05000443/LER-2006-005, Regarding Technical Specification Violation with Inoperable Main Steam Isolation Valve
| ML062150350 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/27/2006 |
| From: | St.Pierre G Florida Power & Light Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-06161 LER 06-005-00 | |
| Download: ML062150350 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 |
| 4432006005R00 - NRC Website | |
text
FPL Energy Seabrook Station FPL Energy Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 JUL 2 7 2006 Docket No. 50-443 SBK-L-06161 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 2006-005-00 Technical Specification Violation with Inoperable Main Steam Isolation Valve Enclosed is Licensee Event Report (LER) 2006-005-00. This LER reports an event that occurred at Seabrook Station on July 3, 2006. This event is being reported pursuant to the requirements of I OCFR50.73(a)(2)(i)(B) and Facility Operating License Condition 2.G.
Should you require further information regarding this matter, please contact Mr. James M.
Peschel, Regulatory Programs Manager, at (603) 773-7194.
Very truly yours, FPL Energy Seabrook, LLC Gene St. Pierre Site Vice President cc:
S. J. Collins, NRC Region I Administrator G. E. Miller, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector an FPL Group company
ENCLOSURE TO SBK-L-06161
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may sfor each block)nnot conduct or sponsor, and a person is not required to respond to, the digits/characters fo ahbok Information collection.
- 3. PAGE Seabrook Station 0500044 1 OF 3
- 4. TITLE Technical Specification Violation with Inoperable Main Steam Isolation Valve
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO.
v105 0
FACILITY NAME DOCKET NUMBER 07 03 2006 2006 - 005 -
00 07 27 2006 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[o 20.2201(b)
[I 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii) 1 0 20.2201(d) 0J 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
[o 20.2203(a)(1)
El 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
[] 50.73(a)(2)(viii)(B)
[o 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A)
[] 50.73(a)(2)(iii)
[l 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A)
E] 50.73(a)(2)(iv)(A)
[] 50.73(a)(2)(x)
[o 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)
[1 73.71 (a)(5) 100 C1 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A) 0l 50.73(a)(2)(v)(C)
E0 OTHER [o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
[I 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 NRC Form 366A) (17)
This was a random failure of a printed circuit board in the Train A MSIV logic cabinet. Review of the failure history of MSIV logic failures indicates relatively few failures of MSIV logic boards. There are no systematic failures occurring with these boards. Based on the random nature of this failure there is no transportability to other printed circuit boards in the MSIV logic cabinets.
The event had no adverse impact on the plant or on the health and safety of the public or plant personnel. No plant transients, systems actuations, or consequences resulted from the event. No other inoperable structures, systems, or components contributed to this event.
This event is of regulatory significance because it met the reporting criterion of 1 OCFR50.73(a)(2)(i)(B) for a condition prohibited by the TS. The event was reported to the NRC on July 3, 2006 at 1623 (event #42684) in accordance with the Seabrook Station operating license condition 2.G for a violation of the TS.
IV. Corrective Action
The failed MSIV valve control module printed circuit board was replaced.
V. Similar Events
This is the first confirmed valve control module failure at Seabrook Station.
VI. Manufacturer Data The valve control module was originally manufactured by Consolidated Control PIN 6N372-1.