ML13319A109
| ML13319A109 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/14/2013 |
| From: | Wang A Division of Operating Reactor Licensing |
| To: | Burmeister B Entergy Nuclear Operations |
| References | |
| MF1867 | |
| Download: ML13319A109 (5) | |
Text
1 NRR-PMDAPEm Resource From:
Wang, Alan Sent:
Thursday, November 14, 2013 5:04 PM To:
BURMEISTER, BARRY M; Joseph Clark (JCLARK@entergy.com); WILLIAMSON, DANNY H Cc:
Burkhardt, Janet; Chen, Qiao-Lynn
Subject:
River Bend Station, Unit 1, Request for Additional Information Regarding Relief Request RBS-ISI-019 (TAC No. MF1867)
Attachments:
River Bend BWRVIP RAI.docx Barry, Danny and Joey, by letter dated May 16, 2013 (ADAMS Accession No. ML13141A257), Entergy Operations Inc., (the licensee) submitted a Relief Request for its fourth ten year interval inservice inspection (ISI) program plan at the River Bend Station, Unit 1 (RBS). The licensees submittal proposes to use various Boiling Water Reactor Vessel and Internals Project guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for ISI of reactor pressure vessel internal components. The NRC staff has determined that additional information is needed to complete the NRC staffs assessment of the subject relief request. Attached is the NRC staffs request for additional information. This request was discussed with Mr. Danny Williamson of your staff on November 14, 2013, and it was agreed that a response would be provided within 30 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.
Alan Wang Project Manager (River Bend Station)
Nuclear Regulatory Commission Division of Operating Reactor Licensing
Hearing Identifier:
NRR_PMDA Email Number:
922 Mail Envelope Properties (C0A338EE37A11447B136119705BF9A3F0204450553D3)
Subject:
River Bend Station, Unit 1, Request for Additional Information Regarding Relief Request RBS-ISI-019 (TAC No. MF1867)
Sent Date:
11/14/2013 5:04:01 PM Received Date:
11/14/2013 5:04:00 PM From:
Wang, Alan Created By:
Alan.Wang@nrc.gov Recipients:
"Burkhardt, Janet" <Janet.Burkhardt@nrc.gov>
Tracking Status: None "Chen, Qiao-Lynn" <Qiao-Lynn.Chen@nrc.gov>
Tracking Status: None "BURMEISTER, BARRY M" <BBURMEI@entergy.com>
Tracking Status: None "Joseph Clark (JCLARK@entergy.com)" <JCLARK@entergy.com>
Tracking Status: None "WILLIAMSON, DANNY H" <DWILL21@entergy.com>
Tracking Status: None Post Office:
HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 1397 11/14/2013 5:04:00 PM River Bend BWRVIP RAI.docx 30203 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST RBS-ISI-019 RIVER BEND STATION REACTOR VESSEL INTERNAL COMPONENTS DOCKET NOS. 50-458 By letter dated May 16, 2013, Entergy Operations Inc., (the licensee) submitted a Relief Request for River Bend Station (RBS) to the US Nuclear Regulatory Commission (NRC) for the fourth ten year interval inservice inspection (ISI) program plan at the River Bend Station, Unit 1 (RBS).
The licensees submittal proposes to use various Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for ISI of reactor pressure vessel internal components. The NRC staff has determined the following information is needed to compete its review:.
(1) RAI-1-The NRC staff requests that the licensee identify whether there are any furnace-sensitized stainless steel vessel attachment welds associated with the RVI components at RBS. It is requested that the licensee provide an explanation regarding the type of inspection program and any additional augmented inspection program that are implemented for any existing furnace-sensitized stainless steel attachment welds at RBS.
(2) RAI Since the following BWRVIP reports are used by the BWR licensees, the NRC staff requests that Entergy should either include or provide an explanation for not including the following BWRVIP reports in Section 5.0 of its submittal dated May 16, 2013.
BWRVIP-138, BWRVIP Updated Jet Pump Beam Inspection and Flaw Evaluation.
BWRVIP-139, BWR Vessel Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines.
BWRVIP-183, BWR Vessel Internals Project, Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines.
(3) RAI The NRC staff requests that the licensee confirm whether NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets.
(4) RAI According to Section 2.0 of the BWRVIP-76 report, core shroud welds shall be inspected every 6 years when the enhanced visual test (EVT-1) method is used for one-sided weld inspections, and shall be inspected every 10 years when the subject welds are examined with the ultrasonic test (UT) method. The inspection frequency for the core shroud welds (H1 through H7) as indicated in Table 1 of Attachment 1 of the submittal dated May 16, 2013, is not consistent with the aforementioned requirement. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Table 1 of of the May 16, 2013, submittal.
(5) RAI-5-Since 182 welds are more prone to inter-granular stress corrosion cracking (IGSCC) than 308/316 welds, the NRC staff requests that the licensee provide information how the aging management program (AMP) is effectively implemented in identifying the extent of aging degradation in these welds in a timely manner.
ENCLOSURE (6) RAI-6-The NRC Staff reviewed the previous inspection results for the various RVI components that are addressed in the Attachment 3 of the licensees May 16, 2013, submittal and determined that additional information is required on the extent of aging degradation in the most susceptible areas of the weld connections in the RVI components as follows:
Top Guide-RAI-6-1: Section 8.1 in BWRVIP-183 states that top guide cells are prone to irradiation assisted stress corrosion cracking (IASCC) when they are exposed to a neutron fluence value greater than 5 x 1020 n/cm2. If the top guide cells at RBS are exposed to a fluence value greater than this threshold limit during the fourth ISI interval, consistent with guidelines addressed in Section 8.1.2 of BWRVIP-183, inspections of the rim areas containing the welds and heat affected zone should be performed every 6 years. Confirm that such inspections will be performed.
Core Spray and Core Spray Spargers-RAI-6-2: During the refueling outages from 2008-2013, a total of 54 welds were inspected and no indications were found. With respect to the examinations of these welds, the staff requests that the licensee provide the following information:
(1) the number of these welds that have Type 304 stainless steel material with a creviced weld geometry, (2) the number of these welds that have Type 304L stainless steel material with a creviced weld geometry, and, (3) the approximate area of inspection coverage.
LPCI Coupling-RAI-6-3: During the refueling outages from 2004-2013, a total of 24 welds were inspected and no indications were found. With respect to the examinations of these welds, the staff requests that the licensee provide the following information:
(1) the number of these welds that have Type 304 stainless steel material with a creviced weld geometry, (2) the number of these welds that have Type 304L stainless steel material with a creviced weld geometry, (3) the approximate area of inspection coverage and, (4) the number of Alloy 182 welds in the inspected population.
RAI-6-4: Provide information for the number of Alloy 182 welds that have been inspected during past outages in the following RVI components and the approximate area of inspection coverage.
(a) jet pumps; (b) in-core dry tubes; and (c) CRD housings ENCLOSURE Core shroud-RAI-6-5: The licensee identified nine percent of weld flaws in core shroud circumferential weld H4 during the 2008 refueling outage inspections. Provide a brief summary of the supporting analyses showing how these findings were dispositioned in the licensees Corrective Action Program.
(7) RAI-7-To assess the effectiveness of RBSs implementation of hydrogen water chemistry (HWC) or HWC in conjunction with noble metal chemical addition (NMCA), the staff requests that the licensee provide the following information:
(1) Measurement of electrochemical potential (ECP) of stainless steel material that represents a typical RVI component. ECP measurement should be made when HWC or HWC and NMCA method is used.
(2) Measurement of the amount of platinum deposit on a stainless coupon if HWC and NMCA method is used.