ML17163A050
| ML17163A050 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/08/2017 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Gerald Williams Tennessee Valley Authority |
| References | |
| MF9257 | |
| Download: ML17163A050 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Saba, Farideh Sent:
Thursday, June 08, 2017 8:12 PM To:
Williams, Gordon Robert; Hammargren, Benjamin John (bjhammargren@tva.gov)
Cc:
Schrull, Edward Dustin; Shoop, Undine; Young, Austin
Subject:
RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 Attachments:
RAI for Browns Ferry 3-ISI-28.docx Importance:
High Tracking Tracking:
Recipient Read Williams, Gordon Robert Hammargren, Benjamin John (bjhammargren@tva.gov)
Schrull, Edward Dustin Shoop, Undine Young, Austin Read: 6/9/2017 9:00 AM
- Gordon, By letter dated January 31, 2017 (Agencywide Documents Access and Management System (ADAMS)
Accession No. 17031A351), the Tennessee Valley Authority (TVA) submitted relief requests 3-ISI-28 and -29, requesting relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for Browns Ferry Nuclear Plant (Browns Ferry) Unit 3. Specifically, pursuant to Title 10 of the Code of Federal Regulations 50.55a(g)(5)(iii), the licensee requested relief from the essentially 100 percent volumetric examination coverage requirements of ASME Code Section XI for the welds on the basis that the code requirement is impractical. The NRC has determined that the following additional information is necessary to complete its review and make a regulatory decision.
The Nuclear Regulatory Commission (NRC) staff has determined that additional information, as described in the attached request for additional information (RAI), is required for the staff to complete its review of the relief request 3-ISI-28. As was requested by TVA, the NRC staff held a clarification call with TVA staff today (06/08/17). As we agreed, please submit to the NRC your response to this RAI by 07/10/17.
- 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:
3557 Mail Envelope Properties (fa547d0ac881468086ba02695a24d9ee)
Subject:
RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 Sent Date:
6/8/2017 8:12:17 PM Received Date:
6/8/2017 8:12:00 PM From:
Saba, Farideh Created By:
Farideh.Saba@nrc.gov Recipients:
"Schrull, Edward Dustin" <edschrull@tva.gov>
Tracking Status: None "Shoop, Undine" <Undine.Shoop@nrc.gov>
Tracking Status: None "Young, Austin" <Austin.Young@nrc.gov>
Tracking Status:: Response: Read : 6/9/2017 9:00:00 AM "Williams, Gordon Robert" <grwilliams1@tva.gov>
Tracking Status: None "Hammargren, Benjamin John (bjhammargren@tva.gov)" <bjhammargren@tva.gov>
Tracking Status: None Post Office:
HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 1478 6/8/2017 8:12:00 PM RAI for Browns Ferry 3-ISI-28.docx 19007 Options Priority:
High Return Notification:
No Reply Requested:
Yes Sensitivity:
Normal Expiration Date:
Recipients Received:
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 3-ISI-28 REGARDING EXAMINATION COVERAGE OF INSIDE RADIUS AND NOZZLE-TO-VESSEL WELDS TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296 CAC NO. MF9257
1.0 INTRODUCTION
By letter dated January 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML17031A351), Tennessee Valley Authority (TVA, the licensee) submitted relief requests 3-ISI-28 and -29, requesting relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for Browns Ferry Nuclear Plant (Browns Ferry) Unit 3. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(5)(iii), the licensee requested relief from the essentially 100 percent volumetric examination coverage requirements of ASME Code Section XI for the welds on the basis that the code requirement is impractical. The NRC has determined that the following additional information is necessary to complete its review and make a regulatory decision.
RAI 1
The examinations performed during this ten-year inservice inspection (ISI) interval show a significant drop in coverage from those reported in the previous interval. The table below compares the coverages reported in this relief request and those reported in Browns Ferry request for relief 3-ISI-18:
Coverage Obtained in the Second ISI Interval (3-ISI-18)
Coverage Obtained in the Third ISI Interval (3-ISI-28)
N1B-NV 77%
25%
N4A-NV 77%
32%
N4B-NV 68%
32%
N4C-NV 68%
32%
N4D-NV 94.37%
32%
N4E-NV 94.37%
32%
N4F-NV 77%
32%
N8A-NV 71%
77%
N9-NV 74%
27%
N10-NV 97.31%
74%
Please discuss what caused the decrease in obtainable coverage and justify how this examination provides an equivalent or greater standard of quality and safety.