05000260/LER-2015-002, Regarding High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure

Regarding High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure

ML15320A421
Person / Time
Site:	Browns Ferry
Issue date:	11/16/2015
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 15-002-00
Download: ML15320A421 (8)

LER-2015-002, Regarding High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
2602015002R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 November 16, 2015 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260 Licensee Event Report 50-260/2015-002-00 10 CFR 50.73 The enclosed Licensee Event Report provides details of High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure. The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations 50. 73(a)(2)(v)(D), as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

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.

Enclosure:

Licensee Event Report 50-260/2015-002 High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure cc (w/ Enclosure):

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

ENCLOSURE Browns Ferry Nuclear Plant Unit 2 Licensee Event Report High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure See Enclosed

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (01-2014)

LICENSEE EVENT REPORT (LER)

APPROVED BY OMB NO. 3150-0104 EXPIRES 01/31/2017

, 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: High Pressure Coolant Injection System Inoperable Due to Turbine Steam Supply Valve Packing Failure

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR N/A N/A 09 16 2015 2015 - 002 - 00 11 16 2015 N/A 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) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)

OTHER Specify in Abstract below or in VI. Corrective Actions:

Corrective Actions are being managed by TVAs Corrective Action Program under Condition Report (CR) 1082405.

To identify the orientation of valve packing, the maintenance procedures will be revised.

Maintenance and engineering personnel will be briefed on the significant learnings of the packing failure of 2-FCV-73-16.

The packing gland follower on similar valves in Units 1 and 3 will be verified as installed correctly.

VII. Additional Information

A. Previous Similar Events at the same plant:

A search of BFN Licensee Event Reports (LERs) for Units 1, 2, and 3 within the last five years revealed the following event. LER 50-260/2012-002 Unit 2 High Pressure Coolant Injection System Rendered Inoperable Due to an Inoperable Primary Containment Isolation Valve. On June 7, 2012, a steam leak from a leak sealant injection port in the valve packing area resulted in exceeding the allowable primary containment leak rate. The resolution of the packing injection port leak would not have prevented the 2-FCV-73-16 valve packing leak.

B. Additional Information

There is no additional information.

C. Safety System Functional Failure Consideration:

This event is considered a safety system functional failure, because it could have prevented fulfillment of the HPCI System safety functions to mitigate the consequences of an accident.

D. Scram with Complications Consideration:

This event did not result in a reactor scram.

VIII. COMMITMENTS

There are no new commitments.