Letter Sequence Request |
|---|
|
|
MONTHYEARRNP-RA/11-0044, Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies2011-06-10010 June 2011 Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request RNP-RA/11-0057, Regarding Condition Prohibited by Technical Specifications When Non-Seismic System Was Aligned to Refueling Water Storage Tank Due to Regulatory Requirements Not Adequately Incorporated in Plant Documentation2011-06-30030 June 2011 Regarding Condition Prohibited by Technical Specifications When Non-Seismic System Was Aligned to Refueling Water Storage Tank Due to Regulatory Requirements Not Adequately Incorporated in Plant Documentation Project stage: Request 05000338/LER-2011-002, Regarding Condition Prohibited by Technical Specifications When a Non-Seismic System Was Aligned to a Seismic System2011-08-27027 August 2011 Regarding Condition Prohibited by Technical Specifications When a Non-Seismic System Was Aligned to a Seismic System Project stage: Request ML11333A2042011-12-0505 December 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: RAI RNP-RA/11-0107, Transmittal of Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2012-01-18018 January 2012 Transmittal of Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Response to RAI ML12032A1542012-01-18018 January 2012 Transmittal of Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Response to RAI ML11292A1902012-01-18018 January 2012 Supporting Document and Examples for Information Notice Sblc and RWST Issues Project stage: Request ML12188A4802012-07-12012 July 2012 Closeout of Bulletin 2011-01, Mitigating Strategies Project stage: Other 2011-06-30
[Table View] |
LER-2011-002, Regarding Condition Prohibited by Technical Specifications When a Non-Seismic System Was Aligned to a Seismic System |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 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)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
|---|
| 3382011002R00 - NRC Website |
|
text
1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 August 27, 2011 Attention: Document Control Desk Serial No.:
11-358 U. S. Nuclear Regulatory Commission NAPS:
RAP Washington, DC 20555-0001 Docket No.: 50-338,339 License No.: NPF-4, NPF-7
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submit the following Licensee Event Report applicable to North Anna Power Station Units 1 and 2.
Report No. 50-338/2011-002-00 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 La~n 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
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 and 2 05000 338 1 OF 3
- 4. TITLE Condition Prohibited by Technical Specifications When a Non-Seismic System was Aligned to a Seismic System
- 5. EVENT DATE
- 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.
North Anna Power Station 05000 339 06 29 2011 2011 I -- 002--
00 08 27 2011 FACILITY NAME DOCUMENT NUMBER j
05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
[]
50.73(a)(2)(i)(C)
[
50.73(a)(2)(vii)
El 20.2201(d)
E] 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) 1 E] 20.2203(a)(1)
El 20.2203(a)(4)
H 50.73(a)(2)(ii)(B)
[] 50.73(a)(2)(viii)(B)
E] 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A)
E]
50.73(a)(2)(iii)
[]
50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E] 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
[]
50.36(c)(2)
[]
50.73(a)(2)(v)(A)
El 73.71(a)(4)
[]
20.2203(a)(2)(iv)
[]
50.46(a)(3)(ii)
[]
50.73(a)(2)(v)(B)
[]
73.71(a)(5)
El 20.2203(a)(2)(v)
E]
50.73(a)(2)(i)(A)
E]
50.73(a)(2)(v)(C)
[]
OTHER 100%
El 20.2203(a)(2)(vi)
[]
50.73(a)(2)(i)(B)
[
50.73(a)(2)(v)(D)
Specify in Abstract below
_______________________or in 4.0 IMMEDIATE CORRECTIVE ACTION(S)
Operating procedures associated with placing the non-seismic RP system in service on seismic systems were suspended.
5.0
ADDITIONAL CORRECTIVE ACTIONS
The UFSAR will be updated to reflect current operating practices.
An assignment has been created in the Corrective Action System to evaluate the extent of condition.
Additional corrective actions being considered include evaluating what is required to qualify the RP system as seismic and revising operating procedures to allow operation of the RP system on the RWST in Modes 5, 6 and defueled.
6.0 ACTIONS TO PREVENT RECURRENCE The actions noted above are sufficient to preclude recurrence.
7.0 SIMILAR EVENTS
There have been no similar events at North Anna.
8.0 ADDITIONAL INFORMATION
Both Units were in Mode 1,100 percent power, at the time of this event and were not affected.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000339/LER-2011-001, For North Anna, Unit 2, Regarding Inoperable Emergency Diesel Generator Due to Coolant Leak | For North Anna, Unit 2, Regarding Inoperable Emergency Diesel Generator Due to Coolant 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000338/LER-2011-001, For North Anna Power Station, Unit 1, Regarding Annunciator Card Failure Due to Carbon Resistor Degradation | For North Anna Power Station, Unit 1, Regarding Annunciator Card Failure Due to Carbon Resistor Degradation | 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-2011-002, Regarding Condition Prohibited by Technical Specifications When a Non-Seismic System Was Aligned to a Seismic System | Regarding Condition Prohibited by Technical Specifications When a Non-Seismic System Was Aligned to a Seismic System | 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-2011-003, Regarding Dual Unit Reactor Trip and ESF Actuations During Seismic Event with a Loss of Offsite Power | Regarding Dual Unit Reactor Trip and ESF Actuations During Seismic Event with a Loss of Offsite Power | 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) |
|