LER-2013-002, V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open |
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| Report date: |
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| Reporting criterion: |
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)(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 |
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| 3952013002R00 - NRC Website |
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text
Thomas D. Gatlin Vice President, Nuclear Operations 803.345.4342 A SCANA COMPANY June 19, 2013 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS), UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 2013-002-00)
COMPONENT COOLING SYSTEM EMERGENCY MAKEUP VALVE FAILED TO STROKE OPEN Attached is Licensee Event Report (LER) 2013-002-00, for the Virgil C. Summer Nuclear Station (VCSNS). This report describes the surveillance test of a normally closed valve that failed to stroke open and was therefore unable to perform its design function. The station continues to investigate the cause of the event. This report is submitted in accordance with 1 OCFR50.73(a)(2)(i)(B).
Should you have any questions, please call Mr. Bruce Thompson at (803) 931-5042.
Very truly yours, Thomas D. Gatlin JMG/TDG/bq Attachment c:
K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton J. W. Williams W. M. Cherry V. M. McCree E. A. Brown NRC Resident Inspector QA Manager - M. N. Browne Paulette Ledbetter J. C. Mellette EPIX Coordinator K. M. Sutton INPO Records Center Marsh USA, Inc.
Maintenance Rule Engineer NSRC RTS (CR-12-05011 & CR-13-00930)
File (818.07)
PRSF (RC-13-0089)
I6~
Virgil C. Summer Station -Post Office Box 88
- Jenkinsville, SC *29065. F (803) 345-5209
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may sfor each block) not conduct or sponsor, and a person is not required to respond to, the digits/characters finformation collection.
- 3. PAGE V. C. SUMMER NUCLEAR STATION, UNIT 1 05000 395 1
OF 3
- 4. TITLE COMPONENT COOLING SYSTEM EMERGENCY MAKEUP VALVE FAILED TO STROKE OPEN
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MYNUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 04 22 2013 2013 2
0 06 19 2013 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
MODE 1 E] 20.2201(b)
El 20.2203(a)(3)(i) 11 50.73(a)(2)(i)(C)
[
50.73(a)(2)(vii)
[]20.2201 (d)
[]20.2203(a)(3)(ii)
[]50.73(a)(2)(ii)(A)
[]50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
[J 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
I] 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[] 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 0% 20.2203(a)(2)(iii)
[
50.36(c)(2)
[
50.73(a)(2)(v)(A)
El 73.71(a)(4) 100%
20.2203(a)(2)(iv)
[
50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
F] 73.71(a)(5) fl 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[
50.73(a)(2)(v)(C)
[JOTHER [J 20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
U 50.73(a)(2)(v)(D)
Specify in Abstract below or in 5.0 PREVIOUS OCCURRENCE There have been no previous occurrences in the last three years.
6.0 CORRECTIVE ACTIONS
The initial corrective action was to manually adjust the valve then retest in accordance with the surveillance test procedure.
The valve passed the surveillance requirements and was declared operable. The valve was subsequently stroke tested three additional times during the outage to flush the seat in support of troubleshooting efforts to determine if the valve was the source of in-leakage to the CC system. The redundant train component was also successfully tested during the outage.
The station will continue to investigate the cause of this event with further reviews to be conducted during the next refueling outage.
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| 05000395/LER-2013-001, V. C. Summer Nuclear Station, Unit 1, Regarding Grid Disturbance Results in an Engineered Safeguard Features Actuation of the a EDG | V. C. Summer Nuclear Station, Unit 1, Regarding Grid Disturbance Results in an Engineered Safeguard Features Actuation of the a EDG | 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)(iv)(B)(8) 10 CFR 50.73(a)(2)(viii)(B) | | 05000395/LER-2013-002, V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open | V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open | 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) | | 05000395/LER-2013-003, Trip Setpoint Renders Chiller and Control Room Emergency Filtration Inoperable | Trip Setpoint Renders Chiller and Control Room Emergency Filtration Inoperable | 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) | | 05000395/LER-2013-004, Regarding Spray System Relief Valve Failure to Lift at Required Setpoint Renders the Reactor Building Spray System Inoperable | Regarding Spray System Relief Valve Failure to Lift at Required Setpoint Renders the Reactor Building Spray System Inoperable | 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) | | 05000395/LER-2013-005, Regarding Unfused Direct Current Ammeter Circuits in Control Room Result in 10 CFR 50 Appendix R Unanalyzed Condition | Regarding Unfused Direct Current Ammeter Circuits in Control Room Result in 10 CFR 50 Appendix R Unanalyzed Condition | 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) | | 05000395/LER-2013-006, Regarding Securing Control Room Ventilation Emergency Recirculation While Associated Radiation Monitor Was Out of Service | Regarding Securing Control Room Ventilation Emergency Recirculation While Associated Radiation Monitor Was Out of Service | 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) |
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