05000456/LER-2006-001, Regarding Unit 1 Reactor Coolant System Pressure Boundary Leakage Due to Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve
| ML061770160 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/26/2006 |
| From: | Polson K Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW060062 LER 06-001-00 | |
| Download: ML061770160 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(B) 10 CFR 50.73(a)(2)(iii) 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 |
| 4562006001R00 - NRC Website | |
text
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BTa dwood Stat 10 CFR 50.73 June 26, 2006 BW060062 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456
Subject:
Submittal of Licensee Event Report Number 2006-001-00, Braidwood Unit 1 Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve The enclosed Licensee Event Report (LER) is being submitted in accordance with 10 CFR 50.73, Licensee event report system, paragraph (a)(2)(i)(B) and paragraph (a)(2)(ii)(A). 10 CFR 50.73(a) requires an LER to be submitted within 60 days after discovery of the event, therefore, this report is being submitted by June 26, 2006.
There are no commitments contained in the attached report. Should you have any questions concerning this submittal, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Keith J. PoIson Site Vice President Braidwood Station
Enclosure:
LER Number2006-001-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)
LICEE EVENT REPORT (LER)
(See reverse for required number of d- ~
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igiLs,c arac ers or eac
~ocj APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 06130/2007 Eshmated, the NRC may not conduct or sponsor, and a person is not required to respond to, the infnrm~tinnrnllw~tinn
- 1. FACILITY NAME Braidwood, Unit 1
- 2. DOCKET NUMBER
- 3. PAGE 05000456 1
of 4
L TITLE Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL MONTH DAY YEAR FACILITY NAME DOCKET NUMBER N/A N/A 04 25 2006 2006 001 00 06 26 2006 FACILITY NAME DOCKET NUMBER N/A N/A
- 3. OPERATING MODE 6
- 11. THIS REPORT IS z,UBMflThD PURSUANT TO THE REQUIREMENTS OF 10 CFR~:(Check al/thatapply) o 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)Ø)(C) 0 50.73(a)(2)(vii) 0 20.2201(d) 0 20,2203(a)(3)(ii)
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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)Oi)(B) 0 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2Xix)(A) 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(1vXA) 0 50.73(a)(2)(x) o 202203(a)(2)Oii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)çi) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(c) 0 OTHER o 202203(a)(2)(vi)
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50.73(a)(2)(i)(B) 0 5073(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)
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Component Failure Data
Manufacturer Nomenclature Model Mfp. Part Number Westinghouse Pressurizer 1100J48 N/A