05000305/LER-2006-008, Diesel Generator Operability Testing Interval Exceeded
| ML062620258 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 09/11/2006 |
| From: | Hartz L Dominion, Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-779 LER 06-008-00 | |
| Download: ML062620258 (5) | |
| Event date: | |
|---|---|
| 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) |
| 3052006008R00 - NRC Website | |
text
- Dominion Dominion Energy Kewaunee, Inc.
N490 Highway 42, Kewaunee, WI 54216-9511 SEP 11 2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.06-779 KPS/LIC/RS: RO Docket No.
50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE. INC.
KEWAUNEE POWER STATION LICENSEE EVENT REPORT 2006-008-00
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. 50-305/2006-008-00 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. Ha Site Vice President, Kewaunee Power Station Attachment Commitments made by this letter: NONE
Serial No.06-779 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 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
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 byinternet 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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If a means used to Impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person Is not required to respond to, the Information collection.
FACILITY NAME (1)
KET NUMBER (2)
Kewaunee Power Station 05 1
(3)
TITLE (4)
Diesel Generator operability testing Interval exceeded EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
SEQUENT REV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER I NO MO DAY YEAR 07 26 2006 2006
-- 008 -
00 09 11 2006 FACILITY NAME DOCKETNUMBER OPERATING N
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)(11) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201 (d) 120.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 100 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) 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) 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)(vl)
_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 Repshas 1
(920) 388-8217 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
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I S U B M I S S I O N YES (If yes, complete EXPECTED SUBMISSION DATE).
X NO DATE (15)1_N ABSTRACT On July 26, 2006, while operating at 100% power, it was discovered that an LCO-required daily test of an emergency diesel generator (EDG) was not performed within the prescribed time period.
Technical Specification 3.7.b.2 states "One diesel generator may be inoperable for a period not exceeding 7 days provided the other diesel generator is tested daily to ensure OPERABILITY and the engineered safety features associated with this diesel generator are OPERABLE."
EDG B was inoperable as of 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> on July 25 due to train B of service water (SW) having been declared inoperable. The daily surveillance test for EDG A was required to be performed by 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> on July 26. At approximately 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on July 26, the operating crew discovered the daily test of EDG A had not been performed. A satisfactory test of EDG A was completed at 1929 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.339845e-4 months <br /> on July 26.
The preliminary cause determination found inadequate communication and incomplete turnover among the operating crews.
This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications." There is no safety system functional failure for this event.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Kewaunee Power Station 05000305 SEQUENTIAL REVISION 2 of 3 1
1 2006 008 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
Event Description
On July 26, 2006, while operating at 100% power, it was discovered that an LCO-required daily test of an EDG [DG] was not performed within the prescribed time period.
Technical Specification 3.7.b.2 states "One diesel generator may be inoperable for a period not exceeding 7 days provided the other diesel generator is tested daily to ensure OPERABILITY and the engineered safety features associated with this diesel generator are OPERABLE."
EDG B was inoperable as of 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> on July 25 due to SW [BI] train B having been declared inoperable.
The daily surveillance test for the operable EDG A was required to be performed by 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> on July 26. At approximately 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on July 26, the operating crew discovered the daily test of EDG A had not been performed. A satisfactory test of EDG A was completed at 1929 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.339845e-4 months <br /> on July 26.
Event Analysis
This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications."
When one train of SW is inoperable, components supported by that train are inoperable, which includes the associated diesel generator. Technical Specification 3.7.b.2 states "One diesel generator may be inoperable for a period not exceeding 7 days provided the other diesel generator is tested daily to ensure OPERABILITY and the engineered safety features associated with this diesel generator are OPERABLE."
With SW train B declared inoperable, EDG A was required to be tested daily which is defined as "at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" per the Technical Specifications. Since testing was required by 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> and was not completed until 1929 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.339845e-4 months <br />, the daily testing requirement was exceeded by 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 48 minutes. Since this was an LCO-required test, there is no grace period and the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> exclusion of TS 4.0.c does not apply.
EDG A met all surveillance requirements. Since it was a short period beyond the daily testing requirement and EDG A was proven OPERABLE, there is no safety significance associated with this event.
Because there were no events or conditions that could have prevented the fulfillment of the safety function of systems (opposite train equipment was operable), there is no safety system functional failure.
Cause
The preliminary cause determination found inadequate communication and incomplete turnover among the operating crews. Any additional causes will be as determined by the Corrective Action Program.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2 LER NUMBER (6)
PAGE (3)
K e e5 YA SEQUENTIAL REVISION e n NUMBER NUMBER 3 of 3 K P 2006 008 00 TEXT (1f more space is required, use additional copies of NRC Form 366A) (17)
Corrective Actions
- 1.
An annotation has been made in the electronic equipment clearance system for the SW pump control switches to alert operators of the EDG testing requirements.
- 2.
Expectations have been communicated to the shift that when logging a SW train inoperable to include in the log entry that daily EDG testing is required.
Any additional corrective actions will be as determined by the Corrective Action Program.
Similar Events
None.