05000296/LER-2010-002, For Browns Ferry, Unit 3, Regarding a Subsystem of the Standby Liquid Control System Was Inoperable Longer than Allowed by the Plants Technical Specifications

For Browns Ferry, Unit 3, Regarding a Subsystem of the Standby Liquid Control System Was Inoperable Longer than Allowed by the Plants Technical Specifications

ML101740434
Person / Time
Site:	Browns Ferry
Issue date:	06/21/2010
From:	Polson K Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 10-002-00
Download: ML101740434 (7)

LER-2010-002, For Browns Ferry, Unit 3, Regarding a Subsystem of the Standby Liquid Control System Was Inoperable Longer than Allowed by the Plants Technical Specifications

Event date:
Report date:
Reporting criterion:	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)(vii), Common Cause Inoperability 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function
2962010002R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 21, 2010 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

Licensee Event Report 50-29612010-002-00 The enclosed Licensee Event Report (LER) provides details of an event involving one subsystem of the Standby Liquid Control (SLC) System being inoperable for longer than allowed by the plant's Technical Specifications.

The Tennessee Valley Authority (TVA) is submitting this report in accordance with 10 CFR 50.73(a)(2)(i)(B), as an operation or condition 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 Dan Williamson, Acting Site Licensing and Industry Affairs Manager, at (256) 729-2636.

Respectfully, Vice President cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 June 21, 2010 Enclosure cc (w/ Enclosure):

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

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 08/31/2010 (9-2007)

, the NRC may not conduct or sponsor, digits/characters for each block) and a person is not required to respond to, the information collection.

3. PAGE Browns Ferry Nuclear Plant Unit 3 05000296 1 of 5

4. TITLE: A Subsystem of the Standby Liquid Control System was Inoperable Longer than Allowed by the Plant's Technical Specifications

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MNH DY YA YER SEQUENTIALI REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SUMEN R

EV MONTH DAY YEAR N/A N/A FACILITY NAME DOCKET NUMBER 04 20 2010 2010 002

- 00 06 21 2010 N/A N/A

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b)

El 20.2203(a)(3)(i)

[I 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii) o 20.2201(d)

El 20.2203(a)(3)(ii)

[] 50.73(a)(2)(ii)(A) 0l 50.73(a)(2)(viii)(A)

[1 20.2203(a)(1) 0l 20.2203(a)(4) 0l 50.73(a)(2)(ii)(B)

[] 50.73(a)(2)(viii)(B) 0_ 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii)

[] 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0

20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A)

[I 50.73(a)(2)(iv)(A)

[I 50.73(a)(2)(x)

Dl 20.2203(a)(2)(iii) 0l 50.36(c)(2)

[E 50.73(a)(2)(v)(A) 0l 73.71(a)(4) 0l 20.2203(a)(2)(iv) 0l 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B) 0l 73.71 (a)(5) 100 El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A) 0l 50.73(a)(2)(v)(C)

El OTHER 0l 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D)

Specify in Abstract belo.o.nNR (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)

VI. CORRECTIVE ACTIONS - The corrective actions are being managed with TVA's Corrective Action Program A.

Immediate Corrective Actions

Operations personnel correctly positioned the 3B SLC pump breaker and the breaker was tested satisfactorily. All other safety-related 480VAC GE AK breakers were visually verified by Operations personnel to be correctly positioned.

B.

Corrective Actions to Prevent Recurrence:

1.

In accordance with TVA policy, appropriate personnel actions were taken for the two AUOs who racked in the breaker for the clearance restoration.

2.

Operations Shift Managers briefed their respective crews about this event.

3.

The event is scheduled to be added and presented to Licensed and Non-Licensed Operator Requalification Training by July 22, 2010.

4.

The GE AK 2A-1 5 type breakers are being evaluated for design modification or additional procedural controls to enhance the reliability of the racking in procedure.

VII. ADDITIONAL INFORMATION

A.

Failed Components:

None B.

Previous LERs on Similar Events:

None C.

Additional Information

Corrective action document for this report is Problem Evaluation Report 225949.

D.

Safety System Functional Failure Consideration:

In accordance with NEI 99-02 guidance, this event is not classified as a safety system functional failure.

E.

Scram With Complications Consideration:

This event did not include a reactor scram.

VIII. COMMITMENTS

None