05000331/LER-2009-002, Manual Reactor Scram Due to Loss of Condenser Cooling
| ML090960312 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/02/2009 |
| From: | Richard Anderson Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-09-0299 LER 09-002-00 | |
| Download: ML090960312 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 |
| 3312009002R00 - NRC Website | |
text
FPL Energy Duane Arnold, LLC 3277 DAEC Road Palo, Iowa 52324 FPL Energy.
Duane Arnold Energy Center April 2, 2009 NG-09-0299 10 CFR 20.2203 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Licensee Event Report #2009-002-00 Please find attached the subject report submitted in accordance with 10 CFR 20.2203. This letter makes no new commitments or changes to any existing
commitments
Richard L. Anderso Vice President, Duane Arnold Energy Center FPL Energy Duane Arnold, LLC cc:
Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC A4~
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Duane Arnold Energy Center 05000 331 1 OF 6 Manual Reactor Scram Due to Loss of Condenser Cooling
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCUMENT NUMBER NUMBER NO.
____05000 02 01 09 2009 001 0
04 02 09 FACILITY NAME DOCUMENT NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E] 20.2201(b)
[]
20.2203(a)(3)(i)
Li 50.73(a)(2)(i)(C)
[]
50.73(a)(2)(vii)
[1]
20.2201(d)
Li 20.2203(a)(3)(ii)
[
50.73(a)(2)(ii)(A)
Li 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
LI 20.2203(a)(4)
Li 50.73(a)(2)(ii)(B)
Li 50.73(a)(2)(viii)(B)
[]
20.2203(a)(2)(i)
[
50.36(c)(1)(i)(A)
E]
50.73(a)(2)(iii)
[3 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E] 20.2203(a)(2)(ii)
[3 50.36(c)(1)(ii)(A)
[
50.73(a)(2)(iv)(A)
Li 50.73(a)(2)(x)
Li 20.2203(a)(2)(iii)
Fi 50.36(c)(2)
Li 50.73(a)(2)(v)(A)
Li 73.71(a)(4) 53%
Li 20.2203(a)(2)(iv)
[3 50.46(a)(3)(ii)
[3 50.73(a)(2)(v)(B)
Li 73.71(a)(5)
[3 20.2203(a)(2)(v)
E]
50.73(a)(2)(i)(A)
[3 50.73(a)(2)(v)(C)
E] OTHER Li 20.2203(a)(2)(vi)
[3 50.73(a)(2)(i)(B)
[
50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Bob Murrell, Engineering Analyst 319-851-7900CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX D
NN CTW M085 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION Li YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE)
LIi NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On February 1, 2009, with the plant operating at 53% power, during plant shutdown evolutions in preparations for Refuel Outage (RFO) 21, operators were in the process of securing the 'A' cooling tower in accordance with Operating Instruction 442, Circulating Water System. While throttling the 'A' cooling tower riser isolation valves in preparations for securing the 'A' circulating water pump, a rupture of the 'B' cooling tower west riser occurred.
In anticipation of a loss of circ water pit level, a manual scram was inserted at 1800. Following the manual scram, the plant was stabilized per abnormal operating procedures. Containment isolation signals operated as designed with Groups 2, 3, and 4 received.
The cause of this event was an inadequate procedure. Operating Instruction 442 was inadequate to prevent an inappropriate operational configuration that resulted in the failure of the cooling tower riser. A design change restored the failed riser with a more robust design, and enhanced the design of the remaining risers on both cooling towers.
There were no actual safety consequences and no effect on public health and safety as a result of this event.
NRC FORM 366 (9-2007)
PRINTED ON RECYCLED PAPER (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) (17)
V. Additional Information
Previous Similar Occurrences:
A review of LERs over the previous 5 years revealed the following similar occurrences:
LER 2007-007 - Reactor Scram Due to 1A2 Non-essential Bus Lockout LER 2007-006 - Reactor Shutdown as a Result of a Chemistry Excursion LER 2006-005 - Reactor Scram During Main Turbine Testing LER 2003-005 - Unplanned Manual Reactor Scram due to High Reactor Coolant Conductivity LER 2003-006 - Unplanned Manual Reactor Scram due to Degrading Condenser Vacuum EUIS System and Component Codes:
Cooling Tower - CTW
Reporting Requirements
This event is reportable under 10 CFR 50.73(a)(2)(iv)(A).PRINTED ON RECYCLED PAPER