LER-2004-001, E-mail from Ronda Daflucas, Entergy, to Rick Ennis, NRC, FW: LER 2004-001-00 Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2712004001R00 - NRC Website |
|
text
Rick Ennis-FW: LER 2004-001-00"Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Ratedg1 l From:
NDaflucas, Rondau <rdafluc@entergy.com>
To:
ORick Ennism <RXE~nrc.gov>
Date:
5/27/04 9:43AM
Subject:
FW: LER 2004-001-00 "Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit
- Rick, Attached is VY's LER, fyi.
Ronda Daflucas 802-258-4232
<<LER 2004-001-OO.pdf>>
M L, '0q)_S-o3S-3 f -" R C tt MI( f,-l I b 5 3
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000249/LER-2004-001, Hearing - Entergy Exhibit 14, LER 2004-001-00, Dresden, Unit 3 Automatic Scram During Testing of the Main Turbine Master Trip Solenoid Valves | Hearing - Entergy Exhibit 14, LER 2004-001-00, Dresden, Unit 3 Automatic Scram During Testing of the Main Turbine Master Trip Solenoid Valves | | | 05000271/LER-2004-001, E-mail from Ronda Daflucas, Entergy, to Rick Ennis, NRC, FW: LER 2004-001-00 Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit | E-mail from Ronda Daflucas, Entergy, to Rick Ennis, NRC, FW: LER 2004-001-00 Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit | | | 05000237/LER-2004-002, Hearing - Entergy Exhibit 15, LER 2004-002-00, Dresden, Units 2 and 3, Unit 3 Automatic Scram Due to Main Turbine Low Pressure Trip and Subsequent Discovery of Inoperability of the Units 2 and 3 | Hearing - Entergy Exhibit 15, LER 2004-002-00, Dresden, Units 2 and 3, Unit 3 Automatic Scram Due to Main Turbine Low Pressure Trip and Subsequent Discovery of Inoperability of the Units 2 and 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000271/LER-2004-002, Regarding Revision to LER 2004-002-00 That Provides the Results of the Special Nuclear Material Inventory Discrepancy Discovered on April 04, 2004 | Regarding Revision to LER 2004-002-00 That Provides the Results of the Special Nuclear Material Inventory Discrepancy Discovered on April 04, 2004 | | | 05000271/LER-2004-003, Regarding Automatic Reactor Scram Due to a Main Generator Trip as a Result of an Iso-Phase Bus Duct Two-Phase Electrical Fault | Regarding Automatic Reactor Scram Due to a Main Generator Trip as a Result of an Iso-Phase Bus Duct Two-Phase Electrical Fault | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(x)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System |
|
