Regarding Revised Target Date for Supplement
Person / Time
ML042180213
Site:	Turkey Point
Issue date:	07/22/2004
From:	Jones T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2004-145 LER 04-001-00
Download: ML042180213 (1)
v • d • e

LER-2004-001, Regarding Revised Target Date for Supplement

Event date:
Report date:
2502004001R00 - NRC Website
v • d • e

text

FPL 10 CFR § 50.73 L-2004-145 JUL 2 2 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Licensee Event Report: 2004-001-00 Revised Target Date for Supplement A supplement was originally planned for Licensee Event Report (LER) 250/2004-001-00 by June 30, 2004. Preparation of the supplement requires further analysis, which is being performed both in-house and by Turkey Point's NSSS vendor. The analyses are scheduled for completion by mid-September 2004. Accordingly, the target date for submitting the LER supplement is revised to October 18, 2004 to allow the analysis information to be incorporated.

If there are any questions, please call Mr. Walter Parker at (305) 246-6632.

Very truly yours, Terry 0. Jones Vice President Turkey Point Nuclear Plant cc:

Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant an FPL Group company

Licensee Event Report

Turkey Point

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000250/LER-2004-001, Regarding Revised Target Date for Supplement	Regarding Revised Target Date for Supplement
05000251/LER-2004-001, Regarding Inadequate Calibration Renders Radiation Process Effluent Monitor Inoperable	Regarding Inadequate Calibration Renders Radiation Process Effluent Monitor Inoperable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000250/LER-2004-002, Regarding As-Found Cycle 20 Main Steam Safety Valve Setpoint Outside Technical Specification Limits	Regarding As-Found Cycle 20 Main Steam Safety Valve Setpoint Outside Technical Specification Limits	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000251/LER-2004-002, Regarding Automatic Reactor Trip Due to Low Steam Generator Level and Steam/Feedwater Flow Mismatch	Regarding Automatic Reactor Trip Due to Low Steam Generator Level and Steam/Feedwater Flow Mismatch	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iv)(B)(6)
05000251/LER-2004-003, Regarding Bearing Oil Leak Causes High Head Safety Injection Pump to Be Inoperable Longer than Allowed by Technical Specifications	Regarding Bearing Oil Leak Causes High Head Safety Injection Pump to Be Inoperable Longer than Allowed by Technical Specifications	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)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000250/LER-2004-003, Regarding Single Failure Vulnerability in Dousing Function Can Cause Emergency Containment Filters to Be Inoperable	Regarding Single Failure Vulnerability in Dousing Function Can Cause Emergency Containment Filters to Be Inoperable	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)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000251/LER-2004-004, Regarding Manual Reactor Trip Due to Lowering Condenser Vacuum	Regarding Manual Reactor Trip Due to Lowering Condenser Vacuum	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) 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)(iv)(B)(6) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iv)(B)(2)
05000250/LER-2004-004, Regarding Plant Shutdowns Due to Drop of Shutdown Bank Rod E-11 During Low Power Physics Testing	Regarding Plant Shutdowns Due to Drop of Shutdown Bank Rod E-11 During Low Power Physics Testing	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)(iv), System Actuation 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)
05000250/LER-2004-005, Re Heat-Damaged Cables Causing Potential Inoperability of 2 of 3 Pressurizer Water Level Monitoring Channels	Re Heat-Damaged Cables Causing Potential Inoperability of 2 of 3 Pressurizer Water Level Monitoring Channels	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)
05000250/LER-2004-006, Manual Reactor Trip Due to Fire in the High Pressure Turbine Area	Manual Reactor Trip Due to Fire in the High Pressure Turbine Area	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)(iv)(B)(1) 10 CFR 50.73(a)(2)(viii)(B)
05000250/LER-2004-007, Regarding Manual Reactor Trip Due to Generator Exciter Turbine Cooling Water Leak	Regarding Manual Reactor Trip Due to Generator Exciter Turbine Cooling Water Leak	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)(iv)(B)(6) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)

05000250/LER-2004-001, Regarding Revised Target Date for Supplement

text

Navigation menu

Search