LER-2018-006, Standby Gas Treatment System Train C Inoperable Longer than Allowed by Tech |
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| Report date: |
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| 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) |
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| 2592018006R00 - NRC Website |
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 December 6, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR 50.73 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Licensee Event Report 50-259/2018-006-00 The enclosed Licensee Event Report provides details of the Standby Gas Treatment System Train C being inoperable 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 plant's Technical Specifications.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact M.W. Oliver, Acting Nuclear Site Licensing Manager, at (256) 729-7874.
Enclosure: Licensee Event Report 50-259/2018-006 Standby Gas Treatment System Train C Inoperable Longer Than Allowed by Technical Specifications cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
ENCLOSURE Browns Ferry Nuclear Plant Units 1, 2, and 3 Licensee Event Report 50-259/2018-006-00 Standby Gas Treatment System Train C Inoperable Longer Than Allowed by Technical Specifications See Enclosed
NRC FORM 366 (04-2018)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2018)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. Facility Name Browns Ferry Nuclear Plant, Unit 1
- 2. Docket Number 05000259
- 3. Page 1 OF 5
- 4. Title Standby Gas Treatment System Train C Inoperable Longer Than Allowed by Technical Specifications
- 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 BFN, Unit 2 Docket Number 05000260 10 06 2018 2018 -
006
- - 00 12 06 2018 Facility Name BFN, Unit 3 Docket Number 05000296
- 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) 80 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 5 of 5 B. For events that occurred when the reactor was shut down, availability of systems or components needed to shut down the reactor and maintain safe shutdown conditions, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident This event did not involve or result in the unavailability of any required systems or components needed to shut down the reactor and maintain safe shut down conditions, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.
SGT A and B remained operable. Operations personnel were able to manually start SGT C.
C. For failure that rendered a train of a safety system inoperable, estimate of the elapsed time from discovery of the failure until the train was returned to service This event resulted in inoperability of the SGT Train C for a time longer than allowed by TS from the last time the SGT train C hand switch was operated on September 27, 2018, until the SGT train C was declared inoperable on October 6, 2018. The switch was replaced and SGT C was returned to service on October 8, 2018.
VI.
Corrective Actions
Corrective actions for this event are being managed under Condition Report 1454001.
A. Immediate Corrective Actions
The SGT train C hand switch was replaced.
B. Corrective Actions to Prevent Recurrence or to reduce the probability of similar events occurring in the future
- 1. All other switches affected by this condition will be replaced.
- 2. A log note will be added to the switchs catalog ID to inspect new switches for barrier plate damage prior to installation.
VII. Previous Similar Events at the Same Site
A search of LERs and the BFN Corrective Action Program found no instances within the past five years of SGT inoperability resulting from a failed switch.
VIII. Additional Information
There is no additional information.
IX.
Commitments
There are no new commitments.
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