ML020450588
| ML020450588 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/14/2002 |
| From: | Alexion T NRC/NRR/DLPM/LPD4 |
| To: | Anderson C Entergy Nuclear Operations |
| References | |
| Download: ML020450588 (4) | |
Text
February 14, 2002 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
CLOSEOUT OF BULLETIN 2001-01 REVIEW FOR ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1) (TAC MB2608)
Dear Mr. Anderson:
On August 3, 2001, the staff issued Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, to the industry requesting that addressees provide information related to the structural integrity of the reactor pressure vessel head penetration (VHP) nozzles for their respective facilities, including the extent of VHP nozzle leakage and cracking that has been found to date, the inspections and repairs that have been undertaken to satisfy applicable regulatory requirements, and the basis for concluding that their plans for future inspections will ensure compliance with applicable regulatory requirements at their respective pressurized water reactor (PWR) plants. You were requested to respond to Items 1 and 2 of Bulletin 2001-01 within 30 days of its issuance.
You provided your Bulletin 2001-01 response by letter dated September 4, 2001, indicating that your plant is classified as having previously identified primary water stress corrosion cracking (PWSCC) in the VHP nozzles. The staff finds that you have provided the requested information. Your Bulletin 2001-01 response stated that you plan to perform a qualified visual examination of 100 percent of the VHP nozzles at your next refueling outage, consistent with the description for such an examination provided in Bulletin 2001-01. Although the proposed inspection method and schedule described in your Bulletin 2001-01 response are not consistent with the discussion in Bulletin 2001-01 for plants which have identified PWSCC in their VHP nozzles, the staff has concluded that the most recent qualified visual examination of 100 percent of the VHP nozzles performed at your plant, in conjunction with your inspection plans, provides reasonable assurance that the public health and safety will be maintained through the next inspection at your plant. Since the proposed inspection scope and schedule described in your response were integral to the staffs finding, it is the staffs expectation that you will submit a revised response to Bulletin 2001-01 if you make any substantive changes to the schedule and/or scope of future inspections for your plant. If warranted by such changes, the staff will reevaluate this issue for ANO-1.
Addressees are reminded that Item 5 of Bulletin 2001-01 requested the following information within 30 days after plant restart following the next refueling outage:
a.
a description of the extent of VHP nozzle leakage and cracking detected at your plant, including the number, location, size, and nature of each crack detected; b.
if cracking is identified, a description of the inspections (type, scope, qualification requirements, and acceptance criteria), repairs, and other corrective actions you have taken to satisfy applicable regulatory requirements. This information is requested only if there are any changes from prior information submitted in accordance with this bulletin.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313 cc: See next page b.
if cracking is identified, a description of the inspections (type, scope, qualification requirements, and acceptance criteria), repairs, and other corrective actions you have taken to satisfy applicable regulatory requirements. This information is requested only if there are any changes from prior information submitted in accordance with this bulletin.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313 cc: See next page DISTRIBUTION:
PUBLIC PDIV-1 Reading RidsOgcRp RidsAcrsAcnwMail Center RidsNrrDlpmLpdiv1 (RGramm)
RidsNrrPMTAlexion RidsNrrLADJohnson K. Brockman, RIV JZimmerman LBurkhart AHiser Accession No.: ML020450588 OFFICE PDIV-1/PM PDIV-1/LA EMCB/BC PDIV-1/SC NAME TAlexion DJohnson WBateman RGramm DATE 11/20/01 11/20/01 02/13/02 02/14/02 OFFICIAL RECORD COPY
March 2001 Arkansas Nuclear One 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 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