05000261/LER-2003-002, Regarding Failure of Automatic Containment Ventilation Isolation During Containment Pressure Relief
| ML032130431 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/31/2003 |
| From: | Cleary T Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/03-0098 LER 03-002-00 | |
| Download: ML032130431 (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)(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 |
| 2612003002R00 - NRC Website | |
text
10 CFR 50.73 q bb Progress Energy Serial: RNP-RA/03-0098 JUL 31 2003 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2003-002-00 FAILURE OF AUTOMATIC CONTAINMENT VENTILATION ISOLATION DURING CONTAINMENT PRESSURE RELIEF Ladies and Gentlemen:
The attached Licensee Event Report is submitted in accordance with the requirements of 10 CFR 50.73. Should you have any questions regarding this matter, please contact Mr. C. T. Baucom.
Sincerely, 3Cre3 Plant General Manager CAC/cac Attachment c:
Mr. L. A. Reyes, NRC, Region II Mr. C. P. Patel, NRC, NRR NRC Resident Inspector, HBRSEP Progress Energy Carolinas, Inc.
Hobinson Nuclear Plant 3581 West Entrance Road HartswIle SC 29550
NRC FORM 366 U.S. NUCLEAR REGULATORY (7-2001)
COMMISSION LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004
, 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)
H. B. Robinson Steam Electric Plant, Unit No. 2 05000261 1
OF 8
TITLE (4)
Failure of Automatic Containment Ventilation Isolation During Containment Pressure Relief EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SEQUENTIAL NUMBER REV NO MO DAY YEAR FACILITY NAME DOCKET NUMBER 06 05 2003 2003 B 002 B 00 07 31 2003 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR : (Check all that apply) (11)
OPERATING MODE (9) 1 20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A) 20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
POWER LEVEL (10) 100%
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) 20.2203(a)(2)(iii) 50.46(a)(3)(ii)
X 50.73(a)(2)(v)(C) 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A)
X 50.73(a)(2)(v)(D)
OTHER Specify in Abstract below or in (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) control switches in each circuit, and that failure of individual component control switches alone will not cause a failure to fulfill a safety function.
This is a planned action with a scheduled completion date of October 25, 2003.
It will be confirmed that functional testing verifies operability of the isolation function or procedural guidance will be established that verifies operability of the isolation function when a source is applied to containment radiation monitors R-11 and R-12. This is a planned action with a scheduled completion date of October 25, 2003.
A permanent modification on the containment vacuum and pressure relief control circuits will be installed to restore the design such that the control switch is wired in series with the Train A and Train B containment isolation relay contacts. This is a planned action with a scheduled completion during the next refueling outage, currently planned for April and May of 2004.
V.
ADDITIONAL INFORMATION
A. Failed Component Information
The failed switch is a GEMCO Switch Model No. 404S-3-2-1-2-2-Y-EE2. The cause of the switch failure has been determined to be age-related degradation and cyclic fatigue.
B. Previous Similar Events
A review of recent (past 3 years) events at HBRSEP, Unit No. 2, for conditions that could have prevented the fulfillment of a safety function was conducted.
There were no events found.