05000445/LER-2003-002, Regarding Actuation of Reactor Protection System
| ML031400205 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/09/2003 |
| From: | Madden F TXU Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200300780, TXX-03066 LER 03-002-00 | |
| Download: ML031400205 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(ix)(A) 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 |
| 4452003002R00 - NRC Website | |
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hx TXu
",1o TXU Energy Comanche Peak Steam Electric Station RO. Box 1002 (E01)
Glen Rose,TX 76043 Tel: 254 897 8920 Fax: 254 897 6652 lance.terry@txu.com C. Lance Terry Senior Vice President &
Principal Nuclear Officer Ref: 10 CFR50.73(a)(2)(iv)(A)
CPSES-200300780 Log # TXX-03066 May 9, 2003 U. S. Nuclear Regulatory Commission AT'TN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 ACTUATION OF REACTOR PROTECTION SYSTEM LICENSEE EVENT REPORT 445/03-002-00 Enclosed is Licensee Event Report (LER) 03-002-00 for Comanche Peak Steam Electric Station Unit 1, "Reactor Trip due to Loss of Main Feedwater".
This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
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TXU TXX-03066 Page 2 of 2 Sincerely, TXU Generation Company LP By:
TXU Generation Management Company LLC, Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By:
,m Fred W. Madden Nuclear Licensing Manager GLM/gm Enclosures c -
E. W. Merschoff, Region IV W. D. Johnson, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES
Encl.osure to TXX-03066; NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (7-2001)
EXPIRES 07t3112004 the NRC nay not conduct or sponsor. and a person is not required to respond to. the nforrmtion collection.
Factity Nare ()
Docket Number (2)
Page (3)
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 05000445 1 OF 5 Ttle (4)
ACTUATION OF REACTOR PROTECTION SYSTEM Event Date (51 LER Number (6)
Report Dae (7)
Other Facilities Involved (8)
Month Day Year Year frf Sequential Revision Month Day Year Facilty Narre Docket Numbers Number Number 05000 03 16 2003 03 _
002 _
00 05 09 2003 05000 Operatin Tis report is submitted pursuant to terequirmns o0 CR(hekal tht ppy)It Mode (9) 1 1
l 20.2201(b) 20.2203(a)(3)(i) l 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
Power 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A)
Level 100
~~20.2203(a)(l) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
=. } 7, -.. r aK -20.2203(a)(2)(i) 50.36(c)(2)(i)(A) 50.73(aX(2)(iii) 50.73(a)(2)(ix)(A) s 1
20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A)
X 50.73(a)(2)(iv)(A) 50.72(a)(2)(x)
- - 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4)
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5 X
20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES On March 16, 2003, CPSES Unit 1 was in Mode 1, Power Operation, operating at 100 percent power. At 2149 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.176945e-4 months <br />, Condensate pump 1-01 motor breaker [EHS: (SD)(P)(MO)(BRK)] unexpectedly tripped and Operators (utility, licensed) in the Unit 1 Control Room received a "Condensate Pump 1 Breaker Open" alarm [EIIS: (SD)(P)(BKR)(ALM)]. Eleven seconds later, Main Feedwater pump 1-02 [EIIS: (SJ)(P)] tripped on low suction pressure and one second later Main Feedwater Pump 1-01 [EIIS: (SJ)(P)] also tripped on low suction pressure. The loss of both Main Feedwater pumps resulted in the automatic start as expected of both Motor Driven Auxiliary Feedwater pumps [EIIS: (BA)(P)]. Operators (utility, licensed) in the Unit 1 Control Room initiated a manual reactor trip based upon the loss of the Main Feedwater pumps and the rapidly decreasing feedwater levels in all four Steam Generators.
The Turbine Driven Auxiliary Feedwater pump [EIIS: (BA)(P)] also automatically started as expected based on Lo-Lo level in 2 of 4 Steam Generators [EIIS: (SB)(SG)]. All control rods fully inserted and the plant response to the manual trip was as expected.
NRC FOR.M 366A (1-2001)
Endlosure to TXX-03066 (It mre space is required, use addaional copes of (If nire space is required, use addiuonal copies of (If more space is required, use additional copiesofNRC Form366A) (17)
IV.
CAUSE OF THE EVENT
The Unit 1 manual reactor trip resulted from the unexpected trip of Condensate pump motor 1-01 and subsequent loss of both Main Feedwater pumps. The trip of Condensate pump motor 1-01 was caused by a phase to phase fault within the motor windings which occurred due to a manufacturing defect. The manufacturing defect was the lack of a clearance or air gap between the two winding coils.
V.
CORRECTIVE ACTIONS
Condensate pump motor 1-01 was repaired, reinstalled, and returned to service. As a part of the CPSES Corrective Action Program, the condition of the winding coils on the other three Condensate pump motors will be evaluated. In addition, an evaluation of the Predictive Analysis Program, specifically for large electric motors, will be performed to determine the adequacy of the current program scope, monitoring practices, and overall effectiveness.
VI.
PREVIOUS SIMILAR EVENTS
In 1995, CPSES Unit 1 experienced a manual reactor trip due to the loss of both Condensate pumps and both Main Feedwater pumps (see LER 445/95-003). However, the loss of both Condensate pumps in the 1995 event was due to a different cause than the March 16, 2003 event.
NRRC FORb1 366A (1i-200i)