NUREG-0697, License NPF-8 for Facility.Environ Protection Plan & NUREG-0697,Revision 1,re Tech Specs Encl
| ML19341D764 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/31/1981 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341D765 | List: |
| References | |
| RTR-NUREG-0697, RTR-NUREG-697 NPF-8, NUDOCS 8104090264 | |
| Download: ML19341D764 (14) | |
Text
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\\, '*Ah, / l ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 FACILITY CPERATING LICENSE License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for licenses filed by the AlaDama Pcwer Company complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Joseph M. Farley Nuclear Plant, Unit 2 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-86 and the application, as amended, the provisions of the Act and the regulations of tne Co: mission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 0.
There is reasonalle assurance: (1) that the activities authorized by tn.) license can ae conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; E.
The Alabama Power Company is technict.lly and financially qualified to engage in the activities authorized oy this license in accordance
(
with the Comission'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 Agreements", of the Comission's regulations; G.
The issuance of this license will not be inimical to the comon defense and security or to the health and safety of the public; 8104090MN
)
, H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-8, subject to the conditions for protection of the environment set forth in the Environmental 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 requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Ccamission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Pursuant to approval by the Nuclear Regulatory Commission at a meeting cn March 11,1981, the License for Fuel Loading and Low Power Testing (MPF-8),
issued on October 23, 1980, as amended, is superseded by Facility Operating License MPF-8 which is hereby issued to the Alabama Power Company (thr, licenset to read as follows:
A.
This license applies to the Joseph M. Farley Nuclear Plant, Unit 2, a pressurized water nuclear reactor and associated equipment (the facility),
owned by the Alabama Power Company. The facility is located in Houston County, Alabama, and is described in the licensee's " Final Safety Analysis Report," as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Alabama Power Company:
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Houston County, Alabama, in accordance with the limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required 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, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment ~ calibration, and as fission detectors in amounts as required;
, (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 associated 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 Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable 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) Maximum Power Level Alabama Power Company is authorized to operate the facility at reactor core power levels not ir. excess of 2652 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 licer.see shall conduct the initial test program (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 14 of the licensee's Final Safety Analysis Report, as amended; 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;
4 c.
Performance of any test at a power level different from the level in the described program; and d.
Failure to complete any t, ts included in the described program (planned or schedu.'d) for power levels up te the authorized power level.
(4) The licensee shall not use the spent fuel cask crane for the purpose of moving spent fuel casks prior to approval by the NRC of the lifting devices which attach the spent fuel cask to the crane.
(5) The interval for testing pumps and valves in accordance with 10 CFR 50.55 a(g)(2) is 120 months commencing with the start of connercial operation.
The licensee shall provide additional information needed by the NRC to complete its detailed review of the licensee's inservice testing program for pumps and valves no later than 6 months prior to the end of the first 120-month interval.
(6) Fire Protection Program The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan except as modified by the NRC's Joseph M. Farley Safety Evaluation Report, Fire Protection Review, Units 1 and 2, transmitted to the licensee on April 13,1979 (Fire Protection SER). The approved fire protection plan consists of the document entitled "Farley Nuclear Plant Fire Protection Program Reevaluation" which includes:
Initial Issue, submitted with letter dated September 15, 1977; Amendment 1, submitted with letter dated February 23, 1978; Amendment 2, submitted with letter dated July 14, 1978; Amendment 3, submitted with letter dated October 27, 1978; Amendment 4, submitted with letter dated January 3,1979, and amended by letter dated October 21, 1980.
Administrative control changes and procedure revisions shall be implemented and maintained in effect as described in NRC's Fire Protection SER.
The licensee shall comply with the fire protection program set forth in Appendix R to 10 CFR Part 50 in accordance with the requirements of $50.48 of 10 CFR Part 50.
('7 ) 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 emergercy preparedness identified by FEMA in its plan, evaluation, ann exercise critique, or by the NRC in its SER and Supplements as requiring further action.
The licensee shall complete its plans for prompt notification, staffing for emergencies, upgrading the meteorological program, and upgrading emergency support facilities on the NRC approved schedule identified in the following sections of !ER Supplement 5:
Section 22.5, Dated Requirements:
Item III.A.1.2 Upgrade Emergency Support Facilities Item III.A.2 Long Term Emergency Prepared'less Appendix B Emergency Preparedness Evaluation Report:
Section B Onsite Emergency Organization Section E Notification tiethods and Procedures (8) On a one-time only basis, The Action Statement of Technical Specification 3.7.4. shall be replaced by the following:
Action:
With only one service water loop OPERABLE, restore at least twc loops to OPERABLE status witnin 72* hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- This 7 ?-hour limit is extended on a one-time only basis to a maximua of 10 days for the recirculation portion of each service water 130p to permit system tr.adifications. Modifications, affecting operability, shall be made on only one of the two service water loops at a time. One loop shall remain OPERABLE until the other loop has been modified and returned to SPERABLE status. All other portions of the service water system are not covered by this one-time only change. All modifict.tions to both loops are scheduled for completion by May.15,1981.
For-record purposes, this license condition expires 90 days from date cf license issuance.
-(9) (a) Prior to exceeding 5 percent power, the licensee shall provide to the NRC the results of the fellowing seven augmented low power tests:
natural circulation natural circulation with simulated loss of offsite powe:
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 after operation for 25,000 MW(e)-days, results for the test of natural circulation cooldown with boron mixing shall be submitted to the NRC.
(10) Prior to exceeding 5 percent power, the licensee shall make fully operational the post-accident sampling system.
(11) Prior to exceeding 5 percent power, the licensee shall complete the training for mitigating core damage.
(12) 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 make provisions (or modifications) as necessary to assure that the safety grade backup means of reactor coolant system depressurization is in accordance with the requirements of Table 1 in Branch Technical Position RSB 5-1, Rev.1.
(c) Prior to startup following the first refueling, the licensee shall provide to the NRC natural circulation cooldown procedures, based on reactor natural circulation cooldown test results applicable to Farley Unit 2.
(13) Prior to exceeding 5 percent power, the licensee shall (a) modify and test reset circuits for the containment air mixing fans, containment purge isolation valves, and auxiliary feedwater pump discharge valves to meet the requirements of IE Bulletin 80-06
" Engineered Safety Feature Reset Controls", and (b) revise procedures to be consistent with the modified designs required by (a).
(14) Prior to exceeding 5 percent power, the following equipment which was not required to be operable by the Fuel Loading and Low Power Testing License is exempt from the Technical Specification (TS) that requires a demonstration of operability:
~
. All fire detectors listed in TS Table 3.3-12 except those in containment (Fire Zone 55)
Reactor coolant system isolation valves listed in TS Table 3.4-1.
(15)
Prior to May 31, 1981, the licensee shall complete modifications to the subcooling monitor system identified in Item II.F.2, Section 22.3 in SER Supplement 5, NUREG-0117.
(16)
The licensee shall re-evaluate and modify, as necessary, safety-related masonry walls in accordance with IE Bulletin 80-11
" Masonry Wall Design". During the re-evaluation if the operability of any safety-related system is judged to be in jeopardy, that system shall be declared to be inoperable and actions taken as required by Technical Specifications for that inoperable system.
Prior to May 17, 1981, the licensee shall provide its response to IE Bulletin 80-11, including its re-evaluation report. Prior to startup following the first refueling, the licensee shall complete any modifications needed to assure the structural integrity of safety-related masonry walls.
(17)-
Prior to October 1,1981, the licensee shall submit to the NRC the design of a modified containment vent and purge system to reduce the use of the 18-inch purge valves during powee operation.
Prior to startup following the first refueling, the licensee shall install the modified system.
(18)
The licensee shall take the following remedial actions, or alternative actions, acceptable to the NRC, with regard to the environmental qualification requirements for Class IE equipment:
(a) Complete and auditable records shall be available and main-tained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with NUREG-0588, " Interim Staff Position on Environmental Qualtrication of Safety-Related Electrical Equipment," dated December 1979. Such records shall be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document comolete compliance no later than June 30, 1982.
(b) Within 90 days of receipt of the equipment qualification safety evaluation (Appendix B to SER Supplement 6, NUREG-0117), the licensee shall either (i) provide missing documentation identified in Sections 3.0, 4.2 and 4.3 of the equipment qualification safety evaluation which will demonstrate compIf ance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.
. (c) No later than June 30, 1982, all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of NUREG-0588.
(19) Prior to resuming power operation following the first refueling, the licensee shall:
(a) Provide additional evaluations of the Westinghouse fuel performance code (PAD 3.3) to demonstrate its applicability to fuel burnups during successive fuel cycles.
(b) Complete modifications of the primary and backup circuit protection devices in containment electrical penetration circuits.
(c) Modify the lubrication system of the two Fairbanks-Morse opposed-piston diesel generators by installing a pre-lube pump arranged for automatic and manual start and powered from a reliable DC power supply or install an equivalent or better system which will prevent dry starting of the diesel generators on an automatic start signal. The licensee shall submit the system final design and implementation schedule to the NRC' vithin six months after this license is issued.
(d) Inspect the main steam turbine for indications of low pressure rotor disc cracking, or replace the present low pressure rotors with refurbished rotors.
(20) Prior to April 30, 1981, the licensee shall provide a schedule 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.
(21) The licensee shall complete each of the following conditions to the satisfaction of the NRC by the times indicated. Each of the following conditions references the ippropriate item in Section 22.5, " Dated Requirements" in SEF Supplement" 5, NUREG-Oll7:
(a) Guidance for the Evaluation and Develop.nent of Procedures for Transients and Acciaents (I.C.1)
Prior to startup following the first refueling after January 1, 1982, complete the upgrading of emergency procedures and associated operator training.
(b) Reactor Coolant System Ients (II.B.1)
Submit a design description and operating procedures for reactor coolant system vents prior to July 1,1981 and complete installation prior to July 1,1982.
~
(c) Plant Shielding (II.B.2)
Prior to April 1,1982, complete all modifications to assure access to vital areas and protection of safety equipment following an accident resulting in a degraded Core.
i (d) Relief and Safety Valve Tests (II.D.1)
Provide information to the NRC Dased on tests to demonstrate qualification of relief valves, block valves, and associated piping as follows:
(1) Report demonstrating qualification of relief valves, and associated piping prior to October 1,1981.
(2) Report demonstrating qualification of block valves prior to. July 1,1982.
(e) Auxiliary Feedwater Initiation and Indication (II.E.1.2)
Prior to startup following the first refueling, make modiff-cations 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 modifiestions to the NRC prior to July 1,1981.
(f) Additional Accident Monitoring Instruments (II.F.1)
Install and provide information regarding accident monitoring instruments as follows:
(1)
Install noble gas effluent monitors prior to January 1, 1982.
(2)
Install capability for continuous sampling of plant gas effluents prior to exceeding 5 percent power.
(3)
Install high-range radioactivity monitors in the containment prior-to January 1,1982.
(4) Provide a description of containment pressure instruments prior to June 1,1981 and install pressure instruments prior to January 1,1982.
(5) Provide a description of a containment water level measurement system prior to June 1,1981 and install water level system prior to January 1,1982.
, (6) Provide a description of the use of the installed hydrogen indication monitors prior to June 1,1981 and make modifications, if required, prior to January 1,1982.
(g)
Inadequate Core Cooling Instruments (II.F.2)
For the proposed reactor vessel water level instrument, (1) Provide detailed design information identified in Section 22.5 of SER Supplement 5, Requirement A, Parts (1)(a), (3),
(4), (7), (8), and (9) prior to July 1,1981.
(2) Provide results of tests on Farley Unit 1 for consideration in this facility prior to July 1,1981.
(3) Provide planned program to complete development, including any additional test data needed to determine feasibility, prior to January 1,1982.
(h) Commission Orders on Babcock & Wilcox Plants, Subsequently Applied to all PWR Plants (II.K.2)
Prior to January 1,1982, (1) Submit a detailed analysis of the thermal mechanical conditions in the reactor vessel during recovery from small break LOCAs with an extended loss of all feedwater (II.K.2.'3).
(2) Provide an analysis of the potential for voiding in the reactor coolant system during anticipated transients (II.K.2.17).
(3) Provide a bench mark analysis of sequential auxiliary feedwater flow to the steam generators following a loss of main feedwater
( II.K.2.19 ).
(i) Final Reconnendations of B&O Task Force, I.K.3)
(1) With respect to an automatic power-operated relief valve (PORV)
-isolation system (II.K.3.1 and II.K.3.2):
(1) Perform a safety examination of an automatic PORY isolation system (II.K.3.1) per the requirement of II.K.3.2..
-(ii) If an automatic PORY isolation system is required per (i) above, provide the information identified under the "Docu-mentation Required" section of II.K.3.1 of NUREG-0737 by July 1,1981.
(iii) If required from (i) above, complete installation and testing of the modified automatic PORV isolation system prior to startup following the first refueling outage tha? is scheduled to occur more than 6 months after NRC approval of the design.
. (2) With respect to tripping of reactor coolant pumps (RCPs)
(II.K.3.5):
(i) Submit to the NRC for approval either (1) an evaluation which shows that sufficient time is available te the operator to manually trip the RCPs in the event of a small break LOCA, or (2) a description of design modifications required to provide for an automatic pump trip. This submittal is required within three months after NRC determination of acceptability of the small break LOCA raadel based on comparisons with LOFT test L3-6.
(ii) If required based on (i) above, complete plant modifica-tions to provide for automatic tripping of reactor coolant pumps within 11 months after NRC determination of model acceptability, provided there is an appropriate outage during that time interval to complete installation or during the first such scheduled outage occurring thereafter.
(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 experiments to determine consequences of a loss of cooling water to the reactor coolant pump seal coolers and describe any modifications found necessary.
(ii) Prior to July 1,1982, complete any necessary modifications.
(4) With respect to a revised small break LOCA model.
(i)
Prior to January 1,1982, submit to the NRC a revised model to account for recent experimental data ( II.K.3.30).
(ii)
Subrait to the NRC the results of plant-specific calculations using the NRC-approved revised model prior to January 1,1983.
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 co'.'.*tments identified in Chapter 15, items '15.1 d, f, and g of The Pnysical Security Plan. Until such time that these commitments are implemented the licensee shall fcilow the provisions contained in their letter of March 12, 1979.
. E. ' The licensee shall report any violations of the requirements contained in Section 2, !ttsms C.(3) through C.(21), and D of this 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 Office of Inspection and Enforcement, or the G1 rector's designate, no later than the first working day following the violation, with a written followup report l
within 14 days.
I F.
Antitrust aspects are pendi'q 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:
l (1) Licensee shall recognize and accord to Alabama Electric Cooperative, l
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 fron 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 cemands of AEC and the territorial peak-hour demands of Licensee (excluding therefrom the peak-hour demands imposed by members of AEC upon the electric system of Licensee) during the hour of peak demand on l
Licensee's electric system in 1976. Contractual arrangements will be entered into between Licensee and AEC by the terms of which AEC will be entitled to purchase and receive the percentage of electrical output of the respective Farley units determined in accordance with the foregoing ratio. Such output from the respective units will be supplied by N:se to AEC for the entire commercial service life l
of the particular units. Such contractural arrangements will also provide that AEC shall pay Licensee on a montnly basis for 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 arrmements shall also provide that AEC shall pay Licensee on a...untniy basis for the energy portion of such unit power, amounts representing l
the percentage of Licensee's <ariable costs incurred in the opera-l 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 provisions of such contractual arrangements shall clearly provide that the net effect of such paymen% to be made by AEC shall be that AEC will pay its proportionate share of
. Licensee's total costs related to such nuclear units including, but not limited to, all costs of construction, installation, ownership, licensing and operation of such units, but no more than such proporticnate share. The centracts covering such unit power shares shall embrace pricing and enarges reflecting conven-tional accounting and rate-making concepts established and applied by the Federal Power Commission or its successor in function, and any disputes concerning the identification or application of such concepts shall be determined by and in accordance with procedures of the Federal Power Commission or its successor in functicn.
(3) Licensee will provide transmission services to enable AEC to receive on its electric system such portion of its entitlement to the output of the Farley units as AEC requires in the operation of its integrated electric systen, and, in addition, Licensee will provide transmission services to the existing members of AEC physically connected to Licensee to enable such members to utilize any of the allocation of AEC's portion of tne output of the Farley units. Contractual arrangements will be entered into between Licensee and AEC or, at the option of AEC, between Licensee and such members by the terms of which Licensee will be paid for such transmission services on the basis o' the ownershio, Saintenance and operation costs associated with such transmission services.
The contractual arrangements covering such transnission servicts shall embrace rates and charces reflecting conventional-account!ng and rate-making concepts followed by the Feferal Dower Connission or its successor in function in testing the reasonableness of rates and charges for transmission services. Such contractual arrange-ments shall contain provisions protecting Licensee against any econmiic detriment reselting from transmission line or tran',for-maticn losses associated with such transmission services.
(4) Licensee will also provide AEC such other bulk power supply services as may be require 6 c, it or such mercers to cover situations wnere such unit power to which AEC shall beccme contractually entitled is unavailable because of forced outages, maintenance requireeents or other unavailability of the Farley haclear Unit for any reason whatever. Such additional or supplemental scryices may be considered in the context of the 1972 Interconnection Agreement now in effect or as such agreement might be codified in accordance with paragraph four hereof. In additien, Licensee will supply the partial power requirements of the existing memcers
,c /EC physically connected to Licenree which may be reasonably necessary to cover their requirements over and above (a) the power available to them throuen their arrangements with SEPA and (b) the allocation of any unit power frun AEC under the arrange?ents contemplated under paragraphs two and three above. The contractual arrangements covering the services described in this paracraph shall be on a basis reflectino Licensee's costs-and at rates and charges reflecting conventional accounting and rate-making concepts followed by the Federal Dcwer Commission er its successors in function.
. (S} Licensee will enter into appropriate contractual arrangements amending the 1972 Interconnection Agreement as last amended to provide for a reserve sharing arrangement between Licensee and AEC under which the reserve obligation of AEC is no greater than the reserve obligation undertaken by Licensee under the terms of the Southern Company Pool Interchange Agreement.
It is the intent and purpose of such contract modification to eliminate from the 1972 Interconnection Agreement between Licensee and AEC a provision relating to protective capacity purchased by AEC.
(6) The foregoing conditions shall be implemented in a manner consistent with the provisions of the Federal Power Act and the Alabama Public utility laws and regulations thereunder and all rates, charges, services or practices in connection therewith are to be subject to the approval of regulatory agencies having jurisdiction over ther'.
G.
The facility requires relief from certain requirements of 10 CFR 50.55a(g) and exemptions from Appendices G, H and J to 10 CFR Part
- 50. The relief and exemptions are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, 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 Commission.
H.
The Alabama Power Company shall immediately notify the NRC of any accident at this facility which could result in an unplanned elease of quantities of fission products in excess of allowable limits for normal operation established by th4 Commission.
I.
The Alabama Power Company shall have and maiatain financial protection of such type and in such amounts as the Comnission shall require 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 of the date of issuance and shall expire August 16, 2012.
FOR THE NUCLEAR REGULATORY COMMISSION Yf Harold R. Denton, Director Office of Nuclear Reactor Regulation
Attachment:
1.
A;,pendix A. Technical bacifications (NUREG-06G, as revised) 2.
Appendix B - Environmental Protection Plan Date of Issuance:
March 31,1981 s
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