete compliance no latee than June 30,19E2.
(b)
.No later *.ran June 30, 1952, all safety-related electrical ecuipren' in the facility shall be cualified in accordance mith the previsions of NUEEG-CEEE.
(20) Prior to startup following the first refueling, the licensee shall obtain NEC aprreval of adciticnal evaluations of tre Festin;ncuse fuel perferrarce code (PAD 3.3) to derenstrate its applicability to fuel burrups during succes:ive fuel cycles.
(21) Prict to startup folle.Ing the first refueling, the licensee shall corplete codifications cf the prirary are backup circuit protection devices in containrent electrical peretratien circuits.
(22) Pricr to startup follcwing the first refueling, tre licensee shall e0dify tre autoratic prelube syster cf the two Fairtarks ve rri s diesel cenerators and shall revise procedures fcr diesel gererater test leading.
(23) Pricr to startup follcwing the first refueling, the licensee shall inspect the rain stear turbine for indicatiens of disc cracting.
(24) The licensee shall complete each cf the follcwir; cencitiens to the satisfaction of the NEC by the tires indicatec. Each of tre fellcwing ccediticns references the apprecriate iter in Secticn 22.5, " Dated Pecuire ents" in SER Supple ent 5, NUREG-C117:
(a) Guidance fer the Evaluatien and Develecment of dretetures fer Trans1ents anc Acc1 cents ti.C.11 Pricr to startup follcwing the first refueling af ter Jaruary 1, 1922, cceplete the upgrading cf erergercy precedurec and ass 0ciated cperater training.
_g-(b)
Reacter Coolant Syster Vents (II.E.1)
Submit a design descriptien and operating procedures for reactor coolant system vents prior to July 1,19P1 and corplete installation prier to July 1,1982.
(c) Plant Shielding (II.B.2)
Prior to April 1,1982, corplete all codifications to assure access to vital areas and protection of safety ecuipment following an accident resulting in a degraded core.
(d) Relief and Safety Valve Tests (II.D.1)
Provide information to the NRC based on tests to deronstrate cualification of relief valves, block valves, and associated piping as follcws:
(1)
Report demonstrating avalificatien of relief valves, and associated piping prior to October 1,1961.
(2)
Report demonstrating cualificatien of block valves prior to July 1,1982.
(e)
Auxiliary Feedwater Initiation and Indicaticn (II.E.1.2)
Prior to startup follcwino the first refueling, rake rediff-caticns to the control and protection circuits for the auxiliary feedwater system to enhance the reliability and tolerance of the system to failures. Submit the design of these modificatiens to the NRC for review and approval prior to July 1,1981.
(f)
Additienal Accident Monitoring Instruments (II.F.1)
Install and provide inforration regarding accident ecnitoring instruments as follows:
(1)
Install noble gas effluent renitors prior to January 1, 1982.
(2)
Install capability for centinuous sarpling of plant gas effluents prior to exceeding 5 percent power.
. (3)
Install hich-range radioactivity renitcrs in the ccr.-
tainment prior to Jaruary 1,1922.
(4) Fr0vice a descriptien of centainrent pressure instru-rents prior to June 1,1981 ard install LPC-acpreved pressure instracents prior to January 1,19E2.
(5) Provide a descriptien cf a containnent water level reasurerent syster prior to June 1,19El and install NRC-a;creved water level systen prior to January 1,1992.
(6) Frevide a description of the use of tre installed hydrcgen indication ocnitors prior to June 1,1981 and rake NRC-recaired redifications price te January 1,19E2.
(g) Inadecuate Cere Cocline Instrurents (!!.F.2)
Fcr the prep 0 sed reacter vessel mater level instrurent, (1) Frevide detailed design f rfcrmation idertified in Secticn 22.5 of SER Supplerent 5, Fecuirerent A, Parts (1)(a),
(3), (4), (7), (8), and (9) pric-to July 1,1931.
(2) Provide results of tests en Farley Unit 1 for consiceration in this facility prior to July 1,19El.
(3) Frevide planred prograr to corplete develeprent, includ-ing anj adciticnal test data neeced to ceterrine feasibil-ity, prier to January 1,1932.
(h)
Conrissien Orders en Eabcock !, i'ilecx Plents, subsecuently Accliec to all PnR Plants (II.t.2J Price to January 1,19E2, (1) Subrit a detailed analysis of tne therral rechanical conditiens in the reacter vessel during recovery frcr srall break LOCAs with an extenced less cf all feecwater
( I I. K. 2.13 ).
(2) Provide an analysis Of the ;ctential fer voiding in the reactor ccolant syster durin9 antici:ated trans-ients (II.r.2.17).
(3) Provide a tench rark analysis of secuential auxiliary feedwater flew to the stean ceneraters fcilewing a less of rain feed ater (II.K.2.19).
.- (i) Final Recommendations of E80 Task Force (II.K.3)
(1) Vith respect to a modified automatic power operated relief valve (PORV) system (II.K.3.1 and II.K.3.2):
(i)
Provide a description and analysis of the modified automatic PORY design for f.'RC approval prior to July 1,1981.
(11) Complete installation and testing of the modified autocatic PCRV prior to startup follcwing the first refueling outage after NRC approval of the design.
(2) With respect to autoratic trip of reactor coolant purp (II.K.3.5),
(1)
Within 3 months after NRC approval of a srall-break LOCA model based on results of LCFT test L3-6, subrit an analysis to the NRC for approval of design rodifications to provide for autoratic trip of the reactor coolant pump in a srall break LOCA.
(ii) Prior to l' arch 1,1982, complete NRC-approved nodifications to r ovide for autoratic trip of the reactor cocla rt pump.
(3) With respect to reliability of reactor coolant pump seal cooling (II.K.3.25),
(1)
Prior to Janaury 1,1982, submit results of analyses or experirents to determine consecuences of a loss of cooling water to the reactor coolant purp seal coolers and describe any modifications fcund neces sa ry.
(ii) Prior to July 1,1982, corplete any necessary modifications.
(4) With respect to a revised srall break LOCA model, (i)
Prior to January 1,1982, subrit to the NPC e revised rodel to account for recent experimental data (II.K.3.30).
_ (ii) Prior to January 1,1983, submit to the NRC the results of plant-specific calculations using the NRC-approved revised model (II.K.3.31).
D.
The licensee shall fully implement and maintain in effect the physical security plan, withheld from public disclosure pursuant to 10 CFR 2.790(d), entitled, " Joseph M. Farley Nuclear Plant Security Plan" dated March 5,1981, and as amended in accordance with the provisions of 10 CFR 50.54(p) (The Physical Security Plan).
Prior to August 1,1981, the licensee shall have fully implemented the commitments identified in Chapter 15, items 15.1 d, f, and g of The Physical Security Plan. Until such time that these commitments are implemented the licensee shall follow the provisions cortained in their letter of March 12, 1979.
E.
The licensee shall report any violations of the requirements contained in Section 2, Items C.(3) through C.(13), and D of thie license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm by telegram, mailgram, or facsimile transmission to the Director for Region II of the C'fice of Inspection and Enforcement, or the Directors designata, no later than the first working day following the violation, with a written followup report within 14 days.
F.
Antitrust aspects are pending before the Atomic Safety and Licensing Appeal Panel and the following antitrust conditions may be modified as a result of this continued litigation. Alabama Power Company (the Licensee) shall meet the following antitrust conditions:
(1) Licensee shall recognize and accord to Alabama Electric Cooperative, Inc. ( AEC), the status of a competing electric utility in central and southern Alabama, and shall take no actions and engage in no course of conduct having the purpose and effect of treating AEC as a mere customer of Licensee for the sale of wholesale power.
(2) Licensee will sell to AEC unit power from Units 1 and 2 of Joseph M.
Farley Nuclear Plant. The amount of capacity to be sold by Licensee from such units to AEC shall be an amount based on a ratio of (a) the aggregate coincident demand of all wholesale-for-resale members of AEC in Alabama during the hour of peak demand on the electric system of Licensee in 1976 to (b) the sum of such coincident demands of AEC and the territorial peak-hour demands of Licensee (excluding therefrom the peak-hour demands imposed by members of AEC upon the electric syster of Licensee) during the hour of peak demand on Licensee's electric syste n in 1976. Centractual arrangements will be entered into between Licensee and AEC by the terms of which AEC will be ertitled to purchase and receive the percentage of electrical cutput of the respective Farley units determined in accordance with the foregoing ratio. Such output from the respective units will be supplied by Licensee to AEC for the entire comercial service life of the particular units. Such contractural arrancements will also provide that AEC shall pay Licensee en a monthly basis fcr the capacity portion of such unit power, amounts representing the percentage of Licensee's fixed costs in such nuclear units based upon the ratio described above. Such contractual arrangenents shall also provide that AEC shall pay Licensee on a conthly basis for the energy portion of such unit power, arcunts representing the percentage of Licensee's variable costs incurred in the cpera-tion of such units based upon the ratio of energy generated for AEC's account to the total energy generated by such units during the billing month. The previsions of such contractual arrangerents shall clearly provide that the net effect of sucn pa, eents to be made by AEC shall be that AEC will oay its propertionate share of Licensee's tctal costs related to sucn nuclear units inclucing, but not limited to, all costs of construction, installation, ownership, licensing and cperation of such units, but no rcre than such propertionate share. The contrects covering such unit power shares shall erbrace pricing and charges reflectinc conven-tional acccunting and rate-raking concepts established and applied by the Federal Pcwer Commission or its successer in function, and any disputes concerning the identification or application of such concepts shall be determined by and in acccrdance with procedures of the Federal Power Commission or its successor in function.
(3) Licensee will provide transmissicn services to enable AEC to receive on its electric system such portion of its entitlerent to the output of the Farley units as AEC recuires in the operation of its integrated electric system, and, in additien, Licensee will provide transmission services to the existing renbers of AEC physically connected to Licensee to enable such renbers to utilize any of the allocation of AEC's portien of the output of the Farley units. Contractual arrangenents will be entered into between Licensee and AEC cr, at the option of AEC, between Licensee and such nerbers by the terrs of which Licensee will be paid for such transmission services on the basis of the ownership, raintenance and operation costs associated with such transmission services.
The contractual arrangements covering such transmission services shall embrace rates and charges reflecting conventicnal acccunting and rate making c:nce:ts fellcwed by the ~ece-al Fe.er Corrissicr er its successer in function in testing the reasonarleress of rates and charges fee trart-issien se" vices. Such ccetractual arrarce-rerts shall centain ;revisicns ;!retecting Licensee against any ecencric detrirert resulting fr]r trars-issi:n line er tra sf:r-r4tien lesse: associated with such trans-issier services.
(4) Licensee will aise provice AEC sech ctrer tulk :: er su;;1y services as ray be re uired by it o such rerters t: c:ver situaticns where such unit pcmer te whict AEC shall be:0e centractually entitled is unavailatle te:ause cf fer ed cutages, raintenarce recuirerents or ctrer unavailability cf ite Farley Nuclear Lnit for any reasen.ratever. Sucn acciticnal or sa;;1erental services ray te censidered in the centext cf the 1972 Inter:en e ticn Agree ent nc. in effect er as su:n agreement rignt te r:cified in acccrdance aitn paragra:n f cur hereef. :n additien, Licensee will su ply tre :artial :: er recuire ents of the existing rerters cf AEC physically c:rnetted to Licensee whier ay be reastnatly necessary to cover their recuire ents ever and areve (a) tre ; er available to ther thr uch treir arrarge ents witr SE3A arc (t) the allccation of any unit ;.er frer aEC urcer the arrangerents center;1ated uncer :aragraphs tm and trree abcve. Tre centractual arrangerents c vering the services cescritec in tris raragra:r shall te en a basis reflectire Licensee's ccsts and at rates and charges reflectirg ccnventional acccunting anc rate aking concepts follc=ed by the Federal ;cwer Com?issice er its su cesscrs in function.
(E) Licensee will enter into a;;r:;riate c:ntractual arrangerents are-ci ;
tre 1972 Inter: nrecticn Acree ent as last arended t: :rovide f:r a reserve sharirg arrangerert tet een Licensee and AEC under whicn the reserve cbligation of AEC is ne greater than tre reserve tligatien undertaken by LicersEe uncer the terrs Cf tre ECutfern CO ary Fool Intercharge Agreerent. It is the intent and ur;cse cf such centract redification to elf-irate fro-the 1972 Intercer ecticn Agreerent bet een Licensee and AEC a previsien relating to pr:tective ca:acity purchased by #EC.
(c) The foregoing conditi rs shall be irclerented in a carrer ;;rsiste-witn the previsiens of the Federal Fe.er Act and tre Ala'cara :ublic Utility laws and regulatiers thereuncer and all rates, charges, services Or Oractices in ::Precticn there=f th are t0 te subject ::
J.: a;;reval of regulatery acercies having jurisci tien ever tre.
. G.
The facility requires relief from certain recuirements of 10 CFR 50.55a(g) and exemptions from Appendices G, H and J to 10 CFR P:-t
- 50. The relief and exemptions are described in the Office of Nuclear Reactor Regulation's safety Evaluation Repcrt, Supplement No. 5.
They are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
Therefore, the relief and exemptions are hereby granted. With the granting of these the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Conmission.
H.
The Alabama Power Company shall immediately notify the NRC of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.
I.
The Alabama Power Company shall have and maintain financial protection of such type and in such arounts as the Commission shall recuire in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
J.
This license is effective as c' the date of issuance and shall expire August 16, 2012.
FOR THE NUCLEAR REGULATORY CCFNISSICN Harold R. Denton, Directer Office of Nuclear Reactor Regulation
Attachment:
1.
Appendix A - Technical Specifications (NUREG-0697, as revised) 2.
Appendix B - Environmental Protection Plan Date of Issuance:
UN!TED STATES NUCLEAP FEGULATCEY CCP'IESICM DCCKET NC. 50-3Ea ALAS AVA PCWER CC!'DANY NOTICE CF 155UA?.CE CF FA'!LITY CFEEATING LICENSE Nctice is r.ereby given that the U.S. Vuclear Fepulatory Core:issicn (the Concissien) has issuec' Facility 0;erating License No. NFF-? tc Alabara Fc-er Corpany wnich authorizes c;eration of the Jose;h M. Fetley -uclear Plant, Unit 2, (Farley ': nit 2), at reacter ccre ;c er levels net in excess of 2652 regawatts tb4: cal (100 percent re er) in acccrearce with the previsiens and cencitiens of the license, the a;cended Technical Specifications anc the Envircr ental Protecticn Plan. ;rier te c;eration at pcwer levels exceeding 5 percent, certain license cenciticns rust be et.
Tnis licerse st;ersedes the Fuel Lcading and Lew Power Testing License issued Octcber 23, 1950.
Farley Unit 2, is a pressurized water reat:cr loca 7d in Housten County, Alatera. Prict public notice cf the everall action invclving the crc:csed issuance of facility ccerating license was issued in the Federal Fecister en N eve-t e r 29,1973 (3? FF 29907).
Tke acclicatier corplies with the standards arc recuirerents cf the Act and the Cer-is3 *nn's rules and regulatiens. The Concissicn has r.ade a ;rc;riate findings as reculi nd by the Atomic Erergy Act of 19Ea, as arended (the Sct),
and the Concission's rules and regulations in 10 CFR Chapter I, which ai set fcrth in the facility c;erating license.
2-The ".ommission has determined that the issuance of this facility full power operating license will not result in any environrental impacts other than those evaluated in the Final Environmental Statement since the activity authorized by the license is encompassed by the overall ar.tTon evaluated in the Final Environmental Statement.
A copy of (1) Facility Operating License NPF-8, corplete with Technical Specifications (NUEEG-0697 as revised) and Environmental Protection Plan; (2) the report of the Advisory Conmittee on Reactor Safeguards dated June 12, 1975; (3) the Office cf Nuclear Reactor Regulation's Safety Evaluation Report (NUREG-75/034) dated P.cy 1975, Supplerent i dated October 1975, Supplement 2 dated Octcber 1976, Supplement 3 dated June 197E, Supplement 4 dated September 1900, and Supplerent 5 dated March 1981 (supplerents are NUEEG-Oll7); (4) the Final Safety Analysis Report and arendments thereto; (E) the licensee's Environrental Peport and supplements thereto; (6) the NRC Draft Environmental State-e:.t dated July 1974; (7) the NRC Final Environrental Statement (FES) dated Decerber 1974, the NRC Environmental Assessment dated April 1977, and the FES Addendum dated September 1980 (NUP.EG-0727); and (6) the NFC Flood Plain Review of the Joseph M. Farley Nuclear Plant site dated September 17, 1980, are available for public inspecticn at the Commission's Public Docurent Room,1717 H Street, N.W., Washington, D. C.,
and the G. S. Housten tiemorial Library, 21; V. Eurdeshaw Street, Dothan, Alabama 36303.
. A copy cf the f acility crerating license ray be obtained upon recuest addressed to the U.S. Nuclear Pegulatory Corcission, Washington, D. C. 20555, Attentier:
Director, Division of Licensing.
Copies of the Safety Evaluaticr. Report and Supplements, and the Final Environmental Staterent and Addendur may be purchased at current rates frem the w:tional Technical Information Service, 52P5 Port Royal Road, Springfield, Virginia 22161, and througn the NRC GPO sales progran by writing to the U.S. Nuclear Regulatory Conrission, Attention:
Sales Far.ager, Kashington, D. C. 20555. GPO deposit holders can call 3Dl 492-953D.
FCR TF'E NUCLEAR REGULATCRY CCM'ISSICN A. Schwencer, Chief Licensing Eranch No. 2 Divisicn of Licensing.
Dated at Eethesca, Faryland tnis day of