05000311/LER-2007-003, Regarding Reactor Trip Due to Spurious Feedwater Interlock Signal
| ML072890086 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/04/2007 |
| From: | Braun R Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N07-0257 LER 07-003-00 | |
| Download: ML072890086 (6) | |
| 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 |
| 3112007003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.
OCT 0 4 2007 10CFR50.73 LR-N07- 0257 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 LER 311/07-003 Salem Nuclear Generating Station Unit 2 Facility Operating License No. DPR-75 NRC Docket No. 50-311
SUBJECT:
Reactor Trip Due to Spurious Interlock This Licensee Event Report, "Reactor Trip Due to Spurious Interlock" is being submitted pursuant to the requirements of the Code of Federal Regulations 1 OCFR50.73(a)(2)(iv)(A).
The attached LER contains no commitments. Should you have any questions or comments regarding this submittal, please contact Mr. E. H. Villar at 856-339-5456.
Sincerely, Robert Braun Site Vice President - Salem Attachments (1)
OCT 0 4 2007 Document Control Desk Page 2 LR-N07- 0257 cc Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Salem Generating Station - Unit 2 05000311 1 OF 4
- 4. TITLE Reactor Trip Due to Spurious Feedwater Interlock Signal S. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONH AY YEA YAR SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MOT DY YER YER NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 08 06 2007 2007 003 00 10 05 2007
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[: 20.2201(b) 0l 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
E: 50.73(a)(2)(vii) 10 20.2201(d) 0l 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 0l 50.73(a)(2)(viii)(A)
El 20.2203(a)(1) 0l 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 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 [I 20.2203(a)(2)(ii)
C3 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)
Cl 50.73(a)(2)(x) 0l 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A) 0l 73.71(a)(4) r-20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[E 73.71(a)(5) 100%
CI 20.2203(a)(2)(v) 0l 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
E[ OTHER 0l 20.2203(a)(2)(vi)
[] 50:73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
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 NRC Form 366A)
CORRECTIVE ACTIONS
- 1. The safeguards output driver card A517 was replaced.
- 2. The Technical Specification required functional surveillance tests on SSPS Train "A" and "B" were satisfactory completed.
- 3. Additional corrective actions are being reviewed as part of the root cause evaluation and will be identified in a supplemental submittal of this event report.
COMMITMENTS
No commitments are made in this LER.