05000390/LER-2005-002, G45 Fuel Assembly Clad Damage (Preliminary Report)
| ML060200275 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 01/13/2006 |
| From: | Skaggs M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 05-002-00 | |
| Download: ML060200275 (8) | |
| 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) 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 |
| 3902005002R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office 2000, Spring City, Tennessee 37381-2000 Miko Skaggs Site Vice President, Watts Bar Nuclear Plant 10 CFR 50.73 JA.N 13 2006 U.S. Nuclear Regulatory Commission ATTIN: Document Control Desk Washington, D. C. 20555 Gen :emen:
In the Matter of
)
Docket No. 50-390 Tennessee Valley Authority
)
WATTS BAR NUCLEAR PLANT (WBN) - UNIT I - FACILITY OPERATING LICENSE NPF LICENSEE EVENT REPORT (LER) 50-390/2005-002 This submittal provides LER 390/2005-002. This LER documents the results of an inspection of spent fuel that was performed on November 14, 2005. During the inspection an opening was found to exist in the cladding of a fuel pin in fuel assembly G45. The degradation of the fuel assembly cladding (a principal safety barrier) was initially reported under 10 CFR 50.72(b)(3)(ii)(A) on November 14,2005 as Event Notification 42140. The enclosed report contains preliminary information regarding this event is provided in accordance with 10 CFR 50.73(a)(2)(ii)(A). Additional inspections of the affected assembly are planned and the results of the inspections will be provided in a supplement to this LER.
There are no regulatory commitments associated with this letter. Should there be questions regarding this submittal, please contact Paul L. Pace at (423) 365-1824.
Sincerel y//
.. M.
.Skaggs
Enclosure:
LER 390/2005-002 cc: See page 2 E5 25 Phitd am fwyIed paw
U.S. Nuclear Regulatory Commission Page 2 cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Institute of Nuclear Power Operations 700 Galleria Parkway, NW Atlanta, Georgia 30339-5957
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 315040104 EXPIRES: 06/30,2007 (6-2004)
, the NRC (See reverse for required number of may not conduct or sponsor, and a person Is not required to respond to, the diqits/characters for each block)
Information collection.
- 3. PAGE Watts Bar Nuc ear Plant 05000 390 1
OF 6
- 4. TITLE G45 Fuel Assembly Clad Damage (Preliminary Report)
- 5. EVENT DAIE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILmES INVOLVED SEUENTIAL REV MONTH FACILITY NAME DOCKET NUMBER MONTH DAY NUMBER NO.
DAY YEAR 05000
[
FACILITY NAME DOCKET NUMBER 11 14 2005 2005 002 00 01 13 2006 05000
- 9. OPERATING MODE 11.THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR§: (Check allthat apply)
Mode 1 a
20.2201(b)
Q 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii)
O 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)
Q 50.73(a)(2)(viii)(A) o 20.2203(a)(1) a 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) a50.73(a)(2)(Vii)(B) 20.2203(a)(2)(i) a 50.36(c)(1)(i)(A) 5 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL.
5 20.2203(a)(2)(ii) 5 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) 1 00 20.2203(a)(2)(iii)
D 50.36(c)(2) 0 50.73(a)(2)(v)(A)
D 73.71(a)(4) 1 00 20.2203(a)(2)(iv) 5 50A6(a)(3)(ii) a 50.73(a)(2)(v)(B) 5 73.71(a)(5)
O 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C) 5 OTHER o
20.2203(a)(2)(vi) 5 50.73(a)(2)(i)(B) 5 50.73(a)(2)(v)(D)
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VI.
ADDITIONAL INFORMATION
A. Failed components The cladding failed as described In Section 111, "Cause of the Event."
B. Previous LERs on Similar Events There have been no previous LERs initiated for Watts Bar that addressed fuel degradation issues.
C. Additional Information
None.
D. Safety System Functional Failure This fuel cladding degradation event is not considered a safety system functional failure in accordance with Nuclear Energy Institute (NEI) 99-02, Revision 3.
E. Loss of Normal Heat Removal Consideration This event is not considered a scram with loss of normal heat removal.
VIl.
COMMITMENTS
None