05000424/LER-2017-001, Regarding Manual Reactor Trip Due to Main Steam Isolation Valve Closure
| ML17093A605 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/03/2017 |
| From: | Taber B Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-17-0510 LER 17-001-00 | |
| Download: ML17093A605 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(1) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 4242017001R00 - NRC Website | |
text
A Southern Nuclear April 3, 2017 Docket No:
50-424 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 B. Keith Taber Vice President Vogtle Units 1-2 Vogtle Electric Generating Plant - Unit 1 Licensee Event Report 2017-001-00 7821 River RD Waynesboro GA. 30830 706-848-0002 tel 706-848-3321 fax NL-17-0510 Manual Reactor Trip due to Main Steam Isolation Valve Closure Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50. 73(a)(2)(iv)(A), Southern Nuclear Operating Company (SNC) is submitting the enclosed Licensee Event Report, 2017-001-00 for Unit 1. This letter contains no NRC commitments. If you have any questions, please contact Dam Sutton at (706) 848-1428.
Respectfully submitted, B. Keith Taber Site Vice President - Vogtle BKT/IBW Enclosure: Unit 1 Licensee Event Report 2017-001-00 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. R. D. Gayheart, Fleet Operations General Manager Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. B. K. Taber, Vice President-Vogtle 1 & 2 Mr. B. J. Adams, Vice President - Engineering Mr. D. D. Sutton, Regulatory Affairs Manager-Vogtle 1 & 2 RType: CVC7000 U. S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager-Vogtle 1 & 2 Mr. M. F. Endress, Senior Resident Inspector-Vogtle 1 & 2
Vogtle Electric Generating Plant-Unit 1 Licensee Event Report 2017-001-00 Manual Reactor Trip due to Main Steam Isolation Valve Closure Enclosure Unit 1 Licensee Event Report 2017-001-00
(NRC FORM 386 U.S. NUCLEAR REGULATORY COMMISSION ! APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (0&-20'61 Estimated burden per 1esponse to comply dl this mandatory colleetlon request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
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- 1. FACILITY NAME
~ DOCKET NUMBER
- PAGE Vogtle Electric Generating Plant 05000424 1 OF2
~-------------------------------~-------------------~------------~
- 4. 11TLE i
Manual Reactor Trip due to Main Steam Isolation Valve Closure
.1
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED 1
MONTH I DAY YEAR I YEAR ISEOUENTIAL I REV MONTH DAY YEAR FACILITY NAME POCKET NUMBER II
_ ___j_ NUMSER_j_,NO*
05000 02 I 03
--- ----Mr03 ___ 2017
-~ FACILITYNAME f?OCKETNUMBER-2017 2017
- - 001
- - 00 '
~ 5000
- 11. 1HS REPORT IS SUBMITTED PURSUANTTO 1HE REQIJREMENI'S OF 10 CFR §: Check all that BDDM 1
0 20.2201(b) 0 20.2203(a)(3){l) 0 50.73(a){2)(ll){A) 0 50.73(a)(2)(viH)(A) 0 20.2201(d) 0 20.2203(a){3)(1i) 0 50.73(a)(2)(U){B) 0 50.73(a)(2)(v1H){B) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(1H) 0 50.73(a)(2)(1x)(A) i I 0 20.2203(a)(2)(l) 0 50.36(c)(1)(1)(A) 181 50. 73(a)(2)(1v)(A) 0 50.73(a)(2)(x)
I
- 10. POWER LEVEL D 20.2203(a)(2)(1i) 0 50.3S(c){1)(11)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) 0 20.2203(a)(2)(lil) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) i 100 0 20.2203(a)(2)(lv) 0 50.46(a)(3)(il) 0 50. 73(a)(2)(v)(C)
D 73.77(a)(1)
I 0 20.2203(a)(2)(v) 0 50.73(a)(2)(1)(A) 0 50.73(a)(2)(v){D) 0 73. 77(a)(2)(1)
I 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii) 0 73.77(8)(2)(11) 0 50.73(a)(2)(1)(C) 00THER Specify In Absll8a.,_ or In NRC F01111 366A
~ENSEE CONTACT
~EI.EPHONE NUMBER (lndude AtVa Cl>rle)
I VogUe Electric Generating Plant, Bennie White!. Licensing S~ervisor I 706-848-3621 I
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SUBMISSION DATE 114. SUPPLEMENTAL REPORT EXPECTED 0 YES (If yes, complete 15. EXPECTED SUBMISSION DA TC)
~BSTRACT (Unrt to 1400 spaces, le.* IIP(YOXima~ 15 ~spaced lypewrllten lines)
On February 03, 2017 at 1545 EST, Vogtle Unit 1 was operating in Mode 1 at 100 percent power when the Loop 1 Outboard Main Steam Isolation Valve (MSIV)[ISV], 1 HV3006B, began drifting closed due to hydraulic oil leak. Operating crew identified the issue and initiated a manual reactor trip due to the MSIV[ISV] drifting closed. All control rods fully 1
inserted and all equipment actuated as designed.
I Unit 1 was stabilized in Mode 3 with the heat sink being maintained by Auxiliary Feedwater (AFW)[BA] and through the Atmospheric Relief Valves (ARVs)[RV]. The Loop 1 MSIV[ISV] closing was caused by an o-ring failure that led to a loss of hydraulic oil used to maintain the MSIV[ISV] in the open position.
This event had no adverse effect on the health and safety of the public, and is of very low safety significance. This event is reportable per 10CFR50. 73(a)(2)(iv)(A) due to manual and automatic actuation of a systems listed in 10CFR50.739(a)(2)(iv)(B). Unit 2 was unaffected.
NRC I'ORJd 366 (06-2016)
A. REQUIREMENT FOR REPORT This report is required per 1 OCFR50. 73(a}(2)(iv)(A) due to unplanned manual actuation of the Reactor Protection System (RPS), with auto actuation of the Auxiliary Feedwater System and Feedwater Isolation.
B. UNIT STATUS AT TIME OF EVENT Mode 1, 100 percent power
C. DESCRIPTION OF EVENT
On February 03, 2017 at approximately 1545 EST, the Unit 1 control room received a trouble alarm for Loop 1 MSIV (1 HV-30068). Immediately after the initial trouble alarm, a second alarm was received in the Main Control Room indicating 1 HV-30068 was no longer in the full open position. The Operator at the Controls (OATC) attempted to re-open the valve manually by holding the control room handswitch in the open position. This was not effective as valve position continued to drift closed and steam flow continued to degrade until the Shift Supervisor (SS) directed a manual reactor trip. This manual trip resulted in an Emergency Safety Feature (ESF) automatic actuation for Auxiliary Feedwater (AFW)[BA], Feedwater Isolation (FWI)[ISV], and Turbine Trip(TT), as expected. The operating crew stabilized plant in Mode 3 using the emergency operating procedures and decay heat was removed via the Atmospheric Relief Valves (ARVs)[RV].
D. CAUSE OF EVENT
The cause of the event was a failure of an o-ring on the MSIV lower manifold pressure boundary. The o-ring failure resulted in a loss of hydraulic pressure on the MSIV which caused the valve to drift closed. 0-ring failed from extrusion because of radial misalignment.
E. SAFETY ASSESSMENT
Plant Operators took manual actions to shut down the Unit 1 reactor due to degrading plant conditions. ESF auto actuations for Auxiliary Feedwater, Feedwater Isolation and Turbine Trip occurred, as expected. Operating crew stabilized plant entering Emergency Operating Procedures (EOP's) and transitioned to Unit Operating Procedures to maintain stable plant conditions. Because all systems responded as required and there were no actual adverse effects on the health and safety of the public. The safety significance of the event is considered very low.
F.
CORRECTIVE ACTION
MSIV 1 HV30068 was repaired by installing a carbon steel bushing in the manifold 0-ring counter bore with a reduced diameter o-ring. Manual honing of the cylinder boss was performed to smooth the surface. The MSIV actuator was reassembled and functionally tested satisfactorily.
G. ADDITIONAL INFORMATION
1 )Previous Similar Events:
This MSIV previously closed at power in 2014.
2}Commitment Information:
No commitments are made in this correspondence.
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