ML041200384

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Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application
ML041200384
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/23/2004
From: Gregory Suber
NRC/NRR/DRIP/RLEP
To: Forbes J
Entergy Operations
Suber G, NRR/DRIP/RLEP 301-415-1124
References
TAC MB8402
Download: ML041200384 (7)


Text

April 23, 2004 Mr. Jeff Forbes Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE ARKANSAS NUCLEAR ONE, UNIT 2, LICENSE RENEWAL APPLICATION (TAC NO. MB8402)

Dear Mr. Forbes:

The U.S. Nuclear Regulatory Commission (NRC) is reviewing a license renewal application (LRA) submitted by Entergy Operators Inc. (Entergy or the applicant) dated October 14, 2003 for the renewal of the operating licenses for Arkansas Nuclear One, Unit 2, pursuant to Title 10 Code of Federal Regulations Part 54 (10 CFR Part 54). The NRC staff has identified, in the enclosure, areas where additional information is needed to complete the review.

Specifically, the enclosed requests for additional information (RAIs) are from Section 2.3 System Scoping and Screening Results: Mechanical. These issues have been discussed with your staff.

Your responses to these RAIs are requested within 30 days from the date of this letter. If you have any questions, please contact me at (301) 415-1124 or e-mail gxs@nrc.gov.

Sincerely,

/RA/

Gregory F. Suber, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-368

Enclosure:

As stated cc w/encl: See next page

April 23, 2004 Mr. Jeff Forbes Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE ARKANSAS NUCLEAR ONE, UNIT 2, LICENSE RENEWAL APPLICATION (TAC NO. MB8402)

Dear Mr. Forbes:

The U.S. Nuclear Regulatory Commission (NRC) is reviewing a license renewal application (LRA) submitted by Entergy Operators Inc. (Entergy or the applicant) dated October 14, 2003 for the renewal of the operating licenses for Arkansas Nuclear One, Unit 2, pursuant to Title 10 Code of Federal Regulations Part 54 (10 CFR Part 54). The NRC staff has identified, in the enclosure, areas where additional information is needed to complete the review.

Specifically, the enclosed requests for additional information (RAIs) are from Section 2.3 System Scoping and Screening Results: Mechanical. These issues have been discussed with your staff.

Your responses to these RAIs are requested within 30 days from the date of this letter. If you have any questions, please contact me at (301) 415-1124 or e-mail gxs@nrc.gov.

Sincerely,

/RA/

Gregory F. Suber, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-368

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION: See next page Accession No: ML041200384 Document Name: C:\\ORPCheckout\\FileNET\\ML041200384.wpd OFFICE:

LA:RLEP PM:RLEP SC:RLEP NAME:

MJenkins GSuber SLee DATE:

4/23/04 4/23/04 4/23/04 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE ARKANSAS NUCLEAR ONE, UNIT 2, LICENSE RENEWAL APPLICATION SECTION 2.3 SCOPING AND SCREENING RESULTS: MECHANICAL (TAC NO. MB8402) 2.3.1 Reactor Coolant system RAI 2.3.1.1-1 Reactor Vessel and CEDM Pressure Boundary It is stated ...The O-rings do not support an intended function of the reactor vessel and are therefore not subject to aging management review. The staff believes that the O-ring leak monitor tube serve as a pressure boundary and the piping should be within the scope of license renewal. Please provide the justification for the exclusion or submit an aging management review (AMR) for the stated component.

RAI 2.3.1.4-1 Pressurizer In Section 2.3.1.4 it is stated that ...The pressurizer components provide RCS pressure control for mitigation of a feedwater line break (FWLB) with AC available as described in Section 15.1.14.2.2.2. However, the most limiting FWLB is without AC power available and the pressurizer sprays are not credited to mitigate that event. Therefore, RCS pressure control using the pressurizer sprays is not an intended function of the pressurizer.

Since credit is taken to mitigate an accident, RCS pressure control using the pressurizer sprays is an accident mitigation function of the pressurizer even if the postulated accident is not the limiting one. Since credit is taken for the pressure control in the accident analysis, pressurizer relief valve discharge pipe and the quencher tank should be within the scope of license renewal. Please provide justification for the exclusion or submit an AMR for the components.

RAI Table 2.3.1-2-1 In Table 2.3.1-3, Class I fittings are listed as components subject to AMR. This a very broad categorization. Please provide a list of specific component fittings.

RAI Table 2.3.1-2-2 Why are the following parts excluded from the scope of license renewal? The staff requests clarification for the following reactor internals exclusion:

CSB Bolts and Lower Internals Assembly Bolts CEA Shroud bolts (Shroud Fasteners are the same as Bolts?)

CSB Snubber Bolts Thermal Shield Bolts Core Shroud Bolts UGS Ring Shim, Tab & Plate, Locking Strip, Guide Pin, Alignment Screw & Nut, Key Slot Tab, Hold Down Ring, Sleeves Lower Internals Assembly Core Support Columns, Core Support Plate, Support beams and flanges, anchor block and dowel pins Thermal Shield positioning Pin and Shim Fuel Assembly Alignment Plate RAI Table 2.3.1-2-3 Diffuser plates are not identified as within the scope of license renewal. The above components provide flow distribution of the reactor coolant and could meet the criteria identified in 10 CFR 54.4(a)(2), and therefore, should be within the scope of license renewal. Please provide justification for the exclusion or submit an AMR for the components.

RAI Table 2.3.1-2-6 In-Core Instrumentation: Instrumentation tubes and safe ends were not identified in the LRA (Table 2.3.1.1) as within the scope of license renewal. The subject components perform a pressure boundary function, and therefore, should be within scope. Please justify the exclusion of this component.

RAI Table 2.3.1-2-7 UFSAR Figure 4.2-14 In-Core Instrument Nozzle indicates that some parts of the nozzle are not within the scope of license renewal. Why are they excluded?

RAI Table 2.3.1-2-8 Are the instrument isolation valve bodies, which act as pressure boundary in the event of a leak in the In-Core Instrumentation System, within the scope of license renewal?

RAI Table 2.3.1-3-1 Reactor Coolant Pumps support lugs were not identified as within the scope of license renewal.

Also in UFSAR 5.5.1.4.2.3, RCP supports, four vertical spring-type hangers, and two horizontal hydraulic snubbers are mentioned. The above components provide structural support and may meet the criteria identified in 10 CFR 54.4(a)(2). Therefore, the components may be within the scope of license renewal. Please provide justification for their exclusion or submit an AMR for the stated component.

RAI Table 2.3.1-5-1 Steam Generators: Why are the internal feedwater distribution ring (elevated feed ring) and the thermal sleeve connecting the header and the nozzle excluded from the scope of license renewal ? Please provide justification for their exclusion or submit an AMP for the stated components.

RAI Table 2.3.1-5-2 Support pads were not identified in the LRA as within the scope of license renewal. The above components provide structural support and could meet the criteria identified in 10 CFR 54.4(a)(2). Therefore, the components should be within the scope of license renewal. Please provide justification for their exclusion or submit an AMP for the stated components.

RAI Table 2.3.1-5-3 Seismic lugs were not identified in the LRA as within the scope of license renewal. The above components provide structural support and could meet the criteria identified in 10 CFR 54.4(a)(2). Therefore, the component should be within the scope of license renewal. Please provide justification for their exclusion or submit an AMP for the stated components.

RAI P&ID-1 On P&ID LRA-M-2236, Sheet 1, a series of screens and supports completely cover the Containment Sump. Also, grading cages and partition plates are in the sump. Are they within the scope of license renewal? Please provide justification for their exclusion or submit an AMP for the stated components.

DISTRIBUTION: Ltr. to Jeff Forbes, RAI Review of the ANO-2 License Renewal Application, Dated: April 23, 2004 Accession No: ML041200384 HARD COPY RLEP RF Gregory Suber E-MAIL:

PUBLIC J. Craig D. Matthews F. Gillespie C. Grimes RidsNrrDe E. Imbro G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair S. Black B. Boger D. Thatcher R. Pettis G. Galletti C. Li M. Itzkowitz R. Weisman M. Mayfield A. Murphy S. Smith (srs3)

S. Duraiswamy Y. L. (Renee) Li RLEP Staff R. Gramm A. Howell T. Alexion Linda Smith RIV

Arkansas Nuclear One, Unit 2 cc:

Executive 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, Richland, Inc.

Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 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 Garry Young 1448 SR 333 Russellville, AR 72802 Mr. Fred Emerson Nuclear Energy Institute 1776 I St., N.W., Suite 400 Washington, DC 20006-3708