05000336/LER-2006-003, Regarding Technical Specifications Required Shutdown
| ML061640262 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/31/2006 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-285 LER 06-003-00 | |
| Download: ML061640262 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 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)(1) |
| 3362006003R00 - NRC Website | |
text
Dominion-Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT 06385 MAY 3 1 200 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/BAK Docket No.
License No.06-285 RO 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 LICENSEE EVENT REPORT 2006-003-00 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN This letter forwards Licensee event Report (LER) 2006-003-00, documenting an event that occurred at the Millstone Power Station Unit 2 on March 31, 2006. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(A) as the completion of any nuclear plant shutdown required by a plant's Technical Specifications.
If you have any questions or require additional information, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Very truly yours, J. a rice Sit~ce President - Millstone zI1z-~ ~
Serial No.06-285 Licensee Event Report 2006-003-00 Technical Specification Required Shutdown Page 2 of 2 Attachments:
1 Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses NRC Senior Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission, Mail Stop 8 C2 One White Flint North 11555 Rockville Pike Rockville, MID 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector
.Millstone Power Station
Serial No.06-285 Licensee Event Report 2006-003-00 Technical Specification Required Shutdown MILLSTONE POWER STATION UNIT 2 LICENSEE EVENT REPORT 2006-003-00 Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc.. (DNC)
V V.
- ~
.{z 1
NRC FORM 366 NUCLEAR REGULATORY COMMI~SSI(kN
'APPROVED BYýOMB! NO. 3150-0104 EXPIRES: 06430/2007 (6-2004)
, the NRC (Seerevrseforreqire nuberof dgit/chracersforeac blck) may not conduct or sponsor. and a person is not required to respond to, the Information coillaction.
FACILITY NAME, (1)
DOCKET NUMBER M2 PAGE (3)
Millstone Power Station -Unit 2 05000336 1 of 2 TITLE (4)
Technical Specification Required Shutdown J
EVENTT AT(5)
LER NUMBER (6)
REPORTD (A~7)
OTHER FACILITIES INVOLVED (8)
I I
}
FACILITY NAME
~DOCKET NUMBER MO DAY YEAR YEAR NUBE RENO MO IDAY YEAR 1NM R1 N.I_______
05000 04 01 2006 2006-003-00 05 31 06
_ ______j 05000 OPEATNGTHIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFRI (Check all that aoply)(11)
MD()
20.2201(b) 20.2203(a)(3)(ii) 150.73(a)(2)(1I)(B) 160.73(a)(2)(lx)(A)
POWER 200 2120.2201 20.2203(a)(4)
__50.73(a)(2)(Iii) 50.73(a)(2)(x)
LVL(0120.2203(a)(1) 50.36(c(1) I A)
__50.73 a) 2) I A) 73.71(a)(4)
S 20.2203(a)(2)(1) 0.36(c)(1)(11)(A)
__ 50.73(a)(2)(v)(A) 73.71(a(5)
S 20.2203(a)(2)(111) 160.6(a)3)(1)
__ % i)(2(V(C Specif I Astract below or
- - J 20.2203(a)(2)(Iv)
X 150.73(a)(2X(1)(A)
__50.73(
a2v)(D)
- ~ 20.2203(a)(2)(v) 0-73 a)(2)(I)(B)
__50.73La 2 vii)~~N~
H
~20.2203(a)(2)(vl)
__50.73(a)(2)(1)(C) 0.73(a(2) vIll A)
~
~
20.2203(a)(3)(1)
- - 50.73(a)(2)(11)(A)
I 150.73(a)(2)(vll (B)
K LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Code)
David W. Dodson, Supervisor Nuclear Station Licensing 1 (860) 447-1791 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
SYSTEM ICOMPONENT I MANU-I REPORTABLE
CAUSE
I I
FACTURER I
TO EPIX I
T 91YES (If yes, complete EXPECTED SUBMISSION DATE).
On April 1, 2006, Millstone Power Station Unit 2 completed a shutdown from 100% power required by the Technical Specifications due to the inoperability of the turbine driven auxiliary feedwater (TDAFW) pump.
On March 29, 2006, Technical Specification (TS) 3.7.1.2 was entered when the TDAFW pump was taken out of service for maintenance and subsequent post-maintenance operability testing. During the operability test, white smoke was observed coming from the TDAFW pump outboard bearing housing vent. The test was terminated and subsequent inspection determined that the pump outboard thrust bearing had tailed. The TDAFW pump could not be restored to an operable status within the specified TS allowed outage time so a shutdown was commenced on March 31, 2006, at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />. The unit reached hot shutdown at 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br /> on April 1, 2006.
The root cause of the bearing failure was overloading as a consequence of balance drum/sleeve wear caused by balance drum/sleeve misalignment. The damage progressed to the point that overloading of the thrust bearing occurred with resultant bearing failure. The time of failure was the time of discovery.
Corrective actions included replacement of damaged components and review of all procedures that affect shaft alignment on HTMA model pumps (such as the TDAFW pump) to ensure correct pump assembly.
This is being reported under 10 CFR 50.73(a)(2)(i)(A) as the completion of any nuclear plant shutdown required by the plant's Technical Specifications.
NRC FORM 366 (6-2004)
(if more space Is required, use additional copies of NRC Foant 366A) (17) 1.
Event DescriDtion On March 31, 2006 at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> with the unit at 100% power, Millstone Power Station Unit 2 commenced a shutdown of the reactor in accordance with Technical Specification (TS) 3.7.1.2.a due to the inability to restore the Turbine Driven Auxiliary Feedwater [B3A] (TDAFW) pump to an operable status following a planned maintenance activity. The shutdown was completed at 1406 on April 1, 2006.
On March 29, 2006, Technical Specification (TS) 3.7.1.2 was entered when the TDAFW pump was taken out of service for maintenance and subsequent post-maintenance operability testing. During the operability test, white smoke was observed coming from the TDAFW pump outboard bearing housing vent. The test was terminated and subsequent inspection determined that the pump outboard thrust bearing had failed. The time of failure was the time of discovery. The TDAFW pump could not be restored to an operable status within the specified TS allowed outage time so a shutdown was commenced on March 31, 2006, at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />. The unit reached hot shutdown at 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br /> on April 1, 2006.
The damaged components were replaced; the pump was successfully tested and restored to an operable status.
This condition is being reported under the provision of 10 CFR 50.73(a)(2)(i)(A) as the completion of any nuclear plant shutdown required by the plant's Technical Specifications.
- 2.
Cause
A Root Cause Evaluation of the event has been completed.
The root cause of the, bearing failure was overloading as a consequence of balance drum/sleeve wear caused by balance drum/sleeve misalignment.
- 3.
Assessment of Safety Conseauences During the shutdown, both motor-driven AFW pumps were available and all safety systems performed as designed.
- 4.
Corrective Action
After thorough inspection of the pump internals, the only damaged components were the bearing, balance drum and sleeve. These components were replaced and the pump was reassembled, tested and returned to service.
IActions to prevent reoccurrence include reviewing procedures that affect s haft alignment on HTMA model pumps (such as the TDAFW pump) to ensure correct pump assembly.
Additional corrective actions are being taken in accordance with the station's corrective action program.
5. Previous Occurrences
,No similar bearing failures of the TDAFW pump have occurred at the Unit Within the previous three years.
Energy Industry Identification System (EIIS) codes are identified In the text as [XX].