05000395/LER-2008-004, V. C. Summer Technical Specification Violation Due to Alternate AC Unavailability
| ML082840701 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 10/09/2008 |
| From: | Archie J South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 08-004-00 | |
| Download: ML082840701 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| 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 |
| 3952008004R00 - NRC Website | |
text
Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY October 9, 2008 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 2008-004)
TECHNICAL SPECIFICATION VIOLATION DUE TO ALTERNATE AC INOPERABILITY Attached is Licensee Event Report (LER) No. 2008-004, for the Virgil C. Summer Nuclear Station (VCSNS). This report describes the sequence of actions that led to a violation of Technical Specification LCO 3.8.1.1. This report is submitted in accordance with 10CFR50.73(a)(2)(i)(B).
Should you have any questions, please call Mr. Bruce Thompson at (803) 931-5042.
Very tru.v yours,
'effrey B. Archie JW/JBA/sr Attachment c:
K. B. Marsh S. A. Byrne N. S. Carns J. H. Hamilton R. J. White K.J. Browne L. A. Reyes 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 File DMS (CR-08-02381/02477)
(818.07)
(RC-08-0128) 345.5209 - www.sceg.com
/A"
,(22 SCE&G I Virgil C. Summer Nuclear Station o P. 0. Box 88 -Jenkinsville, South Carolina 29065.T (803]
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may (See reverse for required number of 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 Technical Specification Violation due to Alternate AC Unavailability
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR Y
FACILITY NAME DOCKET NUMBER MONH AY YEA YAR NUBER NO
____SEQUENTIAL REV MONTH DAY YEAR05 0
!NUMBERI NO.
05000
_____________JFACILITY NAME DOCKET NUMEER 02 15 2007 2008 4
0 10 09 2008 05000 S05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
Mode 1
[] 20.2201(b) jJ 20.2203(a)(3)(i) 50.73(a)(2)(i)(C)
O 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) 20.2203(a)(1)
[]
20.2203(a)(4) 50.73(a)(2)(ii)(B)
O 50.73(a)(2)(viii)(B)
_ 20.2203(a)(2)(i)
[]
50.36(c)(1)(i)(A) jJ 50.73(a)(2)(iii)
Ej 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii)
[J 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A)
[]
50.73(a)(2)(x) 20.2203(a)(2)(iii)
[
50.36(c)(2) 50.73(a)(2)(v)(A)
[
73.71(a)(4) 100%
20.2203(a)(2)(iv) j]
50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) jj 50.73(a)(2)(i)(A) f 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi)
[7j 50.73(a)(2)(i)(B)
[J 50.73(a)(2)(v)(D)
Specify in Abstract below or in
CAUSE OF EVENT
This event is still under investigation. Upon completion of the root cause analysis, the cause will be identified in a supplement to this report. A revised report is projected to be submitted by February 26, 2009.
ANALYSIS OF EVENT
The incorrectly installed reverse power relay called into question the past availabilty of the AAC. During the RF-17 testing the relay actuated and tripped the AAC supply breaker to VCSNS, when a load was being added to the AAC. Further investigation determined that the relay had been installed incorrectly. Even with the relay installed incorrectly, post modification testing and subsequent surveillance testing were successful.
Although the potential unavailability of the AAC resulted in a Technical Specification violation, a PRA evaluation determined that the safety significance was low (< 1 E-6/yr).
CORRECTIVE ACTIONS
Two issues were identified with the AAC power sources: voltage regulation problems and an incorrectly installed reverse power relay. To address the voltage regulation issue an enhanced prejob brief and procedural guidance have been put in place for controlling the Parr hydro units when adding VCSNS loads to the AAC. The reverse power relay function has been interimly addressed by jumpering out this function.
This event is still under investigation. Upon completion of the root cause analysis, the corrective actions will be identified in a supplement to this report. A revised report is projected to be submitted by February 26, 2009.
PRIOR OCCURRENCES There have been no other instances of Technical Specification violations related to AAC unavailability in the past three years.PRINTEO ON RECYCLED PAPERPRINTED ON RECYCLED PAPER