05000280/LER-2008-001, Regarding Turbine Vibration Results in Manual Trip
| ML081820433 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/16/2008 |
| From: | Jernigan D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 08-0257 LER 08-001-00 | |
| Download: ML081820433 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 |
| 2802008001R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 June 16, 2008 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:
SPS:
Docket No.:
License No.:
08-0257 JSA 50-280 DPR-32
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Unit 1.
Report No. 50-280/2008-001-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Re w Committee for its review.
Very ruly yours, Don E.Je igan, Site Vice resident Surry Power Station Enclosure Commitments contained in this letter:
- 1. The turbine vendor, with participation by Dominion personnel, will complete an evaluation of the event and implement internal corrective actions to prevent future occurrences.
412~
cc:
United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Surry Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE SURRY POWER STATION, UNIT 1 105000 - 280 1 OF 4
- 4. TITLE Turbine Vibration Results in Manual 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 DOCUMENT NUMBER II NUMBER NO.
05000 04 20 2008 2008
-- 001 --
00 06 16 2008 FACILITY NAME DOCUMENTNUMBER 1
105000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E] 20.2201(b)
E] 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[]
50.73(a)(2)(vii)
E] 20.2201(d)
El 20.2203(a)(3)(ii)
[]
50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
N El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[
50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
[]
50.36(c)(1)(i)(A)
Ej 50.73(a)(2)(iii)[E 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[
20.2203(a)(2)(ii)
E]
50.36(c)(1)(ii)(A)
Ej 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
[1]
20.2203(a)(2)(iii)
El 50.36(c)(2)
[]
50.73(a)(2)(v)(A)
[
73.71(a)(4) 20.2203(a)(2)(iv)
[]
50.46(a)(3)(ii)
E]
50.73(a)(2)(v)(B)
[7 73.71(a)(5)
El 20.2203(a)(2)(v)
[]
50.73(a)(2)(i)(A)
[]
50.73(a)(2)(v)(C)
[
OTHER 37%
[]
20.2203(a)(2)(vi)
E] 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Include Area Code)
Donald E. Jerni~Qan, Site Vice President (757) 365-2001CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX D
TA TRB W120 N
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION El YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
[]
NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On April 20, 2008, Unit 1 was placed online following repairs to the "B" 6 th point Feedwater Heater. At 54% reactor power, a rapid load reduction was initiated in response to high turbine bearing vibrations. At 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br />, due to sustained high turbine vibrations, a Unit 1 manual reactor trip was initiated with the reactor at 37% power. All safety systems functioned as designed and the operating staff stabilized the unit at Hot Shutdown. Auxiliary feedwater (AFW) automatically initiated, as expected, due to low steam generator levels. The cause of the event was high turbine vibrations resulting from improperly installed balance weights. The installation was made using the turbine vendor's recommendations that were in error. Updated vendor information was received and the balance move was independently verified by station personnel.
The turbine was rebalanced and the unit placed on line April 21, 2008 and ramped to 100%
reactor power with acceptable turbine vibrations. Dominion will participate in the vendor's evaluation of this event and procedures will be revised to ensure independent review of vendor data. There were no significant safety consequences associated with this event. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A) for a manual actuation of the reactor protection system and automatic AFW initiation.
NRC FORM 366 (9-2007)
PRINTED ON RECYCLED PAPER (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) (17) acceptable. The unit was placed on line at 2348 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.93414e-4 months <br /> and ramped to 100% reactor power on 4/22/08 with vibrations remaining acceptable.
5.0 ADDITIONAL CORRECTIVE ACTIONS
A root cause evaluation (RCE) was initiated.
6.0 ACTIONS TO PREVENT RECURRENCE The RCE determined that the vendor made an error in their recommendation for the Unit 1 turbine balance moves made after the 2007 Unit 1 refueling outage. To prevent recurrence, the vendor, with participation by Dominion personnel, will complete an evaluation of the event and implement internal corrective actions to prevent future occurrences.
7.0 SIMILAR EVENTS
There were no similar events where the vendor supplied information on turbine balance moves that was implemented and later found to be incorrect.
8.0 MANUFACTURER/IMODEL NUMBER Westinghouse Electric Corporation/BB-81
9.0 ADDITIONAL INFORMATION
Unit 2 was at 96% power in an end of core life coast down and remained unaffected by the Unit 1 event.PRINTED ON RECYCLED PAPER