ML051530222
| ML051530222 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/02/2005 |
| From: | Gregory Suber NRC/NRR/DRIP/RLEP |
| To: | Forbes J Entergy Operations |
| Suber G, NRR/DRIP/RLEP 301-415-1124 | |
| References | |
| Download: ML051530222 (7) | |
Text
June 2, 2005 Jeffrey S. Forbes, Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72801-0967
SUBJECT:
ERRATA FOR THE U.S. NUCLEAR REGULATORY COMMISSION (NRC)
SAFETY EVALUATION REPORT (SER) RELATED TO THE LICENSE RENEWAL OF ARKANSAS NUCLEAR ONE, UNIT 2
Dear Mr. Forbes:
Please replace the pages of the NRCs SER related to the license renewal of Arkansas Nuclear One, Unit 2, dated April 7, 2005, with the attached revised pages. The issue date of the cover page was incorrect and the closure of an inspection related Open Item was not properly documented in the SER, Section 2. Additionally, several commitments were inadvertently removed from Appendix A.
In accordance with 10 CFR 2.790 of the NRCs ?Rules of Practice, a copy of this letter and its enclosure will be available electronically in the NRCs Public Document Room or in the Publicly Available Records (PARS) component of the Agencywide Documents Access and Management System (ADAMS) using Accession No. ML051530222. The ADAMS Public Electronic Reading Room is accessible from the NRCs Web site at http://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS, or who encounter problems in accessing the documents located in ADAMS, should contact the NRCs PDR Reference staff at 1-800-397-4209, or 301-415-4737, or by e-mail at pdr@nrc.gov.
If you have any questions, please contact me at 301-415-1124 or e-mail gxs@nrc.gov.
/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
ML051530222 Document Name: E:\\Filenet\\ML051530222.wpd OFFICE:
PM:RLEP LA:RLEP SC:RLEP NAME:
G. Suber M. Jenkins S. Lee DATE:
05/ 31 /05 05/ 30 /05 06/ 02 /05
Safety Evaluation Report Related to the License Renewal of the Arkansas Nuclear One, Unit 2 Docket No. 50-368 Entergy Operations, Inc.
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation April 2005
2-110 Based on its review, the staff finds the applicants supplemental response to RAI 2.4-7, part (d),
acceptable because it adequately describes the basis for excluding the unit auxiliary transformer foundation and the main transformer foundation from the scope of license renewal. In addition, it clarifies that the whole turbine building is included within the scope of license renewal. The staff concludes that the applicant has properly applied the scoping criteria of 10 CFR 54.4(a).
Therefore, the staff considers its concern described in RAI 2.4-7 resolved.
On March 1 to 5, 2004, the NRC staff performed a scoping and screening inspection at ANO-2.
During the inspection, the NRC staff noted that cabling necessary for coping with a station blackout event was supported by the concrete floor slab in the switchyard control house. In accordance with 10 CFR 54.4(a)(3), the applicant had appropriately included the cabling in the scope of license renewal as a system relied on for meeting the NRC's station blackout rule (10 CFR 50.63). However, the applicant did not include the structure on which it was mounted.
The staff stated that as the cabling could not perform it's station blackout coping function without adequate support, its structural support system must also be in the scope of license renewal. The applicant agreed to include the entire structure in the scope of license renewal. Subsequent to the inspection, the applicant told the staff that despite this omission, the floor slab was included in a program for managing the effects of aging.
The NRC staff inspection identified an item requiring action by the applicant. The item listed above is identified in the ANO-2 Inspection Report, dated April 19, 2004 (ML0411006481). The applicant indicated that the concrete floor slab was included in an aging management program.
The aging management review is discussed in Section 3.5.2.3.2. The final disposition of this item was addressed by the Aging Management Review Inspection Report, dated January 9, 2005.
2.4.3.3 Conclusion The staff reviewed the LRA and related structural/component information, including the accompanying scoping boundary drawings (if applicable), to determine whether the applicant failed to identify any SSCs that should be within the scope of license renewal. The staff found one omission as indicated above. The staff concludes that the omission was a human error made in implementing the scoping and screening process and not indicative of an inadequate scoping and screening methodology. In addition, the staff performed an independent assessment to determine whether the applicant failed to identify any components that should be subject to an AMR. On the basis of its review, the staff concludes that the applicant has adequately identified the components of the auxiliary building, turbine building, and yard structures that are within the scope of license renewal, as required by 10 CFR 54.4(a), and the components of the auxiliary building, turbine building, and yard structures that are subject to an AMR, as required by 10 CFR 54.21(a)(1).
2.4.4 Intake Structure and Emergency Cooling Pond 2.4.4.1 Summary of Technical Information in the Application In Section 2.4.3 of the LRA, the applicant described the intake structure and emergency cooling pond. The intake structure is in the southeast corner of the plant site. It is a reinforced concrete seismic Category I structure considered an extension of the ANO-1 intake structure.
A-20 Non-EQ Inaccessible Medium-Voltage Cables 40 The ANO-2 Non-EQ Inaccessible Medium-Voltage Cable Program will include testing of underground medium-voltage cables exposed to significant voltage that perform a license renewal intended function, regardless of preventive actions to prevent exposure to significant moisture.
Prior to entering the period of extended operation.
Letter 2CAN020502,
pg 1 Additional Commitments 41 The chemistry procedure and engineering report will be revised to address loss of the passive layer if chemistry limits are out of specification for an extended period.
Prior to entering the period of extended operation Letter 2CAN120403,
pg 1 42 The PSPM Program will be revised to include an inspection of the alternate AC diesel generator starting air tank.
Prior to entering the period of extended operation Letter 2CAN120403,
pg 1
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. James Ross Nuclear Energy Institute 1776 I St., N.W., Suite 400 Washington, DC 20006-3708
DISTRIBUTION: Letter to J. Forbes, Re: Errata for NRC SER related to ANO-2, Dated: June 2, 2005 ADAMS Accession No.: ML051530222 HARD COPY RLEP RF E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li K. Winsberg (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff R. Gramm A. Howell D. Holland Linda Smith RIV R. Nease