LER-2005-001, Regarding Incorrect Installation of Flow Element Resulted in Service Water Flow Below the Technical Specification Limit |
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| 4572005001R00 - NRC Website |
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Exelkn.
Exelon Generation Company, LLC www.exeloncorp.com Braidwood Station Nuclear 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 March 11, 2005 BW050027 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Submittal of Licensee Event Report Number 2005-001-00, "Incorrect Installation of Flow Element Resulted in Service Water Flow Below the Technical Specification Limit" 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). 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 March 14, 2005.
Should you have any questions concerning this submittal, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Ket.olson Site Vice President Braidwood Station
Enclosure:
LER Number 2005-001-00 cc:
Regional Administrator - Region IlIl NRC Braidwood Senior Resident Inspector
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
~6-1004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person Is not required to respond to. the
- 3. PAGE Braidwood, Unit 2 05000457 1 of 4
- 4. TITLE Incorrect Installation of Flow Element Resulted in Service Water Flow Below the Technical Specification Limit
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNIA E
AGCLIY NAME DOK)ItI NUMBER MONTH DAY YEAR YEAR NUMBEN REV MONTH DAY YEAR NIA N/A NUBARN.Y NAME_
__CIEI NUMBER 1
11 2005 2005 - 001-00 03 11 2005 N/A N/A
.OPEATING MDE THIS REPO ISSUBMITTED PURSANTTO HE REQUIREMENTS OF 10 CFR§: (Check all thatapply) o 20.2201(b) a 20.2203(a)(3Xi) 0 50.73(aX2)(i)(C)
Q 50.73(aX2)(vii) 1 D 20.2201(d)
D 20.2203(a)(3Xii)
D 50.73(aX2)(iiXA) 5 50.73(aX2)(viiiXA) o 20.2203(aXl) 5 20.2203(a)(4) 0 50.73(aX2)(iiXB) 5 50.73(aX2)(viiiXB)
D] 20.2203(a)(2Xi)
D 50.36(c)(IXiXA)
D 50.73(aX2)(iii) 5 50.73(aX2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(aX2Xii) 0 50.36(c)(lXii)(A) 5 50.73(aX2XivXA) 5 50.73(aX2)(x) o 20.2203(a)(2Xiii) 5 50.36(c)(2)
D 50.73(aX2)(vXA) 0 73.71(aX4) 100 o 20.2203(a)(2Xiv) a 50.46(aX3Xii) 5 50.73(aX2XvXB)
D 73.71 (aX5) 1 20.2203(a)(2Xv) 5 50.73(aX2Xi)(A)
D 50.73(aX2XvXC) 5 OTHER O 20.2203(aX2Xvi) 0 50.73(aX2XlXB) 5 50.73(aX2XvXD)
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)
Previous Occurrences
There have been no similar Licensee Event Report events at Braidwood Station in the last three years.
3. Component Failure Data
Manufacturer N/A Nomenclature N/A Model N/A Mfg. Part Number N/A
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| 05000456/LER-2005-001, Regarding Technical Specification (TS) 3.9.4 Violation Due to Imprecise Original TS and TS Bases Wording | Regarding Technical Specification (TS) 3.9.4 Violation Due to Imprecise Original TS and TS Bases Wording | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000457/LER-2005-001, Regarding Incorrect Installation of Flow Element Resulted in Service Water Flow Below the Technical Specification Limit | Regarding Incorrect Installation of Flow Element Resulted in Service Water Flow Below the Technical Specification Limit | | | 05000457/LER-2005-002, Re Reactor Trip Due to Main Generator C Phase Bushing Failure Due to Overheating | Re Reactor Trip Due to Main Generator C Phase Bushing Failure Due to Overheating | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000456/LER-2005-002, Re Feedwater Isolation Valve 1FW039A Fails to Stroke in the Required Time Due to Failure of Valve Air Regulator to Maintain Set Pressure | Re Feedwater Isolation Valve 1FW039A Fails to Stroke in the Required Time Due to Failure of Valve Air Regulator to Maintain Set Pressure | 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000456/LER-2005-003, Regarding Licensed Maximum Power Level Exceeded Due to Feedwater Heater Transient | Regarding Licensed Maximum Power Level Exceeded Due to Feedwater Heater Transient | 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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