05000296/LER-2020-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
| ML20189A179 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/07/2020 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 2020-002-00 | |
| Download: ML20189A179 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2962020002R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 7, 2020 10 CFR 50.73 10 CFR 50.4(a)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Licensee Event Report 50-296/2020-002 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints The enclosed Licensee Event Report provides details of the inoperability of Main Steam Relief Valves for longer than allowed by plant Technical Specifications. The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations 50.73(a)(2)(i)(B), as any operation or condition which was prohibited by the plants Technical Specifications.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Site Licensing Manager, at (256) 729-2636.
Respectfully, S. M. Bono Site Vice President Enclosure: Licensee Event Report 50-296/2020-002 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
NRC FORM 366 (04-2020)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2020)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2020
- 1. Facility Name Browns Ferry Nuclear Plant, Unit 3
- 2. Docket Number 05000296
- 3. Page 1 OF 7
- 4. Title Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Rev No.
Month Day Year Facility Name N/A Docket Number N/A 05 08 2020 2020 -
002
- - 00 07 07 2020 Facility Name N/A Docket Number N/A
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. Power Level 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4) 100 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C)
OTHER Specify in Abstract below or in Page 7 of 7 platinum to the pilot discs from Ion Beam Assisted Deposition (IBAD) to Plasma Enhanced Magnetron Sputtering (PEMS) Deposition, which data shows provides a more consistent and forgiving finish on the pilot valve seating surface and gives the platinum more inherent ductility. Use of the PEMS method began in 2019, so the valves involved did not receive PEMS deposited platinum coatings during their rebuilds. The PEMS method was used for the pilot discs of the rebuilt valves installed during the U3R19 refueling outage, and will be used for all pilot discs going forward.
VII. Previous Similar Events at the Same Site
A search of BFN Units 1, 2, and 3 LERs for the last five years identified six LERs associated with MSRV lift settings outside of TS required setpoints:
LER 50-260/2019-002-00, for Unit 2 Cycle 20 LER 50-259/2018-007-00, for Unit 1 Cycle 12 LER 50-296/2018-004-00, for Unit 3 Cycle 18 LER 50-260/2017-004-00, for Unit 2 Cycle 19 LER 50-259/2016-005-00, for Unit 1 Cycle 11 LER 50-296/2016-004-00, for Unit 3 Cycle 17
VIII. Additional Information
There is no additional information.
IX.
Commitments
There are no new commitments.