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| | issue date = 08/02/2006 | | | issue date = 08/02/2006 |
| | title = Issuance of Amendment Technical Specifications Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process | | | title = Issuance of Amendment Technical Specifications Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process |
| | author name = Holland D G | | | author name = Holland D |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Forbes J S | | | addressee name = Forbes J |
| | addressee affiliation = Entergy Operations, Inc | | | addressee affiliation = Entergy Operations, Inc |
| | docket = 05000368 | | | docket = 05000368 |
| | license number = NPF-006 | | | license number = NPF-006 |
| | contact person = Holland D G, NRR/DLPM, 415-1436 | | | contact person = Holland D, NRR/DLPM, 415-1436 |
| | case reference number = TAC MC8540 | | | case reference number = TAC MC8540 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation |
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| =Text= | | =Text= |
| {{#Wiki_filter:August 2, 2006Mr. Jeffrey S. ForbesSite Vice President Arkansas Nuclear One Entergy Operations, Inc. | | {{#Wiki_filter:August 2, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. |
| 1448 S. R. 333 Russellville, AR 72801 | | 1448 S. R. 333 Russellville, AR 72801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBEINSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540) | | ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: |
| | TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBE INSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540) |
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| ==Dear Mr. Forbes:== | | ==Dear Mr. Forbes:== |
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| The Commission has issued the enclosed Amendment No. 266 to Renewed Facility OperatingLicense No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006. The amendment revises the existing steam generator tube surveillance program to beconsistent with the U.S. Nuclear Regulatory Commission's approved Technical SpecificationTask Force Standard Technical Specification Change Traveler, TSTF-449, "Steam GeneratorTube Integrity," Revision 4. TSTF-449 is part of the consolidated line item improvement process. 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 G. Holland, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-368 | | The Commission has issued the enclosed Amendment No. 266 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006. |
| | The amendment revises the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process. |
| | 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 G. 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. 266 to NPF-62. Safety Evaluationcc w/encls:See next page August 2, 2006Mr. Jeffrey S. ForbesSite Vice President Arkansas Nuclear One Entergy Operations, Inc. | | : 1. Amendment No. 266 to NPF-6 |
| | : 2. Safety Evaluation cc w/encls: See next page |
| | |
| | August 2, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc. |
| 1448 S. R. 333 Russellville, AR 72801 | | 1448 S. R. 333 Russellville, AR 72801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBEINSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540) | | ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: |
| | TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBE INSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540) |
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| ==Dear Mr. Forbes:== | | ==Dear Mr. Forbes:== |
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| The Commission has issued the enclosed Amendment No. 266 to Renewed Facility OperatingLicense No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006. The amendment revises the existing steam generator tube surveillance program to beconsistent with the U.S. Nuclear Regulatory Commission's approved Technical SpecificationTask Force Standard Technical Specification Change Traveler, TSTF-449, "Steam GeneratorTube Integrity," Revision 4. TSTF-449 is part of the consolidated line item improvement process. 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/ | | The Commission has issued the enclosed Amendment No. 266 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006. |
| Drew G. Holland, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-368 | | The amendment revises the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process. |
| | 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 G. 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. 266 to NPF-62. Safety Evaluationcc w/encls:See next pageDISTRIBUTION | | : 1. Amendment No. 266 to NPF-6 |
| :PUBLICLPLIV RFRidsNrrDorlDprEThomas, DIRSRidsRgn4MailCenter (DGraves)GHillRidsOgcRpRidsNrrDirsItsbRidsAcrsAcnwMailCenterRidsNrrDorlLpl4RidsNrrLAFeizollahiRidsNrrPMDHollandAccession No.: PKG ML062160314 (ML061940236; TS Pg ML062160471)OFFICENRR/LPL4/PMNRR/LPL4/LAOGC : NLONRR/LPL4/BCNAMEDHollandLFeizollahiMZoblerDTeraoDATE7/18/067/14/067/26/067/28/06OFFICIAL RECORD COPY ENTERGY OPERATIONS, INC.DOCKET NO. 50-368ARKANSAS NUCLEAR ONE, UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 266 Renewed License No. NPF-61.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Entergy Operations, Inc. (the licensee), dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006, 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 No. NPF-6.3.The license amendment is effective as of its date of issuance and shall be implementedwithin 90 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
| | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| | PUBLIC RidsRgn4MailCenter (DGraves) RidsAcrsAcnwMailCenter LPLIV RF GHill RidsNrrDorlLpl4 RidsNrrDorlDpr RidsOgcRp RidsNrrLAFeizollahi EThomas, DIRS RidsNrrDirsItsb RidsNrrPMDHolland Accession No.: PKG ML062160314 (ML061940236; TS Pg ML062160471) |
| | OFFICE NRR/LPL4/PM NRR/LPL4/LA OGC : NLO NRR/LPL4/BC NAME DHolland LFeizollahi MZobler DTerao DATE 7/18/06 7/14/06 7/26/06 7/28/06 OFFICIAL RECORD COPY |
| | |
| | ENTERGY OPERATIONS, INC. |
| | DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. NPF-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, as supplemented by letters dated May 11 and June 19, 2006, 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 No. NPF-6. |
| | : 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 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 Specifications and Renewed Facility Operating LicenseDate of Issuance: August 2, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 266RENEWED FACILITY OPERATING LICENSE NO. NPF-6DOCKET NO. 50-368Replace page 3 of the Renewed Facility Operating License No. NPF-6 with the attached revised page 3.Replace the following pages of the Appendix A Technical Specifications with the attached revisedpages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVEINSERT1-31-31-41-4 3/4 4-63/4 4-6 3/4 4-143/4 4-14 3/4 4-14a3/4 4-14a 6-86-8 6-96-9 6-10---- | | Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 2, 2006 |
| 6-11---- | | |
| 6-12---- | | ATTACHMENT TO LICENSE AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace page 3 of the Renewed Facility Operating License No. NPF-6 with the attached revised page 3. |
| 6-13---- | | Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| 6-226-22 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 266 TORENEWED FACILITY OPERATING LICENSE NO. NPF-6ENTERGY OPERATIONS, INC.ARKANSAS NUCLEAR ONE, UNIT NO. 2DOCKET NO. 50-36 | | REMOVE INSERT 1-3 1-3 1-4 1-4 3/4 4-6 3/4 4-6 3/4 4-14 3/4 4-14 3/4 4-14a 3/4 4-14a 6-8 6-8 6-9 6-9 6-10 ---- |
| | 6-11 ---- |
| | 6-12 ---- |
| | 6-13 ---- |
| | 6-22 6-22 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 266 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 application dated September 19, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052760279), as supplemented by letters dated May 11 (ADAMS Accession No. ML061380106) and June 19, 2006 (ADAMS Accession No. ML061780153), Entergy Operations, Inc. (the licensee) requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2. The supplements dated May 11 and June 19, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 3, 2006 (71 FR 147). |
| | The proposed changes would revise the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, "Steam Generator Tube Integrity," and the model safety evaluation (SE) prepared by the Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298), under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases. |
| | |
| | ==2.0 REGULATORY EVALUATION== |
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| | The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model SE published in the Federal Register on March 2, 2005 (70 FR 10298). The "Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process" was published in the Federal Register on May 6, 2005 (70 FR 24126), which made the model application available to licensees for use. |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
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| | In its September 19, 2005, application and May 11 and June 19, 2006, letters, the licensee proposed changes to the TSs that are consistent with the proposed changes approved in TSTF-449. The NRC model SE provides a detailed evaluation of the proposed changes that are requested by the licensee in its application. Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of IDENTIFIED LEAKAGE and PRESSURE BOUNDARY LEAKAGE in TS 1.14 and 1.16, respectively, (2) a revised TS 3.4.6.2, "Reactor Coolant System Operational Leakage," (3) a revised TS 3/4.4.5, "Steam Generator (SG) Tube Integrity," (4) a revised TS 6.5.9, "Steam Generator (SG) Program," and (5) a revised TS 6.6.7, "Steam Generator Tube Inspection Report." The NRC staff reviewed the licensee's application and found it to be consistent with TSTF-449. |
| | 3.1 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provide reasonable assurance that the SGs can be operated safely without an increase in risk. |
| | The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained. |
| | Failure to meet the performance criteria will be reportable pursuant to the requirements in Parts 50.72 and 50.73 of Title 10 of the Code of Federal Regulations (10 CFR). The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented. |
| | In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its September 19, 2005, application as supplemented by its May 11 and June 19, 2006, letters, conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety. |
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| | ==4.0 STATE CONSULTATION== |
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| ==81.0INTRODUCTION==
| | 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. |
| By application dated September 19, 2005 (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML052760279), as supplemented by letters dated May 11 (ADAMS Accession No. ML061380106) and June 19, 2006 (ADAMS Accession No. ML061780153), Entergy Operations, Inc. (the licensee) requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2. The supplements dated May 11 and June 19, 2006, provided additional information that clarified the application, did not expandthe scope of the application as originally noticed, and did not change the staff's originalproposed no significant hazards consideration determination as published in the FederalRegister on January 3, 2006 (71 FR 147). The proposed changes would revise the existing steam generator (SG) tube surveillanceprogram to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, "Steam Generator Tube Integrity," and the model safety evaluation (SE) prepared by the NuclearRegulatory Commission (NRC) and published in the Federal Register on March 2, 2005(70 FR 10298), under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SGtube integrity), changes to the SG reporting requirements, and associated changes to the TSBases.
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| ==2.0REGULATORY EVALUATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| The background, description, and applicability of the proposed changes associated with theSG tube integrity issue and the applicable regulatory requirements were included in the NRCstaff's model SE published in the Federal Register on March 2, 2005 (70 FR 10298). The"Notice of Availability of Model Application Concerning Technical Specification; Improvement ToModify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated LineItem Improvement Process" was published in the Federal Register on May 6, 2005(70 FR 24126), which made the model application available to licensees for use.
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| ==3.0TECHNICAL EVALUATION==
| | The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published January 3, 2006 (71 FR 147). 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 its September 19, 2005, application and May 11 and June 19, 2006, letters, the licenseeproposed changes to the TSs that are consistent with the proposed changes approved inTSTF-449. The NRC model SE provides a detailed evaluation of the proposed changes thatare requested by the licensee in its application. Consistent with TSTF-449, the proposed TSchanges include: (1) a revised definition of IDENTIFIED LEAKAGE and PRESSURE BOUNDARY LEAKAGE in TS 1.14 and 1.16, respectively, (2) a revised TS 3.4.6.2, "ReactorCoolant System Operational Leakage," (3) a revised TS 3/4.4.5, "Steam Generator (SG) TubeIntegrity," (4) a revised TS 6.5.9, "Steam Generator (SG) Program," and (5) a revised TS 6.6.7,"Steam Generator Tube Inspection Report." The NRC staff reviewed the licensee's applicationand found it to be consistent with TSTF-449. 3.1ConclusionThe proposed TS changes establish a programmatic, largely performance-based regulatoryframework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresseskey shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structuralmargins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provide reasonable assurance thatthe SGs can be operated safely without an increase in risk.The revised TSs will contain limited specific details concerning how the SG Program is toachieve the required objective of maintaining tube integrity; the intent being that the licenseewill have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on theestablishment and implementation of the SG Program such as to provide reasonable assurancethat tube integrity will be maintai ned.Failure to meet the performance criteria will be reportable pursuant to the requirements inParts 50.72 and 50.73 of Title 10 of the Code of Federal Regulations (10 CFR). The NRCreactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.In conclusion, the NRC staff finds that the TS changes proposed by the licensee in itsSeptember 19, 2005, application as supplemented by its May 11 and June 19, 2006, letters,conform to the requirements of 10 CFR 50.36 and establish a TS framework that will providereasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.
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| ==4.0STATE CONSULTATION== | | ==6.0 CONCLUSION== |
| 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==
| | The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| 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. The NRC staff hasdetermined that the amendment involves no significant increase in the amounts, and nosignificant change in the types, of any effluents that may be released offsite, and that there isno 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 published January 3, 2006 (71 FR 147). Accordingly, the amendment meets the eligibilitycriteria 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== | | ==7.0 REFERENCES== |
| 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 the amendment will not be inimical to thecommon defense and security or to the health and safety of the public.
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| ==7.0REFERENCES==
| | A complete list of references used to complete this review can be found in the NRCs model SE published in the Federal Register on March 2, 2005 (70 FR 10298). |
| A complete list of references used to complete this review can be found in the NRC's model SEpublished in the Federal Register on March 2, 2005 (70 FR 10298).Principal Contributor: Eric M. Thomas Date: August 2, 2006 Arkansas Nuclear One cc: | | Principal Contributor: Eric M. Thomas Date: August 2, 2006 |
| Senior Vice President & Chief Operating Officer Entergy Operations, Inc.
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| 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 Regional Administrator, Region IV |
| | & Chief Operating Officer U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 400 P. O. Box 31995 Arlington, TX 76011-8064 Jackson, MS 39286-1995 County Judge of Pope County Director, Division of Radiation Pope County Courthouse Control and Emergency Management Russellville, AR 72801 Arkansas Department of Health 4815 West Markham Street, Slot 30 Vice President, Operations Support Little Rock, AR 72205-3867 Entergy Operations, Inc. |
| | P. O. Box 31995 Winston & Strawn Jackson, MS 39286-1995 1700 K Street, N.W. |
| | Washington, DC 20006-3817 Wise, Carter, Child & Caraway P. O. Box 651 Senior Resident Inspector Jackson, MS 39205 U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847}} |
Letter Sequence Approval |
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TAC:MC8540, Steam Generator Tube Integrity (Approved, Closed) |
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Category:Letter
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Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter
ML23305A0922023-12-0707 December 2023
Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
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
ML23313A0962023-11-13013 November 2023
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
August 2, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBE INSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540)
Dear Mr. Forbes:
The Commission has issued the enclosed Amendment No. 266 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006.
The amendment revises the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process.
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 G. 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. 266 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page
August 2, 2006 Mr. Jeffrey S. Forbes Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATIONS CHANGE TO STEAM GENERATOR TUBE INSERVICE INSPECTION PROGRAM USING CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MC8540)
Dear Mr. Forbes:
The Commission has issued the enclosed Amendment No. 266 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2005, as supplemented by letters dated May 11 and June 19, 2006.
The amendment revises the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process.
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 G. 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. 266 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsRgn4MailCenter (DGraves) RidsAcrsAcnwMailCenter LPLIV RF GHill RidsNrrDorlLpl4 RidsNrrDorlDpr RidsOgcRp RidsNrrLAFeizollahi EThomas, DIRS RidsNrrDirsItsb RidsNrrPMDHolland Accession No.: PKG ML062160314 (ML061940236; TS Pg ML062160471)
OFFICE NRR/LPL4/PM NRR/LPL4/LA OGC : NLO NRR/LPL4/BC NAME DHolland LFeizollahi MZobler DTerao DATE 7/18/06 7/14/06 7/26/06 7/28/06 OFFICIAL RECORD COPY
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. NPF-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, as supplemented by letters dated May 11 and June 19, 2006, 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 No. NPF-6.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 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 and Renewed Facility Operating License Date of Issuance: August 2, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace page 3 of the Renewed Facility Operating License No. NPF-6 with the attached revised page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 1-3 1-3 1-4 1-4 3/4 4-6 3/4 4-6 3/4 4-14 3/4 4-14 3/4 4-14a 3/4 4-14a 6-8 6-8 6-9 6-9 6-10 ----
6-11 ----
6-12 ----
6-13 ----
6-22 6-22
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 266 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 application dated September 19, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052760279), as supplemented by letters dated May 11 (ADAMS Accession No. ML061380106) and June 19, 2006 (ADAMS Accession No. ML061780153), Entergy Operations, Inc. (the licensee) requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2. The supplements dated May 11 and June 19, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 3, 2006 (71 FR 147).
The proposed changes would revise the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, "Steam Generator Tube Integrity," and the model safety evaluation (SE) prepared by the Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298), under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.
2.0 REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model SE published in the Federal Register on March 2, 2005 (70 FR 10298). The "Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process" was published in the Federal Register on May 6, 2005 (70 FR 24126), which made the model application available to licensees for use.
3.0 TECHNICAL EVALUATION
In its September 19, 2005, application and May 11 and June 19, 2006, letters, the licensee proposed changes to the TSs that are consistent with the proposed changes approved in TSTF-449. The NRC model SE provides a detailed evaluation of the proposed changes that are requested by the licensee in its application. Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of IDENTIFIED LEAKAGE and PRESSURE BOUNDARY LEAKAGE in TS 1.14 and 1.16, respectively, (2) a revised TS 3.4.6.2, "Reactor Coolant System Operational Leakage," (3) a revised TS 3/4.4.5, "Steam Generator (SG) Tube Integrity," (4) a revised TS 6.5.9, "Steam Generator (SG) Program," and (5) a revised TS 6.6.7, "Steam Generator Tube Inspection Report." The NRC staff reviewed the licensee's application and found it to be consistent with TSTF-449.
3.1 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provide reasonable assurance that the SGs can be operated safely without an increase in risk.
The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.
Failure to meet the performance criteria will be reportable pursuant to the requirements in Parts 50.72 and 50.73 of Title 10 of the Code of Federal Regulations (10 CFR). The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.
In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its September 19, 2005, application as supplemented by its May 11 and June 19, 2006, letters, conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.
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. 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 published January 3, 2006 (71 FR 147). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
A complete list of references used to complete this review can be found in the NRCs model SE published in the Federal Register on March 2, 2005 (70 FR 10298).
Principal Contributor: Eric M. Thomas Date: August 2, 2006
Arkansas Nuclear One cc:
Senior Vice President Regional Administrator, Region IV
& Chief Operating Officer U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 400 P. O. Box 31995 Arlington, TX 76011-8064 Jackson, MS 39286-1995 County Judge of Pope County Director, Division of Radiation Pope County Courthouse Control and Emergency Management Russellville, AR 72801 Arkansas Department of Health 4815 West Markham Street, Slot 30 Vice President, Operations Support Little Rock, AR 72205-3867 Entergy Operations, Inc.
P. O. Box 31995 Winston & Strawn Jackson, MS 39286-1995 1700 K Street, N.W.
Washington, DC 20006-3817 Wise, Carter, Child & Caraway P. O. Box 651 Senior Resident Inspector Jackson, MS 39205 U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847
