05000339/LER-2008-001, Regarding Manual Reactor Trip Due to Shutdown Bank a Group Step Counter Deviation Greater than Allowed
| ML080990623 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/01/2008 |
| From: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 08-0070 LER 08-001-00 | |
| Download: ML080990623 (7) | |
| 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 |
| 3392008001R00 - NRC Website | |
text
1 0CFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 April 1, 2008 U. S. Nuclear Regulatory Commission Serial No.:
08-0070 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. 50-339/2008-001-00 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, Daniel G. Stoddard, 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 NRC Senior Resident Inspector North Anna Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)
, 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 1OF4
- 4. TITLE Manual Reactor Trip Due to Shutdown Bank "A" Group Step Counter Deviation Greater Than Allowed R NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY.
YEAR IFACILITY NAME DOCUMENTINUMBER 05000 04 01 20081 FACILITY NAME DOCUMENTNUMBER I
1 1
I05000
- 9. OPERATING MODE 3
I
- 10. POWER LEVEL 0%
Eli Eli E]I
- 11. THIS REPORT 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi)
IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E]
20.2203(a)(3)(i)
LI 50.73(a)(2)(i)(C)
Ej 50.73(a)(2)(vii)
LI 20.2203(a)(3)(ii)
[]
50.73(a)(2)(ii)(A)
LI 50.73(a)(2)(viii)(A)
El 20.2203(a)(4)
[]
50.73(a)(2)(ii)(B)
[]
50.73(a)(2)(viii)(B)
[] 50.36(c)(1)(i)(A)
LI 50.73(a)(2)(iii)
[
50.73(a)(2)(ix)(A)
Fl1 50.36(c)(1)(ii)(A)
[]
50.73(a)(2)(iv)(A)
U 50.73(a)(2)(x)
[:j 50.36(c)(2)
F]
50.73(a)(2)(v)(A)
E] 73.71(a)(4)
E]
50.46(a)(3)(ii)
Ej 50.73(a)(2)(v)(B)
LI 73.71(a)(5)
LI 50.73(a)(2)(i)(A)
LI 50.73(a)(2)(v)(C)
Ej OTHER LI 50.73(a)(2)(i)(B)
[]
50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
F. Mladen, Director Station Safety and Licensing (540) 894-2108CAUSE SYSTEM COMPONENT MANU-REPORTABLE I
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX
- - FACTURER TO EPIX X
AA CTR W120 N
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION El YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
[] NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On February 8, 2008, Unit 2 was in Mode 3, zero percent power, preparing for restart following a planned maintenance outage. At 1759 hours0.0204 days <br />0.489 hours <br />0.00291 weeks <br />6.692995e-4 months <br />, a rod control urgent failure alarm was received while withdrawing the "A" Shutdown Bank control rods. Rod withdrawal was stopped and it was noted that the Group Step Counters deviated by three steps. As a result, at 1812 hours0.021 days <br />0.503 hours <br />0.003 weeks <br />6.89466e-4 months <br /> a manual reactor trip was initiated by opening the reactor trip breakers in accordance with Technical Requirement 3.1.3. This is a valid actuation of the Reactor Protection System. Four suspect cards were replaced in Power Cabinet 2AC.
Following card replacement the reactor trip breakers were closed. Shutdown Banks "A" and "B" were fully withdrawn with no concerns. On February 8, 2008, at 1959 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.453995e-4 months <br />, a non-emergency 8-hour report was made in accordance with 10 CFR 50.72(b)(3)(iv)(A) due to actuation of the Reactor Protection System. This event is reportable pursuant to 10 CFR 50.73 (a)(2)(iv)(A) for a condition that resulted in manual actuation of the Reactor Protection System. This event posed no significant safety implications because the reactor was subcritical when the reactor trip breakers were opened. Compliance with all Technical Requirements was maintained. Therefore, the health and safety of the public were not affected by this event.
NRC FORM 366 (9-2007)
PRKTED ON RECYCLED PAPER (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 Logs dated February 8 & 9, 2008.
Commitments
None Action Plan
- 1. Complete RCE000220 following the 2008 Unit 2 RFO.
Changes to the UFSAR or QA Topical Report None