05000296/LER-2010-003, Multiple Test Failures of Excess Flow Check Valves

Multiple Test Failures of Excess Flow Check Valves

ML101470417
Person / Time
Site:	Browns Ferry
Issue date:	05/25/2010
From:	Polson K Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 10-003-00
Download: ML101470417 (8)

LER-2010-003, Multiple Test Failures of Excess Flow Check Valves

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
2962010003R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 25, 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 50-29612010-003-00 The enclosed Licensee Event Report provides details of a failure to meet the requirements of Browns Ferry Nuclear Plant Unit 3 Technical Specification 3.6.1.3 concerning primary containment isolation excess flow check valve operability. The Tennessee Valley Authority is submitting this report in accordance with 10 CFR 50.73(a)(2)(i)(B), as any operation or condition prohibited by the plant's Technical Specifications.

A supplement to this LER will be submitted by August 2, 2010, following completion of the Maintenance Rule a(1) recovery plan to define long term corrective actions. Should you have any questions concerning this submittal, please contact S. T. Day, Jr., Acting Site Licensing and Industry Affairs Manager, at (256) 729-2636.

Respectfully, Ký. J. ol6son Vice President cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 May 25, 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, and a person is not required to respond to, the information collection.

(See reverse for required number of

3. PAGE Browns Ferry Nuclear Plant Unit 3 05000296 1 of 6

4. TITLE: Multiple Test Failures of Excess Flow Check Valves

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MO YEAR YEAR NUMBER NO.

N/A N/A FACILITY NAME DOCKET NUMBER 03 26 2010 2010 -

003 00 05 25 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)

[I 20.2203(a)(3)(i)

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

-] 50.73(a)(2)(vii) 4O 20.2201(d) 0l 20.2203(a)(3)(ii) 0l 50.73(a)(2)(ii)(A)

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

E] 20.2203(a)(1) 0l 20.2203(a)(4)

[I 50.73(a)(2)(ii)(B)

[I 50.73(a)(2)(viii)(B) 0_ 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii)

[1 50.73(a)(2)(ix)(A)

10. POWER LEVEL EJ 20.2203(a)(2)(ii)

Dl 50.36(c)(1)(ii)(A) 0l 50.73(a)(2)(iv)(A)

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

El 20.2203(a)(2)(iii) 0l 50.36(c)(2) 0l 50.73(a)(2)(v)(A)

[1 73.71 (a)(4)

E] 20.2203(a)(2)(iv) 0l 50.46(a)(3)(ii)

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

El 50.73(a)(2)(v)(C)

Dl OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D) ef. n A (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 (if more space is required, use additional copies of NRC Form 366A) (17)

C.

Additional Information

The corrective action document for this report is Problem Evaluation Report (PER) 222850.

D.

Safety System Functional Failure Consideration:

This event is not a safety system functional failure according to NEI 99-02.

E.

Scram With Comolications Consideration:

This event did not include a reactor scram.

VIII. COMMITMENTS

A supplement to this LER will be submitted by August 2, 2010, following completion of the Maintenance Rule a(1) recovery plan to define long term corrective actions.