ML061940236

Issuance of Amendment Technical Specifications Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process

ML061940236
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/02/2006
From:	Holland D G NRC/NRR/ADRO/DORL/LPLIV
To:	Forbes J S Entergy Operations
Holland D G, NRR/DLPM, 415-1436
References
TAC MC8540
Download: ML061940236 (9)

Text

August 2, 2006Mr. Jeffrey S. ForbesSite 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 TUBEINSERVICE 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 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

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.

1448 S. R. 333 Russellville, AR 72801

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)

Dear Mr. Forbes:

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

Enclosures:

1. Amendment No. 266 to NPF-62. Safety Evaluationcc w/encls:See next pageDISTRIBUTION

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

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----

6-11----

6-12----

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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

81.0INTRODUCTION

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.

2.0REGULATORY EVALUATION

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.

3.0TECHNICAL EVALUATION

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.

4.0STATE CONSULTATION

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.

5.0ENVIRONMENTAL CONSIDERATION

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.

6.0CONCLUSION

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.

7.0REFERENCES

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:

Senior Vice President & Chief Operating Officer Entergy Operations, Inc.

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.

Washington, DC 20006-3817Senior Resident InspectorU.S. Nuclear Regulatory Commission

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.

P. O. Box 31995 Jackson, MS 39286-1995Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205