05000339/LER-2007-003, Automatic Reactor Trip Due to Invalid Safety Injection Relay Actuations
| ML072480671 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/27/2007 |
| From: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0538 LER 07-003-00 | |
| Download: ML072480671 (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 |
| 3392007003R00 - NRC Website | |
text
3' 1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 August 27, 2007 U. S. Nuclear Regulatory Commission Serial No.:
07-0538 Attention: Document Control Desk NAPS:
MPW Washington, D. C. 20555-0001 Docket No.: 50-339 License No.: NPF-7
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 2.
Report No. 50-339/2007-003-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.
Sincerely, i
.toddard, P.E.
Site Vice President North Anna Power Station Enclosure Commitments contained in this letter: None cc:
United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station
I A
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB NO. 3150-0104 EXPIRES: 6/30/2007 (6-2004)
, 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 2 05000 339 1 OF 4
- 4. TITLE Automatic Reactor Trip Due to Invalid Safety Injection Relay Actuations
- 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 06 29 2007 2007
-- 003 --
00 08 27 2007 FACILITY NAME DOCUMENT NUMBER 1
05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E] 20.2201(b)
Ej 20.2203(a)(3)(i)
E]
50.73(a)(2)(i)(c)
E 50.73(a)(2)(vii)
[]
20.2201(d)
E]
20.2203(a)(3)(ii)
[-]
50.73(a)(2)(ii)(A)
[]
50.73(a)(2)(viii)(A) 1 LI 20.2203(a)(1)
[
20.2203(a)(4) 0I 50.73(a)(2)(ii)(B)
EJ 50.73(a)(2)(viii)(B)
LI 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
[]
20.2203(a)(2)(ii)
[
50.36(c)(1)(ii)(A)
[]
50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
El 50.36(c)(2)
[
50.73(a)(2)(v)(A)
[j 73.71(a)(4)
LI 20.2203(a)(2)(iv)
[]
50.46(a)(3)(ii)
Ej 50.73(a)(2)(v)(B)
E] 73.71(a)(5)
LI 20.2203(a)(2)(v)
Ei 50.73(a)(2)(i)(A)
[]
50.73(a)(2)(v)(C)
E] OTHER 100%
LI 20.2203(a)(2)(vi)
E]
50.73(a)(2)(i)(B)
E]
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 NRC Form 366A) (17)
5.0 ADDITIONAL CORRECTIVE ACTIONS
An abnormal procedure was developed to reset SI locally and training was provided.
Training included a review of the event and the performance deficiencies noted in the event response.
All SSPS cards were removed and tested using a KIMKA tester. Components were repaired or replaced as necessary to ensure card reliability.
6.0 ACTIONS TO PREVENT RECURRENCE All SSPS cards will be removed from the Unit 1 SSPS and tested during the Fall 2007 Refueling Outage. Components will be repaired or replaced as required to ensure the cards are reliable.
A determination will be made if additional on-line testing/checks for the SSPS can be performed to evaluate card health in order to identify imminent failure.
Life cycle management for SSPS cards will be implemented.
7.0 SIMILAR EVENTS
This event is not a repeat of a card failure due to a zener diode failure nor is it a repeat of a card failure that caused a similar plant transient. Although similar SSPS card failures have occurred a review of the history of this universal card, A313 shows no other failures have occurred. Card failures have previously been repaired and tracked to monitor the overall failure rate. The overall failure rate has been approximately 1% of all cards. Corrective actions have been initiated to establish a strategy to test/repair/replace SSPS cards.
8.0 ADDITIONAL INFORMATION
At the time of this event, North Anna Unit 1 was operating at 100 percent power.
Component Information
Description
Universal Logic Board A313 Manufacturer:
Westinghouse / W893 Model No.:
6056D21G01 Serial No.:
2170