05000424/LER-2011-003, Regarding Control Room Air Damper Found Closed Results in Technical Specification Non-Compliance
| ML11333A135 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/18/2011 |
| From: | Tynan T Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-11-2195 LER 11-003-00 | |
| Download: ML11333A135 (6) | |
| 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) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii)(B), Common Cause Inoperability 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 |
| 4242011003R00 - NRC Website | |
text
Tom Tynan Southern Nuclear Vice President - Vogtle Operating Company, Inc.
7821 River Road Wayneshioi. Georgia 30830 Tel 706.826 3151 Wax 706.826 3321 November 18, 2011 SOUTHERNA
¶OMPANY Docket Nos.: 50-424 NL-1 1-2195 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant-Unit 1 Licensee Event Report 2011-003-00 Control Room Air Damper Found Closed Results in Technical Specification Non-Compliance Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73(a)(2)(i)(B) Southern Nuclear Operating Company (SNC) is submitting the enclosed Licensee Event Report.
This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Respectfully submitted, T. E. Tynan Vice President - Vogtle TET/TMH/kss Enclosure: Licensee Event Report 2011-003-00 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Chief Nuclear Officer Ms. P. M. Marino, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. D. H. Jaffe, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle
Enclosure Vogtle Electric Generating Plant-Unit 1 Licensee Event Report 2011-003-00 Control Room Air Damper Found Closed Results in Technical Specification Non-Compliance
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person Is not required to respond to, the information collection.
- 3. PAGE Vogtle Electric Generating Plant - Upit 1 i05000424
.1 OF 4
.TITLE Control Room Air Damper Found Closed Results in Technical Specification Non-Compliance
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FAIIYNM DOCKET NUMBER MONTH DAY YEAR YEAR SENUENTIAL REV MONTH DAY YEAR NUMBER NO.
09 2011 003 00 11 18 12011 FACILITY NAME DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITnED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o] 20.2201(b)
[0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
[1 20.2201(d)
[0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)
[0 50.73(a)(2)(vlli)(A)
[o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
[0 50.73(a)(2)(vii)(B) rE_ 20.2203(a)(2)(1) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii)
[3 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
'[ 20.2203(a)(2)(li) 0 50.36(c)(1)(1i)(A) 0 50.73(a)(2)(iv)(A) 0I 50.73(a)(2)(x) o 20.2203(a)(2)(11I)
[I 50.36(c)(2)
[0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv)
[0 50.46(a)(3)(ii)
[0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 0 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER [o 20.2203(a)(2)(vi) 19 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Speclfy in Abstract below or in
D. CAUSE OF EVENT
An investigation into the cause for the damper going closed was inconclusive. A review of operating logs, tagging orders and outage work did not find any activity which should have resulted in the damper going closed. Additionally, an inspection of the damper and solenoid valves did not find any condition which would have caused the damper to close unexpectedly.
E. SAFETY ASSESSMENT
During this event, the damper was closed while Unit 1 was in Mode 1 and Unit 2 was in Mode 6 with no fuel movement or core alterations in progress. The CREFS acts to terminate the supply of unfiltered outside air to the control room, initiate filtration, and pressurize the control room. This ensures the control room is kept habitable for operators stationed there during accident recovery and post accident operations by minimizing the radiation exposure of control room personnel. In Modes 1, 2, 3, and 4, the radioactive gas monitor actuation of the CREFS is a backup for the Safety Injection (SI) signal actuation. During movement of irradiated fuel assemblies and core alterations, the radioactive gas monitor actuation is the primary means to ensure control room habitability in the event of a fuel handling accident. During the time the damper was closed, the SI actuation for the Unit 1 CREFS remained operable. Since there was no movement of irradiated fuel assemblies or core alterations on Unit 2 during the time the damper was closed, the radioactive gas monitors were not required to be operable for Unit 2. Since the SI actuation for the Unit 1 CREFS remained operable during the time the damper was closed, the event does not represent a safety system functional failure. Also, based upon these considerations, there was no adverse affect on plant safety or on the health and safety of the public.
F. CORRECTIVE ACTION
A design change package will be developed to provide a control room annunciation to alert the operator of the condition so that necessary actions can be taken. The expected implementation date for the design change is November 15, 2014.
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G. ADDITIONAL INFORMATION
- 1) Failed Components:
None
- 2) Previous Similar Events:
A review of Licensee Event Reports (LER) over the past seven years finds that a similar event occurred in 2004 as documented in LER 2004-002-00. In that event, the damper was found closed also. However, the cause for the damper closing was traced back to switchgear cleaning that caused two of the solenoid valves that are required to be energized to maintain the damper open, to lose power. The switchgear cleaning procedure was revised to alert personnel that this activity would cause the damper to close. The closure of the damper on September 19, 2011 could not be tied to any maintenance activity, including switchgear cleaning.
- 3) Energy Industry Identification System Code:
Control Room Emergency Filtration System - VI Radiation Monitoring System - IL Integrated Plant Computer System - ID