05000305/LER-2006-009, Regarding Emergency Diesel Generator (EDG) Fuel Oil Leak
ML062970434 | |
Person / Time | |
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Site: | Kewaunee ![]() |
Issue date: | 10/16/2006 |
From: | Hartz L Dominion Energy Kewaunee |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
06-896 LER 06-009-00 | |
Download: ML062970434 (6) | |
Event date: | |
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Report date: | |
Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) |
3052006009R00 - NRC Website | |
text
i z*"%DV~minion Dominion Energy Kewaunee, Inc.
N490 Highway 42, Kewaunee, WI 54216-9511 OCT 16 2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.06-896 KPS/LIC/RS: RO Docket No.
50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE. INC.
KEWAUNEE POWER STATION LICENSEE EVENT REPORT 2006-009-00
Dear Sirs:
Pursuant to 10 CFR 50.73, Dominion Energy Kewaunee, Inc., hereby submits the following Licensee Event Report applicable to Kewaunee Power Station.
Report No. 50-305/2006-009-00 This report has been reviewed by the Plant Operating Review Committee and will be forwarded to the Management Safety Review Committee for its review.
If you have any further questions, please contact Mr. Richard Sattler at (920) 388-8121.
Very truly yours, Leslie N. Harz Site Vice President, Kewaunee Power Station Attachment Commitments made by this letter: NONE LiZ..---
Serial No.06-896 Page 2 of 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. D. H. Jaffe Project Manager U.S. Nuclear Regulatory Commission Mail Stop O-7-D-1 Washington, D. C. 20555 NRC Senior Resident Inspector Kewaunee Power Station
NRC FORM 366 US. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (6.2004)
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LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by intemet e-(See reverse for required number of mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0066), Office of Management and Budget, Washington, DC 20503.
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FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Kewaunee Power Station 05000305 1 of 4
TITLE (4)
Emergency Diesel Generator (EDG) Fuel Oil Leak EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REV FACILITY NAME DOCKETNUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR N
W FACILITY NAME DOCKET NUMBER 08 17 2006 2006 009 00 10 16 2006 FACILITYNAME DOCKETNUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (Check all that apply) (11)
MODE (9) 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 1_00 20.2203(a)(1) 50.36(c)(1 )(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4)
_..20.2203(a)(2)(i) 50.36(c)(1 )(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2)
X 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or in 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A)
X 50.73(a)(2)(v)(D) 20.2203(a)(2)(v)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Richard Sattler (920) 388-8121 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR YES (If yes, complete EXPECTED SUBMISSION DATE).
NO SUBMISSION 01 15 2007 x YI IDATE (15)
____1 ABSTRACT At 17:35 on 8/17/06, after approximately 10 minutes of operation during a planned surveillance test on Emergency Diesel Generator (EDG) A, a previously identified minor fuel oil leak (approximately 1 drop/minute) increased and required an unplanned engine shutdown. The EDG had been declared inoperable at the start of the surveillance test and remained so following the leak. At its maximum, the leakrate was estimated at between 0.12 and 0.25 gpm.
By 05:53 on 8/18, the leak had been repaired, the surveillance test completed, and the EDG restored to OPERABLE status.
The fuel oil leak was initially identified on 6/28/06 at 16:48. Between 6/28 and 8/17, the EDG had been operated four times with a cumulative run time of approximately 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The investigation is ongoing and the leak failure mechanism has not been determined. However, since the June leak increased after approximately 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of engine operation, a conservative decision has been made to declare the EDG inoperable from 6/28/06 to 8/17/06.U.S. NUCLEAR REGULATORY COMMISSION (1 -2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL I REVISION Kewaunee Power Station 05000305 Y
NUMBER NUMBER 2 of 4 2006
"" 009 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
At 17:35 on 8/17/06, after approximately 10 minutes of operation during a planned surveillance test on EDG A [DG], a previously identified minor fuel oil leak increased and required an unplanned engine shutdown. The EDG had been declared inoperable at the start of the surveillance test and remained so following the leak. At its maximum, the leakrate was estimated at between 0.12 and 0.25 gpm. The leak did not atomize.
By 05:53 on 8/18, the leak had been repaired, the surveillance test completed, and the EDG restored to OPERABLE.
The fuel oil leak (approximately 1 drop/minute) was initially identified on a copper tubing Swagelock fitting (downstream of the engine-driven fuel oil pump [P] and the fuel priming pump), on 6/28/06 and a Work Order was written to repair it. Between 6/28 and 8/17, with the leak not repaired, the EDG had been operated four times with a cumulative run time of approximately 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
EVENT ANALYSIS
This event is being reported under § 50.73(a)(2)(v)(B) and (D) as a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat and mitigate the consequences of an accident.
This event is also being reported under § 50.73(a)(2)(i)(B) as an operation which was prohibited by the plant's Technical Specifications.
The investigation is ongoing, the failure mode and exact flowrate of the leak have not yet been determined.
Also, the leak rate is not known to have increased between 6/28/06 and 8/17/06. However, it is conservatively assumed that the 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative engine operation caused the pre-existing minor leak to increase in size. Therefore, a decision has been made to declare the EDG inoperable from 6/28/06 until 8/17/06.
The following B Train safety equipment was also inoperable between 6/28/06 at 16:48 and 8/18/06 @ 05:53:
Equip Inoperable Operable Duration (hrs)
Total (hrs)
EDG B 6/29/06 @ 9:27 6/30/06 @ 00:56 15.48 EDG B 7/27/06 @ 7:00 7/27/06 @ 15:49 8.82 29.97 EDG B 8/13/06 @ 8:54 8/13/06 @ 14:34 5.67 SW [BI] Train B 7/23/06 @ 12:30 7/23/06 @ 22:00 9.50 SW Train B 7/26/06 @ 13:27 7/27/06 @ 4:35 15.13 30.10 SW Train B 8/9/06 @ 7:46 8/9/06 @ 11:49 4.05 SW Train B 8/13/06 @ 8:55 8/13/06 @ 10:20 1.42U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
KEAR SEQUENTIAL I REVISION Kewaunee Power Station 05000305 Y
NUMBER I NUMBER 3 of 4 2006 009 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
Equip Inoperable Operable Duration (hrs)
Total (hrs)
RHR [BP] Pmp B 7/13/06 @ 8:43 7/14/06 @ 12:41 27.97 RHR Pump B 7/12/06 @ 15:51 7/12/06 @ 16:33 0.70 RHR Pump B 7/27/06 @ 13:35 7/27/06 @ 16:31 2.93 32.52 RHR Train B 7/12/06 @ 14:54 7/12/06 @ 15:25 0.52 RHR Train B 8/13/06 @ 13:12 8/13/06 @ 13:36 0.4 ICS [BE] Pump B 7/12/06 @ 14:46 7/12/06 @ 15:37 0.85 0.85 SI [BQ] Pump B 7/14/06 @ 1:03 7/14/06 @ 1:19 0.27 1.67 SI Train B 8/10/06 @ 9:41 8/10/06 @ 11:05 1.4 Chg [CB] Pump B 7/11/06 @ 7:04 7/11/06 @ 15:58 8.9 19.3 Chg Pump B 8/8/06 @ 7:09 8/8/06 @ 17:35 10.4 CC [CC] Pump B 7/02/06 @ 10:15 7/02/06 @ 10:30 0.25 CC Pump B 7/28/06 @ 23:40 7/28/06 @ 23:45 0.08 CC Train B 7/30/06 @ 21:39 7/30/06 @ 23:30 1.85 3.98 CC Train B 8/13/06 @ 12:04 8/13/06 @ 12:10 0.10 CC Train B 8/13/06 @ 10:21 8/13/06 @ 12:03 1.7 TDAFW [BA] Pmp 7/3/06 @ 8:58 7/3/06@ 9:07 0.15 TDAFW Pump 7/10/06 @ 9:18 7/10/06 @ 9:26 0.13 0.65 TDAFW Pump 8/3/06 @ 12:32 8/3/06 @ 12:45 0.22 TDAFW Pump 8/7/06 @ 10:24 8/7/06 @ 10:33 0.15 AFW [BA] Pmp B 7/10/06 @ 8:49 7/10/06 @ 8:56 0.12 AFW Train B 7/27/06 @ 10:15 7/27/06 @ 10:45 0.5 2.16 AFW Pump B 8/7/06 @ 10:00 8/7/06 @ 10:07 0.12 AFW Pump 8/13/06 @ 8:55 8/13/06 @ 10:20 1.42 Sfgds [JE] Train B 7/11/06 @ 9:18 7/11/06 @ 11:11 1.88 5.43 Sfgds Train B 8/8/06 @ 9:29 8/8/06 @ 13:02 3.55 With EDG A inoperable, the plant should have entered Tech Spec LCO 3.7.b.2, which states: "One diesel generator may be inoperable for a period not exceeding 7 days provided the other diesel is tested daily to ensure OPERABILITY and the engineered safety features associated with this diesel generator are OPERABLE." This event exceeded 7 days and EDG B was never tested for operability.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
NER EUMERTA NUMBERS4O o
Kewaunee Power Station 05000305 YEAR SEQUENTIAL REVISION 2006 009 00 TEXT (if more space is required, use additional copies of NRC Form 366A) (17)
Also, each of the 32 occasions above (involving concurrently inoperable Train B engineered safety features),
should have resulted in entry into Tech Spec LCO 3.0.c, which did not occur. Tech Spec LCO 3.0.c states:
When a LIMITING CONDITION FOR OPERATION is not met, and a plant shutdown is required except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
- 1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- 3. At least COLD SHUTDOWN within the subsequent 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SAFETY SIGNIFICANCE
During the entire time that EDG A was out of service, offsite power was available. Therefore, at all times power was available to both trains of safeguards equipment. Furthermore, over 97% of the time period, EDG B was available to provide backup power to train B equipment. Station blackout procedures were in place in the highly unlikely event that these sources failed. The safety significance of this event is under review and will be provided in a supplement to this LER.
CAUSE
The cause evaluation of this event is still in progress. The final cause determination will be provided in a supplemental report.
CORRECTIVE ACTIONS
Repaired the leak, performed an operability test, and restored the EDG to OPERABLE status. Any additional corrective actions will be provided in an LER supplement.
PREVIOUS SIMILAR EVENTS
LER 79-025, Non-isolatable leak was discovered on the lube oil sample line for one of the two diesel generator sets