05000327/LER-2010-001, Inoperability of Shutdown Board Because of Spent Fuel Pool Back-Up Pump Breaker Inoperability
| ML101600187 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/04/2010 |
| From: | Church C Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 10-001-00 | |
| Download: ML101600187 (9) | |
| 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 |
| 3272010001R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 June 4, 2010 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
Licensee Event Report 327 and 328/2010-001, "Inoperability of Shutdown Board Because of Spent Fuel Pool Back-Up Pump Breaker Inoperability" The enclosed licensee event report provides details concerning an event where Sequoyah Nuclear Plant, Units 1 and 2 were operated in a condition prohibited by technical specifications., The 480-volt Shutdown Board 2A1 -A was considered inoperable as a result of the spent fuel pool back-up pump common spare breaker being inoperable. This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(i)(B).
Respectfully, Christopher R. Church Site Vice President Sequoyah Nuclear Plant
Enclosure:
Licensee Event Report 327 and 328/2010-001, "Inoperability of Shutdown Board Because of Spent Fuel Pool Back-Up Pump Breaker Inoperability" cc:
NRC Regional Administrator-Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant 2 C')
ENCLOSURE LICENSEE EVENT REPORT 327 AND 328/2010-001, INOPERABILITY OF SHUTDOWN BOARD BECAUSE OF SPENT FUEL POOL BACK-UP PUMP BREAKER INOPERABILITY
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 08/31/2010 (9-2007)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-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 FOINPdvacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory LICENSEE EVENT REPORT (LER)
Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503..
If a means used to impose an information collection does not display a currently valid OMB (See reverse for required number of control number, the NRC may not conduct or sponsor, and a person is not required to respond digits/characters for each block) to, the information collection.
- 3. PAGE Sequoyah Nuclear Plant (SQN), Unit 1 05000327 1 OF6
- 4. TITLE:
Inoperability of Shutdown Board Because of Spent Fuel Pool Back-Up Pump Breaker Inoperability
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NEUMENILR E
N O
NT.AY YA SQN Unit 2 05000328 j
j FACILITY NAME DOCKET NUMBER 04 05 2010 2010 -
001 00 06 04 2010
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D1 20.2201(b)
[
20.2203(a)(3)(i)
L] 50.73(a)(2)(i)(C)
LI 50.73(a)(2)(vii) 11 20.2201(d)
LI 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
[3 20.2203(a)(1)
[3 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
[E 50.73(a)(2)(viii)(B) 1[ 20.2203(a)(2)(i)
[]
50.36(c)(1)(i)(A)
[I 50.73(a)(2)(iii)
[I 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [3 20.2203(a)(2)(ii)
[3 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[3 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
[3 50.36(c)(2)
[E 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[3 20.2203(a)(2)(iv)
[3 50.46(a)(3)(ii)
[3 50.73(a)(2)(v)(B)
LI 73.71(a)(5) 100 [3 20.2203(a)(2)(v)
[3 50.73(a)(2)(i)(A)
[3 50.73(a)(2)(v)(C)
[3 OTHER [3 20.2203(a)(2)(vi)
[
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 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 within the last three years 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.