ML073330006
| ML073330006 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (DPR-051, NPF-006) |
| Issue date: | 02/04/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Wang, A B, NRR/DORL/LPLIV, 415-1445 | |
| Shared Package | |
| ML073330004 | List: |
| References | |
| TAC MD5379, TAC MD5380 | |
| Download: ML073330006 (7) | |
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. 231, 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. 231
3 (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 or instrument calibration or associated with radioactive apparatus or components; and (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 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 EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 274 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
Exemptive 2nd paragraph of 2.C.2 deleted per Amendment 20, 3/3/81.
(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 issuance of the renewed license or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
2.C.(3)(a) Deleted per Amendment 24, 6/19/81.
Renewed License No. NPF-6 Amendment No. 274 Revised by letter dated July 18, 2007
Distribution Systems - Shutdown 3.8.10 ANO-1 3.8.10-1 Amendment No. 215, 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and 120 VAC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE by the following specifications:
LCO 3.3.9, "Source Range Neutron Flux,"
LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits,"
LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled, LCO 3.4.8, "RCS Loops - MODE 5, Loops Not Filled, LCO 3.4.11, "Low Temperature Overpressure Protection (LTOP)
System,"
LCO 3.7.9, "Control Room Emergency Ventilation System (CREVS),"
LCO 3.7.10, "Control Room Emergency Air Conditioning System (CREACS),
LCO 3.9.2, "Nuclear Instrumentation," for one monitor, LCO 3.9.4, "Decay Heat Removal (DHR) and Coolant Circulation - High Water Level," and LCO 3.9.5, "Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level."
APPLICABILITY:
MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE--------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more required AC, DC, or 120 VAC vital bus electrical power distribution subsystems inoperable.
A.1 Declare associated supported required feature(s) inoperable.
OR A.2.1 Suspend CORE ALTERATIONS.
AND Immediately Immediately 231
Programs and Manuals 5.5 ANO-1 5.0-20 Amendment No. 215, 5.0 ADMINSTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.10 Secondary Water Chemistry This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation. The program shall include:
- a.
Identification of a sampling schedule for the critical variables and control points for these variables;
- b.
Identification of the procedures used to measure the values of the critical variables;
- c.
Identification of process sampling points;
- d.
Procedures for the recording and management of data;
- e.
Procedures defining corrective actions for all off control point chemistry conditions; and
- f.
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.
5.5.11 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safeguards (ES) ventilation systems filters at the frequencies specified in Regulatory Guide 1.52, Revision 2. The VFTP is applicable to the Penetration Room Ventilation System (PRVS), and the Control Room Emergency Ventilation System (CREVS).
- a.
Demonstrate that an inplace cold DOP test of the high efficiency particulate (HEPA) filters shows:
1.
t 99% DOP removal for the PRVS when tested at the system design flowrate of 1800 scfm r 10%; and 2.
t 99.95% DOP removal for the CREVS when tested in accordance with Regulatory Guide 1.52, Revision 2, at the system design flowrate of 2000 cfm r 10%.
231
Programs and Manuals 5.5 ANO-1 5.0-21 Amendment No. 215, 5.0 ADMINSTRATIVE CONTROLS 5.5 Programs and Manuals
- b.
Demonstrate that an inplace halogenated hydrocarbon test of the charcoal adsorbers shows:
1.
t 99% halogenated hydrocarbon removal for the PRVS when tested at the system design flowrate of 1800 cfm r 10%; and 2.
t 99.95% halogenated hydrocarbon removal for the CREVS when tested in accordance with Regulatory Guide 1.52, Revision 2, at the system design flowrate of 2000 cfm r 10%.
- c.
Demonstrate that a laboratory test of a sample of the charcoal adsorber meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30°C and 95% relative humidity for a methyl iodide penetration of:
1.
5% for the PRVS; and
- 2.
when obtained as described in Regulatory Guide 1.52, Revision 2, for CREVS i.
d 2.5% for 2 inch charcoal adsorber beds; and ii.
d 0.5% for 4 inch charcoal adsorber beds.
- d.
Demonstrate for the PRVS and CREVS, that the pressure drop across the combined HEPA filters, other filters in the system, and the charcoal adsorbers is < 6 inches of water when tested at the following system design flowrates r 10%:
PRVS 1800 cfm CREVS 2000 cfm The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
231
ARKANSAS - UNIT 2 3/4 9-11 Amendment No.
Next Page is 3/4 9-14 REFUELING OPERATIONS SPENT FUEL POOL WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.
APPLICABILITY:
Whenever irradiated fuel assemblies are in the spent fuel pool.
ACTION:
With the requirement of the specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel pool areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.10 The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the spent fuel pool.
274
ARKANSAS - UNIT 2 6-15 Amendment No. 255, ADMINISTRATIVE CONTROLS 6.5.11 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safeguards (ES) ventilation systems filters at the frequencies specified in Regulatory Guide 1.52, Revision 2. The VFTP is applicable to the Control Room Emergency Ventilation System (CREVS).
- a.
Demonstrate that an inplace cold DOP test of the high efficiency particulate (HEPA) filters shows t 99.95% DOP removal when tested in accordance with Regulatory Guide 1.52, Revision 2, at the system design flowrate of 2000 cfm r 10%.
- b.
Demonstrate that an inplace halogenated hydrocarbon test of the charcoal adsorbers shows t 99.95% halogenated hydrocarbon removal when tested in accordance with Regulatory Guide 1.52, Revision 2, at the system design flow rate of 2000 cfm r 10%.
- c.
Demonstrate that a laboratory test of a sample of the charcoal adsorber meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30 °C and 95% relative humidity for a methyl iodide penetration of:
1.
d 2.5% for 2 inch charcoal adsorber beds, and 2.
d 0.5% for 4 inch charcoal adsorber beds, when obtained as described in Regulatory Guide 1.52, Revision 2.
- d.
Demonstrate that the pressure drop across the combined HEPA filters, other filters in the system, and charcoal adsorbers is < 6 inches of water when tested at the following system design flowrate of 2000 cfm r 10%.
The provision of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.
274