05000327/LER-2008-001, For Sequoyah, Unit 1, Regarding Manual Reactor Trip Resulting from a Failure to Follow Procedures
| ML080650774 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-077) |
| Issue date: | 03/04/2008 |
| From: | James Smith Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| S64 080304 800 LER 08-001-00 | |
| Download: ML080650774 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 3272008001R00 - NRC Website | |
text
March 4, 2008 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 1 -
DOCKET NO. 50-327 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-327/2008-001-00 The enclosed LER provides details concerning a manual reactor trip and engineered safety feature (ESF) actuation of auxiliary feedwater. The trip was initiated because of a low and decreasing steam generator level when a feedwater regulating valve closed as a result of maintenance personnel failing to follow procedures. 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, Original signed by:
James D. Smith Manager, Site Licensing and Industry Affairs Enclosure cc: See page 2 S64 080304 800
U.S. Nuclear Regulatory Commission Page 2 March 4, 2008 Enclosure cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957 Mr. Thomas H. Boyce, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379
U.S. Nuclear Regulatory Commission Page 3 March 4, 2008 JDS:RRT:JWP:KTS Enclosure cc (Enclosure):
G. Arent, EQB 1B-WBN P. M. Billingsley, OPS-4C-SQN (For Web posting)
W. R. Campbell, Jr., LP 3R-C C. R. Church, POB 2B-SQN J. E. Cipriani, OPS 4E-SQN T. P. Cleary, OPS 4A-SQN L. D. Clift, OPS 4G-SQN (Attn: R. N. McKaig)
K. R. Jones, OPS 4A-SQN L. E. Nicholson, BR 4X-C NSRB Support, BR 4X-C M. R. Purcell, BR 4X-C H. R. Rogers, LP 3R-C S. A. Vance, ET 10A-K E. J. Vigluicci, ET 10A-K T. D. Wallace, STC 2A-SQN WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K I:license/lers/2008/LER 1-2008-001.doc
NRC FORM 366 (9-2007)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 08/31/2010
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Sequoyah Nuclear Plant Unit 1
- 2. DOCKET NUMBER 05000327
- 3. PAGE 1 of 5
- 4. TITLE:
Manual Reactor Trip Resulting From A Failure to Follow Procedures
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 01 16 2008 2008 - 001 - 00 03 04 2008 FACILITY NAME DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1
- 10. POWER LEVEL 100 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)
OTHER 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 required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) VII.
ADDITIONAL INFORMATION
A.
Failed Components:
None.
B. Previous LERs on Similar Events:
A review of previous reportable events did not identify any previous similar events.
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.