05000390/LER-2006-009, Regarding Containment Spray Valve Interlock Inoperable

Regarding Containment Spray Valve Interlock Inoperable

ML063560056
Person / Time
Site:	Watts Bar
Issue date:	12/19/2006
From:	Skaggs M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 06-009-00
Download: ML063560056 (7)

LER-2006-009, Regarding Containment Spray Valve Interlock Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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
3902006009R00 - NRC Website

text

Tennessee Valley Authority, Post Office 2000, Spring City, Tennessee 37381-2000 Mike Skaggs Site Vice President, Watts Bar Nuclear Plant DEC 19 2O06 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 390/2006-009 -

CONTAINMENT SPRAY VALVE INTERLOCK This submittal provides LER 390/2006-009.

This LER documents a condition identified involving a containment spray valve interlock issue.

The report regarding this condition is provided in accordance with 10 CFR 50.73(a) (2) (i) (B) and 50.73(a) (2)(v)(D).

Should there be questions regarding this submittal, please contact J.

D. Smith at (423) 365-1824.

Sincerely, Mike Skaggs Enclosure Cc:

See Page 2 Printed on recycled Daper

U.S. Nuclear Regulatory Commission Page 2 DC 9 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. 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. 3150-0104 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 Nuclear Plant, Unit 1 05000 390 1 OF 5

4. TITLE Containment Spray Valve Interlock Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE I

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV M

DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.

___I05000

_____1 26 200 206

- 009 0 ~FACILITY NAME DOCKET NUMBER 10 26 2006 2006

- 009 0

12 19 2006 I05000

9. OPERATING MODE

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

O] 20.2201(b)

[] 20.2203(a)(3)(i)

Q] 50.73(a)(2)(i)(C) fl 50.73(a)(2)(vii)

Core Empty

[] 20.2201(d)

El 20.2203(a)(3)(ii)

E] 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

[J 20.2203(a)(1)

El 20.2203(a)(4)

Q 50.73(a)(2)(ii)(B)

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

[]

20.2203(a)(2)(i)

[] 50.36(c)(1)(i)(A)

[] 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)

10. POWER LEVEL 5

20.2203(a)(2)(ii)

E] 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x) 5 20.2203(a)(2)(iii) 5 50.36(c)(2) 5 50.73(a)(2)(v)(A) 73.71 (a)(4) 5 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

[] 50.73(a)(2)(v)(B)

El 73.71(a)(5) 0%

5 20.2203(a)(2)(v) 5 50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C)

El OTHER

[]

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 (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

VII. ADDITIONAL INFORMATION

A. Failed Components There were no failed components due to this condition.

B. Previous LERs on Similar Events A search of previous LERS, identified no reportable conditions due to a rotor misadjustment.

C. Additional Information

None.

D. Safety System Functional Failure This event involves a safety system functional failure as defined in NEI 99 02, Revision 4. A review of the maintenance rule program records during the period March 2005 to October 2006, each CS train was required for a total of approximately 12,830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />. During that period that this condition existed on train B, train A was not available for approximately 113 hours0.00131 days <br />0.0314 hours <br />1.868386e-4 weeks <br />4.29965e-5 months <br />.

E. Loss of Normal Heat Removal Consideration There was no loss of normal heat removal due to this condition.

VIII. COMMITMENTS

None