05000498/LER-2010-003, Regarding Unit 1 Reactor Trip During Surveillance Testing
| ML102980012 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/19/2010 |
| From: | Peter L South Texas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NOC-AE-10002609 LER 10-003-00 | |
| Download: ML102980012 (8) | |
| 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)(iii) 10 CFR 50.73(a)(2)(ix)(A) 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4982010003R00 - NRC Website | |
text
Nuclear Operating Company South Texas Project lectnc Generating Station PO. Box289 M4dsworth, Texas 77483 A A October 19, 2010 NOC-AE-1 0002609 File No.: G25 10 CFR 50.73 STI: 32767069 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Unit 1 Docket No. STN 50-498 Licensee Event Report 1-2010-003:
Unit 1 Reactor Trip During Surveillance Testing Pursuant to 10 CFR 50.73, the STP Nuclear Operating Company (STPNOC) submits the attached Unit 1 Licensee Event Report (LER) 1-2010-003 to address the Unit 1 Reactor trip during the performance of a scheduled surveillance test of the Solid State Protection System (SSPS).
This condition is considered reportable under 1 OCFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic-actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of this section.
This event did not have an adverse effect on the health and safety of the public.
There are no commitments contained in this LER.
Corrective actiqns will be implemented in accordance with the STP Corrective Action Program.
If there are any questions on this submittal, please contact either J. A. Loya at (361) 972-8005 or me at (361) 972-7158.
L. W. Peter Plant General Manager JAL
Attachment:
LER 1-2010-003: Unit 1 Reactor Tripped During Surveillance Testing
<71
NOC-AE-1.0002609 Page 2 of 2 cc:
(paper copy)
(electronic copy)
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd, Suite 400 Arlington, Texas 76011-4125 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 8 G14) 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN1 16 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 John Ragan Catherine Callaway Jim von Suskil NRG South Texas LP Ed Alarcon Kevin Polio Richard Pena City Public Service Peter Nemeth Crain Caton & James, P.C.
C. Mele City of Austin Richard A. Ratliff Texas Department of State Health Services Alice Rogers Texas Department of State Health Services
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-01.04 EXPIRES: 08/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE South Texas Unit 1 05000498 1 OF 6
- 4. TITLE UNIT 1 REACTOR TRIP DURING SURVEILLANCE TESTING
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER SEQUENTIALEAR REVRMONTH DAY YEAR NA NUMBER NO.
N/A N/A FACILITY NAME DOCKET NUMBER 08 20 10 2010 - 003 -
0 10 19 2010 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[E 50.73(a)(2)(vii) 1 C] 20.2201(d)
El 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
[1 20.2203(a)(1)
[I 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
[E 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
[E 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
[E 73.71(a)(4)
[E 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5) 100%
E] 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
[E 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT August 20, 2010 at approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, a Unit 1 Reactor Operator (RO) functioning as a Test Coordinator (TC) commenced performing Surveillance Test OPSP03-SP-0006R, Train R Reactor Trip Breaker Trip Actuating Device Operability Test (TADOT), in the Unit 1 Solid State Protection System (SSPS) Train R cabinet. The Unit 2 Field Senior Reactor Operator (SRO) performed the supervisor oversight and dual verification in support of the test activities.
During the performance of procedure OPSP03-SP-0006R section 5.3, the TC and SRO completed steps 5.3.1 through 5.3.3 in the SSPS Train R cabinet. The TC then directed the Plant Operators (POs) to perform step 5.3.4 to ensure the Reactor Trip Bypass Breaker R closed. Once the POs reported that step 5.3.4 was completed, the TC then proceeded with steps 5.3.5, then appropriately marked steps 5.3.6 through 5.3.8 as Not Applicable (N/A); and then performed step 5.3.9. The TC then paged forward in the procedure and inadvertently turned two pages instead of one page. This resulted in the TC missing procedure step 5.3.10 that would have blocked the Turbine Trip actuation signal. The SRO did not notice the TC had missed a procedure page. The TC completed step 5.3.12 and the SRO performed the Dual Verification (DV) for the step. The SRO then took the test procedure book to the 10 foot elevation of the Electrical Auxiliary Building and observed Electricians take the continuity reading for the test.
After the Electricians performed their step in the procedure, the SRO returned to the SSPS Train R cabinet and gave the TC the procedure book. The TC then directed the POs to perform steps 5.3.14, 5.3.15, and 5.3.16 at the Reactor Trip Switchgear. While the POs were performing their steps, the TC and SRO discussed how they would perform step 5.3.17. With that discussion the TC and SRO agreed the prudent method to perform step 5.3.17 would be for the TC to manage the procedure book and the headset and the SRO would depress the test pushbuttons. Both the TC and SRO read the procedure step 5.3.17, after which the SRO depressed the test pushbuttons
(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)
V. PREVIOUS SIMILAR EVENTS
None.
VI. ADDITIONAL INFORMATION
None.