05000328/LER-2007-002, Re Manual Reactor Trip Following Partial Loss of Main Feedwater Flow
| ML071370062 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/14/2007 |
| From: | Morris G Tennessee Valley Authority |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| LER 07-002-00 | |
| Download: ML071370062 (6) | |
| 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 |
| 3282007002R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 May 14, 2007 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN:
Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
TENNESSEE VALLEY AUTHORITY -
SEQUOYAH NUCLEAR PLANT (SQN)
UNIT 2 -
DOCKET NO.
50-328 -
FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-328/2007-002-00 The enclosed LER provides details concerning a manual reactor trip and automatic engineered safety feature (ESF) actuation of auxiliary feedwater. The manual trip occurred as a result of partial loss of main feedwater flow to the steam generators which resulted from a failure of a main feedwater pump control system.
This report is being submitted in accordance with 10 CFR 50.73(a) (2) (iv) as an event that resulted in the automatic actuation of engineered safety features, including the reactor protection system.
Sincerely, Glenn W. Morris Manager, Site Licensing and Industry Affairs Enclosure cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957 Printed on recycled paW
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52),
LICENSEE EVENT REPORT (LER)
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by intemet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to (See reverse for required number of impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not digits/characters____
for ech bock)required to respond to, the information collection.
- 3. PAGE Sequoyah Nuclear Plant (SQN) Unit 2 05000328 1 OF 5
- 4. TITLE Manual Reactor Trip Following Partial Loss of Main Feedwater Flow
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV TH DAY YEAR 05000 NUMBER NO.
MON 05000 FACILITY NAME DOCKET NUMBER 03 13 2007 2007
- - 002-00 05 14 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) 0l 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
C1 20.2201(d) 0l 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 0l 50.73(a)(2)(viii)(A) 0J 20.2203(a)(1) 0l 20.2203(a)(4) 0l 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) ol 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E0 20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x) 0l 20.2203(a)(2)(iii) 0l 50.36(c)(2) 0l 50.73(a)(2)(v)(A) 0l 73.71 (a)(4) 100 C1 20.2203(a)(2)(iv) 0l 50.46(a)(3)(ii) 0l 50.73(a)(2)(v)(B) 0l 73.71 (a)(5) 10 20.2203(a)(2)(v) 0l 50.73(a)(2)(i)(A)
E0 50.73(a)(2)(v)(C)
El OTHER Cl 20.2203(a)(2)(vi) 0l 50.73(a)(2)(i)(B)
[] 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 (/f more space is required, use additional copies of (/f more space is required, use additional copies of NRC Form 366A)
B. Corrective Actions to Prevent Recurrence:
Corrective actions will include implementation of a design change to jumper the local/remote switch out of the circuit for the applicable controllers. Applicable preventative maintenance procedures are being reviewed to cycle the K1 relays at appropriate frequencies.
VII.
ADDITIONAL INFORMATION
A.
Failed Components:
The 2A main feedwater pump speed indicating controller failed as a result of a faulty local/remote switch and K1 relay which is internal to the 2A main feedwater pump speed indicating controller.
B.
Previous LERs on Similar Events:
There have been no LERs on similar events in the last three years.
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.
Loss of Normal Heat Removal Consideration:
This condition did not result in a loss of normal heat removal.
VIII.
COMMITMENTS
None.
1