ML14163A589
| ML14163A589 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  (DPR-044, DPR-056) |
| Issue date: | 07/28/2014 |
| From: | Richard Ennis Plant Licensing Branch 1 |
| To: | Pacilio M Exelon Nuclear |
| Ennis R, NRR/DORL/LPLI-2 | |
| References | |
| TAC MF3184, TAC MF3185 | |
| Download: ML14163A589 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 28, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3-ISSUANCE OF AMENDMENTS RE: DELETE NON-CONSERVATIVE NOTE FROM LIMITING CONDITION FOR OPERATION 3.5.1 (TAC NOS. MF3184AND MF3185)
Dear Mr. Pacilio:
The Commission has issued the enclosed Amendment Nos. 292 and 295 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3. These amendments consist of changes to the Technical Specifications (TSs) and Facility Operating Licenses in response to your application dated December 4, 2013.
The amendments revise TS Limiting Condition for Operation 3.5.1 to delete a note that is not conservative. The note is being deleted because plant operation, in accordance with the note, could result in potential damage to the residual heat removal system.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.
Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Amendment No. 292 to Renewed DPR-44
- 2. Amendment No. 295 to Renewed DPR-56
- 3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 292 Renewed License No. DPR-44
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated December 4, 2013, 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 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.
- 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-44 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 292, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
July 28, 2014 UCLEAR REGULATORY COMMISSION
)#~e; ert G. Schaaf, Acting Chief ant Licensing Branch 1-2 ivision of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 292 RENEWED FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 3
Insert 3
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 3.5-1 Insert 3.5-1
Page 3 (5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
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 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 292, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
(3)
Physical Protection Exelon Generation Company 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans\\ submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 283.
(4)
Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report (SER) dated May 23, 1979, and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-44 Revised by letter dated October 28, 2004 Revised by letter dated May 29, 2007 Amendment No. 292
ECCS-Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS CECCS) AND REACTOR CORE ISOLATION COOLING C RC IC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System CADS) function of five safety/relief valves shall be OPERABLE.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) is not required to be OPERABLE with reactor steam dome pressure~ 150 psig and ADS valves are not required to be OPERABLE with reactor steam dome pressure~ 100 psig.
ACTIONS
NOTE------------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable.
subsystem( s) to OPERABLE status.
OR One low pressure coolant injection CLPCI) pump in each subsystem inoperable.
B.
Required Action and 8.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
(continued)
PBAPS UNIT 2 3.5-l Amendment No. 292
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 295 Renewed License No. DPR-56
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated December 4, 2013, 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 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.
- 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-56 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
Attachment:
Changes to the Technical Specifications and Facility Operating License Dateoflssuance:
July 28, 2014 rt G. Schaaf, Acting Chief nt Licensing Branch 1-2 vision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 295 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 3
Insert 3
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 3.5-1 Insert 3.5-1
(5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
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 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications. 1 (3)
Physical Protection Exelon Generation Company 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans2, submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 283.
1Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 141h refueling outage currently scheduled for Fall 2003.
2The training and Qualification Plan and Safeguards Contingency Plan and Appendices to the Security Plan.
Page 3 Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No. 295
ECCS-Operat i ng 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCSJ AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five safety/relief valves shall be OPERABLE.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) is not required to be OPERABLE with reactor steam dome pressure$ 150 psig and ADS valves are not required to be OPERABLE with reactor steam dome pressure$ 100 psig.
ACTIONS
.-----.------------------ *- *---
- NOTE ------ *- *- *------------------ * *- * *--
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS A.l Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable.
subsystem(s) to OPERABLE status.
illi One low pressure coolant injection (LPCIJ pump in each subsystem inoperable.
B.
Required Action and B.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
(continued)
PBAPS UN IT 3 3.5-1 Amendment No. 295
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 292 AND 295 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-44 AND DPR-56 EXELON GENERATION COMPANY. LLC PSEG NUCLEAR LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278
1.0 INTRODUCTION
By application dated December 4, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13339A780), Exelon Generation Company, LLC (Exelon, the licensee), requested changes to the Technical Specifications (TSs) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.
The proposed amendment would revise TS Limiting Condition for Operation (LCO) 3.5.1, "Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC} System, ECCS - Operating," for PBAPS, Units 2 and 3, to delete the following note:
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling isolation pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
The licensee's application stated that the note is being deleted because plant operation, in accordance with the note, could result in potential damage to the RHR system.
2.0 REGULATORY EVALUATION
The construction permit for PBAPS, Units 2 and 3, was issued by the Atomic Energy Commission (AEC) on January 31, 1968. As discussed in Appendix H to the PBAPS Updated Final Safety Analysis Report (UFSAR), during the construction/licensing process, both units were evaluated against the then-current AEC draft of the 27 General Design Criteria (GDC) issued in November 1965. On July 11, 1967, the AEC published for public comment, in the Federal Register (32 FR 1 0213), a revised and expanded set of 70 draft GDC (hereinafter referred to as the "draft GDC"). Appendix H of the PBAPS UFSAR contains an evaluation of the design basis of PBAPS, Units 2 and 3, against the draft GDC. The licensee concluded that PBAPS, Units 2 and 3, conforms to the intent of the draft GDC.
On February 20, 1971, the AEC published in the Federal Register (36 FR 3255) a final rule that added Appendix A to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, "General Design Criteria for Nuclear Power Plants" (hereinafter referred to as the "final GDC").
Differences between the draft GDC and final GDC included a consolidation from 70 to 64 criteria. As discussed in the Nuclear Regulatory Commission's (NRC's) Staff Requirements Memorandum for SECY-92-223, dated September 18, 1992 (ADAMS Accession No. ML003763736), the Commission decided not to apply the final GDC to plants with construction permits issued prior to May 21, 1971. At the time of promulgation of Appendix A to 10 CFR Part 50, the Commission stressed that the final GDC were not new requirements and were promulgated to more clearly articulate the licensing requirements and practice in effect at that time. Each plant licensed before the final GDC were formally adopted was evaluated on a plant-specific basis, determined to be safe, and licensed by the Commission.
The licensees for PBAPS, Units 2 and 3, have made changes to the facility over the life of the plant that may have invoked the final GDC. The extent to which the final GDC have been invoked can be found in specific sections of the UFSAR and in other plant-specific design and licensing basis documentation.
The NRC staff identified the following draft GDCs as being applicable to the proposed amendment:
Draft GDC 44, "Emergency Core Cooling System Capability (Category A)," which requires, in part, that the emergency core cooling system (ECCS) and core be designed to prevent fuel and clad damage that would interfere with the emergency core cooling function and to limit the clad metal-water reaction to negligible amounts for all size of breaks in the reactor coolant pressure boundary.
Draft GDC 46, "Testing of Emergency Core Cooling Systems Components (Category A),"
which requires that capability be provided to periodically test the ECCS active components, such as pumps and valves, for operability and functional performance.
In 10 CFR 50.36, "Technical specifications," the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs.
As stated in 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
The regulations in 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," provide specified ECCS performance acceptance criteria.
As discussed in the PBAPS TS Bases, LCO 3.5.1 helps to ensure that the ECCS acceptance criteria stated in 10 CFR 50.46 will be met following a loss-of-coolant accident (LOCA},
assuming the worst-case single active component failure in the ECCS.
3.0 TECHNICAL EVALUATION
The safety function of the ECCS is to provide core cooling following a LOCA. The ECCS consists of two high-pressure and two low-pressure systems. The high-pressure systems are the high-pressure coolant injection (HPCI) system and the automatic depressurization system (ADS). The low-pressure systems are the LPCI mode of RHR and the core spray system.
Following a LOCA, the RHR system performs two functions as the low head portion of the ECCS:
restore and maintain the coolant inventory in the reactor vessel so that the core is adequately cooled; and provide cooling for the containment so that condensation of the steam resulting from the blowdown is ensured.
The RHR system may also be used in the shutdown cooling (SOC) mode to remove residual heat from the nuclear system to maintain reactor water inventory below 212 degrees Fahrenheit CF) so that refueling and nuclear system servicing can be performed.
The RHR system consists of four heat exchangers, four main system pumps, and four high-pressure service water pumps for each unit. The discharge piping for the SOC mode and the LPCI mode of RHR is the same piping path; however, the suction for these two functions is different. SOC takes suction from one of the recirculation loops off of the reactor pressure vessel and LPCI takes suction from the suppression pool. The RHR system contains two loops which are separated to prevent loss of the entire system and has an automatic fill system to ensure the piping is filled with water.
LCO 3.5.1 requires that each ECCS injection/spray subsystem and the ADS function of five safety/relief valves be operable. The LCO is applicable in Modes 1, 2, and 3, except that HPCI is not required to be operable with reactor steam dome pressure less than or equal to 150 pounds per square inch (psig) and ADS valves are not required to be operable with reactor steam dome pressure less than or equal to 100 psig.
Currently, the note in LCO 3.5.1 states that the LPCI subsystem may be considered operable, during alignment and operation for decay heat removal, with reactor steam dome pressure less than the RHR SOC isolation pressure in Mode 3, if capable of being manually realigned and not otherwise inoperable. The note was added as part of PBAPS, Units 2 and 3, Amendments 259 and 262, which the NRC approved on May 10, 2006 (ADAMS Accession No. ML061070292).
The addition of the note was based on TS Task Force (TSTF) change TSTF-416, Revision 0, "Clarification of LPCI Operability during Decay Heat Removal Operations." The note was intended to provide clarity that LPCI may be considered operable during alignment and operation in the decay heat removal mode.
The licensee stated that, as a result of an operating experience review of an NRC inspection report for Sequoyah Nuclear Plant dated April 30, 2012 (ADAMS Accession No. ML12122A885), it was identified that PBAPS may be susceptible to a similar condition as Sequoyah involving the potential for water hammer in the RHR system. Specifically, an engineering evaluation at PBAPS determined that during operation in Mode 3 (hot shutdown), if a design-basis LOCA occurred, the potential exists for water in the suction piping for the ECCS pumps to flash or boil and prevent the pumps from operating properly. This is possible during swapover from SOC to LPCI because the physical arrangement of the SOC and LPCI suction lines for the RHR pumps may allow high temperature water to flash when introduced to low pressure suction lines. Suction alignment for SOC is from the recirculation loops off the reactor pressure vessel which is at reactor pressure while the LPCI suction alignment is from the low-pressure suppression pool. This threat is greatest during the beginning of Mode 3 when the water temperatures are highest. The licensee stated that actions were promptly put in place at PBAPS to not declare the LPCI mode operable (or attempt to use the LPCI mode), when the potential for water to flash or boil exists, even though the note for LCO 3.5.1 would allow operability. As such, the licensee stated that the removal of the note is appropriate.
Based on the above, the NRC staff finds that the current note in LCO 3.5.1 could potentially allow operating conditions to exist that could adversely impact the function of the RHR system.
As such, the staff finds that removal of the note is acceptable.
The licensee's application dated December 4, 2013, provided revised TS Bases pages to be implemented with the associated TS changes. These pages were provided for information only.
Changes to the TS Bases would be made in accordance with the TS Bases Control Program.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change 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 amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (79 FR 12245). Accordingly, the amendments meet 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 amendments.
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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: D. Woodyatt R. Ennis Date: July 28, 2014
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