05000327/LER-2010-002, Regarding Manual Reactor Trip as a Result of a Failure of Feedwater Control to Maintain Steam Generator Levels
| ML110210113 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/18/2011 |
| From: | Skaggs M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 10-002-00 | |
| Download: ML110210113 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), 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)(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 |
| 3272010002R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 January 18, 2011 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
Licensee Event Report 327/2010-002, Revision 0 The enclosed Licensee Event Report (LER) provides details concerning a manual reactor trip and automatic engineered safety feature actuation of auxiliary feedwater following the failure of the steam generator (SG) level control to maintain SG levels.
The Tennessee Valley Authority is submitting this report in accordance with 10 CFR 50.73 (a)(2)(iv)(A), a condition that resulted in automatic actuation of the reactor protection system.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact B. A. Wetzel, SQN Site Licensing Manager, at (423) 843-7170.
Respectfully, Michael D. Skaggs Site Vice President Sequoyah Nuclear Plant Enclosure: Licensee Event Report - Manual Reactor Trip as a Result of a Failure of Feedwater Control to Maintain Steam Generator Levels cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant
ENCLOSURE LICENSEE EVENT REPORT 327/2010-002, MANUAL REACTOR TRIP AS A RESULT OF A FAILURE OF FEEDWATER CONTROL TO MAINTAIN STEAM GENERATOR LEVELS
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 Sequoyah Nuclear Plant (SQN), Unit 1 05000327 1 OF6
- 4. TITLE:
Manual Reactor Trip as a Result of a Failure of Feedwater Control to Maintain Steam Generator Levels
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL I
REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 11 16 2010 2010 002 -
00 01 18 2011 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201(b)
[
20.2203(a)(3)(i)
[
50.73(a)(2)(i)(C) fl 50.73(a)(2)(vii)
[]
20.2201(d)
D 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A)
[
50.73(a)(2)(viii)(A) 20.2203(a)(1)
D 20.2203(a)(4) 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
EL 20.2203(a)(2)(i)
LI 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL LI 20.2203(a)(2)(ii)
[1 50.36(c)(1)(ii)(A)
Z 50.73(a)(2)(iv)(A)
LI 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
LI 50.36(c)(2)
LI 50.73(a)(2)(v)(A)
LI 73.71(a)(4)
LI 20.2203(a)(2)(iv)
LI 50.46(a)(3)(ii)
[] 50.73(a)(2)(v)(B)
LI 73.71(a)(5) 26 LI 20.2203(a)(2)(v)
LI 50.73(a)(2)(i)(A)
LI 50.73(a)(2)(v)(C)
LI 50.73(a)(2)(i)(B)
LI 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is requeired, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
B.
Previous LERs on Similar Events:
A review of previous reportable events within the last three years identified that there has been a manual reactor trip following a turbine trip as a result of a MSR safety relief valve being unable to seat (LER 1-2009-004); however, there were no previous similar events that were a result of inadequate installation testing.
C.
Additional Information
None.
D.
Safety System Functional Failure:
This event did not result in a safety system functional failure in accordance with 10 CFR 50.73(a)(2)(v).
E.
Unplanned Scram with Complications:
This condition did not result in an unplanned scram with complications.
VIII.
COMMITMENTS
None.