ML17072A010
| ML17072A010 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/14/2017 |
| From: | Phyllis Clark Division of License Renewal, License Renewal Projects Branch 1 |
| To: | Chisum M Entergy Operations |
| Clark P | |
| References | |
| CAC MF7492 | |
| Download: ML17072A010 (4) | |
Text
1 Clark, Phyllis From:
Clark, Phyllis Sent:
Tuesday, March 14, 2017 9:18 AM To:
'mchisum@entergy.com' Cc:
'jjarrel@entergy.com'; 'dfrey@entergy.com'; 'lmurr91@entergy.com'; 'GYOUNG4
@entergy.com'; 'Dlach@entergy.com'; 'ataylo1@entergy.com'; 'aharris@entergy.com';
'Milster, Leia Elizabeth'; Ramirez, Frances; Speer, Chris; Wittick, Brian; Morey, Dennis; RidsNrrDlr Resource; RidsNrrDlrRpb1 Resource; RidsNrrDlrRerb Resource; RidsNrrDlrRarb Resource; RidsNrrDlrRasb Resource; RidsNrrDlrRsrg Resource; RidsNrrPMWaterford Resource; RidsRgn4MailCenter Resource; Folk, Kevin; Keegan, Elaine; Buford, Angela; Prinaris, Andrew; Wong, Albert; Huynh, Alan; Sweat, Tarico; Medoff, James; Gavula, James; Lopez, Juan; Cuadrado de Jesus, Samuel; Min, Seung; Obadina, Sarah; Sadollah, Mohammad; Rogers, Billy; Brittner, Donald; Fu, Bart; Allik, Brian; Lehman, Bryce; Gardner, William; Thomas, George; Mink, Aaron; Doutt, Clifford; Holston, William; Yoo, Mark; Pulvirenti, April; McIntyre, David; Burnell, Scott; Moreno, Angel; Kennedy, Kriss; Scott, Catherine; Yoder, Matthew; Chazell, Russell
Subject:
REF: WATERFORD STEAM ELECTRIC STATION, UNIT 3, LICENSE RENEWAL APPLICATION - RAI SET 15 (CAC NO. MF7492)
Attachments:
Waterford 3 LRA RAI Set 15 (Final) (002).docx UNITEDSTATES NUCLEARREGULATORYCOMMISSION WASHINGTON,D.C.205550001
Mr. Michael R. Chisum Site Vice President Entergy Operations, Inc.
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WATERFORD STEAM ELECTRIC STATION, UNIT 3, LICENSE RENEWAL APPLICATION - SET 15 (CAC NO. MF7492)
Dear Mr. Chisum:
By letter dated March 23, 2016, Entergy Operations, Inc. submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license NPF-38 for Waterford Steam Electric Station, Unit 3. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified areas where additional information is needed to complete the review.
The enclosed requests for additional information were discussed with Mr. Alan Harris and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-6447 or by e-mail at Phyllis.Clark@nrc.gov.
Sincerely,
2 Phyllis Clark Phyllis Clark, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
As stated cc: Listserv ADAMS Accession No.: ML17072A010 *via email
OFFICE PM:RPB1:DLR BC:RPRB:DLR Acting BC:RPB1:DLR PM:RPB1:DLR NAME PClark DMorey*
RChazell*
PClark DATE 3/7/2017 3/1/2017 3/13/2017 3/14/2017
WATERFORD STEAM ELECTRIC STATION, UNIT 3 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION - SET 15 (CAC NO. MF7492)
RAI 4.2.3-1a:
Background:
In its letter dated February 6, 2017, the applicant responded to RAI 4.2.3-1 that addressed the adequacy of updated initial RTNDT values for reactor vessel beltline plates. In its response, the applicant identified specific paragraphs of ASME Section III, NB-2331 (i.e., paragraphs (a)(2),
(a)(3) and (a)(4)) that were used to determine the initial RTNDT values. The provisions in these paragraphs are summarized as follows:
Paragraph (a)(2): TNDT (nil-ductility transition temperature by drop weight tests) is the initial RTNDT if each specimen of the Charpy impact (Cv) test exhibits at least 35 mils (0.89 mm) lateral expansion and absorbed energy not less than 50 ftlb at a temperature not greater than TNDT + 60°F.
Paragraph (a)(3): When paragraph (a)(2) is not met, additional Cv tests are conducted in groups of three specimens to determine the temperature TCv at which they are met. In this case, the initial RTNDT is the higher of TNDT and TCv - 60°F.
Paragraph (a)(4): When a Cv test has not been performed at TNDT + 60°F or the Cv test at TNDT + 60°F does not exhibit a minimum of 50 ftlb and 35 mils lateral expansion, TCv may be determined from a full Cv impact curve developed from the minimum data points of all the Cv tests performed. In this case, the initial RTNDT is the higher of TNDT and TCv -
60°F.
The applicant indicated that the initial RTNDT of lower shell plate M-1004-2 was determined in accordance with paragraph (a)(3) and that TCv of this material is 47°F. In addition, the applicant provided the TNDT values of reactor vessel beltline plates as part of the response to demonstrate the adequacy of the initial RTNDT values.
Issue:
The staff noted that Table 4 (page 124) of the following document referenced in the applicants response does not identify 47°F as a Cv test temperature for lower shell plate M-1004-2.
Therefore, it is not clear to the staff whether the applicant adequately identified the ASME Code provision that was used to determine the initial RTNDT for that material.
C-PENG-ER-004, Revision 0, Volume 1, October 1995, The Reactor Vessel Group Evaluation Program Phase II Final Report for the Waterford 3 RPV Plates, Forging, Welds and Cladding In addition, the staff noted that TNDT values of reactor vessel beltline plates provided in the applicants response are not consistent with those described in FSAR Table 5.3-13 (i.e., TNDT for plates M-1003-2, M-1003-3, M-1004-1, M-1004-2 and M-1004-3). For example, the FSAR table indicates that TNDT of intermediate shell plate M-1003-2 is -50°F in contrast with -40°F that is identified as TNDT of the material in the applicants response.
Request:
- 1. Provide justification for why Table 4 of C-PENG-ER-004, Revision 0, Volume 1 does not identify 47°F as a Cv test temperature for reactor vessel plate M-1004-2 in contrast with the applicants claim that the initial RTNDT of the plate was determined in accordance with ASME Code Section III, NB-2331, paragraph (a)(3). As part of the response, explain how the applicant determined the TCv value of the M-1004-2 plate (i.e., 47°F).
- 2. Resolve the inconsistency regarding the TNDT values of reactor vessel plates between the applicants response and FSAR Table 5.3-13.