05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits

Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits

ML19353B487
Person / Time
Site:	Browns Ferry
Issue date:	12/19/2019
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 2019-001-01
Download: ML19353B487 (9)

LER-2019-001, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)
2602019001R01 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 December 19, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

Licensee Event Report 50-260/2019-001-01 10 CFR 50.73

Reference:

Letter from TVA to NRC, "Licensee Event Report 50-260/2019-001-00,"

dated May 22, 2019 (ML19142A361)

On May 22, 2019, The Tennessee Valley Authority (TVA) submitted Revision Oto Licensee Event Report (LER) 50-260/2019-001-00 (Reference) which provided the details of a failed component that resulted in a principal safety barrier of the nuclear power plant being seriously degraded. The enclosed LER has been revised to correct the manufacturer information for the failed component.

TV A is submitting this revised report in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.73(a)(2)(ii)(A), as a condition that resulted in a principal safety barrier of the nuclear power plant being seriously degraded; in accordance with 10 CFR 50.73(a)(2)(i)(B), as a condition which was prohibited by the plant's Technical Specifications; and in accordance with 10 CFR 50. 73(a)(2)(v)(C), as an event that could have prevented the fulfillment of the safety function of a system that is needed to control the release of radioactive material.

There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.

U.S. Nuclear Regulatory Commission Page 2 December 19, 2019 Enclosure: Licensee Event Report 50-260/2019-001-01 -Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits.

cc (w/ Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant

ENCLOSURE Browns Ferry Nuclear Plant Unit 2 Licensee Event Report 50-260/2019-001-01 Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits.

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 2

2. Docket Number 05000260

3. Page 1 OF 6

4. Title Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits

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 03 23 2019 2019 -

001

- 01 12 19 2019 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) 5 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) 0 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 6 of 6 VI.

Corrective Actions

Corrective actions for this event are being managed under Condition Report 1501555.

A. Immediate Corrective Actions

The failed valve was replaced.

B. Corrective Actions to Prevent Recurrence or to reduce the probability of similar events occurring in the future Design changes will be implemented to add another check valve in series for penetrations 1-X-35F, 2-X-35F, and 3-X-35F to allow dual barrier containment isolation for Units 1, 2, and 3.

While 1-X-35F and 3-X-35F were not affected by this event, they are both single isolation penetrations and therefore vulnerable to a similar condition.

VII. Previous Similar Events at the Same Site

A search of LERs and the BFN Corrective Action Program found no instance within the past five years of the failure of any single isolation PCIV, or of inoperability of any PCIV due to foreign material in the valve.

VIII. Additional Information

There is no additional information.

IX.

Commitments

There are no new commitments.