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{{#Wiki_filter: (4) EOI, 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  
{{#Wiki_filter:
 
(4)
material as sealed neutron sources for reactor startup, sealed sources for  
EOI, 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; (5)
 
EOI, 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 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)
reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) EOI, 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  
EOI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
 
: c.
nuclear material without restriction to chemical or physical form, for  
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:
 
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:
sample analysis byproduct, source or special nuclear material without  
(1)
 
Maximum Power Level EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.
restriction to chemical or physical form, for sample analysis or instrument  
(2)
 
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, are hereby incorporated in the renewed license.
calibration or associated with radioactive apparatus or components; (6) EOI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be  
EOI shall operate the facility in accordance with the Technical Specifications.
 
(3)
produced by the operation of the facility.  
Safety Analysis Report The licensee's SAR supplement submitted pursuant to 10 CFR 54.21(d),
: c. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:
as revised on March 14, 2001, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than May 20, 2014.
 
(4)
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and  
Physical Protection EOI shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, Renewed License No. DPR-51 Amendment No. 233
 
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 EOI is authorized to operate the facility at steady state reactor core power  
 
levels not in excess of 2568 megawatts thermal.  
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through  
 
Amendment No. 233, are hereby incorporated in the renewed license.  
 
EOI shall operate the facility in accordance with the Technical  
 
Specifications.  
(3) Safety Analysis Report The licensee's SAR supplement submitted pursuant to 10 CFR 54.21(d),
as revised on March 14, 2001, describes certain future inspection  
 
activities to be completed before the period of extended operation. The  
 
licensee shall complete these activities no later than May 20, 2014.  
(4) Physical Protection EOI shall fully implement and maintain in effect all provisions of the  
 
Commission-approved physical security, training and qualification, Renewed License No. DPR-51 Amendment No. 233 Reactor Building Spray and Cooling System 3.6.5 ANO-1 3.6.5-3 Amendment No. 215 , 233 SURVEILLANCE REQUIREMENTS SURVEILLANCE  FREQUENCY SR  3.6.5.1 Verify each reactor building spray manual, power operated, and automatic valve in each required flow
 
path that is not locked, sealed, or otherwise secured
 
in position is in the correct position.
 
31 days SR  3.6.5.2 Operate each required reactor building cooling train fan unit for  15 minutes.
31 days SR  3.6.5.3 Verify each required reactor building cooling train cooling water flow rate is  1200 gpm.
31 days SR  3.6.5.4 Verify each required reactor building spray pump's developed head at the flow test point is greater than
 
or equal to the required developed head.
In accordance with
 
the Inservice
 
Testing Program
 
SR  3.6.5.5 Verify each automatic reactor building spray valve in each required flow path that is not locked, sealed, or
 
otherwise secured in position, actuates to the correct
 
position on an actual or simulated actuation signal.
18 months
 
SR  3.6.5.6 Verify each required reactor building spray pump starts automatically on an actual or simulated
 
actuation signal.
18 months
 
SR  3.6.5.7 Verify each required reactor building cooling train starts automatically on an actual or simulated
 
actuation signal.
18 months
 
SR  3.6.5.8 Verify each spray nozzle is unobstructed.


Reactor Building Spray and Cooling System 3.6.5 ANO-1 3.6.5-3 Amendment No. 215, 233 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each reactor building spray manual, power operated, and automatic valve in each required flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
31 days SR 3.6.5.2 Operate each required reactor building cooling train fan unit for 15 minutes.
31 days SR 3.6.5.3 Verify each required reactor building cooling train cooling water flow rate is 1200 gpm.
31 days SR 3.6.5.4 Verify each required reactor building spray pump's developed head at the flow test point is greater than or equal to the required developed head.
In accordance with the Inservice Testing Program SR 3.6.5.5 Verify each automatic reactor building spray valve in each required flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
18 months SR 3.6.5.6 Verify each required reactor building spray pump starts automatically on an actual or simulated actuation signal.
18 months SR 3.6.5.7 Verify each required reactor building cooling train starts automatically on an actual or simulated actuation signal.
18 months SR 3.6.5.8 Verify each spray nozzle is unobstructed.
Following maintenance which could result in nozzle blockage}}
Following maintenance which could result in nozzle blockage}}

Latest revision as of 16:31, 14 January 2025

License Page 3 & Technical Specifications for Issuance of Amendment No. 233 Containment Spray Nozzle Technical Specification Test Requirements
ML081540246
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/09/2008
From:
NRC/NRR/ADRO/DORL/LPLIV
To:
Wang, A B, NRR/DORL/LPLIV, 415-1445
Shared Package
ML081540109 List:
References
TAC MD8310
Download: ML081540246 (2)
v • d • e


Text

(4)

EOI, 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; (5)

EOI, 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 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)

EOI, pursuant to the Act and 10 CFR Parts 30 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 renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:

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 EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, are hereby incorporated in the renewed license.

EOI shall operate the facility in accordance with the Technical Specifications.

(3)

Safety Analysis Report The licensee's SAR supplement submitted pursuant to 10 CFR 54.21(d),

as revised on March 14, 2001, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than May 20, 2014.

(4)

Physical Protection EOI shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, Renewed License No. DPR-51 Amendment No. 233

Reactor Building Spray and Cooling System 3.6.5 ANO-1 3.6.5-3 Amendment No. 215, 233 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each reactor building spray manual, power operated, and automatic valve in each required flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

31 days SR 3.6.5.2 Operate each required reactor building cooling train fan unit for 15 minutes.

31 days SR 3.6.5.3 Verify each required reactor building cooling train cooling water flow rate is 1200 gpm.

31 days SR 3.6.5.4 Verify each required reactor building spray pump's developed head at the flow test point is greater than or equal to the required developed head.

In accordance with the Inservice Testing Program SR 3.6.5.5 Verify each automatic reactor building spray valve in each required flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

18 months SR 3.6.5.6 Verify each required reactor building spray pump starts automatically on an actual or simulated actuation signal.

18 months SR 3.6.5.7 Verify each required reactor building cooling train starts automatically on an actual or simulated actuation signal.

18 months SR 3.6.5.8 Verify each spray nozzle is unobstructed.

Following maintenance which could result in nozzle blockage

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