LER-2010-005, For North Anna Power Station, Regarding Unanalyzed Scaffolding Renders Changing Pump Inoperable Due to Human Error |
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| Report date: |
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| Reporting criterion: |
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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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| LER closed by |
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| IR 05000338/2011003 (28 July 2011) |
| 3382010005R00 - NRC Website |
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text
1 0CFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 February 3, 2011 Attention: Document Control Desk Serial No.:
11-012 U. S. Nuclear Regulatory Commission NAPS:
RAP Washington, DC 20555-0001 Docket No.: 50-338 License No.: NPF-4
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submit the following Licensee Event Report applicable to North Anna Power Station Unit 1.
Report No. 50-338/2010-005-00 This report has been reviewed by the Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee for its review.
Sincerely, N. Larry Lane Site Vice President North Anna Power Station Enclosure Commitments contained in this letter: None cc:
United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station
4.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO, 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE NORTH ANNA POWER STATION, UNIT 1 05000 338 1 OF 3
- 4. TITLE Unanalyzed Scaffolding Renders Charging Pump Inoperable Due to Human Error
- 5. EVENT DATE f.1
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCUMENT NUMBER NUMBER NO.
05000 12 12 2010 2010
-- 005--
00 02 03 2011 FACILITY NAME DOCUMENT NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
FZ 20.2201(b)
El 20.2203(a)(3)(i)
F1 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 0[]
20.2201(d)
El 20.2203(a)(3)(ii)
[
50.73(a)(2)(ii)(A)
E] 50.73(a)(2)(viii)(A) 1 [E
20.2203(a)(1)
[i 20.2203(a)(4)
L 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
[__]
20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A) 50.73(a)(2)(iii)
H 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL I]
20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
E]
50.73(a)(2)(iv)(A)
[]
50.73(a)(2)(x)
[]
20,2203(a)(2)(iii)
[]
50.36(c)(2)
[]
50.73(a)(2)(v)(A)
[]
73.71(a)(4)
El 20.2203(a)(2)(iv)
[E 50.46(a)(3)(ii)
LI 50.73(a)(2)(v)(B)
LI 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[]
50,73(a)(2)(v)(C)
[]
OTHER 100%
El 20.2203(a)(2)(vi)
[l 50.73(a)(2)(i)(B)
[J 50.73(a)(2)(v)(D)
Specify in Abstract below or in 4.0 IMMEDIATE CORRECTIVE ACTION(S)
The Technical Specification action was entered at the time the scaffolding was discovered in the Unit 1 "A" Charging Pump cubicle. The pump was placed in PULL-TO-LOCK with the Unit 1 "C" Charging Pump, powered by the "H" Emergency Bus, in service at the time and the associated actions were cleared. The scaffolding was removed from the pump cubicle and then the pump was returned to AUTO.
5.0 ADDITIONAL CORRECTIVE ACTIONS
The Scaffolding Order will be removed from a scaffold at the time of dismantling and shall be "in hand" when updating the status of that scaffold in the scaffold tracking program. Non-supervisory personnel will be required to obtain a second verification prior to updating scaffolding status. These process enhancements have been implemented.
The scaffold tracking function using electronic Scaffold Orders with electronic approvals and signatures will be fully implemented. The use of hard copy Scaffold Orders will be discontinued. This item will be tracked to completion via the Corrective Action System.
6.0 ACTIONS TO PREVENT RECURRENCE The actions noted above are sufficient to preclude recurrence.
7.0
SIMILAR EVENTS
None.
8.0 ADDITIONAL INFORMATION
Unit 2 was in Mode 1,100 percent power, at the time of this event and was not affected.
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| 05000338/LER-2010-001, Regarding Non-Functional Fire Barrier Penetrations Containing Aluminum Conduit Due to Configuration | Regarding Non-Functional Fire Barrier Penetrations Containing Aluminum Conduit Due to Configuration | 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) | | 05000339/LER-2010-001, For North Anna, Unit 2, Regarding Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance | For North Anna, Unit 2, Regarding Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance | 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) 10 CFR 50.73(a)(2)(viii)(A) | | 05000338/LER-2010-002, Regarding Forced Shutdown Due to Un-isolable C Steam Generator Surface Sample Line Leakage | Regarding Forced Shutdown Due to Un-isolable C Steam Generator Surface Sample Line Leakage | 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) | | 05000339/LER-2010-002, For North Anna, Unit 2, Regarding Automatic Reactor Trip and Engineered Safety Feature Actuation Due to Lightning Strike | For North Anna, Unit 2, Regarding Automatic Reactor Trip and Engineered Safety Feature Actuation Due to Lightning Strike | 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) | | 05000338/LER-2010-003, For North Anna, Units 1 and 2, Regarding Potential for Containment Sump Strainer Blockage Due to Unacceptable Insulation in Containment | For North Anna, Units 1 and 2, Regarding Potential for Containment Sump Strainer Blockage Due to Unacceptable Insulation in Containment | 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) | | 05000339/LER-2010-003, Regarding Failure to Isolate Primary Grade Water to Blender Due to Operator Activities | Regarding Failure to Isolate Primary Grade Water to Blender Due to Operator Activities | 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) | | 05000338/LER-2010-004, For North Anna Power Station, Unit 1, Regarding Manual Reactor Trip Due to Malfunction of the Rod Control In-Hold-Out Selector Switch | For North Anna Power Station, Unit 1, Regarding Manual Reactor Trip Due to Malfunction of the Rod Control In-Hold-Out Selector Switch | 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) | | 05000339/LER-2010-004, Automatic Reactor Trip and Engineered Safety Feature Actuation Due to Lightning Strike | Automatic Reactor Trip and Engineered Safety Feature Actuation Due to Lightning Strike | 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) | | 05000338/LER-2010-005, For North Anna Power Station, Regarding Unanalyzed Scaffolding Renders Changing Pump Inoperable Due to Human Error | For North Anna Power Station, Regarding Unanalyzed Scaffolding Renders Changing Pump Inoperable Due to Human Error | 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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