05000220/LER-2005-001, Regarding Automatic Reactor Scram Due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch
| ML051370403 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/06/2005 |
| From: | O'Connor T Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP1L 1948 LER 05-001-00 | |
| Download: ML051370403 (5) | |
| 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)(vii)(B), Common Cause Inoperability 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2202005001R00 - NRC Website | |
text
Constellation Energy-Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 May 6,2005 NMP1L 1948 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Nine Mile Point Unit 1 Docket No. 50-220 Facility Operating License No. DPR-63 Licensee Event Report 05-001, "Automatic Reactor Scram due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch" I
Gentlemen:
In accordance with 10 CFR 50.73(a)(2)(iv)(A), we are submitting Licensee Event Report 05-001, "Automatic Reactor Scram due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch."
Very truly y ime J. O'Connor Pla eneral Manager TJO/KSE/sc Attachment cc:
Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident ITspector
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person Is not required to respond to, the digits/characters_______for___each
__block)_____
rIformation collection.
- 3. PAGE Nine Mile Point, Unit 1 05000220 1 OF 4
- 4. TITLE Automatic Reactor Scram due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE B. OTHER FACILmES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 03 07 2005 2005 -
001 -
00 05 06 2005
- 9. OPERATING MODE 11.THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OFlO CFR§: (Check all that apply) o 20.2201(b) a 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii) 1 0
20.2201(d)
D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(vii)(B) o 202203(a)(2)(i) 0 50.36(c)(1)(Q(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A)
ID 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
O 20.2203(a)(2)(iii)
D 50.36(c)(2) 0I 50.73(a)(2)(v)(A) 0 73.71 (a)(4) 10o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 10 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER 0
20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 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)
V. Additional Information
A. Failed Components:
Junction Box, Terminal Strip B.
Previous Similar Events
A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Nine Mile Point Nuclear Station Unit 1 could be identified.
C. Identification of systems and components referred to in this Licensee Event Report:
Components IEEE 805 System ID IEEE 803A Function Main/Reheat Steam System SB N/A Reactor Recirculation System AD N/A High Pressure Coolant Injection System BJ N/A Electromatic Relief Valves SB PSV Control Rods AA ROD Reactor Protection System JC N/A Turbine Bypass Valves SB PCV Emergency Diesel Generators EK DG Level Switch SB LS Junction Box SB JBX Terminal Strip SB EB Pump SJ, AD P
Moisture Separator Tank SB TK Motor Generator Set AD MG Main Condenser SG COND