05000237/LER-2006-003, Re Plant Reactor Steam Dome Pressure-Low Permissive Switch Determined to Have Been Historically Inoperable
| ML062160522 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-019) |
| Issue date: | 07/28/2006 |
| From: | Bost D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SVPLTR 06-0041 LER 06-003-00 | |
| Download: ML062160522 (6) | |
| 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 |
| 2372006003R00 - NRC Website | |
text
Exelo n.
Exelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station Nucear 65oo North Dresden Road Morris, IL 60450-9765 10 CFR 50.73 July 28, 2006 SVPLTR # 06-0041 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit No. 2 Renewed Facility Operating License No. DRP-19 NRC Docket No. 50-237
Subject:
Licensee Event Report 237/2006-003-00, "Unit 2 Reactor Steam Dome Pressure-Low Permissive Switch Determined To Have Been Historically Inoperable" Enclosed is Licensee Event Report 237/2006-003-00, "Unit 2 Reactor Steam Dome Pressure-Low Permissive Switch Determined To Have Been Historically Inoperable," for Dresden Nuclear Power Station, Unit 2. This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications."
Should you have any questions concerning this report, please contact Mr. J. Ellis, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, Danny'. Bost Site Vice President Dresden Nuclear Power Station Enclosure cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may digis/carater foreac blck)not conduct or sponsor, and a person Is not required to respond to, the digits/characters for each block) infnrmatinn conlt.ctinn.
- 3. PAGE Dresden Nuclear Power Station Unit 2 05000237 1 OF 5
- 4. TITLE Unit 2 Reactor Steam Dome Pressure-Low Permissive Switch Determined To Have Been Historically Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED 1EUNIA E
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR N/A N/A IFACILITY NAME DOCKET NUMBER 05 31 2006 2006 003 -
00 07 28 2006 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANTTO 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 20.2201(d)
[I 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A) ol 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[I 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[I 50.73(a)(2)(iii)
[I 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
[I 20.2203(a)(2)(iii)
[E 50.36(c)(2)
[E 50.73(a)(2)(v)(A)
[] 73.71 (a)(4) 100 El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5)
[1 20.2203(a)(2)(v)
[: 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
El OTHER o 20.2203(a)(2)(vi)
[3 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) (17)
F.
Previous Occurrences
A review of DNPS Licensee Event Reports (LERs) for the last three years identified six LERs associated with training or procedure issues.
LER 237/2006-001, "Unit 2 Isolation Condenser Declared Inoperable Due To Inadequate Backfilling of Instrument Sensing Lines." The LER identified inadequate procedure guidance in backfilling instrument sensing lines.
LER 249/2004-002, "Unit 3 Automatic Scram Due To Main Turbine Low Pressure Trip And Subsequent Discovery Of Inoperability Of The Units 2 And 3 High Pressure Coolant Injection System." The LER identified inadequate procedure guidance for swapping the Main Turbine lube oil coolers.
LER 237/2004-003, "Units 2 and 3 Control Room Emergency Ventilation System Inoperable Due To Damper Failure To Close." The LER identified inadequate procedure guidance contained on an enclosed figure use to restore the system after a temporary modification.
LER 249/2004-003, "Unit 3 Scram Due To Loss Of Offsite Power And Subsequent Inoperability Of The Standby Gas Treatment System For Units 2 And 3." The LER identified an inadequate leak rate test procedure that permitted a degraded Secondary Containment boundary to be undetected.
LER 249/2003-001, "Drywell Radiation Monitor Detector Not Fully Inserted." The LER identified inadequate procedure direction for placing the detector in its penetration.
LER 237/2003-006, "Unit 2 Torus Purge Valves Open In Conjunction With The Drywell Purge Valve In Mode 2." The LER identified inadequate procedure controls for ensuring needed valve positions in Mode 2.
G.
Component Failure Data
NA