05000458/LER-2003-002, Secondary Containment Door Failure Due to Malfunction of Door Assist Device
| ML031320439 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/06/2003 |
| From: | King R Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| G9.25.1.3, G9.5, RBF1-03-0075, RBG-46119 LER 03-002-00 | |
| Download: ML031320439 (5) | |
| 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) |
| 4582003002R00 - NRC Website | |
text
-~- E nt ergy Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 P. 0. Box 220 St. Francisville, LA 70775 Tel 225 336 6225 Fax 225 635 5068 Rick J. King Director Nuclear Safety Assurance May 6, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
River Bend Station Docket No. 50-458 License No. NPF-47 Licensee Event Report 50-458 / 03-002-00 File Nos.
G9.5, G9.25.1.3 RBG-46119 RBF1 0075 Ladies and Gentlemen:
In accordance with 10CFR50.73, enclosed is the subject Licensee Event Report.
There are no commitments in this document.
Sincerely, RJK/dhw enclosure C-5g
Licensee Event Report 50-458 / 03-002-00 May 6, 2003 RBG-46119 Page 2 of 2 cc:
U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Sr. Resident Inspector P. O. Box 1050 St. Francisville, LA 70775 INPO Records Center E-Mail Mr. Jim Calloway Public Utility Commission of Texas 1701 N. Congress Ave.
Austin, TX 78711-3326 Mr. Prosanta Chowdhury Program Manager-Surveillance Division Louisiana DEQ Office of Radiological Emergency Planning and Response P. O. Box 82215 Baton Rouge, LA 70884-2215
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 (1-2001)
COMMISSION
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
River Bend Station 050- 458 1 OF 3
ITLE (4)
Secondary Containment Door Failure Due to Malfunction of Door Assist Device EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 03 07 2003 2003 002 00 05 06 2003 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RE2UIREMENTS OF 10 C R (Check all that apply) (11)
MODE (9) 1 20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 87%
20.2203(a)(1) 50.36(c)(1)(i)(A) 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)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER Specif infy Abstract below or in 20.2203(a)(2)(iii)
_ 50.46(a)(3)(ii)
X 50.73(a)(2)(v)(C)
NRC Formn366A 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 20.2203(a)(2)(v) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 20.2203(a)(2)(vi) 50.73(a)(2)i)(C) 50.73(a)(2)(viii)(A)
- f;
-¢
_ 2.2203(a)(3)(i)
_50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
XE LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
J.W. Leavines, Manager - Licensing 225-381-4642 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANT-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM CONPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX B
NF DR Overly Door Co.
YES I
l SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR__
X YES (IfIes, complete EXPECTED SUBMISSION DATE.
NOlSSIN X IlYES (If yes, complete EXPECTED SUBMISSION DATE).
I lNO l
DATE (15) l06 l30 2003 l
ABSTRACT (Limit to 1400 spaces. i.e.. aDDroximatelv 15 single-spaced tpewritten lines) 16)
On March 7, 2003, at approximately 2:31 p.m. CST, the door assist device (DAD) on a secondary containment door in the auxiliary building failed, blocking the door open for a period of 78 minutes. At the time, the reactor was operating at approximately 87 percent power in end-of-cycle coastdown. This event is being reported in accordance with 10CFR50.73(a)(2)(v)(c) as a condition that could have prevented the fulfillment of the safety function of secondary,containment. The failure analysis of the DAD is still in progress. A full analysis and corrective action plan will be provided in a supplement to this LER. There were no actual consequences to the health and safety of the public.
Engineering evaluations have shown that, had a design basis accident occurred while the condition existed, the main control room, exclusion area boundary, and low population zone doses would have remained within the limits of 10CFR50.67.
NRC FORM 366 (1-2001)
(If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY SIGNIFICANCE
During the time the door was blocked open, the plant continued to operate normally.
There were no actual consequences to the health and safety of the public. Engineering evaluations have shown that, had a design basis accident occurred while the condition existed, the main control room, exclusion area boundary, and low population zone doses would have remained within the limits of 10CFR50.67.
(NOTE: Energy Industry Component Identification codes are annotated as (**XX**).)