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MONTHYEAR05000529/LER-2006-002, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause2006-09-14014 September 2006 Regarding Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause Project stage: Request ML0704303782007-01-31031 January 2007 Mitigation of Alloy 600/82/182 Pressurizer Butt Welds Project stage: Request ML0704705252007-02-0808 February 2007 Proposed Alternative for PVNGS Use of Full-Structural Weld Overlays in the Repair of Dissimilar Metal Welds - Relief Request No. 36-10 CFR 50.55a(a)(3)(i) and Request to Use a Later Edition and Addenda of the ASME Boiler Project stage: Request ML0705902122007-02-16016 February 2007 Commitment to Perform Enhanced Leak Monitoring Associated with Pressurizer Dissimilar Welds and Reactor Coolant System Project stage: Request ML0706603652007-02-21021 February 2007 2/21/2007 E-Mail to M. Markley, NRR/DORL/LPL4, from M. Glenn, Arizona Public Service Company, Subject: Revised Leakage Monitoring Commitment, Related to Confirmatory Action Letter Project stage: Other ML0706602982007-03-15015 March 2007 Confirmatory Action Letter Alloy 82/182 Pressurizer Butt Welds Project stage: Other ML0724102032007-08-0202 August 2007 Mitigation of Alloy 600/82/182 Pressurizer Butt Welds in 2008 Project stage: Other ML0726904222007-09-19019 September 2007 APSs 60-Day After Plant Restart Letter in Response to First Revised NRC Order EA-03-009, Item Iv.E and Confirmatory Action Letter, NRR-07-004, Dated March 15, 2007 - U1R13 Project stage: Other ML0728200012007-10-31031 October 2007 Completion of Actions for Confirmatory Action Letter NRR-07-004 Project stage: Other 2007-02-21
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10 CFR 50.73 A subsidiary of Pinnacle West Capital Corporation Palo Verde Nuclear Generating Station Cliff Eubanks Vice President Nuclear Operations Tel (623) 393-6116 Fax (623) 393-6077 Mail Station 7602 PO Box 52034 Phoenix, Arizona 85072-2034 102-05566-C E/SABIJAPIDFH September 14, 2006 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No. STN 50-529 License No. NPF 51 Licensee Event Report 2006-002-00 Attached please find Licensee Event Report (LER) 50-529/2006-002-00 prepared and submitted pursuant to 10 CFR 50.73. The LER reports two trains of Auxiliary Feedwater rendered inoperable as a result of a single watertight fire door being left open and uncompensated.
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the NRC Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact James A. Proctor, Section Leader, Regulatory Affairs, at (623) 393-5730.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, CE/SAB/JAP/DFH/gt Attachment cc:
B. S. Mallett M. B. Fields G. G. Warnick NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)
NRC Senior Resident Inspector for PVNGS
- 422,
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/302007 (62004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the digitscharacers fo each lock)information collection.
_ m 7 P
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- 3. PAGE Palo Verde Nuclear Generating Station Unit 2 05000529 1 OF 4
.TITLE Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR Y
SEQUENTIAL REV MONTH DAY YEAR None 05000 NUMBER NO.
N05000 FACILITY NAME DOCKET NUMBER 07 16 20062006 -002-00 09 14 2006 None 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[] 20.2201(b)
E0 20.2203(a)(3)(i) 0 50.73(a)(2Xi)(C)
I@ 50.73(a)(2)(vii) 10 20.2201(d)
[I 20.2203(a)(3)(ii) 0l 50.73(a)(2)(ii)(A) 0l 50.73(a)(2Xviii)(A) 0 20.2203(a)(1) 0l 20.2203(a)(4) 0l 50.73(a)(2)(i)(B)
[I 50.73(a)(2)(viii)(B)
O 20.2203(a)(2)(i)
[I 50.36(c)(1)(D(A)
[I 50.73(a)(2Xiii)
[I 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(H)
[I 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
[o 20.2203(aX2)(iii)
El 50.36(c)(2) 0l 50.73(a)(2)(v)(A)
[I 73.71(a)(4)
O 20.2203(aX2)(iv)
[I 50.46(a)(3)Xii)
[I 50.73(a)(2Xv)(B) 0l 73.71(a)(5) 100 [E
20.2203(a)(2)(v)
[I 50.73(a)(2)(D(A) 0l 50.73(a)(2)(v)(C) 0l OTHER El 20.2203(a)(2)(vi)
[I 50.73(a)(2X(iB) 0l 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)
ICCDP total = 2E-11 + 0 + 2E-9 = 2E-9 This indicates the risk impact of the condition described above with barrier door C-A-06 between train 'A' AF and train 'B' AF pump rooms being left open and unattended, is not significant.
- 6.
CAUSE OF THE EVENT
The direct cause of the event was the ESO failed to follow procedural requirements for closing and securing door C-A-06. The root cause was the ESO inspecting the area inside door C-A-06 did not maintain sufficient attention to ensure the door was closed.
- 7.
CORRECTIVE ACTIONS
The company implemented its' disciplinary policy for this event.
Signs for Units 1, 2, and 3 were posted at the entry to the A train AF room (C-A-01) alerting employees to secure the B train AF room door for each entry and exit.
A site wide communication was distributed and the Vice President of Nuclear Operation directed a plant stand down be held to discuss the importance of door C-A-06 being closed after entry or exit.
A local door alarm will be added to C-A-06 to alert personnel when the door is open.
Until the door alarm is installed, a compensatory measure will be established by posting a Security Officer at the entry point to the AF rooms to ensure plant personnel entering the AF rooms secure C-A-06.
- 8.
PREVIOUS SIMILAR EVENTS
In the past three years, two similar events were reported (LER 50-529/2005-003-00, and 50-530/2006-001-00). The corrective actions associated with these events did not effectively prevent recurrence. Note that the corrective action discussed in LER 50-530/2006-001 -00 to install a local door alarm on C-A-06 had not yet been completed at the time of this event; however, the interim corrective actions were ineffective.
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| 05000530/LER-2006-001, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable | Regarding Two Independent Trains of Auxiliary Feedwater Inoperable | 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)(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 | | 05000528/LER-2006-001, Re Containment Spray Inoperable in Mode 4 with RCS Pressure Greater than 385 Psla | Re Containment Spray Inoperable in Mode 4 with RCS Pressure Greater than 385 Psla | | | 05000529/LER-2006-001, Re TS Required Reactor Shutdown on Failure to Complete Repairs on an AFW Valve within the 7 Day Completion Time | Re TS Required Reactor Shutdown on Failure to Complete Repairs on an AFW Valve within the 7 Day Completion Time | 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) | | 05000528/LER-2006-002, Re Mode 3 Entry Without the Required Number of Pressurizer Heater Groups Operable | Re Mode 3 Entry Without the Required Number of Pressurizer Heater Groups Operable | | | 05000529/LER-2006-002, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause | Regarding Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause | 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), 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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) | | 05000530/LER-2006-002, Regarding Automatic Reactor Protection System Actuation Due to an Invalid Control Element Assembly Calculator Penalty Factor | Regarding Automatic Reactor Protection System Actuation Due to an Invalid Control Element Assembly Calculator Penalty Factor | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000529/LER-2006-003, For Palo Verde, Unit 2, Regarding Unit 2 Variable Overpower Reactor Trip During Main Turbine Control Valve Restoration | For Palo Verde, Unit 2, Regarding Unit 2 Variable Overpower Reactor Trip During Main Turbine Control Valve Restoration | 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) | | 05000528/LER-2006-003, Re Emergency Diesel Generator Actuation on Loss of Power to a Train 4.16KV Bus | Re Emergency Diesel Generator Actuation on Loss of Power to a Train 4.16KV Bus | 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) | | 05000530/LER-2006-003, Regarding Loss of Power to One Class Bus During Testing Due to Human Error | Regarding Loss of Power to One Class Bus During Testing Due to Human Error | | | 05000528/LER-2006-004, Re TS Required Reactor Shutdown on Failure of the Class Pressurizer Heaters to Be Able to Meet Their Mission Time | Re TS Required Reactor Shutdown on Failure of the Class Pressurizer Heaters to Be Able to Meet Their Mission Time | 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) | | 05000530/LER-2006-004, Regarding Emergency Diesel Generator Actuation on Loss of Power to a Train 4.16KV Bus | Regarding Emergency Diesel Generator Actuation on Loss of Power to a Train 4.16KV Bus | 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) | | 05000529/LER-2006-004, Regarding Unit 2 Feedwater Isolation Valve Inoperability Results in Condition Prohibited by Technical Specification | Regarding Unit 2 Feedwater Isolation Valve Inoperability Results in Condition Prohibited by Technical Specification | 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) | | 05000529/LER-2006-005, Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component | Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component | 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) | | 05000528/LER-2006-005, Re Technical Specification Prohibited Condition Due to Check Valve Not Seated | Re Technical Specification Prohibited Condition Due to Check Valve Not Seated | 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) | | 05000530/LER-2006-005, Re Manual Reactor Trip Due to Loss of Main Feedwater | Re Manual Reactor Trip Due to Loss of Main Feedwater | 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) | | 05000528/LER-2006-006, Re Reactor Trip Due to Core Protection Calculator Generated Low Departure from Nuclear Boiling Ratio (DNBR) Trip Signal | Re Reactor Trip Due to Core Protection Calculator Generated Low Departure from Nuclear Boiling Ratio (DNBR) Trip Signal | 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) | | 05000530/LER-2006-006, Regarding Voluntary LER for Failure of Emergency Diesel Generator to Attain Required Voltage Due to Relay Contactor | Regarding Voluntary LER for Failure of Emergency Diesel Generator to Attain Required Voltage Due to Relay Contactor | 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) | | 05000529/LER-2006-006, Regarding Technical Specification 3.7.7 Violation - Inoperable Essential Cooling Water Heat Exchanger | Regarding Technical Specification 3.7.7 Violation - Inoperable Essential Cooling Water Heat Exchanger | 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) | | 05000528/LER-2006-007, Re Emergency Diesel Generator Actuation on Loss of Power to B Train 4.16kv Buses | Re Emergency Diesel Generator Actuation on Loss of Power to B Train 4.16kv Buses | 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) | | 05000530/LER-2006-007, Regarding Manual Reactor Trip Due to Degrading Condenser Vacuum and Condensate Flow | Regarding Manual Reactor Trip Due to Degrading Condenser Vacuum and Condensate Flow | 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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