ML20245L059
| ML20245L059 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/15/1989 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20245K957 | List: |
| References | |
| NUDOCS 8908210252 | |
| Download: ML20245L059 (18) | |
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ATTACHMENT 1 REVISED AND-1 LICENSE 890821o >btI' oh[f s
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4 ARKANSAS POWER AND LIGHT COMPANY (Arkansas Nuclear One, Unit 1)
DOCKET NO. 50-313 FACILITY OPERATING LICENSE License No. DPR-51 1.
The Atomic Energy Commission (the Commission) having found that:
a.
The application for license filed by the Arkansas Power and Light Company (AP&L) and Entergy Operations, Inc., (E01) (the licensees *) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; b.
Construction of Arkansas Nuclear One, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-57, and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; c.
The facility will operate in conformity with the application, as amended, the provisions of the act, and the rules and regulations of the Commission; d.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be ccnducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; e.
EDI is technically qualified and AP&L is financially qualified l
to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; f.
AP&L has satisfied the applicable provisions or 10 CFR Part 140.,
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" Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;
- After a transfer of AP&L nuclear personnel to EDI, ECI has succeeded AP&L as the operator of Arkansas Nuclear One, Unit 1 (the facility).
Consequently, E01 is authorized to act for itself and for AP&L and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
Hereinafter, the term licensees refers to both AP&L and E0I.
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.The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the
- public; h.
Aft'er weighing the environmental, economic,~technica1' and other
' benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License No. DPR-51 is in accordance with 10 CFR Part 50,
. Appendix'D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and 1.
The receipt; possession, and use of source, byproduct and~special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10'CFR Parts 30, 40 and 70, including 10 CFR Section 30.33, 40.32, 70.23 and 70.31.
2.
. Facility Operating; License No. DPR-51, as amended, is hereby issued to AP&L and EDI to read as follows:
~ a.
This license applies to Arkansas Nuclear One, Unit 1, a pressurized water reactor and associated equipment (the facility),
' owned by the AP&L and operated by E01.
The facility is located in 1
-Pope County, Arkansas.and is described in the " Final Safety Analysis Report" as supplemented and amended (Amendments 1 through
- 45) and the Environmental Report as supplemented and amended (Supplements 1 through 5).
~ b.
Subject to.the conditions'and requirements' incorporate herein,
'the Commission hereby licenses:
l' (1). E01,. Pursuant to Section 104b of the Act and 10 CFR Part 50, l
" Licensing of Production and Utilization Facilities," to possess; use, and operate the facility at the designated location in Pope County, Arkansas in accordance with the procedures and limitations set forth in this license; (2) AP&L, pursuant to the Act and 10 CFR Part 70, to receive, I
possess and use at any time special nuclear material as l
reactor fuel, in accordance with the limitations for storage h
and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; Us) E01, 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; (4) E01, 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 l
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reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required.
(5) EDI, pursuant to the Act and'10 CFR Parts 30, 40 and 70, to l
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; (6) E01, pursuant to the Act and 10'CFR Parts 30 and 70, to l
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 following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of-Part 40,-. Sections 50.54 and 50.59 of Part 50, and section 70,32 of Part 70;,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
'E01 is authorized to operate the facility at steady state l
reactor core power levels not in excess of 2054 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment-No. 124 are hereby incorporated in the license.
E01 shall operate the facility l
in accordance with the Technical' Specifications.
(3) AP&L** may proceed with and is required to complete the modifications identified in Paragraphs 3.1 through 3.19 of the NRC's Fire Protection Safety Evaluation (SE) on the facility dated August 22, 1978 and supplements thereto.
These modifications shall be completed as specified in Table 3.1 of the Safety Evaluation Report or supplements thereto.
In addition, the licensee may proceed with and is required to complete the modifications identified in Supplement 1 to the Fire Protection Safety Evaluation Report, and any future supplements.
These modifications shall be completed by the dates identified in the supplement.
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. 4 L(4)- Physical Protection lc EDI shall fully implement and maintain in effect all:.._
l-provisions of the Commission-approved physical security, L
guard training and qualification,'and safeguards contingency-
' plans. including _ amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to
-10 CFR 73.55 (51 FR 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 CFR 73.21, are entitled.
(a) " Arkansas Nuclear.One Physical Security Plan," with revisions submitted'through February 24, 1988; (b) " Arkansas Nuclear One Guard Training and Qualification Plan," with revisions submitted through August 20, 1985;
- and, (c) " Arkansas Nuclear One Safeguards Contingency Plan," with revisions submitted through May 30, 1980.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(5) Systems Integrity E0I shall implement a program to reduce leakage from systems l
outside_ containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
(6) Iodine Monitoring E0I shall implement a program which will ensure the l
capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
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.(7). Secondary Water Chemistry Monitoring A secondary water chemistry monitoring program shall be implemented to minimize steam generator tube degradation.
This program shall include:
1.
Identification'n of a sampling schedule' for the critical parameters and control points for these parameters; 2.
l-Identification of the procedures used to measure the :
values of the critical parameters; 3.
Identification of process sampling points; 4.
' Procedures for the recording and management of data; 5.
Procedures defining corrective actions for off-control point chemistry conditions; and 6.
A procedure identifying the authority responsible:for-
.the interpretation of the data and the sequence and timing of administrative events required to initiate a-corrective action.
d.
'This license is effective as of the date of issuance and shall expire at midnight, December 6, 2008.
FOR THE ATOMIC' ENERGY COMMISSION A.' Giambusso, Deputy Director Date of; Issuance:
May 21 1974
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ATTACHMENT 2 REVISED ANO-2 LICENSE l
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~ ARKANSAS POWER AND LIGHT COMPAF H,
L DOCKET NO. 50-368 l
-ARKANSAS NUCLEAR ONE, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-6 i
i 1.
The Nuclear Regulatory Commission (the Commission) having found that-A.
The issuance of this license amendment to Arkansas Power and Light
.j Company AP&L and Entergy Operations, Inc. (EDI) (the licensees *)
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.(the Act), and the Commission's regulations set forth in 10 CFR Chapter I-I B.
Construction of Arkansas Nuclear One, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-89 and the. application, as amended, the provisions of the Act and the regulations of the Commission; C.
The facility requires exemptions from certain requirements of (1)
Sections 50.55a(g)(2) and 50.55a(g)(4) of 10 CFR Part 50, (2)
Appendices G and H to 10 CFR Part 50 and (3) Appendix J to 10 CFR Part 50 for a period of three years.
These exemptions are described in the Office of Nuclear Reactor Regulation's safety.
j evaluations supporting the granting of these exemptions which are enclosed in the letter transmitting this license amendment.
These i
exemptions are authorized by law and will not endanger life or l
property or the common defense and security and are otherwise in the public interest. The exemptions are, therefore, hereby l
granted.
With the granting of these exemptions, as amended, the provisions of the Act, and the regulations of the Commission; CAfter a transfer of AP&L nuclear personnel to EDI, EDI has succeeded AP&L as the operator of Arkansas Nuclear One, Unit 2 (the facility).
l Consequently, EDI is authorized to act for itself and for AP&L and has l
exclusive' responsibility and control over the physical construction, i
operation and maintenance of the facility.
Hereinafter, the term licensees refers to both AP&L'and E01.
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' D.
There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the
- o health and safety of the public,.and (ii) that such activities l.
will be conducted-in compliance with the regulations of the L
Commission; E.
E01 is technically qualified and AP&L is financially qualified to l
engage in the activities authorized by this operating license in accordance with the regulations of the Commission; F.
AP&L has satisfied the' applicable provisions of 10 CFR j
s Part 140, " Financial Protection Requirements and Indemnity-
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Agreements,"-of the Commission's regulations; j
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The issuance of this amended operating license will not be j
~ inimical to the common defense and security or to the health and safety of the'public;.
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H.
After weighing the. environmental, economic, technical and other j
benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Amendment No.
1-to Facility Operating License No. NPF-6 subject to the conditions for protection'of the environment set forth herein, is
. in accordance with 10 CFR Part 51 (formerly Appendix D to 10 CFR j
Part 50) of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special i
nuclear material as authorized by this license will be in accordance:with the Commission's regulations in 10 CFR Parts 30, 40 and 70, including 10 CFR Sections 30.33, 40.32, 70.23 and 70.31.
2.
Facility Operating License No NPF-6, as amended, is hereby issued to
.AP&L and E01 to read as follows:
A.
This amended license applies to Arkansas Nuclear One, Unit 2, a l
pressurized water reactor and associated equipment (the facility) owned by the AP&L and operated by E01. The facility is l
l located in Pope County, Arkansas and is described in the Final l
Safety Analysis Report as supplemented and amended (Amendments 20 through 47) and the Environmental Report as supplemented and amended (Amendments 1 through 7).
B.
Subject to the Conditions and requirements incorporated herein, the Commission hereby licenses:
l (1) EDI, pursuant to Section 103 of the Act and 10 CFR Part 50, l
" Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Pope County, Arkansas in accordance with the procedures and limitations set forth in this amended license; 2
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(2) -AP&L, pursuant to the Act and 10 CFR Part 50, to possess the facility at the designated location in Pope County, Arkansas, in accordance with the limitations set forth in this license; (3) E0I, pursuant to the Act of 10 CFR Part 70, to receive, possess l
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; (4) EDI, 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 special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoririg equipment calibration, and as fission detectors in amounts as required; (5) EDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to l
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) E0I, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, l but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This amended license shall be deemed to contain and is subject to conditions specified in the following Commission regulations in 10 CFR Chapter.I; Part 20, Section 30.34 of part 30, Section 40.41 of part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 E01 is authorized to operate the facility at steady l
state reactor core power levels not in excess of 2815 megawatts thermal.
Prior to attaining this power level EDI shall comply with the conditions in Paragraph 2.C.(3),
(2) Technical Specifications The Technical Specification.s contained in Appendices A & B, as revised through Amendment No. 98 are hereby incorporated in the license.
EDI shall operate the facility in accordance l
with the Technical Specifications, except where otherwise stated in specific license conditions.
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(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the license-or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.
(a) " Fuel Performance" was deleted.
(b) Fire Protection E0I shall maintain in effect and fully implement all l
provisions of the approved fire protection program.
The approved fire protection program consists of the licensee's documents as follows:
Date Document Final Safety Analysis Report Section 9.5.1 through Amendment 47 dated June 16, 1978 May 17, 1977 AP&L** Letter submitting a comparison of the I
ANO-2 Fire Protection Program to Branch Technical Position 3.5-1.
August 30, 1977 AP&L Letter transmitting the Fire Hazards I
Analysis and responses to staff questions.
September 21, AP&L Letter transmitting responses to staff i
1977 questions and positions.
October 26, 1977 AP&L Letter transmitting Fire Hazards l
Analysis Information and responses to staff questions and positions.
February 3, 1978 AP&L Letter transmitting Fire Hazards l
Analysis Information February 28, AP&L Letter transmitting Administrative l
1978 Controls information.
March 31, 1978 AP&L Letter transmitting responses to I
staff questions.
April 12, 1978 AP&L Letter transmitting responses to l
staff questions and positions.
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- The original licensee authorized to possess, use, and operate the facility was AP&L.
Consequently, certain historical references to AP&L remain in the license conditions.
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m April 17, 1978 AP&L Letter transmitting responses to l
1 staff questions and positions.
April 26, 1978 AP&L Letter transmitting responses to I
staff questions and positions.
June 8, 1978 AP&L Letter transmitting affidavit for 1
previously docketed letters.
June 13, 1978 AP&L Letter transmitting Administrative l
Controls information.
June 15, 1978 AP&L Letter transmitting Administrative l
Controls information.
June 29, 1978 AP&L Letter transmitting Administrative l
l Control information.
July 7, 1978 AP&L Letter transmitting affidavit for i
previously docketed letters.
July 7, 1978 AP&L Letter transmitting Administrative l
Controls information.
July 13, 1978 AP&L Letter transmitting affidavit for l
previously docketed letters.
(c) Less Than Four Reactor Coolant Pump Operation E01 shall not operate the reactor in operational Modes 1 l
l and 2 with fewer than four reactor coolant pumps in I
operation, except as allowed by Special Test Exception 3.10.3 of the facility Technical Specifications.
(d) " Instrument Trip Setpoints Drift Allowance" was deleted.
(e) Fire Protection AP&L shall complete the following modifications by the l
j indicated dates in accordance with the staff's findings 1
as set forth in the fire protection evaluation report, NUREG-0223 " Fire Protection Safety Evaluation Report."
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Implementation Dates for Proposed Modifications Applicable Section of NUREG-0223 Date 3.1 Portable Radio Communication Equipment March 31, 1979 3.2 Separation of Power Cables in Manholes 3.3 Protection from Water Spray 3.4 Protection of Redundant Cables in the MCC Room (2096-M)
December 30, 1978
- 3. 5 Protection of Redundant Cables in the Hallway - Elevation 372 (2109-U) 3.6 Protection of Redundant Cables in the Cable Spreading Room (2098-L) 3.7 Protection of Redundant Cables in the Switchgear Room (2100-Z) 3.8 Protection of Redundant Cables in the Electrical Equipment Room (2091-BB)
September 30, 1978 3.9 Protection of Redundant Cables in the Lower South Electrical Penetration Room (2111-T)
September 30, 1978 3.10 Protection of Safe Shutdown Cables in the Upper South Piping Penetration Room (2084-DD)
September 30, 1978 3.11 Protection of Redundant Reactor Protection System Cables (2136-I) 3.12 Fire Dampers September 30, 1978 3.13 Portable Extinguisher for the Control Room (2199-J)
Novenber 15, 3978 3.14 Smoke Detectors j
3.15 Manual Hose Stations (2055-JJ, 2084-DD, Containment, Elev. 317' of Auxiliary Building 3.16 Portable Smoke Exhaust Equipment December 1, 1978 i
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3.17 Emergency Lighting December 1, 1978 3.18 Reactor Coolant Pump Oil Collection System
.3.19 Control of Fire Doors March 31, 1979 3.20 Administrative Control Changes December 1, 1978 I
(Numbers in parentheses refer to fire zone designations in the AP&l. fire hazards analysis.)
- Prior to startup following the first regularly scheduled refueling outage.
- Technical Specifications covering these items should be proposed not later than 90 days prior to implementation.
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ce:-;c (f)." Overpressure' Mitigating System" was deleted.
t (g) " Verification of Transient Analysis Code" was deleted.
(h)" Main.Feedwater System Modification" was deleted.
(i) Containment Radiation Monitor AP&L shall, prior to July 31, 1980 submit for Commission 1-review and approval documentation which establishes the L
adequacy of the qualifications of-the containment l:
radiation monitors located inside the containment and shall complete the installation and testing of these instruments to demonstrate that they meet the operability requirements of Technical Specification No.
3.3.3.6.
(j)f " Environmental Qualifications of Safety Related l Instrumentation" was deleted.
(k) " Core Protection Calculator System (CPCS)" was deleted.
(1) "CEA Guide Tube Surveillance Program" was deleted.
(m) " Redundant. Valve Position Indication" was deleted.
(n) " Fire Barrier Testing" was deleted.
. (o) "Offsite Power System" was deleted.
(p) Secondary Water Chemistry Monitoring E01 shall-implement a secondary water chemistry l
monitoring program using the overall plant administrative procedure " Steam Generator Water Chemistry Monitoring, Unit II", to minimize steam generator tube-degradation.
The program shall be defined in specific plant procedures and shall include:
1.
Identification of sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of data; 5.
Procedures defining corrective actions for off control point chemistry conditions; and j
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A procedure identifying the. authority responsible for the interpretation of the data,-and the sequence and timing of administrative events required to' initiate corrective action.
(4) E0I shall implement a program to reduce leakage from systems I
outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
This program shall include the following:
1.
Provicions establishing preventive maintenance and periodic visual inspection requirements,.and
'2.
Integrated leak test requirements for each system at.a frequency not to exceed refueling cycle intervals.
(5).'EDI shall implement a program which will ensure the
-l capability.to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1.
. Training of personnel, 2.
. Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
1 D.
Physical Protection E01 shall fully implement and maintain in effect all provisions of l
l the' Commission-approved physical security, guard training and
~
qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments'and Search Requirements revisions to 10 CFR 73.55 (51 i
FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 l
CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
l (a) " Arkansas Nuclear One Physical Security Plan," with revisions submitted through February 24, 1988; i
(b) " Arkansas Nuclear One Guard Training and Qualification Plan,"
l with revisions submitted through August 20, 1985; and, j
i (c) " Arkansas Nuclear One Safeguards Contingency Plan," with j
revisions submitted through May 30, 1980.
Changes made in accordance with 10 CFR 73.55 shall be implemented j
in accordance with the schedule set forth therein.
E.
This license is subject to the following additional condition for the protection of the environment:
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o, Before engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated by the Commission, E01 will prepare and record an l
environmental evaluation or such activity. When the evaluation indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated, in the Fin.il Environmental Statement (NUREG-0254) or any addendum thereto, E0I l
shall provide a written evaluation of such activitir.s and obtain prior approval from the Director, Office of Nuclea' Reactor Regulation.
F.
This license is effective as of the date of issuance and shall expire at midnight, December 6, 2012.
Roger S. Boyd, Director Date of Issuance:
September 1, 1978 10
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PROPOSED ENTERGY OPERATIONS, INC.
ORGANIZATION CHART l
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l BOARD OF DIRECTORS l l
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l l CEO & PRESIDENT l l
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l ACCOUNTING l l EXECUTIVE I
l LEGAL & l l NUCLEAR l
- l. RESOURCES &
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l l VICE PRESIDENTl l EXTERNAL l l ASSURANCE & l l' ADMINISTRATION l l TREASURER I l & CHIEF l
l AFFAIRS l
l FUEL l
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l OPERATIONS l l OPERATIONS l l OPERATIONS l l
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I NOTE:
Quality organizations for each plant have access to President & CEO and Executive Vice President and C00 on matters related to Quality.
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