ML092090249
| ML092090249 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/2009 |
| From: | Kalyanam N Plant Licensing Branch IV |
| To: | Entergy Operations |
| Markley, M T, NRR/DORL/LP4, 301-415-5723 | |
| References | |
| TAC MD7178 | |
| Download: ML092090249 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 31, 2009 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO.1 - INDIVIDUAL PLANT ACTIONS RE:
PRESSURIZED-WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-2374, REVISION 2, "RISK-INFORMED ASSESSMENT OF ONCE THROUGH STEAM GENERATOR TUBE THERMAL LOADS DUE TO BREAKS IN REACTOR COOLANT SYSTEM UPPER HOT LEG LARGE-BORE PIPING" (TAC NO. MD7178)
Dear Sir or Madam:
On June 25, 2009, a meeting was held between representatives of the U.S. Nuclear Regulatory Commission (NRC) staff and the Pressurized-Water Reactor Owners Group regarding the proposed resolution of items related to BAW-2374, Revision 2, "Risk-informed Assessment of Once-Through Steam Generator Tube Thermal Loads due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping." A summary of the meeting can be found at Agencywide Documents Access and Management System (ADAMS) Accession No. ML091820001. During this meeting, representatives of Entergy Operations, Inc. participated in a presentation relating to the status of this matter as it relates to Arkansas Nuclear One, Unit NO.1.
The NRC staff requests that you provide a written response to the enclosed list of actions taken from the meeting summary of the June 25, 2009, meeting. This response should describe your plans to address these items and will enable the staff to evaluate the need for any further regulatory action. A response is requested within 30 days from the date of this letter.
Sincerely, Kaly N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosure:
As stated cc w/encl: Distribution via Listserv
ACTIONS RESULTING FROM JUNE 25,2009 MEETING BETWEEN U.S. NUCLEAR REGULATORY COMMISSION AND PRESSURIZED-WATER REACTOR OWNERS GROUP The U.S. Nuclear Regulatory Commission (NRC) requests that within 30 days from the date of this letter, each Babcock and Wilcox (B&W) licensee submit a letter providing plans to address the following items resulting from the June 25, 2009, public meeting (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091820001), regarding once through steam generator (SG) tube loads under conditions resulting from postulated breaks in reactor coolant system (RCS) upper hot leg large-bore piping:
- 1.
Confirmation that its justification for continued operation for addressing tube integrity following a large break loss-of-coolant accident (LBLOCA) remains valid. (All B&W licensees)
- 2.
Confirmation that compensatory measures, such as changes to emergency operating procedures, have been incorporated into plant procedures and operator training has been performed. (All B&W licensees)
- 3.
Confirmation that Title 10 of the Code of Federal Regulations (10 CFR) 50.46(a)(3) reporting requirements have been satisfied. (All B&W licensees)
- 4.
Confirmation that all LBLOCAs (including those in the candy-cane region) are considered as design basis accidents in the assessments of SG tube integrity following each SG tube inspection. (All B&W licensees)
- 5.
Provide a commitment that an analysis will be performed to confirm that the design of the replacement SGs is sufficient to withstand the loads associated with a LBLOCA including the thermal loads associated with a LBLOCA in the candy-cane region of the RCS and to provide the results of that analysis to the NRC by January 31, 2010. (Three Mile Island Nuclear Station, Unit 1, and Arkansas Nuclear One, Unit 1 (ANO-1))
- 6.
Commitment to provide the structural limit associated with the most limiting LBLOCA for the replacement SGs as part of the next SG tube inspection report (required by the technical specifications) following completion of the next inspection of the tubes in the replacement SGs, unless previously submitted. (All B&W licensees)
The NRC requests further dialogue with Entergy Operations, Inc., regarding the ANO-1 alternate source term license amendment request to ensure alignment on the information necessary to complete the NRC's safety review, including any appropriate licensing conditions.
Enclosure
ML092090249 OFFICE DORULPL41PM DORULPL41LA DRNAADBIBC DPRJPSPBIBC DCIICSGBIBC DORULPL41BC DORULPL41PM NAME NKalyanam MMarkley for JBurkhardt RTaylor SRosenberg MGavrilas MMarkley NKalyanam MMarkley for DATE 7131109 7131109 7131109 7131109 7131109 7131109 7131109