05000296/LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe

Leak in an ASME Class I Code Reactor Pressure Boundary Pipe

ML073270072
Person / Time
Site:	Browns Ferry
Issue date:	11/21/2007
From:	O'Grady B Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 07-003-00
Download: ML073270072 (7)

LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2962007003R00 - NRC Website

text

November 21, 2007 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D. C. 20555-0001

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN)

- UNIT 3 - DOCKET 50-296 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-296/2007-003-00 The enclosed report provides details of a leak in an ASME Class I Code Reactor Pressure Boundary pipe. TVA is reporting this in accordance with 10 CFR 50.73(a)(2)(ii)(A) as an event or condition that resulted in the nuclear power plant, including principal safety barriers, being seriously degraded.

There are no commitments contained in this letter.

Sincerely, Original signed by:

Brian O'Grady cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 November21, 2007 Enclosure cc (Enclosure):

Ms. Eva Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970

U.S. Nuclear Regulatory Commission Page 3 November 21, 2007 JEE:SWA:BAB Enclosure cc (Enclosure):

G.P. Arent, EQB 1B-WBN W. R. Campbell, Jr. LP 3R-C J. R. Douet, LP 3R-C R. G. Jones, POB 2C-BFN R. F. Marks, Jr., PAB 1C-BFN D. C. Matherly, BFT 2A-BFN L. E. Nicholson, BR 4X-C B. A. Wetzel, BR 4X-C S. A. Vance, WT 6A-K E. J. Vigluicci, ET 11A-K INPO:LEREvents@inpo.org NSRB Support, LP 5M-C EDMS WT CA-K, S:lic/submit/lers/296 2007 003.doc

NRC FORM 366 (6-2004)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Browns Ferry Unit 3

2. DOCKET NUMBER 05000296

3. PAGE 1 of 4

4. TITLE: Leak In An ASME Class I Code Reactor Pressure Boundary Pipe

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 None DOCKET NUMBER N/A 09 22 2007 2007-003-00 11 21 2007 FACILITY NAME None DOCKET NUMBER N/A

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

9. OPERATING MODE 3

20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii)

X 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER

10. POWER LEVEL 0

20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D) specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) B.

Corrective Actions to Prevent Recurrence (1)

The 1-inch test line was removed and a cap was welded in its place.

The small bore pipe attached to the RHR system inside the primary containment was visually inspected for absent U-bolts.

TVA will perform a training needs analysis on the removal and installation of pipe support members. Based on the results of the analysis the appropriate personnel may receive training.

VII. ADDITIONAL INFORMATION

A.

Failed Components None.

B.

Previous LERs on Similar Events None.

C.

Additional Information

Corrective action document for this report is PER 130777.

D.

Safety System Functional Failure Consideration:

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

E.

Scram With Complications Consideration:

This event did not result in a complicated scram according to NEI 99-02.

VIII. COMMITMENTS

None.

(1) TVA does not consider this corrective action a regulatory requirement. The completion of this action will be tracked in TVA's Corrective Action Program.