05000413/LER-2003-005, Regarding Reactor Trip Due to Pressurizer Pressure Channel Failure
| ML033090406 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/21/2003 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 03-005-00 | |
| Download: ML033090406 (9) | |
| 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) 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 |
| 4132003005R00 - NRC Website | |
text
or M;Duke cfPower A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax October 21, 2003 U. S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Corporation Catawba Nuclear Station Unit 1 Docket No. 50-413 Licensee Event Report 413/03-005 Revision 0 Reactor Trip due to Pressurizer Pressure Channel Failure Attached please find Licensee Event Report 413/03-005 Revision 0, entitled "Reactor Trip due to Pressurizer Pressure Channel Failure."
This Licensee Event Report does not contain any regulatory
commitments
Questions regarding this Licensee Event Report should be directed to G. K Strickland at (803) 831-3858.
Sincerely, D. M. Jamil Attachment a 9 -';
L www. duke-energy. corn
U.S. Nuclear Regulatory Commission October 21, 2003 Page 2 xc:
L. A. Reyes U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 R. E. Martin (addressee only)
NRC Senior Project Manager (MNS/CNS)
U. S. Nuclear Regulatory Commission Mail Stop 08-G9 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission Catawba Nuclear Site INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957
NfC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7-2001)
COMMISSION
th m
n duct or sponsor, and a person is not required to respond to the
- 3. PAGE Catawba Nuclear Station, Unit 1 05000 413.
1 OF 7
- 4. TITLE Reactor Trip due to Pressurizer Pressure Channel Failure
- 5.
EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER SEOUENTIAL REV MO DAY YEAR YEAR NUMBER NO MO DAY YEAR None FACILITY NAME DOCKET NUMBER 08 29 2003 2003 -
005 -
00 10 21 2003
- 9. OPERATING
=
1.THIS REPORT IS SUBMITTEDPURSUANTTOTHE REQUIREMENTS OF 10 CFR §: (heck all that apply)
MODE 1
=
20.2201 (b)
I 20.2203(a)(3)(ii)
=
50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
- 10. POWER 20.2201 (d)
_ 20.2203(a)(4)
_ 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL 95%
= 20.2203(a)(1) 50.36(c)(1)(i)(A)
X 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)(vA)B 20.2203(a)(2)(ii)
__ 50.36(c)(2)
__ 50.73(a)(2)(v)(B)
Specify in Abstract below e,
20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) or In
Abstract
On August 29, 2003 at 0203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br /> with Catawba Unit 1 operating in Mode 1 at 95% power, an automatic reactor trip occurred due to an instrument failure. The reactor trip was caused by the pressurizer pressure channel 2 failing low resulting in the reduction of the loop 1B overtemperature delta T (OTdT) setpoint to approximately 50%. When the OTdT setpoint reached the operating value of the loop B conditions (approximately 95%), an automatic reactor trip was initiated on 2/4 OTdT trip bistables. The loop 1A OTdT trip bistable was previously tripped due to a reactor coolant system hot leg temperature detector failure.
This event was caused by the equipment failure of the pressurizer pressure loop power supply card. The plant response to the reactor trip remained within the limits of the Updated Final Safety Analysis Report.
Corrective actions for this event included repairs to the pressurizer pressure channel and reactor coolant system hot leg temperature detectors.
NRC FORM 366 (7-2001)
(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 (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)
ADDITIONAL INFORMATION
Within the last three years, three other reactor trip events occurred from power operation at Catawba as follows:
LER 413/01-001 described a Unit 1 reactor trip caused by a turbine trip. The root cause of this event was determined to be an incomplete troubleshooting analysis associated with the main turbine protection system mechanical trip solenoid valve.
LER 414/01-003 described a Unit 2 reactor trip resulting from low reactor coolant flow when the 2D reactor coolant pump 6900 VAC feeder breaker opened in response to protective relay actuation caused by an electrical fault internal to the pump motor.
LER 413/03-001 described a Unit 1 reactor trip resulting from a turbine trip. The turbine trip was due to a steam generator high level. The root cause of this event was determined to be an inadequate understanding of the digital feedwater control system response to a common impulse line hydraulic interaction.
The corrective actions taken in response to these events would not have prevented this latest event from occurring. Therefore, this event was determined to be non-recurring in nature.
Energy Industry Identification System (EIIS) codes are identified in the text as [EIIS: XXI. This event is reportable to the Equipment Performance and Information Exchange (EPIX) program.
This event did not involve a Safety System Functional Failure.
There were no releases of radioactive materials, radiation exposure, or personnel injuries associated with this event.