CNL-21-060, Supplement to Sequoyah Nuclear Plant (Sqn), Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-10
| ML21148A311 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/28/2021 |
| From: | Polickoski J Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNL-21-060 | |
| Download: ML21148A311 (2) | |
Text
1101 Market Street, Chattanooga, Tennessee 37402 CNL-21-060 May 28, 2021 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
Supplement to Sequoyah Nuclear Plant (SQN), Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-10
Reference:
TVA letter to NRC, CNL-21-059, Sequoyah Nuclear Plant (SQN), Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-10, dated May 28, 2021 (ML21148A301)
In the referenced letter, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and Standards," paragraph (z)(2), Tennessee Valley Authority (TVA) submitted a request for an alternative to the inservice testing requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code, Section ISTB-3310, Effect of Pump Replacement, Repair, and Maintenance on Reference Values.
This alternative request applies to testing of the Motor Driven Auxiliary Feedwater (MDAFW)
Pump 1B-B for the Sequoyah Nuclear Plant (SQN), Unit 1 (alternative request RP-10).
TVA is supplementing the information in Section V, Proposed Alternative and Basis for Use, of the referenced letter to provide the following additional information.
In accordance with ISTB-3100, the preservice test method is in accordance with ISTB-5110, which requires flow and differential pressure to be measured at a minimum of five points. If practicable, these points shall be from pump minimum flow to at least pump design flow. The Group A reference value for flow and differential pressure will be essentially the same point as the minimum flow and differential pressure used as the minimum flow point for the preservice test.
U.S. Nuclear Regulatory Commission CNL-21-060 Page 2 May 28, 2021 There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Kimberly D. Hulvey, Senior Manager, Fleet Licensing, at (423) 751-3275.
Respectfully, James T. Polickoski Director, Nuclear Regulatory Affairs cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant