ML120320214

Email, Request for Additional Information, Relief Requests RBS-ISI-016 for Pressure Retaining Welds in Pumps and Valves and RBS-ISI-017 for Pressure Retaining Welds in Control Rod Housings

ML120320214
Person / Time
Site:	River Bend
Issue date:	02/01/2012
From:	Wang A Plant Licensing Branch IV
To:	Burmeister B, Clark J Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME6844, TAC ME6845
Download: ML120320214 (1)

Text

From: Wang, Alan Sent: Wednesday, February 01, 2012 10:54 AM To: 'BURMEISTER, BARRY M'; Joseph Clark (JCLARK@entergy.com)

Cc: Lent, Susan; Burkhardt, Janet

Subject:

River Bend Station Request for Additional Information Regarding RR RBS-ISI-016 and RBS-ISI-017(ME6844 and ME6845)

Joey and Barry, By letter dated August 3, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11221A164), Entergy Operations, Inc (Entergy, the licensee) submitted Entergy Letter RBG-47166, Requests for Relief [RR]from ASME Code Section XI Inservice Inspection Requirements for Pressure Retaining Welds in Control Rod Housings and Pressure Retaining Welds in Pumps and Valves.

The NRC staff has determined that the following additional information is needed to complete our review of these RR. This request for additional information (RAI) was discussed with Mr.

Barry Burmeister of your staff on January 31, 2012, and it was agreed that a response would be provided within 60 days from the issuance of this email. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov.

The following RAIs are related to your letter dated August 3, 2011:

1) General Question for RRs RBS-ISI-016 and RBS-ISI-017 In the licensees submittal dated August 3, 2011, it was noted in the cover letter that RR RBS-ISI-016 and RBS ISI-17 were submitted beyond the one year time frame specified under 10 CFR 50.55a(g)(5)(iv) and that the omission had been address in the Entergys Correction Action Process. Provide an action number, if one exists and date of the action.

What was the reason for the lateness in submitting RRs RBS-ISI-016 and RBS-ISI-017 to the NRC?

2) REQUEST FOR RELEIF RBS-ISI-016 ASME CODE, SECTION XI, TABLE IWB-2500-1, EXAMINATION CATEGORY B-O, ITEM 14.10 WELDS IN CONTROL ROD DRIVE (CRD)

HOUSINGS

a. Since there has been an improvement in visual examinations over the past few years by remote camera, has the licensee considered visual examinations using a remote camera for future visual examinations of the control rod drive (CRD) housings?

b. In keeping of As Low As Reasonable Achievable (ALARA), what would have been the estimated dosage rate if the ASME Code examinations were performed in second 10-year ISI interval?

c. In the staffs evaluation of RR R-004 contained in NUREG-0989, Safety Evaluation Report Related to the Operation of River Ben Station, Supplement 3, Appendix L, dated May 1984

(ADAMS Accession Number ML09138041), it was stated that: In the event that the CRD Housings are disassembled for inservice repair or maintenance, so that the subject welds and bolting are accessible, the staff will require that the presevice be performed at that time. Where the CRD housings ever disassembled for inservice repair or maintenance and the preservice examination performed? What were the results, if the examinations were performed?

d. Was relief given by the NRC for the ASME Code-required examinations of the CRD Housings in the first 10-year ISI interval? Provide the date of the NRC SE if relief was given.

e. Will the licensee commit to perform the required ASME Code examinations in the third 10-year ISI interval if the CRD Housings are disassembled for inservice repair or maintenance, and if the subject welds and bolting are accessible.

3) REQUEST FOR RELEIF RBS-ISI-017 ASME Code CLASS 2 C-G, PRESSURE RETAINING WELDS IN PUMPS AND VALVES

a. Provide materials specifications for the welds and associated components (e.g.,

pumps and valves) for which relief is requested. Discuss which piping systems these welds belong to.

b. Clarify whether these welds were inspected during fabrications. Provide the date of fabrication and pre-service (PSI) inspection, and inspection methods. Discuss any fabrication flaws detected and repaired.

c. Clarify whether these welds have ever been inspected in service in accordance with the requirements of the ASME Code,Section XI, since commercial operation. If yes, discuss the inspection results. If no, provide technical justification for the assurance of the integrity of these welds until the next scheduled inspection.

d. NRC Information Notice (IN) 2011-04, Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized water Reactors, discusses potential stress corrosion cracking (SCC) in stainless steel piping.

1. Provide operating pressure and temperature that these welds are exposed to.

2. Discuss the potential for SCC in these welds.

Alan Wang Project Manager (River Bend Station)

Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan.Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222