05000368/LER-2002-002, Actuation of Reactor Protection System
| ML030430261 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/10/2003 |
| From: | Cotton S Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN020301 LER 02-002-00 | |
| Download: ML030430261 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3682002002R00 - NRC Website | |
text
2CAN020301 PAGE 2 cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents@inpo.org
NRC FORM 366 (1-2001)
NRC FORM 366 U.S. NUCLEAR REGULATORY (1-2001) COMMISSION LICENSEE EVENT REPORT (LER)
APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 Estimated burden per response to comply with this mandatory information collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, DC 20503.
FACILITY NAME (1)
Arkansas Nuclear One - Unit 2 DOCKET NUMBER (2) 05000368 PAGE (3) 1 OF 3 TITLE (4) Automatic Actuation of the Reactor Protection System Caused by a Main Turbine Trip due to Failure of the Main Generator Reverse Power Relay Resulted in a Reactor Trip EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR SEQUENTIAL NUMBER REV NO MO DAY YEAR FACILITY NAME DOCKET NUMBER 12 19 2002 2002 002 00 02 10 2003 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: (Check one or more) (11)
MODE (9) 1 20.2201(b) 20.2203(a)(3)(i) 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 (10) 100 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A)
50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 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 or (17)
(17) The relay was replaced. The replacement relay was monitored during the subsequent plant startup and performed satisfactorily.
The failed relay is being evaluated by the manufacturer to determine if additional information regarding the root cause of the failure can be obtained.
Based on the industry experience review, applicable procedures will be enhanced by a revision to add specific steps to check for clutch tightness during routine relay tests and calibrations.
E.
Safety Significance
The RPS actuated as expected to cause a reactor trip when the Main Turbine tripped. All CEAs fully inserted. There was no ECCS actuation or radioactive release during this event. The electrical grid remained stable and all Emergency Diesel Generators [EK] were operable. The plant was stabilized in hot standby conditions without complications. Therefore, this condition had minimal actual safety significance.
F.
Basis for Reportability Automatic actuation of the RPS is being reported in accordance with 10CFR50.73(a)(2)(iv)(A). A notification of this event was made to the NRC Operations Center in accordance with 10CFR50.72(b)(2)(iv)(B) at 0443 CST on December 19, 2002.
G.
Additional Information
There have been no previous similar events reported by ANO as Licensee Event Reports.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].