ML050550288

ANO, Unit 2 - Issuance of Amendment Request to Support Cycle 18 Core Reload

ML050550288
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/23/2005
From:	Holland D NRC/NRR/DLPM/LPD4
To:	Forbes J Entergy Operations
Holland D, NRR/DLPM, 415-1436
Shared Package
ml051100495	List: ML050550288
References
TAC MC3246
Download: ML050550288 (12)

Text

March 23, 2005 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 2 (ANO-2) ISSUANCE OF AMENDMENT RE: LICENSE AMENDMENT REQUEST TO SUPPORT CYCLE 18 CORE RELOAD (TAC NO. MC3246)

Dear Mr. Forbes:

The Commission has issued the enclosed Amendment No. 257 to Facility Operating License No. NFP-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 12, 2004, as completely superseded by application dated July 8, 2004, as supplemented by letters dated October 14, 2004, and January 19 and March 7, 2005.

The amendment modifies the analytical methods referenced in TS 6.6.5 by replacing the existing physics code package with a Westinghouse nuclear physics code package and incorporating the methodologies that will support the use of ZIRLO fuel cladding and zirconium diboride burnable absorber coating on uranium dioxide fuel pellets. The amendment also implements TS Task Force Traveler No. 363 to revise the way analytical methods are listed in TS 6.6.5 by identifying the topical report numbers and titles only and relocating specific revisions, supplement numbers, and approval dates to the core operating limits report. The portion of the application requesting to delete the TS Index will continue to be reviewed and will not be included in this amendment. Therefore, the correlating Index page will be revised as necessary.

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, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosures:

1. Amendment No. 257 to NFP-6

2. Safety Evaluation cc w/encls:

See next page

March 23, 2005 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 2 (ANO-2) ISSUANCE OF AMENDMENT RE: LICENSE AMENDMENT REQUEST TO SUPPORT CYCLE 18 CORE RELOAD (TAC NO. MC3246)

Dear Mr. Forbes:

The Commission has issued the enclosed Amendment No. 257 to Facility Operating License No. NFP-6 for ANO-2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 12, 2004, as completely superseded by application dated July 8, 2004, as supplemented by letters dated October 14, 2004, and January 19 and March 7, 2005.

The amendment modifies the analytical methods referenced in TS 6.6.5 by replacing the existing physics code package with a Westinghouse nuclear physics code package and incorporating the methodologies that will support the use of ZIRLO fuel cladding and zirconium diboride burnable absorber coating on uranium dioxide fuel pellets. The amendment also implements TS Task Force Traveler No. 363 to revise the way analytical methods are listed in TS 6.6.5 by identifying the topical report numbers and titles only and relocating specific revisions, supplement numbers, and approval dates to the core operating limits report. The portion of the application requesting to delete the TS Index will continue to be reviewed and will not be included in this amendment. Therefore, the correlating Index page will be revised as necessary.

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, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosures:

1. Amendment No. 257 to NFP-6

2. Safety Evaluation cc w/encls:

See next page DISTRIBUTION:

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PDIV-1/SC NAME DHolland DBaxley TBoyce AHodgdon AHowe DATE 3/18/05 3/17/05 3/21/05 3/21/05 3/23/05 OFFICIAL RECORD COPY

ENTERGY OPERATIONS INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 257 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 May 12, 2004, as completely superseded by application dated July 8, 2004, as supplemented by letters dated October 14, 2004, and January 19 and March 7, 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 Facility Operating License No. NFP-6 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 257, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Allen G. Howe, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 23, 2005

ATTACHMENT TO LICENSE AMENDMENT NO. 257 RENEWED FACILITY OPERATING LICENSE NO. NFP-6 DOCKET NO. 50-368 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 XVII XVII 6-20 6-20 6-21 6-21 6-22 6-23 6-22 6-24 6-23 6-25 6-24 6-26 6-25

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 257 TO 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 May 12, 2004 (reference 1), as completely superseded by letter dated July 8, 2004 (reference 2), as supplemented by letters dated October 14, 2004 (reference 3) and January 19 (reference 4) and March 7, 2005 (reference 5), Entergy Operations, Inc. (EOI or the licensee), requested an amendment to modify Arkansas Nuclear One, Unit No. 2 (ANO-

2) Technical Specification (TS) 6.6.5, Core Operating Limits Report (COLR), to support Cycle 18 core reload. Specifically, the amendment would modify the analytical methods referenced in TS 6.6.5 by replacing the existing physics code package with a Westinghouse Nuclear Physics code package, and incorporating the methodologies that will support the use of ZIRLO fuel cladding and zirconium diboride (ZrB2) burnable absorber coating on uranium dioxide (UO2) fuel pellets. The amendment would also revise the way the analytical methods are listed in TS 6.6.5 by identifying the topical report (TR) numbers and titles only, and relocating the specific revisions, supplement numbers, and approval dates to the COLR. The portion of the application requesting to delete the TS Index will continue to be reviewed and will not be included in this amendment. Therefore, the correlating Index page will be revised as necessary.

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR) Paragraph 50.36(c)(2)(ii) requires that TS limiting conditions for operation be established for process variables, design features, and operating restrictions for which a value is assumed as an initial condition of a design basis accident in the licensees safety analyses. As such, amendments are generally required for each fuel cycle to update the values of cycle-specific parameter limits in the TSs. To eliminate the need for an amendment to update the cycle-specific parameter limits for each fuel cycle while complying with 10 CFR 50.36(c)(2)(ii) requirements, the U.S. Nuclear Regulatory Commission (NRC) has allowed licensees to use an alternative incorporating the cycle-specific parameter limits in the COLR. Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications (reference 6), provides the COLR-implementation guidance, which includes the requirement to list the NRC-approved analytical methods used to determine the core operating limits in the TSs. The analytical methods referenced in the TSs would identify the TRs by number, title, and date, or identify the staffs safety evaluation report for a plant-specific methodology by NRC letter and date. To further avoid the need for TS changes every time a revision to an approved TR is approved, the staff approved TS Task Force (TSTF) Traveler TSTF-363, Revised Topical Report Reference in ITS 5.6.5, COLR (reference 7), which allows for the listing of the TRs in the TS by only the numbers and titles, with the detailed identification of the TR revisions, supplement numbers, and approval dates specified in the COLR.

The amendment would add several Westinghouse TRs to TS 6.6.5. These TRs have all been reviewed and approved by the NRC for licensing application. The addition of these TRs to ANO-2 TS 6.6.5 follows the same guidance of GL 88-16 and TSTF-363 in that only the TR numbers and titles will be listed in the TS, with the detailed identification of the report revisions, supplement numbers, and approval dates specified in the COLR. Therefore, the licensees amendment is acceptable with the only remaining issues being the compliance with the conditions and limitations, if any, specified in the staff safety evaluation (SE) for these TRs for plant-specific applications.

3.0 TECHNICAL EVALUATION

The licensee proposed to change TS 6.6.5 as follows:

Replace Item 1 CENPD-266-P-A, ROCS and DIT Computer Codes for Nuclear Design, with Westinghouse Nuclear Physics code package WCAP-11596-P-A, Qualification of the PHOENIX-P/ANC Nuclear Design System For Pressurized Water Reactor Cores, WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, and WCAP-10965-P-A, Addendum 1, ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery.

Revise Items 2 through 12 by deleting the revision and/or supplement numbers and dates and relocating them to the COLR.

Combine Items 4, 5, 6, 7, and 17, all of which refer to CENPD-132-P, Calculative Methods for CE [Combustion Engineering] Large Break LOCA [loss-of-coolant accident] Evaluation Model, as new Item 4.

Combine Items 8, 9, and 10, all of which refer to CENPD-137, Calculative Methods for CE Small Break LOCA Evaluation Model, into new Item 5.

Renumber Items 11 and 12 as new Items 6 and 7, respectively.

Delete Items 13 through 16, which are NRC letters to CE regarding the approval of various supplements of CENPD-132-P, and relocate them to the COLR.

Add NRC approved TRs CENPD-404-P-A, Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs, and WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, as new Items 8 and 9, respectively.

Add NRC-approved TR WCAP-16072-P-A, Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs, as new Item 10.

These proposed changes can be categorized into four parts: (1) replacement of the existing physics code package ROCS and DIT with Westinghouse Nuclear Physics code package PHOENIX-P/ANC, and the addition of Westinghouse Physics code PARAGON to replace the PHOENIX-P lattice code; (2) addition of CENPD-404-P-A related to the use of ZIRLO fuel cladding; (3) addition of WCAP-16072-P-A related to the implementation of ZrB2 coatings in its CE fuel assemblies; and (4) incorporation of TSTF-363 by listing only the TR numbers and titles in the TSs. The staff evaluation for each of these parts is discussed below.

3.1 Use of Westinghouse Nuclear Physics Code Package The licensee proposed to replace CENPD-266-P-A, The ROC and DIT Computer Codes for Nuclear Design, with the following Westinghouse Nuclear Physics code package:

WCAP-11596-P-A, Qualification of the PHOENIX-P/ANC Nuclear Design System For Pressurized Water Reactor Cores WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code WCAP-10965-P-A, Addendum 1, ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery The PHOENIX-P and ANC codes are traditional Westinghouse neutronics methods, which have been approved by the NRC. ANC is a three-dimensional two-group diffusion theory nodal code used for nuclear design analyses for determining the core design parameters, such as the critical boron concentration, control rod worths, reactivity coefficients, assembly average powers and exposures, assembly peak rod powers, peaking factors, and axial power shapes.

TRs WCAP-10965-P-A and WCAP-10965-P-A, Addendum 1, describe the ANC code and enhancements to the neutronic solution. PHOENIX-P is a two-dimensional, multi-group transport theory code traditionally used to calculate lattice physics parameters and provide nuclear input data to the ANC code. TR WCAP-11596-P-A describes the PHOENIX-P/ANC nuclear design system for the pressurized water reactor (PWR) cores and provides demonstration of the qualification of the PHOENIX-P/ANC nuclear analysis package. The qualification process covered an acceptable range of comparisons between the PHOENIX-P/ANC calculations and the operating reactor data measured during startup tests and during normal power operations from several representative reactor cycles from three-loop and four-loop Westinghouse-designed plants. The NRC had reviewed and concluded the PHOENIX-P/ANC nuclear analysis system to be acceptable for use in the PWR design analysis.

In Enclosure 1 to the July 8, 2004, application, the licensee provided supplemental information to demonstrate the applicability of the Westinghouse PHOENIX-P/ANC physics code package to ANO-2, which is a CE-designed plant. This includes comparisons between the predictions made using the PHOENIX-P/ANC physics codes and the ANO-2 Cycles 15 and 16 zero power physics test measurements and at power operating data. The zero power physics tests include critical boron concentrations, moderator temperature coefficient, control rod worth, and differential boron worth. The power operation data include boron letdown curves and axial power distributions. In all the comparisons, the differences between the measured and predicted values are very small, except for only a few low-power fuel assemblies on the core periphery having relatively higher percentage differences. The maximum error for the potential limiting fuel assemblies are within the uncertainty allowance on the assembly power used in the safety analysis. Therefore, the staff concludes that the PHOENIX-P/ANC physics code package is acceptable for the ANO-2 licensing application, and the listing of these TRs is acceptable.

The amendment would also add TR WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, to TS 6.6.5 with the intent to use PARAGON as a replacement for the PHOENIX lattice code. PARAGON is a new neutron transport code that can be used with a nuclear design code system or as a stand-alone code, which can be used as a direct replacement for the PHOENIX-P code. TR WCAP-16045-P-A describes the PARAGON code and confirms the qualification of the code both as a stand-alone transport code and as a substitute for the PHOENIX-P code as a nuclear data source for nodal code. The qualification process includes a comparison of PARAGON predicted values to measured data from several plants, including Calvert Cliffs. Benchmarking has shown that the PARAGON/ANC package is essentially the same as the PHOENIX-P/ANC package. The NRC has previously reviewed and concluded that TR WCAP-16045-P-A is acceptable for licensing applications with the safety evaluation (SE) stating that the staff considers the new PARAGON code to be well qualified as a stand alone code replacement for the PHOENIX-P lattice code, wherever the PHOENIX-P code is used in NRC-approved methodologies. Therefore, the addition of TR WCAP-16045-P-A to TS 6.6.5 is acceptable.

3.2 Addition of TR CENPD-404-P-A ANO-2 plans to implement ZIRLO cladding material for new fuel assemblies to improve fuel performance. ZIRLO is a zirconium-based fuel rod cladding material developed by Westinghouse and approved by the NRC for use in the Westinghouse fuel designs. The use of ZIRLO clad fuel rods will substantially reduce exterior corrosion and particularly the spalling experienced by some current Zircaloy-4 clad fuel rods as they approach higher burnup levels and duty cycles.

TR CENPD-404-P-A, Implementation of ZIRLO Cladding Material in CE Nuclear Power Fuel Assembly Designs, provided justification for the use of ZIRLO in the CE fuel assemblies. The NRC approved TR CENPD-404-P-A for the use of ZIRLO as cladding material for CE-designed plants subject to five conditions stated in the staff SE. In Attachment 1 to the July 8, 2004, application, the licensee responded to the five conditions. Condition 4 states that until data is available demonstrating the performance of ZIRLO cladding in CE-designed plants, the fuel duty will be limited for each CE-designed plant with some provision for adequate margin to account for variations in core design (e.g., cycle length, plant operating conditions, etc.).

Details of this condition will be addressed on a plant specific basis during the approval to use ZIRLO in a specific plant. The licensee proposed to impose 110 to 120 percent of the modified fuel duty index (mFDI) value of 590 as a restriction of the upper fuel duty limit for the CE fuel assemblies, until adequate fuel performance of ZIRLO cladding is demonstrated. In response to a staff request for additional information, the licensee explained that the maximum mFDI value of 590, as constrained by operating experience, was determined to be applicable for the 16x16 CE fuel design as approved by the NRC for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, which are the lead 16x16 CE fuel design units for ZIRLO implementation (reference 8). The licensee further stated that ANO-2 will lift the restriction on fuel duty if the ZIRLO corrosion behavior in CE plants is similar to or conservative relative to the Westinghouse ZIRLO corrosion data, and that EOI intends to lift this restriction, without an NRC evaluation, for the ANO-2 plant based on the NRCs actions relative to lifting the restriction for the lead 16x16 plant PVNGS for ZIRLO implementation. EOI will document its action via 10 CFR 50.59.

In response to a further staff request during a telephone conference call on December 6, 2004, the licensee, in its letter dated January 19, 2005, reduced the mFDI limit from 590 to 572. The licensee described that the basis for this ANO-2 specific mFDI of 572 is to allow the ZIRLO cladding to operate within the current cladding operating limits of less than 100 microns best estimate maximum oxide thickness and no more than minor spallation. The calculation to derive the mFDI limit was based on actual ANO-2 fuel management from a selected set of cycles having relatively adverse corrosion performance. The calculation also conservatively assumed slightly higher local power peaking and reactor coolant temperature, both of which accelerate fuel cladding corrosion. Therefore, the staff concludes the calculated mFDI limit of 572 is acceptable. The licensee also provided a commitment that the upper design limits for ANO-2 will be limited to mFDI values of 629 for the majority of the fuel assemblies, and 686 for a fraction of the fuel pins in a limited number of assemblies (no more than eight fuel assemblies). These upper limit mFDI values, which are 110 percent and 120 percent of 572, respectively, are consistent with the NRC approval for the lead ZIRLO cladding CE-designed plant (PVNGS) with the same mFDI deviations to provide adequate margin to account for variations in core design. The licensee further committed that EOI will not lift the ZIRLO mFDI restriction without either NRC approval of a supplement to TR CENPD-404-P-A that includes corrosion data from two CE plants (not the same plant site) or NRC approval of ANO-2 site specific corrosion data. The staff finds that the licensees commitments regarding the upper limits of mFDI values for the ZIRLO cladding restriction and the removal the mFDI restriction are acceptable.

The staff finds that ANO-2's implementation of ZIRLO cladding in the CE fuel assembly designs as described in CENPD-404-P-A is acceptable. Therefore, the addition of TR CENPD-404-P-A to ANO-2 TS 6.6.5 is acceptable.

3.3 Addition of TR WCAP-16072-P-A The licensee plans to change the burnable absorbers for ANO-2 Cycle 18 from Erbia integral burnable absorber, which is mixed in the fuel, to a burnable absorber using ZrB2, which is coated onto the outer surface of the uranium dioxide fuel pellets. Westinghouse has considerable fabrication and operational experience with the ZrB2 integral fuel burnable absorber (IFBA) in the Westinghouse-designed plants. The use of ZrB2 burnable absorber in CE fuel assemblies is documented in TR WCAP-16072-P-A, Implementation of Zirconium Diboride Burnable Absorber Coating in CE Nuclear Power Fuel Assembly Designs. The NRC staff has approved TR WCAP-16072-P-A for licensing applications to implement ZrB2 IFBA in CE 14x14 and 16x16 fuel assembly designs with conditions and limitations described in Section 4.0 of the NRC SE.

In Attachment 3 to its July 8, 2004, application, the licensee provided its regulatory commitments to comply with the conditions and limitations specified in the NRC SE on WCAP-16072-P-A for the implementation of ZrB2 IFBA for ANO-2. The staff has reviewed these commitments and found them acceptable. A few highlights are summarized below.

The SE Condition 3 requires that the moderator temperature coefficient (MTC) measured at hot full power (HFP) beginning of cycle conditions be adjusted to the maximum HFP soluble boron concentration expected during the cycle and that, for the first application of ZrB2 IFBA in a CE 14x14 or 16x16 fuel assembly design, a direct HFP MTC measurement be made at the maximum HFP soluble boron concentration expected during the cycle in order to confirm conservative adjustment. The licensee committed to a one time action of: Hot full power MTC test within seven days of reaching the highest reactor coolant system soluble boron concentration predicted during full power operation will be performed. To clarify the purpose of the test, in its supplement dated October 14, 2004, the licensee indicated that the first application of ZrB2 IFBA... for CE plants is planned for Calvert Cliffs-Unit 2, Cycle 16 and ANO-2, Cycle 18, whose start-up schedules are approximately the same in the spring of 2005.

In subsequent discussions with the affected utilities and the NRC, it was recommended that the one-time surveillance be performed for ANO-2, independent of exact timing to reach the peak soluble boron concentration. This recommendation was based on the preliminary design results for both plants which indicated little or no boron run-up for the Calvert Cliffs-Unit 2 Cycle 16 implementation, significantly limiting the value of a test at that unit given the basis for the SE condition. In a telephone conference on November 8, 2004, the licensee reaffirmed its commitment to perform the HFP MTC test within seven days of reaching the highest boron concentration. The staff finds the commitment complies with the SE condition.

Condition 4 of the WCAP-16072-P-A SE states that prior to startup following a Condition III and IV event, licensees must evaluate clad hydriding to ensure that hydrides have not precipitated in the radial direction.... The licensees commitment stated that in the event of a Condition III or IV event at ANO-2, an evaluation of fuel structure integrity with respect to radial hydriding will be performed prior to power ascension. The staff requested that the commitment be augmented to include... to ensure that hydrides have not precipitated in the radial direction. In its supplement dated October 14, 2004, the licensee indicated that this commitment refers only to an actual Condition III or Condition IV occurrence at the plant that could result in fuel damage, and would not allow for an immediate plant restart. The evaluation would likely be similar to obtaining the information provided in request for additional information response in Item 6 of Appendix H of WCAP-16072-P-A, relying on the fact that the conditions necessary to allow radial hydriding would not have existed, and therefore the possibility of radial hydriding need not be considered further... In a conference call on November 8, 2008, the licensee reaffirmed its commitment to perform an evaluation of fuel structure integrity regarding radial hydriding prior to power ascension following a Condition III or IV event. The staff concludes that this commitment complies with the SE condition, and is acceptable.

3.4 Incorporation of TSTF 363 The licensee proposed to identify the TRs listed in TS 6.6.5 by listing only the TR numbers and titles, and to relocate the specific revisions, supplement numbers, and approval dates to the COLR. This is consistent with TSTF-363. The citation in the COLR would include specific information for each of the TS references to the TRs used to prepare the COLR (i.e., report number, title, revision, date, and any supplements). This method of referencing TRs allows the licensee to use current TRs to support limits in the COLR without having to submit an amendment to the TSs each time the TR is revised. The licensee also notes that future changes to the values of these limits by the licensee may only be developed using NRC approved methodologies, must remain consistent with all applicable plant safety analysis limits addressed in the safety analysis report, and are further controlled by the 10 CFR 50.59 process. The staff concludes that the licensees amendment conforms to the guidance in NRC GL 88-16 and TSTF-363.

For LOCA methodology TRs, removal of the revision numbers and dates with the titles of TRs needs clarification. Different report numbers, titles, revision numbers, supplements, amendments, dates, and other designations for LOCA methodologies identify specifically different LOCA methodologies. For LOCA codes, 10 CFR 50.46(a)(1) governs methods of calculating emergency core cooling system performance. The NRC staff reviews each revision, supplement, or amendment to these LOCA code TRs in accordance with 10 CFR 50.46. If a new version of such a report is acceptable, the staff generally approves it for use at power reactors at which the conditions under which the report would be applied are within the ranges of the conditions for which the TR is approved. These approved ranges of conditions, as understood at the time of review, are set forth in the TRs and the associated NRC SEs.

With regard to the LOCA methodologies CENPD-132-P and CENPD-137, the staff finds the specific relocation of supplement numbers and dates acceptable because relocation of the specific identifying information for these methodologies, which have been approved for ANO-2 without changing the identifying designations, will preserve the specific identifications of the methodologies and will not introduce unreviewed or unapproved methodologies. The specific identifying information for methodologies employed at ANO-2 is maintained in the COLR. The licensee has stated that changes to the COLR are controlled by its 10 CFR 50.59 program; therefore, the staff finds that there is reasonable assurance that the licensee will employ only methodologies that have been specifically approved for ANO-2 and will identify any conditions that the staff has imposed on those methodologies.

4.0 REGULATORY COMMITMENTS The following table identifies those actions committed to by the licensee in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

COMMITMENT TYPE (Check one)

SCHEDULED COMPLETION DATE (If Required)

ONE-TIME ACTION CONTINUING COMPLIANCE The cycle specific COLR will contain the complete identification of each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

x Entergy will not lift the ZIRLO' mFDI restriction without either NRC approval of a supplement to CENPD-404-P-A that includes corrosion data from two Combustion Engineering plants (not at the same plant site) or NRC approval of ANO-2 site specific corrosion data.

x The upper design limits for ANO-2 fuel will be limited to ZIRLOTM mFDI values of 629 for the majority of the fuel assemblies and 686 for a fraction of the fuel pins in a limited number of assemblies (no more than eight fuel assemblies).

x Cycle specific evaluations will be used to verify that required power margins in the axial cutback regions are maintained within the safety analysis limitations.

x Hot full power (HFP) MTC test within seven days of reaching the highest RCS soluble boron concentration predicted during full power operation will be performed.

x Provide the necessary information from the HFP test at peak boron concentration conditions to Westinghouse for its submittal to NRC.

x Plant procedures will be modified as needed to reflect the calculated peak HFP MTC along with ZrB2 IFBAs distinctive trend in RCS critical boron concentration.

x In the event of a Condition III or IV event at ANO-2, an evaluation of fuel structural integrity with respect to radial hydriding will be performed prior to power ascension.

x Analyses, as part of the ANO-2 reload efforts, will be performed in support of the generic implementation of ZrB2 fuel to ensure that cladding bursts are precluded for Conditions I, II, III and IV events.

x Prior to the use of ZrB2 burnable absorber coatings, the fuel design will be analyzed with applicable NRC staff approved codes and methods.

x The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitments are best provided by the licensees administrative processes, including its commitment management program. The above regulatory commitments do not warrant the creation of regulatory requirements (items requiring prior NRC approval of subsequent changes).

5.0 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.

6.0 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 August 31, 2004 (69 FR 53105). 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 amendments.

7.0 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.

8.0 REFERENCES

1.

Letter from J. S. Forbes, Entergy Operations, Inc., to U.S. Nuclear Regulatory Commission, License Amendment Request to Support Cycle 18 Core Reload, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, 2CAN050405, May 12, 2004, ML041410523.

2.

Letter from J. S. Forbes, Entergy Operations, Inc., to U.S. Nuclear Regulatory Commission, License Amendment Request to Support Cycle 18 Core Reload, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, 2CAN070402, July 8, 2004, ML041960419.

3.

Letter from J. S. Forbes, Entergy Operations, Inc., to U.S. Nuclear Regulatory Commission, Supplement to Amendment Request For License Amendment Request to Support Cycle 18 Core Reload, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, 2CAN100402, October 14, 2004, ML043010595.

4.

Letter from Dale. E. James, Entergy Operations, Inc., to U.S. Nuclear Regulatory Commission, Supplement to Amendment Request For License Amendment in Support of Cycle 18 Core Reload, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, 2CAN010501, January 19, 2005, ML050240333.

5.

Letter from Dale. E. James, Entergy Operations, Inc., to U.S. Nuclear Regulatory Commission, Supplement to Amendment Request For License Amendment in Support of Cycle 18 Core Reload, Arkansas Nuclear One, Unit 2, Docket No. 50-368, License No. NPF-6, 2CAN010501, March 7, 2005, ML050740442.

6.

Generic Letter 88-16, Removal of Cycle-Specific Parameters Limits from Technical Specifications.

7.

TSTF-363, Revised Topical Report Reference in ITS 5.6.5, COLR.

8.

Letter from J. Donohew, U.S. Nuclear Regulatory Commission, to G. R. Overbeck, Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: Technical Specification 5.6.5b, Core Operating Limits Report (COLR) and Use of ZIRLO Cladding Material (TAC Nos. MB3373, MB3374, and MB3375), March 12, 2002, ML020710728.

Principal Contributor: Y. Hsii Date: March 23, 2005

January 2005 Arkansas Nuclear One cc:

Senior Vice President

& Chief Operating Officer Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Mr. Mike Schoppman Framatome ANP 3815 Old Forest Road Lynchburg, VA 24501 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 Vice President, Operations Support Entergy Operations, Inc.

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