ML14114A475
| ML14114A475 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/23/2014 |
| From: | Farideh Saba Division of Operating Reactor Licensing |
| To: | Gerald Williams Tennessee Valley Authority |
| References | |
| MF3260 | |
| Download: ML14114A475 (4) | |
Text
1 NRR-PMDAPEm Resource From: Saba, Farideh Sent: Wednesday, April 23, 2014 1:27 PM To: Williams, Gordon Robert (grwilliams1@tva.gov)
Subject:
RAI regarding the proposed changes to TS 3.
4.9 for Browns ferry Unit 1 (MF3260)
Attachments:
MF3260_BFN1_RAI_P-T limits.docx Importance:
High Gordon, The Nuclear Regulatory Commission (NRC) staff has reviewed the proposed license amendment to modify Technical Specification 3.4.9 "Pressure and Temperature (P/T) Limits" submitted by Tennessee Valley Authority (the licensee, TVA) for Browns Ferry Nuclear Plant, Unit 1 (BFN-1), dated December 18, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A067). The NRC staff has determined that additional information is needed to complete the evaluation pertaining to the request (see attached document).
The attached RAI was discussed for clarification during a conference call between the TVA and the NRC staff on 04/22/14. As we agreed during this call, please submit the TVA's response by May 30 2014.
Please let me know if you have any questions or comments.
Thanks, Farideh E. Saba, P.E. Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV
Hearing Identifier: NRR_PMDA Email Number: 1240 Mail Envelope Properties (36CF286628C20846A68047F2463233090103BBBD5AFC)
Subject:
RAI regarding the proposed changes to TS 3.4.9 for Browns ferry Unit 1 (MF3260) Sent Date: 4/23/2014 1:27:00 PM Received Date: 4/23/2014 1:26:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients: "Williams, Gordon Robert (grwilliams1@tva.gov)" <grwilliams1@tva.gov> Tracking Status: None
Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 1024 4/23/2014 1:26:00 PM MF3260_BFN1_RAI_P-T limits.docx 30756
Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received: ZZZ ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED LICENSE AMENDMENT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 TAC NO. MF3260 The Nuclear Regulatory Commission (NRC) staff has reviewed the proposed license amendment to modify Technical Specification 3.4.9 "Pressure and Temperature (P/T) Limits" submitted by Tennessee Valley Authority (the licensee, TVA) for Browns Ferry Nuclear Plant, Unit 1 (BFN-1), dated December 18, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A067). The NRC staff has determined that additional information is needed to complete the evaluation pertaining to the request, as detailed below.
RAI 1 NEDC-33445P (Reference 1), Enclosure 2 to the proposed license amendment, lists the axial electroslag weld (ESW) as the limiting material for the development of the new P/T limit curves for BFN-1. Measured heat-specific Charpy and drop weight toughness data are not available.
The initial RT NDT value in Tables B-2, B-4, and B-5 for the ESW is listed as 23.1
ûF; Tables B-4 and B-5 use a value of 13
ûF for the standard deviation of the initial value to calculate the margin term based on Regulatory Guide 1.99, Revision 2. These values are based on previously approved submittals (Reference 2), which were initially presented in BAW-2258 for Dresden, Units 2 and 3 (Reference 3) and BAW-2259 for Quad Cities, Units 1 and 2 (Reference 4) from January 1996. The values came from the nil-ductility-temperature (T NDT) data contained in the weld procedure qualification records (PQRs) that were performed in the general time frame when the Quad Cities and Dresden reactor vessels were fabricated. This represented the best data available to characterize the unirradiated RT NDT for any ESW in the fleet at the time.
The submittal does not establish how the previously approved values of initial RT NDT (23.1ûF) and standard deviation (13
ûF) from PQRs for the ESWs at Dresden, Units 2 and 3 and Quad Cities, Units 1 and 2 is applicable to BFN-1.
Discuss the limited PQR database in BAW-2258 and BAW-2259 and explain how that database is relevant to the axial vessel welds at BFN-1. Include a summary of the plant fabrication records for the axial welds and any other newer test results that could be used to supplement the limited PQR database. Justify why the previously approved values can be used at BFN-1.
REFERENCES:
- 1. NEDC-33445P - Pressure and Temperature Limits Report Up to 25 and 38 Effective Full- Power Years, December, 2013.
- 2. U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation, dated February 28, 1997, to Dresden and Quad Cities concerning a revision of their Pressure-Temperature Limits, ADAMS No. ML021150615. 3. Evaluation of RT NDT, USE, and Chemical Composition of Core Region Electroslag Welds for Dresden Units 2 and 3, BAW-2258, January 1996, ML14091A387.
- 4. Evaluation of RT NDT, USE, and Chemical Composition of Core Region Electroslag Welds for Quad Cities Units 1 and 2, BAW-2259, January 1996, ML14091A388.