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| {{#Wiki_filter:May 30, 2006Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. | | {{#Wiki_filter:May 30, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. |
| 1448 S. R. 333 Russellville, AR 72802 | | 1448 S. R. 333 Russellville, AR 72802 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENTRE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUMTEMPERATURE FOR CRITICALITY (TAC NO. MC8539) | | ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUM TEMPERATURE FOR CRITICALITY (TAC NO. MC8539) |
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| ==Dear Mr. Forbes:== | | ==Dear Mr. Forbes:== |
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| The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to RenewedFacility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to theTechnical Specifications (TSs) in response to your application dated September 19, 2005. | | The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated September 19, 2005. |
| The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 byraising the minimum temperature for criticality from the current value of 525 oF to 540 oF, tochange the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace thecurrent statement in Surveillance Requirement 4.1.1.5 with wording consistent withNUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants." A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will beincluded in the Commission's next biweekly Federal Register notice.Sincerely,/RA/Drew Holland, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-368 | | The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement 4.1.1.5 with wording consistent with NUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants." |
| | 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. |
| | Sincerely, |
| | /RA/ |
| | Drew Holland, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 264 to NPF-6 2. Safety Evaluationcc w/encls: See next page May 30, 2006Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. | | : 1. Amendment No. 264 to NPF-6 |
| | : 2. Safety Evaluation cc w/encls: See next page |
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| | May 30, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. |
| 1448 S. R. 333 Russellville, AR 72802 | | 1448 S. R. 333 Russellville, AR 72802 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENTRE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUMTEMPERATURE FOR CRITICALITY (TAC NO. MC8539) | | ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUM TEMPERATURE FOR CRITICALITY (TAC NO. MC8539) |
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| ==Dear Mr. Forbes:== | | ==Dear Mr. Forbes:== |
| The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to RenewedFacility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to theTechnical Specifications (TSs) in response to your application dated September 19, 2005. | | |
| The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 byraising the minimum temperature for criticality from the current value of 525 oF to 540 oF, tochange the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace thecurrent statement in Surveillance Requirement 4.1.1.5 with wording consistent withNUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants." A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will beincluded in the Commission's next biweekly Federal Register notice.Sincerely,/RA/Drew Holland, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-368 | | The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated September 19, 2005. |
| | The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement 4.1.1.5 with wording consistent with NUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants." |
| | 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. |
| | Sincerely, |
| | /RA/ |
| | Drew Holland, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 264 to NPF-6 2. Safety Evaluationcc w/encls: See next pageDISTRIBUTION | | : 1. Amendment No. 264 to NPF-6 |
| :PUBLICRidsOgcRpRidsNrrDorlDpr LPLIV ReadingRidsAcrsAcnwMailCenterGHill (2)RidsNrrDorlLplgRidsNrrDirsItsbYOrechwa RidsNrrPMDHollandRidsRgn4MailCenter (DGraves)RidsNrrLADJohnson Accession Nos.: (Amd) ML060830023 (TS)ML061500260 (Pkg)ML060830026 OFFICENRR/LPL4/PMNRR/LPL4/LAOGCNRR/LPL4/BCNAMEDHollandDJohnsonPMoulding (NLO w/cmts)DTeraoDATE5/25/065/25/065/26/065/30/06OFFICIAL RECORD COPY ENTERGY OPERATIONS, INC.DOCKET NO. 50-368ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 264 Renewed License No. NFP-6 1.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Entergy Operations, Inc. (the licensee) dated September 19, 2005, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense 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 theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and Paragraph 2.c.(2) of Renewed Facility Operating License NFP-6 is hereby amended to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 264 , are hereby incorporated in the renewed license.
| | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| The licensee shall operate the facility in accordance with the TechnicalSpecifications. 3.The license amendment is effective as of its date of issuance and shall be implementedwithin 30 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | PUBLIC RidsOgcRp RidsNrrDorlDpr LPLIV Reading RidsAcrsAcnwMailCenter GHill (2) |
| | RidsNrrDorlLplg RidsNrrDirsItsb YOrechwa RidsNrrPMDHolland RidsRgn4MailCenter (DGraves) |
| | RidsNrrLADJohnson Accession Nos.: (Amd) ML060830023 (TS)ML061500260 (Pkg)ML060830026 OFFICE NRR/LPL4/PM NRR/LPL4/LA OGC NRR/LPL4/BC NAME DHolland DJohnson PMoulding (NLO w/cmts) DTerao DATE 5/25/06 5/25/06 5/26/06 5/30/06 OFFICIAL RECORD COPY |
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| | ENTERGY OPERATIONS, INC. |
| | DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 264 Renewed License No. NFP-6 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Entergy Operations, Inc. (the licensee) dated September 19, 2005, 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. |
| | : 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 NFP-6 is hereby amended to read as follows: |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 264 , are hereby incorporated in the renewed 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 30 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Technical SpecificationsDate of Issuance: May 30, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. NPF-6DOCKET NO. 50-368Replace the following page of the Appendix A Technical Specifications with the attachedrevised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. RemoveInsert3/4 1-63/4 1-6 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 264 TORENEWED FACILITY OPERATING LICENSE NO. NPF-6ENTERGY OPERATIONS, INC.ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-36 | | Changes to the Technical Specifications Date of Issuance: May 30, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 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 Insert 3/4 1-6 3/4 1-6 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 264 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC. |
| | ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated September 19, 2005 (Agencywide Documents Access and Management System Accession No. ML060680651), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2 (ANO-2). |
| | The proposed changes would revise TS 3.1.1.5, Minimum Temperature for Criticality. The request proposes to change the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action Statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement (SR) 4.1.1.5 with wording consistent with NUREG-1432, Standard Technical Specifications-Combustion Engineering Plants. Changes will be made to the ANO-2 TS Bases in accordance with the TS Bases Control Program (ANO-2 TS 6.5.14). |
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| | ==2.0 REGULATORY EVALUATION== |
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| | There are no accident analyses that dictate the minimum temperature for criticality, but all low power safety analyses must assume an initial temperature limit. The regulatory requirement for the specification of a reactor coolant system (RCS) minimum temperature for criticality is set forth in 10 CFR 50.36(c)(2)(ii) Criterion 2. In accordance with 10 CFR 50.91(a)(1), the licensees license amendment request provides the NRC with the licensees analysis regarding the issue of no significant hazards with regard to the proposed changes. The applicable criteria for demonstrating that the proposed amendment involves no significant hazards considerations are stated in 10 CFR 50.92(c)(1)-(3). |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | In support of this amendment, the licensee provided its evaluation of the technical implications of the proposed change to the minimum temperature for criticality at ANO-2. The minimum temperature for criticality represents the limiting temperature at which the core design is verified to satisfy the limits on the most positive moderator temperature coefficient (MTC) specified in the TS/core operating limits report. These MTC limits, specified as TS LCO 3.1.1.4 and TS LCO 3.2.6 in the ANO-2 TS, would not change as a result of the proposed change to the |
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| | minimum temperature for criticality. The NRC staff concludes that because the proposed TS change of minimum temperature for criticality does not affect the NRC-approved analytical methods used to determine core operating limits, and because the MTC will continue to be verified over the appropriate temperature range, the current transient analyses results are bounding and remain valid. Furthermore, the reactor protective instrumentation will continue to function within its normal operating range and accuracies. |
| | The change to the Action Statement for LCO 3.1.1.5 affects only the value at which the action is initiated, namely at 540 oF rather than 525 oF. The action remains the same. |
| | The current SR does not require that the minimum temperature for criticality be monitored after criticality is achieved, unless the temperature drops below 535 oF. The proposed addition of a frequency to monitor the temperature after the reactor is critical is consistent with the frequency in SR 4.2.6, which requires the RCS cold leg temperature to be monitored at least once per 12 hours. The 12 hour frequency takes into account the indications and alarms that are continually available in the Control Room to the Operator. This change is consistent with the Revised Standard TSs for Combustion Engineering Plants contained in NUREG-1432, and the NRC staff concludes that it is acceptable. |
| | Therefore, with the proposed change, the requirement in the current SR 4.1.1.5 to check temperature at least once per 30 minutes when the reactor is critical and the RCS Tavg is less than 535 oF is no longer applicable. If RCS Tavg were to fall below the TS limit of 540 oF, the Action Statement for LCO 3.1.1.5 would require restoration of the temperature to within its limit or shutdown of the reactor. |
| | Furthermore, the current SR 4.1.1.5 to monitor temperature within 15 minutes prior to achieving criticality is redundant, because standard operating practice includes verification that TSs are satisfied prior to entering the Mode of applicability. The current Mode of applicability is Mode 1 and 2 with keff greater than or equal to 1.0. Prior to entering Mode 2 and becoming critical, the minimum temperature for criticality limit (as now proposed 540 oF) has to be met. Currently, administrative controls are in place to verify the temperature every 15 minutes during the approach to criticality. |
| | The NRC staff therefore concludes it is acceptable to replace the current requirement of the ANO-2 SR as proposed. Changes will be made to the ANO-2 TS Bases in accordance with the TS Bases Control Program (ANO-2 TS 6.5.14). |
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| ==81.0INTRODUCTION== | | ==4.0 STATE CONSULTATION== |
| By letter dated September 19, 2005 (Agencywide Documents Access and Management SystemAccession No. ML060680651), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2 (ANO-2). The proposed changes would revise TS 3.1.1.5, "Minimum Temperature for Criticality." Therequest proposes to change the current Limiting Condition for Operation (LCO) for TS 3.1.1.5by raising the minimum temperature for criticality from the current value of 525 oF to 540 o F,to change the current Action Statement for LCO 3.1.1.5 to reflect this change, and to replacethe current statement in Surveillance Requirement (SR) 4.1.1.5 with wording consistent withNUREG-1432, Standard Technical Specifications-Combustion Engineering Plants. Changeswill be made to the ANO-2 TS Bases in accordance with the TS Bases Control Program(ANO-2 TS 6.5.14).
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| ==2.0REGULATORY EVALUATION==
| | In accordance with the Commission's regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| There are no accident analyses that dictate the minimum temperature for criticality, but all lowpower safety analyses must assume an initial temperature limit. The regulatory requirement for the specification of a reactor coolant system (RCS) minimum temperature for criticality is set forth in 10 CFR 50.36(c)(2)(ii) Criterion 2. In accordance with 10 CFR 50.91(a)(1), the licensee's license amendment request provides the NRC with the licensee's analysis regardingthe issue of no significant hazards with regard to the proposed changes. The applicable criteria for demonstrating that the proposed amendment involves no significant hazards considerationsare stated in 10 CFR 50.92(c)(1)-(3).
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| ==3.0TECHNICAL EVALUATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| In support of this amendment, the licensee provided its evaluation of the technical implicationsof the proposed change to the minimum temperature for criticality at ANO-2. The minimum temperature for criticality represents the limiting temperature at which the core design is verifiedto satisfy the limits on the most positive moderator temperature coefficient (MTC) specified in the TS/core operating limits report. These MTC limits, specified as TS LCO 3.1.1.4 and TS LCO 3.2.6 in the ANO-2 TS, would not change as a result of the proposed change to the minimum temperature for criticality. The NRC staff concludes that because the proposed TSchange of minimum temperature for criticality does not affect the NRC-approved analyticalmethods used to determine core operating limits, and because the MTC will conti nue to beverified over the appropriate temperature range, the current transient analyses results are bounding and remain valid. Furthermore, the reactor protective instrumentation will conti nue tofunction within its normal operating range and accuracies.
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| The change to the Action Statement for LCO 3.1.1.5 affects only the value at which the action isinitiated, namely at 540 oF rather than 525 oF. The action remains the same.The current SR does not require that the minimum temperature for criticality be monitored aftercriticality is achieved, unless the temperature drops below 535 oF. The proposed addition of afrequency to monitor the temperature after the reactor is critical is consistent with the frequency in SR 4.2.6, which requires the RCS cold leg temperature to be monitored at least once per 12 hours. The 12 hour frequency takes into account the indications and alarms that are continually available in the Control Room to the Operator. This change is consistent with theRevised Standard TSs for Combustion Engineering Plants contained in NUREG-1432, and theNRC staff concludes that it is acceptable.Therefore, with the proposed change, the requirement in the current SR 4.1.1.5 to checktemperature at least once per 30 minutes when the reactor is critical and the RCS Tavg is less than 535 oF is no longer applicable. If RCS Tavg were to fall below the TS limit of 540 oF, theAction Statement for LCO 3.1.1.5 would require restoration of the temperature to within its limitor shutdown of the reactor.Furthermore, the current SR 4.1.1.5 to monitor temperature within 15 minutes prior to achievingcriticality is redundant, because standard operating practice includes verification that TSs are satisfied prior to entering the Mode of applicability. The current Mode of applicability is M ode 1and 2 with keff greater than or equal to 1.0. Prior to entering Mode 2 and becoming critical, theminimum temperature for criticality limit (as now proposed 540 oF) has to be met. Currently,administrative controls are in place to verify the temperature every 15 minutes during the approach to criticality.The NRC staff therefore concludes it is acceptable to replace the current requirement of theANO-2 SR as proposed. Changes will be made to the ANO-2 TS Bases in accordance with theTS Bases Control Program (ANO-2 TS 6.5.14). | | 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 and changes surveillance requirements. 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 |
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| ==4.0STATE CONSULTATION==
| | occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 72672, December 6, 2005). 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. |
| In accordance with the Commission's regulations, the Arkansas State official was notified of theproposed issuance of the amendment. The State official had no comments.
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| ==5.0ENVIRONMENTAL CONSIDERATION== | | ==6.0 CONCLUSION== |
| The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves nosignificant increase in the amounts, and no significant change in the types, of any effluents thatmay be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed findingthat the amendment involves no significant hazards consideration, and there has been nopublic comment on such finding (70 FR 72672, December 6, 2005). 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.
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| ==6.0CONCLUSION==
| | 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 this amendment will not be inimical to the common defense and security or the health and safety of the public. |
| The Commission has concluded, based on the considerations discussed above, that (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of this amendment will not be inimical to thecommon defense and security or the health and safety of the public.Principal Contributor: Y. Orechwa Date: May 30, 2006 September 2005Arkansas Nuclear One cc: Senior Vice President & Chief Operating Officer Entergy Operations, Inc. | | Principal Contributor: Y. Orechwa Date: May 30, 2006 |
| P. O. Box 31995 Jackson, MS 39286-1995Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867Winston & Strawn1700 K Street, N.W.
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| Washington, DC 20006-3817Senior Resident InspectorU.S. Nuclear Regulatory Commission
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| P. O. Box 310 London, AR 72847Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064County Judge of Pope County Pope County Courthouse Russellville, AR 72801Vice President, Operations SupportEntergy Operations, Inc. | | Arkansas Nuclear One cc: |
| P. O. Box 31995 Jackson, MS 39286-1995Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205}}
| | Senior Vice President Vice President, Operations Support |
| | & Chief Operating Officer Entergy Operations, Inc. |
| | Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1700 K Street, N.W. |
| | Washington, DC 20006-3817 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 September 2005}} |
Letter Sequence Other |
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MONTHYEARML0615002602006-05-30030 May 2006
Technical Specifications, Modification of Technical Specification 3.1.1.5, Minimum Temperature for Criticality, MC8539
Project stage: Other
ML0608300232006-05-30030 May 2006
License Amendment, Modification of Technical Specification 3.1.1.5, Minimum Temperature for Criticality, MC8539
Project stage: Other
ML0618702992006-08-0303 August 2006
Correction to Amendment No. 264 Modification of Technical Specification 3.1.1.5, Minimum Temperature for Criticality
Project stage: Other
2006-05-30
[Table View] |
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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24017A1582024-01-17017 January 2024
Submittal of Emergency Plan Revision 50
IR 05000313/20234202024-01-10010 January 2024
Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420
IR 05000313/20234022024-01-0202 January 2024
Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402
ML23354A0022023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
IR 05000313/20234052023-12-12012 December 2023
Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405
ML23341A0832023-12-11011 December 2023
Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter
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ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23325A1412023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000313/20230032023-11-21021 November 2023
Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001
ML23243B0452023-11-13013 November 2023
Request for Withholding Information from Public Disclosure
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Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000313/20230112023-10-10010 October 2023
Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011
IR 05000313/20230052023-08-21021 August 2023
Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle
IR 05000313/20243012023-08-14014 August 2023
Notification of NRC Initial Operator Licensing Examination 05000313/2024301
IR 05000313/20230022023-08-11011 August 2023
Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation
ML23209A6022023-08-0909 August 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times
IR 05000416/20230022023-08-0808 August 2023
Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001
ML23208A2132023-08-0303 August 2023
Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23208A2112023-07-27027 July 2023
Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
ML23188A1732023-07-12012 July 2023
Request for Withholding Information from Public Disclosure
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
IR 05000313/20234032023-06-28028 June 2023
Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403
ML23178A0892023-06-26026 June 2023
August 2023 Emergency Preparedness Program Inspection-Request for Information
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23180A1082023-06-20020 June 2023
ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report
IR 05000313/20234012023-06-13013 June 2023
Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401
ML23130A2972023-05-17017 May 2023
Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information
ML23121A3012023-05-10010 May 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times
ML23114A3572023-05-10010 May 2023
Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency
ML23130A2732023-05-10010 May 2023
and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000313/20230012023-05-0909 May 2023
Integrated Inspection Report 05000313/2023001 and 05000368/2023001
ML23118A3202023-05-0808 May 2023
Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010)
IR 05000368/20233012023-05-0101 May 2023
NRC Examination Report 05000368/2023301
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML23108A1362023-04-24024 April 2023
Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46
ML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
2024-01-24
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23020A9362023-01-27027 January 2023
Audit Plan to Support Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML22263A1912022-12-0909 December 2022
Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary
ML22291A2392022-10-28028 October 2022
Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI (EPID L-2021-LLA-0181) Letter
ML22165A2442022-07-19019 July 2022
Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22138A4312022-06-23023 June 2022
Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML22039A2822022-03-15015 March 2022
Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping
ML21225A0552021-12-17017 December 2021
Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program
ML21341B2262021-12-13013 December 2021
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21320A2122021-11-17017 November 2021
Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Concerning Revised Dose Calculations
ML21281A2542021-10-15015 October 2021
Audit Meeting Agenda & Audit Questions for LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization and Treatment of Structures, System, and Components for Nuclear Power Reactors (EPIDs L-2021-LLA-0105, L-2021-LLA-0106
ML21208A4492021-09-20020 September 2021
Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels
ML21088A4332021-04-14014 April 2021
Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML21027A4282021-03-23023 March 2021
Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
ML21040A5132021-03-10010 March 2021
Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values
ML20351A1532021-02-0808 February 2021
Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations
NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020
Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432
ML20135H1412020-06-30030 June 2020
Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis
ML20160A1472020-06-30030 June 2020
Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML20087L8032020-04-0808 April 2020
Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times
ML19231A2972020-01-29029 January 2020
Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump
ML19269B6722019-10-22022 October 2019
Issuance of Amendment Nos. 267 and 317 to Extend Implementation Dates for Amendment Nos. 263 and 314, Revision to Emergency Action Level Scheme
ML19220A9382019-09-27027 September 2019
Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML19098A9552019-05-22022 May 2019
Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3
ML19127A2992019-05-15015 May 2019
Correction to Amendment No. 315 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3
ML19063B9482019-04-23023 April 2019
Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3
ML18337A2472019-01-17017 January 2019
Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme
ML18317A3822018-12-19019 December 2018
Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation
ML18306A5132018-11-30030 November 2018
Issuance of Conforming Amendment Nos. 262, 312 and 215 Transfers of Renewed Facility Operating Licenses
ML18298A0122018-11-27027 November 2018
Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits
ML18260A3392018-10-24024 October 2018
Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
ML18115A2822018-06-19019 June 2018
Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267)
ML18134A2532018-06-19019 June 2018
Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268)
ML18051A5892018-02-26026 February 2018
Issuance of Amendment No. 309 to Adopt TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability (CAC No. MG0131; EPID L-2017-LLA-0302)
ML18033A1752018-02-26026 February 2018
Issuance of Amendment No. 259 to Adopt TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability (CAC No. MG0132; EPID L-2017-LLA-0301)
ML18011A0642018-01-18018 January 2018
Issuance of Amendment No. 308 to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26 (Exigent Circumstances)
ML17251A2112017-10-10010 October 2017
Issuance of Amendment No. 307 Revision of Steam Generator Technical Specifications to Reflect Adoption of Technical Specifications Task Force Traveler TSTF-510 (CAC MF9654; EPID L-2017-LLA-0222)
ML17235A5192017-10-10010 October 2017
Issuance of Amendment No. 258 Revision of Steam Generator Technical Specifications to Reflect Adoption of TSTF-510 (CAC MF9653; EPID L-2017-LLA-0221)
ML17096A2352017-05-12012 May 2017
Issuance of Amendment No. 306 Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications
ML16215A3712017-03-29029 March 2017
Issuance of Amendment No. 305 to Adopt Technical Specifications Task Force Traveler TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing...
ML16165A4232017-03-10010 March 2017
Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3,
ML16267A1392016-12-29029 December 2016
Issuance of Amendment Revise Technical Specfications to Adopt TSTF-426, to Revise or Add Actions to Preclude Entry Into Lco 3.0.3 Ritstf Initiative 6b & 6c
ML16223A4812016-10-0707 October 2016
Issuance of Amendment No. 256 Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (Cac No. MF3419)
ML16027A1092016-02-24024 February 2016
Issuance of Amendment Nos. 255 and 303 Cyber Security Plan Implementation Schedule (CAC Nos. MF6258 and MF6259)
ML15096A3812015-04-29029 April 2015
Issuance of Amendment No. 302, Revise Technical Specification Surveillance Requirement 4.1.3.1.2 Note to Eliminate Movement of Control Element Assembly 18 for Remainder of Operating Cycle 24
2024-01-24
[Table view]
Category:Safety Evaluation
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23142A1062023-05-24024 May 2023
Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML22342B1602023-01-10010 January 2023
Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027)
ML22263A1912022-12-0909 December 2022
Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary
ML22236A5452022-08-26026 August 2022
Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22138A4312022-06-23023 June 2022
Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML22039A2822022-03-15015 March 2022
Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping
ML22007A3172022-01-18018 January 2022
1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML21225A0552021-12-17017 December 2021
Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program
ML21341B2262021-12-13013 December 2021
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21208A4492021-09-20020 September 2021
Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels
ML21132A2792021-05-19019 May 2021
Request for Approval of Change to the Entergy Quality Assurance Program Manual
ML21088A4332021-04-14014 April 2021
Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML21027A4282021-03-23023 March 2021
Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
ML21040A5132021-03-10010 March 2021
Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values
ML20351A1532021-02-0808 February 2021
Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations
ML20288A8242020-11-16016 November 2020
Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020
Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432
ML20226A2722020-08-18018 August 2020
Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI
ML20160A1472020-06-30030 June 2020
Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML20135H1412020-06-30030 June 2020
Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis
ML20121A1932020-05-0606 May 2020
Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves
ML20107J3172020-04-23023 April 2020
Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
ML20087L8032020-04-0808 April 2020
Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times
ML20083J9682020-03-26026 March 2020
Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19231A2972020-01-29029 January 2020
Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump
ML19220A9382019-09-27027 September 2019
Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML19184A5542019-07-15015 July 2019
Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval
ML19156A4002019-06-11011 June 2019
Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code
ML19098A9552019-05-22022 May 2019
Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3
ML19063B9482019-04-23023 April 2019
Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3
ML18337A2472019-01-17017 January 2019
Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme
ML18346A3142019-01-0707 January 2019
Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067)
ML18317A3822018-12-19019 December 2018
Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation
ML18298A0122018-11-27027 November 2018
Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits
ML18260A3392018-10-24024 October 2018
Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
ML18192A1042018-08-15015 August 2018
Alternative to Examination of Reactor Pressure Vessel Flange Threads
ML18173A0192018-06-27027 June 2018
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (CAC MG0244; EPID L-2017-LLL-0020)
ML18115A2822018-06-19019 June 2018
Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267)
ML18134A2532018-06-19019 June 2018
Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268)
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
2024-01-24
[Table view] |
Text
May 30, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUM TEMPERATURE FOR CRITICALITY (TAC NO. MC8539)
Dear Mr. Forbes:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated September 19, 2005.
The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement 4.1.1.5 with wording consistent with NUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants."
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.
Sincerely,
/RA/
Drew Holland, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosures:
- 1. Amendment No. 264 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page
May 30, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - ISSUANCE OF AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION 3.1.1.5, MINIMUM TEMPERATURE FOR CRITICALITY (TAC NO. MC8539)
Dear Mr. Forbes:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to Renewed Facility Operating License No. NPF-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated September 19, 2005.
The amendment changes the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement 4.1.1.5 with wording consistent with NUREG-1432, "Standard Technical Specifications-Combustion Engineering Plants."
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.
Sincerely,
/RA/
Drew Holland, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosures:
- 1. Amendment No. 264 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsOgcRp RidsNrrDorlDpr LPLIV Reading RidsAcrsAcnwMailCenter GHill (2)
RidsNrrDorlLplg RidsNrrDirsItsb YOrechwa RidsNrrPMDHolland RidsRgn4MailCenter (DGraves)
RidsNrrLADJohnson Accession Nos.: (Amd) ML060830023 (TS)ML061500260 (Pkg)ML060830026 OFFICE NRR/LPL4/PM NRR/LPL4/LA OGC NRR/LPL4/BC NAME DHolland DJohnson PMoulding (NLO w/cmts) DTerao DATE 5/25/06 5/25/06 5/26/06 5/30/06 OFFICIAL RECORD COPY
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 264 Renewed License No. NFP-6
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (the licensee) dated September 19, 2005, 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.
- 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 NFP-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 264 , are hereby incorporated in the renewed 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 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 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 Insert 3/4 1-6 3/4 1-6
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 264 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By letter dated September 19, 2005 (Agencywide Documents Access and Management System Accession No. ML060680651), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2 (ANO-2).
The proposed changes would revise TS 3.1.1.5, Minimum Temperature for Criticality. The request proposes to change the current Limiting Condition for Operation (LCO) for TS 3.1.1.5 by raising the minimum temperature for criticality from the current value of $ 525 oF to $ 540 oF, to change the current Action Statement for LCO 3.1.1.5 to reflect this change, and to replace the current statement in Surveillance Requirement (SR) 4.1.1.5 with wording consistent with NUREG-1432, Standard Technical Specifications-Combustion Engineering Plants. Changes will be made to the ANO-2 TS Bases in accordance with the TS Bases Control Program (ANO-2 TS 6.5.14).
2.0 REGULATORY EVALUATION
There are no accident analyses that dictate the minimum temperature for criticality, but all low power safety analyses must assume an initial temperature limit. The regulatory requirement for the specification of a reactor coolant system (RCS) minimum temperature for criticality is set forth in 10 CFR 50.36(c)(2)(ii) Criterion 2. In accordance with 10 CFR 50.91(a)(1), the licensees license amendment request provides the NRC with the licensees analysis regarding the issue of no significant hazards with regard to the proposed changes. The applicable criteria for demonstrating that the proposed amendment involves no significant hazards considerations are stated in 10 CFR 50.92(c)(1)-(3).
3.0 TECHNICAL EVALUATION
In support of this amendment, the licensee provided its evaluation of the technical implications of the proposed change to the minimum temperature for criticality at ANO-2. The minimum temperature for criticality represents the limiting temperature at which the core design is verified to satisfy the limits on the most positive moderator temperature coefficient (MTC) specified in the TS/core operating limits report. These MTC limits, specified as TS LCO 3.1.1.4 and TS LCO 3.2.6 in the ANO-2 TS, would not change as a result of the proposed change to the
minimum temperature for criticality. The NRC staff concludes that because the proposed TS change of minimum temperature for criticality does not affect the NRC-approved analytical methods used to determine core operating limits, and because the MTC will continue to be verified over the appropriate temperature range, the current transient analyses results are bounding and remain valid. Furthermore, the reactor protective instrumentation will continue to function within its normal operating range and accuracies.
The change to the Action Statement for LCO 3.1.1.5 affects only the value at which the action is initiated, namely at 540 oF rather than 525 oF. The action remains the same.
The current SR does not require that the minimum temperature for criticality be monitored after criticality is achieved, unless the temperature drops below 535 oF. The proposed addition of a frequency to monitor the temperature after the reactor is critical is consistent with the frequency in SR 4.2.6, which requires the RCS cold leg temperature to be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> frequency takes into account the indications and alarms that are continually available in the Control Room to the Operator. This change is consistent with the Revised Standard TSs for Combustion Engineering Plants contained in NUREG-1432, and the NRC staff concludes that it is acceptable.
Therefore, with the proposed change, the requirement in the current SR 4.1.1.5 to check temperature at least once per 30 minutes when the reactor is critical and the RCS Tavg is less than 535 oF is no longer applicable. If RCS Tavg were to fall below the TS limit of 540 oF, the Action Statement for LCO 3.1.1.5 would require restoration of the temperature to within its limit or shutdown of the reactor.
Furthermore, the current SR 4.1.1.5 to monitor temperature within 15 minutes prior to achieving criticality is redundant, because standard operating practice includes verification that TSs are satisfied prior to entering the Mode of applicability. The current Mode of applicability is Mode 1 and 2 with keff greater than or equal to 1.0. Prior to entering Mode 2 and becoming critical, the minimum temperature for criticality limit (as now proposed 540 oF) has to be met. Currently, administrative controls are in place to verify the temperature every 15 minutes during the approach to criticality.
The NRC staff therefore concludes it is acceptable to replace the current requirement of the ANO-2 SR as proposed. Changes will be made to the ANO-2 TS Bases in accordance with the TS Bases Control Program (ANO-2 TS 6.5.14).
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arkansas 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 and changes surveillance requirements. 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 significant hazards consideration, and there has been no public comment on such finding (70 FR 72672, December 6, 2005). 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 this amendment will not be inimical to the common defense and security or the health and safety of the public.
Principal Contributor: Y. Orechwa Date: May 30, 2006
Arkansas Nuclear One cc:
Senior Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1700 K Street, N.W.
Washington, DC 20006-3817 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 September 2005
