ML112850265
| ML112850265 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/28/2011 |
| From: | Lynnea Wilkins Plant Licensing Branch IV |
| To: | O'Grady B Nebraska Public Power District (NPPD) |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| TAC ME4974 | |
| Download: ML112850265 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 28, 2011 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - ISSUANCE OF AMENDMENT RE: NON CONSERVATIVE BATrERY TERMINAL VOLTAGE ON FLOAT CHARGE AND SPECIFIC GRAVITY ACCEPTANCE CRITERIA IN TECHNICAL SPECIFICATION (TAC NO. ME4974)
Dear Mr. O'Grady:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 239 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 29, 2010, as supplemented by letters dated June 10 and August 31,2011.
The amendment revises the acceptance criteria in CNS TS 3.8.4, "DC [Direct Current]
Sources - Operating," Surveillance Requirement (SR) 3.8.4.1, and TS 3.8.6, "Battery Cell Parameters," Table 3.8.6-1, "Battery Cell Parameter Requirements." Specifically, the amendment revises the acceptance criteria in TS SR 3.8.4.1 and TS Table 3.8.6-1 by revising the battery terminal voltage on float charge and specific gravity acceptance criteria to ensure that the safety-related batteries can perform their safety functions and will remain operable during postulated design basis events.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
- ?~l Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
- 1. Amendment No. 239 to DPR-46
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 239 License No. DPR-46
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nebraska Public Power District (the licensee),
dated October 29,2010, as supplemented by letters dated June 10 and August 31,2011, 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; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-46 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. DPR-46 and Technical Specifications Date of Issuance: October 28, 2011
ATIACHMENT TO LICENSE AMENDMENT NO. 239
.RENEWED FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Renewed Facility Operating License No. DPR-46 and Appendix A Technical Specifications with the enclosed revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT
-3 Technical Specifications REMOVE INSERT 3.8-17 3.8-17 3.8-25 3.8-25
- 3 (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 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2419 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 239, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, 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 combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Cooper Nuclear Station Safeguards Plan," submitted by letter dated May 17, 2006.
NPPD shall fully implement and maintain in effect all provisions of the Commission approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NPPD CSP was approved by License Amendment No. 238.
(4) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Cooper Nuclear Station (CNS) Updated Safety Analysis Report and as approved in the Safety Evaluations dated November 29,1977; May 23,1979; November 21, 1980; April 29, 1983; April 16, 1984; June 1,1984; January 3,1985; August 21,1985; April 10, 1986; September 9,1986; November 7,1988; February 3,1989; August 15,1995; and July 31, 1998, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 239
DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage on float charge is: 7 days
- a. ~ 125.9 V for the 125 V batteries; and
- b. ~ 260.4 V for the 250 V batteries.
SR 3.8.4.2 Verify no visible corrosion at battery terminals and 92 days connectors.
OR Verify battery connection resistance meets the limits specified in Table 3.8.4-1.
SR 3.8.4.3 Verify battery cells, cell plates, and racks show no 18 months visual indication of physical damage or abnormal deterioration that degrades battery performance.
SR 3.8.4.4 Remove visible corrosion and verify battery cell to 18 months cell and terminal connections are coated with anti-corrosion material.
SR 3.8.4.5 Verify battery connection resistance meets the limits 18 months specified in Table 3.8.4-1.
SR 3.8.4.6 Verify: 18 months
- a. Each required 125 V battery charger supplies ~
200 amps at ~ 125 V for ~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and
- b. Each required 250 V battery charger supplies?
200 amps at? 250 V for? 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(continued)
Cooper 3.8-17 Amendment 239
Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)
Battery Cell Parameter Requirements PARAMETER CATEGORY A: CATEGORY B: CATEGORYC:
LIMITS FOR EACH LIMITS FOR EACH LIMITS FOR EACH DESIGNATED PILOT CONNECTED CELL CONNECTED CELL CELL Electrolyte > Minimum level > Minimum level Above top of Level indication mark, and indication mark, plates, and not
~ 'V4 inch above and ~ 'V4 inch above overflowing maximum level maximum level indication mark(a) indication mark(a)
Float Voltage ~ 2.13 V ~ 2.13 V > 2.10 V Specific ~ 1.205 ~ 1.200 Not more than Gravity( b)( c) 0.020 below AND average of all connected cells Average of all connected cells AND
> 1.205 Average of all connected cells
~ 1.205 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during and following equalizing charges provided it is not overflowing.
(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when on float charge and battery charging current is < 2 amps.
(c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected celJ shall be measured prior to expiration of the 7 day allowance.
Cooper 3.8-25 Amendment 239
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By application dated October 29,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103080079), as supplemented by letters dated June 10 and August 31, 2011 (ADAMS Accession Nos. ML11167A083 and ML11250A160, respectively),
Nebraska Public Power District (the licensee), submitted a license amendment request (LAR) in which it requested changes to the Technical Specifications (TSs) for Cooper Nuclear Station (CNS). The amendment would revise the acceptance criteria in CNS TS 3.8.4, "DC [Direct Current] Sources - Operating," Surveillance Requirement (SR) 3.8.4.1, and TS 3.8.6, "Battery Cell Parameters," Table 3.8.6-1, "Battery Cell Parameter Requirements." Specifically, amendment would revise the acceptance criteria in TS SR 3.8.4.1 and TS Table 3.8.6-1 by revising the battery terminal voltage on float charge and specific gravity (SG) acceptance criteria to ensure that the safety-related batteries can perform their safety functions and remain operable during postulated design basis events.
The supplemental letters provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 25, 2011 (76 FR 4386).
2.0 REGULATORY EVALUATION
2.1 System Description The electrical power system at CNS consists of various alternating current (AC) and DC systems. Two of the DC power systems are the 125 Volt (V) system and the 250 V system.
These two systems provide both motive and control power to the selected safety-related and non-safety-related equipment. The systems are designed to have sufficient independence, redundancy, and testability to perform their safety functions, assuming a single failure.
Enclosure 2
-2 Each of these systems provides two independent on-site sources of DC power for startup operation, shutdown, and the loads required for station safety. The loss of anyone source will not prevent safe shutdown of the station. The safety objective of these two systems is to provide an uninterruptible source of power to supply normal and emergency 125 V DC and 250 V DC control and power loads under all conditions.
The 125 V DC and 250 V DC systems each have two subsystems. The Division I and II 125 V DC subsystems each consist of a 125 V battery, battery charger, and distribution system.
The Division I and II 250 V DC subsystems each consist of a 250 V battery, battery charger, and distribution system. Each 125 V battery has 58 individual cells and each 250 V battery has 120 individual cells.
2.2 General Requirements Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRC's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications,"
which requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operations; (3) SRs; (4) design features; and (5) administrative controls. The regulations in 10 CFR 50.36(c)(3) specify that SRs are "requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."
The regulations in 10 CFR 50.63, "Loss of all alternating current power," require that each light water-cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout (S80).
General Design Criterion (GDC) 17, "Electric power systems," of Appendix A\ "General Design Criteria for Nuclear Power Plants," to Part 50 of 10 CFR requires, in part, that, An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components that are important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.
The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure.
The 1967 Proposed GOC as described in the CNS updated safety analysis report, Appendix F, are the licensing basis for CNS; however, the NRC staff concluded in its 1973 Safety Evaluation Report for CNS that the intent of the 1971 Final Rule for 10 CFR Part 50, Appendix A, had also been met.
- 3 The regulations in Appendix R, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," to 10 CFR Part 50 require, in part, that:
During the postfire shutdown, the reactor coolant system process variables shall be maintained within those predicted for a loss of normal [AC] power, and the fission product boundary integrity shall not be affected; i.e., there shall be no fuel clad damage, rupture of any primary coolant boundary, of rupture of the containment boundary.
NRC Regulatory Guide (RG) 1.155, "Station Blackout," August 1988 (ADAMS Accession No. ML003740034), describes an acceptable alternative method for complying with NRC regulations in 10 CFR 50.63.
Nuclear Management and Resources Council, Inc. (NUMARC) 87-00, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors,"
November 1987, provides guidance and methodologies for implementing SBO initiatives.
The Institute of Electrical and Electronics Engineers Standard 485-1983, "IEEE Standard for the Sizing of Large Stationary Type Power Plant and Substation Lead Storage Batteries," describes methods for defining the DC load and for sizing a lead-acid battery to supply that load for stationary battery applications in full float operations.
While CNS is not currently committed to NRC RG 1.129, Revision 2, "Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants,"
February 2007 (ADAMS Accession No. ML063490110), the NRC staff used this document as a technical reference during its review of this amendment. RG 1.129, Revision 2, describes a method that the NRC staff considers acceptable for use in complying with the agency's regulations with regard to the maintenance, testing, and replacement of vented lead-acid storage batteries in nuclear power plants.
3.0 TECHNICAL EVALUATION
3.1 Proposed Changes Current TS SR 3.8.4.1 states:
SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage on float charge 7 days is:
- a. .::. 125 V for the 125 V batteries; and b . .::. 250 V for the 250 V batteries.
-4 Revised TS SR 3.8.4.1 would state:
SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage on float charge 7 days is:
- a. ~ 125.9 V for the 125 V batteries; and
- b. ~ 260.4 V for the 250 V batteries.
Current TS Table 3.8.6-1, regarding Specific Gravity, states:
PARAMETER CATEGORY A: CATEGORYB: CATEGORYC:
LIMITS FOR LIMITS FOR LIMITS FOR EACH EACH EACH DESIGNATED CONNECTED CONNECTED PILOT CELL CELL CELL Specific Gravity(b)(C) ~ 1.195 ~ 1.190 Not more than 0.020 below AND average of all connected cells Average of all connected cells> AND 1.200 Average of all connected cells
~ 1.190 Revised TS Table 3.8.6-1, regarding Specific Gravity, would state:
PARAMETER CATEGORY A: CATEGORY B: CATEGORY C:
LIMITS FOR LIMITS FOR LIMITS FOR EACH EACH EACH DESIGNATED CONNECTED CONNECTED PILOT CELL CELL CELL Specific Gravity(b)(C) ~ 1.205 .:: 1.200 Not more than 0.020 below AND average of all connected cells Average of all connected cells> AND 1.205 Average of all connected cells
.:: 1.205
-5 The licensee also proposed to make conforming changes to the TS Bases.
3.2 NRC Staff Evaluation CNS Updated Safety Analysis Report (USAR), Chapter VIII, "Electrical Power Systems",
Section 6.0, "125/250 Volt DC Power Systems," describes the design of the safety-related 1251250 V DC power systems. CNS USAR Chapter VIII, Section 6.2, "Safety Design Bases,"
states that each 125 V and 250 V safety-related battery must have adequate capacity to safeguard the station until AC power sources are restored. The 125/250 V safety-related batteries must provide power for maintaining the plant in a safe hot shutdown condition in the event control room operation is prevented by fire and the alternate shutdown system is used.
The 125/250 V Division I and II safety-related batteries must provide power for a 4-hour duration during an SBO in accordance with 10 CFR 50.63, NUMARC 87-00, and RG 1.155. In addition, the Division II 125 V and 250 V safety-related batteries are required to provide power for a 4 Yl-hour duration in accordance with Appendix R to 10 CFR Part 50.
SR 3.8.4.1 requires verification of battery terminal voltage while on float charge to ensure the adequacy of the charging system and the ability of the batteries to perform their intended safety function. Based on its evaluation and calculation, the licensee determined that the current battery terminal voltage on float charge acceptance criteria in the TS SR 3.8.4.1 is non-conservative. At CNS, the battery cells are deSigned for a nominal electrolyte SG of 1.215.
The corresponding minimum cell float voltage for the nominal SG of 1.215 is 2.17 V per cell.
The licensee's evaluation determined that the correct battery terminal voltage on float charge would be 125.9 V and 260.4 V, respectively, based on the total number of battery cells (Le.,
58 cells in a 125 V DC subsystem and 120 cells in a 250 V DC subsystem) and the battery design data. The NRC staff reviewed the above evaluation and concludes that the proposed acceptance criteria for battery terminal voltage on float charge will ensure that the battery is maintained in a fully-charged state. Maintaining the battery in a fully-charged state provides assurance that the battery will be capable of performing its safety functions. Based on the above, the NRC staff concludes that the proposed change to TS SR 3.8.4.1 is acceptable.
The licensee stated that the current CNS TS Table 3.8.6-1 includes non-conservative battery electrolyte SG acceptance criteria. Specifically, the current TS Table 3.8.6-1 SG values
(<:: 1.195 for Category A, <:: 1.190 and> 1.200 for Category B, and <:: 1.190 for Category C) do not represent the limits necessary to demonstrate that sufficient capacity exists for the safety related batteries to perform their intended safety functions. The proposed values (<:: 1.205 for Category A, ;;:: 1.200 and> 1.205 for Category B, and;;:: 1.205 for Category C) have been incorporated into the licensee's DC Load Flow Analysis. The licensee stated that the consideration of the correct SG limits resulted in an average SG value (1.205) less than the low end (1.210) of the nominal SG range (1.2151: 0.005) that required a derating of the battery capacity from 100 percent to 96 percent. According to the licensee, this reduced battery capacity of 96 percent is already included in the design margin factor consideration in the battery-sizing calculation. By letter dated June 10, 2011, in response to the NRC staff's request for additional information (RAI) dated May 13, 2011 (ADAMS Accession No. ML111320511), the licensee stated that it consulted the battery manufacturer who provided an engineering estimate of battery capacity of 96 percent of rated capacity based on the average SG. The licensee analyzed both divisions of the 125 V and 250 V DC safety-related systems using nuclear qualified Electrical Power Systems DeSign, Simulation and Analytic (EDSA) software and concluded that the proposed SG values would ensure that the 125 V and 250 V DC safety
- 6 related systems would be able to meet electrical requirements and perform their safety functions to ensure safe shutdown and for maintaining the plant in safe shutdown mode. In addition, the licensee also evaluated SBO scenarios and Appendix R fire scenarios (Division II only for Appendix R) and found the scenarios bounded by the load flow analyses and the proposed SG values. By letter dated August 31, 2011, the licensee provided a copy of the battery manufacturer's estimate of the battery capacity based on the average SG. The NRC staff verified that the battery capacity would be 96 percent using the average SG values.
The CNS safety-related batteries are sized in accordance with Institute of Electrical and Electronics Engineers Standard 485-1983, "IEEE Standard for the Sizing of Large Stationary Type Power Plant and Substation Lead Storage Batteries." Based on the CNS battery design, the minimum required battery capacity is 90 percent or greater of the manufacturer nameplate rating. Since the proposed TS SG acceptance limits correspond to battery capacity that is higher than the minimum CNS required capacity, the NRC staff concludes that the proposed change to TS Table 3.8.6-1 will restore conservatism to the battery SG acceptance limits and will ensure that the safety-related batteries will perform their safety functions. Based on the above, the NRC concludes that the proposed change to TS Table 3.8.6-1 is acceptable.
3.3 NRC Staff Conclusion
The NRC staff reviewed the licensee's proposed changes to CNS TS SR 3.8.4.1 for battery terminal voltage on float charge and TS Table 3.8.6-1 for the SG acceptance criteria. The NRC staff concludes that the proposed changes to CNS TS SR 3.8.4.1 and TS Table 3.8.6-1 provide reasonable assurance of the continued availability of the required DC electrical power to shut down the reactor and to maintain the reactor in a safe condition after an anticipated operational occurrence or postulated design-basis events. The amendment corrects the non-conservative minimum battery float voltage acceptance criteria in TS SR 3.8.4.1 and the non-conservative battery electrolyte SG acceptance criteria in TS Table 3.8.6-1. The staff concludes that the proposed changes are conservative, consistent with the CNS deSign basis, and consistent with the battery manufacturer's recommendation and are, therefore, acceptable. Furthermore, the NRC staff concludes that the proposed TS changes are in accordance with 10 CFR 50.36 and 10 CFR 50.63, and meet the intent of GDC 17, and the guidance in RG 1.129, RG 1.155, and NUMARC 87-00. Therefore, the NRC staff concludes that the proposed changes are acceptable.
The NRC staff has no objection to the licensee's proposed changes to the TS Bases.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no
-7 significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on January 25, 2011 (76 FR 4386). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: P. Sahay Date: October 28, 2011
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