05000390/LER-2006-005, Regarding Automatic Reactor Trip Due to Generator Trip

Regarding Automatic Reactor Trip Due to Generator Trip

ML063100073
Person / Time
Site:	Watts Bar
Issue date:	09/26/2006
From:	Skaggs M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 06-005-00
Download: ML063100073 (7)

LER-2006-005, Regarding Automatic Reactor Trip Due to Generator Trip

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3902006005R00 - NRC Website

text

Tennessee Valley Authority, Post Office 2000, Spring City, Tennessee 37381-2000 Mike Skaggs Site Vice President, Watts Bar Nuclear Plant SEP 2 2200 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of Tennessee Valley Authority

))

Docket No.

50-390 WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 -

LICENSEE EVENT REPORT 390/2006-005 -

REACTOR TRIP DUE TO MAIN GENERATOR TRIP This submittal provides LER 390/2006-005.

This LER documents a event that occurred on July 31,

2006, involving an automatic reactor trip due to a main generator trip.

The report contains information regarding this event is provided in accordance with 10 CFR 50.73(a) (2) (iv)

(A).

There are no regulatory commitments associated with this letter.

Should there be questions regarding this submittal, please contact James D. Smith at (423) 365-1824.

Sincerely,

<ie17 Mike Skaggs Enclosure cc:

See Page 2 Printed onrc-do f

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U.S. Nuclear Regulatory Commission Page 2 SEP 2 6 2006 Enclosure cc (Enclosure)

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr.

D. V. Pickett, Senior Project Manager U.S. NuQlear 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. 3150-0104 EXPIRES: 06/3012007 (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.

Watts Bar Nuclear Plant, Unit 1 05000 390 1 OF 5

4. TITLE Automatic Reactor Trip Due to Generator Trip

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

05000 FACILITY NAME DOCKET NUMBER 07 31 2006 2006

-, 005 000 09 26 2006 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5 20.2201(b) 5 20.2203(a)(3)(i)

[5 50.73(a)(2)(i)(C)

E] 50.73(a)(2)(vii) 1 20.2201(d)

[J 20.2203(a)(3)(ii) 5 50.73(a)(2)(ii)(A)

[]

50.73(a)(2)(viii)(A) o] 20.2203(a)(1) 5 20.2203(a)(4) 5 50.73(a)(2)(ii)(B)

[

50.73(a)(2)(viii)(B)

[]

20.2203(a)(2)(i)

[J 50.36(c)(1)(i)(A) 5 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)

10. POWER LEVEL 5

20.2203(a)(2)(ii) 5 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) 5 20.2203(a)(2)(iii) 5 50.36(c)(2) 5 50.73(a)(2)(v)(A) 5 73.71(a)(4) 5 20.2203(a)(2)(iv) 5 50.46(a)(3)(ii) jJ 50.73(a)(2)(v)(B) 5 73.71(a)(5) 100%

E] 20.2203(a)(2)(v) 5 50.73(a)(2)(i)(A)

E] 50.73(a)(2)(v)(C) 5 OTHER [J 20.2203(a)(2)(vi) 5 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 (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

E. Loss of Normal Heat Removal Consideration This event is not considered a scram with loss of normal heat removal.

VII. COMMITMENTS

None