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| {{#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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| ==Dear Mr. Forbes:== | | ==Dear Mr. Forbes:== |
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| The Commission has issued the enclosed Amendment No. 265 to Facility Operating LicenseNo. 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 will modify ANO-2 Surveillance Requirement TS 3.1.1.4, "ModeratorTemperature Coefficient," and will allow the use of WCAP-16011-P-A, "Startup Test ActivityReduction Program."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. 265 to 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 will modify ANO-2 Surveillance Requirement TS 3.1.1.4, Moderator Temperature Coefficient, and will allow the use of WCAP-16011-P-A, Startup Test Activity Reduction Program. |
| | 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. 265 to NPF-62. Safety Evaluationcc w/encls:See next page | | : 1. Amendment No. 265 to NPF-6 |
| | : 2. Safety Evaluation cc w/encls: See next page |
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| Pkg ML062160317 (ML062000152, TS pgs ML062160468)OFFICENRR/LPL4/PMNRR/LPL4/LANRR/SPWB/BCOGC: NLONRR/LPL4/BCNAMEDHollandLFeizollahiJNakoskiSHamrickDTeraoDATE7/24/067/20/066/9/067/25/067/28/06 ENTERGY OPERATIONS, INC.DOCKET NO. 50-368ARKANSAS NUCLEAR ONE, UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 265 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), datedSeptember 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 No. NPF-6.3.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 | | Pkg ML062160317 (ML062000152, TS pgs ML062160468) |
| | OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/SPWB/BC OGC: NLO NRR/LPL4/BC NAME DHolland LFeizollahi JNakoski SHamrick DTerao DATE 7/24/06 7/20/06 6/9/06 7/25/06 7/28/06 ENTERGY OPERATIONS, INC. |
| | DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 265 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, 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 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 Specifications and Facility Operating LicenseDate of Issuance: August 2, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 265RENEWED FACILITY OPERATING LICENSE NO. NPF-6DOCKET NO. 50-368Replace page 3 of the Facility Operating License with the attached revised page 3.Replace the following page of the Appendix A Technical Specifications with the attached revisedpage. The revised page is identified by an amendment number and contains marginal lines indicating the areas of change. RemoveInsert3/4 1-53/4 1-5 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 265 TORENEWED FACILITY OPERATING LICENSE NO. NPF-6ENTERGY OPERATIONS, INC.ARKANSAS NUCLEAR ONE, UNIT NO. 2DOCKET NO. 50-36 | | Changes to the Technical Specifications and Facility Operating License Date of Issuance: August 2, 2006 |
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| ==81.0INTRODUCTION==
| | ATTACHMENT TO LICENSE AMENDMENT NO. 265 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace page 3 of the Facility Operating License with the attached revised page 3. |
| By letter dated September 19, 2006 (Reference 1), Entergy Operations, Inc. (Entergy) requestedan amendment to the Operating License and Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2). The request will modify ANO-2 Surveillance Requirement TS 3.1.1.4,"Moderator Temperature Coefficient" (MTC), utilizing WCAP-16011-P-A, "Startup Test ActivityReduction [(STAR)] Program" (Reference 2). The U.S. Nuclear Regulatory Commission (NRC)staff's original proposed no significant hazards consideration determination was published in theFederal Register on December 6, 2005 (70 FR 72671). WCAP-16011-P-A describes methods to reduce the time required for startup testing. To this end, WCAP-16011-P-A proposes methods to eliminate the control element assembly (CEA) worth and isothermal temperature coefficient (ITC) measurements at hot zero power (HZP).
| | Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by an amendment number and contains marginal lines indicating the areas of change. |
| WCAP-16011-P-A includes a method to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured critical boron concentration (CBC) at HZP. WCAP-16011-P-A adds an ITC measurement at intermediate to hot full power, and applicability requirements for core design, fabrication, refueling, startup testing,and CEA lifetime viability requirements. WCAP-16011-P-A methods can only be applied to coresthat are well characterized by an existing database. In Reference 1, the licensee has only requested to substitute the measured value of the MTC atHZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured CBC at HZP. Therefore, the NRC staff's review was limited to this sc ope.
| | Remove Insert 3/4 1-5 3/4 1-5 |
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| ==2.0REGULATORY EVALUATION==
| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC. |
| The regulations (Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50)) do notexplicitly prescribe specific post-refueling startup testing. However, the genesis for post-refueling startup testing can be traced to the preoperational testing required to be specified in the final safety analysis report by 10 CFR 50.34. Section 50.36 of 10 CFR specifies surveillancerequirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and thatthe limiting conditions for operation will be met. Part 50 of 10 CFR, Appendix A, "General Design Criteria" (GDC), apply, in that the GDCs establish the necessary design, fabrication, construction,testing, and performance requirements for structures, systems, and components important tosafety. Accordingly, the MTC is a parameter controlled in the licensee's TS, including surveillance requirements. As a value in the TS, MTC and the applicable surveillance requirements are subjectto regulatory oversight.
| | ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368 |
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| ==3.0TECHNICAL EVALUATION== | | ==1.0 INTRODUCTION== |
| As stated previously WCAP-16011-P-A describes methods to reduce the time required for startuptesting. The NRC-approved WCAP-16011-P-A on January 14, 2005, for referencing in licenseapplications to the extent specified and under the limitations stated in the topical report and theNRC safety evaluation (SE). Since the NRC staff found the report acceptable, the review of thelicensee's September 19, 2005, application was to ensure that WCAP-16011-P-A is applicable toANO-2 and that WCAP-16011-P-A is being implemented appropriately.Entergy has only requested a partial implementation of WCAP-16011-P-A for ANO-2, that portionthat replaces the current MTC Surveillance with an MTC Alternate Surveillance. However, the NRC's SE and WCAP-16011-P-A make no differentiation between the limitations, conditions, andrequirements for partial or full implementation. Nor has the licensee's application requested anydifferentiation of the limitations, conditions, or requirements for its partial implementation. Therefore, the licensee's partial implementation of WCAP-16011-P-A requires the full acceptanceof the limitations, conditions, and requirements specified in the NRC's SE and WCAP-16011-P-A.In the SE for WCAP-16011-P-A, the NRC identified three conditions and limitations for theapplication of WCAP-16011-P-A to individual licensees.1.The STAR program is applicable only to the participating plants as defined in Table 3-1 ofWCAP-16011-P-A.2.Should any of the STAR test results fall outside of the test criteria, either ascertain that thesafety analysis and STAR applicability requirements are satisfied, or discontinue use of theSTAR program for that fuel cycle.3.The Staff requires each licensee using STAR to submit a summary report following the firstapplication, either successful or not, of STAR to its plant. The report should (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the corresponding core design method uncertainties and show compliance with the STAR applicability requirements. If the application of STARis unsuccessful, identify the reasons why the STAR application failed.With respect to these conditions and limitations, the licensee meets the first as ANO-2 is includedin Table 3-1 of WCAP-16011-P-A. The licensee meets the second and third items as licensing commitments. Therefore, it is reasonable to conclude that WCAP-16011-P-A is applicable to ANO-2 and that WCAP-16011-P-A is being implemented appropriately.The NRC staff reviewed the licensee's license amendment request (LAR) reports submitted byEntergy, to support ANO-2 TS change to modify ANO-2 SR 4.1.1.4.1 and 4.1.1.4.2 to allow theuse of WCAP-16011-P-A. Based on this review, the NRC staff concludes that appropriatedocumentation was submitted and that the proposed changes satisfy the staff positions and requirements in these areas. Therefore, on the basis of the above review and justification, theNRC staff concludes that the proposed changes to the TS are acceptable.
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| ==4.0STATE CONSULTATION==
| | By letter dated September 19, 2006 (Reference 1), Entergy Operations, Inc. (Entergy) requested an amendment to the Operating License and Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2). The request will modify ANO-2 Surveillance Requirement TS 3.1.1.4, Moderator Temperature Coefficient (MTC), utilizing WCAP-16011-P-A, Startup Test Activity Reduction [(STAR)] Program (Reference 2). The U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination was published in the Federal Register on December 6, 2005 (70 FR 72671). |
| 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.
| | WCAP-16011-P-A describes methods to reduce the time required for startup testing. To this end, WCAP-16011-P-A proposes methods to eliminate the control element assembly (CEA) worth and isothermal temperature coefficient (ITC) measurements at hot zero power (HZP). |
| | WCAP-16011-P-A includes a method to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured critical boron concentration (CBC) at HZP. WCAP-16011-P-A adds an ITC measurement at intermediate to hot full power, and applicability requirements for core design, fabrication, refueling, startup testing, and CEA lifetime viability requirements. WCAP-16011-P-A methods can only be applied to cores that are well characterized by an existing database. |
| | In Reference 1, the licensee has only requested to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured CBC at HZP. Therefore, the NRC staffs review was limited to this scope. |
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| ==5.0ENVIRONMENTAL CONSIDERATION== | | ==2.0 REGULATORY EVALUATION== |
| The amendment changes a requirement with respect to installation or use of a facility com ponentlocated within the restricted area as defined in 10 CFR Part 20. The NRC staff has determinedthat the amendment involves no significant increase in the amounts, and no significant change inthe types, of any effluents that may be released offsite, and that there is no significant increase inindividual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and therehas been no public comment on such finding published December 6, 2005 (70 FR 72671).
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| Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in10 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 regulations (Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50)) do not explicitly prescribe specific post-refueling startup testing. However, the genesis for post-refueling startup testing can be traced to the preoperational testing required to be specified in the final safety analysis report by 10 CFR 50.34. Section 50.36 of 10 CFR specifies surveillance requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Part 50 of 10 CFR, Appendix A, General Design |
| 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 by operationin the proposed manner, (2) such activities will be conducted in compliance with the Commission'sregulations, and (3) the issuance of the amendment will not be adverse to the common defenseand security or to the health and safety of the public. | |
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| ==7.0REFERENCES==
| | Criteria (GDC), apply, in that the GDCs establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety. Accordingly, the MTC is a parameter controlled in the licensees TS, including surveillance requirements. As a value in the TS, MTC and the applicable surveillance requirements are subject to regulatory oversight. |
| 4.Letter from Jeffery S. Forbes, Arkansas Nuclear One, to U.S. NRC, Re: "LicenseAmendment Request to Modify Technical Specification 3.1.1.4, Surveillance Requirementsas Allowed by WCAP-16011-P-A, Startup Test Activity Reduction Program, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6," dated September 19, 2005,Agencywide Documents Access and Management System (ADAMS) Accession No. ML052760278.5.WCAP-16011-P-A, "Startup Test Activity Reduction Program," dated February 2005. ADAMS Accession No. ML050660118 (Nonproprietary version).Principal Contributor: K. Wood Date: August 2, 2006 September 2005Arkansas Nuclear One cc: Senior Vice President
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| & 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. | | ==3.0 TECHNICAL EVALUATION== |
| P. O. Box 31995 Jackson, MS 39286-1995Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205}} | | |
| | As stated previously WCAP-16011-P-A describes methods to reduce the time required for startup testing. The NRC-approved WCAP-16011-P-A on January 14, 2005, for referencing in license applications to the extent specified and under the limitations stated in the topical report and the NRC safety evaluation (SE). Since the NRC staff found the report acceptable, the review of the licensees September 19, 2005, application was to ensure that WCAP-16011-P-A is applicable to ANO-2 and that WCAP-16011-P-A is being implemented appropriately. |
| | Entergy has only requested a partial implementation of WCAP-16011-P-A for ANO-2, that portion that replaces the current MTC Surveillance with an MTC Alternate Surveillance. However, the NRCs SE and WCAP-16011-P-A make no differentiation between the limitations, conditions, and requirements for partial or full implementation. Nor has the licensees application requested any differentiation of the limitations, conditions, or requirements for its partial implementation. |
| | Therefore, the licensees partial implementation of WCAP-16011-P-A requires the full acceptance of the limitations, conditions, and requirements specified in the NRCs SE and WCAP-16011-P-A. |
| | In the SE for WCAP-16011-P-A, the NRC identified three conditions and limitations for the application of WCAP-16011-P-A to individual licensees. |
| | : 1. The STAR program is applicable only to the participating plants as defined in Table 3-1 of WCAP-16011-P-A. |
| | : 2. Should any of the STAR test results fall outside of the test criteria, either ascertain that the safety analysis and STAR applicability requirements are satisfied, or discontinue use of the STAR program for that fuel cycle. |
| | : 3. The Staff requires each licensee using STAR to submit a summary report following the first application, either successful or not, of STAR to its plant. The report should (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the corresponding core design method uncertainties and show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, identify the reasons why the STAR application failed. |
| | With respect to these conditions and limitations, the licensee meets the first as ANO-2 is included in Table 3-1 of WCAP-16011-P-A. The licensee meets the second and third items as licensing commitments. Therefore, it is reasonable to conclude that WCAP-16011-P-A is applicable to ANO-2 and that WCAP-16011-P-A is being implemented appropriately. |
| | The NRC staff reviewed the licensees license amendment request (LAR) reports submitted by Entergy, to support ANO-2 TS change to modify ANO-2 SR 4.1.1.4.1 and 4.1.1.4.2 to allow the use of WCAP-16011-P-A. Based on this review, the NRC staff concludes that appropriate documentation was submitted and that the proposed changes satisfy the staff positions and |
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| | requirements in these areas. Therefore, on the basis of the above review and justification, the NRC staff concludes that the proposed changes to the TS are acceptable. |
| | |
| | ==4.0 STATE CONSULTATION== |
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| | 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== |
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| | 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 December 6, 2005 (70 FR 72671). |
| | 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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| | ==6.0 CONCLUSION== |
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| | 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 Commissions regulations, and (3) the issuance of the amendment will not be adverse to the common defense and security or to the health and safety of the public. |
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| | ==7.0 REFERENCES== |
| | : 4. Letter from Jeffery S. Forbes, Arkansas Nuclear One, to U.S. NRC, Re: License Amendment Request to Modify Technical Specification 3.1.1.4, Surveillance Requirements as Allowed by WCAP-16011-P-A, Startup Test Activity Reduction Program, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, dated September 19, 2005, Agencywide Documents Access and Management System (ADAMS) Accession No. ML052760278. |
| | : 5. WCAP-16011-P-A, Startup Test Activity Reduction Program, dated February 2005. |
| | ADAMS Accession No. ML050660118 (Nonproprietary version). |
| | Principal Contributor: K. Wood Date: August 2, 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}} |
Letter Sequence Approval |
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MONTHYEARML0531301232005-11-17017 November 2005
Biweekly Notice Memo, Notice of Consideration, to Modify the Surveillance Requirements Related to Technical Specification for Moderator Temp Coefficient
Project stage: Other
ML0621604682006-08-0202 August 2006
Technicial Specification, Modify Moderator Temperature Coefficient Surveillance Requirements
Project stage: Other
ML0620001522006-08-0202 August 2006
Issuance of License Amendment to Modify Moderator Temperature Coefficient Surveillance Requirements
Project stage: Approval
2005-11-17
[Table View] |
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Category:Letter
MONTHYEARML24318C2732024-11-13013 November 2024
Request for Exemptions from 10 CFR 50.82(a)(8)(i) and (II) for Use of Nuclear Decommissioning Trust Funds for Disposal of Major Radioactive Components During Operations
ML24316A0032024-11-11011 November 2024
Relief Request ANO2-RR-24-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 71 – One Cycle Justification
ML24295A1202024-10-21021 October 2024
Relief Request ANO2-RR-24-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 71
ML24185A2602024-10-0404 October 2024
Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications
IR 05000368/20253012024-09-0909 September 2024
Notification of NRC Initial Operator Licensing Examination 05000368/2025301
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
IR 05000313/20240112024-09-0505 September 2024
Comprehensive Engineering Team Inspection Report 05000313/2024011 and 05000368/2024011
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
IR 05000313/20240052024-08-21021 August 2024
Updated Inspection Plan for Arkansas Nuclear One – Units 1 and 2 (Report 05000313/2024005, 05000368/2024005)
ML24198A0722024-08-21021 August 2024
Correction to Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24220A2642024-08-20020 August 2024
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML24185A1522024-08-13013 August 2024
Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205
IR 05000313/20240022024-08-0606 August 2024
Integrated Inspection Report 05000313/2024002 and 05000368/2024002
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
05000313/LER-2024-001, Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications2024-07-0101 July 2024
Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications
ML24101A1792024-06-25025 June 2024
Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24143A0632024-05-22022 May 2024
Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information
ML24128A2472024-05-0808 May 2024
Project Manager Assignment
IR 05000313/20240012024-05-0808 May 2024
Integrated Inspection Report 05000313/2024001 and 05000368/2024001
ML24017A2982024-04-18018 April 2024
Summary of Regulatory Audit Regarding the License Amendment Request to Revise Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
ML24107A0282024-04-17017 April 2024
Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information
ML24086A5412024-04-10010 April 2024
Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval
IR 05000313/20244022024-04-0808 April 2024
Security Baseline Inspection Report 05000313/2024402 and 05000368/2024402 (Full Report)
IR 05000313/20244042024-04-0808 April 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000313/2024404 and 05000368/2024404)
ML24089A2262024-03-29029 March 2024
Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams
ML24075A1712024-03-15015 March 2024
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
ML24074A2892024-03-14014 March 2024
Proof of Financial Protection (10 CFR 140.15)
ML24031A6442024-03-14014 March 2024
Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure
ML24102A1342024-03-12012 March 2024
AN1-2024-03 Post Exam Submittal
IR 05000313/20230062024-02-28028 February 2024
Annual Assessment Letter for Arkansas Nuclear One- Units 1 and 2 Report 05000313/2023006 and 05000368/2023006
IR 05000313/20243012024-02-27027 February 2024
NRC Initial Operator Licensing Examination Approval 05000313/2024301
IR 05000313/20230042024-02-0808 February 2024
Integrated Inspection Report 05000313/2023004 and 05000368/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023002
ML24012A0502024-02-0202 February 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0054 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23326A0392024-01-24024 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
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
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
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
ML23324A0172023-11-16016 November 2023
Submittal of Amendment 31 to Safety Analysis Report
2024-09-09
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24185A2602024-10-0404 October 2024
Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications
ML24185A1522024-08-13013 August 2024
Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205
ML24101A1792024-06-25025 June 2024
Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24031A6442024-03-14014 March 2024
Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure
ML23326A0392024-01-24024 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)
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)
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)
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)
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)
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)
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,
2024-08-13
[Table view]
Category:Safety Evaluation
MONTHYEARML24185A2602024-10-0404 October 2024
Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications
ML24185A1522024-08-13013 August 2024
Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205
ML24101A1792024-06-25025 June 2024
Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24086A5412024-04-10010 April 2024
Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval
ML24031A6442024-03-14014 March 2024
Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure
ML23326A0392024-01-24024 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
2024-08-13
[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 (ANO-2) RE: ISSUANCE OF LICENSE AMENDMENT TO MODIFY MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS (TAC NO. MC8538)
Dear Mr. Forbes:
The Commission has issued the enclosed Amendment No. 265 to 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 will modify ANO-2 Surveillance Requirement TS 3.1.1.4, Moderator Temperature Coefficient, and will allow the use of WCAP-16011-P-A, Startup Test Activity Reduction Program.
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. 265 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page
Pkg ML062160317 (ML062000152, TS pgs ML062160468)
OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/SPWB/BC OGC: NLO NRR/LPL4/BC NAME DHolland LFeizollahi JNakoski SHamrick DTerao DATE 7/24/06 7/20/06 6/9/06 7/25/06 7/28/06 ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 265 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, 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 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 and Facility Operating License Date of Issuance: August 2, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 265 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace page 3 of the Facility Operating License with the attached revised page 3.
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by an amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3/4 1-5 3/4 1-5
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 265 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, 2006 (Reference 1), Entergy Operations, Inc. (Entergy) requested an amendment to the Operating License and Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2). The request will modify ANO-2 Surveillance Requirement TS 3.1.1.4, Moderator Temperature Coefficient (MTC), utilizing WCAP-16011-P-A, Startup Test Activity Reduction [(STAR)] Program (Reference 2). The U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination was published in the Federal Register on December 6, 2005 (70 FR 72671).
WCAP-16011-P-A describes methods to reduce the time required for startup testing. To this end, WCAP-16011-P-A proposes methods to eliminate the control element assembly (CEA) worth and isothermal temperature coefficient (ITC) measurements at hot zero power (HZP).
WCAP-16011-P-A includes a method to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured critical boron concentration (CBC) at HZP. WCAP-16011-P-A adds an ITC measurement at intermediate to hot full power, and applicability requirements for core design, fabrication, refueling, startup testing, and CEA lifetime viability requirements. WCAP-16011-P-A methods can only be applied to cores that are well characterized by an existing database.
In Reference 1, the licensee has only requested to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured CBC at HZP. Therefore, the NRC staffs review was limited to this scope.
2.0 REGULATORY EVALUATION
The regulations (Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50)) do not explicitly prescribe specific post-refueling startup testing. However, the genesis for post-refueling startup testing can be traced to the preoperational testing required to be specified in the final safety analysis report by 10 CFR 50.34. Section 50.36 of 10 CFR specifies surveillance requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Part 50 of 10 CFR, Appendix A, General Design
Criteria (GDC), apply, in that the GDCs establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety. Accordingly, the MTC is a parameter controlled in the licensees TS, including surveillance requirements. As a value in the TS, MTC and the applicable surveillance requirements are subject to regulatory oversight.
3.0 TECHNICAL EVALUATION
As stated previously WCAP-16011-P-A describes methods to reduce the time required for startup testing. The NRC-approved WCAP-16011-P-A on January 14, 2005, for referencing in license applications to the extent specified and under the limitations stated in the topical report and the NRC safety evaluation (SE). Since the NRC staff found the report acceptable, the review of the licensees September 19, 2005, application was to ensure that WCAP-16011-P-A is applicable to ANO-2 and that WCAP-16011-P-A is being implemented appropriately.
Entergy has only requested a partial implementation of WCAP-16011-P-A for ANO-2, that portion that replaces the current MTC Surveillance with an MTC Alternate Surveillance. However, the NRCs SE and WCAP-16011-P-A make no differentiation between the limitations, conditions, and requirements for partial or full implementation. Nor has the licensees application requested any differentiation of the limitations, conditions, or requirements for its partial implementation.
Therefore, the licensees partial implementation of WCAP-16011-P-A requires the full acceptance of the limitations, conditions, and requirements specified in the NRCs SE and WCAP-16011-P-A.
In the SE for WCAP-16011-P-A, the NRC identified three conditions and limitations for the application of WCAP-16011-P-A to individual licensees.
- 1. The STAR program is applicable only to the participating plants as defined in Table 3-1 of WCAP-16011-P-A.
- 2. Should any of the STAR test results fall outside of the test criteria, either ascertain that the safety analysis and STAR applicability requirements are satisfied, or discontinue use of the STAR program for that fuel cycle.
- 3. The Staff requires each licensee using STAR to submit a summary report following the first application, either successful or not, of STAR to its plant. The report should (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the corresponding core design method uncertainties and show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, identify the reasons why the STAR application failed.
With respect to these conditions and limitations, the licensee meets the first as ANO-2 is included in Table 3-1 of WCAP-16011-P-A. The licensee meets the second and third items as licensing commitments. Therefore, it is reasonable to conclude that WCAP-16011-P-A is applicable to ANO-2 and that WCAP-16011-P-A is being implemented appropriately.
The NRC staff reviewed the licensees license amendment request (LAR) reports submitted by Entergy, to support ANO-2 TS change to modify ANO-2 SR 4.1.1.4.1 and 4.1.1.4.2 to allow the use of WCAP-16011-P-A. Based on this review, the NRC staff concludes that appropriate documentation was submitted and that the proposed changes satisfy the staff positions and
requirements in these areas. Therefore, on the basis of the above review and justification, the NRC staff concludes that the proposed changes to the TS are acceptable.
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 December 6, 2005 (70 FR 72671).
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 Commissions regulations, and (3) the issuance of the amendment will not be adverse to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 4. Letter from Jeffery S. Forbes, Arkansas Nuclear One, to U.S. NRC, Re: License Amendment Request to Modify Technical Specification 3.1.1.4, Surveillance Requirements as Allowed by WCAP-16011-P-A, Startup Test Activity Reduction Program, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, dated September 19, 2005, Agencywide Documents Access and Management System (ADAMS) Accession No. ML052760278.
- 5. WCAP-16011-P-A, Startup Test Activity Reduction Program, dated February 2005.
ADAMS Accession No. ML050660118 (Nonproprietary version).
Principal Contributor: K. Wood Date: August 2, 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
