05000498/LER-2006-005, Re Quadrant Power Tilt Ratio Surveillance Not Performed as Required by TS 3.3.1 Action 2
| ML070160218 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/28/2006 |
| From: | Halpin E South Texas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NOC-AE-06002097 LER 06-005-00 | |
| Download: ML070160218 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 |
| 4982006005R00 - NRC Website | |
text
Nuclear Operating Company South Texas Project Electric Gencratin, Station PO. Box 289 Wadsworth. Teas 77483
/
December 28, 2006 NOC-AE-06002097 1 OCFR50.73 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Unit I Docket No. STN 50-498 Licensee Event Report 2006-005, Quadrant Power Tilt Ratio Surveillance Not Performed As Required By TS 3.3.1 Action 2 Pursuant to 10 CFR 50.73(a)(2)(i)(B), STP Nuclear Operating Company submits the attached Unit 1 Licensee Event Report 2006-005 regarding the failure to perform TS 3.3.1 Action 2 requirements associated with an inoperable Power Range Excore Nuclear Instrumentation channel.
This event did not have an adverse effect on the health and safety of the public.
There are no commitments contained in this event report. Resulting corrective actions will be implemented in accordance with the Corrective Action Program.
If there are any questions regarding this submittal, please contact S. M. Head at (361) 972-7136 or me at (361) 972-7849.
/
Edward D. Halpin Site Vice President &
Plant General Manager jrm/
Attachment: South Texas Unit I LER 2006-005 STI: 32102936
NOC-AE-06002097 Page 2 of 2 cc:
(paper copy)
(electronic copy)
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Steve Winn Christine Jacobs Eddy Daniels Marty Ryan Harry Holloway NRG South Texas LP J. J. Nesrsta R. K. Temple Kevin Pollo E. Alarcon City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.
- 3. PAGE South Texas, Unit 1 05000498 1 OF 5
- 4. TITLE TS 3.3.1 Action 2 requirements not performed.
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED S
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NUMBER NO.
50 FACILITY NAME DOCKET NUMBER 11 06 2006 2006 - 005 -
00 12 28 2006 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
[I 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
[] 20.2201(d)
[1 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[E 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 078 [E 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[] 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES On November 5, 2006 at 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br />, Unit 1 was operating at approximately 63% power in power ascension operations following refueling outage 1 RE1 3. At this time, the Loop 3 Overtemperature / Delta Temperature (OT/AT) channel spiked high. In response to this spike, the Loop 3 temperature channel was declared inoperable, placed in bypass mode, and corrective maintenance activities were initiated.
On November 6, 2006 at 0126 hours0.00146 days <br />0.035 hours <br />2.083333e-4 weeks <br />4.7943e-5 months <br />, with Unit 1 at approximately 78% power, Power Range Excore Nuclear Instrumentation channel NI-43 was declared inoperable to perform axial flux difference (AFD) calibrations. Power Range NI-43 provides the nuclear power input into the Loop 3 OT/AT Reactor Trip circuitry.
At approximately 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, Instrumentation & Control (I&C) Technicians working on the Loop 3 temperature channel encountered a problem with a tester card which would extend this work for another ten to twelve hours. Shortly afterward, I&C Technicians working on NI-43 notified the Control Room that the NI-43 AFD calibration was complete. However, NI-43 could not be returned to service because bistables associated with Loop 3 OT/AT were in bypass, leaving NI-43 inoperable.
(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)
VI.
PREVIOUS SIMILAR EVENTS
There have been two Licensee Event Reports in the past three years regarding missed TS actions.
" Unit 1 LER 2004-005: Engineered Safety Features (ESF) Diesel Generator 12 was not declared Inoperable and verification of ESF power availability was not performed as required by TS 3.8.1.1. Auxiliary Feedwater (AFW) Pump 12 was inoperable for cell switch replacement. A non-functional cell switch on an ESF 4160V load disables the diesel output breaker from auto closing when started in an emergency mode.
The root cause of this event was inadequate communication among SROs responsible for the configuration management and work implementation processes of this "out-of-the-ordinary" condition where AFW Pump breaker maintenance affects DG operability.
Unit 2 LER 2005-005: Unit 2 was in Mode 6 with irradiated fuel being moved in the Unit 2 Fuel Handling Building (FHB). Direct Current (DC) Switchboard E2C1 1 was de-energized without placing the FHB Heating, Ventilation, and Air Conditioning (HVAC) in the Emergency Recirculation mode as required by Technical Specification 3.3.2 Action 30. The FHB HVAC actuation relays are located in Relay Rack (RR) 145C and powered from 125V DC Panel 039C; which is in turn is powered from Switchboard E2C1 1. These relays require DC power to automatically place the FHB HVAC in the Emergency mode and would not have actuated with Switchboard E2C1 1 deenergized.
The root cause of this event was the over-reliance on individuals to plan and schedule electrical bus outages and the failure to develop and implement procedures to provide guidance for these evolutions.
VII.
ADDITIONAL INFORMATION
Operations Management will review this and previous events at STP to identify and implement process improvements concerning the tracking of Technical Specification Action Statements in effect.