05000395/LER-2006-004, Re Turbine Trip Due to High Steam Generator Level P-14
| ML070240123 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/19/2007 |
| From: | Archie J South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-004-00 | |
| Download: ML070240123 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv), System Actuation 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 |
| 3952006004R00 - NRC Website | |
text
Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY January 19, 2007 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Ladies and Gentlemen:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 2006-004-00)
TURBINE TRIP DUE TO HIGH STEAM GENERATOR LEVEL P-14 Attached is Licensee Event Report (LER) No. 2006-004-00, for the Virgil C. Summer Nuclear Station (VCSNS). The report describes the sequence of actions that led to a turbine trip due to P-14 actuation.
This report is submitted in accordance with 10CFR50.73(a)(2)(iv).
Should you have any questions, please call Mr. Bruce Thompson at (803) 931-5042.
FWK/JT/J BNdr Attachment c:
K. B. Marsh S. A. Byrne N. S. Cams J. H. Hamilton R. J. White W. D. Travers R. E. Martin NRC Resident Inspector M. N. Browne K. M. Sutton D. L. Abstance P. Ledbetter EPIX Coordinator INPO Records Center J&H Marsh & McLennan NSRC RTS (C-06-4275)
File (818.07)
DMS (RC-07-0012)
SCE&G I Virgil C. Summer Nuclear Station
- P. 0. Box 88
- Jenkinsville, South Carolina 29065. T (803) 345.5209
- www.scanacaom
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC (See reverse for required number of may not conduct or sponsor, and a person is not required to respond to, the diqits/characters for each block) information collection.
- 3. PAGE Virgil C. Summer Nuclear Station 05000 395 1
OF 3
- 4. TITLE Turbine Trip Due To High Steam Generator Level P-14
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 11 22 2006 2006 4
0 01 19 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 2 E] 20.2201(b)
[
20.2203(a)(3)(i)
E] 50.73(a)(2)(i)(C) 5 50.73(a)(2)(vii) o 20.2201(d)
[
20.2203(a)(3)(ii) 5 50.73(a)(2)(ii)(A) 5 50.73(a)(2)(viii)(A)
LI 20.2203(a)(1)
E] 20.2203(a)(4) 5 50.73(a)(2)(ii)(B) 5] 50.73(a)(2)(viii)(B)
_E]
20.2203(a)(2)(i)
[J 50.36(c)(1)(i)(A) 5 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL Li 20.2203(a)(2)(ii)
LI 50.36(c)(1)(ii)(A)
[
50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 5 20.2203(a)(2)(iii) 5 50.36(c)(2) 5 50.73(a)(2)(v)(A)
E] 73.71 (a)(4) 1 - 3%
5 20.2203(a)(2)(iv) 5] 50.46(a)(3)(ii) 5 50.73(a)(2)(v)(B)
Q 73.71(a)(5)
[
20.2203(a)(2)(v) 5] 50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C) 5 OTHER O 20.2203(a)(2)(vi)
Li 50.73(a)(2)(i)(B)
[=
50.73(a)(2)(v)(D)
Specify in Abstract below or in
CAUSE OF EVENT
The major issue was a failure of the operators to utilize all available indications and anticipate plant response. Contributing factors include: equipment issues with the FWP Master Speed Controller not being able to control speed in automatic during no or low FW flow conditions. FW flow indications are not accurate at low flow conditions. Narrow range (NR) SGWL lags actual level at low power. These factors contributed to the FW Operator not recognizing adequate flow to the SGs.
ANALYSIS OF EVENT
At the time of the event, the plant was at less than 3% reactor power. Operators were performing secondary plant startup. The FWP Master Speed Controller and the Bypass FRVs were in manual due to low flow conditions. All plant systems functioned as designed and remained operable. The P-14 signal isolated FW, tripped the main FWP turbines, and tripped the Main Turbine.
CORRECTIVE ACTIONS
After the transient, the crew established EF flow to the SGs, restored RCS temperature and pressure to normal, and then restored letdown. The oncoming operations crew received simulator training on the startup evolution. The crew then assumed the watch and successfully raised power, and continued with the secondary plant startup.
Condition Evaluation Report C-06-4275 was initiated to document actions and evaluations for this event.
Corrective actions to preclude recurrence include improving pre-job briefings and just-in-time (JIT) training for the startup evolution to include equipment issue awareness. Additionally, licensed operators will be provided training on the event during the next scheduled Licensed Operator Requalification training cycle and simulator training on this evolution will be added to the Licensed Operator Requalification Program. These actions will be completed by April 1, 2007.
PRIOR OCCURRENCES There have been no similar events that have occurred at VCSNS during the last five years.PRINTED ON RECYCLED PAPERPRINTED ON RECYCLED PAPER