05000338/LER-2013-001, Emergency Diesel Generators Inoperable During Core Alterations
| ML13338A283 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/21/2013 |
| From: | Gerald Bichof Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 13-001-00 | |
| Download: ML13338A283 (5) | |
| 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 |
| 3382013001R00 - NRC Website | |
text
10CFR50.73 Virginia Electric and Power Company North Anna Power Station 1022 Haley Drive Mineral, Virginia 23117 November 21, 2013 Attention: Document Control Desk Serial No.:
13-574 U. S. Nuclear Regulatory Commission NAPS:
MPW Washington, DC 20555-0001 Docket No.: 50-338 License No.: NPF-4
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Power Station Unit 1.
Report No. 50-338/2013-001-00 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, erald T. Bischof 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 05000 338 1 OF 4
- 4. TITLE Unit 1 Emergency Diesel Generators Inoperable During Core Alterations
- 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 I
NUMBER NO.
05000 09 26 2013 2013
-- 001 --
00 11 21 2013 FACILITY NAME DOCUMENTNUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E] 20.2201(b)
F] 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
[] 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) 6 El 20.2203(a)(1)
E]
20.2203(a)(4)
H 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A) 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[E 50.36(c)(1)(ii)(A)
[]
50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii) 0]
50.36(c)(2)
F-] 50.73(a)(2)(v)(A)
[]
73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
[]
50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
E]
50.73(a)(2)(i)(A)
E]
50.73(a)(2)(v)(C)
El OTHER 0
El 20.2203(a)(2)(vi)
[]
50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below' or in loads to offsite power could not be performed to satisfy the TS surveillance requirement.
2.0
SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS
No significant safety consequences resulted from this event since one OPERABLE qualified circuit between the offsite transmission network and the onsite Class 1 E AC electrical power distribution subsystem(s), required by TS 3.8.10, was available and the station blackout EDG was also available to supply power if required. Additionally, had a loss of offsite power occurred, the 1 H EDG would have been able to supply power to the emergency bus. As such, the health and safety of the public were not affected by the event.
This event is reportable per 10 CFR 50.73(a)(2)(i)(B) for a condition prohibited by Technical Specifications.
3.0
CAUSE
A cause evaluation is currently being finalized to determine the apparent cause of the 1 H EDG inoperability.
4.0 IMMEDIATE CORRECTIVE ACTION(S)
Following the loss of load the 1 H EDG was tripped from the Control Room.
5.0 ADDITIONAL CORRECTIVE ACTIONS
The 1 H EDG mechanical actuator, DRU, and power supply fuse holder for fuse FU1 NA were subsequently replaced. All wiring connections were verified tight.
Post maintenance testing was performed under 1-PT-82.12H, 1H Diesel Generator Isochronous Mode (Start by ESF Actuation) and 1-PT-83.12H, 1H Diesel Generator Test (Start by ESF Actuation) followed by 24-hour run and hot restart test. Post maintenance testing was completed satisfactorily.
The mechanical governor and DRU removed from the 1 H EDG were sent to a vendor for testing. The mechanical governor and DRU were found to operate properly following 24-hour bench testing. A loose power supply fuse holder (fuse holder for FU1 NA) to the 2301A Load Sharing and Speed Control and DRU was also identified. Additional testing is ongoing at the vendor to validate a momentary loss of power scenario.
6.0 ACTIONS TO PREVENT RECURRENCE Actions to prevent recurrence will be developed upon completion of the apparent cause evaluation.
7.0 SIMILAR EVENTS
None.
8.0 ADDITIONAL INFORMATION
Unit 2 was operating in Mode 1,100 percent power, and was not affected by this event.