05000461/LER-2008-001, Regarding Automatic Scram on High RPV Water Level Due to Reactor Pump Trip
| ML081080103 | |
| Person / Time | |
|---|---|
| Site: | Clinton  (NPF-062) |
| Issue date: | 04/09/2008 |
| From: | Kearney F AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SRRS 5A.108, U-603852 LER 08-001-00 | |
| Download: ML081080103 (4) | |
| 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 |
| 4612008001R00 - NRC Website | |
text
AmerO SM An Exelon Company Clinton Power Station R. R. 3, Box 228 Clinton, IL 61727 10 CFR 50.73 SRRS 5A.108 U-603852 April 9, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Licensee Event Report 2008-001-00 Enclosed is Licensee Event Report (LER) No. 2008-001-00: Automatic Scram on High RPV Water Level Due to Reactor Recirc Pump Trip. This report is being submitted in accordance with the requirements of 10 CFR 50.73. A supplement will be issued to this report following completion of the root cause investigation for this event. The supplemental report is expected to be issued by May 2, 2008.
This document has no regulatory commitments.
Should you have any questions concerning this report, please contact Mr. T. D. Chalmers, Shift Operations Superintendent, at (217)-937-2203.
Respectfull A.KearteY, Site Vice President Clinton Power Station RSF/blf
Enclosures:
Licensee Event Report 2008-001 -00 cc:
Regional Administrator-NRC Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - IEMA Division of Nuclear Safety
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 I6-2004)
(Estimated
, the NRC may not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) ifirito lp~in
- 3. PAGE Clinton Power Station 05000461 1 OF 3 C. TITLE Automatic Scram on High RPV Water Level Due to Reactor Recirc Pump Trip
- 5. EVENT DATE
- 6. LER NUMBER _
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR Y EAR SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER YEAR NUMBER NO.
MONTH DAY YEAR None 05000 IFACILITY NAME DOCKET NUMBER 02 10 2008 2008 - 001 -
00 04 09 2008 JNone 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[E 50.73(a)(2)(vii)
[1 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
[1 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 E] 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)
El 20.2203(a)(2)(iii)
[I 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 95 [1 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[I 50.73(a)(2)(v)(C)
El OTHER (10 CFR 21)
El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of NRC Form 366A) (17)
Initial troubleshooting determined that excessive leakage current through a high level optical isolator card [OB] caused actuation of the non-safety portion of the Division 3 End of Cycle - Reactor Recirculation Pump Trip (EOC-RPT) trip circuit, resulting in a trip of the 'B' Reactor Recirculation Pump.
No other inoperable equipment or components directly affected this event.
This event is reportable under the provisions of 10 CFR 50.73(a)(2)(iv)(A).
This event report does not identify any safety system functional failures.
The root cause evaluation and corrective actions for this event are tracked under Issue Report 734254. A supplemental report will be submitted identifying the cause, the safety analysis, the corrective action, any previous occurrences, and any component failure data for this event.