05000313/LER-2009-002, For Arkansas Nuclear One, Regarding Manual Reactor Trip from Power in Response to a Fire at the Main Generator Hydrogen Addition Station Caused by a Personnel Error

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For Arkansas Nuclear One, Regarding Manual Reactor Trip from Power in Response to a Fire at the Main Generator Hydrogen Addition Station Caused by a Personnel Error
ML090920266
Person / Time
Site: Arkansas Nuclear 
Issue date: 04/01/2009
From: David Bice
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1CAN040901 LER 09-002-00
Download: ML090920266 (8)


LER-2009-002, For Arkansas Nuclear One, Regarding Manual Reactor Trip from Power in Response to a Fire at the Main Generator Hydrogen Addition Station Caused by a Personnel Error
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
3132009002R00 - NRC Website

text

1CAN040901 April 1, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Licensee Event Report 50-313/2009-002-00 Arkansas Nuclear One - Unit 1 Docket Nos. 50-313 License Nos. DPR-51

Dear Sir or Madam:

In accordance with 10CFR50.73(a)(2)(iv)(A), enclosed is the subject report concerning a manual reactor trip from power.

New commitments contained in this submittal are documented in the attachment.

Sincerely, DBB/rs Attachment Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4710 David B. Bice Acting Manager, Licensing Arkansas Nuclear One

1CAN040901 Page 2 cc:

Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents@inpo.org

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 8/31/2010

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Arkansas Nuclear One 05000313 1

OF 4

4. TITLE Manual Reactor Trip From Power in Response to a Fire at the Main Generator Hydrogen Addition Station Caused by a Personnel Error
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 05000 2

7 2009 2009 002 00 4

01 2009 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 90 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER-Specify in Abstract below or in C. Root Cause The root cause of this event was determined to be personnel error. The IAO mistakenly assumed that H2-109 was stuck on its closed seat and proceeded to attempt to open the valve using aTorque Amplifying Device (TAD) without first requesting prior supervisor approval to use such a device, as required by procedure. In addition, the IAO did not apply acquired skills and abilities to the task.

D. Corrective Actions

Immediate corrective actions taken with respect to this event included:

The IAO was removed from shift.

Stand Down meetings were conducted with Operations Department personnel regarding this event.

In addition, remediation training and requalification will be provided for the IAO involved with this event.

E. Safety Significance

Operations personnel responded quickly and appropriately to the hydrogen fire by expeditiously isolating the hydrogen supply and extinguishing the fire. In addition, a conservative decision to manually trip the reactor was made. All systems performed as designed during and after the plant trip. Main steam safety valves lifted as expected following the plant trip from 90 percent power and subsequently reseated, as designed.

Considering the expeditious and appropriate actions taken by the operators to minimize the consequences of this event, the actual safety significance is considered to be minimal.

F. Basis for Reportability The NUE and manual reactor trip were reported to the NRC Operations Center at 1118 CST on February 7, 2009. An update notification reporting the termination of the NUE was made at 1238 CST on February 7, 2009.

A manual reactor trip from power is reportable pursuant to 10CFR50.73(a)(2)(iv)(A).

G. Additional Information

There have been no previous similar events in which a fire resulted in a reactor trip reported as LERs at ANO.

Attachment 1CAN040901 List of Regulatory Commitments

Attachment to 1CAN040901 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

COMMITMENT

TYPE (Check One)

SCHEDULED COMPLETION DATE (If Required)

ONE TIME ACTION CONTINUING COMPLIANCE Remediation training and requalification will be provided for the IAO involved with this event X

5/5/2009